ML102571448

Enclosure C-1 (RAI 8) Latent Debris Calculation C11928, Revision 0

ML102571448
Person / Time
Site:	Kewaunee
Issue date:	02/04/2010
From:	Dominion, Dominion Energy Kewaunee
To:	Office of Nuclear Reactor Regulation
References
C11928, Rev 0
Download: ML102571448 (164)

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{{#Wiki_filter:Serial No. 10-025 Docket No. 50-305 ENCLOSURE C-1 (RAI 8) LATENT DEBRIS CALCULATION C11928, REVISION 0 CALCULATION ATTACHED CALCULATION COVER SHEET AND REVIEW REPORT Calculation No. C11928 Title of Calculation: Latent Debris Determination Rev. No. 0 Addendum Letter N/A Title of Addendum: N/A Safety Related 0 Yes El No (1) (2)System(s) / System No(s): ICS/23, S1133, RHR/34 (3)Oridinatina Document: CR347736 (4)Supersedes: uperseded By: Calculation No(s). N/A Calculation No(s). N/A Addendum No(s). 1 ddendum No(s).(5 (6)Discipline: El Engineering Mechanics/Structural Engineering (EM/SE) El I&C El Chemistry/Radiation Protection (ChemIRP) El Nuclear L-I Computer [ Mechanical El Electrical (7)This Calculation has been reviewed and was accomplished by the following: Reviewers' Initials (8 N Verification (Independent Review) ___0l Technical Review Preparer Reviewer Comments Discipline Printed Name Signature -ESP Qual Date (9)Attached Required 0 [] El Yes [ No Mech Lana Rabas -- El 0 0 Yes El No Mech Lori Christensen (644 ___E] El Yes E No El ] [El Yes [1 No 50.59 Applicability, Form Attached 0 Yes 50.59 Screen Form Attached El Yes 0 No 50.59 Pre-Screen Form Attached 0 Yes El No 50.59 Evaluation Attached El Yes 0 No Approver: Wisconsin PE Stamp (If Required)Printed Name: K. IJ. M-A/Ai-4x_4,eA N/A Signature: 9.tJ. )?.S' *,-- .-Date: A/ o/0 Effective Date: ) '/- /0 (See Steps 6.4.4 and 6.4.5 if Effective Date is different from Approver Date)(10 (n1 Form GNP-04.03.04-1 Rev. 20 Date: AUG 25 2009 REFERENCE USE Page 25 of 29 TABLE OF CONTENTS AND REVISION CONTROL Calculation No. C11928 Revision No. 0 Addendum Letter N/A Section, Attachment, or Other Description Page #(s) Revision Calculation Cover Sheet and Review Report (Form GNP-04.03.04-1) NA NA Table of Contents and Revision Control (Form GNP-04.03.04-2) NA NA Calculation Verification Checklist (Form GNP-04.03.04-3) NA NA Calculation Verification Comment/Resolution (Form GNP-04.03.04-4) NA NA Impacted Documents / Alternate Plant Configurations (Form GNP-04.03.04-5) NA NA Applicable 50.59 Review Forms (Reference NAD-04.04) NA NA Section 1.0 -Purpose 1 0 Section 2.0 -Background 1 0 Section 3.0 -Inputs and Assumptions 1 0 Section 4.0 -Methodology and Acceptance Criteria 3 0 Section 5.0 -References 5 0 Section 6.0 -Calculation and Results 6 0 Section 7.0 -Conclusions and Recommendations 10 0 Attachment 1 12 pgs. 0 Attachment 2 8 pgs. 0 Attachment 3 6 pgs. 0 I ___ I __i ma Form GNP-04.03.04-2 Rev. 20 Date: AUG 25 2009 REFERENCE USE Page 26 of 29 CALCULATION VERIFICATION CHECKLIST Calculation

1. C 11928 Revision 0 Verification Items YES NO N/A Purpose* Clear objective and problem statement

[ L Li" Affected SSC been identified .El 11* Intended use of results been identified E3 EL 0i* Any limitation of applicability LI Li 11* Revision content been summarized Li Li [* Appropriate 50.59 products completed 0 Li Li Methodology" Discussion of the method/approach and major steps [i(" Li* Limitation of use of methodology identified El EL B" Acceptance Criteria* Clear definition of acceptance criteria Br' E L il" Exceptions clearly defined i EL [I* Sources of acceptance criteria clearly defined El 'EL Assumptions 0 Sufficient rationale to permit verification of assumption B" E L il* Have unverified assumptions been identified as such [ Li Li* References provided for assumptions LL Li1 Inputs* All applicable Design Inputs been identified [ Li Li 0 Has source document for inputs been identified and verified to be 0 Li El appropriate for use 0 Computer data program SQA approval EL Li E'References

• Have all controlled plant input documents been identified 0 Li Li* If a procedure is cited, has the process owner been notified Li Li* Are references available from KPS records, or have they been attached ER EL 0I Calculation and Results* Correct formula/method used to support the objective El Li Li" Formula variables (including units) clearly labeled and consistent with 1:1 EL sources* Computer program input/output been reviewed [ :L EL" Reference to sketches provided L"7 Li
• Sufficient bases/rational to permit verification of engineering judgment Li Li" Proper carry over and use of significant digits I 1L Li* Computations reasonable, correct. t: 0L LI Conclusions and Recommendations" Clear statement of the results consistent with the objective

[ 1 Li" Acceptability of the results clearly defined [] Li* Recommendation for unacceptable results, CR written if necessary EL EL' IEr* Clear definition of limitations or requirements imposed by the calculation (5 EL Li necessary to maintain the validity of the results* Have the effects of the calculation on output documents been identified [' Li Li and addressed Form GNP-04.03.04-3 Rev. 20 Date: AUG 25 2009 Page 27 of 29 REFERENCE USE CALCULATION VERIFICATION COMMENT/RESOLUTION Calculation

1. Cl 1928 Revision 0 Reference Material Used: GNP-04.03.04 and Cl1928 references Reviewer Item # Reviewer's Comment Preparer Resolution Reviewerc_____ ____________________________IreprerConcurrence 5.2.1 -The cited reference is not retrievable Cited a different probability and purchased).

C new reference statistic book that I have available. that is readily available. Additional impacted documents include: 51-9020502, Rev. 3, including Addendum Documents added on Form GNP-A, CN-CSA-05-78, Rev. 1, including 04.03.04-5 and GNP-05.27.07-1. Addendum A, and CN-CSA-05-79, Rev. 1.Latent debris total quantity acceptance criteria shall be listed in 4.2, else make Provided in 4.2. Revised 7.0 reference to plant procedures where the accordingly. ___acceptance criteria currently resides.Add additional references: 51-9020502, Rev. 3, sample and evaluation procedures Included references.(NEP-04.22, NEP-04.23, CM-AA-CRS-101), and P&S Activity RE304731.Table 6-2 and Attachment 2, corrections 5 noted for cable trays 1CL7S5, ICT106N, Corrected values.1CTI07N, 1CT108N and ICX112N.Attachment 3, revise mass and area values 6 for horizontal equipment surfaces (pg 5 of Revised values.6).Incorporate changes to Sections 4 and 7 to 7 allow deletion of NEP-04.22 and NEP- Incorporated changes.04.23.Comment cycle complete: Preparer: Lana Rabas K_ _ _ ---___Date: la]a -]oO_Print S' nature -ESP Qual Required Reviewer: Lori Christensen Date: /,2 A?Print Signature -ESP Qual Required Form GNP-04.03.04-4 Rev. 20 Date: AUG 25 2009 REFERENCE USE Page 28 of 29 KEWAUNEE IMPACTED CALCULATION DOCUMENTS / ALTERNATE PLANT PROCESS CONFIGURATIONS SNOTE: Refer to GNP-04.03.04, Step 6.2.12 or Step 6.5.5 for Form Instructions. Calculation Number: C11928 Rev.: 0 Title: Latent Debris Determination Document or APC Document or APC Responsible Revisions Condition Report or Individual or Corrective Action Number Description or Title Process Owner Required Number(s)32-9071852, Kewaunee Power Station -L Christensen Yes CR 360908 Rev. 0 Debris Transport WPS-06-36, Rev Downstream Effects Evaluation L Christensen Yes CR 360908 0 including Add. To Support The Resolution Of A GSI-191 For Kewaunee Update Nuclear Fuel and Reactor Vessel Analysis To Reflect WCAP-16406-P Revision 1 And Debris Load Changes TDBD-KPS-Generic Safety Issue -191 L Christensen Yes CR 360908 GSI-191, Rev. 2 Assessment of Debris Accumulation on PWR Sump Performance, Kewaunee 2004-08820, GSI-191 Debris Generation L Christensen Yes CR 360908 Rev. 3 Calculation 51-9020502, Chemical Precipitation Analysis L Christensen Yes CR 360908 Rev. 3 For Kewaunee Power Station Using WCAP- 16530-NP CN-CSA-05-78, GSI-191 Downstream Effects for L Christensen Yes CR 360908 Rev. I including Kewaunee Debris Ingestion Add. A Evaluation CN-CSA-05-79, Kewaunee GSI-191 Downstream L Christensen Yes CR 360908 Rev. 1 Effects Debris Fuel Evaluation 51-9020502, Chemical Precipitation Analysis L Rabas Yes CR 360908 Rev. 3 Add. A For Kewaunee Power Station Using WCAP- 16530-NP Maximum Allowable Aluminum Content Evaluation C 11828, Rev. 0 Kewaunee Post-LOCA L Christensen Yes CR 360908 Particulate Deposition on Fuel Form GNP-04.03.04-5 Rev. 20 Date: AUG 25 2009 REFERENCE USE Page 29 of 29 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 1.0 PURPOSE This calculation determines the total quantity of latent debris (dirt, dust) in Containment. The quantity is determined by debris samples collected by CM-AA-CRS-101, Latent Debris Collection and Sampling Procedure (Reference 5.2.14).Latent debris is part of the Post-LOCA (Loss of Coolant Accident) generated debris inventory. This debris inventory is an input to the debris transport calculation (Reference 5.2.9). The transport calculation determines the quantity of post-LOCA debris that has the potential to reach the Containment recirculation sump strainer (158-051) and affect the head loss for the strainer (Reference 5.2.11). The transported debris can also affect the quantity of debris that can bypass (flow through) the strainer and impact the amount of wear on downstream components due to operating with debris-laden fluid, as well as potentially impact the debris bed formed on the nuclear fuel support grids (Reference 5.2.8 and 5.2.10). Latent debris is also an input to the post-LOCA chemical precipitation analysis (Reference 5.2.13).

2.0 BACKGROUND

This calculation supersedes Attachment 8.12 of Calculation 2004-08820, Rev. 3, "GSI-191 Debris Generation." During a review of the latent debris sampling and statistical analysis evaluation it was noted that several surface areas were omitted from the original calculation that should have been included (Reference 5.2.12). This calculation is updated to include the new surfaces and re-evaluates the overall quantity of latent debris in Containment with the additional surfaces.3.0 INPUTS AND ASSUMPTIONS

3.1 INPUTS

3.1.1 Sample

Data Table 3-1: Sample Data Debris Area Loading Sample (g) Area (ft) (g/ft) Surface Direction Elevation 12 0.7 11'0" x 3'0" 33.0 0.021 Clean Floor Horiz 649'13 0.15 7'0" x 8'0" 56.0 0.003 Clean Floor Horiz 592'4 1.8 3'6" x 5'6" / 2 9.625 0.187 Dirty Floor Horiz 592'5 -0.1 4'4" x 5'2" 22.4 0.000 Clean Wall Vert 606'7 0.1 5'9" x 9'0" 51.8 0.002 Clean Wall Vert 626'9 0.3 4'0" x 18'0" 72.0 0.004 Clean Wall Vert 626'6 0.3 Various 3.4 0.088 Dirty Horizontal Horiz 606'8 0.8 2-60 x 4'0" 10.0 0.080 Dirty Equipment Horiz 626'14 0.4 1'4" x 5'8" 7.6 0.053 Dirty Ductwork Horiz 592'11 0.1 3'0" x 4'0" x 3 36.0 0.003 Dirty Ductwork Vert, 649'10 0.5 4'6" x 7'9" 34.9 0.014 Dirty Wall Vert 649'15 2.0 5'0" x 9'0" 45.0 0.044 Dirty Wall Vert 592'Page 1 of 10 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 See Attachment 1 for sample collection data sheets.The initial debris sample collections were performed by Sargent & Lundy during the 2004 refueling outage.Samples 1, 2, and 3 were preliminary samples and the results were skewed;therefore, these were not included.3.1.2 t -Distribution Values The upper-tailed t-distribution values provided are at the 90% confidence level (Q = 1 -0.9 = 0.1), where the degrees of freedom (v) is the number of samples minus 1 (Ref. 5.2.1) [partial table below].t = 1 .886 c for 3 samples t = 3.078 a for 2 samples Table 3-2: Upper-Tailed t-Distribution Values v / Q 0.15 (85%) 0.10 (90%) 0.05 (95%) 0.025 (97.5%)1 1.963 3.078 6.314 12.706 2 1.386 1.886 2.290 4.303 3 1.250 1.638 2.353 3.182 4 1.190 1.533 2.132 2.776 5 1.156 1.476 2.015 2.571 6 1.134 1.440 1.943 2.447 7 1.119 1.415 1.895 2.365 8 1.108 1.397 1.860 2.306 9 1.100 1.383 1.833 2.262 3.2 ASSUMPTIONS 3.2.1 It is assumed that the debris is normally distributed for a given surface type. This assumption is supported by walkdown observations that debris distribution appeared uniform for a given surface type.3.2.2 It is assumed that the debris loading on cable trays is the same as the loading on ventilation ductwork. Debris samples are not collected from cable trays (Reference 5.2.14).Page 2 of 10 Dominion Energy Kewaunee, Inc. Calculation C11928 Calculation/Evaluation Revision 0 Title: Latent Debris Determination 3.2.3 It is assumed that debris loading for a given surface or surface type, when not available due to lack of sample data, is the same as debris loading for a similar surface type. The assumptions will be documented in Table 6-2.4.0 METHODOLOGY AND ACCEPTANCE CRITERIA 4.1 METHODOLOGY 4.1.1 Data collection is performed in accordance with procedure CM-AA-CRS-101, Latent Debris Collection and Sampling Procedure (Reference 5.2.14).4.1.1.1 Using Table 6-2, determine the locations for sample collection. 4.1.1.2 Obtain at least 24 usable samples, with samples from each of the surface types.4.1.1.3 Determine if the new sample data will supersede the previous samples, or if the new sample data will be added to the existing data.Consideration should be given to cleaning activities that many have occurred since the previous samples were obtained.4.1.2 The Containment surfaces used to determine the total post-LOCA latent debris (dirt, dust) loading that can potentially reach the Containment sump recirculation strainer are listed in Table 6-2.4.1.2.1 The surface area calculations are included as Attachment 2.4.1.3 For each surface or surface type, dependent on sample availability, determine the sample mean and sample standard deviation. ST___1 (Eq. 4-1)s 1 ' -01X1)2] (Eq. 4-2)Where: , = mean for group of samples (g/ft 2)X= individual sample mass per area (g/ft 2)n number of samples in group s = sample standard deviation (g/ft 2)N 4.1.4 Assuming the debris is normally distributed and the number of samples is small relative to the total population, determine an upper limit on the mean debris loading from the t-distribution at 90% confidence.- .-tU L 7= '< 11< t+ t 'S n tUL 7 , Page 3 of 10 Dominion Energy Kewaunee, Inc. Calculation C11928 Calculation/Evaluation Revision 0 Title: Latent Debris Determination S/JuLx+tuL7 (Eq.4-3)Where: tUL = t distribution value at 90% confidence for sample size n/UL = upper limit on the mean debris loading at 90%confidence (g/ft 2)4.1.5 Estimate the total debris mass for each surface and surface type by multiplying the total area for the surface type by the upper limit on the mean debris loading at 90% confidence (g/ft 2).4.1.6 When data is not available for a given surface, substitute a debris loading from a similar surface type until future data is available. Document the substitution as a calculation assumption in Table 6-2.4.1.7 When the acceptance criteria administrative limit is exceeded, or is being approached, initiate a Condition Report (CR) to evaluate Containment cleanliness and determine if corrective actions are necessary.

4.2 ACCEPTANCE

CRITERIA 4.2.1 The acceptance criteria for the total allowable quantity of latent debris in Containment is determined by the quantity of latent debris assumed in the GSI-191 tests and analyses.4.2.1.1 The acceptable quantity of latent debris for the entire Containment Building is 100 lbs.4.2.1.2 Fifteen (15) percent of the latent debris is assumed to be fibrous debris.4.2.1.2.1 The acceptance criteria for latent fibrous debris is 15 lbs.4.2.1.2.2 The administrative limit for latent fibrous debris is 10 lbs.4.2.1.3 Eighty-five (85) percent of the latent debris is assumed to be particulate debris.4.2.1.3.1 The acceptance criteria for latent particulate debris is 85 lbs.4.2.1.3.2 The administrative limit for latent particulate debris is 60 lbs.Page 4 of 10 Dominion Energy Kewaunee, Inc. Calculation C11928 Calculation/Evaluation Revision 0 Title: Latent Debris Determination

5.0 REFERENCES

5.1 DRAWINGS

5.1.1 S-220, Revision J, Reactor Building Containment Vessel 5.1.2 S-220, Revision U, Reactor Building Containment Vessel 5.1.3 S-235, Revision Q, Reactor Building Concrete Basement Floor El. 592'-0".5.1.4 S-237, Revision Q, Reactor Building Concrete Sections & Details.5.1.5 S-239, Revision Y, Reactor Building Concrete Mezzanine Floor El. 606'-0".5.1.6 S-246, Revision BC, Reactor Building Concrete Floor Plan at El. 626'-0".5.1.7 S-258, Revision V, Reactor Building General Section -Concrete Reinforcing. 5.1.8 S-263, Revision H, Reactor Building Unit 1 Reactor Shield Liner 5.1.9 S-250, Revision AB, Reactor Building Concrete Floor Plan at El. 649'-6'.5.1.10 S-272, Revision S, Reactor Building Wall Reinforcing -Elevation & Details.5.1.11 S-273, Revision T, Reactor Building Wall Reinforcing -Elevation & Details.5.1.12 E-314, Revision E, Cable Tray & Conduit System Reactor Bldg. Partial Plans El.606'-0" Sh. 1.5.1.13 E-315, Revision H, Cable Tray & Conduit System Reactor Bldg. Partial Plans El.606'-0" Sh. 2.5.1.14 E-316, Revision J, Cable Tray & Conduit System Reactor Bldg. Plan El. 592-0" 5.1.15 E-317, Revision Q, Cable Tray & Conduit System Reactor Bldg. Plan El. 606'-0".5.1.16 E-318, Revision N, Cable Tray & Conduit System Reactor Bldg. Plan El. 626'-0".5.1.17 M-365, Revision AK, Reactor Bldg. Piping-Chem & Vol. Control, Sample, Reactor Coolant, Waste Disposal 5.1.18 M-684, Revision D, Ventilation Reactor Building Dome.5.1.19 M-685, Revision F, Ventilation Reactor Building El. 649'-8".5.1.20 M-686, Revision N, Ventilation Reactor Building El. 626'-0".5.1.21 M-690, Revision C, Ventilation -Reactor Building CRDM Cooling.5.1.22 M-693, Revision D, Ventilation Reactor Building Elevations. 5.1.23 M-694, Revision C, Ventilation -Reactor Bldg. Sections.5.1.24 M-695, Revision E, Ventilation Reactor Building -Sections.5.1.25 M-696, Revision D, Ventilation Reactor Building Sections.5.1.26 XK-100-1, Revision 17A, Steam Generator, 51 Series -Outline Sh. 1 and 2 5.1.27 XK-100-161, Revision 5, Pressurizer Relief Tank 5.1.28 XK-106-27, Revision 0, Crane Girder 5.1.29 XK-126-1, Revision 4A, General Arrgt of 2 Bridges Plan & Elevation 5.1.30 XK-126-5, Revision SA, General Arrgt 3 Motor Trolley -Plan View 5.1.31 XK-126-6, Revision 2, General Arrgt 3 Motor Trolley -Elevations 5.1.32 XK-310-19, Revision C, Pump, Coolant -Insulation Arrangement 5.1.33 XK-310-22, Revision A, Pump, Coolant -Insulation Top & Bottom Head Page 5-of 10 Dominion Energy Kewaunee, Inc. Calculation C11928 Calculation/Evaluation Revision 0 Title: Latent Debris Determination

5.2 OTHER

DOCUMENTS 5.2.1 Walpole, Ronald E., et al. Probability & Statistics for Engineers & Scientists. 7 th Edition. Upper Saddle River, NJ: Prentice-Hall Inc., 2002 5.2.2 Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Generic Letter 2004-02, Nuclear Energy Institute Guidance Report (Proposed Document Number NEI 04-07), "Pressurized Water Reactor Sump Performance Evaluation Methodology," Draft Issued September 20, 2004.5.2.3 Calculation 2006-01660, Revision 1, Post LOCA Containment Flood Level (DCR 3605).5.2.4 Vendor Technical Manual ALLIE-0004, Revision 0, Telescoping Boom Crane Model TB24-65.5.2.5 Kewaunee Power Station Updated Safety Analysis Report (USAR), Section 6.2.2 and Table 6.2-13, Revision 21.4- Updated Online 09/30/09.5.2.6 Kewaunee Cable Raceway Application, Version 1.0.0, Run Date: 10/28/09.5.2.7 Calculation 2004-08820, Revision 3, GSI-191 Debris Generation

