Text

Draft Bypass Fiber Quantity Test Plan
	ML12331A175
Person / Time
Site:	Robinson
Issue date:	11/26/2012
From:	; ALION Science & Technology Corp
To:	; Enercon Services, Division of Operating Reactor Licensing
	Billoch, Araceli
References
	ALION-PLN-ENER-8707-02, Rev 0C
	Download: ML12331A175 (59)
	v • d • e

Form 3.3.1 Revision 2 Effective Date: 2/28/07 TECHNICAL DOCUMENT COVER PAGE Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page 1 of 22 Document

Title:

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Project No: 261-8707 Project Name: H. B. Robinson Plant Top Hat Strainer Bypass Testing Client: ENERCON Document Purpose/Summary:

This document presents the Alion Test Plan for the H. B. Robinson Plant Top Hat Strainer Bypass Testing measurement. All design inputs are based on the Enercon Design Input Letter [Ref. 10].

This test plan is prepared Safety-related in accordance with the Alion Science and Technology Innovative Technology Solutions Operation Nuclear Quality Assurance Program.

Total Page Count: 59 pages Design Verification Method:

X Design Review Alternative Calculation Qualification Testing Professional Engineer (if required) Approval:

Date Prepared By:

Matthew G. Jursich Printed/Typed Name Signature Date Reviewed By:

David Jurjevich Jeff Poska Printed/Typed Name Signature Date Approved By:

Megan Stachowiak Printed/Typed Name Signature Date

REVISION HISTORY LOG Form 6.1.3 Revision 1 Effective Date: 2/28/07 Page _2__ of _22_

Document Number: ALION-PLN-ENER-8707-02 Revision:

0C Document

Title:

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Instructions:

Project Manager is to provide a brief description of each document revision including rationale for the change and, if applicable, identification of source documents used for the change.

REVISION DATE Description 0A 9/28/2012 DRAFT Issue 0B 10/15/2012 Incorporated client comments in Sections1, 2, 2.2, 3.1, 3.4, 3.5, 4.1, 4.4, 4.5, 4.6.1, 4.6.2, 4.6.3, 4.7, 4.10, 5, 7.2, 11, 12 and Appendix 1 and Attachment A.

0C DRAFT Added DRAFT watermark. Incorporated client comments in Sections 2.0, 3.4, 4.2, 4.4, 4.6.1, 4.6.3, 5.0, 8.1.

Note - This test plan was marked up by H.B. Robinson to reflect an initial test approach velocity of 1.5X design (0.003 ft/s). A revision is planned to incorporate the approach velocity and to add measurement of bypass following stopping and restarting the test pump.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 3 of 22 TABLE OF CONTENTS 1.0 Background........................................................................................................................................................... 6 2.0 Test Objectives................................................................................................................................................... 6 2.1 Strainer Design............................................................................................................................................... 6 2.2 Fiber Bypass Testing...................................................................................................................................... 8 3.0 Technical Approach........................................................................................................................................... 8 3.1 Overview of Testing Strategy..................................................................................................................... 8 3.2 Debris Load Definition................................................................................................................................. 8 3.3 Scaling of Debris Quantities for Testing.................................................................................................. 8 3.4 Filter Bags........................................................................................................................................................ 8 3.5 Assumptions.................................................................................................................................................... 9 4.0 Test Description................................................................................................................................................. 9 4.1 Scaling and Selection of Prototype.......................................................................................................... 10 4.2 Debris and Flow Scaling............................................................................................................................. 10 4.3 Fiber Debris Size Distribution.................................................................................................................. 11 4.4 Debris Preparation-Fiber.......................................................................................................................... 11 4.5 Debris Introduction.................................................................................................................................... 12 4.6 Hydraulic Test Conditions........................................................................................................................ 12 4.6.1 Strainer Approach Velocity.................................................................................................................. 12 4.6.2 Water Temperature and Chemistry.................................................................................................. 12 4.6.3 Water Level............................................................................................................................................. 12 4.6.4 pH............................................................................................................................................................... 12 4.6.5 Turbidity................................................................................................................................................... 13 4.7 Debris Type.................................................................................................................................................. 13 4.8 Test Control................................................................................................................................................. 14 4.9 Preparation.................................................................................................................................................... 14 4.10 Debris Addition............................................................................................................................................ 15 5.0 Test Matrix......................................................................................................................................................... 15 6.0 Test Procedures................................................................................................................................................ 16 7.0 Test Equipment and Specifications............................................................................................................... 17 7.1 Equipment Specifications............................................................................................................................ 17 7.2 Test Equipment and Accuracy.................................................................................................................. 17 8.0 Test Acceptance Criteria................................................................................................................................ 18 8.1 Fiber Bypass.................................................................................................................................................. 18 8.2 Head Loss...................................................................................................................................................... 18 8.3 Testing Stabilization Criteria..................................................................................................................... 19 8.3.1 Step Stabilization Criteria..................................................................................................................... 19 8.3.2 Final Stabilization Criteria..................................................................................................................... 19 8.4 Test Termination......................................................................................................................................... 20 9.0 Test Documentation and Records............................................................................................................... 20 10.0 Debris Handling Requirements..................................................................................................................... 20 11.0 Quality Assurance Requirements................................................................................................................. 21 12.0 References.......................................................................................................................................................... 22

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 4 of 22 LIST OF FIGURES Figure 2-1: Strainer and Test Tank Layout.................................................................................................................. 7 Figure 2-2: Arrangement of the 1 X 4 Array in the Test Tank.............................................................................. 7 Figure 4-1: Alion Hydraulic Test Tank Diagram....................................................................................................... 10 LIST OF TABLES Table 4 Fibrous Material Comparison................................................................................................................. 14 Table 5 Bypass Test Matrix.................................................................................................................................... 16 LIST OF APPENDICES Appendix 1 - Calculation of Testing Parameters........................................................................................ (5 pages)

LIST OF ATTACHMENTS Attachment A - Design Input Letter.............................................................................................................. (9 pages)

