Text

Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis for Salem Nuclear Generating Station, Units 1 & 2.
	ML20045B880
Person / Time
Site:	Salem
Issue date:	05/21/1993
From:	; ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	;
Shared Package
ML18100A416	List: ML18100A415; ML18100A417; ML20045B880;
References
	CEN-606, CEN-606-R, CEN-606-R00, NUDOCS 9306210212
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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606, REV. 00 TECHNICAL BASES AND OPERATIONAL ANALYSIS i

i FOR ,

SALEM NUCLEAR GENERATING. STATION ,

r UNITS 1 AND 2 i

PREPARED FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY- '

BY t

! ABB COMBUSTION ENGINEERING NUCLEAR SERVICES AUTHOR: V -

b QAREVIEf:/ _d 8-Z/-7J f m ,

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIB REV. 00 Table of Contents Section Title Pace

1.0 INTRODUCTION

. . . . . . . . . . . . . . . . . . . . . . 6 1.1 PURPOSE AND SCOPE . . . . . . . . . . . . . . . . . . . 6 1.2 REPORT ORGANIZATION . . . . . . . . . . . . . . . . . . 8 1.3 PAST vs. PRESENT METHODOLOGY OF SETTING BAT CbtCENTRATION 9 2.0 TECHNICAL BASES FOR REDUCING BAT CONCENTRATION . . . . . 12 '

2.1 BORIC ACID SOLUBILITY . . . . . . . . . . . . . . . . . 12 2.2 METHOD OF ANALYSIS AND ASSUMPTIONS . . . . . . . . . . . 12 2.2.1 RCS Boron Concentration vs. Temperature . . . 12 2.2.2 Impact of Cooldown Rate . . . . . . . . . . . 19 2.2.3 Acolicability to Future Reload Cycles . . . . 21 2.2.4 Boron Mixina in the RCS and in the Pressurizer . . . . . . . . . . . . 22 2.3 BORATED WATER SOURCES - SHUTDOWN (MODES 5 AND 6) . . . . 23 2.3.1 Boration Reauirements for Modes 5 and 6 . . . 23 2.3.2 Assumptions Used in the Analysis of Modes-5 ,

and 6 . . . . . . . . . . . . . . . . . . . . 23 !

2.3.3 Modes 5 and 6 - Analysis'and Outline

. . . . . 24 2.3.4 Modes 5 and 6 - Cooldown - Makeup from the RWST . . . . . . . . . . . . . . . . . . .- . . 25 2.3.5 RWST Boration Reauirements - Modes 5 &6 . . . 29 e 2.3.6 Modes 5 and 6 - Cooldown. Usina BATS BAT Storace Reauirements . . . . . . . . . . . 31 ABB Combustion Engineering Nuclear Services Page 2 of 133 a

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table of Contents (continued)

Section Title Pace 2.4 BORATED WATER SOURCES - OPERATING (MODES 1, 2, 3, and 4) 32 2.4.1 Boration Recuirements for Modes 1, 2, 3, and 4 . . . . . . . . . . . . . . . . . . . . 32 2.4.2 Assumptions Used in the Modes 1, 2. 3. and 4 Analysis . . . . . . . . . . . . . . 32 2.4.3 Modes 1. 2, 3. and 4 Analysis Results-Eauilibrium Xenon Scenario . . . . . . . . . . 34 2.4.4 Modes 1, 2, 3, and 4 Analysis Results-Peak Xenon Scenario . . . . . . . . . . . . . 38 2.4.5 Simplification Used Followina RHRS Initiation . . . . . . . . . . . . . . . . . . 40 2.5 BORATION SYSTEMS - BASES . . . . . . . . . . . . . . . . 42 2.5.1 Derivation of the 73,800 Gallon Volume (RWST) . . . . . . . . . . . . . . . . . . . . 43 2.5.2 Derivation of the 41.800 Gallon RWST Volume ,

Reauired when the smallest BAT volume is Used . . . . . . . . . . . . . . . . . . . . . 44 i 2.6 ACTION STATEMENTS ON FLOW REQUIREMENTS . . . . . . . . . 45 TABLES - SECTION 2 . . . . . . . . . . . . . . . . . . . 48 FIGURES - SECTION 2 . . . . . . . . . . . . . . . . . . 87 i

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BORIC ACID CONCENTRATION REDUCTION EFFORT .CEN-606 TECNNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 ]

Table of Contents (continued)

Section Title Pace 3.0 OPERATIONAL ANALYSIS . . . . . . . . . . . . . . . . . . 95

3.1 INTRODUCTION

TO THE OPERATIONAL ANALYSIS . . . . . . . . 95-1

\

3.2 RESPONSE TO EMERGENCY SITUATIONS . . . . . . . . . . . . 95 3.2.1 Accident Boration Recuirements . . . . . . . . 96 [

3.2.2 Shutdown Marcin Recoverv . . . . . . . . . . . 97 .

3.2.3 Emercency Boration . . . . . . . . . . . . . . 98- ,

3.3 FEED-AND-BLEED OPERATIONS . . . . . . . . . . . . . . . . . 99 f

3.4 BLENDED MAKEUP OPERATIONS . . . . . . . . . . . . . . . 101 !

3.5 SHUTDOWN TO REFUELING - MODE 6 . . . . . . . . . . . . . 103 !

3.6 SHUTDOWN TO COLD SHUTDOWN - MODE 5 . . . . . . . . . . . 107 3.7 LONG TERM COOLING AND CONTAINMENT SUMP pH . . . . . . . 109 'i 110 TABLES - SECTION 3 . . . . . . . . . . . . . . . . . . .

FIGURES - SECTION 3 . . . . . . . . . . . . . . . . . . 123 r

4.0 REFERENCES

. . . . . . . . . . . . . . .- . . . . . . . . 133 i

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table of Contents (continued)

Section Title Page I

List of Aopendices Appendix 1 Derivation of the Reactor Coolant System Feed-and-Bleed Equation . . . . . . . . . . . Al-1 Appendix 2 Methodology for Calculating Dissolved Boric Acid per Gallon of Water. . . . . . . . A2-1 Appendix 3 Methodology for Calculating the Conversion Factor Between Weight Percent Boric Acid and ppm Boron . . . . . . . . . . . . . . . . A3-1 1

Appendix 4 Bounding Core Reactivity Considerations. . . A4-1 ABB Combustion Engineering Nuclear Services Page 5 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00

'1. 0 INTRODUCTION 1.1 PURPOSE AND SCOPE This report defines the methodology and outlines the technical bases which allow a reduction in the Boric Acid Tank (BAT) concentration to the point where heat tracing of the boric acid makeup system is no longer required to 1 prevent boric acid precipitation. The basic methodology or procedure used to set the minimum BAT concentration and level for Modes 1, 2, 3, and 4 is derived from the safe ,

shutdown requirements of Reference 4.1, (NUREG 0800 Branch Technical Position RSB 5-1, " Design Requirements for the Residual Heat Removal System", (BTP 5-1)). For purposes of implementing the requirements for heat removal capability for compliance with this position, plants were divided into three classes by the NRC. Salem Unit 1 is a Class 3 plant ,

and Unit 2 is a Class 2 plant per BTP 5-1. Classes 2 and 3 ;

are defined as follows in the Branch Technical Position:

Class 2

" Partial implementation of this position for all plants (custom or standard) for which CP or PDA applications

~

are docketed on or after January 1, 1978 and for which an OL issuance is expected on or after January 1, 1979."

Class 3 I

"The extent to which the implementation guidance in Table 1 will be backfitted for all operating reactors and all other plants for which the issuance of the OL

, is expected before January 1, 1979, will be based on the combined I&E and DOR review of related plant features for operating reactors."

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 I A table is included in the BTP which describes recommended implementation for Class 2 and 3 plants.

Two independent and redundant boration flow paths with appropriate borated water are provided in Salem Units 1 and 2 to compensate for reactivity changes and all expected transients throughout core life. The sources of borated water are the BATS and the Refueling Water Storage Tank (RWST). The design bases used to establish the required volume and boron concentration in the BAT have been examined, and the results are presented in this Section. In addition, the minimum RWST volume requirements for RCS boration have been calculated. Sufficient dissolved boric acid must be maintained in the BATS to provide the shutdown margin specified in the LCOs for Technical Specification (TS) 3.1.1.1 for a cooldown from hot standby (Mode 3) to cold shutdown (Mode 5) conditions. Further, both the minimum level and boron concentration which must be maintained in the BATS for Modes 5 and 6 are based upon the ability to maintain the shutdown margin specified in the LCOs for TS 3.1.1.2 (Mode 5) following xenon decay and cooldown from 200*F to 135'F.

This document has been prepared to support a reduction in the concentration and volume of boric acid which must be maintained in the BATS at Salem Units 1 and 2 to maintain adequate shutdown margin. It also shows that this margin can be provided by one (1) BAT for each unit for most of the operational conditions as shown in Technical Specification Figures 3.1.2.8 (Unit 1) and 3.1.2.6 (Unit 2). The studies

. described herein support a reduction in boric acid concentration to levels below that at which precipitation can occur at the temperatures normally expected in the BATS ABB Combustion Engineering Nuclear Services Page 7 of 133

L BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 and associated piping areas of the plants. This reduction eliminates the requirement for heaters and heat tracing on the BATS and associated piping. To accomplish this, the analysis performed to support the original requirements for boric acid has been reevaluated, incorporating the revised boration-to-cold-shutdown methodology. This methodology has been developed to demonstrate the acceptability of reducing the concentration and volume of stored boric acid.

The work described in this report was performed specifically for Salem Units 1 and 2. To the extent possible, the calculations performed and the values obtained will be applicable to future fuel cycles. (See Section 2.2.3.) The physics parameters used in this analysis have been selected conservatively to bound core physics parameters for the next reload fuel cycle. Future cycle core physics parameters are to be compared to the data in Appendix 4 to ensure that the results of these calculations remain bounding. The values in Technical Specification Figure 3.1.2.8 (Unit 1) and Figure 3.1.2.6 (Unit 2) may change slightly; however, there should not be a need to heat trace the piping and components of the boric acid system for the remainder of plant life.

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

Introduction, Technical Bases, and Operational Analysis. In Section 2.0, " Technical Bases for Reducing BAT ,

Concentration", the methodology which allows a significant l reduction in BAT tank concentration and volume is outlined, and the results of the detailed calculations performed in !

support of the Technical Requirements for the Technical Specifications are presented. Separate calculations were ABB Combustion Engineering Nuclear Services Page 8 of 133 1

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 performed for TS 3.1.2.7 (Unit 1) and TS 3.1.2.5 (Unit 2)

(Borated Water Source - Shutdown); TS 3.1.2.8 (Unit 1) and TS 3.1.2.6 (Unit 2) (Borated Water Source - Operating); as well as Bases Specification 3/4.1.2 (Boration System Bases).

In addition, revised action statements have been prepared for TS 3.1.1.1 (Reactivity Control Systems / Shutdown Margin /T,, >2 00

F) , TS 3.1.1.2 (Reactivity Control Systems / Shutdown Margin /T ,, 1200*F), Specification 3.9.1 (Refueling Operations / Boron Concentration), Specification 3.10.1 (Special Test Exception / Shutdown Margin), and Surveillance Requirement 4.1.2.2 (Reactivity Control Systems / Flow Paths Operating) (Unit 2 only in current Technical Specifications).

In Section 3.0, " Operational Analysis", the impact of the reduction in the concentration of boric acid stored in the BATS on normal operations is outlined. The operations evaluated in Section 3.0 are as follows: feed-and-bleed, blended makeup, shutdown-to-refueling, and shutdown-to-cold-shutdown. Tables and figures are contained at the end of Sections 2.0 and 3.0 for convenient reference.

1.3 PAST vs. PRESENT METHODOLOGY OF SETTING BAT CONCENTRATION i

( Prior to the development of the new methodology for setting BAT concentration and level described in this report, the level and concentration specified in the plant Technical i

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). Using the old methodology, the reactor coolant system (RCS) was borated prior to initiating cooldown to the boron concentration required to provide a ABB Combustion Engineering Nuclear Services Page 9 of 133

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 i TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 i

l shutdown margin 21.6% Ak/k at temperatures >200'F (refer to TS 3/4.1.1.1). Boration without letdown can be accomplished using safety grade equipment. In the limiting situation, it was assumed that letdown was not available, and boration was accomplished by charging to the RCS (consequently filling the pressurizer) . In this scenario, boron concentration in the RCS typically had to be increased by approximately 900 ppm prior to commencing cooldown, and the limited volume available in the pressurizer necessitated storing highly concentrated boric acid solution in the BATS.

However, subsequent advances have made it possible to develop new methodologies for setting BAT 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 RCS is performed concurrently with plant cooldown, i.e.,

concentrated boric acid is added concurrently with cooldown, thereby providing the RCS inventory makeup to compensate for coolant contraction. By determining the boron concentration required to maintain proper shutdown margin at each temperature during a plant cooldown, the concentration of boric acid in the BATS can be decoupled from available pressurizer volume. As the present study shows, the concentration of boric acid which must be maintained in the BATS to allow cooldown-without-letdown to cold shutdown conditions can be reduced to a value between 3.75 and 4.0 weight percent, where heat tracing of the boric acid system is no longer required, i.e., the ambient temperature in the auxiliary building is sufficient to prevent boric acid

. precipitation.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Similarly, this new methodology was utilized in setting the minimum concentration and level of the boration source which is required to be operational in Modes 5 and 6. Since letdown is available in the cooldown scenarios of Modes 5 and 6, feed-and-bleed may be conducted when it is necessary to increase RCS boron concentration. In addition, boration can be conducted concurrently with cooldown as part of normal system makeup. By ensuring that the boron concentration is maintained greater than that required for proper shutdown margin at all temperatures, the boric acid concentration in the BATS can be lowered to a value between 3.75 and 4.0 weight percent for Modes \S and 6.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 2.0 TECHNICAL BASES FOR REDUCING BAT CONCENTRATION 2.1 BORIC ACID SOLUBILITY Figure 2-1 is a plot of solubility of boric acid in water vs. temperature, for temperatures between 32*F and 160*F.

The data for Figure 2-1 were obtained from Reference 4.2 and are included herein as Table 2-1. Note that the solubility of boric acid at 32*F is 2.52 weight percent ahd, by interpolation, at 58'F is 4.00 weight percent. 'At or below a concentration of 4.0 weight percent boric acid, the normal ambient temperature in the auxiliary building will be sufficient to preclude precipitation within the Boric Acid Makeup Subsystem. In Reference 4.3, the requirement for monitoring and recording the ambient temperature in the vicinity of the BATS was identified to verify that the temperature is maintained above 63*F. The 63*F temperature is specified to provide a 5 F margin of conservatism above the 58 F solubility limit. Maintenance of the ambient temperature is further ensured by Technical Specification Surveillance Requirements.

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 -

Equilibrium Xenon Scenario As described in Section 1.3, the methodology developed to

. justify a significant reduction in the concentration of boric acid which must be maintained in the BATS in Modes 1, ;

2, 3, and 4 differs from the previous methodology in that ABB Combustion Engineering Nuclear Services Page.12 of 133 l

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 boration of the RCS is performed concurrently with cooldown.

In order to ensure adequate shutdown margin during the cooldown process, concentrated boric acid solution is added as part of normal system makeup. To employ a methodology allowing boration concurrent with cooldown, the exact boron concentration in the reactor coolant necessary to maintain the required shutdown margin must be known at any temperature during the cooldown process. In addition, in order to ensure applicability for the entire fuel cycle, a conservative cooldown scenario has been developed which incorporates the maximum increase in RCS boron concentration which the operator must achieve in order to maintain an adequate shutdown margin at the most limiting time in the fuel cycle. Such a limiting scenario is as follows:

1. Conservative core physics parameters are used to determine both the concentration and the volume of boric acid solution which must be provided from the BATS during plant cooldown. For this analysis, the end-of-life (EOL) initial boron concentration is assumed to be zero ppm. EOL moderator cooldown effects are used to maximize the reactivity change during the plant cooldown. EOL values of inverse boron worth (IBW) were used in combination with EOL moderator reactivity insertion rates, normalized to the most Negative Technical Specification Moderator Temperature Coefficient (MTC) limit, since it is known that this yields results that are more limiting than any actual combination of MTC and 1BW values throughout the fuel cycle. These assumptions assure that the required a boron concentration and the minimum BAT volume requirements conservatively bound all plant cooldowns during core life.

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2. The most reactive rod is stuck in the full out position.

3. Prior to time zero, the plant is operating at 100%

power, with core xenon concentration at the 100% power ,

equilibrium level.

4. There is zero RCS leakage.

5. At time zero, the plant is shutdown and held at hot zero power conditions for 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months , at which time the xenon transient after shutdown will have decayed back to the 100% power equilibrium level. (Further xenon decay will add positive reactivity to the core during the plant cooldown). No credit was taken for the negative reactivity added during the xenon transient following reactor shutdown.

6. At time a 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months , loss of offsite power is assumed, and all non-safety grade plant equipment and components are assumed to become inoperative. A cooldown-to-cold-shutdown is initiated.

The scenario outlined above has been used to generate the borated water requirements for Modes 1, 2, 3, and 4. It j produces a situation wherein positive reactivity will be added to the reactor core from two sources at the time cooldown-from-hot-shutdown is initiated.

The two reactivity sources are (1), the temperature effect

. due to an overall negative isothermal temperature coefficient of reactivity, and (2), the poison (xenon) effect due to the decay of xanan-135 below the 100% power i .

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 equilibrium level. This scenario, therefore, represents the greatest operational challenge in meeting the requirement for boration of the RCS and maintaining the shutdown margin required by the Technical Specifications while cooling the plant from hot standby to cold shutdown conditions.

Although this specification is only applicable to Modes 1, 2, 3, and 4, sufficient volume is stored in the BATS to provide for boration to Mode 5 (Cold Shutdown).

2.2.1.2 Operating Modes 1, 2, 3, and 4 -

Peak Xenon Scenario A second scenario has been considered in this study. In this case, the bounding assumptions in Section 2.2.1.1 have been modified to cover the condition of peak xenon in the core at the time cooldown is initiated. Additionally, to ensure applicability for the entire fuel cycle, a conservative cooldown scec.ario has been devised which incorporates the maximum increase in RCS boron concentration which the operators must achieve in order to maintain an adequate shutdown margin at the most limiting time in the fuel cycle. Such a limiting scenario is as follows:

1. Conservative core physics parameters are used to determine both the concentration and the volume of boric acid solution which must be provided from the BATS during plant cooldown. As in the equilibrium xenon scenario (Section 2.2.2.1), one case has been examined, with the initial boron concentration equal to zero (0) ppm, with xenon concentration in the core at ,

. the post-trip peak at the time cooldown is initiated. !

EOL moderator cooldown effects are used to maximize the reactivity change during the plant cooldown.

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l BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 EOL values of inverse boron worth (IBW) were used in combination with EOL moderator reactivity insertion rates, normalized to the most Negative Technical Specification Moderator Temperature Coefficient (MTC) limit, since it is known that this yields results that are more limiting than any actual combination of MTC and IBW values throughout the fuel cycle. These assumptions assure that the requirements for minimum BAT volume and boron concentration conservatively bound all plant cooldowns during core life.

2. The most reactive rod is stuck in the full out position.

3. Prior to time zero, the plant is operating at 100%

power, with core xenon concentration at the 100% power equilibrium level.

4. There is zero RCS leakage.

5. At tine zero (t=0), the plant is shut down and held in the hot, zero power condition (547*F and 2250 paia) for approximately 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , at which time the xenon transient after shutdown will have reached its peak.

During this interval, the plant is diluted by 140 ppm to zero ppm boron. (Reference 4.4). This dilution is the maximum possible at EOL during thin time period. '

6. For conservatism, reactor coolant avetage temperature has been assumed to be 547*F. At time m 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , with core xenon at the post-shutdown peak, a cooldown-to- ,

cold-shutdown is initiated.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 The peak xenon scenario described herein has been used to define, for plant administrative procedures, the volume of borated water which must be available in the two BATS in the event that the plant operating staff intends to maintain the criticality at hot, zero power conditions for seven hours by deborating to compensate for xenon buildup. The scenario is postulated to account for the following:

1. Conditions exist which cause the operating , staff to hold the plant at hot standby conditions,'and

2. During this interval, core xenon concentration peaks.

For the ensuing cooldown, the two elements which add positive reactivity to the core are considered in this analysis. The plant must be borated to maintain the required shutdown margin as core xenon decays to the equilibrium level. When cooldown is initiated, additional boration will take place as makeup from the BAT and RWST is added to compensate for coolant contraction.

2.2.1.3 Operational Modes 5 and 6 The methodology developed to determine the boration requirements for Modes 5 and 6 differs from the method used in previous refueling cycles. Consistent with the new methodology, boration of the RCS is performed concurrently with cooldown. Concentrated boric acid is added during the cooldown evolution as part of normal system makeup. To employ this methodology, the exact boron concentration required in the RCS must be known throughout the temperature l range during the cooldown process.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 The following scenario was developed to identify the most limiting cooldown transient for Modes 5 and 6.

1. EOL conditions are assumed, with the initial boron concentration in the reactor coolant at the level necessary to provide a shutdown margin of 1.0% Ak/k at 200 F and with a xenon free core. EOL MTC effects are used to maximize the reactivity change during the plant cooldown. IBW data at EOL were used in conjunction with EOL MTC reactivity insertion rates normalized to the most Negative Technical Specification MTC limit, since it is known that this yields results more limiting than does any actual combination of MTC and IBW values throughout the fuel cycle.

2. The most reactive rod is stuck in the full out position.

3. There is zero RCS leakage.

4. RCS feed-and-bleed can be used to increase boron concentration.

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5. RCS makeup is supplied either from the RWST alone or from a blended combination of makeup from the BAT and the Demineralized Water Storage Tank (DWST).

6. The most limiting scenario for boration in Modes 5 and 6 requires that a shutdown margin of 1.0% Ak/k be o maintained during the cooldown from 200*F to 135'F.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 l

In Mode 6, with the reactor vessel head detensioned or removed, the boron concentration in the RCS, the refueling l canal, and the refueling cavity must be maintained at the most restrictive of the following two reactivity conditions:

a. k,n of 50.95 or less, which includes a 1% Ak/k allowance for uncertainties, or

b. A boron concentration a2000 ppm, which includes a 50 ppm allowance for uncertainties.

f If the required shutdown margin for Mode 6 is not satisfied, the current TS 3.9.1 requires an immediate suspension of core alteration or of positive reactivity addition and initiation of boration at a rate a10 gpm of a solution containing a20,000 ppm boron, to be maintained until the required concentration has been restored. The rate at which borated solution is to be added in this case must be increased in. proportion to the decrease in the concentration of the solution in the BATS.

TS 3.1.2.1 requires that a flow path from either the RWST or at least one BAT be available to meet this requirement.

2.2.2 Imoact of Cooldown Rate As discussed in the previous section, a conservative cooldown scenario was selected for use in determining the boron concentration levels required in the RCS. These concentration results were then used to define the minimum

. Technical Specification BAT tank inventory requirements.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNIC 3L BASES AND OPERATIONAL ANALYSIS REV. 00 _

In the equilibrium xenon scenario for Modes 1, 2, 3, and 4, positive reactivity was added concurrently from two sources at the time that plant cooldown from hot standby was initiated. The component resulting from an overall negative isothermal temperature coefficient of reactivity is independent of time but is directly dependent on the change in coolant temperature. In contrast, the component resulting from the decay of xenon-135 below the equilibrium value at 100% power is independent of temperature but is directly dependent on time. As a result, for a given temperature decrease, a slow cooldown rate vill require the addition of more boron to the reactor coolant than will a fast cooldown rate, since compensation must be provided for more positive reactivity due to xenon decay.

A maximum allowable cooldown rate of 100*F/hr is established in Salem Technical Specification 3/4.4.9; however, there is an administrative limit of 50*F/hr. The required boron concentration as a function of temperature during a plant cooldown is shown graphically in Figure 2-2. The bases for Technical Specifications 3.1.2.7 (Unit 1) and 3.1.2.5 (Unit

2) include the consideration of a cooldown following xenon decay. As a result, boration requirements are independent of cooldown rate for the analysis of Mode 5.

An effective cooldown rate of 10*F/hr was assumed for tae determination of the required volume of boric acid solution and the boron concentration of that solution in the BATS during Modes 1, 2, 3, and 4; these calculations establish the Technical Specification limits for these parameters.

This slow cooldown rate was selected to ensure that the required volume of boric acid solution was chosen ABB Combustion Engineering Nuclear Services Page 20 of 133

DORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 conservatively. As shown in Table 2-2, taking the plant from hot standby to cold shutdown (a change of 347 F) requires 34.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , including an initial delay at hot standby of 4.0 hours0 days 0 hours 0 weeks 0 months and an additional 13.35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months for added conservatism. An effective cooldown rate of 10.0 F/hr is thereby maintained in cooling the plant from an average coolant temperature of 547*F to an average coolant temperature of 200*F in 34.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months . This scenario will conservatively bound cooldowns that occur earlier and/or at higher cooldown rates.

The above scenario bounds the reactivity effects of the BTP 5-1 cooldown. It is assumed in the BTP 5-1 scenario that Safety Grade plant equipment will be capable of bringing the RCS to RHRS entry conditions within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months after cooldown is initiated.

2.2.3 Acolicability to Future Reload Cycles To ensure that the current analysis will be valid for future cycles, data provided by Salem conservatively bounding both Units 1 and 2 was utilized in the analysis. It is anticipated that the physics data used in this analysis will bound future fuel cycles of similar reload cores unless changes are made to the fuels related Technical l Specifications.

Appendix 4 contains the bounding physics assumptions used to produce the required boron concentration values. As long as the input is-more conservative than the physics parameters

. used in this analysis, the values generated in this analysis and presented in this report will bound the boron concentration values for future reload cycles.

ABB Combustion Engineering Nuclear Services Page 21 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIB REY. 00 2.2.4 Boron Mixinc in the RCS and in_the Pressurizer A constant pressurizer level was assumed throughout the cooldown calculations described in Sections 2.3 and 2.4, i.e., plant operators charged to the RCS only as necessary to makeup for coolant contraction. In this situation, the driving force for the mixing of fluid between the RCS and the pressurizar is small.

