ML053330361

Calculation LM-0642, Rev 0, Suppression Pool Ph Calculation for Alternative Source Terms, Attachment 002

ML053330361
Person / Time
Site:	Limerick
Issue date:	09/27/2005
From:	Reichert P, Rothstein H Exelon Generation Co, Exelon Nuclear
To:	Office of Nuclear Reactor Regulation
References
CC-AA-309-1001, Rev 2 LM-0642
Download: ML053330361 (184)

Text

{{#Wiki_filter:ADDITIONAL ATTACHMENTS TO 10-10-05 Letter: Supplement to Request for LAR Application of AST 02 AST - LM-0642 Rev 1 pH.

CC-AA-309-1001 Revision 2 AITACIIMEN171 Desirn Anatrsi CowT Sheet Design Analysis (Major Revision) Last Page No. 16 Att. H-1 Analysis No.: IM-0642 Revision: 2 1

Title:

3 Suppression Pool pH Calculation for Alternative Source Terms ECIECR No.: 04-00003 Revision: ' 0 Station(s):r Limerick Component(s): Unit No.:' 1 & 2 WA Discipline: MEDC Descrip. Code/Keyword:'° H84 /AST. LOCA SafetyJOA Class: SR System Code: t2 912 Structure: N/A CONTROLLED DOCUMENT REFERENCES Document No-romlTo Document No.: romlTo LGS UFSAR =rom/To LGS Unit 1 & 2 Tech. Specs. romth LGS Dwg No.M-213 -rn LGS Unit I & 2 Tech. Spec. Bases FrornrTo LOS Dwg No.M-108 ro LGS Procedure CH-C-105-3 -ror Is this Design Analysis Safeguards Information? Yes [ No 0 If yes. see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? Yes 0 No 3 I ys, ATI/ARV: This Design Analysis SUPERCEDES: LM 0642. Rev. 0 In its entirety. Description of Revision (list affected pages for partials): "' This revision Incorporates clarifications regarding the conservatism of use of maximum Suppression Pool volumes for detennination of both minimurn sodium pentaborate quantity required and minimum time after the LOCA before its injection is completed. It also Incorporates responses to pertinent NRC Requests for Additional Information (RAis) with respect to li Exelon Nuclear Station Alternative Source Term License Amendment Applications 4A( /etZ Preparer ' Harold Rothstein Print Name gr262005 Sigh Name Date Method of Review: Detailed Review 0 Alternate,alcuu at hj) 0 Testing Q Revlewer: n Paul Reichert iQ4 O 7 5 9/26/2005 Print Name Sign Name Date Review Notes: 3 Independent review 0 Peer review Q ( a.Ex Exteal Approver: 2' t, e

7.

/ A o A -h- ° Print Nirame Sign Nfam Date Exelon Reviewer:. 7/Ja' Print Name Sko me Date Is a Supplemental Review Required? 2 Yes IJ No > It yes. complete Attachnent 3 ExelonApprover.' (10a.fpjr, 7FL04:/ Print Name Sign Name Date

I CALCULATION No. LM-0642 I-REV. NO. I PAGE 2 of 16 l TABLE OF CONTENTS

1.

PURPOSE AND OBJECTIVE.......................................................................... 3

2.

METHODOLOGY AND ACCEPTANCE CRITERIA......................................................................... 3

3.

ASSUMPTIONSIENGINEERING JUDGENMENTS......................................................................... 3

4.

DESIGN INPUT......................................................................... 3

5.

REFERENCES..................................................................................................................................................................... 6

6.

CALCULATIONS....... 7

7.

SUMMARY

OF RESULTS AND CONCLUSIONS......................................................................... 12

8.

OWNER'S ACCEPTANCE REVIEWN' ChECKLIST FOR EXTERNAL DESIGN ANALYSIS............................. 15

9.

ATTACHIMENTS......................................................................... 16 A - Determination of Total Exposed Cable Quantities Inside Containment 28 PAGES B - Dose Assessment, Core Cs & 1, and Gamma Mean Free Path Determination 14 PAGES C - pH Transient Spreadsheet 7 PAGES D - pH Transient Spreadsheet Cell Formulae 13 PAGES E - pH Transient - Grand Gulf Reference Data (unchanged from Rev. 0) 7 PAGES F - Reference 5.1 (unchanged from Rev. 0) 30 PAGES G - Reference 5.2 (unchanged from Rev. 0) 26 PAGES H - Computer Disclosure Sheet I PAGE

ICALCULATION No. LM-0642 I REV. NO. I I PAGE3of16 l

1. Purpose and Objective In order to prevent iodine re-evolution following an accident, the pH of the Suppression Pool should be maintained above 7.0. The chemistry of this phenomenon and methods of pH control are discussed in References 5.1 and 5.5.

The Objective of this calculation is to determine the pH of the Suppression Pool following a Loss of Coolant Accident (LOCA) based on the use of Alternative Source Terms (AST) as defined in References 5.4 and 5.6. The pH values are determined, as a function of time, with and without the addition of the sodium pentaborate in the Standby Liquid Control System. The minimum quantity of sodium pentaborate required to maintain the Suppression Pool at a pH above 7.0 is determined and compared to the current Technical Specifications (TS) limit.

2. Methodology and Acceptance Criteria This calculation is based on the methodology developed for the equivalent calculation done for the Grand Gulf Nuclear Station, Unit 1 as revised December 2000. [Ref. 5.1 & 5.2]. These references are included in this calculation as Attachments F and G. The Grand Gulf calculation was provided to the Nuclear Regulatory Commission (NRC) and the associated AST application was approved by the NRC. The calculation formulas developed in these Ref. 5.1 and 5.2 documents were reviewed by an experienced Washington Group International Chemical Engineer and used by him to develop the spreadsheets included herein in Attachments C and D. The accuracy of translation of the equations in these documents into spreadsheet cell formulas is verified by duplicating the Grand Gulf calculation. This verification is presented as Attachment E and accurately duplicates all of the Grand Gulf results.

As noted in this calculation, injection of sodium pentaborate solution by the Standby Liquid Control System (SLCS) is a required function in order to control post-LOCA pH in the Suppression Pool, and prevent iodine re-evolution. Based on the worst case beginning of cycle, injection should be completed within 13 hours after the start of the Design Basis Accident (DBA) LOCA. Therefore, manual initiation is acceptable. Manual initiation of SBLCS is expected early in a DBA-LOCA as a result of emergency operating procedures and severe accident guidelines, particularly for events resulting in fuel damage that would be consistent with AST source terms. Per the guidance of Appendix A of Regulatory Guide 1.183 [Ref. 5.6], the Suppression Pool pH should be controlled at values of 7 or greater, following loss of coolant accidents.

3. AssumptionsfEngineering Judgements The Suppression Pool is assumed to be well mixed so that the pH at any time can be represented by a single value.

As a worst case for determination of both the minimum sodium pentaborate quantity required and the minimum time after the LOCA before its injection is completed, the maximum Suppression Pool volume condition (to maximally dilute the initial Cesium from the core release and the sodium pentaborate addition) is utilized. For cable parameters, the cable data presented in Attachment A is used. It provides the lengths and outside diameters of all cables located in raceways in the drywvell, all considered as exposed to Post-LOCA environment. As a conservative estimate of the cable lengths in free air, an additional 10% of the totals are assumed to be in free air. A 10% contingency on the cable surface area, reported in Attachment A is also included. Radiolysis of surface coatings on the steel and concrete surfaces in the Drywell and Containment would not be significant contributors, since the coatings utilize non-chlorinated polymers.

4. Design Input 4.1 Cable Data Cable lengths, diameters, and average jacket thickness are developed separately and presented in Attachment A.

I CALCULATION No. LM-0642 I REV. NO. I I PAGE4 of 16 1 4.2 Temperature Suppression Pool temperatures are taken from SIL-636 results, as contained in Attachment E of the Limerick Generating Station (LGS) Calculation LM-0646 (Ref. 5.16). This data only extends to 100,000 seconds, but as indicated in UFSAR Figure 6.2-9A, Suppression Pool temperatures are going down with time by 100,000 seconds, and there is no mechanism for the temperatures to rise between 100,000 seconds and 720 hours. Therefore, the Suppression Pool temperature at 100,000 seconds is used from then until 720 hours, as this is conservative (higher temperatures give lower calculated pH values). 4.3 Sodium Pentaborate Mass in SBLC Tank The minimum quantity of sodium pentaborate required to maintain the Suppression Pool at a pH above 7.0 is determined and compared to the current minimum available volume of sodium pentaborate solution stored in the SBLC tank of 3160 gallons, as per LGS Technical Specification section 4.1.5. Per the LGS TS Figure 3.1.5-1 [Ref. 5.7], a 10% solution concentration, by weight, is chosen to conservatively bound the acceptable operable range. As per reference 5.11 (Table CH-C-105-3) and Attachment C, a specific gravity of 1.0485 gm/cm3 corresponds to this Na2B30016*10H20 concentration. Based on the TS 3160 gallon volume and this specific gravity, the total solution mass equals 27,651 lbs. and, at lOwt% the total mass of Na2B10016.10H 20 in solution is 2765 lbs. Although references 5.3, 5.8, and 5.11 indicate that artificially enriched Boron is used in the SBLC sodium pentaborate, for this calculation, the natural ioB enrichment of Boron, 19.9%, is assumed in order to conservatively minimize its available gm-moles. Because ioB has an atomic weight of 10.0129 gm/mole, and "1B has an atomic weight of 11.0093 gm/mole, the calculated naturally occurring molar mass of Boron is 10.811 gm/mole. This value agrees with the periodic table value. The total molar mass of Na2BI 0016.10H20 is 590.23 gm/mole. Based on the 10.811 gm/mole mass of Boron, the percentage of total Boron in Na2B100 6-10H2O is 18.3165%. Taking 18.3% of the 2765 lbs. total mass ofNa2BI0016.10H 20 forthe TS 3160 gallon volume gives a total of 506 lbs., or21,249 gm-atoms of total available Boron for the TS 3160 gallon volume. Attachment C page C-6 provides the corresponding derivation of the minimum quantities in gallons of sodium pentaborate solution stored in the SBLC tank and resulting lbs. and gm-atoms of total available Boron required to maintain the Suppression Pool at a pH just above 7.0. 4.4 Suppression Pool and Drywell + Suppression Pool Airspace Volume In order to determine the minimum quantity of sodium pentaborate required to maintain the Suppression Pool at a pH above 7.0 for the purposes of this calculation, the maximum Suppression Pool volume and corresponding minimum Drywell + Suppression Pool Airspace volume is required. Initially, for maximal conservatism in this calculation, the entire 200,000 gal. (26,736 cu. ft.) Condensate Storage Tank capacity provided in Design Baseline Document L-S-41 (Ref. 5.14) was considered as added to the maximum Suppression Pool volume as derived from the UFSAR Table 6.2-4A High Water Level volume of 134,600 cu. ft. plus a maximum Reactor Coolant System liquid and applicable piping volume for a total of approximately 185,000 cu. ft. However, the Condensate Storage Tank volume would not be applicable to large break DBA-LOCA conditions considered herein, where low-pressure Emergency Core Cooling Systems would be utilized. Considering this, an approximately 154,000 cu. ft. maximum Suppression Pool volume is derived, as shown in the Exelon e-mail included in Attachment C. However, to increase the conservatism, a 175,000 cu. ft. maximum Suppression Pool volume is used. For the corresponding minimum Drywell + Suppression Pool Airspace volume, the 403,120 cu. fl. value from ST LLR-00-1 [Ref. 5.15] is used minus the above 175,000 cu. fl. conservative maximum Suppression Pool volume and plus the 122,120 nominal minimum Suppression Pool volume provided in TS 3/4.5.3 for a value of 350,240 cu. ft. 4.5 Adequacy of Mixing The Emergency Core Cooling System (ECCS) takes water from the Suppression Pool and pumps it into the core region of the reactor vessel. Additionally, the SBLC System will pump from the SBLC Tank into the reactor vessel, above the core, so that it mixes with the ECCS water in the core region. This mixed ECCS water and SBLC solution

I CALCULATION No. LM-0642 I REV. NO. I PAGE 5 of 16 will refill the reactor pressure vessel under post-LOCA conditions, and eventually spill out of the break into the Suppression Pool. To illustrate the adequacy of the SBLC solution mixing in the Suppression Pool, a minimum spillage and bounding maximum volume of the Suppression Pool are considered. The minimum spillage is taken as just one core spray loop at its minimum allowed run-out flow condition of 6250 gpm, as per LGS UFSAR Table 6.3-1 on Significant Input Variables Used in the SAFER/GESTR-LOCA Analysis. This flow rate is significantly less than any of the LGS UFSAR Table 6.3-3 Single Failure Evaluation conditions, including the assumed failure of the Division 2 dc source or of the Diesel Generator. The maximum post-LOCA volume of the Suppression Pool of 175,000 cu. ft from Section 4.4 above is also utilized for additional conservatism. A two-hour delay before ECCS and SBLC initiation to refill the reactor pressure vessel is also conservatively assumed, consistent with the event timing in Regulatory Guide 1.183. After two hours, simultaneous injection of SBLC solution and ECCS fill of the reactor pressure vessel takes place. However, no consideration of the filling rate from SBLC is conservatively considered. Using these assumptions, the reactor pressure vessel volume of 19,090 cu ft (including piping) indicated on Attachment C page C-7 would be flooded in [(19,090 cu fl) x 7.4805 gallon / cu ft] / 6250 gallon / minute = 22.8 minutes, or by 2.38 hours after the LOCA. The minimum Suppression Pool volume turnover rate is then calculated as: [175,000 cu ft x 7.4805 gallon / cu ft] / 6250 gallon / minute = 209 minutes = 3.49 hours. Thus, the initial turnover of one Suppression Pool volume containing essentially 100% of the SBLC injection is calculated to be completed by 2.38 + 3.49 = 5.87 hours after the LOCA, with subsequent Suppression Pool turnover of the full Suppression Pool volume taking place every 3.49 hours, with approximately 6 Suppression Pool volume turnovers per day. Thus, adequate mixing of the Suppression Pool with the SBLC Sodium Pentaborate is assured.

CALCULATION No. LM-0642 REV. NO. I PAGE 6 of 16

5. References 5.1.

GGNS-98-0039, Rev. 3, "Entergy Operations Engineering Report for Suppression Pool pH and Iodine Re-Evolution Methodology", Applicable Site: Grand Gulf Nuclear Station, 12/20/00. 5.2. XC-QI 111-98013, Rev. 2, Grand Gulf Design Engineering Calculation "Suppression Pool pH Analysis", 12/20/00. 5.3. LGS Units I & 2 UFSAR, Rev. 12. 5.4. NUREG-1465, "Accident Source Terms for Light-Water Nuclear Power Plants", February 1995. 5.5. NUREG/CR-5950, "Iodine Evolution and pH Control", December 1992. 5.6. USNRC Regulatory Guide 1.183, "Alternative Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", July 2000. 5.7. LGS Unit I Technical Specification, Rev. 177, and LGS Unit 2 Technical Specification, Rev. 139. 5.8. LGS Units I & 2 Technical Specification Bases, Rev. 0. 5.9. LGS Design Analysis LM-0645, "Re-analysis of Fuel Handling Accident (FHA) Using Alternate Source Terms", Rev. 0. 5.10. GE Report NEDC-32963A, "Prediction of the Onset of fission Gas Release From Fuel in Generic BWR", March 2000 (Allows a 121 -second delay in timing of fission product release following design basis accidents). 5.11. LGS Procedure CH-C-105, Rev. 5, "Boron Analysis by Automatic Titration". 5.12. Radioactive Decay Data Tables by David C. Kocher, Report DOE/TIC-1 1026 Technical Information Center U.S. DOE, Washington, D.C., 1981 5.13. LGS Units I & 2 Drawing No. M-108 Rev. 7, "General Arrangement Section C-C". 5.14. L-S-41, Condensate Storage & Transfer System Design Baseline Document, Rev. 6. 5.15. ST-4-LLR-00I -I, "The LLRT Program and Accountability Test", Rev. 8. 5.16. LGS Design Analysis LM-0646, "Re-analysis of Loss of Cooling Accident (LOCA) Using Alternative Source Terms", Rev. 1.

I CALCULATION No. LM-0642 I REV. NO. I I PAGE7of16 I

6.

Calculations pH - Fundamental Relationships pH = -loglo[H ] 6-1 [H+].[OH ] = Kw(T) 6-2 where: [Hi] = concentration of hydrogen ions in moles/liter [OH] = concentration of hydroxyl ions in moles/liter Kw(T) = ionization constant for water as a function of temperature T The data for Kw for T between 77 and 212 'F can be represented by the following correlation developed in Section 3.0 of Reference 5.1: -LogloKw(T) = 15.5129 - 2.24E-2

• T + 3.352E-5
• T2 6-3 Hydriodic Acid Production Iodine, accompanied by Cesium, is released during the Gap Release and Early In-Vessel Release phases.

The following equation, valid during the Early Vessel Release Phase, includes the release during the Gap Release Phase. See analysis in Reference 5.1 (Section 3.1 and Equation 3-1d). Iodine and cesium core inventories are calculated for both beginning and end of cycle (BOC and EOC) conditions (See Attachment B for a discussion of the assumed BOC conditions). Since EOC conditions result in increased inventory of both acidic (iodine) and basic (cesium) compounds, pH values are calculated for both conditions. For conservatism, the EOC radiation doses are used for the BOC calculation. The hydriodic acid concentration is governed by the following equation: [HI](t) = ml / (120

• VPOOL) * [t - (0.5 + tgap)] + min/ (400
• VPOOL) 6-4 where:

[HI](t) = concentration of Hydriodic Acid at time t (moles/liter) ml = core iodine inventory (gram-moles) VPOOL= Suppression Pool volume (liters) t = time after start of accident (hrs) (includes tgap + Gap Release [0.5 hrs] + Early In-Vessel Release [1.5 hrs] duration for a t,,, = 2.0336 hrs) [Ref. 5.6, Table 4, page 1.183-15] tgap= time of onset of gap release = 121 seconds = 0.0336 hrs [Ref. 5.6 and 5.10] tma, = 2.0336 hrs = end of Early In-Vessel Release [See Attachment C Spreadsheet: Sheets I (EOC) and 5 (BOC), Col H] Nitric Acid Production Nitric Acid is produced by radiolysis of the water in the Suppression Pool with a G value of 0.007 molecules HNO3 / 100 eV absorbed dose or 7.3E-6 g moles / megarad-liter [Ref. 5.1, Section 3.2, Equation 3-2b]. The nitric acid concentration is governed by the following equation:

I CALCULATION No. LM-0642 I REV. NO. I PAGE 8of16 [HNO3](t) = 7.3E-6

• D(t)p..

6-5 [See Spreadsheet Col. 1] where: [HNO3](t) = nitric acid concentration at time t (moles/liter) D(t)r 1ol = Total accumulated dose in Suppression Pool at time t (megarad) Hydrochloric Acid Production Hydrochloric Acid is produced by radiolysis of chlorinated polymer cable jacketing. Radiolysis of surface coatings on the steel and concrete surfaces in the Drywell and Containment would not be significant contributors, since the coatings utilize nonchlorinated polymers. The calculation of the resulting concentration in the Suppression Pool is based on the equations in Section 3.3 of Reference 5.1 [see Ref. 5.2, Equations 5-1, 5-2, and 5-3]. These equations are in turn based on the following G value for HCI production in Hypalon chlorinated polymer given in Reference 5.5. G11rc= 2.115 molecules/lOOeV = 3.512E-20 g moles HCI / MeV The hydrochloric acid concentration is governed by the following equations: Doses from beta and gamma radiation are calculated separately. [HCl]p(t) = G11c, / VPOOL * (Stray / 2 + Sfa) / Pp air

• Dp(t) 6-6 where the effective cable surface area for f3 dose is:

Stray / 2 + Sfa = n

• Do * (Ltry /2 + Lfa)

[See Spreadsheet Cols J & L] [HCI]y(t) = GFIcI / VPOOL * (Stry + SO) * (1-e -Xair A) / Ptrair

• ( - e - a hypalon I th)
• DY(t) 6-7 where: Stry + Sfr = 2!
• Do * (Ltray + Lfga)

[See Spreadsheet Cols K & M] where: [HCl]p(t) = HCI concentration from Beta radiation at time t (g moles/liter) [HCl]I(t) = HC1 concentration from Gamma radiation at time t (g moles/liter) Do = cable diameter (cm) Lray = cable length in trays (raceways) (cm) Lfa = cable length in free air (cm) P[ air = linear beta absorption coefficient in air (1/cm) pxair= linear gamma absorption coefficient in air (1/cm) rx = gamma free path (cm) Pxhypalon = linear gamma absorption coefficient in Hypalon (I/cm)

I CALCULATION No. LM-0642 I REV. NO. I I PAGE 9of 16 th = Hypalon jacket thickness (cm) Dp(t) = accumulated beta dose per unit volume at time t (MeV/cm 3) D1 (t) = accumulated gamma dose per unit volume at time t (MeV/cm 3) Gace= 3.512E-20 (g moles HCI / MeV) VPOOL= Suppression Pool volume (Liters) Stray= Cable surface area in trays (cm2) Sfa = Cable surface area in free air (cm2) Cesium Hydroxide Production Cesium, accompanied by Iodine, is released during the Gap Release and Early In-Vessel Release phases. The following equation, valid during the Early Vessel Release Phase, includes the release during the Gap Release Phase. See analysis in Reference 5.1 (Section 3.4 and Equation 3-4d). Iodine and cesium core inventories are calculated for both beginning and end of cycle (BOC and EOC) conditions (See Attachment B for a discussion of the assumed conditions). Since EOC conditions result in increased inventory of both acidic (iodine) and basic (cesium) compounds, pH values are calculated for both conditions. For conservatism, the EOC radiation doses are used for the BOC calculation. The cesium hydroxide concentration is governed by the following equation: [CsOH](t) = (0.4

• mc,- 0.475
• ml) / 3
• VpooL) * [t - (0.5 + tgp)]

+( 0.05

• mc,- 0.0475
• mi) / VPOOL 6-8

[See Spreadsheet: Sheets I (EOC) and 5 (BOC), Col 0] [CsOH](t) = concentration of Cesium Hydroxide at time t (g moles/liter) ml = core Iodine inventory (gram-moles) mc, =core Cesium inventory (gram-moles) VPOOL= Suppression Pool volume (liters) t = time after start of accident (hrs) (includes tgap + Gap Release [0.5 hrs] + Early In-Vessel Release [1.5 hrs] duration for a tmax =2.0336 hrs) [Ref. 5.6, Table 4, page 1.183-15] tgap= time of onset of gap release = 121 seconds = 0.0336 hrs [Ref. 5.6] = 2.0336 hrs = end of Early In-Vessel Release Final Pool pH Calculation (No SBLC Addition) The net Suppression Pool pH can be calculated from the total of the [Hi] and [OH'] concentrations using the following equations developed in Reference 5.1, Section 3.5. [H+](t) = [H+](t=O) + [HI](t) + [HNO3](t) + [HCI](t) [H+](t)= 10-Pf'(t=0) + [Hl](t) + [HNO3](t) + [HCI](t) 6-9 [See Spreadsheet Col N] [OH-](t) = [OH'](t=0) + [CsOH](t) [OH'](t) = I0-'4 /I0-P"(t=0)+[CsOH](t) 6-10 [See Spreadsheet Col P] Accounting for the concentration of neutralized ions [x]:

I CALCULATION No. LM-0642 l REV. NO. I I PAGE 10 of 16 ( [H+] - [x] ) * ( [OH-] - [x] ) = Kw(T) [x] ={ [H+] + [OH-] - {([H+]+[OH-])2 - 4*([H+]*[OH-]-Kw)} "2 } /2 6-11 [See Spreadsheet Col R] note: Kw = 1 0+ Log Kw) [See Equation 6-3 and Spreadsheet Col Q] The equation for the net [H+] becomes: [H+].ct = [H+] - [x] 6-12 [See Spreadsheet Col S] and pH = - logio([H ].,t) 6-13 [See Spreadsheet Col T] Effect of Sodium Pentaborate (SBLC) Addition The pH of the Suppression Pool is increased by the addition of Sodium Pentaborate from the Standby Liquid Control (SBLC) System. As per Section 4.3 of this calculation, a limiting value (minimum weight) of Boron is used. The limiting value is used since it minimizes the number of moles available for buffering. Addition of Sodium Pentaborate introduces a buffer into the Suppression Pool, which will maintain the pool at a pH corresponding to the following equation: [Ref. 5.1, Sec. 6.1, p. 21]. pH = pK. + loglo ( [anion] / [acid]) 6-14 with data for Ka fitted by the equation Ka = (0.0585

• T + 1.309)E-10 6-15

[See Spreadsheet Col U] where: Ka = boric acid dissociation constant PKa =negative of the log of the boric acid dissociation constant [See Spreadsheet Col Z] T = °F [anion] = borate concentration of [2B(OH)4 [acid] = boric acid concentration of [8H3BO3] based on the equation Na2B,0O,6 + 16H 20 <4 2Na + 2B(OH)4. + 8H3BO3 Therefore,

I CALCULATION No. LM-0642 I REV. NO. I I PAGE 11 of 16 Borate (g-equivalents) = 2

• Na2B10O16
• 10 H20 (g-moles)

Boric acid (g-equivalents) = 8

• Na2B10O06
• 10 H20 (g-moles)

Using the methodology of reference 5. 1, the net strong acid equivalents [H+]nec calculated in Equation 5-12 are neutralized by the borate and the above equations become: Borate (g-equivalents) = 2

• Na2B10O16 (g-moles) - [H+]n
• VPWI 6-16

[See Spreadsheet Col X] Boric acid (g-equivalents) = 8

• Na2B30O16 (g-moles) + [H+]nt
• VP.,

6-17 [Sec Spreadsheet Col Y] And equation 6-14 becomes: (2

• Na2B10O16 (g-moles) - [H ]nct
• Vp. 1) / VP1 pH = -logioKa +loglo (8
• Na2B10O16 (g-moles) + [H+]net
• Vp~o,)

/ VP001 6-18 [See Spreadsheet Col AA]

I CALCULATION No. LM-0642 I REV. NO. I I PAGE 12 of 16

7. Summary of Results and Conclusions The post accident Suppression Pool pH is calculated as a function of time after accident initiation. The results are shown below in Figures 7-1 and 7-2 for Beginning of Cycle (BOC) and End of Cycle (EOC) conditions respectively. These graphs are based on Excel spreadsheet calculations presented in Attachment C (Sheets I and 5). The inputs to the pH calculation of radiation doses (based on the Source Term data from Reference 5.9) and the Iodine and Cesium inventories are presented in Attachment B.

The BOC (actually early cycle) condition produces the lowest pH and is therefore the limiting case. Without addition of sodium pentaborate from the Standby Liquid Control (SBLC) System, the pH in the Suppression Pool could drop below pH 7 after about 13 hours. Therefore, SBLC addition is required to prevent iodine re-evolution. With SBLC addition of only 1500 gallons (of the TS 4.1.5 3160 gallons available), the Suppression Pool remains above pH 7 at 30 days (720 hours). This equates to 240 lbs. total Boron or 1313 lbs. sodium pentaborate.

I CALCULATION No. LM-0642 I REV. NO. I I PAGE 13 of 16 l Figure 7-1 pH vs. Time - BEGINNING OF CYCLE 10.00 9.00 8.00 7.00 6.00 cL 5.00 4.00 3.00 2.00 1.00 0.00 1 10 100 Time (Hours) 1000

I CALCULATION No. LM-0642 I REV. NO. I l PAGE 14 of 16 l Figure 7-2 pH vs. Time - END OF CYCLE 9.00 8.00 7.00 6.00 5.00 no 4.00 3.00 2.00 1.00 0.00 1 10 100 Time (Hours) 1000

I CALCULATION No. LM-0642 lREV. NO. I PAGE 15 of 16 l

8. OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS DESIGN ANALYSIS NO. LM-0642 REV: I

1.

