ML081090501

Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Pages E1-1 Through Figure 4.24 - Case 3

ML081090501
Person / Time
Site:	Watts Bar
Issue date:	03/31/2008
From:	Brandon M K Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
GL-04-002, TAC MC4730
Download: ML081090501 (197)

Text

ENCLOSURE1 This Enclosure provides the necessary supplemental response addressing Generic Letter 2004-02 actions at Watts Bar Nuclear Plant (WBN) Unit 1, using the guidelines set forth in the NRC letter to Nuclear Energy Institute (NEI) dated November 21, 2007, "Revised Content Guide for Generic Letter 2004-02 Supplemental Responses." 1. Overall Compliance:

Provide information requested in GL 2004-02 Requested Information Item 2(a) regarding compliance with regulations.

GL 2004-02 Requested Information Item 2(a)Confirmation that the ECCS and CSS recirculation functions under debris loading conditions are or will be in compliance with the regulatory requirements listed in the Applicable Regulatory Requirements section of this GL. This submittal should address the configuration of the plant that will exist once all modifications required for regulatory compliance have been made and this licensing basis has been updated to reflect the results of the analysis described above.TVA Response The emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions are in compliance with the with the regulatory requirements listed in the Applicable Regulatory Requirements section of Generic Letter (GL) 2004-02 for debris loading conditions.

The NRC performed an audit of the WBN sump evaluations and issued a final report by letter entitled 'Watts Bar Nuclear Plant, Unit 1 -Audit Report of New Strainer Design in Response to Generic Letter 2004-02 and Generic Safety Issue -191" dated February 7, 2007. The letter concluded that "overall the staff's impression is that the WBN new sump modifications appear to be robust with sufficient design margin." The report did have open actions for resolution which are provided in Enclosure 2 of this supplementary response.The containment walkdowns, debris generation calculations, debris transport calculations, downstream effects evaluations for blockage and long-term wear, and allocation of an allowance for chemical effects have been completed as follows.Containment Walkdowns Containment walkdowns were performed at WBN to support the analysis of debris blockage as identified in the GL. The walkdowns were performed by personnel from Enercon, Westinghouse Electric Corporation (WEC), ITSC, and Transco in consultation with TVA personnel using the guidelines provided in Nuclear Energy Institute (NEI) 02-01, "Condition Assessment Guidelines, Debris Sources inside Containment," Revision 1.Debris Generation Analysis An analysis to establish the types, quantities, and locations of debris generated during a loss of coolant accident (LOCA) event in which the plant enters the recirculation mode was performed using NEI Guidance Report 04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology" as supplemented by the NRC in the "Safety Evaluation by The Office of Nuclear E1-1 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."'

Debris Transport Analysis This analysis was based on the NEI 04-07 guidance report for refined analyses as supplemented by the NRC's safety evaluation report (SER), as well as the refined methodologies suggested by the SER in Appendices III, IV, and VI. The specific effect of each mode of transport was analyzed for each type of debris generated, and a logic tree was developed to determine the total transport to the sump screens.Downstream Effects Evaluation The evaluation of downstream effects was performed in accordance with the methodologies in Topical Report No. WCAP-16406-P, Revision 01, "Evaluation of Downstream Sump Debris Effects in Support of GSI-191." Chemical Effects Evaluation A comparison of the NRC industry integrated chemical effects test program Test 5 and the WBN plant specific parameters has been performed.

The evaluation concluded that the critical parameters in the integrated chemical effects test program Test 5 are similar to WBN plant parameters.

To account for chemical effects, margin was added to the WBN strainer area design requirements.

Based on the results of the debris generation and transport analyses, the original containment sump intake screens were replaced with an advanced design containment sump strainer arrangement.

A "stacked disk" strainer design was selected to maximize the available sump flow area in the existing containment sump structure "footprint." The advance design strainer increased the available containment sump strainer area from approximately 200 ft 2 to approximately 4600 ft 2.Scale testing of the advanced design strainer design confirmed the acceptability of the strainer arrangement to support ECCS and CSS operation for the design basis debris load with significant margins to accommodate beyond design basis debris loads.2. General Description of and Schedule for Corrective Actions: Provide a general description of actions taken or planned, and dates for each. For actions planned beyond December 31, 2007, reference approved extension requests, or explain how regulatory requirements will be met as per Requested Information Item 2(b).GL 2004-02 Requested Information Item 2(b)A general description of and implementation schedule for all corrective actions, including any plant modifications, that you identified while responding to this GL. Efforts to implement the identified actions should be initiated no later than the first refueling outage starting after April 1, 2006. All actions should be completed by December 31, 2007. Provide justification for not implementing the identified actions during the first refueling outage starting after April 1, 2006. If all corrective actions will not be completed by December 31, 2007, describe how the regulatory requirements discussed in the Applicable Regulatory Requirements section will be met until the corrective actions are completed.

E1-2 TVA Response The containment sump intake structures were modified to include advanced designed strainers during the Unit 1, Cycle 7 refueling outage in the fall of 2006. Additionally, an additional flow orifice was installed in the Chemical Volume Control System to allow the loop injection throttle valves to be set in a more open position to prevent debris trapping in those valves.During the Unit 1 Cycle 8 refueling outage, several large pieces of min-K fiber insulation were replaced with reflective metal insulation (RMI) and others were banded. This brings the plant in compliance with the final debris generation calculation and with the zone of influence testing documented in WCAP-16783-P, "Jet Impingement Testing to Determine the Zone of Influence (ZOI) of Min-K and 3M M20C fire Barrier Insulation for Watts Bar Nuclear Plant." This testing documented ZOI reduction from 28.6D to 11D for 3M material and 10D for banded min-K material.

Completion of the banding and replacement of the large pieces of min-K with RMI were the only remaining physical corrective actions required to comply with the requirements of GL 2004-002.A request to move the overall WBN completion date for the GL to after the spring 2008 refueling outage was submitted to the NRC on August 1, 2007 (T04 070801 833) and revised October 2, 2007 (T04 071002 835). The request was approved by the NRC on December 6, 2007 in a letter entitled "Watts Bar Nuclear Plant, Unit 1 -Generic Letter 2004-02, 'Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors,'

Extension Request Evaluation (TAC No. MC4730)." 3. Specific Information Regarding Methodology for Demonstrating Compliance:

3.a. Break Selection The objective of the break selection process is to identify the break size and location that present the greatest challenge to post-accident sump performance.

3.a. 1. Describe and provide the basis for the break selection criteria used in the evaluation.

TVA Response The following break locations were selected and analyzed for WBN:* Break 1: Locations in the RCS with the largest potential for debris generation.

• Break 2: Locations with two or more different types of debris." Break 3: Locations with the most direct path to the sump.* Break 4: Locations with the largest potential particulate to insulation ratio.* Break 5: Locations that would generate debris that could potentially form a thin-bed.The objective of the break selection process was to determine the break size and possible locations that result in the greatest debris generation and/or the debris generation and transport combination that present the greatest challenge to post-accident sump performance.

Additionally, breaks that result in a "thin-bed" effect were given consideration since these also have the potential to challenge sump screen performance.

E1-3 3.a.2. State whether secondary line breaks were considered in the evaluation (e.g., main steam and feedwater lines) and briefly explain why or why not.TVA Response Break locations were selected based on the accident scenarios that could lead to ECCS recirculation, the size of the pipe break, and the proximity of other insulated pipes or equipment.

Secondary line breaks were considered in the evaluation but eliminated as bounding events.Secondary line breaks have a smaller zone of influence (ZOI) for destruction (due to lower pressure), are terminated by operator action (feedwater and auxiliary feedwater isolation), and do not require sump recirculation for reactor coolant system decay heat removal. Only minimal intermittent operation of the containment spray system in the containment sump recirculation mode for long term containment temperature reduction may be required if other means are not available.

3.a.3. Discuss the basis for reaching the conclusion that the break size(s) and locations chosen present the greatest challenge to post-accident sump performance.

TVA Response The five different break scenarios discussed in the response to Item 3.a.1 above were evaluated for the accident scenario that requires operation in the containment sump recirculation mode (i.e., large break loss-of-coolant) as follows.Break 1 -Largest Potential for Debris Generation The largest quantity of insulation in containment is located on or around the reactor coolant system (RCS) loops near each of the steam generators (SGs) and reactor coolant pumps (RCPs). Due to the size of the primary RCS loop piping and the quantity of insulation in close proximity to these pipes, a double-ended guillotine break of one of the primary loop pipes presents the limiting case. The inside diameters of the primary RCS pipes are 27.5 inch for the cold legs, 29 inch for the hot legs, and 31 inch for the crossover legs. A break in one of the 31 inch inner diameter crossover legs would create the largest ZOI. However, depending on the exact location of various types of insulation, a break in the smaller hot or cold leg could result in the generation of a larger quantity of debris. Therefore the worst case location was considered for each of the four loops.Break 2 -Two or More Types of Debris The WBN lower containment contains reflective metallic insulation, 3M M20C (Interam) fire wrap, and min-K insulation.

All breaks considered encompass this scenario since multiple types of debris exist in each of the loop areas.Break 3 -Most Direct Path to the Sump At WBN, the emergency core cooling recirculation sump is located beneath the refueling cavity in the lower containment.

This area is between loops 3 and 4. Therefore breaks in these loops would have a direct path to the sump.E11-4 Break 4 -Larqest Particulate to Insulation Ratio Of the three principal insulation types in lower containment, RMI is the least problematic.

RMI does not transport as easily as the particulates and is not a major contributor to head loss. The bounding case is the one that generates the most destruction of min-K and 3M M20C fire wrap insulation.

The debris generation analysis identified that a break in the crossover leg near the steam generator nozzle generated the most particulate debris.Break 5 -Potential Formation of the Thin-Bed Effect This scenario addresses the generation of a small quantity of fibrous debris that, after its transport to the sump screen, could form a uniform thin bed that would subsequently filter sufficient particulate debris to create a relatively high head loss. With the exception of a small quantity of mineral wool in penetrations where it would not be destroyed, a relative low amount of min-K fiber, and the 3M M20C radiant heat shield material, WBN does not have large amounts of fibrous material inside containment.

Each of the break cases examined includes the analysis of potential fiber release. Testing of the strainer established the adequate performance of the advanced design for the worst case fiber loadings.Based on these results, debris generation calculations were performed for a break in the 31 inch inner diameter crossover leg at the base of the steam generator for each of the primary .system loops. The design basis debris loading was .established for testing by bounding the worst case RMI debris load with the worst case fiber and particulate load.3.b. Debris Generation/Zone of Influence (ZOI) (excluding coatings)The objective of the debris generation/ZOI process is to determine, for each postulated break location:

(1) the zone within which the breakjet forces would be sufficient to damage materials and create debris; and (2) the amount of debris generated by the breakjet forces.3.b. 1. Describe the methodology used to determine the ZOls for generating debris. Identify which debris analyses used approved methodology default values. For debris with ZOls not defined in the guidance report/SE, or if using other than default values, discuss method(s) used to determine ZOI and the basis for each.TVA Response As documented in NEI 04-07, the destruction pressures for various insulation materials were determined by performing air jet or water/steam jet tests. These tests were carried out by directing high-energy jets on various insulation targets at varying distances.

The destruction pressures were then quantified by observing the effects of the jet on the insulation and the corresponding stagnation pressure in the flow field.In a pressurized water reactor (PWR) containment building, the worst case hypothetical pipe break would be a double-ended guillotine break (DEGB). In a DEGB, jets of water and steam would blow in opposite directions from the severed pipe. One or both jets could impact an obstacle and be reflected in different directions.

To take into account the double jets and potential jet reflections, NEI 04-07 recommended using a spherical ZOI centered at the break location to determine the quantity of debris that could be generated by a given line break. Since E1-5 different insulation types have different destruction pressures, different ZOls must be determined for each type of insulation.

The ZOls for WBN were established using the NEI 04-07 methodology.

Items not specifically addressed in the methodology were addressed consistent with the NRC Safety Evaluation Report (SER) issued for NEI 04-07. Additional testing was performed at WYLE labs for min-K and 3M M20C jacketed insulation types.3.b.2. Provide destruction ZOls and the basis for the ZOls for each applicable debris constituent.

TVA Response Consistent with NEI 04-07 and the associated NRC SER, the equivalent spherical ZOI radii divided by the break diameter (r/D) for each representative material in the WBN containment was established as follows.ZOI Radii for WBN Debris Types Insulation Type ZOI Radius/Break Diameter (riD)Protective Coatings (epoxy and epoxy- 10.0*phenolic paints)Mirror RMI 28.6 3M M20C 11.0 Min-K 10.0 Nir.I f't" C~l r -r ....-J -l /" , , I~NNU r- ~reC menI~iILfus 2-0 UI 10.0 luD as a conserIvative eSLillie.3.b.3. Identify if destruction testing was conducted to determine ZOls. If such testing.has not been previously submitted to the NRC for review or information, describe the test procedure and results with reference to the test report(s).

TVA Response Destructive testing was conducted at WYLE labs for 3M M20C fire barrier and min-K jacketed insulation used at WBN. This testing is documented in WCAP-1 6783-P (proprietary) dated July 2007.El -6 Pre-prepared samples configured to match the plant installation were subjected to direct jet impingements at simulated PWR LOCA conditions.

A blowdown tank capable of providing a 30 second blowdown at 2000 psia and 530 OF though a nominal 3 inch nozzle (3.5 inch diameter actual) was used. A dual rupture disk arrangement was included to approximate instantaneous break opening. The test articles were positioned in accordance with calculations using a subcooled jet expansion model from ANSI/ANS standard 58.2-1988 which is consistent with approach taken in NEI 04-07. The testing determined that the 3M material survived a break ZOI of 11 D and that, if banded, the jacketed min-K material survived a rupture ZOI equivalent to 10D.3. b.4. Provide the quantity of each debris type generated for each break location evaluated.

If more than four break locations were evaluated, provide data only for the four most limiting locations.

TVA Response Debris generation calculations were performed for a break in the 31 inch inner diameter crossover leg at the base of the steam generator for each of the primary system loops. The quantity of each debris type generated for each break location is as follows.Debris Source Term for a Loop 1 Crossover Leg Break Debris Type Small Pieces Large Pieces Total Stainless Steel 75,902 ft 2 (75%) 25,300 ft 2 (25%) 101,202 ft 2 RMI Debris Type Fines Large Pieces Total 3M M200 nM Fibe 52.5 ft 3 0 ft 3 52.5 ft 3 (Interam)

Fiber Latent Fiber 12.5ft 3 0 ft 3 12.5 ft 3 Min-K Fiber 0.25 ft 3 0 ft 3 0.25 ft 3 Debris Type Fines Chips Total 3M M20C (Interam) 1031b 0 lb 1031b Particulate Min-K Si0 2 13.1 lb 0 Ib 13.1 lb Min-K TiO 2 3.02 lb 0 lb 3.02 lb Dirt/Dust 170 lb 0 lb 1701b Phenolic Paint 137 lb 0 lb 137 lb IOZ Paint 1,152 lb 0 Ib 1,152 lb.Alkyd Paint 44 lb 0 lb 44 lb Epoxy Paint 251b 0 Ib 251b Carboline 295 752 lb 0 lb 752 lb Silicone Paint 42 lb 0 lb 42 lb E1-7 Debris Source Term for a Loop 2 Crossover Leg Break Debris Type Small Pieces Large Pieces Total Stainless Steel 75,220 ftW (75%) 25,073 ft 2 (25%) 100,293 ft 2 RMI Debris Type Fines Large Pieces Total 3M M20C nM Fibe 75.5 ft 3 0 ft 3 75.5 ft 3 (Interam)

Fiber Latent Fiber 12.5 ft 3 0 ft 12.5 ft 3 Min-K Fiber 0.39ft 3 0 ft 3 0.39 ft3 Debris Type Fines Chips Total 3M M20C (Interam) 148 lb 0 Ib 148 lb Particulate Min-K Si0 2 20.5 lb 0 lb 20.5 lb Min-K TiC 2 4.7 lb 0 lb 4.7 lb Dirt/Dust 170 lb 0 lb 170 lb Phenolic Paint 137 lb 0 lb 137 lb IOZ Paint 1,161 lb 0 lb 1,161 lb Alkyd Paint 44 lb 0 lb 44 lb Epoxy Paint 25 lb 0 lb 25 lb Carboline 295 753 lb 0 lb 753 lb Silicone Paint 49 lb 0 lb 49 lb Debris Source Term for a Loop 3 Crossover Leg Break Debris Type Small Pieces Large Pieces Total Stainless Steel 63,865 ft 2 (75%) 21,288 ft 2 (25%) 85,153 ft 2 RMI Debris Type Fines Large Pieces Total 3M M20C (Interam)

Fiber 14.9 ft 3 0 ft 3 14.9 ft 3 Latent Fiber 12.5 ft 3 0ft 3 12.5 ftf Min-K Fiber 0.16 ft 3 0 ft 3 0.16 fty Debris Type Fines Chips Total 3M M20C (Interam) 29.3 lb 0 lb 29.3 lb Particulate Min-K Si0 2 8,32 lb 0 lb 8,32 lb Min-K TiO 2 1.92 lb 0 lb 1.92 lb Dirt/Dust 170 lb 0 lb 170 lb Phenolic Paint 149 lb 0 lb 149 lb IOZ Paint 1,147 lb 0 lb 1,147 lb Alkyd Paint 44 lb 0 lb 44 lb Epoxy Paint 25 lb 0 lb 25 lb Carboline 295 836 lb 0 lb 836 lb Silicone Paint 48 lb 0 lb 48 lb E1-8 Debris Source Term for a Loop 4 Crossover Leg Break Debris Type Small Pieces Large Pieces Total Stainless Steel 63,483 ft 2 (75%) 21,161 ft 2 (25%) 84,644 ft 2 RMI Debris Type Fines Large Pieces Total 3M M20C (Interam)

Fiber 14.9 ft 3 0 ft 3 14.9 ft 3 Latent Fiber 12.5 ft 3 0 ft 3 12.5 ft 3 Min-K Fiber 0.40 ft 3 .0 ft 3 0.40 ft 3 Debris Type Fines Chips Total 3M M20C (Interam) 29.3 lb 0 lb 29.3 lb Particulate Min-K SiO 2 20.61 lb 0 lb 20.61 lb Min-K TiC 2 4.76 lb 0 lb 4.76 lb Dirt/Dust 170 lb 0 lb 170 lb Phenolic Paint 146 lb 0 lb 146 lb IOZ Paint 1,148 lb 0 lb 1,148 lb Alkyd Paint 44 lb 0 lb 44 lb Epoxy Paint 25 lb 0 lb 25 lb Carboline 295 817 lb 0 lb 817 lb Silicone Paint 40 lb 0 lb 40 lb 3.b.5. Provide total surface area of all signs, placards, tags, tape, and similar miscellaneous materials in containment.

TVA Response A conservative allowance of 1000 ft 2 was used for tapes, tags, labels, etc inside the containment.

Based on containment walkdown results documented in WAT-D-1 1530, a conservative estimate of the total surface area of all signs, placards, tags, tape and similar miscellaneous materials in containment was established as 697 ft 2 thereby confirming the adequacy of the original design allowance.

The entire quantity of signs, placards, tags, tape, and similar miscellaneous materials were conservatively assumed to be transported to the sump intake. Based on Section 3.5.2.2.2 of.the NRC SER for NEI 04-07, a 75 percent packing ratio was applied to this debris which resulted in a 750 ft 2 surface area blockage for design and testing.E1-9 3.c. Debris Characteristics The objective of the debris characteristics determination process is to establish a conservative debris characteristics profile for use in determining the transportability of debris and its contribution to head loss.3.c. 1. Provide the assumed size distribution for each type of debris.TVA Response The size distribution for the different types of debris applicable to the WBN containment building is as follows.Insulation Mirror/RMI Generic testing of the RMI used in the WBN containment established that 71 percent of the RMI was destroyed in 1/4-inch to 2-inch pieces and 29 percent was destroyed in 4-inch to 6-inch pieces. Based on this data, Section 3.4.3.3.2 of NEI 04-07 recommends using a size distribution of 75 percent small pieces and 25 percent large pieces, where small pieces are defined as anything less than 4 inches. This recommendation was used to size the WBN RMI debris.Min-K Min-K is composed of fiber, fumed silica, and titanium dioxide and has a bulk density ranging from 8-16 Ib/ft 3.The size distribution recommended in section 3.4.3.3.1 for Min-K is 100% fines.The following characteristic sizes were used in the analysis: Debris type Characteristic Size Min-K fiber 6 pm Min-K Si0 2 20pm Min-K Ti0 2 2.5 pm 3M M20C (Interam)

Radiant Energy Shield This insulation is a "felt-like" material and was treated as a high density fiberglass (HDFG) with a manufactured density of 39 Ib/ft 3.Upon destruction, the debris fines lose their felt characteristic and become individual fibers. The HDFG fines have been assumed to be similar to LDFG fines debris. NUKON will be used as the surrogate of LDFG. It will be assumed that the 3M material fails as 55% LDFG NUKON individual fibers at 7 micron and 45% vermiculite at 10 micron particulate.

Debris Type Characteristic Size 3M M20C (interim) 7 pm Fiber Portion 3M M20C (interim)

Particulate 10pm Portion II El-10 Coatings Generally, carbon steel surfaces inside WBN containment are coated with CarbozincTM 11 (an inorganic zinc primer). All steel 6 feet from the containment'floor has also been top coated with PhenolineTM 305. The containment liner is also coated with CarbozincTM 11 and has been left without a topcoat. Even though failure of this coating is not likely, it has been conservatively assumed to fail. The concrete floors and walls have been painted with PhenolineTM 305. All concrete below 6 feet has been painted with a CarbolineTM 295 surfacer and then painted with two coats of PhenolineTM 305. The original steam generators were coated with CarbolineTM 4674 underneath the RMI insulation. (Note: the debris analysis was performed for the original steam generators which have since been removed and replaced with upgraded steam generators in U1 RFO7. The replacement generators are uncoated.

The debris generation analysis continues to bound the current U1 configuration).

The original CarbolineTM 4674 coating is a high temperature silicone that was not DBA qualified and was assumed to fail as fines if the RMI that encapsulates it fails. All qualified coatings outside the coatings ZOI will remain intact.The sizing of the coating debris was established as follows.CarbozincTM 11 -The characteristic particle diameter of inorganic zinc (IOZ) was assumed to be 10 /,m. Based on Table 3-3 of NEI 04-07, the density of IOZ particulate is 457 Ib/ft 3.However, the dry film bulk density of CarbozincrMl 1 is only 223 Ib/ft 3.This value was derived from the liquid density and other published properties for Carbozinc T M 11.CarbolineTM 295 -The characteristic particle diameter of CarbolineTM 295 was assumed to be 10 pm. A dry film bulk density of. 123 lb/ft 3 was derived using published properties of CarbolineTM 295. This value was also assumed to be the density of the particulate, as this value is higher than the 94 Ib/ft 3 density recommended for generic epoxy/phenolic particulate in Table 3-3 of NEI 04-07.PhenolineTM 305 -The characteristic particle diameter of PhenolineTM 305 was assumed to be 10 pm. A dry film bulk density of 105 lb/ft 3 was derived using published properties for PhenolineTM 305. This value was also assumed to be the density of the particulate, as this value is higher than the 94 Ib/ft 3 density recommended for generic epoxy/phenolic particulate in Table 3-3 of NEI 04-07.CarbolineTM 4674 -The characteristic particle diameter of CarbolineTM 4674 was assumed to be 10 pm. Based on the CRC Handbook of Chemistry and Physics, the density of silicone particulate is 145 Ib/ft 3.A dry film bulk density of 87 Ib/ft 3 was derived using published properties for CarbolineTM 4674.Latent Debris Dirt/Dust-The representative size and density of dirt/dust particulate was assumed to be 17.3 pm and 169 Ib/ft 3 respectively based on Section 3.5.2.3 of the NRC SER for NEI 04-07.Fiber -The representative bulk density of latent fiber was assumed to be 2.4 lb/ft 3 , and the material (individual fiber) density of latent fiber was assumed to be 94 Ib/ft 3 based on Section 3.5.2.3 of the NRC SER for NEI 04-07. The SER does not give a characteristic latent fiber diameter, but it does indicate that it is appropriate to assume the same diameter as commercial fiberglass (7 pm for Nukon per NUREG/CR-6224).

This value was used for the WBN analysis.El-11 3.c.2. Provide bulk densities (i.e., including voids between the fibers/particles) and material densities (i.e., the density of the microscopic fibers/particles themselves) for fibrous and particulate debris.TVA Response The bulk densities and material densities used to analyze fibrous and particulate debris at WBN are as follows.Physical Properties of Particulate Debris Material Bulk Particulate/Individual Debris Type/Size Density Fiber Density Min-K Fiber 16 lb/ft 3 165 lb/ft 3 Min-K SiO 2 16 lb/ft 3 137 lb/ft 3 Min-K TiO 2 16 lb/ft 3 262 lb/ft 3 3M M20C (Interam) 2.4 lb/ft 3 175 lb/ft 3 Fiber Portion 3M M20C (Interam) 4 lb/ft 3 156 lb/ft 3 Particulate Portion Phenolic Paint 105 lb/ft 3 105 lb/ft 3 (Fines)IOZ Paint 223 lb/ft 3 457 lb/ft 3 (Fines)Alkyd Paint (Fines) 98 lb/ft 3 98 lb/ft 3 Carboline 4674 87 lb/ft 3 145 lb/ft 3 (Fines)Carboline 295 123 lb/ft 3 123 lb/ft 3 (Fines)Epoxy (Fines) 94 lb/ft' 94 lb/fte Dirt/Dust 169 lb/ft 3 (Fines)Latent Fiber 2.4 lb/ft 3 94 lb/ft 3 (Fines)3.c.3. Provide assumed specific surface areas for fibrous and particulate debris.TVA Response The head loss across the current advanced design containment sump strainers was established by test. As such, these values are not part of the current sump strainer design basis.El-12 3.c.4. Provide the technical basis for any debris characterization assumptions that deviate from NRC-approved guidance.TVA Response The debris characterization assumptions used in the WBN debris generation analysis are consistent with NEI 04-07 as modified by the NRC SER for NEI 04-07. No deviation from the guidance documents was required.3.d. Latent Debris The objective of the latent debris evaluation process is to provide a reasonable approximation of the amount and types of latent debris existing within the containment and its potential impact on sump screen head loss.3.d. 1. Provide the methodology used to estimate quantity and composition of latent debris.TVA Response The quantity and composition of the latent debris in the WBN containment building was based on the assumptions discussed in Item 3.d.2 below. A quantitative latent debris walkdown was performed on WBN to confirm that the actual latent debris was bounded by the assumed values.This walkdown was based on as-found conditions at the start of a refueling outage. The walkdown involved the collection of debris samples from 26 locations inside the containment building selected to provide a representative sample of the latent debris preset in the containment building.

The sample collection area for each location varied in size from 1.3 ft 2 to 104.5 ft 2.The samples collected were analyzed for both quantity and type of debris. The latent debris from the sampled areas was then projected for the entire containment building based on the total amount of surfaces similar to those surveyed.3.d.2. Provide the basis for assumptions used in the evaluation.

TVA Response The assumptions concerning latent debris in the WBN containment building involved 1) latent debris types, 2) latent debris physical characteristics, and 3) total quantities of latent debris.Consistent with the guidance provided in the NRC SER for NEI 04-07, the latent debris characteristics were assumed to be as follows: " Fiber contributes 15 percent of the mass of the total latent debris inventory with particulate contributing the remaining 85 percent." Latent fiber material has an average density of 94 Ib/ft 3* Latent particulate material has a nominal density of 169 Ib/ft 3* Latent fiber material has an as-manufactured density (dry bed bulk density) of 2.4 Ib/ft 3* Latent fiber has the same diameter as commercial fiberglass (7 pm for Nukon per ,NUREG/CR-6224).

E1-13 Based on Section 3.5.2.2 of NEI 04-07, the maximum quantity of latent debris inside containment was assumed to be 200 lb. Of the 200 Ibs, 170 lbs was assumed to be dirt/dust and the remaining 30 lbs was assumed to be fiber.3.d.3. Provide results of the latent debris evaluation, including amount of latent debris types and physical data for latent debris as requested for other debris under c. above.TVA Response The latent debris walkdown found small quantities of particulate debris such as dust, dirt, paint chips, wood chips, concrete chips, metal shavings, metal washers, nails, screws, wire powder, tape, and miscellaneous artifacts.

The quantity found projects to a total containment quantity of 69.2 pounds. Only a few latent fibers and string material were found. A 1% fiber loading was estimated from the samples which equates to approximately 0.7 lb. The latent debris survey results confirmed that the assumptions described in Item 3.d.2 above are conservative with respect to both composition and quantity of the actual latent debris in the WBN containment building.3.d.4. Provide amount of sacrificial strainer surface area allotted to miscellaneous latent debris.TVA Response As discussed in the response to Item 3.b.5 above, a sacrificial surface area of 750 ft 2 (1000 ft 2 x 0.75 loading) has been established for latent debris in the form of signs,, placards, tags, tape, and similar miscellaneous materials.

3.e. Debris Transport The objective of the debris transport evaluation process is to estimate the fraction of debris that would be transported from debris sources within containment to the sump suction strainers.

3.e. 1. Describe the methodology used to analyze debris transport during the blowdown, washdown, pool-fill-up, and recirculation phases of an accident.TVA Response The debris transport methodology used for WBN involves the estimation of the fraction of debris that is transported from debris sources (break location) to the sump screens. The four major debris transport modes used in the WBN methodology are:* Blowdown transport

-the vertical and horizontal transport of debris to all areas of containment by the break jet.* Washdown spray transport

-the vertical (downward) transport of debris by the containment sprays and break flow.El-14

• Pool fill transport

-the horizontal transport of debris by break and containment spray flows from the refueling water storage tank (RWST) to areas that may be active or inactive during recirculation.

• Recirculation transport

-the horizontal transport of debris from the active portions of the recirculation pool to the sump screen by the flow through the emergency core coolant system (ECCS).The specific effect of each mode of transport was analyzed for each type of debris generated, and a logic tree was developed to determine the total transport to the sump screens. The purpose of this approach is to break a complicated transport problem down into specific smaller problems that can be more easily analyzed.The detailed methodology used for the WBN transport analysis is as follows: 1) A 3-dimensional model was built using computer aided drafting (CAD) software based on containment building drawings.2) A review was made of the drawings and CAD model to determine transport flow paths.Potential upstream blockage points including screens, fences, grating, drains, etc. that could lead to water holdup were addressed.

3) Debris types and size distributions were gathered from the debris generation calculation for each postulated break location.4) The fraction of debris blown into the ice condenser was determined based on the flow of steam during the blowdown.5) The quantity of debris washed down by ice melt and spray flow was conservatively determined.

6) The quantity of debris transported to inactive areas or directly to the sump screens was calculated based on the volume of the inactive and sump cavities proportional to the water volume at the time this cavity was filled.7) Using conservative assumptions, the locations of each type/size of debris at the beginning of recirculation was determined.

8) A computational fluid dynamic (CFD) model was developed to simulate the flow patterns that would occur during recirculation.

9) A graphical determination of the transport fraction of each type of debris was made using the velocity and turbulent kinetic energy (TKE) profiles from the CFD model output, along with the determined initial distribution of debris.10) The recirculation transport fractions from the CFD analysis were gathered to input into the logic trees.E1-15

11) The quantity of debris that could experience erosion due to the break flow, spray flow, or ice melt drainage was determined.

12) The overall transport fraction for each type of debris was determined by combining each of the previous steps in logic trees.The methodology is based on NEI 04-07 for refined analyses as modified by the NRC SER for NEI 04-07, as well as the refined methodologies suggested in Appendices Ill, IV, and VI of the SER.Loop 4 Crossover Lao Break Case 1: S=== =='Loop.I Crossover mensional CFD Model 3.e.2. Provide the technical basis for assumptions and methods used in the analysis that deviate from the approved guidance.TVA Response None of the transport analysis assumptions and methods deviates from the approved guidance documents discussed in Item 3.e.1 above.3.e.3. Identify any computational fluid dynamics codes used to compute debris transport fractions during recirculation and summarize the methodology, modeling assumptions, and results.TVA Response The CFD calculation for recirculation flow transport in the WBN containment building was performed using Flow-3D, Version 8.2. Flow 3-D is a commercially available general-purpose computer code for modeling of dynamic behavior of liquids and gases influenced by a wide variety of physical processes.

The program is based on the fundamental laws of mass, momentum and energy conservation.

It has been constructed for the treatment of time-dependent multi-dimensional problems and is applicable to most flow processes.

Version 8.2 of El-16 Flow-3-D has been validated and verified under ALION Science and Technology's (TVA Contractor)

Quality Assurance program.The CFD model was developed to simulate the flow patterns that occur during recirculation using the following methodology.

1) The mesh in the CFD model was sized to sufficiently resolve the features of the CAD model discussed in the response to Item 3.e.1 above.2) The boundary conditions for the CFD model were set based on the configuration of WBN during the recirculation phase.3) The ice melt and containment spray flows were included in the CFD calculation with the appropriate flow rate and kinetic energy to accurately model the effects on the containment pool.4) At the postulated break location, a mass source was added to the model to introduce the appropriate flow rate and kinetic energy associated with the break flow.5) A negative mass source was added at the sump location with a total flow rate equal to the sum of the spray flow and break flow.6) An appropriate turbulence model was selected for the CFD calculations.

7) After running the CFD calculations, the mean kinetic energy was checked to verify that the model had been run long enough to reach steady-state conditions.

8) Transport metrics were determined based on relevant tests and calculations for each significant debris type present in the WBN containment building.Significant assumptions used in the development of the CFD model include the following.

1) Transport calculations were performed for a break in the 31 inch inner diameter crossover leg at the base of the steam generator for each of the primary system loops. It was assumed that breaks in Loops 1 and 2 (locations on the far side of containment from the sump) would have equivalent recirculation transport fractions, and breaks in Loops 3 and 4 (locations near the sump) would have equivalent transport fractions.

This is reasonable since the containment building is almost completely symmetric, which would cause the pool flow paths and velocities to be very similar during recirculation.

2) The water falling from the RCS breach was assumed to do so without encountering any structures before reaching the containment pool. This is a conservative assumption since any impact with structures would dissipate the momentum of the water and decrease the turbulent energy in the pool.3) It was assumed that the agitation caused by the ice melt drainage as it reaches the containment pool can be conservatively introduced at the bottom of the pool. This approach is conservative since the floor is where sunken debris that could be tumbled along or re-suspended would reside. Additional studies were also performed which introduced the drainage at the surface of the pool in a more realistic fashion with less conservative results.E1-17

4) It was assumed that the small fraction of spray water that flows through the fans into the accumulator rooms is negligible in terms of affecting the pool flow (maximum design flow of 127 gpm through Room 3 and 18 gpm through Room 4). Therefore, all of the spray water was introduced through the refueling canal drains.The debris transport fractions determined from the CFD simulations performed for a break in the 31 inch inner diameter crossover leg at the base of the steam generator for each of the primary system loops. As described above, the transport fraction for Loops 1 and 3 were conservatively taken from the results of Loops 2 and 4 (i.e. the transport fraction for fine debris was taken from Loop 2 and the transport fraction for RMI debris was taken from Loop 4). The limiting transport fractions for all break locations are summarized as follows.Transport Fractions of Debris to Sump Screen (Bounding Quantities)

Debris Type Fines Small Pieces Large Pieces Stainless Steel RMI* NA 53.5% 17.9%Min-K Insulation 100% NA NA 3M M20C (Interam)

[Fiberglass]

100% NA NA Phenolic Paint (inside ZOI) 100% NA NA Epoxy Paint (outside ZOI) 100% NA NA Inorganic Zinc Paint (inside ZOI) 100% NA NA Inorganic Zinc Paint (outside ZOI) 100% NA NA Modified Silicone Paint (inside ZOI) 100% NA NA Modified Silicone Paint (outside 100% NA NA ZOI)Alkyd Paint (outside ZOI) 100% NA NA Dirt/Dust 100% NA NA Latent Fiber* 100% NA NA ,---*Note an error was.discovered in the method for introduction of ice melt water into the containment after the original analysis was completed.

A correction to the model indicates that overall RMI transport for the worst case changes from approximately 71% total to approximately 48% total and Fiberglass debris transport reduced from 100% to 96%. The conclusion of the corrective action review was that the original analysis remained bounding.3.e.4. Provide a summary of, and supporting basis for, any credit taken for debris interceptors.

TVA Response No credit was taken for debris interceptors in the WBN debris transport analysis.3.e.5. State whether fine debris was assumed to settle and provide basis for any settling credited.TVA Response Calculations accomplished as part of the debris transport analysis led to a determination that fine debris was not significantly removed from the pool.El-18 3.e.6. Provide the calculated debris transport fractions and the total quantities of each type of debris transported to the strainers.

TVA Response The overall debris transport fractions and the bounding quantities of each type of debris transported to the containment sump are as follows: Bounding LBLOCA Debris Source Term Debris Debris Type Debris Quantity Transport Quai Fraction (DTF) At Sump Insulation RMI 101,202 ft 2 x 0.48 60,458 ft 2 (1)85,153 ft 2 x 0.71 Fiber 3M M20C Fiber [LDFG 75.5 ft 3 1.0 75.5 ft 3 volume (2)] __ 75._1.0_5.5_

Min-K Fiber 0.40 ft 3 1.0 0.40 ft 3 Coatings/Particulate 3M M20C Particulate 148 lb 1.0 148 lb Min-K SiO 2 20.61 lb 1.0 20.61 lb Min-K TiO 2 4.76 lb 1.0 4.76 lb Phenolic 149 lb 1.0 149 lb IOZ 1,161 lb 1.0 1,161 lb Alkyds 44 lb 1.0 44 lb Epoxy Paint 25 lb 1.0 25 lb Carboline 295 836 lb 1.0 836 lb Silicone 49 lb 1.0 49 lb Latent Debris Latent Fiber(3) 12.5 ft 3 1.0 12.5 ft 3 Dust & Dirt 1701b 1.0 1701b Tags and Tape(4) 1000 ft 2 1.0 1000 ft 2 (U)(2)(3)(4)Ine uuantity at dump is me greater or -ui0,2u0 ift x u.48 or 85,103 ft X U.0.The volume of 3M is the LDFG volume, the equivalent volume at a bulk density of 39 Ib/ft 3 is 8.45 ftW.The volume of latent fiber was calculated by dividing the mass of latent fiber by the bulk density of NUKONas shown in NEI 04-07 (2.4 lb/ft 3). This gives a latent fiber volume of 12.5 ft 3 (30 lb/2.4 lb/ft 3).Section 3.5.2.2.2 of the SER for NEI 04-07 allows a 75 percent overlap of tags/tape/labels on a strainer screen. As a result, the wetted sump screen flow area was reduced by an area equivalent to 75 percent of this area.The most limiting amount of each debris type was taken from each of the 4 loop cases. This table is therefore not representative of the debris quantities for any individual loop.E1-19 3.f. Head Loss and Vortexing The objectives of the head loss and vortexing evaluations are to calculate head loss across the sump strainer and to evaluate the susceptibility of the strainer to vortex formation.

