RS-03-053, Additional Information Supporting the Request for License Amendment Related to Application of Alternatives Source Term

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Additional Information Supporting the Request for License Amendment Related to Application of Alternatives Source Term
ML030990563
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 03/28/2003
From: Simpson P
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-03-053
Download: ML030990563 (34)
v • d • e


Text

Exeltnm.

Exelon Generation wwwexeloncorp corn Nuclear 4300 Winfield Road Warrenville, IL 60555 RS-03-053 March 28, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term

Reference:

Letter from K. R. Jury (Exelon Generation Company, LLC) to U. S.

Nuclear Regulatory Commission, "Request for License Amendments Related to Application of Alternative Source Term," dated October 10, 2002 In the referenced letter, Exelon Generation Company, LLC (EGC) requested an amendment to the facility operating licenses for Dresden Nuclear Power Station (DNPS),

Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The proposed change supports application of an alternative source term methodology. The referenced letter described the method used for controlling pH of the suppression pool.

The analyses assumed that injection of a borated solution is initiated and that a minimum of 3769.4 pounds of sodium pentaborate, or equivalent, is delivered into the suppression pool within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a large-break loss of coolant accident (LOCA). This amount of sodium pentaborate will produce the buffering effect required to maintain the suppression pool pH above 7 for the 30-day duration following the postulated large-break LOCA.

On February 24, 2003, the NRC requested additional information regarding the control of suppression pool pH for the 30-day period after a large-break LOCA. Attachment 2 provides the requested information. provides calculation DRE02-0033/QDC-1 100-N-1 259, Revision 0, "Ultimate Suppression Pool pH Following a Loss of Coolant Accident." This calculation

March 28, 2003 U. S. Nuclear Regulatory Commission Page 2 demonstrates that the suppression pool pH will remain above 7 for the 30-day duration following a large-break LOCA.

Attachment A, "Description and Safety Analysis for the Proposed Changes," of the referenced letter tabulated the radiological consequences of a main steam line break (MSLB) accident in Tables 11 a and 11 b for DNPS and QCNPS, respectively. These radiological consequences were also listed in Attachment D, "Information Supporting an Environmental Assessment," of the referenced letter. On February 26, 2003, the contractor that performed the MSLB analysis notified EGC of an error that impacts the radiological consequences provided to the NRC in the referenced letter. Revised radiological consequences of a MSLB accident are provided in Attachment 4.

The referenced letter requested NRC approval of the proposed amendments by October 31, 2003, with an implementation period of 60 days. In order to support the implementation plan for the proposed amendments, EGC requests to revise the implementation period as follows. For DNPS, the approved amendments shall be implemented prior to the start of refueling outage D2R18, which is currently scheduled to commence in November 2003. For QCNPS, the approved amendments shall be implemented prior to the start of refueling outage Q2R1 7, which is currently scheduled to commence in February 2004.

EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Attachment C of the referenced letter. The supplemental information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.

If you have any questions or require additional information, please contact Mr. Kenneth M. Nicely at (630) 657-2803.

Respectfully, Patrick R. Simpson Manager - Licensing Mid-West Regional Operating Group Attachments: : Affidavit : Response to Request for Additional Information : Calculation DRE02-0033/QDC-11 00-N-1 259, "Ultimate Suppression Pool pH Following a Loss of Coolant Accident,"

Revision 0 : Revised Main Steam Line Break Accident Radiological Consequences

March 28, 2003 U. S. Nuclear Regulatory Commission Page 3 cc:

Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety

ATTACHMENT 1 Affidavit STATE OF ILLINOIS COUNTY OF DUPAGE IN THE MATTER OF EXELON GENERATION COMPANY, LLC DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

)

)

Docket Numbers 50-237 and 50-249 50-254 and 50-265

SUBJECT:

Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term AFFIDAVIT I affirm that the content of this transmittal is true and correct to the best of my knowledge, information and belief.

Patrick R. Simpson Manager - Licensing Mid-West Regional Operating Group Subscribed and sworn to before me, a Notary Public in and for the State above named, this

69 day of

, 2003.

"FI No "

Pi

1 q ATTACHMENT 2 Response to Request for Additional Information Introduction In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to the facility operating licenses for Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The proposed change supports application of an alternative source term methodology.

Reference 1 describes the method used for controlling pH of the suppression pool. The analyses assumed that injection of a borated solution is initiated and that a minimum of 3769.4 pounds of sodium pentaborate, or equivalent, is delivered into the suppression pool within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a large-break loss of coolant accident (LOCA). This amount of sodium pentaborate will produce the buffering effect required to maintain the suppression pool pH above 7 for the 30-day duration following the postulated large-break LOCA.

On February 24, 2003, the NRC requested additional information regarding the control of suppression pool pH for the 30-day period after a large-break LOCA. Specifically, the NRC requested EGC to provide the following.

1. The amounts of acidic and basic chemical species released to the containment for which the licensee takes credit in its analysis.
2. The sources that contribute to the pH changes in the suppression pool (e.g., nitric acid from the post accident radiation field, hydrochloric acid by decomposition of the chlorine bearing cables, or the chemical species released from the damaged core).
3. The calculations used to determine the pH in the suppression pool after the LOCA If a computer code was used in the calculations of the suppression pool pH, please provide:

(a) the name of the code and (b) input to and output from the code. If hand calculations were used, please provide a sample of the calculations.

Response to Request I The dissociation of sodium pentaborate produces the only basic species credited in the suppression pool pH analysis. As stated above, the analyses assumed that a minimum of 3769.4 pounds of sodium pentaborate, or equivalent, is delivered into the suppression pool within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the postulated LOCA.

The following table lists the concentrations of acidic chemical species assumed to be released to the containment. The methodology and assumptions supporting these concentrations are described in Reference 2, which is provided as Attachment 3 to this submittal.

Acidic Chemical Species.

Concentration (moliL)

Nitric acid 3.802 x 104 Hydrochloric acid 1.376 x 10-3 Page 1 of 3

ATTACHMENT 2 Response to Request for Additional Information Response to Request 2 The analysis to demonstrate that the suppression pool pH will remain above 7, for the 30 days following a postulated LOCA, accounts for changes in pH due to the production of nitric acid from the post accident radiation field and hydrochloric acid from radiolysis of chloride-bearing cable jacketing. The analysis assumed that injection of a borated solution is initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a large break LOCA, and that a minimum of 3769.4 pounds of sodium pentaborate, or equivalent, is delivered into the suppression pool.

The quantity of hydriodic acid introduced into the drywell with the release of core iodine was assumed to be negligible considering the large quantity of hydrochloric acid produced by decomposition of the chlorine bearing cables. Reference 2 assumes: (1) no credit is taken for shielding of cable in cable trays, by other cables, and by the cable tray itself, from beta radiation; (2) no credit is taken for shielding of cable in conduit or totally enclosed raceways from gamma radiation; and (3) the mass of non-chloride bearing cable materials, such as insulation and fillers, is assumed to generate hydrochloric acid. The conservatively high production of hydrochloric acid compensates for neglecting hydriodic acid.