Attachment B - Table 3-2 of NUREG/CR-6808............................................................................................ (1 page)

Attachment C - Vortex Strength Scale............................................................................................................ (1 page)

Attachment D - Material Safety and Data Sheets.....................................................................................(21 pages)

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 5 of 22 ACRONYMS AND DEFINITIONS inches (length)

°C Degrees Celsius

°F Degrees Fahrenheit Alion Alion Science and Technology CFR Code of Federal Regulations cm centimeter D

Diameter dp differential pressure ECCS Emergency Core Cooling System FE Flow Element GL Generic Letter gpm gallons per minute (flow)

GSI Generic Safety Issue ft Feet (of water)

HDFG High Density Fiberglass in inch ITSO Innovative Technology Solutions Operation kg Kilogram LDFG Low Density Fiberglass lb Pound LOCA Loss of Coolant Accident MSDS Material Safety Data Sheet NI National Instruments PCI Performance Contracting, Inc.

PWR Pressurized Water Reactor QA Quality Assurance RNPP Robinson Nuclear Power Plant S or sec second TB Turbidity USNRC/NRC United States Nuclear Regulatory Commission

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 6 of 22

1.0 BACKGROUND

The design of the Emergency Core Cooling System (ECCS) at the Robinson Nuclear Power Plant provides a suction source for the ECCS pumps, allowing the ECCS to operate in a containment recirculation mode. If a Loss-of-Coolant-Accident (LOCA) inside containment were to occur, it could generate debris that, if transported to and deposited on the containment sump screens, could pass through the screens and affect downstream components and/or the ability to maintain long term core cooling.

The United States Nuclear Regulatory Commission (NRC) Staff has identified Generic Safety Issue (GSI)

-191, "Assessment of Debris Accumulation on PWR Sump Performance." To this end, on September 13, 2004, the NRC issued Generic Letter (GL) 2004-02 to Pressurized Water Reactor (PWR) Owners for action to ensure that LOCA-generated debris does not degrade ECCS performance.

2.0 TEST OBJECTIVES The objective of this test program is to measure the mass of the fibrous debris that passes through the screen perforated area using:

Prototype strainer hydraulic tank testing 5-micron nominal inline filters to capture bypassed fiber and subsequently take the difference of pre and post-test weights Incremental fiber loading to ensure conservative measurement of fiber bypass 2.1 Strainer Design A double ring top-hat array with debris bypass eliminators will be installed in the Alion test tank. The strainer layout utilized for testing will be a top hat array with four top hats installed horizontally, see Figure 2-1 and Figure 2-2. Debris bypass eliminators, commonly referred to as mesh, will be installed in both the inner and outer annuluses of all four Top-Hats in the prototype test array.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 7 of 22 Figure 2-1: Strainer and Test Tank Layout Figure 2-2: Arrangement of the 1 X 4 Array in the Test Tank

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 8 of 22 2.2 Fiber Bypass Testing Alion will perform a fiber bypass test on a prototypical section of the sump strainer that is comprised of four Top Hats to measure the maximum fiber bypass quantity. The testing will be performed in the Alion Test tank located in Warrenville, Illinois.

3.0 TECHNICAL APPROACH The discussion of technical approach implemented in this plan includes the following:

an overview of testing strategy debris load definition scaling of plant quantities for testing filter bags assumptions 3.1 Overview of Testing Strategy The technical approach implemented in this test plan is to measure the bypassed fiber quantity for a prototypical ECCS strainer using test conditions that conservatively maximize fiber bypass. Alion will perform bypass testing for Enercon in accordance with the requirements of the project plan [Ref. 14].

A representative approach velocity will be passed through a prototypical strainer. Incremental fiber additions simulate the worst-case scenario for fiber bypass by minimizing the concentration, which prevents early bed formation. Bypassed fiber will be captured using downstream 5-micron filter bags via a 100% pass through alignment in the flow stream, so that bypassed fiber can be captured and measured.

See Section 3.4 for filter bag preparation, processing and measuring. The test report will show the measured bypassed fiber quantities per addition and the total quantity of bypassed fiber.

3.2 Debris Load Definition Debris load definition is provided by the Enercon Design Input Letter which identifies the fibrous debris source terms for the current plant configuration. The current debris types are NUKON, Temp-Mat, Kaowool, Unibestos, and other fiberglass (LDFG) [Ref. 10]. The debris source terms are scaled for the test article in Appendix 1. NUKON will be the surrogate utilized during testing to represent the different fibrous types (see Section 4.7). NUKON fines and smalls will be created according to the current revision of the NEI ZOI Fibrous Debris Preparation [Ref. 12].

3.3 Scaling of Debris Quantities for Testing Scaling of debris quantities is detailed in Appendix 1.

3.4 Filter Bags The filter bags used for this test will be 5-micron mesh size, which will capture bypassed NUKON particles/fibers, which typically have a diameter of 7-micron and are expected to have a much longer

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 9 of 22 characteristic length, thereby facilitating high capture efficiencies. Before use and in accordance with ALION-SPP-LAB-2352-70 [Ref. 3], the filters will be prewashed to remove any loose material. The filters will be dried and weighed before and after testing to calculate the amount of NUKON that was captured in the filter bags during the test. Alion lab procedure ALION-SPP-LAB-2352-70, "Filter Bag Preparation and Processing Procedure, will be the procedure utilized to measure the collected NUKON.

At least 13 filter bags will be prepared before each test. During testing one filter bag will be set up to capture NUKON, another used as a control, and the remaining filter bags will be switched out one at a time for each fiber addition. Also, filter bags may be replaced as required to maintain acceptable filter bag differential pressure. Filter bags will be dried with set drying times until the difference in weight change between drying sessions is minimal. The test procedures will specify drying time intervals and the weight change differential. Additionally, the filter bags will be stored for future analysis, if required.

Prior to testing, another set of cleaning filter bags shall be used to completely filter out any latent debris that would affect the post-test mass of the testing filter bags.