3.1 1. Provide a schematic diagram of the emergency core cooling system (ECCS) and containment spray systems (CSS).TVA Response Schematic flow diagrams of the WBN ECCS and CSS are contained in the WBN Updated Final Safety Analysis Report (UFSAR). Refer to Figure 6.2.2-1 for the CSS and Figure 6.3-1 for the ECCS. (Copies provided below for convenience.)

E1-20

3. f.2. Provide the minimum submergence of the strainer under small-break loss-of-coolant accident (SBLOCA) and large-break loss-of-coolant accident (LBLOCA) conditions.

TVA Response The minimum submergence of the WBN containment sump strainer under LBLOCA and SBLOCA conditions occurs at the time of initial recirculation operation.

Minimum submergence values are as follows.Containment Sump Strainer Minimum Submergence Conditions Minimum Sump Strainer Assembly Minimum Level Height(1) Submergence Large Break LOCA ECCS Recirculation 9.02 ft Short -4.81 ft 4.21 ft 9.02 ft Tall -5.52 ft 3.50 ft CSS Recirculation 12.07 ft Short- 4.81 ft 7.26 ft 12.07 ft Tall 5.52 ft 6.55 ft Small Break LOCA (2)ECCS Recirculation 6.54 ft Short -4.81 ft 1.73 ft 6.54 ft Tall 5.52 ft 1.02 ft CSS Recirculation 5.48 ft Short -4.81 ft 0.67 ft 5.48 ft Tall 5.52 ft Effectively Submerged 1) WBN strainers are of different heights as discussed in Item 3.j.1 below.2) SBLOCA results are for the 120 gpm SBLOCA case. 2000 gpm SBLOCA also examined in sump water inventory calculations for NPSH.3.1 3. Provide a summary of the methodology, assumptions, and results of the vortexing evaluation.

Provide bases for key assumptions.

TVA Response The original WBN containment sump intake structure contained a number of design features (i.e., grating, baffle plates, and screens) that were designed to prevent vortex formation.

The effectiveness of the original design to prevent vortex formation was verified through 1:4 scale testing performed prior to initial plant operation.

Modification of the sump for GL 2004-02 compliance involved the removal of the original inlet structure and replacement with advanced design strainer assemblies.

As none of the other vortex suppression features shown in WBN UFSAR Figure 6.3-6A were altered by the modification, the effect of the change was qualitatively determined to be neutral or decrease the potential for vortex formation such that the original scale testing remained valid.The potential for vortex formation in the strainer assembly was also evaluated.

WBN's strainer module disks are nominally 5/8 inch thick with a 1 inch separation between adjacent disks. The interior of the disks contain rectangular wire stiffeners for support. They are configured as a"sandwich" made up of three layers of wires. The disks are completely covered with perforated plate having 0.085 inch diameter holes. Based on this configuration, the largest opening for E1-23 water into the strainer flow channel is through the 0.085 inch diameter holes. An air ingestion evaluation based on Froude number was performed.

It was determined that the calculated Froude number was 50% of the criteria for air ingestion.

It would therefore be expected that air ingestion would be less than 2% and vortex formation unlikely.

A void fraction analysis was also conducted.

It was determined that the void fraction would remain less than 3% at expected containment conditions even at atmospheric pressure.Even for a very small SBLOCA, all of the WBN sump strainers are effectively submerged at the initiation of sump recirculation operation.

Thus, vortex formation in the sump would not be expected to occur for SBLOCA recirculation operation.

31.4. Provide a summary of the methodology, assumptions, and results of prototypical head loss testing for the strainer, including chemical effects. Provide bases for key assumptions.

TVA Response Testing of the advanced design containment sump suction strainers was conducted at Alden Research Laboratory in Holden, Massachusetts to confirm strainer performance and design margins for various service conditions.

The testing was performed to assess the effects of debris loading on strainer performance based on the final strainer configuration for WBN (i.e., the strainer surface area and maximum strainer opening size) and the existing plant emergency core cooling system (ECCS) flow requirements.

The testing was conducted in a flume with approximate dimensions of 27 inches wide x 39 inches high x 20 feet, 9 inches long. The test apparatus included the test flume, a recirculation pump, the test strainer module, instrumentation and controls, and associated piping to operate the pump in a recirculation mode. The recirculation flow rate used in the testing was based on the scaled WBN design basis ECCS volumetric flow rate. The debris quantity for the strainer test was in proportion to the scaled flow through the test module.The following debris loading conditions were included in the strainer test program.Test 1 -Design Basis Test This test measured the performance of the containment sump strainers for the design basis debris load case established by the WBN plant specific debris transport study. The size of the failed coatings in this test was 10 pIm particles to match the assumption of the design basis transport analysis.

This assumption was intended to maximize the amount of failed coatings which could transport to the sump screen for potential formation of a fiber thin bed. The results of the transport study confirmed that a thin bed would not form based on WBN plant specific sump recirculation flow and debris characteristics.

This test matched the design basis conditions and established the design basis performance for the strainers.

Test 2 -Limiting Coating Size Test This test measured the performance of the containment sump strainers for the design basis debris load case established by the WBN plant specific debris transport study with a modified failed coating size. The debris load is the same as for the design basis test with one exception.

While the size of the failed coatings modeled in the design basis maximizes the debris transport, E1-24 the size does not result in maximum strainer blockage given that the analyzed conditions are such that "thin bed' fiber blockage will not occur. To maximize the failed coating blockage effect, the size of the failed coatings in this test were paint chips which were all larger than the sump strainer openings (i.e., approximately 1/8 inch square and 5 mils thick). While there will be more settling of the larger size chips before they reach the strainers, the same transport fraction for the 10 pm particles was conservatively applied to the chips. This test established the design basis performance for the strainers for the worst case failed coating size (i.e., larger than the 0.085 inch maximum strainer opening size).Test 3 -Maximum Coating Inventory Test This test measured the performance of the containment sump strainers for a maximum coating debris load case. The debris load is the same as for the design basis test with the following exceptions.

The failed coating quantities for phenolic and inorganic zinc coatings (IOZ) have been increased to reflect the total amount of qualified and unqualified coatings inside containment.

The quantities of these coatings were conservatively established by increasing the design basis quantities approximately an order of magnitude.

The size of the failed coatings was revised to reflect a spectrum of chip sizes which are reflective of the actual coating failure mode with the exception of the IOZ coatings.

Based on industry testing, the IOZ coatings will fail as particulate.

As the revised coating sizes will be equal to or greater than the size modeled in the debris transport study, they will conservatively maximize the potential strainer blockage assuming the same transport fraction.

Additionally, debris to address potential containment sump chemical effects was also added. The chemical information is based on Test No. 5 of the Integrated Chemical Effects Test (ICET) project conducted by industry groups. The results from Test No. 5 are intended to be applicable to ice condenser containment materials.

This test established strainer performance for beyond design basis quantities of failed coatings and established the strainer design margin for failed coating debris. It was intended to demonstrate operational margins needed to address potential containment qualified coating issues beyond the established design basis as well as potential strainer blockage due to chemical effects.Test 4 -Test 4 was bounded by Test 3, therefore test 4 was not performed.

Test 5 -Limiting Coating Size with 3M M20C Removed This test measured the performance of the containment sump strainers for a the design debris load case established by the WBN plant specific debris transport study with a modified failed coating size and a modified insulation type. The debris load is the same as for the limiting coating size case with the following exceptions.

The 3M M20C was replaced with RMI. (The 3M M20C was removed as a debris source and RMI quantity increased.

This test established the strainer performance with the majority of the fiber insulation removed and a worst case failed coating size.Two informal tests were conducted following Test 2 and Test 3 to gain insight on the "near field" effects and the effects of fibrous debris on strainer head loss.Informal Test following Test 2 Following test 2 additional fiber was poured into the flume within 1 foot of the strainer.

At a flow rate of 68 gpm, the head loss was observed to be 0.101 ft and at 129 gpm, the head loss was observed to be 0.27 ft.E1-25 Informal Test following Test 3 Following test 3, the mixed debris was manually pushed towards the strainer (the mixed debris, consisting mostly of paint chips, formed a mound over the strainer and completely covered the strainer).

At a flow rate of 68 gpm, the head loss was observed to be 0.03 ft, at 120 gpm, the head loss was 0.2 ft.The specific measured head loss experienced during each test is summarized below.Summary of As-Tested Strainer Head Loss with Debris Loaded Flume Test Number Clean Strainer Measured Velocity Debris Average Head Loss (ft) Head Loss Head Loss Load Head Water (ft) (ft) Loss (ft) Temperature (OF)1 0 0.022 0.0111 0.011 49.5 2 0 0.027 0.0109 0.016 51.5 3 0 0.060 0.0109 0.049 51.3 5 0 0.030 0.0109' 0.019 53.1 (1) Test 4 was bounded by Test 3; therefore test 4 was not performed.

(2) There was insufficient fiber collection at the strainer during the tests to form a dense thin bed.3. f.5. Address the ability of the design to accommodate the maximum volume of debris that is predicted to arrive at the screen.TVA Response For the design basis debris load, the volume of debris was determined to.be less than the maximum volume of debris that the WBN containment sump strainers could accommodate.

Based on this result, the total design basis debris load was conservatively assumed to be deposited on the sump strainer assemblies.

The weight of the total debris load was calculated from this volume of material to establish the maximum debris dead weight acting on the strainer assemblies; The maximum dead weight load was included in the structural analysis of the strainer assemblies.

The ability of the strainer assemblies to accommodate the post-accident debris volume in terms of head losswas established by testing as discussed in the response to Item 3.f.4 above.3.f.6. Address the ability of the screen to resist the formation of a "thin bed" or to accommodate partial thin bed formation.

TVA Response The WBN advanced design containment sump strainers have been designed to preclude the formation of a fiber bed (thin or thick) for post accident sump recirculation operation.

Based on containment building walkdowns performed for WBN, the principal source of fibrous material debris available for transport to the containment sump is the 3M M20C material.

WBN plant E1-26 conditions are such that a thin bed is unlikely (i.e., large strainer area, advanced strainer design, low fiber, principally RMI insulation, a deep water pool, with debris predominantly in the form of fines), the analysis of thin bed effects was performed primarily to establish the minimum flow area criteria to prevent thin bed formation.

The final sump strainer flow area (4600 ft 2) was selected such that thin bed effect head losses are not expected to occur.To confirm this design objective, a series of flow transport/blockage tests were performed.

The design basis test case was performed with all failed coatings simulated as 10 pm particles.

This test was intended to maximize small particulate transport to the sump screen and serve as a limiting case for thin bed blockage effects. Upon confirmation that the strainer design will preclude thin bed formation, additional tests were performed to evaluate other sump blockage mechanisms.

These tests included 1) the limiting failed coating size for maximum strainer blockage (i.e., the size of the failed coatings in this case were approximately 1/8 inch square and 5 mils thick and were considered small enough to maximize transport and large enough to maximize strainer blockage);

and 2) the maximum coating inventory (i.e., the coating quantities for phenolic and inorganic zinc coatings were increased to reflect the total amount of qualified and unqualified coatings inside containment).

In all cases, thin bed formation did not occur.3.f. 7. Provide the basis for the strainer design maximum head loss.TVA Response The head loss across the clean strainers and the associated flow plenum was established by calculation for the WBN ECCS and CSS service conditions.

The limiting measured debris head loss discussed in the response to Item 3.f.4 was adjusted for dynamic viscosity temperature effects between the test temperature and the post-accident sump temperature.

The maximum expected head loss across the advanced design strainer was established by adding the limiting case debris blockage head loss to the calculated clean strainer/flow plenum head loss. This final value was established as the WBN strainer design maximum head loss.3.f.8. Describe significant margins and conservatisms used in the head loss and vortexing calculations.

TVA Response The significant conservatisms used in the WBN head loss and vortexing calculations used to establish strainer assembly design margins are as follows.a. Strainer head loss values established from prototype test data were increased by 6 percent to bound test measurement uncertainties.

b. Strainer flow plenum head loss values calculated using standard hydraulic flow resistance equations were conservatively increased by 10 percent.c. The various size strainer assemblies have varying clean strainer head loss values. The largest strainer assembly clean head loss value was applied to the design basis head loss calculation.

d. The total debris head loss was established using the limiting measured head loss value.This value was produced by a conservative debris load (see description of Test 3 in the response to Item 3.f.4 above).El-27 3.f.9. Provide a summary of the methodology, assumptions, bases for the assumptions, and results for the clean strainer head loss calculation.

TVA Response The WBN clean strainer head loss calculation methodology involved establishment of individual head loss values for .1) the strainer assemblies and 2) the strainer discharge flow plenum.Head loss across the strainer assemblies was calculated using prototype strainer head loss test data applicable to the WBN strainers.

This result was then adjusted to address 1) measurement uncertainties associated with the prototype testing and 2) configuration differences between the prototype test strainer configuration and the WBN strainer configuration.

Prototype testing performed by the strainer vendor established an empirical relationship for clean strainer head loss as a function of 1) the kinematic viscosity of water (a function of water temperature) and 2)the strainer exit velocity (a function of strainer flow rate and exit area). This equation was used to establish the "Clean Strainer Test" head losses summarized in the Table below. A maximum test measurement uncertainty of 6 percent was then applied to this result to bound any measurement error associated with the prototype testing equipment.

This value is recorded as the "Test Uncertainty Correction" in the table below. Key features of the prototype test assembly were then reviewed relative the WBN strainer assemblies for potential correction.

These features included 1) internal strainer core tube diameter and exit velocity, 2) strainer disk dimensions, 3) strainer perforation configuration and 4) strainer length dimensions.

The head loss across the strainer collection plenum into the sump was calculated using standard hydraulic head loss equations.

Head losses were calculated for 1) the strainer discharge flow entering the plenum and 2) the plenum discharge into the sump. The strainer plenum head losses were calculated using a standard head loss equation for water exiting a pipe. The equation establishes head loss as a function of water velocity.

The results of this relationship were then conservatively increased by 10 percent to establish bounding values. The sump pit entrance head losses were calculated using a standard head loss equation for water entering a reservoir.

The equation also establishes head loss as a function of water velocity.The results of this relationship were then conservatively increased by 10 percent to establish bounding values.The methodology described above for the clean strainer head loss calculation did not involve any significant assumptions.

The individual head loss results for the strainer assemblies and the collection plenum were summed to obtain the head losses for the strainer/plenum assemblies.

The results of the clean strainer head loss calculations are as follows.WBN Clean Containment Sump Strainer Head Loss Summary WBN "Long" WBN "Short" Head Loss Parameter Strainer Type Strainer Type"A" ..B" Strainer Assembly Uncorrected Clean Strainer 0.0729 ft 0.0523 ft Test 0.0729 ft _0.0523_ft 6% Test Uncertainty 0.0044 ft 0.0032 ft E1-28 Correction Flow, Perforated Plate 0.000 ft 0.000 ft Strainer Length 0.000 ft 0.000 ft Discharge Flow Plenum Strainer Discharge to Plenum 0.180 ft 0.180 ft (+10%)Plenum (+10%) 0.0748 ft 0.0528 ft Water Entering Sump Pit 0.483 ft 0.483 ft (+10%)Disk Disk Internal Flow Resistance 0.000 ft 0.000 ft Total Strainer Head Loss 0.815 ft 0.773 ft Based on these results, a limiting clean strainer head loss value the WBN strainer assemblies.

of 0.815 ft was established for 3.f. 10. Provide a summary of the methodology, assumptions, bases for the assumptions, and results for the debris head loss analysis.TVA Response The WBN debris laden strainer head loss calculation methodology involved application of the limiting debris head loss value established by the testing described in the response to Item 3.f.4.above to the limiting clean strainer head loss value established as described in the response to Item 3.f.9 above. The limiting measured debris head loss value was adjusted to account for dynamic viscosity temperature effects between the test temperature and the post-accident sump temperature as discussed in the response to Item 3.f.13 below.The methodology described above for the debris laden strainer head loss calculation did not involve any significant assumptions.

E1-29 The results of the debris laden strainer head loss calculations are as follows.WBN Debris Laden Containment Sump Strainer Head Loss Summary WBN "A-Tall" WBN "B-Short" Head Loss Parameter Strainer Strainer Assembly Assembly Clean Strainer Head Loss 0.815 ft 0.773 ft Strainer Debris Laden Head Loss (Tested)with Temperature Correction for Post- 0.022 ft 0.022 ft LOCA Temperatures Applied I I Total Strainer Head Loss 0.837 ft 0.795 ft Based on these results, a limiting debris laden head loss value of 0.837 ft was established for the WBN strainer assemblies.

31.11. State whether the sump is partially submerged or vented (i.e., lacks a complete water seal over its entire surface) for any accident scenarios and describe what failure criteria in addition to loss of net positive suction head (NPSH) margin were applied to address potential inability to pass the required flow through the strainer.TVA Response As discussed in the response to Item 3.f.2, the WBN advanced design containment sump strainers are fully submerged upon initiation of containment sump recirculation operations for a large break LOCA. All of the sump strainers are effectively submerged for ECCS recirculation for a small break LOCA. As discussed in the response to Item 3.f.3, sump vortexing and significant air intrusion do not occur for this operating configuration.

3.f. 12. a description of the scaling analysis used to justify near-field credit.TVA Response Near-field settling was not credited as a debris reduction mechanism for the head loss testing performed for WBN. As discussed in response to Item 3.f.4, two informal tests were performed to establish that potential "near field flow effects" associated with the testing configuration do not a have a significant effect on the measured strainer head loss.3.f. 13. State whether temperature/viscosity was used to scale the results of the head loss tests to actual plant conditions.

If scaling was used, provide the basis for concluding that boreholes or other differential-pressure induced effects did not affect the morphology of the test debris bed.TVA Response For WBN, temperature/viscosity was used to scale the results of the head loss tests to actual plant conditions.

The head loss resulting from flow through a fiber-particulate debris bed at the approach velocities of the WBN advanced design strainers (i.e., 0.014 ft/s) is 100 percent E1-30 viscous flow (as opposed to inertial flow). As viscous flow, head loss is linearly dependent on the product of viscosity and velocity.

To adjust the measured head loss across the debris bed under test conditions, the ratio of dynamic viscosities for the warmer post-accident water temperature to the colder test water temperature was applied to the measured head loss to correct the measured value to the expected head loss under post-accident operating temperatures.

Given that the measured WBN head losses due to debris loading were 1) relatively small when compared to the calculated clean strainer/flow plenum head losses and 2) do not vary significantly with significant changes in the tested debris quantities, no other effects or scaling considerations were applied to the head loss results.3.f. 14. State whether containment accident pressure was credited in evaluating whether flashing would occur across the strainer surface, and if so, summarize the methodology used to determine the available containment pressure.TVA Response Containment accident pressure was not credited in evaluating flashing across the strainer surface (atmospheric pressure assumed).3.g. Net Positive Suction Head (NPSH)The objective of the NPSH section is to calculate the NPSH margin for the ECCS and CSS pumps that would exist during a loss-of-coolant accident (LOCA) considering a spectrum of break sizes.3.g. 1. Provide applicable pump flow rates, the total recirculation sump flow rate, sump temperature(s), and minimum containment water level.TVA Response The pump flow rates (per train) used in the WBN sump recirculation NPSH calculation are as follows.WBN ECCS and CSS Flows Rates for Sump Recirculation NPSH Calculation Small Break Large Break LOCA lBCa LOCA Unit 1 CSS 4600 gpm 4600 gpm Unit 1 ECCS (Residual Heat 5000 gpm 5000 gpm Removal)Total Recirculation Flow 9600 gpm 9600 gpm The sump recirculation inventory temperature used in the WBN NPSH analysis is a constant 1901F, which represents maximum post-accident sump temperature.

The minimum containment sump water levels used in the analysis are the same as those summarized in the response to Item 3.f.2 above.E1-31 3.g.2. Describe the assumptions used in the calculations for the above parameters and the sources/bases of the assumptions.

TVA Response No significant assumptions were used in the calculation of the flow parameters listed in the response to Item 3.g.1 above. Where necessary, conservative modeling techniques and design inputs were used to provide bounding results. These inputs and modeling techniques include: 1) Both trains of CSS and RHR (within the computational model) will be in operation since the suction lines from the containment sump to the RHR pumps are totally independent.

2) The containment sump fluid is at the design temperature of 190 0 F.3) The pressure in containment will be at 0 psig 4) For SBLOCA, the level at the time of RHR switchover in the containment sump following a SBLOCA will be used.5) For SBLOCA, each train of RHR receives a flow of 5000 gpm. This assumption is very conservative since for most of the smaller breaks the RHR pumps are not capable of pumping into the RCS, Therefore the highest flow that could be expected would be the total runout flow of both trains of the SIPs and CCPs (approx 2400 gpm) when being supplied by one train of RHR (no RHR flow is discharging directly into the RCS.6) The maximum calculated CSS flow from the sump for each train (4600 gpm) will be assumed.The assumptions used to establish the minimum containment sump water levels used in the analysis are summarized in the response to Item 3.g.9 below.3.g.3. Provide the basis for the required NPSH values, e.g., three percent head drop or other criterion.

TVA Response The required NPSH values were obtained from vendor requirements specific to the WBN ECCS and CSS pumps. The values were based on factory NPSH testing which was performed by the pump vendors in accordance with the industry standards in place at the time of original equipment manufacture.

The 3 percent head drop criterion was typically used for this type testing.3.g.4. Describe how friction and other flow losses are accounted for.TVA Response Suction piping line losses (which include entrance losses and frictional losses through pipe, valves and fittings) for the ECCS and CSS pump suction piping were quantified using a computer flow simulation model which establishes gauge pressure for each point within the model. The analytical model was constructed for the WBN plant specific piping configuration using the MULTIFLOW, Version 1.21 computer code. Input parameters which conservatively maximize flow through the piping were then applied to the model to establish the bounding friction losses used in the NPSH analysis.E1-32 3.g.5. Describe the system response scenarios for LBLOCA and SBLOCAs.3.g.6. Describe the operational status for each ECCS and CSS pump before and after the initiation of recirculation.

TVA Response (items 5 & 6)In response to a LOCA, the residual heat removal (RHR), centrifugal charging (CCP), and safety injection (SIP) pumps automatically start upon receipt of a safety injection signal. These pumps initially inject borated water from the refueling water storage tank to the primary system cold legs. This mode of operation is referred to as the ECCS injection mode of operation.

The containment spray system (CSS) pumps start automatically when the containment pressure reaches the high setpoint for CSS actuation.

The CSS pumps also initially take suction from the RWST.When the water level in the RWST reaches a low level setpoint (coincident with a containment water level (sump) level above the high level setpoint), switchover to the ECCS recirculation mode of operation occurs. Switchover to the recirculation mode is a semi-automatic process which involves the following.

• The containment sump isolation valves automatically open and the RHR pump block valves in the suction piping from the RWST automatically close when the RWST level reaches the low level setpoint." Manual operator action is taken to 1) terminate CSS pump operation prior to a RWST low-low level setpoint, 2) perform the valve realignments required to provide suction to the CCP and SIP pumps from the discharge of the RHR pumps, 3) isolate the CCP and SIP suction piping from the RWST, 4) isolate the CSS pump suction from the RWST, 5) open the CSS pump suction to the containment sump and 6) restart the CSS pumps.After the ECCS recirculation operating mode is established, the RHR pumps inject to the primary system cold legs and supply water to the suction of the CCP and SIP pumps. The CCP and SIP pumps continue to inject to the primary system cold legs. This configuration is referred to as the ECCS cold leg recirculation operating mode.If the containment building pressure exceeds an established high value and more than one hour has elapsed since the start of the event, one train of RHR may be directed to the containment RHR spray headers to assist containment pressure control. This alignment is established by manual operator action.At a time in the event analyzed to prevent boron precipitation in the reactor vessel, recirculation flow to the primary system hot legs is established.

For WBN U1 this is approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the event due to the higher boron requirements for the tritium producing burnable absorber rod program. At this point, for hot leg SI recirculation, the SIP pumps are realigned by manual operator action to inject to the primary system hot legs rather than the cold legs. One RHR pump may also be realigned to supply flow to two loop hot legs. The CCP pumps continue to provide flow to the primary system cold legs. This configuration is referred to as the ECCS hot leg recirculation operating mode.The significant differences between the response to a large break LOCA and a small break LOCA are as follows.E1-33

" Depending on the size of the break, primary system pressure may stabilize at a value that does not allow injection from the RHR pumps and the SIP pumps.* In a small break LOCA scenario, the containment accident pressure may remain below the actuation setpoint for CSS.* In the small break LOCA scenario, drawdown of the RWST inventory may be sufficiently low such that the safe shutdown condition is reached before the RWST low level setpoint for ECCS switchover is reached." The quantity of debris generated in the small break LOCA scenariolis a fraction of the total design basis debris used. to evaluate containment sump strainer performance.

3.g. 7. Describe the single failure assumptions relevant to pump operation and sump performance.

TVA Response The limiting single failure assumption for those transients which require containment sump recirculation operation at WBN (i.e., large break LOCA and small break LOCA) is the complete loss of one train of ECCS equipment.

3.g. 8. Describe how the containment sump water level is determined.

TVA Response The containment sump water level is established by comparison of the sump and lower containment volumes which are available to collect water for recirculation to the minimum volume of water discharged during the event reduced by the volume which is unavailable to the sump/lower containment.

The sump and lower containment volumes available to collect recirculation inventory was established by calculation of the available free volume in the areas which communicate with the event discharge sources and the recirculation sump intake.Discharge sources for the sump recirculation inventory are based on the nature of the event and the safety system responses.

The sources include 1) primary system inventory, 2) cold leg accumulator inventory, 3) RWST inventory and 4) ice condenser ice melt inventory.

Discharge volumes which are unavailable to the sump recirculation volume include 1) water held up in the reactor cavity, 2) water held up on the operating deck floor, 3) water in the upper containment atmosphere, 4) refueling canal holdup, 5) water in the containment spray piping, and 6) pocket sump holdup. Additionally, in the long term, excess water spills from inside the crane wall through unsealed penetrations into the raceway where it is unavailable for future recirculation.

E1-34 3.g.9. Provide assumptions that are included in the analysis to ensure a minimum (conservative) water level is used in determining NPSH margin.TVA Response The significant assumptions included in the containment sump level analysis to ensure that a minimum water level is applied to the ECCS and CSS pump NPSH evaluation are as follows.AssumptionsApplicable to the Minimum Level for a Large Break LOCA (1) The maximum flow rates for two trains of ECCS and CSS pump flow are assumed for-the pumps taking suction from the RWST during the injection phase. The amount of water in the sump at any given time will come from a combination of 1) RWST water, 2)water from the primary system, 3) accumulator discharge and 4) ice melt. The primary system and accumulator water volumes are independent of the number of operating trains of ECCS/CSS pumps. If only one train of ECCS and CSS are operating, the time to deplete the RWST will be longer than for the two train case. In both cases, the total volume of water discharged at the time the RWST water is depleted will be the same.With the extended depletion time in the single train case, more ice will be melted by the time the RWST empties. Therefore, at the time the RWST empties more water will have accumulated in the sump for the one train case than for the two train case. Using maximum flow rates (as opposed to nominal or minimum guaranteed flow rates) for the pumps will provide the shortest depletion time of the RWST which further limits the amount of ice melt. The maximum flow rates in combination with operation of two trains of ECCS and CSS minimizes the amount of water in the sump at both the low level switchover setpoint and the low-low level CSS realignment setpoint in the RWST.(2) The initial water level in the RWST is the "minimum full" level and was conservatively chosen to minimize the water delivered to the containment sump thereby minimizing the water level in the containment sump.(3) Water droplets from the containment spray will remain constant in size. The amount of CSS water suspended in the atmosphere is dependent on the droplet size. The smaller drops conservatively increase the amount of suspended CSS water.(4) A reduction in the lower containment volume to account for equipment and structures in the lower containment is included in the calculation.

This allowance is not used for the sump pocket, the refueling canal, or the reactor cavity, since they do not contain equipment.

(5) All CSS flow falling onto the reactor enclosure in the upper compartment is assumed to flow to the operating deck prior to entering the refueling canal. This is a simplifying assumption which is conservative since it maximizes the water volume held up on the operating deck by increasing the height of water (and thereby the holdup) required to provide a flow into the refueling canal equal to the containment spray rate that falls on the floor.Assumptions Applicable to the Minimum Level for Small Break LOCA (1) The small break LOCA must be evaluated for two possible scenarios regarding minimum containment sump elevations.

These scenarios are 1) a very small break assumed at E1-35 120 gpm to be slightly above the definition of a LOCA and 2) a more typical small break LOCA of 2000 gpm. Consideration of both scenarios will ensure that the minimum level is calculated.

(2) Limited credit is taken for water from melted ice. Any break that does not activate the.containment spray may release an amount of energy within the capacity of the lower compartment coolers. That size break would melt very little ice.(3) The break is assumed to be located such that break flow is directed to the reactor cavity.This minimizes water in the containment sump.(4) No credit is taken for water from the cold leg accumulators.

The break may be too small to allow the primary system pressure to reach the accumulator dump setpoint.(5) Because of the small break size possible, the only credit taken for primary system inventory discharge is the SBLOCA flow rate.3.g. 10. Describe whether and how the following volumes have been accounted for in pool level calculations:

empty spray pipe, water droplets, condensation, and holdup on horizontal and vertical surfaces.

If any are not accounted for, explain why.TVA Response The volumes for empty spray pipe, water droplets, vapor content, and holdup on horizontal and vertical surfaces have been accounted for in the WBN pool level calculations as follows.Empty Spray Pipe -The volume of the containment spray pipe and header that is empty during normal operation was calculated.

Water Droplets -The volume of water suspended between the spray header exit and the operating deck/ refueling canal was calculated for steady state conditions is a function of 1)CSS spray flow, 2) fall distance and 3) vertical droplet velocity.

The vertical droplet velocity was established as a function of droplet size (mass) and the drag force exerted on the droplet due to the resistance of the upper compartment atmosphere.

Condensation

-Mass and energy released from the primary system in the form of steam was condensed by the ice condenser and was included in the sump discharge volume used to establish sump level. No credit was taken for condensation on other lower containment structures.

Horizontal and Vertical Surface Holdup -The volume of water suspended in horizontal or on vertical surfaces was accounted for and subtracted from the sump discharge volume as follows.* Reactor Cavity Volume -The reactor cavity volume was assumed to fill initially as a result of the high energy line break." Operating Deck -Water will accumulate on the operating deck, steam generator enclosure roof, and pressurizer enclosure roof before draining into the refueling canal. The curbing surrounding the operating deck and pressurizer enclosure roof acts similar to a weir. The steam generators do not have the curb over approx 25% length. The water accumulation on E1-36 the operating deck and enclosure roofs was calculated for the curb height under equilibrium conditions (i.e., flow onto the surface equals the flow off the surface into the refueling canal)using relationships developed for a rectangular weir.* Refuelinq Canal -During CSS operation, water falling on the upper containment surfaces will collect in the refueling canal prior to draining to the lower containment sump through two 14 inch diameter drains in the canal. Water will collect in the canal until the drain flow out of the canal is equal to equal the containment spray flow. The level of water suspended in the canal was calculated for equilibrium conditions as function of 1) canal drain flow resistance, 2) canal level (i.e., driving head though the drains) and 3) containment spray flow rate. The volume of water suspended in the refueling canal was established from the equilibrium level of water held up in the canal* Accumulator Rooms -During operation of the containment air return fans, the upper containment atmosphere is recirculated to the lower containment through Accumulator Rooms 3 and 4 (which are located outside the crane wall). Since the upper containment atmosphere contains suspended droplets of containment spray, a portion of the containment spray will be directed to the accumulator rooms by the air return fans, where the inventory will drain back inside the polar crane wall for sump recirculation.

The impact of this flow was evaluated.

3.g. 11. Provide assumptions (and their bases) as to what equipment will displace water resulting in higher pool level.TVA Response The volume of the major equipment and structures which have the potential to be submerged during sump recirculation operations was established by calculation.

The equipment included in this volume calculation included primary system piping, primary system piping supports, the reactor coolant pumps, and RHR system piping.3.g. 12. Provide assumptions (and their bases) as to what water sources provide pool volume and how much volume is from each source.TVA Response Water sources for the sump recirculation pool inventory are based on the nature of the event and the safety system responses.

The sources include 1) primary system inventory, 2) cold leg accumulator inventory, 3) RWST inventory and 4) ice condenser ice melt inventory.

The volumes of water credited from these sources in the WBN minimum containment sump level calculation were established as follows.1) Primary System Inventory

-For a large break LOCA, it is assumed that the primary system inventory will drain to approximately the bottom of the reactor vessel nozzles. The primary system inventory was established by subtracting the volume in the reactor vessel below the reactor nozzles (less the volume of the reactor core and vessel internals) from the nominal primary system operating volume. For a small break LOCA, only the leakage flow until switchover is considered for the primary system inventory.

E1-37

2) Cold Leg Accumulator Inventory

-For a large break LOCA, it is assumed that the cold leg accumulator volume is equal to the minimum contained volume for operability for 3 of 4 accumulators.

For a small break LOCA, no credit is taken for the volume of the accumulators.

3) RWST Inventory

-For both the large and small break LOCA, the RWST inventory is established by subtracting the retained volume at the low-low CSS pump shut-off setpoint from the initial value which is assumed to be equal to the minimum contained volume for operability.

4) Ice Melt Inventory

-For a large break LOCA, the ice melt inventory is established by determining the amount of ice melted from the long term containment integrity analysis at the earliest sump recirculation initiation time (i.e., when the RWST low level setpoints are reached).

The earliest sump recirculation time is based on the quickest RWST drawdown time (which occurs with two trains of ECCS and CSS pumps in service).

Application of the minimum sump recirculation initiation time minimizes the amount of ice melted and the contribution of the ice melt to sump level. For a small break LOCA, limited credit is taken for ice melt inventory.

The volume of water from each of the sources used in the sump minimum level calculation is as follows: WBN Sump Recirculation Pool Source Inventory Summary (RHR switchover)

Large Break LOCA Small Break LOCA*Primary System Inventory 54,610 gallons 42,810 gallons Cold Leg Accumulator Inventory 22,900 gallons 0 gallons RWST Inventory 202,000 gallons 202,000 gallons Ice Melt Inventory 154,500 gallons 50,752 gallons Total 434,000 gallons 295,561 gallons 2000 gpm SBLOCA case shown, 120gpm SBLOCA also analyzed for strainer performance with slightly more limiting water level results.3.g. 13. If credit is taken for containment accident pressure in determining available NPSH, provide description of the calculation of containment accident pressure used in determining the available NPSH.TVA Response No credit is taken for containment accident pressure in determining the available NPSH for sump recirculation operation for WBN.3.g. 14. Provide assumptions made which minimize the containment accident pressure and maximize the sump water temperature.

TVA Response The WBN containment sump NPSH calculations assume that containment pressure remains at the minimum internal building pressure of 14.3 psia. The calculations also assume that the sump recirculation inventory temperature is a constant 190 0 F. This value represents maximum E1-38 post-accident sump temperature as established by the plant long term containment integrity analysis.3.g. 15. Specify whether the containment accident pressure is set at the vapor pressure corresponding to the sump liquid temperature.

TVA Response The WBN containment sump operation NPSH calculations assume that containment pressure remains ata minimum building pressure of 14.3 psia. The vapor pressure of the sump inventory corresponds to the vapor pressure of the maximum sump liquid temperature (i.e., 9.34 psia for a temperature of 190 0 F).3.g. 16. Provide the NPSH margin results for pumps taking suction from the sump in recirculation mode.TVA Response The available excess NPSH for WBN sump recirculation operation is as follows: WBN Excess NPSH for Containment Sump Recirculation Operation at RHR Switchover Small Break LOCA Excess Pump Large Break LOCA NPSH Excess NPSH 2 pm 2000 gpm A RHR Pump 13.5 ft 12.0 ft B RHR Pump 14.6 ft 13.1 ft A CSS Pump 10.6 ft 9.1 ft B CSS Pump 8.8 ft 7.2 ft 3.h. Coatings Evaluation The objective of the coatings evaluation section is to determine the plant-specific ZOI and debris characteristics for coatings for use in determining the eventual contribution of coatings to overall head loss at the sump screen.3.h. 1. Provide a summary of type(s) of coating systems used in containment, e.g., Carboline CZ 11 Inorganic Zinc primer, Ameron 90 epoxy finish coat.TVA Response As described previously, carbon steel surfaces inside WBN containment are generally coated with CarbozincTM 11 (an inorganic zinc primer). All steel 6 feet from the containment floor has also been top coated with PhenolineTM 305. The containment liner is also coated with CarbozincTM 11 and has been left without a topcoat. Even though failure of this coating is not likely, it has been conservatively assumed to fail. The concrete floors and walls have been painted with PhenolineTM 305. All concrete below 6 feet has been painted with a CarbolineTM 295 surfacer and then painted with two coats of PhenolineTM 305. The original steam generators were coated with CarbolineTM 4674 underneath the RMI insulation. (Note: the debris analysis was performed for the original steam generators which have since been removed and replaced with upgraded steam generators in U1 RFO7. The replacement generators are E1-39 uncoated.

The debris generation analysis continues to bound the current Ul configuration).

The original CarbolineTM 4674 coating is a high temperature silicone that was not DBA qualified and was assumed to fail as fines if the RMI that encapsulates it fails. All qualified coatings outside the coatings ZOI will remain intact 3.h.2. Describe and provide bases for assumptions made in post-LOCA paint debris transport analysis.TVA Response The significant assumptions included in the post-LOCA debris transport analysis and the bases for those assumptions are as follows.General Assumptions

1) It was assumed that 1 inch to 4 inch pieces of RMI debris can be conservatively treated as1/2 inch pieces and 4 inch to 6 inch pieces can be conservatively treated as 2 inch pieces for transport purposes.

This is a conservative assumption designed to maximize transport based on size.2) It was assumed that the settling velocity of fine debris (dirt/dust and paint particulate) can be calculated using Stokes' Law. This is a reasonable assumption since the particulate debris is generally spherical and would settle slowly (within the applicability of Stokes' Law).3) It was conservatively assumed that the transportable miscellaneous debris addressed in the debris generation calculation including tags, labels, etc. as well as debris trapped in the ice condenser, would be transported to the emergency sump during recirculation.

This is a conservative assumption designed to maximize this debris type at the sump strainers.

Debris Transport Logic Tree Assumptions

4) It was assumed that all fines generated by the LOCA would be blown upward into the ice condenser.

This is a reasonable assumption since the plant is designed to relieve steam from the blowdown into the ice condenser, and fine debris generated by the LOCA would be easily entrained and carried with the blowdown flow.5) The small and large piece debris (RMI) was assumed to fall to the floor of containment.

In reality, some of the RMI debris would likely be blown into the ice condenser.