The quantity of cesium hydroxide introduced into the drywell with the release of core cesium was assumed to be negligible. This assumption is conservative since crediting this strong base would increase the suppression pool pH.

Response to Request 3 Calculation DRE02-0033/QDC-1100-N-1259, Revision 0 (i.e., Reference 2), demonstrates that the suppression pool pH will remain above 7 for 30 days following a LOCA. This calculation is provided as Attachment 3 to this submittal.

Attachments 1 and 2 of Reference 2 state that a DNPS Unit 2 calculation is in progress to validate the estimated cable insulation mass used for Duane Arnold is applicable to DNPS and QCNPS. The DNPS Unit 2 calculation has been completed, and validated the assumption.

This calculation was performed for DNPS Unit 2 only, since the estimated cable insulation mass of DNPS Unit 2 bounds the cable insulation mass of DNPS Unit 3 and QCNPS Units 1 and 2.

The use of DNPS Unit 2 as the bounding case for calculating the cable insulation mass inside the drywell is acceptable since the volumes of all four units' drywells are similar and the equipment layout in the drywells are approximately the same, resulting in similar cable lengths for each of the four units. The individual cables for the various components are also similar in conductor size. All four units have the same major components within the drywell, and each unit has approximately the same number of motor operated valves (MOVs), drywell cooler blowers, reactor recirculation pump motors, and sumps pumps. The four units also have similar instrumentation. In addition, DNPS Unit 2 has four MOVs associated with each of the reactor recirculation headers. DNPS Unit 3 and QCNPS Units 1 and 2 do not have these MOVs.

Based on the above, there are sufficient similarities between all four units to justify use of DNPS Unit 2 as the bounding case for calculating bulk quantities of cable jacket/insulation material.

Page 2 of 3

ATTACHMENT 2 Response to Request for Additional Information References

1. Letter from K. R. Jury (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Request for License Amendments Related to Application of Alternative Source Term," dated October 10, 2002
2. Calculation DRE02-0033/QDC-1100-N-1259, "Ultimate Suppression Pool pH Following a Loss of Coolant Accident," Revision 0 Page 3 of 3

ATTACHMENT 3 Calculation DRE02-0033/QDC-1100-N-1259, "Ultimate Suppression Pool pH Following a Loss of Coolant Accident," Revision 0

CC-AA-309 - ATTACHMENT 1 - Design Analysis Approval Page 1 of 2 DESIGN ANALYSIS NO.:

DRE02-0033, Revision 0 PAGE NO. 1 QDC-110O-N-1259, Revision 0 Major REV Number: NA Minor Rev Number: NA

[ ] BRAIDWOOD STATION DESCRIPTION

[ ] BYRON STATION CODE:(C018)

Coo, N0l, ROO, ROl, R02

[ ] CLINTON STATION DISCIPLINE CODE:

[X] DRESDEN STATION DCIL CD N

[

L LASALLE CO. STATION (C0il)

[ X] QUAD CITIES STATION Unit AD CTE STATION

[

1 lSYSTEM CODE: (C011) 11 (DRE) SC (QDC)

Unit:(

]0

[XII

[XJ2 I X ]3 TITLE: Ultimate Suppression Pool pH Following a Loss of Coolant Accident

[X Safety Related

[ l Augmented Quality

[ ] Non-Safety Related ATTRIBUTES (C016)

TYPE j

VALUE TYPE VALUE Elevation Software COMPONENT EPN: (C014 Panel)

DOCUMENT NUMBERS: (C012 Panel) (Design EPN TYPE Analyses References)

Type/Sub Document Number Input (YIN)

REPT/ENG GE-NE-A22-00103-08-01, R1 Y

LTRIENG EXELON TODI ER2002-9994, R1 Y

LTR/ENG EXELON TODI QDC-02-019,, R1 Y

a i

I I

I i

__________________________________ II REMARKS:

Page 1 of 25 (Printed: 08/05/02 2:11 PM)

E-Forrn CC-AA-309-1 vi.1 for use with CC-AA-309 Revision 1 and above.

CC-AA-309 - ATTACHMENT 1 - Design Analysis Approval Page 2 of 2 DESIGN ANALYSIS NO.

DRE02-0033, RO; QDC-1100-N-1259, RO PAGE NO.

2 Major REV Number: NA Minor Rev Number: NA Revision Summary (including EC's incorporated):

Revision 0, Original Issue Electronic Calculation Data Files:

(Program Name, Version, File Name extensionlsize/date/hour/min)

Design impact review completed?

[ ] Yes I X ] N/A, Per EC#: 3s6w. 337 (If yes, attach impact review sheet)

Prepared by:

S. Frank/K. P. Ferguson (Ap. A) I Date Reviewed by:

J. H. Cho/ W. Pena (ApD. A)

/

Method of Review:

[x] Detailed

[ ] Alternate

] Test This Design Analysis supersedes: N/A (See Revision Summary)

Supplemental Review Required? ( ] Yes

[X ] No

[ Additional Review

[]Special Review Team Additional Reviewer or Special Review Team Leader EI Print Sign Date Special Review Team: (N/A for Additional Review)

Reviewers: 1) 1 1

2)

Pri"t Sign Date Print Sign Date

3) 4)

Print Sign Date Print Sign Date Supplemental Review Results :

Approved by:

Frank A. Elia Pnt Sign S

Date External Design Analysis Review (Attachment 3 Attached)

Reviewed by:

-Pnint Sign Date Approved by:.

I

-Print Sign Date Do anyASSUMPTIONS/ENGINEERING JUDGEMENTS require later verification?

] I Yes [X] No Tracked By: AT#, EC# etc.)_

Page 2 of 25 (Printed: 08105/02 2:11 PM)

E-Form CC-AA-309-1 v1.1 for use with CC-AA-309 Revision 1 and above.

NES-G-1 4.01 Effective Date:

04/14/00 TABLE OF CONTENTS CALCULATION NO. DRE02-0033, RO; ODC-1100-N-1259, RO PAGE NO.3 SECTION:

PAGE NO.

SUB-PAGE NO.

TITLE PAGE 1

REVISION

SUMMARY

2 TABLE OF CONTENTS 3

1.0 PURPOSE / OBJECTIVE 4

2.0 METHODOLOGY AND ACCEPTANCE CRITERION 4

3.0 ASSUMPTIONS / ENGINEERING JUDGMENTS 7

4.0 DESIGN INPUT 7

5.0 REFERENCES

8 6.0 CALCULATION 9

7.0

SUMMARY

AND CONCLUSION 11 APPENDIX A. Post-LOCA 30-Day Gamma and Beta Doses in the 12 Suppression Pool and 30-Day Beta Dose in the Containment Atmosphere (3016 MWt Reactor Core)

ATTACHMENTS 15

1. Parameter list for post-LOCA suppression pool 16 pH - Dresden Nuclear Station (Ref. 6)
2. Parameter List For Post-LOCA Suppression Pool pH - Quad 21 Cities Nuclear Station (Ref. 7)

Total Pages Including Attachments = 25 11 E-FORM l

NES-G-1 4.01 Effective Date:

04114/00 DESIGN ANALYSIS NO. DRE02-0033, RO; QDC-1100-N-1259, RD PAGE NO.4 1.0 PURPOSE IOBJECTIVE The purpose of this calculation is to determine the pH of the suppression pool following a loss of coolant accident (LOCA), taken as the pH value in the pool water 30 days after the event. The calculation is an enveloping analysis, applicable to both the Dresden and Quad Cities plants.