As a conservatism, complete mixing was assumed between all makeup fluid added to the reactor coolant system through the loop charging nozzles and the pressurizer. Further, system pressure must be reduced during the plant cooldown process, as indicated in Section 2.4. This pressure reduction is necessary to ensure that the Reactor Vessel pressure-Temperature limits are not violated; it is also required since the RHRS is a low pressure system and is normally aligned at or below an RCS pressure not greater than 375 psig; in this analysis, realignment was assumed to occur at '

a pressure of 350 psia. During a natural circulation cooldown, this depressurization is typically performed using the auxiliary pressurizer spray system. For additional conservatism, boron added to the pressurizer via the spray ,

system in Modes 1, 2, 3, and 4 was assumed to remain in the pressurizar and thus to be unavailable for mixing with the fluid in the remainder of the RCS. ~~~ '" '

e ABB Combustion Engineering Nuclear Services Page 22 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 2.3 BORATED WATER SOURCES - SHUTDOWN (MODES 5 AND 6) 2.3.1 Boration Recuirements for Modes 5 and 6 As stated in the plant Technical Specifications, a boration capacity providing a shutdown margin of 1.0% Ak/k following xenon decay is required at temperatures less than or equal to 200 F. This boration capability is sufficient to provide the required shutdown margin during a plant cooldown from 200 F to 135'F.

The required RCS boron concentrations were determined on this basis for temperatures of 200*F and 135'F, using conservative core physics data furnished by Salem (Reference 4.5). Intermediate points were determined by linear interpolation. The data for a Mode 5 and 6 cooldown are given in Table 2-3 and are plotted as the required shutdown curve in Figures 2-3 and 2-4. Note in Table 2-3 that a l total increase in boron concentration of 83.3 ppm is required for the plant cooldown from 200*F to 135*F in Modes l 5 and 6.

l 2.3.2 Assumotions Used in the Analysis of Modes 5 and 6 l

A complete list of assumptions and initial conditions used I in calculating the minimum BAT inventory requirements for l

Modes 5 and 6 is contained in Table 2-4. In the process of taking the plant from hot standby to cold shutdown, the RHRS will normally be aligned after entering Mode 4, i.e., when the RCS temperature and pressure have been lowered to I

. approximately 350*F and 375 psig. For conservatism, in this analysis the RHRS operating pressure is assumed to be 350 psia. As shown in the next section, the total system ,

ABB Combustion Engineering Nuclear Services ,

Page.23 of 133

l BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 volume, i.e., RCS volume, plus pressurizer (PZR) volume, plus RHRS volume, must be known for the analysis of Modes 5 and 6 cooldowns. The exact volumes of each of these have-been determined for use in this analysis to establish the -

BAT inventory requirements. The volume of the RHRS has been determined in Reference 4.6.

The system volume used in the calculation is as follows:

(RCS volume) + (PZR volume at 0% power) + (RHRS Volume) or (10,812 f t ) + (500 f t ) + (1700 ft ) = 13,012 ft 2.3.3 Modes 5 and 6 - Analysis and Outline As noted in Section 2.3.1, the required boration capacity is based upon providing shutdown margins of 1.0*< Ak/k following xenon decay and a plant cooldown from 200 F to 135"F. The operating scenario employed in determining the required RCS boron concentration and ensuring that proper shutdown margin will be maintained is as follows:

A. The systems are initially at a temperature and pressure of 200*F and 350 psia. At EOL, the initial boron concentration in the RCS, pressurizer, and the RHRS is 893.9 ppm boron. The RHRS is aligned and in operation.

i The core is xenon-free.

. B. With charging limited to makeup for coolant contracti'on only, the RWST alone does not provide sufficient boron ,

to compensate for the pc4;tive reactivity added during ABB Combustion Engineering Nuclear Services Page 24 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 the cooldown by the moderator coefficient. Using borated water from the RWST (boron concentration = 2300 ppm), a system feed-and-bleed must be conducted to increase boron concentration in the RCS before proceeding with the cooldown below 200 F. This initial feed-and-bleed (60 minutes at 75 gpm) to approximately 960.0 ppm ensures that the RCS boron concentration is maintained above the level required to provide adequate shutdown margin while the plant is cooled from 200 F to 135 F.

C. A plant cooldown is then performed from an average coolant temperature of 200*F to an average temperature of 135 . Makeup water from the RWST (2300 ppm boron) is charged to the RCS as necessary to compensate for.

coolant contraction during the cooldown.

D. Alternatively, with the BATS available, makeup may be supplied by blending boric acid solution from the BATS with demineralized water from the PWSTs.

2.3.4 Modes 5 and 6 - Cooldown Makeup from the RWST From Equation 2.0 of Appendix 2 and the conversion factor that is derived in Appendix 3, the initial boric acid mass in the system can be calculated as follows:

ABB Combustion Engineering Nuclear Services Page 25 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 At EOL, 89 3 . 9 ppm ' 12,512.0 ft3 '

, 500.0 ft3 17 4 8. 34 ppm /wt. % 0. 01662 f t /lb,, 0.01912 fC 3/lb,,,,

3

(

100 - [ ( 893. 9 ppm) / (17 4 8. 34 ppm / wt. %) ]

or i

Hu = 4,003.3 lb, boric acid (EOL)

The initial total system mass of 782,981.8 lb, 'given in Tables 2-5 and 2-6 was obtained as follows:

Minic = (Initial Boric Acid) + (Initial RCS Water Mass) i

+ (Initial RHRS Water Mass) + (Pressurizer Water Mass)

N g"j e = 4 0 0 3 . 3 lb, +

(10,812 ft3 + 17 00 f t3) . (500.0 f t 3)

'(0. 0166 2 f c 3/lb,) -(0.01912 f t /lb,)

3 Thus, i

Mfnic =

7 82,9 81. 8 lb, (EOL) i The boron concentration at the end of the feed-and-bleed l evolution is determined by an iterative calculation. This .{

endpoint concentration then permits charging (from the RWST)

only as required to compensate for coolant contraction and i ensures that the final concentration provides the required shutdown margin at the end of the cooldown, (135*F).

l ABB Combustion Engineering Nuclear Services Page 26 of 133 4

. . ~ . -

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BABES AND OPERATIONAL ANALYSIS REV. 00 As indicated above, the initial boron concentration is equal to 893.9 ppm; the mass of boric acid in the system is 4,003.3 lb,; and the total system mass (Mm) is equal to 782,981.8 l b, . The volume of water and the pressure in the pressurizer are held constant at 500.0 ft3 and 350 psia, respectively, and complete mixing is assumed between the PZR and the RCS, as dir, cussed previously. The boron concentration in the RWST is 2300 ppm.

Equation 9.0 of Appendix 1 was used to determine the time and volume required to complete the initial feed-and-bleed evolution.

Defining the time constant as follows, (m,) ,,+ (m,) aup,+ (m,)na (d!) in

'10,812 ft3 + 1,7 0 0 f t 3' f '

500.0 ft3 T =

3 O.01662 ft /lb, , y 0. 01912 ft3 /lb,,

(75 gal / min) x (8.329 lb,/ gal) m Therefore, T = 1, 2 47 . 01 minutes (at 200 F and 350 psia)

The feed-and-bleed equation is:

I .t C(t) = Co (e ') + Cjn (1-e ')

l l ABB Combustion Engineering Nuclear Services Page 27 of 133

(

l .

I l

u l

l BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Conducting a feed-and-bleed operation with one charging pump delivering 75 gpm and letdown flow equal to 75 gpm, 60 minutes are required to reach a boron concentration of 960.0 ppm in the RCS. This equates to a feed-and-bleed volume of 4,500 gallons.

The volume and concentration of makeup required was then '

calculated for each 10 F increment of cooldown from 200*F to 135*F, and the results are tabulated in Table 2-5. The BACR Code (Reference 4.7) and the following equations were used to perform this analysis:

Shrinkage Mass = (12,512 f t 3) 11 s Vf vg hrinkage Mass RWST Wa ter Volume (@ 7 0* F) ,

8. 329 0 lb,/ gal m Boric Acid Added = (RWST Volume) x 0.11103 lb,/ gal II Total Boric Acid =

Initial Boric Acid + Boric Acid Added Total System Mass = Initial System Mass + Shrinkage Mass

+ Boric Acid Added Final Concentration =

(Total Boric Acid) (100) (1748.34)(')

Total System Mass Reference 4.8

$ Appendix 2 Appendix 3 ABB Combustion Engineering Nuclear Services Page 28 of 133

I BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 l

The data are plotted as the actual shutdown curve in Figure 2-3. As shown in the figure, a shutdown margin greater than that required by the Technical Specifications was maintained throughout the evaluation. A minimum RWST concentration of 2300 ppm boron is therefore specified to ensure that the proper shutdown margin is maintained.

2.3.5 RWST Boration Reauirements - Modes 5 and 6 Four factors must be considered in determining the RWST water volume required to cool the plant from 200*F to 135 F while maintaining the required shutdown margin. These factors are as follows:

(1) Initial feed-and-bleed volume (2) Coolant contraction volume (3) An adjustment to insure conservatism '

(4) Roundup to next 100 gallons Therefore, the total required volume is as follows:

Vol me7 = Feed-and-Bleed + Shrinkage + Conserva tism or Valmg7 = 4 , 5 0 0 gal + 2 . n 29 . 6 gal + 5 00 gal ABB Combustion Engineering Nuclear Services Page 29 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 and Volgm = 7,029.6 gallons Round upwards to nearest 100 gallons:

Volag = 7,100 gallons Volume allowance for level instrument uncertainties: ,

Vol inst = 8,550 gallons Volume below lower instrument tap:

Vol linst = 21,210 gallons The sum of these volumes yields a required volume of 36,860 gallons. Rounded upwards to the nearest 1000 gallons, this becomes:

i Volym = 37,000 gallons The Bases number will reflect this new requirement.

l l.

l ABB Combustion Engineering Nuclear Services Page .30 of 133 l

~ .-. . _ _ _ _ _ - - _ _ _ _ _ - - - _ - _ _ _ _ - _ _ _ _ _ - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ - _ _ _ - _

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 2.3.6 Modes 5 and 6 - Cooldown. Usina BATS BAT Storace Reauirements The analysis of a cooldown from 200*F to 135'F using makeup from the BATS is described in this section. Initial conditions and assumptions used in this analysis are identical to those used in the analysis of cooldown using the RWST and are listed in Table 2-4. The results are shown in Table 2-6.

The results of the calculations for system cooldown in Modes 5 and 6, from 200*F and 350 psia to 135*F and 350 psia and using boric acid from the BATS for makeup, are given in Table 2-6. These data are plotted as the actual shutdown curve in Figure 2-4. As shown in the figure, a shutdown margin greater than that required by the Technical Specifications is maintained throughout the transient.

For Modes 5 and 6, a minimum BAT concentration of 6560 ppm boron (equivalent to 3.75 weight percent boric acid) is therefore prescribed in TS 3.1.2.7 (Unit 1) and TS 3.1.2.5 (Unit 2).

The minimum usable volume to be prescribed in the Technical Specifications is 2,600 gallons. This volume was determined as follows:

Makeup volume'" = 2,029.6 gallons Additional volume = 500.0 gallons for Conservatism Total = 2,529.6 gallons e

Round up to nearest 100 gallons = 2,600.0 gallons Total of values in BAT Volume column in Table 2-6 ABB Cornbustion Engineering Nuclear Services Page 31 of 133-

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 2.4 BORATED WATER SOURCES - OPERATING (MODES 1, 2, 3 and 4) 2.4.1 Boration Recuirements for Modes 1, 2, 3, and 4 A shutdown margin 2 1.6% Ak/k must be maintained throughout j the cooldown. From this basis, the required RCS boron concentrations were determined using conservative core physics data provided by Salem (Reference 4.3) and the limiting cooldown scenario outlined in Section 2.2.1.1 above. These data are given in Table 2-7 and are plotted as the Required Shutdown curve in Figure 2-5.

The results of the analysis are shown in Table 2-9 and are plotted as the Actual 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 calculating the minimum BAT inventory required for Modes 1, 2, 3 and 4 is contained in Table 2-8. As stated in Section 2.2.4, all fluid added to the RCS via the loop charging nozzles is assumed to mix completely and instantaneously with the RCS and the PZR. In line with this assumption, the mass of water in the PZR was added to and treated as part of the total mass of water in the RCS, and this total was then used in calculating system boron concentration. Boron concentration in terms of weight fraction is defined as follows:

Baron Concentration = Mass of Baron in System Total System Mass ABB Combustion Engineering Nuclear Services Page 32 of 133 7.

. . . _ - - . - - - -. .- .. . - - - - . - - . ~-

'l l

l

-l i

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606

. TECHNICAL BASES AND OPERATIONAL ANALYSIS. REV. 00 !

where,' if complete mixing is assumed between the-RCS-and the ,

PZR, the total system mass is the sum of the mass-of boron !

in the system, the mass of water in the RCS, and the mass of _ ,

water in the PZR.

For the EOL case analyzed, the initial total system mass of 527,311.7 lb, in Tables 2-9 through 2-33 was calculated as :

follows:

r f

Total Mass =: Initial Baron Mass + Initial RCS Water Mass i

+ Initial PZR Water Mass or ;

-t 10,812 ft3 500.0 ft3 M*

= 0+ ,

3 0.021251 ft /lbj" =0.026975 ft 3 /lbj" - [

.t

= 5 27 , 311. 7 lb, ;

f k

i 6

Specific volume of compressed water at 547'F and 2250 psia Specific volume of saturated water at 2250 psia ABB Combustion Engineering Nuclear Services Page 33 of 133 9

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 2.4.3 Modes 1, 2. 3, and 4 Analysis Results-Equilibrium Xenon Scenario As previously stated, the boration capacity required to reduce the average coolant temperature to or below 200 F is determined by the requirement for providing a shutdown margin of at least 1.6% Ak/k, after xenon decay and a plant cooldown to greater than 200*F from normal operating conditions. Assuming the initial conditions outlined in Table 2-8, a plant cooldown to an RCS average temperature of 200 F is conducted, starting f, rom an initial RCS average temperature of 547 F.

Charging to the RCS is performed only as necessary to compensate for coolant contraction. Initially, the charging pumps will take suction from the BAT; when the BAT has been drained, the charging pump suction is aligned to the RWST for the duration of the cooldown.

The calculated RCS boron concentration versus temperature for plant cooldown and depressurization from 547 F and 2250 psia to 200 F and 350 psia, with a boric acid concentration of 3.75 weight percent in the BAT and a boron concentration in the RWST of 2300 ppm, is giver. in Table 2-9.

The required concentration as a function of temperature is given in Table 2-7 and is plotted on Figure 2-5 as the Required Concentration curve.

For the EOL case analyzed, the results of these calculations

. are plotted as the actual concentration curve in Figure 2-5.

The exact temperature at which the charging pump suction was transf erred from the BATS to - " RWST was determined using l ABB Combustion Engineering Nuclear Services Page 34 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 an iterative calculation; in this way, the smallest BAT j volume necessary to maintain the required shutdown margin was determined for the given set of tank concentrations. At all times, the RCS boron concentration is greater than that necessary for the required shutdown margin during the cooldown.

Note in Table 2-7 that the required shutdown margin drops from 1.6% Ak/k to 1.0% Ak/k at an average coolant temperature of 200*F. Following xenon decay, with the <

coolant at 200 F, the final concentration required in the RCS is 893.9 ppm boron. Using the scenario outlined above, the final system concentration will always be greater than this amount. A detailed parametric analysis was performed for the Modes 1, 2, 3, and 4 Technical Specification (Specification 3.1.2.8 (Unit 1) and 3.1.2.6 (Unit 2)). In this study, BAT concentration was varied from 6560 ppm boron (3.75 weight percent boric acid) to 6990 ppm boron (4.0 weight percent boric acid) and RWST concentration was varied from 2300 ppm boron to 2500 ppm boron.

The results are shown in Tables 2-9 through 2-33 for the EOL case analyzed.

The following equations were used to obtain the values in these tables:

r s A A Shrinkage Mass = (10,812)

. < Vr V 4 ,

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALi3IS REV. 00 hrinkage Mass BAT Vol . =

(8.3290 lb,/ gal) m

.NST Vol = hrink ge Mass (8. 3290 lb,/ gal)

Boric Acid Added =

(BAT Vol) x (Mass of Boric Acid / gal) W or Boric Acid Added = (RWST Vol) x (Mass of Boric Acid / gal)

Total Boric Acid =

(Initial Boric Acid) + (Boric Acid Added)

Prior to RHRS alignment, Total System Mass = (RCS Water Mass) + (PZR Water Mass)"'

+ (Total boric acid)

Final Concentra tion = (Total Boric Acid) (100) (1748.34)

(Total System Mass) e

Density of Water at 70*F

See Appendix 2 PZR Water Mass = (500.0 f t') - v, at applicable p.

ABB Combustion Engineering Nuclear Services Page .36 of'133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 The value of the total system mass at any temperature and pressure in Tables 2-9 through 2-33 may be obtained as follows:

Meae = RCS Water Mass + PZR Water Mass + Total Boric Acid Mass + RHRS Water Mass (when on RHRS)

For example, the Total System Mass at 200'F and 350 psia in-Table 2-9 is as follows:

10,812 ft3 500.0 ft) 1,700 ft3 M = . .

0 . 016 6 2 f t /lb," 3 3

0. 01912 f t 3/Jbj213 0. 01662 fC3 /lb,

+ 4,3 5G 8 lb, or N eoe =

7 8 3,13 5. 4 lb, For the EOL case analyzed, the calculated concentration values given in Tables 2-9 through 2-33 were compared to the values in Table 2-7, which shows the concentrations which.

must be maintained at all temperatures during cooldown through the range from 547'F to 200'F. In each case, the actual system boron concentration was greater than that necessary for the required shutdown margin.

{ v,of compressed water @ 200'F and 350 paia vr of saturated water 0 350 psia ABB Combustion Engineering Nuclear Services Page 37 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 To set the minimum Technical Specification BAT volume ,

corresponding to the various BAT and RWST concentrations, the makeup volumes from Table 2-9 through 2-33 were combined into Table 2-34. To establish the required volumes which :

must be stored in the BATS, the higher boration volumes were adjusted by adding 100 gallons for conservatism and rounding the result upwards to the nearest 50 gallons.

These results are given in Table 2-35 and are illustrated in Figure 2-6, which shows the boration volumes, and in Figure 2-7, which shows the required volume which must be available in the BAT.

' 4.4

. Modes 1, 2. 3. and 4 Analysis Results -

Peak Xenon Scenario The initial conditions are identical to those for the equilibrium xenon analysis in Section 2.3.3 and are given in ,

Table 2-8. The plant is held at the hot, zero power temperature of 547 F. The required boron concentration data as a function of temperature for the peak _ xenon scenario were provided in Reference 4.3. These data points were adjusted upwards by 140 ppm to describe a conservative late-in-life scenario. The data are shown in Table 2-36 and are plotted as the Required Concentration curve in Figure 2-8.

i For the cooldown from 547"F to 200*F in the peak xenon scenario, charging to the RCS is performed only as necessary to compensate for coolant contraction. Initially, the i charging pumps will take suction from the BAT; an iterative

. calculation is then performed to determine the temperature l at which the charging pump suction is to be realigned to the RWST, to avoid overborating *he RCS during cooldown.

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i 1

l J

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 ;

In this way, the smallest BAT volume required to maintain the required shutdown margin throughout the cooldown is established.

The analysis has been performed using near EOL conditions, with an initial RCS baron concentration of zero (0) ppm.

Note in Table 2-36 that the required shutdown margin decreases from 1.6% Ak/k to 1.0% Ak/k at a coolant temperature of 200 F. Following xenon decay, with the coolant temperature at 200 F, the final boron concentration required in the RCS is 1033.9 ppm.

The results are plotted as the Actual Concentration curve in Figure 2-8. At all times, the RCS boron concentration is greater than that necessary for the required shutdown margin during the cooldown.

The equations used in calculating the values in Table 2-37 were identical to those described in Section 2.4.3.

As in Section 2.4.3, the total system mass at any temperature and pressure in Table 2-37 may be obtained as follows:

M,,, = RCS Water Mass + PZR Water Mass

+ Total Boric Acid Mass

+ RHRS Water Mass (when on RHRS)

For example, the Total System Mass at 200 F and 350 psia, with boron concentration at 3041.4 ppm, in Table 2-37 is as e follows:

ABB Combustion Engineering Nuclear Services Page 39 of 133

w BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00-10,812 ft 3 500.0 fc3 17 00 f t 3 y' # , . .

0.01662 fC /lb m 3

0. 01912 f t /lbj")

3

0. 01662 f t /lb, 3

+ 4 , 6 6 7 . 9 lb, or Me ,e = 7 8 3,6 4 6 . 4 lb, The activities involved in bringing the plant to the conditions described by the peak xenon scenario are considered to be unrealistic. Nevertheless the results of the analysis are provided as guidance to the o.nerating staff. Should a situation arise at or near EOL where-it may be deemed desirable to maintain hot, zero power conditions for a sustained period, i.e., several hours, before shutdown, it would be necessary to have a usable BAT inventory of approximately 10,000 gallons of 3.75 wt's boric acid available in the BATS.

2.4.5 Simolification Used Followina RHR.S Initiation The results of the analysis of cooldown and depressurization are given in Tables 2-9 through 2-33 and in Table 2-37. In the cooldown procedure for Salem Units 1 and 2, the RHRS must be aligned to the RCS at a_ temperature of 350*F and a pressure below 375 psig. In this analysis, the RHRS is conservatively assumed to be aligned at'an RCS temperature and pressure of 350 F and 350 psia. Following this alignment, the volume and mar + af the system that the ABB Combustion Engineering Nuclear Services Page 40 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 operator must consider during the subsequent cooldown will be increased by the volume and mass of fluid present in the RHRS. In addition, the total mass of boron in the system will also be increased by the amount of boron in the RHRS prior to alignment. For this analysis, a value of 1700 ft 3 was used for the RHRS volume. In the tables in Section 2.4.3 and 2.4.4, this RHRS volume is added when the system reaches 350 F and 350 psia. The boron concentration in the RHRS is assumed to be equal to that in the RCS at the time the RHRS is brought into service.

ABB Combustion Engineering Nuclear Services Page 41 of 133

- a. a a :, _ u. - . . . .a a a > 2.sx- --w-w,.s.-- .s- = . , ~ . .>w- .m. s-w ,

a>. i > s +1 t

BORIC ACID CONCENTRATION REDUCTION EFFORT- -CEN-606 l

- TECHNICAL BASES AND OPERATIONAL ANALYSIS 'REV. 00 .;

2.5 BORATION SYSTEMS - BASES ,

The BASES section of the Technical Specifications was -j developed to demonstrate the capability of the'boration i system to maintain adequate shutdown margin from all ]

operating conditions. The following change to Bases Section' '!

t 3/4.1.2 of the plant Technical Specifications is proposed: ~ .

t "With the RCS temperature above 200*F, a minim'um of two boron injection flow paths are required to endure single l

functional capability in the event an assumed failure l renders one of the flow paths inoperable. The boration ^i capability of either flow path is sufficient to provide a i SHU'DOWN MARGIN from expected operating conditions of 1.6% i ak/k after xenon decay and cooldown to 200*F. The maximum expected boration capability (minimum baration volume) !

requirement is established to conservatively bound expected 1 operating conditions throughout core operating life.

The analysis assumes that the most reactive control rod is'not

_l inserted into the core. The. maximum expected capability o occurs at EOL from full power equilibrium xenon conditions and requires boric acid solution from the BATS in the >

allowable concentrations and volumes of Technical l Specification Figures 3.1.2.8 (Unit 1)- and 3.1.2. 6 (Unit 2),

plus approximately 41,800 gallons of 2300 ppm barated water :

from the RWST. With the refueling water storage tank as the '

only borated water source, a maximum of 73,800 gallons of. s 2300 ppm borated water is required. However, to be ;

consistent with the ECCS requirements, the RWST is required ;

to have a minimum contained volume of 350,000 gallons for {

., operation in' Modes 1, 2, 3, and 4." I t

e 1

ABB Cornbustion Engineering Nuclear Services Page 42 of 133 ;

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 ,

TECHNICAL DA8E8 AND OPERATIONAL ANALYSIS REV. 00 l Note that the bases were derived for a cooldown-with-letdown !

scenario in which we calculate RWST volume alene or the RWST volume required with the smallest BAT volume being used prior to using the RWST. This is a cooldown beyond the requirements of BTP 5-1.

2.5.1 Derivation of the 73,800 Gallon Volume (RWST)

The required RWST volume of 73,800 gallons was determined as follows:

A. Calculations were performed for a plant cooldown from 547'F and 2250 psia to approximately 350*F and 350 ,

psia, compensating for coolant contraction by charging of 70*F borated water from the RWST, at a concentration of 2300 ppm boron. The boron concentration in the RCS is initially at 0 ppm.

B. The RHRS is aligned to the RCS when the RCS reaches a temperature and pressure of 350*F and 350 psia. The RHRS volume has been determined to be 1700 ft3 , and, at the time of shutdown cooling initiation, the concentration in the RHRS is assumed to be equal to the concentration in the RCS. Typically, the RHRS will be at normal refueling concentration (> 2300 ppm), but the lower value was chosen for added conservatism.

C. Cooldown of the system is continued from 350*F and 350 psia to 200*F and 350 psia, using borated water from the RWST (2300 ppm and 70*F) as necessary to makeup for

. contraction.

D. Using the methodology described in Appendix 1, a feed-ABB Combustion Engineering Nuclear Services Page 43 of 133

l BORIC ACIDECONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 .

and-bleed calculation is performed'until.the boron ;

concentration in the RCS reaches a value not less than-920.8 ppm to ensure that an adequate shutdown margin is maintained during cooldown to 200'F. ,

E. The volumes calculated in paragraphs A through D are '

summed, and the total is then rounded up to the nearest 1000 gallons.

F. RWST volume adjustments of 21,210 gallons that is undetectable due to lower instrument tap location and $

of 8,550 gallons for instrumentation error are added to >

the total from E. above and rounded up'to the nearest 100 gallons, giving a total of 73,800 gallons for cooldown using water from the RWST alone.

This value is contained in Table 2-38 and in the Bases Section 3/4.1.2.

2.5.2 Derivation of the 41,800 Gallon RWST Volume Recuired when the Smallest BAT Volume is Used 1

The RWST volume used after the BAT is used per Technical !

Specification 3.1.2.8 (Unit 1) and 3.1.2.6-(Unit 2) consists ,

of the following parts:

A. Calculations were performed-for.a plant cooldown from 547'F and 2250 psia to approximately 350*F and-350 psia, compensating for coolant-contraction byfcharging.