However, since RMI pieces would not transport as easily as fine debris (around corners, past equipment, etc), it would be difficult to accurately determine the blowdown transport fraction.

In order to analyze the transport of RMI, a conservative initial distribution of the RMI at the beginning of recirculation was used.6) It was conseryatively assumed that all debris blown upward would be trapped by the ice baskets and subsequently washed back down with the melting ice flow.7) During pool fill-up, it was conservatively assumed that a fraction of the fine debris would be transported directly to the sump strainer as the sump cavity fills with water. This fraction was determined based on the ratio of the sump cavity to the pool volume at the point where when the sump cavity is filled (6-inch water level). No debris would be transported to the inactive incore tunnel/reactor cavity, or outside the crane wall until after recirculation has E1-40 been initiated, since all points of communication with these areas are above the minimum water level.Debris Distribution at the Beginning of Recirculation

8) It was conservatively assumed that all latent debris is in lower containment.

Some of this debris could be transported to the sump strainer during fill-up, but the remainder was assumed to be uniformly distributed in the containment pool at the beginning of recirculation.

This is a conservative assumption since no credit is taken for debris remaining on structures and equipment above the pool water level.9) The unqualified coatings in upper containment were assumed to be washed down at some point during recirculation (as opposed to being washed down during pool fill-up and spread around the pool). This is a conservative assumption since the two drain lines discharge next to the sump screens.10) It was assumed that the unqualified coatings in lower containment would enter the recirculation pool in the vicinity of the location where they were applied. This is a reasonable assumption since unqualified coatings outside the ZOI would break down gradually, and would likely fail after recirculation has been initiated.

11) It was assumed that the debris washed down by the ice melt flow would enter the pool below the ice melt drain lines during recirculation (as opposed to the debris entering the pool before recirculation is initiated and subsequently migrating to other portions of the pool).This is a conservative assumption, since the local turbulence caused by the ice melt flow would increase the likelihood of transport.

12) It was assumed that small and large piece debris would be uniformly distributed between the locations where it is destroyed and the closest sump screen. This is a conservative assumption since it neglects the fact that some debris would be blown or washed to areas farther away from the sump during the blowdown and pool fillkup phases.3.h.3. Discuss suction strainer head loss testing performed as it relates to both qualified and unqualified coatings and what surrogate material was used to simulate coatings debris.TVA Response The WBN containment sump strainer test program is described in the response to Item 3.f.3 above. The various debris loads used in the strainer testing established the ability of the sump strainer design to accommodate coating debris equal to the total amount of qualified and unqualified coatings inside containment.

This included coating failure modes as fines (maximum transport) and chips (maximum blockage).

Surrogate materials used to simulate coating debris in the testing were as follows." Silicon Carbide -This material was substituted for phenolic, alkyd and silicone coatings where the coatings were assumed to fail as particulates.

• Amerlock 400 NT -This material was substituted for phenolic, alkyd and silicone coatings where the coatings were assumed to fail as chips.El-41

• Tin Particles

-This material was substituted for inorganic zinc coatings which were assumed to fail as particulate.

3.h.4. Provide bases for the choice of surrogates.

TVA Response The surrogate materials described in the response to Item 3.h.3 above were selected on the following basis.o Silicon Carbide -The actual phenolic, alkyd, and silicone coatings used inside the WBN containment building are no longer available.

Silicon carbide was selected as a substitute for these materials based upon sufficient similarities in material density and particle size distribution.

o Amerlock 400 NT -The actual phenolic, alkyd, and silicone coatings used inside the WBN containment building are no longer available.

Amerlock 400 NT was selected as a substitute for these materials based upon sufficient similarities in material density and chip size distribution.

o Tin Particles

-This material was substituted for inorganic zinc particulate because zinc is considered to be a hazardous material.

Tin was substituted for zinc based on similarities in material density and particle size distribution.

3.h. 5. Describe and provide bases for coatings debris generation assumptions.

For example, describe how the quantity of paint debris was determined based on ZOI size for qualified and unqualified coatings.TVA Response The type, quantity, and size distribution of coating debris generated following a postulated high energy line break at WBN was established based on the following methods/assumptions.

1) A containment walkdown was performed to identify and locate coatings in lower containment.

2) Pipe break locations were selected based on the accident scenarios that could lead to containment sump recirculation operation.

3) An affected coating ZOI was established from an assumed equivalent spherical ZOI radii to pipe break diameter ratio (r/D) of 10.0.4) The quantity of coating debris generated was determined based on 1) all coatings (qualified or unqualified) in the pipe break ZOI will fail, 2) all qualified coatings outside of the ZOI will remain intact and 3) all unqualified coatings outside of the ZOI will fail.5) All coatings within the ZOI were assumed to fail as 10 micron particulate.

Unqualified coatings (alkyd, inorganic zinc, and modified silicone paint) outside the ZOI in lower containment or subject to spray in the upper containment were also assumed to fail as 10 micron particulate.

The methods/assumptions included in the WBN coating debris generation analysis are consistent with NEI 04-07 and the associated the NRC SER.El-42 3.h.6. Describe what debris characteristics were assumed, i.e., chips, particulate size distribution, and provide bases for the assumptions.

TVA Response A detailed description of the failed coating characteristics is contained in the response to Item 3.c.1 above. The assumed characteristics of the failed coating debris for WBN are consistent with NEI 04-07 and the associated NRC SER (as well as applicable test data).3.h. 7. Describe any ongoing containment coating condition assessment program.TVA Response The current TVA protective coating program contains requirements for conducting periodic visual examinations of Coating Service Level I and Level II protective coatings.

The inspections are performed as part of the plant preventative maintenance program to periodically evaluate the condition of the applied coatings and determine their capability for performing their intended function.

These inspections are performed by qualified personnel according to established inspection plans and acceptance criteria.

Coating defects identified as part of the periodic inspection are identified and placed in the plant corrective action program for evaluation and disposition.

Additionally, a separate general inspection of all Coating Service Level I coating is performed during each refueling outage. Coating defects identified as part of the outage inspection are identified and placed in the plant corrective action program for evaluation and disposition.

3.i. Debris Source Term The objective of the debris source term section is to identify any significant design and operational measures taken to control or reduce the plant debris source term to prevent potential adverse effects on the ECCS and CSS recirculation functions.

Provide the information requested in GL 04-02 Requested Information Item 2. (f0 regarding programmatic controls taken to limit debris sources in containment.

GL 2004-02 Requested Information Item 2(f)A description of the existing or planned programmatic controls that will ensure that potential sources of debris introduced info containment (e.g., insulations, signs, coatings, and foreign materials) will be assessed for potential adverse effects on the ECCS and CSS recirculation functions.

Addressees may reference their responses to GL 98-04, 'Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System after a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment, 'to the extent that their responses address these specific foreign material control issues.In responding to GL 2004 Requested Information Item 2(f), provide the following:

• A summary of the containment housekeeping programmatic controls in place to control or reduce the latent debris burden. Specifically for RMI/low-fiber plants, provide a description of E1-43 programmatic controls to maintain the latent debris fiber source term into the future to ensure assumptions and conclusions regarding inability to form a thin bed of fibrous debris remain valid." A summary of the foreign material exclusion programmatic controls in place to control the introduction of foreign material into the containment.

• A description of how permanent plant changes inside containment are programmatically controlled so as to not change the analytical assumptions.

and numerical inputs of the licensee analyses supporting the conclusion that the reactor plant remains in compliance with 10 CFR 50.46 and related regulatory requirements.

• A description of how maintenance activities including associated temporary changes are assessed and managed in accordance with the Maintenance Rule, 10 CFR 50.65.If any of the following suggested design and operational refinements given in the guidance report (guidance report, Section 5) and SE (SE, Section 5. 1) were used, summarize the application of the refinements." Recent or planned insulation change-outs in the containment which will reduce the debris burden at the sump strainers.

• Any actions taken to modify existing insulation (e.g., jacketing or banding) to reduce the debris burden at the sump strainers.

• Modifications to equipment or systems conducted to reduce the debris burden at the sump strainers.

• Actions taken to modify or improve the containment coatings program TVA Response Design and administrative controls are in place at WBN to ensure that potential quantities of post-accident debris are maintained within the bounds of the analyses and design bases that support ECCS and CSS recirculation functions.

The following is a summary of the procedures and engineering specifications which constitute the present containment material control and inspection requirements at WBN that pertain to ensuring operability of the containment sump.1) Surveillance Instruction 1-SI-304-2, "18 Month ECCS Containment Sump Inspection" -Verifies the integrity and cleanliness of the EGOS containment sump, containment spray piping, RHR suction piping, and floor drains in Accumulator Rooms 3 and 4.2) Technical Instruction TI-61.003, "Ice Condenser Loose Debris Log" -A procedure that describes the steps to record, track, and evaluate any debris in the ice condenser.

3) Standard Programs and Processes (SPP) SPP-10.7, "Housekeeping/Temporary Equipment Control" -A procedure that delineates controls for housekeeping, material condition, and temporary equipment at TVA nuclear sites. This encompasses housekeeping responsibilities for all workers to preserve the quality of the work environment and the material condition of the plant.4) SPP-6.0, "Maintenance and Modifications" -This maintenance and modification process ensures that conduct of maintenance activities and the physical implementation of design changes support safe operation of the station.E1-44

5) SPP-9.3, "Plant Modifications and Change Control" -This procedure establishes a uniform process of administrative controls and regulatory/quality requirements for plant modifications and changes to engineering documents.

It includes consideration of materials introduced into the containment that could contribute to sump strainer blockage.6) SPP-9.5, "Temporary Alterations" -This procedure provides the requirements for controlling temporary alterations to systems, structures and components (SSCs) of TVA's 10 CFR 50 and 10 CFR 72 facilities in a manner which ensures operator awareness, conformance with design basis and operability requirements, and preservation of plan safety and reliability.

7) Technical Instruction TI-12.07, "Containment Access" -This instruction provides documentation of containment entry/exit and cleanliness (housekeeping) requirement when the plant is in Modes 1 through 4. Performance ensures no loose debris (rags, trash, clothing, failed protective coatings, tools, etc.) is present in containment, specifically debris that could impact RHR, CSS, and ECCS operability due to adverse impact on the containment sump.8) SPP-6.5, "Foreign Material Control" -This procedure provides the requirements for maintaining cleanliness by preventing the uncontrolled introduction of foreign material such as maintenance residue, dirt, debris, or tools into open systems or components, and recovery from intrusion of foreign material.9) General Engineering Specification G-55, "Technical and Programmatic Requirement for Protective Coating Program at TVA Nuclear Plant" -This engineering specification provides the technical and programmatic requirements for the protective coating programs at TVA nuclear plants.10) Modification/Addition Instruction MAI-5.3, "Protective Coatings" -This procedure covers the technical and verification requirements to implement a protective coating program at WBN that meets TVA's commitments as defined in Engineering Specification G-55.11) Technical Instruction TI-279, "Modification Review for Sources and Quantities of Aluminum and Zinc" -This procedure provides the requirements for controlling design changes and modifications to ensure the inventory of light metals (aluminum and zinc) inside containment is maintained within FSAR limits and design bases. TVA is committed to USNRC Regulatory Guide 1.7 which states under section C.6, "Materials within the containment that would yield hydrogen gas due to corrosion from the emergency cooling or containment spray solutions should be identified, and their use should be limited as much as practical." Collectively, these documents provide the technical and programmatic controls necessary to ensure that design change, maintenance, and modification activities are conducted in a manner that assures operability of the containment sump.Additionally, during the current WBN refueling outage, U1RFO8, a few large pieces of min-K insulation installed on secondary side piping inside containment will be removed under DCN 51755/PIC 52187 and replaced with RMI. Also, .several smaller pieces of min-K used for hot pipe/conduit protection will be banded or replaced under DCN 52226 and DCN 52226/PIC 52314. These modifications will bring the min-K quantity and installation in compliance with the latest debris generation analysis and conform to the tested configuration in the jet impingement tests (ZOI) described above.E1-45 3.j. Screen Modification Package The objective of the screen modification package section is to provide a basic description of the sump screen modification.

3.J. 1. Provide a description of the major features of the sump screen design modification.

TVA Response The WBN advanced design containment sump strainers are based on a "stacked disk" strainer design manufactured by Performance Contracting, Incorporated (PCI). The "stacked disk" design is comprised of a series approximately 1 inch thick disks covered with a stainless steel skin which is punched with 0.085 inch diameter flow openings.

After passing through the strainer skin, intake flow is directed to a central flow channel. The strainer disks are stacked upon top each other to from strainer modules.WBN has one recirculation strainer assembly that feeds a common suction sump via a plenum.The single strainer assembly consists of. 23 vertically oriented strainer stacks, 14 of which are taller Type "A" strainers and 9 of which are shorter Type "B" strainers.

Each of the Type "A" strainers consists of 4 strainer modules that are vertically stacked on top of each other. The first module has 7 disks and the other three modules have 6 disks. Each of the Type "B" strainers consists of 3 strainer modules that are vertically stacked on top of each other with each having 7 disks. The 23 strainers provide a total of 4,675.1 ft 2 of area. Flow leaves each of the strainers where it enters a rectangular, horizontally oriented, collection plenum that is positioned over the top of the sump pit.E1-46 3.j.2. Provide a list of any modifications, such as reroute of piping and other components, relocation of supports, addition of whip restraints and missile shields, etc., necessitated by the sump strainer modifications.

TVA Response The only modifications required to support installation of the advance design sump strainers were demolition of the original flat plate sump intake screen and the minor rerouting of electrical conduit to establish the required clearances.

3.k. Sump Structural Analysis The objective of the sump structural analysis section is to verify the structural adequacy of the sump strainer including seismic loads and loads due to differential pressure, missiles, and jet forces.Provide the information requested in GL 2004-02 Requested Information Item 2(d)(vii).

GL 2004-02 Requested Information Item 2(d) (vii)Verification that the strength of the trash racks is adequate to protect the debris screens from missiles and other large debris. The submittal should also provide verification that the trash racks and sump screens are capable of withstanding the loads imposed by expanding jets, missiles, the accumulation of debris, and pressure differentials caused by post-LOCA blockage under flow conditions.

.3.k. 1. Summarize the design inputs, design codes, loads, and load combinations utilized for the sump strainer structural analysis.TVA Response The structural evaluations of the WBN sump strainers and flow plenum assembly were performed using a combination of manual calculations and finite element analyses using the GTSTRUDL Computer Program and the ANSYS Computer Program. The evaluations follow requirements imposed by the TVA Design Specification for the containment building sump strainers which are consistent with the plant design and licensing basis requirements.

A summary of the design inputs, design codes, loads and load combinations used in the strainer/plenum structural analyses are as follows.Design Input The design inputs used in the structural analysis of the WBN sump strainers and plenum assembly consisted of the following.

1) Strainer/plenum arrangement and dimensional data from the appropriate component design and fabrication drawings.2) Strainer/plenum material types from the appropriate component design and fabrication drawings.3) Design and maximum operating temperatures from the strainer/plenum design specification

4) WBN plant specific seismic acceleration response spectra from the strainer/plenum design specification.

El-47

5) Structural analysis load type, combinations, and acceptance criteria from the strainer/plenum design specification.

Design Codes The WBN containment sump strainers and flow plenum assembly were designed, fabricated, and inspected in accordance with the following codes and standards.

Unless otherwise stated, the standards were the latest in effect on the date of the purchase order.1) American Institute of Steel Construction (AISC), Speciation for the Design, Fabrication, and Erection of Structural Steel for Buildings, 7 th Edition, adopted February 12, 1969.2) ASME Section II, "Material Specifications." 3) ASME Section III, Division 1, Subsection NF, "Supports," 2004 Edition thru July 2005 Addenda.4) ASME Section V, "Non-Destructive Examination," 2004 Edition thru July 2005 Addenda.5) ASME Section IX, "Welding and Brazing Qualification," 2004 Edition thru July 2005 Addenda.6) AWS D1.6 -1999, "Structural Welding Code -Stainless Steel." The primary design and fabrication standard for the WBN strainer equipment was the AISC standard cited above. The equipment structural analysis acceptance criteria were primarily established in accordance with this standard.

In circumstances where the AISC Code does not provide adequate guidance for a particular component, other codes or standards are used for guidance.

These alternate codes are discussed briefly below. .The AISC Code does not provide any design guidelines for perforated plate. Therefore, the equations from Appendix A, Article A-8000 of the ASME B&PV Code,Section III, 1989 Edition, were used to calculate the perforated plate stresses.

The acceptance criteria are also based on this code. In addition, the AISC Code does not specifically cover stainless steel materials.

Since the strainers are fabricated entirely from stainless steel, the ANSI/AISC N690-1994,."Specification for the Design, Fabrication, and- Erection of Steel Safety Related Structures for Nuclear Facilities" was used to supplement the AISC in any areas related specifically to the structural qualification of stainless steel. Only the basic acceptance criteria (allowable stresses)are used from the ASME Code and load combinations and allowable stress factors for higher service level loads are not used.The strainer also has several components made from thin gage sheet steel and cold formed stainless sheet steel. For these components SEI/ASCE 8-02, "Specification for the Design of Cold-Formed Stainless Steel Structural Members" was used where rules specific to thin gage and cold form stainless steel are applicable.

The rules for Allowable Stress Design (ASD) as specified in Appendix D of this code were used. This is further supplemented by the AISI Code where the ASCE Code is lacking specific guidance.

Finally guidance is also taken from AWS D1.6, "Structural Welding Code Stainless Steel" as it relates to the qualification of stainless steel welds.Structural Analysis Loads, Load Combinations, and Acceptance Criteria The structural analysis of the strainers and associated flow plenum considered the following design basis loads.1) DW -Strainer and support dead weight loads and forces.E1-48

2) TOL -Thermal effect loads during normal operation (loads imposed by a conservatively assumed maximum normal operating temperature of 140 0 F)3) OBE -Seismic loads generated by the operating basis earthquake

4) SSE -Seismic loads generated by the safe shutdown earthquake

5) TAL -Thermal effect loads during accident operation (loads imposed by the maximum accident operating temperature of 190 0 F)6) JIL -Jet impingement equivalent static load (if applicable)

-Note 3 7) DIL -Debris impact equivalent static load 8) DP -Differential pressure across perforated plates and other pressure boundaries

-Note 4 9) DEB -Debris Weight -Note 5 These design basis loads were combined and confirmed to meet the indicated acceptance criteria as follows: Load Combination 1 -DW + DP + DEB < S Note 1 Load Combination 2 -DW + OBE _< S Note 1 Load Combination 3 -DW + TOL + OBE < 1.5 x S Note 1 Load Combination 4 -DW + TOL + SSE < 1.6 x S Note 1 Load Combination 5 -DW + DP + DEB + TAL < 1.6 x S Note 1 Load Combination 6 -DW + JIL + DIL + SSE < 1.6 x S Note 2 Notes 1) For structural steel, the "S" value is the required section strength based on the elastic design methods and the allowable stresses defined in Part 1 of the AISC specification, Seventh Edition. The 33 percent increase in allowable stresses for steel due to seismic or wind loadings permitted by the AISC standard was not applied to this evaluation.

When alternate standards were used to supplement the AISC specification as indicated below, the "S" value was consistent with the AISC definition except that the allowable stresses were taken from the alternate standard.For perforated plates, the "S" value was the allowable stress from the ASME Section III Boiler and Pressure Vessel Code,Section III, 1989 Edition including Appendix A, Article A-8000 provisions for calculating perforated plate stresses.For concrete anchor bolts, the tensile and shear forces shall not exceed the allowable loads for the selected anchor bolts in TVA Design Standard No.DS-C1.7.1 Revision 11. TVA concurrence with anchor bolt selection required.

Thermal stresses on anchor bolts shall be considered and minimized by the design.2) The AISC allowable load combination for Load Case 6 shall not exceed the following limits 0.9 x FY for Tension or Bending Stress (0.9 x Fy) + (3.0)05 for Shear Stress 0.9 x Fcritical buckling for Compression Stress where Fy = minimum specified yield strength of the material, and Fcritical buckling = the compressive stress calculated by the AISC equations without the appropriate factor of safety E1-49

3) The jet impingement load (JIL) and debris impact load (DIL) are negligible for the final strainer design.4) The differential pressure (DP) shall be the component design basis 3.5 feet of water.5) Debris weight shall be considered for Loading Combinations 1 and 5. The debris weight on the strainer structure shall be the larger of 25 pounds per square foot applied to the total strainer/flow plenum horizontal footprint area or the maximum calculated debris weight transported to the strainer under design basis operating, conditions.

6) It is not necessary to consider hydrostatic or hydrodynamic loads for the load combinations which include OBE and SSE loads.7) Since stainless steel does not display a single, well defined modulus of elasticity, the allowable compression stress equations from the AISC specification, Seventh Edition shall not be applied to stainless steel materials.

For stainless steel materials, the allowable compression stress will be based on the lower allowable from ANSI/AlSC N690-1994.

The allowable stresses for tension, shear, bending and bearing for stainless steel materials shall be taken from the allowables provided for carbon steel in the AISC specification, Seventh Edition.E1-50 3.k.2. Summarize the structural qualification results and design margins for the various components of the sump strainer structural assembly.TVA Response The structural analysis of the strainer and flow plenum assemblies established that they meet the structural acceptance criteria for all applicable loadings.

A summary of the limiting stress interaction ratios (i.e., calculated stress divided by allowable stress) is as follows: WBN Containment Sump Strainer and Flow Plenum Structural Analysis Interaction Ratios Maximum Maximum Strainer Component Stress Flow Plenum Component Stress Ratio ___________

__ Ratio Radial Stiffener (w/ Collar). 0.85 Support Beams 0.09 Tension Rods 0.46 Support Floor Beam Local 0.94________Web Edge Channels 0.81 Top Cover Plate 0.60 Cross Bracing 0.41 Lower Deck Plate 0.25 Hex Coupling 0.30 Plate Beam Over Pit 0.24, Core Tube 0.18 Hex Couplings 0.22 Radial Stiffeners (Bent Portion) 0.28 Plenum Box Channels 0.17 Spacer 0.86 Plenum Box Channel Local 0.17_______Web Spacer Separation 0.85 Lower Deck Drainage 0.46____ ___ ___ ____ ___ ___ _ __ ___ ___ Perforated Plate Perforated Plate (DP Case) 0.21 Lower Deck Drainage Plate 0.03________Openings Perforated Plate (Seismic Case) 0.04 Top Strip to Hex Couple Bolts 0.48 Perforated Plate (inner Gap) 0.13 Channel to Support Beam 0.32_____ ____ Bolts Inner Gap Buckling 0.19 Channel Local Flange at Bolts 0.93 Wire Stiffener 0.52 Bottom Plates to Beam Bolts 0.20 Perforated Plate (Core Tube End 0.27 Channel Splice Plate Bolts 0.36 Cover DP Case) _____________

Radial Stiffening Spokes of the 0.40 Channel to Channel Splice 0.87 End Cover Stiffener Welds End Cover Sleeve 0.13 Channel Splice Plate 0.64 Weld of End cover Stiffener to 0.11 Channel to Channel Welds at 0.29 End Cover Sleeve Curb Corner Weld of Radial Stiffener to Core 0.09 Concrete Expansion Anchors 0.86 Tube Edge Channel Rivets 0.08 Floor Beam Local Flange at 0.97 Bolts Inner Gap Hoop Rivets 0.03 Clip Angle -to Sump Curb Weld 0.71 End Cover Rivets 0.00 TS to Strip Plate 0.27 Connecting Bolts 0.31 Strip Plate Local Stress at TS 0.28_______________________

________connection El-51 3.k.3. Summarize the evaluations performed for dynamic effects such as pipe whip, jet impingement, and missile impacts associated with high-energy line breaks (as applicable).

TVA Response The location of the WBN containment sump strainers was reviewed relative to the existing containment pipe break dynamic effects analysis.

The strainers are located in a relatively protected location in the lower containment below the refueling cavity as shown in FSAR figures 6.3 and 6.3A. The review found that the location of the strainers was not subject to jet impingement, pipe whip or missile impacts from high energy line breaks inside containment.

This evaluation is consistent with current WBN licensing basis which has deleted the dynamic effects of a primary system pipe break from consideration based on the application of leak-before-break criteria.

As such, jet impingement, pipe whip and debris impact loads were not included in the strainer/plenum assembly structural analysis.--------3 X 3. X 1 /1..,I II)ITYP WON)A.AA iLACOR( BUILDING WALL----* AMENDMENT 6 P L A N. N I S WATTS 3AR NLCLEAR _LLANT FTNAI SAFITY ANALYSIS REFOA-CONTATNMEN-

• SMP rFI. 6.3 -6 E1-52 EL , 8,ý,'1.I1. /I10- /!'n EL 70,2. 78 8 !CI I A I NMI N i-I GON 4 SS-:f;li"J C ,:' 51!)71 I ,Il NI)REAR WALL OF SUM:/L ME:MII-P-I 1/4 " SS WATTS 7AR NUCLEAR :LAN-FINAL SAFETY A ANALYSIS REFPO-1IVENT S.LMPý F[G ..3 -5:A SECTICN A.-N IS 3.k.4. If a backflushing strategy is credited, provide a summary statement regarding the sump strainer structural analysis considering reverse flow.TVA Response The WBN containment sump strainer design does not credit back flushing.

The strainer structural analysis did not consider reverse flow accordingly.

3.1. Upstream

Effects The objective of the upstream effects assessment is to evaluate the flowpaths upstream of the containment sump for holdup of inventory which could reduce flow to and possibly starve the sump.Provide a summary of the upstream effects evaluation including the information requested in GL 2004-02 Requested Information Item 2(d)(iv).GL 2004-02 Requested Information Item 2(d)(iv)The basis for concluding that the water inventory required to ensure adequate ECCS or CSS recirculation would not be held up or diverted by debris blockage at choke-points in containment recirculation sump return flow paths.E1-53 3.1. 1. Summarize the evaluation of the flow paths from the postulated break locations and containment spray washdown to identify potential choke points in the flow field upstream of the sump.3.12. Summarize measures taken to mitigate potential choke points.3.1.3. Summarize the evaluation of water holdup at ,installed curbs and/or debris interceptors.

3.1.4. Describe

how potential blockage of reactor cavity and refueling cavity drains has been evaluated, including likelihood of blockage and amount of expected holdup.TVA Response (items 1 through 4)Containment walkdowns were performed in accordance with the guidance in NEI 02-01. These walkdowns showed that there are three potential chokepoints that could prevent adequate water inventory from reaching the containment sump. The potential chokepoints are the two refueling canal drains and the drains in accumulator rooms 3 and 4.The drains in the Accumulator Rooms allow the small amount of spray flow that directly hits the air return fans to be returned inside the polar crane wall. Curbs are present in the upper compartment around the fan suction that prevents spray water on the refueling floor from spilling through the fans. Thus the only potential debris from the spray system entering the Accumulator Rooms is very small debris that has traveled through the strainers.

Neither the upper compartment nor the Accumulator Rooms are subjected to high energy jets. The only potential for debris in these compartments is failed coatings.

The size of the failed coatings or debris that passes through the spray pumps is small and will not block any of these drains. RMI debris (large or small) will not be present to block these drains. It is therefore concluded, that there will be no water inventory holdup or diversion due to debris blockage at chokepoints.

The 14 inch drains in the refueling canal discharge on opposite sides of the sump strainer area.The plant was designed such that almost all of the spray water flows to lower containment through these two drain lines. If these drain lines were to become clogged with debris, it could eventually starve the sump. However, given the size of these lines and the debris that would be washed down with the sprays (latent debris, paint chips, and possibly a small amount of LOCA generated fines blown past the ice baskets);

these lines are not likely to become clogged.The debris transport analysis also identified one additional "set" of potential chokepoints which could prevent adequate water inventory from reaching the containment sump. That "set" of chokepoints is the twenty ice condenser drains that drain ice melt water from the ice condenser to the lower compartment.

If one of the 20 ice condenser drain lines were to become clogged, the water would flow to one of the other drains. It is not likely that all 20 drains would become clogged. If all drains were to clog, the ice melt water would spill over through the ice condenser bay doors (this is the normal path early in the event when the ice melt overwhelms the drain lines). Therefore this chokepoint is not considered a problem.An inspection for non-LOCA generated material that could potentially obstruct recirculating water is conducted as part of WBN's containment cleanliness inspection program prior to restart following a refueling outage. This program specifically addresses the need to assure that the containment is free of items that could be washed to the sump.3.m. Downstream effects -Components and Systems The objective of the downstream effects, components and systems section is to evaluate the effects of debris carried downstream of the containment sump screen on the function of the E1-54 ECCS and CSS in terms of potential wear of components and blockage of flow streams.Provide the information requested in GL 04-02 Requested Information Item 2(d)(v) and 2(d)(vi) regarding blockage, plugging, and wear at restrictions and dose tolerance locations in the ECCS and CSS downstream of the sump.GL 2004-02 Requested Information Item 2(d)(v)The basis for concluding that inadequate core or containment cooling would not result due to debris blockage at flow restrictions in the ECCS and CSS flow paths downstream of the sump screen, (e.g., a HPSI throttle valve, pump bearings and seals, fuel assembly inlet debris screen, or containment spray nozzles).

The discussion should consider the adequacy of the sump screen's mesh spacing and state the basis for concluding that adverse gaps or breaches are not present on the screen surface.GL 2004-02 Requested Information Item 2(d)(vi)Verification that the close-tolerance subcomponents in pumps, valves and other ECCS and CSS components are not susceptible to plugging or excessive wear due to extended post-accident operation with debris-laden fluids.3.m. 1. If NRC-approved methods were used (e.g., WCAP-16406-P with accompanying NRC SE), briefly summarize the application of the methods. Indicate where the approved methods were not used or exceptions were taken, and summarize the evaluation of those areas.3.m.2. Provide a summary and conclusions of downstream evaluations.

3.m.3. Provide a summary of design or operational changes made as a result of downstream evaluations.

TVA Response (items 1 through 3)The evaluations listed below were developed to address effects of debris carried downstream of the containment sump screen on the function of the ECCS and CSS in terms of potential wear of components and blockage of flow streams. Close-tolerance subcomponents in pumps, valves, and other ECCS and CSS components were evaluated for potential plugging or excessive wear due to extended post-accident operation with debris laden fluids. The evaluations were developed in accordance with WCAP-16406-P, "Evaluation of downstream sump debris Effects in Support of GSI-191" prior to issuance of Revision 1 and accompanying NRC SER. No exceptions were taken to the WCAP-16406-P methodology.

A revision to the evaluation was issued to incorporate the methodology from WCAP-16406-P revision 1. The results of the revised evaluation indicate that the WBN ECCS equipment will adequately perform during the required mission time as detailed in the Tables below.Calculation Note, 'Watts Bar GSI Down Stream Effects Debris Ingestion Evaluation" The quantity of debris in the recirculating fluid that passes through the sump is characterized in terms of volume concentration.

For downstream effects, this debris concentration (y) is defined as the ratio of the solid volume of the debris in the pumped fluid to the total volume of water that is being recirculated by the ECCS and CSS.y =0.0003186 E1-55 The mass of debris in the recirculating fluid that passes through the sump is characterized in terms of parts per million (ppm). For downstream effects, the total initial debris concentration comprised of the individual debris concentrations is defined as the ratio of the solid mass of the debris in the pumped fluid to the total mass of water that is being recirculated by the ECCS and CSS.Debris Type Concentration Fibrous 3 ppm Particulate 308 ppm Coatings 593 ppm Total 904 ppm Calculation Note, "Watts Bar Sump Debris Downstream Effects Evaluation for ECCS Equipment" This evaluation was issued to incorporate the methodology from WCAP-16406-P Revision 1.The results of the revised evaluation indicate that the WBN ECCS equipment will perform adequately during the required mission time. This addresses Open Item 8.The effects of debris ingested through the containment sump screen during the recirculation mode of the ECCS and CSS include erosive wear, abrasion, and potential blockage of flow paths. The smallest clearance found for the WBN heat exchangers, orifices, and spray nozzles in the recirculation flow path is 0.375 inches for the containment and RHR spray nozzles;therefore, no blockage of the ECCS flow paths is expected with a sump screen hole size of up to 0.25 inches (0.25 inches is used for conservatism, the actual sump screen hole size is 0.085 inches).Instrumentation Blockage Evaluation:

The instrumentation tubing is also evaluated for potential blockage of the sensing lines. The transverse velocity past this tubing is determined to be sufficient to prevent debris settlement into these lines, so no blockage will occur. The transverse velocity past this tubing is documented in Table 1. The reactor vessels level instrumentation system (RVLIS) is also evaluated.

The WBN RVLIS is a Westinghouse design and based on this evaluation no effect on its performance.

is expected from the debris.Table 1: Instrumentation Evaluation Location Instrumentation No. Transverse Velocity (ft/s) Failure (yes/no)Charging/SI Flow FT-63-170 12.43 no FE-63-27, 29, 31, 33 14.92 no High Head SI Flow FE-63-20, 151 20.12 no FE-63-159, 160,161,162 22.08 no FE-63-122, 123, 124, 125 19.89 no RHR/Low Head SI Flow FE-63-91, 92 5.99 no Heat Exchanger Evaluation:

The WBN heat exchangers, orifices, and spray nozzles were evaluated for the effects of erosive wear for a constant debris concentration of 904.46 ppm over a mission time of 30 days. The erosive wear on these components is determined to be insufficient to affect the system performance.

The heat exchanger wear and plugging evaluation results are documented in Table 2 and Table 3 below.E1-56 Table 2: Heat Exchanger Wear Evaluation Internal External tactual Failure D0 (in) tm (in) tm (in) .(in) teroded (yes/no)RHR Heat Exchangers 0.625 0.0114 0.0144 0.049 2.28E-4 no Seal Water Heat Exchanger 0.750 0.0046 0.0173 0.049 2.28E-4 no CSS Heat Exchangers 0.750 0.0069 0.0173 0.049 2.28E-4 no Table 3: Heat Exchanger Plugging Evaluation Number Tube ID (in) Plugging (yes/no)RHR Heat Exchangers 2 0.527 no Seal Water Heat Exchanger 1 0.652 no CSS Heat Exchangers 2 0.652 no Orifice Evaluation:

If the orifice inside diameter due to erosive wear is changed by less than 3%, the system performance may be considered negligible.

This criterion was established in WCAP-16406-P which states that an insignificant amount of wear occurs when the system flow through the orifice is changed by less than 3%. This evaluation considers the initial ratio of the diameters before erosive wear and the ratio of the diameters after erosive wear for single plate and multiple plate multiple hole orifices.

It was found that the inside diameters of all the orifices change by less than 3% and therefore are not expected to fail.Flow restricting, wear, and plugging evaluations for the Single plate, multiple plate, and barrel orifices can be found in Table 4 -Table 11 below.Table 5: Multiple Plate Orifice Wear Evaluation At time 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Zaj (in 2) Pipe Area (in 2) f0 Plate 1 12.370 36.456 0.339 Plate 2 11.486 36.456 0.315 Plate 3 13.253 36.456 0.364 At mission time fl (720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />)Plate 1 12.473 36.465 0.342 Plate 2 11.598 36.465 0.318 Plate 3 13.350 36.465 0.366 Table 6: Multiple Plate Orifice Wear Evaluation Failure Orifice Location Number Roi R_ i AQ/Q (yes/no)RHR cold leg injection flow (1) 2 16.246 15.914 0.0104 no RHR cold leg injection flow (2) 2 19.516 19.061 0.0118 no RHR cold leg injection flow (3) 2 13.655 13.408 0.0092 no E1-57 Table 7: Barrel Orifice Wear Evaluation Bore Orifice Velocity Reynolds Friction Location ID No. Size (in) (ft/s) Number Factor SI hot leg injection 1-OR-63-857, 0.7033 269.71 1.22E06 0.026 856, 853, 855 CC pump mini-flow line OR-62-106, 110 2.624 3.56 6.03E04 0.030 CC to SI cold leg 1-OR-63-854, 0.4381 340.94 9.64E05 0.026 injection flow 850, 851,852 SI cold leg injection flow 1-OR-63-860, 0.4909 285.78 9.05E05 0.026 861,859,_858 Table 8: Barrel Orifice Wear Evaluation Location ID No. L (in) fL/d 0 fL/d 1 AQ/Q Failure (yes/no)Sl hot leg injection flow 1-OR-63-857, 12 0.4436 0.4213 0.008 no 856, 852, 855 CC pump mini-flow line OR-62-106, 13 0.1486 0.1468 0.000 no 110 CC to SI cold leg 1-OR-63-854, 12 0.7122 0.6268 0.026 no injection flow 850, 851,852 SI cold leg injection flow 1-OR-63-860, 12 0.6356 0.5856 0.015 no 861,859,_858 , I Table 9: Orifice Plugging Evaluation Orifice Location Number Bore Size (in) Plugging (yes/no)SI hot leg injection flow 4 0.7033 no SI cold leg injection flow 4 0.4909 no CC to Sl cold leg injection flow 4 0.4381 no RHR cold leg injection flow 2 0.75 no Charging pump header 1 1.161 no Spray Wear Evaluation:

The flow is changed by less than 2.5% which is less than the 10% limit, so the nozzles do not fail. See Table 10 for nozzle wear evaluation results.Table 10: Spray Nozzle Wear Evaluation Nozzle Velocity Erosive Wear Flow (ft/sec) (in) D 1 (in) Increase (%)CSS Spray Headers 44.18 1.9E-3 0.3789 2.09 RHR Spray Headers Unit 1 40.69 1.7E-3 0.3783 1.80 Table 11: Spray Nozzle Plugging Evaluation Number per Orifice Size (in) Plugging (yes/no)Header CSS Spray Headers 263 0.375 no RHR Spray Headers Unit 1 142 0.375 no Pump Wear Evaluation:

For pumps, the effect of debris ingestion through the sump screen on three aspects of operability, including hydraulic performance, mechanical shaft seal assembly performance, and E1-58 mechanical performance (vibration) of the pump, were evaluated and are recorded in Table 12.The hydraulic and mechanical performances of the pump were determined to not be affected by the recirculating sump debris. The mechanical shaft seal assembly performance evaluation resulted in the one action item with the suggested replacement of the pumps' carbon/graphite backup seal bushings with a more wear-resistant material, such as bronze. However, since WBN has an Engineered Safety feature (ESF) atmospheric filtration system in its auxiliary building, this action item is not required.Because the increased clearance for the pumps is within the 3X design clearance, no effect on the hydraulic performance of the RHR and CS pumps is expected, see Table 12.Table 12: Hydraulic Performance Evaluation Pump Normal Erosive Abrasive Total Increased 3X Design Wear Wear Wear Wear Clearance Clearance (mils) (mils) (mils) (mils) (mils) (mils)RHR 3.0 3.97E-3 1.98 1.99 27.98 69 CS 0.0 3.97E-3 1.67 1.68 28.67 81 Calculation Note, 'Watts Bar Sump Debris Downstream Effects Evaluation for ECCS Valves" According to the criteria established in WCAP-16406-P, all valves pass their respective evaluations.