5.2.8 Calculation

51-9017897, Revision 2, Kewaunee RHR, SI and ICS Pump Evaluation for GSI-191 Downstream Effects 5.2.9 Calculation 32-9071852, Revision 0 including Add. A, Kewaunee Power Station -Debris Transport 5.2.10 Calculation WPS-06-36, Revision 0 including Add. A, Downstream Effects Evaluation To Support The Resolution Of GSI-191 For Kewaunee 5.2.11 Calculation TDI-6008-06, Revision 8, Total Head Loss (ECCS Recirculation Strainer) -Kewaunee Power Station 5.2.12 CR347736, GSI-191 Latent Debris Calculation, 9/9/2009.5.2.13 Calculation 51-9020502, Revision 3, Chemical Precipitation Analysis For Kewaunee Power Station Using WCAP-16530-NP 5.2.14 CM-AA-CRS-101, Revision 1, Latent Debris Collection and Sampling Procedure 5.2.15 Planning and Scheduling Activity RE304731, Latent Debris Collection 5.2.16 TDBD-KPS-GSI-191, Revision 2, Generic Safety Issue -191 Assessment of Debris Accumulation on PWR Sump Performance, Kewaunee.6.0 CALCULATION AND RESULTS 6A1 Sample data collection results are included as Attachment 1.6,2 The surface area evaluations are included as Attachment 2 and the results are presented in Table 6-2.Page 6 of 10 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 6.3 Using the t-distribution values from Input 3.1.2, the mean debris loading at 90% confidence was determined for each surface type or specific surface listed in Table 6-2. Refer to Attachment 3 for the mean debris loading evaluation. 6.3.1 The results of the evaluation are summarized in Table 6-1 and are based on sample data available to date.Table 6-1: Debris Loading Results SURFACE TYPE SAMPLE NUMBERS DEBRIS LOADING (g/ft 2)Floors and Horizontal Structures 4, 12, 13 0.181 Containment Liner 7, 9 (sample 5 omitted) 0.006 Walls 10, 15 0.076 Vertical Ventilation/Ductwork 11 0.003 -Horizontal Ventilation/Ductwork 14 0.058 Cable Trays Not sampled (use horizontal 0.058 vent/duct data)Horizontal Equipment Surfaces 6, 8 0.097 Vertical Equipment Surfaces Not available (use wall data) 0.076 6.4 The total debris mass for each surface type and specific surface are listed in Table 6-2.Page 7 of 10 Dominion Energy Kewaunee Inc.Calculation/Evaluation Tritle: Latent Debris Determination Calculation C11928 Revision 0 Table 6-2: Latent Debris Evaluation and Results DEBRIS DEBRIS DEBRIS SURFACE AREA LOADING TOTAL TOTAL ASSUMPTIONS/NOTES SU(t) ,f) *l Ibm)649M-8" Floor Elevation 4,670,995 0.181 845.450 1,864 626'-0" Floor Elevation 2,478.400 0.181 448.590 0.989 60-" Floor Elevation 5,758.569 0.181 1,042.301 2.298 597-W" Floor Elevatlon 8,145.001 0.181 1,474.245 3.250 666'-0" Pressurizer Missile Shield 306.326 .0.181 .55.445 0.122 Includestop of vault walls at this location 65&'-" Elevation RCP AIB Vault Wall Tops 257.971 0.181 46.693 0.103 660'-0" Elevation SG A/B Vault Wall Tops 483.906 0.181 87.587 0.193 Refueling Cavity Pool Floor (Elevations 623'-r, 613' 4, & 608 1,021.754 0.181 184937 0.408 a n d A I a u t F l m ( E e a t os00 -4 , 60)1 1 ,7 2 4 .4 4 4 0 .1 8 1 3 1 2 .1 2 4 0 .6 8 8 S laIn c lu d e so el vtw o nW s la b s 6 1 ,0a t e le v a tinon l n6 0 9 ' "l"B v a p e r v a u lt and 616i -Vauat onor eleevation 6056-4" onl09nB-vul Flo r/S ai Grtig 248000 0.81448.880 0 .990 Surface area per USAR Table 5.8-1 (assume Subject to Containment Spray 41,239.087 0.006 247.435 0.545 '-0" elevation and above Basement Elevation 4,618.141 0.006 27.709 0.061 592'-0" elevation SG and RCP Vault Walls 12,902.052 0.076 980.556 2.162 Press rizerExterior Vault W alls .....835.33 I9 0 076 63 486 0 140 .Interior walls protected from spray and break jet Prssrie_ Eteirautals____30.7 by missile shield and floors within vaults Ray Pool Walls 5,33.580.076 38252 0.843 als likel cleaner due to ool flood/drain Horizontal 649-6" Elevation and Above 1,833.057 0,058 106.867 0.236 Due to only one sample available, 10% is added-_----_---_--_t the debnis Ioadinj for margin ---Ho r i zo n t a l C R D M a n d 6 2 6 -0 " E le v a t io n ..... .3 2 3 ..0 .0 5 8 .. 2 9 .. .0 .6 4 --D e t o o n ly o n e s a m p l e a v a i l a b le , 1 0 % is a d d e d Horiontl CRM ad 86'-0 Elvaton 4932 0 58 2.11 0 o the debris _loadirNgfor margin Vertical 649'-" Elevation and Above 3,887.397 0.003 12.828 0.028 Due to only one sample available. 10% is added C R D M and 62,- E levation 779. 8 ,4 I 0 ..,3 / 2. -, /D ue to only o ne sa m ple availa ble , 10% is ad ded Vefa RMad66WEeain7984003257 0.0 the debris loaing for margin Page 8 of 10 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Table 6-2: Latent Debris Evaluation and Results (cont.)DEBRIS DEBRIS DEBRIS SURFACESURFACE AREA LOADING TOTAL TOTAL ASSUMPTIONS/NOTES (ftZ) 7 I (g )Ibm)Subject to Containment Spray 1,794.500 2,773.000 0.058 0.058 104.619 161.666 0.231 0.356 Due to only one sample available, 10% is added to the debris loadin tfo rmargn Due to only one sample available, 10% is added reaesia, ~,rane 75.oo00 0.097 7 275, 0.016 Polar Crane Polar Crane Rails (Elevations 715'-6" and 703'-6-)Steam Generators 1,802.354 3,646863 409 488 ir,7 nAn 0.181 0.181 0.097 tA (107L 326.226 660.082 39.720 1K R 07 0.719 1.455 Due to no (or infrequent) cleaning, assume higher debris load similar to floor vs. the equpment s urface loading Due to no (or infrequent) cleaning, assume higher debris load similar to floor vs. the pquipment surface load ing Insulated diameter 0 088 n nAA Pedestal Crane Polar Crane Polar Crane Rail Supports Steam Generator Sides RCPs/Motor sides 200.000 4,444.852 1,067.500 0.076 0.076 0,076 0.076 0.076 15.200 337.809 81.130 471 949 119.381 0.034 0.745 0.179 Assume debris loading same as walls due to lack of eipment surface data Assume debris loading same as walls due to lack oqfeuipment surface data Assume debris loading same as walls due to lack of equrpment surface data Insulated diameter; assume debris loading same as walls due to lack of equipment surface data 6,209,853 1.570.796 1.040 0.263 lInsulated diameter; assume debris loading same ias walls due to lack of equipment surface data Floor/Stair Grating (Vertical Surfaces)Pms~surze Relief Tank 9,9200001 542.4481 0.076 0.0761 Surface area per USAR Table 5.8-1 (assume 753.920 1.662 80% of grating is vertical surface); assume debris I.. ~ loadin similar to wall sample data 41 .226 i 0.091 100% of tank surface; ssume debris loading 412261.. 0ý09 ý.._ -c*-L-*J-- Page 9 of 10 Dominion Energy Kewaunee, Inc. Calculation C11928 Calculation/Evaluation Revision 0 Title: Latent Debris Determination

7.0 CONCLUSION

S AND RECOMMENDATIONS

7.1 Conclusions

7.1.1 The total quantity of latent debris in Containment is 21.903 lbs.7.1.1.1 The quantity of latent fibrous debris is 3.285 lbs. This is below the administrative limit of 10 lbs.7.1.1.2 The quantity of latent particulate debris is 18.618 lbs. This is below the administrative limit of 60 lbs.7.2 Recommendations 7.2.1 No CR is required. Latent fiber and particulate debris quantities remain well below the administrative limits.Page 10 of 10 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment I KEWAUNEE NUCLEAR POWER PLANT LATENT DEeR WALIDOWN Sfq* 4 Aslin VaDeaMu MW VAcuum F~tW & B" Wept Inftb li-s A,~7-O*Am. Twoe maw, ft*, *k) Fi&Dewla 1!~ tk -4, Of AMu(A4pW=Ibft)I~xW1 1~i5( 2f 1-1 j!6h ifL~P.0k a *AIM alwm em eOw hdudfnahmnait I! Ia~l" igoafewo. murmnwb): Page I of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1-5vb KEWAUNCE NUCLEAR POWER PLANT LATENT DEORM-WALKDOO Flir Beg Wuight lvd"~122 2L- ~Dole,. Vacuusm After Vacuum Dam I Am Typ*(FboTEmJ~ c)Elevalon 6L Z. 1~A L /d~O#Arm (4pA~odmo) ILx W) 4_____K ()5i 1~jti i-71-provie S pkI,,h o1 the am. below (hindu contskmdi -I'omdon uewen ma'nmouv s)A: 4 I 11ýz I.W.L SIp'*ws Page 2 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination KEWAUNE0 NUCUEM POWER P LATENT VE11S)WALM2M Calculation C11928 Revision 0 Attachment 1 8810 Vsacuum AV&G urm FOW & ft Wekt Ir lo0. 6f , I-f le A D, , -Aims TWOMME(W.6Il~. gi).r-A 10 ka -s --Msm. oiS. LW ...- .o.' ._tP,4. Prouvi a sluat d e ause below (include co M InutmcUn m lams F muMMruM ): S44 9...J 1 4 ,)Laa.t 4.2 50 4-lib g" "tSLO...14#0 Odf 4 59.1w. S Page 3 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment I SeIMn1es?KEWAUNKE M&CEA POWER PMAE LAENIT 090111111 WAL-KDOWN FItr & BegWeIW BilasVsovau Oft Me"mVon A_ __ _ "___e_ M-A6 7-0j: PMVuW a Ownd of ft ares beowm Onduf 0otSkinmw solow wep~ MeawMinenW 4"mrr Stnows Page 4 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1-BnW KEWAUNEE NUCLEAR POWER PLANT LATENT WALKOWN FtmW &'Be We" InUlf-I Ilk Aftem Veom Dal*Aime Type U'loo. Eqsip% sic) 6W-git yt sAton .ýa- o O I_ _-Am (Approftail) L x W) £"0LIAt .: P,*Ide a a', 10 d fte area belw (hIrude cordabngfd lacon miesm P)WMuuwunfu): W-MM 4ýýýýOsw t2A&*-Page 5 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1 SOMw9 KOWAUN9 NUCLEAR POER AN LATENT DEBRIS WALKDOWN P113-jag /'S W. ~ hAW 1a~~ 6U2W9 Before Vamcum"M Vacuum Oft.. /e-7-o4-Arem (Floor, Equo, a" 4- f.APda(Appmdms)jLXhl Ir'WxjA'fd a e I.): Pt~f sketd al4 ft *ars jbe (Incklud cmimicrmJ'. i om -rofsa ma sessupemewa): 4 7 i8'8lOWeM-"ýý%-zV Page 6 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1 SNpl 10 KEWBUNEE NUCLEAR POWER PLANT L.-i~M OE-MS WALKDWN FIr&BMwIQW Inm Istore Vscw Mar VauM Ode Am Type (FO-. Equip, oft) ,, r() LxWI W A 1"4,9 Proymd a edtih al ft Was bob (hkdod Owalntamot Wa~ON WWaflo MOONieaMiwi --17-0 4-0 IA S~a.-u Page 7 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1 Samphle KEWAUNEE NUCLEAR POWER PLANT ,LATEN DEBRI Fler efBt WWit kift1b ,A, -4au,, -J00,& .. 62Ul/t 4 4býBoorM VwuumVacuum I o.-Area Two (Plo.' Equip, so) "DZOM AMe 0(AWMIdel) IL x Vq 31 Vo 1A f/-27-O4-Ptoif a sk*dh al Ow ames b0M3O=:*W=M~ lacibi relmmooc MOM&AWMai)-cai I I SMA Sirown of Page 8 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1 Smpe 2 KEWAUINEE NUCLEAR POWER PLANT LATENT DEBRIS WALKDOWN Fib, S U~g Weitkla SBrem Vauuim Aflhi Vacuu Dabs je4*7-Of-Afft Type (Floa, Eqip e"o kw.EhuidlonJ:S. ,w _ _ _ _Awna(A~presdmee)A. x W1 ______ 3/__Off-_Pawida a Sketd~ de area below (lnchde wbnthrm~t loI- 'M eleinisi mbammwnenw): a iA 5lp~te '~ 0816f Page 9 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1 ftMpIOMJ.KEWAUNEE NUCLEAR POWER PLANT LAT RENTDEBRIWALKDMW Filter & Bag Weight Inmtls I/pp. o ~ /I14 Before Vacuum Aftir Vacuum Vote Am Type (Moor. Equip. ot) i Amee(A4proximtue)lLxW) " i).L / iff -lo-.27-o,, Provide a 3imich of the area below (include containment location refrnco asurenmente): OW olft.&OL Page 10 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1 5EWAUNEE NUCLMA -POWER PAI Sample %I+861cr. Vacuum Afterv Vacuum FMer & On WeWgh of lt-a Dj7o* 1-Arsea Type (Floor, Equip. ate) ODW2-Elwmaton 5. fQ /Ar" (APPrOW01mat. IL xW1 Vi ..6L&.4#L&2 Proide. asketch of fte area below (Include cartainmo nt locatin 1Utwen meBSuTflharfllO pi SiWnatur Da Oe MAP Page 11 of 12 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 1-ampIXj5 KEWAUNEE NUCL.AR PMOWME1R LATNT DEBRIS WALKDO Filfter & Bag Welght Inhtuls-, '---BeftoVmecuum After Vacuum Dole 27-0~Am Type (Floor, Equp. ate) W/ALL Elevation imate) (LxW1 6 'd AP-.27-0*- Provide a skaech of #hw arm below (Include onaminment locutallon Wresce rnsuremwM): '4 ewvc-C"VrAq. I(kA 6,- 4.'AI.jM J.M6AmJ Aw*.t; 1&4" krftJt 6c UA JAruiJPr %j am.SignaDate -22hLP V-Page 12 of 12 Dofihinlor EnrgyW Kewaunee, Inc.Cakuhilionffivauatbon 1TUe: Lateunt Debris Deterrnnahioo Calculation C1 1928 Revision 0 Attachment 2 AREA DETERMINATIONS ty ty)Ic.ry Sheld Wall 4-SG A Cavity Waft 4-Fboor Elevvatin.... .. .I --7 781W x 32+ 14'-5 3116 + 19-9 3/16") x Y-2" 8) x 3'-2*"Al x 3-2 11/8") x Y-2" 'I 6.-+ 7-7 7/81) x 3-2 0*-3W + 14'-5 316 + 101-9 3/16") x 3T-2 I.-13-101/4")I-Primary Shield Wall th Stalrwell , Wait I m CuoW 11 -R & 444 R 0 V Veilical 32-l0%A R m x 17-8 9/1(r (21%"-l'-10 548) x 31-2* (11) W Y (W + -10 1/r) x 3*-2' 2 13/111 -V-711W) x Y-2" (2 1 3/8" -Y-10 1/8") x 3%2'*- Wx 3*-2 (17 4 x Y-2 *7 1/16 +1.1W-l*-12'-W) xY-2-4 Page I of a Doriwuo Energ Kew""., ftc.Tide La~ Debris Dellariirmnon Calculation C1 1928 Revision 0 Attachment 2 AREA DETERMINATIONS Cstsgo&&gb-aemor ________________________Am____M2)_ Referonc._1__-8 7/1_16+ 2_-7 W/8 _ -7_-0_) x 3_-__ (29.6710 S-235 3'-2* + 8-3 3/6 + 14'-5 3W16 + 4-8A) x 3T-2 J .7977) S-235 A CavWftwa 5*-8 71("+ 2*-7 7/81 x 3-r (2 43 S-235 2__-4 _ __ __ -2 _-7 7_8- 112'-W) x T-2" (44,9438) S-235__'.,,6,-!_-1__"_x 3_-2_ (117.0868 S-235 I'-__" x__ _-2"

• __ 11.74831 S-235 (4_-1_1 3W- 3'.10 118W) x 7_-2"" 'A (1.7483] S-235 (5!-7%' + T_-10 I/8M x 3-2'- (29.918 4 S-235 (r-5 13M1 -5"-7'A) x 3-2" -(2.9770] S-235 5927-0 Floor Elevation (V-614 -T- W) x 3-2 m98WW S-235 T_-7 SW6, x 3'-2" (11.5122 S-235 (Cont) (V-2* + &4r + 3-r) x 3-2* (62,2778 S-235 1-rna _x_2_-0_x_4 (20.0OWO S-235 3*-0" x 2'-0" x 2 (12.0000)

S-235 2_-0" x 2-0" x 1 (4.0S00 8-235 Fi Rx Wall X_-79/16 x _4 __0 (14.5208 S-235__-0" x (3-2" + 4-4%" + 4'-3 SW6 -1'.6Y/) (61.9375) S-235__.8__"_x 64-O"" 4 (4.56 2 5 S-235 1'-_/A" x 6-0" 'A (4,5625) S-235-0" x 3-0" (18.0000j S-235 Area AdH. toSG 81 19-10"x 1V-2 916" 222.4019 S-250 666-0" Pressunzer TdairAreas -1 716, x 6-1 7116" 374519 S-250 Missile Shiewl R Area between Triangular Area T-7 1/8* x 6-11 7/16, 46.4722 S-250 B WestWail 1 _-Wx 12_-3/8" 21.0547 S-250 B otWall '-2 x 18'-4 5/11 58.1380 S-250 B, at -Wa8 3-2_x 16- 3/16, 48.8689 S-250 A Wan 1_-9"x 15-2 39r" 26.5964S-250 R A Souh Wal _-2"x 1r_-2 5/16, 54.4436 S-250 A West WaN 88-22 x 156-5 3812 48.8_S-250 RCP&SG Vault Wall West Wll -2x 21V-5 5/W 67.9844 S-250 Tops 8 Norlh Wll 3Y-2, x 16-8 M16 52.922 S-250 B East Wael __-2" x 15_-8 3/8" 49.7101 S-250 aEat Wag _ _-2_x 12_-1 3W 38.3628 S-250 A Wall 3_-2" x 20_-1/4" 63.3993 S-250 AWest"WaNl __-2" x 12_-5 3/16" 39.3689 S-250 A Wast WaN __-2" x 1_-11 V 44.0094 S-250 GAWSouthII Wl-2Tx 1rT-89W11r 56.0 929 250 OA East WaN W-2-x2Z-8 1 71.9922 S-250 Page 2 of 8 Douninion Enrgy Kemkinee. Inw.Titl: Laleri Debris Deteffirtation Calculation C11928 Revision 0 Attachment 2 AREA DETERMINATIONS Category ,oDlmensions Area f12) Reference Rx Vessel Elevation 23'-7" 22-0' x 26'-6" 583 0000 S-258 & S-246 Vessas Area 14-" D (153.9380W r263 Elevation 613'-6" Rectar 22'-0" x 13-3.24" 291.9400 S-258 & S-246 & Figure I Refueling CavityPoo MidPl evation 615"e-6" a V11*-0.12* x'-11.76" 98.8698 S-258&S-246&Fi 1grI Floor 613-" Tri 17-10.44" x I'4-S" 2.2243 S-258 & S-246 & Fgure M l 61 Trian'-T gle 114'-11.52x 8-1.44" 60.7376 S-258 & S-246 & Fimn 1 Elevation 613'-6" Tdg& W-1M1.76" x 11I"-0.126 32.9199 S-258 & S-246 & Filgure 1 FT Transfer Eleiton Q-0" 106,0000 Caic. 2006-01660 (pa 29)Vault B 816'-0" Platform below PZR 13'.-8 x 14C-2" 191.2500 S-272, S-246 104 w--&x wl- 3V8"x 19-1 3/4"max.) 201,6296 S-272. S-248 Steam Generator A/B vault B 809' North Shlo 5T3/4" x 19-1 3/4" (max.) 100.9145 S-272. S-246 Vault______Vault 8 6-4 Shoff 23'-2 5/8 x 19-1 3/4" (max.) 444.5423 S-272, S-246 VALt A W- I o Se 104-6 3/V x 20Y-I 3/4" (max.) 212.1608 S-273 S-246 Aj,,gSheff 5'-3 1/4" x 20-1 3/4" (max.) 106.1853 S-273! S-246 23A A -2Z-2 SW x 217-1314" max. 467.7611 S-273. S-246 IUsAR Table 5.8-1 Flko/Stair Grating______________USAR Table 5.8-1 Liner [05D %Oin 731'-8 to $1080 1 41,-3983372 S-220 Contanent 15'-2 x 10'-" S-221 I I III Eg A Cavt (11'-5" + -3 9/16*) x (El. 6 -0" -649-" + 3-4" + 2'-r) 292.2734 S-250 & S-273 A Cty Outer Permeer (El. 60'-0"- El. 649'-6") x (13'-11" + 4'-1 3/8 + 7-5 13/1" 736.8047 S-250 & S-273+ 20-OA" + 37 + 3'-2" +10-0" + 8'-3 5/8")86 A Cavity Inner Perimeter (B. 880-0" -El. 606'-0") x (5!-7"AA + 3'-10 1/6" + 8'-3 5/8" 2046.9375 S-250 & S-273+ +10'-0"+13'-11"- 1'-1W" -2*-778"7)_ EOA Cavfty (11-W + V-3 911") x (El. 6WO -06494r + 3'4*+2'-8) 2922734 S-250 &8-273 RCP A Cavity Outer Perimeter El. 655', -El. 649'-) x (15'-5 1/16" + 18'-4%* + 13'-11 3/1" 293.8438 S-250 & S-273+ 1'-33116") RCP A Cavity nner Perimeter E.65 " -El. 606'-0") x (10'-9 3/1" + 1'-3 3/16"+ 15'-5 1/1" 2857.3359 S-250 & S-273--777/8" + 11'-5" + 6'-3 9116" -2'-6" + 11'-5" + 6'-3 9/16")Vault Walls 8 CIM* (10Y-5" + 6'-3 916") x (El. 66(7-0" 6-49-8" + 3-4" + 4-8") 275.7734 S-250 & S-272 Vau Wgavit Outer Perimew (E]. 60-0" -El. 640-6" x 13N-11" + 4'A1 3/8 +r -5 13/16" + 37' 526,5859 S-250 &s-272+ 3'-2" *' 10'-0" ÷ 8'-3 5/8") _____________ SG B Cavity lener Perimeter (El. 660"0" -El. 68-W0") x (56-7% + 3-10 I/8" + V-3 5W + 10'0 2,046.9375 S-250 & S-272+ 13'-11" -1/1'" 7 7/8")8GB Inner Perimeter (Przr Side) El. 660-0" -El. 646-0") x (14'-8") 205.3333 S-250 & S-272 (B10,-5" + 6'-3 9/16") x (El. 660-0" -649-6" + 3'4" + 2'-8") 275.7734 S-250 & S-272 a B____OuterP__ner _El. 655'-" -El. 649-6")x (15'-5 1/16" + 1I'-4%" + 13'-11 3/16" + 1'-3 3/16") 293.8438 S-250 & S-272 i e C_ _ _ Inner Pe__e__ EI. 6-8"- El. 608'-0") x (10(-9 3/16" + 1-3 3/16" + 15-5 1/18" 2,756.3359 S-250 & S-272-27-7 7/8" + 10-5" + 6'-3 9116"- 2'-8" + 10-5" +8'-3 9116")Pagc 3 of 8t Domviion ErmWg Kewsurtme Im.CA~hErdsudion Tide: Latert Debris Detennintsor CalcuLation 011928 Rtevision 0 Aftactwnent 2 AREA DETERMINATIONS Rekfu Cavity Pool WaNs to 649~-W* orizonta I-6-I-I-I-6-.---.-a-I-I Vertllatb"o uctwork Y- Horizonta Y- Horbm" Y- Hodzo" X Horiax"t Page 4 of 8 Dcn*ion Energ Kowwroe, kr Title: Latet Debris Delermirwibon Calcuation C1 1928 Re,&vion 0 Attachment 2 AREA DETERMINATIONS 0- Dlnsions Area()Reww V=nm Van. .P4"f x 4g x 2 SM752 1"9 Sc D-u & E-E e, Hot ý Vertical ?rx44' 264.0000 .-W ler, Hot jg& -Vw*l 0x16' 80-0000 M-.85 Plenu-Vertcl 34"x36"x 12.5' 106.2500 M-685 & M-693 SecB-B Rx Go Vert -Ve* 24'0 x IV' x 2 226.1947 M.-M Sec B-8 VentmS -. Vehtcal 48"D x IT 213.6283 M-893 Sec B-B Purgs EAM -VeWrcal 40'D x 24 251.3274 M-5 & M-..4 Sec A-A ,urg SU,4 -VetcWl 3(r x 42" x 14.5' 174.0000 M-.85 & M-694 Sec A-A=eV= ,uv.y -Veruc 48 x Ir 2 13 628u M-M~ Sec P-A Vervtitiaton(ucwo (Cont.)l- Vetical 4 -Vrtical K Verfical t s&poy -Voertical n4 suodv- votikw A WIV- \*1w .\Avc x8'x2 x 2 x 2 x 2 2 x 2.x2 2 x 2 x 2 x 2.9 Cable Trays 4 N I-I-I-4-I-I-+ 24 x 21T I-I-I-I-4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 4 -E-318 I-I-I-.-1-I-4-I-Page 5 of 8 Dominion Energ Keweuwm. ftc.Tide Lahmt Debris Doelrrtinabon Calculation C11928 Revision 0 Attachmenot 2 AREA DETERMINATIONS catgoy Raferonce-314 -E-318*314 -E-318.314 -E-318.314 -E-318 Cable Trays (Cont.)1 LIOIN. 4x r 6.0000 E-316 & Cable aew A .TC-L102N rxI 6.&OD E-316 & Cable RottAp ICL103N lrx 12" 700 E-316 &Cablesa~m o 1 L104N 17X121-00E36&Cal tovyAP ICLI05N 2-Tx 17 300 -1r al wwyA ICIOSN 16 xl 12 8.0000 jE-316 &Cable aoiyAP ICLI07N I&x12"1.00 -1 CbeRaowyAP 1CL108N 2Y x12" 23.0000 E-316 & Cable Racewa A.ICLI09N 20x 12" 20.0000 E-316 & Cable RacewayA.ICLIOS 25!x12" 25.0000 E316 &Cable RacewaYAP 1CL11ON 4Tx18' 64.5000 E-316 &Cable RacewayAp ICLIIIN 31Yx 18 45.0000 E 316 &Cable Raceva APP ICLI12N 4Yx I 64. DE-316 &Cable RaoevvayA. ICLI13N 2rx 18' 40.5E-316 &Cable R0wyAP ICL114N 2Yx IS 30. DE-316 &Cable aewyAP ICL115N MYx IS 30.00 E-316 &Cable RacewauAp________________ __ __Y_ __ _ __x__ _ __I__ _ ___r_ _ 23. EV316 &Cable RowyAp 1OL12SS________ 4r _________x______18________ 70.500 E-316 &Cable RacemwAm I __ __L13_ __ __ __ 3Y _ __ _ __ _ __x__ _ __ _ __ _ __ _ __ 49.W E-316 & CableRace yA PPa ICL14_ __ __ __ __ 4 _ _ __ _ _ __ __x_ _ __ __Ur_ __ _ _ 72.00 E-316 &Cable RacewayA ._______________ 3 ___________x_______1W_____ 52.5000 E-316 &Cable RacewayAP________________ 2r __________x_______12_________ 27.0000 E-316 &Cable Race"w APP ICL2______________2______x____IT___ 2700001 E-3161& Cable RcwyAP IWO______________________ 2r x 25700001E316 &Cable PcwyA 1CAS 3 ________________________ 188 45 E-316 &Cable 5SMAP 1cL9S5 I& ____x___IT____16.0000_______ ~IE316& Cable RcwyAP 1CL IV x______________________ _ 12 1600E-316 &Cable R~wyAP 1CLBO2N 2r __________x__________________ 27,00001E-316 &Cabl aS em AP IGTO3 3V __________________________ 252'380000 E 316 &Cable ce"AP 1104ON 26 ________x______12_______ 27 00E-316 & CabloRae m"A ICT102N 2 ________________________ 3 227 OOOE316 &Cable RovyAp ICT103N 2 _______________________ x42 5.00 E-31 & Cable Rq nAP ICT104N 2 ___________________________ x30'2.0000 E-316 & Cable RacewayAP iCTIOPI 32x __________________________ 42 2.0 0 E-316 &Cable RcwyAP ICT107N W _________x_________IT________ 25.OD E-316 & Cable Racewa A , IC 1105 _________x________12___________