6,911.3 gallons from the BAT and then with-70*F borated

, water (2300 ppm) from the RWST.. The concentration in- .

the RCS is initially at 0 ppm. Using a O ppm start' will maximize the required RWST volume makeup.

-ABB Combustion Engineering Nuclear Services Page 44 of.133.

. - _ . _ _ _ , _ . . . . _ _ . _ . __m - _ _ . .- m _ . _ . _ _ . . . .

i BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 B. The RHRS is aligned to the RCS when the RCS' reaches a temperature and. pressure of 350'F and 350 psia. As i determined-in Reference 4.6,-the RHRS volume is 1700 e 3

ft , and,.at the time of initiation, the concentration-in the RHRS is assumed to be equal to the concentration in the RCS. Normally, the RHRS will be at refueling concentration (22300 ppm), but the lower value was i chosen for conservatism. .

C. Cooldown of the system is continued from 350'F and 350 psia to 200*F and 350 psia, using borated water from e the RWST (2300 ppm and 70*F) as necessary to makeup for contraction.

D. RWST. volume adjustments of 21,200 gallons (undetectable due to lower instrument tap location) and of.8,550 gallons (for instrumentation error)-are'added to the total from C.'above and rounded up to.the nearest 100 '

gallons, giving a minimum of 41,800 from the'RWST. ,

gallons when the smallest BAT volume is used.

The plant cooldown using water from the BAT'andlthen the RWST as discussed above results in a minimum required RWST-water volume of 41,800 gallons. This value'is derived in' ,

Table 2-39 and is incorporated into Technical Specification >

Bases Section 3/4.1.2.

2.6 ACTION STATEMENTS ON FLOW REQUIREMENTS -

e '

The current Salem. Units 1 and 2 Technical Specifications ~

. -contain action statements-which-require boration from the BATS. Since the concentration of boron in the BATS;will be reduced, an increase'in the etnimum flow rate'isLrequired.

ABB Combustion Engineering Nuclear Services Page 45:of 133 !

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 The increased flow rate is applicable to Technical Specifications 3.1.1.1, 3.1.1.2, 3.9.1, and 3.10.1, as well as in Surveillance Requirement 4.1.2.2 (Unit 2 only in current Technical Specifications).

The current Action Statement is as follows:

"Immediately initiate and continue boration at 2 10 gpm of 20,000 ppm boric acid solution or equivalent."

This boration capability uses the current minimum boric acid concentration in the BAT. The specified flow rate is -

limited by the current indicating range of the flow measurement instrumentation in the boric acid line to the blending tee, which provides an alternate flow path for emergency boration.

To determine the new requirements, the amount of boron added to the system under the existing requirements must be evaluated. Using the methods and equations in Appendix 2,.

the mass of boric acid per gallon of solution is as follows:

CxM y Nba

10 0 - C where: C = Concentration in weight percent boric acid and: F(= 8.13 98 5 lb,/ gallon at 165'F (Reference 4.8)

Therefore:

[1748.34/20,000I8.13985 y', 1 20,000

100 11748.34 1 ABB Combustion Engineering Nuclear Services Page;46 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 and Mu = 1. 0514 3 2b,,,lgallon At a flow rate of 10 gpm, 10.1543 pounds of boric acid are added to the system per minute.

At the new minimum boric acid concentration of 6,560 ppm of boron (3.75 wt% boric acid), one gallon of solu, tion contains 0.32451 pounds of boric acid. The new flow requirement is determined by dividing the current minimum boric acid injection rate by the new minimum concentration, as follows:

= 0' A# l#A""E' F1ow Ra te*"' O.32451 lb/ gal or Flow Ra ce, = 32. 4 gpm which is rounded upwards to Flow Ra ce, = 3 3 gpm Therefore, the new Technical Specification action statements should read as follows:

" Initiate and continue boration at greater than or

, equal to 33 gpm of a solution containing greater than or equal to 6560 ppm boron or its equivalent."

ABB Combustion Engineering Nuclear Services Page 47 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 2-1 Boric Acid Solubility in Water"'

Temperature H,BO

(*F) (wt.%)

32.0 2.52 41.0 2.98 50.0 3.49 59.0 4.08 68.0 4.72 77.0 5.46 86.0 6.23 95.0 7.12 104.0 8.08 113.0 9.12 122.0 10.27 131.0 11.55 140.0 12.97 149.0 14.42 158.0 15.75 167.0 17.41 176.0 19.10 ,

t Reference 4.2 ABB Combustion Engineering Nuclear Services Page:48 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 7'ECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 2-2 !

Time Intervals for Determining an Effective

~

RCS CoOldown Rate InitialyotStandbyhold Period 4.00 hours0 days 0 hours 0 weeks 0 months ,.

Plant Cooldown from 547 F to 200 F (2) 17.35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months Additional Conservatism 13.35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months Total 34.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months e

i r

4-hours per requirements of BTP RSB 5-1

An average cooldown rate of 20"F/hr is assumed for this analysis.

Integrated Operating Procedure IOP-6, " Hot Standby to Cold Shutdown", specifies a cooldwn rate _ less than 100*F/hr with an administrative limit of 50 ' .

ABB Combustion Engineering Nuclear Services Page 49 of 133

i DORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS' REV. 00 Table 2-3 Required Baron Concentration for a Plant Cooldown Modes 5 and 6 Temperature Concentration

(* F) (ppm Boron)

Equilibrium Xenon EOL 200"' 320.8 200'2' 893.9 190 906.5 180 920.2 170 933.9 160 945.6 150 958.9 9

140 970.8 ,

135 977.2 l

Shutdown Margin = 1.6 Ak/k

Shutdown Margin = 1.0 Ak/k ABB Combustion Engineering Nuclear Services Page.50 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-6o6 TECHNICAL BASES AND CPERATIONAL ANALYSIS REV. oo Table 2-4 initial Conditions and Assumptions Used in the Modes 5 and 6 Calculation

a. Reactor Coolant System Volume 10,812 ft'

h. Reactor Coolant System Pressure 350 psia"'

c. Pressurizer Volume (@ 0% Power Level) 500.0 ft'

d. Pressurizer is at Saturation -

e. Reactor Coolant System Leakage O

f. Boration Source Concentration Refueling Water Storage Tank (RWST) 2300 ppm boron Boric Acid Storage Tank (BAT) 3.75 wt% BoricAcid

g. Boration Source Temperature 70'F

h. Initial RCS Concentration (EOL) 893.9 ppm boron

j. Complete and instantaneous Mixing -----

Between Pressurizet and RCS

k. Constant PZR Level Maintained, Charging to ----

Compensate for Coolant Contraction

1. RHRS Volume 1700 ft'

m. Total System Volume (RCS + RHRS + PZR) 13,012.0 f t' f

e

RHRS entry pressure is assumed to be 350 psia for conservatism-ABB Combustion Engineering Nuclear Services Page 51 of 133

. BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 TABLE 2-5 Salem Nuclear Generating Station Pbnt Cooldown from 200 F to 135 *F Feed & Bleed Using the RWST @ 2300 ppm Boric Acid 70 F AVG. SYS. TEMP. PZR SPECIFIC SHRitKAGE RWST B/A TOTAL B/A TOTAL FINALCONC.

PFESS VOLUME MASS VOLUAE ADDED SYS. MASS Ti Ti (cu.ft./lbrn) (cu.ft/lbm)

(*F) (9 (psia) Vi Vf (Ibm) (gal) (Ibm) (Ibm) (Ibrn) (ppm boron) 200 200 350 0.01662 0.01662 0.0 0.0 0.0 4,0(X3.3 782,981.8 893.9 Feed and Bleed from RWST 60 Minutesat 75 GPM 200 200 350 0.01662 0.01662 0.0 0.0 0.0 4,300.7 783,279.3 9010 200 190 350 0.01662 0.01655 3,184.2 382.3 42.4 4,343.2 786,505.9 965.5 190 180 350 0.01655 0.01649 2,750.8 330.3 36.7 4,379.8 789,293.3 970.2 180 170 350 0.01649 0.01643 2,770.9 332.7 36.9 4,416.8 792,101 2 974.9 170 100 350 0.01643 0.01638 2,324.6 279.1 31.0 4,447.8 794,456.7 978.8 100 150 350 0.01638 0.01632 2,808.3 337.2 37.4 4,485.2 797,302.5 983.5 150 135 350 0.01632 0.01626 3.065.7 368.1 40.9 4,526.1 800,409.1 988.6 Shrinkage Volume = 2029.6 Gallons Feed-and-Bleed Volume = 4500.0 Gallons 75 GPM for 60 Minutes RWST Total Volume = 6529.6 Gallons f BACR Version 2 ABB Combustion Engineering Nuclear Services Page 52 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 TABLE 2-6 Salem NuclearGenerating Station Plant Cooldown - Modes 4 & 5 BAT @ 3.75 wt.% Boric Acid 70 T 200 T to 135 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT B/A TOTAL B/A TOTAL FINAL CONC.

TEMPERATURE PRESS. VOLUME MASS VOLUME ADDED SYS. MASS

, Ti Tf Vi Vf (P) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (Ibm) (gaf) (Ibm) (Ibm) (bm) (ppm boron) 200 200 350 0.01662 0.01662 0.0 0.0 0.0 4,003.3 782,981.8 893.9 200 190 350 0.01662 0.01655 3,184.2 382.3 124.1 4,127.3 786,290.0 917.7 190 180 350 0.01655 0.01649 2,750.8 330.3 107.2 4,234.5 789,148.0 938.1 180 170 350 0.01649 0.01643 2,770.9 332.7 108.0 4,342.5 792,026.9 958.6 170 160 350 0.01643 0.01638 2,324.6 279.1 90.6 4,433.0 794,442.0 975.6 160 150 350 0.01638 0.01632 2,808.3 337.2 109.4 4,542.4 797,359.7 996.0 150 135 350 0.01632 0.01626 3.065.7 368.1 119.4 4,661.9 800,544.9 1,018.1 TOTAL BAT VOLUME = 2,029.6 G ALLONS l Bacavenen 2 ABB Combustion Engineering Nuclear Services Page 53 of 133

, - =. - - . . .

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 i TECHNICAL BASES AND OPERATIONAL ANALYSIS- REV. 00 l

1 Table 2-7 Required Boron Concentration for a Cooldown From 547'F to 200*F ;

Equilibrium Xenon Scenario l Temperature EOL

'F Concentration ;

(ppm boron) '

mmmmmmmmmmmmmm- !

547 -79.0 637 -15.4 527 42.3 517 96.0 >

507 148.6 497 191.8 487 237.8 477 281.9 [

487 315.2 457 353.8 ;

447 385.0 +

437 418.9 427 451.7 417 478.8 407 608 0 397 533.4 387 560.1 l 377 686.1 ;

367 608.4 357 632.3 347 653.6

'337- 675.6 327 697.3

[

317 716.4 307 736.7 297 755.0 287 774.1 277 792.8 267 811.4 ,

257 629.6 247 843.9 237 861.1 227 878.2 e 217 892.9 e 207 909.0 200 920.8

^

200* 893.9

" ~

After Shutdown Margin Change from 1.6%Ak/k to 1.0% Ak/k ABB Comb'ustion' Engineering Nuclear Services Page 54_of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 2-8 initial Conditions and Assumptions Used in the Modes 1,2,3, and 4 Calculation

a. Reactor Coolant System Volume 10,812 ft 3

b. Reactor Coolant System Pressure 2250 psia

c. Pressurizer Volume (9 0% Power Level) '500.0 ft3

d. Pressurizer is at Saturation -----

e. Reactor Coolant System Leakage O

f. RCS Depresurization Performed as Shown -----

in Tables 2-9 through 2-33

g. Initial RCS and PZR Concentration -

EOL 0 ppm boron

i. Complete and Instantaneous Mixing -----

Between Pressurizer and RCS

j. Constant PZR Level Maintained, Charging -----

to Compensate for Coolant Contraction

k. Boron Concentration in RCS equal to -----

Concentration in RHRS at Time of Residual Heat Removal Initiation i 1. Boration Source Temperature -----

I Refueling Water Storage Tank (RWST) 70*F Boric Acid Tank (BAT) 70*F

m. RHRS Volume 1,700 ft3 3

n. Total System Volume (RCS+PZR+RHRS) 13,012 ft l

l .

ABB Combustion Engineering Nuclear Services Page SS of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-9 Salem Nuclear Generating Station Plant Cooldown from BAT 3.75 wt. % Boric Acid 70 T 547 T to 200 T RWST 2300 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWSi B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tf Vi VI (T) (T) (psia) (cu.ft/lbm) (cu.ftdibm) (Ibm) (gal) (gal) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 311.2 311.2 535,611.2 101.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 369.9 681.2 545,476.3l 218.3 520 510 2250 0.02055 0.02031 6,089.2 731,1 0.0 237.2 918.4 551,802.7 291.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 227.1 1,145.5 557,859.4 359.0 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 210.8 1,356.4 563,481.8 420.8 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 215.1 1,571.5 569,218.4 482.7 480 470 2250 0.01969 0.01951 5,3 8.2 625.3 0.0 202.9 1,774.4 574,629.5 539.9 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 201.2 1,975.6 579,993.8 595.5 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 193.5 2,169.0 585,152.6 . 648.1 450 432 2250 0.01916 0.01887 8,494.7 1,019.9 0.0 331.0 2,500.0 593,978.3 735.9 432 420 2250 0.01887 0.01869 5,548.6 0.0 666.2 74.0 2,574.0 599,600.8 750.5 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 60.3 2,634.3 604,184.2 762.3 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 54.9 2,689.1 608,354.9 772.8 400 380 2250 0.01842 0.01816 8,408.4 0.0 1,009.5 112.1 2,801.2 616,875.3 793.9 380 370 2250 0.01816 0.01804 3,962.6 0.0 475.8 52.8 2,854.0 620,890.7 803.7 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 53.5 2,907.6 624,959.8 813.4 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 49.7 2,957.3 628,738.1 822.3 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,957.3 636,353.0 812.5 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,957.3 630,777.3 819.7 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,402.9 725,825.1 819.7 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 287.6 3,690.4 747,683.9 863.0 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 201.8 3,892.3 763,024.7 891.8 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 139.3 4,031.6 773,616.6 911.1 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 125.2 4,156.8 783,135.4 928.0 l TOTAL BAT VOLUME = 7,704.0 GALLONS l l uca venam :

ABB Combustion Engineering Nuclear Services Page 56 Of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-10 Sal 0m Nuclear Generating Station Plant Cooldown from BAT 3.8125 wt % Boric Acid 70 T 547 P to 200 T _

RWST 2300 ppm Boric Acid 70 f AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tf Vi Vf (T) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (Ibm) (gal) (gal) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 l 547 535 2250 0.02125 0.02092 ,

7,988.2 959.1 0.0 316.6 316.6 535,616.6 103.3 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 376.4 693.0 545,488.1 222.1 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 241.4 934.3 551,818.6 296.0 510 500 2250 0.02031 0.02009 5,829.6 '699.9 0.0 231.1 1,165.4 557,879.3 365.2 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 214.5 1,379.9 563,505.3 428.1 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 218.8 1,598.7 569,245.6 491.0 480 470 2250 0.01969 0.01951 5,2D8.2 625.3 0.0 206.4 1,805.2 574,660.2 549.2 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 204.6 2,009.8 580,028.0 605.8 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 196.8 2,2D6.6 585,190.2 659.3

, 450 436 2250 0.01916 0.01893 6,618.5 794.6 0.0 262.3 2,468.9 592,071.0 729.1 436 425 2250 0.01893 0.01877 5,112.7 0.0 613.8 68.2 2,537.1 597,251.8 742.7 425 410 2250 0.01877 0.01855 6,835.2 0.0 820.7 91.1 2,628.2 604,178.2 760.5 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 54.9 2,683.1 608,348.8 771.1 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 85.9 2,769.0 614,881.4 787.3 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 79.0 2,848.0 620,884.6 802.0 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 53.5 2,901.5 624,953.8 811.7 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 49.7 2,951.2 628,732.1 820.7 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,951.2 636,347.0 810.8 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,951.2 630,771.3 818.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

l 350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,395.9 725,818.1 818.0

! 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 287.6 3,683.5 747,676.9 861.3 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 201.8 3,885.3 763,017.8 890.3 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 139.3 4,024.6 773,609.6 909.6 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 125.2 4,149.9 783,128.4 926.5

~

[ TOTAL BAT VOLUME = 7,478.7 GALLONS l l BACR Vmon 2 l

ABB Combustion Engineering Nuclear Services Page 57 of 133 l

l BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00

! TABLE 2-11 l Salem Nuclear Generating Station l Plant Cooldown from BAT 3.875 wt.% Boric Acid 70 7 l

547 T to 200 T RWST 2300 ppm Boric Acid 70 7 AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tl Vi Vf (T) (T) (psia) (cu.ftllbm) (cu.ft/lbm) (lbm) (gal) (gal) (ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 322.0 322.0 535,622.0 105.1 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 382.8 704.8 545,499.9 225.9 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 245.5 950.3 551,834.5 301.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 235.0 1,185.3 557,899.1 371.4 500 490 2250 0.02009 0.01989 5.411.5 649.7 0.0 218.2 1,403.4 563,528.8 435.4 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 222.6 1,626.0 569,272.9 499.4 480 465 2250 0.01969 0.01942 7,777.8 933.8 0.0 313.5 1,939.5 577,364.2 587.3 465 450 2250 0.01942 0.01916 7,558.9 907.5 0.0 304.7 2,244.2 585,227.8 670.5 450 440 2250 0.01916 0.01900 4,754.5 570.8 0.0 191.7 2,435.9 590,174.0 721.f, 440 420 2250 0.01900 0.01869 9,288.8 0.0 1,115.2 123.8 2.559.7 599,586.6 7M4 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 60.3 2,620.0 604,170.0 158.2 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 54.9 2,674.9 608,340.6 768.8 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 85.9 2,760.8 614,873.2 785.0 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 79.0 2,839.8 620,876.5 799.7 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 53.5 2,893.3 624,945.6 809.4 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 49.7 2,943.0 628,723.9 818.4 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,943.0 636,338.8 808.6 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,943.0 630,763.1 815.7 Add in RHRS VOLUME (ASSUME BORON CONC. == RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,386.5 725,808.7 815.7 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 287.6 3,674.1 747,667.5 859.1 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 201.8 3,875.9 763,008.4 888.1 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 139.3 4,015.2 773,600.2 907.4 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 125.2 4,140.4 783,119.0 924.4

[ TOTAL BAT VOLUME = 7,254.9 G ALLONS I

~

l BACR Vmem 2

{ ! ABB COmbuStiori Enginee~rin~g Nuclear SefviceS Page 58 Of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-12 i Salem Nuclear Generating Station Plant Cocidown from BAT 3.9375 wt.% Boric Acid 70 T 547 T to 200 T RWST 2300 ppm Boric Acid 70 7 AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tt Vi Vf (T) (T) (psia) (cu.ft.Abm) (cu.ft.Abm) (lbm) (gal) (gaf) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 327.4 327.4 535,627.4 106.9 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 389.2 716.6 545,511.7 229.7 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 249.6 966.2 551,850.5 306.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 238.9 1,215.2 557,919.0 377.7 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 221.8 1,427.0 563,552.4 442.7 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 226.3 1,653.3 569,300.2 507.7 480 470 2250 0.01969 0.01951 5,208.2 625.3 00 213.5 1,866.8 574,721.9 567.9 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 211.6 2,078.4 580,096.6 626.4 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 203.5 2,281.9 585,265.5 681.7 450 442 2250 0.01916 0.01903 3,797.2 455.9 0.0 155.6 2,437.6 589,218.4 723.3 442 430 2250 0.01903 0.01884 5,640.2 0.0 677.2 75.2 2,512.8 594,933.8 738.4 430 410 2250 0.01884 0.01855 9,128.9 0.0 1,096.0 121.7 2,634.5 604,184.4 762.3 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 54.9 2,689.3 608,355.1 772.9 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 85.9 2,775.3 614,887.7 789.1 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 79.0 2,854.2 620,890.9 803.7 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 53.5 2,907.8 624,960.0 813.5 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 49.7 2,957.5 628,738.3 822.4 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,957.5 636,353.2 812.5 350 350 350 0.01781 0.01797 (5,575.7)} 0.0 (669.4) 0.0 2.957.5 630,777.5 819.7 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,403.1 725,825.3 819.7 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 287.6 3,690.7 747,684.1 863.0 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 201.8 3,892.5 763.024.9 891.9 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 139.3 4,(X31.8 773.616.8 911.2 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 125.2 4,157.0 783,135.6 928.11

[ TOTAL BAT VOLUME = 7,140.0 GALLONS l l nacavmim:

} ABB Combustion Engineering Nuclear Services Page 59 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV.00 TABLE 2-13 Salem Nuclear Generating Station Plant Cooldown from BAT 4.0 wt.% Boric Acid 70 P 547 T to 200 T RWST 2300 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

_T Tf Vi VI (T) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (lbm) (gaQ (ga0 (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 332.8 332.8 535.632.8 108.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 395.6 728.5 545,523.6 233.5 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 253.7 982.2 551,866.5 3112 510 500 2250 C.02G31 0.02009 5,829.6 699.9 0.0 242.9 1,225.1 557,m9.0 383.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 225.5 1,450.6 563,576.0 450.0 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 230.1 1,680.6 569,327.5 516.1 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 217.0 1,897.6 574,752.7 577.2 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 215.1 2,112.8 580.131.0 636.7 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 206.9 2,319.7 585,303.3 692.9 450 445 2250 0.01916 0.01908 2,367.3 284.2 0.0 98.6 2,418.3 587,769.2 719.3 445 430 2250 0.01908 0.01884 7,070.1 0.0 848.9 94.3 2,512.5 594,933.6 738.4 430 410 2250 0.01884 0.01855 9,128.9 0.0 1,096.0 121.7 2,9 4.2 604,184.2 762.3 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 54.9 2,689.1 608,354.8 772.8 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 85.9 2,775.0 614,887.4 789.0 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 79.0 2,854.0 620,890.7 803.7 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 53.5 2,907.5 624,959.8 813.4 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 49.7 2,957.3 628,738.1 822.3 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,957.3 636,353.0 812.5 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,957.3 630,777.3 819.7 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.) .

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,402.9 725,825.1 819.7 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 287.6 3,690.4 747,683.8 862.9 300 260 350 0.01743 0.01707 15.139.0 0.0 1,817.6 201.8 3,892.2 763,024 7 891.8 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 139.3 4,031.6 773,616.5 911.1 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 125.2 4,156.8 783,135.3 928.0 ;

l TOTAL BAT VOLUME = 6,968.3 GALLONS l l BACR Verson 2 ABB Combustion Engineering Nuclear Services Page 60 Of 133

B'ORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-14 Salem Nuclear Generating Station Plant Cooldown from BAT 3.75 wt.% Boric Acid 70 T 547 T to 200 T RWST 2350 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIF!C SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL

[ TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

n Tf vi vt (T) (T) (psia) (cu.ft./lbm) (cu.ftlibm) (Ibm) (gal) (gal) (Ibm) (ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 311.2 311.2 535,611.2 101.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 369.9 681.2 545,476.3 218.3 ,

! 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 237.2 918.4 551,802.7 291.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 227.1 1,145.5 557,859.4 359.0 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 210.8 1,356.4 563,481.8 420.8 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 215.1 1,571.5 569,218.4 482.7 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 202.9 1,774.4 574,629.5 539.9 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 201.2 1,975.6 579,993.8 595.5 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 193.5 2,169.0 585,152.6 648,1 450 434 2250 0.01916 0.01890 7,555.0 907.1 0.0 294.4 2,463.4 593,002.0 726.3 434 420 2250 0.01890 0.01869 6,488.2 0.0 779.0 88.4 2,551.8 599,578.6 744.1 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 61.6 2,613.4 604,163.4 756.3 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 56.1 2,669.5 608,335.2 767.2 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 87.8 2,757.3 614,869.7 784.0 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 80.7 2,838.0 620,874.7 799.2 370 360 2250 0.01104 0.01792 4,015.6 0.0 482.1 54.7 2,892.7 624,945.0 809.3 360 350 2250 0.01/92 0.01781 3,728.5 0.0 447.7 50.8 2,943.5 628,724.4 818.5 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,943.5 636,339.3 808.7 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,943.5 630,763.6 815.9 l

i Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,387.1 725,809.3 815.9 l 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 293.9 3,681.0 747,674.4 860.7 300 260 350 0.01743 0.01707 15.139.0 0.0 1,817.6 206.3 3,887.2 763,019.7 890.7 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 142.4 4,029.6 773,614.6 910.7 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 128.0 4,157.6 783,136.2 928.2

{ TOTAL BAT VOLUME = 7,591.2 GALLONS l l BACR Venm>n 2 ABB Combustion Engineering Nuclear Services Page 61 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-15 Salem Nuclear Generating Station Plant Cooldown from BAT 3.8125 wt. % Boric Acid 70 T 547 T to 200 T RWST 2350 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tf Vi VI (T) (T) (psla) (cu.ft./lbm) (cu.ft./lbm) (lbm) (gaf) (ga!) (ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 316.6 316.6 535,616.6 103.3 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 376.4 693.0 545,488.1 , 222.1 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 241.4 934.3 551,818.6 296.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 231.1 1,165.4 557,879.3 365.2 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 214.5 1,379.9 563,505.3 428.1 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 218.8 1,598.7 569,245.6 491.0 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 206.4 1,805.2 574,660.2 549.2 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 204.6 2,009.8 580,028.0 605.8 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 196.8 2,206.6 585,190.2 659.3

! 450, 438 2250 0.01916 0.01896 5,685.0 682.5 0.0 225.3 2,431.9 591,100.5 719.3 438 420 2250 0.01896 0.01869 8,358.3 0.0 1,003.5 113.9 2,545.8 599,572.7 742.4 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 61.6 2,007.4 604,157.4 754.6 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 56.1 2,663.5 608,329.3 765.5 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 87.8 2,751.3 614,863.8 782.3 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 80.7 2,832.1 620,868.7 797.5 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 54.7 2,886.8 624,939.1 807.6 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 50.8 2,937.6 628,718.4 816.9 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,937.6 636,333.4 807.1 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,937.6 630,757.7 814.2 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,380.2 725,802.4 814.2 350 300 350 0.01797 0.01743 21771.2 0.0 2,589.9 293.9 3,674.1 747,M7.5 859.2 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 206.3 3,880.4 763,012.8 889.1 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 142.4 4,022.8 773,007.8 909.1 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 128.0 4,150.8 783,129.3 926.7 VOLUME = 7,366.6 GALLONS l

