ML042930715
| ML042930715 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/23/2004 |
| From: | Metcalf J Energy Northwest |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GO2-04-170 NE-02-03-15, Rev 0 | |
| Download: ML042930715 (30) | |
Text
ENERGYC BDC/PDC Page
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ENERGYCALCULATION NORTHWEST COVER SHEET People -Vision-Bolutions Equipment Piece No.
Project Page Confd on Page Columbia 1.0 1.1 Discipline Calculation No.
Containmnent NE-02-03-15 Nuclear Quality Class I I Remarks Non-Proprietary Version TITLEISUBJECTIPURPOSE T~ileSubjed S
POST-LOCA SUPPRESSION POOL pH Purpose The purpose of this calculation is to determine the pH of the Columbia Generating Station containment water pool as a function of time following a DBA-LOCA during the initial phase of the accident prior to the addition of sodium pentaborate via the SLC system (Part A), and out to 30 days after the addition of sodium pentaborate (Part B).
CALCULATION REVISION RECORD REV STATUSI REVISION DESCRIPTION INITIATING TRANSMITTAL NO.
F.P. OR S DOCUMENTS NO.
O F
ORIGINAL ISSUANCE PDC 240&;
PERFORMANCEIVERIFICATION RECORD REV VRFE YDT NO.
PERFORMED BYIDATE VERIFIEAPPROVED BYIDATE 0
J. M 7k'! R. Hobbins 71X
/3V R. Hobbinsj 0. etayn~z; z~Aff i~.30 Study Calculations shall be used only for the purpose of evaluating alternate design options or assisting the engineer in performing assessments.
ENERGY Page No.
Contd on page
) NORTHWEST CALCULATION INDEX 1.1 1.2 People* VisionB Solutions Calculation No. NE-02-03-15 Revision No.
0 ITEM PAGE NO. SEQUENCE Calculation Cover Sheet Calculation Index Verification Checklist for Calculations and CMR's Calculation Reference List Calculation Output Interface Documents Revision Index Calculation Output Summary Calculation Method Sketches Manual Calculation 1.0 -
1.1 -
1.2 -
1.3 -
1.4 -
2.0 -
3.0 -
4.0 -
5.0 -
1.31 5.13 APPENDICES:
Exhibit 1: Radiolysis of Water Input and Output Exhibit 2: Radiolysis of Cable Input and Ei.
- 3. A..
Exhibit 3: Add Acid Input and Output - Base Case Exhibit 4: Add Acid Input and Output - Reduced Boron Case Details for Assumption 9 Gamma + Beta Power Added to Containment Water and Insulation Jacket Material Appendix Appendix Appendix Appendix Appendix Appendix Appendix A
I Pages B
I Pages C
1 Pages D
I Pages E
2 Pages F
I Pages G
1 Pages Molar Concentration of Chemical Species Affecting Short-and Long-Term Pool pH Appendix Pages
PaNoI7 on'd onpage NORTHWEST VERIFICATION CHECKLIST -
12 1 3 People-Vision Solutions a
N I Revision No.
0 CalculationlCMR t
2
- Revision 0
was verified using the following methods:
i[
Checklist Below a
Alternate Calculation(s)
Checklist Item Verifier initials Clear statement of purpose of analysis........................................................................
Methodology is clearly stated, sufficiently detailed, and appropriate for the proposed application..............................................................................................
j Does the analysis/calculation methodology (including criteria and assumptions) differ from that described in the Plant or ISFSI FSAR or NRC Safety Evaluation Report, or are the results of the analysis/calculation as described in the Plant or ISFSI FSAR or NRC Sa affected?
IN Yes 0 No............
l.......................
Vag_
If Yes, ensure that the requirements of 10 CFR 50.59 and/or 10 CFR 72.48 have been processed in accordance with SWP-LIC-02........................................
A h/
Does the analysis/calculation result require revising any existing output interface document as identified in DES-4-1, Attachment 7.3?
1l Yes 0 No.
ti 1 If Yes, ensure that the appropriate actions are taken to revise the output interface documents per DES-4-1, section 3.1.8 (i.e., document change is initiated in accordance with applicable procedures)..............................................
O r
Logical consistency of analysis.....................................................................................
M4 Completeness of documenting references............................................................
IR Completeness of input.........................................................................................
122 Accuracy of input data............................................................
R 12 J Consistency of input data with approved criteria...................................................
R R A Completeness in stating assumptions....................................................................
Q12 14 Validity of assumptions..................------------------------------
2 d Calculation sufficiently detailed............................................................
j22 X
- Arithmetical accuracy........................................................................----................
Physical units specified and correctly used...........................................................
_ __z_
Reasonableness of output conclusion............................................................
12,?}
Supervisor independency check (if acting as Verifier)
ANA Did not specify analysis approach Did not rule out specific analysis options Did not establish analysis inputs................................
AA If a computer program was used:.............................................................
Z Is the program appropriate for the proposed application?