2.0 METHODOLOGY AND ACCEPTANCE CRITERION Methodology The long-term suppression pool pH is determined as follows:

1.

Suppression Pool Water Volume Since a larger pool water volume yields a slightly lower ultimate pH, a maximum volume is conservative.

An appropriate value is obtained from the initial pool water volume by adjusting for the final pool temperature and accounting for additions of reactor coolant, water pumped into containment from outside sources, and addition of sodium pentaborate solution from the Standby Liquid Control tank.

2.

Nitric Acid Production Irradiation-assisted nitric acid production in the suppression pool is based on a G value of:

G(HNO3) = 0.007 molecules/100 eV which corresponds to 7.255 x 104 mol HNO3lMrad-L (Ref. 1, p. 4). This value is multiplied by the total integrated 30-day dose (gamma + beta) in the liquid of the suppression pool to give the concentration of nitric acid.

3.

Hydrochloric Acid Production Radiolysis of chloride-bearing cable jacketing results in production of HCI vapor based on a G value of:

G(HCI) = 2.1 molecules/100 eV which corresponds to an estimated 4.6 x 104 mol HCI/Mrad-lb of insulation (Ref. 1, p. 6). The mass of cable-less-conductor (i.e., jacket, insulator, and fillers) in the drywell is divided into two groups according to whether or not it is in conduit. The mass that is not in conduit receives both the 30-day post LOCA beta dose and the 30-day post LOCA gamma dose in the drywell atmosphere. The cable mass that is in conduit receives only the gamma dose. Since only the cable jacket, which is made of Hypalon (a chloro-sutfonated polyethylene rubber), is chloride-bearing (27 wt % chlorine), use of the additional mass provided by the insulation and filler material is conservative. All HCI thus produced is assumed to enter the suppression pool water.

4.

Calculation of Intermediate pH (Without Buffer)

The hydrogen ion and hydroxide ion concentrations (molL) after 30 days are determined by:

[HI = 10 -pH, + [HNO3] + [HCI]

and, neglecting the beneficial effect that CsOH in the pool would have:

lO~

o-14

[OHi

-lo-pHo Some of the generated H' ions will be neutralized with the OH ions such that:

11E-FORM IA

NES-G-1 4.01 Effective Date:

04/14/00 DESIGN ANALYSIS NO. DRE02-0033, RO; ODC-110O-N-1259, RO PAGE NO.5 tH-j-x) iO1-1-1, x)=K,,M where the ionization constant for water as a function of temperature (T in *F) is determined with (Ref. 2, p.

4):

-log10Kv(T) = 15.5129 - 0.0224T + 3.352x1 0-4T2 The solution of the quadratic equation is:

[H+]+tOH-io -I[H']+[OHi-o0y

-4(EH1+-[OH1]0 -Kw )

2 and the intermediate (prior to addition of buffer) hydrogen ion concentration is:

[Hi1 n1e.eate = [HI - x from which the intermediate pool pH is:

PH~rWe.medate = - Iog1o([HJ,,1.smdat.)

5.

Calculation of Final (Ultimate) pH (With Buffer)

This calculation adopts the method of Grand Gulf Nuclear Station (Ref. 2, p. 20), in which the dissociation constant for boric acid (K.) is used to determine the buffering effect of sodium pentaborate (Na2B,0O16) on the suppression pool pH (Assumption 7). The sodium pentaborate stored as an aqueous solution in the Standby Liquid Control (SLC) tank was originally intended to address the Anticipated Transient Without Scram (ATWS) concern (10CFR50.62).

It can be introduced into the system by redundant injection pumps that are manually operated from the control room.

The dissociation equation for sodium pentaborate is:

Na2B1 0O16 +16H 20 < 2Na' +2B(OH)- +8B(OH) 3 The boric acid dissociation (Ka) constant is determined as a function of temperature (T in IF) from Ref. 5.

The SLC solution of aqueous sodium pentaborate is prepared from stoichiometric quantities of borax (Na2BI00 7 *1 0H 220) and boric acid (H3B0 3). The weak acid and its conjugate base buffer the pool water at a pH given by:

= PKa +1og 0 T[anion] = PKa +log10 [B(OH)-]

pH[acid]

[B(OH)3]

A molecular weight of 410 is used to determine the number of moles from the mass (in grams) of injected sodium pentaborate:

nsp = msp 410 The number of equivalents of strong acid present in the pool is found from the previously determined intermediate hydrogen ion concentration as:

IE-FORM __

NES-G-1 4.01 Effective Date:

04114/00 DESIGN ANALYSIS NO. DRE02-0033, RO; QDO-1100-N-1259, RO PAGE NO.6 n.q = Vpod [H~lrtldoate and this quantity is used to modify, by neutralizing, the equivalents of borate ions and of boric acid present in the pool, yielding a final pool pH according to:

2nsp -nq pHfin,, =-1og1 0K. +loglO 8n5 p +flq Vr0.

Acceptance Criterion The equilibrium suppression pool pH is required to be above 7.0 to ensure that significant long-term re-evolution of iodine does not occur (Ref. 3).

IE E--FORM jI

NES-G-1 4.01 Effective Date:

04114100 DESIGN ANALYSIS NO. DRE=2-0033, RO; DC-1100-N-1259, RO PAGE NO.7 I

3.0 ASSUMPTIONS / ENGINEERING JUDGMENTS

1.

The quantity of hydriodic acid (HI) introduced into the drywell with the release of core iodine is negligible. An estimate of the amount of HI relative to the total (neglecting the Mark Ill HCI contribution from containment) indicates it is less than 2% (Ref. 2, Attachment 2, p. 19). The conservatively high production of iHCI in this calculation (see Assumptions 3 - 5) compensates for neglecting HI.

2.

The quantity of cesium hydroxide (CsOH) introduced into the drywell with the release of core cesium is negligible. This strong base would act to increase the pool pH, and, therefore, neglecting it is conservative.

3.

In calculating the amount of HCl produced, no credit is taken for shielding of cable in cable trays, by other cables and the cable tray itself, from beta radiation.

4.

In calculating the amount of HCl produced, no credit is taken for shielding of cable in conduit or totally enclosed raceways from gamma radiation.

5.