A more detailed summary can be found below.Valve Plugging Evaluation:

Twelve valves meet the criteria for specific plugging evaluation.

Because the valves are currently being positioned to ensure that no plugging will result, all of the vales pass the evaluation.

The results are summarized in Table 13 below.Table 13: Valve Plugging Evaluation

1. System Customer ID Type Size (in) Min Clearance (in) Evaluation Results 9 SI 63-542 globe 2 0.0925 No blockage 10 SI 63-544 globe 2 0.0925 No blockage 11 SI 63-546 globe 2 0.0925 No blockage 12 SI 63-548 globe 2 0.0925 No blockage 24 SI 63-550 globe 2 0.0925 No blockage 25 SI 63-552 globe 2 0.0925 No blockage 26 SI 63-554 globe 2 0.0925 No blockage 27 SI 63-556 globe 2 0.0925 No blockage 76 CVCS* 63-582 globe 1.5 0.1257 No blockage 77 CVCS* 63-583 globe 1.5 0.1257 No blockage 78 CVCS* 63-584 globe 1.5 0.1257 No blockage 79 CVCS* 63-585 globe 1.5 0.1257 No blockage Sedimentation:

Twenty three valves meet the requirements for a specific sedimentation evaluation.

All of the valves passed the evaluation; the results are summarized in Table 14 below.E1-59 Table 14: Sedimentation Evaluation

1. System Customer Type Size Min Flow Velocity Acceptable?

ID (in) Rate (gpm) (ft/s) (v 0.42 ft/s)21 Sl FCV-63-22 gate 4 628 16.16 yes 22 SI FCV gate 4 636 16.37 yes________ 152 __ _ _ _ __ _ _ _ __ _ _ _ _ _23 SI FCV gate 4 636 16.37 yes 153__ _ _ _ _ __ _28 SI 63-551 piston check 2 154 15.85 yes 29 SI 63-553 piston check 2 154 15.85 yes 30 SI 63-555 piston check 2 154 15.85 yes 31 SI 63-557 piston check 2 154 15.85 yes 32 SI 63-560 swing check 10 154 0.63 yes 33 SI 63-561 swing check 10 154 0.63 yes 34 SI 63-562 swing check 10 154 0.63 yes 35 SI 63-563 swing check 10 154 0.63 yes 51 RHR FCV-74-33 gate 8 1785 11.48 yes 52 RHR FCV-74-35 gate 8 1785 11.48 yes 56 RHR 63-633 swing check 6 1000 11.44 yes 57 RHR 63-632 swing check 6 1000 11.44 yes 58 RHR 63-634 swing check 6 1000 11.44 yes 59 RHR 63-635 swing check 6 1000 11.44 yes 60 RHR FCV-63-93 ate 8 2096 13.49 yes 61 RHR FCV-63-94 gate 8 2096 13.49 yes 86 RSPRAY FCV-72-40 gate 8 1556 10.01 yes 87 RSPRAY FCV-72-41 gate 8 1556 10.01 yes 88 RSPRAY 72-562 check 8 1556 10.01 yes 89 RSPRAY 72-563 check 8 1556 10.01 yes Wear: Twelve valves met the criteria for a detailed wear evaluation.

No valves passed the evaluation using a constant debris wear model. The results are summarized in Table 15 below.Table 15 -Constant Debris Wear Analysis Customer ID System AA/Ao Acceptable?63-542 SI 89.38% no 63-544 SI 89.38% no 63-546 SI 89.38% no 63-548 SI 89.38% no 63-550 SI 89.38% no 63-552 SI 89.38% no 63-554 SI 89.38% no 63-556 SI 89.38% no 63-582 CVCS 22.48% no 62-583 CVCS 22.48% no 63-584 CVCS 22.48% no 63-585 CVCS 22.48% no El-60 Using the depleting debris wear model detailed in WCAP-16406-P, all valves passed the evaluation.

The results are summarized in Table 16 below.Table 16 -Depleting Debris Wear Evaluation Customer ID System AAIAo Acceptable?63-542 SI 1.20% yes63-544 SI 1.20% yes63-546 SI 1.20% yes63-548 SI 1.20% yes63-550 SI 1.20% yes63-552 SI 1.20% yes63-554 SI 1.20% yes63-556 SI 1.20% yes63-582 CVCS 0.31% yes63-583 CVCS 0.31% yes63-584 CVCS 0.31% yes63-585 CVCS 0.31% yes 3.n. Downstream Effects -Fuel and Vessel The objective of the downstream effects, fuel and vessel section is to evaluate the effects that debris carried downstream of the containment sump screen and into the reactor vessel has on core cooling.3.n. 1. Show that the in-vessel effects evaluation is consistent with, or bounded by, the industry generic guidance (WCAP-16793), as modified by NRC staff comments on that document.

Briefly summarize the application of the methods. Indicate where the WCAP methods were not used or exceptions were taken, and summarize the evaluation of those areas.TVA Response: The following evaluations consider the effects of debris carried downstream of the containment sump screen and into the reactor vessel on core cooling, including fuel and vessel blockage.These evaluations were performed in accordance with WCAP-16406-P,"Evaluation of Long-Term Cooling Considering Particulate and Chemical Debris in the Recirculation Fluid," with no exceptions taken.Calculation Note, 'Watts Bar GSI-191 Downstream Effects- Vessel Blockage Evaluation" In this evaluation it was found that all evaluated dimensions of essential flow paths through the reactor internals are adequate to preclude plugging by sump debris. There is sufficient clearance for debris that may pass the containment sump screen since the limiting dimensions of the essential flow paths in the upper and lower internals are all greater than the maximum debris dimension.

The maximum debris dimension is defined as 2 times the sump screen hole diameters.

The smallest clearance found was 1.85 inches, therefore any screen with holes smaller than 0.92 inches will not cause plugging by debris in the vessel. The WBN replacement sump screen has holes with a diameter of 0.085 inches.El-61 Calculation Note. "Watts Bar GSI-191 Downstream Effects Debris Fuel Evaluation" Further support of this statement is provided by the results of the WCAP-16406-P, Revision 1 evaluation performed for WBN 1 for fibers. The conclusion of the this evaluation indicates that the amount of fibrous debris generated by a large break LOCA in WBN will not produce a fibrous debris build-up on the underside of the fuel bottom nozzle that exceeds the acceptance criterion of 0.027 inches. This conclusion is based on fibrous debris bypass test data specific to WBN conditions.

Since a continuous fiber bed thicker than 0.125 inches does not form, adequate long term core cooling will be provided to all WBN 1 fuel assemblies.

Further, WCAP-16793-NP states that the formation of a fibrous debris bed on the underside of the fuel assembly bottom nozzles will not cause sufficient blockage to prevent long-term core cooling.WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid" In WCAP-16793-NP, three supporting topical areas were evaluated to demonstrate that long-term core cooling would be maintained post-accident with the ECCS aligned to recirculate coolant from the containment sump to the core. The selection of the topical areas was based on the uncertainty perceived to be associated with each area. The evaluations presented are either extreme cases or parametric studies that demonstrate margin in the PWR design. These topical areas are: 1. Evaluation of fuel clad temperature response to blockage at the inlet to the core.2. Evaluation of fuel clad temperature response to local blockages or chemical precipitation on fuel clad surface.3. Evaluation of chemical effects in the core region, including potential for plate-out on fuel cladding.The evaluations performed for the three areas identified above, in conjunction with other information,'

provide reasonable assurance of long-term core cooling for all plants within the scope of the WCAP-16793-NP.

This WCAP is applicable to and bounds WBN 1. The evaluations presented were either extreme cases or parametric studies that demonstrate margin in the PWR design. These topical areas are: 1. Evaluation of fuel clad temperature response to blockage at the inlet to the core. The evaluation addressed a blockage of about 99.4% of the core inlet area, or alternatively, flow into the core was provided by the flow area of a single fuel assembly.

The evaluation demonstrated that adequate core cooling flow would be established such that negligible impact on clad temperature would be expected due to blockage alone.2. Evaluation of the impact of both the reduction of flow at a fuel grid, and the precipitation of chemical product on the surface of fuel cladding.

A range of thermal conductivities for the precipitation were considered for both of these evaluations, ranging from a low value of 0.1 Btu/(hr-ft-°F) to 0.9 Btu/(hr-ft-°F).

Over the range of conditions considered, the cladding surface temperature was, in all cases, evaluated to be below 800°F.3. Evaluation of chemical effects in the core region to form precipitation on the cladding surface. Considering the variation in plant-specific chemistries, this evaluation was E1-62 performed by extending the method of WCAP-16530-NP to estimate the potential for plate-out on the surface of fuel cladding.In summary, reasonable assurance of long-term core cooling for all plants was demonstrated by the following:

1. The size of holes in replacement sump screens designs limits the size of debris that is passed through the screen during operation of the ECCS in the recirculation mode.2. Based on available test observations, the characteristic dimension of this debris is typically less than the screen hole size, even for fibrous debris. Consequently, debris buildup at critical locations in the reactor vessel and core is not expected.3. Based on data presented internationally during the resolution of the BWR strainer performance concerns, fibrous debris was observed to not strongly adhere to fuel cladding.Thus, the small size of the debris and its tendency to not adhere to fuel indicates that long-term core cooling of the fuel will not be impaired by either the collection of fibrous and particulate debris in fuel elements, or by the collection of fibrous debris on fuel cladding surfaces.4. Supporting calculations have demonstrated long-term core cooling will be maintained with about 99.4% of the core blocked. The cladding temperature response to blockage at grids and the collection of precipitation on clad surfaces was also demonstrated to be acceptable with resulting cladding temperatures less than 400°F.5. A method to evaluate chemical effects on fuel has been developed, applied to several "worst case" plant chemistries and acceptable clad temperatures were calculated.

It was concluded that reasonable assurance of acceptable long-term core cooling with debris and chemical products in the recirculating fluid is demonstrated for all plants. Items 1 through 4 are directly applicable to all PWRs including WBN 1.A comparison to the conditions evaluated by the sample calculation in WCAP-16793-NP was made to WBN 1 plant parameters.

This comparison is summarized below: E1-63 Comparison of LOCADM Sample Calculation Parameters to WBN 1 Plant Conditions Parameter Sample Calculation WBN 1 Core Thermal Power Rating 3188 MWth 3459 MWth Fiber (fiberglass)

Debris Load 7000 ftW 90.67 ft 3 Calcium Silicate Debris Load 80 ft 3 0 ft 3 Sump pH Control Buffer Agent Sodium Hydroxide Sodium Tetraborate Hot Leg Switchover Time 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 3 hours Aluminum Surface Area in Containment 15,189 ft 2 1146 ft 2-unsubmerged Aluminum Surface Area in Containment 799 ft 2 203 ft 2-_submerged Based on this comparison, it was concluded the sample calculation in WCAP-16793-NP was conservative with respect to WBN 1 plant conditions.

WCAP-16793-NP is currently under review by the NRC. The NRC SER on WCAP-16793-NP is pending.This evaluation closes Open Item 7.WBN has also converted to the alternate p-grid design for the robust fuel assemblies (RFA-2)fuel used in WBN. 161 assemblies in the cycle 9 core have the alternate p-grid design; 32 assemblies in the cycle 9 core do not have the alternate p-grid design. The original p-grid design at the bottom of the fuel had cruciforms that partially bisected the inlet flow hole in the bottom of the fuel. This was evaluated to not be a problem but the alternate p-grid design raises the grid an additional amount away from the bottom nozzle which allows further clearance for debris passage and additional conservatism in the design.3.o. Chemical Effects The objective of the chemical effects section is to evaluate the effect that chemical precipitates have on head loss and core cooling.3.0.1. Provide a summary of evaluation results that show that chemical precipitates formed in the post-LOCA containment environment, either by themselves or combined with debris, do not deposit at the sump screen to the extent that an unacceptable head loss results, or deposit downstream of the sump screen to the extent that long-term core cooling is unacceptably impeded.Content guidance for chemical effects is provided in Enclosure 3 to a letter from the NRC to NEI dated September 27, 2007 (ADAMS Accession No. ML0726007425).

TVA Response The purpose of this analysis is to determine the type and quantity of chemical precipitates which may form post-LOCA.

This input is intended to be used for screen performance testing and may be used in the evaluation of chemical effects on downstream equipment.

TVA has calculated the quantities of precipitates expected to form post-LOCA using the chemical model/methodology developed in WCAP-16530-NP, prior to release of the accompanying NRC SER. Based on the relatively limited quantities of precipitate material predicted by the calculation, and the large strainer surface area to debris loading ratio, the WBN replacement E1-64 sump screen was tested with chemical precipitate surrogates during certification testing only in the maximum coating inventory test.Excel Spreadsheet: "WOG Chemical Effects Calculator 19 WBN corrected 4.1 PH Cold.xls" This calculation determines the type and expected quantity of chemical products that would be expected to form in the recirculation fluid specifically for WBN. No deviations were taken to the WCAP-16530-NP methods.Input assumptions (and their basis) used to determine chemical effects loading: pH range, temperature profile, duration of containment spray, and materials expected to contribute to chemical effects are listed in the input tabs of the spreadsheet.

The materials expected to contribute to the formation of chemical precipitates are: submerged aluminum, non-submerged aluminum, fiberglass, Min-K, Aluminum Silicate, and concrete.

The buffering agent, NaTB, is used to buffer the sump pH from a minimum pH of 4.1 to a maximum pH of 8.2 post-LOCA.

A sensitivity case was performed with the recirculation water volume of 54,907 ft 3.Table 1 shows the recirculation water volume, the inputs for the amount of materials, and the buffering agent used in the chemical effects evaluation for WBN.Thkl,ý I -1 AIM I E1-65 Table 2 shows the "Time Temp pH Input" worksheet from the chemical effects model. The sump pH increased to a maximum pH of 8.2 from a minimum pH of 4.1 during the 30 days evaluated and from the time of recirculation the spray pH values were assumed to equal the sump pH values. This is conservative because higher pH values are expected to generate more precipitates.

This evaluation was performed with spray inputs up to 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> post-LOCA.

Table 2: WBN Time Temo ut 30 60 120 180 200 400 600 800 1000 1200 1400 1600 1800 3200 4600 6000 7400 8800 10200 11600 13000 14400 46400 86400 172800 259200 345600 432000 864000 1296000 1728000 2160000 2592000 4.1 1UU 4.1 U2 4.1 189 4.1 88 4.1 188 4.1 87 4.1 185 4.1 88 4.1 182 4.1 95 4.1 181 4.1 90 4.1 172 4.1 103 5.5 168 4.1 106 5.5 166 4.1 107 5.5 165 4.1 107 5.5 164 4.1 107 5.5 163 8.2 107 8.2 163 8.2 108 8.2 140 8.2 108 8.2 136 8.2 108 8.2 134 8.2 135 8.2 135 8.2 135 8.2 136 8.2 135 8.2 137 8.2 135 8.2 138 8.2 133 8.2 138 8.2 133 8.2 135 8.2 133 8.2 130 8.2 131 8.2 126 8.2 126 8.2 122 8.2 120 8.2 118 8.2 116 8.2 114 8.2 110 8.2 110 8.2 96 8.2 106 8.2 90 8.2 100 8.2 80 8.2 96 8.2 90 8.2 80 8.2 70 The chemical model calculated the releases from the containment materials based on the temperature and pH conditions of the sump and spray solutions within containment post-LOCA for the recirculation water volume of 54,907 ft 3.The total amount of calcium (Ca), silicon (Si), E1-66 and aluminum (AI) released based on these inputs are used to determine the amount of precipitates formed from the containment materials as shown in Table 3.Table 3: WBN Material Release and Precipitate Formation Releases by Material (kg) Precipitates by Material (kg)Material Class Ca Si Al Ca 3 (PO 4)2 NaAISi 3 0 8 AIOOH MetallicAluminum 0.00 0.00 0.38 0.00 1.85 0.00 Submerged Metallic Aluminum 0.00 0.00 0.87 0.00 4.20 0.00 Not-Submerged I Calcium Silicate 0.00 0.00 0.00 0.00 0.00 0.00 E-Glass 2.13 10.78 0.03 0.00 6.28 0.00 Silica Powder 0.00 1.14 0.00 0.00 0.65 0.00 Mineral Wool 0.00 0.00 0.00 0.00 0.00 0.00 Aluminum silicate 0.00 0.71 0.21 0.00 1.40 0.00 Concrete 0.11 0.07 0.00 0.00 0.05 0.00 Interam 0.00 0.00 0.00 0.00 0.00 0.00 Total 2.24 12.70 1.49 0.00 14.43 0.00 For WBN, sodium aluminum silicate (NaAISi 3 O 8) precipitates are the major products of the chemical model evaluation.

NaAlSi 3 0 8 is formed from the release of silica from insulation sources and aluminum from either aluminum metal or fibrous insulation.

The sufficient quantities of insulation containing silica were present for the formation of the NaAISi 3 O 8 precipitate which was limited by the amount of aluminum released.

The low total amount of aluminum released was due to both the moderate pH and low temperatures of the sump and spray solutions, and the major source of aluminum released in containment for WBN was the aluminum metal exposed to the spray. Zero aluminum oxyhydroxide (AIOOH) was generated from the excess aluminum that did not contribute to-NaAISi 3 O 8 , and no calcium phosphate (Ca 3 (PO 4)2) precipitate formed due to the absence of trisodium phosphate (TSP) which the available phosphate would react with the calcium released from the E-glass insulation and concrete.Therefore, with the small amount of containment materials, the moderate pH, low temperatures, and the current buffering agent the predicted total amount of precipitates formed for WBN over the 30-day period was 14.43 kg as shown in Table 4. The total amount of precipitates formed over the 30 days evaluated remained less than the 45 pounds stated in TVA's response to question 4 in its July 3, 2006 letter to NRC, "Watts Bar Nuclear Plant (WBN) Unit 1 -Generic Letter 2004-02 -Request for Additional Information Regarding the Nuclear Regulatory Commission Staff Audit on the Containment Sump Modifications (TAC No. MC4730)." Table 4: Predicted Chemical Precipitate Formation for WBN Precipitates kg NaAlSi 3 0 8 14.43 AIOOH 0.0 Ca 3 (PO4)2 0.0 Total 14.43 E1-67 3.p. Licensing Basis The objective of the licensing basis section is to provide information regarding any changes to the plant licensing basis due to the sump evaluation or plant modifications.

Provide the information requested in GL 04-02 Requested Information Item 2(e) regarding changes to the plant licensing basis. The effective date for changes to the licensing basis should be specified.

This date should correspond to that specified in the 10 CFR 50.59 evaluation for the change to the licensing basis.GL 2004-02 Requested Information Item 2(e)A general description of and planned schedule for any changes to the plant licensing basis resulting from any analysis or plant modifications made to ensure compliance with the regulatory requirements listed in the Applicable Regulatory Requirements section of this GL.Any licensing actions or exemption requests needed to support changes to the plant licensing basis should be included.TVA Response The, FSAR has been updated to describe the new sump strainers.

No other changes to the licensing basis are planned. Closure of this issue will complete the WBN actions.E1-68 ENCLOSURE 2 NRC AUDIT OPEN ITEMS The following information is provided relative to open items from the NRC audit of the WBN GL 2004-02 resolution (Report ADAMS Accession Number ML062120469).

Open Item 1 The licensee should submit the final debris generation calculation to verify that the impact of the revised debris quantities has been adequately addressed.

TVA Response The revised debris generation analysis, ALION-CAL-TVA-2739-03 Rev 3, "Watts Bar Reactor Building GSI-191 Debris Generation Calculation," is provided in Attachment 1.Open Item 2 The licensee should submit the final debris generation calculation that addresses crediting debris shielding by robust barriers.TVA Response Credit for shielding by robust barriers is described in the revised debris generation analysis in Attachment 1.Open Item 3 The licensee should complete the walkdown and the confirmatory analysis to show that the assumptions regarding the amount of latent debris are valid.TVA Response The walkdown for latent debris was completed and verified that the assumptions used in the debris generation analysis were conservative as described above. The latent debris walkdown final report is contained in WAT-D-11530, "WBN Unit 1, Containment Latent Debris Walkdown, Transmittal of the Final Report for Containment Latent Debris Walkdown", (LTR-CSA-06-74, Proprietary).

Open Item 4 The licensee should provide additional justification for the conclusion that the maximum head loss across the new strainer is less than the NPSH margin available.

TVA Response The original NPSH analyses supporting the FSAR demonstrate that adequate NPSH margin exists for the emergency core cooling and containment spray systems. The analyses reviewed by the NRC in the audit (Westinghouse calculation FSDA-C-597, and TVA calculation EPM-E2-1 RCP-120291) do not credit water levels above the containment floor and are therefore conservative.

A revised NPSH calculation was completed with more realistic assumptions to determine a better estimate of available margin. Calculation MDQ001063200601 10, "CCP, SIP, CSP, and RHR Pump NPSH Evaluation," Revision 0, demonstrates that considerable margin exists for all pumps. The strainer testing demonstrated very little head loss for all cases tested including a non-mechanistic sensitivity test where all coatings were placed at the screen. It is TVA's position that due to low head loss, relatively low debris loading, low chemical effects, and a large screen area, further testing would not provide additional safety benefit.Open Item 5 The licensee should provide the final structural analysis report for the replacement strainer.TVA Response The final structural analyses are provided in Attachments 2 and 3. These include calculations PCI-5464-S01 Revision 2, "Structural Evaluation of Advanced Design Containment Building Sump Strainers" and PCI-5464-S02, Revision 2, Structural Evaluation of Advanced Design Containment Building Sump Strainer Plenum.Open Item 6 Upon the completion of PWROG generic methodology development and NRC's approval, the licensee should evaluate the effects of plate out or local deposition of materials concentrated within the reactor core on core heat transfer during the long-term cooling period and submit the results for staff's review.TVA Response NRC evaluation of WCAP-16793-NP for issuance of an SER is ongoing. A comparison of the chemical effects source term loading for WBN is less limiting than the chemical loading debris conditions used for the example case from WCAP 16793-NP, Section 5.7 "EXAMPLE RUN OF LOCADM MODEL." The limited quantity of source term material available for dissolution and subsequent deposition in the core is also confirmed by the WCAP-16530-NP, "Evaluation of Post-Accident Chemical Effects in Containment Sump Fluids to Support GSI-191," chemical effects calculations for WBN.WCAP-1 6793 E Codtn WBN Conditions Comments Example Conditions Fiber mass quantities converted to Nukon fiberglass debris equivalent volume based upon worst case (7000 ft 3) 90.67 W fiber sources of debris from all 4 loops. See 3.b.4.calcium silicate debris WB only has 37 ftW of Aluminum Silicate (80 ft 3) No CalSil and 1.29 ft 3 of silica available for dissolution HLSO time 13 hrs 3 hrs Longer time to HLSO is more limiting -allows more deposition to occur.E2-2 Open Item 7 The licensee should address the fact that following a large hot leg break, a debris bed might form at the entrance to the core which would be greater than the licensee's acceptance criterion of 0. 125 inches and evaluate the impact on the core heat transfer.TVA Response See 3n above.Oven Item 8.The licensee should identify any analysis methods, assumptions, and downstream components, which may be affected by changes to WCAP-16406-P and need to be revisited, and verify the components still applicable criteria.TVA Response See 3m above.Open Item 9 The licensee should re-evaluate the basis for the estimate of latent fibrous screen penetration to ensure that the estimate is adequately conservative.

TVA Response Fibrous -debris downstream impacts were based on strainer test results and the test determined bypass fractions.

The NUKON fiber used in the strainer test was a surrogate for the latent fiber which was present in very low quantities in the test and confirmed in the latent debris walkdown.Other fibrous debris included 3M M20C fire wrap and min-K thermal insulation.

A revision to the analysis for downstream debris concentration resulted in a slightly higher concentration used in the final analysis (904 ppm). This should provide adequate assurance the evaluations are conservative.

Open Item 10 The licensee should provide justification for the conclusion that epoxy phenolic coating is resistant to leaching in the WBN post-LOCA environment.

In addition, although the WBN alkyd coatings are already considered in the debris term, the evaluation of alkyd coating should include an understanding of how this coating interacts with the projected post-LOCA environment.

TVA Response The epoxy leaching issue was addressed generically in PWROG letter OG-07-129 concerning NRC RAIs for WCAP-16530, "Evaluation of Chemical Effects in Containment Sump Fluids to Support GSI-191." Originally the question was posed as RAI#13 on the document and then additional information was requested in a second set of RAIs as RAI#2. Although the example calculations performed for RAI#2 in the PWROG response were for a dry containment, the values are not significantly different for an ice condenser containment (order of magnitude).

The E2-3 volumetric concentration of chlorides from leaching was shown to be relatively low and insignificant as a chemical reactant as would be expected for WBN.The question on alkyd coatings was addressed in WCAP-16793-NP Rev 0 Section 2.5.2. Here it is stated that the amount is generally limited (as it is at WBN). "... these coatings are, as a class, chemically benign and do not react to the post-LOCA sump fluid. In the case of alkyds, the coating would break down into oligomeric carboxylate

salts and glycol. The oligomeric carboxylate salts would actually tend to inhibit-the formation of precipitates.

However, since the amount of alkyds inside containment is small, and the salts are expected to be altered by radiolysis, no credit is taken for their presence inside containment.

For these reasons, these non epoxy coatings are evaluated to have a negligible effect on post-LOCA chemical precipitant production and are therefore not a concern with respect to long-term cooling." Open Item 11 WBN indicated that the WCAP-16530-NP chemical model spreadsheet contained an error that affected the amount of chemical precipitate for WBN. The licensee should provide an evaluation of the plant specific impact of any changes to the WCAP chemical model in the WBN GL 2004-02 response supplement.

TVA Response Letter OG-06-232, PWR Owners Group Letter Regarding Additional Error Corrections to WCAP-16530-NP (PA-SEE-0275) was issued from Westinghouse to the Pressurized Water Reactor Owners Group (PWROG) to identify two errors discovered in the WCAP-16530-NP chemical model spreadsheet.

The first spreadsheet error was discovered in the Si Release column of the "Results Table" worksheet; the silicon release from silica powder material, i.e. Microtherm and Min-K, was not included in the sum. The second error was found in Cell F15 of the "Materials Conversion" worksheet.

This cell incorrectly referenced the total volume of silica powder insulation as opposed to the total mass.Both errors were in the non-conservative direction, as the first discounted the contribution of the silica powder insulation materials to the silicon release, and the second reduced the material available for dissolution by almost a factor of two. The resulting impact from the correction is an increase in the amount of sodium aluminum silicate (NaAlSi 3 O 8) precipitate predicted to form.WBN was impacted by those spreadsheet errors because it contains Min-K insulation.

The overall impact from 3.2 ft 3 of Min-K insulation mentioned in the OG letter was an increase of<3Kg of additional NaAISi 3 O 8 generated.

WBN has since reduced the Min-K insulation to a maximum of <1.29 ft 3 as mentioned above.E2-4 ATTACHMENT 1

9 A LION SCINCt AND' TtCHNoLOG' DESIGN CALCULATION AND ANALYSIS COVER PAGE Calculation No: ALION-CAL-TVA-2739-03 TRevision:

3 Page 1 of 60 Calculation Title: Watts Bar Reactor Building GSI-191 Debris Generation Calculation Project No: 261-2739 Project Name: Watts Bar GSI-1 91. Debris Generation/Transport Analysis and Sump Screen Testing Client: Tennessee Valley Authority Document Purpose/Summary:

An analysis was performed to predict the type, quantity, and size distribution of debris that would be generated should a high energy line break requiring recirculation through the emergency sump ever occur at Watts Bar. Four cases were postulated for breaks in the crossover leg piping at the base of each of the steam generators.

These breaks are considered to be bounding for all loss of coolant accidents that could be postulated at Watts Bar. This report describes the input, assumptions, methodology, and results of the debris generation analysis.All software used in the preparation of this calculation meets QAP 3.5, Use of Computer Software and Error Reporting requirements.

Preparer Signature:

...-- Date: I!4S/I qi DESIGN VERIFICATION METHOD QA APPLICABILITY LEVEL Z Design Review Z Nuclear Safety Related[] Alternative Calculation

[] Quality Significant II Qualification Testing [] Nuclear Non-Safety Related Pmfessional Engineer Approval (if required)+

A i 2 DateA/ {.Signature, I I Form 3.4.1 Revision 3 Effective Date: 2/28/07 A~ '.K., REVISION HISTORY LOG Page 2 of 60 Document Number: ALION-CAL-TVA-2739-03 Revision:

3 Document Title: Watts Bar Reactor Building GSI-191 Debris Generation Calculation REVISION DATE Description 0 Original Issue Fixed error with density of phenolic paint used in volume 11/08/05 calculation.

Updated format of calc to meet new Alion QA standards." Independently re-created and included insulation spreadsheets 2 08/03/07 for each break location so that insulation values are completely traceable (Appendix 1-3)." Included screenshots from AutoCAD which illustrate each step of the paint calculation process so that paint calculation values are completely traceable (Appendix 4)" During the independent re-creation of the insulation spreadsheets, 2 areas of Min-K that are approximately 17 cuft each were found to be omitted from the previous revision of the calculation and are now included in the calculation.

• During the independent re-creation of the insulation spreadsheet, several areas of Min-K and 3M-M20C (Interam) that were judged to be shielded or outside the ZOIs in the previous version of the calculation were considered to be debris source terms in this version of the calculation.

Included example calculation in Section 4.5.1." New paint calculation methodology was used for this revision of the calculation.

Subsequently, the values have risen." Corrected area of containment dome liner above crane wall for IOZ calculation from upper containment (5.1, 5.2, 5.3, 5.4)." In coatings calculations, Carboline 295 and epoxy have been detailed out on their own (5.1, 5.2, 5.3, 5.4)." For the particulate density of Carboline 4674, pure silicone was used. This is consistent with the SER using the particulate density of zinc for IOZ coatings." Added Tables 5.1.1, 5.2.1, 5.3.1, 5.4.1 which show the values Form 6.1.3 Revision I Effective Date- 2/28/07 REVISION HISTORY LOG A.L.4.0 N.-Page 3 of 60 Document Number: ALION-CAL-TVA-2739-03 Revision:

3 Document Title: Watts Bar Reactor Building GSI-191 Debris Generation Calculation obtained from coatings Appendix 4. Added equation to section 4.5.2 that shows how the coatings surface area is calculated along with a reference to the Alion Technical Document which derives this equation." Each coating type has been listed explicitly in Tables 6.1-6.5." Added Table of Definitions and Acronyms" Added words and references to Section 4 that point to AutoCAD and Inventor 10 being V&Vd by Alion." Added Figure 4.4.1 to clarify how the volumes of RMI reported by Enercon in the insulation spreadsheet were converted to surface areas." In the previous revision of the calculation, the thickness of the coatings were pulled from the manufacturers sheets, in this revision, the thicknesses reported in the walkdown report were used [9, Attachment L]." LDFG density was corrected to be. 175 pcf [20]." Added email to Attachment H which further clarifies the constituents of Min-K." Changed breakdown of 3M-M20C (Interam) from 100% LDFG failure to 55% LDFG failure and 45% vermiculate particulate per instruction by TVA (Attachment F)." Corrected Table of Contents pagination for Attachments and Appendices." Added reference for RCS pipe sizes (Ib)." Added Interam behind 3M-M20C notations (numerous locations)." Added short calculation to show what "D" means in reference to ZOI size (Section 4.4)." Changed wording for Assumption 3.12" Updated formatting of calculation to meet new Alion QA standards." Added words on how break locations were selected (Section 5, Break 1 criteria).

Form 6.1.3 Revision I Effective Date: 2/28/07 1LI0N REVISION HISTORY LOG Page 4 of 60 Document Number: ALION-CAL-TVA-2739-03 Revision:

3 Document Title: Watts Bar Reactor Building GSI- 191 Debris Generation Calculation" Added explanation that shadowing was not used to credit debris destruction, but that the robust barrier of the refueling canal and the primary shield wall were (Section 4.4)." Added subsection in both the Min-K and 3M-M20C (Interam)sections for each break location that show a calculation example for how values were arrived at (5.1, 5.2, 5.3, 5.4)." Added latent fiber subsection to each break location calculation (5.1, 5.2, 5.3, 5.4)." Added explanation of where the 17.3 micron particle size comes from for dirt/dust (Section 4.5.3)." Added note that the calculation was not evaluating the existing strainer (Section 5, Break 5 criteria)" Added Figure 5.1 which shows the break locations for each case." Added 3M-M20C shielding effect calculations to results tables" Added Appendix 5 -3M-M20C insulation shielding calculations" Added Assumption 3.13 relating coatings data sheet appendices to installed coatings" Changed wording in Unverified Assumption 1" Minor grammatical and editorial corrections throughout.

3 See Cover

• Modified ZOI for 3M-M20C to 11 .OD (based on TVA Input)Page

• Modified ZOI for Min-K (with additional banding) to 10.0D (based on TVA input)e Modified resulting debris generation for all break cases due to modification of 3M-M20C and Min-K ZOI@ Analyzed shadowing effects for large equipment as it relates to 3M-M20C debris generation.

Form 6.1.3 Revision I Effective Date: 2/28/07 Watts Bar Reactor Building GSI-191 Debris Generation Calculation A L I 0 N. Document No: ALION-CAL-TVA-2739-03 Rev: 3 Page: 5 of 60 TABLE OF CONTENTS Table of Contents ............................................................................................................................

5 List of Figures .................................................................................................................................

5 List of Tables ..................................................................................................................................

6 List of A PPEN DICES ............................................................................................................

6 List of A TTA CHM EN TS ..........................................................................................................

6 D efinitions and A cronym s ...........................................................................................................

7 1 Purpose ....................................................................................................................................

8 2 D esign Input ............................................................................................................................

9 3 A ssum ptions ..........................................................................................................................

10 4 M ethodology

.........................................................................................................................

13 4.1 D ebris Types and Spreadsheet

..................................................................................

13 4.2 CA D M odel ...................................................................................................................

13 4.3 Break Selection

........................................................................................................

15 4.4 D ebris G eneration

......................................................................................................

16 4.5 D ebris Characteristics

...............................................................................................

18 5 A nalysis .................................................................................................................................

26 5.1 Case 1 -LBLO CA in Loop 1 ..................................................................................

28 5.2 Case 2 -LBLO CA in Loop 2 ...................................................................................

34 5.3 Case 3 -LBLO CA in Loop 3 ...................................................................................

40 5.4 Case 4 -LBLO CA in Loop 4 ...................................................................................

46 6 Results ..................................................................................................................................

52 7 Conclusions

...........................................................................................................................

57 8 References

.............................................................................................................................

58 LIST OF FIGURES Figure 4.2.1 -Plan View of Watts Bar Lower Containment CAD model ...............................

14 Figure 4.2.2 -Close-up of Prim ary RCS Piping in Loop 1 ......................................................

15 Figure 4.4.1 -RMI Cylindrical to Rectangular Volume Conversion

.......................................

18 Figure 4.5.1 -RM I debris size distribution

..............................................................................

19 Figure 5.1 -D ebris G eneration Break Locations

....................................................................

27 Figure 5.1.1 -Case 1 RM I ............................................................................................................

28 Figure 5.1.2 -Case 1 Coatings, Min-K and approximate 3M-M20C ZOI ...............................

29 Figure 5.2.1 -Case 2 RM I ............................................................................................................

34 Figure 5.2.2 -Case 2 Coatings, Min-K and approximate 3M-M20C ZOI ..............................

35 Figure 5.3.1 -Case 3 RM I .........................................................................................................

40 Figure 5.3.2 -Case 3 Coatings, Min-K and approximate 3M-M20C ZOI ...............................

41 Figure 5.4.1 -Case 4 RM I .........................................................................................................

46 Figure 5.4.2 -Case 4 Coatings, Min-K and approximate 3M-M20C ZOI ...............................

47 Watts Bar Reactor Building GSI-191 Debris Generation Calculation

/l IIiOJN Document No: ALION-CAL-TVA-2739-03 Rev: 3 Page: 6 of 60 LIST OF TABLES Table 4.4.1 -ZOI Radii for Watts Bar Insulation Types ..........................................................

16 Table 4.5.1 -Ice Condenser Debris .........................................................................................

24 Table 5.1.1 -Surface Area Calculations Within the Loop 1 ZOI ...........................................

31 Table 5.2.1 -Surface Area Calculations Within the Loop 2 ZOI ...........................................

37 Table 5.3.1 -Surface Area Calculations Within the Loop 3 ZOI ......................

43 Table 5.4.1 -Surface Area Calculations Within the Loop 4 ZOI ...........................................

49 Table 6.1 -Case 1 Debris Source Term for a Break in Loop 1 ...............................................

52 Table 6.2 -Case 2 Debris Source Term for a Break in Loop 2 ...............................................

53 Table 6.3 -Case 3 Debris Source Term for a Break in Loop 3 ...............................................

54 Table 6.4 -Case 4 Debris Source Term for a Break in Loop 4 ...............................................

55 Table 6.5 -Physical Properties of Debris ................................................................................

56 LIST OF APPENDICES Appendix 1 -Numbered Enercon Insulation Spreadsheet

.....................................................

1-1 A ppendix 2 -R M I W orksheets

...................................................................................................

2-1 Appendix 3 -Debris Source Summary Sheets ......................................................................

3-1 A ppendix 4 -A utoCA D Figures .................................................................................................

4-1 A ppendix 5 -3M W orksheets

.................................................................................................

5-1 LIST OF ATTACHMENTS Attachment A -Enercon Insulation Spreadsheet

...................................................................

A-1 Attachment B -CarbozincTM 11 .............................................................................................

B-1 Attachment C -CarbolineTM 295 ........................................

C-1 A ttachm ent D -PhenolineTM 305 ...............................................................................................

D -1 Attachment E -CarbolineTM 4674 .........................................................................................

E-i Attachment F -3M-M20C (Interam)

....................................................................................

F-1 A ttachm ent G -M in-K ...............................................................................................................

G -1 Attachment H -Foamglass/Armaflex

....................................................................................

H-1 Attachment I -Ice Condenser Debris ......................................................................................

I-1 Attachment J -Diamond Power RMI .....................................................................................

J-1 Attachment K -Main Steam and Feedwater Breaks ............................................................

K-1 A ttachm ent L -C oatings .............................................................................................................

L -I Attachment N -Comment Resolution

..................................................................................

N-i Attachment M -Review Checklist

.......................................................................................