Do assumptions have sufficient rationale?

2.

Are assumptions compatible with the way the plant is operated and with the licensing basis? (

r A45i

3.

Do the design inputs have sufficient rationale?

4.

Are design inputs correct and reasonable?

5.

Are design inputs compatible with the way the plant is operated and with the licensing basis? ( ;> A<i )

6.

Are Engineering Judgments clearly documented and justified?

7.

Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis? { F.ZI'r rAt)

8.

Do the results and conclusions satisfy the purpose and objective of the Design Analysis?

9.

Are the results and conclusions compatible with the way the plant is operated and with the licensing basis? £ / r-As-r)

10.

Does the Design Analysis include the applicable design basis documentation? Have any limitations on the use of the results been identified and transmitted to the appropriate organizations?

12.

Are there any unverified assumptions?

13.

Do all unverified assumptions have a tracking and closure mechanism in place?

14.

Have all affected design analyses been documented on the Affected 14 Documents List (ADL) for the associated Configuration Change? Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments? (If the input sources or

15.

analysis methodology are based on an out-of-date methodology or code, additional reconciliation may be required if the site has since committed to a more recent code)

16.

Have vendor supporting technical documents and references (including GE DRFs) been reviewed when necessary? EXELON REVIEWER: I...] 9' DATE: _PQTA/ Sign Yes V11 No El 11 11 El S S: n N/A S1 S: c S: S1 S3 S: El El 1 O1 EB,o0,s10H 20 Borate Borc Add 12 -onstliter efore SLC Net tH+l

• VP 0-roos agdotv.

a equlv. I*S13-BS3

• 3SVS4
• W132-V13 J-514-SBS3
• =SVS4 "W14-2-V14 15 16 17

=iN15+P15-SORT(POWER((SN51+!15) (N1 SPt '(N16+P16-SQRT(POWER((SN16+SP16),2i4-(N16'P1 (N17+P1 7-SORT(POWER((SN17+SPIT7).2-4(N17'P1 '1N18.P18-SORTIPOWER((SN18+SP18),2)41N1&PI (N19*P19-SORT(POWER((SN SP19),2X4-(N19-P1 =( N20+P20SRT(POWER((SN20 *SP20).2)4-(N20 P2 -(N21.P21-SORT(POWER((SN21 SP21I.24'(N21-P2 'SN 15-SR15 '(O.0585-B15+1 S1515BS3 =SVS4 =-W152-V15 .W16-2-VI6

• SN16-SR16 3.-SO 1))))y2 D.-S019))))Y2 3..SQ201111y2

'SN17- -LOG10(5S 16) -LOG10SS1l7) t-LOG10(M5191 Lo1o(s9 '(0.0585'B16+1., =S16-SBS3 'S17-SBS3

• S18-BS3

'S1918$53 -S20-SBS3

• S21 SBS3

'WI 5*8-V15 =SVS4 .SVS4

• SVS4

-SVS4 -W1618+V16 1 309Y10000000000 I 'W192-V19 1-WI 8+V1 I;n-I^ l_^ 20 21

• (0.0585820+1.309Y10000000000 I

-3SV34

• wZu-V-Z0 T-Wlz-tsv2o 22

'(N224P22-SORT(POWER((SN22+$P22).2H ER(10,-S021))))y2 tE(10L-SO22))))Y2 2o3l .(N24+P24-SQI A,; -;M^CzD^c r,^, za -Nza......... 26 27 '(N26+P26-SQRT( (PRUWEn RWSU 4b '(N27+P27-SORT(POWER(($N27+SP27).2N 'sN21-SR21 'SN22-SR22

• SN23-SR23
• SN24-SR24

'SN25-SR25 =SN26-SR26

• SN27-SR27
• SN28-SR28
• SN29-SR29
• SN30-SR30

-SN31-$R31 -. MŽ'2YX'2 )_ -LOGIO($S526) 28

• (N28+P28-t

'(.0 585-B25+1.i !f.0585Bf26+1.3 =(0.0585-B27+1.3 =(0.0585-B28+..3 '(0.0585B291.3 '(0.0585-B30+1.,j (0.0585-B31+13 !(0_0585-B32+1. '(0.0585B33*1.3 r(0.0585-B34+1.3 r(0.05855B35+1.3 i 309)10000000000 1 4 *S25-SBS3

• SVS4 S26-SBS3 SVS4

' 5S27fSBS3 'SVS4 =528-SBS3 'SVS4 =S29'SBS3 $SVS4 = JS30-S83 JSVS4 5 'W2618+V26

• W2r8+V27

'W2818+V28 sW2918+V29 'W308+V30

SVS4

W21-2-V21 I'W21-8-V21

'W25-2-V25 'W2518+V25 'W30 2-V30 '-4 .S31'SBS3 .$VS4 I1 'W31P8+V31 PC =SN32-SR32 33 '(N33+P33-SORT(POWER((SN33+SP33).2H I.-S033)))2 -LOG10(SS32) LOG10G(SS33) LOGO(S534) '-LOGIO(SS351 34 1-iN34 +P34 -SQRTI N {I<CD< ED 'S35-SB3 'W35-2-V35 I=W35 8+V35 XOG1tSS35) 40 41 42 4B 47 48 49 52531 LM-0642, Rev. 1, Atiament D, Page D-11 of D-13

LIMERICK GENERATING STATION TRANSIENT POOL pH CALCULATION I 2 3 4 5 6 16 ITRLOG ULIE SOLU.LONi(X6SS)f 81 40 41 K.p 42

,.K 43

_LGI__3__ Z3_O_0_X__N__lY 8$) 144-OI(I)-l+Ol0(M SyY4S$ 45 -O1(I)-I+OI(X~$$yY~S$) 46 LOIUl lZ6L i0(q B sta 471-LGDU7 M OGO(74 3 7M 48 I-_G___8______G_ M 1_$3 (Y W$ S 195 LGO0) -i+Ol(Xj$$ 9$$ 51=LGDU0 -2+L~0(~S3 O$$) 521 LGOU1 -2+Ol(X1$ yfl$ 53-OI(2)IZ2LGI(X2$$yY2$$) 54 _LOGI (U23 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __3/8$3) LM-642, Rev. 1, Attachment 0, Page D-12 of 0D13

LIMERICK GENERATING STATION TRANSIENT POOL pH CALCULATION A BC 0 A Available Boron Calculation C_ D 4 Vuantiv_ Value Basis 5 6 Volume of Solution (gal)- 1500 Assumed Minimum (LGS Tech Spec Sect. 7 Indicates 3160 gatons) 8 wvt% of Na2B100161OH20 0.1 LGS Technical Specification figure 3.1.5-1 9 Speclflc Gravltyjgm/cm3)-

• 0.5O(SBS8)+0.9985 Table CH-C-105-3 10 Conversion Factor (cm3lgai)-

3785.412 11 Converslon Factor (lbs/gm)- =(1/453.59) 13 Total Mass of Solution (Ibs)-

• B6-B9-B10-B11 14 Total Na2B,,0,*10" 20 (lbs).

=B13-B8 15 Total Na2 B,*01,10H20 (gm)) =B141B11 16 Total Na2B,0O,.10i 2O 17 ?gm-moles). =B15/028 18 Total Boron (gm-atoms). =10-B17 19 20 21 TotalAvai/able Boron (Ibs)-

• B14-B35 22 Total Available Boron (gm-atoms).

21/B11yB29 23 24 B-10 Enrichment-0.199 25 26 Molar Mass Total Molar Mass of 27 (atgn/mote) Na2B100I6

• 101H20 28 Sodium 22.98977
• 2'(B28)+10 (B29)+1 6(B30)+10-((2-B31)+(1 (B30)))

29 Boron

• B32-(B24)+B33-(1-B24) 30 Oyen 15.9994 31 Hydrogen 1.00794 32 Boron-10 10.0129369 33 Boron-1I 11 0093054 34 35 Percentage of Total Boron-
• -10(B29Y)D28 LMt0642. Rev. 1, Attachment D, Page D-1 3 of D-1 3

GRAND GULF REFERENCE CALCULATION A B I C I 0 E F G H I J K I I M N I o I P I CASEI 1GRAND GULF REFERENCE DATA pH TRANSIEN J..I 2 Linear Absorption CoeffiCients' LA. fb] 873.65 Cable Length [trays]- Zone A SLC fibs] 3 VpOyL 4.841E+06Llters [Min.Tech Spec Basis B3.6.2.21 UbftD 1.980E-02 1/cm LAI. fib] 873.65 Cable Length Ifreeair]- Zone A 4 Ml 325,Iodine inventory ["-toms] Ub~s hyp~ael 52.08 Ilcm La ft fib] 14049.2 Cable Length ptrays] - Zone B 5 Mc$ 240 Ceslum Inventory fg-atoms] Ugamm.aair 3.75E-05 Ilcm Lsf. fib] 1561.03 cable Length [free air].Zone B 6 twa 0.0336 Onsel of Gap release hfrs] U00"In 0.099 11cm R, [crIn~b 80 Cable AreaI 7______________ _____Ij.fle

• pe.i 1112.5~crn th [cm) 0.71 Hyao aklTickness 8

_1384__ cm _1 9 INTEGRATED DOSES ~ 34mCONCENTRATIONS_____ 10 ____Bl+am Gamma Beta Gamma Bela____ From Beta From Gamm From Bela From Gamma 11 I TIME POO TemrFq [NP HC RC A POOL DRYWELL DRYWELL CONTAINMENT CONTAINMENT [H] [Nj~(C]A [CJA HCLj -13 Total -14+ IfCsOH] Total [OH-1j 12 Hus Deg F Mrad MeV_____ g-mols/liter g-mols/liter g-molsl~ter g-mols)Iiter g-molstitier g-mois/Iter g-lons~liter g-molstfiter g-ionsditer 1 4 1 __ 160 iiI 4.288E-07 .45.4416E-06' 4.74726-05! 4.75E-05 1 5 2 160 1.3645E.01 1.42006.1 2.8733E+12 0.ODOOE+ 1.1220+ 9 82E-07 9.961 E-07 1.1046-0 1.067E-06 2.824E6 0.OOOE2+00 1.199E-051 1.0295E-041 1.03E-04 16 2.0336 160 1.42296.01 1.4506E+1 2 74+ .00+0 8+6-i-6 09-6 116-0 .9E0 70.E0' 126-5 .48-4 .5-4 17 3 159.1 2.94156.01 2.6 0 .5 E 17.6 111-061 1.625E-06 3.2496E0 55606.07 14766.05' 1.0481 18 5 155.5 co464-, 301613.28E.1: 6.467161 E.4468E.2Y07E t3.969E-0 iE-2.328E-06. 3.6416.0 5.3736.06, 2.261E.05 1.0481E-041 1.05E-04 1 9 1 2 149.2 1.1306E+. 473E1 43126.1: 1.6404E*+1 1.9789E.1 1.00IE 8.2~53E. T660 .33E.06 4.980E-6 1.363E-5 38E-5108604 1.05E-04 20 1__ 18 146.4 1.4 046 5.4462E+1~ 5.1609E6.1 2.106Ef+1 2.4183E,121t4.091EE0 1.08 1.04817404 1.05E-04 2 __24 144.3 1.7610E.0 5.97336.1 5.9584E+1: 2.4271E+11 280E1107-0 1.86E05 2296.6 487-6 7.155E-06 2.016E1-05 5.2976.05~ 1.0481E0! 10E0 22 __ 48 139.4 2.5674E+C 7.2434E+1 8.85036.11 3.2138E.1' 4.4038E.1 1.0071 E-06 1.8746-05, 3400.6 5.442E-06 1.108E-05 2.6706.05 7.1386.05' 1.0481E-4 10E0 23 72 13.5310+W 7.98636+1 1.1319E.13! 3.87406+1' 5.7649E1 1.01.6234.0 .460 .06-6 1.4516-05 3.526-05 8.444E.51086-4 10E0 24 96 134.4 3.55. 85361 1.3425E+13 4.0005E+1, 6.9521E.1 1.0071E-06 2.665E-05 .5E0 .960 .5E0 .260 9.495E-05' 1.04816E-041 1.504 25 120 132.8 4.0931 E+O 8.9224E+l1 1.52246.1~ 4.2538E+14 7.9874E+1l 1.00716-E62.988E.05 .460 .0E0 2.01OE-05 3.534E.05 1.039E-04 1.04816-041 1.05E-04 26 ISO_ 15 T31-.3 4.60106.O 9.3312E120 1.7105E.1N 4.50716.1 - -9.09756-+1 1.0071E-06 3.359E-05 8.571E.06 7.010E-06 2.290E-05 3.744E.05 1.135E-04 1.0481E I.05E.04 271 200 129.2 5.3738E+O 9.8584E6.1 1.952116+11 4.8336E+1' 107EI~ 1.001T6 3.923E-05 7.499E.06 7A406E.06 2.661 E-05 4.016E-05 1.269E-04 1.0481E-04 1.05E-04 28 ___240 127.9 5.9431E+0 1.0192E+1. 2.0955E+1l 5.0405E+Il 1.14866.13. 1.0071E-06 4.338E-05 8.050E.06 7.657E-06 2.8916E-05 4.187E-05 1.359E.04 1.04816E.04 1.05E-04 29 300 128.3 6.7335E+f 1.0601E+13 2.2506E.1~ 5.2938E.1 1.2519E6I, 130-0-716-06 4.915E-05 8.6456-06 7.964E-06 3.151E-0-5 4.398E-05 1.4736-04 1.0481E-04 1.0560 30 360 125 7.4620E6. 1.0935E+13! 2.35516+1r 5.5007E.1 1.3252E4.13!1.0071E.06 5.4.47E-05 9.047E-06 8.2156-06 3.3356-05 4.570E-05 1.568E-04 1.04816E-04 1.05E-04 31 ___400 124.3 7.91916+O I.II28E.13 2.40496.13 5.6203E2+1 1.3618E+13 1.0071E-06 5.781 E-051 9.238 -6~.660 .427E-05 4.6696-05 1.6246-04 1.04816-04 1.05E2-04 32 480 123 8.7770E. 1.1463E+1 2.47276.13, 5.8272E~i 1.41436+135.00716-068.4076-05 9.499E-06 8.812E-06 3.5596-05 4.841 E.05 1.722E-04 1.04816E-04 1 OSE-04 33 600 121.4 9.940+ 1.18716+13 2.5259E+13 6.0805E.12 1.4592E.13! 1.0071E-06 7.266E-05 9.703E-06 8.9186-06 3.672E-05 5.0516-05 1.4E0 .410~ 10E0 34 700 120.3 1.081.1 1.2154E.1 254726.13 6.2555E1Z 1.47916E13 1.00716-06 7.928EE5-0685 9.1316.061 3.722E-051 5.1976-051 1.9346.04: 1.04816-04 1.056-04 35 720 120.1 1.10356+01 1 2 5 1 3 5 0 6 4 .87E2 1.4819E+13T E~8.0566-05 9.795606 9.169E-06 3.7296-05 5.2236-05! 1.951 E-0410481E-04: 1.056-04 36 37 NOTES__ 38 1EntergyEng. Report GGNS-98-0039 Rev.3, Equation 3-Id [30+90min rlase duration) 14.Acid dissociation constant from: EntergyEng. Rep. GGNS-98-0039 Rev.3, Sect.6.1,.21 39 2 Ibid, Eiainsb_____________ 15neg Cat( C-O1111-98013 Rev.2. Section 5.7 40 3 Ibid, Equation 3-4d [30+90 min release duration] 41 4 Ibid.TableA-42 5 Ibid, qain33:Etrg~l.CO11-81 Rev.2, Equatin-_________________ 43 6 Ibid. Equto -b neg~l.XC-011111-98013 Rev.2E Eqation 5-2 44 7 Ibid. Equation 3-a; neg~l.X-111903Rv2 eto 5.7 45 8 Ibid. Equation 3-Sb: Entergy Ca~c. C-Q1 111-9801 3 Rev.2. Section 5.7 46 9 Ibid. -Equation 3-0a; EnteryCalc. XC-a11111-98013 Rev.2, Section 5.7 47 1 0 Ibid, Equation 3-Sd: Entergy Cale. XC-01 1III -98013 Rev.2, Section 5.7 ________________________ 4i8 11 Ibid. Equa~tion_3-Sd:, EntergyCac. XC-O11 111-98013 Rev.2, Secton5.7 49 12 Ibd qu ton 3-eIEnbiyad, XC 11 1 -9 01 R011Se tin1.71__ __98013_ Re__ ___2_ __Section_ ___5___7_ -50 131 Enterqy Calc. XC-O11111-98013 Rev.2.,Section 5.2.2 I LM.062. Rev. 1, Attachment E. Page E.1 of E-7

GRAND GULF REFERENCE CALCULATION a 0 R S [T u v w fx lY Z MA IAB AC 1 I I_ 2 5800 Na2B,0O 1 Added [MW--4101 3 4 5 6 8 pH EFFECT OF ADDITION OF SODIUM PENTABORATE STANDBY LIOUID CONTROL (SLCJ SOLUTION 10 Strong Acid 11 -LOG(Kw) Root'x Net [H+-] K. g-equiv. Na2B,00, Borate Bol c AAcid pK, pH t 2 g'ons/ler 14 Net [-+- V 9-moos -equiv. 9UiV iog, 0K. 13 1.399E+0' -6.1360E.-1 5.0119E46 5300 5.8135E-t0C 2.4262E+01 6416.8 12809 51359 9.24 8.63 14 1.279E+01 5.4368E-06 3.8846E49 8.411 1.0669E45 1.8805E42 6416.8 12834 51334 8.97 8.37 15 1.279E+01 1.1989E-05 1.7953E49 8.746 1.0669E 8909E43 6416.8, 12834 51334 8.97 8.37 16 1.279E+01 1.2309E-05 17653E49 8.753 1.0669E9 8.5458E03 6416. 1 2 8 3 4 51334 8.97 8.37 17 1.280E+01 1.4755E5.7698E09, 8.752 1.0616E-091 8.5676E43' 6416.8i2834 51334 8.97 8.37 18 1.284E+01 2.2603E-05 1.7573E-09 8.755 1.0406E 9j 8.5071E-03 6416.8 12834 51334 8.98 8.38 19 1.292E+0' 3.8076E-05 1.8140E-09 8741 1.0037E49, 8.7813E 616.8 1283 51334 9.00 8.40 20 1.295E+01 4.6435E-05 1.9133E49 8.718 9.8734E.10 9.2620E-0 641. 12834 51334 9.01 8.40 21 1.298E+01 5.2967E-05 2.0264E-09 8.693 97506E-10 9.898E-03 6416.8 12834 51334 9.01 8.41 22 1.304E+01 7.1382E-05 2 E7173E.9 8.566 9.4639E-10 154E-02 6416.8 12834 51334 9.02 8.42 23 1.308E+01 8.4432E405l4.0825E.9 8.389 9.2943E.10 1.9763E-02 6416.8 12834 51334 9.03 8.43 24 1.311E+01 9.4943E5-7.9048E-09 8.102 9.1714E-103i 66E-0 6416.8 12834 51334 9.04 8.441 25 1.313E+01 1.0382E.04 7.4496E-08 7.128 9.0778E-1 3.6063E-01 6416.8 12833 51335 9.04 8.44 26 1.315E+01 1.0480E-04 8.7215E-06 5.059 8.9901E-10 4.2220E+01 6416.8 12791 51376 9.05 8.44 27 1 E0 4.655 8.8672E-1I 1.0703E+02 6416.8 12727 51441 9.05 8.45 28 1.320E+01 1.0481E404 3.1080E-05 4.508 8.7912E.10 1.5045E+02 6416.8 12683 51485 9.06 8.45 29 1.322E+01 1.0481E404 4.2457E405 4.372 8.6976E.1l 2.0553E+02 6418.8 12628 51540 9.06 8.45 30 1.3245;01 1.0481E-04 5.19904-05 4.284 8.621SE-1l 2.5t68E+02 6416.8 12582 51586 9.06 8.45 31 1.325E+01 1.0481E-04 5.7578E-0 4.240 8.5806E-.10 2.7873E+02 6416.8 12555 51613 9.07 8.45 32 1.326E+01 1.0481E-04 6.7392E-05 4.171 8.5045E-.1 3.2624E+0: 6416.8 12507 51660 9.07 8.45 33 1.329E+01 1.0481E-04 7.9730E-05 4.098 8.4109E-1 3.8596E+0 6416.8. i2448 51720 9.08 8.461 34 1.330E+01 1.04815E4 8.8596E-05 4.053 8.3466E.1 4.2888E+02 6416.8 12405 51763 9.08 8.46 35 1.331E+01 1.0481E44 9.0259E51 4.045 8.3349E-10 4.3693E+ 6416.8 12397 51771 9.08 8.46 37 38 39 4 1 42 43 45 46 478

lllll

LM-642. Rev. 1. Attachment E. Page E-2 of E-7

GRAND GULF REFERENCE CALCULATION A I B C D E F G H 1 CASE I GRAND GULF REFERE pH TRANSIENT 2 Linear Absorption Coeffci 3 VpooL =170954-28.3168 Liters [Min.Tech Spec Basis Ube_ at 0.0198 4 ml =325 Iodine Inventory [g-atoms Ubems hyo,, 52.08 5 mc, =2400 Cesum Inventory [g-astomsl Ua_ ar_ 0.0000375 6 tm =12113600 Onset of Gap release [hrs] 1.1w hypabn 0.099 7 1112.5 8 r W__ 1384 9 INTEGRATED DOSES 10 Beta+Gamma Gamma Beta Gamma Beta 11 TIME POOLTemp POOL DRYWELL-A DRYWELL-A DRYWELL-B DRYWELL-B [Hq 12 Hours Deg F Mrad MeV/rcm? MeV/crnm MeV/rm' MeV/rm' g-mols/ilRer 130 77 0 141 160

• SBS4/(120-SBS3)'(SA14-0.5+SBS6)tS$B4i/(400SBS3_

152 160 1.3783 1420000000000 2873300000000 0 1122000000000 =$SBS4/(t20-SBS3)(SA150.5+$SBS6)).SBS4/(400-SBS3L 16 =0.541.S+B6 160 1.3792 1450600000000 2878400000000T0 1214800000000 SBS4/(120-SBS3)-(SAI 6-0.5+SBS6))+SBS4/(400-S8S3) 17 3 159.1 1.4049 2163000000000 3023500000000 66925000000 1290800000000 HSt16 185 t555 1.4581 3099100000000 _3208000000 6467100000 1446800000000 =HSt6 19 12 149.2 1.6425 4703200000000 4331200000000 1640400000000 1978900000000 -H$16 20 18 146.4 1.7985 5446200000000 5160900000000 2100600000000 2418300000000 =HS16 21 24 144.3 1.9526 5973300000000 5958400000000 2427100000000 2843000000000

• HS16 22 48 139.4 2.5509 7243400000000 8850300000000 3213800000000 4403800000000

=HSI6 23 72 136.5 3.1213 7986300000000 1131t9000000000 3674000000000 5764900000000 =HSt6 24 96 134.4 3.6648 8513500000000 13425000000000 4000500000000 6952100000000 =HS16 25 120 132.8 4.183 8922400000000 15224000000000 4253800000000 7987400000000 =HS16 26 150 131.3 4.7966 9331200000000 17105000000000 4507100000000 9097500000000 =HS16 27 200 129.2 5.7409 9858400000000 19521000000000 48336000000000 10574000000000 =HS16 28 240 127.9 6.4313 10192000000000 20955000000000 5040500000000 11486000000000

• HS16 29 300 126.3 7.3686 10601000000000 22506000000000 5293800000000 12519000000000

=HS16 30 360 125 8.1999 10935000000000 23551000000000 5500700000000 13252000000000 _H$16 31 400 124.3 8.7011 11`128000000000 24049000000000 5620300000000 13618000000000 =H$16 32 480 123 9.5911 11463000000000 24727000000000 5827200000000 14143000000000 =HSI6 33 600 121.4 10.685 11871000000000 25259000000000 6080500000000 14592000000000 =HS16 34 700 120.3 11.417 12154000000000 25472000000000 6255500000000 14791000000000 =HSI6 35 720 120.1 11.546 12205000000000 25500000000000 !6287500000000 14819000000000 =HS 16 36 _t 37 NOTES 38 1 Eentrgy Eng. Report GG I 14 39 2 Ibid. Equation 3-2b 15 403 Ibid Equation 3-4d 30+ 414 Ibid. Table A-I 42 5 Ibid. Equaton 3-3a: Ent_ 43 6 Ibid, Equation 3-3b; Ent 44 7 Ibid. Equation35a-Ent 45 8 Ibid. Equation 3-5b: Ent_ 46 9 Ibid. Equation 3-Oa:_Ent_ 47 10 Ibid, Equation 3-5d: Ent_ 48 11 Ibid, Equation 3-5d: Ent_ 49 12 Ibid. Equation 3-Se: EntI 50 13 Entergy Calc. XC-111 LM-W42. Rev. 1t Attachment E. Page E-3 of E-7

GRAND GULF REFERENCE CALCULATION IJK L 2 LA V" flb]87365 KCable Length (trays]- Zone A 3 1 1cm LA?. hblb873.65 Cable Length (free air]- Zone A 4 1/cm ey Vib) 14049.27 Cable Length [Itrays] - Zone B 5 11cm Let, h b] 1561.03 Cable Length (free air) - Zone B 6 1/cm Ro (cm2 /ib 800 Cable Area 7 cm th (cm] *0.28-2.54 Hypalon Jacket Thickness " 8 rrn 9 CONCENTRATIONS 10 From Beta From Gamma From Beta 11 (HNOA] 2 JHCLI-A 5 [HCL]-A ' (HCL]-B - 12 g-mostter g-ml&iiter g-mosniter g-molsitter 14 15 =0.0000073-SC15 =3.512E-20tSBS3-$KS6-($KS2124SK3YSHS3 SE15

• 3.512E-20tS8S3'SKS6-(SKS2+SKS3) 1-EXP(-SESS HSf) SH$S(1.EXP(.SHS6-SKS7)rSD15
• 3.512E-20/SBS3$SKS6 (SKS4/2+$KSYSHS3 SG15 16 =0.0000073-SC16_

=3.512E2015 SK$6(KS212+SK3HS3'SE6 3.512ES S3$SKS67SKS2+SKS3$EXP(-SHSSSHS 1-EXP($SHS6$SKS'$D16 =3.512E-20/SBS3 SKS6c(SKS412.SKsSYsHs3 SG16 17 .0000073-SC17 $3.512E20ISBS3VSKS6( KS2K2.SKS3YSHS3SE17 --3512E-20SBS3KS86(SKS2+SKS3)H(1-EXP(-H H H S6SKS7)S17 =3.512E-20ISBS3*SKS6BSK$2Q S SySHS3SG17 18 =0.0000073SC18 =3'.512E-20/SBSV3SKS6-(SKS2I2+$K3ySHS3 SE18

• 3.512E-20/SBS3$SKS(SKS2+SKS3)(1.EXP(.SH$5SHSys$H$S5(1.EXP(.SHS6-SKS7))-SD18
• 3.512E-20/SBS3$SKS6-(SK$42+SKSSSHS3SSG18 19 =0.0000073SC19 33512E-20$BS3-SK$§SKS2I2+SKS3ySHS3SE199
• 3.512E-20SBS3-SKS6-(SK2+$KS3)(1-EXP[(-HS$SHS7)y$s5- (-EXP -SHS6-SKSDtD19 =3.512E-201SBS3 SK56SKS4/2+$KSSyHS3 SG19 20 *0.0000073-SC20