. In calculating the amount of HCI produced, the mass of non-chloride bearing cable materials, such as insulation and fillers, is assumed to generate HCI.

6.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the LOCA, all the sodium pentaborate is injected into the suppression pool, and the pool water is thoroughly mixed and at a uniform pH.

7.

The pH correlation for boric acid/borax is applicable to sodium pentaborate.

4.0 DESIGN INPUT Unless otherwise indicated, input parameters are obtained from Attachments 1 and 2, for Dresden and Quad Cities, respectively. Since this is a bounding calculation for both plants, the more conservative value is selected from the attachments.

1.

Maximum suppression pool water temperature after 1 day = T = 156.60F (temperature after 5.2 days from Ref. 4)

2.

Maximum initial suppression pool water volume = VY = 119,800 ft3 at 950F.

3.

The minimum initial pH (pHO) is 5.6.

4.

Maximum reactor coolant mass = mRC = 590,000 lb

5.

Maximum volume of water pumped into containment post-LOCA = Vp = 10,000 ft3 at 950F

6.

Minimum mass of sodium pentaborate delivered within 100 minutes post-LOCA = msp = 3,769.4 lb.

7.

The maximum volume of sodium pentaborate solution delivered = Vsp = 3,253.4 gallons at 1100F.

8.

Maximum cable mass in conduit, including jacket, insulation, and fillers (70% of total) = mcic 17,250 lb.

lI E-FORM 1

NES-G-1 4.01 Effective Date:

04/14/00 DESIGN ANALYSIS NO. DRE02-0033, RO; QDC-1100-N-1259, RO PAGE NO.8

9.

Maximum cable mass not in conduit, including jacket, insulation, and fillers (30% of total) = mcoc

= 5,750 lb

10.

Integrated worst-case 30-day post-LOCA, dose in the containment atmosphere = DPA = 1,700 Mrads (from Appendix A).

11.

Integrated worst-case 30-day post-LOCA I dose in the containment atmosphere = D7A = 98.1 Mrads. (This value is a one-year value, conservatively applied at 30 days.)

12.

Total integrated 30-day dose (y + 3) in the suppression pool = Dep = 52.4 Mrads (from Appendix A).

13.

Minimum ECCS flow rate from suppression pool = 4,500 gpm per pump.

5.0 REFERENCES

1.

NUREG/CR-5950, ORNLrTM-12242, Iodine Evolution and pH Control", December, 1992.

2.

Engineering Report No. GGNS-98-0039, Rev. 3, "Engineering Report for Suppression Pool pH and Iodine Re-Evolution Methodology", Entergy Operations, 12/20/00.

3.

NUREG-0800, U. S. NRC Standard Review Plan, Section 6.5.2, Containment Spray As A Fission Product Cleanup System', Rev. 2, December, 1988.

4.

GE-NE-A22-00103-08-01, Rev. 1, Project Task Report, 'Dresden and Quad Cities Extended Power Uprate", Task T0400, Containment System Response, Table C-1, December, 2000.

5.

WCAP-3269-51, The Calculated pH of Aqueous Boric-Acid Solutions as a Function of Temperature and Added Base Content", K11 in Figure 2, March, 1965.

6.

Exelon Transmittal of Design Information (TODI) No. ER2002-9994, "Dresden Station Concurrence with the Design Inputs as Established for Altemate Source Term (AST) LOCA Analysis", Attachment 2, Rev. 1, 7/31/02 (included here as Attachment 1).

7.

Exelon Transmittal of Design Information (TODI) No. QDC-02-019, "Quad Cities Station Concurrence with the Design Inputs as Established for Altemate Source Term (AST) LOCA Analysis', Attachment 2, Rev. 1, 8/1/02 (included here as Attachment 2).

I1 E-FORM

NES-G-1 4.01 Effective Date:

04114/00 DESIGN ANALYSIS NO. DRE02-0033, RO; QDC-1100-N-1259, RD PAGE NO.9 6.0 CALCULATION

1. Suppression Pool Water Volume at One Day Vpw =[LT (Vo+VP)+VTVsP+VTmR]C

= [0-016377 (119,800 +10,000) + 0.016377 (3253.4)0.13368

- + 0.016377(5 90,000)]28.31685 L

=401610.016114 0.016165 gal

Wt

= 4,021,6-41 L where:

VT = specific volume of water at T after one day = 156.60F vo = specific volume of water at 950F v, = specific volume of water at 1 100F

2.

Nitric Acid Production

[HNO3] = 7.255 x 10.6 D-op = 7.255 x 10 6 (52.4) = 3.802x 10 4 mol/L

3.

Hydrochloric Acid Production

[HCIJ Vp00j = 4.6 x 10'4 [ mcoc(DmA + DyA) + mcIc DyA] = 4.6 x 104 [5750(1700+98.1)+17250(98.1)]

= 5,534.4 mol HCI and

[HCq = 5,534.4/4,021,641 = 1.376 x 10' molIL

4.

Calculation of Intermediate pH (Without Buffer)

The hydrogen ion and hydroxide ion concentrations (mot/L) after 30 days are:

[HI = 1 0<H° + [HNO3] + [HCI] = 5.012xlO4 + 3.802x104 + 1.376x10 3 = 1.759x104 and, neglecting the beneficial effect that CsOH in the pool would have:

lo14 1S)=04

[OH]0

= 1 0

=14.S6)

= 10

- 3.981x10 Some of the generated H+ ions will be neutralized with the OH ions such that:

kH] -x)-liOH-],o -x)=Kw,(T) where the ionization constant for water is:

K (M) = lo-15.5129-0 0224T+3 352x1O 6T2) =1.489x10' 3 and, therefore, x is:

X

[H+[+[OH-]o -VH]+[OH-]0 y -4[H1].[OH-]i0 -Kw) 2

= 3.896x1 0l L1 E-FORM l

NES-G-14.01 Effective Date:

04114100 DESIGN ANALYSIS NO. DRE02-0033, RD; QDC-110O-N-1259, RO PAGE NO.10 and the intermediate (prior to addition of buffer) hydrogen ion concentration is:

[H1linermeediate = [HI - x = 1.759 x 1 0mol/l-from which the intermediate pool pH is:

pHl,-iermed,,iawe = - logio([Hilntsate) = 2.75

5.