3.5 Assumptions The following assumptions are made:

Ten percent of the total volume of Unibestos will be in fibrous form. Unibestos is the trade name for a calcium-silicate material containing asbestos fibers [Ref. 8]. Alion experiences with various calcium-silicate materials have shown that they contain a 0-4% fibrous component [Ref.

15]. Therefore, it is conservative to assume 10% of the total volume of Unibestos will be in fibrous form.

The effective surface area of the strainer is 4178 ft2 [Ref. 10]. However, testing will be performed using a scaling ratio based on a 4000 ft2 strainer. This incorporates margin into the results for tag/label sacrificial area or in case it becomes necessary to remove Top Hat strainer modules in the future.

The fiber from each addition collects on the screen and does not remain suspended in the tank volume.

4.0 TEST DESCRIPTION The test will be performed at the Alion Hydraulics Laboratory located in Warrenville, IL. A diagram of a typical test tank instrumentation setup is illustrated in Figure 4-1.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 10 of 22 Figure 4-1: Alion Hydraulic Test Tank Diagram 4.1 Scaling and Selection of Prototype A prototype section of the strainer will be tested in the tank. This assures a 1 to 1 scaling ratio for dimensions and perforated plate hole size including gaps installed at the base of Top Hats at the plenum.

The height of the gap between the plenum and Top Hat will be 1/16 inch (+1/32, -0). The total length of the gap between the Top Hats and the plenum will be 8 9-3/8 (+/- 1/16). Additionally, there are 1/2 gaps in the two cover plates on the transition plenum. The two cover plates will be separated by 1/16 (+1/32, -0) and the length of the gaps will be 5 9-1/4 (+/- 1/16). The effective surface area of the plant strainer and the test module (four Top Hats) are 4178 ft2 and 121.24 ft2, respectively [Ref. 10].

Testing will be performed using a ratio based on a 4000 ft2 strainer. This incorporates margin into the results for tag/label sacrificial area or in case it becomes necessary to remove top hats in the future. The other test parameters are scaled and are included in Appendix 1.

4.2 Debris and Flow Scaling All testing parameters will be based on the project inputs outlined in the Design Input Letter [Ref. 10].

These parameters will be scaled based on the ratio of testing strainer area to plant net effective area.

This scaling factor and its use in determining test parameters are shown in Appendix 1.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 11 of 22 4.3 Fiber Debris Size Distribution Fibrous debris size distributions are developed for the following debris types:

NUKON Temp-Mat Kaowool LDFG Unibestos The fiber debris size distribution given in the design input letter [Ref.10] for the above debris types classifies the fibrous debris as small fines. For the tests outlined in this document, two fibrous debris classifications will be used, fines characterized as Classes 1-3 in NUREG/CR-6224 [Ref.11] and smalls characterized as Classes 4-6 in NUREG/CR-6224. Classes 1-3 fines will be used to represent the latent debris source term for all tests.

The small fines characterized in the design input letter [Ref. 10] are broken into 17% fines and 38%

smalls for destroyed NUKON and Temp-Mat insulation and 22% fines and 63% smalls for Kaowool, Unibestos and fiberglass debris.

Unibestos - Unibestos is the trade name for a calcium-silicate material containing asbestos fibers [Ref.

8]. NUKON fines will be the surrogate used to represent the fibrous portion of the Unibestos material.

Alion experiences with various calcium-silicate materials have shown that they contain a 0-4% fibrous component [Ref. 15]. Therefore, it is conservative to assume 10% of the total volume of Unibestos will be in fibrous form.

4.4 Debris Preparation-Fiber Debris will be prepared according to the NEI ZOI Fibrous Debris Preparation procedure [Ref. 12]. This procedure produces the required size distribution of fiber fines and smalls that are easily transportable and readily disperse in the testing medium. Fines are defined in the NEI procedure document [Ref. 12]

as readily suspendable in water and are Classes 1 through 3 while smalls are class 4 and 5 of Table 3-2 of NUREG/CR-6808 [Ref. 13]. Table 3-2 is in Attachment B. All fiber will be Performance Contracting, Inc.

(PCI) NUKON single side baked between 6 and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Fibrous fines will be cut, weighed out and separated using a commercially available pressure washer, and then verified to meet the correct classification of fiber sizes. Fiber fines are then combined to maintain a fiber mass to volume ratio less than or equal to 0.21 lbs/gal. Fibrous smalls will be cut for the appropriate mass for each specific addition, soaked in water and stirred with a hand paddle until the pieces are fully saturated and separated from each other. Samples of fiber smalls and fines will be examined and photographed using a

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 12 of 22 light-board, or equivalent device, to ensure fiber preparation is consistent with the guidance provided in Reference 12.

4.5 Debris Introduction Debris will be introduced into the tank in areas of high velocities near the pump return line. This will allow the flow within the tank to carry the debris to the Top Hats. Adjustable tank internal mixing will be added to areas of low velocities. Batches of fiber will be added in increments that ensure the concentration in the test tank is less than or equal to the plants concentration. The plant concentration is calculated in Appendix 1.

Fiber additions are included in the test matrix in Section 5.0.

4.6 Hydraulic Test Conditions 4.6.1 Strainer Approach Velocity Plant and prototype strainer surface areas for which the approach velocity is used to calculate the testing flow rates are given in the design input letter [Ref. 10] and are specified Appendix 1. The approach velocity at the start of the test is 0.004 ft/s. After full screen coverage is achieved, the flow will be reduced to the normalized approach velocity of 0.00213 ft/s based off the ECCS flow rate of 3820 gpm (see Appendix 1) [Ref. 10]. Screen coverage must be determined through visual, tactile, or other means that do not disrupt the debris bed. The equivalent flow rates for the approach velocities are 218 gpm and 116 gpm, respectively.

4.6.2 Water Temperature and Chemistry The water temperature will be maintained above 60 °F during the course of the test. Temperature shall not exceed the maximum limit of 110 °F. Deionized/demineralized water will be used and the chemistry will not be monitored or controlled during this test other than initially verifying the use of deionized/demineralized water.