=3.512E-201$BS3SKS6 (SKS2SKS3YSHS3SE20 =3.512E-201SBS3'SKSSKS2+KS3) (1-EXP(-SHS$SHS7)Y$HS5'(1-ExP(-SHS6 SKS7))'DO20 =3.512E-20/SBS3-SKS6 ($KS4/2+KSSy$HS3 SG20 21 =0.0000073-SC21 =3.512E-201SBS3SK5$§KS212+SKS3YSHS3 SE21

• 3.512E-20/SBS3$SKSU$KS2+$KS3)(EX--SH$51-HSlySHs5'(1-EXP(-SHS6-SKS7))$D21
• 3.512E-2OSBS3-SKS6'(SKS4/i+SK$5ySHS3-SG21 22 =0.0000073-SC22_ =3.512E-201BS3KS6(K2+SKS3ySHS3-SE22

=3.512E-20/SBS3$K6($KS2+SKS3)'(1-EXP(- H5 S f$lHS51(XPCSHSI6SKS7))D022 =3.512E.20SBS3$KS6($KS42+$KS5y HS3-SG22 23 0.0000073SC23 -3.512E-20/SBS3$KS(SKS2l24SKS3Y$HS3 SE23 =3.512E-20/$BS3-SKS6-(SKS2+$K$3)r(1-EXP(-SHS5$HS7)YSHS5(1-EXP(-SHS6SKSl)r5D23 =3.512E-201SBS3$SKS6'(SKS42+$KS~y HS3-SG23 24 =0.0000073-SC24

• 3.512E-20SBS3-SKS6-KS2/2+5KS3YSHS3E24
• 3.512E-20$SBS3SKSmSKS2S+KS3y(1EXP-SHS SHS~ySHS-(1EXP(.SHS6SKS7))-$D24
• 3.512E-201SBS3 SKS6 (SKS4/2+$SSySHS3-SG24 25 =0.0000073-SC25

=3.512E-20ISBS3-SKS6 2+SKS3YSHS3SE25 =3.512E-201/BS3 SKS6 (SKSi SKS -SHSSSHS~ySHlS(1-E -(SHS6 KSZ)SD25 =3.512E-20/SBS3SSSKS412+$KS5y$HS3SG25 28 =0.0000073-SC26 =3.51i2E201SBS3 SKS6 ($K$2n+K$3y$H$3$E26

• 3.512E-201S8S3'SK6-(SKS2_K$3)-(1-EXP(SHS5$SHS7)YSH$S5-(1-EXP(-SHS6 KS7)rSD26

=3.512E-20ISB$3-SKS6 (SKS4q+$KS5ySHS3 SG26 27 -0.0000073-SC27

• 3.51 2E-20SS3-SKSSKS2/2.SKS3ysH_3-SE27

=3.512E-201SBS3$SKS6-(SKS2+SKS3)-EXP-SHS5$SHS7IySHSSXP(.HS6-SKS7)-D27

• 3.512E-20/SBS3SKS6-(SKS4I2+SKS5ySHS3SG27 28 0.0000073SC28

=3.5122E-20SBS3-SKS6(SKS22+SK$3_SHS3SE28 --3.512E.20IS8S3SKS6SKS2SKS3)(¶-EXP(-SHSSSHS7)YSHSS'(1-EXP(-SHS6$SKS7)SD28 =3.512E-201$BS3KSSKS4I2+SKS$ySHS3 G28 29 =0.0000073-SC29

• 3.512E-20/SBS3 SKS6(SKS2IsKS3YSHS3E9
• 3.512E-20/SBS3$SKS6-(SKS2+KS3)

-EXP SH$!KSHSi/SHS- )P-SHS6HSKS ))D29 =3.512E-201SBS3-SKS'SKS4"K S S2yX $t SG29 30 =0.0000073-SC3Q *3.512E-201SBS3-SKS6(SKS2I2.SKS3ys_53-SE3O _S 2_-205SBS3-k (SKS2+S3)(1.EXP(-SHSSHSflySHSS-(1-EXP(SHS6-SSo~o

• 3.512E-20SBS3SKS6-(SKS412.SKSYSHS3SG30 31 *0.00 00073-SC31

=3.51 2E-20/BS3-SKSSKS2I2.$K$ SSj3-SE31 =3.51 2E-20lSB$3-SKS6-(SKS2.5KS3)-(1-EP(-HSSSyHE-X(SS-K~5 =3.51 2E-2OISB ____

• SS4+KS5SH$H3-SG31 32 =0.0000073-SC32
• 3.512E-20/SBS3 SKStSKS22.SKS3ySHS3 SE32
• 3.512E-20/SBS3'SKS6'($K$24KS3)r(1-EXPtSHS5-SHS7)YSH$5(1-EXP(-SHS6-SKS7))SD32

=3.512E-20/$BS3$SKS(SKS4/2.SKS5ySHS3SG32 33 -0D00000731S33 =3.512E-20 BS3SKS6(SKS SKS3y HS3-E33 =3.512E-Ki$SBS3KSKS6(SKS2+SKS3n1$E$P(-$SHSS HS7)ysH55(1BE3$SHS6-SKS3K3(033 -3.512E-20/SBS3SKS6 (SK$472SKSy H53 SG33 34

• 0.0000073SC34

=3.512E-20/SBS3'SSK6-SKS2*$SKS3ySHS3 SE34 =3.512E.20/$B$3'SKS6-(SKS24SK$3)-(1-EXP(-SHSS$HS7)ySHS (- HS6-SKS7))SD3 -3 512E-201SBS3SKS6 (SKS412+SKSSySHS3SG34 35 =0.0000073SC35

• 3.512E-20/SBS3-SKS6-(SKS2/+SKS3ys_53-SE35
• 3.512E-20ISBS3-SKS6-(SKS2+SKS3)(1-EXP(-SHSS-HS7)ySHS S S6SKSfSD3s

=3.51 2E-20ISBS3-SK $KS42.+SKSSYHS3-SG35 36 37 38 Acid dissociationn rconst 39 EnergyCalc. XC-Q11 40 41 42 43 44 446_ 47 48 4 79 _ _ _ _ _ _ _ _ _ 4 8s o_ LM-0642. Rev. 1, Attachment E. Page E-4 of E-7

GRAND GULF REFERENCE CALCULATION M [ N l 0 1 2 3 4 5 6 7 8 9 10 From Gamma 11 [HCLj Total [H+I (CsOH] 12 g-9olsditer g-ons/liter g-mols/flter 13 =POWER(10,-STS13)+$H13+SI13+SJ13+SK13+SL13+SM13 0 14 =POWER(10,-STS13)SH14+$114+SJ14.SK14+$L14+$M14 =(0A4-SBS5-0.475-BS4y(3-B 3r)5A14-(0:S+SBS6))+(O.05$SB$5-0. 0475 B$4ySBS3 15 =3 512E-20/$B$3-SK$6S(SK14+1K5JSI-EXP(-5HS5SH$8)y$H$5 (1-EXP(-$H$6-SK$7)r$Fl5 k(10, $f$13)+5H15+$115+5J15+5K15+5L15+$ISP =(0.4-SBS5-0.475SBS4y(3$BS3)-(SA15 0.5+S B6))+(0.05-SBS5-0.0475-SBS4SBS3 16 *3.512E-20/SBS3-SKS6-(SKS4+SKSR( EXPt-SHS5SHS8)y$HS-(1EXF *HS6-KS) 7)SF16 =POWER(10.-STS13)+SHl6+S116+SJ16+SK16+SLl6SM16 (0.4-SBSS0.475$BS4V(3-SBS3)-(SA16-0.5.$S6))+(0.05-BS5-0.0475-SBS4y$BS3 17 =3.512E.20/$B$3-$KS(SKS4+SKS5)'(1-EXP(-SHS5SHS8)"H 5(1.EXP -SHS6 SKS7))-5F17 =POWER(10-STS13)+5H17 117+SJ1$7+SK17+SL17+SM17 -SOS16 18 =3.512Ei20/SBS3SKS6-(SKS4+SKS51 EXP-SH SHS)y$H$S5(1-EXP(-SHS6-SKS7iSF18 -POWER(_LSTS13)+SH18+SI18+SJ18+SK18+SL18+SM18 =S0S16 19.3.512E-20/$BS3$SKS6(SK$4+SKS5)(1-EXP(-HS5SHS8)y$Hs5 1EXP(-SHS6 SKS)SF19 =POWER(10,-STS13$SH19+SI19+SJ19+SK19+SL19+SM19 =S0S16 20 -3.512E-20l$BS3-SKS6nSKS4+SKS5)(1-EXP(-SHS5SH 8)ySHS5(1-EXPfLHS6SKS7L$F20 =POWER(10.-STS13)+SH20+SI20)+SJ20+SK20+.SL20SM20 -S0S16 21 =3.512E:20$SB$3$SKSgS$S4SKS5)'(1-EXP(-4HS5SHS8)ySHS5C(1-EXP(-4HS6-SKSWrSF21 -POWER(10.-STS13)j+H21+S121+SJ21+SK21+SL21+SM21 -SOS16 22 .36512E-20ISBS3-SKS6-(SKS4S+KS5)1-EXP sHS5 SHS8)y$H$S-EXP(-SHS6-SKS7))SF22 =POWER(10,STS13SH22+W122+ J22+$K22+.L22+$M22 -SOS16 23 =3.512E.20/$BS3 SKS6-(SKS4+sKS5)C(1-EXP(-SH$S5SHS8) Y$H5-(-EXP(-SHS6SKS7)) SF23 =POWER(10,-STS13)+SH23+S123+SJ23+SK23+SL3+SM23 -SO$16 24 -3.512E-20/SBS3-SKS86(SKS4+SKSS)1 -EXP-SHS5SSHS8))yHS S-EXPSHS6SKS)t~SF24 =POWER(10,5TS1T3)+SHN4$124+SI J24+SK24+SUL4+SM24 =SO516 25 ;3512E-201$B$Z-SKnSS S=SS)-1-EXP(-SHSS SH$8)y $5-(IEXP HS63W)rSF25 =POWER10,-9STS13)+$H25+$125+$J25+$K25+$L25+SM25 =SOS16 26 =3.512E-20$9S3$SKS6'(SK$4+SKS5r(1 -EXP(-SHS5SHS8))YSHS (1-EXPt SHS6 KSDF2 POWER(10,-STS13)+$H26+$126+SJ26+SK26+$L26+SM26 =50516 27 =3.512E-20SBS3-SKS6SKS4 SKS5)(1.EXP(.SHS-SHS8)ySHS5(1.EXP(-SHS6-S ISLSF2M =POWER(0.-STS1 3)+5H27+5127+.J27+5K27+5-27+5M27 =50516 28.3.512E-20/SBS3-SKS6$(5KS4+SKS-( (SHS5SHS8)yDHS5(1.EXP(-SHS6'SKS7)rSF28 =POWER(10.-STS13)+SH28+St28+SJ28+SK28+SL28+SM28 =SO16 29 =3.512E.20BSSK$6-($KS4+SKS5)-(1-EXP(-SHS5SHS8)YSHS5 (1-EXP(-SHS6-SKS7))SF29 -POWER 1,STS131+$H29+129.SJ29+$K29+$L29+SM29 =SO16 30 -3.512E-20/SBS3-SKS6(SKS4+SKS5r(I-EXP(- HSSSHS8)Y$HS5-1-EXP(-$HS6SKSfL7SF30 =POWER(10,-STS13)+SH30+SI30+SJ30+SK30+SL30+SM30 =50516 31 =3 512E-20/SBS3 SKS6-(SKS4+$KSS(-EXP - HS5SH -EXP(.$H$6-K$7)'SF31 =POWER(10,-STS13)SH31+SI31+SJ31 +SK31+SL31+SM31 =S016 32 3 2E.2_S3SS S5K54 S)(1-EXP(-SLHS 5 8)yS Q5(1.EXP(:SSH6WSKS7))-SE32 --POWER(10,STS13)+SH32+S132+SJ32+SK32+SL32+SM32 S0S16 33 =3.512E-20/$B$3'$K$6-($K$5K$5)(1-EXP( SHSSKSHS8)V5H5(1*EXP(-SHS6SKS7))-SF33 =POWER(10.-STS13)+SH33+SI334SJ33+SK33+SL3+SM33 =-016 34 =3.51 2E120/SBS3SKS6-(SKS4+SK5K (-EXPtCSHS$5SH$8)y$HS5-(1.EXP(-SHS6-SKS7DJF34 POWER(1 0.-STS13LSH34+$134+SJ34+SK34+$L34+$M34 =S016 35 =3.512E-2015$53SK5(SK6_4!+K5r)(1-EXP(-$H$555HS8)YSHS5'(1-EXP(-SHS6-SKS7))-SF35 =POWER(1T 3 1 U 1 5 5$ M 50516 36 38 39 40 41 42 43 45 46 47 48 49 50 LMW0642, Rev. 1, Attadcment E, Page E-5 of E-7

GRAND GULF REFERENCE CALCULATION P a R I s I T i U 2 SLC rbs) 5800 Na2BO,010H20 Added [MW-A410] 3 4 6 7 8 pH EFFECT OF ADDITION OF SODIU 190 11 Total [OH+] -LOG(Kw) Root x Net pH 12 g-onsfiter g-nsfiter Id 13 -POWER(10,-14yPOWER!(STS13).SO1 3 =15.5129-.0 224-SB 3+0.00003352-POWER(B1 3,2L =(N1 3+P13-SQRT(POWE(SN13+5P1 3).2X.(N1 3-P13-POWER(1 0.-S013))))y2 =$N 13SR13 5.3 =(0.0585B13+.1.309y10000000000 14 LPOWER( .-14 OWER(10,-$TS13) SO14 =15.5129-0.0224S814+0.00003352-PWER(814,2_ =(N14+P14-SORT(POWER((SN14+$P14).2 N4P14-POWER{10.-S014))))Y2 =SN14-SRI4 -LOG1O(SS14) -(0.05SB1E41.309y1o00oooooo_ 15 =POWER(10,.14yPOWER(1o.-sTs13)so15 =15.5129-0.0224'$315+0.00003352POWER(B15.2) =(N1J15P-SORT( POWER((SNis+SP15.2):(4j(NIs 5P5POWER(10-sO15))))y2 SN1 5-SRiS 5 -LOG1O(SS1 5( 0.0585B1+ 51.309 0000000000 16 zPOWER(0.-14yPOwER(10 -STS13)+O1 6 *15.5129-0.0224'SB16+0.00003352-POWER(B1 6.2) =(N16+P16.SQRT(PoWER (sN16+sP16).2)4(N16 PI6 POWER(1O-sQ16))))y2 -SN=6$SR1 6 =-LOGi(516 =(.00585 B1t61.309y10000oooo 17 *POWER(10,.14yPOWERf19.-STS3)+5017 =15.51290.0224SB17+0.00003352POWER(B1i7,2) =(N17.P17-sRT(POWE ((sN17+SP17),2M4(N17P17-POWER(o,-sa7))))2_ -SN17-R OGI(57 =(.0585B17+1.309y00000000 18 =POWER(Lo..14YPOWER(10,-sTs13)+s018 z 5.5129-0.0224-SBI8+000003352-POWER(B18,2) = Ni 8+P1 8-S0RT(P BR((s$ =Pi.2$4N15-P9WER(10 Sal8)))$2 SNI8=R18 =.LOGI OssI8 f(058-B1 .309yo00000o __ 19 =POWER(10.-14iPYowER(1 0,-STS 13)S019 =15.5129M.0224SB19+0.00003352POWEB19.2) =(N19+P19-sORT(PoWER(($N19+sPl9).2 4-(4N19P19.POWER(19$-01 9)))y)2 SN19-SRI9 SOG1O SS19)

• 0.0585B1 9+1.309y10000000000 20 =POWER( 0,-14ypowER(1i0-sTs13L)SO2

=15.5129-0.0224SB20+0.00003352'POWER(B20,2)_ (N20+P20 SORT(POWER((sN20+SP20).2H4(N20 P20-POWER(10 S-20)))))2 -SN20-SR20 =-LOGIO($S20 =(o0_85B2041309y_000 ooo 21 -POWER(10Or14ypowER(1.-sTsI3)+s021 =5512,9.0224$21+.0.00003352'POWER(B21,2) =(N21 +P21-SORT(PowER((sN2I+P21).2H4-(N21vP21-POWER(1o-$02 )))Y2 =SN21-SR21 s 2 =(s0.0585B21+ 1.309Y10000D0000 22 rPOWER(1o0.14yPOwER(10,-STS13)'022

• 15.5129-0.0224' 122+0.00003352-POWER(822,24 N22+P22-SORT POWER((sN22+sP22).2)-((N22.P22.POWER(9.-S022))))y2
• SN22-SR22

-LOG10SS22 =0.05858B22+1.309y10000000000 2 =POWER(10,.14y OWER(10-STSi3)1+023 =5.5129o.o2241823+0.00003352POWEBR(23L2) =(N23+P2 T(P WE 3SN23+SP23)M2 N23

3POWER(10,-SQ23)))Y2 SN23-5R23

-LOG10($S23 =(0.0585B23+1.309y10000000000 24 =POWER(10..14yPOWER(10o-STS13)+5024 =i5.5129-0.0224S824+0.00003352'POWER(824,2) =(N24+P24-S0RT{P!WER((SN244SP24) 20I(N24P24-POWER(1_024))))y2 sN2_4SR24 -LOGIO(SS24 =(.0585-B24+1.309Y10000000000 25 1POWER( 1014 YOWER10,.STS13 O25 15.51290.0224S825+.00003352-POWER(B25.2) (N25+P25-SORT(PwER(($N25+SP25).2X4(N25P25-POWER(10 -5025))))y2 =SN2-SR25 t -OG1OS(2S5)

• (0.05856B25+1.309Y10000000000 26 =POWER(10,-14YPOWER(I0.-STS13)+S026

=15.5129-.0224-SB26+0.00003352-POWEVB26,2= =(N26+P26.SRT(POWER((sN26+sP26)L2) 4(26-P26 oWER(j0-.S26)))))f2 =SN26-5R26 LOGIo(5S26 (0.05856B26+1.309y10000000000 27 =POWER(10,-14yPOWER(1i0-sTs13)+s027 =15.5129-0.022415827+0.00003352POWER(B272) -(N27.P27-SOT E`WER((sN27+sP27).2H4(N2rP274POWER(1 0 S2Z))))2 -SN27-SR27 =-LOGI S2L =(0.0585-B27+1.309yl000000000 28 *POWER( 10-14YPOWER(0,-STS13)+s028

• 15.5129-o.0224-SB28+0.00003352POWER(28.2)

=(N284P28-SORT(POWER((sN28+sP28).2H4(N28 P28-POWER(1i0-$028))))y2 =SN28-SR28 -LOG1O(SS28 = 0.0585828+.309Y10000000000 29 =BPOW ER(10,14ypowER(1o-sTS13+SO29 =15.5129002241629+*0.00335P0wER(929.2L =( N79+P29_ ORT(POWEN(SN29+ S29),242N29P29-POWER(I0,-os0 )))Y2 =SN295R29 j_ OG1( SS29) 005856B29+1.309y100000B0 30 =POWER(10..14YPOwER(10.-STS13)+s030 =15.5129-0.0224-SB30+0.00003352-POWER(B30,2) =(N30.P30oSRT(POWER((sN30+sP30),2X4(N30P30-POWER(1 o-s030))))y2 -SN30-SR30 =-LOG1O(5S30) =.0585;B30+1.309y10000000000 31 =POWER(10..14YPO/ER(10,-STS13)+5031 =15.5129o.0224-sB31+0.00003352'POWE(312_ L(N31+P31-SORT(POWER((sN31+sp3j.2X4-(N31P31*POWER(10.-s031))))y2

• SN31-5R31

-LOG10(SS3i ( 0.0585B31+1.309y10000000000 32 =POWER( 0.-14YPOwER(10.-sTs13)+so32 =15.5129.0224 $B32+0.00003352 POWER(B32.2) =(N32+P32-sORT(POWER((sN32+SP32y2XN32P32-POWER(io-sQ32))))y2 =SN32-SR32 _LoG10(5S32 2(0.0585-B32+1.309y100000000 33 =POWER(10,-14yPOWER(10.-STS13)+033 =15.5129-0.0224SB33.0.00003352-POWER(B33,2) =(N33+P33-SQRT(POWER(($N33$SP33),2X4(N33P33-Er(10033))))Y2 =SN335R33 =LOG 10 -S3 (0.0585B33+1.309y100000000oo 34 sPOWER(s0.-14yPOWER(t0.-$T513)+so34 15s51294 0224-S34+*0.00003352-POWER(B34,2) ON34+P34-S`RTowER((SN34+SP34).2H:4(N34 P34-POWER(10,4034))))y2 -SN34-SR34 -LOG1 tSS34 = 0.0585B34+1.309Y10000000000 35 14POWER(1 -sT=13);SO35 -15.5129-0.0224 $B35+0.00003352'POWER(B35,2) =(N35+P35-SR(OWER( P (SP3.-POWER(10,-O 35))))R SN3s-SR35 L s(o0585 37 39 40 4-2 43 44 45 46 48 50 LM-062, Rev. 1, Attachment E. Page E4 of E-7

GRAND GULF REFERENCE CALCULATION v i w I___ z AAM 3 4 10 Strn g Acdd 1 1 g-equiv. Na2B40,10H20 Borate Botic Add pK. pH 12 Net (H+J VpooL. g-mols g-equiv. g-equik 4Iog,0K. 13-1SS3

• 0S2'453.61410

-WI 32V3 W38V -401(U3 zZ13+LOGIO((X31$B$3y(YI3ISBS3) 14 =S14$8S3 =SOS2'453.61410 *Wl4'2-Vl4 *Wl4'8+V14 -LOG1O(LL14)_=214.ILOGIO((XI4I$B$3y(Y14l$B$3)) 15_ ;s1,5S8S3 40SF$4537.6)410 =Wl152.-V15 =Wl5'8.V15 -tOGI Ul5) *Zl5.LOG10 Xl5/B$3y(YlBS3)) 16 ~S B3 =SQS2'453.61410 =W 162-Vl 6 =W6168+V16 =-LOG!0o(U1B) =1LG ( 616/SBSy(Y16l$MS3)) 17 =S17S2S$3 =S0S2-453.61410 TW17r2-V1 =W17;8+V17 ~-LOG10(U17 f217.LOG10O((X17I$B$3y(a17ISBS3)) 1-8 -s-18S$BS3 =SQ$2'453.61410 =W18'2-Vl8 -Wl8'8+V18.-LOGI10U 8) fZ18+OGIOQ(XI8/$MSyfY18$83)) 19.S195$8S3

$S0S2453.61410 =W912-VI9 =Wl9'8.Vlg =.OGIOLjU19

-Z19.LOG10 (X19/SB$3yoY19/SB$3)j 20 =S2SB3 SO2-453.6/410 =W20'2-V20 =W20'8+/-.V2Q f-LO:nlO(U201 =Z2Q+LQOG10((X20I/S3yYf20/$B$S) 21 =S21PSB$3 S025.6/410 W2V-V21 *21'8+V21. -LOG10 U21 =Z21+LOG10 ((X2/sSMY(Y2 ISBS3)) 22 *S22S6S$3 =$OS2'453.6/410 =W22'2-V22 =W22'8.V22 -LOGIO(U22) *Z22.LOGIO((X22/SB$3y(Y22/SB$3)1 23 =S23S9S$3 s$SFS45i.6I410 =W -V23 =W23'8+V23 -LOGIO(U23) =Z23+LOGIO((X231$ $ yff3ISBS)l 274 ~S4 3 =$0S2'453.61410 sW2412-V24 *WV2418+V24 -LOG10 U24) =2+O1((X24/S8S3YM2SB$3)j 25 Pt515 =$5 3.61410 I W22-5 ~W5.2 LGIO(U251 *Z25+LOG10 (X25/$B$3y(Y25/S83)) 26 =S26S$B$3 .S0S2453.6/410 -=W2612-V26 -W226'8+V26 =-LOG1 (U26 I=Z26.LOG10 (X2615B$3y(Y26tSBS3)) 27 =S275$BS3 =S0S2453.6/410 *W2r2-V27.WV2ra.V27 =-LOGI9 2U7 =ZZ7+LO'i0l(x7/$8$3yff2l/$BS3)) 28 1.S28S6S$3 $0S2'453.6/410 =W2812-V28 =Wi28'8*V28 O1 2 Z28+LOG10 X281SBS3yY8/$BS3] 29=S29S6S$3

• O$QWJSP45.6410

=W29g2-V29 --W29'8+V29 -L~0U9 Z29+LG0( 9B3 ( JBS3) 30 S30S8S3 -=S02?453.6/410 =WV30'2-V30 =W30'8+V30 -LOGIO3U30) 31 =S31VSBS3 =S0S2F453 40=W3112-V31 =W31V8+V31 fp0G0(31 t"3 +OG0(X3$BL3YAY31ISBS3)j 32 =S32S$BS .$0S2453.61410 =W3212-V32 =W32 8+V32 -L 10(U3)=3+OI(X23$yY2SS) 33 S33S8S =$0S2'453.61410 -W33'2-V33 -W33'8.V33 =-OI(U3 Z33+LOGIO((X33/$BS3y(Y33ISS3)) 34 S34SB$3 $0S2'453.6/410 I=W3412-V34 =W34'8.V34 ~-OI(3 Z4LG0(X34 4IS 8Y4$S3)) 35 =S35S8S$3 SO25.41 W5-3 W 8V35 ~-LOGI0(LU35) =Z35+LOG10 (X35ISBS$ Y35SY 3) 36 =$__0_2_453__6 410____ W35__2_V35_=W35__8_V___5__B_3 3 7 38 43 _ _ _ _ _ _ _ 44 _ _ _ _ _ _ _ 4 5 46 47 48 49 50 LM-642. Rev. 1, Attachment E. Page E.7 of E.7

Calc. LM-0642, Rev. 0, Attachment F: GGNS-98-0039, Rev. 3, "Entergy Operations Engineering Report for Suppression Pool pH and Iodine Re-Evolution Methodology" 12/20/00 (Grand Gulf Nuclear Station) 30 Pages LM-0642, Rev. 0, Attachment F Page F-I of F-30

Engineering Report No.: GGNS-98-0039 Rev. 3 Page 1 of 22 ENTERGY OPERATIONS Engineering Report For SUPPRESSION POOL PH AND IODINE RE-EVOLUTION METHODOLOGY I-ANO Unit 1: 0 ANO Unit 2: 0 APPLICABLE SITES GGNS: 0 RBS: 0 W-3: 0 ECH: 0 Safety Related: X Yes No Prepared by3\\ E s iTe J 1espons'Ne Engineer Reviewed by: Re(vb/b9ei9-er Reviewed by-a. Os Date: kZ oZ*(0-Date: X r/o/o Date:,Z A/20/6 Supervisor/Reviewer Approved by: A'/A Responsible CDE Manager (for multiple site reports only) Date: LM-0642, Rev. 0, Attachment F Page F-2 of F-30

E' Sine-artn;@- -. v~c.. I,~.: Page 2 cr 22 TABLE OF CONTENTS

1.0 INTRODUCTION

3

2.0 BACKGROUND

...................................,,,,,,,,,,,,,,.3 3.0 GGNS MODEL DESCRIPTION................................................................................ 4 3.1 Hydriodic Acid Production..................... 6 3.2 Nitric Acid Production...... 3.3 'Hydrochloric Acid Production........................ .,.8 3.4 Cesium Hydroxide Production............................... ..................... 10 3.5 Summary........ 12 4.0 SAMPLE PH CALCULATION. 13 5.0 IODINE RE-EVOLUTION.,,,,,, 15 5.1 Methodorogy.,................. is 5.2 Partition Coefficient...................................... 17 5.3 Governing Formula.............. 18 6.0 CONTROL STRATEGIES. 20 6.1 Standby Liquid Control. 20

7.0 REFERENCES

.22.............................................................................................. 22 ATTACHMENT 1 - SAMPLE PH CASE RESULTS APPENDIX A - HYDROCHLORIC ACID PRODUCTION MODEL LM-0642, Rev. 0, Attachment F Page F-3 of F-30

b

1.0 INTRODUCTION

Section 5.2 of NUREG-1465 [1j reports that the re-evoluticn of icdine can impac: the giant radiological analyses if the suppression pool pH drops belcw a value of 7. Specisicaily. fcr those BWRs that credit the long-term retention of iodine in the suppression poCl via sprays or pool scrubbing, NUREG-1465 suggests that the maintenance of a pH at cr abcve a level cf 7 should be demonstrated. Since BWRs generally do not have a requirement to contrcl Cos'- accident pool pH, the expected pcol pH transient has not been evaluated. This report develops a methodology for calculating the suppression pool pH transient using the available NRC research results. This methodology explicitly considers the acids and bases expected to be available in BWR containments under post-accident conditions. Revision 2 adds the temperature dependence of the water ionization constant and bases the hydrochloric acid production term on an energy flux approach. Revision 3 adds methodology for considering standby liquid control (sodium pentaborate) as a pH buffer. This methodology develops a reasonably bounding negative pH transient for application in radiological analyses in order to quantify (i) the timing requirements for pH control actions, (ii) the required inventories of pH control chemicals, and (iii) as input to the iodine re-evolution calculation in the event the pool pH is uncontrolled. In reality, the pool pH is not anticipated to experience this chemistry transient in the event of a recirculation line break since the EP actions directing operators to flood the containment with outside water sources would result ih the significant dilution of any acids in the suppression pool. Some background on pool pH issues is reported in Section 2. The GGNS model is developed in Section 3 and applied to a sample plant in Section 4. Section 5 develops a method for determining the amount of iodine re-evolution in the event the pool pH is calculated to drop below 7.0. Section 6 describes a pH control strategy while Section 7 lists the references applied in this report.