Vj*
Have the program error notices been reviewed to determine if they pose any limitations for this application? A#4 Is the program name, revision number, and date of run inscribed on the output? )"el Is the program identified on the Calculation Method Form? go 5 If so, is it listed in Chapter 10 of the Engineering Standards Manuar?.
Other elements considered:
If separate Verifiers were used for validating these functions or a portion of these functions, each sign and Initial below.
Based on the foregoing, the CalculationlCMR is adequate for the purpose intended.
Verifier Signature(s)/Date Verifier Initials 7R t4 _-6 4
7/
o
_ HAZ Y.
i zU1WWq 7W-7-1 ' 44114 7
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H ACO' 7,
Page No.
Conrd on page
- ENERGY CALCULATION 1
.3 1.31 N ORTHWEST REFERENCE LIST Calculation No. NE-02-03-15 Peaop
- Vision. solutions Prepared by Date:
> 7 hzi,. Verified by/Date: 7/27 Revision No.
0 ISSUE DATE/
NO AUTHOR EDITION OR TITLE DOCUMENT NO.
REV.
1 Polestar Applied February 16, STARpH Code Description and PSAT C107.02, Technology, Inc.
2000 Validation and Verification Report Revision 4 2
Polestar Applied Revision 0 Dose Calculation Data Base NE-02-04-01 Technology, Inc.
3 E. C. Beahm, et al.
- December, Iodine Evolution and pH Control NUREG/CR-5950 3.C ehe1t 1992NUECR55 Radiat. Phys. Chem., Vol. 27, pp. 157-4 Arakawa, et al 1986 163 Polestar Applied Calculation of Fraction of Containment PSAT 04202H.12 Technology, Inc.
Aprl, 1996 Aerosol Deposited in Water (Perry)
US Nuclear Altemative Radiological Source Terms 6
Regulatory July 2000 For Evaluating Design Basis Accidents RG 1.183 Commission At Nuclear Power Reactors Polestar Applied 7
R. R. Hobbins October 23, Chemical Forms of Iodine and Cesium Technology, Inc.,
1997 in the Reactor Coolant System Proprietary Memorandum Polestar Applied Effect of Boric Acid on Cesium Technology, Inc.,
8 R. R. HobbinsAprl, 2001 Chemistry and pH Proprietary Memorandum Polestar Applied R. HobbiOctober 31, Behavior of Sodium Pentaborate Technology, Inc.,
9 obIns 1998 Introduced into a Hot Core Proprietary Memorandum 10 D.PRLide, CRC 77th Edition, Handbook of Chemistry and Physics K. Denbigh, 11 Cambridge University 1957 The Principles of Chemical Equilibrium Press 12 E. C. Beahm, et al.
April '1992 Iodine Chemical Forms in LWR Severe NUREG/CR-12E.Bam ta.
Arl92 Accidents 5732, ORNL Columbia Generating Station Final November Safety Analysis Report, Figure 6.2-9, 13 Energy Northwest 1998 Suppression Pool Temperature Amendment 53 Response, Long-Term Response -
_Original Rated Power
ENERGY CALCULATION Page No.
ONORTHWEST REFERENCE LIST Calculation No. NE-02-03-15 P 43ie eVision
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NO AUTHOR EDITION OR TITLE DOCUMENT NO.
REV.
14 Hill and Petrucci, 2002 General Chemistry, Third Edition Prentice-H all, Inc.
15 R. Sher October 15, Energy Split 7.xIs I Polestar Applied 15R hr2001 EnrySlt7xsITechnology, Inc.
16R hrOctober 12, EnryeofinxsPolestar Applied 16 R. Sher 2001 EnergyDeposition.xls Technology, Inc.
17 J. Wing September, Post-Accident Gas Generation from NUREG-1081 1984 Radiolysis of Organic Materials Polestar Applied 1 8 R. R. 11obbSeptember 11, Effect of Temperature on the Technology, Inc.,
oins00 Dissociation Constant of a Weak Acid Proprietary Memorandum 19 C. F. Bonilla, 1957 Nuclear Engineering to 'Memorandum for 20 Robert M. Bernero May 16, 1984 February 7-8 NRC/IDCOR Attendees, Summary of NRC/IDCOR Meeting on Fission Product Release and Transport" 21 J. R. Lamarsh, 1983 Introduction to Nuclear Engineering, Addison-Wesley Second Edition
ENERGY CALCULATION OUTPUT Page No.
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2.0 P
Noplo.VlsionRTHW Eutins REVISION INDEX Calculation No. NE-02-03-15 Prepared by / Date~y,&, i(*oi R
Verified by/Date: 7'4 J, v
Revision No.
0 The below listed output interface calculations and/or documents are impacted by the current revision of the subject calculation. The listed output interfaces require revision as a result of this calculation. The documents have been revised, or the revision deferred with Manager approval, as indicated below.
CHANGED BY CHANGED DEFERRED DEPT.
AFFECTED DOCUMENT NO.