30. 00E-316 &Cable Raceway m ICTIION 2r __________x_______2__________

54.000E-316 & Cable 5EMA ICT111N 12(Y___________x___________ 20.000E-316 & Cable RacewayAP Page 6 of 8 Do*mion Energy Kewauniee, Inc.Cdculationu-valuaton Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 2 AREA DETERMINATIONS Catgor Su-aiw Imrl Are () efrnce 2ff x 12" 28.uuuw -31i & uable Racewav ADO.ICMISS "~8x 12" 28.0000 E316& (iCT2SS IS x 12' 500 -1 4bW Race"bl Racev 5____________________~4.000 E_________316____________ & Cable Raceway p.S 43'x 12" 43.0000!E-316 & Cable Raceway App.43" 17'434 x. ---E-316 & Cable Raceway App.E-316 & Cable Raceway App.1CT7S5 45'x 12"-4 40'x 12" 40o.oo0W-316 & Cable Raceway App.I d,5' V 12" E-316 & Cable Racewav Ano.-4& x i--XI01N 3W'x 12'E-316 & (F-318 & (my --4).I ,, R" 7.5iflnl ,5! 18"E-31 &32' V 1f" 4B.UUUU E-316 &Cable Raceway Ano.A2 x --'V41~AkIA*; fli=.UF'IR ,A Ann Cable Trays (Cont.)05N 4' x418" 67.5000 E-316 & Cable Raceway APP.0CX06N 42'x 18" 63.0000 E-316 & Cable Racewa App.CX107N 40 x 18" 60.0000 E-316 & Cable Raceway App.CX10N 43' x 18" 64.5000 E-316 & Cable Raceway App.CX10N 35' x 18" 52.5000 E-316 & Cable Raceway App.CXl0S5 52'x 18' 78.0000 E-316 & Cable Raceway App.MCXOSN 30' x 18" 5.0 E-316 & Cable Raceway App.1CX11N 32'x 18" 48.0000 E-316 & Cable Raceway App.1CX112N 30 x 12" 30.0000 E-316 & Cable Raceway App.ICXl125 'x 18" 37.5000 E-316 & Cable Raceway App.CXi2S5 25'x 17' 25.0000 E-316 & Cable Raceway App.CX1S5 2V x 12" 25.0000 E-316 & Cable Raceway App.1CX2S5 I 2x1 12.0000 E-316 & Cable Raceway App.CXS205 x 18" 30.0000O E-316 & Cable RcwyAp ICX4S 35'x 18" 52.5000 E-316 & Cable Raceway App.iCXSS5 xis, 630.0000 E-316 & Cable RacewayAp lCUS V2 x 18" 52.5000 E-316 & Cable Raceway App.Cx6s5 4Z x 18" 67.0000 E-316 & Cable Raceway App.CX745 x 18" 64.5000 E-316 & Cable Raceway AppR

• iJ A j4V EU '.,, W'-1.-31 ' al R~ A -4I 37' IR1'55.5000 E-316 & Cable Raceway App.Note: Not all of the above cable trays will be totally submerged, but this is a conservative value and will also encompass the small amount of piping that will be WM Vr I~M ALLIE-0004 Pedestal Crane I I TM ALE00 437.5000 IXK-126-5 4 ~~ii.iI>Bwdole Too Surwfac 9T-6 7f8 x T-" (value doubled to account for additional surfaces)1.364.8542 IXK-126-1 I-I__Polar Crane 4 I-rroaev Side Sur7aces I2 Sides7 14'-0" x 9'4r7 + 31'-3" x 8'-0 724.0000 IXK-126-6:: T':ZJ I.-9r-5 7/8" x 9-6 1/2" 3r,720S524 IXK-126-1 Page 7 of 8 DWOmion Energy Kewwe, Inc CalcistoAveluson

'rde Latent Debris Determination Catculaticn C11928 Revision 0 Afttacment 2 AREA DETERMINATIONS I isgerI DkmensnskmAms Romefee F~rnnn .U15Z2- -8A85901148 XK-106-27 IRadiusto Insi4-7 W1 635.5834 XK-106-27 Polar Crane Rails -sdeu" xS' (2sides) x1-2 h23.7222 XK-106-27[pof1 '1 204.7438 .XK-100-1 Uin ulkon00ness: 15V added for aides and 075' added for top___________ Steam Gewators3 +75' 11'+ 1.5' 1.5148249 IXK-100-1 WeigfD 37' TV 4D-7.3/4"r+1.5' 141eat--1,590.1013 IXK-100-1 15I added for sides and 0.75V added for too II L .... ..... .. .. .. .... L .. .... .5.. ... .... .I 4-o !.... ... .NO 100 I'D '4 I.Yu I O lm i 78.5-wo IXK-3110-22 I-I RCOP/Motors Pressurizer Rle Tard 365 & XK-310-19 ,-100-161 Figure 1: 613'W6 Elevation of Refueling Cavity Pool Page 8 of 8 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 3 Sample Type 1: Floors and Horizontal Structures tUL 1.886 for 90% probability that the mean will be less than x + t*s/(n/2) with 3 samples Assumes Normal Distribution Sample # Mass Area Mass/Area 12 0.7 33 0.02121212 13 0.15 56 0.00267857 4 1.8 9.625 0.18701299 Sample Mean (x) =Sample Std Dev (s) =90% Confidence Limit Mean (iL) =0.070 0.101 0.181 g/fi 2 g~ft 2 g/ft 2 Eq. 4-1 Eq. 4-2 Eq. 4-3 Page 1 of 6 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Sample Tvpe 2: Containment Liner Calculation C11928 Revision 0 Attachment 3 tUL 3.078 for 90% probability that the mean will be less than x + t*s/(n" 2) with 2 samples Assumes Normal Distribution Estimate with 2 Samples Sample # Mass Area Mass/Area (g) (ft 2) I (g/ft 2)7 0.1 51.8 0.0019305 9 0.3 72 0.00416667 Sample Mean (x) =Sample Std Dev (s) =90% Confidence Limit Mean (LUk) =0.003 gift 2 0.002 g/ft 2 0.006 g/ft 2 Eq. 4-1 Eq. 4-2 Eq. 4-3 tUL -=1.886 for 90% probability that the mean will be less than x + t*s/(n 1 2) with 3 samples Assumes Normal Distribution Estimate with 3 Samples Sample # Mass Area Mass/Area (_______ (g/ft 2)5 0 22.4 0 7 0.1 51.8 0.0019305 9 0.3 72 0.00416667 Sample Mean (x)Sample Std Dev (s) =90% Confidence Limit Mean (PO) =0.002 0.002 0.004 g/ft 2 gift 2 g/ft 2 Eq. 4-1 Eq. 4-2 Eq. 4-3 Page 2 of 6 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 3 Sample Type 3: Walls, Vertical EquiDment Surfaces, Other tUL=3.078 for 90% probability that the mean will be less than x + t*s/(nlf2) with 3 samples Assumes Normal Distribution F Sample #10 15 Mass (9)0.5 2.0 Area 34.9 45.0 Mass/Area (g/ft 2 0.01432665

0.0 4444444

Sample Mean (x) =Sample Std Dev (s) =90% Confidence Limit Mean (gut) =0.029 g/ft 2 0.021 g/ft 2 0.076 g/ft 2 Eq. 4-1 Eq. 4-2 Eq. 4-3 Page 3 of 6 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 3 Sample Type 4: Ventilation/ductwork, Cable Trays Sample #Mass (g)Area (ft 2)Mass/Area (g/ft 2)I 1 0.1 36.0 0.00277778 14 0.4 7.6 0.05263158 Vertical Horizontal Since only one sample was obtained for the vertical and horizontal ductwork, a 10% margin will be added to the loading for conservatism. As more samples are taken during future walkdowns, the debris loading will be obtained by using the t-distribution 90% confidence level.Vertical Loading with 10% Margin:.003 gift 2 Horizontal Loading with 10% Margin: .058 g/ft 2 Page 4 of 6 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 3 Sample Type 5: Horizontal Equipment Surfaces tUL=3.078 for 90% probability that the mean will be less than x + t*s/(nh1 2) with 3 samples Assumes Normal Distribution Sample # Mass Area Mass/Area (g) (f2) (g/ft)6 0.3 3.4 0.08823529 8 0.8 10 0.080 Sample Mean (x) =Sample Std Dev (s) =90% Confidence Limit Mean (PUL)0.084 g/ft 2 0.006 g/ft 2 0.097 g/ft 2 Eq. 4-1 Eq. 4-2 Eq. 4-3 Page 5, of 6 Dominion Energy Kewaunee, Inc.Calculation/Evaluation Title: Latent Debris Determination Calculation C11928 Revision 0 Attachment 3 Equation Sheet for Sample Type 1: Floors and Horizontal Structures tUL=1.886. for 90% probability that the mean will be less than x + t*s/(nl/2) with 3 samples Assumes Normal Distribution Sample Mean (x) =Sample Std Dev (s) ==AVERAGE(E7:E9) =SQRT(1/(COUNT(E7:E9)- 1)*(SUM(E7^2,E8^2,E9^2)-(SUM(E7:E9)^2/COUNT(E7:E 9))))g/ft 2 g/ft 2 g/ft 2 Eq. 4-1 Eq. 4-2 Eq. 4-3 90% Confidence =Ell+$C$2*E12/(SQRT(COU Limit Mean (jiuL) = NT(E7:E9))) Page 6 of 6 50.59 APPLICABILITY REVIEW (Is the activity excluded from 50.59 review?)1. Document/Activity number: Calculation C 11928, Rev. 0 2. Brief description of proposed activity (what is being changed and why): This calculation determines the total latent debris in Containmentbased on sample measurments and Containment surface areas Does the proposed activity involve or change any of the following documents or processes? Check YES or NO for EACH applicability review item.Explain in comments if necessary. [Ref. USA 50.59 Resource Manual]NOTE: If you are unsure ifa document or process may be affected, contact the process owner.Yes No Document or Applicable" Process Regulation ContacttActlon a 5 0 Technical Specifications or Operating License IOCFR50.92 Process change per LI-AA-101. Contact Licensing. Identify NRC letter in comments below. Process b l 0 Activity/change previously approved by NRC in IOCFR50.90 change.license amendment or N RC SER Contact Licensing for assistance. Activity/change covered by an existing approved IOCFR50 Appendix B Identify screening or evaluation in comments below.c I 0 10CFR50.59 review, screening, or evaluation. Process change.d 0 0 Dominion Quality Assurance Program Description lOFR50.54(a) Contact QA.___ (DOM-QA-I) Refer to NO-AA- 101.Contact EP.e ] 0 Emergency Plan 10CFR50.54(q) Refer to FP-R-EP-02. f ] 0 Security Plan 10CFR50.54(p) Contact Security.Refer to FP-S-SPE-01. g 11 [] 1ST Plan I0CFR50.55a(f) Contact IST process owner.Refer to ER-AA-IST-10. h 0 ID ISI Plan I0CFR50.55a(g) Contact ISI process owner..Refer to_ _ _ ER-AA-NDE-122, NAD-01.05, and NAD-05.1 I.i] 0 ECCS Acceptance Criteria IOCFR50.46 Contact Licensing. USAR or any document incorporated by reference-Process USAR change per NEP-05.02. j El [] Check YES only if change is editorial (see IOCFR50.71 Contac USAR cess oer foPasitac. Attachment A). Contact USAR process owner for assistance. Commitment -Commitment changes associated Contact Licensing. k with a response to Generic Letters and Bulletins, or IOCFR50 Appendix B Referct Licensin1. if described in the USAR require a pre-screening. RefertoL_-AA-__lO. Maintenance activity or new/revised maintenance Evaluate under Maintenance Rule.I [] procedure -Check YES only if clearly maintenance IOCFR50.65 Refer to ER-AA-MRL-10, ER-AA-MRL-100, and and equipment will be restored to its as-designed NAD-08.21. condition within 90 days (see Attachment C).New/revised administrative or managerial directive/procedure (e.g., NAD, GNP, Fleet m Procedure) or a change to any procedure or other 10CFR50 Appendix B Process procedureldocument revision.controlled document (e.g., plant drawing) which is clearly editorial/administrative. See Attachments A and B.n 0 Fire Plan IOCFR5.48 Fire Protection Program Document Change Control, GNP-05.30.0O. o 0] 0 Independent Spent Fuel Storage Installation (ISFSI) IOCFR72.48 Implement DNAP-3004, starting with Applicability.

4. Conclu Li sion. Check one of the following:

All documents/processes listed above are checked NO. IOCFR50.59 applies to the proposed activity. A 50.59 pre-screening shall be performed. One or more of the documents/processes listed above are checked YES, AND controls all aspects of the proposed activity. IOCFR50.59 does NOT apply. Process the change under the applicable program/process/procedure. One or more of the documents/processes listed above are checked YES, however, some portion of the proposed activity is not controlled by any of the above processes. IOCFR50.59 applies to that portion. A 50.59 pre-screening shall be performed. LII 5. Comments: None 6. Print name tollowed by signature. Attach completed form to document/activity/change package.Prepared by: Lana Rabas / ,Y --R -4_, .(print/sign) Date:J a b Date: Reviewed by: Lori Christensen (print/sign) Form GNP-04.04.01-1 Rev. 12 Date: APR 08 2008 INFORMATION USE Page 15 of 16 50.59 PRE-SCREENING (Is a 50.59 screening required?)

1. Document/Activity number: Calculation C! 1928, Rev. 0 2. Brief description of proposed activity (what is being changed and why): This calculation determines the total latent debris in Containment based on sample measurements and Containment surface areas.3. Does the proposed activity involve or change any of the following documents or processes?

Explain in' Comments if necessary. Check YES or NO for EACH pre-screening item. [Ref. USA 50.59 Resource Manual]NOTE: If you are unsure if a document or process may be affected, contact the process owner.NOTE: An asterisk (*) indicates that the document is incorporated by reference in the USAR or is implicitly considered part of the USAR.NOTE; Check NO if activity/change is considered editorial, administrative, or maintenance as defined in Attachments A, B, and C. Explain in Comments if necessary. Yes V NoV Document/Process Directive/ Procedure.a [] Updated Safety Analysis Report (USAR) NEP-05.02 b EJ

• Technical Specifications Bases or Technical Requirements Manual (TRM) LI-AA-IOI0 LI-AA-101-1001 c
• Commitments made in response to NRC Generic Letters and Bulletins, and those described in the USAR LI-AA- 110 d E] [
• Environmental Qualification (EQ) Plan NAD-01.08 e [] Z
• Regulatory Guide 1.97 (RG 1.97) Accident Monitoring Instrumentation Plan NAD-05.22 f E] N
• Fire Plan NAD-01.02 g
• Appendix R Design Description NAD-0 1.02 h [] [
• Fire Protection Program Analysis (FPPA) NAD-01.02 i EJ
• Offsite Dose Calculation Manual (ODCM) NAD-05.13 j
• Radiological Environmental Monitoring Manual (REMM) NAD-05.13 k [] [
• Station Blackout Design Description I [] 0
• Control Room Habitability Study Plant Drawing Changes/Discrepancies-Check YES only if: I) the change adds information to, deletes information m I from, or alters the configuration of a drawing that is incorporated in the USAR, or 2) configures an SSC NAD-05.01 differently than described or credited in USAR text.Calculations/Evaluations/Analyses/Computer Software -Check YES only if: I) It affects a method of evaluation described in the USAR, or 2) It independently (i.e., not part of a modification) affects the licensing or design basis. _ aons o [] N Permanent Plant Physical Changes -All require a screening.

NAD-04.03 Temporary Plant Physical Changes (TCRs) -Check No only if installed for maintenance AND in effect for less NADO4.03 p El ff than 90 days at power conditions. q QA Typing Determinations -Check YES only if reduction in classification, or affects design function as described NAD-01.01 q [] [] in USAR.r [ 0 Setpoint or Acceptance Criteria -Check YES only if change affects plant monitoring, performance, or operation. Various Plant Procedures/Revisions -Check YES only if the change directly or indirectly involves operating,,controlling NAD-03.01 s I or configuring an SSC differently than described or credited in USAR.t [] 0 Engineering Specifications -Check YES only ifa design function or design requirement may be affected. NAD-05.03 u ii 0D Operations Night Orders or Operator Work Arounds -Check YES only if SSCs are operated or configured GNP-03.30.01 differently than described in USAR.NAD-08.14, Temporary plant alterations (e.g., jumpers, scaffolding, shielding, barriers) -Check YES only if installed (or in GMP-127, v [] effect) for maintenance for longer than 90 days at power conditions. GNP-01.23.04, FPP-08-09 w E] I0 Temporary plant alterations -Check YES only if not associated with maintenance. Corrective/Compensatory Actions -Check YES only if degraded/non-conforming plant condition accepted "as-is" OP-AA-102 x ] ]or compensatoryý action taken.4 Conclusion. Check one of the following: All of the documents or processes listed above are checked NO. A 50.59 screening is NOT required. Process change in accordance with the applicable program/process/procedure. [] One or more of the documents or processes listed above are checked YES. A 50.59 screening shall be performed. 5 Comments: Item n: This calculation does not affect a method of evaluation. It does not independently affects the licensing or design basis as the latent quantity remain below the analyzed quantity.6 Print name followed by signature. Either the preparer or reviewer shall be 50.59 screening qualified. Attach completed form to document/activity/change package. yb <-at: O, =Prepared by: Lana Rabas / -~"Date: JL .i)(ptint/sign) J A .~ k .Reviewed by: Lo~ri Christensen Date: 7/If7 7 C We I Pae 6of1 Form GNP-04.04.01-2 Rev. 12 Date: APR 08 2008 INFORMATION USE Page 16 of 16 Serial No. 10-025 Docket No. 50-305 ENCLOSURE C-2 (RAI 8),LATENT DEBRIS PROCEDURE CM-AA-CRS-101, REVISION 2 PROCEDURE ATTACHED Nuclear Fleet Dominion Technical Procedure Title: Latent Debris Collection and Sampling Procedure Procedure Number Revision Number Effective Date and CM-AA-CRS-101 2 Approvals On File Revision Summary Section 1.1 -Added "[CM 8.1.4]." Section 1.3 -Added "[CM 8.1.1] [CM 8.1.2] [CM 8.1.3] ([CM 8.1.5] KPS only)." Section 3.5" Added "Use the site's current latent debris evaluation or tracking document to determine the quantity and locations of samples to be collected (See Section 5.2)."" After "should be" replaced "identified" with "listed or documented."" After "walkdown" deleted "in order" and "assure a comprehensive collection population." Section 4.8 -Move first sentence to last sentence position.Section 5.3, last sentence -Changed "bag and cloth or filter" to "bags and cloths or filters." Section 5.4" (old)The sample area size should be an area between 1 ft 2 and 100 ft 2.Samples are required from each of the following surface types in the areas subject to containment spray or post-LOCA flooding.* Horizontal concrete surfaces" Vertical concrete surfaces" Containment steel liner" Equipment surfaces such as ductwork, piping, fan coils, valves, etc.SELECT the specific location for sample collection as previously determined during the walkdown plan and obtain sample. MEASURE the area from which the sample was taken and record the results on Attachment 1." (new)The sample area size should be selected to provide a representative quantity of debris on the surface type.MEASURE and DOCUMENT the sample dimensions of the surface area from which the sample will be taken and RECORD the results on Attachment 1.Functional Area Manager: Manager Nuclear Site Engineering Programs INFORMATION USE DOMINION CM-AA-CRS-101 REVISION 2 PAGE 2 OF 10 Revision Summary (continued) Sections 5.9 and 5.10 (old section) -Reversed order.Section 5.10 (renumbered 5.9) -Moved "Provide results to GSI-191 Site Owner" to Section 5.11 (new section).5.9 (renumbered 5.10)" After "zero" added "and not within the scale accuracy."" Changed "REPEAT Section 5.8" to "REPEAT Sections 5.3 through 5.9, as necessary." Section 5.12 (new section)" STORE the sample collection bags in a proper containment storage area, or as advised by Health Physics staff, until notified by Engineering that the samples may be discarded. Section 5.13 (new section)" WHEN notified by Engineering that samples may be discarded, THEN CONTACT Health Physics for disposal Guidance.Section 8.1.1 -Added "(See Section 1.3)." Section 8.1.2 -Added "(See Section 1.3)." Section 8.1.3 -Added "(See Section 1.3)." Section 8.1.4 -Added "(See Section 1.1)." Section 8.1.5 (new section) -Dominion Letter to NRC, Serial No. 05-212, Kewaunee Power Station, Millstone Power Station, Units 2 and 3, North Anna Power Station, Unit 1 and 2, Surry Power Station, Units 1 and 2, Response to Generic Letter 2004-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (See Section 1.3) 1 Section 8.3.12 (new section) -Dominion Letter to NRC, Serial No. 05-212, Kewaunee Power Station, Millstone Power Station, Units 2 and 3, North Anna Power Station, Unit 1 and 2, Surry Power Station, Units 1 and 2, Response to Generic Letter 2004-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Section 8.3.13 (new section) -Kewaunee COMTRACK 2005-167, NRC Commitment to Develop a Procedure to Routinely Sample Containment Latent Debris Attachment I -Reformatted table and added Sample Surface Type Code "OTH (Other)." Added form number.INFORMATION USE DOMINION CM-AA-CRS-101 REVISION 2 PAGE 3 OF 10 TABLE OF CONTENTS Section Page 1.0 PURPOSE ..................................................................................................................................... 4 2.0 SPECIAL TOO LS AND EQUIPM ENT ......................................................................................... 4 3.0 PREREQUISITES ............................................................................................................................ 4 4.0 PRECAUTIONS AND LIM ITATIONS ........................................... ................................................ 5 5.0 INSTRUCTIONS .............................................................................................................................. 5 6.0 ACCEPTANCE AND SIGN OFF ............................................. .................................................. 7 7.0 RECORDS ....................................................................................................................................... 7 8.0 ADM INISTRATIVE INFORMATIO N ........................................................................................... 7 8.1 Com m itm ents ........................................................................................................................ 7 8.2 Definitions ................................................................. .................................. 8 8.3 References ............................................................................................................................ 8 ATTACHMENTS 1 Latent Debris Walkdown Sample Record Sheet (Form No. 729451 (Jan 2010)) .................. 10 INFORMATION USE DOMINION CM-AA-CRS-101 REVISION 2 PAGE 4 OF 10 1.0 PURPOSE 1.1 This procedure outlines the-guidelines and methods for the collection and sampling evaluation of latent debris (particulate and fibrous debris, i.e., dust, dirt, lint, fibers, shavings, etc.) in containment. [CM 8.1.4]1.2 This procedure outlines the walkdown activities for collection of debris samples, required equipment, collection methods, and proposed locations. 1.3 This procedure is used to gather latent debris samples to determine if the current quantity of latent debris in containment (debris inventory) remains bounding by the debris assumption for design basis for the Emergency Core Cooling Sump (ECCS)Recirculation Strainer. [CM 8.1.1] [CM 8.1.2] [CM 8.1.3] ([CM 8.1.5] KPS only)2.0 SPECIAL TOOLS AND EQUIPMENT 2.1 Instruments and equipment for latent debris walkdown collection and sampling activities may include, but are not limited to: " Personnel Protective Equipment (to be determined by the governing Radiation Work Permit (RWP) and Site Safety Manual" Masslin cloth (at least 50 approx. 24" x 24")* HEPA vacuum cleaner designated for ise in Radiologically Controlled Area (RCA)with removable filter element" Calibrated scale with an accuracy of at least 0.1 gram" Plastic ziplock bags (at least 50), bags sized to contain one Masslin cloth or HEPA vacuum cleaner filter element" Approved ink type markers" Location maps" Labels (at least 50) minimum size 1" x 3"* Narrow brush with long bristles and long handle* Portable illumination, i.e., flashlight -Tape measure 3.0 PREREQUISITES

3.1 Walkdown

personnel shall be aware of the potential for inaccuracies involving the initial and post collection weights of specimen containersland specimen samples taken for debris determination inventory. This discrepancy has been described in Sargent & Lundy Performance Improvement Process (PIP) 2005-0278 (Reference 8.3.6).3.2 Walkdown personnel should be familiar with the walkdown plan by the GSI-1 91 Site Owner, and knowledgeable on use of the equipment used for sampling.INFORMATION USE DOMINION CM-AA-CRS-101 REVISION 2 PAGE 5 OF 10 3.3 Health Physics (HP) shall be notified prior to performing the walkdown inside containment, as well as requisite HP briefing.3.4 The sampling frequency shall be every fifth refueling outage after completion of the sump modification, if containment wash downs are performed during each refueling outage. The sampling frequency shall be every other outage after completion of the sump modification if containment wash downs are not performed. Sampling shall also be performed after any invasive or extended maintenance has occurred such as a steam generator replacement, or more frequently if determined by the GSI-191 Site Owner.3.5 Use the site's current latent debris evaluation or tracking document to determine the quantity and locations of samples to be collected (See Section 5.2). Sample area locations should be listed or documented on the respective site containment area maps prior to walkdown to identify areas for HP assessment, preparation of RWP requirements, and to maximize ALARA while collecting the samples in containment.