2.0 BACKGROUND

Unlike PWRs, BWRs currently do not have requirements to control post-accident suppression pool pH. PWRs include boric acid in the reactor coolant which introduces a negative pH transient at the onset of the accident and the PWR sump dose rates are an order of magnitude higher than in BWRs as reported in Section 2.2.4 of NUREG/CR-5950 [2] increasing the production rate of nitric acid (as discussed in Section 3.2). BWRs contain a much larger water inventory in the suppression pool since this volume is credited for condensation of the released reactor coolant, thereby suppressing the containment pressurization transient. As a result, the extent of iodine re-evolution can be significantly higher in PWRs. As illustrated in Figure 4.1 of NUREG/CR-5732 [3], an uncontrolled sump pH can result in the re-evolution of nearly 100% of the dissolved iodine in a PWR sump and as much as -25% in BWR suppression pools. This figure also illustrates that essentially no iodine is re-evolved if the pool pH is controlled. LM-0642, Rev. 0, Attachment F Page F-4 of F-30

4 E:n,irneering Pi=Pr'c.: (- - -i -3. -3 Th.-vis~cn No: 3 -age X of 22 3.0 GGNS MODEL DESCRIPTION Through basic chemistry relationships, the pH of a solution is directly related to the concentration of H' ions by the formulas: pH = -1og aH-D oH1]-g 1 2]= 9 (T) -logK,,(T) = 15.5129 -2.24E-2 *T+3.352E-5 *Ta2 (3-0a) where: . [Hj fis = concentration ofIf ions in moles per liter, = concentration of OH-ions in moles per liter, = ionization constant for water', and = pool temperature (0F) up to 212 OF The temperature dependence of the ionization constant is taken from associated curve fit is documented in the following table. Reference 7 and the Table 3-1 Water Ionization Constant Data Fit Temp ('C) Temp ( 0F) -LOG(K,) Data Fit 25 77 13.995 13.987 30 86 13.836 13.834 35 95 13.685 13.687 40 104 13.542 13.546 45 113. 13.40-5 13.410 50 122 13.275 _ 13.279 55 131 13.152 13.154 60 140 13.034 13.034 65 149 12.921 12.919 70 158 12.814 12.810 75 167 12.712 12.707 80 176 12.613 12.609 85 185 12.520 12.516 90 194 12.428 .12.429 95 203 12.345 12.347 100 212 12.265 12.271 A methodology to calculate the concentration of Ho ions in the suppression pool will be developed in this section. Equation 3-Oa can then be applied to determine the pool pH Value. I. Although the impact of pool temperature on the ionization constant Is small at the depressed pH values associated with iodine re-evolution, it's consideration is necessary to accurately characterize the pH values of alkaline solutions at elevated temperatures. LIM-0642, Rev. 0, Attachment F, Page 5 of 30

As discussed in Section 2 of NUREG/CR-5950. a variety of acids and bases are prcduced in containment during accidents. These chemicals are addressed individually belcw: Boric Acid is an acid introduced from the reactor coolant system, refueling water storage tanks, and containment sprays. These sources are not borated in BWRs and are consequently not considered in this methodology. Hydriodic Acid is a strong acid introduced into the containment with the release of iodine. As reported in Section 2.2.2 of NUREG/CR-5950 and Section 4.5 of NUREG-1465. no more than 5%8tO of the core iodine inventory is expected to be released from the RCS in this chemical fcrm. As such, the production of this acid is explicitly considered in this methodology. Carbon Dioxide depresses the pH of pure water by absorption. Carbonic acid is a weak acid and is expected to be insignificant compared to other acids produced in containment during an accident. However, the initial pool pH may be depressed below 7.0 during normal operations by the absorption of COO. As such, the effects of carbon dioxide will be considered in the initial condition assumed for pool pH. Nitric Acid is a strong acid produced by the irradiation of water and air during accidents. The production of this acid is explicitly considered in this methodology. Hydrochloric Acid is a strong acid produced by the radiolysis of chloride-bearing insulation during accidents. The production of this acid is explicitly considered in this methodology. The pyrolysis of chloride-bearing insulation produces HCI at temperatures near 572 0F (per Section 2.2.5.3 of NUREGICR-5950). Since drywell or containment temperatures above 330 OF are not postulated during accidents in BWRs, pyrolysis is not considered in this methodology. Cesium Hydroxide is a strong base introduced into the containment with the release of cesium. The production of this base is explicitly considered in this methodology. Core-Concrete Aerosols are basic materials produced from the interaction of the molten core materials with the concrete containment. Since SECY-94-302 [5] reports that the core damage may be assumed to be arrested after the in-vessel release phase, these chemicals are not considered in this methodology. LM-0642, Rev. 0, Attachment F Page F-6 of F-30

Ennerr

• ., 2.

3.1 Hydriodic Acid Production Iodine is released from the core as fuel failure occurs. Table 3.12 of NUREG-l46E indic-tes that 5%Mo of the core halogen inventory is released during the gap release phase.while an additional 25% is released during the early in-vessel phase. The core damage is assumed to be arrested after the in-vessel release phase in accordance with the NRC recommendation in SECY-94-302. Consistent with Section 4.5 of NUREG-1465, no more than 5%' of the iodine exiting the reactor coolant system will be composed of I and HI. This methcdolcgy will conservatively assume that all 5% of this release is in the form of HI in order to maximize the acid generation. This release process is assumed to occur at a constant rate over the release period (i.e., 30 and-90 minutes for the gap and early in-vessel release phases, respectively). The core iodine inventory includes the stable I'27.species to maximize the amount of acid produced. The following equations describe this release. d Hl= 005 0.5O i (Gap Release Phase) (3-1 a) dt VP.,0.5 h-r dHI 0.05 025 m, t V[H *]1.5 hr (Early In-Vessel Release Phase) (3-lb) where: m, = core iodine inventory (grarni-mols), and .VP" = volume of the suppression pool (liters). A conservatively small pool volume should be applied as generally used in the plant containment thermal-hydraulic analyses. In addition, any changes to the pool volume throughout the duration of the accident should be addressed such as losses due to humidity and ESF leakage and increases from the reactor coolant inventory and any expected pool water supplements. For example, at GGNS, the suppression pool makeup system would automatically transfer water from the upper containment pools into the suppression pool within 30 minutes in the event of a LOCA. This release can be integrated considering the 1/2-hour BWR gap release duration to yield the following equations during the gap and in-vessel release periods. ](t) 200V (t - t.,) (Gap Release Phase) (3-1c) I)=*t - (0.5 + t,)] 400. (Early in-Vessel Release Phase) where: t = time into accident (hrs), and tgap = onset of gap release (hrs). LM-0642, Rev. 0, Attachment F Page F-7 of F-30

i - !II:;;cn ANT:.; rP,;t ]Cl 7c 3.2 Nitric Acid Production Section 2.2.4 of NUREG/CR-5950 and Section 3.3.1.1 of NUREG/CR-5732 report fhe experimental results of irradiation-assisted nitric acid production with the following constant (based on data at 86 OF): 0.007 molecules HNO, 100 eV This constant is assumed to be conservative for water temperatures above 86 'F considering the reduced solubility of nitrogen at elevated temperatures. For a water density of 1 g/cc, this constant can be calculated to be 7.3E-6 moles of nitric acid per liter per Megarad of absorbed energy which matches the reported generation term in Section 2.2.4 of NUREG/CR-5950. 0.007 molecules eV mole 100 ergs 106 rads 1 g 1000cc 100eV 1.60219E-12erg 6.022E23molecules rad-g Megarad cc liter =7.3E-6 _holes L -Megarad Water densities less than 1 g/cc are applicable in post-accident suppression pools making the above constant conservative. Alternatively, an analysis considering the mass of water in the pool can be applied. Since nitric acid is a strong acid, [Hi and [NOl increase by 7.3E-6 for each Megarad received by the pool, the following formula can be developed. dr[HNO.17.3E -6 MO/IHNO, t)., (3-2a) dt lL - Megarad where: ~t),8, = the time-dependent dose rate' in the suppression pool (Megarads/hr). The previous equation can be integrated to yield the nitric acid concentration throughout the accident. [HNO,3 (t) = 7.3E-6l X(t),P,,dt (3-2b) where: t = time into accident (hrs). Since the 30-day suppression pool dose rates generated with TID-14844 source terms have been shown to bound those generated with NUREG-1465 (per Figure 5 of SECY-98-154). EQ dose rates generated by the current TID methods are conservative and acceptable for determining the HNO0 production rate. Note that this dose rate represents an energy deposition to the pool water such that alt decay mechanisms need to be considered including both gamma and beta emissions. Existing pool analyses may neglect beta decay if developed for calculated doses to equipment external to the pool. LM-0642, Rev. 0, Attachment F Page F-8 of F-30

F.aeve 3 C; '^ 3.3 Hydrochloric Acid Production The radiolysis of chloride-bearing cable jacketing will result in the production of HCI vapor as reported in Section 2.2.5.2 of NUREGICR-5950. A model for the production cf HIGCI from cable jacketing is developed in Appendix A based on the approach in NIUREG/CR-5950 and concludes the HCI produced from the radiolysis of a cable is predicted by the fcilowing formula. Beta: M,>,(t) =.3.512E-202x-R, -- t 0 l-t dt(3-3 Gamma: M1,,(t) =3.512E-20 per -R

i.

dt (3-3b) where: MHct _ total HCI production (g mols). V = energy release rate per unit volume (MeVlhr-cm3) for beta radiation. EV = energy release rate per unit volume (Meayhr-cm2) for gamma radiation, V#7 - linear absorption coefficient of.beta radiation in air (cm'), .,P A= linear absorption coefficient of gamma radiation in air (cm'), u = linear absorption coefficient of gamma radiation in Hypalon (cm'). = cable length (cm), th = thickness of the Hypalon jacket (cm), R = cable radius (cm), and t time Into accident (hrs). 6 - 3,5,2 0 - Xo l t lie L Equations 3-3a and 3-3b can be applied to all cables in the containment to determine the total HOE generation in containment. Dose rates and the cable inventories may vary throughout containment such that local dose rates can be applied to local cable quantities. Although it is anticipated that a significant portion of the HCI produced from cable radiolysis would react with the plentifuf metal surface areas In the containment (e.g., gratings, etc.), the gaseous HCI will be conservatively assumed to be immediately dissolved in the suppression pool water. In the suppression pool, the HCI concentration is given by: Y-CIXI)= V EMfw(t)+M° (t) (3-3b) ea# The following considerations may be used for determining the HCI production from chloride-bearing cable Jackets. 1-Consistent with NUREG-0588 [41, Rev. 1, Section 1.4(9), the beta dose to cables) arranged-invcable trays 4s-reduced by-a-factori i;Zdu toc-ieatized shielding by f othN cables and thWe a61bdray itself.

2. Cables in conduit or totally enclosed raceways will not contribute any HCO to the suppression pool. This assumption is consistent with Section 2.2 of NUREG-1081 and Table 2.2 of NUREG/CR-5950, which does not include the 15% of LM-0642, Rev. 0, Attachment F Page F-9 of F-30

Engin.egrine Rfe,-'r NO.: '3;,S-.CO3 F.e',*li'n.N1: 3 Page 9 cl 22 cables at Fermi that are routed in conduit. These conduits are water-resistant and generally routed between seated terminal boxes at which the cables - terminate or are routed through other conduit. There is no significant driving force for source terms to enter this conduit and any potential diffusion of containment atmosphere into these conduits would be a long-term process occurring after a significant decay time and result in minimal dose rates. In addition, these cables are shielded from any beta dose from the containment and drywell atmosphere outside the conduit due to the metal conduit structure. Although some HCI production may occur due to gamma radiation from the containment and drywell atmosphere outside the conduit, the limited amounts of gaseous HCI evolved from these cables would most likely react with the metal conduit structure considering the tortuous path out of the conduit and therefore is assumed to not enter the suppression'pool.

3. Since the airborne dose rates generated with TID-14844 source terms have been shown to bound those generated with NUREG-1465 in SECY-98-154 (6],

EQ dose rates generated by the current TID methods are acceptable in determining the HCI evolution rate. LM-0642, Rev. 0, Attachment F Page F-10 of F-30

Enepr eer ra lnlr,,.it. e ; Pace :0 :- 22 3.4 Cesium Hydroxide Production Cesium is released from the core as fuel failure occurs. Table 3.12 of NUREG-1465 indicates that 5% of the core alkali metal inventory (including cesium) is discharged during the cap release phase while an additional 20%o is discharged during the early in-vessel phase. The core damage is assumed to be arrested after the in-vessel release phase in accordance with the NRC recommendation in SECY-94-302. For iodine, Table 3.12 of NUREG-1465 indicates that 5% of the core halogen inventory is discharged during the gap release phase while an additional 25% is discharged during the early in-vessel phase. Consistent with Section 4.5 of NUREG-1465, the iodine exiting the reactor coolant system will be composed of at least 95% cesium iodide (Csl). These cesium and iodide inventories include the stable isotopes of 1'27 and Cs'3. The cesium that is not in the chemical form of Csl is assumed to exit the RCS in the form of cesium hydroxide (CsOH) and be deposited into the suppression poolP. This CsOH inventory is illustrated in Figure 3-1 below. Csl Cesium s HI Iodine CsOH Figure 3-1 CsOH Inventory Assumption Both the cesium and iodine core inventories -grow throughout the cycle with the cesium inventory increasing significantly. Therefore, the EOC core exposure will result in the largest CsOH release. Although-a BOC exposure may result in a reduced CsOH release and lower pool pH, the core source term inventory, pool iodine concentration, EQ dose rates, and core decay heat would all be lower at this BOC exposure. Since the radiological analyses are based on EOC conditions, the EOC core source terms for cesium and iodine are considered appropriate for the pool pH analysis. This release process is assumed to occur at a constant rate over th;,lgp1_e peq e 30 1 and 90 'minutes for the gap and early in-vessel release phases, respectively). The ollowing equations describe this release. Although, in reality, some CsOH may remain airborne in the containment. this assumption is expec:ed to be sufficiently conservative when taken in conjunction with the assumption in Section 3.3 that all HCI evolved from cable radiolysis immediately enters the pool. Considering the hygroscopic nature of CsOH and its release in the vicinity of the suppression pool. the probability of CsOH migrating to the pool is considered higher than that of HCI produced from cable radiolysis in locations that may be some distance from the pool and are likely to contain large metal surface areas. LM-0642, Rev. 0, Attachment F Page F-l I of F-30

Engineering Rcpcr NiO.: (,GiS_. ,OJ_30 Page 1I cl 22 d[CsOH] = 0.05m, - 0.95 0.05m, (Gap Release Phase) (3-la) dt VOH = 5 hr d.[CsOH] = 0.2mc., - 0.95 0.25m,' (Early In-Vessel Release Phase) (3-4b) dl V'. 1.S hr where: Mr., = core cesium inventory (gram-mols)'. This release can be integrated considering the 1/2-hour BWR gap release duration to yield the following equations during the gap and in-vessel release periods. Gap Release Phase: [CSOH 0(t) =.lMc. -0.095mt [o ) C (3-4c) (3-4d) Early In-Vessel Release Phase: [CsOH](t) = O.4me, - 0.475m,. [t- (0.5 + t)]+ 0.05mc - 0.0475m, 3 ~ VVa I Since cesium is being credited for a beneficial effect, a conservatively small cesium inventory should be applied. LM-0642, Rev. 0, Attachment F Page F-12 of F-30

Enoincerirn, Replrr to.: NO .IS.- .O3 Revisicui Mc: 3 Fzise 1Z.:f 22 3.5 Summary The combined effects of the acids and bases that occur during BWR accidents can-be calculated as a function of time and initial pool pH with the formulas in Equation 3-Ca by separating the acid and base generation terms. [H et)=( =0t=O)+jd.[Hljt)dt+' d[HNO3 it)dt J.d [HCIt)dt 0t 0 a0d = J p + { d(t)dt + [HNQJ I t)dt + J[HCIt)dt (3-5a) 0 0 00 [QHjlc) [OH-}t°) I dt[CsOH)it)dt= pi IJ~ d[sQH1t)dt (-b where: pHo is the initial pool pH value, (HI](t) is given in Equations 3-1c and 3-1d, (HNO3](t) is given is Equation 3-2b, [HCq(t) is given in Equation 3-3b, and

• (CsOH](t) is given in Equations 3-4c and 3-4d.

Some of the generated HI ions will be neutralized with the OH' ions such that Equation 3-0a will be true at the final conditions. qH-]- x). {,0 ] - X) = K.(7) (3 SC) -logK.(T) = 15.5129 -2.24E -2 ' T+3.352E -5 (5 T2 Solving for x leads to the final H' concentration of: [H-,, = [W x (H- ,(OH + (Hi -]-OHi +jH -4 {4OH] 4H}-10 4'"u -'t4 (3-5d) 2 The pool pH can then be directly calculated from Equation 3-Oa as pH= -logGH4J,,s) (3-5e) LM-0642, Rev. 0, Attachment F Page F-13 of F-30

P.lse 1_.:;3 4.0 SAMPLE PH CALCULATION This section develops a sample calculation applying the methodologies developed in Sections 3 with the following input parameters. Samole Case: The pH transient for a BWR with a suppression pool water volume of 3.5E6 liters is evaluated based on an initial pH value of 6.0 (based on a normal pool temperature of 77O F). This plant has 150,000 pounds of chloride-bearing cable insulation in containment, of which 50° is run in conduit and the remainder is in cable trays. All this cable is identical to the NRC model cable in Appendix A. The core inventories of cesium and iodine have been calculated to be 2500 (minimum) and 200 (maximum) gram mols, respectively. The BWR generic gap release time is 121 seconds. The containment has a radius of 63 feet (1920 cm) and the post-accident pool temperature drops linearly from 150 0F at 1 hour to 120 'F at 30 days. The 30-day integrated sump radiation dose is 10 Nlegarads while the 30-day containment gamma and beta integrated airborne energy depositions are 4E1 1 MeV/cc and 6E1 2 MeV/cc, respectively. Solution: This sample can be solved on a spreadsheet with the formulas summarized in Section 3.5. The results are illustrated in Figure 4-1 and reported in Attachment 1. The final results can be checked as follows. The initial Ho concentration (in gram-mols per liter) can be determined from the initial pool pH as 1.OE-6 from Equation 3-Oa. From Section 3.1, 5% of the released iodine is assumed to enter the pool as Hi. With 30% of the core iodine inventory released, the Hi concentration can be calculated as 8.5714E-7. 0.05

• 0.3
• m, = 0.05 0.3 200 = 8.5714E -7 Vp~a 3.5E6 From Section 3.2, the final HNO0 concentration can be calculated from the final integrated sump dose as 8.76E-5.

[HN],,,, = 7.3E X(t),,o, dt = 7.3E - 6

• 12 = 8.76E - 5 The HCI concentration can then be calculated from the final integrated airborne dose.

Neglecting the cable in conduit and reducing the beta dose by a factor of two for the 75,000 pounds of cable run in trays, the HCI concentration can be calculated to be 1.2069E-4. MeV lb [ e 3512E 20 973 75,000' [ 05 006E62+0069 =0.01 1 0.0198 3.74E -5 1.0= ISE LM-0642, Rev. 0, Attachment F Page F-14 of F-30

Enrp1neea-nn; R-!e,.,;rt Mlo.: I;1:i ^3 Fieviscn io: 3 Fase I_ 'i From Section 3.4. 95%' of the released iodine is assumed to enter the pool as Csl with the remainder of the cesium as CsOH. With 25% of the core cesium inventor/ released, the CsOH concentration can be calculated as 1.62286E.4. 8I [CsOH],^ 0.25

• mcs - 0.95 ' 0.3 ' m, 0.25
• 2500 - 0.95 - 0.3 ' 200 = 1.62266E-4 V,..I 3.5E6 The total H' concentration is the sum of the previous results.

[H-],,: =lE-6+8.5714E-7+8.76E-5+1.2069E-4=2.10147E-4 (OOH-], = 1 E1--14/1 E-6 +1.62286E - 4 = 1.62296E-4 The final pH is determined with the neutralized portion. x, calculated with Equation 3-5d to be 1.62295E-4. The final pH can then be calculated to be 4.32. pH = -logql-r,,1 -1.62295E - 4)= -4og(4.7851 E - 5) = 4.32 a a a

• l

.a a a-----F-10 .9 .0a-C. C .7 .2 0. 6 ° C,) 5 14 0.01 0.1 1 10 Time (Hours) 100 1000 .Figure 4-1 Sample Results LM-0642, Rev. 0, Attachment F Page F-15 of F-30

pdvtF1;:cfl. t: 3 5.0 IODINE RE-EVOLUTION As shown in Figure 4-1, the pool pH may drop below a value of 7 depending on plant-specific parameters such as the plant cable inventory or pool volume. This section develcps a methodology fort determining the amount of iodine that may evolve from a pool with a pH. less than 7 based on the NRC research in NUREG/CR-5950. Specifically, an equation describing the equilibrium concentration of elemental iodine in the air volume above the pool is developed 'as a function of the pool pH, temperature, and iodine concentration. 5.1 Methodology Aqueous iodine will exist in water pools in both 1 and 12 species. Appendix C of NURECG/CR-5950 derives the following relationship between the dissolved iodine ions [II and the aqueous 12 concentration. d +e[H'j where: [121 = concentration of elemental iodine (g-moles/liter)

• d

= 6.O5E-14 : 1.83E-14 e = 1.47E-09 [HI = concentration of H' ion (g-moles/liter) [ti = concentration of ionic iodine (g-moleslliter) In order to maximize the amount of 12 in solution (and consequently the amount in the gas phase), the conservative value of the 'd' parameter should be the lower of the specified range or 4.22E-14. Although these values are based experimental data at 25 SC, Appendix C of NUREGICR-5950 indicates that this model conservatively over-predicts the conversion to 12 at higher temperatures. The total iodine concentration in the pool is given by the following expression per Section 3.2 of NUREG/CR-595o and would include the non-radioactive isotope of iodine (i.e., Ilv). [1In =2 [12., +[] + (5-2) where: [I]a7 = total iodine concentration (g-atoms/iter)5 As described in Section 3.2 of Reference S. it Is convenient to use g-atom rather than mol in aqueous radioactive iodine concentrations because 12 contains 2 g-atom I per mol while 1 contains only I g-atom. For each radioactive isotope of iodine, the total iodine concentration in 9-atoms/liter can be calculated from the activity and pool volume as: A.(Ci) a3.7EI0 toms I )C - S A.(s1)* 6.022E23 --5--

• Vol(liters) g - atom LM-0642, Rev. 0, Attachment F Page F-16 of F-30

Engineering Re por 0 to.: GGNS-:'*-JU39 r~evi'Sion sNo: 3 Page 1 cl 22 Eliminating the variable for the ionic iodine parameter [l(] and considering that [Hi1=1O'. the following equation relates the aqueous 12 concentration to the pool pH and the total iodine concentration [I]. [12 ]q [1]2 d+e1QPH 1 0° 8[lq (d+e1OPH) 2 a ' 10-2H 8'1P 10-2 (5-3) Applying the nominal value of the "d" parameter of 6.05E-14, the fraction of iodine in the 12 species (i.e., 2[ll2[l]) can be determined as a function of pH for various total iodine concentrations, [1]. The results are plotted below and are identical to those presented in Figure 3.1 of NUREG/CR-5950. 1.0 0.9 0.8 0.7 0.6 0.5 0.4 cm 0, W C 0 C a IL 0.3 0.2 0.1

• 0.0 2

2.5 3 3.5 4 4.5 5 s.5 6 6.5 Pool pH Figure 5-1 Benchmark Model Results for Aqueous Iodine Considering the non-linear behavior of this Equation 5-3, the aqueous 12 concentration for each isotope cannot merely be calculated individually for each isotope, but must be calculated based on the total iodine concentration. For example, the total aqueous iodine concentration for the isotopic concentrations reported in Table 5-1 is 8E-6 g-atomslL. Based on this total iodine LM-0642, Rev. 0, Attachment F Page F-17 of F-30

Pa31c 1I 2 concentration, Equation 5-3 predicts a total aqueous 12 concentration of 3.63E-6 g-molsiL at a pool pH of 4 while, if this concentration were calculated for each isotope and summed. a total aqueous 1z concentration of 3.417E-6 g-mols/L would be predicted as shown in Table 5-1. Table 5-1 Example Isotopic Distribution Isotope Aqueous Isotopic 12 Concentration Concentration based on Eq. 4-1 (9-(g-atoms/L) mols/L) at pH of 4 1-131 SE-6 t 2.21 E-6 1-132 1 1E:6 3.81E-7 1-133 2E-6 Totals 8E-6 3.417E-6 Consequently, the total pool iodine concentration (including the stable isotope 1-127) should be applied to calculate the total aqueous 12 concentration. For the case above, since the 1-131 is 62.5% of the pool iodine inventory, the 13" concentration in the pool would be 2.27E-6 g-mols/L (62.5% of 3.63E-6 g-molsIL) instead of the 2.21E-6 concentration based on only the 1-131 concentration. The isotopic distribution for this example is listed in Table 5-2. Table 5-2 A plied Aqueous Isotopic Distribution Isotope Percent of Isotopic 12 Concentration Pool Iodine (g-morIsIL at pH of 4 1-131 62.5 2.27E-6 1-132 12.5 4.54E-7 1-133 25 9.08E-7 Totals 100 3.63E-6 Section 3.1 of NUREGICR-5950 cautions that the data at very low iodine concentrations (<-104 g-atom/L) are less reliable due to the formation of lodate. Fortunately, at these low concentrations, there Is little Iodine available for re-evolution. 5.2 Partition Coefficient The gaseous concentration of iodine above the pool can be determined from the aqueous concentration of iodine in the pool via the partition coefficient (PC). The iodine partition coefficient is defined in Section 3.3.1 of NUREGICR-595o as: PC= ([§2 .]W =lO&9401g (5-4) (1219a where T = pool temperature (Kelvin) U1z]aq = the iodine concentration in the pool (g-moles/liter) RIM ',a = the iodine concentration in the air (g-molesAiter) LM-0642, Rev. 0, Attachment F Page F-IS of F-30

,nuineennr.; ^ I::,;rt ': -:.8.s:^

4.;

3:1 Pise is-,If 212 The temperature dependence of the iodine partition factor is illustrated below. As the pool temperature increases the iodine partition factor decreases, driving the iodine into the airborne phase.