~

[ TOTAL BAT l uca ven.m 2 IBB Combustion Engineering Nuclear Services Page 62 Of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-16 Salem Nuclear Generating Station Plant Cooldown from BAT 3.875 wt.% Boric Acid 70 T 547 7 to 200 7 RWST 2350 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tf Vi Vf (T) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (lbm) (gaf) (gal) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 322.0 322.0 535,622.0 105.1 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 382.8 704.8 545,499.9 225.9 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 245.5 950.3 551,834.5 301.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 235.0 1,185.3 557,899.1 371.4 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 218.2 1,403.4 563,528.8 435.4 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 222.6 1,626.0 569,272.9 499.4 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 210.0 1,835.9 574,691.0 558.5 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 208.1 2,044.1 580,062.3 616.1 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 200.2 2,244.2 585,227.8 670.5 450! 441 2250 0.01916 0.01901 4,275.4 513.3 0.0 172.4 2,416.6 589,675.6 716.5 441 420 2250 0.01901 0.01869 9,767.8 0.0 1,172.7 133.1 2,549.7 599,576.5 743.5 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 61.6 2,611.3 604,161.3 755.7 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 56.1 2,667.4 608,333.1 766.6 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 87.8 2,755.2 614,867.6 783.4 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 80.7 2,835.9 620,872.6 798.6 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 54.7 2,890.6 624,942.9 808.7 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 50.8 2.941.4 628,722.3 817.9 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,941.4 636,337.2 808.2 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,941.4 630,761.5 815.3 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,384.7 725,806.9 815.3 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 293.9 3,678.6 747,672.0 860.2 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 206.3 3,884.8 763,017.3 890.1 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 142.4 4,027.2 773,612.2 910.1 230 200 350 0.01683 0.01662 9.393.6 0.0 1,127.8 128.0 4,155.2 783,133.8 927.6

[ TOTAL BAT VOLUME = 7,197.4 GALLONS l

~ ~

l BACR Vensm 2 l I BB Combustion Engineering Nuclear Sen/ ices Page 63 of 133

^

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-17 Salem Nuclear Generating Station Plant Cooldown from BAT 3.9375 wt.% Boric Acid 70 P 547 T to 200 V RWST 2350 ppm Boric Acid 70 P AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tf Vi Vf (P) (T) (psia) (cu.ftllbm) (cu.ft./lbm) (Ibm) (gal) (ga!) (ibm) (ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 327.4 327.4 535,627.4 106.9 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 389.2 716.6 545,511.7 229.7 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 249.6 966.2 551,850.5 306.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 238.9 1,205.2 557,919.0 377.7 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 221.8 1,427.0 563,552.4 442.7 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 226.3 1,653.3 569,300.2 507.7 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 213.5 1,866.8 574,721.9 567.9 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 211.6 2,078.4 580,096.6 626.4 460 450 2250 0.01933 0.01916 4.965.4 596.2 0.0 203.5 2,281.9 585.265.5 681.7 450 445 2250 0.01916 0.01908 2,367.3 284.2 0.0 97.0 2,379.0 587,729.8 707.7 445 430 2250 0.01908 0.01884 7,070.1 0.0 848.9 96.3 2,475.3 594,896.3 727.5 430 415 2250 0.01884 0.01862 6,858.6 0.0 823.5 93.4 2,568.7 601,848.3 746.2 415 400 2250 0.01862 0.01842 6,386.1 0.0 766.7 87.0 2,655.7 608,321.5 763.3 l 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 87.8 2,743.6 614,856.0 780.1 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 80.7 2,824.3 620,860.9 795.3 1 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 54.7 2,879.0 624,931.3 805.4 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 50.8 2,929.8 628,710.6 814.7 l

l 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,929.8 636,325.6 805.0 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,929.8 630,749.9 812.1 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,371.3 725,793.5 812.1 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 293.9 3,665.2 747,658.6 857.1 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 206.3 3,871.4 763,003.9 887.1 260 230 350 0.01707 0.01683 10.452.5 0.0 1,254.9 142.4 4,013.8 773,598.8 907.1 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 128.0 4,141.8 783,120.4 924.7 u l TOTAL BAT VOLUME = 6,968.3 GALLONS l l aAcR versam 2 ABB Combustion Engineering Nuclear Services Page 64 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-18 Salem Nuclear Generating Station Plant Cooldown from BAT 4.0 wt.% Boric Acid 70 T 547 T to 200 P RWST 2350 ppm Boric Acid 70 P AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL J TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tl Vi Vf (T) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (Ibm) (ga) (gal) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 332.8 332.8 535,632.8 108.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 395 6 728.5 545,523.6 233.5 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 253.7 982.2 551,866.5 311.2 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 242.9' 1,225.1 557,939.0 383.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 225.5 1,450.6 563,576.0 450.0 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 230.1 1,680.6 569,327.5 516.1 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 217.0 1,897.6 574,752.7 577.2 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 215.1 2,112.8 580,131.0 636.7 460 448 2250 0.01933 0.01912 5,909.9 709.6 0.0 246.2 2,359.0 586,287.2 703.5 i 448 435 2250 0.01912 0.01892 6,141.8 0.0 737.4 83.7 2,442.7 592,512.7 720.8 435 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 94.8 2,537.5 599,564.3 739.9 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 61.6 2,599.1 604,149.1 752.2 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 56.1 2,655.2 608,320.9 763.1 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 87.8 2,743.0 614,855.4 780.0 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 80.7 2,823.7 620,860.4 795.2 l 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 54.7 2,878.4 624,930.7 805.3 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 50.8 2,929.2 628,710.1 814.6 l 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,929.2 636,325.0 804.8 i 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,929.2 630,749.3 811.9

Add in RHPS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.) .

l 350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,370.6 725,792.8 811.9 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 293.9 3,664.5 747,657.9 856.9 l

l 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 206.3 3,870.8 763,003.2 886.9 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 142.4 4,013.2 773,598.2 907.0 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 128.0 4,141.2 783,119.7 924.5 l

l TOTAL BAT VOLUME = 6,797.5 GALLONS l l

l uncawn.>o 2 ABB Combustion Engineering Nuclear Services Page 65 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-19 l Salem Nuclear G0nerating Station l

Plant Cooldown from BAT 3.75 wt.% Boric Acid 70 T l 547 T to 200 T RWST 2400 ppm Boric Acid 70 P

( AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL l TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

l Ti Tr vi vt (T) (T) (psla) (cu.ftJ1bm) (cu.ftlibm) (Ibm) (gah (gaQ (Ibm) (Ibm) (bm) (ppm boron)

! 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 311.2 311.2 535,611.2 101.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 369.9 681.2 545,476.3 218.3 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 237.2 918.4 551,802.7 291.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 227.1 1,145.5 557,859.4 359.0 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 210.8 1,356.4 563,481.8 420.8 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 215.1 1,571.5 569,218.4 482.7 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 202.9 1,774.4 574,629.5 539.9 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 201.2 1,975.6 579,993.8 595.5 g 470 460 450 2250 0.01933 0.01916 4.965.4 596.2 0.0 193.5 2,169.0 585,152.6 648.1 450 436 2250 0.01916 0.01893 6,618.5 794.6 0.0 257.9 2,426.9 592,029.0 716.7 436 420 2250 0.01893 0.01869 7,424.8 0.0 891.4 103.3 2,530.2 599,557.1 737.8 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 63.0 2,593.2 604,143.2 750.4 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 57.3 2,650.5 608,316.2 761.8 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 89.7 2,740.2 614,852.6 779.2 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 82.5 2,822.7 620,859.3 794.9 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 55.9 2,878.5 624,930.8 805.3 370 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 51.9 2,930.4 628,711.3 814.9 360 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,930.4 636,326.2 805.2 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,930.4 630,750.5 812.3 350 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,372.0 725,794.2 812.3 350 350 0.01797 0.01743 21,571.2 0.0 2,589.9 300.2 3,672.2 747,665.7 858.7 -

350 300 0.01743 0.01707 15,139.0 0.0 1,817.6 210.7 3,883.0 763,015.4 889.7 300 260 350 350 0.01707 0.01683 10,452.5 0.0 1,254.9 145.5 4,028.4 773.613 4 910.4 ,

260 230 0.01683 0.01662 9,393.6 0.0 1,127.8 130.7 4,159.2 783,137.7 928.5 230 200 350 l TOTAL BAT VOLUME = 7,478.7 GALLONS ]

l BAcn vmna 2 ABB Combustion Engineering Nuclear Services Page 66 Of 133 w

B'ORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV.00 TABLE 2 - 20 Salem Nuclear G0nerating Station Plant Cooldown from BAT 3.8125 wt. % Boric Acid 70 f 547 T to 200 T RWST 2400 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

B B W Vf (T) (T) (psla) (cu.ftllbm) (cu.ft./lbm) (lbm) (gal) (gaQ (Ibm) (lbm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 316.6 316.6 535,616.6 103.3 1

535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 376.4 693.0 545,488.1 222.1 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 241.4 934.3 551,818.6 296.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 231.1 1,165.4 557,879.3 365.2 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 214.5 1,379.9 563,505.3 428.1 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 218.8 1,508.7 569,245.6 491.0 480 470 2250 0.01969 0.01951 5,E 8.2 625.3 0.0 206.4 1,005.2 574,060.2 549.2 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 204.6 2,009.8 580,028.0 605.8 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 196.8 2,W 6.6 585,190.2 659.3 450 440 2250 0.01916 0.01900 4,754.5 570.8 0.0 188.4 2,T5.1 590,133.2 709.6 440 420 2250 0.01900 0.01869 9,288.8 0.0 1,115.2 129.3 2,524.3 599,551.2 736.1 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 63.0 2,587.3 604,137.3 748.8 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 57.3 2,644.6 608,310.3 760.1 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 89.7 2,734.3 614,846.7 777.5 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 82.5 2,816.8 620,853.4 793.2 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 55.9 2,872.7 624,924.9 803.7 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 51.9 2,924.6 628,705.4 813.3 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,924.6 636,320.3 803.5 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,924.6 630,744.6 810.6 350 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,365.2 725,787.4 810.6 350 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 300.2 3.065.5 747,658.9 857.1 260 350 0.01743 0.01707 15.139.0 0.0 1,817.6 210.7 3,876.2 763,008.6 888.2 300 350 0.01707 0.01683 10,452.5 0.0 1,254.9 145.5 4,021.7 773,606.6 908.9 260 230 0.01683 0.01662 9,393.6 0.0 1,127.8 130.7 4,152.4 783,131.0 927.0-230 200 350 VOLUME = 7,254.9 GALLONS l

~

[TdTAL BAT l uca vm.m :

'AB'B Combustion Engineering Nuclear Services Page 67 Of 133

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BQRIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2 - 21 Salern Nuclear Gen 0 rating Station Plant Cookiown from BAT 3.875 wt.% Boric Acid 70 T 547 T to 200 T RWST 2400 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti TI VI Vf (T) (T) (psia) (cu.ftJlbm) (cu.ftllbm) (Ibm) (gal) (gal) (ibm) (lbm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 322.0 322.0 535,622.0 105.1 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 382.8 704.8 545,499.9 225.9 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 245.5 950.3 551,834.5 301,1 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 235.0 1,185.3 557,899.1 371.4 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 218.2 1,403.4 563,528.8 435.4 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 222.6 1,626.0 569,272.9 499.4 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 210.0 1,835.9 574,091.0 558.5 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 208.1 2,044.1 580,062.3 616.1 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 200.2 2,244.2 585,227.8 670.5 450 443 2250 0.01916 0.01904 3,319.8 398.6 0.0 133.8 2,378.1 588,681.4 706.3 443 420 2250 0.01904 0.01869 10,723.5 0.0 1,287.5 149.3 2,527.3 599,554.2 737.0 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 63.0 2,590.3 604,140.2 749.6 ,

410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 57.3 2,647.6 608,313.3 760.9' 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 89.7 2,737.3 614,849.7 778.4 400 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 82.5 2,819.7 620,856.4 794.0 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 55.9 2,875.6 624,927.9 804.5 370 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 51.9 2,927.5 628,708.4 814.1 360 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,927.5 636,323.3 804.4 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2.927.5 630,747.6 811.5 350 350 350 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

0.01797 0.01797 0.0 0.0 0.0 0.0 3,368.7 725,790.9 811.5 350 350 350 0.01797 0.01743 21,571.2 0.0 2.589.9 300.2 3,668.9 747,662.3 857.9 350 300 350 '

350 0.01743 0.01707 15,139.0 0.0 1,817.6 210.7 3,879.6 763,012.1 889.0 300 260 0.01707 0.01683 10,452.5 0.0 1,254.9 145.5 4,025.1 773,610.1 909.7 260 230 350 0.01662 9,393.6 0.0 1,127.8 130.7 4,155.8 783,134.4 927.8 230 200 350 0.01683 VOLUME = 7,082.7 GALLONS l

[TdTAL BAT l BACR Verma 2 ,

Page 68 Of 133

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-22 Salem NuclearGenerating Station Plant Cooldown from BAT 3.9375 wt.% Boric Acid 70 T 547 T to 200 T RWST 2400 ppn Boric Acid _

70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tl VI V!

(T) (T) (psla) (cu.ftllbm) (cu.ftlibm) (Ibm) (gal) (gal) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 327.4 327.4 535,627.4 106.9 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 389.2 716.6 545,511.7 229.7 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 249.6 966.2 551,850.5 306.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 238.9 1,205.2 557,919.0 377.7 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 221.8 1,427.0 563,552.4 442.7 0.01989 0.01969 5,521.5 662.9 0.0 226.3 1,653.3 569,300.2 507,7 490 480 2250 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 213.5 1,866.8 574,721.9 567.9 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 211.6 2,078.4 580,096.6 626.4 460 447 2250 0.01933 0.01911 6,383.4 766.4 0.0 261.6 2,340.0 586,741.6 697.3 435 2250 0.01911 0.01892 5,668.4 0.0 680.6 78.9 2,418.9 592,488.9 713.8 447 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 96.8 2,515.8 599,542.6 733.6 435 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 63.0 2,578.7 604,128.7 746.3 420 .

0.01855 0.01842 4,115.8 0.0 494.1 57.3 2,636.0 608,301.7 757.6 f 410 400 2250 0.01842 0.01822 6,446.7 0.0 774.0 89.7 2,725.7 614,838.1 775.1 400 385 2250 2250 0.01822 0.01804 5,924.2 0.0 711.3 82.5 2,808.2 620,844.8 790.8 385 370 0.01804 0.01792 4,015.6 0.0 482.1 55.9 2,864.1 624,916.4 801.3 370 360 2250 0.01781 3,728.5 0.0 447.7 51.9 2,916.0 628,096.8 810.9 360 350 2250 0.01792 0.01912 7,614.9 0.0 914.3 0.0 2.916.0 636,311.8 801.2 350 350 350 0.02698 0.01797 (5,57 5.7) 0.0 (669.4) 0.0 2,916.0 630,736.1 808.3 350 350 350 0.01781 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

808.3 0.01797 0.0 0.0 0.0 0.0 3,355.4 725,777.6 350 350 350 0.01797 0.01743 21,571.2 0.0 2,589.9 300.2 3,655.6 747,649.0 854.8 350 300 350 0.01797 0.01707 15,139.0 0.0 1,817.6 210.7 3,866.3 762,998.8 885.9 300 260 350 0.0i743 0.01683 10,452.5 0.0 1,254.9 145.5 4,011.8 773,596.8 906.7, 260 230 350 0.01707 9,393.6 0.0 1,127.8 130.7 4,142.5 783,121.1 924.8}

230 200 350 0.01683 0.01662

[~ TOTAL BAT VOLUME = 6,854.3 GALLONS l l uca vmm 2 XB5DOmbustiOn Engineering Nuclear Services Page 69 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2- 23 Salem Nuclear Generating Station Plant Cooidown from BAT 4.0 wt.% Boric Acid 70 T 547 T to 200 T RWST 2400 ppm Boric Acid 70 T AVERAGE SYSTEM PIR SPECIFIC SHRINKAGE BAT RWST B/A TTOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

T1 TT Vi Vf (T) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (Ibm) (gal) (gal) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 332.8 332.8 535,632.8 108.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 395.6 728.5 545,523.6 233.5 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 253.7 982.2 551,866.5 311.2 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 242.9 1,225.1 557,939.0 383.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 225.5 1,450.6 563,576.0 450.0 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 230.1 1,680.6 569,327.5 516.1 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 217.0 1,897.6 574,752.7 577.2 470 460 2250 0.01951 0.01933 5.163.1 619.9 0.0 215.1 2,112.8 580.131.0 636.7 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 206.9 2,319.7 585,303.3 692.9 450 435 2250 0.01916 0.01892 7,086.4 0.0 850.8 98.6 2,418.3 592,488.3 713.6 435 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 96.8 2,515.1 599,542.0 733.4 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 63.0 2,578.1 604,128.0 746.1 410 400 2250 0.01855 0.01842 4.115.8 0.0 494.1 57,3 2,635.4 608,301.1 757.4 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 89.7 2,725.1 614,837.5 774.9 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 82.5 2,807.5 620,844.2 790.6 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 55.9 2,863.4 624,915.7 801.1 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 51.9 2,915.3 628,696.2 810.7 360 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,915.3 636,311.1 801.0 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,915.3 630,735.4 808.1 350 ,

Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,354.6 725,776.8 808.1 350 350l 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 300.2 3,654.8 747,648.3 854.7 350 350 0.01743 0.01707 15.139.0 0.0 1,817.6 210.7 3,865.6 762,998.0 885.8 300 260 0.01707 0.01683 10,452.5 0.0 1,254.9 145.5 4,011.0 773,596.0 906.5 260 230 350 0.01683 0.01662 9,T3.6 0.0 1,127.0 130.7 4,141.8 783,120.3 924.7 230 200 350 l TOTAL BAT VOLUME = 6,684.1 GALLONS l l BACR Vmem 2 ABB Combustion Engineering Nuclear Services Page 70 of 133

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV.00 TABLE 2-24 Salem Nuclear Generating Station Plant Cooldown from BAT 3.75 wt.% Boric Acid 70 T 547 T to 200 T RWST 2450 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

B R W W (T) (T) (psia) (cu.ft/lbm) (cu.ft/lbm) (lbm) (gal) (gal) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 311.2 311.2 535,611.2 101.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 369.9 681.2 545,476.3 218.3 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 237.2 918.4 551,802.7 291.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 227.1 1,145.5 557,859.4 359.0 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 210.8 1,356.4 563,481.8 420.8 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 215.1 1,571.5 569,218.4 482.7 l 480 470 2250 0.01969 0.01951 5,3 8.2 625.3 0.0 202.9 1,774.4 574,629.5 539.9 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 201.2 1,975.6 579,993.8 595.5 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 193.5 2,169.0 585,152.6 648.1

! 450 439 2250 0.01916 0.01898 5,219.3 626.6 0.9 203.4 2,372.4 590,575.3 702.3 439 420 2250 0.01898 0.01869 8,823.9 0.0 1,059.4 125.4 2,497.8 599,524.6 728.4 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 64.3 2,562.1 604,112.0 741.5 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 58.5 2,620.6 608,286.3 753.2 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 91.6 2.712.2 614,824.6 771.2 i 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 84 2 2,796.4 620,833.0 787.5 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 57.1 2,853.5 624,905.7 798.3 360 350 2250 001792 0.01781 3,728.5 0.0 447.7 53.0 2,906.5 628,687.3 808.3 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,906.5 636,302.2 798.6 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,906.5 630,726.5 805.7 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,344.4 725,766.6 805.7 l

350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 306.6 3,651.0 747,644.4 853.8 -

)

350 0.05743 0.01707 15.139.0 0.0 1,817.6 215.2 3.866.2 762,998.6 885.9 I 300 260 230 350 0.01707 0.01683 10,452.5 0.0 1.254.9 148.6 4,014.7 773,599.7 907.3 260 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 133.5 4,148.2 783,126.8 926.1 230 l

l TOTAL BAT VOLUME = 7,310.7 GALLONS I

[ HACR Versa >n 2 ABB Combustion Engineering Nuclear Services Page 71 of 133 l

BDRIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV.00 TABLE 2-25 Salem Nuclear Generating Station Plant Cooldown from BAT 3.8125 wt. % Boric Acid 70 7 547 T to 200 T RWST 2450 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tf VI Vf (T) (T) (psla) (cu.ft./lbm) (cu.ft./lbm) (1bm) (gaQ (gal) (ibm) (ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 316.6 316.6 535,616.6 103.3 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 376.4 693.0 545,488.1 222.1 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 241.4 934.3 551,818.6 296.0 510 500 2250 0.02031 0.02009 5,829.6 -699.9 0.0 231.1 1,155.4 557,879.3 365.2 50C 490 2250 0.02009 0.01989 5.411.5 649.7 0.0 214.5 1,379.9 563,505.3 428.1 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 218.8 1,598.7 569,245.6 491.0 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 206.4 1,805.2 574,660.2 549.2 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 204.6 2,009.8 580,028.0 605.8 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 196.8 2,3)6.6 585,190.2 659.3 450 442 2250 0.01916 0.01903 3,797.2 455.9 0.0 150.5 2,357.1 589,137.9 699.5 442 425 2250 0.01903 0.01877 7,933.9 0.0 952.6 112.8 2,469.9 597,184.6 723.1 425 410 2250 0.01877 0.01855 6,835.2 0.0 820.7 97.1 2,557.0 604.117.0 742.9 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 58.5 2,625.5 608,291.3 754.6 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 91.6 2,717.1 614,829.5 772.7 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 84 2 2,801.3 620,838.0 788.9 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 57.1 2,858.4 624,910.7 799.7 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 53.0 2,911.4 628,692.2 809.6 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,911.4 636,307.2 799.9 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,911.4 630,731.5 807.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,350.1 725,772.3 807.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 306.6 3,656.7 747,650.1 855.1 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 215.2 3.871.8 763,004.3 887.2 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 148.6 4.020.4 773,005.4 908.6 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 133.5 4,153.9 783,132.5 927.4

[ TOTAL BAT VOLUME = 7,140.0 GALLONS l l BACR Versam 2

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ABEfCOmbuStiOn Engineering Nuclear Services Page 72 Of 133

BDRIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABl.E 2 - 26 Salem Nuclear Generating Station Plant Cooldown from BAT 3.875 wt.% Boric Acid 70 P 547 T to 200 T RWST 2450 ppm Boric Acid 70 T _

AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti TI VI VI (T) (T) (psla) (cultJlbm) (cu.ft./lbm) (Ibm) (gal) (gal) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 322.0 322.0 535,622.0 105.1 535 520 2250 0.02092 0.02055 9.495.2 1,140.0 0.0 382.8 704.8 545,499.9 225.9 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 245.5 950.3 551,834.5 301.1 ,

510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 235.0 1,185.3 557,899.1 371.4 !

500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 218.2 1,403.4 563,528.8 435.4 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 222.6 1,626.0 569,272.9 499.4 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 210.0 1,835.9 574,691.0 558.5 l 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 208.1 2,044.1 580,062.3 616.1 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 200.2 2,244.2 585,227.8 670.5 l 450 446 2250 0.01916 0.01909 1,892.2 227.2 0.0 76.3 2,320.5 587,196.4 690.9 446 430 2250 0.01909 0.01884 7,545.2 0.0 905.9 107.2 2,427.8 594,848.8 713.6 l 430 410 2250 0.01884 0.01855 9,128.9 0.0 1,096.0 129.7 2,557.5 604.107.5 740.2 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 53.5 2,616.0 608,281.7 751.9 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 91.6 2,707.6 614,820.0 770.0 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 84 2 2.791.8 620,828.5 786.2 .