4.6.3 Water Level The pool water level for the bypass test will be initially set at 36 inches. If vortexing occurs, a vortex suppressor will be installed or the water level will be increased. Any required actions will be recorded in the test logs. The water level will be recorded during testing and increase with each debris addition.

Test tank water may be removed to mix the next debris addition and re-introduced into the test tank.

Test tank water may be discarded after visually verifying there is an insignificant quantity of fiber within the water to ensure there is room for further debris additions.

4.6.4 pH pH will not be monitored or controlled during this test.

0.003 164

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 13 of 22 4.6.5 Turbidity The tank liquid may be sampled for turbidity when determined by the test engineer. Turbidity measurements will be recorded for informational purposes only.

4.7 Debris Type A description of each of the debris materials and surrogates used for testing follows:

NUKON - The low density fiberglass insulation quantities that transport to the strainer will be accurately represented by NUKON. NUKON, provided by PCI, is specified as the plant fibrous insulation. The as-fabricated density of NUKON is 2.4 lb/ft3 and the fiber diameter is 7 microns

[Ref. 8]. Attachment D contains Material Safety Data Sheet (MSDS) information.

Temp-Mat - Temp-Mat is a woven fiberglass fabric with a fiber diameter of 9 microns. The as-fabricated density of Temp-Mat is 11.8 lb/ft3 [Ref. 8]. NUKON will be used as a surrogate for Temp-Mat throughout testing. The use of NUKON, a LDFG, as a surrogate is conservative due to the smaller fiber diameter and characteristic length. Additionally, previous Alion testing has shown that smaller diameter fibers with shorter characteristic lengths consistently causes higher bypass. Attachment D contains Material Safety Data Sheet (MSDS) information.

When determining the volume of the scaled NUKON debris load from the mass calculated in Appendix I to be used in the tests, the density of NUKON (2.4 lb/ft3) will be used. This results in a larger apparent scaled volume of fiber to be used for testing. This alternate, lower density is chosen due to Alions previous testing observations regarding the destroyed density of Temp-Mat. The 2.4 lb/ft3 density more accurately represents destroyed Temp-Mats volume. This density is then used to calculate an equivalent bed thickness for a determined volume of fiber.

Equivalent bed thickness is the only use of the scaled debris volume in testing.

Unibestos - Unibestos is the trade name for a calcium-silicate material containing asbestos fibers

[Ref. 8]. NUKON fines will be the surrogate used to represent the fibrous portion of the Unibestos material. Alion experiences with various calcium-silicate materials have shown that they contain a 0-4% fibrous component [Ref. 15]. These fibers have comparable characteristics to both NUKON and Temp-Mat that can be seen in the table below [Ref. 8].

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 14 of 22 Table 4 Fibrous Material Comparison NUKON Temp-Mat Asbestos Fibers Destruction Pressure (psi) 10*

17 10 Characteristic length (um) 7 9

1-8 Material Density (lb/ft3) 2.4 11.8 7-10

Destruction pressure for Unjacketed NUKON 4.8 Test Control All testing actions and control must be noted in the test log. This includes flow adjustments, debris addition (beginning and completion), stirring (including the duration of the stir), and all other acts that affect the testing environment. The test logs shall be able to describe everything about the test without recourse to the test engineer.

The flow rate of the system should be maintained at - 10 gpm, +20 gpm of the prescribed value.

Stabilization criteria for each subtest are given in Section 8.0.

4.9 Preparation The test tank must be arranged and equipped as per the following (see Figure 2-1):

A sparger system will be installed on the return line to aid in the suspension of the debris within the water. Mechanical mixers may be utilized in low velocity areas to ensure settled debris becomes re-suspended. Hydraulic shakedown testing can be conducted to ensure that the return flow will create adequate turbulence to suspend the test debris.

The differential pressure tubing, both the High and Low lines must be securely fastened inside the tank to prevent vibrations that cause noisy signals. Furthermore, the Low side must be securely fastened to the plenum to prevent ambient leakage.

The National Instruments LabVIEW' data acquisition program must be programmed to match the test parameters, such as screen area and correct orifice plate conversion (see Section 7.0). Imperial units will be displayed and recorded in the test logs and data during testing.

The debris batches of Section 5 must be prepared according to the test matrix and the latest NEI debris preparation procedure [Ref. 12]. The debris preparation documentation from Reference 3 will be included with the execution of this Test Plan.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 15 of 22 4.10 Debris Addition All debris will be added in two places directly over the sparger system, which will allow the flow within the tank to carry debris to the Top Hat.. This will allow for equal debris bed growth on the top hats.

The debris must be added in a controlled manner as to not disturb the debris bed through unnecessary turbulence.

Also, visual observations shall be made to ensure that a vortex does not form during the testing. If a vortex does form, water shall be added to the tank to raise the water level until no vortices are observed or a vortex suppressor may be installed.

5.0 TEST MATRIX To maintain the correct debris concentration below that of the plant and to maintain the correct fiber mass to volume ratio given in the NEI debris preparation procedure [Ref. 12], the volume of water per addition is specified. The six gallons of water added to the test tank per stage will satisfy both criteria above while maintaining practical testing actions during testing. It is worth noting that the last addition for each addition will have a different concentration because the addition represents the remaining amount of scaled test fiber for that size classification. See Section 4.6.1 regarding which flow rate will be used during testing.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 16 of 22 Table 5 Bypass Test Matrix Stage Flow Rate (GPM)

NUKON Fines (lbs)

NUKON Smalls (lbs)

Tank Volume (gal)

Tank Level (in)

Nominal Bed Thickness (in)

Concentration (ft3/gal) lbs/gallon Added (NEI Criterion)