4.0 PRECAUTIONS

AND LIMITATIONS

4.1 Sampling

for latent debris collection shall commence near the end of the outage after bulk work in containment is completed.

4.2 Perform

walkdown, and latent debris collection in a safe manner practicing ALARA.4.3 Prior to starting work in a Radiation Area, have HP survey the work area. Ensure the proper RWP has been issued.4.4 Ensure components and structures will not be damaged (gouged, dented, deformed)or operationally altered while gaining access or while obtaining debris samples.4.5 Steps may be performed concurrently or in any sequence consistent with good engineering and construction practices.

4.6 During

collection of sample, minimize to greatest extent possible, the creation of fugitive airborne dust and dirt. Give special attention to assure the items within the vicinity of the sample collection, are covered and protected as required.4.7 Provide adequate supplemental lighting as necessary to perform sample collection activities. 4.8 If samples are collected from cable trays, energized equipment, electrical cabinets, and equipment with moving parts, ensure equipment is placed in a safe condition prior to obtaining sample. Personnel collecting samples on all energized equipment shall be qualified and have completed the necessary site electrical training.4.9 Remove all collected samples from the RCA, in accordance with HP directives. If contaminated after evaluation, then dispose of in accordance with HP procedures as Radwaste.Site 5.0 INSTRUCTIONS Engineering or Designee 5.1 Walkdowns may require climbing ladders or scaffold access. ADHERE to site procedures governing the use of these items for access and approval from HP.INFORMATION USE DOMINION CM-AA-CRS-101 REVISION 2 PAGE 6 OF 10 5.2 REFER to the site specific design basis calculation for guidance on general area locations, number of samples, and sampling methodology. In general, sample locations should include floors, containment liner, horizontal, and vertical ventilation duct, walls, horizontal and vertical equipment, horizontal, and vertical piping, and miscellaneous items such as structural steel, junction boxes, and monitoring devices.The specific number and location of sample locations should approximately correspond to the original site specific sampling locations performed for the original walkdown where samples were obtained that established the original latent debris design input. As a minimum, there should be at least three samples from each distinctive surface type.5.3 PLACE Masslin cloth or HEPA vacuum filter element inside the respective plastic collection bag. The collection bag should have an identification label with a unique identifying number correlating to all pre-determined locations in containment where samples are desired. PRE-WEIGH the sample bags and cloths or filters element and RECORD on Attachment 1.5.4 The sample area size should be selected to provide a representative quantity of debris on the surface type.MEASURE and DOCUMENT the sample dimensions of the surface area from which the sample will be taken and RECORD the results on Attachment 1.5.5 WIPE with the Masslin cloth or vacuum the selected area collecting as much of the debris as possible and deposit debris and cloth or vacuum filter element in the collection bag.5.6 The actual sample area locations may be changed during the walkdown if the original location can not be accessed, or due to HP discretion based on ALARA considerations, or interference with other on-going outage activities. Clearly identify location on Attachment

1. Consider supplementing sample location information using marked up area maps.5.7 For cylindrical horizontal sections (pipe, equipment, etc.) WIPE only the top portion of the surface. On the Latent Debris Walkdown Sample Record Sheet'(Attachment 1), RECORD the length and the outside diameter of the section.5.8 WEIGH each -sample on a calibrated scale and record on Attachment 1.NOTE: For samples measured at zero to less than 0.1 gram, round up to 0.1 gram.5.9 TABULATE the results.5.10 IF the weight of the post walkdown sample is questionable (i.e., less than zero and not within the scale accuracy, Reference 8.3.6), THEN INVESTIGATE the discrepancy and obtain another sample from a similar surface at comparable plant location.

REPEAT Sections 5.3 through 5.9, as necessary. 5.11 PROVIDE results to the GSI-191 Site Owner.INFORMATION USE DOMINION CM-AA-CRS-101 REVISION 2 PAGE 7 OF 10 5.12 STORE the sample collection bags in a proper containment storage area, or as advised by Health Physics staff, until notified by Engineering that the samples may be discarded. 5.13 WHEN notified by Engineering that samples may be discarded, THEN CONTACT Health Physics for disposal Guidance.6.0 ACCEPTANCE AND SIGN OFF 6.1 Verify that all work areas are cleaned and all collection bags and Masslin cloths brought in containment are accounted for and removed from containment. Site Engineering or Designee 6.2 Complete the required work entries on the Work Order package.NOTE: Formally document results (e.g., Technical Report, Engineering Transmittal, etc.).GSI-191 Site Owner Site Engineering or Designee 6.3 Compare tabulated results against data in the design basis. For non-acceptable results, initiate CR for follow-up evaluation and to clean containment, if necessary.

6.4 Confirm

that a repetitive work order/activity exists to evaluate the need for a sampling activity for the next refueling outage to meet the frequency requirements of Section 3.4.7.0 RECORDS Complete all documentation and related documents completed as a result of performance or implementation of.this procedure and submit to Records Management in accordance with site procedures.

8.0 ADMINISTRATIVE

INFORMATION

8.1 Commitments

8.1.1 Dominion

Letter to NRC, Serial No. 08-0017, Kewaunee Power Station NRC Generic Letter 2004-02, Supplemental Response Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (See Section 1.3)8.1.2 Dominion Letter to NRC, Serial No. 07-0797, Millstone Power Station Units 2 and 3 Supplemental Information of Corrective Actions in Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer Water Reactors (See Section 1.3)8.1.3 Dominion Letter to NRC, Serial No. 08-0019, North Anna Power Station Units 1 and 2 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer-Water Reactors (Implied reference in NRC GL 2004-02, Plant Audit of North Anna Power Station ADAMS ML072740400) (See Section 1.3)I INFORMATION USE DOMINION( CM-AA-CRS-101 REVISION 2 PAGE 8 OF 10 8.1.4 Dominion Letter to NRC, Serial No. 08-0018, Surry Power Station Units 1 and 2 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (See Section 1.1)8.1.5 Dominion Letter to NRC, Serial No. 05-212, Kewaunee Power Station, Millstone Power Station, Units 2 and 3, North Anna Power Station, Unit 1 and 2, Surry Power Station, Units 1 and 2, Response to Generic Letter 2004-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (See Section 1.3)8.2 Definitions

8.2.1 Latent

Debris Unintended dirt, or combination of particulate and fibrous matter such as dust, dirt, lint, shavings, grit, sand, paint chips, fibers, pieces of paper (shredded or intact), plastic, tape, or adhesive labels, fines or shards of thermal insulation, fireproof barrier or other materials that are already present in the containment prior to a postulated break in a high-energy line inside containment. Potential origins for this material include activities performed during outages and foreign particulates brought into containment during outages.8.3 References 8.3.1 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors 8.3.2 NEI 04-07, Pressurized Water Reactor Sump Performance Evaluation Methodology, Revision 0, including NRC Safety Evaluation dated 2004 8.3.3 NEI 02-01, Condition Assessment Guidelines: Debris Sources Inside PWR Containment

8.3.4 Dominion

Topical Report DOM-QA-1, Nuclear Facility Quality Assurance Program Description

8.3.5 American

Society of Mechanical Engineers, ASME NQA-1-1994, Quality Assurance Requirements for Nuclear Facility Application

8.3.6 Sargent

& Lundy Performance Improvement Process (PIP) 2005-0278, Latent Debris and Label Walkdown Deficiencies

8.3.7 Dominion

Letter to NRC, Serial No. 08-0017, Kewaunee Power Station NRC Generic Letter 2004-02, Supplemental Response Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors INFORMATION USE DOMINION CM-AA-CRS-101 REVISION 2 PAGE 9 OF 10 8.3.8 Dominion Letter to NRC, Serial No. 07-0797, Millstone Power Station Units 2 and 3 Supplemental Information of Corrective Actions in Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer Water Reactors 8.3.9 Dominion Letter to NRC, Serial No. 08-0019, North Anna Power Station Units 1 and 2 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer-Water Reactors 8.3.10 Dominion Letter to NRC, Serial No. 08-0018, Surry Power Station Units 1 and 2 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors 8.3.11 NRC Generic Letter 2004-02, Plant Audit of North Anna Power Station (ADAMS ML072740400) 8.3.12 Dominion Letter to NRC, Serial No. 05-212, Kewaunee Power Station, Millstone Power Station, Units 2 and 3, North Anna Power Station, Unit I and 2, Surry Power Station, Units I and 2, Response to Generic Letter 2004-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors 8.3.13 Kewaunee COMTRACK 2005-167, NRC Commitment to Develop a Procedure to Routinely Sample Containment Latent Debris INFORMATION USE 0 E Dominion Latent Debris Walkdown Sample Record Sheet C -A-R 10 ATAHMN 1 Page 1*f A. B. C. D. E. F. G. H. 1.Sample No. Surface Surface Location Surface Type Surface Area Initial Sample Post-Walkdown Debris Weight Debris Loading Type/Description (elevation, Code (ft2) Bag Weight Sample Bag (grams) G -F (g/ft2) H/E and Size (ft xft) quadrant, other) (grams) Weight (grams)Sample Surface Type Code: HCT- Horizontal Cable Tray Station: I] KPS E] MPS [] NAPS E] SPS VCT -Vertical Cable Tray HE -Horizontal Equipment HD -Horizontal Duct VD- Vertical Duct Unit: Li1 L12 L13 OTH -Other Prepared by (print/sign): Date: 0>CD 0 cn Form No. 729451 (Jan 2010) Serial No. 10-025 Docket No. 50-305 ENCLOSURE D (RAI 9) DEBRIS INTERCEPTORS INSTALLED IN THE PLANT DEBRIS INTERCEPTOR Page 1 of 2 Serial No. 10-025 Docket No. 50-305 ENCLOSURE D (RAI 9) DEBRIS INTERCEPTORS INSTALLED IN THE PLANT Page 2 of 2 Serial No. 10-025 Docket No. 50-305 ENCLOSURE E-1 (RAI 13/15/16) ARL PRESENTATION FROM 9/15/09 TELECONFERENCE WITH NRC ARL PRESENTATION DATED SEPTEMBER 15, 2009 Kewaunee Power Station__ ..NRC Agenda Setting Meeting 9/15/2009 Yl ALDE USovn flo prbems sic 1 RAI E9j: Concentrated sources of drainage No concentrated spray and drainage sources are located in the immediate vicinity of the strainer The closest source is modeled in the transport calculation and the flume wall calculation The influence of the source can be seen in the calculated approach velocity profile* The drainage source influence was represented in the large flume test W ted Average and Average Approach Velocities 0080 0040 0,020 0000 0 S 10 is1 30 35 El 3a-e: CFD modeling of containment flow* Simulations were conducted using Fluent and followed the standard calculation methodology" The standard k-s model was used for turbulence calculations ° Debris transport calculations were conservatively performed at the water level for the start of recirculation High transport fractions were obtained for most zones up to a tumbling velocity of 0.2 ft/sec -...., V El 3a-e: CFD modeling of containment flow* Detailed accounting was performed to model spray and break flow drainage into the recirculation pool" Concentrated sources of falling water were treated ideally converting all water potential energy into kinetic energy" The debris interceptor curb was modeled with few simplifying assumptions

• No assumptions with regard to debris interceptor debris loading were necessary" No credit was taken for lift-over-curb transport limitations over the debris interceptor curb ALDE El 5: Turbulence in containment and flume / test configuration
• Flume configuration based on long-term recirculation conditions-Achieved 14 minutes after recirculation start* Water level in containment for analysis and test maintained at 40.5"-40.5" is water level for the start of recirculation

-Actual water depth is more than 2 ft higher for long-term recirculation" Velocity and turbulence levels in vicinity of strainer are low" Containment structure divides break flow into three sources distributing break flow momentum 2000-013* ~ 1000-03 6850.-03 I 70.Cl600l 6000-03 100.-Cl7.50103 140-017.000-03 130-01 6500 1.200-01 0s3 109.01 5.500-03 10.01 5,004-03 9006-0 4506-03 6000-0 4000-03 7000-02 350o-03 5 00.-02 2560 1 00 006M D-03 2.000-02 s.0 10.02O- 5006-04 0000.00000o..00 Long-term recirculation velocity magnitude (if's) Lonq-term recirculation TKE (ft 2 1S 2)ALDEN El 5: Turbulence in containment and flume / test configuration" Debris interceptor, despite its low height blocks most break flow from reaching strainer W* Flume Reynolds numbers are in the turbulent range* Flume effective turbulence is on par with that calculated in containment Turbulence levels calculated in containment correspond to a maximum of 0.02 ft/sec RM 0.0015 w S0.001 0.0005 Distance from Velocity Flume Width Hydraulic Radius screen (ft) (ft/sec) (in) (ft) Reynolds #1 0.10 10.4 0.39 6704 2 0.10 9.9 0.37 6045 3 0.10 11.3 0.41 6644 6 0.08 14.3 0.51 6435 10 0.09 11.7 0.42 6617 21 0.12 8.9 0.33 6821 25 0.13 8.5 0.32 6852 30 0.13 8.4 0.32 6861 10 15 20 25 30 35 Distance Back From Strainer (ft)ALDE El 6: Pool fill transport & distance traveled by debris* Preferential pool fill transport is limited except during sump C fill-up Sump C fill-up preferentially causes debris to move away from strainer bank No credit for this transport is taken in the analysis* The average distance traveled by debris is greater than 30' when considering calculated zone exit flow splits

• TempMat calculated transport fraction was increased by 20% of debris generated for conservatism in determining test quantity* Transport testing at Alden showed 3x -4x approach velocity profile only yielded partial transport of TempMat smalls.ALDEN Solvina flovv probý(ýrns sit-ice 1894 Serial No. 10-025 Docket No. 50-305 ENCLOSURE E-2 (RAI 13/15/16)

ARL PRESENTATION FROM 11/10/09 TELECONFERENCE WITH NRC ARL PRESENTATION DATED NOVEMBER 10, 2009 Kewaunee Power Station NRC Follow-Up Meeting 11/10/2009 0& §~y6~ "'~///~4~¶/ALDE Sovn flo prblm s inc 1894 Kewaunee Containment

• Sump area is covered and does not receive spill flow* Break flow does not directly impact Zone 1 dmBreak flow separates into three parts w Break flow sources: Two ledges & one hatch* 22% of flow is through hatch'A ALDEN E15: Velocity & Turbulence
• Test velocity based on long-term recirculation conditions

-Conditions after RWST injection has ceased-Water level is assumed to remain at that for start of recirculation

• True water level is 70% higher I 5.000-01 4.75e-01 4.50e-01 4.250-01 4.00".01 3.75e-01 3.500-01 3.250-01 3.000-01 2.75"-01 2.500-01 2.250-01 2.00e-01 1.75e-01 1.500-01 1.259-01 1.00e-01 7.500-02 5.000-02 2.500-02 0.00+O(I 1 .000-02 9.50e-03 9.000-03 8.50e-03 8.000-03 7.500-03 7.000-03 6.500-03 6.009M0 5.50~0M 5.00e-03 4.500-03 4.00e-03 3.509-03 3.009-03 2.500-03 2.008-03 1.500-03 1 .00e-03 5.009-04 0.00e+00 Velocity magnitude (ft/s)ALDE EIS: Velocity & Turbulence" Area immediately around strainers is very calm" Dominant strainer approaches are slow: ~'0.12 ft/s" Break flow does not aggressively leave Zone 1 w..- 22%Dominant exit paths of Zone 1 away from strainer bank of break flow 6% of break flow Sapproaches strainers through opening ALDEN Zone I Flow Pattern* Break flow from hatch streams along floor* Debris interceptor curb turns flow vertically upward I* Flow pattern sets up lar I I M400.0 6.00-01=.OO.4 7 50.01 2.0041 1.00"-01 210.-02 0 00.41 e toroidial "roller" Toroidial flow Dattern I 5.00.-01 4.75o.-l 4.50.-Cl 4_25".-1 4.00.-01 3.75.-Cl 3.50e-01 3.25.-01 3.00.-01 2.75e-01 2.50.-0l 2.25.-"1 2.00.-Cl 1.75.-01 1.50.-01 1.25.-Cl 1.00.-Cl 7.50*-02 5.00*-02 2.100-02 a. e400&

Zone 1 Flow Pattern" Net flow through from Zone 1 to strainer bank is low" Significant areas of reverse flow in center of opening I 1.20e-01 1.05"01 9.009-02 7.50e-02 6.006-02 4 508-02 3 .009-02 1 .50e-02 0 .00.400-1.500-02-3,008-02-4.506-02-6.00e-02 4M90-02-9.00-02-1.05e-0l-1.2D0 01-1.350-01-150e-01 Thru-flow velocity (Positive is to strainer bank)ALDEN Solving floýv problerns since 1894 1 ____j EI1: Turbulence comparison" Flume Reynolds numbers are in the turbulent range* Flume effective turbulence is on par with that calculated in containment" Turbulence levels calculated in containment correspond to a maximum of 0.02 ft/sec RMS 0.002S ii IC S Distance from Velocity Flume Width Hydraulic Radius screen (ft) (ft/sec) (in) (ft) Reynolds #1 0.10 10.4 0.39 6704 2 0.10 9.9 0.37 6045 3 0.10 11.3 0.41 6644 6 0.08 14.3 0.51 6435 10 0.09 11.7 0.42 6617 21 0.12 8.9 0.33 6821 25 0.13 8.5 0.32 6852 30 0.13 8.4 0.32 6861 0 5 10 15 20 25 30 35 Distance Back From Strainer (ft)ALDEN Sol,,ýing flow problenis since 1894 E16: Debris Addition Distance* Pool fill transport: -Transport is out of Zone 1 into Zones 2,4 and 6 predominantly -15% inactive sump hold-up not credited* Mostly suspended debris-Preferential transport to Zone 6" Zone 6 contains > 60% of volume" Not credited in pool fill analysis Sump C opening ALDE Sovig '1_).% pobes sne19 ED._:, Debris. A-dion.- Dis ncer Debris Transport is based on peak transport conditions 0-Near end of RWST injection-only short-term at recirculation start Large fraction of debris transports: -More than 75% for vtumble = 0.06 ft/s-More than 66% for Vtumble = 0.12 ft/s* Performed analysis determining a measure of distance traveled by debris* Look at flow balance by zone first (Th-~ 0 (Lf@ K;Y&__~~U 4I ALDE-Slvn flo prblm s inc 189 E16: Debris Addition Distance U Ui 2292 83%-2482-1713 4039 3438 54%46%-46~A3DE A16 Debrisn Distance Complex containment flow pattern 0 NO net flow from Zone 1 to strainer train* Zone 1 & Zone 6 have two exits:-Divide Zone 1 into areas according to flow fraction* Nearly 50/50 split-Divide Zone 6 into areas according to flow fraction* Very little flow approaches strainer train from left from Zone 6 (ALDE Sovn flo prblm since 1894 E16: Debri's Distance e Example distance calculation for 0.06 ft/s proj. surface-Logical division of Zone 6-Simple segments from centroid to calculate distance-ZONE63 ZONE DISTANCE (ft)Zil 41.14 Z13 39.43 Z2 39.56 Z3 24.18 Z4 30.74 ZS 6.10 Z61 61.73 Z63 88.06 ZONE61 ZONE1 ZONE4 ZONE13 ZONE5 KEWAUNEE CONTAINMENT VELOCITY = 0.06 FT/S ZONE3 0 10'30'ALDE E1,6V Debris Distance Apply to all initial tumbling velocity surfaces 0 Weight the distance from each zone by local debris:-Allows distance to properly represent initial debris distribution

• Calculation results: , For 100% transportable debris: 51 ft-For transport velocity 0.06 ft/s: 50 ft-For transport velocity 0.25 ft/s: 45 ft Minimum debris distance (for v = 0.66 ft/s): 38 ft* Adding debris at "29ft from the strainer is conservative K K 2 \ / \/,~ 5/C, ALDE Sovn flo prblm since 1894 Serial No. 10-025 Docket No. 50-305 ENCLOSURE E-3 (RAI 14) CONTAINMENT DRAINAGE~SOUTH STAIRWELL PRESSURIZER VAULT INORTH STAIRWELLI Page 1 of 3 Serial No. 10-025 Docket No. 50-305 ENCLOSURE E-3 (RAI 14) CONTAINMENT DRAINAGE Containment floor plan -one elevation above the basement (sump) level. Worst case postulated RCS break locations (RCS Loops) are within the concrete vaults (compartments) shown on previous page. Smaller breaks outside the compartments do not generate large quantities of debris that could block the unobstructed south stairwell at this elevation, or the north or south stairwells at the upper containment elevations.