Calculation of Final (Ultimate) pH (With Buffer)

The boric acid dissociation constant is determined at T = 1571F from Ref. 5:

Ka(T)=9.3x 10' The number of moles from the mass (in grams) of injected sodium pentaborate is:

ns = 3769.4(453.6gAb) = 4,170 mol The number of equivalents of strong acid present in the pool is found from the previously determined intermediate hydrogen ion concentration as:

neq = Vp.o. [Higrgemate = 4,021,641 (1.759 x 103) = 7,073 and this quantity is used to modify, by neutralizing, the equivalents of borate ions and of boric acid present in the pool, yielding a final pool pH according to:

2nsp -neq 2(4170) -7073 pl-fnal =4ogOKKa +1l91og

-- og10(9.3x1 0.10) +Iog10 8(4170)+7073 8nsp +neq 8_4_7________

bre Vpoo VP00'V00

= 9.032 -1.504 = 7.53 It is noted that the time to replace one pool volume with one pump operating is as follows:

Vpi, (4021641) 0.26417 LUgal = 236 min. = 3.93 h a

4500 gpm I

E-FORM

NES-G-1 4.01 Effective Date:

0414100 PAGENO.11 IDESIGN ANALYSIS NO. DRE02-0033, RO; QDC-1100-N-1259, RO mm 7.0

SUMMARY

AND CONCLUSION The suppression pool water pH from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 30 days after a LOCA is 7.53, which exceeds 7.0 as required.

IE E-FORM I

NES-G-1 4.01 Effective Date:

04/14100 DESIGN ANALYSIS NO. DRE02-0033, RO; QDC-1100-N-1259, RO PAGE NO.12 Appendix A Post LOCA 30-Day Gamma and Beta Doses In the Suppression Pool and 30-Day Beta Dose In the Containment Atmosphere (3016 MWt Reactor Core)

The purpose of this appendix is to provide bounding estimates of the Dresden and Quad Cities post-LOCA 30 day integrated:

gamma and beta doses in the suppression pool water, and beta dose in the containment atmosphere These dose estimates are based on design inputs from existing calculations. The estimated doses are used to determine nitric acid production by radiolysis in the suppression pool liquid, and hydrochloric acid production from cable degradation due to radiation damage in the containment atmosphere.

30-Day Post LOCA Gamma Dose in the Suppression Pool Water From inspection of the gamma doses provided in References 1 and 2, it is noted that the gamma dose contribution from activity in the suppression pool gas region is over 5 times higher than the gamma dose contribution from activity in the liquid region. For purposes of a conservative estimate of the 30 day gamma dose in the suppression pool water, this assessment assumes that the suppression pool water does not attenuate the airborne activity.

As stated above, the gamma doses provided in References 1 and 2 do not reflect EPU. The bounding Dresden and Quad Cities EPU gamma dose Scaling Factor that can be applied to any source or configuration in containment is 1.47 from page 56 of Reference 4. The post LOCA 30-day gamma doses in the suppression pool that reflect EPU are calculated below using the bounding EPU Scaling Factor Dresden and Quad Cities EPU gamma pre-EPU gamma dose (rad)

Scaling Factor EPU gamma dose (rad) 2.7E7 rads (gas region) 1.47 3.97E7 4.87E6 rads (liquid region) 1.47 7.16E6 TOTAL 4.69E7 30-Day Beta Dose in the Suppression Pool Water Since the airborne beta radiation contribution will be attenuated very quickly by the pool water to insignificant levels, it appropriately assumed that airborne beta activity in the gas region will have an insignificant contribution to the beta dose in the pool water.

The beta emission rate (Sv ) to dose rate (D) conversion factor for an infinite water medium is calculated by:

Il E-FORM l

NES-G-1 4.01 Effective Date:

04/14/00 DESIGN ANALYSIS NO. DRE02-0033, RO; ODC-1100-N-1259, RO PAGE NO.13 D

Mev erg Irad icm3 3600sec

  • rad D= ~

x.xO-x

=5.76 xIO-'S sec-cm3 Mev 10erg gm hr hr The equation above is used to estimate the beta dose to a detector submerged in the suppression pool.

The total integrated energy release from all beta activity in the suppression pool that reflects EPU, is 3.02x1 020 Mev-hr/sec, and is taken directly from Table D9 of Reference 4. The Suppression pool liquid volume (112,203 ft3) is taken from Reference 3. The volumetric integrated Sis:

3.02x10° Mev-hr Sv =

sec

_9.

5 1xI 0 10 Mev-hr (I 12,203ft x283177f3)

CC-sec The 30day integrated beta dose (D) in the suppression pool = 5.5 x 10 rad (i.e., 9.51x1010 x 5.76x1 0'5) 30-Day Beta Dose in the Containment Atmosphere Per Reference 5, the integrated 30 day post-LOCA airborne beta dose in containment at pre-EPU conditions is as follows airborne sources :1.19 E9 Rads (Ref 5, Sheet 12) plateout sources: 1.386E9 Rads (Ref 5, Sheet 16)

However, as noted in Reference 6, Section 6, the pre-EPU beta dose due to airborne sources developed in Reference 5 was based on a conservative drywell volume, and a correction factor of 0.59 is to be applied to the pre-EPU dose estimate. In addition, Reference 6, Section 6, also notes that the pre-EPU dose due to plate-out sources used a conservative plate-out surface area, and that a correction factor of G.48 is applicable to the estimated dose.

Taking into consideration the above correction factors, the updated integrated 30 day post-LOCA beta dose in the containment atmosphere at pre-EPU conditions is as follows airborne sources :1.19 E9 Rads X 0.59 = 7E8 Rads plateout sources: 1.386E9 Rads X 0.48 = 6.65E8 Rads Based on Reference 4, Section 7.2, the 30 day EPU scaling factor for airborne beta sources is 1.3 and that for a purely halogen source (representative of a plateout source) is 1.12.

Taking into consideration the above EPU scaling factors, the updated integrated 30 day post-LOCA airborne beta dose in containment at uprated conditions is as follows:

airborne sources : 7E8 Rads X 1.3 = 9.1 E8 Rads plateout sources: 6.65E8 Rads X 1.12 = 7.5E8 Rads Total = 1.7E9 Rads

]

E-FORM I

NES-G-1 4.01 Effective Date:

04114100 PAGE NO.14 I

1DESIGN ANALYSIS NO. DRE2-0033, RO; QDC-1100-N-1259, RO RESULTS The total EPU 30 day Integrated Dose (gamma+beta) In the suppression pool is then the sum of the calculated beta and gamma doses above:

D(P+7) = 5.5E6 rad + 4.69E7 rads = 524E7 rod The EPU 30 day Integrated Beta dose in the Containment Atmosphere = 1.7E9 Rads.

REFERENCES

1.

TODI No. ER2002-9994, 'Dresden Station Concurrence with the Design Inputs as Established for Alternate Source Terms(AST) LOCA Analysis", Revision 1

2.

TODI No. QDC-02-019, "Quad Cities Station Concurrence with the Design Inputs as Established for Alternate Source Terms(AST) LOCA Analysis", Revision 1

3.

Bechtel Calculation NUC-1, R2 "Post Accident Integrated Doses'

4.

S&W Calculation DREOO-0073, RO, QDC-0000-N-1022, RO 'Dose and Dose Rate Scaling Factors to Evaluate Impact of EPU on Radiological Equipment Qualification and Vital Access"

5.

Bechtel Calculation NUC-2, Rev 1, "Drywell Post Accident Integrated Beta Dose"

6.