Gallons Added F.1 218/116 1.22 0

1500 36.00 0.050 0.00034 0.20 6

F.2 218/116 1.23 0

1506 36.16 0.101 0.00034 0.20 6

F.3 218/116 1.23 0

1512 36.32 0.152 0.00034 0.21 6

F.4 218/116 1.24 0

1518 36.48 0.203 0.00034 0.21 6

F.5 218/116 0.72 0

1518 36.48 0.233 0.00020 0.12 6

S.1 218/116 0

1.24 1524 36.64 0.284 0.00034 0.21 6

S.2 218/116 0

1.25 1530 36.80 0.336 0.00034 0.21 6

S.3 218/116 0

1.25 1536 36.96 0.387 0.00034 0.21 6

S.4 218/116 0

1.26 1542 37.12 0.439 0.00034 0.21 6

S.5 218/116 0

1.26 1548 37.28 0.491 0.00034 0.21 6

S.6 218/116 0

1.27 1554 37.44 0.544 0.00034 0.21 6

S.7 218/116 0

0.92 1554 37.44 0.582 0.00025 0.15 6

6.0 TEST PROCEDURES The Alion Test Program has developed generic test procedures for debris preparation, fill and start-up testing, and head loss testing. These generic test procedures are applicable, and the current revisions at the time of testing will be used to perform the testing specified in this test plan. Generic test procedures are listed in References 2 through 7.

The Test Lab Safety Procedure, ALION-SPP-LAB-2352-21 [Ref. 7] shall be followed at all times.

The general sequence of the test is as follows:

1. Prepare test filter bags in accordance with procedure ALION-SPP-LAB-2352-70 [Ref. 3].

2. Verify the tank has been cleaned in accordance with ALION-SPP-LAB-2352-45 [Ref. 4] and filled according to ALION-SPP-LAB-2352-44 [Ref. 5].

3. Verify the tank is setup correctly and dimensional variations from the general layout included in Figure 2-1 and Figure 4-1 are approved by the Project Manager and/or Test Coordinator.

4. Debris shall be prepared in accordance with the latest NEI debris preparation Procedure [Ref.

12].

5. Photographs of typical samples of prepared debris will be taken.

164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 17 of 22

6. For cleaning purposes, filter bags shall be used to filter water in the tank for at least 5 turnovers prior to adding any debris at a cleaning flow rate greater than the test flow rate to ensure that no residual debris interferes with the measured bypass quantities.

7. Strainer bypass testing will be performed in accordance with test specific procedures and the Test Matrix described in Section 5 of this Test Plan.

8. Photographs of the debris bed and any non-attached settled debris must be taken when visibility permits.

9. At the conclusion of testing, process test filter bags in accordance with ALION-SPP-LAB-2352-70 [Ref. 3].

10. Drain and clean the Test Tank in accordance with Test Tank Draining and Cleaning Procedure, ALION-SPP-LAB-2352-45 [Ref. 4].

7.0 TEST EQUIPMENT AND SPECIFICATIONS This section details the test specification requirements in which the test instrumentation must conform.

In addition, the test equipment used and the accuracy of each instrument are discussed.

7.1 Equipment Specifications The equipment employed during testing and their associated accuracies are given in Section 7.2. The data acquisition system is used to collect flow rate, differential pressure, and temperature data throughout the performance of the test. This system also allows for the creation of graphs of the data as well as tables of the raw data.

Due to instrument noise and combined instrument uncertainties, the data that is displayed via LabVIEW' (version controlled by [Ref. 1] and verification controlled by [Ref. 2]) is a floating-average, averaged over the previous 10 data points, with each data point recorded every 2 seconds. This averaging may lead to small discrepancies in instrument readouts. In such a case, the most conservative measurement for any given instrument will be recorded in the test logs. For instance, the lowest flow rate, highest differential pressure, and highest temperature shall be recorded in the test logs.

7.2 Test Equipment and Accuracy The details of the equipment used and the calibration of the following instruments in this testing are identified and controlled in the Test Program Description, ALION-PLN-LAB-2352-003, Hydraulic Testing of Debris Program

Description:

Test Tank [Ref. 1] and Alion Test Equipment Verification Procedure [Ref. 2]. Note that tape measures are commercial instruments and are excluded from the Alion QA Program. The following is a summary of the equipment used in this testing:

Scales and Balances, as needed (balances verified prior to use) o 0 to 150 lbs range, +/- (1% of reading + 0.1 lbs) o 0 to 610 grams range, +/- 0.02 grams

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 18 of 22 o 0 to 6 kilograms range, +/- 0.002 kilograms o 0 to 10 kilograms range, +/- 0.006 kilograms Pressure transmitters, as needed o 0 to 100 inches of water range, +/- 0.17% accuracy of upper range o 0 to 250 inches of water range, +/- 0.17% accuracy of upper range o 0 to 300 inches of water range, +/- 0.25% accuracy of upper range o 0 to 25 psi range, +/- 0.25% accuracy of upper range o 0 to 50 psi range, +/- 0.25% accuracy of upper range Flow orifice o 70 gpm to 900 gpm, +/- 0.25 % of measured velocity Thermocouples o 32 °F to 1652 °F range, +/- 3 °F, LabVIEW' verified to +/-5%

Temperature probe o -40 °F to 1999 °F range, +/- (0.1% reading + 2 °F) o -50 to 300 °C range, +/- 1 °C NI LabVIEW' data acquisition system, (version controlled by [Ref. 1])

o Real-time analog data acquisition system, allowing continuous display of test parameter values and trends. Data is sampled every two seconds, and averaged over the previous 10 data points. Test data is recorded for each instrument in a simple spreadsheet for later analysis.

5-micron nominal filter bags Digital Caliper o 0 to 6 inches, +/- 0.001 inches Commercially Available Tape Measure o 0-25, 1/16th inch divisions o 0-12, 1/32th inch division up to one foot, 1/16th inch division after one foot 8.0 TEST ACCEPTANCE CRITERIA In accordance with the test objective, the acceptance criterion for this testing is to conduct the fiber bypass test in accordance with applicable test procedures outlined in this document and to successfully collect and record data. The duration of the test shall be no shorter than 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months .

8.1 Fiber Bypass Fiber that bypasses the test strainer will be collected continuously throughout the test, examined and quantified at the conclusion of testing.