Page 2 of 3 Serial No. 10-025 Docket No. 50-305 ENCLOSURE E-3 (RAI 14) CONTAINMENT DRAINAGE-Steam Generator[Pressurizer >7] Reactor Coolant Pump 4;j LII.t A'~V~t1 ILL-I ft.L -IF jI~'FQ,", L t 1;Niny J~-t+ *CAW LUCI%.IX~rs~-1/2 4n--~ Vault Wall (typ.) b~4~s I-If][i=L-.4 ~ ~ -I P .l~U~9z-~---- 4 F-t. I! I* " dl___*1-I 4ý7L\--~Lt'-7-. _r-~~ Fie i, h ~ ~ ~unI- .P , " --Drainage Path out of /iliV a u V Containment Sump (basement elevation) a.Page 3 of 3 Serial No. 10-025 Docket No. 50-305 ENCLOSURE F-1 (RAI F.19.A) EXCERPT FROM CLEAN STRAINER HEAD LOSS CALCULATION 7.0 Calculation(s) In order to determine the Total Corrected Clean Strainer Head Loss two (2)distinct calculation methodologies are employed as described in section 5.0 Methodology. Each methodology is utilized to separately calculate the head loss for the strainer and for the pipe and fittings.7.1 Clean Strainer Head Loss As summarized in [Reference 9.3], PCI developed a head loss curve as a function of strainer exit velocity for the test strainer, PCI Prototype II. The subject curve supports the determination of strainer head loss for strainers of different diameter internal core tubes from the =prototype that was tested (NOTE: The subject head loss determination must be corrected for the Kewaunee strainer assemblies). PCI also considered a number of minor adjustments to address other physical differences between the Kewaunee strainer and the PCI Prototype II, such as the differences in strainer length between the Prototype II strainer and the Kewaunee strainer, and the specific penetration velocity through the Kewaunee strainer plates.7.2 Clean Strainer Test Data In order to calculate the Clean Strainer exit velocities, PCI utilized Equation I from [Reference 9.4]. The calculation is as follows.Equation I V = Qg I Aex [Reference 9.4]Where, Qtr = strainer water flow rate, gpm x 0.002228 to convert to ft 3/sec Aex = exit area, or cross section ,area of the inside of the strainer's core, ft 2 V. = Strainer Exit Velocity, ft/sec As discussed in [Reference 9.4], the equation for the strainer only (i.e., without any pipe and/or fitting losses) Clean Head Loss is given by Equation 2 below:.Equation 2 A + K, v V.. + K2 (V, 1 2! 2g) [Reference 9.4]Page 1 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE F-1 (RAI F.19.A) EXCERPT FROM CLEAN STRAINER HEAD LOSS CALCULATION Where, v = water's kinematic viscosity, ft/sec (a function of water temperature) g = gravitational constant, which is 32.2 ft / sec 2 A = a constant with a very small value of 0.002205 feet of water -0, as defined in [Reference 9.31, and can therefore be ignored.Ki =a coefficient multiplied by v to allow adjustment to the water temperature 1(2 = another coefficient that is multiplied times the dynamic head of the water at the strainers exit.In [Reference 9.3], it is also shown that these coefficients, K, and K2 have the following values (determined by a regression analysis of the test data): K = 1,024 and K2 = 0.8792 With the values of the coefficients determined and utilizing Equation 2, the Base Head Loss, HLem, was calculated for different water temperatures where the value of kinematic viscosity, v is selected based on the design basis water temperature. Kewaunee has specified that the water temperature for long term cooling following the initiation of a LOCA is 65°F [Reference 9.1]. Accordingly, the actual base Clean Strainer Head Loss can be computed using the value of Exit Velocity, V., for the particular water flow rate. Selecting a value of v. for the particular water temperature from [Reference 9.7], the Exit Velocity can be computed using Equation I and the values of specified water flow rate values, respectively, for the Kewaunee strainer. Each strainer's core tube has an 18.00 inch outside diameter and a 0.06 inch wall thickness [References 10.1 -10.7, inclusive). Therefore, the value of intemal cross sectional area of the core tube can be computed by Equations 3 and 4 as follows.Equation 3 AOX = IDex 2 1 4 where Dex = inner core tube diameter Equation 4 outer diameter -2 x core tube wall thickness= 17.88 inches Page 2 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE F-1 (RAI F.19.A) EXCERPT FROM CLEAN STRAINER HEAD LOSS CALCULATION Therefore, Aex = 1.744 ft 2 Using Equation I above, and the value for A.. computed above, we can then calculate the values for Exit Velocity, Vex, for the strainer assembly using the specified flow rate of 1920 gpm.Vex = Q& I A..= 1920 gpm x 0.00222 ft 3 / s gpm / 1.744 ft 2= 2.453 ft/s The resultant value for V 6 x was then utilized to calculate the Clean Strainer Head Loss from the previously discussed equations as follows, HvL- == K1 v Vex + K 2 (Vex2 1 2g)= (1024) (1.138 x 10-) (2.453) + (0.8792) (2.4532/ 64.4)= 0.02859 + 0.08215= 0.111 Table I provides a summary of the values obtained from the subject equations and the resultant Clean Strainer Head Loss for the strainer assembly.Page 3 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE F-1 (RAI F.19.A) EXCERPT FROM CLEAN STRAINER HEAD LOSS CALCULATION Table I -Summary of Calculated Strainer Only Clean Strainer Head Loss Parameter Value Reference Total Suction Flow, gpm 1.920 9.10 Water Temperature, OF 65 9.1 Water Kinematic Viscosity, ftelsec 1.138 x 10-5 9.7 Internal Corn Tube Outer Diameter, Inches 18.00 9.5 Internal Core Tube Thickness, Inches 0.06 9.5 Internal Core Tube Inner Diameter, inches 17-88 Equation 4 Internal Core Tube Cross-Sectional Area, ft 1.744 Equation 3 Design Strainer Exit Velocity, ftMsec 2.453 Equation I Calculated Uncorrected CSHL, feet of water 0.111 Equation 2 Page 4 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE F-2 (RAI F.19.A) EXCERPT FROM TOTAL HEAD LOSS CALCULATION

7.2 Strainer

Debris Laden Head Loss The Kewaunee Debris Laden Strainer Head Loss tests performed at ARL are summarized in Table 4.AREVA Tests Nos. 3 and 9 (Reference 9.5] are the Design Basis Test and the Supplemental Design Basis Test for Kewaunee, respectively. Both Kewaunee Design Basis tests are intended to show recirculation at 1,920 gpm with a water level above the top of the Kewaunee strainer.AREVA Test No. 9 Supplemental Design Basis Test was 'performed with an increased debris load to add debris inventory margin.Additional Information regarding both the Clean Head Loss and Debris Laden Head Loss testing that was performed at ARL is specifically discussed In detail In [Reference 9.5].Table 4- ARL Test Debris Laden Strainer Head Loss Test Strainer Debris Test Laden Head Temperature, Loss, ft of water OF Test No. 3 Design Basis Test 0.51036 105.8 Test No. 9 Supplemental Design 1.66970 116.1 Basis Test NOTE: Debris laden head losses were the measured head losses minus the ARL piping and the Kewaunee clean strainer head losses.PCI utilized the head losses associated with both Test 3 and Test 9 ARL test results, respectively in combination with the Kewaunee post-LOCA specified recirculation temperature (i.e.,65 OF) to determine the various Kewaunee Strainer Total Head Losses.7.2.1 Temperature Correction Strainer Debris Laden Head Loss The dynamic viscosity of the specific test water (i.e., 105.8 OF and 116.1 OF, respectively) and the post-LOCA temperature (i.e., 65 OF)is determined by linear interpolation utilizing dynamic viscosity values taken from [Reference 9.7]. Table 5 provides a summary Page 1 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE F-2 (RAI F.19.A) EXCERPT FROM TOTAL HEAD LOSS CALCULATION of the dynamic viscosity associated with the various test and post LOCA water temperatures that are utilized in this calculation. Table 5 -Water Dynamic Viscosity Test I Event Temperature, 'F Dynamic Viscosity, Ib,-sift Debris Testing 69 2.06462 x 10"'(Clean Strainer Head Loss Test)Debris Testing 105.8 1.33909 x I0"5 (Test 3 -Design Basis)Debris Testing 116.1 1.20832 x 10-5 (Test 9 -Supplemental Design Basis)End of Post-LOCA 65 2.18108 x 10"s Period (End of Post-LOCA Recirculation Period)The head loss for low velocity water in the laminar flow regiodn through a debris bed of fibers plus particulate is linearly dependent on the water's dynamic viscosity. The Kewaunee specified post-LOCA water temperature is specified in [Reference 9.1]. The debris head loss requires correction to this temperature to determine the head loss at the Kewaunee specified post-LOCA temperatures. See Section 7.2.2 for temperature correction methodology. The strainerdebris laden head loss for low velocity water flow through a debris bed of fibers plus particulate is linearly dependent on the water's dynamic viscosity [Reference 9.19].7.2.2 Post-LOCA Temperature Correction Strainer Debris Laden Head Loss A head loss correction utilizing Assumption 3.4, which is based on the standard debris head loss equation [Reference 9.111, can be used to calculate a temperature adjusted debris head loss, HLTA.The HLTA adjusted temperature can be calculated by taking a ratio of dynamic viscosity values at the two different temperatures being Page 2 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE F-2 (RAI F.19.A) EXCERPT FROM TOTAL HEAD LOSS CALCULATION considered (i.e., the test water temperature and the Kewaunee specific post-LOCA sump water temperature). HLTA = HLDL,C (IsT / P TT)Where HLDLC= corrected, Debris Loaded Head Loss, ft lPST = dynamic viscosity at the Kewaunee Design Basis specified temperature of 650 F pTT = dynamic viscosity at the various average test temperatures of 69 OF, 105.8 OF, and 116.1 OF HLTA = temperature adjusted debris head loss, ft Applying the HLTA equation to the ARL measured head loss with the three water viscosities (i.e., two (2) average test water temperatures and Kewaunee specified post-LOCA water temperature), the value of HLTA is calculated by the above equation. The HLTA is added to the clean strainer head loss that results in the total head loss for the Kewaunee ECCS based on the various specified post-LOCA water levels and temperatures. Table 6 in Section 7.3 provides a summary of the Kewaunee ECCS head losses based on the Kewaunee specified post-LOCA water level and temperature. Page 3 of 4 Table 6 -Strainer Debris Laden Total Head Loss Test Results Clean Head CSHL ARL Clean Head Debris Head Loss, Debris Laden Total Head Loss, Regression Loss, (Table 5) Head Loss, Loss, Temperature Formula, ft of Temperature _ Temperature Temperature Corrected, ft of water at OF Corrected, ft of Corrected, ft of Corrected, ft of water at OF water at OF water at OF water at OF[Reference 9.3][Reference 9.3] [Reference 9.4]65 65 65 105.8 116.1 65 65 Design Basis 0.365 0.111 0.01807 0.51036 N/A 0.8313 1.1034 Supplemental 0.365 0.111 0.01807 N/A 1.66970 3.0139 3.2860 Basis CD 0 NOTES: 1. "Design" corresponds to full submergence conditions [Reference 9.11.2. The Clean Head Loss (Temperature Corrected) is based on the Clean Head Loss determined in calculation TDI-6008-05. The Clean Head Loss has been temperature corrected for the Kewaunee specified post-LOCA recirculation temperature. The Clean Head Loss for Kewaunee is a 'worse case" head loss that may not be applicable to all of the various ECCS operational scenarios. However, it does provide a "bounding worse case" head loss for Design Basis conditions that was conservatively utilized for all Kewaunee head loss determinations.

3. The Debris Laden Head Loss (Temperature Corrected) is based on Sections 7.2.1 and 7.2.2 and the test data of Table 4.4. The Total Head Loss (Temperature Corrected) is determined by subtracting the CSHL Regression Formula value from the Clean Head Loss (Temperature Corrected) which results in head losses from only the strainer discharge piping and assembly, adding the ARL Test Clean Head Loss (Temperature Corrected) value, and adding the Debris Laden Head Loss (Temperature Corrected) which cumulatively results in the maximum Kewaunee strainer head loss (clean strainer/strainer assembly losses plus debris (i.e., fibrous, particulate, miscellaneous, and chemical precipitates) laden losses).5. The values reflected herein may not show traiing digits, which simply means the checking of calculations can yield slightly different values than has been calculated for the calculation.

These rounding errors are considered insignificant and therefore acceptable. Any rounding errors are bounded by the uncertainty applied to the Clean Strainer Head Loss.-"1 m x 0 m-n X 0 0 M 0 r-I-" 0 C)0 I-I-" H 0 z m r-)0 C,, M-n 0 0 U)0OCD CD00 C) 0 6 6 C)N)(CTI CD 0-nl C.o C)m 0 m CD 0 z I-I 0 C z X.-a 0 1 0 0 I",, m z 0 I-0 U)C m G)TEST FLUME CONFIGURATION (TOP VIEW)0 0 CD x M.z z 0 0 00C 66~ 540ý362-&i16.~4O5~80 -rm-S 324____3I CD r'3)0 FLUME LENGTH DIMENSIONS (INCHES)-n, m 0'M zO0-<z X 0 G)0 m (n FLUME WIDTH DIMENSIONS (INCHES)0 o C/0 CD z z 0 0 C?1-C.0l C) 14 14 Flume Width vs. Distance-from Strainer i .......j---i ,+/-:4 -,-I- ---I- I -I -+-I-+-I-+-{-I-i-t-4 --f--i--I- ----I 01 2 34 5 6 783 9 10,11 12.314 1516 17IS 19 20 21 222,24 25 26272S .29 30 31:3a..Distance from Strainer (ft), CD 0 r M¢0 0 S mE C: m M 0 m I-G 0 C-I z 0 0 0"0"-m z 0 r-0 C m Flume Width at Flu me Width at Distancefromn Point A fftj Unear Interpotation .ncefrom PcintA Distan.efrom PointAlin) 1.OO .0.104 o.S69 103/8 1.396 -0.138 0.829 i0 3.000 .0.096 0.939 112/8 6.000 0.076 L. 18 14 2/8 10.000 0.093 0,972 115/8 21.000 0.122 0.741 8 7/8 25.000 0.128 0.706 84/8 30.000 0.130 0.697 83/8 Figure A-6: Flume Width vs Distance from Strainer 0 0 0 CD z 0 CI)01 C)CD 0 z 6 01 0Q CA Serial No. 10-025 Docket No. 50-305 ENCLOSURE G (RAI F.19.C.VI) FLUME DESIGN LAYOUT AND PHOTOGRAPHS STRAINER MODULE I Page 4 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE H (RAI F.19.C.XV) PHOTOS OF DEBRIS ADDITION DURING LARGE SCALE TESTS Latent Fines I acu m iicate I Page 1 of 5 Serial No. 10-025 Docket No. 50-305 ENCLOSURE H (RAI F.19.C.XV) PHOTOS OF DEBRIS ADDITION DURING LARGE SCALE TESTS A Coatings Tin (Zinc surrogate) Page 2 of 5 Serial No. 10-025 Docket No. 50-305 ENCLOSURE H (RAI F.19.C.XV) PHOTOS OF DEBRIS ADDITION DURING LARGE SCALE TESTS Coatings Acrylic Powder Coatings Acrylic Chips Page 3 of 5 Serial No. 10-025 Docket No. 50-305 ENCLOSURE H (RAI F.19.C.XV) PHOTOS OF DEBRIS ADDITION DURING LARGE SCALE TESTS Fine TempMat Fine Owens Corning Page 4 of 5 Serial No. 10-025 Docket No. 50-305 ENCLOSURE H (RAI F.19.C.XV) PHOTOS OF DEBRIS ADDITION DURING LARGE SCALE TESTS STempMat Smalls ical Debris Page 5 of 5 Serial No. 10-025 Docket No. 50-305 ENCLOSURE I-1 (RAI 23 & F.19.C.XIV) CLEAN STRAINER HEAD LOSS TEST DATA Figure 8-1: Temperature Corrected Clean Strainer Head Loss vs. Flow Rate Flow Rte vs. Clean Stananr Head Loaa 0.0300 -0.0250-0.0200--0.0150-0.0100 0.0050 Y 4E-07x? + 4E-05x + 0.0004 Fe =0.9918 I I 0,0000 50.c 10 70.00 90.00 110.00 130.00 150.00 Flow RMe (aPm)170.00 190.00 210.00 230.00 Note that a polynomial trend line of a 2Ix order was used to model the clean strainer head loss versus flow and is shown in Equation 8-1.Equation 8-1: Clean Strainer Head Loss Trend Une Equation y=4E-O7*x 2 +4E-05*x+0.0004 Where, y = head loss (ft of water)x = flow rate (gpm)The raw head loss data and flow data collected during testing is displayed in Figure 8-2.Page 1 of 2 Figure 8-2: Test I Raw Data (Flow and Head Loss)0 ft 250 225 200 175 1150 125 1100 75 50 25 0.035 0.032 0.029 0.026 0.023 0.02 A 0.017 0.014 i 0.011 CA)90 0 r-m z m m 0 r-0 CO)C)CD--q m z)m z 0 r-0 U)C m----- ----- L., *l mj I.0.008 0.005 0.002 04-0.00--40.001 80.00 10.00 20.00 30.00 40.00 50.00 60.00 Time (Minutes)a Measured Flow Rate

• Measured Head Loss 70.00 0 CD z z 0 0 CI 0 ON)O cn cn Figure 8-3: Test 3 Raw Data (Flow and Head Loss)0.65 T--I-I0.6 0.55 Design Basis Flow Rate (136.9_gpm)

T-I i \ i I I Ilncreased Measured Head No]Loss due to a Flow Adjust ment J--to 215 gpm' ...!IMaximum Measured(L 225 200 L. -J175 0.45 CD 0 0.4* 0.35 Cu C 0.3-2 0.&25 E J-J-Chemical Debris Test Termine IBatching Complete Criteria Met* ,Decreased Measured Head Loss due to a Flow Adjustment to -69 gpm--------- ------- -. ..:.. ...--- ----I, I i I -- -i WIU E 125 LL 100 0 75 5 50 25-- -r N0-n, C/)M M m mm C/Z-0 G)r-Zo 0C/)'mC;um cr-rN)0 M 0-I m rC 0 m C,, H 0.1 0.05 0.00 0.00 4.00 8.00 12.00 16.00 Time (Hours)20.00-h0 32.00 24.00 28.00-Measured Head Loss -Measured Flow Rate 0 o0 C z z 900 CI 0 (o.-6 N)l C(J10 Figure 8-4: Test 9 Raw Data (Flow and Head Loss)CE)0 ,0 2D x 150 140 130 120 110 100 a.90 CL 80 , 0 70 LL.60 C 6o 40 40 30 20 10 N)"13-In O0 m CfD i C--H C.0 H Co-rn m0>r-0 m C/)r-0 0 M 0 CfD C/)m z 0 r" 0 C m C/)04-0.00-40 32.00 4.00 8.00 12.00 16.00 20.00 24.00 28.00 Time (Hours)I -Measured Head Loss -- Measured Flow Rate I 0 o CD 7- M zz 0 0 00 IO 6 0 N0 0101 Serial No. 10-025 Docket No. 50-350 ENCLOSURE I-4 (RAI F.19.C.XIV) PHOTOS OF FLUME DRAIN DOWN Page 1 of 4 Serial No. 10-025 Docket No. 50-350 ENCLOSURE I-4 PHOTOS OF FLUME DRAIN DOWN (RAI F.19.C.XIV) I Page 2 of 4 Serial No. 10-025 Docket No. 50-350 ENCLOSURE I-4 (RAI F.19.C.XIV) PHOTOS OF FLUME DRAIN DOWN DEBRIS INTERCEPTOR I"1 UPSTREAM END OF FLUME Page 3 of 4 Serial No. 10-025 Docket No. 50-350 ENCLOSURE I-4 (RAI F.19.C.XIV) PHOTOS OF FLUME DRAIN DOWN FIBROUS AND PARTICULATE DEBRIS FIOW _ _I Page 4 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE J (RAI F.19.C.XV) CHEMICAL CONCENTRATION WORKSHEETS Test 3 -Design Basis Chemical Batching Volumes ATTACHMENT 3 -Chantlial Concentration Calculation I Batch Sizing & Estimatod PTO% to Conipek IP"wlgn kMWCf Igsle'alod 111" W"y I TDI-6058-02 Rev 0 Page I PIV Tot, F Ou ,ne r 0m Fl,...P#.8PFLOWRATE@STARTIW PurlFx..(pm, tt'tem] (LOlePt F- icuf() (gad) Ift cIll.) (s(cu a1 OJW Per TD40.28-02 136.9 __ 0.30S 40 238.10 30.79 268.8 1.011.441 0.305 881.50 114.691 29.39 Ahleilet° Test Water LeeI 136.9 0.305 0.0 0.00 30.719 30.79 0.00 1 0000 0.00 0.00 0.00 Chsxot.1 Dettirs Co~mcenlt~aoll Ctemiall" Dun* Up Added tor Soluasiftt Chtme-ka "tm Up to It~ldoali, fag Filte-Sodiums Ahle,wium Sikcate Alumna.. Oxyliydroxgle Cale or Ph'osphate UlM%'Scaled OtY 71It QboI leor 7.1,3um% u$]l max Ibm 12.51 I. 0.930 0.00 max Ibmt50m 0 2M Total WCAP Surrotate eo.tws .In 0.113 Al [2est A urogt -AIs VTi 40.21 WCAP Surrogate -AJOOOI OM 9A WCAP Swrfoqatu -Calciumn Pttospatt b.'. 6.211 Ch@Tf4Wt DITNo. 08 2o'!.. OVd..ma Aldim emlall dated Avg00. 2M 7 More Padt Vxahe DIT No. PC I 1 4 1 Fill., In Tex kst clumii 1.wirntO -0.93 _ CA 0000044 0000402 llWQ 0.00 0.0 0.0 58.75 1 48 0.03 walor -ý 0 0.00 Clo.M C= 0000 0.00000 I'bskud 0.0 jfM I 0.00 0 0.00o IToial 12.51 1 0,93 1 Towlat 00004 00061 0 00 0.03 10.02 385.75 1746 18.93-..T 1 4 .0.4k IA 38,153 I 28,.9 i"MSizs.%aw Calclved~ed ul ofer ALGOOJProcipieta tloe Added Os Ftuoe. 10.1 oadmý.KM .1JW ILSt.1.81 .3 OA 0. 91 .03 0.02 1 0.751.3(91 if, k t d .WA#e.gtera. Ilowmoe woonttotal jCa~4PO.0x. 0.0% 10.006 0 0.00 10.00 ji0.00 10.00 ri o -0 00001 Conversmog of -emx I lite to -11M I genow. I grarm .0.02205 be lIgor .0.284172 9eltorg;thoereto,.. 1 11 0.006345 4,si gallo 11 gil: : 0.010 , , Igat OIT No. 90OPI!M e ial 'Q. I n, 19 sawt Ra Bn as vch ohalumn I l Nalltlwo, 12.81 0 Pt" 33 R OIhtto *4 # ln AIOCIH 41.00, 0 rim 24% Htuongs 4.9181 w Tuall I 1011 tO to 36%iflt~ha@ CM I MoI, 0.32 goli.I~ALOO~~eto.4 i Totals, -51 0 n% Balic- --"M AlOG Chemicxal Precifidetoadical0. Tortlet tOi of ALOO ~ t-- 4 C9377ba.1 tAt.LQOI xAi O Elatita,QM Totollijw '100a alA..4710 36 3S5 2 Hae..IP $ TO15.4A09"tiel Th-at liottttt 10,13 2.84 0.114 10.13 a1t at ALOWI 1.00 ml .tCoOgs 10.13 Teida Page 1 of 2 Serial No. 10-025 Docket No. 50-305 ENCLOSURE J (RAI F.19.C.XV) CHEMICAL CONCENTRATION WORKSHEETS Test 9 -Supplemental Design Basis Chemical Batching Volumes MrAH I LEO 22= hom o ft C~ ntratlOo Calculation~ I Elatch Siloing & EStlimated PTOY's to Complete totTM9 T014-056.02 Rev 1 Page 1 AU-P ,--FI W.l!cL4tdl Pl"Vok-t VO- I TotldVrok-ItFlJmSI" T-owml l T u~vmtJ iroýPUMPFl.CWRAlE@STARrup Poele ow(W-1 (lfescj fltN.) 0I N] (ul (PI) (0), 6y=ot--)n f'os0, FMO(m.I P~rTD .0202821 130.2 02305 4. 230.10 20,7 " 260.60 2011.44 0.305 601.5 14.60 29.39 Alenlat Test Water Level 0.205 0 0.0 00.79 00.7 0.00 .0,00 0.0 0.00 0.00 Ch-.n.o1 Debris C-onnatutlon. Chworiat 8Sump Up Addd IaT SaltnnbiIy C12est~ Bum~p Up to Eliminate On~ Filters Sodium Alumnuom Silillost Alwrnlnom 0,ohydioxid Calcumn, Phosphat~e LM Owli, (lb" ý W"or hi) W WSunn, up. UWhA 3.10% WU.13%17T111 Ibm I~ I 1.66 Ibm max Wa 25.02[ 1.m8 0.00 Ibm max WI~l +0linbr maxgam WQAj OU-00 lotall WOAP Sur~rogate 0612.1. 1107 11.60 tbm factors 0.43 WCAP Sutogate-AIC01 0,00 WCAP Statwgalo -Csiciun, Phosphate 12A3 EZJTV" V.* 10A~Ih*e 50.9nstod Glsorth0. Belo.RIrl odVala OJ No A Pd1,en4u~tsL0409 hann~s~~n ge 0us I .TQ -UronA)$n R212Btolna l,.n.ln 2 ITTO A 910hdae 4 iAu Iaumll Iaobdao 25.02 1.8 J ALO 0.000608 00500925 lb ~al 0.11 0.0s 6 .04 1200.75, 740 1.SO ClumPhsotut -; 0.-5 1000 (ofo 0.000 0.0 0.ll 0.00 1 0.60 Total; IR 0 -=312 0 l02 Ib~.j 01 .6 00 07270 18(tal CO0,intd Vs12nofIAt.0011 Prodplatte tobe Addetd to Fhn 20,3 otore,.398153 280.0 1 33.3%120.00 1 12.43 i1201219 h ,AlOO1l 100.00% a188 010 0.0 0.04 078 ' 3 I 1.6 1 0.00% 0.00D 1 0.001) 0.00o1 .0 0..I0 0 ..0o0 Conversion 6Of "0lai I litor" to "lb b9 1gallon" I gram thereor., I q/i 12 gi/0.0522 lbs 023417 Valiums 000835 Ibs; gall..0.09"8 b1o. Gallon, n-,? I , W, 0.940 galefAtOL00Hst 12.60. eCaIP~el " lotip m:.0.000 .inICutilp1.hot~.lool, ALOOMC M901flJ~ustegptlteithei. 751700.0ibm 01AL00 l4Z ittn siAE a ito~ mon 20*ll~oý 1LgtU"gj 1050&d 04270 711,70 0,44 Tat.'.I0. r~AIW03"ld TotdiilaOKMo 20.28 12.27 1.69 20.126 1201 o Nt6'2.Mf GnoloieAoO.I 20.28 To.tt.010.Page 2 of 2 Serial No. 10-025 Docket No. 50-305 ENCLOSURE K (RAI 20/21/22) VORTEX CALCULATION TDI-6008-07, REVISION 6 CALCULATION ATTACHED ýDOmv in ion Calculation Cover Sheet C.... .. ATTC H 1 .P g 1 Calculation Number: Revision: Addendum: TDI-6008-07 6 N/A Calculation Quality Class: [ Safety Related [I NSQ El Non-Safety Related Installation Verification Required? EI Yes E] No Z N/A Note: Not applicable for Virginia Plants Subject (Calculation Title): Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Addendum Title (if applicable): N/A Station(s) and Unit(s): Kewaunee Affected System(s), Structure(s), or Component(s): 33/Safety Injection, 34/Residual Heat Removal Purpose: This calculation was revised to address NRC questions documented in NRC Letter dated August 14, 2009, Request for Additional Information, Resolution of Generic Safety Issue 191, PWR Sump Blockage.A flashing and gas evolution analysis was added to the calculation. Supercedes Revision 4 Originator: Provide printed name and signature (Qual. Required): Date: By Vendor 1/6/2010 Reviewer: Provide printed name and signature (Qual. Required): Date: By Vendor 1/6/2010 Suitability Reviewer (Qual. Required): Date: Lori Christensen 4406 644] //,bo, Approval: Provide printed name and signature: Date: Joseph McNamara /If.4J. -)99, ,/,/. oo (1) At the discretion of the originator, a facsimile of this cover sheet that does not contain the "CM-AA-CLC-301"or"Attachment 1" headers may be used. Facsimiles must reflect the current revision from which they were copied. (2) Add lines for additional originators or reviewers as necessary. Note if reviews are "Independent", "Peer", "Subject Matter Expert","Supervisor", or "Owner's". Form No. 131189 (Apr 2009) KEWAUNEE IMPACTED CALCULATION DOCUMENTS I ALTERNATE PLANT PROCESS CONFIGURATIONS SNOTE: Refer to 3GNP-04.03.04, Step 6.2.12 or Step 6.5.5 for Form Instructions. Calculation Number: TDI-6008-07 Rev.: 6 Title: Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -KeWaunee Power Station I ... >" Condition Report orr Document or Document or APC Responsible Individual Revisions Corective Action APC Number Description or Title or Process Owner Required Numbr(s)None identified ____ I. _________ I ______ ___ ______ 4 I- --4-+/- -L *- 4. _______________________ Form GNP-04.03.04-5 Rev. 20 Date: AUG 25 2009 REFERENCE USE Page 29 of 29 QF-0547(t) (FP-E-MOD-1

1) Rev. 2 Modification Process External Design Document Suitability Modifcatin PrcessReview Checklist External Design Document Being Reviewed: Title: Vortex, Air Ingestion

& Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Doc. I.D. #: TDI-6008-07 This design document was received from: Rev: 6 Date: 1/6/10 Organization Name: PCI PO or DIA

Reference:

70177019: Guidance: The purpose of the suitability review is to ensure that a calculation, analysis or other design document provided by an External Design Organization complies with the conditions of the purchase order and/or Design Interface Agreement (DIA) and is appropriate for its intended use. The suitability review does not serve as an independent verification. Independent verification of the design document supplied by the External Design Organization should be evident in the document, if required.The reviewer should use the Review Items' criteria below as a guide to assess whether the overall quality, completeness and usefulness of the design document is satisfactory (SAT). The reviewer is not required to check calculations in detail.L REVIEW ITEMS SAT N/A 1. Design inputs correspond to those that were transmitted to the External Design Organization.. ...______2. Assumptions are described and reasonable. EI.3. Applicable codes, standards and regulations are identified and met. ..4. Applicable construction and operating experience is considered. El _______.5_. Applicable structure(s), system(s), and component(s) are listed. .El 6. Formulae and equations are documented. Unusual symbols are defined. '.7. Acceptance criteria are identified, adequate and satisfied. El 8: Results are reasonable compared to inputs....