35 30 V 0a C -C 0 25 20 is 10 I 5 0 120 130 140 150 160 170 180 190 200 210 220 Temperature (OF) Figure 5-2 Iodine Partition Coefficient versus Temperature 5.3 Governing Formula Combining Equations 5-3 and 5-4, the equilibrium concentration of iodine in the gaseous phase can be determined from the pool pH and temperature, and total aqueous iodine concentrabon as follows: [I2 ] [12] [I2]g, PC [ d d+el OPH 1 j(d+elO-PH)- 2 8 l 1 2PH 810p' 1O 2 + 8p] H(d+e1OP) 1 0 629-o.0149T (5-5) LM-0642, Rev. 0, Attachment F Page F-19 of F-30

Patge 2CI 2 where:II 2] J = iodine concentration in the air above the pool (g-moles/liter) [lJ^ = total iodine concentration in the pool (g-atoms/liter) pH = pool pH d = 4.22E-14 e = 1.47E-09 T = pool temperature (K) Any differences in vapor pressure among the iodine isotopes in the pool are assumed to be negligible based on the relatively small differences in atomic weight. This assumption is conservative since the iodine isotopes with the relatively lower weights are 1-127 and 1-129 which have little or no dose consequences. As such, the iodine isotopic distribution in the gaseous phase above the pool can be assumed to be identical to the isotopic distribution in the pool. LM-0642, Rev. 0, Attachment F Page F-20 of F-30

m '1 :'*'.:. 6.0 CONTROL STRATEGIES There are a variety of pctentiJl strategies to control the posw-accident pcol pH in nuclear plants. PWRs utilize baskets of tri-scdium phosphate (TSP) that dissolve into the sump water when the containment sprays are initiated. Other r--WFs may use socdium hydroxide. These systems. however, are already designed into these plants and are ensured to be operable via existing Technical Specifications. In B'NRs. a supply of a buffering scdium pentaborate solution is available with the Standby Liquid Control (SLC) system for injection into the reactor vessel. This capability may also be provided with additional alternate injection procedures for mixing a batch of sodium pentaborate in an outdcor storage tank and injecting it into the vessei or suppression pool. 6.1 Standby Liquid Control Standby Liquid Control was generally introduced into BWRs to address the Anticipated Transient Without Scram (ATWNS) rule in 10CFR50.62. This system consists of a tank of a sodium pentaborate solution with redundant injection pumps that are manually operated from the control room. This system can be initiated in the event of an ATWS to inject this boron-rich solution into the-reactor vessel and shut down the reactor core in place of the inoperable control rods. Some plants enhance this shutdown effect by using a solution enriched in the neutron-absorbing isotope, Boron-10, with a corresponding lower sodium pentaborate concentration. The SLC solution is aqueous sodium pentaborate (Na2B10O16) which is prepared from stoichiometric quantities of borax (Na2B6O7-10H20) and boric acid (H3BO). This weak acid and its conjugate base will buffer the pool water at a pH corresponding to the following formula 110,1 1]. pH = pK, +log [anion) (acid] where: pKm = negative of the log of the acid dissociation constant [anion) = borate concentration (acid] = acid concentration The dissociation of sodium pentaborate is given by the following formula [1f]. Hence, each mole of sodium pentaborate provides 2 equivalents of borate and 8 equivalents of boric acid. The acid and anion concentrations can then be determined from the amount of sodium pentaborate that reaches the pool and the amount of acid produced. The adequacy of this approach was confirmed via a laboratory experiment [12]. _.: 5 -4 NazBic,0,s + 16 H20 4 2Na' + 2B(OH); + 8B(OH)0 II The temperature dependence of the dissociation constant for boric acid is listed below [7]. As shown in this table, this constant increases with temperature; however, the slope decreases as the solution temperature is increased. Therefore, linear extrapolation of this data to temperatures above 50 'C is expected to result in conservatively high dissociation constants and correspondingly lower pool pH values. Fitting a linear regression line through this data and adjusting the constant term such that all data points are bounded leads to the following equation for the temperature dependence of the boric acid dissociation constant where T is the solution temperature in "F. LM-0642, Rev. 0, Attachment F Page F-21 of F-30

.X-*!8;:; 'i: Z-IO =13.: I9 K,

• low =O0.0585*T + 1.309 Table 6-1 Temperature-Dependence of Boric Acid Dissociation Constant Solution Solution Dissociation Average Change in Fit of Temperature Temperature Constant Dissociation Dissociation

(*C) (F) (K'100 1 Constant per 'C Constant 5 41 3.63 I 3.71 10 50 4.17 0.108 I 4.23 1 15 59 I 4.72 0.11 I 4.76 20 68 5.26 0.108 I 5.29 25 77 5.79 0.106 5.81 30 86 I 6.34 0.11 6.34 35 95 6.86 0.104 6.87 40 I 104 7.38 0.104 1 7.39 50 j 122 8.32 0.094 8.45 As a test, the final pH of the sample calculation in Section 4 is calculated assuming that 5000 pounds of sodium pentaborate are injected into the suppression pool. At 30 days, this suppression pool is at 120 *F and the pK, can be calculated as 9.08. Ka 10' 0 =0.0585-120+1.309=8.33 pKa = -log(8.33E -10) = 9.08 This injected 5000 pounds of sodium pentaborate is equal to 5543 g-moles based on a molecular weight of 410. This 5543 moles will result 11,086 equivalents of borate and 44,344 equivalents of boric acid. The 11,086 equivalents of borate are neutralized by the 167 (4.785E-5 eq.liter 3.5E6 liters) equivalents of strong acid, leaving 10,919 (11,086-167) equivalents of borate ions and 44,511 (44,344+167) equivalents of boric acid. The pH of this solution would therefore be 8.47 instead of the unbuffered value of 4.32. [10,9191 pH = 9.08 + log 351 =8.47

• 3.5E6 J S

-~'~: LM-0642, Rev. 0, Attachment F Pagc F-22 of F-30

Pag~e __ I; 22

7.0 REFERENCES

1.

NUREG-1465, Accident Source Terms for Liaht-Water Nuc!ear Power Plants, dated February 1995.

2.

NUREG/CR-5950, Iodine Evolution and oH Control, dated December 1992.

3.

NUREG/CR-5732, Iodine Chemical Forms in LWR Severe Accidents, dated April 1992.

4.

NUREG-0588, Interim Staff Position on Environmental Cualification of Safety-Related Electrical Equipment, dated July 1981.

5.

SECY-94-302, "Source Term-Related Technical and Licensing Issues Pertaining to Evolutionary and Passive Light-Water-Reactor Designs', dated December 19,1994.

6.

SECY-98-154; 'Results of the Revised (NUREG-1465) Source Term Rebaselining for Operating Reactors", dated June 30, 1998.

7.

CRC Handbook and Chemistry and Physics, 73"d Edition, 1992-1993.

8.

NUREG-1081, Post-Accident Gas Generation from Radiolysis of Orqanic Materials, dated September 1984.

9.

NUREG/CR-1237, Best-Estimate LOCA Radiation Signature, dated January 1980. 10: S. Parker, McGraw Hill Encvclopedia of Chemistry, 1983

11.

GEXI 2000-00157, M.A. Morris to G.E. Broadbent, 'Suppression Pool pH", dated December 19, 2000.

12.

GIN 2000-01204, G.E. Broadbent to Central File, "Post-Accident Suppression Pool pH Chemistry Results", dated December 18, 2000. LM-0642, Rev. 0, Attachment F Page F-23 of F-30

APcer.dC: A. FPae I ct j APPENDIX A - HYDROCHLORIC ACID PRODUCTION MODEL The evolution of gaseous HOl from chloride-bearing cable is described in Secticn 2.2.5.2 of NUREG/CR-5950 (2]. Based on this description and the production model in Appendix 6 to NUREG/CR-5950, this appendix develops a generic methodology for calculating the HCI production rate for cables based on the individual cable dimensions. A1 Model Cable The NRC's model for a cable is illustrated in Figure A-1. It is a 600-volt reactor power cable consisting of a copper core with ethylene-propylene rubber (EPR) elastomer insulation and a chloro-sulfonated polyethylene rubber (Hypalon) jacket. The dimensions are illustrated in Figure A-1 which is repeated from Section 4.2 of NUREG-1081 8j. The material properties of the cable components and air are listed in Table A-1 as reported in Sections 2.1 and 4.2 of NUREG-1081. This model was originally reported in NUREG/CR-1237 [91] and has been referenced in NUREG-1081 and Appendix B to NUREG/CR-5950. The chloride-bearing component of this cable is the Hypalon jacket which is 27 weight percent chlorine per Section 2.2.5.1 of NUREG/CR-5950. Dimensions (cm)

• Ro 1.1304 01s R.

th=0.183 ° Re=0.729 R.:-* th:* I I '-4 Ix Copper Jacket Conductor. Insulator Figure A-1 NRC Cable Model Table A-1 Cable and Air Material Properties Linear Absorption Coefficient (cm') Material Density (gWcm) Beta Radiation Gamma Radiation Hypalon 1.55 52.08 [ 0.099 EPR. 1.27 42.67 0.081 Air 5.88E-4 0.0198 3.74E-5 LM-0642, Rev. 0, Attachment F Page F-24 of F-30

Enrgineerr.- Report No.: GGNS*-CO .:9 Revis;Cn No: 3 Appendix A, Page 2 of 6 For the cable illustrated in Figure A-1, the absorption of a radiation flux at a radius, r. can be described from basic principles as: d(r) = ¢Reg"~ where: = linear absorption coefficient (from Table A-1), and R, = outside cable radius. Figure A-2 illustrates the beta and gamma radiation fluxes through the 78.7-mil (0.183-cm) Hypalon jacket of the NRC's model cable based on the linear absorption coefficients in Table A-1. Based on Figure A-2, the beta energy is completely absorbed by this Hypalon jacket in application while the gamma energy is only fractionally absorbed. 1.2-0 0.8 0.6 gamma C, 0 0.4- \\beta tar. 0 LU 0 - 0 10 20 30 40 50 60 70 80 Cable Depth (mils) Figure A-2 Radiation Flux Profiles Through Hypalon Jacket of NRC's Model Cable A.2 GGNS DETAILED MODEL Similar to the approach in Appendix B to NUREG/CR-5950, the production of HCI from radiolysis can be given by the following formula. R=G*S-.*A (A-1) where: R = HCI production rate G = radiation G value for Hypalon, S = surface area of cable, 0= incident radiation energy flux, and A = absorption fraction of energy flux in the Hypalon jacket6. Energy absorption in the insulator need not be considered since this component does not contain chlorine. LM-0642, Rev. 0, Attachment F Page F-25 of F-30

Enginee2ring Rcpcrr N:. GP. S:*:G-9 Revi'crn No: 3 Appendix A. Page 3 c¶ Radiation G Value The radiation G value for Hypalon adopted in Appendix B of NUREG/CR-5950 is 2.115 molecules HCI per 100 eV. This G value is based on the energy absorbed by the polymer consistent with the footnote to Table 3 of NUREG-1081. As described in the NUREG, this value represents a balance between the increased HCI production at elevated temperatures expected during accidents and the neutralization potential of fillers in the cable. This value corresponds to 3.512E-20 g-mols HCVMeV. G=2.115molecules g-mol 106 eV=3.512E-20 g-mols 100 eV 6.022E23 molecules MeV MeV Cable Surface Area The surface area of the cable depends on the cable radius and length. S =2-R.

• 1 (A-2) where:

S = cable surface area (cm2). Bo = cable radius (cm), and I = cable length (cm). Incident Energy Flux Since the above HO generation term is based on deposited energy in the cable jacket, the energy flux incident on the cable needs to be developed. Section 2 of NUREG-1 081 develops an approach in which the radiation flux Is integrated from the center of the containment to the wall at a radius r. This approach is subsequently applied to cable insulation in Section 2.2 of NUREG-1081. The energy flux on a surface area that is a distance, r, from the center of containment is calculated for each radiation type to be: V( g(A-3) where: =energy flux (MeV/hr-cm2) EV energy release rate per unit volume (MeVlhr-cmr) u =linear absorption coefficient in air (1/cm), and r average distance of air to the cable (cm). From Equation A-3 and the linear absorption coefficient in Table A-1, it can shown that the beta radiation energy flux can be conservatively approximated by the following equation due to the short range of beta radiation in air relative to the distances in containment. EO1 Et1(A-4) Vp, LM-0642, Rev. 0, Attachment F Page F-26 of F-30

Engineeringj Rp.i4zlt No:: GGNS-~f3.t'XY3Z Revi5;ean No: 3 Appendix A. Page Of where: 00 = beta energy flux (MeV/hr-cm2) 'a = beta energy release rate per unit volume (MeV/hr-cm:), and ,uO = beta radiation linear absorption coefficient in air (1/cm). For the gamma radiation, a conservatively large distance that is characteristic of the plant containment should be applied in Equation A-3. Absorption Fraction The absorption fraction is the fraction of incident radiation energy flux absorbed by the Hypalon. As reported in Section 4 of NUREG-1081, this factor is calculated with the following equation for each radiation type. A = 1-(A-5) where: A = absorption fraction, th = thickness of the Hypalon jacket (cm), and A = linear absorption coefficient in Hypalon (1/cm). From the above equation and the beta linear absorption coefficient in Table A-1, it can shown that the beta dose Is completely absorbed by Hypalon jackets typically used in industry consistent with Figure A-2. This methodology will assume that the beta energy is completely absorbed in the Hypalon jacket. Equation A-5 above will be applied to explicitly calculate the absorption fraction for gamma radiation. HCI Generation The HCI generation rate can be calculated with the equations above as: Beta: R=G-S-0-A=3.512E-20-2.-R,-I- .1 I' (A-6a) GV LM-0642, Rev. 0, Attachment F Page F-27 of F-30

Engineering F~epcrt No,: GGsIS9S-OO2D Revisicr. No: 3 Appendix A. Page 5 o 6 where: R = HCl production rate (g-mol/hr), = energy release rate per unit volume (MeV/hr-cm3) for beta radiation. V = energy release rate per unit volume (MeV/hr-cm3) for gamma radiation, ,U = linear absorption coefficient of beta radiation in air (cm'), Pair'= linear absorption coefficient of gamma radiation in air (cm'), = linear absorption coefficient of gamma radiation in Hypalon (cm"'), r = containment radius (cm), t = cable length (cm), th = thickness of the Hypalon jacket (cm), and R. = cable radius (cm). Equations A-6a and A-6b can be integrated to determine the total HCi generated from an integrated energy release. Beta: M,0(t)=3.512E-20*2_r*R..1-4 Jfldt (A-7a)

Gamma

M (t)= 3.512E-20 R0.e )-(1 -e4 jj Er dt* (A-7b) where: Mha= total HCI production (g mols), and t = time into accident (hrs). A3 SAMPLE CALCULATION As a test of this methodology, the HCI production from a 1-cm segment of the NRC model cable is calculated from an Integrated beta energy release of 3.67E1 1 MeV/cc in the containment. Solution: Applying Equation A-7a, Mi: = 3.512E -20 9 2I.5-(1.1304 cm)-(Icm)- I 3.67E11 M.V = 4.626E-6g-molsHC MeV 0.01 98 cm" cc As a check, this result can be compared to that reported in NUREG/CR-05950. The weight of this section of cable can be calculated to be 1.85 grams of Hypalon and 1.46 g of EPR for a total mass of 7.3E-3 pounds. Hypalon: mn =p _4R: -(R. _th)2]. =1.55 9,.3.1416.l.1304 cm)' -(o.9474 cm)2]. 1cm=1.85 9 cm LM-0642, Rev. 0, Attachment F Page F-28 of F-30

• SF.

Engineering Reporl Pic.: GGNJS-98-1039 Retvisicn MNc: 3 Appendix A. Fage 6 cl 6 Total: (1.85 g + 1.46 g) ( k0g kg2 0 ls 7.30E -3 lbs (10009) ( kgj) The total absorbed dose is calculated to be 1.14 Megarads below. 4.626E -6 g - mols 3.512E-20 g Dose = MeV =1.1.4 Megarad 106 Rads

• 100 ers.6.24146E5 MeV *1..85 Megarad Rad - g erg Considering that this segment is 7.3E-3 pounds of insulation, a rate constant of 5.55E-4 g-mols of HCI per pound of insulation per Megarad of absorbed dose can be calculated for the NRC model cable. This result compares well with (and is conservative with respect to) the 4.6E-4 value reported in Section 2.2.5.2 of NUREG/CR-5950.

4.626E - 6 mols 5.55E - 4 mols HCI (7.3E - 3 lbsX1.14 Megarad absorbed) lb of insulation - Megarad absorbed dose ( LM-0642, Rev. 0, Attachment F Page F-29 of F-30

I Engineering Report No.: GGNSL .j39 Revision No: 3, Page 1 of I ATTACHMENT i - SAMPLE CASE RESULTS Pool rt .d O r Irt Dow PNWCC) (HI) jj Do "C (- i G3 Eea .J L. TcW [1-+1 J l Tcta CdLh x Fina IH-1{ ri-1%01 0OX.00014 Q(1&DE4 0QCUX400O)QEr840D C100001EO) QOX00E4O 1.OXIXDEC6 MOflXE.W 1.0:ttTE-CB -1.025E 71.10xn5E0 SMS9 0Q03h6 15Q.0 (100XXE.340

1. fl 1.13MI-4 a7amE.0 m&w4.(

imnsw( tO1wsC QOXUCww t(DXC&Cs -To0191E0 1.113TZC3 !iE6 a1 15Q0o i.eqsso 46EcX3 am)1EC 1.117E4CM 1.891&W, a7lIXEC8 l1fl)17EC6 4.38167E-06.4.39167E-M 1.0W3l7EC6 a7lW1EEC8 7.431 CQ&336 iio 1.420SEJ7 Z47E-C2 1.80M-0 &M&M 1cr.008i ola2o1 7 1.4148C a3oXXem a~nwcc-cs 1.52021Mc ag3Xos3 5.4( 1 iSO a6495E07 4.E-a3747W0 1.11648iW 1.93&1o a76507 zu7s7~r6 7.3 i gEcS 7xmgc 27zurmm u.4117Eoo 5750 2 iQon a4ll4E207 9Z36M &73750T 22.034M a77J5Eio 7.920E0(7 a2B737Ec i.5~oE-oi 1.5(1ffo4 a~awEw 7.qz3E-lo 9.101 acrmsi 1500 a.5742.0 a.9Ec2 amsa0 zav7ECBg aamwEio 7.64eqO7 axw7E( 1.62am-1.mEE-oi acawDE-c6 7.71fl34E-10 9.1WF 1 149.5 5.5742.0 544E01 am74sw( 1.,i34E4-1o 22338E+1 4.4S2E-03 1.Cxl5E-0 1.62WS 1.6296-1 1.(~Xo0 a.01572-10 9.033 24 149.0 a.5742. 1.07Efco 7.77~8C6E 261 17E.-0 4.%63+1i a7556M 1.BM0EC5 1.6nEO4 1.629Eoi 1.5.8342.0 a37472E-10 90677 6C 147.5 5.5714E.07 25.-CD 1. 3E 6 2M75721 1.0179.-12 2GX0C6E 4.1025DE.c5 1.620E04 1.6296-04 4.10241E4C6 9.518.X)E-10 9021 1o 1459 a.57480 S9C8.0 2-8441E205 1Afl15&11 l.zm~v a3o38(5 &a3)19E33 1.6zm04 i.n.04 ruxo6E-33 1.113YE-co a.Ci; 2____ 141.7 5.57480 66E.00 4.835M 1.802E.11 Z92.E+12 5843DE(5 1.(m~w.1.6296O4 1.6226E-1.o(F6380 1.813778.0) 8.74 W__ 137.5 as57480 5.548*0 BZ2M71546 24430E11 a899E+1 7.7853E-C 1A4217E-04 l.1286G 1.6206E1 1.42013E-W 4.z257E-3 8373 3% 135.4 as571480 a~E6 r,7 (62 2.71348.11 4.mag+12 1157B486M 1.550SN 1.6261t0 1.629E04 1.562YE-W 1.14332EtB 7.012 1314 5.5714807 a87E+.W 7ZJ7SC 29551511 4.M.-12 9.27EC5 1.89MO1 l.6Z604 1.62EE01 1.6278EO4M 4.3M~E-05 5.35 129_ 12 as571487 1.6so.01 7.m6E-(6 a3548E~ii K1577.13-2 1.041215-0 1.84a)E04 1.62BE01 1.6229GEO 1.622E-1 2-2~602E0 64& 12__ io 5.5714E807 1.Il.01 axazm( aem*ii j 56169&12 1.129Ot0 1.9644a801 1.6266s 1.6220E1 1.62wig-H6i29E-05 4.442 12518 5.5714E07 1.10E01 K75E.7516 a 4 1i 1 9445E121 1.195E-04 2(8 E-47t 1.MMO4 1.AM6E01 1.~6ME04146175CE0C6 4.336 aio I.5714E07 l2E.0 5.7M(51 4.OOE.11 aXO.-I21 1.20E-1 210147E0-N ~ i1.0 1.56O414.M~486C6 4 3al or S V 71

0 fr

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Calc. LM-0642, Rev. 0, Attachment G: XC-QI 11 1-98013, Rev.2, Grand Gulf Design Engineering Calculation- "Suppression Pool pH Analysis", 12/20/00 26 Pages LM-0642, Rev. 0, Attachment G Page G-1 of G-26

DESIGN ENGINEERING CALCULATION GRAND GULF NUCLEAR STATION UNIT ONE CALC NO REVIS;ON PAGE xc_0l1 11 -1san: z I: 2 i ct iii TITLE: Suporession Pool pH Analysis REVISION SUPERSEDED BY: SUPERSEDES: F Safety STATUS Related 0 Pending N/WA LE MA 0 Non Safety FE Final Calc. Calc. Related D Canceled Rev.: Rev.: _ Ap;endix B ORG CODE: NPE-Satety Analysis l CALC TYPE NUCSAFE KEYWORD(S): AFFECTED COMPONENT(S): (add sheets as needed) ACCIDENT N/A DOSE SYSTEM(s): N/A COMMENT(s): N/A SOFTWARE USED FOR CALCULATION: []Yes No Software Software Name/ Version/ Manufacturer Program No: Release _No: REVIEW AND APPROVAL PREPAREDBY: 9 1u I. 5c @D' DATE: CHECKED BY: DATE: /Z o~yatre / Name REVIEWED BY: 2 M. D. V-Ayow D ATE: Supervisor Signature I Name APPROVED BY: / A9M W;pAl row DATE: ______/_ Responsible Manager Signature I Name FORMn 3r)5.1 RevisturIS LM-0642, Rev. 0, Attachment G Page G-2 of G-26

a-.lIc::J;l :;:n:.eC ^ I i - Y:O X 3 selel t njZ REVISION STATUS SHEET ENGINEERING CALCULATION REVISION

SUMMARY

REVISION 1 2 DATE DESCRIPTION 2124/99 Issue for use Revised to address changes to pH 11/14100 methodology documented in Revision 2 to Engineering Report GGNS-98-0039 Revised to address impact of SLC i o/,' injection via the pH methodology documented in Revision 3 to Engineering Report GGNS-98-0039 SHEET REVISION STATUS A SHEET NO. Ii iii 1 2 3 4 REVISION 2 2 2 2 1 1 2 SHEET NO. 5 6 7 8 . 9 10 11 12 REVISION 1 1 .1 1 1 1 1 1 SHEET NO. 13 14 15 16 17 18 19 20 REVISION 1 1 2 2 2 2 2 2 APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO. REVISION ATTACHMENT NO. 1 2 3 REVISION 1 1 I LM-0642, Rev. 0, Attachment G Page G-3 of G-26

She.,et tat Cc.-: tn CONTENTS 1.0 PURPOSE............. 1............. ,,,,. 1

2.0 BACKGROUND

1,,,,,....,,,, 1 3.0 GIVEN.2 3.1 INITIAL PH VALUES. 2 3.2 POOL WATER VOLUME.................................. 2 3.3 CHLORIDE-BEARING CABLE INVENTORY. 3 3.4 RADIATION DOSE PROFILES. 3 3.5 SOURCE TERM INVENTORIES. 4 3.6 STANDBY LIOUID CONTROL (SLC) SYSTEM................................. 4 4.0 ASSUMPTIONS............... 5,,,,,,,,,,,,, 5 4.1 POOL MIXiNG....5............................................................................................................. 5 5.0 CALCULATION. 6 5.1 RADIATION DOSES.................... 6 5.2 CABLE MODEL CALCULATIONS. 6 5.3 HYDRIODIC ACID............................. ,.,.,.,,.,,,,,.,,,,,.,.,.11 5 .4 NITRIC ACID......... 12 5.5 HYDROCHLORIC ACID................... 13 5.6 CESIUM HYDROXIDE.14 5.7 FINAL POOL PH CALCULATION.......................... 1 5 6.0 RESULTS.18

7.0 REFERENCES

20 LM-0642, Rev. 0, Attachment G Page G4 of G-26

_f .1 --- ENTERGY CALCULATION SHEET Sheiet : C'r.:nZr. 'Z Calculation No. XC-_1 1 1-99013 Rev. 2 Prepared B S .2 Date tLi I Checked By )at I 1.0 PURPOSE The purpose of this calculation is to develop the GGNS post-LOCA suppression pccl pH transient based on the methodology reported in Engineering Report GGNS-98-0039 [1!. Revision 1 of this calculation applies the revised methodology documented in Revision 2 to GGNS-98-0039 and develops an HCI generation rate based on the energy flux to the cable surface. In addition, the GGNS suppression pool dose also considers the impact of beta radiation. Revision 2 addresses the buffering impact on the pool pH for the Standby Liquid Control system injection.