8.2 Head Loss Head loss measurements will be recorded continuously throughout the test and are used to determine the stability of the debris bed before ending the test.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 19 of 22 To prevent structural failure to the prototype or tank system, a head loss limit of 15 ft-water will be imposed during testing. Above this head loss, the Test Module, tank pump, and other components may become susceptible to fatigue or failure; therefore, the head loss across the debris bed should not exceed this value. If the head loss approaches this value, the flow rate of the system will be reduced to maintain a value slightly less than the limit.

8.3 Testing Stabilization Criteria The head loss measurements for this test will be continuously recorded by the data acquisition system.

The test will be monitored by lab personnel and measurements will additionally be recorded manually throughout the test. There are multiple stabilization points throughout the test, each with a particular level of required stability. The criteria are listed in the following sections. Note that pool turnover times are based on water level and flow rate, and must be calculated separately for each addition.

8.3.1 Step Stabilization Criteria At least 5 pool turnovers must occur after the end of the debris addition and before the beginning of the next debris addition.

At the completion of each fiber addition step in the test matrix, settled debris shall be agitated manually with the intent to ensure that debris reaches the strainer module and that no significant quantities of debris are allowed to settle elsewhere in the tank environs. However, manual agitation shall continue only until further manual stirring has no noticeable effect on the system head loss or the amount of settled debris. Agitation may be provided through use of a wooden oar or through temporary adjustment of the mechanical mixers. Supplemental agitation shall be conducted carefully to avoid disturbing the debris bed on the strainer module.

8.3.2 Final Stabilization Criteria Manual agitation of settled debris will be done to ensure all debris reaches the strainer. Additionally, head loss stabilization may be required by the test coordinator. The test can be considered complete after the following criteria are satisfied:

The bypass test has to have run for at least 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months .

A minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months have elapsed since the last debris batch was added to the tank.

During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of the 4-hour hold, the filter bags must be switched out every 30 minutes (this results in at least 4 filter bags being used for this step) and once every hour after the 2-hour hold.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 20 of 22 Two consecutive filter bags appear to be clean during or after the 4-hour hold (e.g. No visible fiber, etc.). These filter bags cannot be the first two filter bags changed out during the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of the 4-hour hold.

8.4 Test Termination The following cases require that the test be immediately terminated and the pump secured OFF to avoid equipment damage or personal injury:

a) The head loss across the debris bed should not exceed 15 ft-water. If reached, the flow rate will be reduced as specified in the test procedure. If reducing the flow rate as specified fails to maintain the head loss below 15 ft-water, the test must be terminated and the pump must be secured OFF.

b) Any catastrophic system failure, such as loss of power or equipment malfunction (for which no spare is available), will require test termination if deemed necessary by the Project Manager or Test Coordinator.

9.0 TEST DOCUMENTATION AND RECORDS The test specific procedure and Test Matrix provide the instructions for performing the required test steps and the associated signatures provide documentation for the performance and witnessing of critical steps. The test specific procedure also provides a test log, which is used to document significant points during the performance of the test.

The Test Equipment Verification Procedure [Ref. 2] provides the means to verify the calibration and setup of each instrument before testing to ensure error-free data acquisition. Furthermore, the procedure is run again near the end of testing to check for instrument failure or inaccuracies produced during testing.

Other test laboratory procedures are provided in Section 6.0.

The test logs are used to track the overall progression of testing and not used as safety-related measurements. The data file recorded by the data acquisition system is used for all stabilization calculations, post-test analysis, trending, and application. The Fiber Bypass Report will further clarify how the test data can be utilized.

10.0 DEBRIS HANDLING REQUIREMENTS This test plan identifies a test matrix using fiberglass. All appropriate MSDS shall be followed and the following will be used when handling (preparing, mixing, and adding into the test tank) the materials:

Safety glasses with side shields or goggles,

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 21 of 22 Cloth or Tyvek laboratory coat, Dust mask with a N95 rating similar to 3M Model 8210, Latex, nitrile or neoprene gloves (leak check gloves before use),

Long-sleeved shirt and long pants (recommended),

Fire extinguisher with water, foam, carbon dioxide or dry powder, and Filled eye wash station in proximity to debris.

None of the testing debris is directly harmful under normal testing use (submerged in the test tank water); therefore, the above personnel safety equipment is unnecessary between debris additions or preparation.

11.0 QUALITY ASSURANCE REQUIREMENTS The test program is developed, implemented, and maintained in accordance with the Alion Science and Technology Innovative Technology Solutions Operation (ITSO) Quality Assurance (QA) Program for nuclear safety-related services. Those processes that affect the quality of the output are identified and controlled by project specific procedures.

The goal of the testing program is to develop bypass data that may be used to support safety related analyses; therefore, the data shall be obtained and developed in accordance with the Alion ITSO 10CFR50 Appendix B QA Program. Although this test is designed to measure the quantity of fiber that bypasses the strainer, head loss data will be monitored to ensure strainer integrity is maintained and therefore the Alion QA program will be followed. Materials, parts, and components used by the testing program do not perform safety related functions and are not designated for installation and use in nuclear facilities. The data developed from the testing program, however, will be used to validate the performance and/or form the basis for design of components installed in a nuclear facility. Measuring and test equipment is calibrated in accordance with the ITSO QA Program.

It should be noted that the performance or critical characteristics of the test apparatus and equipment are not the same as that required for a nuclear safety-related system (i.e. not withstand a design basis accident); however, to ensure a quality output, the input and process will be controlled in a quality manner. Those processes that affect quality will be identified and controlled by project-specific procedures. Those processes that affect quality are preparation of test specimens, measurement and test equipment (procurement, calibration, and data collection), and test operation.

The fit, form, and function of materials, parts, and components used for testing and analysis by Alion are controlled by specification to ensure the required design characteristics are established to duplicate and/or model safety-related nuclear components. Certificates of conformance and compliance may be

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page: 22 of 22 used to document specification or design compliance for materials, parts, or components. Debris materials tested are supplied commercially from original equipment manufacturers.

12.0 REFERENCES

Current revisions of all Alion procedures shall be used.