M- 1 Watts Bar Reactor Building GSI-191 Debris Generation Calculation

ý L1 -AL-V 2790 I RN: Document No: ALION-CAL-TVA-2739-03 Rev: 3 Page: 7 of 60 DEFINITIONS AND ACRONYMS Acronym Definition BWR Boiling Water Reactor CAD Computer Aided Drafting ECCS Emergency Core Cooling System ESF Engineered Safety Features GR NEI 04-07 Guidance Report HELB High Energy Line Break IOZ Inorganic Zinc LBLOCA Large Break Loss of Coolant Accident LDFG Low Density Fiberglass LOCA Loss of Coolant Accident NEI Nuclear Energy Institute NPSH Net Positive Suction Head NRC Nuclear Regulatory Commission PWR Pressurized Water Reactor QA Quality Assurance RCS Reactor Coolant System RHR Residual Heat Removal RMI Reflective Metal Insulation SER Safety Evaluation Report STL Stereolithography URG Utility Resolution Guide ZOI Zone of Influence

.. ... Watts Bar Reactor Building GSI-191. Debris Generation Calculation SIOiNi Document No: ALION-CAL-TVA-2739-03 Rev: 3 Page: 8 of 60 1 PURPOSE The design of the emergency core cooling system (ECCS) in pressurized water reactor (PWR)nuclear power plants includes sumps in the containment building that provide a suction source from the containment to the ECCS pumps allowing the ECCS to operate in a containment recirculation mode following a loss of coolant accident (LOCA). If a high-energy line break (HELB) inside the containment were to occur, it could result in the generation of debris that, if transported to and deposited on the containment sump screens could challenge the function of the ECCS recirculation sumps. Specifically, debris that accumulates on the sump screens would cause an increase in the head loss across the resulting debris bed and sump screens. This head loss may be sufficiently large such that it would exceed the available net positive suction head (NPSH) margin of the ECCS pumps and/or could structurally challenge the sump screens.The sump screen head loss due to the LOCA-generated debris accumulated on the sump screens will be computed based on the quantity determined to be destroyed and transported.

This calculation is the first of a three step process associated with the mechanistic evaluation of the Watts Bar recirculation sump screen due to post-LOCA debris blockage.

The three steps are: Step 1: Debris Generation Step 2: Debris Transport Step 3: Debris Accumulation and Head Loss This calculation shows the inputs, assumptions, and methods used to determine the type, quantity, and size distribution of debris that would be generated given various postulated break locations.

The results of this calculation will be used in conjunction with the debris transport calculation to determine the types and overall quantity of debris that could reach the Watts Bar sump screens.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation

A LION Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 9 of 60 2 DESIGN INPUT This section lists the design inputs used to determine the types, quantity, and representative size distribution of debris generated by a postulated break.1) Accident Analysis a. According to the Watts Bar Updated Final Safety Analysis Report (UFSAR), the types of LOCA breaks that could lead to ECCS recirculation are defined as breaks in the reactor coolant system (RCS) piping or connected piping where the break flow exceeds the makeup flow of the charging pumps [2].b. The worst case break location is a function of the size of the ruptured pipe and the proximity to insulation that could be destroyed.

The inside diameter of the primary RCS piping is 27.5" for the cold legs, 31" for the crossover legs, and 29" for the hot legs [3.14, 3.15].c. A three-dimensional computer aided drafting (CAD) model has been developed for the Watts Bar debris transport calculation.

As a visualization aid for this analysis, the CAD model was extended to the operating floor based on various plant drawings.

The CAD model was also used to calculate the surface area of coatings on walls, supports, and major equipment.

It was also used to determine the quantity of some insulation debris as detailed in Section 4.d. Various isometric drawings were used to determine the quantity of insulation within specific distances from the postulated breaks [3].2) Debris Types and Characterization

a. Based on the Enercon developed Watts Bar insulation spreadsheet (See Attachment A), the insulation types in containment include RMI, Cal-Sil, Min-K, Interam 3M-M20C (Attachment F), Foamglass, RTV, Armaflex, Marinite, and Mineral Wool. The locations and quantities of each type of debris are specified in the insulation spreadsheet.

b. Coatings within the zone of influence (ZOI) at the postulated high energy line break (HELB) were considered.

The walkdown report [9, Attachment L] and coatings specifications (Attachment B, C, D, E) were used to determine the type, thickness, and number of coats applied.c. The density, microscopic size, and other material-specific properties were taken from the NEI-04-07, SER, vendor-specific information, or plant specific data sheets as applicable.

This is discussed in detail in Section 4.5.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation

A:L 1:0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 10 of 60 3 ASSUMPTIONS This section lists the assumptions made in the debris generation analysis.1) Interam 3M-M20C debris has the composition of 40-60% vermiculite, 10-15% aluminum silicate, 2-10% organic binder, 5-10% metal foil, with the remaining 5-40% not being specified (Attachment F). Vermiculite and the metal foil are not fibrous materials and will be treated as particulate (Attachment F). Using a conservative approach, the particulate components are minimized resulting in 45% of the 3M-M20C (Interam)treated as particulate.

The organic binder, aluminum silicate, and unknown material are assumed to be fibrous, resulting in a maximum 55% fibrous component of 3M-M20C. In addition, since the majority of the 3M-M20C is vermiculite, the density of the expanded 3M-M20C insulation for the particulate component is assumed to be the minimum expanded bulk density of vermiculite, 4 pcf with a manufactured density of 156 pcf (Attachment F). The particulate component of 3M-M20C was assumed to fail as 10 micron particulate.

The fibrous component of the 3M-M20C will be assumed to have the same debris characteristics as low density fiberglass (LDFG). The MSDS received for 3M-M20C (Interam), vermiculite and a statement for treatment of the material by Watts Bar are included as Attachment F.2) Jacketing, wire ties, buckles and straps are conservatively assumed to be the same as RMI foils and are accounted for within the RMI load as such a highly conservative RMI ZOI was used. This is conservative because RMI foils would transport more readily than the heavier metal straps, etc.3) It was assumed that the Mineral Wool, Cal Sil and RTV that reside in the crane wall penetrations would not be destroyed and will subsequently be ignored. Upon blowdown, if this material were to fail, it would be blown to the area outside the crane wall, which has no communication with the emergency sump inside the crane wall.4) In accordance with Attachment K, main steam line and feedwater pipe breaks within the reactor building penetrations are very low probability pipe breaks. As such, main steam line and feedwater pipe breaks will not be further considered in this calculation.

Debris quantities generated by primary breaks are conservatively assumed to bound the debris quantities generated by secondary line breaks. This assumption is reasonable since secondary piping pressures are significantly lower than the primary piping pressure, hence the secondary pipe break ZOI will be significantly smaller than primary line breaks and will not be able to capture the quantity of pockets of 3M-M20C and Min-K that a primary break is able to. Additionally, the blowdown of secondary pipe breaks is of much shorter duration than primary pipe breaks since the secondary water/steam inventory of a steam generator and associated piping is significantly less than the inventory of the RCS.As such secondary pipe breaks inside containment will not be further considered in this calculation.

5) The Rubatex/Armaflex wrap and Foamglass insulations are closed cell insulations that reside in upper containment and in the ice condensers (Attachment H). Foamglass also resides in the raceway. Both insulations would be shielded from the LOCA jet forces and Watts Bar Reactor Building GSI-191 Debris Generation Calculation A LIONi Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 11 of 60* .......- .....will be assumed to remain intact. This is part of the design basis of the plant (Attachment H). The Rubatex/Armaflex and Foamglass insulations are not located in any direct flow paths so failure by erosion would not be likely [3.16-3.20, Attachment H]. Even if the Rubatex/Armaflex or Foamglass were postulated to fail, they would be caught in the tight array of ice baskets or lattice structure in the ice condensers.

Finally, if either did transport to the pool, both of these insulation types float and they would not be a debris source which would transport to the sump (Attachment H).6) The marinite board resides in the fan room outside the crane wall and will not be subject to LOCA jet forces and will be assumed to remain intact and will subsequently be ignored.7) All coatings within the ZOI will be assumed to fail as 10 micron particulate.

Unqualified coatings (alkyd, inorganic zinc, and modified silicone paint) outside the ZOI in lower containment and subject to spray in upper containment will be assumed to fail as 10 micron particulate

[5].8) It was assumed that the LOCA blowdown, upon reaching upper containment, would be dry as the ice condensers condense all the blowdown steam before it reaches upper containment

[13-17]. This along with the containment sprays being designed not to hit the containment dome liner, an argument could be made that the unqualified

/undetermined IOZ on the containment dome does not fail. Notwithstanding the above, it was conservatively assumed that the IOZ on the dome above the crane wall and refueling canal would fail and contribute to the debris source term.9) It was conservatively assumed that Min-K has a bulk density of 16 lb/ft 3 as stated by the manufacturer (Attachment G). The particle densities of the Min-K components are assumed to be the same for Microtherm as there is no data for the Min-K available and both materials are microporous insulations of the same composition.

10) It was assumed that all jacketed insulation outside of the ZOI would not undergo any erosion by either break or spray flows (i.e. no insulation debris would be generated outside of the postulated ZOIs). This assumption is considered acceptable by the NRC as stated in the SER Section 3.4.3.2 [5].11) It was conservatively assumed that the "undetermined coatings" on the pressurizer relief tank are unqualified and would fail [9].12) Transco provided sample drawings and a formal letter (Attachment J) stating the foil spacing for the Diamond Power RMI installed at Sequoyah, Unit 1 is expected to be 3 foils per inch based upon sample information.

Transco then states that "based on this sample information, it is expected that the number of liners per inch would not change throughout the four (4) projects listed" which includes Watts Bar. Personnel at Watts Bar took measurements of the RMI at random locations in containment and found the foil spacing to be 3 foils per inch. It has also been Alion's experience that Diamond Power RMI has a foil spacing of 3 foils per inch. For this analysis it will be assumed that the Diamond Power RMI installed at Watts Bar has a foil spacing of 3 foils per inch.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation t q' Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 12 of 60 13) It was reasonably assumed that the coating data sheets (Attachment B through Attachment E) accurately represent the respective coating formulations within containment as the product names have not changed.14) It was assumed that the quantity of latent debris at Watts Bar is equal to 200 lb. A latent debris survey was completed at Watts Bar on 09/06 [Ref. 25]. It indicated a total latent debris load of 69.2 lbs. 200 lbs. of latent debris will be assumed to provide margin in this calculation.

SER Section 3.5.2.3 suggests that 15% of the latent debris should be assumed to be fiber, and the other 85% particulate

[5]. Thus, 170 lb was assumed to be dirt/dust and the remaining 30 lb was assumed to be latent fiber.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation IL- ION Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 13 of 60 4 METHODOLOGY The following general steps were taken in determining the types, quantity, and size distribution of debris generated following a postulated HELB at Watts Bar: 1. The Enercon Walkdown Report [9] was used in conjunction with the Enercon provided debris spreadsheet (Attachment A) to identify and locate the quantities of insulation in lower containment (see Section 4.1).2. The CAD model was used as a visual aid to show the extent of the ZOI spheres around the postulated breaks (see Section 4.2).3. Break locations were selected based on the accident scenarios that could lead to ECCS recirculation, the size of the pipe break, and the proximity of other insulated pipes or equipment (see Section 4.3).4. The quantity of each type of debris generated was determined based on the amount of insulation that falls within the specific ZOI for that material (Attachment B), (see Section 4.4).5. The size distribution and characteristic properties were defined for each material based on the NEI-04-07 and SER methodologies, as well as applicable test data, (see Section 4.5).The debris generation analysis was carried out in accordance with Alion's quality assurance (QA) program. The program is fully compliant with 10 CFR 50, Appendix B, NQA-1, and NQA-2 Section 2.7. It includes provisions for 10 CFR Part 21 notifications.

Various area calculations were performed using AutoCAD 2006 and Inventor 10. These software packages are commercially available computer codes. The CAD software used in the debris generation analysis is configuration-controlled under Alion's QA program and has been validated and verified under the Alion QA program [22].4.1 Debris Types and Spreadsheet A spreadsheet showing the location and quantity of each type of insulation in containment was provided as design input. This spreadsheet was based on the Enercon Walkdown Report [9, Attachment A] performed in late 2004 that identified potential sources of debris: insulation, coatings and latent debris. The types of debris found in lower containment were RMI, Min-K, 3M-M20C (Interam), Cal-Sil, Foamglass, RTV, Marinite, Armaflex, and Mineral Wool. The potential coatings found in lower containment were CarbozincTM 11, CarbolineTM 295, PhenolineTM 305, and CarbolineTM 4674. The Enercon provided insulation spreadsheet was checked for accuracy and is included in this report as Attachment A.4.2 CAD Model A CAD model of the Watts Bar lower containment was developed for use in the debris generation and debris transport analyses.

For this analysis, the model was used to assist in the identification of debris sources and robust barriers within a given ZOI. Figure 4.2.1 shows a plan

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 14 of 60 view of the CAD model. Figure 4.2.2 shows an isometric view of the primary RCS piping in Loop 1.Figure 4.2.1 -Plan View of Watts Bar Lower Containment CAD model

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation AI 0L N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 15 of 60 Figure 4.2.2 -Close-up of Primary RCS Piping in Loop I 4.3 Break Selection The objective of the break selection process is to determine the break size and possible locations that would result in the greatest debris generation and/or the debris generation and transport combination that present the greatest challenge to post-accident sump performance.

Additionally, breaks that would cause a "thin-bed" effect are given consideration since these also have the potential to significantly impair sump screen performance.

The following break locations were analyzed for Watts Bar: S 0 S Break 1: Locations in the RCS with the largest potential for debris generation.

Break 2: Locations with two or more different types of debris.Break 3: Locations with the most direct path to the sump.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation.A L I 0 N:ý. Document No:ALION-CAL-TVA-2739-03 I Rev:3 Page: 16 of 60* Break 4: Locations with the largest potential particulate to fiberglass ratio." Break 5: Locations that would generate debris that could potentially form a thin-bed.For debris generation, all LBLOCAs and SBLOCAs not able to be isolated from the RCS by any combination of two automatic or remotely operated isolation valves that fail to the "closed" position, or one passive component in the "closed" position must be evaluated.

LOCAs involving failures of the PORVs and pressurizer safety valves do not need to be evaluated due to their ability to be neutralized as a leakage source prior to initiation of recirculation

[19].4.4 Debris Generation As documented in NEI-04-07, the destruction pressures for various insulation materials were determined by performing air jet or water/steam jet tests. These tests were carried out by directing high-energy jets on various insulation targets at varying distances.

The destruction pressures were then quantified by observing the effects of the jet on the insulation and the corresponding stagnation pressure in the flow field.In a PWR reactor containment building, the worst case hypothetical pipe break would be a double-ended guillotine break (DEGB). In a DEGB jets of water and steam would blow in opposite directions from the severed pipe. One or both jets could impact an obstacle and be reflected in different directions.

To take into account the double jets and potential jet reflections, the NEI-04-07 proposes using a spherical zone of influence (ZOI) centered at the break location to determine the quantity of debris that could be generated by a given line break. Since different insulation types have different destruction pressures, different ZOIs must be determined for each type of insulation.

Table 4.4.1 shows the equivalent spherical ZOI radii divided by the break diameter (r/D) for each representative material in the Watts Bar containment.

To calculate the ZOI radius, one only needs to multiply the pipe diameter by the r/D term. For example, the coatings ZOI has a size of lOD, which means that for a 20 inch pipe, the ZOI radius would be (10*20") 200 inches or 16.67 feet.Table 4.4.1 -ZOI Radii for Watts Bar Insulation Types Destruction Pressure ZOI Radius/Break Diameter Insulation Type (psi) (r/D)Protective Coatings N/A 10.01 3M-M20C (Interam)

N/A 11.02 Mirror RMI 2.4 28.6'Mmn-K with standard bands N/A 28.62 Min-K with additional banding N/A 10.02 1) SER recommends ZOI of 10.0 r/D as a conservative estimate.2) See Section 4.5.1 3) Recommended value from SER.In some cases, if the ZOI for a particular material is very large (e.g. it has a low destruction pressure), the radius of the sphere may encounter a robust barrier and be truncated.

Robust barriers, i.e., structures and equipment that are impervious to jet impingement, are assumed to prevent further expansion of the break jet. The volume of a spherical ZOI with a

Watts Bar Reactor Building GSI-191 Debris Generation Calculation

L ION Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 17 of 60 radial dimension extending beyond robust barriers such as walls or encompassing a large component such as a tank or steam generator is truncated by the barrier. The SER, Section 3.4.2.3, states that the shadow surfaces of components should be included in the analysis and not truncated.

No credit was given in this report for equipment shielding (with the exception of 3M-M20C (Interam), see Section 4.5.1), however credit was given for robust barriers due to the primary shield wall around the reactor vessel and the refueling canal.By placing a ZOI sphere centered at the break location within the CAD model, the insulated piping and equipment within that sphere can be visualized and the quantity of debris determined based on the information in the Watts Bar insulation spreadsheet

[9]. For most types of insulation, it is necessary to calculate the volume or mass of debris that would be generated.

However, RMI insulation is somewhat different, since it is made up of individual flat foils within cartridges.

To specify the RMI debris generated, it is more appropriate to calculate the single sided foil surface area. This can be reasonably approximated using the following equation: SA = (OD + t)* z* L*n

• t where: SA = Single-side RMI foil surface area (ft 2)nf = Number of foils per inch (thickness) in an RMI cassette OD = Pipe outer diameter (in)t = Insulation thickness (in)L = Insulated length of pipe inside the zone of influence (ft)In many occasions on the received Enercon insulation spreadsheet (Attachment A) only volumetric data was reported.

The volumetric data was converted to a surface area by relating the cylindrical volume calculation above to a rectangular volume. The circumference of the pipe is held in the (OD+t)*7r term, which can be translated to the width of the volume. The length of the pipe is held in the L term, which can be translated to the length of the volume. The thickness of the insulation is held in the t term, which can be translated to the height of the volume.

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation AL N DocumentNo:ALION-CAL-TVA-2739-03 Rev:3 Page: 18 of 60-, ~ ~ ocmn L t Figure 4.4.1 RMI Cylindrical to Rectangular Volume Conversion Thus, the above equation can be simplified to: SA = W

• L *t *n Where W*L *t is the reported volume of RMI.4.5 Debris Characteristics There are three primary types of potential debris in containment buildings

-insulation, coatings, and latent debris. In order to perform debris transport and head loss calculations, the characteristics of the debris generated must be defined. These characteristics include the size distributions and densities of the debris.4.5.1 Insulation Mirror RMI Figure 4.5.1 shows a debris size distribution plot summarizing the results of 2-phase jet tests of MirrorTM RMI [7]. This plot shows that 71% of the RMI was destroyed in 1/4-inch to 2-inch pieces, and 29% was destroyed in 4-inch to 6-inch pieces. Based on this data, the NEI-04-07 (Section 3.4.3.3.2) recommends using a size distribution of 75% small pieces and 25% large pieces, where small pieces are defined as anything less than 4 inches [4].

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation L.I 0IN Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 19 of 60 30%25.6%25%J 20.2% 20.9%16.8%15%10 12.2%S10%5% 4.3%0% -t1, 1/4" 1/2" 1" 2" 4" 6" Debris Size Figure 4.5.1 -RMI debris size distribution Min-K The size distribution recommended in the NEI-04-07 Section 3.4.3.3.1 for Min-K is 100% fines and a ZOI radius of 28.6D [4]. This ZOI and distribution is based on the SER recommended destruction pressure of 2.4 psi for blanketed and unjacketed Min-K. However, at Watts Bar the Min-K is covered with the same stainless steel jacketing as RMI. Jet impingement testing was performed to determine the zone of influence (ZOI) of Min-K with additional banding (banded with 0.5-inch wide stainless steel bands at a center spacing of 6-inches) and 3M-M20C (Interam)insulation for Watts Bar Nuclear Plant. Westinghouse calculation WCAP-16783-P

[23]documents this testing and calculates the ZOI for Min-K (with additional banding) as 10.0 D.Min-K is composed of fiber, fumed silica, and titanium dioxide and has a bulk density ranging from 8-16 lb/ft 3 (Attachment G). Table 4.5.1 shows the composition and corresponding densities for MinK.

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation

ALI N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 20 of 60 Table 4.5.1 -Min-K Composition Components

% of Material Particle Particle Density by Weight Diameter (gm) (lb/ft 3)Fiber 20% 6* 165" Fumed Silica (SiO 2) 65% Varies, centered 137"*at 20 Titanium Dioxide (TiO 2) 15% 2.5-10 262"*Due to a lack of data and the similar composition of Microtherm and Min-K, these properties of Microtherm will be used (Attachment G).**Taken from Table 2-1 of Perry's Chemical Engineering Handbook [12]3M-M20C (Interam)This insulation is a "felt-like" material that expands when subjected to fire or high temperature, and will be treated as a high density fiberglass (HDFG) with a manufactured density of 39 lb/ft 3 (Attachment F). Upon destruction, the HDFG fines debris loses its "felt" type characteristics and becomes individual fibers in this case (see NUREG/CR-6224 size classes 1 through 4). As such, the HDFG fines debris will occupy a larger volume as the density of HDFG fines is significantly less than the density of the original felt material.

The HDFG fines debris has been assumed to be similar to the LDFG fines debris. NUKON will be used as the surrogate of LDFG per the SER[5]. It will be assumed that it fails as 55% LDFG Nukon individual fibers (175 lb/ft 3 [20] -7 micron [5]) and 45% vermiculite (156 lb/ft3 -10 micron [Attachment F]) particulate.

In order to obtain the portion of 3M-M20C (Interam) destroyed as LDFG, one would multiply the volume of 3M-M20C destroyed by 55% and then by the bulk density (for Interam, 39 lb/ft 3)and divide by the LDFG bulk density (in this case, 2.4 lb/ft 3) [Attachment F].In order to obtain the portion of 3M-M20C (Interam) mass as particulate, one would multiply the volume of 3M-M20C destroyed by 45% and then by the bulk density (for Interam, 39 lb/ft 3).[Attachment F]Jet impingement testing was performed to determine the zone of influence (ZOI) of Min-K and 3M-M20C (Interam) insulation for Watts Bar Nuclear Plant. Westinghouse calculation WCAP-16783-P [23] documents this testing and calculates the ZOI for 3M-M20C (Interam) as 11.0 D.The application of 3M-M20C (Interam) as a radiant energy shield on conduit raceways and junction boxes confines it to a relatively centralized location within containment.

The centralized arrangement and significant impact on sump performance of 3M-M20C (Interam)makes it desirable to analyze the effects of equipment shielding on debris generation quantities for this material.

The SER states that the truncation of the ZOI "should be conservatively determined with a goal of +0/-25 percent accuracy, and only large obstructions should be considered." To insure that the shielding effects are conservative, the following equation was used where only 75% of the shielded debris is credited.

Appendix 5 contains the results of this analysis.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation SL ION Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 21 of 60 Vold = Volt x (L, -(L, x0. 75))Lt Where: Void = Volume of insulation destroyed Vol, = Total volume of insulation on the entire length of conduit L, = Total length of conduit L, = Length of conduit determined to be shielded 4.5.2 Coatings Essentially all steel surfaces at Watts Bar are coated with CarbozincTM 11 (an inorganic zinc primer). All steel 6 feet from the containment floor has also been topcoated with PhenolineTM 305. The containment liner is also coated with CarbozincTM 11 [9, Attachment L] and has been left without a topcoat. Even though failure of this coating is not likely, it has been conservatively assumed to fail in this analysis as discussed in Assumption

8. The concrete floors and walls have been painted with PhenolineTM 305. All concrete below 6 feet has been painted with a CarbolineTM 295 surfacer and then painted with two coats of Phenoline 305TM [9, Attachment L]. The steam generators are coated with CarbolineTM 4674 underneath the RMI insulation.

This coating is a high temperature silicone that is not DBA qualified and will be assumed to fail as fines if the RMI that encapsulates it fails [9]. All qualified coatings outside the coatings ZOI will remain intact [5].CarbozincTM 11 -(Inorganic Zinc)The characteristic particle diameter of inorganic zinc (IOZ) was assumed to be 10 ýtm [4]. Based on the NEI-04-07 Table 3-3, the density of IOZ particulate is 457 lb/ft 3 [4]. The dry film bulk density of CarbozincTM 11 is only 223 lb/ft 3 , however. This was derived from the liquid density and other properties found on the data sheet for CarbozincTM 11 (Attachment B) as shown in the following calculation:

Liquid Density = 23 lb/gal Percent Solids by Weight = 79% +/- 2% = 81%Solids per gallon = (23 lb/gal)*(0.81)

= 18.6 lb/gal Spread Rate = 1,000 ft 2/gal/mil Volume per gallon = (1,000 ft 2/gal/mil)

• (0.001 in/mil)*(1 ft/12 in) = 0.083 ft 3/gal Dry Density = (18.6 lb/gal)/(0.083 ft 3/gal) = 223 lb/ft 3 According to the walkdown report [9, Attachment L], the recommended application for CarbozincTM 11 is a dry film thickness of 2.5-5 mils per coat. Since this coating was used as a primer at Watts Bar, it was assumed that one coat of CarbozincTM 11 with an average thickness of 4.0 mil was applied on all carbon steel surfaces and the containment dome.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation A 11::: L.1 N.:: Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 22 of 60 Carboline T M 295 -(Epoxy)The characteristic particle diameter of CarbolineTM 295 was assumed to be 10 ýtm [4]. A dry film bulk density of 123 lb/ft 3 was derived using properties found on the CarbolineTM 295 datasheet (Attachment C) as shown in the following calculation:

Liquid Density = 16 lb/gal Percent Solids by Volume = 68% +/- 2% = 70%Solids per gallon = (16 lb/gal)*(0.70)

= 11.2 lb/gal Spread Rate = 1,091 ft 2/gal/mil Volume per gallon = (1,091 ft 2/gal/mil)*

(0.001 in/mil)*(l ft/12 in) = 0.091 ft 3/gal Dry Density = (11.2 lb/gal)/(0.091 ft 3/gal) = 12,3 lb/ft 3 This value will also be assumed to be the density of the particulate, as this value is higher than the 94 lb/ft 3 density recommended for generic epoxy/phenolic particulate in the NEI 04-07 Table 3-3, and is therefore more conservative with respect to debris headloss.

This was applied to all floor surfaces and on the walls up to 6 feet from the floor. As up to 60 mils are required to obtain a smooth surface according to the data sheet and the walkdown report [9, Attachment L], this value will be used.PhenolineTM 305 -(Phenolic)

The characteristic particle diameter of PhenolineTM 305 was assumed to be 10 [tm [4]. A dry film bulk density of 105 lb/ft 3 was derived using properties found on the PhenolineTM 305 datasheet (Attachment D) as shown in the following calculation:

Liquid Density = 13.6 lb/gal Percent Solids by Volume = 64% +/- 2% = 66%Solids per gallon = (13.6 lb/gal)*(0.66)

= 9.0 lb/gal Spread Rate = 1,026 ft 2/gal/mil Volume per gallon = (1,026 ft 2/gal/mil)

• (0.001 in/mil)*(1 ft/12 in) = 0.086 ft 3/gal Dry Density = (9.0 lb/gal)/(0.086 ft 3/gal) = 105 lb/ft 3 Again, this value will also be assumed to be the density of the particulate.

According to the walkdown report [9, Attachment L], the application for PhenolineTM 305 is a dry film thickness of 4-6 mils per coat, with a single coat on steel structures within 6' of the floor, a single coat on concrete inside the crane wall, and two coats on the floor and concrete within 6' of the floor. For this analysis, the average dry film thickness of 5-mil will be used.Carboline T M 4674 -(Silicone)

The characteristic particle diameter of CarbolineTM 4674 was assumed to be 10 jIm. Based on the CRC Handbook of Chemistry and Physics [10], the density of Silicone particulate is 145 lb/ft 3 [4]. A dry film bulk density of 87 lb/ft 3 was derived using properties found on the CarbolineTM 4674 datasheet (Attachment E) as shown in the following calculation:

Watts Bar Reactor Building GSI-191 Debris Generation Calculation A i .LI 0N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 23 of 60 Liquid Density = 11 lb/gal Percent Solids by Volume = 40% +/- 2% = 42%Solids per gallon = (11 lb/gal)*(0.42)

= 4.6 lb/gal Spread Rate = 640 ft 2/gal/mil Volume per gallon = (640 ft 2/gal/mil)*(0.001 in/mil)*(1 ft/12 in) 0.053 ft 3/gal Dry Density = (4.6 lb/gal)/(0.053 ft 3/gal) = 87 lb/ft 3 According to the walkdown report [9], the application of CarbolineTM 4674 is a dry film thickness of 1 mil, which is the thickness that will be used for this analysis.To find the surface area of the equipment or concrete enveloped by the coatings ZOI sphere, three calculations must be made using AutoCAD. The methodology for doing this calculation can be found in the Alion Paint Surface Area Calculation methodology report [21 ]. However, the equation for calculating the surface area is: Coated Surface Area = (Areaj,,..ecd

+ AreaS~bL,,,d

-AreaSphere) 2 Each of these numbers used in the paint calculation equation can be found in the paint calculation section for each break in Section 5. An AutoCAD screenshot of each of these numbers is included in Appendix 4 for traceability.

Unqualified Coatings According to the SER, all unqualified coatings, inside or outside the coatings ZOI, fail. Due to a lack of data, all failed coatings must be assumed to fail as 10 micron particulate.

4.5.3 Latent

Debris Latent debris is defined as dirt, dust, paint chips, fibers, paper scraps, plastic tags, tape, adhesive, labels, fines or shards of thermal insulation, fireproof barrier, or other materials that may be present in containment prior to a postulated LOCA. Potential origins for this material include foreign particulate brought into containment during refueling outages and the normal deterioration of coatings, etc.Items such as labels, tags, tape, light-bulbs, and other miscellaneous items were identified in the walkdown report. However, no values were assigned to the quantity of these debris types.Therefore, these debris types were not addressed in this analysis.

The significance of the miscellaneous debris can be addressed once the impact of the quantity of debris transported to the strainer in relation to the strainer size is assessed.A latent debris survey was completed at Watts Bar on 09/06 [Ref, 25]. It indicated a total latent debris load of 69.2 lbs. 200 lbs. of latent debris will be assumed to provide margin in this calculation.

SER Section 3.5.2.3 suggests that 15% of the latent debris should be assumed to be Watts Bar Reactor Building GSI-191 Debris Generation Calculation A lIO:N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 24 of 60 fiber, and the other 85% particulate

[5]. Thus, 170 lb was assumed to be dirt/dust and the remaining 30 lb was assumed to be latent fiber.Dirt/Dust The representative size and density of dirt/dust particulate was assumed to be 17.3 jIm and 169 lb/ft 3 respectively based on the SER Section 3.5.2.3 [5]. 17.3 [im is the equivalent spherical diameter of a particle that has a surface to volume ratio as noted in the SER [5].Latent Fiber The representative bulk density of latent fiber was assumed to be 2.4 lb/ft3, and the material (individual fiber) density of latent fiber was assumed to be 94 lb/ft 3 based on the SER Section 3.5.2.3 [5]. The SER does not give a characteristic latent fiber diameter, but they do indicate that it is appropriate to assume the same diameter as commercial fiberglass (7 jim for Nukon per NUREG/CR-6224).

Ice Condenser Debris Watts Bar has provided a log of the debris trapped in the ice condensers which is included at the end of this report as Attachment I. The log was analyzed and separated into two groups. The items that were large and rigid would not be able to transport both out of an ice basket and through the ice condenser lattice. Items small enough to fall through the baskets to the floor will be considered debris that could be washed down through the ice condenser and are included in the list below. These items will be analyzed for transport in the debris transport calculation and will be addressed as a reduction in strainer area in the head loss calculation.

Table 4.5.1 -Ice Condenser Debris Bay No. Basket No. Debris Description I A6 Gray duct tape, 2-3 inches in length 1 Undetermined length of grass tie-off rope 1 Seven (7) screws lost 1 NEAR A6 Red shackle pin I Electrical Tape 1"x 12" 3 H4 Wood splinters 4 D4 Ink Pen 5 A2 Plastic hook (small piece of plastic) from tube light found 5 H3 Orange plastic(most likely from the bags used to maintain the ice) found -2" sq 6 I/H Yellow plastic found 7 C9 Small piece of black insulation 8 E3 1-1/16 inch nut 8 Screw(s) lost 9 B8 Yellow/Black tape is balled up configuration about the size of a golf ball Watts Bar Reactor Building GSI- 191 Debris Generation Calculation L: N DocumentNo:ALION-CAL-TVA-2739-03 Rev:3 Page: 25 of 60 9 H7 1" diameter plug of silicone like caulk 10 18 Duct tape approximately 6 to 8 -inches long found balled up 11 BI Piece of electrical wire, 1/4"x2" found inside a basket 11 15 2 inch square piece of duct tape found wadded 13 C1 rubber like material 13 1/4-20 x 1" cap screw 13 Small nut 14 H7 Flow passages 116/118, next to basket H7, 12 feet up from bottom of basket 16 14 1 inch piece of wood 17 D8 1 inch square plastic sheeting 17 H 1 Orange plastic(most likely from the bags used to maintain the ice) found Red duct tape found in a balled up configuration the size 17 13 of a golf ball 17 4-screw heads from top ring are lost 18 C3 Black duct tape found in a balled up configuration the size of a golf ball 18 El Duct tape 18 F4 12 in. wadded duct tape found 18 Duct tape, Red Lanyard, key ring, keys, TLD, badge and pens may 20 remain as a unit or get separated during a Design Basis event.21 A8 Brown plastic sheet- shredded-2"x2' 21 F9 Cord used to lower the thermal drill down ice basket found 23 Two 9/16" 24 H3 Orange paper from a bag that contained tie wraps 24 G6 Orange plastic bag material (l"x3")24 H8 Clear plastic from bags used to maintain the ice 24 El One 1 1/8" nut 24 18 Pencil?? IPencil

:.: I Watts Bar Reactor Building GSI-191 Debris Generation Calculation A I 0 Ni Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 26 of 60 5 ANALYSIS According to the Watts Bar UFSAR [2], the accident scenarios that could lead to recirculation are a small break LOCA (SBLOCA), a large break LOCA (LBLOCA), and a main steam or feedwater line break [2]. The main steam and feedwater breaks are bounded by the LBLOCA as stated in Assumption 3.4. The five different break scenarios suggested in Section 4.3 were considered.

Break 1: Largest Potential for Debris Generation The largest quantity of insulation in containment is located in the RCS loops near each of the steam generators (SGs) and reactor coolant pumps (RCPs). Due to the size of the primary RCS loop piping and the quantity of insulation in close proximity to these pipes, a double-ended guillotine break of one of the primary loop pipes presents the limiting case for SBLOCAs and LBLOCAs at Watts Bar. The inside diameters of the primary RCS pipes are 29" for the hot legs, 27.5" for the cold legs, and 31" for the crossover legs [3.14, 3.15]. Clearly, a break in one of the 31" crossover legs would create the largest ZOI (31 in.*28.6/12

= 73.9' ZOI radius). However, depending on the exact location of various types of insulation, a break in the smaller hot or cold legs could result in the generation of a larger quantity of debris. Therefore, to analyze this scenario, the worst case break location and corresponding debris generation must be considered for all 4 loops. SER Section 3.3.5.2 advocates break selection at 5-ft intervals along a pipe in question but clarifies that "the concept of equal increments is only a reminder to be systematic and thorough".

It further qualifies that recommendation by noting that a more discrete approach driven by the comparison of debris source term and transport potential can be effective at placing postulated breaks. The key difference between many breaks (especially large breaks) will not be the exact location along the pipe, but ratherthe envelope of containment material targets that is affected.Break 2: Two or More Tvpes of Debris All of the breaks discussed above encompass this break scenario since multiple types of debris are present in each loop.Break 3: Most Direct Path to the Sump Since the ECCS recirculation sump is in close proximity to the RCS piping in Loops 3 and 4, a break in both of these cases would have a direct path to the sump.Break 4: Largest Particulate to Fiberglass Ratio The Watts Bar debris spreadsheet identified Min-K, 3M-M20C (Interam) and RMI within containment.

Of these three types of insulation, RMI is the least problematic.

RMI does not transport as easily as particulate and is not a major factor in developing headloss.

Min-K is predominantly a particulate insulation material.

This insulation is in various locations close to Watts Bar Reactor Building GSI-191 Debris Generation Calculation AL I 0,N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 27 of 60 Doc men ... .L. .the main steam lines and steam generators and throughout containment (Attachment A). There is also 3M-M20C (Interam) insulation in small areas throughout containment (Attachment A).Therefore, as the quantity of RMI is not significant and the quantity of coatings debris would be relatively the same for each break, the bounding case for each loop is which RCS break would destroy the most Min-K and 3M-M20C (Interam) debris. A thorough analysis has shown that a break in each of the crossover legs near the steam generator nozzle yields the most of these debris types.Break 5: Potential Formation of the Thin-Bed Effect This scenario addresses the generation of a small quantity of fibrous debris that, after its transport to the sump screen, could form a uniform thin bed that would subsequently filter sufficient particulate debris to create a relatively high head loss. It takes a relatively small quantity of debris to form a thin bed and is dependent on both the insulation materials and the screen size.With the exception of a small quantity of mineral wool in penetrations where it would not be destroyed and a small amount of the 3M insulation, Watts Bar has no fibrous insulation in containment.

However it could be postulated that latent fiber would be transported to the sump followed by the washdown of latent particulate debris, potentially resulting in the thin-bed effect.The existing strainer area at Watts Bar is approximately 265 ft 2 as calculated from plant drawings [3]. Given this surface area, approximately 2.75 ft 3 of fiber would be required to form a 1/8" thin-bed.

Note that the above thin bed comparison is for illustrative purposes only, the existing strainer is not being analyzed.The break locations that will be analyzed in this report are identified below in Figure 5.1.I--. ....,. ...Case 3 Cs I I* " .." ..' .' .' .;Figure 5.1 -Debris Generation Break Locations

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation t.LI1ON Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 28 of 60 5.1 Case I -LBLOCA in Loop I Figures 5.1.1 and 5.1.2 show the ZOIs for the four types of debris in Loop I for a break in the 31" crossover leg at the base of the steam generator.

This was determined to be the worst case break location for this loop since it generates a significant amount of coatings and RMI debris as well as encompassing the greatest total amount of 3M-M20C (Interam) and Min-K.Figure 5.1.1 -Case 1 RMI

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 29 of 60 Figure 5.1.2 -Case 1 Coatings, Min-K and approximate 3M-M20C ZOI RMI According to the Enercon developed insulation spreadsheet (Attachment A), RMI is located on nearly every major pipe and piece of equipment in lower containment.

As shown in Figure 5.1.1, the postulated break at the base of the steam generator would destroy most of the RMI in Loops I and 4, the RMI on most of the pressurizer, and RMI on some of the piping and equipment in Loop 2. Some of the equipment and piping in Loop 4 is on the other side of the reactor vessel Watts Bar Reactor Building GSI-191 Debris Generation Calculation A -Il 0_N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 30 of 60 and would not be destroyed.

The equipment and lines included in the quantity destroyed are tabulated line by line in Appendix 3.Using the provided insulation spreadsheet (Attachment A) and the walkdown package [9], the spreadsheets included in Appendices 1-3 were created. These spreadsheets calculate the quantity of RMI postulated to be destroyed by using the equation defined in Section 4.4. The RMI is made up of 0.004 inch stainless steel foils, which are spaced at 3 foils per inch of panel thickness[Attachment J]. Therefore, multiplying the volumes reported in Appendix 2 by the number of foils per inch (as described in Section 4.4), a total foil surface area of 101,202 ft 2 of RMI would be destroyed.