370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 57.1 2,843.9 624,901.2 797.1 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 53.0 2,901.9 628,682.7 807.0 350 350 350 0.02693 0.01912 7,614.9 0.0 914.3 0.0 2,901.9 636,297.7 797.3 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,901.9 630,722.0 804.4 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,339.1 725,761.3 804.4 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 306.6 3,645.7 747,639.2 852.5 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 215.2 3,860.9 762,993.4 884.7 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 148.6 4,009.4 773,594.4 906.1 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 133.5 4,143.0 783,121.5 924.9 FTOTAL t BAT VOLUME = 6,911.3 GALLONS l l BACR Venmin 2 Page 73 Of 133

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[ ABB Combustion Engineering Nuclear Services

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2 - 27 {

Salem Nuclear Generating Station Plant Cooldown from BAT 3.m75 wt.% Borc Acid 70 7 547 T to 200 T RWST 2450 ppm Boric Acid 70 T FINAL AVERAGE SYSTEM PZR SPECFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

TEMPERATURE PRESS. ,

B R W Vf (Ibm) (ga!) (gal) (Ibm) (ibm) (bm) (ppm boron) i (T) (T) (mds) (cu.ft/bm) (cu.ft/lbm) 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 547 2250 0.02125 0.02092 7,988.2 959.1 0.0 327.4 327.4 535,627.4 106.9 547 535 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 389.2 716.6 545,511.7 229.7 535 520 2250 0.02031 6,089.2 731.1 0.0 249.6 966.2 551,850.5 306.1 520 510 2250 0.02055 0.02009 5,829.6 699.9 0.0 238.9 1,m5.2 557,919.0 377.7 510 500 2250 0.02031 5,411.5 649.7 0.0 221.8 1,427.0 563,552.4 442.7 500 490 2250 0.02009 0.01989 0.01969 5,521.5 662.9 0.0 226.3 1,653.3 569,300.2 507.7 490 480 2250 0.01989 0.01951 5,208.2 625.3 0.0 213.5 1,866.8 574,721.9 567.9 480 470 2250 0.01969 0.01933 5,163.1 619.9 0.0 111.6 2,078.4 580,096.6 626.4 470 460 2250 0.01951 5,437.3 652.8 0.0 222.9 2,301.3 585,756.7 686.9 460 449 2250 0.01933 0.01914 6,614.5 0.0 794.1 94.0 2,MS.3 592,465.2 706.8 449 435 2250 0.01914 0.01892 6,956.9 0.0 835.3 98.9 2,494.1 599,521.0 727.4 435 420 2250 0.01892 0.01869 4,523.1 0.0 543.1 64.3 2,558.4 604,108.4 740.4 420 410 2250 0.01869 0.01855 4,115.8 0.0 494.1 58.5 2.616.9 608,282.7 752.2 410 400 2250 0.01855 0.01842 6,446.7 0.0 774.0 91.6 2,708.6 614,821.0 770.2 400 385 2250 0.01842 0.01822 5,924.2 0.0 711.3 84 2 2,792.7 620,829.4 786.5 385 370 2250 0.01822 0.01804 4,015.6 0.0 482.1 57.1 2,849.8 624,902.1 797.3 370 360 2250 0.01804 0.01792 3,728.5 0.0 447.7 53.0 2,902.8 628,683.7 807.3 360 350 2250 0.01792 0.01781 7,614.9 0.0 914.3 0.0 2,902.8 636,298.6 797.6 350 350 350 0.02698 0.01912 0.0 0.0 2,902.8 630,722.9 804.6 350 350 0.01781 0.01797 (5,575.7) (669.4) 350 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.) 0,0 0.0 3,340.2 725,762.4 804.6 350 350 0.01797 0.01797 0.0 0.0 350 3,646.8 747,640.2 852.8 l

0.01743 21,571.2 0.0 2,589.9 306.6 350 300 350 0.01797 15,139.0 0.0 1,817.6 215.2 3,862.0 762,994.4 884.9 300 260 350 0.01743 0.01707 0.0 1,254.9 148.6 4,010.5 773,595.5 906.4 350 0.01707 0.01683 10,452.5 260 230 783,122.6 925.2) 9,33.6 0.0 1,127.8 133.5 4,144.0 230 200 350 0.01683 0.01662 VOLUME = 6,740.7 GALLONS l

[ TOTAL BAT l BACRVmon 2 Page 74 Of 133 ABB Combustion Engineering Nuclear Services

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV.00 TABLE 2 - 29 Salem Nuclear Generating Station Plant Cooldown from BAT 3.75 wt. % Boric Acid 70 T 547 T to 200 T RWST 2500 nm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT l.f.-3T B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

11 TI Vi Vf (T) (T) (psla) (cu.ft/lbm) (cu.ftJ1bm) (Ibm) (gal) (gat) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 311.2 311.2 535,611.2 101.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 369.9 681.2 545,476.3 218.3 520 510 2250 0.02055 0.02031 6,069.2 731.1 0.0 237.2 918.4 551,802.7 291.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 227.1 1,145.5 557,859.4 359.0 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 210.8 1,356.4 563,481.8 420.8 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 215.1 1,571.5 569.218.4 482.7 480 470 2250 0.01969 0.01951 5,3 8.2 625.3 0.0 202.9 1,774.4 574,629.5 539.9 470 460 2250 0.01951 0.01933 5.163.1 619.9 0.0 201.2 1,975.6 579,993.8 595.5 460 450 2250 0.01933 0.01916 4.965.4 596.2 0.0 193.5 2,169.0 585,152.6 648.1 2250 0.01916 0.01901 4,275.4 513.3 0.0 166.6 2,335.6 589,594.7 692.6 450 441 420 2250 0.01901 0.01869 9,767.8 0.0 1,172.7 141.7 2,477.3 599,504 2 722.5 j 441 2250 0.01869 0.01855 4,523.1 0.0 543.1 65.6 2,542.9 604,092.9 736.0 420 410 0.01855 0.01842 4,115.8 0.0 494.1 59.7 2,602.6 608,268.4 748.1 410 400 2250 0.01842 0.01822 6,446.7 0.0 774.0 93.5 2,696.1 614,808.5 766.7 400 385 2250 0.01822 0.01804 5,924.2 0.0 711.3 85.9 2,782.1 620,818.7 783.5 385 370 2250 0.01804 0.01792 4,015.6 0.0 482.1 58 3 2,840.3 624,892.6 794.7 370 360 2250 0.01781 3,728.5 0.0 447.7 54.1 2,894.4 628,675.3 804.9 360 350 2250 0.01792 0.01912 7,614.9 0.0 914.3 0.0 2,894.4 636,290.2 795.3 350 350 350 0.02698 0.01797 (5,575.7) 0.0 0.0 2,894.4 630,714.5 802.3 350 350 350 0.01781 (669.4)

Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

725,752.8 802.3 0.01797 0.01797 0.0 l 0.0 0.0 0.0 3,330.6 350 350 350 0.01743 21,571.2 0.0 2,589.9 312.9 3,643.5 747,636.9 852.0 350 300 350 0.01797 0.01707 15,139.0 0.0 1,817.6 219.6 3,863.1 762,995.6 885.2 300 260 350 0.01743 10,452.5 0.0 1,254.9 151.6 4,014.7 773,509.7 907.3 260 230 350 -0.01707 0.01683 9,393.6 0.0 1,127.8 136.3 4,151.0 783,129.6 926.7 230 200 350 0.01683 0.01662i

[ TOTAL BAT VOLUME = 7,197.4 GALLONS I l BACR Venein 2 ABB Combustion Engineering Nuclear Services Page 76 Of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS DRAFT 5/13 TABLE 2-30 Salem Nuclear Generating Station Plant Cooldown from BAT 3.8125 wt. % Boric Acid 70 7 547 T to 200 P RWST 2500 ppm Boric Acid 70 P AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tl VI Vf (T) (T) (psia) (cu.ftJ1bm) (cu.ftlibm) (Ibm) (gal) (gaf) (Ibm) (ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 316.6 316.6 535,616.6 103.3 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 376.4 693.0 545,488.1 222.1 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 241.4 934.3 551,818.6 296.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 231.1 1,165.4 557,879.3 365.2 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 214.5 1,379.9 563,505.3 428.1 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 218.8 1,598.7 569,245.6 491.0 480 470 2250 0.01969 0.01951 5,m 8.2 625.3 0.0 206.4 1,805.2 574,660.2 549.2 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 204.6 2,009.8 580,028.0 605.8 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 196.d 2,206.6 585,190.2 659.3 450 445 2250 0.01916 0.01908 2,367.3 284.2 0.0 93.8 2,300.4 587,651.3 684.4 445 420 2250 0.01908 0.01869 11,676.0 0.0 1,401.8 169.4 2,469.8 599,496.7 720.3 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 65.6 2,535.4 604,085.4 733.8 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 59.7 2,595.1 608,260.9 745.9 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 93.5 2,688.7 614,801.1 764.6 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 85.9 2,774.6 620,811.3 781.4 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 58.3 2,832.9 624,885.1 792.6 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 54.1 2,886.9 628.667.8 802.9 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2.886.9 636,282.7 793.3 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,886.9 630,707.0 800.3 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,322.0 725,744.2 800.3 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 312.9 3,634.9 747,628.3 850.0 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 219.6 3,854.5 762,987.0 883.2 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 151.6 4,006.1 /73,591.1 905.4 230 200 350 0.01683 0.01662 9,5 3.6 0.0 1,127.8 136.3 4,142.4 783,121.0 924.8.

[iDTAL BAT VOLUME = 6,968.3 G ALLONSl l BACR Verss>n 2

~-

~dBB CoriibuStion Engineering Nuclear Services Page 77 of 133

i BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-31 Salem Nuclear Generating Station Plant Cooldown from BAT 3.875 wt. % Boric Acid 70 7 547 T to 200 T RWST 2500 ppm Boric Acid 70 7 ;

AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL ,

TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC. ,

Ti Ti VI Vf ,

1 (T) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (Ibm) (gal) (gal) (Ibm) (Ibm) (t>m) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 322.0 322.0 535,622.0 105.1 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 382.8 704.8 545,499.9 225.9 ,

1 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 245.5 950.3 551,834.5 301.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 235.0 1,185.3 557,899.1 371.4 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 218.2 1,403.4 563,528.8 435.4 .

490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 222.6 1,626.0 569,272.9 499.4 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 210.0 1,835.9 574,691.0 558.5 1 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 208.1 2,044.1 580,062.3 616.1 I

460 448 2250 0.01933 0.01912 5,909.9 709.6 0.0 238.2 2,282.3 586,210.5 680.7 448 435 2250 0.01912 0.01892 6,141.8 0.0 737.4 89.1 2,371.4 592.441.4 699.8 435 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 100.9 2.472.3 599,499.2 721.0 -

} 4,523.1 0.0 543.1 65.6 2,538.0 604,087.9 734.5 420 410 2250 0.01869 0.01855 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 59.7 2,597.7 608,333.4 746.6 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 93.5 2,691.2 614,803.6 765.3 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 85.9 2,777.1 620,813.8 782.1 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 58.3 2,835.4 624,887.7 793.3 ,

360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 54.1 2,889.5 628,670.3 803.6 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,889.5 636,285.2 793.9 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,889.5 630,709.5 801.0 !

Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.) ,

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,324.9 725,747.1 801.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 312.9 3,637.8 747,631.2 850.7 :

260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 219.6 3,857.4 762,989.9 883.9 300 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 151.6 4,009.0 773,594.0 906.1 260 350 0.01683 0.01662 9,393.6 0.0 1,127.8 136.3 4,145.3i 783,123.9 925.4 230 200 FTOTAL BAT VOLUME = 6,797.5 GALLONS l __

l HACR Venna 2

~ ~ ~

[ ABB Combustion Engineeriig~f65 fear Services Page 78 Of 133 l

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B'ORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-32 i Salem Nuclear Generating Station i

Plant Cooldown from BAT 3.9375 wt.% Boric Acid 70 V j 547 7 to 200 T RWST 2500 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tf Vi Vf (T) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (Ibm) (ga0 (gaf) (Ibm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 327.4 327.4 535,627.4 106.9 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 389.2 716.6 545,511.7 229.7 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 249.6 966.2 551,850.5 306.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 238.9 1,205.2 557,919.0 377.7 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 221.8 1,427.0 563,552.4 442.7 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 226.3 1,653.3 569,300.2 507.7 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 213.5 1,866.8 574,721.9 567.9 470 460 2250 0.01951 0.01933 5.163.1 619.9 0.0 211.6 2,078.4 580,096.6 626.4 460 452 2250 0.01933 0.01919 3,965.3 476.1 0.0 162.5 2,240.9 584,224.4 670.6 452 435 2250 0.01919 0.01892 8,086.5 0.0 970.9 117.3 2,358.2 592,428.2 696.0 435 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 100.9 2,459.2 599,486.0 717.2 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 65.6 2,524.8 604.074.7 730.7 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 59.7 2,584.5 608,250.2 742.9 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 93.5 2,678.0 614,790.4 761.6 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 85.9 2,763.9 620,800.6 778.4 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 58.3 2,822.2 624,874.5 789.6 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 54.1 2,876.3 628,657.1 799.9 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,876.3 636,272.1 790.3 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,876.3 630,696.4 797.3 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,309.7 725,731.9 797.3 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 312.9 3,622.6 747,616.1 847.2 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 219.6 3,842.2 762,974.7 880.4 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 151.6 3,993.9 773,578.8 902.6 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 136.3 4,130.1 783,108.7 922.1,

_230

{ TOTAL BAT VOLUME = 6,564.0 GALLONS I l uca vm.. 2 ABB Combustion Engineering Nuclear Services Page 79 of 133

BDRIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABLE 2-33 ,

Salem NuclearGen0 rating Station Plant Cooldown from BAT 4.0 wt.% Boric Acid 70 T 547 T to 200 T RWST 2500 pom Boric Acid 70 P AVERAGE SYSTEM PZR SPECFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tl W VI (T) (T) (psia) (cu.ft./lbm) (cu.ft./lbm) (lbm) (gal) (gal) (Ibm) (ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,968.2 959.1 0.0 332.8 332.8 535,632.8 108.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 395.6 728.5 545,523.6 233.5 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 253.7 982.2 551,866.5 311.2 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 242.9 1,225.1 557,939.0 383.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 225.5 1,450.6 563,576.0 450.0 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 230.1 1,680.6 569,327.5 516.1 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 217.0 1,897.6 574,752.7 577.2 470 454 2250 0.01951 0.01922 8,131.8 976.3 0.0 338.8 2,236.5 583,223.4 670.4 454 450 2250 0.01922 0.01916 1,996.7 0.0 239.7 29.0 2,265.4 585,249.0 676.8 450 435 2250 0.01916 0.01892 7,086.4 0.0 850.8 102.8 2,368.2 592,438.2 698.9 435 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 100.9 2,469.1 599,496.0 720.1 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 65.6 2,534.8 604,084.7 733.6 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 59.7 2,594.5 608,260.2 745.7 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 93.5 2,688.0 614,800.4 764.4 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 85.9 2,773.9 620,810.6 781.2 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 58.3 2,832.2 624,884.5 792.4 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 54.1 2,886.3 628,667.1 802.7 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,886.3 636,282.1 793.1 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 2,886.3 630,706.3 800.1 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.) ,

350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,321.2 725,743.4 800.1 350l 350 300 350 0.0C97 0.01743 21,571.2 0.0 2,589.9 312.9 3,634.1 747,627.5 849.8 300 260 250 0.01743 0.01707 15,139.0 0.0 1,817.6 219.6 3,853.7 762,986.2 883.1 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 151.6 4,005.4 773,590.3 905.2 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 136.3 4,141.6 783,120.2 924.6, l TOTAL BAT VOLUME = 6,444.3 GALLONS l l BacRvmno2 ABB Combustion Engineering Nuclear Services Page 80 Of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 2-34 Minimum Boration Volume vs.

Stored Boric Acid Concentration for Modes 1,2,3, and 4 - Equilibrium Xenon EoL Case - Minimum volume (callons)

BAT CONC. BAT CONC. RWST RWST RWST RWST RWST (ppen (wt% CONC. CONC. CONC. CONC. CONC.

Boron) Boric Acid) 2300 ppm 2350 ppen 2400 ppen 2450 ppen 2500 ppe 6560 3.75 7,704.0 7,591.2 7,478.7 7,310.7 7,197.4 6668 3.8125 7,478.7 7,366.6 7,254.9 7,140.0 6,968.3 6775 3.875 7,254.9 7,197.4 7,082.7 6,911.3 6,797.5 6883 3.9375 7,140.0 6,968.3 6,854.3 6,740.7 6,564.0 6990 4.00 6,968.3 6,797.5 6,684.1 6,564.0 6,444.3 e

ABB Cornbustion Engineering Nuclear Services Page 81 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 2-35 Minimum Volume Stored in Boric Acid Tank vs.

Stored Boric Acid Concentration for Modes 1, 2, 3, and 4 Minimum Stored Volume (Gallons)*

BAT CONC. BAT CONC. RWST RWST RWST RWST RWST (ppen (wt.% CONC. CONC. CONC. CONC. CONC.

Boron) Boric Acid) 2300 ppm 2350 ppm 2400 ppe 2450 ppm 2500 ppm 6560 3.75 7,850 7,700 7,600 7,450 7,300 6668 3.8125 7,600 7,500 7,400 7,250 7,100 6775 3.875 7,400 7,300 7,200 7,050 6,900 6883 3.9375 7,250 7,100 7,000 6,850 6,700 6990 4.0 7,100 6,900 6,800 6,700 6,550

Stored BAT Volume equal to Boration Volume from Table 2-34, plus 100 gallons for conservatism, rounded up to the nearest 50 gallons.

ABB Combustion Engineering Nuclear Services Page 82 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 2-36 Required Boron Concentration for a Cooldown From 547'F to 200*F Peak Xenon Scenario Temperature EOL + 140

'F Concentration (ppm boron) mummmmmmmmmmmmmmmmu 547 -107.2 637 -55.8 627 -8.1 517 42.7 507 93.2 497 136.8 487 183.6 477 230.9 467 267.3 457 310.7 447 347.0 437 386.9 427 426.0 417 459.0 407 496.0 397 526 8 387 560.1 377 592.7 367 6 21.3 357 651.6 347 876.7 337 706.8 327 734.2 317 756 8 307 784.4 297 807.8 287 831.7 277 855.2 267 878.7 257 900.7 247 918.9 237 940 0 227 9606 217 978.8 207 998.1 e 200 1013 0 200* 1033.9 a' After Shutdown Margin Change from 1.6% ak/k to 1.0% Ak/k ABB Combustion Engineering Nuclear Services Page 83 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 TABt.E 2 - 37 Salem NuclearGenerating Station - Peak Xenon Case Plant Cooldown from BAT 3.75 wt. % Boric Acid 70 P 547 T to 200 P RWST 2300 ppm Boric Acid 70 T AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS. VOLUME MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tl Vi Vf (T) (T) (psla) (cu.ftJibm) (cu.ftJibm) (Ibm) (gal) (gal) (!bm) (Ibm) (bm) (ppm boron) 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 0.0 527,311.7 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 311.2 311.2 535,611.2 101.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 369.9 681.2 545,476.3 218.3 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 237.2 918.4 551,802.7 291.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 227.1 1,145.5 557,859.4 359.0 563,481.8 500 490 2250 0.02009 0.01989 5.411.5 649.7 0.0 210.8 1,356.4 420.8 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 215.1 1,571.5 569,218.4 482.7 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 202.9 1,774.4 574,629.5 539.9 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 201.2 1,975.6 579,993.8 595.5 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 193.5 2,169.0 585,152.6 648.1 450 435 2250 0.01916 0.01892 7,086.4 850.8 0.0 276.1 2,445.1 592,515.1 721.5 435 420 2250 0.01892 0.01869 6,956.9 835.3 0.0 271.0 2,716.2 599,743.0 791.8 420 410 2250 0.01869 0.01855 4,523.1 543.1 0.0 176.2 2,892.4 604.442.4 836.6 410 400 2250 0.01855 0.01842 4,115.8 494.1 0.0 160.4 3,052.7 608,718.5 876.8 400 393 2250 0.01842 0.01832 3,141.3 377.1 0.0 122.4 3,175.1 611,982.1 907.1 393 380 2250 0.01832 0.01816 5,267.1 0.0 632.4 702 3,245.3 617,319.4 919.1 380 360 2250 0.01816 0.01792 7,978.2 0.0 957.9 106.4 3,351.7 625,404.0 937.0 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 49.7 3,401.4 629,182.2 945.2 360 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 3,401.4 636,797.2 933.9 350 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 3,401.4 631,221.5 942.1 350 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

0.01797 0.01797 0.0 0.0 0.0 0.0 3,913.9 726,336.1 942.1 350 350 350 350 0.01797 0.01743 21,571.2 0.0 2,589.9 287.6 4,201.5 748,194.9 981.8 350 300 0.01743 0.01707 15,139.0 0.0 1,817.6 201.8 4,403.3 763,535.8 1,008.3 300 260 350 0.01707 0.01683 10,452.5 0.0 1,254.9 139.3 4,542.7 774,127.6 1,025.9 260 230 350 0.01662 9,393.6 0.0 1,127.8 125.2 4,667.9 783,646.4 1,041.4 230 200 350 0.01683 VOLUME = 9,784.5 GALLONS l

~

[ TOTAL BAT l BACR Venon 2 XBB Combustion Engineering Nuclear Services Page 84 Of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 2-38 Calculation of the 73,800 Gallon RWST Volume In Bases Section 3/4.1.2 -

a 24,375.0 gallons System Feed-and-Bleed (Part D) 12,067.3 gallons Cooldown to 350'F and 350 psia (Part A) 6,790.3 gallons Cooldown to 200*F on RHRS (Part C) 43,232.6 gallons Total' 44,000.0 gallons Final Volume Rounded up to the nearest 1000 gallons 21,210.0 gallons Volume adjustment due to instrument tap location 8,550.0 gallons Volume adjustment due to instrumentation uncertainties 73,800.0 gallons Total volume required for cooldown using RWST only e

ABB Combustion Engineering Nuclear Services Page 85 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Tablo 2-39 Calculation of the 41,800 Gallon Volume in Bases Section 3/4.1.2 12,067.3 gallons Cooldown to 350*F and 350 psia (Part A) 6,790.3 gallons Cooldown to 200'F on RHRS (Parts B and C)

(6,968.3) gallons Smallest BAT Inventory for 2300 ppm Boron in RWST (from Table 2-13) 11,889.3 gallons Total 12,000.0 gallons Total, Rounded up to Nearest 1,000 gallons 21,210.0 gallons IVolumeadjustmentduetoinstrumen location 8,550.0 gallons Volume adjustment due to instrumentation uncertainties

?

41,800.0 gallons Total RWST volume required when minimum BAT volume is used I

ABB Combustion Engineering Nuclear Services Page. 86.of 133

' BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 FIGURE 2-1 SALEM -

UNITS 1 & 2 SOLUBILITY OF BORIC ACID IN WATER 20 0 -

U U 15 --

E O

e lNSOLUBLE 2R v

3:

10 -- . . . -

Z O

C SOLUBLE

$5 LU U

Z O

O -

I I I i 0 O 50 100 150 2 c' ,

TEB.' ;AATURE - "F h

l ABB Combustion Engineering Nuclear Services Page 87 of 133 ,

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 ,

F iGURE 2-2 SALEM - UNITS 1 ANO 2 REQUIRED BORON CONCENTRATION FOR PLANT COOLDOWN 1,000 800 --

Z O

C O _

(D E

a a 600 --

I Z

O 1- 400 -- 4 4

C H

Z w

o Z

O o 200 -. ,

Z O

C b

~

Q

$ 0 5

0 w _

E l (200) 600 500 400 300 200

, RCS 'EMPERATURE -

F ABB Combustion Engineering Nuclear Services Page 88 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECNNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 F I GURE 2- 3 EOL SALEM - MODES 5 & 6 COOLDOWN - 200*F TO 135*F INIT I AL FEED-&-8LEED FROM RWST @ 2300 ppm BORON 1000 FEED-&-BLEED FAOM RWST 4500 GALLONS t

~

INCREASE CONCENTRATION ,

893.9 ppm TO 960 ppm ggg __. . . (C.9.f. : . .T A.B L E S ?.- 3 , .4 .?. ,5.).

a s8 O s co - ,x ' '

/

E /

960 --

~<- -

y'. -

i /

Z J/

O / ~

9AO --

t- - .

p /

< Y T - ,/

H- /

Z '

/

920 --

-l. -

Z '

/ ,

O -

,/ EQUILIBRIUM XENON ;

(n /

L) 900 --

/- -

C !

u I

880 I I I 220 200 180 160 140 120 ;

ACS TEMPERATUAE - F ACTUAL CONC AEOUIAED CONC. '

o C ---p+--

ABB Combustion Engineering Nuclear Services Page 89 Of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606-TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 FIGUAE 2-4 -

.EOL a

SALEM - MODE 5 COOLDOWN - 200'F TO 135*F MAKEUP FROM BAT @ 3.75 wt% BORIC ACID 1,040

~

1,020 --

l Z

O c 1000 --

O ,

03 '

E o.

o. 980 --

/~

Z O ,

s' 960

'-y, '-

a -

/

Z LU 940 -

-A -

U /

Z )<'

O -

U j in 920 -- -

X' -

O s' C '

s'

~

,,a'

t 900 -- ,'

(ref. TABLES 2-3 & 2-6) 880 I ' ' '

220 200 180 160 140 1'20 RCS TEMPERATURE - F

., ACTUAL CONC REQUiAED CONC.

O ----M--- ,

r ABB Combustion Engineering Nuclear Services Page.90 of 133

___.--_i__..__-- . _ _ .

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY.'00 FIGURE.2 EOL 3 SALEM NUCLEAR GENEAATING STATION - UNITS 1 & 2 MODES 1 THROLGH 4 COOLDOWN - EQUlLlBRIUM XENON ;

1,000 - +

l Z 800 -

--/

O ,#'

a .-

O /

CD ~

/

g ,r' O. a' O. 600 -

,;f -

i

/ ,

Z _ / l O- '

/ ,

I

$ 400 -

/- - -

H RwST 0 2300 porn OOAON h '

/~/ BAT 0 3.75 wt% BOAIC ACIO ,

j

/ (ref. TABLES 2-7 & 2 .9)

O l 0 /

O 200 --

t-U /

C

/ :

0 ,

/ '

I ! I 1 600 500 400 300 200 100 !

l RCS TEMPERATURE - *F

.g ACTUAL CONC. AEOUIAED CONC.

ABB Combustion Engineering Nuclear Services Page 91 of 133 >

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND-OPERATIONAL ANALYSIS REY. 00 F IGURE 2-6 SALEM NUCLEAR GENERATING STATION -

UNITS 1 & 2 i BORATION VOLLME vs CONCENTRATION IN BAT ;

7,800 .l

l l

_) . . . ./.. . .:. . .; . . .; . .

I AEGION OF ACCEPTABLE OPERATION (n 7,600 z x-s <

i O N s .: l g y. .S.. .

l

< w , s 0 N s g.

s.

7, ADO -

%- s- - e i

\

s s

Xs l

s. <

g ,

% '?,g. .h s . .:. . . . ;. . . .2.

< ss s .- -

cD s.s..,~ s.v,,, N( - .

y 7,200 n.- -

'%:,_ - -- k;. , .' ' Q , - - - - +-

O cr

, s, , 's .,

.j M v$

s : Ne ll.

w

.4....

. .'3.....

N:, .I?sQ.,\..i.

s; y .,

s s. .s, s si

] 7,000 .

? L. , .

h.c, . A- q bh v- -

O

. w , -x.

. x. .

N, Z

'~. '

' .s 3..>.c..i.

'.(i . . . .i. . s... M 1

O 's'-

s-Q: hs

,,s .

s

> 6,800 :- : -

'M;q ' -%:: ,'s;-

A h CONCENTRATilON IN: RwST:

s,% :

. ; 'N,'t O 2300 ppm , ' N.,

CD -. . .; . ? %.,

g35 g . ppm. . .

v;

. .'s;;'N 2400 ppm -

2450 ppm * -

'N 6,600 "

'2500 pi.im' ~ : N .<'

' '. 'N ( .

.6560 opm

~~

-. ..CL25 wL%. , , . > . . ': n ,. ; .

. .. , 7 ,

6 400 I ' I i' ' i I '

6,600 6,700 6,800 6,900 -7,000-

, CONCENTRATInN.IN BAT- -

ppm BORON i

l ABB Combustion Engineering Nuclear Services Page 92 of 133

i BORIC-ACID CONCENTRATION REDUCTION' EFFORT CEN-606 'i TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 ,)

i F IGUAE 2- 7 SALEM NUCLEAR GENERATING-STATION - UNITS 1 & 2 BAT' STORED VOLUME REQUIRED vs. BAT CONCENTRATION W .

7,B00 - - - - - -

t- -

.AEGION OF ACCEPTABLE OPERATION.

g q. . . . . .i. .. . . ,

O \ '

s: -

J N

--l 7,600 Q;, , D .g. . ; . , '. . .i.

< s .

O 's . s:

s i .

I.'s. . . i N' . . . ;. . . . . .:. . . :. . . . :

s . .

}-

i

'f': .. N's s: s: ,

to 7,400 'N s.: ; ?T& -'>D N ---,, - L- - - -

s s . ,

- s:

x.s.s.