S&W Calculation DRE01 -0006, RO, QDC-O000-N-1 070, RO, "Equipment Qualification Dose to Cable inside Containment following Extended Power Uprate' Preparer:

K.P. Ferauson (See Dage 2)

Reviewer:

W.H. Pena (See page 2)

I E-FORM I

N NES-G-1 4.01 Effective Date:

0414/00 DESIGN ANALYSIS NO. DRE02-0033, RO; QDC-1100-N-1259, RO PAGE NO.15 ATTACHMENTS

1. Exelon Transmittal of Design Information (TODI) No. ER2002-9994, "Dresden Station Concurrence with the Design Inputs as Established for Alternate Source Term (AST) LOCA Analysis', Attachment 2, Rev. 1, 7/31102.
2.

Exelon Transmittal of Design Information (TODI) No. QDC-02-019, "Quad Cities Station Concurrence with the Design Inputs as Established for Alternate Source Term (AST) LOCA Analysis', Attachment 2, Rev. 1, 8/1/02.

I E-FORM II

CacHA)e.

,t _

OR2E E° 0033 44.0,; qDc - 1170-1v-/24 a1s, tf

° p-Mip 16 RXELON TRANSMITTAL OF DESIGN INS UKMA I IUIN If IULfl INO.

1KLUUL-f'Y'

ItzV.

j fI X SAFETY-RELATED Originating U

_NON-SAFETY-RELATED X Exelon

_REGULATORY RELATED

_Other (specify)_

Station Dresden Unit(s) 2(3- )

System Designation:

(0000) rganization OJL)J) No. r'11UVV1-vyyy rev. I 0

\\1_

PD<n^5 Nina 1

Page 1

of 2

To S. Ferguson - Stone and Webster

Subject:

Dresden Station Concurrence with the Design Inputs as established for Alternate Source Term (AST) LOCA Analysis.

D. Oakley 6'7 -

C m

7 3 i-o2x Preparer Preparer's Signature Date M. Molaei JCL/

Approver Status of Information:

X Approved for Use

/)A_

/7sI

/7 Approver's Signature Date

-Unverified Method and Schedule of Verification for Unverified TODIs:

N/A Description of Information:

Transmit Dresden Station concurrence with the revised design inputs for the AST LOCA Analysis. These inputs were derived based upon the combined efforts of Quad Cities Station, Dresden Station, and Corporate Engineering Subject Matter Expert. The attachment contains a finalized list of these design inputs. Information was retrieved from controlled sources as listed in the attachment.

Purpose of Issuance:

Transmit a finalized revised list of design inputs Limitations:

None Source Documents: Various - The referenced source documents have been listed with each value in the attachment.

Distribution: D. Galanis, G. Lahti, R.Ruffin, M. Uhrich., RLV I '%'1

C

. 1k. DRgc 2- - 0033, At J. o et) -//Oo.--

( 2 i9 7v

. 0 Pax-. /7 PARAMETER LIST FOR POST LOCA SUPPRESSION POOL pH - DRESDEN NUCLEAR STATION Item Reference Value Comments

1. Maximum Suppression Pool Mass UFSAR Section 6.2.1.1 119,800 ft @ 950 F This is the maximum pressure suppression Section 6.2.1.3.1 pool water volume at minimum allowed Table 6.2-3a torus temperature assuming t=0.

Tetin 6,2-3a Note: The minimum Reactor building temperature is 65° F, as stated in UFSAR TS Table 3.6.1-1 Min pH : 5.6 section 9.4.5.

2. Maximum Reactor Coolant mass Dresden UFSAR Table 15.6-1 590,000 Ibm This is the mass of the reactor coolant in the NDIT EMF-96-165 Rev. 2 vessel mixing volume for Dresden. The and NDIT EMF-94-193 Rev.

design inputs for the Siemens-14 fuel show 2

that D/Q Reactor System Geometry are identical within +/- 0.001%. This value also assumes that t=0.

3.Maximum mass of any additional water pumped UFSAR Section 6.2.1.1 7,415 ft' Max Normal Level = 14'-6.5" into containment post LOCA from a source Section 6.2.1.3.1 Rounded up to Max High Level = 15'- 5. 625" outside the containment Table 6.2-3a 10,000 f' @ 95° F Conservatively the curvature of the torus was not included. 688 cu.ft/in level - 7,415 Section 9.4.5 ft'. rounded to 10,000 cu.ft (-20% Margin).

TS 3.3.5.1 Note: The minimum Reactor building temperature is 650 F, as stated in UFSAR section 9.4.5.

Volume does not include volume of Sodium Pentaborate solution noted in Item 4 below

4. Minimum mass of sodium pentaborate and UFSAR 9.3.5.1 3769.4 lbs This based upon a fluid temperature of 110 volume of sodium pentaborate solution delivered NED-M-MSD-2, RO

[3,391 gallons (includes degF and a Sodium Pentaborate to the containment / reactor vessel / suppression unusable volume);

Concentration of 14% by weight (specific pool following a LOCA 3034.8 gallons is the gravity of 1.069 at 80F).

useable volume]

TODI ER2002-9994 Rev IAttachment 2 Page AI of A4

/.

/

IDlj^x I So^

PARAMETER LIST FOR POST LOCA SUPPRESSION POOL pH - DRESDEN NUCLEAR STATION Item Reference Value Comments

5. Confirm that the entire inventory of sodium UFSAR 9.3.5.3 Approximately 80-100 Note that this is from the point of initiation.

pentaborate discussed above will be delivered and minutes.

Given the short amount of time to inject, mixed in the suppression pool within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the entire volume of sodium pentaborate after the LOCA.

can be procedurally assured to inject within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Using single pump injection rate, the SBLC system is capable of reducing power at a rate of 1% per minute: thus the time required to reach the zero power or hot shutdown condition from full power is 80 to 100 minutes.

Duane Arnold AST Submittal, 17,250 pounds The conservative estimates of cable

6. Maximum mass of cable Insulation, fillers and 10/19/2000 Assume Hlypalon insulation mass used in the Duane Arnold jacket materal in Conduit SL-5657. Rev 0 with 27wt % chloride.

AST submittal will be assumed to be Weight fraction of chloride applicable to Dresden and Quad Cities.

Weight fraction of fluoride 75% of the total mass of 23,000 pounds is Weight fraction of sulfur conscrvatively assumed to be in conduit and the other 25% is "free drop". A specific Dresden Unit 2 calculation is in ptogress to validate this assumption. T)ue to the similai vintage of the Dresden / QDC' Units. it is believed that the results of the in-containment cable inventory revicwv at Dresden Unit 2 is representative of the remaining units at Dresden and QDC.

Duane Arnold AST Submittal, 5750 pounds

--same as note for item 6, above-

7. Maximum mass of cable Insulation, fillers and 10/19/2000 Assume Hypalon 25% of Cable not in conduit jacket material not in Conduit with 27wt % chloride.