(e.g., RFTS, LETTER NO.)
MANAGER*
FMAe (5d1*.5
'Poric. 7qO6
- Required for deferred changes only.
PageNo. Cont onpage 0 ENERGY ALULATION OUTPUT Pag2e0 3.0 NORTHWEST
SUMMARY
Calculation No. NE-02-03-15 People VislionSolutions Revision No.
0 REV BAR.
Discussion of Results Part A In the short-term following a DBA-LOCA, the pH of water inside the Columbia Generating Station containment (suppression pool, vessel, and other bodies assumed well-mixed) will be increased from an initial value of 5.3 to a value above 7 due to the addition of fission product cesium. Depending on the form of the fission product cesium (e.g.. CsOH or CsBO 2), the pH will eventually drop below 7 as HN03 (from radiolysis of water) and HCI (from radiolysis of cable) are added to the water. The pH is expected to remain above 7 for sufficient time to permit injection and mixing of the Standby Liquid Control (SLC) sodium pentaborate (see Justification for Assumption 4).
Part B In the long-term (30 days), the pH of the containment water decreases from a peak of -8.4 as shown in the following table (assuming all sodium pentaborate in the SLC system is injected but no credit for fission product cesium):
pH results vs. time Time 18h 45h 76h 112h 160h 210h 275h 360h 480h 600h 720h 8.3 8.2 8.1 8.0 7.9 7.8 7.7 7.6 7.5 7.4 7.3 If as little as 95% of the sodium pentaborate is injected and/or mixes with the containment water, the containment water pH will remain greater than 7 for 30 days.
Conclusions Part A The pH of the containment water pool in the Columbia Generating Station will remain above 7 for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the release of radioactivity into the containment following a DBA-LOCA without sodium pentaborate credit assuming cesium is released in the form of CsOH. Therefore, there will be sufficient time to inject the sodium pentaborate from the SLC system and to have the sodium pentaborate mix with the containment water.
Part B The pH of the containment water pool in the Columbia Generating Station decreases from 8.4 to 7.3 over 30 days following the release of fission products into the containment for a DBA-LOCA given the addition of all SLCS sodium pentaborate. Only 95% of the total boron available is necessary to maintain pH 2 7 for 30 days.
I Page No. I Contd on page NORTHWEST CALCULATION METHOD 3
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'_REV Analys Method (Check approprae boxes)
BAR.
El Manual (As required, document source of equations in Reference List) l Computer E
Main Frame s
Personal a]
In-House Program Ea Computer Service Bureau Program l BCS ECDC El PCC E
OTHER l
Verified Program: Code name/Revision STARDH. Version 1.04 E
Unverified Program:
AproachlMethodotogy Methodology There are two parts to this analysis. The first part (Part A) deals with the determination of the short-term pH (prior to injection and mixing of the sodium pentaborate injected by the SLC system). In this part, fission product cesium is credited to be in the form of hydroxide in terms of its effect on maintaining suppression pool pH above
- 7. The second part (Part B) deals with the determination of the long-term pH (up to 30 days post-accident),
crediting the injected sodium pentaborate but no crediting fission produce cesium (except for the minor effect of neutralizing the initial pool pH and fission product HI).
In completing both Parts A and B of the analysis, Steps I through 3 are employed. Step 4 is used only for Part B.
- 1. Calculate the [HNO 3] concentration in the water pool as function of time after reactor scram using the Radiolysis of Water model of the STARpH 1.04 code (Reference 1).
- 2. Calculate the [HCI] concentration in the water pool as a function of time using the Radiolysis of Cable model of the STARpH 1.04 code (Reference 1).
- 3. Manually calculate the (HI concentration added to the pool as a function of time from the results of the two previous calculations.
- 4. Calculate the pH of the water pool considering the concentration of sodium pentaborate in the pool and [HI additions as a function of time using the Add Acid model of the STARpH 1.04 code (Reference 1).
In both Parts A and B, the following chemical reactions in containment water are considered (in the presence of radiation):
[H*l + [NO31 is produced by the radiolysis of water containing dissolved nitrogen, but the exact mechanism is not known (per Section 2.2A of Reference 3).
2[H20] + 2[CW -
2[H+] + 2[CH + 2[HOCI -
4[H+] + 4[CI-] + 102] (from chlorine gas being released from radiolysis of fire retardant cable insulation in the containment atmosphere and then dissolving in the water)
In Part A, the following additional chemical reactions are considered:
[HXXj - lH+] + [XX-] (from initial pool pH, where HXX is any acid that may be present)
(HI] - [H+] + [I-] (from fission product iodine being released in the form of HI)
[CsOH] -
[Cs+] + [OH-] (from fission product cesium being released in the form of CsOH)
In Part B, the following additional chemical reaction is considered:
[Na2O-5B203-10H 201-2[NaBO2] + 8[HBO2] + 6[H20-2[Na+] + 8[H+] + 10[B02-] + 6[H20]
(from injected sodium pentaborate which mixes with recirculated water from the containment)
NOTE THAT THE EQUATIONS REPRESENTING THE METHODOLOGY DESCRIBED IN THIS SECTION ARE PRESENTED AS THEY ARE USED IN THE CALCULATION SECTION.