9. Source documents are referenced.

..10. The document is appropriate for its intended use. El 11. The document complies with the terms of the Purchase Order and/or DIA. El'12. Inputs, assumptions, outputs, etc. which could affect plant operation are enforced by adequate procedural controls. List any affected procedures: Procedure ES-1.3 ensures El adequate sump level for recirculation.

13. Plant impact has been identified and either implemented or controlled. (e.g., For piping analyses, the piping and support database is updated or a tracking item has been El 9 initiated.)

Provide explanation for response: Completed by, Lori Christensen Print Name I--O/..t4Le J~. ::;* o67 _I& eýV, kL.I45f N -q$ aAuepL~a( ~by Page 1 of 1 ..I .50.59 APPLICABILITY REVIEW (Is the activity excluded from 50.59 review?)1. Document/Activity number: TDI-6008-07, Rev. 6 2. Brief description of proposed activity (what is being changed and why): Air ingestion and vortex evalaution; revision to address NRC questions in RAT letter dated 8/14/09.Does the proposed activity involve or change any of the following documents or processes? Cheek YES or NO for EACH applicability review item.Explain in comments if necessary. [Ref. USA 50.59 Resource Manual]NOTE: If you are unsure if a document or process may be affected, contact the process owner.Yes No Document or Applicable" Process Regulation. Cotact/Action a 0] Z Technical Specifications or Operating License I 0CFR50.92 Process change per LI-AA-101. Contact Licensing. bChange previously approved by NRC in license Identify NRC letter in comments below. Process b amendment or NRC SER, or supports ITS LA/LAR. IOCFR50.90 change. Contact Licensing/ITS group for assistance, amendmentor__RCSER,_orsupports___SLA/_AR. _as required.Activity/change covered by an existing approved 10CER50 Appendix B Identify screening or evaluation in comments below..c I 0CFR50.59 review, screening, or evaluation. Process change.Dominion Quality Assurance Program Description 10CFR50.54(a) Contact QA.dR.(DOM-QA-1) Refer to NO-AA-101. e [ Emergency Plan 10CFRS.54(4) Contact EP.Refer to FP-R-EP-02. f El 0 Security Plan 10CFRS0.54(p) Contact Security.Refer to FP-S-SPE-O1. Contact IST process owner.g ] El ISTPlan 10CFR5O.55a() .Refer to ER-AA-IST-10. h El 0 IS1 Plan TOCFR50.55a(g) Contact ISI process owner. Refer to__ ,_, ER-AA-NDE-122, NAD-0 1.05, and NAD-05.1 1.i 0] 0 ECCS Acceptance Criteria 10CFR50.46 Contact Licensing.

• USAR or any document incorporated by reference

-Process USAR change per NEP-05.02. Check YES only if change is editorial (see 10CFR50.71 Contact USAR process owner for assistance. Attachment A). C ntactUSARprocessownerforassistance. Commitment -Commitment changes associated Contact Licensing. k with a response to Generic Letters and Bulletins, or IOCFR5O Appendix B Refer to LI-AA-I 10._____ 'if described in the USAR require a pre-screening.. Maintenance activity or new/revised maintenance Evaluate under Maintenance Rule.I [] procedure -Check YES only if clearly maintenance 10CFR50.65 Refer to ER-AA-MRL-10, ER-AA-MRL-I 00, and and equipment will be restored to its as-designed NAD-08.2i condition within 90 days (see Attachment C). NAD_08 _ _1.New/revised administrative or managerial directivelprocedure (e.g., NAD, GNP, Fleet m El 0 Procedure) or a change to any procedure or other I0CFR50 Appendix B Process procedure/docmcnt revision, controlled document (e.g., plant drawing) which is clearly editorial/administrative. See Attachments A and B.F nIOCFR50.48 Fire Protection Program Document Change Control, SFire Plan / 1CFR0.48 GNP-05.30.01, o 0 Independent Spent Fuel Storage Installation (ISFSI) 1OCFR72.48 Implement DNAP-3004, starting with Applicability.

4. Conclusion.

Check one of the following: [] All documents/processes listed above are checked NO. 10CFR50.59 applies to the proposed activity. A 50.59 pre-screening shall be performed. One or more of the documents/processes listed above are checked YES, Ah92 controls all aspects of the proposed activity. I0CFR50.59 does NOT apply. Process the change under the applicable program/process/procedure.. E] Oni or more of the documents/processes listed above are checked YES, however, some portion of the proposed activity is not controlled by any of the above processes. 1OCFR50.59 applies to that portion. A 50.59 pre-screening shall be performed.

5. Comments: Item c -Screening 06-007-02 was performed for DCR 3605 that addressed the new strainer design, submergence and prevention of vortex/air ingestion.

6. Print name followed by signature.

Attach completed form to do Ient/activity/change package.Prepared by: Lori Christensen / Date: 1/7/2010 (print/sign) Reviewed by: Scott Putman .Date: / '9 0 (print/sign) Form GNP-04.04.01-1 Rev. 13 Date: NOV 24 2009 INFORMATION USE Page 15 of 16 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strair WFPC I Kewaunee Power St PERFORMANCE Technical Document No. TDI-60(CONIIRACIING INC Revis CALCULATION COVER SHEET Calculation Number: TDI-6008-07 Technical Document Rev. No. 6 Addenda No.: N/A Calculation Title: Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Safety Related? YES ier) -ation 08-07 lion 6 Calculation Verification Method (Check One):[ Design Review [] Alternate Calculation Scope of Revision: Revision to address and incorporate KPS comments.Revision 6, pages: All Qualification Testing Documentation of Reviews and Approvals: Originated By: Verified B./Approved Date: //(,/0o Date: 0a Z2' -.o0/0 Date: / i , TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 1 of 32, 1 FIPCI PERFORMANCL C(ONIRAC1ING INC I I Calculation Title: Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 CALCULATION VERIFICATION CHECKLIST Vortex, Air Ingestion & Void Fraction (ECCs Recirculation Strainer) -Kewaunee Power Station 6 Revision: CHECKLIST Yes No n/a 1. Were inputs correctly selected and incorporated? OL E] I]2. Are assumptions adequately described and reasonable? [ Li 3. Are the appropriate quality and quality assurance requirements specified? 0 El El Are the applicable codes, standards and regulatory requirements identified and ED El El met?5. Have applicable construction and operating experience been considered? M El LI 6. Have the design interface requirements been satisfied? 0 El El 7. Was an appropriate design method used? M El E 8. Is the output reasonable compared to input? O ZE 9. Are specified parts, equipment, and processes suitable for the required application? El El 0 10. Are the specified materials compatible with design environmental conditions? El EL 0 11. Have adequate maintenance features and requirements been specified? El El 0 12. Are accessibility and other design provision adequate? El [I 0 13. Has adequate accessibility been provided to perform the in-service inspection? El 0l 0 14. Has the design properly considered radiation exposure? El El 0 15. Are the acceptance criteria incorporated in the design documents sufficient to allow Z] El 1 verification?

16. Have adequate pre-operational and subsequent periodic test requirements been El El Z specified?

17. Are adequate handling storage, cleaning and shipping requirements specified?

E] E] 0 18. Are adequate identification requirements specified? 0 El Z 19. Are requirements for record preparation, review, approval, retention, etc., m 1 El 0 adequately specified? 20.Has the appropriate Calculation Guideline Verification Checklist been reviewed and signed?0-his Pis m3060-3 Revision 3 Verified bylDate TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 2 of 321 SPCI PERFORMANCE CON IRACIING INC I Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 TABLE OF CONTENTS CALCULATION COVER SHEET CALCULATION VERIFICATION CHECKLIST TABLE OF CONTENTS 1.0 Purpose and Summary Results 2.0 Definitions and Terminology

3.0 Facts

and Assumptions

4.0 Design

Inputs 5.0 Methodology

6.0 Acceptance

Criteria 7.0 Calculation(s)

7.1 Vortex

7.2 Air Ingestion 7.3 Void Fraction 8.0 Conclusions

9.0 References

10.0 Drawings ATTACHMENTS Attachment 1 Flashing & Gas Evolution Analysis TABLES Table 1 Results Summary Table 2 Calculation Results Originated By: _______________ TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Date: 3/of Page 3of 32 SPCI PERFORMANCE CONIRACIING INC I Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 1.0 Purpose and Summary Results The US Nuclear Regulatory Commission (USNRC) in generic safety issue (GSI)191 identified it was possible that debris in PWR containments could be transported to the emergency core cooling system (ECCS) sump(s) following a main steam line break (MSLB) and/or a loss of coolant accident (LOCA). It was further determined that the transported debris could possibly clog the sump screens/strainers and impair the flow of water, thus directly affecting the resultant operability of the various ECCS pumps and the containment spray (CS) system pumps, and their ability to meet their design basis function(s). In order to address and resolve the various issues identified by the USNRC in GSI-191, utilities have implemented a program of replacing the existing ECCS sump screens or strainers with new and improved designs.Dominion Energy Kewaunee, Inc. (DEK) entered into a contract with Performance Contracting, Inc. (PCI) to address and resolve the specific issues associated with USNRC GSI-191 for the Kewaunee Power Station (Kewaunee). The primary objective of the contract was for PCI to provide a qualified Sure-Flow' Suction Strainer that has been specifically designed for Kewaunee in order to address and resolve the NRC GSI-191 ECCS sump clogging issue.PCI has prepared a Qualification Report specifically for the subject strainer. The Qualification Report is a compilation of the various documents and calculations that support the strainer qualification. As part of the Kewaunee Qualification Report, PCI has performed a number of hydraulic calculations in support of the replacement Sure-Flow Suction Strainer.This calculation TDI-6008-07, Vortex, Air Ingestion & Void Fraction -Kewaunee Power Station is one of a number of hydraulic calculations that specifically supports the design and qualification of the subject strainer.This calculation addresses the various issues associated with the separate but related issues associated with vortex, air ingestion, and void fraction as they relate to the sump and strainer assembly that has been designed specifically for Kewaunee.Kewaunee has one recirculation strainer assembly that feeds a common suction sump. The Kewaunee 'A' or 'B' train ECCS and the CS system are supplied by the recirculation strainer. The horizontally oriented recirculation strainer assembly is comprised of fourteen (14) modules each made up of six (6) strainer disks for a total strainer area of 768.7 ft 2.Flow leaves the strainer and enters a combination of pipe and fittings before discharging into the sump pit. A maintenance hatch (employing two (2) disks) for the sump also provides for Orialinated By: Date:--- -qiil ........ * -rý- -------- ----Page 4 of 32 TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc SPCI PERFORMANCE CON IRACIING INC I Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 water entry into the sump at a lower elevation. However, the maintenance hatch is not credited as a recirculation system strainer and it is not included in the PCI calculations for the recirculation strainer. PCI drawings [Drawings 10.1 -10.8, inclusive] provide details of the subject configuration. The results of the calculation are provided in Table 1. The calculation utilizes the Acceptance Criteria established in both Kewaunee and USNRC documents with respect to PWR sump performance to specifically evaluate the Kewaunee Sure-Flow Suction Strainer assembly.Table I -Results Summary Issue Acceptance Criteria Results USNRC Kewaunee Vortex No vortex No detrimental ACCEPTABLE -Vortex formation is effects on ECCS precluded by the PCI Sure-Flow Suction& CS pumps Strainer design and configuration Air 0% or <2% <2% ACCEPTABLE -Air ingestion will not occur Ingestion since there is no vortex formation associated with the PCI Sure-Flow Suction Strainer design and configuration Void <3% Flashing ACCEPTABLE -Voids will not occur at the Fraction prevented down strainer (calculation indicates <0%) based stream of the on Kewaunee specified post-LOCA strainer pressure and temperature parameters. In addition, the calculation also concludes that voids occurring in the Sure-Flow Suction Strainer assembly will have collapsed by the time the sump water leaves the strainer assembly and discharge piping, and before leaving the KPS containment sump.Attachment 1, Flashing & Gas Evolution Analysis provides an evaluation of the subject issues. It was determined that there are no flashing or gas evolution issues for KPS.It was concluded that this calculation, an integral portion of the Qualification Report completely supports the qualification, installation, and use of the PCI Sure-Flow Suction Strainer for DEK's Kewaunee Power Station without any issues or reservations. -,looz2 zly Originated By: Date: //, Page 5 of 32 1-1 TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -F PC I Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 CONIRACIING INC Revision 6 2.0 Definitions & Terminology The following Definitions & Terminology are defined and described as they are utilized in this calculation. Sure-Flow Suction Strainer -Strainer developed and designed by Performance Contracting, Inc. that employs Sure-Flow technology to reduce inlet approach velocity.Emergency Core Cooling System (ECCS) -The ECCS is a combination of pumps, piping, and heat exchangers that 'can be combined in various configurations to provide either safety injection or decay heat cooling to the reactor.Kewaunee Power Station -also known as Kewaunee and KPS.Main Steam Line Break -also known as MSLB. A MSLB is not a LOCA.Containment Spray System -also known as CSS or CS. System is utilized to address either a MSLB or a LOCA.Loss-Of-Coolant-Accident -also known as a LOCA. A LOCA is theresult of a pipe break or inadvertent leak that results in the discharge of primary reactor coolant from the normal nuclear steam supply system (NSSS) boundary. A LOCA can be classified as a large break LOCA (LBLOCA) or a small break LOCA (SBLOCA). Classification is directly dependent upon the nominal size of the affected pipe that is associated with the LOCA.3.0 Facts and Assumptions The following Facts (designated as [F]) & Assumptions (designated as [A]) were utilized in the preparation of this calculation.

3.1 Pressure

of 39.3989 psia and temperature of 214.7111 'F were provided by Kewaunee as design input in order to determine head-loss, vortex, air ingestion, and void fraction in accordance with various USNRC guidance documents [Reference 9.18] [F].3.2 A flow velocity of 0.0056 fps would be characteristic of the Kewaunee strainer, through a debris bed consisting of fibers and particulate is 100%viscous flow. Accordingly, the head loss is linearly proportional to dynamic viscosity [A].Originated By: Date: Za Tv A o v r / .6.-- Pae- /TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 6 of 32 1 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -!iPC I Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07-C()NIRACJIN(; INC Revision 6 3.3 A scale strainer, which is designed to maintain the same approach velocity as the full scale production strainer, can accurately simulate the performance of the full scale production strainer so long as the same scaling factor is used for strainer area, water flow rate, and debris quantities. The scaling factor is defined as ratio of the surface area of the scale strainer and the surface area of the full scale production strainer [A].3A The head loss resulting from flow through a fiber -particulate debris bed at the approach velocity for the Kewaunee strainer (0.0056 ft/s)[Reference 9.10], is 100% viscous flow, as opposed to inertial flow. As viscous flow, head loss is linearly dependent on the product of viscosity and velocity. Therefore, to adjust the measured head loss across a debris bed with colder water, a ratio of water viscosities, between the warmer specified post-LOCA water temperature and the colder test temperature, can be multiplied by the measured head loss to obtain a prediction of the head loss with water at the specified post-LOCA temperature [A].4.0 Design Inputs The following combination of DEK and PCI Design Inputs were utilized in the preparation of this calculation.

4.1 Dominion

Energy Kewaunee, Inc., Kewaunee Power Station, Technical Specification for Containment Sump Strainers, No. K-4890, Revision 0[Reference 9.1]. This document provides design input associated with strainer flow rate, water temperature, and the maximum allowable head loss.4.2 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCI-06-008, Replace Containment Recirculation Sump B Screens, dated 4/18/06 [Reference 9.8]. This document provides specific information for calculating the void fraction for the new strainer.4.3 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCI-06-011, Replace Containment Recirculation Sump B Screens, dated 4/21/06 [Reference 9.3]. This document provides specific information for calculating the void fraction for the new strainer.4.4 Performance Contracting, Inc. (PCI) Calculation TDI-6008-02, SFS Surface Area, Flow and Volume Calculation, Revision 1 [Reference 9.16].Originated By: Date: TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 7 of 32 1 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -KAPC I Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 CONIRACIIN(. INC Revision 6 This document provides relevant dimensions and other information specifically associated with the Kewaunee strainer.4.5 PCI Calculation TDI-6008-05, Clean Head Loss (ECCS Recirculation Strainer) -Kewaunee Power Station, Revision 4 [Reference 9.10]. This document provides the head loss associated with the "clean" Kewaunee strainer and attached pipe and fittings.4.6 PCI Calculation TDI-6008-06, Total Head Loss (ECCS Recirculation Strainer) -Kewaunee Power Station, Revision 8 [Reference 9.9]. This document provides the total head loss associated with the Kewaunee strainer and attached pipe and fittings.4.7 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCl-06-015, Replace ECCS Recirculation Strainer, dated 7/7/06 [Reference 9.17]. This document provides specific information for calculating the void fraction for the new strainer.4.8 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCI-06-016, Replace ECCS Recirculation Strainer, dated 7/12/06 [Reference 9.18]. This document provides specific information for calculating the void fraction for the new strainer.4.9 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), GSI Chem-2008-04, Revision 2, Chemical Effects Testing, dated 7/16/08 [Reference 9.20]. Document provides revision of Kewaunee debris allocation and ECCS flow rates.4.10 AREVA Engineering Information Record, Document Identification No. 66-9089247, Kewaunee Test Report for ECCS Strainer Performance Testing, Revision 0, September, 2008 [Reference 9.4]. This document provides the method and value of the tested debris head loss and the mechanism of adjusting the tested debris head loss to the specified post-LOCA water temperature. 4.11 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCl-09-001, GSI-191 Resolution, dated 9/24/09 [Reference 9.21]. This document provides specific information regarding the post-LOCA containment water level for calculating flashing and determining gas evolution for the new strainer.Originated By: (2.Date: /.o An ... /TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 8 of 32 1 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -KIF PC IKewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 I( ONIRACIINC. INC Revision 6 4.12 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, EOP Setpoint Calculation Wide Range Containment Sump Level Versus Available RWST Volume, C10984, Revision 1, Addendum A [Reference 9.22]. This document provides specific information regarding the post-LOCA containment water level for calculating flashing and determining gas evolution for the new strainer.5.0 Methodology PCI utilized classical standard hydraulic principles and equations to address the subject issues. PCI recognizes that if it is determined that one of the issues cannot occur and/or can be prevented, then one or more of the other issues cannot occur (e.g., if a vortex is not predicted by calculation then there should be no air ingestion). However, PCI has conservatively assumed that each issue is separate, and each issue will be addressed on its own merits.6.0 Acceptance Criteria This specific calculation addresses three (3) separate but related issues -vortex, air ingestion and void fraction. Accordingly, each issue has it own separate acceptance criterion. The final overall acceptance criterion is that the Kewaunee ECCS pumps have adequate NPSH margin under all postulated post-LOCA conditions. Vortex The USNRC in RG 1.82 Revision 3 [Reference 9.6] has indicated that air ingestion can lead to ECCS pump degradation and/or failure. A vortex is a potential source of air ingestion. A vortex can be prevented due to various combinations of sump configuration and the addition of vortex suppressors in the sump.The Acceptance Criteria for vortex is the complete elimination of occurrence. Air Ingestion RG 1.82 Revision 3 [Reference 9.6] states that air ingestion can lead to ECCS pump degradation and/or failure if air ingestion is > 3%. Accordingly, the USNRC has recommended a limit of 2% by volume on sump air ingestion. In addition, the USNRC has also recommended that even with air ingestion levels at 2% or less, NPSH can still be affected. The USNRC has further recommended that if air ingestion is indicated, that the NPSH be corrected from the pump curves.The Acceptance Criteria for air ingestion 'is < 2%.Originated By: ___ ______ Date: ///0 TDI-008.7 Vrtex Ai Ingstin & oid racion Re.6.dc Pge/012 TDIA008-07 Vortex. Air Ingestion & Void Fraction -RevAdoc Page 9 of 32 SPCI PERFORMANCE CONIRACIING INC r -] _Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 Void Fraction USNRC GSI-191 SE [Reference 9.5] has indicated that ECCS pumps can experience cavitation problems when inlet void fraction exceeds approximately 3%.The Acceptance Criteria for void fraction is <3% in conjunction with an acceptable sump pool temperature operating range as specified in Attachment V-1 of [Reference 9.7].7.0 Calculation(s) In order to address and determine the acceptability and/or issues potentially associated with the three (3) separate but related issues of vortex, air ingestion and void fraction, a separate analysis of each issue was performed.