Weight fraction of chloride SL-5657, Rev 0 Weight fraction of fluoride Weight fraction of sulfur Page A2 of A4 TODI ER2002-9994 Rev I Attachment 2

I? t f. '0 I

Qj) (

_ // (.'70.- 4j-12 J-2, -/Tq %/,

0 C- 0 IC - de, 1) R I lo 7- - 0 0.3 3 f r9 0 1 2

/V PARAMETER LIST FOR POST LOCA SUPPRESSION POOL pH - DRESDEN NUCLEAR STATION Item Reference Value Comments Calculation DREO1-0006, 8.9E8 rads (airborne soulce)

This is an unshielded l-year value and has

8. Integrated worst case 30-day post LOCA Beta QDC-0000-N-1070, Rev. 0

+ 7.2E8 rads (plateout not been uprated for EPU. The 10% margin Dose in the Containment Atmosphere as specified source) = I.6E9 rads total for EQ is not included in this value. If a 30 in the EQ Program day value is necessary Exelon iequests that S&W use NUC-2 to obtain the pre-uprate dose, and then adjust that value for EPU.

9. Integrated worst case 30-day post LOCA QDC 0000-1n-1070 Rev 0 i9.81 E7 radsdTis is an unshielded 1-year value. It has Gamma Dose in the Containment Atmosphere as been upiated for EPU. The 10% margin for specified in the EQ Program EQ is not included in this value.
10. Total Integrated 30-day Dose (Gamma+

Beta) in the Suppression Pool as specified in the Calculation NUC I, Sheet 27 Gamma (pre-uDrate)

EQ Program 2.7E7 rads (gas region) 4.87E6 rads (liquid Region)

S&W to develop EPU dose Beta Exelon requests S&W to develop this value as it is currently not available.

TODI ER2002-9994 Rev lAttachment 2 Page A3 of A4

Cm IG. d. /)

T0

.- C7 3 3 AOft Y-0.

ha QI- /00 -A)J

- izis v,

4pee,. 0 PARAMETER LIST FOR POST LOCA SUPPRESSION POOL pH - DRESDEN NUCLEAR STATION Item Reference Value Comments I 1. Minimum ECCS flow from suppression pool UFSAR section 6.2.1.3.2.3 4,500 gpm per pump The minimum value for ECCS flow from TS SR 3.5.1.5 suppression pool would be significantly NEDC-32990, June 2000 higher in the first 10 minutes of the DBA SAFR/GESTR LOCA. This value is associated with long, term operation. The resulting long term containment cooling configuration consists of I LPCI pump, 2 CCSW and LPCI heat exchanger performance. The various analyses used different pump flow rates and heat exchanger performance values which were also evaluated for the various flows.

The evaluated heat exchanger performance values are identified in table 6.2.3b.

12. Vendor curves or table providing pH of Refer to the methodology pH Correlation for Boric The methodology for pH determination that sodium pentaborate solution vs sodium submitted by Grand Gulf AST Acid/Borax will be utilized was identified in Grand Gulf AST submittal pentaborate concentration including titration Submittal for sodium pentaborate.

shall be used for Dresden and Quad Cities curves.

Stations, as this is a simplified approach that has been accepted by the NRC. The Grand Gulf submittal used a simplified model that reflects disassociation of sodium pentaborate into borax and boric acid TODI ER2002-9994 Rev IAttachment 2 Page A4 of A4

Cj,-.

/ve. hp

° 0L. -0o'3 ev.o 0;(Dc!. -/v V/P e

xJ/J F C

2!

Jpc'.q A 2 f EXELON TRANSMITTAL OF DESIGN INFORMATION X SAFETY-RELATED Originating Organization TODI No. ODC-02-019 Revision I NON-SAFETY-RELATED X Exelon REGULATORY RELATED Other (specify)

Station Quad Cities Unit(s) 1I2)

Page 1

of 2

System Designation:

(0000)

To S. Feriuson - Stone and Webster Iihiet-QOiad Cities Station Concurrence with the Desigzn Inputs as established for Alternate Source Term (AST) LOCA

144

Analysis.

M. Uhrich Preparer R. H evn A-nurnve reparees Signature C 4"olm -

C 46 _V ;

Approver's Sgnature Date Date err Status of Information:

X Approved for Use

-Unverified Method and Schedule of Verification for Unverified TODls: N/A Description of Information:

Transmit Quad Cities Station concurrence with the design inputs for the AST LOCA Analysis. These inputs were derived based upon the combined efforts of Quad Cities Station, Dresden Station, and Corporate Engineering Subject Matter Expert. The attachment contains a finalized list of these design inputs. Information was retrieved from controlled sources as listed in the attachment.

Purpose of Issuance:

Transmit a finalized list of design inputs (Revision 1) Further refine the volume and concentration of SBLC System, revise the % cable inside and outside of conduit in the drywell, and minor changes in the comments section.

Limitations:

None Source Documents: Various -The referenced source documents have been listed with each value in the attachment.

Distribution: J. Gaudet, G. Lahti, B. Porter, D. Oakely.

I

In,.

Ad.

JAuIA On-c2 ci

,.1 0

O/)DC -,/ck'- o-

/fk9 R

1.O 5~--°J

,'t t0.'

{l D){

C pq,7 e 7 7 I/ 1I

.O I

I L;

PARAMETER LIST FOR POST LOCA SUPPRESSION POOL pH - QUAD CITIES NUCLEAR STATION Item Reference Value Comments

1. Maximum Suppression Pool Mass UFSAR Section 6.2.1.1 and 115,655 cu.ft. @ 65 degF This is the pressure suppression pool water 9.4.4.1 volume at minimum allowed torus UFSAR Table 5.2-4 Min pH: 5.6 temperature assuming t=O.
2. Maximum Reactor Coolant mass Dresden UFSAR Table 15.6-1 590,000 Ibm This is the mass of the reactor coolant in the NDIT EMP-96-165 Rev. 2 vessel mixing volume for Dresden. The and NDIT EMF-94-193 Rev.

design inputs for the Siemens-14 fuel shows 2

that D/Q Reactor System Geometry is identical within +/. 0.001%. This value also assumes that t=0.

3.Maximum mass of any additional water pumped TS Table 3.3.5.1 -I, TS Table 10,000 cu.ft. @ 65degF Max Normal Level = 14'-5" into containment post LOCA from a source outside 3.3.5.2.1, and TS 3.6.2.2 Max High Level = 15'- 11. 25" the containment QCOP 2300-10 Rev. 3 (HPCI/RCIC Torus Transfer).

QCOP 1600-12 Rev.1 l Conservatively the curvature of the torus UFSAR 9.4.4.1 was not included. 688 cu.ftlin level - 8000 cu.ft. rounded to 10,000 cu.ft (-20%

Margin).