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V REV BAR.
Design Inputs Items 1-4, and 6-14 are from Reference 2 (Item numbers are stated). Other items are as noted.
- 1. Reactor power = 3556 MWM (Item 1.1)
- 2. Volume of water in wetwell = 137,262 ft3 (Item 3.3)
- 3. RCS inventory = 6.59E5 Ibm (Item 8.22)
- 4. Pool initial pH = 5.3 (Item 6.1)
- 5. Fission product inventory, see Assumption 1
- 6. Mass of jacket = 1.673E6 g of Hypalon, 0.798E6 g of Neoprene (Item 6.2)
- 7. Density of jacket = 1.55 g/cm3 for Hypalon, 1.42 g/cm3 for Neoprene (Reference 30 of Reference 2 and Reference 17)
- 8. Thickness of jacket = 0.107 cm for Hypalon, 0.106 cm for Neoprene (Item 6.3)
- 9. Cable OD = 2.980 cm for Hypalon, 0.589 cm for Neoprene (Item 6.3)
- 10. Drywell free volume = 200,540 ft3 (Item 3.1)
- 11. Wetwell free volume = 144,184 ft3 (Item 3.2)
- 12. Mass of sodium pentaborate available for injection = 4,062.8 Ibm (Item 6.4)
- 13. Chemical formula for sodium pentaborate = Na2O*56203-10H 20 (Item 6.5)
- 15. G-factor for Hypalon = 2.1 molecules/100 eV (Reference 3)
- 16. G-factor for Neoprene = 3.5 molecules/100 eV (Reference 4)
Proprietary Information Deleted Assumption 3:
Justification:
The SLCS is actuated and the sodium pentaborate is injected and mixed with the pool within -8 hours of accident initiation.
A core damage event large enough to release the substantial quantities of fission products in the time frame considered for the alternative source term in Reference 6 will be very evident to the operators (e.g., radiation level in the drywell, pressure and temperature in the drywell, hydrogen level in the drywell) within minutes of the initiating event. Thus it is reasonable to assume for purposes of this calculation that the Columbia EOPs and SAMGs provide for SLCS actuation within a few hours of accident initiation.
If SLCS injection is into the pool (i.e., into the reactor vessel with the vessel communicating with the pool as in a recirculation line break), significant mixing will occur quickly, on the order of a few hours based on an RHR/drywell spray flow rate of -7450 gpm and a pool volunm of-1E6 gallons per Reference 2 (about 0.5 pool volume/hour).
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If the reactor vessel is not immediately communicating with the pool, some additional hours might be required before the operators flood the vessel up to the break to assure communication with the pool or inject sodium pentaborate to the pool via alternate paths.
REV BAR.
Assumption 4:
The unbuffered pH of the pool should remain above 7 for a period of time sufficient to accommodate injection and mixing even if some fission product cesium appears in forms other than CsOH (the form assumed by default in STARpH).
Justification:
Proprietary Information Deleted Assumption 6:
Injected sodium pentaborate will remain effective in controlling pool pH even if it is sprayed onto hot surfaces.
Justification:
Proprietary Information Deleted
ENERGY Page No Cont'd on page NORTHWEST MANUAL CALCULATION
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Proprietary Information Deleted Assumption 7:
The G value for HNO3 production by the radiolysis of water containing dissolved nitrogen used in the STARpH 1.04 code is 0.007 molecules per 100 eV absorbed (Reference 3, Equation 1).
Justification:
Proprietary Information Deleted Assumption 8:
Beta radiation from activity deposited directly on cables may be ignored.
Justification:
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ESTMANUAL CALCULATION 5.3 1
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Proprietary Information Deleted Assumption 9:
Justification:
HNO3 generation in the core may be ignored.
Proprietary Information Deleted
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Proprietary Information Deleted
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Calculation No. NE-02-03-15 People VisionySolutions
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Assumption 10:
Justification:
Assumption 11:
Justification:
Sequestering of the injected sodium pentaborate within the reactor vessel does not have to be assumed in the pH analysis.
The SLC injects boron solution via the HPCS line to the top of the core region. The AST DBA-LOCA analysis assumes an ECCS system recovery after sufficient core damage has occurred. For a DBA-LOCA of the recirculation piping, water level is recovered at least to the top of the jet pumps providing water to 2/3 core height and circulation via the bypass region to the break area. For a break high in the vessel, such as the MSLB inside containment, the operators are instructed to flood the vessel, permitting ECCS flow to communicate through the break, to the downcomers, and to the suppression pool. Mixing in the suppression pool is promoted by the ECCS system suction points being approximately 17 feet below the downcomer outlets. Therefore, the warmer water from the vessel tends to rise while the suction is from the cooler, heavier water in the bottom establishing circulation and mixing in the suppression pool.