7.1 Vortex

The Kewaunee specification [Reference 9.1], specifically section 3.6.9 addresses strainer vortex, but does not provide limitations on the new strainer design that specifically prohibits the formation of a vortex (i.e., no vortex allowed). Accordingly, PCI has utilized the guidance of USNRC RG 1.82, Revision 3 [Reference 9.4] to address the vortex issue for the Kewaunee strainer.In [Reference 9.6], the USNRC provided generic guidance with respect to PWR sump performance, sump design, and vortex suppression. The subject reference can be utilized as a means of assessing sump hydraulic performance, specifically the issues associated with a potential vortex in the sump.The Kewaunee sump pit is approximately 8'-6" (W) x 8'-6" (L) x 7'-9" (D), including the height of the curb around the sump. The opening into the sump is approximately 2'-8" (W) x 8'-6" (L). The majority of the sump is covered by the Reactor Building floor slab located at elevation 592'-0".The opening into the sump was previously covered by a plate on which were mounted, two (2) "conical-shaped" vertically oriented strainer elements that were made of Johnson screen [Reference 9.1].Since the Kewaunee sump and ECCS pump inlets were modified by the addition of the PCI Sure-Flow suction strainer, the guidance offered by the USNRC in [Reference 9.6] is not entirely or specifically applicable. However, the guidance does provide some information that can be utilized Originated By: Date: 116,11(1 T v Faco- ZR "eif TDI-6008-07 Vortex, Air ingestion & Void Fraction -Rev.6.doc Page 10of 32I Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -F PC I Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 CONIRACIINGC INC Revision 6 in the assessment of the revised Kewaunee sump and strainer configuration with regard to vortex issues.The "revised" Kewaunee sump and strainer configuration utilizes a horizontally oriented, fourteen (14) module PCI Sure-Flow suction strainer that discharges through attached pipe and fittings to a cover plate mounted directly on the sump. In addition to the suction strainer, a removable maintenance hatch was installed containing a two-disk vertically oriented PCI Sure-Flow suction strainer [Drawing 10.1 -10.8, inclusive]. The PCI Sure-Flow suction strainer and removable maintenance hatch will be separately analyzed and addressed with respect to vortex issues.PCI Sure-Flow Suction Strainer The PCI Sure-Flow suction strainer for Kewaunee is comprised of fourteen (14) horizontally oriented modules each containing six (6) disks.The disks are a nominal 5/8" thick and are separated 1" from each adjacent disk. The interior of the disks contain rectangular wire stiffeners for support, configured as a "sandwich" made up of three (3) layers of wires -7 gauge, 8 gauge, and 7 gauge. The disks are completely covered with perforated plate having 0.066" holes. The end disk of a module is separated approximately 5" from the end disk of the adjacent module.The 5" space between adjacent modules is covered with a solid sheet metal "collar." Each of the modules has cross-bracing on the two exterior vertical surfaces of each module.Based on the design configuration of the Kewaunee strainer assembly, the largest opening for water to enter into the sump is through the perforated plate 0.066" holes. The size of the perforated plate holes by themselves would preclude the formation of a vortex. However, in the unlikely event that a series of "mini-vortices" combined in the interior of a disk to form a vortex, the combination of the wire stiffener "sandwich" and the small openings and passages that direct the flow of water to the strainer core tube would further preclude the formation of a vortex in either the core tube or the sump.The USNRC in [Reference 9.6], specifically Table A-6 guidance is provided with regard to vortex suppressors. The table specifies that standard 1.5" or deeper floor grating or its equivalent has the capability to suppress the formation of a vortex with at least 6" of submergence. Originated By: Date: 1A 11 TDI-6008-07 Vortex, Air Ingestion & Vold Fraction -Rev.6.doc Page 11 of 321 WA PC I PERFORMANCE CONIIWJIING INC Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 The design configuration of the PCI Sure-Flow suction strainer for Kewaunee due to the close spacing of various strainer components and the small hole size of the perforated plate meets and/or exceeds the guidance found in Table A-6. The Kewaunee strainer does not meet the 6" submergence requirement. The configuration for Kewaunee results in an actual Submergence of 3" (2" utilized for calculations) to the top of the strainer assembly. However, there is a submergence level of approximately 11" to the top of the core tube. In addition the water flow would have to pass through more than 8" of combined perforated plate, wire stiffener "sandwiches", and cross-bracing which would further preclude the formation of a vortex.The USNRC carried out a number of tests regarding vortex suppressors at the Alden Research Laboratory (ARL) to arrive at, the information summarized in Table A-6 of [Reference 9.6]. The PCI Sure-Flow@ suction strainer prototype for Kewaunee was also tested at ARL under various conditions. During the original testing of the Kewaunee strainer even when partially uncovered, did not exhibit any characteristics associated with a vortex or vortex development. The recent Kewaunee strainer testing at ARL in August 2008 indicated that there was no indication or observation of vortex initiation or formation [Reference 9.4].It can therefore be concluded that the configuration of the Kewaunee Sure-Flow) suction strainer will prevent the formation of vortex development. Removable Maintenance Hatch The Removable Maintenance Hatch for Kewaunee is comprised of a single vertically oriented module containing two (2) disks. The disks are a nominal 5/8" thick and are separated 1" from each other. The interior of the disks contain a circular "spider" rectangular wire stiffeners for support, configured as a "sandwich" made up of three (3) layers of wires -7 gauge, 8 gauge, and 7 gauge. The disks are completely covered with perforated plate having 0.066" holes. An external radial debris stop with integral cross-bracing assists in both the structural stability of the two strainer disks as well as to preclude the introduction of large debris to the disks.Based on the fact that the subject strainer disks, cross bracing and the addition of the "spider" stiffener are of similar design configuration as that of the Kewaunee strainer assembly, and based upon its lower sump elevation and thus greater submergence than the ECCS Recirculation Strainer it can be concluded that the configuration of the Kewaunee Originated By: ____________ Date: / 4/'/TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 12 of32 1 SPCI PERFORMANCL CONIRACIING INC I Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 Removable Maintenance Hatch strainer will prevent the formation of vortex development. 7.2 Air Ingestion The Kewaunee specification [Reference 9.1], sections 3.4.1.10 and 3.4.1.13 address vortex issues, and section 3.4.1.13 specifically requires that the new strainer have a design that limits air ingestion to <2%. This requirement is in accordance with USNRC RG 1.82, Revision 3[Reference 9.6]. Appendix A and Table A-I of [Reference 9.6] indicate that sump performance specifically related to air ingestion is a strong function of the Froude Number, Fr. By limiting the Froude Number to a maximum of 0.25, air ingestion can be maintained to <2%.The flow of post-LOCA water from a piping system associated with a LBLOCA or SBLOCA, or a CS initiation associated with a LOCA collects in the lower areas of the containment and eventually migrates to the ECCS sump. The flow can be considered to be and is classified as open channel flow. For open channel flow, the Froude Number, Fr, is defined as follows[Reference 9.11].Fr = V I (g X S)1/2 Where V = the velocity of water exiting the core tube. For Kewaunee V. = 2.453 ft/s [Reference 9.10].S = the ratio of the cross-sectional area of the PCI Sure-FlowTM suction strainer core tube, Ae,, and the equivalent diameter of the core tube smallest orifice, Dhole , ft.g = gravitational constant, 32.2 ft/s 2 The most conservative value that can be utilized for s is the case of the core tube cross-sectional area and the smallest hole in the core tube.From the Kewaunee Clean Head Loss report [Reference 9.10], A. .1.744 ft 2.The Kewaunee Core Tube Design report [Reference 9.19]indicates that the smallest calculated hole / slot area, Ahole, lB = 0.720 in 2 , or 0.0050 ft 2 , Therefore, the equivalent diameter of the smallest core tube hole can be calculated as follows.Originated By: ______;_Date: TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc I.Page 13 of 32 1 NPCI PERFORMANCE CON IRAI..IING. INC Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 Dhole, 1A = (4 Ahole, 1B / "IT )112-(4 x 0.0050 / irr )112= 0.0798 ft The value s can be calculated as follows.S = A.x I Dhole, 1B= 1.744 / 0.0798= 21.8546 Accordingly, value of Fr can be calculated as follows.Fr = V I (g x s)112 Fr = 2.453 / (32.2 x 21.8546)1/2 = 2.453 / 26.5277= 0.0925 The calculated Froude Number for the Kewaunee PCI Sure-Flow suction strainer is substantially smaller than the USNRC guidance of 0.25 found in[Reference 9.6]. Therefore due to the combination of a low Froude Number and lack of an air entrainment mechanism (i.e., vortex formation) in conjunction with the complete submergence of the strainer, air ingestion is not expected to occur.7.3 Void Fraction The Kewaunee specification [Reference 9.1], does not specifically address the issue of Void Fraction. Accordingly, PCI has utilized the guidance of USNRC documents [Reference 9.5, 9.6. 9.7, and 9.15] to address the void fraction issue for the Kewaunee strainer.Although it is asserted in various regulatory documents that void formation is directly related to air ingestion, this is not correct. Void formation is the result of the pressure of a fluid being reduced below the saturation (Z/'Originated By:.../°Date: Page 14 of 32 TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -F/IFPC I Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 INCRevision 6 pressure with the resulting voids being formed by the flashing of the liquid phase. Air does not need to be present to create significant voiding.PCI has evaluated the issue of Void Fraction by the use of conventional hydraulic and fluid flow calculations to determine the Kewaunee Void Fraction.Conventional Calculation Methodology Kewaunee [Reference 9.18] defined the containment post-LOCA water temperature as being 214.71.10 F. A corresponding containment pressure of 39.3989 psia was provided [Reference 9.18]. The measured strainer Design Basis debris head loss was 1.1034 feet of water [Reference 9.9]and the Supplemental Design Basis debris head loss was 3.2860 feet of water [Reference 9.9], based on and adjusted for the Kewaunee Design Basis temperature of 65 OF. By applying a temperature viscosity adjustment [Reference 9.9] to the strainer debris head losses (i.e., Design Basis and Supplemental Design Basis) from the Kewaunee Design Basis water temperature of 65 OF to the specified post-LOCA condition of 214.711 °F, the maximum expected debris head losses (i.e., Design Basis and Supplemental Design Basis) at the subject post-LOCA water temperature can be determined. Design Basis HLTA = HLDL,C (IST/ IIJ TT)Where HLDL,C= corrected, Design Basis Debris Loaded Head Loss, 1.1034 ft of water PST = dynamic viscosity at the post-LOCA specified temperature of 214.711 OF= 0.000186426 lb/ft-s IJTT = dynamic viscosity at the Kewaunee Design Basis temperature of 65 °F= 0.000701778 lb/ft-s HLTA = temperature adjusted debris head loss, ft= 1.1034 ft (0.000186426 / 0.000701778) Originated By: 2 , _Z Date: 47//TD-00-7 oteAi ngso Vi Frcin-Re..o / gio3 TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 15 of 32 01 11PCI PERFORMANCE CONIIA('IING INC Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6= 1.1034 ft x 0.2657= 0.2932 ft of water, or= 0.1271 psi Supplemental Design Basis HLTA = HLDL,C (PST I pI T)Where HLDL,C = corrected, Supplemental Design Basis Debris Loaded Head Loss, 3.2860 ft of water PST = dynamic viscosity at the post-LOCA specified temperature of 214.711 OF= 0.000186426 lb/ft-s PTT = dynamic viscosity at the Kewaunee Design Basis temperature of 65 OF= 0.000701778 lb/ft-s HLTA = temperature adjusted debris head loss, ft= 3.2860 ft (0.000186426 / 0.000701778) 3.2860 ft x 0.2657= 0.8731 ft of water, or= 0.3785 psi Subtracting the calculated head losses for the Design Basis and Supplemental Design Basis (i.e., 0.1271 and 0.3785 psi, respectively) from the Kewaunee specified containment post-LOCA pressure of 39.3989 psia [Reference 9.1 and 9.18] results in respective pressures of 39.2718 and 39.0204 psia associated with the downstream side of the strainer debris bed. The water vapor pressure at 214.7111 OF is 15.509 psi. This is 23.7628 and 23.5114 psi, respectively less than the calculated downstream strainer debris bed pressures of 39.2718 and 39.0204 psia.Originated By: Date: Page 16 of 32 TDI-6008-07 Vortex, Air Ingestion & Vold Fraction -Rev.6.doc SPCI PERFORMANCE CON IRACIING INC Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 Therefore boiling and flashing of the sump water will not occur across the strainer debris bed and would not create a > 3% void fraction.Because "flashing" would not occur at the strainer based on the Kewaunee specified temperature and pressure parameters within the post-LOCA containment, it is highly unlikely that "flashing" or a void fraction > 3% would be present at the outlet of the strainer piping as the strainer discharge flow enters the containment sump.This conclusion is based on the following analysis.Given [Reference 9.16]: Available submergence (total water depth in Kewaunee containment @ centerline of sump suction): Worse-Case Strainer Head Loss (i.e., Supplemental Design Basis): Difference: 9.175' (110.1")0.8731'8.3019' (3.5991 psi)It was previously determined that a minimum pressure of 0.3785 psi (i.e., Supplemental Design Basis Head Loss) is required to prevent "flashing" and subsequent void fraction formation. Accordingly, it can be concluded that any voids caused by "flashing" of the water in the strainer would have collapsed by the time the water leaves the strainer assembly and discharge piping. This is based on the fact that the containment water head is at least 8.3019 feet greater than saturation (i.e., 3.5991 psi >0.3785 psi). Therefore it can be concluded that there will be 0% void fraction associated with the strainer discharge flow before it leaves the Kewaunee containment sump under the post-LOCA containment pressure and temperature parameters of 39.3989 psia and 214.7111 °F, respectively.

8.0 Conclusions

The result of this calculation, specifically the acceptability of the issues associated with vortex, air ingestion, and void fraction are summarized in Table 2. Flashing and gas evolution are addressed in Attachment 1.It was concluded that the subject issues have been addressed for Kewaunee and the results indicate that there are no problems. This specific calculation Originated By: (j/ 4 9 Date: TDI-6008-07 Vortex, Air ingestion & Vold Fraction -Rev.6.doc Page 17 of 321 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -PU I Kewaunee Power Station)RMANCE Technical Document No. TDI-6008-07 ACIINGINiN(;Revision 6 completely supports the qualification, installation, and use of the PCI Sure-Flow Suction Strainer for DEK's Kewaunee Power Station without any issues or reservations. dl Originated By: Date: /0 Page18of32 I TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc .PCI PERFORMANCE CONIRACIING INC Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 Table 2- Calculation Results Issue Acceptance Criteria Results Comments USNRC Kewaunee Vortex None No ACCEPTABLE Results applicable to the Kewaunee Sure-Flow9 detrimental .strainer.(Ref: RG No Vortex -vortex formation is 1.82, 3)v. effects on precluded by the PCI Sure-Flow 5 3) ECCS & Suction Strainer design and CS pumps configuration. Air Ingestion 0% or <2% ACCEPTABLE Per RG 1.82, Revision 3, if air ingestion is > 0%,<2% Air Ingestion could occur- calculation the pump NPSH must be corrected by the (Ref: RG indicates > 0% but < 2%. However, relationship, NPSHrequired (up<%) = NPSH 1.82, Rev. since it has been determined that vortex required(Ilquid)X 13, where 13 =1 + 0.50ap and ap is the 3) formation will not occur then it can be air ingestion rate (in percent by volume) at the reasonably concluded that air ingestion pump inlet flange.will also not occur.Void <3% Flashing ACCEPTABLE Conventional calculation methodology indicates Fraction (Ref prevented Voids will not occur at the strainer that a void fraction of >0% will not occur at the USNRC down (calculation indicates <0%) based on strainer.GSI-191 stream of Sft thstanrKPS specified post-LOCA pressure and .Safety the strainer Evaluation temperature parameters. In addition, (SE)) the calculation also concludes that voids occurring in the strainer will have collapsed by the time the sump water leaves the strainer assembly and discharge piping, and before leaving the KPS containment sump.(K7~/Originated By: Date: 1/4///TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 19 of 32 1 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)F Pc I -Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 CONIRACIING INC i , Revision 6 9.0 References