. h a s

g..

,S.

. s. . . A. s. s. . . . y. .

.s s. s.

w '

Xs 'N N s

f 7,200 ;N . ;. -

-3

.N;' s. '

'i :N % ::s-- N O ,s. ' *

's'q

.i. : 'g,. . . . ?g. . . .y. i . .i. ,,

s O .: s '

w .s a y,000 ; +

. ': . y;s. 's.

N s O

F

.Q: . .hs.

(f)

', s" ., . .' N, s. s-

' N

~

O d6NU$$NhkTION"IN'dNisYi '

N.

W C

- 2300 pprn ' -, , "'.- N,

- 6,800 .2150.pp C D

2A00 poni

. . . .s I-)

t

O .

's % s.

w 2450 ppm-

's,4 2 2$00 opni . .i. S..

l - . . ..

01 .

_ 6560 ppm ' ,..,

( 6,600 -

f ~ 75 ON - - - -

? e.'-

l h ! t ! t l l

6,600 6,700 6,800 6,900 7,000 l

l.

L .

CONCENTRAT'ON IN BAT -

ppm BORON t

l 1

- ABB Combustion Engineering Nuclear Services Page 93 of 133 l.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 3.0 OPERATIONAL ANALYSIS

3.1 INTRODUCTION

TO THE OPERATIONAL ANALYSIS The results of the evaluation performed to demonstrate the general impact on plant operations of a reduction in the boron concentration in the BATS are presented in this section. The specific areas discussed include (1) operator response to emergency situations, (2) typical plant feed-and-bleed operations, (3) typical plant blended makeup operations, (4) plant shutdown to refueling, and (5) plant shutdown to cold shutdown. Since it would be impossible to evaluate each of these five areas while considering all possible combinations of plant conditions, conservative initial plant parameters and analysis assumptions were selected for use in the analyses which would lead to " worst case" results. As a consequence, the results, i.e., the volumes and final concentrations that were obtained, will in general be bounding for any event or any set of initial plant conditions.

3.2 RESPONSE TO EMERGENCY SITUATIONS Several operating evolutions which may have to be performed in response to a variety of emergency situations are discussed in this section. Accident boration requirements, shutdown margin recovery, and emergency boration have been evaluated, and the findings are reported in the following paragraphs. This discussion includes an explanation of the manner in which the plant operating staff can continue to operate Salem Units 1 & 2 safely with a reduction in the boron concentration in the solution stored in the BATS.

ABB Combustion Engineering Nuclear Services Page 95 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 3.2.1 Accident Boration Recuirements During the feasibility study, the plant Accident Analyses in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) were reviewed. In the UFSAR, no mention is made of boric acid addition to the RCS from the BATS. During safety injection, the charging pumps are aligned to the RWST for reactivity control. Accordingly, the immediate consequences of such events as the steam line break, overcooling, boron dilution, etc., will not be affected by the red'uction in the concentration of boron in the BATS.

A generic concern exists regarding a potential return to criticality during the cooldown following a Main Steam Line Break (MSLB) or a Steam Generator Tube Rupture (SGTR) event.

Following is a list of plant instructions and procedures which instruct the operator, either directly or by reference, to maintain shutdown margin by boration either from the RWST or the BAT. With the reduction in ,

concentration in the BATS, it will be necessary to revise the required BAT volumes. With a minimum concentration of 3.75 wt% boric acid, the new required volumes will be 3.2 times greater than the present requirements.

I S1.OP-SO.CVC-0006(Q) Boron Concentration Control OP-AB.SG-0001(Q) Steam Generator Tube Leak EOP-SGTR 1 Steam Generator Tube Rupture EOP-SGTR 2 Post-SGTR Cooldown l EOP-SGTR 3 SGTR with LOCA, Subcooled Recovery I.

EOP-SGTR 4 SGTR with LOCA, Saturated Recovery

. EOP-LOCA 2 Post-LOCA Cooldewn with Depressurization EOP-FRSM 2 Response to Loss of Core Shutdown ABB Combustion Engineering Nuclear Services Page 96 of 133 l

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.I BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00.

l EOP-LOSC 1 Loss of Secondary Coolant EOP-LOSC 2 Multiple Steam Generator Depressurization EOP-TRIP-5 Natural Circulation Cooldown without RVLIS During an MSLB, plant procedures and instructions-also direct the operating personnel to borate the RCS to maintain shutdown margin. With the reduction in BAT concentration, it will also be necessary to revise the requirements for stored volume in the BATS, as in the case of the SGTR discussed above.

3.2.2 Shutdown Marain Recovery In the event that the required shutdown margin is lost, the action statements associated with Technical Specifications 3.1.1, 3.1.2, 3.9.1, and 3.10.1 require that boration be initiated immediately. In Technical Surveillance Requirement 4.1.2.2, verification is required that a flow rate of 10 gpm is provided by the boration system flow path from the BATS to the RCS. This requirement is discussed in detail in Section 2 of this report. The reduction in boric acid concentration in the' BATS necessitates a revision to the TSR, increasing the flow rate' requirement from 10 gpm to 33 gpa.

T t

i e

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poRIC ACID CONCENTRATION REDUCTION EFFORT CEM-606 TECRErICAL BAaBS AND OPERATIOMAL ANALY8I8 REY. 00 3.2.3 Emer_cency Beration The main flow path for emergency boration runs from the ,

boric acid transfer pumps directly to the charging pump suction, via emergency flow control valve, 1(2)-CV-175.

These flow control valves and the flow path are designed for a flow of 150 gpm, the output of 2 boric acid transfer pumps.

f-The Salem Boron Concentration Control Procedure, S1.0P-SO.CVC-0006(Q), discusses the use of other flow paths for emergency boration. Boric acid solution can be charged through either the normal boration path (via 1(2)-CV-172 and 1(2)-CV-181), or the alternate emergency boration path (via 1(2)-CV-172 and 1(2)-CV-174). In the existing configuration, 1-inch diameter piping has been used in these flow paths. Should it be necessary to increase the system flow capacity, the piping in the normal boration flow path to the charging pump suction may be replaced with 2-inch diameter piping. Since the alternate emergency flow path is the third option, with limited usage, it is judged that this piping may remain as 1-inch diameter.

Information is also provided regarding the volumo(s) of boric acid required for boration when energency boration is called for in response to a cooldown or in the event one or more Rod Cluster Control Assemblies (RCCAs) are not fully i inserted. A listing is provided of the required volumes of boric acid solution at a concentration of 20,000 ppm; volumes are provided as a function of RCS average temperature range and as a function of the number of RCCAs not fully inserted. At the new minimum concentration of solution in the BATS, 3.75 weight percent, it will be ABB Combustion Engineering Nuclear Services Page 98 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 necessary to revise the listing to increase the volumes of i solution which must be maintained in the BATS by a factor of 3.2, i.e, the stored volume will be 3.2 times greater than the volumes currently listed. 1 l

3.3 FEED-AND-BLEED OPERATIONS i During a feed-and-bleed operation performed to increase system boron concentration, 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 at any given point in time is proportional to the difference between the system concentration and the concentration in the charging fluid. The equation describing feed-and-bleed has been derived from this relationship; the equation and its derivation are presented in Appendix 1. It is axiomatic that, with a reduction in the boron concentration in the BATS to the point at which heat tracing is no longer required, the maximum rate of change of RCS boron concentration that can be achieved during feed-and-bleed will be less than is currently achievable.

The purpose of the evaluation described in this Section was to determine the rate of change in RCS boron concentration which may be achieved with a reduced concentration of boron in the BATS, using feed-and-bleed. The analysis was j performed assuming hot zero power conditions, with other key parameters and conditions as shown in Table 3-1. Feed-and-bleed operation was analyzed with one and two charging pumps

. operating, and from initial boron concentrations in the RCS of zero ppm and 1000 ppm.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 r

The results are presented in Tables 3-2 through 3-5.

Equation 9.0 cf Appendix 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:

i (m,) =

(m ) ,

+ (m.) [

or g, ) ,

10,812 fc3 .

500.0 fc3 = 5 27 , 3 0 8 . 3 lb,,

0. 021251 fc3/lb,m 0. 02698 fc3/lb,ta) t From this system mass (527,3 08. 3 lb,) , the value of the i feed-and-bleed time constant with one charging pump l delivering 75 gpm is 527, 3 0 8. 3 lb,,

7 5 gpm x 8. 329 lb,,/ gallon W or !

T = 844.13 minutes The value of the Feed-and-Bleed time constant with two charging pumps delivering 75 gpm each (total of 150 gpm) is e

Specific volume of compressed water 0 547*F and 2250 psia f, Specific volume of saturated water 9 2250 psia Density of water at 70*F ABB Combustion Engineering Nuclear Services Page 100 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEM-606 ,

TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 527,3 08. 3 lb, 150 gpm x 8. 3 29 lb,,/ gal or ,

t uo = 420.07 minutes NOTE: Use of 2 charging pumps is limited to Modes 1, 2, and 3 by TS 3.1.4.

The boron concentration required for the cases shown in Tables 3-2 through 3-5 are plotted in Figures 3-1-through 3-4 for comparison. Note that even with reduced boric acid concentrations in the BATS, significant rates of increase-in-boron concentration in the RCS will still be achievable.

3.4 BLENDED MAKEUP OPERATIONS During typical plant blending operations, concentrated boric-acid via 1(2)-CV-172 is mixed with demineralized water via 1(2)-CV-179 at the blending tee and then added to ,

the volume control tank (VCT). Since the ability to blend '

and add makeup to the RCS and to other systems is important to plant operations, two parametric studies were performed to demonstrate the effect of a reduction in boron concentration in the BAT. The studies performed were as follows:

1. Flow through 1(2)-CV-172 was varied between 2.0 gpm and

40.0 gpm while the flow through 1(2)-CV-179 is varied to give a total flow out of the blending tee of 75 gpm, through Flow Control Valve 1(2)-CV-181.

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 i TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00

2. Flow through 1(2)-CV-172 is varied between 2.0 gpm and 40.0 gpm while the flow through 1(2)-CV-179 is varied to give a total flow out of the blending tee of 150 gpm, through Flow Control Valve 1(2)-CV-181.

In each of these studies, the temperature in both the BAT and the demineralized water supply was assumed to be 70*F, ,

and boric acid concentrations of 3.75, 3.8125, 3.875, 3.9375, and 4.0 weight percent were considered.

The results are shown in tables 3-6 and 3-7. The final concentration out of the blending tee in each of these tables was obtained using the following equation:

(Fy x Cy) (100) (1748.34)

(Fy x C y) + (Fouc XD)iir i

In this equation, C,t is the boron concentration leaving the ,

blending tee in ppm boron, Fy is the flowrate coming out of 1(2)-CV-172 in gallons per minute, Cy is the boron concentration in the BATS Ib, per gallon, F,, is the total ;

i flow leaving the blending tee in gpm, D, is the density of water at 70*F in lb, per gallon, and 1748.34 is the conversion factor between concentration expressed in weight ,

percent boric acid and concentration expressed in terms of ppm boron. (see Appendix 3 for a derivation of this conversion factor). The data contained in Tables 3-6 and 3-7 are plotted in Figures 3-5 and 3-6. Note that following the reduction in BAT concentration, a full range of L

i flowrates and boron concentrations is available for blended .

l makeup operations.

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- l BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 :

TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 l i

3.5 SHUTDOWN TO REFUELING - MODE 6 Shutdown to refueling conditions is normally the most limiting evolution that an operator must perform involving system boration, i.e., this evolution involves the addition of the maximum amount of boron to the RCS. A shutdown to refueling normally occurs at the end of each fuel cycle, when the boron concentration for criticality is low, and an increase to the refueling boron concentration must be accomplished. In the most limiting case, boron concentration must be raised from zero ppm to an assumed refueling concentration of 2300 ppm.

The results of the evaluation of plant shutdown to refueling conditions are discussed in this Section. The evaluation was performed to demonstrate the effect on makeup inventory requirements of a reduction in BAT concentration. A list of key parameters and conditions assumed in the analysis is contained in, Table 3-8. The evaluation was performed for EOL conditions in order to maximize the amount of boron that must be added to the RCS. During'this transient, it is necessary to increase the boron concentration in the RCS from zero ppm to the assumed refueling concentration of 2300 ppm. The shutdown for refueling was assumed to take place as follows:

1. RCCAs are inserted to bring the reactor to hot zero power conditions.

2. At time = 0 (following shutdown), feed-and-bleed is commenced, with one charging pump operating and taking suction from the BATS. (Two cases were run, the first with the boron concentration in the BATS at 3.75 weight ABB Cornbustion Engineering Nuclear Services Page 103 of 133

. ._ _ . . . _ ~ - - . - - .-

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 percent, the second with the concentration in the BATS at 4.00 weight percent).

3. The feed-and-bleed operation is continued for 168 minutes for the first case (BATS at 3.75 weight percent) and for 107 minutes in the second (BATS at 4.0 weight percent).

4. Plant cooldown and depressurization is commenced, taking the RCS from an average coolant temperature and ,

system pressure of 547'F and 2250 psia, to a pressure of 350 psia and an average coolant temperature 5 350*F.

5. The RHRS is aligned and placed in operation after the primary coolant is at 350 psia and the temperature has decreased below 350*F; the boron concentration in the RHRS is assumed to be equal to that in the RCS.

6. Following alignment of the RHRS, plant cooldown-is continued from 350*F to 135'F at'350 psia.

7. Makeup inventory is supplied from the BATS.

The boric acid concentration as a function of temperature and the corresponding inventory required from the. BATS as determined by the analysis are shown in Tables 3-9 and 3-10.

The coolant average temperature and boron concentration data.

from this table are plotted in Figures 3-7 and 3-8. The boric acid concentration during the initial feed-and-bleed operation was calculated for each case using the' methodology e discussed in Section 3.3 above. Concentration during the subsequent plant cooldown was calculated in the same manner as the concentration for the plant cooldown in Section 2.4.

ABB Combustion Engineering Nuclear Services Page 104 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Note that the boron content of the RCS was raised from zero ppm at the start of the evaluation to greater than 2300 ppm by the time the plant had been cooled and depressurized to 135'F and 350 psia. A total volume of 29,962.6 gallons of 3.75 weight percent boric acid solution was required. Of this volume, 9,075.0 gallons were used during the initial 121 minute feed-and-bleed operation, and 20,887.6 gallons were charged into the P.CS to compensate for coolant shrinkage during the cooldown. For the 4.0 weight percent case, a total volume of 28,912.6 gallons was required. Of this volume, 8,025.0 gallons were used during the 107 minute feed-and-bleed operation, and 20,887.6 gallons were charged to compensate for coolant contraction.

Each BAT contains a usable volume of approximately 7,500 gallons, defined as the volume between upper and lower leve]

taps. There are two BATS in each unit; thus the available volume from both tanks is approximately 15,000 gallons. As shown in Table 3-10, the volume of 4.0 weight percent boric acid solution required to conduct the shutdown to refueling operation is approximately 1.9 times the capacity of the BATS. (With a boron concentration of 3.75 weight percent in the BATS, the volume required is 2.0 times the capacity of two BATS). This result is conservative or bounding and thus represents the maximum volume that could be required, l

assuming a refueling concentration of 2300 ppm boron and the specified BAT concentration. The stored volume of boric acid solution required by Technical Specifications 3.1.5 and 3.1.6 should be contained in one BAT for each Unit. Since I

there are only two BATS for each Unit, with a combined

. capacity of approximately 15,000 gallons, additional provisions or operator action may be required in order to establish a Mode 6 condition in the plant.

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t BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 These provisions could include some combination of the following:

1. The initial plant feed-and-bleed and some portion of the plant cooldown.may be performed using the RWST, decreasing the total inventory needed from the BATS.

2. a. Prior to commencing the evolution, both BATS are filled and are available for use'.

b. During the initial phase of the 'ooldown, c makeup may be taken from one BAT until depleted. ,

The charging pumps may then be realigned to take suction from the second BAT for continued charging, and the first BAT may be replenished i while cooldown is continued. ,

These provisions or operator actions would be necessary only. j once during each fuel cycle, just prior to the time a shutdown for refueling is to be performed. These are ;

relatively simple actions which may be planned in advance so {

as to have no impact on maintenance activities or on the ;

refueling schedule.

a P

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s _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ _ . - _

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 3.6 SHUTDOWN TO COLD SHUTDOWN - MODE 5 As discussed above, shutdown to refueling is the most limiting evolution that an operator must perform involving system boration. That evolution is normally performed only once during each fuel cycle, just prior to refueling.

Conditions such as unscheduled plant maintenance may occur during a fuel cycle, however, which require that the plant be taken to cold shutdown conditions. Although not limiting with respect to boration requirements, it is important to have the ability to perform such a shutdown quickly and efficiently.

The results of the evaluation of shutdown to cold shutdown are described in this section. The analysis was performed to determine the effect on makeup inventory requirements of a reduction in BAT concentration. A list of key parameters and conditions assumed in the analysis is contained in Table 3-11.

This evaluation was performed for EOL conditions, with an MTC of -44 and an assumed required cold shutdown boron concentration of 920.8 ppm boron. The actual concentration required through most of cycle life will be lower, and the volume of boric acid actually required from the BATS will be significantly lower than those calculated herein. The steps followed in reaching cold shutdown are as follows:

1. RCCAs are inserted to bring the reactor to hot zero power conditions. ,

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1 BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 l i

2. A plant cooldown and depressurization is initiated to reduce system pressure from 2250 to 350 psia and ;

average coolant temperature from 547'F to a temperature 5350*F. Hakeup inventory is supplied from the BATS.

3. The RHRS is aligned and placed in operation at a pressure of 350 psia and a temperature 1350*F.

4. After placing the RHRS in operation, plant cooldown is continued from 350*F to 200*F. Makeup inventory is supplied from the BATS.

The results of the evaluation showing the system boron concentration as a function of temperature and the total BAT inventory requirements are given in Tables 3-12 and 3-13.

In both cases, the concentration in the RHRS was assumed to be equal to the concentration of the RCS at the time of RHRS initiation. System boron concentration as a function of temperature ,is plotted in Figures 3-9 and 3-10. The concentration at each timo step during the plant cooldown was calculated using the methodology described in Section 2.4 of this report. During the period in which blended makeup was used, data was calculated using the methodology described in Section 3.4.

A total volume of 11,963.6 gallons of 3.75 weight percent boric acid solution (11,366.0 gallons of 4.0 weight percent) >

was required to complete the shutdown to cold shutdown with the boric acid concentration in the RHRS equal to that in the RCS at the time of system initiation. These results are

, conservative, as plant operating procedures require.

recirculation of the RHRS through the RWST prior to initiation of RHRS, and the concentration within that system ABB Combustion Engineering Nuclear Services Page 108 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 will normally be at or near that of the RWST any time that the RHRS is placed in operation.

3.7 LONG TERM COOLING AND CONTAINMENT SUMP pH The impact of the Boric Acid Reduction Effort on post-LOCA long term cooling and containment sump pH has been reviewed ,

and evaluated. The results of each evaluation are discussed qualitatively below. .

Typically, the performance of the Emergency Core Cooling System (ECCS) during extended periods of time following a' loss-of-coolant accident (LOCA) is analyzed to address residual heat removal via continuous boiling of fluid in the reactor vessel. As borated water is delivered to the core region via safety injection while virtually pure water escapes as steam, high levels _of boric acid may accumulate in the reactor vessel. As an input to this analysis, boron con.entration in the BATS was assumed to be at the maximum concentration of 22,500 ppm (12.87 weight percent). .Any such calculation will conservatively bound the maximum boric acid and tank concentration of 4.0 weight percent proposed as the result of the analysis described in this report.

1 Since the solution stored in'the BATS is not pumped into the.

RCS by the Emergency Core Cooling System during the Design Basis Accident, the change in BAT concentration proposed herein will have no effect on the containment Sump pH Analysis. .

t I

ABB Combustion Engineering Nuclear Services Page 109 of 133 ;

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i BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 3-1 Salem Nuclear Generating Station - Units 1 & 2 Key Plant Parameters and Conditions Assumed in Generating the Feed-and-Bleed Curves 3

RCS Volume 10,812 ft RCS Pressure 2250 psia RCS Average 547'F Temperature 3

Pressurizer Volume 500.0 ft Pressurizer Temp. Saturation

& Press.

RCS Leakage Zero BAT Temperature 70*F Mixing Between RCS Complete and and PER Instantaneous PER Level During Constant Feed and Bleed Letdown Flowrate:

1 - Charging Pump 75 gym 2 - Charging Pumps 150 gpa ABB Combustion Engineering Nuclear Services Page 110 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 I

TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3 - 2

.. SAWM NUCLEAR GENERATING STATION - FEED AND BLEED EVALUATION FEED-A-BLEED @ 75 GPM: INITIAL CONCENTRATION @ 0 ppm BORON TIME EXFOMEDfnAL CDNC w/ OONC W/ CONC W/ QNC W/ CONC W/ CONC W/

VALUE RWST @ 2300 gia BAT @ 3.75 wV% BAT @ 3.8125 wV% BAT @ 3.875 wV% BAT @ 3.9J75 ott% BAT @ 440meE (minstes) l-e ^ (-LAsu) ppm gpa ppen pgun ppen g5am 0.00 0.00CD 0.000 OD'" 0.000 0.000 0.000 0.000 10.00 0.0118 27.086 77211 78.497 79.784 81071 82.358 20 00 0.Q134 53.853 153.512 156.070 158.29 161.187 163.746 30.00 0.03 6 80.305 228.915 232.730 236.545 240360 244.176 40.00 0.0463 106.446 303.429 308.486 313 344 318.e01 323.658

50.00 0.0575 132278 377.067 383.351 389.635 395 K 0 402 m 60.00 0.06M 157.807 449.837 457.334 464.831 472 E8 479 r6 70.00 0.0796 183Q14 521.750 530.445 539.141 547.837 556533 80 00 0.090s 207.965 592.816 602.696 612.576 622.457 632 117 l

90 00 0.1011 232.602 663.045 674.0M 681146 696 197 707248 100(U 0.1117 256.949 732.447 744.655 756.M2 769tb9 781277 l 110.00 0.1222 281.009 801.032 814.383 827.733 841.054 854 434 120m 0.1325 304.786 868 2 9 883289 897.M 912250 926.730 130m 0.1427 328283 935.788 951J85 966.951 982.577 998.174 140.00 0.1528 351 503 1001.978 1015678 1031378 1052 077 106& 777 150 00 0 1628 374.450 1067.389 1081179 lic969 Il2a758 183&548 100m 0.1727 397.126 1131029 115a896 I169.764 118& 631 1207_498 170.00 0 1824 419.535 1191908 1211840 1231772 1251704 1271636

~

I80 00 0.1920 441.681 1259.035 128a019 ,

l301.003 1321 987 1341971 190 00 0.2016 463.566 1321.419 1341442 1361466 1387490 1409.513 2002 0.2110 4&5.192 138.1067 140&ll9 1429.170 1452.221 1975272 210 00 02202 506.565 1441990 1468.057 1491123 1516190 1543256 01294 527.685 1504.1 % 1529265 1554.335 1579 405 1fx)4 475 220m 01385 548.557 1561692 1589.753 1611815 1641.876 1667.938 230 00 0.2475 569.183 1621487 1649S29 1676570 1701612 1730653 240(D ABB Combustion Engineering Nuclear Services Page III of 133 WSASEC3FB i

e BORIC ACID CONCENTRAllON REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV.00 TABLE 3- 3 SALEM NUCLEAR GENERATING STATION - FEED AND BLEED EVALUA110N FEED-A-BLEED @ 150 GPM; INITIAL CONCENTRATION @ 0 ppm BORON

TIME EK N L CDNC ed ODNC WI CONC W/ CDNC W/ CONCW/ CONC W/

j VAllJE RWST @ 2300 ppe BAT @ 3.75 wt/% BAT @ 3.8125 wi/% BAT @ 3.875 wt/% BAT @ 3.9375 wire BAT @ 4.00wi/%

. (minute) 1-e " (-tAae) ppua ppm ppe ppe ppe ppa

! 0.00 0_00G) 0.000 0.000 0.000 0.000 0.000 0.000 ,

10.00 0.0234 $3.853 153.512 156 070 158.629 161.187 161746 20.00 OD463 106.446 303 429 308.486 313.544 318.e01 323 658 30.00 OJ0686 157A07 449.837 457.D4 464.831 4 72.3I8 479.8 M 40.00 0.0904 207.965 592.816 602.e96 612.576 622.457 632.137 50.00 0.1117 256.949 732.447 744.655 7 % 862 769.069 781277 60 00 0.1325 304.786 868.809 883289 897.769 912.250 926.730 70 00 0.1528 351.503 1001.978 1011678 1031378 1051077 106&777 ,

so ul 0.1727 397.126 1131029 Il5a896 1869.764 118& 633 1207.498 90 01 0.1920 441.681 1259 035 128a019 1301.003 1321.987 1341973 100.00 0.2110 485.192 1381067 1406119 I429.170 1452.221 1475272 110.00 02294 527.685 1504.196 1529265 1554.335 1579.405 1604 475 120.00 02475 569.183 1621487 1649529 167&570 1701612 173a653 130R) 0.2651 609.709 173&O10 17% 976 1791943 1824910 1851877 140.00 0.2823 649287 I85a827 1881474 1911521 1941368 1974.215 150.00 02991 687.937 1961.003 1991686 2026369 2059053 209L736 160.00 0.3155 - 725.683 2061599 2101075 2137.552 2171028 220&505 170.00 0.3315 762.545 2171675 2209.903 22M131 2281359 2311587 180.00 0.3472 798.543 2276292 2314.230 2351168 2390 106 2421044 190.00 0.3625 831699 2376505 241&lI4 2451722 2495.330 2534939 200.G1 03774 868432 2474.372 2515 612 25 % 851 259E&71 2639331 ,

210.00 03920 901.561 2569.948 - 2611781 2651613 2691 446 2741278 220.00 0.4062 934.305 2661286 2707.674 2751062 279&450 284a838 0.4201 966.282 2754 438 280a346 28 M 253 2891160 293&ou 230.00 0 4337 997.510 2841456 289a847 2938238 2981629 3033020 240.00 l ABB Combustion Engineering Nuclear Services Page 112 of 133 WSASEC3FB i

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t BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 l

TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3 - 4 SALEM NUCLEAR GENERABNG STADON - FEED AND BLEED EVALUABON FEED- A-BLEED @ 75 GPM; INITIAL CONCENTRARON @ 1000 ppm BORON 11ME 1-EXP EKPONENTIAL CX)NC ut l CDNC W/ CONC W/ CONC W/ CI)NC W/ CONC W/ ,

VALUE VALUE RWST @ 2300 ppen ' BAT @ 3.75 wv5 BAT @ 3.8125 wt/% BAT @ 3.875 e6 BAT @ 3 9375 wt/% BAT @ 4.00=v5

=

(misutes) l-e ^ (-tAau) e ^ (-tAau) ppen ppen ppen ppen nun ppan v 0.00 0.0000 IJ0000 100a000 100a000 100n000 100a000 100a000 louacuo 10.00 0.0118 0.9882 1015310 1061434 10M 721 106&o08 1069295 ItT7a581 t 20.00 0.0234 0.9766 103a439 113a097 1131656 1131214 1137.773 114a332 30.00 0.0349 0. % 51 1041390 1191999 1197J14 1201430 1201445 1209260 t 40.00 0.0463 0.9537 106al65 1257.149 1261206 1267.263 1272.320 1277.377 I 50 00 0.0575 0.9425 1074766 1389.554 1321839 1331123 133&406 1344692 60.00 0.0686 0.9314 1089.195 1381.225 138&722 1396220 1401717 1411.214 70 00 0.0796 0.9204 1101454 1441169 145a865 1459.561 146&257 147&953 ,

60 00 0 0'JO4 0.9096 1117.545 1501396 1512.276 1521 157 1531037 1541.917 90 ou 0.10 I 0.8969 1131.471 1561.914 1571964 1584 015 1595 066 1606117 i

i. 1631938 1641145 1657.353 1669.560 i 100.00 0.1117 08883 1145232 1620 730 110m 0.1222 0.8778 115&831 1671854 1691205 1701555 171&906 1731256 120.00 0 1325 0.8675 1172.270 17%293 175a774 1765254 1779.734 1794214 130.00 0.1427 0.8573 118155I 1791056 1808653 1824249 1839 846 1555442 140.00 0 1528 0.8472 l19& 676 I849I5I I865 85I I882.550 1899250 1911949 150.00 0.1628 0.8372 1211.645 1904.585 1921375 194al64 1957.954 1971744 0.1727 0.8273 1224463 1959.366 197&233 1997.100 2011967 2034834 160.00 0.1824 0.81M 1237.129 2011502 2011434 2051365 2071297 2tN1229 170.00 0.1920 0.8080 1249.646 2067.0m) 2087.984 210&968 2129.952 215a936 .