The SLC system is adequately qualified and suitably redundant as a system to be credited in DBA-LOCA dose analysis.
Epuipment Qualification REV BAR.
Based on the ability of the fission product cesium to maintain suppression pool pH above 7 for a period of -8 hours, it is judged that the SLC system will have completed its DBA-LOCA safety function within that time.
The active components of the SLC system are being qualified to DBA-LOCA with seismic qualification [Reference Columbia MEL]. The system is being qualified to operate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a LOCA environment Suitable Redundancy At the time of this calculation, the NRC guidance on the requirements for SLC to be credited in a DBA-LOCA is a draft document to Vermont Yankee. ENW has evaluated these requirements and found SLC meets the draft requirements. A submittal position on the use of SLC will be provided. Since the requirements and submittal position are draft, no reference is provided. Any change to the acceptability of the SLC system upon NRC review may impact this analysis.
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Computations Common to Parts A and B Calculation of LHNOW1 in water pool as a function of time The Radiolysis of Water model in the STARpH 1.04 code (Reference 1) calculates the nitric acid concentration,
[HNO3], in the containment water pool generated by radiolysis.
Inputs to the Radiolysis of Water model are: reactor power = 3556 MWL, initial pH = 5.3, fraction of aerosol in water = 0.90 (Assumption 2), water pool volume = 4.18E6 L (calculated below), and core inventory of fission products (in Table 1 below)
Proprietary Information Deleted Table 1. Fission product inventory Grout Title Elements in Grouc Core Inventory (Ka)
I I, Br 32.7 Cs Cs, Rb 359 Te Te, Sb, Se 68.9 Sr Sr 94.3 Ba Ba 158 Ru Ru, Rh, Mo, Tc, Pd 981 Ce Ce 1,342 La La, Zr, Nd, Eu, Nb, 1,243 Pm, Pr, Sm, Y Total containment water volume = water volume of wetwell + RCS volume Water volume of wetwell = 137,262 f 3
- 2.83E1 Lf 3 = 3.88E6 L RCS volume = 6.59E5 Ibm /61.7 Ibm/f 3
- 2.83E1 Lft3 = 3.0E5 L where 61.7 Ibmft 3 = density of water in the suppression pool at 120 F (a representative value from Reference 13).
Total containment water volume = 3.88E6 L + 3.0E5 L = 4.18E6 L Proprietary Information Deleted The output of the calculation with the Radiolysis of Water model in the form of [HNO3] as a function of time is provided as Appendix A, Exhibit 1. The time-dependent gamma and beta power added to the pool is shown on Figure F-1 of Appendix F expressed as % of full core power. The integrated 30-day absorbed energy in the containment water (contributing to fHNO3]) is 261 full-power seconds.
Calculation of IHCI1 in water Pool as a function of time The concentration of HCI in the water pool as a result of radiolysis of electrical cable insulation is calculated using the Radiolysis of Cable model of the STARpH 1.04 code (Reference 1). The inputs to the Radiolysis of Cable model are: reactor power = 3556 MWI, water pool volume = 4.18E6 L (calculated above), aerosol fraction in pool
= 0.90 (Assumption 2), equivalent mass of Hypalon jacketing = 6,615 Ibm (calculated below), containment free volume = 9.76E9 cm3 (calculated below), Proprietary Information Deleted I
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Containment free volume = free volume of wetwell + free volume of drywell
= 144,184 f 3 + 200,540 f 3
= 344,724 f3 * (12 in/ft)3 (2.54 cm/in)3
= 9.76E9 cm3 REV BAR.
Proprietary Information Deleted
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EORTHWEST MANUAL CALCULATION F
5.11 NORT WESTCalculation No. NE-02-03-15 People -Vision -Solutions I
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ESMANUAL CALCULATION 5.1 1
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Proprietary Information Deleted The output of the calculation with the Radiolysis of Cable model in the form of [HCI] as a function of time is provided as Appendix B, Exhibit 2. The time-dependent power absorbed in the cable insulation jacket material (in Rads/hr) is presented in Appendix F, Table F-1. The integrated value over 30 days is 6.1 E8 Rads.
Calculation of rHI added to the Dool Proprietary Information Deleted
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Table 2. Calculation of [HI added to pool (all values in molL)
REV BAR.
Time 1h 2h 5h 12h id 3d 10d 20d 30d I
IHNO31 5.79E-06 7.95E-06 1.24E-05 1.97E-05 2.94E-05 5.67E-05 1.07E-04 1.40E-04 1.61E-04 2
Net EOH-1.17E-04 1.15E-04
- 1. 1 1E-04 1.03E-04 9.37E-05 6.63E-05 1.56E-05
-1.70E-05
-3.80E-05 3
1.99E-05 3.75E-05 8.05E-05 0.000153 0.000243 0.000489 0.000818 0.000933 0.000967 4
MI+ Added 2.57E-05 4.54E-05 9.29E-05 1.73E-04 2.72E-04 5.46E-04 9.25E-04 1.07E-03 1.13E-03 6
Net [H*l Added
-9.71 E-05
-7.75E-05
-3.05E-05 5.00E-05 1.49E-04 4.23E-04 8.02E-04 9.50E-04 1.00E-03 Part A - Sholrt-Term pH Calculation In the short-term, one is interested only in suppression pool pH without injection of sodium pentaborate.