The size distribution would be 75% small pieces (75,902 ft 2) and 25% large pieces (25,300 ft 2).Min-K Most of the Min-K in containment is installed in small places on lines such as the pressurizer spray line, excess letdown lines, auxiliary feedwater line and auxiliary spray line. TVA Calculation MDQ0010622007115

[24] details Min-K which will have additional banding installed.

The Min-K ZOIs (28.6 as originally installed and 10.0 for additionally banded Min-K)were mapped in a 3D CAD model and the destroyed Min-K insulation was calculated (Appendix 3). The amount of Min-K that would be destroyed is 1.26 ft 3 (Appendix

3) which equals 20.2 lb (1.26 ft 3

• 16 lb/ft 3) with a debris size distribution of 100% fines. This equates to 0.252 ft 3 of fiber (1.26 ft 3

• 20%), 13.1 lb of fumed silica (20.2 lb

• 65%), and 3.02 lb of titanium dioxide (20.2 lb

• 15%).3M-M20C (Interam)This insulation is on boxes, conduit, and supports near the 716' and 745' elevations in patches throughout containment

[9]. The ZOI for this material envelops all of the 3M-M20C (Interam)in Loops 1, 2 and 4 (Appendix 3). Equipment shielding effects were analyzed in relation to this material the details of which are presented in Appendix 5. The total amount of 3M material that could be destroyed is 5.87 ft 3 (Appendix

3) which equals 229 lb (5.87 ft 3

• 39 lb/ft ) with a distribution of 55% LDFG fibers and 45% vermiculite particulate (Attachment F).The LDFG portion of the Interam equals 52.5 ft 3 [(5.87 ft 3

• 39 lb/ft 3

• 55%) / (2.4 lb/ft 3)]The vermiculite portion of the Interam equals 103 lb (5.87 ft 3

• 39 lb/ft 3

• 45%)Paint Coatings For the qualified coatings, the SER recommends using a spherical ZOI for coatings with a radius equal to 10 times the diameter of the postulated pipe break. The total concrete and steel surface area within this ZOI was calculated using the Watts Bar CAD model. Table 5.1.1 below shows the surface area calculations.

Section 4.5.2 shows the equation used to calculate the final surface area. Appendix 4 contains screenshots of each value used to calculate an area for traceability purposes.

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation aL, I-O-N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 31 of 60 Table 5.1.1 -Surface Area Calculations Within the Loop 1 ZOI Case I -Full 10D ZOI ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. I Equipment Subtracted from Sphere (sq. ft.): 6914 Appendix 4 -Fig. 2 Sphere and Equipment Intersected (sq. ft.): 9702 A endix4-Fi 3 Final Surface Area Equals (sq. ft.): 4115 ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. I luipment Subtracted from Sphere (sq. ft.): 10586 Appendix 4 -Fig. 4 Sphere and Equipment Intersected (sq. ft.): 2248 Final Surface Area Equals (sq. ft.): 2224 Case I -10D ZOI Within 6' of Floor ZOI Sphere Area (sq. ft.): 3939 Appendix 4 -Fig. 6 0 Equipment Subtracted from Sphere (sq. ft.): 2596 Appendix 4 -Fig. 9 Sphere and Equipment Intersected (sq. ft.): 3787 Final Surface Area Equals (sq. ft.): 1222 ZOI Sphere Area (sq. ft.): 3939 Appendix 4 -Fig. 6 Equipment Subtracted from Sphere (sq. ft.): 4409 Appendix 4 -Fig. 7 Sphere and Equipment Intersected (sq. ft.): 767.9.-Final Surface Area Equals (sq. ft.): 619.1.~Case, I -Steam Generator Silicone Ca ZOI Sphere Area (sq. ft.): 8386 lations Appendix 4 -Fig. I 0: 3 SGs Subtracted from Sphere (sq. ft.): 9195 Appendix 4 -Fig. 35-+_=Sphere and SGs Intersected (sq. ft.): 1204 Appendix 4 -Fig. 36 21 Final Surface Area Equals (sq. ft): 1007 0 Z75 ZOI Sphere Area (sq. ft.): 68597 Appendix 4 -Fig. 37 Equipment Subtracted from Sphere (sq. ft.): 74080 Appendix 4 -Fig. 38 Sphere and Equipment Intersected (sq. ft.): 6051 A*Final Surface Area Equals (sq. ft.): 5767 The total concrete surface area within the ZOI was calculated to be 4,115 ft 2.Of this total, 1,222 ft 2 is within 6 feet of the containment floor and is coated with CarbolineTM 295 as well as two coats of PhenolineTM 305.The total steel surface area within the coatings ZOI was calculated to be 2,224 ft 2.In order to account for other steel surfaces like gratings, handrails, and miscellaneous items not included in the CAD model, the steel surface area was increased by 10% (222 ft 2) to 2,446 ft 2.Of this total, Watts Bar Reactor Building GSI-191 Debris Generation Calculation A L I t N Document No:ALION-CAL-TVA-2739-03 Rev:3. Page: 32 of 60 approximately 619 ft 2 is within 6 feet of the containment floor and is also coated with a 5 mil coat of Phenoline 3 05TM. In order to account for other steel surfaces like gratings, handrails, and miscellaneous items not included in the CAD model, this surface area was also increased by 10%(62 ft 2) to 681 ft 2.The containment dome liner is also coated with a non-DBA certified CarbozincTM 11 primer coat, therefore these coatings will also fail as fines. The dome has an 89' radius [3.19] and taking the projected area of the dome over the area inside the crane wall (radius of 57.5' [3.19])yields a surface area of 11,868 ft 2 (See Appendix 4, Figure 4.52). In order to account for other steel surfaces, 10% of this total (1,187 ft 2) was added to the upper containment unqualified coatings to give a total of 13,055 ft2. As discussed in Section 4.5.2, the thickness of IOZ paint applied to all steel surfaces is approximately 4 mils, and the applied density is approximately 223 lb/ft 3.The RMI on the pressurizer and on steam generators 1 and 4 will fail (Appendix

3) and is coated with CarbolineTM 4674. As the CarbolineTM 4674 coatings are unqualified, any coating exposed due to the failure of the RMI will fail. 1,007 ft 2 of the steam generators was determined to be within the 1OD coatings ZOI. The surface area inside the RMI ZOI and outside the coatings ZOI was determined to be 4,760 ft 2 (5,767 ft 2 -1,007 ft 2).The walkdown report specifies 0.45 ft 3 of unqualified alkyds throughout containment.

The SER recommends a density of 98 lb/ft 3 for alkyds [5]. The walkdown report specifies that the pressurizer relief tank has been coated with approximately 400 ft 2 of epoxy with a thickness of 8 mil which has not been DBA certified and will also be assumed to fail [9] with a density of 94 lb/ft 3 [4].Using the calculated surface areas within the ZOI, this gives a total quantity of 1,152 lb of IOZ (182 lb+970 lb) paint, 137 lb of phenolic paint, 752 lb of Carboline 295, 25 lb of epoxy, 44 lb of alkyds, and 42 lb (35 lb+7 lb) of silicone as shown in the following calculations:

Watts Bar Reactor Building GSI-191 Debris Generation Calculation A :1. I 0N~i Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 33 of 60 QuantityjozLoe...

= (2,446ft 2) * (0.004in)

• lfi

• 223/b = 1821b (Eq. 2)12in ft 3 Quantity lOzupper = (13,055ft 2)* (0.004in)*

Ift

• 223/ b 9701b (Eq. 3)12in ft 3 2lf!t10 lb Quantityphenolidnsid1zoJ

= (681ft2 + (2

• 1,222ft2 ))*(0.005)*

• o5* 105- = 1371b (Eq. 4)12in ft 3 QuantityCabalin2951nsideZO]

= (1,222ft 2) * (0.060in)

• 13 lb 7521b (Eq. 5)12in fT 3 QuantityEpoxyOudeZOl

= (400ft 2) * (0.008)

• lft 94 lb = 251b (Eq. 6)12in ft 3 Quantitys.

dezo]= (1,007ft 2) * (0.001in)

• ft* 87 lb = 7/b (Eq.7)l2in ft 3 Qluantity

• f (00 un __ lb Qua SiliconeOutsideCoatingsZOz

= (4,760f 2) 00 lin)

• lft-

• 87 lb = 35/b (Eq.8)12in ft 3 Quantity Alkyd, = (0.45ft 3)*98lb -- 441b (Eq.9)ft 3 As discussed in Section 4.5.2, the size distribution for the IOZ, phenolic, silicone and alkyd coatings will be 100% particulate.

Latent Debris It was assumed that the quantity of latent debris at Watts Bar is equal to 200 lb. SER Section 3.5.2.3 suggests that 15% of the latent debris should be assumed to be fiber, and the other 85%particulate

[5]. Thus, 170 lb was assumed to be dirt/dust and the remaining 30 lb was assumed to be latent fiber. The representative bulk density of latent fiber was assumed to be 2.4 lb/ft 3 , and the material (individual fiber) density of latent fiber was assumed to be 94 lb/ft 3 based on the SER Section 3.5.2.3 [5]. Thus, (30 lb of latent fiber)/ (2.4 lb/ft 3) = 12.5 ft 3 of latent fiber.

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation ,N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 34 of 60 5.2 Case 2 -LBLOCA in Loop 2 Figures 5.2.1 and 5.2.2 show the ZOIs for each type of insulation in Loop 2 for a break in the 31" crossover leg at the base of the steam generator.

As in Case 1, this was determined to be the worst case break location for this loop since it generates a significant amount of coatings and RMI debris as well as encompassing the greatest total amount of 3M-M20C (Interam) and Min-K.Figure 5.2.1 -Case 2 RMI

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation ,N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 35 of 60 Figure 5.2.2 -Case 2 Coatings, Min-K and approximate 3M-M20C ZOI RMI According to the Enercon provided insulation spreadsheet (Attachment A), RMI is located on nearly every major pipe and piece of equipment in lower containment.

As shown in Figure 5.2.1, the postulated break at the base of the steam generator would destroy most of the RMI in Loops 2 and 3, the RMI on most of the pressurizer and some of the RMI on the piping and equipment in Loop 1. Some of the equipment and piping in Loop 4 is on the other side of the reactor vessel and would not be destroyed.

The equipment and lines included in the quantity destroyed are tabulated line by line in Appendix 3.Using the provided insulation spreadsheet (Attachment A) and the walkdown package [9], the spreadsheets included in Appendices 1-3 were created. These spreadsheets calculate the quantity of RMI postulated to be destroyed by using the equation defined in Section 4.4. The RMI is Watts Bar Reactor Building GSI-191 Debris Generation Calculation ALIO 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 36 of 60 made up of 0.004 inch stainless steel foils, which are spaced at 3 foils per inch of panel thickness[Attachment J]. Therefore, multiplying the volume reported in Appendix 2 by the number of foils per inch (as described in Section 4.4), a total foil surface area of 100,293 ft 2 of RMI would be destroyed.

The size distribution would be 75% small pieces (75,220 ft 2) and 25% large pieces (25,073 ft 2).Min-K Most of the Min-K in containment is installed in small places on lines such as the pressurizer spray line, excess letdown lines, auxiliary feedwater line and auxiliary spray line. TVA Calculation MDQOO 10622007115

[24] details Min-K which will have additional banding installed.

The Min-K ZOIs (28.6 as originally installed and 10.0 for additionally banded Min-K)were mapped in a 3D CAD model and the destroyed Min-K insulation was calculated (Appendix 3). The amount of Min-K that would be destroyed is 1.97 ft 3 (Appendix

3) which equals 31.5 lb (1.97 ft 3

• 16 lb/ft 3) with a debris size distribution of 100% fines. This equates to 0.394 ft 3 of fiber (1.97 ft 3

• 20%), 20.5 lb of fumed silica (31.5 lb

• 65%), and 4.7 lb of titanium dioxide (31.5 lb

• 15%).3M-M20C (Interam)This insulation is on boxes, conduit, and supports near the 716' and 745' elevations in patches throughout containment

[9]. The ZOI for this material envelops all of the 3M-M20C (Interam)in Loops 1 and 2 (Appendix 3). Equipment shielding effects were analyzed in relation to this material the details of which are presented in Appendix 5. The total amount of 3M material that could be destroyed is 8.45 ft 3 (Appendix

3) which equals 330 lb (8.45 ft 3

• 39 lb/ft 3) with a distribution of 55% LDFG fibers and 45% vermiculite particulate (Attachment F).The LDFG portion of the Interam equals 75.5 ft 3 [(8.45 ft 3

• 39 lb/ft 3

• 55%) / (2.4 lb/ft 3)]The vermiculite portion of the Interam equals 148 lb (8.45 ft 3

• 39 lb/ft 3

• 45%)Paint Coatings For the qualified coatings, the SER recommends using a spherical ZOI for coatings with a radius equal to 10 times the diameter of the postulated pipe break. The total concrete and steel surface area within this ZOI was calculated using the Watts Bar CAD model. Table 5.2.1 below shows the surface area calculations.

Appendix 4 contains screenshots of each value used to calculate an area for traceability purposes.

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation ,A L I ,O N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 37 of 60 Table 5.2.1 -Surface Area Calculations Within the Loop 2 ZOI-Case 2 -Full 10D ZOI ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. I Equipment Subtracted from Sphere (sq. ft.): 7201 Appendix 4 -Fig. 11 Sphere and Equipment Intersected (sq. ft.): 10151 A endix 4 -Fi .12 Final Surface Area Equals (sq. ft.): 4483 ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. I Equipment Subtracted from Sphere (sq. ft.): 10699 Appendix 4 -Fig. 13 Sphere and Equipment Intersected (sq. ft.): 2353 A endix 4 -Fi .14 Final Surface Area Equals (sq. ft.): 2333 Case 2- IOD ZO Within 6' of Floor-'ZOI Sphere Area (sq. ft.): 3939 Appendix 4 -Fig. 6 Equipment Subtracted from Sphere (sq. ft.): 2596 Appendix 4 -Fig. 15 Sphere and Equipment Intersected (sq. ft.): 3793 A endix 4 -Fi .16 Final Surface Area Equals (sq. ft.): 1225 ZOI Sphere Area (sq. ft.): 3939 Appendix 4 -Fig. 6 Equipment Subtracted from Sphere (sq. ft.): 4408 Appendix 4 -Fig. 17 Sphere and Equipment Intersected (sq. ft.): 767 Appendix 4 -Fig. 18 Final Surface Area Equals (sd. ft.): 619 Case 2 -Steam Generator Silicone Calculations ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. 1 Z N SGs Subtracted from Sphere (sq. ft.): 9183 Appendix 4 -Fig. 40 Sphere and SGs Intersected (sq. ft.): 1204 A endix,4 -Fig. 41 Final Surface Area Equals (sq. ft.): 1001 ZOI Sphere Area (sq. ft.): 68597 0 U Appendix 4 -Fig. 37-+Equipment Subtracted from Sphere (sq. ft.): 75406 Appendix 4 -Fig. 42 Sphere and Equipment Intersected (sq. ft.): 6841 A -V;" Aq~1~Final Surface Area Equals (sq. ft.): 6825 The total concrete surface area within the ZOI was calculated to be 4,483 ft 2.Of this total, 1,225 ft 2 is within 6 feet of the containment floor and is coated with CarbolineTM 295 as well as two coats PhenolineTM 305.The total steel surface area within the coatings ZOI was calculated to be 2,333 ft 2.In order to account for other steel surfaces like gratings, handrails, and miscellaneous items not included in the CAD model, the steel surface area was increased by 10% (233 ft 2) to 2,566 ft 2.Of this total, Watts Bar Reactor Building GSI-191 Debris Generation Calculation A L I 01N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 38 of 60 approximately 619 ft 2 is within 6 feet of the containment floor and is also coated with 5 mil of Phenoline 305TM. In order to account for other steel surfaces like gratings, handrails, and miscellaneous items not included in the CAD model, this surface area was also increased by 10%(62 ft:) to 681 ft 2.The containment dome liner is also coated with a non-DBA certified CarbozincTM 11 primer coat, therefore these coatings will also fail as fines. The dome has an 89' radius [3.19] and taking the projected area of the dome over the area inside the crane wall (radius of 57.5' [3.19])yields a surface area of 11,868 ft 2 (See Appendix 4, Figure 4.52). In order to account for other steel surfaces, 10% of this total (1,187 ft 2) was added to the upper containment unqualified coatings to give a total of 13,055 ft 2.As discussed in Section 4.5.2, the thickness of IOZ paint applied to all steel surfaces is approximately 4 mils, and the applied density is approximately 223 lb/ft 3.The RMI on the pressurizer and on steam generators 2 and 3 will fail (Appendix

3) and is coated with CarbolineTM 4674. As the CarbolineTM 4674 coatings are unqualified, any coating exposed due to the failure of the RMI will fail. 1,001 ft 2 of the steam generators was determined to be within the 1OD coatings ZOI. The surface area inside the RMI ZOI and outside the coatings ZOI was determined to be 5,824 ft 2 (6,825 ft 2 -1,001 ft 2).The walkdown report specifies 0.45 ft 3 of unqualified alkyds throughout containment.

The SER recommends a density of 98 lb/ft 3 for alkyds [5]. The walkdown report specifies that the pressurizer relief tank has been coated with approximately 400 ft 2 of epoxy with a thickness of 8 mil which has not been DBA certified and will also be assumed to fail [9] with a density of 94 lb/ft 3 [4].Using the calculated surface areas within the ZOI, this gives a total quantity of 1,161 lb of IOZ (191 lb+970 lb) paint, 137 lb of phenolic paint, 753 lb of Carboline 295, 25 lb of epoxy, 44 lb of alkyds, and 49 lb (42 lb+7 lb) of silicone as shown in the following calculations:

Watts Bar Reactor Building GSI-191 Debris Generation Calculation AIO 0 , :Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 39 of 60 QuantitylozL....

= (2,566ft 2) * (0.004in)

• lift, 223 lb = 19 l1b (Eq. 10)12in fh 3 Quantity ozuppr = (13,055ft 2)* (0.004in)

• ift

• 223/lb = 970/b (Eq. 11)12in ft 3 Qua tit Phnohlnsdezl lft 10 lb

= (681ft 2 +(2*1,225ft 2))*(0.005in)*l--t 105- = 1371b (Eq.12)12n ft 3 Quantity C.,Min 295 niodzoJ = (1,225ft 2) * (0.060in)

• 1--if, 123-lb = 753/b (Eq. 13)12n ft 3 Quantity EpoxyO.,ideZO, = (400ft 2) * (0.008in)

• 9f 4 b 25/b (Eq. 14)12in ft 3 QuantitySilk, .mn.idCZOJ

= (1,00 lft 2) * (0.00 in)

• lft

• 87 lb= 71b (Eq. 15)12in ft 3 Quantitysjjý,ou,,sjdeCoatngszo, = (5,824ft 2) * (0.00 lin)

• ift

• 87 lb = 42/b (Eq. 16)12in ft 3 Quantity Alkyd, = (0.45ft 3)*98 lb = 44/b (Eql7)ft As discussed in Section 4.5.2, the size distribution for the IOZ, phenolic, silicone and alkyd coatings will be 100% particulate.

Latent Debris It was assumed that the quantity of latent debris at Watts Bar is equal to 200-lb. SER Section 3.5.2.3 suggests that 15% of the latent debris should be assumed to be fiber, and the other 85%particulate

[5]. Thus, 170 lb was assumed to be dirt/dust and the remaining 30 lb was assumed to be latent fiber. The representative bulk density of latent fiber was assumed to be 2.4 lb/ft 3 , and the material (individual fiber) density of latent fiber was assumed to be 94 lb/ft 3 based on the SER Section 3.5.2.3 [5]. Thus, (30 lb of latent fiber)/ (2.4 lb/ft 3) = 12.5 ft 3 of latent fiber.

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 40 of 60 5.3 Case 3 -LBLOCA in Loop 3 Figures 5.3.1 and 5.3.2 show the ZOIs for each type of insulation in Loop 3 for a break in the 31" crossover leg at the base of the steam generator.

As in Case 1, this was determined to be the worst case break location for this loop since it generates a significant amount of coatings and RMI debris as well as encompassing the greatest total amount of 3M-M20C (Interam) and Min-K.Figure 5.3.1 -Case 3 RMI

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation AL,.ION Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 41 of 60 Figure 5.3.2 -Case 3 Coatings, Min-K and approximate 3M-M20C ZOI RMI According to the Enercon developed insulation spreadsheet (Attachment A), RMI is located on nearly every major pipe and piece of equipment in lower containment.

As shown in Figure 5.3.1, the postulated break at the base of the steam generator would destroy most of the RMI in Loops 2 and 3 and the RMI on most of the pressurizer.

Some of the equipment and piping in Loop I is on the other side of the reactor vessel and would not be destroyed.

The equipment and lines included in the quantity destroyed are tabulated line by line in Appendix 3.Using the provided insulation spreadsheet (Attachment A) and the walkdown package [9], the spreadsheets included in Appendices 1-3 were created. These spreadsheets calculate the quantity of RMI postulated to be destroyed by using the equation defined in Section 4.4. The RMI is made up of 0.004 inch stainless steel foils, which are spaced at 3 foils per inch of panel thickness[Attachment J]. Therefore, multiplying the volume reported in Appendix 2 by the number of foils per inch (as described in Section 4.4), a total foil surface area of 85,153 ft 2 of RMI would be destroyed.

The size distribution would be 75% small pieces (63,865 ft 2) and 25% large pieces (21,288 ft 2).

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation ALL 1 N0 Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 42 of 60 Min-K Most of the Min-K in containment is installed in small places on lines such as the pressurizer spray line, excess letdown lines, auxiliary feedwater line and auxiliary spray line. TVA Calculation MDQ0010622007115

[24] details Min-K which will have additional banding installed.

The Min-K ZOIs (28.6 as originally installed and 10.0 for additionally banded Min-K)were mapped in a 3D CAD model and the destroyed Min-K insulation was calculated (Appendix 3). The amount of Min-K that would be destroyed is 0.80 ft 3 (Appendix

3) which equals 12.8 lb (0.80 ft 3

• 16 lb/ft 3) with a debris size distribution of 100% fines. This equates to 0.16 ft 3 of fiber (0.80 ft 3

• 20%), 8.32 lb of fumed silica (12.8 lb

• 65%), and 1.92 lb of titanium dioxide (12.8 lb* 15%).3M-M20C (Interam)This insulation is on boxes, conduit, and supports near the 716' and 745' elevations in patches throughout containment

[9]. The ZOI for this material envelops all of the 3M-M20C (Interam)in Loop 2 (Appendix 3). Equipment shielding effects were analyzed in relation to this material the details of which are presented in Appendix 5. The total amount of 3M material that could be destroyed is 1.67 ft 3 (Appendix

3) which equals 129 lb (1.67 ft 3

• 39 lb/ft 3) with a distribution of 55% LDFG fibers and 45% vermiculite particulate (Attachment F).The LDFG portion of the Interam equals 14.9 ft 3 [(1.67 ft 3

• 39 lb/ft 3

• 55%) / (2.4 lb/ft 3)]The vermiculite portion of the Interam equals 29.3 lb (1.67 ft 3

• 39 lb/ft 3

• 45%)Paint Coatings For the qualified coatings, the SER recommends using a spherical ZOI for coatings with a radius equal to 10 times the diameter of the postulated pipe break. The total concrete and steel surface area within this ZOI was calculated using the Watts Bar CAD model. Table 5.3.1 below shows the surface area calculations.

Appendix 4 contains screenshots of each value used to calculate an area for traceability purposes.

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation AL I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 43 of 60 I Table 5.3.1 -Surface Area Calculations Within the Loop 3 ZOI Case 3 -Full 1OD Z01 I ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. 1 Equipment Subtracted from Sphere (sq. ft.): 6880 Appendix 4 -Fig. 19 Sphere and Equipment Intersected (sq. ft.): 11359 A endix 4 -Fi .20 Final Surface Area Equals (sq. ft.): 4927 ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. 1 Equipment Subtracted from Sphere (sq. ft.): 10531 Appendix 4 -Fig. 21 Sphere and Equipment Intersected (sq. ft.): 2192 A endix 4 -Fi .22 Final Surface Area Equals (sq. ft.): 2169'Case 3 -IOD ZOI Within 6' of Floor ZOI Sphere Area (sq. ft.): 3939 Appendix 4 -Fig. 6 Equipment Subtracted from Sphere (sq. ft.): 2590 Appendix 4 -Fig. 23 Sphere and Equipment Intersected (sq. ft.): 4067 Appendix 4 -Fig. 24 Final Surface Area Equals (sq. ft.): 1359 ZOI Sphere Area (sq. ft.): 3939 Appendix 4 -Fig. 6 Equipment Subtracted from Sphere (sq. ft.): 4409 Appendix 4 -Fig. 25 Sphere and Equipment Intersected (sq. ft.): 767 A endix 4- Fig. 26 Final Surface Area Equals (sq. ft.): 619 Case.3 .- Steam Generator Silicone Calculations S-s ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. I 7 N SGs Subtracted from Sphere (sq. ft.): 9190 Appendix 4-Fig. 44Sphere and SGs Intersected (sq. ft.): 1204 Appendix 4 -Fig. 45 Final Surface Area Equals (sq. ft.): 1004 ZOI Sphere Area (sq. ft.): 68597 Appendix 4 -Fij. 37; 0 0 U, Equipment Subtracted from Sphere (sq. ft.): [75126 1 Appendix 4 -Fig. 46 Sphere and Equipment Intersected (sq. ft.): 6675 ArnAiA -1Ph A'7 Final Surface Area Equals (sq. ft.): 6602 The total concrete surface area within the ZOI was calculated to be 4,927 ft 2.Of this total, 1,359 ft 2 is within 6 feet of the containment floor and is coated with CarbolineTM 295 as well as two coats of PhenolineTM 305.The total steel surface area within the coatings ZOI was calculated to be 2,169 ft2. In order to account for other steel surfaces like gratings, handrails, and miscellaneous items not included in the CAD model, the steel surface area was increased by 10% (217 ft 2) to 2,386 ft 2.Of this total, Watts Bar Reactor Building GSI-191 Debris Generation Calculation AL LON Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 44 of 60.. ... ....... ..o u e t o L O approximately 619 ft 2 is within 6 feet of the containment floor and is also coated with 5 mil of Phenoline 305TM. In order to account for other steel surfaces like gratings, handrails, and miscellaneous items not included in the CAD model, this surface area was also increased by 10%(62 ft 2) to 681 ft 2.The containment dome liner is also coated with a non-DBA certified CarbozincTM 11 primer coat, therefore these coatings will also fail as fines. The dome has an 89' radius [3.19] and taking the projected area of the dome over the area inside the crane wall (radius of 57.5' [3.19])yields a surface area of 11,868 ft 2 (See Appendix 4, Figure 4.52). In order to account for other steel surfaces, 10% of this total (1,187 ft 2) was added to the upper containment unqualified coatings to give a total of 13,055 ft 2.As discussed in Section 4.5.2, the thickness of IOZ paint applied to all steel surfaces is approximately 4 mils, and the applied density is approximately 223 lb/ft 3.The RMI on the pressurizer and on steam generators 2 and 3 will fail (Appendix

3) and is coated with CarbolineTM 4674. As the CarbolineTM 4674 coatings are unqualified, any coating exposed due to the failure of the RMI will fail. 1,004 ft 2 of the steam generators was determined to be within the 1OD coatings ZOI. The surface area inside the RMI ZOI and outside the coatings ZOI was determined to be 5,598 ft 2 (6,602 ft 2 -1,004 ft 2).The walkdown report specifies 0.45 ft 3 of unqualified alkyds throughout containment.

The SER recommends a density of 98 lb/ft 3 for alkyds [5]. The walkdown report specifies that the pressurizer relief tank has been coated with approximately 400 ft 2 of epoxy with a thickness of 8 mil which has not been DBA certified and will also be assumed to fail [9] with a density of 94 lb/ft 3 [4].Using the calculated surface areas within the ZOI, this gives a total quantity of 1,147 lb of IOZ (177 lb+970 lb) paint, 149 lb of phenolic paint, 836 lb of Carboline 295, 25 lb of epoxy, 44 lb of alkyds, and 48 lb (41 lb+7 lb) of silicone as shown in the following calculations:

I Watts Bar Reactor Building GSI- 191 Debris Generation Calculation

.0..... N.. Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 45 of 60 QuantityozL....

= (2,386ft2

)*(0.004in)

• l--f-i

• 223 lb = 1771b (Eq. 18)l2in ft 3 Quantity,ozu,, = (13,055ft2)

• (0.004in)

• lift

• 223 l = 970lb (Eq. 19)12in ft 3 Quantityph,.o,n..o1zodZO

= (68 lft 2 + (2 *1,359f))

• (0.005in)*-f--*li 5 5b 1491b (Eq. 20)l2in ft 3 Quantityc.boii,, zo = (1,359fti)

• (0.060in)

• ift

• 123 lb = 836/b (Eq. 21)12in ft 3 Quantityzox,,isdzo, = (400ft!) * (0.008in)

• lft

• 94/lb = 251b (Eq. 22)12in ft 3 Quantitysjins.e,,,azo, = (1,004ft 2 ) * (0.001in)

• lft- -= 7b (Eq.23)l2in ft 3 E.3 Quantitysi,..oneo,,,dca,,ngzoI

= (5,598 (0.001in)fft

• lf 87 = 41b (Eq.24)12in fi3 Quantitylkyd, = (0.45ft 3 98lbp = 44/b (Eq.25)ft 3 As discussed in Section 4.5.2, the size distribution for the IOZ, phenolic, silicone and alkyd coatings will be 100% particulate.

Latent Debris It was assumed that the quantity of latent debris at Watts Bar is equal to 200 lb. SER Section 3.5.2.3 suggests that 15% of the latent debris should be assumed to be fiber, and the other 85%particulate

[5]. Thus, 170 lb was assumed to be dirt/dust and the remaining 30 lb was assumed to be latent fiber. The representative bulk density of latent fiber was assumed to be 2.4 lb/ft 3 , and the material (individual fiber) density of latent

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation , .0I , N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 46 of 60 5.4 Case 4- LBLOCA in Loop 4 Figures 5.4.1 and 5.4.2 show the ZOIs for each type of insulation in Loop 4 for a break in the 31" crossover leg at the base of the steam generator.

As in the previous cases, this was determined to be the worst case break location for this loop since it generates a significant amount of coatings and RMI debris as well as encompassing the greatest total amount of 3M-M20C (Interam) and Min-K.Figure 5.4.1 -Case 4 RMI

• Watts Bar Reactor Building GSI-191 Debris Generation Calculation ,N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 47 of 60 Figure 5.4.2 -Case 4 Coatings, Min-K and approximate 3M-M20C ZOI RMI According to the Enercon developed insulation spreadsheet (Attachment A), RMI is located on nearly every major pipe and piece of equipment in lower containment.

As shown in Figure 5.4. 1, the postulated break at the base of the steam generator would destroy most of the RMI in Loops 1 and 4 and the RMI on most of the pressurizer.

Some of the equipment and piping in Loop 2 is on the other side of the reactor vessel and would not be destroyed.

The equipment and lines included in the quantity destroyed are tabulated line by line in Appendix 3.Using the provided insulation spreadsheet (Attachment A) and the walkdown package [9], the spreadsheets included in Appendix 1-3 were created. These spreadsheets calculate the quantity of RMI postulated to be destroyed by using the equation defined in Section 4.4. The RMI is made up of 0.004 inch stainless steel foils, which are spaced at 3 foils per inch of panel thickness[Attachment J]. Therefore, multiplying the volume reported in Attachment B b' the number of foils per inch (as described in Section 4.4), a total foil surface area of 84,644 ft of RMI would be destroyed.

The size distribution would be 75% small pieces (63,483 ft 2) and 25% large pieces (21,161 ft 2).

Watts Bar Reactor Building GSI-191 Debris Generation Calculation A: ION Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 48 of 60 Min-K Most of the Min-K in containment is installed in small places on lines such as the pressurizer spray line, excess letdown lines, auxiliary feedwater line and auxiliary spray line. TVA Calculation MDQ0010622007115

[24] details Min-K which will have additional banding installed.

The Min-K ZOIs (28.6 as originally installed and 10.0 for additionally banded Min-K)were mapped in a 3D CAD model and the destroyed Min-K insulation was calculated (Appendix 3). The amount of Min-K that would be destroyed is 1.98 ft 3 (Appendix

3) which equals 31.7 lb (1.98 ft 3

• 16 lb/fl 3) with a debris size distribution of 100% fines. This equates to 0.396 ft 3 of fiber (1.98 ft 3

• 20%), 20.61 lb of fumed silica (31.7 lb

• 65%), and 4.76 lb of titanium dioxide (31.7 lb

• 15%).3M-M20C (Interam)This insulation is on boxes, conduit, and supports near the 716' and 745' elevations in patches throughout containment

[9]. The ZOI for this material envelops all of the 3M-M20C (Interam)in Loops 4 and 1 (Appendix 3). Equipment shielding effects were analyzed in relation to this material the details of which are presented in Appendix 5. The total amount of 3M material that could be destroyed is 1.67 ft 3 (Appendix

3) which equals 65.1 lb (1.67 ft 3

• 39 lb/ft 3) with a distribution of 55% LDFG fibers and 45% vermiculite particulate (Attachment F).The LDFG portion of the Interam equals 14.9 ft 3 [(1.67 ft 3

• 39 lb/ft 3

• 55%) / (2.4 lb/fl 3)]The vermiculite portion of the Interam equals 29.3 lb (1.67 ft 3

• 39 lb/ft 3

• 45%)Paint Coatings For the qualified coatings, the SER recommends using a spherical ZOI for coatings with a radius equal to 10 times the diameter of the postulated pipe break. The total concrete and steel surface area within this ZOI was calculated using the Watts Bar CAD model. Table 5.4.1 below shows the surface area calculations.

Appendix 4 contains screenshots of each value used to calculate an area for traceability purposes.

Watts Bar Reactor Building GSI- 191 Debris Generation Calculation A. L CI O N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 49 of 60[Table 5.4.1 -Surface Area Calculations Within the Loop 4 ZOI Case 4 -Full 10D ZOI ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. 1 Equipment Subtracted from Sphere (sq. ft.): 6842 Appendix 4 -Fig. 27 Sphere and Equipment Intersected (sq. ft.): 11124 A endix4-Fi 28 Final Surface Area Equals (sq. ft.): 4790 ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. I pment Subtracted from Sphere (sq. ft.): 10547 Appendix 4 -Fig. 29 Sphere and Equipment Intersected (sq. ft.): 2205 Ann,-nA1vA14 c -;( n Final Surface Area Equals (sq. ft.): 2183 Case 4- 10D ZOI Within"of Floor ZOI Sphere Area (sq. ft.): 3939 Appendix 4 -Fig. 6 0 Equipment Subtracted from Sphere (sq. ft.): 2614 Appendix 4 -Fig. 31 Sphere and Equipment Intersected (sq. ft.): 3982 A.4 -Fin. 32 Final Surface Area Equals (sq. ft.): 1329 ZOI Sphere Area (sq. ft.): 3939 Appendix 4 -Fig. 6 Equipment Subtracted from Sphere (sq. ft.): 4409 Appendix 4 -Fig. 33 1 Sphere and Equipment Intersected (sq. ft.): 767 A, 4-Fig34 I Final Surface Area Equals (sq. ft.): 619 Case 4-. Steam Generator Silicone Calculations ZOI Sphere Area (sq. ft.): 8386 Appendix 4 -Fig. 1 SGs Subtracted from Sphere (sq. ft.): 9190 Appendix 4-Fig. 48 Sphere and SGs Intersected (sq. ft.): 1204 Appendix 4 -Fig. 49 Final Surface Area Equals (sq. ft.): 1004 ZOI Sphere Area (sq. ft.): 68597 0 U ADpendix 4 -Fig. 37 Equipment Subtracted from Sphere (sq. ft.): 74108 Appendix 4 -Fig. 50 Sphere and Equipment Intersected (sq. ft.): 5543 A A -17i" '1 Final Surface Area Equals (sq. ft.): 5527 The total concrete surface area within the ZOI was calculated to be 4,790 ft 2.Of this total, 1,329 ft 2 is within 6 feet of the containment floor and is coated with CarbolineTM 295 as well as two coats of PhenolineTM 305.The total steel surface area within the coatings ZOI was calculated to be 2,183 ft 2.In order to account for other steel surfaces like gratings, handrails, and miscellaneous items not included in the CAD model, the steel surface area was increased by 10% to 2,401 ft 2.Of this total, Watts Bar Reactor Building GSI- 191 Debris Generation Calculation

A: L:LI: 0 N DocumentNo:ALION-CAL-TVA-2739-03 Rev:3 Page: 50 of 60 approximately 619 ft 2 is within 6 feet of the containment floor and is also coated with 5 mil of Phenoline 305TM. In order to account for other steel surfaces like gratings, handrails, and miscellaneous items not included in the CAD model, this surface area was also increased by 10%(62 ft 2) to 681 ft 2.The containment dome liner is also coated with a non-DBA certified CarbozincTM 11 primer coat, therefore these coatings will also fail as fines. The dome has an 89' radius [3.19] and taking the projected area of the dome over the area inside the crane wall (radius of 57.5' [3.19])yields a surface area of 11,868 ft 2 (See Appendix 4, Figure 4.52). In order to account for other steel surfaces, 10% of this total (1,187 ft 2) was added to the upper containment unqualified coatings to give a total of 13,055 ft 2.As discussed in Section 4.5.2, the thickness of IOZ paint applied to all steel surfaces is approximately 4 mils, and the applied density is approximately 223 lb/ft 3.The RMI on steam generators 1 and 4 will fail (Appendix

3) and is coated with CarbolineTM 4674. As the CarbolineTM 4674 coatings are unqualified, any coating exposed due to the failure of the RMI will fail. 1,004 ft 2 of the steam generators was determined to be within the IOD coatings ZOI. The surface area inside the RMI ZOI and outside the coatings ZOI was determined to be 4,523 ft 2 (5,527 ft 2 -1,004 ft 2).The walkdown report specifies 0.45 ft 3 of unqualified alkyds throughout containment.