180.00 02016 0.7904 1261015 2119.869 2141.892 2161916 2181939 2207.963 190.00 01110 0.7890 1274239 2171114 2191165 221&217 2241268 2264.319 200.00 ,

0.7798 1286319 2:21745 2247.811 2278.878 2291944 2323011 2 tom 0.2202 .

0.2294 0.7706 129&257 2274767 2299.837 232t907 2349 777 2375 047 220.00 0.7615 131a054 2321189 2351250 2377.312 2401373 2429435 230 2 02385 0 7525 1321.712 2371087 2401058 2429.099 2456141 2481182 240 00 02475 ABB Combustion Engineering Nuclear Services Page 113 0f 133 r wsAstura I

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3- 5 SAGM NUCLEAR GENERATING STAHON - FEED AND BLEED EVALUATION FEED- A-BWED @ 150 GPM; INITIAL CONCENTRATION @ 1000 ppm BORON VME l-EXP EXPONENDAL CONCad (X)NC W/ CONC W/ OONC W/ CONC W/ CONC W/

VALUE VALUE RWST @ 2300 pra BAT @ 3.75 wt/% BAT @ 3.8125 wi/% BAT @ 3.875 wt/% BAT @ 3.9375 wt/% BAT @ 4 00 wtr%

(minutes) 1-e * (-tAsu) e^(-RAau) ppm ppa ppa ppa ppa ppa 0.00 0.0000 1.00G) 100a000 100a000 100a000 100a000 100a000 10tM ou0 10.00 0.GZ34 0.97 2 10 2 439 113a097 1131656 1131214 1137.773 114a332 20.00 0.0463 0.9537 106al65 1257.149 IM W 1267263 1271320 1277.377 30.00 0.0686 0.9314 1039.195 1381225 138&722 13 % 220 1401717 1411234 40.00 0 0904 0.9096 1117345 1501396 1512.276 1521157 1531037 1541917 50.00 0.1117 0.8883 1141232 162a730 1632.938 1641145 1657353 1669 560 60.00 0.1325 0.8675 1872270 17%293 175a774 1765254 1779.734 1794214 70 00 0 1528 0 8472 119&676 I849.I51 1861851 1882.550 1899250 1911949 N)OO 01727 0.8273 1224.463 1959366 197&233 1997.100 2011 % 7 2034834 w in) 01920 0 8080 1249.646 2067.000 2087.984 2101968 2129.952 2150 936 100 01 0.2110 0.789) 1274139 2171114 2191165 221&217 2241268 2264319 110.00 0.2294 0.7706 129&257 2274 767 2299.837 2324.907 2349.977 2371047 120.G) 02475 0.7525 1321.712 2371017 2401058 2429 099 24 % 141 2481182 130,00 0.2651 0.7349 1344 618 2471919 2501.885 253Q852 2559 819 258&786 02823 0.7177 1366988 256&528 2599.375 263a223 2661 070 2691917 140 00 02991 0.7009 138& 834 2661.899 2694.583 2727266 2759.950 2791633 150 00 0.3155 0.6845 141Q169 2751084 2787.561 2821038 28 % 514 2891WI 160.00 0.6685 1431.004 2841134 2878362 2914.590 295a818 2987 046 170.00 0.3315 0.3472 0.6528 1451351 2729 099 2 % 7.037 3004 975 3041913 3twi852 180 00 0.6375 1471221 3014.027 3051636 3091244 3132.853 3172.46l 190.00 03625 03774 0.6226 149a627 30 % % 7 313&207 3179.446 322a686 3261.925 200.00 0.6080 1509.578 3177.965 322a798 3261630 3306463 3349.295 210.00 0.3920 0.5938 1521 085 3257.067 3301 455 3341843 339a231 3434 619 220.00 0.4062 0.579) 1546159 3334.316 338a223 3426130 3471038 3517.945 230 00 0.4201 1561810 3409.756 3457.147 3504.538 3551.929 35W 320 240 06 0 4337 0 5663

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Page 114 of 133

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN 606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 i

TABLE 3-6 SALEM NUQ. EAR GENERATING STATION - TYPICAL BLENDED MAKEUP OPERATIONS

@ '75 GPM OUT OF BLENDING TEE CONCENTRATION OUT OF TEE (ppm BORON)

FLOW (GPM)*IEROUGH BAT BAT BAT BAT BAT 1(2)-CV-172 1(2)-CV-179 @ 3.75 wt% @ 3E12S wt% - @ 3E75 wt% @ 39375 wi% @ 4Dwt%

i 2.00 73.00 181A6 18460 187.74 19039 194D4 4.00 71.00 36234 36831 375D8 38137 38746 6.00 69.00 543.25 55264 562D2 571A3 58034 8.00 67.00 72358 736D7 74836 761D8 77360 10.00 65.00 90354 919.12 934.70 95032 96593 12.00 63.00 1083.13 1101.79 112a44 1139.14 1157E4 14.00 61.00 126235 1284.07 1305.79 1327.56 134932 16.00 59.00 1441.20 1465.97 1490.74 1515.56 154038 18.00 57.00 1619.68 1647.49 167530 1703.16 1731.02 20.00 55.00 1797.80 182& 63 1859.46 189036 1921.24 22.00 53.00 1975.55 2009.40 204323 2077.15 2111.05

- 24.00 51.00 2152.93 2189.78 2226t62 2263.53 2300.44 26.00 49.00 2329.95 2369.79 2409.61 2449.52 2489.41 28.00 47.00 250&61 2549.42 2592.22 2635.10 2677.97 30.00 45.00 2682.90 272&68 2774.44 2820.29 236612 32.00 43.00 285&84 2907.57 295&27 3005.08 3053.85 34.00 41.00 3034.42 3086c08 3137.72 3189.47 3241.18 36.00 39.00 3209.63 3264.23 331&79 3373.46 342&l0

38.00 37.00 3384.49 3442.01 3499.48 3557B7 3614.61 40.00 35.00 3559.00 3619.41 3679.78 3740.27 380a72 ABB Combustion Engineering Nuclear Services Page 115 of 133 BLEND

- - . . _ . . . . . . _ . , .- . . _ - . ~ . _ . . . . _- ,_ . ._ -- ._. -

. _ . _ _ = _ _ _ _ _ _

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN 606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-7 SALEM NUCLEAR GENERATING STATION - TYPICAL BLENDED MAKEUP OPERATIONS

@ 150 GPM OUTOF BLENDING TEE CONCENTRATION OUT OF TEE (ppm BORON)

FLOW (GPM)THROUGH BAT BAT I BAT BAT BAT 1(2)-CV-172 1(2)-CV-179 @ 3.75 wt% @ 3E125 wt% @ 3375 wt% @ 39375 wt% @ 4D wt%

2.00 148D0 90.78 92.35 93.92 95.50 97.03 4.00 14600 181.46 18460 187.74 190B9 1941M 6.00 144.00 272D5 276.76 281.46 286.18 29090 8.00 142D0 36234 36831 375D8 38137 38766 10.00 140D0 45294 460.77 468L0 476.45 48430 12.00 138DO 54325 55264 562D2 571.43 58034 14.00 136D0 633.46 644.40 65534 66631 67727 16.00 134D0 72338 736D7 74836 761D8 77360 1800 132D0 81361 82765 84168 855.75 869E2 20.00 130D0 90334 919.12 934.70 95032 96593 22.00 128.00 99339 101031 1027.62 1044.78 1061.94 24.00 126D0 1083.13 1101.79 1120.44 1139.14 1157E4 26.00 124D0 1172.79 1192.98 1213.17 1233.40 1253.63 28.00 122D0 126235 1284.07 1305.79 132736 134932 30.00 120D0 1351.82 1375.07 139831 1421.61 1444.90 32.00 118D0 1441.20 1465.97 1490.74 151536 154038 34.00 116D0 1530.49 1556.78 1583.07 1609.41 1635.75 36.00 114D0 1619.68 1647.49 167530 1703.16 1731.02 38.00 112D0 1708.79 1738.11 1767.43 1796.81 1826.18 40.00 110D0 179720 1828.63 1859.46 189036 1921.24 ABB Combustion Engineering Nuclear Services Page 116 of 133 BLEND

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 3 - 8 Key Plant Parameters and Conditions Assumed in the Shutdown-to-Refueling Evaluation 3

RCS Volume 10,812 ft Initial RCS Average 547'F Loop Temperature 3

Pressurizer Volume 500.0 ft Pressurizar Pressure Saturation RCS Leakage Zero BAT Temperature 70*F Mixing Between RCS Complete and and Pressurizer Instantaneous Pressurizer Level Constant During Feed & Bleed Initial RCS Concentration 0 ppm Boron BAT Concentration 3.75 & 4.0 wt.% Borio Acid RWST Concentration 2300 ppa Boron 3

RERS Volume 1700 ft Boron Concentration in RERS=

Boron Concentration in RCS at Time of RERS Initiation Refueling Concentration 2300 ppa boron (Mode 6)

O ABB Combustion Engineering Nuclear Services Page 117 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV.00 TABLE 3-9 SALEM NUCLEARGENERATING STATION - REFUELING COOLDOWN FROM 547*F TO 135"F FEED-AND-BLEED AND MAKEUP FROM BAT w/3,75 wt% BORIC ACID @ 70"F AVG.SYS. TEM P. PZR SPECIFIC VOLUME SIIRINKAGE BAT VOL B/A TOTAL TOTAL SYST. FINAL PRESS. MASS @ 70*F ADDED BORIC ACID MASS CONC.

Ti rr) To cP) (p..) vi(nub.) vt(rimb.) 06.) (g.11...) (16.) (16.) (16.) (pp. n .)

547 547 2250 0.021251 0.021251 0.0 9,075.0 0.0 2,831E 530,140.1 933.9 547 540 2250 0.021251 0.02106 4,7362 568.6 184.5 3,0163 535,060 3 985.6 540 530 2250 0.02106 0.02079 6,5453 785.9 255.0 3,2713 541,8613 1,055.5 530 500 2250 0.02079 ('.02009 18,120.5 2,175.6 706.0 3,9773 560,687E 1,2402 500 470 2250 0.02009 0.01951 16,141.2 1,938.0 628.9 4,6062 577,457E 1,394.6 470 440 2250 0.01951 0.01900 14,883.0 1,786.9 579.9 5,186.0 592,920.7 1,529 2 440 410 2250 0.01900 0.01855 13,811.9 1,6583 538.1 5,724 2 607,270.7 1,M8.0 410 390 2250 0.01855 0.01828 8,613.6 1,034 2 335.6 6,059E 616,219.9 1,7193 390 360 2250 0.01828 0.01792 11,888.7 1,427.4 463.2 6323.0 628,571.8 1,8143 wo 150 2250 0.01792 0.01781 3,7283 447.7 145 3 6,6682 632,445.6 1,843.4 W MO 350 0.01781 0.01797 (5,575.7; (669.4; (2172; 6,451.0 626,652.7 1,799.8 60 350 350 0.02698 0.01912 7,618.4 914.7 2%.8 6,747E 634,567.9 1,859.1 UU 350 350 0.01797 0.01797 0.0 0.0 0.0 6,747E 634,567.9 1,859.1 ADD IN RIIRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 7,764.6 730,186.8 1,859.1 350 300 350 0.01797 0.01743 21,571.2 2,589.9 840.4 8,605.0 752,5983 1,999.0 250 350 0.01743 0.01699 18,590.4 2,232.0 724 3 9,3293 771,9132 2,113 0 300 350 0.01699 0.01691 3,484.0 4183 135.7 9,465.1 775,532.9 2,133E 250 240 0.01691 0.01676 6,6222 795.1 258.0 9,723.1 782,413.1 2,172.7 240 220 350 0.01676 0.01662 6,2883 755.0 245.0 9,968.1 788,946.6 2,209.0 220 200 350 0.01662 0.01649 5,935.0 712.6 231.2 10,1993 795,112E 2,242.7 200 180 350 0.01M9 0.01638 5,0953 611.8 198.5 10,397.9 800,406E 2,2712 180 160 350 0.01638 0.01633 2,5733 309.0 100.3 10,498.1 803,080.6 2,285 3 160 150 350 0.01633 0.01628 2,1183 254.4 82.5 10,580.7 805,281.7 2,2972 150 140 350 0.01628 0.01626 1,182.0 141.9 46.1 10,626.7 806,509.7 2,301.6 140 135 350 FEED-AND-BLEED BAT VOL(0 ppm to 1103.7 ppm) = 9,075.0 GALLONS (121 minutes at 75 gpm)

TOTAL BAT VOLUME = 29,%2.6 GALLONS Page 118 of 133 X6ECUhTBUSTION ENGINEERING NUCLEAR SERVICES SSLC3RLl-

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV.00 TABLE 3-10 SALEM NUCLEAR GENERATING STATION - REFUELING COOLDOWN FROM 547F TO 135'F FEED-AND-BIFFn AND MAKEUP FROM BAT w/4.0 wt% BORIC ACID @ 7&F AVG.SYS. TEM P. PZR SPECIFIC VOLUME SHRINKAGE BAT VOL B/A TOTAL TOTALSYSr. F1NAL PRESS. MASS @ 70*F ADDED BORIC ACID MASS CONC.

T:CF) Toff) (paia) Vi(ftMba) Vf(ftMba) Obs) (ganome) Oba) Oba) Obe) (ppm uaron) 547 547 2250 0.021251 0.021251 0.0 8,025.0 0.0 2,523.0 529,8313 832.6 547 540 2250 0.021251 0.02106 4,7362 568.6 254.1 2,777.1 534,821 4 907.8 540 530 2250 0.02106 0.02079 6,545 3 785.9 272.7 3,049 3 541,639E 984.4 530 500 2250 0.02079 0.02009 18,120.5 2,175.6 730.5 3,7803 560,490.7 1,1792 500 470 2250 0.02009 0.01951 16,141.2 1,938.0 672 6 4,452.9 577,3(M3 1,348.5

-470 440 2250 0.01951 0.01900 14,883.0 1,786.9 620.1 5,073.0 592,807.6 1,4%2 440 410 2250 0.01900 0.01855 13,811.9 1,6583 575.5 5,648.5 607,195.0 1,626.4 410 390 2250 0.01855 0.01828 8,613 6 1,0342 358.9 6,007.4 616,1673 1,7(4 6 390 360 2250 0.01828 0.01792 11,888.7 1,427.4 4914 6,502.7 623,551 6 1,808 3 Tt.o . 3;0 2250 0.01792 0.01781 3,728.5 447.7 155.4 6,658.1 632,435.5 1,840.6 o tso 350 0.01781 0.01797 (5,575.7) (669.4) 0.0 6,658.1 626,859.8 1,857.0 u l' SAT 350 0.02698 0.01912 7,618.4 914.7 0.0 6,658.1 634,4782 1,834.7 no 350 350 0.01797 0.01797 0.0 0.0 0.0 6,658.1 634,4782 1,834.7 ADD IN RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 7,661.4 730,083.6 1,834.7 350 300 350 0.01797 0.01743 21,571.2 2,589.9 869.6 8,530.9 752,524.4 1,982 0 300 250 350 0.01743 0.01699 18,590.4 2,232.0 749.4 9,280.4 77I,8M2 2,102.I 250 240 350 0.01699 0.01691 3,484.0 4183 140.4 9,420E 775,488 6 2,123.9 240 220 350 0.01691 0.01676 6,622.2 795.1 267.0 9,6873 782,377E 2,164.9 200 350 0.01676 0.01662 6,288.5 755.0 253.5 9,9413 788,9193 2,203 1 220 200 180 350 0.01662 0.01649 5,935.0 712.6 2393 10,180 5 795,094.0 2,238 6 180 IM) 350 0.01649 0.01638 5,0953 611.8 205.4 10,385.9 800,394.9 2,268 6 150 350 0.01638 0.01633 2,573.5 309.0 103.7 10,489.7 803,072.I 2,283.7 160 350 0.01633 0.01628 2,1183 254.4 85.4 10,575.1 805,276.1 2.296 0 150 140 135 350 0.01628 0.01626 1,182.0 14L9 47.6 10,622.7 806.505 7 2,302E 140 FEED- AND-BLEED BAT VOL (0 ppm to 832,6 ppm) = 8,025.0 GALLONS (107 minutes at 75 gpm)

TOTAL BAT VOLUME

= 28,912 6 GALLONS

~

.j Page I19 of 133

[ABB COMBUST ~10N E UI 55Ih~SG NOUEL[AR SERVICES ssEc3nt F

- _ - - - - - _ - . _ . . _ _ = _ _ . _ . _ - --- .. . . _ . . , _-

l 1

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 l TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 l i

Table 3-11 l l

Key Plant Parameters and Conditions Assumed in the Shutdown-to-Cold-Shutdown Evaluation 3

RCS Volume 10,812 ft Initial RCS Average Temperature 547*F 3

Pressurizer Volume 500.0 ft Pressurizar Condition Saturation RCS Leakage Zero BAT Temperature 70*F Domineralized Water Temp. 70*F Mixing Between RCS Complete and and Pressurizar Instantaneous Pressurizer Level Constant During Cooldown Initial RCS Boron 0 ppm Boron Concentration BAT Concentration 3.75 & 4.0 wt% Boric Acid RWST Concentration 2300 ppa Boron 3

RERS Volume 1700 ft Boron Concentration in RHRS Equal to Concentration in RCS at time of RHRS Initiation (Cases I and II) e ABB Combustion Engineering Nuclear Services Page 120 of 133

BOR!C ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV.00

, . TABLE 3-12 SALEM NUCLEAR GENERATING STATION - PLANTCOOLDOWN FROM 547'FTO 20&F WITH BLENDED MAKEUP BAT @ 3.75 wt% BORIC ACID AVG.SYS. TEMP. PZR. SPECIFIC VOLUME SilRINKAGE BLEND BAT VOL PRIMARY 1I20 B/A TOTAL TOTAL FINAL PR ESS. MASS RATIO @ 70*F @ 70*F ADDED BORIC ACID SYS. MASS CONC.

Ti (*F) Tf (*F) (psis) Vi(ft3Abm) Vf (ft3Abm) (Ibm) (gallons) (gallons) (ibm) (Ibm) (ibm) (ppm boron) 547 547 2250 0.021251 0.021251 00 0.0 0.0 0.0 0.0 00 527,3083 00 547 540 2250 0.021251 0.02106 4,7362 0.0 568.6 00 184.5 184.5 532,229.0 60.6 540 $30 2250 0.02106 0.02W9 6.5415 0.0 785.9 0.0 255 0 439.5 539,029.5 142.6 530 500 2250 0.02079 0.02009 18,120.5 0.0 2,1716 0.0 706.0 1,1415 557,856 0 359.0 500 470 2250 0.02009 0.01951 16.1412 0.0 1,93&O 0.0 628.9 I,7744 574,626.1 539.9 470 440 2250 0.01951 0.01900 14,883.0 1.0 893.4 893.4 289.9 2,0643 589,799 0 6 11.9 440 410 2250 0.01900 0.01855 13,811.9 1.0 829.1 829.1 269.1 2,3314 603,879.9 675 6 410 390 2250 0.01855 0.01828 8,6116 1.0 517.1 517.I 167.8 2,501.2 612,661.4 713 8 390 370 2250 0.0I828 0.01804 7,8711 1.0 472.6 472.6 153.4 2,654 6 620,6873 747.7 UU 350 2250 0.01804 0 0178I 7,744.2 1.0 4 64.9 00 150.9 2,8014 628,5828 780.3 350 350 350 0.01781 0.01797 (5,575.7; 1.0 0.0 0.0 00 2,8014 623,007.1 787.3 350 350 350 0.02698 0.01912 7,61&4 1.0 4 57.3 00 0.0 2,8014 630,6253 777.8 ADD IN RilRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 00 1.0 0.0 0.0 0.0 3,22& 2 725.650 4 777 8 350 320 350 0.01797 0.01763 13,427.8 1.0 806.1 806.1 261.6 3,489 8 739,3393 825 2 320 290 350 0.01763 0.01734 11,8693 1.0 712.5 712.5 231.2 3,721.0 751,4402 865.7 290 260 350 0.01734 0.01'107 11,4132 1.5 548.1 822.2 17L9 3,89&8 763,0313 893.3 260 240 350 0.01707 0.01691 6,9314 2.0 277.6 555.1 90.1 3,98&9 770,056.7 905 6 240 220 350 0.01691 0 01676 6,6212 2.0 265.0 $30.0 86.0 4,074.9 776,764.9 917.2 220 200 350 0.01676 0.01662 6.28& 5 2.0 251.7 503.3 .

81.7 4,1566 783,1351 928 0 TOTAL BAT VOLUME = 11,963.6 GALLONS TOTAL PRIMARY WATER VOLUME = 6,641.6 GALLONS ABB COMBUSTION ENGINEERING NUCLEAR SERVICES Page 121 of 133 sto c m2

l CEN-60G REV. 00 ,

BORIC ACID CONCENTRATION REDUCTION EFFORT -

TECHNICAL BASES AND OPERATIONAL ANALYSES D MAKEUP L NTCOOLDOWN FROM TOTAL 547'FTO TOTAL20(TF WITil B I FINAL TABLE 3-13 B/A CONC.

SALEM NUCLEAR GENERATING STATION PRIMARY-1120 P A i

I SYS MASS BAT VOL ADDED BORIC ACID { ppm boron) _

BLEND @ 70*F (Ibm)

BAT _@PZR. I 4.00_wt% BORIC ACIDSPECIFICVOLUME I

MASS RATIO @ 70*F 'SilRINKAGE (gallons) _

(Ibm) _ (Ibm) 0.0 527.308 3 0.0 64.8 AVG.SYS. TEMP. __(gallonsL 0.0 0.0 532,2413 VI(ft3Abm)IVf(ft3yA_ (Ibm)0.0 _

PRESS. 0.0 197.3 0.0 197.3 152.5 (pais) 00 470.1 539,060.0 Ti ('F) 0.021251 0.0 568.6 272.7 383.9 Ti {F) 5 47 2250 0.021251 4,734.2 785.9 0.0 1,2211 557,935.5 547 0.021251 0.02106 0.0 755.0 574,7493 577.2 2250 6,5415 0.0 540 0.02M9 2,1716 1,897.6 6543 547 0.02106 0.0 00 672.5 589,942.4 2250 18,120.5 2,207.7 530 0.02009 1,93a0 3 10.1 7 22.3 540 0.02079 0.0 893.4 604,0420 500 2250 16,141.2 893.4 2,4914 530 0.01951 1.0 287.7 763.1 2250 0.02(D9 I4,883 0 829.1 612.835 0 470 0.01900 829.1 2.674.9 8 17.6 500 0.01951 1.0 179.4 2250 13,811.9 517.1 2,9226 624.971.4 440 0.01855 517.I 247.7 8 34.2 470 0 01900 1.0 713.7 628,777.6 410 2250 8,6116 3,0002 440 0.01828 713.7 77.7 841.71 0.01855 1.0 0,0 623,201.9 2250 11,888.7 3,0002 390 0 01792 223 8 00 8 31.5 410 j 0.01828 1.0 0.0 630,8203J 2250 3,72&5 0.0 3.000.2 360 0.01781 l .0 0.0 ;

190 l 2 250 0.01792 (5,575.7' 0.0 j J 350 0 01797 457.3 j 725,874 5f 831.5 tw 0 01781 1.0 j I 350 7,61&4 l 3,4523 854 6 350 0 01912; 00' 350j 0.02tW8 0.0 f 739,464.7 W2) 350 j j RON CONC. = RCS BORON 2.0 CONC.) 00 I 1623 3,614.7 751,477 4 874 4

.150 ) I 00 i 1,074 8 3,75&2 ADD IN HllRS350f VOLUME 0.01797 (ASSUME BO

! 0 Ol???