1. ALION-PLN-LAB-2352-003 - Hydraulic Testing of Debris Program

Description:

Test Tank, Revision 6, 1/9/09

2. ALION-SPP-LAB-2352 Test Equipment Verification Procedure

3. ALION-SPP-LAB-2352 Filter Bag Preparation and Processing Procedure

4. ALION-SPP-LAB-2352 Test Tank Draining and Cleaning Procedure

5. ALION-SPP-LAB-2352 Test Tank Fill Procedure

6. ALION-SPP-LAB-2352 Test Tank Debris Head Loss Procedure

7. ALION-SPP-LAB-2352 Test Lab Safety Procedure

8. NEI 04-07, Volume 1, Pressurized Water Reactor Sump Performance Evaluation Methodology, Rev. 0, December 2004

9. NEI 04-07, Volume 2, Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Generic Letter 2004-02, Rev. 0, December 6, 2004

10. Enercon Design Input Letter, PER-021-LTR-001, Revision 2, October 9, 2012 (Included as Attachment A)

11. NUREG/CR-6224 Parametric Study of the Potential for BWR ECCS Strainer Blockage Due to LOCA Generated Debris., October 1995

12. Nuclear Energy Institute, ZOI Fibrous Debris Preparation: Processing, Storage and Handling Revision 1, January 2012

13. NUREG/CR-6808 Knowledge Base for the Effect of Debris on Pressurized Water Reactor Core Cooling Sump Performance, February 2003

14. ALION-PLN-ENER-8707-01, Revision 0, H.B. Robinson Plant Top Hat Strainer Bypass Testing

15. Calcium Silicate Product Data Sheet (Included in Attachment D)

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page:

1-1 of 1-5 Appendix 1 - Calculation of Testing Parameters Inputs:

Net surface area of 48 in test top hat = 30.31 ft2 [Ref. 10]

RNP total plant strainer screen area 4000 ft2 net (see Section 4.1)

Start-of-test approach velocity = 0.004 ft/s [Ref. 10]

ECCS Flow Rate = 3820 gpm [Ref. 10]

NUKON Insulation =164.8 ft3 [Ref. 10]

Temp-Mat Insulation = 16.3 ft3 [Ref. 10]

NUKON or Temp-Mat = 0.8 ft3 [Ref. 10]

Temp-Mat or Kaowool Insulation = 4.6 ft3 [Ref. 10]

Unibestos Insulation = 32.2 ft3 [Ref. 10]

Fiberglass (LDFG) = 11.8 ft3 [Ref. 10]

Latent Fiber = 60.0 lbm [Ref. 10]

Maximum Containment Water Volume = 56533 ft3 [Ref. 10]

Tank volume = 37.5 gallons/inch (approximately) +150 gallons (piping volume)

Determination of Test Tank Flow Rates Top-hat array surface area (4 top hats) = 4 x Net surface area of 48 in test top hat Top-hat array surface area (4 top hats) = 4 x 30.31 ft2 Top-hat array surface area (4 top hats) = 121.24 ft2 Scaling factor (Test Surface Area / Plant Strainer Screen Area) = 121.24 ft2 / 4000 ft2= 0.0303 The testing flow rates are determined by the following formulas, as mentioned in Section 4.6.1:

Test Flow Rate (Pre-Full Screen Coverage) = Approach Velocity (ft/s) x Strainer Screen Area (ft2)

Test Flow Rate (Pre-Full Screen Coverage) = 0.004 ft/s x Strainer Screen Area (ft2)

Test Flow Rate (Pre-Full Screen Coverage) = 0.004 ft/s x 121.24 ft2 x 448.83 gpm/ft3/s Test Flow Rate (Pre-Full Screen Coverage) = 217.7 gpm Approach Velocity (Post-Full Screen Coverage) = Plant Flow (gpm) / Plant Strainer Area (ft3)

Approach Velocity (Post-Full Screen Coverage) = 3820 gpm / (4000 ft2 x 448.8 gpm/ft3/s)

Approach Velocity (Post-Full Screen Coverage) = 0.00213 ft/s 0.003 0.003 0.003 163.2

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page:

1-2 of 1-5 Test Flow Rate (Post-Full Screen Coverage) = Approach Velocity (ft/s) x Strainer Screen Area (ft2)

Test Flow Rate (Post-Full Screen Coverage) = 0.00213 ft/s x Strainer Screen Area (ft2)

Test Flow Rate (Post-Full Screen Coverage) = 0.00213 ft/s x 121.24 ft2 x 448.83 gpm/ft3/s Test Flow Rate (Post-Full Screen Coverage) = 115.9 gpm The flow is rounded up to the nearest gpm for practicality in testing therefore, 218 gpm and 116 gpm will be used for the pre-and post-full screen coverage flow rates respectively.

Table A1-1: Scaling of Flow Rate Stage Scaling Ratio Plant Strainer Net Effective Screen Area (ft2)

Approach Velocity (ft/s)

Scaled Test Tank Flow (gpm)

Pre-Full Coverage 0.0303 4000 0.004 218 Post-Full Coverage 0.0303 4000 0.00213 116 Determination of Plant Concentration and Batch Size The plant concentration is determined by taking the total debris transported to the sump divided by the maximum containment water volume. This concentration is maintained throughout testing with the exception of the last debris batches for each debris size. The initial batch (F.1) is calculated below.

The water level changes with each addition and therefore the amount of NUKON required to maintain the plant concentration also changes. See the following calculations:

Plant Concentration = Total Transported Debris (ft3) / Maximum Containment Water Volume (gal)

Plant Concentration = 141.72 ft3 / (56533 ft3

7.48 gal/ft3)

Plant Concentration = 0.00034 ft3 / gallon Initial Batch Size = Initial Tank Volume

Plant Concentration

NUKON Density Initial Batch Size = [(36 inches

37.5 gallons/inch ) +150 gallons]

0.00034 ft3/gallon

2.4 lb/ft3 Initial Batch Size = 1.22 lbs This batch size will model the fiber suspended in the sump pool.