The SER recommends a density of 98 lb/ft 3 for alkyds [5]. The walkdown report specifies that the pressurizer relief tank has been coated with approximately 400 ft 2 of epoxy with a thickness of 8 mil which has not been DBA certified and will also be assumed to fail [9] with a density of 94 lb/ft3 [4].Using the calculated surface areas within the ZOI, this gives a total quantity of 1,148 lb of IOZ (178 lb+970 lb) paint, 146 lb of phenolic paint, 817 lb of Carboline 295, 25 lb of epoxy, 44 lb of alkyds, and 40 lb (33 lb+7 lb) of silicone as shown in the following calculations:

AL IO : Watts Bar Reactor Building GSI-191 Debris Generation Calculation Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 51 of 60 Quantity IOZLower = (2,40f!)*

(0.004in)

• lfti

• 223E = 1781b (Eq. 26)(2,401,ft 2) 223- =78b l2in ft 3 Quantity 1 ozuer = (13,055f2)

(0.004in)

____

• 223 = 9701b (Eq.27)12in ft 3 It2 9f2 ift lb QuantityPheo,UgsidezoI

= (681,3 +(2

• 1,32(0.6 (0i* in) *

• 105 1 146/b (Eq. 28)12in ft 3 QuantityCobu,, 2 9 5 1sjdezo, = (l,329ft 2)*(0.008 in)* *f*123 , = 81=7/b (Eq. 29)12in ft 3

= (400ft 2) * (0.00 lin)

• lft

• 94 lb = 25/b (Eq.30)12in ft 3 Quantitys,,,... = (1,004ft 2) * (0.00in) *1ft

• 87 7 lb = 7 1b (Eq.31)12in ft 3 QuantltySii'lneo1,SideCoai,ingZOI

=(4,523ft

• (0.001in)

• f*87-ft 33/b (Eq.32)12in ft Quantity Alkyds = (0.45ft 3) *98b = 44/b (Eq.33)ft 3 As discussed in Section 4.5.2, the size distribution for the IOZ, phenolic, silicone and alkyd coatings will be 100% particulate.

Latent Debris It was assumed that the quantity of latent debris at Watts Bar is equal to 200 lb. SER Section 3.5.2.3 suggests that 15% of the latent debris should be assumed to be fiber, and the other 85%particulate

[5]. Thus, 170 lb was assumed to be dirt/dust and the remaining 30 lb was assumed to be latent fiber. The representative bulk density of latent fiber was assumed to be 2.4 lb/ft 3 , and the material (individual fiber) density of latent fiber was assumed to be 94 lb/ft 3 based on the SER Section 3.5.2.3 [5]. Thus, (30 lb of latent fiber)/ (2.4 lb/ft 3) = 12.5 ft 3 of latent fiber.

:Watts Bar Reactor Building GSI-191 Debris Generation Calculation SI Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 52 of 60 6 RESULTS Tables 6.1 through 6.4 summarize the Watts Bar debris generation results for Cases 1 through 4 which all involve a break in the 31" crossover leg at the base of the steam generator.

Table 6.5 shows the material properties of the generated debris.Table 6.i -Case I 1ebris Source I erm for a break, in LOOP I Debris Type Small Pieces Large Pieces Total Stainless Steel RMI 75,902 ft 2 (75%) 25,300 (25%) 101,202 ft 2 Debris Type Fines Large Pieces Total 3M-M20C (Interam) 52.5 ft 3 0 ft 3 52.5 ft 3 Fiber Latent Fiber 12.5 ft 3 0 ft 3 12.5 ft 3 Min-K -Fiber 0.25 ft 3 0 ft 3 0.25 ft 3 Debris Type Fines Chips Total 3M-M20C (Interam) 103 lb 0 lb 103 lb Particulate Min-K -'Si0 2 13.1 lb 0 lb 13.1 lb Min-K -TiO 2 3.02 lb 0 lb 3.02 lb Dirt/Dust 170 lb 0 lb 170 lb Phenolic Paint 137 lb 0 lb 137 lb IOZ Paint 1,152 lb 0 lb 1,152 lb Alkyd Paint 44 lb 0 lb 44 lb Epoxy Paint 25 lb 0 lb 25 lb Carboline 295 752 lb 0 lb 752 lb Silicone Paint 42 lb 0 lb 42 lb Watts Bar Reactor Building GSI-191 Debris Generation Calculation

ik~li:N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 53 of 60 Table 6.2 -Case 2 Debris Source Term for a Break in Loop 2 Debris Type Small Pieces Large Pieces Total Stainless Steel RMI 75,220 ft(75%) 25,073 ft 2 (25%) 100,293 ft 2 Debris Type Fines Large Pieces Total 3M-M20C (Interam) 75.5 ft 3 0 ft 3 75.5 ft 3 Fiber Latent Fiber 12.5 ft 3 0 ft 3 12.5 ft 3 Min-K -Fiber 0.39 ft 3 0 ft 3 0.39 ft 3 Debris Type Fines Chips Total 3M-M27 C (Interam) 148 lb 0 lb 148 lb Particulate Min-K -SiO 2 20.5 lb 0 lb 20.5 lb Min-K -TiO 2 4.7 lb 0 lb 4.7 lb Dirt/Dust 170 lb 0 lb 170 lb Phenolic Paint 137 lb 0 lb 137 lb IOZ Paint 1,161 lb 0 lb 1,161 lb Alkyd Paint 44 lb 0 lb 44 lb Epoxy Paint 25 lb 0 lb 25 lb Carboline 295 753 lb 0 lb 753 lb Silicone Paint .49 lb 0 lb 49 lb Watts Bar Reactor Building GSI-191 Debris Generation Calculation

L I 0 N: Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 54 of 60 Table 6.3 -Case 3 Debris Source Term for a Break in Loop 3 Debris Type Small Pieces Large Pieces Total Stainless Steel RMI 63,865 ft 2 (75%) 21,288 ft 2 (25%) 85,153 ft 2 Debris Type Fines Large Pieces Total 3M-M20C (Interam) 14.9 ft 3 0 ft 3 14.9 ft 3 Fiber Latent Fiber 12.5 ft 3 0 ft 3 12.5 ft 3 Min-K -Fiber 0.16 ft 3 0 ft 3 0.16 ft 3 Debris Type Fines Chips Total 3M-M20C (Interam) 29.3 lb 0 lb 29.3 lb Particulate Min-K -Si0 2 8.32 lb 0 lb 8.32 lb Min-K -TiO 2 1.92 lb 0 lb 1.92 lb Dirt/Dust 170 lb 0 lb 170 lb Phenolic Paint 149 lb 0 lb 149 lb IOZ Paint 1,147 lb 0 lb 1,147 lb Alkyd Paint 44 lb 0 lb 44 lb Epoxy Paint 25 lb 0 lb 25 lb Carboline 295 836 lb 0 lb 836 lb Silicone Paint 48 lb 0 lb 48 lb Watts Bar Reactor Building GSI- 191 Debris Generation Calculation A L I 0.N Document No:ALION-CAL-TVA-2739-03 I Rev:3 Page: 55 of 60 Table 6.4 -Case 4 Debris Source Term for a Break in Loo 4 Debris Type Small Pieces Large Pieces Total Stainless Steel RMI 63,483 fW 2 (75%) 21,161 ft' (25%) 84,644 ft 2 Debris Type Fines Large Pieces Total 3M-M20C (Interam) 14.9 ft 3 0 ft 3 14.9 ft 3 Fiber Latent Fiber 12.5 ft 3 0 ft 3 12.5 ft 3 Min-K -Fiber 0.40 ft 3 0 ft 3 0.40 ft 3 Debris Type Fines Chips Total 3M-M20C (Interam) 29.3 lb 0 lb 29.3 lb Particulate Min-K -Si0 2 20.61 lb 0 lb 20.61 lb Min-K -TiO 2 4.76 lb 0 lb 4.76 lb Dirt/Dust 170 lb 0 lb 170 lb Phenolic Paint 146 lb 0 lb 146 lb IOZ Paint 1,148 lb 0 lb 1,148 lb Alkyd Paint 44 lb 0 lb 44 lb Epoxy Paint 25 lb 0 lb 25 lb Carboline 295 817 lb 0 lb 817 lb Silicone Paint 40 lb 0 lb 40 lb Watts Bar Reactor Building GSI- 191 Debris Generation Calculation 101-N. Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 56 of 60 Table 6.5 -Physical Properties of Debris Debris Type/Size Material Bulk Particulate/Individual Characteristic Size Density Fiber Density Stainless Steel RMI 1/41/' -4" (Small Pieces)Stainless Steel RMI 4" -6" (Large Pieces)Min-K -Fiber 16 lb/ft 3 165 lb/ft 3 6 ptm Min-K- Si0 2 16 lb/ft 3 137 lb/ft 3 20 ptm Min-K -TiO 2 16 lb/ft 3 262 lb/ft 3 2.5 pim 3M-M20C (Interam) 2.4 lb/ft 3 175 lb/ft 3 7 [tm Fiber Portion 3M-M20C (Interam) 4 lb/ft 3 156 lb/ft 3 10 ptm Particulate Portion Phenolic Paint 105 lb/ft 3 105 lb/ft 3 10 ptm (Fines)IOZ Paint 223 lb/ft 3 457 lb/ft 3 10 gm (Fines)Alkyd Paint (Fines) 98 lb/ft 3 98 lb/ft 3 10 [tm Carboline 4674 87 lb/ft 3 145 lb/ft 3 10 [Lm (Fines)Carboline 295 (Fines)123 lb/ft 3 123 lb/ft 3 10 ptm Epoxy (Fines) 94 lb/ft 3 94 lb/ft 3 10 ptm Dirt/Dust 169 lb/ft 3 17.3 ptm (Fines)Latent Fiber 2.4 lb/ft 3 94 lb/ft 3 7 pim (Fines)

Watts Bar Reactor Building GSI-191 Debris Generation Calculation 1,L 9 I U0N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 57 of 60 7 CONCLUSIONS Based on the results presented above, the following conclusions can be drawn for debris generation in the Watts Bar containment building:* The worstbreak location in each loop is in the crossover leg at the base of the steam generator.

This break location allows for the largest amount of coatings and RMI and also allows for the ZOI to envelop a large portion of the Min-K and 3M-M20C (Interam)insulation.

• The worst loop break location in regards to RMI is Loop 1. This break location (Loop 1)is also in close proximity to the emergency sump.* The Loop 2 break location destroys the most 3M-M20C (Interam) insulation and consequently, the greatest total fiber debris.* A break in Loop 4 destroys the greatest amount of Min-K insulation.

• All four loops generate comparable quantities of coatings debris.* The destruction pressure of 2.4 psi and the corresponding ZOI of 28.6D are likely overly conservative for the Min-K with no additional banding in Watts Bar. These Z01 values are for unjacketed Min-K and the installed Min-K at Watts Bar is jacketed in the same jacketing as the RMI. However, the SER instructs to use this value if no test data is available for the plant-specific jacketing.

Jet impingement testing has been conducted on the Watts Bar Min-K configuration with additional banding which shows no insulation destruction at distances beyond 10.0D.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation A:L IO0 N DocumentNo:ALION-CAL-TVA-2739-03 Rev:3 Page: 58 of 60 8 REFERENCES

1. Regulatory Guide 1.82, "Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident", USNRC, Rev. 3, November 2003.2. Watts Bar, Updated Final Safety Analysis Report, Revision Dated 27 March, 2003.3. Watts Bar Isometrics and Drawings Used to Determine Quantity of Insulation Within Specific ZOIS 3.1 "Problem 0600200-03-01 Analysis Isometric of RHR Piping", 1-47W432-215A, Rev. 0.3.2 "Problem N3-74-02A Analysis Isometric of RHR Piping", 47W432-305A, Rev 0.3.3 "Problem 0600200-13-09 Analysis Isometric of RCS Drain Line", 47W466-202, Rev 0.3.4 "3M-M20C Radiant Energy Shield, Inside Primary Containment Reactor Building", 47W234-6 Rev 0.3.5 "3M-M20C Radiant Energy Shield, Inside Primary Containment Reactor Building", 47W234-7 Rev 0.3.6 3M-M20C Radiant Energy Shield, Inside Primary Containment Reactor Building", 47W234-8 Rev 0.3.7 "Min-K to Waste Disposal Line", 47W2500-4 Rev 0.3.8 "Problem 0600200-13-02 4" Diameter Pressurizer Spray Line", 47W465-205 Rev 0.3.9 "Problem 0600200-09-01 Isometric of SIS Piping", 47W435-260C Rev 0.3.10 "Problem 0600200-08-11 Isometric of CVCS Piping", 47W406-321B Rev 0.3.11 "Problem 0600200-08-12 Isometric of CVCS Piping", 47W406-322A Rev 0.3.12 From the Walkdown Report, Drawing 47W401-209 Rev D.3.13 "Miscellaneous Steel Sump Liner Sheet 3", 48N919 Rev 14.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation

L I0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 59 of 60 3.14 Drawing Number 47W2500-1, Rev. 1 3.15 Drawing Number 47W2500-6, Rev. 2 3.16 Drawing Number 41N716-4, Rev. 6 3.17 Drawing Number 41N716-5 Rev. 5 3.18 Drawing Number 47W200-1 1, Rev. 9 3.19 Drawing Number 47W200-13, Rev. 5 3.20 Drawing Number 47W200-14, Rev. 5 4. NEI-04-07, Volume 1, NEI PWR Sump Performance Task Force, "Pressurized Water Reactor Sump Performance Evaluation Methodology", Rev. 1, November 19, 2004.5. NEI-04-07, Volume 2, NRC Safety Evaluation Report, "Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Generic Letter 2004-02, Nuclear Energy Institute Guidance Report 'Pressurized Water Reactor Sump Performance Evaluation Methodology"', Rev. 0, December 2004.6. NRC Bulletin 96-03, "Utility Resolution Guidance (URG) for ECCS Suction Strainer Blockage", Volume II, BWROG, November 1996.7. Rao, D. V., et al., "Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance", NUREG/CR-6808, Los Alamos National Laboratory, February 2003.8. Alion Document ALION-REP-ALION-2806-01, "Insulation Debris Size Distribution for use in GSI-191 Resolution", Rev. 3.9. "Report on Watts Bar Unit 1 Containment Building Walkdowns for Emergency Sump Strainer Issues", TVAWOO 1 -RPT-00 1, Rev 0.10. "CRC Handbook of Chemistry and Physics", David R. Lide, 75h Edition, 1994.11. "Technical and Programmatic Requirements For the Protective Coating Program For TVA Nuclear Plants", Robert L. Phillips, Rev 13, 10/14/2004

12. Perry's Chemical Engineering Handbook, 7th ed. McGraw Hill, 1997.

Watts Bar Reactor Building GSI-191 Debris Generation Calculation L: O L NI Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 60 of 60 13. Grimm, N.P., and Colenbrander, H.G.C., "Long Term Ice Condenser Containment Code-LOTIC Code," WCAP-8354-P-A, July 1974 (Proprietary), WCAP-8355-A (Nonproprietary), July 1974.14. Newby, D., "Test Plans and Results for the Ice Condenser System," WCAP-81 10, Supplement 6, May 1974.15. "Final Report Ice Condenser Full Scale Section Test at the Waltz Mill Facility," WCAP-8282 (Proprietary), February 1974, WCAP-821 1, Appendix (Nonproprietary), May 1974.16. Hsieh, T., and Raymund, M., "Long Term Ice Condenser Code-LOTIC Code, "WCAP-8354-P-A, Supplement 1 (Proprietary), June 1975, and WCAP-8355 Supplement 1 (Nonproprietary), June 1975.17. Krish M. Rajan, "Tennessee Valley Authority Watts Bar Nuclear Plant -Effect of Increased ERCW Temperature," WAT-D- 11144, 5/21/2003.

18. Phillips, R.L., "Technical and Programmatic Requirements for the Protective Coating Program for TVA Nuclear Plants," G-55 R-13, September 22, 2004.19. ALION-REP-TVA-2739-02, "Watts Bar Unit 1 Event Characterization", Rev. 0.20. NUREG/CR 6762, Vol. 3, "GSI-191 Technical Assessment:

Development of Debris-Generation Quantities in Support of the Parametric Evaluation," LA-UR-01-6640, 2002.21.. Alion Methodology Report ALION-REP-ALION-2806-03, "Coatings Surface Area and Quantity Calculation Methodology", Rev. 0.22. Software Document ALION-SVWD-ALION-3145-03, "User's Manual for Various CAD Software Packages", Rev. 1.23. Elliot, A.S and Andreychek, T.S., "Jet Impingement Testing to Determine the Zone of Influence (ZOI) of Min-K and 3M Fire Barrier Insulation for Watts Bar Nuclear Plant", WCAP- 16783-P, Rev.0, July 2007 24. Robertson, J., "Banding Requirements for Min-K Insulation Inside Containment", TVA Calculation MDQ0010622007115, Rev.0, July 2007 25. Westinghouse letter LTR-CSA-06-74 Regarding Watts Bar Latent Debris Survey Watts Bar Reactor Building GSI-191 Debris Generation Calculation Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 1-1 of 1-12 APPENDIX 1 -NUMBERED ENERCON INSULATION SPREADSHEET This Appendix contains the same Enercon provided Watts Bar insulation spreadsheet showing the type, quantity and location of insulation within containment with an additional column for each line item number. This spreadsheet is used by Appendix 2 and 3 to relate back to the Enercon provided insulation spreadsheet (Attachment A).

ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-2 of 1-12 DESCRIPTION Line Item NSUL VOLUME INSULATION JACKET STRAP Numbor (FT3) AREA PROBLEM NUMBER LOCATION ELEV. 00 IN) LENGTH (IT) INSUL TYPE THICKNESS (IN) MATERIAL BUCKLE TYPE TYPE COMMENTS PACKET LETTER SEALANT AROUND STAINLESS SEALANT BET SHEET METAL AND CONTAINMENT WALL Ite1 0327 1 N/A RACEWAY 702' N/A SEE CALC SILICON/RTV SEE CALC N/A NA N/A STEEL CONTAINMENT BEHIND PANEL 11.e 2 26073 1 N/A RACEWAY 702* N/A SEE CALC FOAMGLASS SEE CALC N/A N/A N/A N/A A SEALANT AROUND COVERS Item 3 NIA 1 N/A RACEWAY 702' N/A NIA N/A N/A N/A N/A N/A SEALANT APPLIED ALL AROUND B COVER MIRRORREFLECTIVE It.. 4 N/A 1 N/A RACEWAY 702' N/A NIA N/A SEE C0ALC WRi-OW- NIA N/A N/A MRI (LETDOWN LINES) C INSULATION 001, LABELS SIGNS In 5 0 N RACEWAY 702' N/A N/A N/A N/A N/A N/A N/A SEE REPORT FOR COMMENTS D PENETRATION NO. It.5 00 TIE WRAPS Ite7 U N/A 1 N/A RACEWAy 702' N/A N/A N/A N/A N/A N/A N/A SEE REPORT COMMENTS E CALCIUM SILICATE Item 7 56.70 1 N/A RACEWAY 702' SEE CALC SEE CALC CALCIUM SILICATE SEE CALC N/A N/A N/A SEE CALCULATION E SEAL AROUND PENETRATION PiPE It.. 8 0.02 1 N/A RACEWAY 702' N/A N/A RTV SEE CALC NIA NIA N/A N/A F FOAM IN PENETRATION It.. 9 3.18 1 N/A RACEWAY 702' N/A N/A FOAM SEE CALC N/A N/A N/A N/A F LETDOWN LINE Item 10 12.98 I 0100200-0U-09 RACEWAY 702' 350 64.75 RMI 1375 SS STD N/A 7" O INSULATION 0 LETDOWN LINE 11em 11 21,57 1 0600200-08-09 RACEWAY 702' 2.38 13034 RMI6 181 SS STD NWA 6"OD INSULATION G LETDOWN LINE Item 12 3.31 1 0600200408-09 RACEWAY 702' 2.26 534 RMI 4.31 5S. STD N/A 51 OD INSULATION G LETDOWN LINE Item 13 025 1 0600200-0-B09 RACEWAY 702' 2.38 436 RMI 081 SS STO N/A 4"OD INSULATION G LETDOWN LINE -it. 14 028 1 0600200-)0009 RACEWAY 702' 2.38 2.70 RMI 1.31 SS STD N/A 5OD INSULATION (2.38" 0O PIPING) G LETDOWN LINE item 15 0.10 1 0600200-06-09 RACEWAY 702' 1.06 0.0 RMI 1.97 S.S. STO N/A 5" 00 INSULATION O1.06" 0O PIPINGD G CALCIUM SILICATE Item 16 56.79 f N/A RACEWAY 702' SEE CALC SEE CALC CALCIUM SILICATE SEE CALC N/A N/A N/A SEE CALCULATION G EXCESS LETDOWN item 17 1.39 1 N/A RACEWAY 702' 1.32 7.46 RMI 2.34 S.S. STO N/A 6" 00 INSULATION J EXCESS LETDOWN IRem 18 044 1 N/A RACEWAY 702' 1.32 344 RMI 1.64 S.S. STO N/A 5" DO INSULATION J EXCESS LETDOWN It0m710 043 1 N/A RACEWAY 702' 1.32 1.00 RMI 384 S.S. STD N/A 9" OD INSULATION J SEAL WATER RETURN LINE 110.720 38.16 1 0600200ý06-06.

-07. 13 RACEWAy 702' 450 160.00 RMI 1.75 SS. STD N/A 60 INSULATION K SEAL WATER RETURN LINE Item 21 0.18 1 0600200-04)6-,-7, -13 RACEWAY 702' 4.50 205 MIN-K 0.75 N/A N/A N/A U" OD MIN-K INSULATION K SEAL WATER RETURN LINE Item 22 0.59 1 0600200-08-06d

-07. -13 RACEWAY 702' 4.50 379 RMI 125 SS STD WA 7"O INSULATION K SEAL WATER RETURN LINE Item 23 0.09 1 0600200-06-06, -07, -13 RACEWAY 702' 4.50 158 MIN-K 0.5 N/A NA NA 55" OD MIN.K INSULATION K SEAL WATER RETURN LINE Item 24 0.08 1 060020800-06, -07. -13 RACEWAY 702' 4.50 152 MIN-K 0.5 NIA N/A N/A 6.12' ODMIN-K INSULATION K SEAL WATER RETURN LINE /tem725 020 1 06002004-0800, -07.-13 RACEWAY 702' 4.50 094 RFI 1.625 SS, STD N/A 7.75" OD INSULATION K SEAL WATER RETURN LINE 1-07728 352 1 060020"08-06

-07, -13 RACEWAY 702' 3.50 1754 RMI 1.75 S.S STD N/A 7" OD INSULATION K SEAL WATER RETURN LINE l10727 0.05 1 0600200406-R, 407. -13 RACEWAY 702' 3.50 1.00 MIN-K 0.56 N/A N/A N/A 4.62' OD MIN-K INSULATION K SEAL WATER RETTJRN LINE It.7 28 035 1 0600200-08606.

-07, -13 RACEWAY 702' 350 2.74 RMI 1.25 SS STO N/A 6" 00 INSULATION K SEAL WATER RETURN LINE 11ra729 05S 1 0600200-06-OR, .07, -13 RACEWAy 702' 1.06 6.87 RMI 1947 SS STO N/A 4"OD INSULATION K SEAL WATER RETURN LINE I1em 30 0.11 1 0600200-06-OR.

-074 -13 RACEWAY 702' 1 06 1.37 MIN-K 1.47 S.S. STD N/A 4" OD M/N-K INSULATION K SEAL WATER RETURN LINE It.0 31 040 1 1000200086-06.

07, -13 RACEWAY 702' 106 0.92 RMI 397 S.S STD N/A 9 OD INSULATION K SEAL WATER RETURN LINE It.7 32 0.29 1 0600200-06-06.

-07. -13 RACEWAY 702' 0.36 2.76 RMI 1.31 OS. STO WA 5" OD INSULATION K SEAL WATER RETURN LINE It.. 33 0.11 1 0600200-08-06.

-07. -13 RACEWAY 702' 236 065 RMI 181 S.S STD WA 6OD INSULATION K SEAL WATER RETURN LINE item 34 0.55 1 0600200 086-08. 07, -13 RACEWAY 702' 2.36 234 RMI 2.31 S.S, STD N/A 7*OD INSULATION K STEAM GENERATOR 13LOWDOWN Item 35 49.57 1 0600200-07.02 RACEWAY 702' 4.50 14959 RMI 2.25 SS STD N/A 9" OD INSULATION L STEAM GENERATOR STEAM GEerO 38 0.61 1 0600200-07-02 RACEWAY 702' 4.50 2.57 RNIV 1.75 SS. STD N/A 8" OD INSULATION BLOWDOWN STEAM GENERATOR BLOSGDOWN Item 37 027 1 0600200-07-02 RACEWAY 702' ,600 1.52 " MINK

• 1.375 SS. STO NIA 7.25" 00 INSULATION STEAM GENERATOR SLOWDOWN 1107736 0.36 1 0600208-07-02 RACEWAy 702' 2.3U 1.54 RMI 3.31 0.5. STO N/A 7" 00 INSULATION STEAM GENERATOR BLOWDOWN Item139 0.55 6 0600200-07-02 RACEWAy 702' 2.36 1.72 R.I 2.61 S.S4 STD N/A 6" OO INSULATION STEAM GENERATOR 1140 58.98 1 0600200-07-03 RACEWAY 702' 4.50 17800 RMI 2.25 S'S STD N/A 9" OD INSULATION M BLOWDOW'N I STEAM GENERATOR SLOWDOWN It.0 41 0.30 1 0600200-07-03 RACEWAY 702' 4.50 1.27 RMI 1.75 S.S. STD WA 8" OD INSULATION N STEAM GENERATOR SLOWADOWN 07Itm42 039 1 0600200-07.03 RACEWAY 702' 4.50 2.48 RMI 1.25 S4& STD N/A 7" OD INSULATION STEAM GENERATOR

-323 7 I SLOWDOWN Item743 0.35 1 0600200-07-03 RACEWAY 702' 238 1248 RMI 331 SS. TD N/A 70 INSULATION STEAM GENERATOR OItm44 0.32 1 0600200-07-03 RACEWAY 702' 236 2.0 RMI 311 S.S, ST7 )A 7 OD INSULATION M SILOWDOWN

-STEAM GENERATOR SLOWDOWN Item745 0.38 10. 0800200-07-03 RACEWAY 702 1 8.62 073 RMI 2A9 S-S.STD INA 13" OD INSULATION (FLANGE)M LABELS. SIGNS. &PENETRATION NO It.. 52 0.00 1 2 N/A LOOPS 702' " N/A N/A N/A N/A N/A N/A /WA SEE REPORT FOR COMMENTS D ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-3 of 1-12 I DESCRIPTION L Linet J INSUL.VOLUME INSULATION JACKET STRAP.I 31 AREA PROBLEM NUMBER LOCATION ELEV. OD (IN) LENGTH (FT) I INSUL TYPE I INSUNI I TYPE PACKET LETTER Numbe, ITT3)I THICKNESS (IN) MATERIAL TYPE CMET MIN K TO WASTE DISP LINE Ite68 1 0.08 5 N/A LOOP 4 7024 4.50 WRAP AROUND 4' PIPE Dobl, banded par 1. TVA calulatJi MD00010632007115 Rev. 0 Volume changed per TVA cac/lnation MDQOOIO632007115 Ry. 0 2.00 1 MI-K I SEE CALC I NA NIA N4A D INSULATION 235 0,1U75 N/A WA I /A SEE CALCULATION D CONDUIT 3M-M20C It/089 1 43 6 N/A LOOP 1 716' 1 90 N/A 3M-M20C 0.1875 N/A WA WA SEE CALCULATION D INSULATION CONDUIT 3M-M20C item 90 1.70 6 N/A LOOP 1 716' 238 N/A 3M.M20C 0.1875 N/A NWA NIA SEE CALCULATION D INSULATION CONDUIT 3M-M20C Iu-9 01 0.52 6 N/A LOOP 1 716' N/A N/A 3MIM20C WNA NIA WA NA JUNCTION BOXES SEE CALCULATION D INSULATION CONDUIT 3M M2OC Item 02 2.31 U N/A LOOP 1 758' N/A N/A 3M.M200 1A N/A WA WA SUPPORT SEE CALCULATION INSULATION LABELS, TAGS, AND TIE Item 93 N/A 6 N/A LOOP 1 710-720 N/A N/A N/A NIA N/A NWA NIA SEE REPORT FOR COMMENTS E WRAPS 4" PRESSURIZER SPRAY LINE Item 94 18.88 6 0500200-13-02 LOOP 1 7168 4.50 4340 RMI 2.75 SS STO N/A 10OD INSULATION F 4* PRESSURIZER SPRAYLINE Item 95 0.10 6 0600200-13-02 LOOP 1 716' 4.50 121 RMI 0.75 SS STO N/A 6" OD iNSULATION F 75" OD INSULATION 4" PRESSURIZER SPRAY LINE It/. /o 0.13 6 0600200-13-02 LOOP 1 718, 4.50 0.67 MIN-K 1.5 SS. STO WA Double banded par 1. TVA calUatio MD0OO1I632007115 Roe 0 4" PRESSURIZER SPRAY LINE Item 97 2.51 6 0600200-13 02 LOOP 1 716' 4.50 1.21 RMI 7.75 S'S' STD NA 20' OD INSULATION F 3/4' PRESSURIZER SPRAY Item 98 135 6 0600200-13-02 LOOP 1 716' 1 05 517 RMI 2.975 S.S. STD NWA 7"OD INSULATION F BYPASS LINE 3/4' PRESSURIZER SPRAY Item 9/ 0.35 6 0600200-13-02 LOOP 1 715' 1.05 434 RMI 1.470 B.B. STO 4" OD INSULATION F BYPASS LINE 3/4W PRESSURIZER SPRAY Item 100 0.18 6 0800200-13-02 LOOP 1 718' 1.05 0.50 RMI 335 SS STO NWA 7.5 OR INSULATION F BYPASS LINE HOT LEG Item 101 69.55 6 NIA LOOP 1 716' SEE CALC SEE CALC RMI SEE CALC SS STT N/A NIA G COLD LEG Item 102 55.34 6 N/A LOOP 1 716' SEE CALC SEE CALC RMI SEE CALC 0S STE N/A WA H BORON INJECTION Item 103 1.40 6 0600200-095 LOOP 1 716' 1.90 565 RMI 2.55 S0 STT N/A 7' 00 INSULATION BORON INJECTION Item 104 1.51 B 0600200-09-05 LOOP 1 716' 1.90 096 RMI 7.6 S.S. STT N/A 85" OD INSULATION ACCUMULATOR INJECTION Item 105 0.47 6 0600200.09-01 LOOP 1 716' 1075 2.36 RMI -0.795 0S STD WA 1234' OD INSULATION K ACCUMULATOR INJECTION Ioem 106 1553 6 0600200-09-01 LOOP1 716' 10.75 1542 RMI 3.125 &S. STD ONA 17'OD INSULATION K 1325' OD INSULATION ACCUMULATOR INJECT7ON It.. 107 0.13 6 060200-09-01 LOOP1 716' 10.75 2.65 MINK 1.25 B.S0 STD NA Volumea hanged per TVA caIctimon K MDTO010632007115 Reo. 0 ACCUMULATOR INJECTION I/tem 108 21 U1 6 0600200-09-01 LOOP 1 716' 1075 509 RMI 9.635 S.S STD N/A 30" 00 INSULATION

-K ACCUMULATOR INJECTION Item 109 129 6 0600200-09-01 LOOP 1 716' 10.75 057 RMI 6,12R S0S STT WA 23 DOD INSULATION K LOWHEAD SAFETY INJECTION Ion, 110 4.34 8 0 .00200-09.1 LOOP 1 716' U..3 714 R.I 2.875 S.s STO WA 12' OD INSULATION L RESIDUAL HEAT REMOVAL Iem 111 2.90 6 N/A LOOP 1 716' 6.63 3.50 RM? 38875 SS STT WA 14" OD INSULATION M RESIDUAL HEAT REMOVAL Item 112 0.23 6 NIA LOOP 1 716' 6.83 2.09 RM. 0.8875 SS STD N/A 8" O INSULATION M RESIDUAL HEAT REMOVAL Item 113 7.48 6 N/A LOOP 1 716' 6.63 2.17 RMI 98675 SS STD NWA 26" OD INSULATION M RESIDUAL HEAT REMOVAL Item 114 102.56 6 N/A LOOP 1 716' 8.63 2650 RMI 98875 SS STT NVA 11 OD iNSULATION M 105' OT INSULATION RESIDUAL HEAT REMOVAL Item 115 0.08 B NIA LOOP 1 716' 8.83 1.10 MINK 09375 S0S. OTD WA Volume changed per TVA calculation M MDCO010632007115 Rev. 0 NORMAL CHARGING 11-tm118 20.44 6 0600200-08-11 LOOP I 716' 3.50 54.50 RMI 2.75 S.S. OST WA 5' 00 INSULATION N

ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-4 of 1-12 DESCRIPTION Lin. Itam INSUL. VOLUME INSULATION JACKEO STRAP Number AREA PROBLEM NUMBER LOCATION ELEV. 00 (1N) LENGTH (FT) INSULV TYPE THICKNESS

ýIN MATERIAL BUCKLE TYPE TYPE COMMENTS PACKET LETTER NORMAL CHARGING Item 117 0.15 6 0600200-08611 LOOP 1 716' 3.50 089 RMI 15 S.S STO KIA 6.5' OD INSULATION N NORMAL CHARGING Item 118 0.80 6 0600200-06-11 LOOP 1 716' 3.50 2,50 RMI 2 S.S, STO N/A 75' 0(3 INSULATION N$TEAM GENERA7ORS STEAK/G NEItem 119 11.76 6 0600200-07-01 LOOP I 716' 350 41.67 RMI 225 SS STD N/A S" OD INSULATION P BLOWDOWN STEAM GENERATOR 111120 953 6 0600200.07-01 LOOPI 766' 4.50 301 6KI 225 SS' STD N/A 9 00 INSULATION P BL OWDOWN51 STEAM GENERATOR SLOWDOWN Item 126 0.26 6 0600200-07-01 LOOPI 716' 4.50 05 RMI 0.75 S.S STO N/A S" OD INSULATION P STEAM GENERATO tam 122 020 6 0600200-07-01 LOOP1 716 1.3 059 RMI 3.325 SS STD N/A 8GOO INSULATION P BLOWDOWN STEAM GENERATOR n SS STD N/A 6-GO INSULATION P STEAM G N Item 124 064 6 0600200-07-01 LOOP 1 716' 3 31 015 RMI 28345O NSULATION SLOWDOWN Item 125 0.36 6 0600200-07-01 LOOP1 716' 6.30 1.13 RK/3 S.S. STD NIA GE INSULATION P STEAM GENERATOR SLOWDOWN Ie 2 ,8 6 00200-18 DiSLTO STEAM G N Item 128 0.06 6 0600200-07-01 LOOP 1 716' 2.91 0.29 RMI 2045 S.S, STD N/A 7'O INSULATION P BLOWDOWII MINK Item 127 0.964 6 N/A LOOP I 716' N/A N/A MIN-K 336 N/A N/A NIA Doble banded par 1. TVA calclation MDKO010632007115 Rev. 0 3" ALTERNATE CHARGING Itom 128 16,53 6 060120010-111 LOOP 1 716' 3.50 44.09 RMI 2.75 SS9 STD N/A 9" OD INSULATION R 6" OD INSULATION 30ALTERNATE C-AG/NO Ite, 126 08 6 0600200-0-11 LOOP 1 716' 3.50 1.83 MIN-K 1.25 S.S STD N/A Volume hanged par TVA elcuatfon R MDO0010632007115 Rev. 0 STEAM GENERATOR It.. 130 21560 7 N/A LOOP2 710' SEE CALC SEE CALC RMI SEE CALC S.& STD N/A WNA A STEAM GENERATOR item 131 0.67 7 N/A LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC S.S STD N/A AT ROOT VALVES A CONDUIT 3M-M20C INSULATION it.. 132 2.19 7 N/A LOOP2 716' 1.90 5000 3M K20C 0.1675 N/A NA NA SEE CALCULATION B CONDUIT 3M-M20C INSULTION OIntem 133 3.65 7 N/A LOOP2 716' 2.38 7000 3M-M2OC 0,1875 N/A N/A N/A SEE CALCULATION a NUIINSULATION CONDUIT 3M-M2IO It.. 134 1.79 7 N/A LOOP2 716' N/A NIA 3M-M2C N/A N/A N/A N/A SUPPORT INSULATION SEE B INSULATION CALCULATION PRESSURIZER SURGE LINE Item 135 62.48 7 0600200-13,01 LOOP 2 716' 14.00 3440 RMI 4.5 S.S STO N/A 23 O INSULATIONS C PRESSURIZER SURGE LINE It.. 136 1.21 7 0600200-13-01 LOOP2 716' 1400 7.67 RMI 05 S0S. STD N/A 15 00 INSULATIONS C PRESSURIZER SURGE LINE item 137 1.09 7 0600200-13,01 LOOP 2 716' 1400 334 RMI 1 SS ST1 N/A 16' OD INSULATIONS C PRESSURIZER SURGE LINE It.. 138 2.71 7 0600200-13,01 LOOP 2 716' 1400 301 RMI 25 SS. STO NfA 19 OD INSULATIONS C PRESSURIZER SURGE LINE Item 139 4.40 7 0800200-13,01 LOOP 2 716' 14.00 867 RMI 1.5 S0S ST1 N/A 17OD INSULATIONS C FEEDWATER It.. 140 1867 7 0600200-02-02 LOOP2 716' 1400 18.50 RMI 2.5 SS STD N/A 21'OD INSULATION D FEEOWATER Ioem 141 0.63 7 0600200-02-02 LOOP 2 716' 16.00 080 RMI 2 S0 STO N/A 206 O INSULAT7ON 0 18" O INSULATION Doubt banded per 1. 'TA Iawlation FEEDWATER Item 142 0.58 7 0600200-02-02 LOOP2 716' 16.00 1.56 KINK I S. STO WA MD00010532007115 Rev 0 0 VoIlmo changed per TVA ctnilation MDQ0010632007115Rev.