Observing Table 2 Column 5 'Net [HI Added" (the result of subtracting Column 2 from Column 3), one can see that the [HI ions exceed the [OH] ions (from fission product cesium) sometime between 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (see Assumption 4 for a further discussion of the impact of fission product cesium on short-term pH).
Proprietary Information Deleted Based on Assumption 3, effective boron buffering is assumed to begin by -8 hours. Thus, for times up to -8 hours, the pH may be determined from the Net [H] Added column in Table 2 (Column 5), keeping in mind that negative values correspond to positive values of [OH] ions.
Part B - Long-Tenm pH Calculation Calculation of vH of the water Dool Proprietary Information Deleted
a Page No.
Cont'd on page
~ ENE GYMNUL ACUATO 5.13 1
A-I NORTHWESTICalculation No. NE-02-03-15 People-VIslon*
olutions CalclatonN._N-02-3-1 Prepared by I
Date:
Ad
~
Verified by/Date: 7 7
Revision No. 0 cnnain RV
\\>J REV The concentration of is calculated as follows:
BAR.
The mass of sodium pentaborate in the SLCS is 4,062.8 Ibm, or 454 gAbm
- 4,062.8 Ibm = 1.84E6 g.
The molecular weight of sodium pentaborate (Na2O-5B203-10H20) with boron of natural enrichment is:
2 x 22.990 + IO x 10.811 + 20 x 1.008 + 26 x 15.999 = 590 g/mol The moles of sodium pentaborate present are 1.84E6 g/590 g/mol = 3.12E3 mol.
There are 10 moles of B per mole of sodium pentaborate, so there are 3.12E3 x 10 = 3.12E4 mol of B.
Therefore, the concentration of B is 3.12E4 moV4.18E6 L = 7.46E-3 moVL In Part B, the (Proprietary Information Deleted) pH is obtained by (Proprietary Information Deleted) Appendix C, Exhibit 3. Figure 1 presents the results.
Figure 1- [H+] Added vs. Time 1.20E-03
[-- 1 l -
0 1F[
PJ1 6 8.OOE 0E 6.OOE -
v 4.OOE -
2.OOE -
O.OOE+00 -_
H f7. 7 pH 7 8. I ohr i
p7.9,1 r
pH.0,12
_/ I I.1, 76 hn rs
'w1 ir_____=_
10 100 1000 10 Hours Calculation of fraction of total boron necessary to maintain DH 2 7 The Add Acid model was run in an iterative fashion to determine the fraction of total boron necessary to maintain pH 2 7 over 30 days. Appendix D, Exhibit 4 is the STARpH result. It was found that 95% of the total boron available (i.e. a boron concentration = CI on Appendix D, Exhibit 4 of 7.08E-3 moVL) is necessary to maintain pH 2 7 with the 30 day (HI1 Added from Table 2 (1.13E-3 moIL).
Results and Conclusions The pH of the containment water pool in the Columbia Generating Station decreases from 8.4 to 7.3 over 30 days following the release of fission products into the containment in a DBA-LOCA with core damage. However, 95%
of the total boron available is necessary to maintain pH 2 7 for 30 days.
Input:
A a
C D
E F
a H
I J
K Th Power Pool Vol Inmal pH FP SW FP Inv kg Adj FP Inv lFP R actl FP In Cont Fract In FP in Pool BurupMWdt I
MW L
nfapHP StFnvg ka kgM~ac Poo kgnuM~
2 3558 4.1SE+40 5.3 I
18.8 32.7 0o3 9.81 0.9 8.829 33000 3
BVR Cs 230.3 359 0.25 89.75 80.775 4
Vo___n To 34.9 68.9 0.05 3.445 3.1005 Versjon 5
1.04 sr 27 94.3 0.02 1.888 1.0974 6
Be_
a 105 158 0o02 3.18 2844 7
Ru 584 981 0.0025 2.4525 2.20725 8
Ces 992 1342 0.0005 0.671 0.e039 9
La 838.8 1243 0.0002 0.2488 0.22374 output:
M N
2 2
3 4
5 S
7 8
9 10 11 12 13 14 15 16 17 IS Hi M.L fH+j Inmal 8.21ssE4-07 5.01187E-08 AZ BA BB BC Do BE OF 1*403 MR.