2.0 BACKGROUND

BWR suppression pools are credited in minimizing containment pressurization by condensing steam resulting from a loss of coolant accident (LOCA). At GGNS, the suppression pool is also credited for the long-term retention of iodine, which is washed into the pool by containment spray and by the scrubbing of airborne source term flows through the pool. Standard Review Plan, NUREG-0800. Section 6.5.2 (15] addresses sump pH considerations for PWRs in Section II.C.1 (g) stating: The pH of the aqueous solution collected in the containment sump after completion of injection of containment spray and ECCS water, and all additives for reactivity control, fission product removal, or other purposes, should be maintained at a level sufficiently high to provide assurance that significant long-term iodine re-evolution does not occur. Long-term iodine retention is calculated on the basis of the expected long-term partition coefficient. Long-term iodine retention may be assumed only when the equilibrium sump solution pH, after mixing and dilution with the primary coolant and ECCS injection, is above 7 (Ref. 5). This pH value should be achieved by the onset of the spray recirculation mode. Section 5.2 of NUREG-1465 (2] applies these considerations to BWRs reporting that, although there is no current requirement for pH control of BWR suppression pools, there is a potential for these pools to scrub substantial amounts of iodine in the early phases of an accident only to re-evolve it later as elemental iodine. This NUREG also notes that the cesium hydroxide in the pool may well counteract any acid generation to ensure the pH Is maintained sufficiently high that iodine re-evolution is precluded. This calculation determines the GGNS post-accident pH transient based on the methodology reported in Engineering Report GGNS-98-0039, which was developed from NRC research reported in NUREG/CR-5950 (3]. These results may then be applied in the LOCA airborne dose calculation in the event iodine re-evolution is predicted. LM-0642, Rev. 0, Attachment G Page G-5 of G-26

ENTESqGY CALCULATION SHEET Sheet 2 Cor-t On Calculation No. X C-0t1 1 1-9801:] Rev. Prepared ByS t8 aexllt CekdEy< o Date //3o 3.0 GIVEN 3.1 Initial pH Values The allowable suppression pool pH range is 5.3 to 8.6 consistent with the reactor water chemistry guidelines and SAR Section 9.3.6.1.2 and is confirmed quarterly per 08-S-03-10 (4J with temperature-corrected pH meters. This analysis will conservatively assume an initial suppression pool pH value of 5.3. Per SAR Table 5.2-6, the minimum allowable 24-hour reactor coolant chemistry during operation is 5.6 with a minimum pH of 5.3 when depressurized. As such, the reactor coolant pH will conservatively be modeled as 5.3 such that no suppression pool pH elevation need be considered due to the released reactor coolant mixing with the suppression pool inventory. 3.2 Pool Water Volume The minimum suppression pool volume is 135,291 ft3 based on Table 1 of ABD-4 (5S and Technical Specification Bases 83.6.2.2. Corisistent with Calculation MC-O1 E30-90112 [6]. a volume of 500 fte is subtracted from this value for the new ECCS suction strainer installed in RFO9. The total suppression pool volume is therefore 134,791 ft3 or 3.817E6 liters (based on 28.317 liters/ft3). In the event of a LOCA, the suppression pool makeup (SPMU) system is automatically initiated after a 30-minute timer starts on a LOCA signal (high drywell pressure or low-low reactor water leveol. The volume added to the suppression pool based on low water level in the upper pools is 36,163 ft3 (6]. This volume will be added to the original suppression pool volume after 30 minutes for a total water volume of 170,954 fte or 4.841 E6 liters. The reactor vessel will discharge a large quantity of reactor coolant to the suppression pool in the event of a DBA. A significant fraction of this inventory (-60%1o) will be discharged as a liquid while most of the resulting steam is quenched in the suppression pool. This reactor coolant inventory is reported as 6.815ES lbs IS]. Also, some of the suppression pool inventory will vaporize to become humidity In the drywell and containment. Based on the total volume of both drywell and containment of 1.67E6 ft3 [15 and bounding conditions of atmospheric pressure and 702 F. the total mass of air in the drywell and containment can be calculated to be 1.25ES lbs (p--0.075 Ibs/ft (7]). At 100% humidity, a bounding low atmospheric pressure, and 1859 F. the moisture content is 0.836 pounds of water vapor per pound of dry air 181. Consequently, the 1.25ES lbs of dry air wYil carry 1.045ES Ibs of water vapor, or significantly less than the 6.81SE5 lbs released. Since the additional pool inventory from the reactor coolant release bounds the inventory toss due to evaporation, both of these components will be conservatively neglected in this analysis. The impact of ESF leakage is small-compared to the large suppression pool volume and is consequently ignored. 1 An alternate SPMU initiation signal is Iow-low suppression pool level in association with a LOCA signal. Since. in the proposed core melt scenario. the ECCS pumps are not assumed to be injecting into the reactor vessel for apProximately 2 hours, the potential immediate SPMU actuation on low4ow suppression pool level (which is caused by the ECCS actuation) is not considered in this analysis. LM-0642, Rev. 0, Attachment G Page G-6 of G-26

ENTERGY CALCULAT ION SHEET Sheet 3 Cont On a. Calculation No. XC-Q1111-9F013 Rev. 1 Prepared By Date_\\%L-JIDO Checked By g-% Date /,/,r/oo 3.3 Chloride-Bearing Cable Inventory GGNS SAR Table 6.1-2 reports the containment and drywell weights of Hypalon. EPS or cross-linked polyethylene as 176.400 and 9835 Ibs, respectively. These values are also reported in Table 2.2 of NUREG/CR-5950 and have been confirmed in EAR X-002-96 (9] to be bounding values based on the GGNS cable database. A more detailed review of the GGNS chloride-bearing cable inventory in the containment and drywell was performed in EAR X-003-98 [10] based on the methodology reported in Engineering Report GGNS-98-0039. This review concluded that approximately 90% of the cable inventories in the GGNS containment and drywell are routed in conduit or totally enclosed raceways. Consistent with the methodology in Engineering Report GGNS-98-0039. these cable inventories are not included in the HCI generation calculation. The following exposed cable inventories were. developed with significant conservatisms that would bound any additional cable lengths that may be added to the GGNS containment or drywell in future design changes. Table 3-1 Total Combined Pounds of Exposed Cable Jacketing and Insulation Dro well A Containment Free Air Drop _IRouted in Trays Free Air Drop I Routed in Travs 873.65 873.65 1,561.03 1 14,049.27 In addition to Hypalon, a limited number of cables in the GGNS containment are jacketed with neoprene with a chemical formula of (C4H5Cl),. Based on this formula, neoprene is 35.weight percent (w/o) chlorine relative to the 27 w/o value reported for Hypalon in Section 2.2.5.1 of NUREG/CR-5gSO. Based on the similar chemical composition of this material relative to Hypalon and the very small inventories in the plant, this material is treated identically to Hypalon in this calculation and is included in the above table. 3.4 Radiation Dose Profiles The radiation doses that result in the production of acids are due to the presence of radioactive source terms in the containment atmosphere and suppression pool. Some of these source terms will be dissolved in the suppression pool generating nitric acid while others, such as the noble gases and organic species of halogens, will remain airborne irradiating exposed cabling and generating hydrochloric acid. To quantify the applicable radiation dose profiles for this event, this calculation evaluates two bounding profiles for the radiation doses.

1. The first profile assumes that all source terms (except noble gases) are deposited upon release into the suppression pool water. This profile maximizes the Suppression pool dose and the generation of nitric acid. Noble gases in'the drywell and containment atmosphere are modeled with the same flows as the LOCA dose analysis in which the drywell and lower containment nodes become well mixed aher 2 hours.

2-The second profile emphasizes hydrochloric acid production from cable radiolysis by assuming the maximum airborne source term inventory. The lower-bound (10%) deposition constants and the elemental iodine plate-out coefficients LM-0642, Rev. 0, Attachment G Page G-7 of G-26

~ErTRGVt CALCULATION SHEET Sheet 1 CcntOn

• Calculation No.

XC-Q1111-98013 Rev. Prepared By_' Date MM ( I Checked a Date /a/s/ez applied in the LOCA dose analysis [211 are also used in this case. Source terms calculated to deposit or plateout in the drywell are considered via a plate-out dose. Source terms removed from the containment atmosphere by containment spray are modeled to enter the suppression pool and generate nitric acid. Since this analysis specifically considers the impact of daughter products such as Ea-137m, no adder to the gamma dose is required per Section 7 of R.G. 1.183. The RAPTOR ccde has been qualified to perform energy deposition calculations in Reference 16. 3.5 Source Term Inventories The cesium and iodine inventories are considered in the suppression pool pH methodology in Engineering Report GGNS-98-0039. These inventories have been calculated for the GGNS core in Calculation XC-1J11-96010 (12] as 2400 and 325 g-atoms for cesium and iodine. respectively. These inventories are based on EOC core conditions and include the stable Cs'3 and 1127 species. The cesium inventory is a conservatively low estimate for the EOC conditions while the iodine inventory is a conservatively high estimate. 3.6 Standby Liquid Control (SLC) System in the event of an unmitigated LOCA, the GGNS Severe Accident Procedures (SAPs) direct the operators to inject the SLC solution into the vessel in the early stages of the accident for both vessel inventory and re-criticality protection when the core is re-flooded. As required by Technical Specification 3.1.7, the associated Basis, and Reference 22, the GGNS SLC system Is designed to inject at least 5800 pounds of sodium pentaborate into the reactor vessel at a minimum pump flow rate of 41.2 gpm for each of the two SLC pumps. As such, injection of the entire usable volume of the SLC tank would take approximately 2 hours to complete with a single pump. Considering the small flow out of the break until the core is re-flooded, no credit will be taken for the SLC system in the suppression pool for the first 2 hours, after which, the SLC solution will be assumed in the pool. If the alternate SLC injection were used, 5,000 pounds each of anhydrous borax and boric acid (warehouse stock codes 82267132 and 82267131) would be mixed in the CST per the guidance in Attachment 28 of Reference 23. These fractions are a nearly stoichiometric mixture per Reference 22 making approximately 10,000 pounds of sodium pentaborate. Since the HPCS system can inject nearly all of this solution into the vessel or directly into the suppression pool, the limiting SLC case is via the injection from the SLC tank. LM-0642, Rev. 0, Attachment G Page G-8 of G-26

- ENTERGY Calculation No. XC-O1 Prepared By _ _31t1-5 = CALCULATION SHEET Sheet 5 Ccnt On (7 Rev. I Date 111-98013 Date \\la Checked By_ 4.0 ASSUMPTIONS 4.1 Pool Mixing After 2 hours, at least three ECCS pumps will be available to take suction from the pool. At approximately 7000 gpm per pump, at least 21,000 gpm will be circulating from the suppression pool to the reactor vessel or containment spray system. Based on the maximum pool inventory (including the upper containment pool) of 4.841E6 liters, this ECCS flow represents approximately one complete exchange of the pool volume per hour. On this basis, the suppression pool is assumed to be well-mixed such that a single pool pH value can be applied. I LM-0642, Rev. 0, Attachment G Page G-9 of G-26

ENTERGY CALCULATION SHEET Sheet 8 Ccrt Cn I Calculation No. XC-O111-98013 Rev. 1 Prepared By I3 DateN sl71 Chec!ed By -5 Date 5.0 CALCULATION 5.1 Radiation Doses The RAPTOR calculations are documented in Attachment 1. RAPTOR calculates an integrated suppression pool dose of 14.7 Mrad assuming all decay energy is absorbed in the water. Calculation XC-O1 111-98012 [14] performs a more detailed calculation of this dose considering the potential for some limited gamma release from the pool water with a result 11.54 Mrad. This calculation will apply the results of the detailed analysis in Reference 14. These integrated radiation doses are integrated in Attachment 2 via a fit to one of the following equations. A*(1-B-e-') or A+B-ln(t) 5.2 Cable Model Calculations There are many different types of cables in application at GGNS including single and multiple conductor. Some of these cables include interior Hypalon jackets on each individual conductor and some multiple-conductor cables have outer interstices filled with extruded Hypalon. The cable jacket/insulation inventories reported in Section 3.3 include all of these cable types. Some of these GGNS cable types are illustrated below. Rubber 45-mil Hypalon Hypalon 5-mi Jacket Jacke EPR JacketInsulator 65-Mul Coppem EPR Conducto Insulator 60-mit Conductors Single Conductor Jacket Copper Two-Conductor Conductor 15-mil Hypalon Hypalon extruded Jacket .to filt outer interstices 30-mil and 45-mil EPR Hypalon outer Insulator Jacket Three-Conductor Figure 5-1 Sample GGNS Cable Types LM-0642, Rev. 0, Attachment G Pge G-l 0 of G-26

~ ENTERGY CALCULATION SHEET Sheet 7 Cora On En Calculation No. XC-O1111-98013 Rev. X Prepared By f.4 3. Date i\\leD Checked By 51* Date IL The methodology in Engineering Report GGNS-98-0039, however, is based on simple single-conductor, single-jacketed cables like the NRC model cable in NUREGFCR-1237 f131. Therefore, to simplify this analysis, the beta and gamma exposures are addressed separately as discussed in detail below. 5.2.1 Beta Radiation As described in Engineering Report GGNS-98-0039, the beta dose is assumed to be completely absorbed by the cable in the chloride-bearing exterior jacket. Since the beta dcse is completely absorbed in the first -40 mils, the internals of the cable construction may be ignored for the beta calculation. As such, since the cable inventories are reported in terms of pounds, the specific GGNS cable types were reviewed to determine an appropriate surface area per unit mass for application in this calculation. The six cable types (B'6, B7, C-2, C-4, C'7, and C'9) that make up over 85% of the exposed cables in the drywell and containment are listed below based on the data in Attachment 1 to EAR X-003-98. Table 5-1 Primary Cable Types in GGNS Containment I/ EAR AttlCable Type Outer Outer Jacket Jacket Total Ins Surface GGNS V Page Diam Radius Thickness Mass Mass Area Inventory I_ (in) (in) (lbstft) (Ibs/11) (cm 2 /1b) (Ibs) NRC Model 0.89 0.445 0.072 0.1237 0.2225 972.9 3 B6 0.678 0.3390 0.060 0.0779 0.2210 746.2 3396 4 6-7 0.639 0.3195 0.060 0.0729 0.2080 747.2 3496 16 C 2 0.522 0.2610 0.045 0.0451 0.1360 933.5 5427 17 C-4 0.634 0.3170 0.060 -. 0.0723 0.1925 801.0 1847 19 C7 0.745 0.3725 0.060 0.0863

• 0.2500 724.8 4480 20 C 9 1.024 0.5120 0.080 0.1586 0.4540 548.6 947 Based on the data in Table 5-1, the worst cable type is C2 with a total surface area of 933.5 cm2/lb. However, all other cable types have significantly less surface area per unit mass than this C'2 type due to their larger size. Considering the abundance of these larger cables, an appropriate value for this calculation would be 800 cm2/lb since it bounds (or effectively equals) all but one cable type and is higher than the typical GGNS cable.

The HCI production rate is given by Equation 3-3a of Engineering Report GGNS-98-0039 below. 3.512E-20 1 ' E,, 3-12 -20g - mols2 E 352 20MeV 80cm2(m 0 1 J, t(-1) 4.841E6 liters lb M c L0.01m98 cm" =2.93E 2 + mk 3. dtV LM-0642, Rev. 0, Attachment G Page G-1 I of G-26

ENTERGY CALCULATION SHEET Sheet 8 Cont On 9 Calculation No. XC-01 111 -98013 Rev. 1 Prepared By

z.

Date A:7 1 Checked By 5e'.S Date i///J c where: = the mass of combined cable jacket and insulation routed in exposed cable trays (Ibs), mfg = the mass of combined cable jacket and insulation in free air drops (Ibs), and = energy release rate per unit volume (MeV/hr-cm3) for beta radiation at time t (hours). 52.2 Gamma Radiation Unlike beta radiation, gamma radiation can penetrate the cable interior and HCI may be generated from the interior Hypalon jackets or extruded Hypalon fillers in some of the GGNS cable types. Absorption Faction As illustrated in Figure 5-1, a cable type is needed to bound the various types routed in the GGNS containment. Considering that the worst-case cable would have a large radius and have the interstices between the interior cables are filled with Hypalon, a radius of 0.35* inches is taken to represent the typical GGNS cable. This radius bounds most of those cables in Table 5-1 and is larger than the average GGNS cable. Since the Hypalon depth could range from -0.090 inches to the entire radius of the cable depending on angle, this calculation will. conservatively assume, based on the GGNS cable drawings in Reference 10, an average Hypalon depth of 80% of the cable radius for an average Hypalon depth of 0.28 inches. For this cable, the absorption fraction, (_ e-M'j.8 can be calculated with the linear absorption coefficient of 0.099 cm' from Table A-1 of Engineering Report GGNS-98-0039 to be 0.068, which is signrficantly higher than the 0.0179 value generated for the NRC's model in Section 4.2 of NUREG-1081. Gamma Free Path In the drywell, the largest radial distance would be approximately 20'20 based on the shield wag outer radius at 16'4' and the drywell wall inner radius of 36'6' per Reference 18. This calculation will conservatively apply a value of 36'6 (111Z5 cm) in the drywell. In the containment, the gamma free path in the annular region is severely restricted except in the large open area In the containment dome. Considering the compartments in the containment annulus, the free path in the annular region is taken to be 20'6* based on the 41'6' outer radius of the drywell and the 62' outer radius of the containment wall. In the containment dome, the containment radius of 62' is applied for the gamma distance. Although most cabling is in the annulus (where most of the containment equipment is located), the average containment gamma distance is conservatively taken as the volume-average of the above distances and calculated below to be 1384 cm. These volumes are calculated in the LOCA dose analysis [21] as 5.6E5 ft-for the unsprayed region and 8.4E5 ft3 for the sprayed region. 8.4 ES ft6' 5.6E5 ft2 (L) 62'+ .20.5'= 45.4'= 1384 cm IA4E6 tt 14E6 ft" LM-0642, Rev. 0, Attachment G Page G-12 of G-26

ENTERGY CALCULATION SHEET Sheet 9 Ccnt On l Calculation No. XC-01111-98013 Rev. 1 Prepared By Date %t (I I Co Checked By Date 4 The HCI production rate is given by Equation 3-3b of Engineering Report GGNS-98-0039 and is reproduced below. Drvvwell: HCI(t) 3-512E-20.2r. 3.512E-20 g-2mols 2 3.74E E = MeV 80E (m VWY+mJ)- 4 e) 0.068 - dt (5-2) 4.841E6 liters lb 3.74E-5cm" 0 V 4.3-EE-22. (mve + mh) l V dt a where: movy = the mass of combined cable jacket and insulation routed in exposed cable trays (Ibs),. M& = the mass of combined cable jacket and insulation in free air drops (Ibs), and 'V = energy release rate per unit volume (MeV/hr-cm) for gamma radiation at time t (hours). Containment: [HCIJ() 3.512E -20 .r dt pV 3.512E-20 g-mols 2 -4 74-3 cm I.m =- MeV .8 fl9 e, ~,A0i.06 -d 53 4.841E6 liters lb c

• (,

+ 374E - cm" 0.068 V 5.32E-22.(ma f+ mA).Ldt Lov 5.2.3 Deposition Doses Case 1 involves no deposition since the only airborne source terms are noble gases2 which do not plateout or deposit. For Case 2, the source terms that are removed by deposition and plate-out in the drywell, will result in additional energy absorption by the cables. The drywell plateout area is 181,608 itf [20] or 1.69EB crm2. This area conservatively does not include the area of the cables. 2 Some noble gases decay into radioactive daughters such as Rb-88 or Cs-135. These particulates are modeled to be removed Irom the atmosphere into the suppression pool with a large lambda. LM-0642, Rev. 0, Attachment G Page G-13 of G-26

ENTERGY CALCULATION SHEET Sheet 10 Cont On aI Calculation No. XC-O1111-9813 Rev. Prepared By 9p.-.'? Date \\k(f ! - Checked Bv -,Z5; Date.1 -'/0 The deposited source terms are conservatively assumed to be on the surface of the cable such that half of the released energy is in the direction of the affected cable. Similar to the airborne dose, the beta energy is assumed to be completely absorbed in the cable jacket while 6.8% of the gamma dose is absorbed. 4.841 RE6 Itr 8 0 lb .2 (a ^-0.6. Etd+(m +m)- d l 5 a512-JE.- 24).0 2[(+ r m 06* (5-4) -MeV cmo! 1 Ifr 4.841 E6liters 9i A 2e~jE~t =2.SE-24.[(m, +mb).0.068.JE-fft.d+( -+ M.)JEJ..+/--dt] where: '-A() = energy release rate per unit area (MeV/hr-cm2) for gamma radiation at time t (hours) and A = energy release rate per unit area (MeV/hr-cm2) for beta radiation at time t (hours). LM-0642, Rev. 0, Attachment G Page G-14 ofG-26

ENTERGY CALCULATION SHEET Sheet 11 Cont On L. Calculation No. XC-Q1 111-98013 Rev. 1 Prepared By JV:* Date '\\()1Wt Checked By 5C5 Date L4Xo 5.3 Hydriodic Acid The final hydriodic acid can be calculated from the iodine core inventory of 325 g-atomS reported in Section 3.5. 120 - V.,, (0.5400 'V, where: ml = core iodine inventory (gram-mols), and Vpoa = volume of the suppression pool (liters). t = time into accident (hrs), and tap= onset of gap release (121/3600 hrs). The final HI concentration at 7321 seconds is calculated below to be 1.0076E-6 moles per liter. [HFit = 7321s) = 325

• 7321/3600 -(O.S + 121/3600)1+

325 =1.0070E-6 120- 4.841 E6 400 -4.841 E6 AL LM-0642, Rev. 0, Attachment G Page G-15 of G-26

ENTERGY CALCULATION SHEET Sheet 12 Cant On I3 Calculation No. XC-01111-98013 Rev. 1 Prepared B Date "\\(-7 kz Checked 8y..:5c Date.. 40zoa 5.4 Nitric Acid The nitric acid is calculated from the integrated pool dose. From Section 3.2 of Engineering Report GGNS-98.0039, the transient nitric acid concentration is given by: (HNO3 lt) = 7.3E - 6X(t) dt where:

• (t),,

= the time-dependent dose rate in the suppression pool (Megarads/hr) The final HNO3 concentration at 30 days is calculated below to be 8.424E-5 mots per liter. [HNOit= 30 days) =7.3E-6 *11.54 =8.424E-5 For Case 2, the nitric acid production is calculated to be 6.787E-5 mols per liter. 0.007 molecules Os 3 9El 4 MeV. eV.1o000- [HNOQkt=30days)= 100eV cc MeV liter = 6.787E --- 6.022E23 molecules liter mol LM-0642, Rev. 0, Attachment G Page G-16 of G-26

-ENTERGY CALCULATION SHEET Sheet 13 Ccrnl Cn : Calculation No. _XC-Q 1 11 1-9801 3 _RFev. Prepared 8 ,Date-vvIt(Iem~ Checiced 9v -;5e Date x 'O 5.5 Hydrochloric Acid The hydrochloric acid transient can be calculated from the equations developed in Secticn --2. Since the containment and drywell contain different quantities of cable insulation and have different radiation profiles, the HCI generation in each of these regions is evaluated separately and then summed consistent with the well-mixed pool assumed in Section 4.1. The 30-day HCI concentrations are manually calculated below. The 30-day drywell integrated beta and gamma dose results calculated in Attachment 1 are reported below. The containment doses are based on the volume-average of the sprayed and unsprayed regions. y eil Containment Beta Gamma Beta Gamma Case 1 2SSE+13 MeVc 1.22E+13 MeV/cc 1.48E+13 MeV/cc 6.29E+12 MeV/cc Case2 Airbome 2.91 E+13 MeV/cc 1.72E+13 MeV/cc 1.S7E+13 MeV/cc 6.81 E+12 MeV/cc Deolpjateout 3.75E+23 MeV 1.12E+24 MeV 7.17E423 MeV 2.11E+24 MeV Case 1: Drywell Beta: [HCI] 2.93E - 22. (.265 + 873.65) 2-55E+13=9.79E-6 Containment Beta: [HCI] 2.93E _2.(14049.27 + 1561.03 )1.48E ÷13 = 3.72E - 5 Drywell Gamma: [HCI = 4.3E -22. (873.65 + 873.65) 1.22E13 = 9.1 7E - 6 Containment Gamma: [HCI] = 5.32E - 22. (14049.27 +1561.03). 6.29E12 = 5.22E -5 Total HCI Concentration: 1.084E-4 mols/liter Case 2: Drywell Beta: [HCI] = 2.93E - 22. (173.h6 + 873.65) 2.91E+13= 1.12E-5 Containment Beta: [HCI] = 2.93E - 22.(1449.27+1S6103)-157E + 13 = 3.95E - S Dryywell Gamma: (HCIl = 4.3E-22.(873.65 + 873.65). 1.72E13 =1.29E -5 Containment Gamma: IHC= 5.32E -22 *(14049.27 + 1561.03). 6.81 E12 =5.66E -5 Drywell Dep/Plateout: IH1 = 2-9E - 24

• (873.65 + 873.65).- 068,1.12E + 24 MeV + (873.65 3.75E +23 MeV 1107E S 1.69E+8cm' 2

1.6-EScm' Total HCI Concentration: 1.309E-4 mols/liter LM-0642, Rev. 0, Attachment G ?age G-17 otG-26

, ENTERGY CALCULATION SHEET Calculation No. XC-O1111-98013 Prepared By-,

3.

Date.J-IM Checked By 5 Sheet 14 Cont On 15 Rev. I -Date_ 0ooX r  I 5.6 Cesium Hydroxide The final cesium hydroxide is calculated from the cesium and iodine core inventories reported in Section 3.5 of 2400 and 325 g-atoms for cesium and iodine respectively. rCsOH0t) 0.4mc - 0.475m,.*(o t )]+ 0.05mc -0.0475ms The final cesium hydroxide concentration at 7321 seconds is calculated below to be 1.0481 E-4 moles per liter.