9.1 Dominion

Energy Kewaunee, Inc., Kewaunee Power Station, Technical Specification for Containment Sump Strainers, No. K-4890, Revision 0 9.2 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCI-06-008, Replace Containment Recirculation Sump B Screens, dated 4/18/06 9.3 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCI-06-011, Replace Containment Recirculation Sump B Screens, dated 4/21/06.9.4 AREVA Engineering Information Record, Document Identification No. 66-9089247, Kewaunee Test Report for ECCS Strainer Performance Testing, Revision 0, September, 2008 9.5 U.S. Nuclear Regulatory Commission, Safety Evaluation, Pressurized Water Reactor Sump Performance Evaluation Methodology, Guidance Report of the Nuclear Energy Institute (NEI), GSI-191 SE, Revision 0, dated December 6, 2004 9.6 U.S. Nuclear Regulatory Commission, Regulatory Guide 1.82, Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident, Revision, 3, dated November 2003 9.7 U.S. Nuclear Regulatory Commission, GSI-191 SE, Attachment V-i, NUREG/CR-6224 Head Loss Temperature Assessment. Revision 0, December 2004 9.8 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCI-06-008, Replace Containment Recirculation Sump B Screens, dated 4/18/06.9.9 PCI Calculation TDI-6008-06, Total Head Loss (ECCS Recirculation, Strainer) -Kewaunee Power Station, Revision 8 9.10 PCI, Technical Document Number, TDI-6008-05, Clean Head Loss (ECCS Recirculation Strainer) -Kewaunee Power Station, Revision 4 Originated By: K~ " t 4 Date: /~TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 20 of 321 SPC!PERFORMANCL CONIRACTING INC Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 9.11 Urquhart, Leonard C., Civil Engineering Handbook, Fourth Edition, McGraw-Hill Book Company, Inc., 1959 9.12 DELETED -Not Used 9.13 Nazeer, Ahmed, Fluid Mechanics, Engineering Press, Inc., 1987 9.14 NEI 04-07, Pressurized Water Reactor Sump Performance Evaluation Methodology, Rev. 0, December, 2004 9.15 DELETED- Not Used 9.16 PCI, Technical Document Number, TDI-6008-02, SFS Surface Area, Flow and Volume Calculation, Revision 1 9.17 Dominion Energy Kewaunee, Inc., Kewaunee Power Information Transmittal (DIT), DIT No: PCl-06-015, Recirculation Strainer, dated 7/7/06 9.18 Dominion Energy Kewaunee, Inc., Kewaunee Power Information Transmittal (DIT), DIT No. PCl-06-016, Recirculation Strainer, dated 7/12/06 Station, Design Replace ECCS Station, Design Replace ECCS 9.19 PCI, Technical Document Number, TDI-6008-03, Core Tube Design-Kewaunee Power Station, Revision 2 9.20 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), GSI Chem-2008-04, Revision 2, Chemical Effects Testing, dated 7/16/08 9.21 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, Design Information Transmittal (DIT), DIT No. PCI-09-001, GSI-191 Resolution, dated 9/24/09 9.22 Dominion Energy Kewaunee, Inc., Kewaunee Power Station, EOP Setpoint Calculation Wide Range Containment Sump Level Versus Available RWST Volume, C10984, Revision 1, Addendum A 9.23 Westinghouse Electric Company, Evaluation of Post-Accident Chemical Effects in Containment Sump Fluids to Support GSI-191, WCAP-16530-NP, Revision 0, February 2006 (21/'1 Originated By: Date: TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 21 of 32 1 ,NPCI PERFORMANC[ CONIRACIING INC.Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 I 10.0 Drawings 10.1 SFS-KW-GA-01, Revision 3, Kewaunee Strainer, General Arrangement 10.2 SFS-KW-GA-02, Revision 6, Kewaunee Strainer, Strainer A 10.3 SFS-KW-GA-03, Revision 5, Kewaunee Strainer Sump Cover and Piping Layout 10.4 SFS-KW-PA-7100, Revision 5, Kewaunee Strainer Module Assembly 10.5 SFS-KW-PA-7103, Revision 4, Kewaunee Strainer, Maintenance Hatch 10.6 SFS-KW-PA-7161,' Revision 4, Kewaunee Strainer Pipe I 10.7 SFS-KW-PA-7162, Revision 3, Kewaunee Strainer Pipe 2 10.8 SFS-KW-PA-7163, Revision 3, Kewaunee Strainer Pipe 3 Originated By: TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Power Power Power Power Power Power Power Power Station, Station, Station, Station, Station, Station, Station, Station, Sure-FlowO Sure, Flow Sure FlowSure FlowSure-FlowO Sure FlowSure FlowSure FlowDate: / (/ " Page 22 of 32 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer),PcI -Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 CONIRACIIN(_ INC Revision 6 ATTACHMENT 1 -Flashing & Gas Evolution Analysis The application of either static water head and/or post-LOCA containment over-pressure for the Kewaunee Power Station (KPS) strainer will result in no flashing based on the very conservative use of the KPS strainer head loss associated with the 65 °F Design Basis temperature (i.e., post-LOCA long-term cooling). In addition the analysis of gas evolution downstream of the strainer indicates that it is significantly less than 0.5% which is also less than the allowable 3% value stated in RG 1.82, Revision 3.Flashing (boiling) of the post-LOCA containment fluid would occur if the post-LOCA containment pressure was reduced to a value below the corresponding fluid temperature (saturation temperature), or if the head loss associated with the strainer and debris bed is such that the post-LOCA containment fluid passing through the strainer and debris bed is reducedto a value below the corresponding fluid temperature (saturation temperature). The flashing post-LOCA containment fluid would release both condensable and non-condensable gases (gas evolution). If the gases are released in a manner such that they are 'captured' by the strainer discharge fluid flow, they would cumulatively result in potential voids (void fraction) that could be transported to the ECCS/CSS pumps.In order to address the associated but separate issues of flashing and gas evolution (de-aeration) in a logical and concise manner, the large break loss-of-coolant accident (i.e., LBLOCA) will be addressed to determine and address the issue of flashing including minimum margin to flashing at the strainer debris bed and within the KPS sump. In addition, an evaluation of gas evolution (de-aeration) downstream of the strainer (void fraction) that could reach the ECCS/CSS pump suctions is also provided.BACKGROUND Large Break Loss-of-Coolant Accident (LBLOCA)The maximum ECCS/CSS recirculation flow is based on the KPS Design Basis conditions of Case 1, 1,920 gpm at 214.7111 OF (i.e., initial post-LOCA ECCS/CSS recirculation), and Case 2, 1,920 gpm at 65 OF (i.e., long-term post-LOCA ECCS/CSS recirculation). Conservatively evaluating for a post-LOCA containment water level (i.e., minimum water level) at the initiation of ECCS/CSS recirculation for a LBLOCA equal to 2" strainer submergence (i.e., 39.25"), the water level is at Elevation 595.27' (i.e., 3.27'above KPS containment floor elevation of 592'-0"). The post-LOCA containment water level for long-term post-LOCA ECCS/CSS recirculation for a LBLOCA is Elevation 598.17' (i.e., 6.17' above KPS containment floor elevation of 592'-0") [Reference 9.21].Originated By: _K--Ihs" Date: A TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 23 of 321 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)VIA PC- Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 CON[IRACIIN(C INC I Revision 6 Elevation 598.17' results in 36.79" of strainer submergence during long-term recirculation. VOID FRACTION PCI Technical Documents No. TDI-6008-07, Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer) -Kewaunee Power Station provides the basis for addressing flashing across the strainer surface. The subject calculation provides the specific methodology, basis, and assumptions for evaluating KPS with regard to the subject issue. However, the subject document initially only addressed the KPS Design Basis case associated with a LBLOCA. Subsequently, the Staff has identified a number of other related issues associated with flashing (void fraction) including head loss at the strainer module debris bed and the evolution of gas (de-aeration) downstream of the strainer module that could reach the ECCS/CSS pump inlets.Therefore, the strainer head loss is evaluated for two (2) distinct LBLOCA scenarios (i.e., Case 1,920 gpm at 214.7111 OF, and Case 2, 1,920 gpm at 65 OF) based on two (2) distinct time periods (i.e., post-LOCA short-term and post-LOCA long-term). In addition, the related issues of flashing and the evolution of gas (de-aeration) downstream of the strainer module are also evaluated for KPS.LBLOCA Scenario The post-LOCA short-term is defined as the time period from LOCA initiation to the time when stable containment pressure, post-LOCA containment fluid temperature, and post-LOCA containment water level are achieved, which would occur in the first 24 hours following the initiation of the LOCA. During the initial period of the accident response, chemical precipitate debris and the associated effects on strainer head loss are not required to be considered in the determination of strainer head loss since chemical precipitate debris would not have begun to fully influence the strainer head loss for several more days. The post-LOCA long-term is defined as the post-LOCA containment conditions beyond the initial 24 hours through the end of the post-LOCA mission time (i.e., 30 days). The long-term post-LOCA period conservatively includes the maximum quantity of chemical precipitate debris and its effect on strainer head loss.In accordance with the guidance provided in USNRC Safety Guide 1.1 (Regulatory Guide 1.10), the post-LOCA containment initial conditions must be exactly the same as the pre-LOCA conditions for evaluating NPSH. In other words, immediately before the initiation of a LOCA, the pressure and temperature in the containment are at 'normal'operating conditions -usually atmospheric pressure :and the associated 'normal'operating temperature. Accordingly, it is very conservatively assumed that the containment post-LOCA fluid peak temperature is >212 OF and atmospheric pressure Originated By: ( /' Date: a TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 24 of 32 1 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)!PC I- Kewaunee Power Station PERFORMANCE Technical Document No. TDI-6008-07 CON IRACIINfG INC Revision 6 [was utilized to evaluate the KPS strainer for flashing (void fraction). Based on the stated assumptions, this would result in a very conservative analysis. It is also recognized that the application of post-LOCA containment 'over-pressure' (i.e., containment accident pressure) was limited to NPSH calculations as discussed in USNRC Safety Guide 1.1 (Regulatory Guide 1.10). It should be noted that KPS does not take 'credit' for post-LOCA containment 'over-pressure' in their NPSH calculations. The recent issues of strainer blockage and associated head loss (i.e., RG 1.82 Rev. 3, GSI-191, and GL-2004-02) at the time SG 1.1 was developed were never considered with regard to the application of the 'over-pressure' credit for addressing strainer head loss rather than NPSH. It should be noted that KPS does not take 'credit' for post-LOCA containment 'over-pressure' in their evaluation of GL 2004-02 issues.The USNRC safety evaluation report (SER) provided in Volume 2 of NEI 04-07 indicates that ECCS pumps can experience cavitation problems when inlet void fraction exceeds approximately 3%. Since it is very difficult (if not impossible) to calculate the actual percentage of flashing (void fraction) due to the many variables and dynamics of the post-LOCA strainer debris bed, PCI has chosen a solution that completely eliminates flashing (void fraction). There are two (2) possible methods to address flashing. The first is to assess the static, head of water based on the post-LOCA containment minimum water level. The static water head based on the height of the post-LOCA minimum containment water level to the centerline of the ECCS/CSS pump suction inlet must be determined. If the static water head height exceeds the calculated head loss across the strainer debris bed, then the static water head will have 'collapsed' any voids before they leave the containment (sump). In many cases this is the most straightforward and simple method of assessing flashing issues. However, if the static water head height does not exceed the calculated head loss across the strainer bed, then flashing is present. In this case, post-LOCA containment over-pressure credit is needed in order to eliminate the issue of flashing.The issues of USNRC Safety Guide 1.1 requirements and GSI-191 with regard to credit of post-LOCA containment over-pressure was recently addressed by the Advisory Committee on Reactor Safeguards (ACRS) Letter of March 18, 2009, titled, Crediting Containment Overpressure in Meeting the Net Positive Suction Head Required to Demonstrate that the Safety Systems Can Mitigate'the Accidents As Designed (Accession No: ML090700464). LBLOCA SCENARIO FOR FLASHING At the initiation of the LBLOCA (i.e., Case 1, 1,920 gpm at 214.7111 TF), the amount of post-LOCA debris transported to the strainer will be less than that for the long-term KPS Design Basis LBLOCA. Unqualified coatings and 'wash-down' debris may not have Originated By: _ 2/ Date: /A, 7 TDI-6008-07 Vortex. Air Ingestion & Void Fraction -Rev.6.doc Page 25 of 32 1 !PCI PERFORMANCE CONIRACIING INC.II Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 I reached the sump. Post-LOCA chemical particulate debris per the WCAP [Reference 9.23] will not begin to form until the post-LOCA water temperature is approximately 140 OF or less. Therefore, the initial post-LBLOCA debris head loss will be much less than the evaluated KPS Design Basis debris head loss.Utilizing the KPS Design Basis flow rate of 1,920 gpm for the LBLOCA, the CSHL and total strainer head loss (TSHL) based on the KPS strainer module arrangement were determined including uncertainty. Table Al-1 provides a summary of the estimated approximate head loss associated with the respective flow rates.Table Al-1 -KPS LBLOCA Scenario Head Loss LBLOCA Scenario CSHL, ft TSHL W/O TSHL, ft of of water Chemical Debris, water ft of water Case 1, 1,920 gpm at 214.7111 OF 0.344 0.4444 0.5528 Case 2, 1,920 gpm at 65 OF 0.365 0.7384 1.1034 NOTE: The CSHL, TSHL without chemical debris, and the TSHL were determined based on a combination of PCI KPS calculations and KPS ARL/AREVA Large Flume Test Results. For Case 2, PCI utilized the calculated values in TDI -6008-05 & -06. For Case 1, since the subject temperature was not a KPS Design Basis temperature, PCI utilized the same calculation methodology and philosophy found in TDI-6008-05 & -06 to determine the CSHL, TSHL without chemicals debris, and the TSHL for the KPS specified Case I temperature of 214.7111 'F.KPS is a Westinghouse 2 -loop NSSS based design. This design is unique because of the fact that before the Refueling Water Storage Tank (RWST) reaches its 'low' level alarm with respect to remaining volume, post-LOCA ECCS/CSS recirculation is initiated before the RWST is 'emptied'. In other words, ECCS/CSS recirculation is occurring at the same time that the RWST is being depleted by the ECCS/CSS injection process.Therefore, the KPS strainer experiences continuous rising post-LOCA containment water level following the initiation of ECCS/CSS recirculation until the RWST is depleted.A conservative timeline for the KPS post-LOCA events [Reference 9.18, 9.20, 9.21, and 9.22] is as follows: T + 0 min. LBLOCA occurs and RWST injection is initiated for ECCS/CSS Post-LOCA Containment Water Level: El. 592' (0.00')Sump Temperature: -120 OF T + 29 min ECCS/CSS recirculation is manually initiated, assuming 8 minutes operator response time Originated By: __ _ _,_ _ Date: /'I TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 26 of 32 1 SPCI PERFORMANCE CON IRACIING INC I Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 Post-LOCA Containment Water Level: El. 595.62 (+3.62' & rising)Sump Temperature: -212 OF -RWST injection ends; RWST at 4% level Post-LOCA Containment Water Level: El. 598.17 (+6.17' final)Sump Temperature: -206 °F T + 43 min.It has been determined that post-LOCA chemical precipitate debris does not begin to form until the post-LOCA containment fluid has dropped to 140 °F or lower in order to'support' formation of the precipitates. Therefore, the TSHL for temperatures greater than 140 °F should not include the head loss associated with chemical precipitate debris.Based on this scenario of minimal initial debris transport and chemical particulate debris generation, the KPS LBLOCA scenario can be evaluated by simply utilizing the first method of comparing the submerged strainer elevation static head of water (i.e., submergence depth) to the top of the strainer at the initiation of ECCS/CSS recirculation (i.e., 595.62' -595.10' = 0.52') and to the ECCS/CCS inlet pipe centerline elevation (i.e., 595.62'- 586.17" = 9.45'), which is 0.52 and 9.45 ft of water respectively based on the post-LOCA containment minimum water level to the calculated CSHL. However, the post-LOCA containment water level will continue to rise to a minimum high water elevation of 598.17'. Therefore, based on the final high water minimum level, the submerged strainer elevation static head of water (i.e., submergence depth) to the top of the strainer at the initiation of ECCS/CSS recirculation (i.e., 598.17' -595.10' = 3.07')and to the ECCS/CCS inlet pipe centerline elevation (i.e., 598.17'- 586.17" = 12.00'), is 3.07 and 12.00 ft of water respectively. Table A1-2 provides a summary comparison of the LBLOCA Strainer Submergence scenario for CSHL.Table A1-2 -KPS IBLOCA Strainer Submergence Scenario Head Loss Comparison for CSHL LBLOCA Scenario CSHL, ft of water Comparison, ft of water Case 1, 1,920 gpm at 214.7111 OF 0.344 0.52 > 0.344 Case 2, 1,920 gpm at 65 OF 0.365 3.07 > 0.365 I NOTE: For Case 2 at 65 F, the post-LOCA containment water level will be at the high water level of Elevation 598.17', or a strainer submergence level of 3.07'. 1 Date: ltX0 Originated By: f -TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 2'7 of 32 1 v PCI PERFORMANCE CONIRACIlNG INC I Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 Based on the results summarized in Table A1-2, there is sufficient strainer submergence to preclude flashing at the KPS strainer debris bed.Table A1-3 provides a summary comparison of the LBLOCA Strainer Submergence scenario for the TSHL without Chemical Debris Head Loss.Table A1-3 -KPS LBLOCA Strainer Submergence Scenario Head Loss Comparison for TSHL Without Chemical Debris Head Loss LBLOCA Scenario TSHL W/O Comparison, ft of Chemical Debris water HL, ft of water Case 1, 1,920 gpm at 214.7111 OF 0.4444 0.52 > 0.4444 Case 2, 1,920 gpm at 65 OF 0.7384 3.07 > 0.7384 NOTE: For Case 2 at 65 0 F, the post-LOCA containment water level will be at the high water level of Elevation 598.17', or a strainer submergence level of 3.07'.Based on the results summarized in Table A1-3, there is sufficient strainer submergence to preclude flashing at the KPS strainer debris bed.Table A1-4 provides a summary comparison of the LBLOCA Strainer Submergence scenario for the TSHL.Table A1-4 -KPS LBLOCA Strainer Submergence Scenario Head Loss Comparison for TSHL LBLOCA Scenario TSHL, ft of water Comparison, ft of water Case 1, 1,920 gpm at 214.7111 °F 0.4444 0.52 > 0.4444 Case 2, 1,920 gpm at 65 OF 1.1034 3.07 > 1.1034 NOTE: It should also be noted that the stated TSHL value for Case 1 of 0.4444 ft of head loss is realistic and conservative. It is based on the WCAP [Reference 9.23] that concluded thatzchemical precipitate debris will not form at temperatures greater than 140°F. Therefore, since the Case 1 temperature is 214.7111 OF, chemical precipitate debris will not form and is not considered as part of the TSHL. For Case 2 at 65 OF, the post-LOCA containment water level will be at the high water level of Elevation 598.17', or a strainer submergence level of 3.07'.61/ýZ7 /Originated By: Date: /11(1(2 TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 28 of 321 SPCI PERFORMANCE CONIRACIING INC.F -I Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 Tables A1-2, A1-3 and A1-4 have shown that flashing will not occur at the KPS strainer perforated plate and/or associated debris bed based on the various 'types' of head loss (i.e., CSHL, TSHL without Chemical Precipitate Debris, and TSHL). In the highly unlikely event that potential flashing does take place at the strainer discharge and/or within the associated KPS sump, and voids occur, Table A1-5 provides a summary comparison of the LBLOCA Strainer Submergence for all of the various 'types' of head loss related to the ECCS/CSS Inlet Pipe Submergence scenario.Table A1-5 -KPS LBLOCA ECCSICSS Inlet Pipe Submergence Scenario LBLOCA Scenario CSHL, ft TSHL W/O TSHL, ft Comparison, ft of of water Chemical of water water Debris, ft of water Case 1, 1,920 gpm at 0.344 0.4444 0.5528 12.00 > 0.5528 >214.7111 OF 0.4444 > 0.344 Case 2, 1,920 gpm at 0.365 0.7384 1.1034 12.00 > 1.1034 >65 OF 0.7384 > 0.365 Based on the results summarized in Table A1-5, there is sufficient ECCS/CSS inlet pipe submergence to preclude flashing voids from leaving the KPS sump.An additional evaluation regarding the second method assumed that the static water head height does not exceed the calculated head loss (i.e., across the strainer bed), and therefore flashing is present. It should be noted that for KPS, this is not the case.However, PCI evaluated this case for KPS regarding post-LOCA containment over-pressure credit in order to eliminate the issue of void fraction.The maximum LBLOCA scenario head loss for KPS based on the Beyond Design Basis Supplemental Design Basis is 3.2860 ft of water (- 1.425 psi) at 65 OF for KPS. The KPS maximum allowable head loss of 10.00' results in an equivalent head loss of approximately 4.335 psi at 65 OF for KPS.Accordingly, post-LOCA containment over-pressure of 1.425 psi or 4.335 psi at 65 OF would be required for KPS to prevent flashing at the, strainer debris bed for the calculated (i.e., 1.425 psi or 3.2860 ft of water) and Design Basis allowable maximum head loss (i.e., 4.335 psi or 10.00 ft of water), respectively.. Based on the KPS design basis and safety analysis report, there will always be more than adequate post-LOCA containment over-pressure to prevent flashing of the KPS strainer for the LBLOCA (1*1ýOriginated By: Date: / /TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 29 of 32 1 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)VA" PC I -Kewaunee Power Station PERFORMANCI Technical Document No. TDI-6008-07 ICONIRACTIN INC Revision 6 scenario. The report indicates that there will be post-LOCA containment over-pressure of 39.3989 psia at 214.7111 OF.In addition to the two (2) possible methods to address flashing at the KPS strainer debris bed for the Design Basis SBLOCA scenario, the static water head above the ECCS/CSS pump inlet lines within the sump always exceeds the 'worse-case' strainer total head loss, which is the LBLOCA Design Basis case. Accordingly, in both cases, any voids caused by flashing will have collapsed before they enter the ECCS/CSS pump inlet lines.STRAINER DOWNSTREAM GAS EVOLUTION EVALUATION In the PCI Technical Documents No. TDI-6008-06, Total Head Loss (ECCS Recirculation Strainer) -Kewaunee Power Station the KPS head loss values were determined for the two (2) KPS Design Basis,'conditions of Case 1, 1,920 gpm at 214.7111 OF, and for Case 2, 1,920 gpm at 65 °F as 1.263 and 2.37 ft of water, respectively. The vortex, air ingestion, and void fraction analysis concluded that void fraction occurring at the strainer debris bed due to head loss and the accompanying post-LOCA conditions would be reversed and any voids would have collapsed before the strainer discharge fluid left the containment sump and entered the ECCS/CSS inlet lines. The net void fraction (i.e., net air production) is therefore 0%. Therefore, void fraction is not an issue for any of the post-LOCA fluid associated pressure and temperature combinations associated with the subject fluid flow from the strainer to the ECCS/CSS inlet lines.It is recognized that a small amount of de-aeration will occur due to the difference in the solubility of air in water resulting from the pressure differential across the strainer and debris bed. A conservative assessment was made of the theoretical void fraction (air ingestion rate) which is expected to be minimal.The solubility of air in water is inversely proportional to the water temperature. In other words, the solubility is a maximum at the lowest water temperature of interest. In addition, the solubility is proportional to absolute pressure. The difference of solubility is 0.023 g Air / kg Water per one atmosphere. The KPS bounding differential pressure for the strainer is 10.00' (i.e., Design Basis Maximum Allowable Head Loss). Therefore, 10.00' = 3.048 m = 0.295 atm.Conservatively assuming that the water entering the strainer is fully saturated with air, the bounding difference of air solubility in water is as follows: 0.295 x 0.023 = 0.006785 g Air / kg Water Originated By: Date: I/Z/1 Zi TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 30 of 32 1 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station PERFORMANC[ Technical Document No. TDI-6008-07 (I(ONIRACIING INC Revision 6 The densities of air and water are: Air: 1.169 kg/M 3 at 250C and one atmosphere Water: 997 kg/m 3 at 25 0C The volume ratio of air and water therefore is: (0.000006785 kg Air/ kg Water) / 1.169 kg/M 3 x 997 kg/m 3.= 0.00579 or 0.579%The subject solubility value is at the top elevation of the strainer, actually at the water surface above the top of the strainer that is in contact with the containment post-LOCA atmosphere. At the ECCS/CSS pump suctions from the KPS sump pit, the strainer discharge water experiences a pressure increase again due to the static water head (i.e., the water column above the ECCS/CSS pump suctions inlets within the sump). The minimum LBLOCA post-LOCA containment water elevation for evaluating -2" strainer submergence is 595.27', but the minimum high water elevation is 598.17'. The ECCS/CSS pump suction inlets in the sump are located at centerline elevation 586.17'.This would theoretically result in an elevation difference of 9.1' or 12.00', respectively based on the post-LOCA containment water level evaluated. If the minimum post-LOCA water level of 595.27' is utilized, this results in a value, 9.1' of water which is less than the postulated strainer differential pressure of 10.00'. However, the ECCS/CSS pump inlets are located at elevation 569.396'. This would result in an elevation difference of 25.874', which is more than the postulated strainer differential pressure of 10.00'. In the case of the minimum high water elevation of 598.17', the postulated strainer differential pressure is less, 10.00' < 12.00'. Even though there would be no gas evolution for this case, evaluating the ECCS/CSS pump inlets located at elevation 569.396', results in 28.774'.It should be further noted that the aforementioned discussion was based on a water temperature of 25 0C which is 77 °F. The KPS Design Basis minimum post-LOCA water temperature is 65 OF which is slightly less. Accordingly, at the KPS Design Basis minimum temperature the solubility of air in water would be approximately 15% higher than the conservatively calculated value of 0.579%.Therefore any void fraction that could occur at the strainer debris bed is very minimal. If any should occur, it is reversed before the strainer discharge water leaves the sump due to the significant static head of water above the ECCS/CSS pump suction inlets within the sump. The net void fraction is therefore zero and is not a problem for any of Originated By: ___________ Date: /11 ,'/t TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 31 of 32 1 rPCI PERFORMANCE CONIRACIING INC I 1 Vortex, Air Ingestion & Void Fraction (ECCS Recirculation Strainer)-Kewaunee Power Station Technical Document No. TDI-6008-07 Revision 6 the KPS pressures and temperatures from the strainer to the ECCS/CSS pump suction inlets within the sump.Even though it has been shown that there will be zero void fraction associated with-the KPS strainer, the following assessment is provided to address potential void fraction from the sump outlet to the ECCS/CSS pump suction inlets. The assessment will utilize the same methodology utilized to assess void fraction within the sump by demonstrating that the elevation difference (i.e., static water head) between the sump outlet and the pump inlets is greater than the respective piping head losses.The minimum elevation difference between the sump outlet (elevation 586.17') and the pump inlet elevation 569.396' is 16.774'. This difference is significantlymore than the maximum allowable suction line head loss of 10.00' (which also includes the head loss due to the new strainer). Therefore, re-initiating void fraction downstream of the sump outlet is not possible. This analysis results in a void fraction of zero at the ECCS/CSS pump inlets.(:ý5/Date: Originated By: TDI-6008-07 Vortex, Air Ingestion & Void Fraction -Rev.6.doc Page 32 of 321 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-1 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER MODULE STRUCTURAL EVALUATION Page 1 of 8 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-1 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER MODULE STRUCTURAL EVALUATION tstfnr --T L lg~Ie'w-A K crss Figure 5.2-1 -Side view of Strainer Module Page 2 of 8 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-1 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER MODULE STRUCTURAL EVALUATION L2 Wend Figure 5.2-2 -Axial view of Strainer Module Page 3 of 8 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-1 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER MODULE STRUCTURAL EVALUATION y Figure 6.5-1 GTSTRUDL Model (Horizontal Solid Model)Page 4 of 8 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-1 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER MODULE STRUCTURAL EVALUATION RRcen hback 6.10-1 -End Cover Stiffener Configuration Page 5 of 8 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-1 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER MODULE STRUCTURAL EVALUATION-Vbolt.z ehkb1 ehkb.2-Figure 6.14-1 -Angle Iron Track Configuration for Mid Modules Lsprt 'bolt..y.DP Figure 6.14-3 -Angle Iron Track Configuration for the End Module Page 6 of 8 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-1 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER MODULE STRUCTURAL EVALUATION

7.0 RESULTS

AND CONCLUSIONS The results of this calculation indicate that the strainers meet the acceptance criteria for all applicable loadings. A summary of the maximum stress Interaction Ratios (calculated stress divided by allowable stress) is provided below.Strainer Component Ref. Section Interaction Ratio (OBE DB T External Radial Stiffener (Including Collars) 6.6 IRrad.stfnr = (0.80 0.67 T Tension Rods 6.6 IRrod = (0.96 0.68)Spacers 6.6 IRspacerT = (0.63 0.43)T Edge Channels 6.6 IRchan = (0.66 0.57)Seismic Stiffeners 6.6 IRseis.stfnr.HT = (0.76 0.T Maintenance Hatch Cover Plate 6.6 IRmh.cover.2 = (0.82 0.T 2-Disk Support Channels 6.6 IRsprt.2T = (0.22 0.15 )Core Tube (Biggest Holes) 6.6 IRtube T = (0.05 0.03)T Perforated Plate (DP Case) 6.8.1 IRface.dp = (0.64 0.54)T Perforated Plate (Seismic Case) 6.8.1 IRface.bp = (0.06 0.09)Perforated Plate (Edge Channels)

6.8.3 IRedgeT

= (0.10 0.09)T Perforated Plate (Inner Gap) 6.8.4 IRgap (0.10 0.14)Wire Stiffener

6.9 IRwire

= 0.59 T Perforated Plate (Core Tube End Cap DP Case) 6.10.1 IRfront.end = (0.29 0.25 T Perforated Plate (Core Tube End Cap Seismic Case) 6.10.1 lRback.end = (0.09 0.15 Radial Stiffening Spokes of the End Cover Stiffener 6.10.2 IRspoke = (0.71 0.62)End Cover 6.10.4 IR T (0n71 0a62)IE)58)55)i)r L Il[ -v ,* v Page 7 of 8 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-1 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER MODULE STRUCTURAL EVALUATION RESULTS AND CONCLUSIONS (Cont.)Strainer Component End Cover Welds Weld of Radial Stiffener to Core Tube Weld of Radial Stiffener to Seismic Stiffener Weld of hex coupling nut to M.H. cover plate Edge Channel Rivets Inner Gap Hoop Rivets End Cover Rivets Module-to-module Sleeve Module-to-module Latch Connection Mounting Pins Clevis Hitch Pins Angle Iron Tracks Expansion Anchors Alternate Angle Iron Welds Bolt connecting cover plate to support channels Lift Case Outage Case Ref. Section 6.11.1 6.11.2 6.11.3 6.11.4 6.12.1 6.12.2 6.12.3 6.13.1 6.13.2 6.14.1 6.14.1 6.14.2 6.14.3 6.14.4 6.14.5 6.15 6.16 Interaction Ratio T IRw.cover (0.69 0.48)T IRweld.ct (0.29 0.32)T IRweld.cb (0.89 0.61)T IRweld.hex = (0.32 0.16)T IRrv.face = (0.05 0.04)IRrv.gap 0.03)T IRrv.end (0.01 0.01)IRsleeveT (0.07 0.10)T IRlatch = (0.29 0.46)T IRboft = (0.91 0.66)T IRhitch = (0.21 0.26)IRangleT (0.76 0.61)T IRhkb = (0.39 0.90)T IRweld.alt = (0.43 0.32)T IRbolt.2 = (0.14 0.09)IRlift = 0.76 IRoutage = 0.77 Page 8 of 8 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-2 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER PIPING STRUCTURAL EVALUATION Page 1 of 6 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-2 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER PIPING STRUCTURAL EVALUATION Mo1 MODEL PLOT OF STRAINER PIPING 4 AM Page 2 of 6 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-2 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER PIPING STRUCTURAL EVALUATION Ly, C Figure 6.7.1 Three-way Restraint bpit Opit Figure 6.6.1 -Sump Pit Cover Details Page 3 of 6 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-2 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER PIPING STRUCTURAL EVALUATION bch Lch wL_Figure 6.6.2 -Sump Pit Layout 1/4" Inset Plate R = 9" IL , L I R = 13.5" R = 14.5" Figure 6.5.1 -Flange to Sump Cover Plate Page 4 of 6 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-2 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER PIPING STRUCTURAL EVALUATION

7.0 RESULTS

AND CONCLUSIONS A summary of the maximum calculated piping stresses is shown in Section 6.4. Calculated support component stresses are shown in Section 6.7. The interaction ratio for the pipe stresses, flanges, sump cover plate, and supports is shown below: Pipe Stresses IRpipe := max(IRnormal, IRupset, IRfaulted, IRthermal) IRpipe = 0.28 Stress Summary for other Components Component In-Line Flange Flange Bolting Flange Bending Flange Weld to Pipe Flange to Sump Cover Plate Flange Bending Flange Weld to Pipe Flange Plate Tabs Hold Down Bolts Sump Cover Plate Cover Plate Bending Weld Sump Cover Plate to Inset Plate Inset Plate Bending-Channel Bending Channel Bending Local Stress Ref. Section 6.5.1 6:5.1 6.5.1 6.5.2 6.5.2 6.5.2 6.5.2 6.6 6.6 6.6 6.6 6.6 Interaction Ratio IRbolt1 = 0.43 IRflangel = 0.46 IRwl = 0.19 IRflange.plate = 0.94 IRw2= 0.84 IRtabs = 0.38 IRtab.bolts = 0.30 IRpit.pi = 0.97 IRweld.sump = 0.22 IRinpl-= 0.19 IRch = 0.43 IRi= 0.09 Page 5 of 6 Serial No. 10-025 Docket No. 50-305 ENCLOSURE L-2 (RAI 37) PHOTOS AND EXCERPTS FROM STRAINER PIPING STRUCTURAL EVALUATION Component Pive Supports Ref. Section Interaction Ratio Angle Normal Stress Angle Shear Stress Expansion Anchors Baseplate Weld of Angle to Baseplate Saddle Plate Bending 6.7 6.7 6.7 6.7 6.7 6.7 6.7 6.7 6.7 6.7 6.8 0.66)IRangle-norm = I0.57 Rangle-sh 0.05)(0.05)IRbolt-supp = 0.7)(0.709'IRbpl ! C 0.90 IRweld (0.76)(0.376 lRspl-bd ý 0.31)(0.35 IRspi-sl = .0.975)(0.87pI IRwld'-spi = ,0.273)(0.257 IRpin ý 0.385)= (0.38)IRlugsj,0. 1 0)IRiwa = 0.46 Upset Emerg Saddle Plate Shear Saddle Plate Welds Saddle Plate Pins Shear Lugs Integral Welded Attachment The evaluation of the piping and piping supports associated with the suction strainers has shown that the pipe stresses and support loads are acceptable. The piping stresses, flanges, and support component stresses are within their respective applicable limits and are therefore acceptable. Page 6 of 6 Serial No. 10-025 Docket No. 50-305 ENCLOSURE M (RAI 40) REFUELING CAVITY DRAIN LOCATION Page 1 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE M (RAI 40) REFUELING CAVITY DRAIN LOCATION Reactor Coolant Pump Vault Limiting Hot Leg Break below the Steam Generator Refueling Cavity Drain in recessed area below refueling crane and below fuel transfer lifting frame Page 2 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE M (RAI 40) REFUELING CAVITY DRAIN LOCATION I IDrain is in lower cavity (not shown in this photo)Page 3 of 4 Serial No. 10-025 Docket No. 50-305 ENCLOSURE M (RAI 40) REFUELING CAVITY DRAIN LOCATION I Standpipe (not installed) /Page 4 of 4}}