13,4273 2.0 537 4 950 0 143.5 3,89&2 763,028.6 892.7 350 0 01763 475.0 1 38.0 903 6 0.01797 2.0 770,047 3 350f 320 350 0.01734 11,8693 456 8 913.5 818 3,98a0 913.9 350' 0.01763 2.0 555.1 776.750 1 350 11,413.2 4,060.1 923 4 f 320 290 3 50 0.01734 0.01707 6,9314 2.0 277.6 530.0 80.1 4,1% 1 ' 780.114 6 i 260 0 01691 265.0 76.0 29G 0 01707 2.0 5033 t

350 6,6212 251.7 240 0.01676 2.0 l i 260 0 01691 6,28& 5 350 l 220 0.01662 1 1 240 0.01676 200 i 350 L 220 I

= 11,366.0 GALLONS 7,480.2 GALLONS Page 122 of 133 TOTAL BAT VOLUME .

SEC3CM)2 TOTAL PRIMARY WATER VOLUME =

ING NUCLEAR SERVICES j i ABBCOMBUSTION ENGINEER

l BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 l

FIGUAE 3-1 .

SALEM NUCLEAR GENERATlNG STATION -

UNITS 1 &.2 FEED.& BLEED @ 75 GPM FROM HOT ZERO POWER

,f INITIAL CONCENTRATION = 0 ppm BORON 1,500 --

(ref. TABLE 3-2)

. ~ /-

. Y%/

, . -[

../

z ~

o . , p/

u -

O . .~ ./

E

..Y O.

a-f.9' 1,000 7

.9 -

.. /

z c' ,

O H ., . .,/ i 4

1 -

H . -l z - ./

w . g' s O .'

z . -l O . -l O 500 -- ' -

(D ,.> -

o t C

t 4

OL I I

'i O 50 100 150 200 250 ;

t TIME MINUTES 1 BAT 0 3,75 wt% BAT 9 3 875 wi% BAT @ 4.0 wt%

, c ..:<.... ...

ABB Combustion Engineering Nuclear Services Page 123 of 133 - !

i

+

.)

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 .

i F IGURE 3-2 SALEM NUCLEAR GENEAATING STATION - UNITS 1 & 2 FEED & BLEED 0 150 GPM FROM HOT 'ZERO POWER 3,500

~

INITIAL CONCENTRATION = 0 ppm BORON Cref. TABLE 3-3) 3,000 --

e, Z ~

C3 ,'

a- :s:

o *. is',*

to 2,500 --

. . ,/ ' ~

E O.

k' a -

a : t ,#

.Y 2,000 --

p - +

~

O -

~

t >'

~

F--

t Cr .,

y 1,500 --

vp' -

tu ..,

O .,

Z -

O U .>'

g 1,000 --

.?' -

O .

CI '

500 -~ -

' ' ' I OL O 50 100 150 200 250 .

TIME -

MINUTES BAT @.3.75 wt% BAT @ 3.875 wt% BAT 9 4.0 wt%

, c . ..y . . ,: . .

ABB Combustion Engineering Nuclear Services Page-124 of 133

i BORIC ACID CONCENTRATION REDUCTION EFFORT CEM-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 '

F IGURE 3-3 SALEM NUCLEAR GENERATING STATION - UNITS 1 & 2 i

FEED- AND-BLEED 0 75 GPM FROM HOT ZERO POWER 2, ADO --

,f:

1 N o T I AL CONCENT AAT ION = 1000 ppm EDAON ,

- (ref . TABLE 3-4) .,-

.../

Z 2,200 -- -M O a 1 >*.s' o

a2

.y

.: s' k 2,000 -- -

.-[ -

a .. ,

.^s' i -

.cr' z 1,800 --

-!.9' 9 .7

& . r' 4 -

.. a' g ,

l-- .

Z 1,600 *'

w . :< c U 'w" Z _

O .<

U . , Y' ?

v3 1,A00 -- - ~ - -

o .)

C ,f

- . . ,3 1,200 --

l t 1 i t 1,000 L O 50 100 '150 200 250 TIME -

MINUTES ;

BAT 0 3.75 wt% BAT @ 3.875 wt% BAT 9 4.0 wt%

+

o 1 ...

1 f

ABB Combustion Engineering Nuclear Services Page 125_of 133- .

i BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECENICAL BASE 8 AND OPERATIONAL ANALYSIS REY. 00 ,

i FIGURE 3-4 l SALEM NUCLEAR GENERATIFG STATION - UNITS 1 & 2 .l FEED-&-BLEED @ 150 GPM FROM HOT ZERO POWER +

4,000

~

1NITIAL CONCENTAATION = 1000 oom BOAON Cref. TABLE 3-5) ,

<:s i

3,500 -- *

, ,, N-Z .' s' O .. y' ,* h E

<*):JX,, '

~

Q .

Gl,',

E G

3,000 --

. ':S ,

Q ,'$'/.

i 7

s'/

l l'4 /

,4e' Z /

o 2,500 -- - - '-

p .,

4 /,'

1 -

jh' b ,,

Z ,.,'

tu p 2,000 --

,E".. , > >

I O

O .

s,,/'

tn -

u .y C "

4

~

1,500 - -

?

~'

I I I I 1,000 L 50 150 200 250-O 100 '

TIME -

MINUTES !

BAT 0 3.75 wt% BAT @ 3.875 wt% BAT 9 4.0 wt%

, c ....4. . . .q. . . ,

e i

k ABB Combustion Engineering Nuclear Services- Page 126 of 133 Li e . .

b

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 -

TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 F iGURE 3-5 SALEM NUCLEAR GENEAATING STATION - UNITS 1 AND 2 OLENDED MAKEUP OPERATIONS w/ 75 GPM OUT OF TEE ,

4,000 i '

. -/)

. /)' >

.//

5 Y[

a o/

O 3,000 -- - .<?,/ -

D </

g

./

a ."/

a ti*a" l"

s ?/

5'

& W?

n 2,000 --

~'

u <<

O -//

O ~

o h

2 I#

?

F- r 8 1,000 -- - - -

Z uJ U

Z =

O -

O Cref. TABLE 3-6)

I I I 0k. ,

O 10 20 30- AO' FLOW FROM 1C 23- CV- 172 -

GPM

g. BAT 0 3.75 at% BAT 0 3.a75 wt% BAT 0 4.0 wt%

_.p e . . . <.:. . .

I ABB Combustion Engineering Nuclear Services Page 127. of 133 !

.__ _ . . _ _ . . _ . - ._ _ _ m.

-e i

~ BORIC ACID CONCENTRATION REDUCTION-EFFORT 'CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS- REY.'00 F IGUAE 3-6 SALEM NUCLEAR GENERAT ING STATION - UNITS 1 AND 2 !

dLENDED MAKEUP OPERAT IONS w/ 150 GPM OUT OF TEE ,

2,000 ,

f%

y.: ;

.-! X ;

- ;l ,f, ' >

Z ./, t O .-l / ;

C .%

8 .

/7,'

1,500 -- - +

/ /.

E . . . , .

a. .t

/,r 7 a.

fa'

.'s' I -

. e..'?,/

,1,4 W /s' w . -s e W

1,000 -

.'/,' - 4 LL ./ -i O .',' ,

. .y s W . !

D /, .

O , ,f/ 1 Z- I'Y O .

H u

4 -

a 500 - - - --

i H

Z +

W O r Z ?

O -

U (ref. TABLE 3- 7) i I ' !

0L

0. .10 20- 30- 40- ,

FLOW-FROM 1(23-CV 172 GPM i BAT 0,3.75 wt% GAT 0 3,875 wt% BAT 0 4 0 wt%- j c ..

3...

ABB Combustion Engineering Nuclear Services Page 128 of 133.

i

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 1

F I GURE 3- 7 SALEM NUCLEAR GENERATING STATION -

UNITS 1 &2 AEFUELING COOLDOWN FROM 547*F TO 135*F 2,500 Z

@ 2,000 --

o '

CD $.

E ,

O.

' 1,500 --

Z O

F-i

<C C

F-h 1,000 --

i N INIT I AL FEED-&-BLEED:

O 121 MINUTES 0 75 GPM FROM ,

BAT 0 3,75 wt% BOAIC ACID !

C (ref. TABLE 3-9) 500 -- - -

E I I I '

O O l 600 500 400 300 200- 1C' l RCS AVERAG: TEMPERATURE -

'F !

l I ABB Combustion Engineering Nuclear Services ' Page 129 of 133

. .- . .. . .. .- - . - . . . ~ . _.

4 BORIC ACID CONCENTRATION REDUCTION EFFORT. CEN-606 '

TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 F iGURE 3- 8 SALEM NUCLEAR GENERATING STATION -

UNITS 1 & 2- !

AEFUELING COOLDOWN FROM 547'F TO 135'F 2,500 Z

O C 2,000 -- - - -

0 1 CD t

E -

O. .

Q.

1,500 -- - - -

Z O

<C :

T 1,000 -- - ' - -

H Z '

LU ( INITIAL FEED-6-BLEED:

U -

107 MINUTES 0 75 GPM Z pa BAT 9 4.0 wt% 00AIC ACIO Cref . TABLE 3- 10)

' (f) 500 -- - - - "

O E

i l l ,

l !

I I I I I 0 ;;

600 500 400- 300 200 100~

' - RCS~ AVERAGE TEMPERATURE -

F

- ABB Combustion Engineeri ng Nuclear Services Page 130 Of 133

- - . - - - ._ -. . - . ~_

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 FIGUAE 3-9 SALEM NUCLEAR GENEAAT IPG STAT ION - UNITS 1 & 2 SHUTDOWN TO COLO SHUTDOWN - 547.*F TO 200*F 1,000

?

b 800 -- a.",-

C O '

CD E -

Q-r

' 600 -- - - -

r Z

O _

H -

<C C ,

H Z

W 400 -- - -

U

Z ,

O U

~

tn o >

" I 200 -- - .

BLENDED MAKEUP w/ BAT 9 3. 75 wt* DOAI C AC I D -

~

(rer TABLE 3-12)

' ' ' 1 0 v 600 500 400 300 200 100 ACS AVERAGE COOLANT TEMPERATURE -- F e i F

ABB Combustion Engineering Nuclear Services Page 131 of 133 ;

EORIC ACID CONCENTRATION REDUCTION EFFORT CEN-605 TECNNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 F I GURE 3- 10 SALEM NUCLEAR GENERATING STATION - UNITS 1 & 2 SHUTDOWN TO COLD SHUTOOWN - S47'F TO 200'F 1,000 z 800 -- -

O E

8 ~

E G

G

, 600 -- - - - ,

z O

C F-l @ 400 -- -

i U i z 1

8 .

(A O

C 200 -- -

FEED-&-BLEED BAT 0 4.0 wt% BOAIC ACID (ref. TABLE 3-13)

L

' ' ' I f- 0 y 600 '500 400- 300 ,200 100 RC5' AVERAGE TEMPERATUAE -

F i i

ABB Combustion Engineering Nuclear Services Page 132 of 133

DORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00

4.0 REFERENCES

4.1 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" 4.2 Technical Data Sheet IC-11, US Borax & Chemical Corpo-ration, 3-83-J.W.

4.3 Phase II Report, " System Modificatien Study for Salem Nuclear Generating Plants", March 1993 4.4 Letter, Mr. Glenn Schwartz, PSE&G, to Ms. Donna Hayes, ABB Combustion Engineering Nuclear Services, May 12, 1993 4.5 ABB Nuclear Fuels QA Verified Boron Requirements for l

Salem, ,GM-FE-0092, Rev. 01, K. J. Loeffler, ABB Nuclear Fuels, to D. Hayes, ABB Combustion Engineering Nuclear Services, May 5, 1993 4.6 Residual Heat Removal System Volume Calculation, Calculation No. MISC-MECH-CALC-100, Rev. 00, April 30, 1993 l

4.7 BACR Computer Code, Version 2, Calculation OOOOO-MPS-2 CALC-013, Rev. 01 4.8 " Flow of Fluids", Technical Paper No. 410, Crane Co., 1988 ABB Combustion Engineering Nuclear Services Page 133 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 Appendix 1 Derivation of the Reactor Coolant System Feed-and-Bleed Equation Purnose 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:

Eign = mass flowrate into the RCS m ,a = mass flowrate out of the RCS m3 = boron mass flowrate ny = water mass flowrate ng = boron mass n( = water mass C in = boron concentration going into RCS C ,a = boron concentration going out of RCS Co = initial boron concentration C(t) = boron concentration as a function of time Cacs = RCS boron concentration Sinnlifyina Assumntions During a feed-and-bleed operation, the RCS can be pictured as a closed container having a certain volume, a certain mass, and

, an initial boron concentration. Coolant is added at one end via the charging pumps. The rate of addition is dependent on i , ABB Combustion Engineering Nuclear Services Page Al-1 of Al-6 I

~ . - .. .- .

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 the number of charging pumps that are running with the 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 c'oncentration determined by fluid mixing within the RCS. The mass flowrate into system is given by the following equation:

6, = (63 + h,)

For typical boron concentrations within the chemical and volume control system, ny is very much greater than ug. (For example, a 3.5 weight percent boric acid solution contains only 0.04 lb, of boric acid per lb, of water) . Therefore the above equation can be simplified to the following:

6,= (6 ,) 3 (1.0)

In a similar manner, the mass flowrate coming out of the system, given by bout " $bb*b v out can be simplified by again realizing that n( is very much greater than m3 or 6,,, = (6 ,) ,ue (2.0)

For a feed-and-bleed operation with a constant pressurizer ,

level and system temperature, the mass flowrate into the RCS will be equal to the mass flowrate out of the RCS, or ABB Combustion Engineering Nuclear Services Page Al-2 of Al-6

l BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 i

i Since g >> mb , then s

C"" = (m,) ga where (g)acs is a constant for a constant system temperature. l The rate of change of the RCS concentration is therefore d "b **

g C,a = (6.0) w) RW Substituting Equation 5.0 into Equation 6.0 yields the-following:

_d -

C'" =

" 1" '" ~ ' " '

dc ( m ,) ,a j

and from Equation 4.0

~

I " '" '" ""

(7

0) dt - C** =

(m),a

+

ABB Combustion Engineering Nuclear Services Page Al-4.of'Al-6

I BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 [

TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00

Solving Equation 7.0 for concentration yields: j t

'*' = " '"

dc :

d ( Cj, - C,c,) (m,) ,c, i

or c(c) d ' = ' '"

e dc :

c o, C,-Cacs 3

(m,) acs [a I

l

}

Integrating from some initial concentration C,to some final -

concentration C(t) and multiplying through by a minus one gives {

the following:

i

.?

C(0) ( ) '"

1n (C,c,- Cin) =- c C(c) w Rc8

'C(c) - C ,' f =-

(th,) f, In C Co -C in (m,)acs j

k ABB Combustion Engineering Nuclear Services Page Al-5 of Al-6 y

i BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 Continuing to solve for C(t) , this equation becomes:

C(c) -C fn = e #d h / ("d

i Co -C,g or C(t) =CJn + (C o-Cfn) e (#d '* *# I*d " (8.0)

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

(m,) ,a T=

(bw in then rquation 8.0 becomes C( c) = Ca (e-8/') + C , (1-e-*/')

j (9. 0)

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BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REY. 00 ,

Appendix 2 Methodology for Calculating Dissolved Boric Acid t per Gallon of Water Purpose 3

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. A solution temperatures of 70*F was used for both the RWST and the BAT.

Methodoloav and Results ;

Boric acid concentration expressed in terms of weight percent >

is defined as follows:

g, mass of boric acid total solution mass ,399 or mass of boric acid C= x 100 (1.0)

(mass of boric acid) + (mass of wa ter)

ABB Combustion Engineering Nuclear Services Page A2-1 of A2-3

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BORIC ACID CONCENTRATION REDUCTION-EFFORT ~ CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Defining the mass.of boric acid as ma and the mass of water as m,, and substituting into equation (1.0) gives the following:

~

C= ** x 100 s mu + m, -

or '

(C) x (m.)

mu= 100 -C I

From Appendix A of Reference 4.8, the density of water at '70 F i s 8 . 3 2 9 0 l b ,/ g a l l o n . Using this' figure and Equation 2.0, the-mass of boric acid per gallon of solution is calculated as shown in the following table: :

ABB Combustion Engineering Nuclear Services - Page A2-2 of'A2-3

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Appendix 3 Methodology for Calculating the Conversion Factor Between Weight Percent Boric Acid and ppm Boron Purpose The purpose of this appendix is to show the methodology used to derive the conversion factor between concentration in terms of weight percent boric acid and concentration in terms of parte per million (ppm) of naturally occurring boron.

Results For any species (solute) dissolved in a solvent, a solution having a concentration of exactly 1 ppm can be obtained by dissolving i lb, of solute in 999,999 lb, of solvent. An aqueous solution having a concentration of 1 ppm boric acid, therefore, is obtained by dissolving i lb, of boric acid in 999,999 lb, of water, or 1 lb, boric acid 1 lb, boric acid 1 lb, boric acid + 999,999 lb, water " 10' lb, solucion ABB Combustion Engineering Nuclear Services Page A3-1 of-A3-2

i BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES VD OPERATIONAL ANALYSIS REV. 00 For any species (solute) dissolved in some solvent, a solution having a concentration of 1 weight percent (w/%)

can be obtained by dissolving 1 lb, of solute in 99 lb, of solvent. An aqueous solution having a concentration of 1 weight percent boric acid, therefore, can be obtained by dissolving i lb, of boric acid in 99 lb, of water, or 1 wtt , 1 lb, boric acid ,

1 lb, boric acid 100 1 lb, boric acid + 99 lb, water 100 lb, solucion Dividing these last two equations yields a ratio of 10', or 1 weight percent boric acid = 10,000 ppm boric acid (1.0)

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 H 3 B0 3 ) to the atomic weight of naturally occurring boron.

From the Handbook of Chemistry and Physics, CRC Press, O1 1 weight percent boric acid = (10,000) ppm boron g

where (10.81/61.83) is the ratio of the mass of boron in the boric acid to the total molecular mass of boric acid.

or i

e 1 weight percent boric acid = 1748.34 ppm boron ABB Cornbustion Engineering Nuclear Services Page A3-2 of A3-2

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Appendix 4 Bounding Core Reactivity Considerations '

The methodology used to compute core reactivity and the required changes in boron concentration resulting therefrom are described in this appendix. This methodology was used -

to conservatively bound the reactivity effects of the cooldown described in Section 2.2.1.1 of this report. The cooldown scenario is summarized in the following paragraphs, along with a discussion of the methods used to compute the changes in boron concentration made necessary by the cooldown.

Cooldown Scenario and Assumotions The following scenario was evaluated to establish the bounding boron concentrations which have been used.in this report.

1. Shutdown Margin Requirements:

200*F < T,, < 547'F 1600 pcm T,,S 200*F 1000 pcm

2. Reactor is initially at Hot Full Power (HFP),

equilibrium xenon and samarium conditions, resulting'in a boron concentration of 0 ppm. In addition, the control rods are at the~ Technical Specification

, Insertion Limits. This combination of conditions maximizes the change in boron concentration required to ABB Combustion Engineering Nuclear Services Page A4-1 of A4-9

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 maintain Shutdown Margin (SDM) and to compensate for a reactor trip and subsequent cooldown to cold, xenon free conditions.

3. The most reactive control rod is assumed to be stuck in the fully withdrawn position and is therefore not available for shutdown reactivity control.

4. At t=0, the reactor is tripped and held at Hot Zero Power (HZP) conditions (547'F) for 22.0 hours0 days 0 hours 0 weeks 0 months .

5. At t=22.0 hours0 days 0 hours 0 weeks 0 months , a plant cooldown from 572*F to 135'F is initiated, at an average rate of 10*F/hr. (At temperatures at and below 200*F, it is assumed all xenon has decayed and that the core is xenon free).

The use of assumptions 4 and 5 ensures that the maximum rate of xenon decay is accounted for in the bounding boron calculations. The peak xenon concentration is reached approximately seven (7) hours after reactor shutdown. After the xenon peak is reached the xenon in the core begins to decay, adding reactivity to the system. This reduces the negative reactivity which had been added by the initial increase in xenon, and the xenon returns to the steady-state operating value approximately 22.0 hours0 days 0 hours 0 weeks 0 months after shutdown.

6. At times beyond 22.0 hours0 days 0 hours 0 weeks 0 months , the reactor must be borated to compensate for the continuing decay of xenon. Thus, the bounding boron concentration which are calculated

. must offset the the positive reactivity contribution from both the cooldown and the xenon decay.

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^l BoaZC ACID CONCENTRATION REDUCTION EFFORT CEN-sos i TacnNIchL R&sts AND' OPERATIONAL ANALYSIS ggy. OO

-l

7. The samarium concentration is assumed to remain constant for the entire scenario. This is a conservative assumption which increases the calculated boron requirements, since the negative reactivity worth of the samarium increases with time after shutdown.

-. . e

8. The boron concentrations were normalized to an End-of-Life (BOL), HFP NTC of -44.0 pcm/'F. This was-done to bound current Technical specification limits and is- ;

considered conservative for current cycle' lengths and feed enrichments.

9. It has been noted that under certain conditions and for a limited time, the boration transient from peak xenon conditions is more limiting.than the equilibrium xenon '

case described here. In the unlikely event that the plant were to be held at hot, zero power conditions for several hours until the xenon transient reached its peak, additional boric acid would-be required. This is not considered to be a realistic situation, but this scenario has been analyzed. The results of the analysis are presented in section 2.4.4 of the report.

P

- . . ~ %

l l

.i

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l BORIC ACID CONCENTRATION REDUCTION RFFORT CEN-606 TECHNICAL bases AND OPERATIONAL ANALYSIS REY. 00 1

The limiting boron concentration curves were calculated for Salen Unit 2, Cycle 6. Unit 2, Cycle 6 is the most limiting case and bounds the reload design boron requirements; hence, with additional conservatism, the results may be considered bounding for near-term future reloads. The results are also conservative for Salem Unit 1, Cycle 11. The limiting boron' curvas used in this report were determined from the most rastrictive normalized cycle calculations (Unit 2, Cycle 6),

with additional conservatism. These curves are shown in Figures A5-1 and A5-2.

Descrintion of Methodoloav The bounding changes in boron concentration which are required to maintain SDM during the conservative post-trip cooldown were calculated using the ste.ndard Westinghouse shutdown margin procedure. A brief description of this procedure follows.

For a given fuel cycle, a table of required boron concentration versus temperature and average burnup is utilized to maintain SDM during shutdown and cooldown. The values of boron concentration in the table are calculated using the following assumptions:

1. No xenon or samarium pl auant -hrcolu,-

2. Most reactive control rod stuck out of core,

3. The maximum Technical Specification SDM of 1600 pcm is present, and

4. A margin of safety is included in the maximum boron '2ncentrations as an allowance for ca?- ~ 2tional uncertainty.

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)

BORIC ACID CONCENTRATION REDUCTIDW EFFORT cEN-606 TBCENICAL BASES AND OPERATIONAL ANALYSIS REV. 00 l

l Implicitly included in the table are the changes in total temperature defect and rod worth associated with changes in j temperature and burnup.

Corrections are made to the values in this table to account

~~

for the presence of xenon and samarium and for the change in required SDM which occurs at toeparatures at and below 200*F, and to normalize the data to the most negative moderator temperature coefficient (MTC) of -44.0 pcm/ *F.

The xenon worth correction is determined from a table of total xenon worth as a function of equilibrium power level and time following plant trip for BOL conditions and is calculated with no boron.

The samarium worth correction is determined from a table of total samarium worth as a function of power level before trip and time following plant trip, and is also calculated with no boron. Because the negative reactivity worth of samarium increases following a plant trip, the value of samarium worth at the time of trip was used in all calculations as an additional conservatism.

A reactivity correction versus temperature is made to normalize the actual most negative EOL MTC to the proposed most negative Technical Specifi.dtics. MTC value of

-44.0 pcm/*F. This was done conservatively by linearly applying the difference between the predicted actual most-negative MTC and -44.0 pcm/ar times the cooldown temperature.

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BORIC ACID CONCENTRATION REDUCTION RFFORT cgN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Integral boron worths are used to translate the previously discussed reactivity corrections into changes in boron concentration. These integral boron worths are obtained from a table of integral boron worth vs. boron concentration for temperatures ranging from 68'F to 547*F calculated at roL' conditions. The integral worth is used to determine a correction factor for xenon and samarium worth at the maximum boron concentration and to determine the final boron concentration after accounting for the xenon and samarium, any change in SDM requirement, and the maximum Technical Specification BOL NTC normalization.

The final minimum boron concentration as a function of temperature is determined as follows:

a. The maximum boron concentration is determined from the table of maximum boron concentration.

b. The reactivity contributions of baron-free xenon and namarium, the SDM requirements, and the most negative MTc normalization are determined. ,

c. The integral boron worth for the max' am boron is read from the table at the shutdown tempersture,

d. A correction factor is determined from this worth and is applied to the xenon and samarium worth to account for the reduction in xenon and samarium worth due to the presence of boron. '

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l DORIC ACID CONCENTRATION REDUCTION EFFORT CEN-SOS TECINICAL BASES AND OPERATIONAL ANALYSIS REV. 00 l

e. The corrected xenon and samarium worth, the SDM requirement correction, and the most negative MTC normalization reactivity are subtracted from the integral boron worth to obtain the net reactivity required to supply minimum SDM.

f. With this value, the resulting boron concentration required to provide SDN is read from the integral boron Worth table.

Verification of Future Reloads The methodology discussed above will be applied to future reload cores to ensure that the required boron concentrations calculated for the reload are bounded by the limiting curves (Figures A4-1 and A4-2) given in this report.

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BDRIC ACID REDUCTION CONCENTRATION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV.00 FIGURE A4-1 Salem Unit 2 EOC 6 BORAD Analysis i

MTC = -44, Cooldown @ Max Xe., abOut t=7 hrs. After Shutdown 1200 1000 '

7 E 800 -

a 600 /

! 400 ca f

/

$M s

E O

/

=

l

-200 ,

/

l

-400 . .

1 ,

0 20 40 60 80 100 120 140 160 l

Time After Shutdown (hours)

ARI-WRSO i

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BORIC ACID REDUCTION CONCENTRATION EFFORT '

- fECHNICAL BASES AND OPERATIONAL ANALYSES CEN-606 ~

REV.00 FIGURE A4-2 Salem Unit 2 EOC 6 BORAID Analysis MTC 1200-

= -44, Cooldown @ Eq. Xe., t=22 hrs. After Shutdown 1000- i

/

800- f '

I '

s e00 /

2 /

v 400 m

-g 200- /

[

0- ,

-200, ,

20- 40 60 80 100 120 140 160 i80 Time After Shutdown (hours)

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ML20045B880

Text

1.0 INTRODUCTION

3.1 INTRODUCTION

4.0 REFERENCES

3.1 INTRODUCTION

4.0 REFERENCES

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