_~~~c c-SS

[CsOHjt = 7327s) = 0.4 2400-0.475 325 [ [7321/3600 - (0.s + 121/3600)l [CSO~t731s) 3 -4.841 E6 + 0.05-2400 - 0.0475.325 = 1.0481 E - 4 mols/liter I 4, /41 t) I-1 t ,2,lat 1=-'5. LM.0642, Rev. 0, Attachment G Page G-18 of G-26

~~ENTERGY CALCULATION SHEET Sheet 15 Cont Cn Calculation No. XC-01111-98013 Rev. 2 Prepared By e <.8. Date A MLXfil. Checked By S Date.L/1z1V 5.7 Final Pool pH Calculation From the results of Sections 5.3-5.7, the pool pH at 30 days may be calculated for the limiting case (Case 2) with the methodology in Section 3.5 of Engineering Report GGNS-98-0039 where pHo is the initial pool pH value. [H-jt) = io-^' + l [Hlt)dz + l [HNOit)dt + -[HCl(t)dt 0 0 0 [HjIt =30 days) = 10`' +1.0070E-6 + 6.787E-5 +1.309E-4 = 2.0479E-4 [OH-1 t) = 1 0 i + ldt [CsOHIt)dt 10 - [OH-it=30days) = 1 +1.0481E-4 =1.0481E-4 At 120 'F, the ionization constant of water is lo.I' per Equation 3-Oa of Engineering Report GGNS-98-0039. The neutralized ions can then be calculated as 1.0481 E-4 mols per liter. X=OHWJ+gH-]_4[o-J+JH-1Y-4-q0H-I [H-J-n) 2 1.0481 E-4 + 2.0479E 4(1.0481 E - 4 + 2.0479E - 4)2 (1.0481 E - 4.2.0479E 10-'-') 2, -1.0481E-4 The final H' concentration can then be determined as 9.998E-5 mols per liter. [d' ],i,, = [H' ] - x = 9.998E - 5 The final pool pH can then be calculated as 4.0. This value matches the result in Attachment 3 considering the slight round-off errors in the intermediate values. pH = -logqfHirj= -log(9.998E-5)= 4.0 The pool pH at intermediate points is calculated in Attachment 3... The injection of 5,800 pounds of sodium pentaborate (or 6,416 g-mols based on a molecular weight of 410) from the SLC tank would introduce 12,832 equivalents of borate and 51,328 equivalents of boric acid into the suppression pool. LM-0642, Rev. 0, Attachmcnt G Page G-19 of G-26

=

=: ENTERGY CALCULATION SHEET Sheet 16 Con: On \\'? Calculation No. XC-O1111-98013 Rev. 2 Pr'MnnrnA M., e- --- M-.. to t1 oS n a, ro- .I _ / rL~ aC Co ~.I7 ale 1L Al \\ 14LJ.. sniecx a by UAce iaze o ,'eo-ndo (5800 it)4 4 5 3.6~ -61g-o lb= 6416 g -mol 410 g-mol The number of strong acid equivalents in the pool after 30 days is 484 based on the 9.998E-5 mols per liter calculated above and the pool volume of 4.841E6 liters. The additional pool inventory associated with the SLC tank is conservatively neglected. Using the methodology in Reference 1, the resulting equivalents of borate and boric acid can then be calculated as 12,348 and 51,812 respectively. Equivalents Borate: 12,832 - 484 = 12,348 Equivalents Boric Acid: 51,328 + 484 = 51,812 The pool pH at 30 days can then be calculated to be 8.46 based on a temperature of 120 'F. K.-10'0 =0.0585-120+1.309=8.33 pK, .-log(8.33E - 10)= 9.08 [(12.348 ) pH = 9.08 + log 1E812 18.46 4.841 E6 As a bounding sensitivity case, none of the cesium hydroxide and only 10% the sodium pentaborate are assumed to reach the pool, which is also conservatively assumed to be at the design temperature limit of 185 IF. In this case, the number of strong acid equivalents in the pool after 30 days is 991 based on the 2.0479E-4 mols per liter calculated above and the pool volume of 4.841 E6 liters. The pool pH at 30 days can then be calculated to be 7.60. Equivalents Borate: 12,832/10 - 991 = 292 Equivalents Boric Acid: 51,328/10 + 991 = 6124 K.- 10 0 = 0.0585 -185 +1.309 = 12.13 pK, =-log(12.13E-10)=8.92 2921 pH = 8.92....log17.60( 6124 ) 4.841 E6 LM-0642, Rev. 0, Attachment G Page G-20 of G-26

-ENTERGY CALCULATION SHEET Sheet 17 Cont On\\ E Calculation No. XC-01111-98013 Rev. 2 PreparedB 5:1.4.. Date -21 %9 (C' Checked -Date e!Le44 As such, the sodium pentaborate solution is a very effective buffer for the post-accident suppression pool chemistry transient and can ensure, with significant safety margin, that the suppression pool pH will remain above a value of 7. 'LM-0642, Rev. 0, Attachment G Page G-21 of G-26

'- ENTERGY CALCULATION SHEET Sheet 18 Cont On kct Calculation No. XC-01111-98013 Rev. 2 Prepared By

4. 7?.

Date k2,1%% CO Checked B

5S Date

..z~r 6.0 RESULTS The un-buffered GGNS post-accident suppression pool pH profile is calculated in Attachment 3 and illustrated in Figure 6-1 below. The pH rises steadily during the gap and in-vessel release due to the introduction of CsOH into the pool. The pH then begins to decrease after the vessel release terminates due to the continued formation of nitric acid in the suppression pool and hydrochloric acid from radiolysis of the Hypalon cable jacketing. As the pH approaches a value of 7, the slope becomes more negative due to the approaching complete neutralization and the logarithmic function of pH. After approximately 4.days, a pH transient is experienced and the pool becomes somewhat acidic. 10 -+4-- Case I (Mvaxrxmit WMo)a s o r l = !Butfered Case -- mCase 2 (lcxkamsn1e rl a- -- -- -- --- 6--

• s B r d,

8 ' Poundin Figure~~Bffre 6-GSPo rnin Cas-CL 0.010.1 0 10 0 0. As discussed in Section 3.6, the SLC system will be injected early in the event that such the SLC solution will reach the pool within 2 hours. With only a small credit for CsOH, the suppression pool pH will remain above 7 for the first 2 hours. After the SLC solution reaches the pool. the pH will remain above 7 for the 30-day duration of the accident even without credit for CsOH and assuming only a small fraction of the sodium pentaborate reaching the pool. This 'bounding buffered case' is reported in the above figure as calculated in Section 5.7. LM-0642, Rev. 0, Attachment G Page G-22 of G-26

GY CALCULATION SHEET Sheet _ Crt Cn 2 _ Calculation No. XC-0i111-9sG13 Rev. 2 PreparedBy Date

2t WIC) Checked 5

Da:e.zzga Therefore, with the injection of only small amounts of sodium pentaborate, the suppression pool pH will be maintained in an alkaline state such that iodine re-evolution need not be considered. To evaluate the relative importance cf each type of acid, a comparison oi the origin of each acid is presented in Figure 6-2. The primary source of acid is from radiolysis of the cable insulation, particularly from the beta dose. The nitric acid generated from radiolysis of the suppression pool water is the second largest source of acid. The hydriodic acid is nearly insignificant in this analysis considering the large quantities of hydrochloric and nitric acids. j. S17 I 48% 4%0 Figure 6-2 Acids by Contribution (after 30 days) This calculation results in a more severe chemistry transient than the previous revision. primary reasons for this change in results are described below. The

1. The calculation includes beta dose in the pool dose calculation.

This consideration will increase the nitric acid production.

2. This calculation uses simplified models for generating the energy flux into cables based on the volumetric energy release rate and a large gamma energy. The previous calculation applied the GGNS EQ results which are based on a complex shielding model and a time-varying gamma energy spectrum which is generally less than the 1 MeV applied in this calculation.

3. This calculation generates the containment volumetric energy release rate without credit for suppression pool scrubbing. The previous calculation took some credit for suppression pool scrubbing. This revision therefore results in higher source terms in the containment and a larger HCI generation rate.

LM1-0642. Rev. 0. Attachment G. Page 23 of 26

= -*GLCLA.DC;\\: CSiET Si.eH T Cen; C<-'. Calculation No. XC-a1 11-98013 Rev. 2 Prepared Ba Date t(cz Checked Date

7.0 REFERENCES

t.

Engineering Report GGNS-98-0039, Rev. 3, Supcression Pool oH and Icdine Re-evolution Methodoloov.

2.

NUREG-l4es Accident Source Terms for Licht-Water Nuclear Power Plants, dated February 1D995

3.

NUREG/CR-5950, Iodine Evolution and DH Control, dated December 1992.

4.

Chemistry Procedure 08-S-03-10, Rev. 28, Chemistrv Sarnclino Program. S. Analysis Basis Document (ABD) 4, Rev. 0, Analytical Bases for Ccntainment Performance.

6.

Calculation MC-Q1E30-90112, Rev. 1, Calculation in Suooort of UFSAR Table 6.2-50 MSu~pression Pool Geometrv-GGNS" Values.

7.

Crane Technical Paper 410, Flow of Fluids through Valves, Fittings, and Pipe, 25w' Printing, 1991.

8.

Cooling Tower Institute Code Tower Standard Specifications, 'Acceptance Test Code for Water-Cooling Towers", CTI Code ATC-1 05, dated February 1990.

9.

Engineering Assistance Request X-002-96, dated April 3,1996.

10.

Engineering Assistance Request X-003-98, dated November 30, 1998.

11.

Bechtel Calculation 5.8.3, Rev. 5, NUREG-0588 Source Terms & Integrated Doses.

12.

Calculation XC-Q1J11-98010, Rev. 0, Cesium and Iodine Inventories for Pool pH Palcula lion.

13.

NUREGJCR-1237, Best-Estimate LOCA Radiation Signature, dated January 1980.

14.

Calculation XC-Q1111-98012, Rev. 1, Suppression Pool Radiation Doses.

15.

NUREG-0800, Standard Review Plan, Section 6.5.2, "Containment Spray As a Fission Product Cleanup System' Rev. 2, December 1988.

16.

Engineering Report GGNS-00-0014, Rev. 0, RAPTOR Comouter Code Validation: Phase I.

17.

GGNS Technical Specifications and Bases, Amendment 136.

18.

Drawing C-1000, Rev. 3, Unit 1 General Arrangement Plans and Sections.

19.

Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, dated July 2000.

20.

Calculation XC-Q1J11-97003, Rev. 0, NUREG-1 465 Input Items for NRC Re-baselining.

21.

Calculation XC-Q1l11 -98017, Rev. 1, LOCA Dose Analysis with Revised Source Term.

22.

22A7419AA, Rev. 5, GE Design Specification Data Sheet, Standby Liquid Control System.

23.

Emergency Procedure 05-S-01-EP-2, Rev. 30, RPV Control. LM-0642, Rev. 0, Attachment G. Page 24 of 26

Calculation XC " '-98013 Altactunt Rov. I ,1o12 Transient Pool pH Results CASE I IL s

x C4 DRYWEI l

COurtAlmENT Thk Poolh bltama hdm Hta Bs .tanma Pau Pool Mmt) t Dos(Rad) (WlO3J o11 D #(UVkc) Ds(uV/xJ HC Dm.(*/te) Dou (LkVkc) 1HCJ 70o1*Ipj jC80111 ToblDO)A TMP (F).100(Kw) AMoor O O.OOOOE.02 0.00006+0 OM.00E+00 5.011672Eat O.XE400 19095282E09 77.0 1399 t.13ta28tE 0.3361 O.Ow mOO O.06O.

0.

Oo00OE.O 5.01187260E-0O.OOE+00 1.09S2EM 160.0 12.79

• 3.039112E-o.t 22261E-0 0.0000cf0 OowE4o0 50 31157E0t 2.887SE60 2.MOQIOCO6 160.0 122Jo 239691SE4 053381 1.67BtE-07 0O.o03f O.E0 W t.l79710E6.

21599Eo5 2.180135E45 16O.0 12.79 5.169771E4 I 42978E47 0.006OE00 5.440831460 C.747165 4.773054.0 1b0.0 12.9 5.436750E4 2 O.M22E-07 1.3783E600 1.006IC-05 1.AM0E#12 t8733E412 +/-1702E6-O.0003E400 12122Ei12 3.04W3E-t.126101E05 14M E04 1.29454044 160.0 12.70 2.127902E-2.31 1.0070E4-6 1.37ME6400 1.00680 t.450sE t2

2.

4E+t2 91051608 O.OOO4603 1.2148612 3.05sE45 2.133792E-OS L.8IEV4 .045ME41 100.0 12.79 2l33597E4 3 1.0070E60 1.4049E+00 1.0258e6S 2.18306,12 3&0=35612 27M1E40 8.692SEtO 1203E612 3.O29064 22u8333E5 1.04IE804 1.4 4 159.1 12.80 2.2816E-5 1.0070E40 1.45S1E0oo 1.06446.0 3.05 914E12 328+12 003560E6 6.4871E6.1 1.46E,12 9.0102EMt 2.27868E-05 1.04ot61E4t4 4809 4 155.5 12.84 2.927477E-t2 1.0070EM0 1.642S5O. 1.19E-05 4.7032E+12 4.3312E+12 51988E£ 1.NE412 1.2789E612 IM E4-05 4.1 E3s05 tOt81E4t 1.04809E44 14.2 12.92 4.042E. 18 1.00705-086 1 8E5600 1.312915 5.4482E612 SAM&6.12 0O.73860 2.100612 2.4133EA2 23s2sE05 4s74925-05 1.046E04 1.04801 146.4 12.95 4.87472EE. 24 1.7OEs06 1.9526E400 1.425sEs05 S.73E+12 5S. 4E0*2 c775ssE 2.427tE612 2 0M2 2V3cE05 s4358E-05 1Ot4t4 1480399-4 144.3 12.98 5.43S36E tt 1.0070E6-2.559E.00 1.0622E45 7.2434E12 8.853E.12 t.tS4056 321386.12 4.MW8E+12 3.77886E 7.121sO5E406 l.4O8E.04 ,08996.4A 139.4 13.04 7.1246E6s 72 1.00700E 3.1213E+00 2.278s5E45 7M 3E+12 1.1319E+13 LO3M4E-% 3.6740E#12 5.7S 9E.12 4.5011E405 368.41376405 1.04816E4 14809s4 130.5 13.08 S.AM6MIE-96 1.0070E-06 3.6848E+00 2.8753E-0s 8.513ME12 t34s56t3 1.15M5160 4.O00E,12 .M5216E12 5.07t2E0S 950557.035 1 E0t81E.04 1 4099E4 134.4 13.11 9.502750E 120 1.0070E-4.1830+00 3.053E-05 8.224E612 1.5224E+13 t.2549t54 425386.12 7.974E+12 5.5420ES IMS233E-4t 1.0481E-04 1t460aoE4 132.8 13.13 I.4358sE Iso IDO70-4,7080f 3.5015E05 9.3312E12 1.710SE. 1.3579EM 5 4X5071E12 9.09756E12 8.0318E45 1.149281EM4 1Ot8IE.04 1.0t0 4t 131.3 13.15 1.04102$E 200 1.0070Et06 5.7409E+00 J.1609E45 9.8S84EM12 19521EM1S 1.4903645 4.833812 1.0576E.13 6.814M-05 1295707E44 1.041E04 1.04809E604 129.2 13.18 L.O80ME 240 1.0070E40 6.4313e.00 4.8948EO5 1.0102E#13 2.9$55E13 t 405 5.0405M.12 1.1488E,13 7.075E5 t 391428E04 10t51E404 1.048099E04 127.0 13.20 1.048086E

• 300 I.0070EC t

73688E00 5.379005 1.0601E+13 225066+13 1.U807EOS 5293SA .12 12510Et13 75155E45 1.518712E04 I314-1 1.04 099E44 i28.3 1322 1.048M06E 360 1.0070E0t 8.19990E40 5.9859E45 1.0035.+13 2 E3551213 1.7250.5.S076122 IME2526*13 7.901tE405 tt21547E4J IMIIE414 101B009E4J 125.0 13.24 L.OWN669E 400 1.0070E6t 8.7011E600 6.3518.E05 1.1128.+13 2.4049E#13 t.7595£45 5.203E.12 1.5018E413 8.09336O5 180606E44-. 1.0491El04 1.0 M44 124.3 13.2S 1.048090E 480 1.0070E45 0.5911EE00 7.0015E-OS 1.1483E613 2,4727+13 1Sl0sE40 552726.12 1.4143E613 .3971E405 1.78tIM0-6 I0S4E804 1.048099E4 123.0 13.27 1.040091E 600 1.0070E4M0 1.56E01 7.8CtE45 1.1871E+13 252596+13 1h018E-0. S060612 1.4522,13 8720545 198S45E44 1.08E104 1.049109644 121.1 1320 1.048093E 700 t.070E45 1.1417E.01 8UU4-5 12154EM13 2.5472613 tJ912E45 8.2555612 1.4791E,13 8.O11586OE 1S74317E41 1C481E4 1.04800.0E4 120.3

13.

1.049E > 720 1.0070E40 1.15466E01 8A288E4 1.22 13 250413

1. 405 8285TE412 1.M819E13 8Dt94E465 1.726E44 l1.04104 1,04M90E-120.1 13.31 1.04M4E Flbu1lll.1 nII

--11 &01193*E0 53A 08 S.042263E-60 5.291 DO 2.23723SEC6 S.650 08 9.938219E6.9 8.003 04 3 BM754E-0 8.411 05 1.99OM07E-03 8.94 05 1.95630mr-0 8.7(9 05 1.946042E-09 8II. 05 I.M4l617E609 0.719 a5 1.923S53E03 8.711 4S 1.989732E40 8.701 ,O5 2.082674-3 8..1 45 2.703981E40 8.WS E45 4MD285E-c0 8 395 E45 7M982502E6CO I 80 -04 1.t47163E07 t.7a3 E04 1.0125SIE05 4.99S 04 2.476347E45 .6(A 04 3.461794E.05 4.461 E04 4.706257E-S 4.327 04 5.734533C 4 241 04 6.325705E-05 4.199 .44 7.330164E45 4.13S -04 8.5323E6.S 4 070 044 9262239E-CS 4.C33 E44 9.395320E05 4.u27 0 n (3 ED aU ri cm0 't1i Olt

Calculatlon XC AtMach 1-908013 3, Rov. 1 iageo2of2 CASE 2 DRiYWpi. lWAk~smom bInAkBts NrDspGwamn l,40p0.4i Int G om mtl pots Pool tmh PodJ MI ftm) [ Dosse WV.c) (WO31 0 0.03588 Q1 ft 2 Z03351 3 5 12 Is 24 48 72 98 120 ISO 200 240 300 .400 00 46O C 20 Vwo rv

7 r p

C) 0ff as 00 0\\ 0.00006;0 0.0000E#00 2.2285E-M 1.87ME407 42878607 9.82E-07 3.00356*13 1.0070E-t 30413 1.0070606 310126.13 t1.07060 3.6UEM13 1.o070606 4.85526.13 1.0070E-08 .9399E13 1.0070E4M 7.0CS31513 1.00706.0 1.IOOE.14 1.007 06 I826Ei14 1.00706-08 1.84006.14 1.0070 218836E14 1.0070608 2.5488E614 1.0070E-0 110MEM14 1.0070EM 3.4978E.1 t.oo70EM 4.00326.14 .O0706M 6 4.42S4l14 1.X070E456 4.687SE~1 1.0070E4-0 50723E4tt 1.0070E0t 5.5241E614 1.eo70E08t 5.741EM1 1.0070E0M 6.1391EW4 O.OWOOOEO 00OE+00 000E0060 3.4912E60 3.49066-06 3.70VE4M 4.1438EM 5.64386-06 6.110486-0 8.1 430E-06 1.267060 2.13M86-5 UVIEM 2.520546 2.960l46-3.6112E-O6 4.8 0 5.1UIM4 54255E-6S 6.tME405 6.4212E-5 6.7351E-05 6.7074E 60 E PAWM) i(ReVc) E YUVMIU) I (WVICM) KCIJ DOl$(V/c) Dule (U.cc) jHCf ToMal [18 [C.OH) ToWtsOl.o) Tamp(F) Finle(Hil 5.0l1872F6t Oa0E0400 1.995262E49 77.0 501193464 5.011872E6M 0GOCE+00 1.9226E49 td6.0 S0422636E-0 5.0341576. 2t879E06 281D91CE806 160.0 2.277233E-06 5.17071E0- 2.1596E-05 216013sE05 160.0 s93U82E109 t.44034E-4.74716 45 41747304E.0S 180.0 3 SW47U4M 6.27066.2 &48946,12 2.6853+14 1.1184E614 7M.2E46 25227E11 1.4AUE#12 7U2E-06 2297374E45 1.0294E44 1.029454E04 160.0 20419300Ea 63JO1E0 12 14743612 167256.14 t1214E 14 7.7455£60 2.704E+611 1.48136E12 I9253E05 2.318841E45 1.0481E04 1.04809.04 1500 200056sE-09 7.02SE12 6S.65+12 2U.E0361 1.2076E14 6.O79M20 7.042E011 15515612 t.7497E-08 2.75721E46 1.0481E4t 1.04809E44 I15.1 2.072309-0 7.27176E12 1O055612 J3014E11 1.3850614 925136E0 12732E12 1.73E.12 1.941 5-06 3t438540E.06 1.0461E04 .0.41ODSE44 iS5.5 2050281E09 0.88616.2 7.8910EM2 4.788E4 t4 t.941E14 .1157405 ??241E12 25851,E12 2.4823E60 4.74,12S6OE5 1.048164 1.0480E44 1492 2112865E09 1.03J7E13 7013E612. 6.029214 1504164EI 12276r05 27M E012 28176I12 19574E45 6.4847865 1.046iE04 1.04896E44 148.4 2.2333E-09 1.08MEM13 9.481E12 724996E14 3.0013E#14 1.3196 5 3.02012 3,0785E612 33586E45 6.0949E45 1.0481E4t 1.04860E04 144.3 2.3954s7E09 121486,13 12317E.13 1.10186,5 4.6786M 14 1120E.05 3.79s1E.12 S51A2 2 4.4t3tE5 7955Ut4s4 1.0416 0 1.0489E.04 139.4 3s93262-9 1.m E13 1I470EM13 1.62864D15 6.5772614 1.E4135 42448E612 6.724612 62173E405 9.39173E45 1.0481E4 1.048E40E4 138.5 7.6107030E-1.34216.13 1IA W13 2.m030f35 L12366M14 103406.5 4.55E 12 .O472E12 5.1157E60 1.C5904JIE4 1.0411E64 1.0489E44 13.4l 1.1614tEO6 1.340.13 1.88256,13 240846415 9.524E,4 2.2tOOE5 4.8140612 9.1771E612 6.30UE45 1.1287t44 1041E04 .048M9E04 132.6 I.148,1SEOS 1.42526413 Z20507613 2U.0615 1.1106.15 2.761E45 .OW06 12 1036E6 81126E-05 127515E60 1.0481E44 1.049 .E04 131.3 222703E-00 1.4783E13 12942 13 1414615 1.337615 2118tE45 .3831CM12 1.1891E+13 7.4418645 1.429384E44 1.04614 1.04809644 129.2 3112823E-05 1.6119613 244016.13 I9295lS 1.4441 7724E605.8E 412 12E 3 7.85976 1.629984E44 1.0481E44 1.0499E44 127.9 4818987E-45 1.531*E13 2.699S 13 4.5015£15 1MltE4,1 294S5645 5.3t49412 1.3793E61 18315t4605 1.52513E44 1.048lE41 1.04M9E04 126.3 60424J65 1.5886UE13 2.706,E13 4.9921EtlS 1J132EMI 100326E05 6.M30612 1.444E#,13 1265 1.749199E64 1.04614E1 1.048ME.04 120 7.011083E64 1.U0E12 2.76 1J 6264615 i.6W91IS 3.114E45 .15546E12 1.47ME88 3 6.313605 1.013E6 1.0481E44 1.046ME44 124.3 7.S4214E45 I.8319031 23 1324E61 6.73356lS ZO0E05 3.28376E5

• 6.355412

1. 513 9.1106E406 1.892567 44 1.048144 1.04aM E44 123.0 6.4t1650.E45 1.6811631 2*1613 620615 1427+IS 1 3025.E05 6.071.E12 157E1 9.40496E45 1.83049E4 1.0481E44 10489E44 121.4 9.3t9551E5 1.7098E613 2.1376.13 6tI DE615 2.2101E15 3.4t92E6-5 8.77612 157161 95.t3145 2.03928E44 1.0l1ME4t 1.048 E44 120.3 99Ct34265 1.7148E.13 2919 1M 8.6116E415 2.22066S 3.4tOIE45 8.1103612 1.5735E13 9.139E5 2.045323E41 1.048.E44 1.0489E.04 120.1 1 O =EO04 p11 5.300 5 227 6 650 8003 8.4 I1 8 693 8 US a 615 8 515 8 621 8.41S 8119 S 915 t 910 4.4li t.317 J.?19

• .154 t.122 4.0r5 t.0?9 ON

I CALCULATION NO. LM-0642 IREV. NO. I lPAGENO.H1 of HI Computer Disclosure Sheet Discipline Nuclear Client:: Exelon Corporation Date: September 2005 Project: Limerick Generating Station pH AST Job No. Program(s) used Rev No. Rev Date Calculation No.: LM-0642, Rev. 1 Excel Spreadsheet included N/A N/A Status [ ] Prelim. [X] Final [ Void WGI Prequalification [ I Yes [ X I No, the Excel Spreadsheet qualification is included herein Run No. N/A

== Description:== The Excel spreadsheet utilized is presented In Attachment C included with the Calculation. The cell formulae, presented in Attachment D of this Calculation, are based on the methodology developed for the equivalent calculations done for the Grand Gulf Nuclear Station, as described in Attachment F and G Included with the Calculation. The accuracy of translation of these formulas is verified by duplicating the Grand Gulf calculation, as presented in Attachment E included with the Calculation. Analysis

Description:

The Excel spreadsheet uses input values of pool volume, I and Cs Inventory, onset of gap release, absorption coefficients, cable surface area and Hypalon jacket thickness, pool temperature as a function of time, and integrated drywell and containment air beta and gamma doses as a function of time. It calculates HI, Nitric acid, hydrochloric acid (from cable radiolysis), H+, CsOH, OH, and pH in the suppression pool as a function of time. This calculation Is done with consideration of sodium pentaborate addition (as an Input quantity). The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established. By: On: March 2004 - September 2005 Run by: Harold Rothstein Checked by: Paul Reichert I D L9 Approved by: Harold Rothstein /-t

ADDITIONAL ATTACHMENTS TO 10-10-05 Letter: Supplement to Request for LAR Application of AST 03 AST - LM-0642 Rev 1 pH Att B (Pages 6-9)