(OH-Jat 1h M
143at 1h Corr. jH+l ABS (H+I pH at 1h Tst pH u 7 H
h 0.000117284 8.5277E-11 8.52774E-11 8.52774E-11 10.0891659 10.069189 5.79432E-08 2h 2h 2h 2h 0.000115107 8.887eE-11 s.e8757E211 8.88757E-11 10.08110149 10.08110149 7.95171 E-08 5h 5h Sh 5h 0.00011061 9.038E-11 9.036e2E-11 9.03662E211 10.0430939 10.043ss3s 1.23978E-05 12h 12h 12h 12h 0.000103384 9.8745E-11 g.e7452E-11 9.e7452E-11 10.01437036 10.01437038 1.9944E-05 Id 1d Id 1Id 9.3688M-I 1.087SE210 1.06748E-10 1.06748E-10 9.97184882 9.9718482 2.93786E-05 3d 3d 3d 3d
.e8348sE-05 1.572-10 1.50719E-10 1.S5719E.10 9.821833109 9.821833109 5.870982E-0 10d 10 10d 10d 1.563sE-5 6.3959E2.10 6.3959E-10 8.3o99E.10 9.194098417 9.194098417 0.000107424 20d 20d 20d 20d v.18831E-05
-5.9338E-10
.1.6S31E-0 1.sS531E5 4.773319894 4.773319894 0.000139912 30d 30d SOd S30
-3.7987E-05
-2.832SE-10
-3.7987E-05 S7987E4s5 4.420365377 4.420385377 0.000161046 0
C7 0)
~1 0
0.,
01 MC la S
0se i*2m wOzc 5.rn lal V
0 as 0
z 0
0 0) 0 It 6
(:)
U'
&z P
0
'0 0) co 1(3
a Input:
A a
C D
E F
0 H
I Th Powr,
- CorVol, I -Gem NW cmS Pool Vol. L I Insulatlon. lb I Th POWfr. W Fract In Pod LestgI Csmma IRRta 2
3556
- 9. 76E.09 4.18E+0 6
ee1s I35560000 0.9 1.0 I 1.49E-15I 2.76E.15 3
4 Hypalon 5
e Version 1.04 Output:
2 3
4 5
6 7
a II 12 13 14 is 16 17 lS HCI P Hyp M HCI P Hyp MIL HCI B Hyp M HCI E Hyp MIL 1h 1h I h 1h 99,7220932 2.3857E-05 83.36767 1.§94E-05 2h 2h 2h 2h 187.9535s2 4.4985E4.5 156.5656317 3.745SE-05 5h 5h 5h 5h 406.949443 9.7356E.05 336.547189 8.0514E-05 12h 12h 12h 12h 774.573999 0.0001853 637.474402 0.00015251 Id Id 1d Id 1242688B94 0.00029729 101e.50319 O.024318 3d 3d 3d 3d 2508.07922 0.00080002 2044.08457 0.00048902 10d 10d 10d 10d 4133.38386 0.00O98885 3418.30829 0.00081778 20d 20d 20d 20d 4i09.24853 0.001102e9 3899.42425 0.00093288 30d 30d 30d 30d 4775.5866 0.001142A8 4040.14634 0.00096654 m
x K)
%al 01 0
a) 0*~5.1 0.
z 0
0
U
.zm sOZ 05 am S0 r %A Input:
Output:
0 A
a C
0 p
Q Add AC 1.04 pH Pl C1 Ki ea 8.6 2.51E-09 0.00746 9E-10 67 8.5 3.16E-09 0.00746 9E-10 B8 8.4 3.98E-09 0.00746 9E-10 69 8.3 5.01E-09 0.00746 9E-10 so 8.2 6.31E-09 0.00746 9E-10 e1 8.1 7.94E-09 0.00746 9E-10 62 8
1.00E-08 0.00746 9E-10 63 7.9 1.26E-08 0.00746 9E-10 64 7.8 1.58E-08 0.00746 9E-10 as 7.7 2.00E-08 0.00746 9E-10 66 7.6 251E-08 0.00746 9E-10 67 7.5 3.16E-08 0.00746 9E-10 68 7.4 3.98E-08 0.00746 9E-10 69 7.3 5.01E-08 0.00746 9E-10 70 7.2 6.31E-08 0.0074S 9E-10 71 7.1 7.94E-08 0.00746 9E-10 72 7
1.00E-07 0.00746 9E.10 db SUdb Acid Added 0.00033376 0.0056565
-0.00055484 0.00029642 0.00595292
-0.00025842 0.00025842 0.00621134 0
0.00022179 0.00643313 0.00022179 0.00018769 0.00662081 0.00040947 0.00015711 0.00677792 0.00056658 0.00013014 0.00690806 0.00069672 0.0001069 0.00701496 0.00080362 8.7599E-05 0.00710256 0.00089122 7.0797E-05 0.00717336 0.00096202 5.7412E-05 0.00723077 0.00101943 4.6259E-05 0.00727703 0.00106569 3.7151E-05 0.00731418 0.00110284 2.9783E-05 0.00734396 0.00113262 2.382E-05 0.00736778 0.00115644 1.904E-05 0.00738682 0.00117548 1.5188E-05 0.00740201 0.00119067 Q..