Determination of Scaled Mass Values for Test Debris Loads NUKON will be used throughout testing as the surrogate debris for Temp-Mat and LDFG. This is conservative, as previous Alion experience has shown NUKON to result in higher bypass quantities 0.003 164 164

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page:

1-3 of 1-5 than Temp-Mat. NUKON also has a characteristically smaller diameter (7 um versus 9 um) [Ref. 8],

The mass of NUKON surrogate quantities will be scaled by volume via density for Temp-Mat and Kaowool. The debris transport fractions are taken from the Enercon Design Input Letter [Ref. 10].

For low density fibrous debris, the mass is determined by multiplying the volume of fiber by the density of NUKON (2.4 lb/ft3) [Ref. 8].

For high-density fibrous debris, the mass is determined by multiplying the volume of fiber by the density of Temp-Mat (11.8 lb/ft3) [Ref. 8]. The scaled mass is determined by multiplying the mass by the scaling factor (0.0303). The scaled volume is then determined by dividing the scaled mass by the density of NUKON (2.4 lb/ft3) rather than that of Temp-Mat due to previous testing observations regarding the destroyed density of Temp-Mat, and then the bed thickness is determined by dividing the scaled volume by the prototype strainer area (121.2 ft2) [Ref. 10].

Unibestos - Unibestos is the trade name for a calcium-silicate material containing asbestos fibers [Ref.

8]. NUKON will be the surrogate used to represent the fibrous portion of the Unibestos material.

Alion experiences with various calcium-silicate materials have shown that they contain a 0-4% fibrous component (see Attachment D). These fibers have comparable characteristics to both NUKON and Temp-Mat that can be seen in the table below [Ref. 8]. Therefore, it is conservative to assume 10% of the total volume of Unibestos will be in fibrous form. The scaled mass of NUKON surrogate is determined by multiplying the transported volume by the 10% fibrous portion then by the scaling factor (0.0303) and the density of the NUKON (2.4 lb/ft3).

The latent debris source term is documented in the Enercon Design Input Letter is treated at LDFG and will be scaled in the same manner as NUKON above.

The small fines characterized in the design input letter [Ref. 10] are broken into 17% fines and 38%

smalls for destroyed NUKON and Temp-Mat insulation and 22% fines and 63% for Kaowool, Unibestos and fiberglass debris.

For the debris source term defined as NUKON or Temp-Mat the debris is assumed to be Temp-Mat, and for the debris source term defined as Temp-Mat or Kaowool the debris is assumed to be Kaowool. These quantities are calculated in Table A1-2 and tabulated in the test matrix in Table A1-3.

It is worth noting that the last addition for each size will have a different concentration due to it being the remaining amount of scaled test fiber.

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page:

1-4 of 1-5 Table A1-2: Scaling Fiber for Test Quantities Debris Type Volume Generated (ft3)

Transport Fraction Volume Transported to Sump (ft3)

Scaled Volume Transported to Sump (ft3)

Surrogate Material Material Density (lbs/ft3)

Scaled Surrogate Mass (lbs)

NUKON 164.8 0.38 (Smalls) 62.62 1.90 NUKON 2.4 4.6 0.17 (Fines) 28.02 0.85 2.0 Temp-Mat 16.3 0.38 (Smalls) 6.19 0.19 NUKON 11.8 2.2 0.17 (Fines) 2.77 0.08 1.0 NUKON or Temp-Mat 0.8 0.38 (Smalls) 0.30 0.01 NUKON 11.8 0.1 0.17 (Fines) 0.14 0.004 0.0 Temp-Mat or Kaowool 4.6 0.63 (Smalls) 2.90 0.09 NUKON 11.8 1.0 0.22 (Fines) 1.01 0.03 0.4 Unibestos 32.2 0.85 (Fines) 2.74**

0.08 NUKON 2.4 0.2 Fiberglass (LDFG) 11.8 0.63 (Smalls) 7.43 0.23 NUKON 2.4 0.5 0.22 (Fines) 2.60 0.08 0.2 Latent Fiber (lbs) 60.0*

1 (Fines) 25.00 0.76 NUKON 2.4

1.8 TOTAL

141.7 4.29 TOTAL:

14.1

Latent fiber is treated as LDFG and scaled directly from the mass given as an input in the Enercon Design Input Letter [Ref. 10]. The volume is calculated using the density of NUKON.

- This value included the 10% fibrous assumption (see Section 3.5).

Robinson Nuclear Plant: Bypass Fiber Quantity Test Plan Document No: ALION-PLN-ENER-8707-02 Revision: 0C Page:

1-5 of 1-5 Table A1-3: Test Matrix Stage Flow Rate (GPM)

NUKON Fines (lbs)

NUKON Smalls (lbs)

Tank Volume (gal)

Tank Level (in)

Nominal Bed Thickness (in)

Concentration (ft3/gal) lbs/gallon Added (NEI Criterion)

Gallons Added F.1 218/116 1.22 0

1500 36.00 0.050 0.00034 0.20 6

F.2 218/116 1.23 0

1506 36.16 0.101 0.00034 0.20 6

F.3 218/116 1.23 0

1512 36.32 0.152 0.00034 0.21 6

F.4 218/116 1.24 0

1518 36.48 0.203 0.00034 0.21 6

F.5 218/116 0.72 0

1518 36.48 0.233 0.00020 0.12 6

S.1 218/116 0

1.24 1524 36.64 0.284 0.00034 0.21 6

S.2 218/116 0

1.25 1530 36.80 0.336 0.00034 0.21 6

S.3 218/116 0

1.25 1536 36.96 0.387 0.00034 0.21 6

S.4 218/116 0

1.26 1542 37.12 0.439 0.00034 0.21 6

S.5 218/116 0

1.26 1548 37.28 0.491 0.00034 0.21 6

S.6 218/116 0

1.27 1554 37.44 0.544 0.00034 0.21 6

S.7 218/116 0

0.92 1554 37.44 0.582 0.00025 0.15 6

164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116 164/116