Isotopic Class Nuclide 9 6 6 8 8 8 9 9 7 7 3 3 3 2 2 2 2 2 1 1 1 1 9 9 9 7 9 9 8 9 8 8 8 8 3 7 7 7 7 4 4 5 5 5 5 7 4 4 4 4 4 4 1 1 9 9 9 9 9 9 Am-241 Ba-139 Ba-140 Ce-141 Ce-1 43 Ce-1 44 Cm-242 Cm-244 Co-58 Co-60 Cs-1 34 Cs-136 Cs-37 1-131 1-132 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Kr-88 La-140 La-141 La-1 42 Mo-99 Nb-95 Nd-147 Np-239 Pr-143 Pu-238 Pu-239 Pu-240 Pu-241 Rb-86 Rh-105 Ru-103 Ru-105 Ru-106 Sb-127 Sb-129 Sr-89 Sr-90 Sr-91 Sr-92 Tc-99m Te-127 Te-127m Te-129 Te-129m Te-131m Te-132 Xe-1 33 Xe-135 Y-90 Y-91 Y-92 Y-93 Zr-95 Zr-97 24 Hours 96 Hours 720 Hours 1.31E-02 5.47E-02 4.15E-01 4.41 E+02 4.41 E+02 4.41 E+02 9.05E+03 3.48E+04 1.45E+05 2.11E+02 8.52E+02 4.98E+03 1.53E+02 3.48E+02 4.03E+02 1.81E+02 7.49E+02 5.51 E+03 5.96E+00 2.47E+01 1.77E+02 1.15E+00 4.79E+00 3.63E+01 3.63E+00 1.49E+01 9.98E+01 4.36E+00 1.82E+01 1.37E+02 1.14E+04 4.75E+04 3.56E+05 3.38E+03 1.31E+04 5.51E+04 1.01 E+04 4.24E+04 3.21 E+05 7.24E+04 2.67E+05 8.56E+05 1.11 E+04 1.11 E+04 1.i1 E+04 1.05E+05 1.90E+05 1.99E+05 3.76E+03 3.76E+03 3.76E+03 4.96E+04 5.47E+04 5.47E+04 3.56E+03 1.48E+04 1.12E+05 1.45E+04 1.49E+04 1.49E+04 5.34E+03 5.34E+03 5.34E+03 2.35E+04 2.36E+04 2.36E+04 7.85E+01 1.95E+02 2.42E+02 1.66E+01 1.69E+01 1.69E+01 4.68E+00 4.68E+00 4.68E+00 1.04E+03 3.10E+03 4.91E+03 8.70E+01 3.52E+02 2.10E+03 3.32E+01 1.26E+02 4.86E+02 2.72E+03 7.68E+03 1.12E+04 7.51 E+01 2.90E+02 1.24E+03 1.22E+00 5.09E+00 3.86E+01 5.86E-02 2.05E-01 1.47E+00 1.26E-01 5.28E-01 4.01 E+00 2.45E+01 1.02E+02 7.71 E+02 1.11E+02 4.39E+02 2.16E+03 4.93E+02 1.16E+03 1.37E+03 9.89E+02 4.01 E+03 2.45E+04 1.52E+02 1.57E+02 1.57E+02 3.71E+02 1.54E+03 1.14E+04 9.90E+02 3.21 E+03 6.28E+03 8.88E+02 9.12E+02 9.12E+02 4.94E+03 2.02E+04 1.29E+05 6.29E+02 2.62E+03 1.98E+04 2.77E+03 3.42E+03 3.43E+03 8.28E+02 8.30E+02 8.30E+02 3.24E+02 3.50E+02 3.50E+02 4.72E+02 5.78E+02 5.79E+02 1.81 E+02 7.45E+02 5.21 E+03 1.39E+02 1.39E+02 1.39E+02 7.73E+02 3.12E+03 1.84E+04 1.89E+03 4.11 E+03 4.63E+03 1.63E+04 5.08E+04 8.93E+04 4.81E+05 1.66E+06 4.01E+06 5.97E+04 7.24E+04 7.25E+04 5.68E+00 1.67E+01 2.60E+01 6.42E+01 2.63E+02 1.72E+03 1.16E+01 1.18E+01 1.18E+01 2.36E+01 2.98E+01 2.98E+01 8.68E+01 3.56E+02 2.35E+03 5.10E+01 8.23E+01 8.40E+01 24 Hours 96 Hours 720 Hours 1.10E+02 4.56E+02 3.46E+03 3.68E+06 3.68E+06 3.68E+06 7.55E+07 2.90E+08 1.21E+09 1.76E+06 7.11E+06 4.16E+07 1.28E+06 2.90E+06 3.36E+06 1.51E+06 6.25E+06 4.60E+07 4.97E+04 2.06E+05 1.48E+06 9.59E+03 3.99E+04 3.03E+05 3.03E+04 1.24E+05 8.33E+05 3.64E+04 1.52E+05 1.14E+06 9.49E+07 3.96E+08 2.97E+09 2.82E+07 1.09E+08 4.60E+08 8.46E+07 3.53E+08 2.68E+09 6.04E+08 2.23E+09 7.14E+09 9.22E+07 9.23E+07 9.23E+07 8.79E+08 1.59E+09 1.66E+09 3.13E+07 3.13E+07 3.13E+07 4.14E+08 4.56E+08 4.56E+08 2.97E+07 1.24E+08 9.37E+08 1.21 E+08 1.25E+08 1.25E+08 4.45E+07 4.45E+07 4.45E+07 1.96E+08 1.97E+08 1.97E+08 6.55E+05 1.63E+06 2.02E+06 1.39E+05 1.41 E+05 1.41 E+05 3.91 E+04 3.91 E+04 3.91 E+04 8.71E+06 2.58E+07 4.10E+07 7.26E+05 2.94E+06 1.75E+07 2.77E+05 1.05E+06 4.05E+06 2.27E+07 6.40E+07 9.32E+07 6.26E+05 2.42E+06 1.04E+07 1.02E+04 4.25E+04 3.22E+05 4.89E+02 1.71 E+03 1.23E+04 1.05E+03 4.40E+03 3.35E+04 2.04E+05 8.49E+05 6.43E+06 9.26E+05 3.66E+06 1.80E+07 4.11E+06 9.64E+06 1.14E+07 8.25E+06 3.35E+07 2.04E+08 1.27E+06 1.31 E+06 1.31 E+06 3.10E+06 1.29E+07 9.52E+07 8.26E+06 2.68E+07 5.24E+07 7.41 E+06 7.61 E+06 7.61 E+06 4.12E+07 1.68E+08 1.08E+09 5.25E+06 2.18E+07 1.66E+08 2.31E+07 2.86E+07 2.86E+07 6.90E+06 6.92E+06 6.92E+06 2.70E+06 2.92E+06 2.92E+06 3.94E+06 4.83E+06 4.83E+06 1.51 E+06 6.22E+06 4.35E+07 1.16E+06 1.16E+06 1.16E+06 6.45E+06 2.61E+07 1.54E+08 1.58E+07 3.43E+07 3.86E+07 1.36E+08 4.24E+08 7.45E+08 4.02E+09 1.39E+10 3.35E+10 4.98E+08 6.04E+08 6.05E+08 4.74E+04 1.39E+05 2.17E+05 5.36E+05 2.19E+06 1.43E+07 9.71 E+04 9.82E+04 9.82E+04 1.97E+05 2.48E+05 2.49E+05 7.24E+05 2.97E+06 1.96E+07 4.25E+05 6.86E+05 7.01 E+05 8.343E+03

Class 9 6 6 8 8 8 9 9 7 7 3 3 3 2 2 2 2 2 9 9 9 7 9 9 8 9 8 8 8 8 3 7 7 7 7 4 4 5 5 5 5 7 4 4 4 4 4 4 9 9 9 9 9. 9 Isotopic Nuclide Am-241 Ba-139 Ba-140 Ce-141 Ce-143 Ce-144 Cm-242 Cm-244 Co-58 Co-60 Cs-1 34 Cs-136 Cs-t37 1-131 1-132 1-133 1-134 1-135 La-1 40 La-141 La-142 Mo-99 Nb-95 Nd-147 Np-239 Pr-143 Pu-238 Pu-239 Pu-240 Pu-241 Rb-86 Rh-105 Ru-103 Ru-105 Ru-106 Sb-127 Sb-129 Sr-89 Sr-90 Sr-91 Sr-92 Tc-99m Te-127 Te-127m Te-129 Te-129m Te-131m Te-132 Y-90 Y-91 Y-92 Y-93 Zr-95 Zr-97 24 Hours 3.19E-02 1.07E+03 2.20E+04 5.14E+02 3.72E+02 4.39E+02 1.45E+01 2.80E+00 8.83E+00 1.06E+01 2.77E+04 8.22E+03 2.47E+04 1.76E+05 2.69E+04 2.56E+05 9.14E+03 1.21 E+05 1.91 E+02 4.04E+01 1.14E+01 2.54E+03 2.12E+02 8.09E+01 6.62E+03 1.83E+02 2.97E+00 1.42E-01 3.06E-01 5.95E+01 2.70E+02 1.20E+03 2.41 E+03 3.70E+02 9.03E+02 2.41 E+03 2.16E+03 1.20E+04 1.53E+03 6.75E+03 2.01E+03 7.89E+02 1.15E+03 4.40E+02 3.38E+02 1.88E+03 4.60E+03 3.97E+04 1.38E+01 1.56E+02 2.83E+01 5.73E+01 2.11 E+02 1.24E+02 96 Hours 720 Hours 1.33E-01 1.01 E+00 1.07E+03 1.07E+03 8.46E+04 3.52E+05 2.07E+03 1.21 E+04 8.46E+02 9.80E+02 1.82E+03 1.34E+04 6.00E+01 4.31 E+02 1.16E+01 8.82E+01 3.62E+01 2.43E+02 4.42E+01 3.34E+02 1.16E+05 8.67E+05 3.18E+04 1.34E+05 1.03E+05 7.82E+05 6.50E+05 2.08E+06 2.69E+04 2.69E+04 4.63E+05 4.83E+05 9.14E+03 9.14E+03 1.33E+05 1.33E+05 4.74E+02 5.89E+02 4.12E+01 4.12E+01 1.14E+01 1.14E+01 7.54E+03 1.20E+04 8.57E+02 5.1 OE+03 3.07E+02 1.18E+03 1.87E+04 2.72E+04 7.06E+02 3.03E+03 1.24E+01 9.39E+01 4.98E-01 3.58E+00 1.28E+00 9.76E+00 2.48E+02 1.88E+03 1.07E+03 5.26E+03 2.81 E+03 3.33E+03 9.76E+03 5.95E+04 3.81 E+02 3.81 E+02 3.75E+03 2.78E+04 7.81 E+03 1.53E+04 2.22E+03 2.22E+03 4.91E+04 3.14E+05 6.37E+03 4.83E+04 8.33E+03 8.34E+03 2.02E+03 2.02E+03 8.51 E+02 8.51 E+02 1.41 E+03 1.41 E+03 1.81 E+03 1.27E+04 3.38E+02 3.38E+02 7.60E+03 4.48E+04 1.00E+04 1.13E+04 1.24E+05 2.17E+05 4.06E+01 6.33E+01 6.40E+02 4.18E+03 2.86E+01 2.86E+01 7.24E+01 7.25E+01 8.66E+02 5.73E+03 2.00E+02 2.04E+02 24 Hours 96 Hours 720 Hours 1.10E+02 4.56E+02 3.46E+03 3.68E+06 3.68E+06 3.68E+06 7.55E+07 2.90E+08 1.21E+09 1.76E+06 7.11E+06 4.16E+07 1.28E+06 2.90E+06 3.36E+06 1.51E+06 6.25E+06 4.60E+07 4.97E+04 2.06E+05 1.48E+06 9.59E+03 3.99E+04 3.03E+05 3.03E+04 1.24E+05 8.33E+05 3.64E+04 1.52E+05 1.14E+06 9.49E+07 3.96E+08 2.97E+09 2.82E+07 1.09E+08 4.60E+08 8.46E+07 3.53E+08 2.68E+09 6.04E+08 2.23E+09 7.14E+09 9.22E+07 9.23E+07 9.23E+07 8.79E+08 1.59E+09 1.66E+09 3.13E+07 3.13E+07 3.13E+07 4.14E+08 4.56E+08 4.56E+08 6.55E+05 1.63E+06 2.02E+06 1.39E+05 1.41E+05 1.41E+05 3.91 E+04 3.91 E+04 3.91 E+04 8.71E+06 2.58E+07 4.10E+07 7.26E+05 2.94E+06 1.75E+07 2.77E+05 1.05E+06 4.05E+06 2.27E+07 6.40E+07 9.32E+07 6.26E+05 2.42E+06 1.04E+07 1.02E+04 4.25E+04 3.22E+05 4.89E+02 1.71E+03 1.23E+04 1.05E+03 4.40E+03 3.35E+04 2.04E+05 8.49E+05 6.43E+06 9.26E+05 3.66E+06 1.80E+07 4.11E+06 9.64E+06 1.14E+07 8.25E+06 3.35E+07 2.04E+08 1.27E+06 1.31 E+06 1.31 E+06 3.1 OE+06 1.29E+07 9.52E+07 8.26E+06 2.68E+07 5.24E+07 7.41 E+06 7.61 E+06 7.61 E+06 4.12E+07 1.68E+08 1.08E+09 5.25E+06 2.18E+07 1.66E+08 2.31 E+07 2.86E+07 2.86E+07 6.90E+06 6.92E+06 6.92E+06 2.70E+06 2.92E+06 2.92E+06 3.94E+06 4.83E+06 4.83E+06 1.51 E+06 6.22E+06 4.35E+07 1.16E+06 1.16E+06 1.16E+06 6.45E+06 2.61E+07 1.54E+08 1.58E+07 3.43E+07 3.86E+07 1.36E+08 4.24E+08 7.45E+08 4.74E+04 1.39E+05 2.17E+05 5.36E+05 2.19E+06 1.43E+07 9.71E+04 9.82E+04 9.82E+04 1.97E+05 2.48E+05 2.49E+05 7.24E+05 2.97E+06 1.96E+07 4.25E+05 6.86E+05 7.01 E+05 3.43E+03

ADDITIONAL ATTACHMENTS TO 10-10-05 Letter: Supplement to Request for LAR Application of AST 04 AST - LM-0642 Rev 1 pH Att B (Pages 10-13)

ADDITIONAL ATTACHMENTS TO 10-10-05 Letter: Supplement to Request for LAR Application of AST 05 AST - LM-0642 Rev 1 pH Aft C,D,&E.

pH vs. Time - BEGINNING OF CYCLE 10.00~ 9.00 -Di-8.00-7.00-6.00 .= 5.00wihSC 4.00 3.00 2.00-1.00 0.00-1 10 100 1000 Time (Hours) LGS pH CALC.xls BOC Graph

pH vs. Time - END OF CYCLE 9.00 8.00 7.00 6.00 5.00 I _X0 l: =_~~~~~~*wt ____SL=_CS _-'--00 4.00 3.00 2.00 1.00 0.00 1 10 100 1000 Time (Hours) LGS pH CALC.xls EOC Graph

UMERICK GENERATING STATION TRANSIENT POOL pH CACLCLATION l A I B I C D E l F l l H J I K L i M I N O I UMERICK pH CALCULATION pHTRANStENT BEGINNINGOFCYCLE I Cable Data 22 i 2 _ I I Liear Absorption CoefficientS 4 S..., [cm) 2.668.443 Cable Surface [trays]- Drywel + 10% ronthgeney 3 VpOOL 4.955E.06 Liters [175,000 ft'[" _M Ui l 1t.980E-02 11cm SA [cm] 133.422 Cable Surface [free alr]Dr-rywell+10% contingency 4 ml 1.700 E.02 lodine Imventory [9-at s[ BOC Ubft ab. 52.08 1/cm So [cm' 0 Cable Surface [trays]. Supp. Pool + 10% contingency 5 mC 1.600E603 Cesum Inventory [g-atoms] BOC9 Ur* 3.75E-05 1/cm S,,. [cm) 0 Cable Surface [freeiq a Supp. Pool + 10% contingenrcy 6 tgw 3.36tE-02 Onset ot Gap release [hrs II 0099 1km I I I I 7 1310.421cm th [cm] 0.629 21Mypaion Jacket TrlIcknee - I I I I INTEGRATED DOSES if -I- + 1-1- 1310.421cm + 10 Bela+ nrna' Gamma' I Betal Garmrma'" Beb" Fr 11t TiME lPOOL Tem~pT POOL DDRYWELL I DRYWELL Supp. Pool AiR Supp. Pool Ai LrL'-A ne-1 ot/ I.~... _tR t~ EiLL - LI SNTAWCTota [HN] I LI4sU"] 12 Hours Lreg r Mrad ReVIrn I Mevkcm Mevkcmr Mevkcm g9inlter I g-os/ter g-moISter g-moistiter g-moliter I a-ro/iter o-ons/bter i go isliter 13__0 ___95I 14 1 187.2 15

• +121 5.050E-074 16 0.000E.00i 0.000E.001 1.322E-051 7.094E-0!

19 12 24 48 199S! 193.1 188.6 186.6 18.6 1 86.6 2.158E-01 3.988E-01 8.293E-01 1.086E400 1.292E+00 1.883E.00 8.368E.121 3.6896E.12i 8.368E.121 3.689E, 3.408E-06 7.1 .+13 5.146E-07i 7.927E-0r 9.432E-06 1.135E-05 1.709E-05 2.141E-05 2201 E-! 4208E-0! 5.256E4-0 6.060E-0! 8.348E-0! 1.006E-04 0.000Es001 I 5.709E+131 3.409E+131 5.709E+131l 24 =.: 5.615E613i 5.146E-071 2.192E-051 2S E041i 0.000Ei001 0.0004001 2 186.6 3.942E6s0 1.135E.14 72746E13 I., 186.6 4.3866.00 l247,14 79286.13 t 7.094E-0! 7.094E-0! 7.094E-4! 7.094 E4-7.094E-5! 7.094E-O4 E-071 3.182E-Of 3.975E-05 E-0713 14 9.436E613 1.538ME14 9.436E+131 5.146E-071 0.0001.00 3.347E-041 7 32 4801 186.61 6.438E6 1.133+,141 5.146E4071 5.330E-0! 0.000E+001 4.400E-041 7.094E6-! 35 720 186.61 8.094E+001 2.198E+141 1201E+14 38 16 Seeattachment B for gamma tree paths 41 1 41id, Table A-1 11-98013 Rev2, Section 5.7 11-98013 Rev.2, Section 5-7 11-98013 Rev.2. Section 5-7 IC( 46 3-C 12 Ibid. Equation 3-Se: Entery CaIc. XC-O1 II11-I 51 UFSAR TOU i Pool volume of 134.600 cu t y Core Cooling System sources, roundd up to 175,000 cu. FL 54 LMU0642. Rev. 1, Attachment C, Page C-i of C-7

LIMERICK GENERATING STATION TRANSIENT POOL pH CALCULATION P S I T U V W X Y Z AA AB I pH TRANSENT BEGINNING OF CYCLE 2 Cable Daa 3 2.425.858 Cable Surface [Trays - DRYWELL [cm2j 4 12t29 Cable Surface [Free aIr - DRYWELL [cm22 1008.67 9. moas Na2BpOWI0HgO Addede_ 5 0 Cable Surface [Free arl. Supp. Pool [crn2l 10088.71 g.oatwS total boron" e 0 Cable Surface [Trays - Supp. Pool [cm2j 7 __F 8 pH EFFECT OF ADOITION OF SODIUM PENTABORATE STANDBY LtUtUD CONTROL [SLCj SOLUTION 9 I tO1 .tw t Acid t Total H+ -ITO i(Kw) Roo0tx NeTHt pH K. I 9-eq._... Ns,B,,tO.I0HOj Borate Boric Acid I pK. pH 12 tgortstlIter I g4ortser I Before SLC 8.17 1 Net [H+I

• Vor.

2.485E+0O 5.91 SE-02 3.379E-02 3.323E-02 4203E-02 6.019E-02 2.033E-01 2268E+01 9-equS. I Q-equF. 80941 9.161 8.55 4o9,oK. 171 7.094E-051 1.237E+011 2.118E-05O 1008.7 1008.7 1008.7 1008.7 1008.7 1008.7 2017 2017 2017 1995 80691 8.881 8.28 20 7.094Ef05 1244E.01 7.086E6.0 4.578E-06 5.341 1 211 7.094E435 7.092E-OF 1.f 221 - - 7.094E-05 7.094E4.! 1 0 0 8.7, 16 5 8 4 3 .9 8 2 251 7.094E-051 1.250+,011 7.094E-051 1.130E-044 3.951 1.223E-091 5.599E+02 1008.7 1198 8891 8.91 8.tl4 1009.7 t083 9003 8.91 7.99 301 7.094E-051 1.250E01 I 7.094E-051 2.46eE-04 3.611 1 1 223E+03 1.307E+03 1.462E403 1.670E.03 331 7.094E-05f 1.250E+0Ij 7.094E4051 3.371 E041 3.471 1 1008.7 347 36 391 44 47 50 LM.0642, Rev. 1. Attachment C, Page C-2 of C-7

UMERICK GENERATING STATION TRANSIENT POOLr pH CALCULATION A I B I C I D l E F lI K I L M I N I 0 LIMERIC pH CALCULATION pH TRANSIENT ENDOFCYCtE Cable Data 221 2 Linear Absorption Coefficients SAW (cm 2] 2,668,443 Cable Surface [rays]- Dryweal + 10% contlirc 3 Vpoo. 4.955E+06 LAWS 11 75,000 ttl Ubft 's 1.980E-02 Ikm SAI. [r1n2 133,422 Cable Surface [tree air Drywetl + 10%contingency 4 ml 2.900E.02 Iodine Irrverrorylg atornslEEOC` Ub_______ 52.08 1km So w e oma l 0 Cable Surface tMays]- Supp. Pool + 10% contingency 5 mC, 3.200E.03 Cesium hventory (9 toms] EOCS U9ara A 3.75E-05 1km Sa. [cm21 l Cable Surface [free air - SupP. Pool + 10% contingency 8 tM 3.361E-02 Onset of Gap rele hraU 0.099 I/cm 7 r,_ 1310.42 cm th (Cm] 0.70514 Hnalo Jacket frickness 8 r _ W,,,, 'A POO.LA" 1310.42m 9 INTEGRATED DOrSES 10 GammaBe's aIrrra Beta" Garnrna Beta's From Beta From Gamma From Beta From Gamma 11 TIME POOL Temp POOL DRYWELL DRYWELL Supp. Pool AIR Supp. Pool AIR 1H'F NO [

RiO'

[HC]B o LL wra' [HC otA [H-t] fflr ri otal (H+. (CsO] ~~~~~ .^_ A A...... iA A i A }l_vA_ [HNO.. ,] 12 Hours I Ueg F MMd Mev/cm-Mev/cm-MevIcm Mev/cm-9-mo/iter Ig-mosItner g-mowlier -mnos/llter I g-mo/iter i-molsliter glonsifter I g-molshIter 15 1.0IE-01 3.956E411 8.675E-07 6.45tE-Ot 0.000E.001 0.000E.001 1.392E-051 1.422E-04 18 2.0331 4.121E+1 9.037E-07 E+00 t 17 3 18 199.91 - 2.1588-011 8l.368.121 3.68E 212 8.368E +2 369 SOM-fl IAOF,1 R.97F12 .808.1e707FI2 I 1.575E-O0 1.850E-06 3.408E-06 7.124E-08 9.432E-06 E+00i3 20 193.1 1.086E+00 3:1 3 8 13 I 1 0 I 91:1 4 1 3 2 5.709E+131 3.4 0.000E+001 0.000E.001 8.186E-05 1.448E804 1.1 35E-05 E+001 i 1.448E-04 3.409E+131 8.778E-07i 1.375E-C5 1.709E-05 2.141 E-05 2.501 E-05 2.81 SE-5

+00 3 1.U3448-4 04 34 25 1201 186.61 3.002E+001 8.778E+131 5.615E+13 8.778Et13 5.615E+131 8.778E-071 2.192E4-5 1.431 E-04 0.000E+001 0.000E+001 1.991 E-041 1.448E-04 E+131 3.1 E+131 8.778E-071 28 4.359E+00 4.939E+00 5.473E+00 5.809E+00 8.438E+00 7.301 E+00 3.647E-05 3.975E-05 4.389E-05 4.732E4-5 1.538E+141

- 9.436E+131 1.538E+141 9.436E+131 8.778E-071 3.995E-O5 0.00OE+001 0.000E +001 3.440E041 1.448E-04 33 6001 18i.e 2.000E+141 1.133E814 2.000,E141 O.OOE+00 O.OOOE+001 4.421E-041 1.448E-04 414 000)E8+00 0.0 414 1201E+141 1 5 6.020E-051 - 3.583E-04 0.0002+00 0.0 36 Add dissociation constant ronm: Er

nterv Calc.XC-01I11 -98013 F I GGNS-99 39 42 4

11 12 13 Ibid. Equation 3-2b Ibid, Equation 3-4d 13 Ib6kd.Table A-1 l ased S I Atbachment B at, .7 2t _age c-e oithis attachment i 22 Cable Data from Attachment A. Ibid, Equation 3-Sd; Enteray Calz. XC-t1 1 1 1-98013 Rev2, Section 5-7 I 'idg atlon 3-Sd-Erne Cat. XC-01 1111-98013 Rev2 Section 5-7 Ibid. Equation 3-5e; Entergy Calc. XC-t1 1111-98013 Rev2 Section 5-7; Intial 5.3 pH value (beforeCesCum addition) from UGS UFSAR Sec. 6.1.1.2 Max. Suppression Pool volume from Calc. body section 4.4 hchdi UFSAR Table 62-4A HWL Suppresilon Pool volume of 134.600 cu tL ReactorCoolant Systm Liqud Volume of 13.109 cu I and low-esure Emercen Core Cooing System soures. oundd up tot 75,000 cu.FL I I = 50 53 (For Aittchment B he LLNTT P i~ LM0642. Rev. 1, Attachment C. Page C-3 of C-7

LIMERICK GENERATING STATION TRANSIENT POOL pH CALCULATION P 0 a I S I T I U I V W X Y l ZA AS I l pH TRANStIENT ENDt OF CYCIL£E 2 Cable Data 22 3 2.425.858 Cable Surface (Trays]. DRYWELL [crm2 4 12129 Cable Surface [Free alr - DRYWELL [cm2_ 1008.67 g. rols NaB,O,r, 10H2O Addee_ 5 0 Cable Surface [Free al. Suop. Pool [cm2j 10086.71 g.atorra total bo a 0 Cable Surface rrral - Sump. Pood [crrl _ e 1pH EFFECT OF ADDO-ON OF SODIUM PENTABORATE STANDBY LtOUtO CONTROL ISLC] SOLUTION 9 10 .o ._ 5 Acid 11 Total [OH+1 -LOG(K. 7 Root'x Net [IK e] pH K. Na2B,00,It1OH20 Borate Bovlc Acid pK. pH 12 9g n-flter I I g-lona'tIer Belore SLC Net [HK+1*Vpo gmoh I g-equhv. g-equiv. I 40og,0 E-496 1.496E-04 E6 1.470E4;2 17 1.448E-041 1.237E+011 2.296E4!51 3.465E-091 8.461 1.300E-091 1.717E-02 1008.7 1008.7 1008.7 1008.7 1008.7 1008.7 20171 80691 8.891 829 8.28 8_8 20 1.448E.04 11244E+01 _8.1886E051 5.807E-09 8.241 1.2e1E-09 2.878E.02_ 20171 80691 8.901 8.30 21 1.448E-04 9 e257E4091 8201 1223E46__ 3.1OIE-( 22 1.448E-04 1 2.114E-081 7.671 1223E6-091-1.047E4-8.911 8.30 25 1.448E-041 1250E+011 1.448E-04 5.433E-051 4261 1223E6-09 2.692E+02 1008.1 1008.i 1008.1 1008.1 1008.1 1008.1 1008.1 100&1 1008.1 1748 1e6t 1465 134: 1178 1030 83391 744 8.911 8.10 30 1.448E-041 1250E.01 1.448-E041 1.992E6041 3.701 1.223E6091 9.873E+02 77 93te 8.91 7.83 9543 8.91 7.67 _W 331 1.448E-041 1250E+011 1.448E-041 2.973E-041 3.531 1223E6-091 1.473E+03 E4c 36 39 441 471 50 _ LM-0142. Rev. 1, Attachment C. Page C-4 of C-7

Weight % Sodium Pentaborate in Solution vs. Specific Gravity @ 80 F 1.075 - y 0.5x 0.99 1.07 - 1.065 U-0 1.06-e Data between 1 1wt% and to 15wt% is from LGS _ 1.055 Procedure-Noi-GH-CG105, Rev. 5, Table CH-C-105-3 0. U, (Ref. 5.11) 1.05 - 1.045 - 1.04 10.00% 11.00% 12.00% 13.00% 14.00% 15.0'0% Weight % Sodium Pentaborate in Solution LM-0642, Rev. 1, Attachment C, Page C-5 of C-7

LIMERICK GENERATING STATION TRANSIENT POOL pH CALCULATION A B I C D E 1 Available Boron Calculation 4 Ouantity Value BasIs 6 Volume of Solution Igal). 1 5000E+03 Assumed Minimum (LGS Tech Spec Sect 4.1. 7 clnricates 3180 arons) 1 8 wt% of NaB3,O 1,10H=0 10% LGS Technical S Iecficalton figure 31.5-1 9 Spectiic tr vtty (gmfc - 1.0485 Table CH-C-105-3 10 ConversionFactor(cmm/gal). 3785.41 T 11 Conversion Factor (Ibs/gm) 0.0022 13 Total Mass of Solution (Ibs). 1.3125E+04 14 Total NsaB,.01tOH,O (lbs). 1.3125E+03 15 Total NsaB,qO, tlOHO (gm). 5.9535E+O5 18 Total NaWB,00 1610*1-,0 17 gm -mofes). 1.0087E+03 18 Total Boron (grn-atoms). 1.0087E=04 20 21 TotalAvaltable Boron fibs). 2.4041E+a2 22 lAvafable Boron (gmftonm)r 1.0087E+04 23 24 B-10 Enrichment. 19.90% 25 26 Molar Mass Total Molar Mass of 27 _(gnvmole) Na&2,0O, t10OH,O 28 Sodurn 22.99 590_2330 29 Boron t1@8110 30 Oxygen 16.00 31 Hydrogen 1.01 32 Boron-10 10.0129 33 Boron-11 11.0093 34 35 Percentage of Total Boron. 18.3165% LM-0642, Rev. 1. Attachment C. Page C-6 of C-7}}