T 0.
-o 0) to k
w a
5 0
0)
(5) la CD 0.C) coz 0
0 0
0) 2 a) 0 zp zm6 6
tn 0
o C-,
0 0..0 5a)
~0a)
T;U
(
Input:
Output.
0 A
a C
D P
Q
=
AddAC1.04 pH
[N.J C1 K1 68 8.6 251E-09 0.00708 9E-10 R7 8.5 3.16E-09 0.00708 9E-10 68 8.4 3.98E-09 0.00708 9E-10 69 8.3 5.01E-09 0.00708 9E-10 s0 8.2 6.31E-09 0.00708 9E-10 61 8.1 7.94E-09 0.00708 9E-10 62 8
1.00E-M 0.00708 9E-10 aS 7.9 1.26E-08 0.00708 9E-10 64 7.8 1.58E-08 0.00708 9E-10 6S 7.7 2.00E-08 0.00708 9E-10 as 7.6 2.51E-08 0.00708 9E-10 67 7.5 3.16E-08 0.00708 9E-10 a8 7.4 3.98E-08 0.00708 9E-10 e9 7.3 5.01E-08 0.00708 9E-10 70 7.2 6.31E-08 0.00708 9E-10 71 7.1 7.94E4-8 0.00708 9E-10 72 7
1.00E-07 0.00708 9E-10 db SUdb Acid Added 0.00031676 0.00536837
-0.00052657 0.00028132 0.00564969
-0.00024525 0.00024525 0.00589494 0
0.00021049 0.00610543 0.00021049 0.00017813 0.00628356 0.00038862 0.0001491 0.00643266 0.00053772 0.00012351 0.00655618 0.00066123 0.00010145 0.00665763 0.00076269 8.3137E-05 0.00674077 0.00084583 6.719E-05 0.00680796 0.00091302 5.4487E-05 0.00686245 0.0009675 4.3903E-05 0.00690635 0.00101141 3.5259E-05 0.00694161 0.00104668 2.8266E-05 0.00696987 0.00107493 2.2607E-05 0.00699248 0.00109754 1.807E.05 0.00701055 0.00111561 1.4414E-05 0.00702496 0.00113002 rn X
x 0w CL a
0.
a 0
CD 0.
0.
r-0 (0
CD
ENERGY Page No. l on page ENORTHWEST Appendix E E-1 I
E-2 People RTV HWlon*
6olutons Calculation No. NE-02-03-15 Prepared by / Date:
Verified bylDate: 5
/ /
Revision No.
0
_II Trzk IA4 416f Proprietary Information Deleted
ENERGY Page No.l Contd on page P
NORTHWEST Appendix E E-2 I
F-1 Neople Vision-Bolutions Calculation No. NE-02-03-15 Prepared by / Date:
FIz
,f.
Verified by/Date:
2-.
/
Revision No.
0 Proprietary Information Deleted
p ENERGY Page No.
Cond on page E NERGHYES Appendix F F-G-Pe NORTHWEST Vppendi o Calculation No. NE-02-03-15 Peopae b Vision
- V d
tRutionse Prepared by /Date:<
1^lX4 Verifiedby/Date: 71/ffit I Revision No.
0
\\
Gamma + Beta Power Added to Containment Water and Insulation Jacket Material The combined gamma and beta power added to the containment water by activity deposited in the water is shown as a function of time in Figure F-I (Proprietary Information Deleted)
Figure F-1 Energy Absorption Rate In Containment Water (Integrated 30-day 261 Full Power Seconds)
E.%
0.250% _r 0.200%
0.10 C 0.250%
0 0.200%
U. 0.150% _-
06 Time Frames The radiation dose rate (rads/hour) for exposure of cable insulation jacket material to radiation in the gas space of the containment is shown in the following table individually for gamma and beta radiation. The corresponding integrated radiation exposure (gamma and beta radiation combined) over 30 days is 6.1E8 rads.
Table F-I Energy Absorption Rate In Cable Insulation Jacket Material Time Gamma Beta Interval Radslhr Rads/hr 0-1 hr 6.54E+06 6.10E+06 1-2 hr 5.73E+06 5.37E+06 2-5 hr 4.74E+06 4.36E+06 5-12 hr 3.41E+06 3.11E+06 12-24 hr 2.50E+06 2.29E+06 24-72 hr 1.67E+06 1.58E+06 72-240 hr 6.01E+05 6.40E+05 240-480 hr 1.44E+05 1.60E+05 480-720 hr 4.18E+04 4.72E+04
M. *_J fENERGYPage No.
Confd on page ENORTHWEST Appendix G CIA I PeopleN VionR
- HESutlon.
Calculation No. NE-02-03-15 Prepared by I Date:\\
1k Verified by/Date: 7/
7 Revision No.
0 U
I I I I
Proprietary Information Deleted