Volume does not include volume of Sodium Pentaborate solution noted in Item 4 below

4. Minimum mass of sodium pentaborate and UFSAR 9.3.5.1 4041 lbs This based upon a fluid temperature of 110 volume of sodium pentaborate solution delivered Calc NED-M-MSD-2, rev. 0

[3607 gallons(includes degF and a Sodium Pentaborate to the containment / reactor vessel / suppression unusable volume);

Concentration of 14% by weight.(specific pool following a LOCA 3253.4 gallons is the gravity of 1.069 at 80F).

useable volume]

TODI-02-019 Rev 1 Attachment 2 Page BI of B4

Cc,/c.Sfe d, o z -e o 33 R.*v, 0; DC -j1x0

- Al - /Z -.

ie a, O I

2-3 PARAMETER LIST FOR POST LOCA SUPPRESSION POOL pH - QUAD CITIES NUCLEAR STATION Item Reference Value Comments

5. Confirm that the entire inventory of sodium UFSAR 9.3.5.3 Approximately 83 minutes.

Note that this time is started from the point pentaborate discussed above will be delivered and of initiation. Given the short amount of time mixed in the suppression pool within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to inject, the entire volume of sodium after the LOCA.

pentaborate can be procedurally assured to inject within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The time frame can also include a test to ensure that the sodium pentaborate is required before injection occurs.

IDuane Arnold AST Submittal, 17,250 pounds The conservative cstimates of cable

6. Maximum mass of cable Insulation, fillers and

.0110(

suCHplnisltinms sdi h ~aeAnl

.ae maera inCndi 10119/2(X)(1 Asutme Hypalon insulation mnass used in Ilhe Duane Arnold jacket material in Condult SL-56S7 Rcv 0 with 27wi %S chloride AST submittal will be assumed to be Weight fraction of chloride i

applicable to Dresden ant Quad Cities. 75%

Weight fraction of fluoride of the total mass of 23,000) pounds is Weight fraction of sulfur conservatively assumed to be in conduit and 25% is "free drop". A specific Dresden Unit 2 calculation is in progress to validate this assumption. Due to the similar vintage or the Dresden / QDC Units, it is believed that the results of the in-containment cable inventory review at Dresden Unit 2 is representative of the remaining units at Dresden and QDC Duanc Arnold AST Submittal.

5.750 pounds

--samc as note for item 6, above-

7. Maximum mass of cable Insulation, fillers and

/1/0)AsuiIlaln2%oCbentinodi.

jacket material not in Conduit with19/201X Assume lly calonr2i7d o.Cable not in Conduit.

Weight fraction of chloride SL-5657. Rev 0 Weight fraction of fluoride Weight fraction of sulfur TODI-02-019 Rev IAttachment 2 Page B2 of B4

'4 Co I c. tac

/Je-ORP 2- - 00 :3 3. lge tf C),' (Db. - 4/0o

- A)- /Zj-5i /eJ 0

/Ra t 2 q

-I PARAMETER LIST FOR POST LOCA SUPPRESSION POOL pH - QUAD CITIES NUCLEAR STATION Item Reference Value Comments Calculation DRElO l -06, 8.9-E-rads (airborne source)

This is an unisielded 1-year valueand has

8. Integrated worst case 30-day post LOCA Beta QDC-0)(000-N-1 070. Rev 0

+ 7.2E9 rads (platcout not been Uprated lor EPU. The 10S% margin Dose in the Containment Atmosphere as specified cource) = 1.6F9 rads total for EQ is not included in this value.. If 3(1 in the EQ Program day value is necessary Exclon requests that S&W use NUC-2 to obtain the pre-uprate (dose, and then adjust that value fur EPU.

9. Integrated worst case 30-day post LOCA CaQculatinn D RIe01-v006v 9

v1117 rads0This is an unshielded I-year value. It has Gamma Dose in the Containment Atmosphere as been Uprated for EPU. The 10%l margin for specified in the EQ Program EQ is not included in this value.

10. Total Integrated 30-day Dose (Gamma + Beta) in the Suppression Pool as specified in the EQ Calculation NTC 1, Sheet 27 GanImT1 (pre-uprate)

Program 2.7E37 rads (gas region) 4.X71.6 rads (liquid Region)

S&W to develop EPU dose Beta Exclon requests S&W to develop this value as it is currently not available i 1. Minimum ECCS flow from suppression pool TS SR-3.5.1.5 and NEDC-4,500 gpm per pump The minimum value for ECCS flow from 32990, June 2000 suppression pool would be significantly SAFRIGESTR higher in the first 10 minutes of the DBA LOCA. This value is associated with long term operation. It is recognized that under EPU the value for Minimum ECCS Flow may be greater than 4500 gpm. This value is conservative with respect to EPU flows.

TODI-02-019 Rev lAttachment 2 Page B3 of B4

CCJ, lo. to0. -b Ra 0 2 - e0e633) ?e :1. eO - SDC - //O 0 - Al- / -Z

  • 7 A

, '2 -

PI I

PARAMETER LIST FOR POST LOCA SUPPRESSION POOL pH - QUAD CITIES NUCLEAR STATION item Reference Value Comments

12. pH Correlation for Sodium Pentaborate Refer to the methodology pH Correlation for Boric The methodology for pH determination that submitted by Grand Gulf AST Acid/Borax will be utilized was identified in Grand Gulf AST Submittal Submittal for sodium pentaborate.

shall be used for Dresden and Quad Cities Station, as this is a simplified approach that has bee accepted by the NRC. The GG submittal used a simplified model that reflects disassociation of sodium pentaborate into borax and boric acid.

L AS-r ipfq P.)5, YGE Pj S n

-I TODI-02-019 Rev I Attachment 2 Page B4 of B4

ATTACHMENT 4 Revised Main Steam Line Break Accident Radiological Consequences 9

.'Lie-r

'bDresden

- Main Steam Line Break Accident

'Radiological.Consequence Analysis i

4.0 gCilg, Dose 0.2 jpDCilgm Dose" EquivalEquivalent quivalent 1-131 Regulatory Limit, Location Duration'-.

TEDE (rem)

TEDE (rem)

TEDE (rem)

Control 30-day 0.502 2.51 E-2 5

Room integrated dose EAB Worst 0.127 6.36E-3 25 (4.0 pCi/gm) 2-hour 2.5 (0.2 pCi/gm) integrated dose LPZ 30-day 1.59E-2 7.95E-4 25 (4.0 pCi/gm) integrated 2.5 (0.2 gCi/gm) dose Quad Cities -'Main Steam Line Break Accident Radiological Consequence Analysis

,4.0 ',iigr Dose" 0.2 p1Cilgm Dose Equivalent 1-131.

Equivalent 1-131, Regulatory'Limit' Location Duration TEDE (rem)

-- TEDE,(rem)^' ')

'TEDE (rem).

Control 30-day 0.502 2.51 E-2 5

Room integrated dose EAB Worst 0.250 1.25E-2 25 (4.0 laCi/gm) 2-hour 2.5 (0.2 gCi/gm) integrated dose LPZ 30-day 2.51 E-2 1.25E-3 25 (4.0 pCi/gm) integrated 2.5 (0.2 gCi/gm) dose

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