S FEEDWATER Item 143 1.95 7 0600200.02-02 LOOP2 716' 1600 1064 RMI 0.5 S.S STD NIA 17" OD INSULATION D FEEDWATER Item 144 0.42 7 0600200.02-02 LOOP2 716' SEE CALC SEE CALC RMI SEE CALC S.S STD N/A AT 1.88' OD LINE D FEEDWATER Item 145 0.27 7 0600200.02-02 LOOP 2 716' SEE CALC SEE CALC RMKI SEE CALC S.S ST7 N/A AT 1" LINE D FEEDWATER lenm 146 0.70 7 0600200-02-02 LOOP2 716' 30.25 050 MINERAL WOOL 2 NIA STO NKA AT PENETRATION A X-12B 0 4"PRESSURIZER SPRAY LINE Item 147 14.21 7 0600200-13,02 LOOP2 716' 4.50 3267 RMI 275 S.S ST7D NA 10' OD INSULAT 1 ON E 4 PRESSURIZER SPRAY LINE I0tm 148 2.51 7 0600200-13.32 LOOP 2 716' 4.50 121 RKI 7.75 SS. STD K/A 206 O INSULATION E 3/4 PRESSURIZER SPRAY BYPASS LINE Item 149 0.11 7 0600200-13-02 LOOP2 716' 1.05 042 RMI 2.975 S0S. STD NIA 7"OD INSULATION E 3/4" PRESSUR/ZER SPRAY BYPASS LINE item 150 0.68 7 0600200-13.02 LOOP 2 716' 1.05 842 RMI 1475 S.S STD N/A 4 OD INSULATION E HOT LEG Item 151 74.60 7 N/A LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC SS STE N/A N/A F HOT LEG Item 152 6 IS 7 N/A LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC SS STD NIA AT 6K SAFETY INJECTION F COLD LEG Itnm 153 5542 7 N/A LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC SrS. STD N/A N/A G BORON INJECT/ON Iten 154 0686 7 0600200 09-06 LOOP2 716' 1.90 3994 RMI 2.55 SrS STD N/A 7"OD INSULATION H BORON NJECTION Iten 155 1 70 7 0600200.09-06 LOOP2 716' 1.90 1.08 RMI 76 S.S STD N/A 9.5" 00 INSULATION H ACCUMULATOR INJECTION Item 156 16.79 7 0600200-09-02 LOOP 2 716' 1075 17.75 RMI 3.125 S.S. STD N/A 17" O INSULATION J ACCUMULATOR INJECTION Itnm 157 21.31 7 0600200-09-52 LOOP2 716' 1071 4.98 RMI 9.625 S.S. STD NIA 30"OD INSULATION J ACCUMULATOR INJECTION Inn, 158 0.65 7 0600200309-02 LOOP2 716' 10.75 09.6 RMI 0.625 S4S, STD N/A 12' 00 INSULATION J ACCUMULATOR INJECTION It.n 159 0.54 7 0600200-09.02 LOOP2 716' 10.75 1.24 RMI 1.625 S.S, STE N/A 14"OD INSULATION J LOWHEAD SAFETY INJECT1ON Ion, 160 532 7 0600200.05.02 LOOP 2 716' 6.63 9.75 RMI 2.6675 SS STD N/A 12" O INSULATION K RESIDUAL HEAT REMOVAL Ion, 161 7.94 7 N/A LOOP2 716' 863 31.25 RM, 1.1875 SS STD N/A i"OD INSULATION RESIDUAL HEAT REMOVAL 1 Ite-1.2 1 ý12 1 7 N/A LOOP 2 716' 1 ý.63 1 2.74 1 WN-K I .,- [ -I rT.9.765 OD MIN-K INSULATION N/A Vmonue -hanged por TVA calnajen MDO0010632007115 Ro-. 0 L ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-5 of 1-12 DESCRIPTION Line Item INSUL VOLUME INSULATION JACKET STRAP M Num, F3) AREA PROBLEM NUMBER LOCATION ELEV. 0O (IN) LENGTH (FT) INSUL TYPE THICKNESS (IN) MATERIAL TYPE COMMENTS PACKET LETTER N6 O D INSULATIO N EXCESS LETDOWN Itse 188 0.72 7 .6 00200-2 0 -12 LOOP 2 71.' 132 387 MIN-K 2.34 SS STO A Double banded per 1. TVA ceasaflon N MDQO010632007l118Rev 0 EXCESS LETDOWN Ite. 169 0.86 7 0600200008-12 LOOP 2 716' 132 6.75 RMI 1.84 SS. STD WA 5 00 INSULATION N EXCESS LETDOWN item 170 0.02 7 0600200-08-12 LOOP 2 716' 1 32 059 RMI 0384 SS. STD NIA 3 OD INSULATION N BLOWDOWN Item 171 9.95 7 0600200-07-02 LOOP 2 716' 350 3525 RMI 225 SS ST7D NA 8 OD INSULATION P STEAM GENERATOR temn 172 9.47 7 0600200-07-02 LOOP2 716' 450 28.59 RMI 225 S.S STD NWA 9 O0 INSULATION P SLOWDOWN STEAM GENENATOR Item 173 0.55 7 0600200-07-02 LOOP2 716' 450 3.50 RMI 1725 S.S. S-D -A 7 D0 INSULATION P SLOWDOWN BLOWDOWN Item 174 0.43 7 0500200-07-02 LOOP2 716' 1.31 1.67 RMN 2.845 S.S. STD N/A 700 INSULATION P STEAM GENERATOR Item 175 0.14 7 C.02.0-O7-02 LOOP2 716' 1.31 0.73 RMl 2.345 S.S STD NIA 600 INSULATION P STEAM GENERATOR STEAM GENERATOR Item 176 020 7 0600200-07-02 LOOP2 716' 1.31 059 RMI 3.345 SS' STO WA U OD INSULATION P BLOWDOWN STEAM GENERATOR Item 177 008 7 0600200.07 02 LOOP2 716' 2.88 0.28 RMI 2,06 SS. STO NWA 7' OD INSULATION P BLOWDOWN CONDUIT INSULATION 3M Ite. 178 1.51 7 NSA LOOP2 720-737 132 45.00 3M20C SEE CALC NIA WA NWA SEE CALCULATION a SUPPORT Iten 179 0.77 7 NSA LOOP2 720-737 N/A N/A NIA SEE CALC NIA WA NWA SEE CALCULATION 0 LETDOWN LINE Item 180 1.586 7 0600200-08-10 LOOP2 716' 350 217 RMI 4.25 SS STD NWA 120D INSULATION R LETDOWN LINE item 181 22.73 7 0600200 08-10 LOOP2 7165 350 47.50 RMI 325 SS STD NWA 10* O INSULATION R LETDOWN LINE Item 182 1.21 7 0600200 08-10 LOOP2 716' 350 429 RMI 225 S.S -STD WA 8"OD INSULATION R LETDOWN LINE Item 183 0.1 7 0600200 08-10 LOOP2 716' 350 3009 RMI 1.5 SS STD N/A 6.5" 00 INSULATION R AT MIN-K INSULATION L E T D O W N L IN E ten , 18 4 0 .04 7 0 6 0 02 0 0 10 L O O P 2 7 167 3 5 0 0 5 9 M IN -K 0 .7 5 S S S T D W A D ubla b a n d e d p e r I. T V A c ates oie n R MD00010632007115 Roe. 0 3 ALTERNATE CHAG INO Iten 185 9.41 7 0600200-08-11 LOOP? 716' 350 2509 RMI 275 S.S. STD NSA 9"OD INSULATION S Y ALTERNATE CHARGING Item 186 005 7 0600200 -08w 1 LOOP2 716' 3503 25 RMI 0.5 S.S STD N/A 4.5"0 INSULATION S 3 ALTERNATE CHARGING item 187 0.21 7 0600200-08-11 LOOP2 716! 3.53 334 RMI 0.75 S.S. STD WA 53 O0 INSULATION S STEAM GENERATOR i tet 188 215.60 8 NSA LOOP 3 716 .SEE CALC SEE CALC AMI SEE CALC S.S. STO WA NIA A STEAM GENERATOR Item 189 0.62 8 NSA LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC S.S. STD WA AT ROOT VALVES A FEEDWATER Item 190 19.60 8 0 800200.32-03 LOOP 3 716' 1600 1942 R MI 2.5 S.S STO NWA 21- OD INSULATION 1 FEEDWATER Item 191 0.86 8 OUO 8200 -02 03 LOOP 3 716' 1800 1.09 RM8 2 S'S' STO WA I9" OD INSULATION B FEEDWATER Item 192 1.14 8 0830203.02.03 LOOP 3 716' 18.70 34 RMt 0.5 SS9 ST1 WA 17" OD INSULATION B FEEDWATER Item 193 0335 8 -0800200.32.03 LOOP 3 716' SEE CALC SEE CALC RM) SEE CALC SS9 STD NWA AT 1 86" OD LINE B FEEDWATER Item 194 024 8 0860230.02.03 LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC SS STD WA AT 1" LINE B FEEDWATER Item 195 0.70 8 0600203-02-03 LOOP 3 718' 30.25 050 MINERAL WOOL 2 NSA STD WA ATPENETRATION#X.12C B LETDOWN LINE Item 186 1843 8 0600200-08 10 LOOP 3 716' 350 38.50 RMI 325 SS STD N/A 10" 00 INSULATION C HOT LEG Item 197 4989 8 N/A LOOP 3 718' SEE CALC SEE CALC RMI SEE CALC SS STD WA NWA D COLD LEG Item 108 54.69 8 N/A LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC SrS. STD NWA NWA E BORON INJECTION Item 199 1.29 8 0600200.0890 LOOP 3 716' 190 520 RMI 255 SS STD W ,A 7"OD INSULATION F BORON INJECTION Ien, 200 7.57 8 0600200.09-06 LOOP 3 716' 1.00 096 RMI 7.6 S.S STD N/A 9.5"O(3 INSULATION F ACCUMULATOR INJECTION Iten 201 16.32 8 0600200.09.02 LOOP 3 716' 1075 17.25 RMI 3.125 S.S. STD NWA 17" 00 INSULATION 0 ACCUMULATOR INJECTION Ite. 202 22.16 8 0600200 02 LOOP3 716' 103.75 518 RMI 9625 S.S STD NWA 30 O00 INSULATION G ACCUMULATOR INJECTION ten, 203 0.17 K 0800200.09-0?

LOOP 3 778' 1075 107 N I 0820 S.S STD NSA 1?" 00 INSULATION 0 ACCUMULATOR INJECTION Item 204 0.77 6 060020090).02 LOOP 3 7167 10.75 182 RMI 0375 S.S STD NWA 12" O0 INSULATION G LOWHEAD SF0ETY INJECTION Item 205 1.38 8 0600200-09-02 LOOP 3 716' 863 2.53 RMI 2.8875 S.S. STD A 1 2"OD INSULATION N LOWHEAD SAFETY INJECTION Item 208 047 8 0600200-09-02 LOOP 3 716' 683 428 RMI 0.0875 S.S STD NWA 0" 00 INSULATION H RESIDUALNHEAT RE MOVAL Item20 7 1. 05 N NSA LOOP 716 " 8.83 80 RMI 1.875 , STO WA 1" OD INSULATION H RESIDUAL HEAT REMOVAL Item 208 748 B NSA LOOP 3 716' 6.63 2.17 RMI 9.6875 -S. STD WIA 26" OD INSULATION (VALVE) J RESIDUAL HEAT REMOVAL Item 209 0.41 8 NSA LOOP 3 716' 663 3.75 RMI 0.8875 S.S STO WA B OD INSULATION J RESIDUAL HEAT REMOVAL Item 210 2.22 8 NSA LOOP 3 716 " 8.63 267 RMI 3.6875 SiS STD WIA 14'OD INSULATION J EXCESS LETDOWN Item 211 800 a 0630200-081.2 LOOP 3 716' 1.32 42.84 RMI 2.34 S'S. STD NWA 6OD INSULATION K EXCESS LETDOWN Item 212 016 8 0600200308-12 LOOP 3 716 1.32 063 RMI 2.84 SS, STO N/A 7" OD INSULATION (VALVE) K EXCESS LETDOWN Item 213 07n 8 0600200-081.2 LOOP 3 71M 1.32 617 R81 1.84 S.S' STD WA 5'OD INSULATION K EXCESS LETDOWN Item 214 010 8 0600200-09.12 LOOP 3 716 ' 1.05 078 RMI 1.975 SS. STO WA 5'OD INSULATION K EXCESS LETDOWN Iten 215 009 8 0600200-09.12 LOOP 3 716T 1.05 046 RMi 2.475 SS. STD NWA 6 OD INSULATION (VALVE) K STEAM GENERATOR Ien 216 12.68 8 0600200-07-03 LOOP3 716' 3.50 44.92 RMI 2.25 S.S STD WVA 8" OD INSULATION L BLOWDOWN STEAM GENERA ie217 7.10 8 0600200-07-03 LOOP3 716' 4.53 2142 RMI 225 S.S STD WA 900D INSLLAT7ON BLOWDOWN Item___ 2___7_ 7.10_____

_ 3___ _______________225 STEAMA GENERATOR tml .0 a 00200w3LO3 76 wO 31 M ,5S T I "DISLTO BLOWDOWN BLOWDOWN item 218 0.50 8 0600200.07-03 LOOP 3 716' 6.50 3.77 RMI 1.25 S.S STD NWA 7" OD INSULAT7ON STEAM GENERATOR Item 210 0.45 8 0600200-07-03 LOOP 3 716' 1.31 1.75 R MI 2.845 S.S STO NIA 7O0 INSULATION STEAM GENERATOR Ien, 200 0.14 S 0600200-07-03 LOOP 3 718' 6.37 075 RNMI 2,345 -S.S STO W/A 6" OD INSULATION BLOWHDOWN STEAM GENERATOR len,221 038 8 0600200-07-03 LOOP 3 716' 1.31 1.11 R81 3.345 SS. STD WA 8 OD INSULATION SEAM GENERATOR Itm 222 00. 8 "0020O-03 LOOP 3 716' 2.8 028 RMI 2.06 SS STD W/A 7- OD INSULATION L SBLOWDOWN SLOWDOWN ln,22 08 8 00003-3LO3 71' 28 0288120SSSTWA100ISAIN ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-6 of 1-12 DESCRI.PTION LiI ..... IINSUIL. VOLUMEI O(N E.. F) IS .. INSULATO ... AKT UCL YI STRAYOM..

A.. TE Number F'r3 AREA PROBLEM NUMBER LOCATION ELEV. O(I) LNT(F)THICKNESS (IN) MATERIAL BUKEYPE OMET STEAM GENERATOR Item 223 21560 9 NIA LOOP 4 716' SEE CALC SEE CALC RMI SEE CALC S S STO WVA A AUSTEAM GENERATOR Item 224 0.58 9 N/A LOOP4 716' SEE CALC SEE CALC RMI SEECALC SS STD N/A AT ROOT VALVES A A MFEEDWATER N tem 225 20.25 9 0800200-02 04 LOOP4 716' 1600 2007 RMI 245 S.S STD N/A 21"0 O INSULATION FEEDWATER item 220 122 9 0600200-02-04 LOOP4 718 16000 678 RMI 05 S.S STD N/A 17' OD INSULATION 0 FEEDWATER item 227 0.35 9 0600200-02-04 LOOP 4 716, SEE CALC SEE CALC RMI SEE CALC SS' STD NIA AT I 88" OO LINE FEEDWATER item 226 0.14 9 0600200-02-D4 LOOP 4 718' SEE CALC SEE CALC RMI SEE OALC S'S' STD NIbA AT I -LINE B FEEDWATER Item 229 0N70 9 0 N00200-02-D4 LOOP4 7127 3025 0.50 MINERAL WOOL 2 N/A STD N/A ATEENRERTRATION#

12D B HT0 LEG Item 23O 72A51 9 N/A LOOP 4 712' SEE CALC SEE CALC RMI SEE CALC SS. ST N/A N/A COLD LEG Item 231 54486 9 N/A LOOP 4 716W SEE CALC SEE CALO RMII SEE CALC S.S. STD NIA N/A O)BORON INJECTDON Item 232 1910 9 0600200.07-05 LOOP 4 716' 1 90 4345 RMI 2.55 S.S. STD WA 7- O INSULATION E BORON INJECTION Item 233 1.42 9 0600200-09-05 LOOP 4 710' 1490 0390 RMI 726 SS STD N/A 95' 00 INSULATION 1 ACCUMULA70R INJECRTON I/- 234 24.03 9 0600200-09401 LOOP4 710' 1075 2625 RMI 3.125 S0S. STD N/A 17" 0 INSULATION F ACCUMULA70R INJEC71ON Itarm 235 2319 9 0600200-09-01 LOOP 4 716' 10675 5942 RMI 0.625 S.S9 STD N/A 30" OO INSULATION

_ P LOWHEAD SAFEM Y INJECTION It/m236 143 9 0600200-09401 LOOP4 716' 6.63 7.04 RMI 1 1875 S.S STD N/A 9 OO INSULATION G LABELS AND TIE WRAPS- Iterm 237 N/A 9 NIA LOOP4 720.737 NIA NIA NIA PUA NIA NA N/A SEE REPORT FOR COMMENTS H RVD SEALANT It. 238 N/A 9 NIA LOOP4 720-737 NIA NIA NIA TA N/A N/A NIA NIA J STEANM GENERATOR STEAM GENERATOR Item 234 9095 9 0600200-07-04 LOOP4 716' 3250 3525 RMI 2325 S. STO NIA 9"OD INSULATION K SLOWDOWN STEAM GENERATOR Item 240 12021 9 0600200-07-04 LOOP4 716' 4.50 3614 RMI 225 S S STO N/A 9"OD INSULATION K BLOWDOWN STEAM GENERATOR EtRN 241 205 9 0600200-04-11 LOOP4 716' 3.50 6.79 RMI 2. S.S. STD N/A 9' OD INSULATIONK SLOWDOWN Itm21 01 9 06004.0 07 M12SD NI 'DISLTO STEAM GENERATOR item 242 042 9 0600200-07-04 LOOP 4 716' 1.32 L63 RMI 2.24 SS0 STO N/A 7" OD INSULATION K SLOWDOWN STEAM GENERATOR Item 243 0.14 9 0600200-07-04 LOOP4 716' 1.32 0.75 RMI 2.34 SS. STD N/A 7 " 00 INSULATION K SLOWDOWN STEAM GENERATOR Item 24 0.20 1 0600200-07-04 LOOP4 716' 1932 0.59 RMI 3.34 S.S. STD N/A 8"OD INSULA71ON K SLOWDOWN STEAM GENERATOR Item 245 0.10 9 0600;200-07-03 LOOP 4 716S 2.1B 034 RMI 2.56 SS STD NIA IN OD INSULATION K BLOWDOWN_-T3 ALTERNATE CHARGING Item 246 24.65 9 06D0200.08-11 LOOP4 716' 350 65.75 RMI 2.75 S.S9 STD N/A 9" OO INSULATION L_3' Al TERNATE CHARGING Itera 247 0.66 9 0600;200.08,11 LOOP 4 716" 3950 2.34 RMI 2.25 SqS STO NIA IF DO INSULATION L 3T ALTERNATE CHARGING Item 248 4.39 g 0600200-08-11 LOOP 4 716' 350 2991 RMI 675 S9S STD NIA 17' OD INSULATION AT VALVES L MAIN STEAM item 249 171.24 10 0600;200.06-01 LOOP t 745' 3200 63.17 RMI 35 SS9 SD -NIA NIA A NEAR PENETRATION MAIN STEAM 1I0-1250 1766 10 0600200-06-01 LOOPS 745' 32.00 355 MIN-K 0 50 N/A N/A Touel ragouge bryng DOs nP- 21.. A DCN 51755 NEAR TOP OF SG MAN/STEAM Item 251 3.10 50 0600200-06-01 LOOP 1 745' 32.00 2.63 Traaso RMI 1.5 SS N/A N/A RepAlod wkh T7-n oRM/ par DCN A 51755 MAIN STEAM Item 252 149 10 0600200-06-01 LOOP1 745' SEE CALC SEE CALC RMI SEE CALC SS STD N/A AT 1 VENT LINE A MAIN STEAM It.. 253 0.34 10 0600200-06-01 LOOP 1 745' SEE CALC SEE CALC RMI SEE CALC S.S STD N/A AT I* INSTRUMENT TEST LINE A-MAIN STEAM Item 254 1.34 10 0600200-06901 LOOP 1 745' SEE CALC SEE CALC RMI SEE CALC S.S STD K/A AT 3/4" INSTRUMENT TEST LINES A STEAM GENERATOR Item 255 451.03 10 N/A LOOP 1 745' SEE CALC SEE CALC RMI SEE CALC S.S STU N/A N/A B AUX ILIARY FEEDWATER item 256 4.24 10 0600200-02-05 LOOP ! 745' 6.63 3.17 RMI 5 1875 S.S. STOD WA 17'00 INSULATION C AU)SILIARY FEEDWATER Item 257 32.21 10 0600200-02-05 LOOP 1 745' 6.63 59.00 RMI 2.6875 U.S STU N/A 12'OO INSULATION C 12.25" O INSULATION Vok0m0 changed p6r TVA Latin, W-6061.AUSLILIARY FEEDWATER Item 258 064 50 0600200-02-05 LOOPI 745' 063 301 MIN-K 22125 S0S STD N/A *Subjec: WatS Bar Nuclear Plant LWBN)-Plant Data Request -Suspplemnfnt' Doublb banded par 1. TVA calcwlatian MDO0010632007115 R-. 0 RMI constiuent added pr /TVA Leoter W-8076 dated Dec. 10, 2007. '

Subject:

Wtts Bar Nacloar Plant (WBN) -Plarn AUALILIARY FEEDWATER It.. 258 1.10 10 0600200-02-05 LOOPS 745' 6.63 3,01 RMI 2.8125 S. STU N/A Data Re0est" Afttn6on:

Kdch M. Rajan C Volume changed Per TVA Letter W-8011.'

Subject:

Wads Bar Nuclear Plant (WSN)-Plant Data Requost -Supplement' AUXLILIARY FEEDWATER It. 259 044 10 0600200-02-05 LOOPS 745' 663 1.43 RMI 1 6875 S.S9 STD N/A 10' OD INSULATION C AUXLILIARY FEEDWATER Item 260 0.31 10 0600200.02-05 LOOPS 745' 1.31 1.20 RM. 2645 S.S. STD WA AT 1.31" 00 LINE C SEAL AROUND HVAC Item 261 NIA 10 N/A LOOPI 745' NIA NIA NI A NIA N/A NIA VA O DIFFUSER CONDUIT INSULATION 3M 0am262 022 10 N/A LOOP1 745' 1.90 500 3M21C SEE CALC NIA IA N/A SEE CALCULATION E RADIANT JUNCTION BOX .t.0 263 020 10 N/A LOOPI 745' N/A N/A 3M20C SEE CALC N/A WA N/A SEE CALCULATION E SUPPORT item 264 026 10 N/A LOOPS 745' N/A N/A 3M20C SEE CALC N/A N/A N/A SEE CALCULATION F MAIN STEAM it.. 265 182.97 11 0600200-09-02 LOOP2 745' 32O00 67.50 RMI 3.5 SS. STD N/A N/A A NEAR TOP OF SG MAIN STEAM 1te0-267 3.01 11 0600200-02 LOOP2 745' 32.00 2.75 TransmsoRM 1.5 /A N/A Replacedwih TrannstRMI porOCA 51755 ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-7 of 1-12-1 LJoln BS~0UEARE4 PROBLE.11MDER I LOCATION IBFEE. I OD (IN) ILENGTH4 FET) I INSUL.TYPE INSULATION JACKET STRAPMATE/RhA I BUCKLE TYPE STRP j COMMENTS jPACKET LETTER AULILIARY FEEDWATER Iten 2-5 007 11t 0800200-05-02 MAIN STEAM IIt. 282 340 12 0100200-08-03 LOOP 2 LOOP 2 LOOP 2 LOOP2 LOOP 2 LOOP2 LOOP3 LOOP3 LOOP 3 LOOP 3 LOOP 3 LOOP 3 LOOP 3 LOOP 3 LOOP3 LOOP3 LOOP3 LOOP3 LOOP3 LOOP3 LOOP3 LOOP3 LOOP 4 LOOP 4 LOOP 4 745' 8 83 244 MIN-K 0.3771 Os SS as.SS.SS.S.S.SS.SS, STD 738" 00 INSULATION N/A Valume changed per TVA caldeaion MD00010632007115 Ra. 0 745' 3200 1 3.1 Trans-o RMI 1.5 NIA N/A Reqplead w=h Ttanso RMI per 0CN 51755 AT 1" VENT LINE AT " INSTRUMENT TEST LINE AT 3/4" tNSTRUMENT TEST LINES N/A/7" O0 INSULATION 14" O0 INSULATION 12" OD INSULATION

-10" OD INSULATION 8" O INSULATION 12" O INSULATION 10" OD INSULATION 8" OD INSULATION 16" OD INSULATION 8" OD INSULATION W/A N/A NEAR PENETRATION T. be ranonvered during Spring 2008 refueling outage by DCNs P-52187-A and DCN 51755 C E A A A A C C C C C 0 D 0 0 A B B MAIN STEAM Item 299 1 1746 13 0600200 06-04 745' 3200 3.51 1 MIN-K I I NIA N/A NEAR TOP OF SG MAIN STEAM Item 300 348 13 0600200-06-04 LOOP4 745' 32,00 3 17 Trans RMI 15 N/A Repoated kh Tmsnso RMI per DON B S1755 MAIN STEAM Itn- 301 145 13 0600200 06-04 LOOP4 745' SEE CALC SEE CALC RMI SEE CALC S.S STO N/A AT 1" VENT LINE 8 MAIN STEAM Item 302 035 13 0600200 08-04 LOOP4 745' SEE CALC SEE CALC RMI SEE CALC S.S STO N/A AT 1" INSTRUMENT TEST LINE B MAIN STEAM Item 303 1.13 13 0600200-06 04 LOOP4 745' SEE CALC SEE CALC RMI SEE CALC S.S STO N/A AT 3/4" INSTRUMENTTEST LINES 8 STEAM GENERATOR Iam 304 451.03 13 N/A LOOP 4 745' SEE CALC SEE CALC RMI SEE CALC S.S STO N/A N/A C AUXIILIARY FEEDWATER Ita. 305 4.47 13 0600200-02-08 LOOP4 745' 6.63 334 RMI 5.1875 S.& STD NfA 17" OD INSULATION D AUMIOLIARY FEEDWATER item 306 26.88 13 0600200-02-08 LOOP4 745' 6863 4920 RMI 2.6870 ,S'S STD N/A 12" OD INSULATION D 12.25" OD INSULATION Vnhmoe ohatged per TVA Leler W-8081.AUXLILIARY FEEDWATER Ite. 307 0.75 13 0600200-02-08 LOOP4 745' 683 3,01 MIN-K 2,8125 .ST, NIA Sbject: Weals Bar Nudear Plant (WEN) 0-Plant Date Request -Supplement" DoubA banded per 1 TVA n MDI0010632007115 Rev. 0 AUXILIARY FEEDWATER 0600200-02-08 Item 307 1 0.99 1 13 LOOP4 LOOP4 LOOP4 LOOP 4 LOOP4 745'745'745'745'745'6.63 1 301 1 RMI 1 2.8125 0.S STD N/A RMI onnsti..nt added per TVA Letter W-8078 dated D.e, 10. 2007, "

Subject:

Watts Bar Nucler Plant (WEN) -Plane Oats Roedest" Attentn, : Kish M. Rojan Voaume changed poeTVA Letter W 8081'Subjet: Waats Bar Nuclear Plant (7/SN)-Plant Dats Request -Supplement" D CONDLIT INSULATION SM I1,. 311 0.08 13 N/A RADIANT I 3 1.90 2.50 3M20C SEE CALC N/A N/A SEE CALCULATION ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-8 of 1-12 DiS~PIN Llna~e ISOUL VOLUME I HCNsINSULATION 8TERI JACKET STRAPTCMMNSYAKEPETE NRa.ba AREA( PROBLEM NUMBER LOCATION ELEV. 00 (IN) LENGTH (PT) INSUL TYPE IN )BUCKIEITYPE TYPENT S STEAM GENERATOR STEAMG NE 1 ?.3 4 0000200-07-3 P,6 ROOM 1 71,' 4.50 2202 RSH 225 SS. STD N/A 9'D0 INSULATION G STEAM GENERATOR Item 319 1 28 14 0F0A200-07-54 PN ROOM 1 716' 4,50 1.34 RMI 4.75 S'S. STD N/A 14" OD INSULATION (VALVE) G BLOWDOWN STEAM GENERATOR BLOWDOWN It1m 320 1.02 14 0600200-07-04 FAN ROOM 1 716' 11.75 1.59 RMI 2,125 S.S' STD NIA 16" 0O INSULATION (FLANGE) G STEAM GENERATOR Itm 321 1.26 14 0600200 07-04 FAN ROOM 1 716' 4.50 1.55 RMI 4.25 U.S STO N/A 13" 00 INSULATION (VALVE) G STEAM GENERATOR I item 3T2 BLOWDOWN I/a 322 0.81 14 0600200-07-04 FAN ROOM 1 716' 2.38 1.98 RMI 3131 S.S STO NA 9" 00 INSULATION (VALVE) G BLOWDOWN STEAM GENERATOR BLOWDOWN Itam 323 1.62 14 0600200-07-04 F06 ROOM 1 716' 2.38 040 RMI 12.5 S.S. STO N/A -7" 00 INSULATION G STEAM GENERATOR BLCWDOWN Itam 324 0.33 14 0600200.07-04 FAN ROOM 1 716' 8.62 0.64 RMI 2.19 S.S STD N/A 13" O INSULATION (FLANGE) G STEAM GENERATOR BLOWDOWN Item 325 056 14 S.0-0.2007-04 FAN ROOM 1 718' 4.50 2.5 MIN-K 1.5 S.S STO WA 75" 30 INSULATION G CONDUIT INSULATION 3M m 32 34 14 N/A FAN ROOM 1 716' 132 40.00 3M20C SEE CALC N/A N/A N/A SEE CALCULATION H RADIANT em36 14 1 SUPPORT Itm 327 064 14 N/A FAN ROOM 1 716' N/A N/A 3M20C SEE CALC N/A N/A N/A SEE CALCULATION H BOX Iam 328 208 14 NIA FAN ROOM 1 716' N/A N/A 3M20C SEE CALC N/A N/A N/A SEE CALCULATION H LOWHEAD SAFETY INJECTION I11m 329 2948 14 0600200 0901 FAN ROOM 1 716' 6.63 54.00 RMI 2,6875 SS STO W/A 12" 00 INSULATION J LOWHEAD SAFETY INJECTION Itam 330 002 14 0800200-09-01 FAN ROOM 1 716' 1.05 043 RMI 0,975 S.S. STO N/A 3" 00 INSULATION J LOWHEAD SAFETY INJECTION Item 331 003 14 0500200-09-01 FAN ROOM 1 716' 1.05 034 RMI 1,475 S.S. STON WA 4" 00 INSULATION J LOWHEAD SAFETY INJECTION Item 332 0.34 14 0600200-09-01 FAN ROOM 1 716' 2.38 0.63 RMI 061 S.S. STD N/A 4'O5 INSULATION J MIN-K-WR 1tam 333 0.02 14 N/A FAN ROOM 1 716' N/A SEE CALC MIN-K-WR 05 N/A N/A N/A ENCAPSULATED IN STAINLESS FOIL K RESIDUAL HEAT REMOVAL Wiam 334 1267 14 N/A FAN ROOM 1 716' 8.63 4964 RMI 1.1675 S'S' STD N/A 11' OD INSULATION L RESIDUAL HEAT REMOVAL It1m 335 12.67 14 N/A FAN ROOM 1 716' 863 49.64 RMI 1.1875 S.S SID N/A 11' OD INSULATION M RESIDUAL HEAT REMOVAL 11am 336 0.34 14 N/A FAN ROOM 1 716' 863 1.72 MIN-K 0.9375 S.S STD N/A 105" OD MIN-K NSULATION M LOWHEAD SAFETY INJECTION 11am 337 11.34 14 0600200-0...2 FAN ROOMS 716' 863 44S60 RMI 1.1875 SS. STD N/A II" 0D INSULATION N LOWHEAD SAFETY INJECTION Item 338 0.22 14 000230-09-02 IAN ROOM 1 718' 883 1.08 MIN-K 0.56 SS STD N/A 9-75" OD INSULATION N LOWHEAD SAFETY INJECTION It/m 339 0.35 14 0600200-09-02 FAN ROOM I 718' 8.3 2.50 RMI 0.5875 SS, STO N/A 10" O0 INSULATION N$TEAM GENERATOR BLSEM DOGENE I/am 340 9097 14 0600200-07-01 FAN ROOM 1 716' 4.50 3009 RMI 2.25 S.S. STD WA 9" 00 INSULATION P STEAM GENERATOR SLOWDOWN Item 341 025 14 0600200-07-01 FAN ROOM 1 716P 4.50 1.04 RMI 1.75 SS. STD N/A U" O0 INSULATION P STEAM GENERATOR BL0WD034 Item 342 028 14 0600200-07-01 FAN ROOM I 71/ 4.50 1.81 MIN.K 1.25 S.S. STD N/A 7" 00 INSULATION P STEAMGENEATO 11am 343 1.23 14 0600200O07-0I FAN ROOM 1 716' 4.50 126 RMI 4.75 S.S. STO N/A 14"O0 INSULATION P BLOWDOWN STEAM GENERATOR 1t1m 345 1.12 14 0800200-07-01 FAN ROOM I 716' 4.50 1.57 RMI 42.5 S.S STD N/A 13" O0 INSULATION P BLOWDOWN STEAM GENERATOR BLOWDOVWN Item 345 1.21 14 0600200-07-01 FAN ROOM 1 716' 11.50 1.57 RMI 4,25 S.S STD) NIA 16"OD INSULATION FLNS)p STEAM GENERATOR STEAMeGNm 348 0.74 14 0900200-07-01 FAN ROOM 1 716' 2.38 1.79 RMI 331 S.S STD N/A 1 O INSULATION P BLOWDOWVN

_____ _______STEAM GENERATOR STEAM G N Item 347 0.31 14 0600200-07-01 FAN ROOM I 716' 2.38 1.33 RMI 3.31 S.S. STD N/A 7" O0 INSULATION P BLOWDOWN STEAM GENERATOR SLOWDOWN I/am 349 0.317 14 0800233-07-01 FAN ROOM I 718' 2038 1.33 RMI 0831 0.S STD N/A 6"003 INSULATION P STEAM GENERATOR Item 340 037 14 0600200-07-01 FAN ROOM 1 716' 42. 015. RMI 201. S.S STD N/A 52" OD INSULATION P BLOWDOWN STEAM GENERATOR lam 350 067 14 060.200-.7-01 FAN ROOM 1 715' 4.50 25.42 RMI 20.2 S.S STD N/A 9" OD INSULATION P BLOWDOWN STEAM GENERATOR SLOWDOW 1tem 350 943 14 0800200-07-01 FAN ROOM 1 71U' 4.50 I.81 RMI 4.25 S.S STD N/A 13" O0 INSULATION 0 BLOWDOS WN Item 35 1.31 14 0600200-07-02 FAN ROOM 1 7168 4.50 16.3 RMI 4.25 SS STD N/A 9" 00 INSULATION 0 STEAM GENERATOR BLOWDOWN lam 353 1.31 14 0600200-07-02 FAN ROOM 1 716' 4,50 1,37 RMI 4.75 SS STD N/A WOO INSULATION 8TM GENERATOR 11-m 354 8.83 14 060=200-O7-03 FAN ROOM 1 716' 4.50 20.00 RMI 225 SS. STD N/A 9" OD INSULATION R BLOWDOWN STEAM GENERAT am 35 .8 14 0600200-07-03 FAN ROOM 1 71' 4.50 20.5 RMI 125 SS. ST) N/A 7" O0 INSULATION R BLOWDOWN 1-5 0 1' 4W .5 M STEAM GENERATOR BLOWDOWN EtR m 358 1.28 14 0600200-07-03 FAN ROOM 1 716' 4.5 1.4 RMI 4.75 S.S STO N/A 14" OD INSULATION (VALVE) R STEAM GENERATOR Im 35 12 14 00200-07-03 FAN ROOM 1 716' 4.50 1.55 RMI 425 S.S STD N/A 13" 00 INSULATION (VALVE) R BLOWDOWN Item 357 1,26 14 MIN K-WR It/m 358 002 15 N/A FAN ROOM 2 716' N/A SEE CALC MIN-K-WR 0.5 N/A N/A N/A ENCAPSULATED IN STAINLESS FOIL A MARINITE BOARD It/m 359 003 15 N/A FAN ROOM 2 718 N/A SEE CALC MARIN1TE I NIA WA N/A N/A A LOWHEAD SAFETY INJECTION 11am 350 9.33 15 0800600-09-02 EA. ROOM 2 71W' 6.83 48.09 RMI 1.1875 S.S0 STD N/A 9 00) INSULATION B

ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-9 of 1-12 DESCRIPTION L tem INSULVOUE INSULATION JACKET STRAP PACKET LETTER N) -PROBLEM NUMBER LOCATION ELEV. 00 (IN) LENGTH () INSUL TYPE T EBUCKLE TYPEITYPHC LOWHEAD SAFETY INJECTION Item 361 0.25 15 0600200-09-02 FAN ROOM 2 716' 6.63 2.25 RMI 06875 S.S. STD NIA VOID INSULATION B LOWHEAD SAFETY INJECTION 11-m 362 5.67 15 0600200-09-02 FAN ROOM 2 716' 663 065 MIN-K 11B75 SS STD WA 90ODMIN-KIINSULATION B CONDUIT INSULATION 3M Item 363 2.46 15 N/A FAN ROOM 2 716' 2.38 47.50 3M20C SEE CALC NIA N/A N/A SEE CALCULATION C RADIANT SUPPORT Itam 364 0.77 15 N/A FAN ROOM 2 716' N/A N/A 3M20C SEE CALC N/A N/A N/A SEE CALCULATION C BOX It.m 365 2.06 15 N/A FAN ROOM 2 716' NIA N/A 3M20C SEE CALC N/A N/A N/A SEE CALCULAT/ON C STEAM GENERATOR Item 366 389 15 0600200-07-02 FAA ROOM 2 716' 4.50 11.75 RMI 225 S.S. STO N/A 9WOO INSULATION D BLOWDOWN STEAM GENERATOR510-0-703-311015F1.

ROOM 2 71'W 2.38 1.66 RMI 2.31 S.S, STD NIA 7' OD INSULATION D SLOWVDOWN STEAM GENERATOR STEAG NIo 366 366 15 060=200-07-03 FAA ROOM 2 716' 4.50 11.05 RMI 2.25 S.S STO NWA 9"OD INSULATION E BLOM/DO/NA_

____STEAM GENERATOR LOWDOWN Item 369 019 15 0600200-07-03 FAN ROOM 2 716' 2.36 0.82 RMI 2.31 S.S. STO N/A 7" OD INSULATION E STEAM GENERATOR Item 370 019 15 0600200-07-03 FAA ROOM 2 716' 2.38 0.59 RMI 2.81 S.S STO N/A 8' OD INSULATION E SLOWDOWN MINEK Item 371 003 15 N/A FAN ROOM 2 716 N/A N/A MIN-K 0.505 N/A N/A N/A N/A F TAGS & LABELS Itlm 372 N/A 16 N/A ACCUMULATOR ROOM 1 716' NIA N/A N/A N/A N/A N/A N/A SEE REPORT FOR COMMENTS A POTENTIAL PAINT CHIPS Ilem 373 N/A 16 N/A ACCUMULATOR ROOM 1 716' N/A N/A N/A N/A N/A N/A N/A SEE REPORT FOR PAINT ISSUE B SEE SEESEWI0W-1,-04.-6&-

C MIRROR INSULATIONS Item 374 SEE COMMENT 16 N/A ACCUMULATOR ROOM 1 716' SEEMENT MMENTSEE C OM T S- SEE O E A -014E. F&-COMMENT COMMENT SEE COMMENT SEE CALC SEE COMMENT NIA W/A16 LOWHEAD SAFETY INJECTION Item 375 687 16 0600200-09-01 ACCUMULATOR ROOM 1 716' 6.63 16,24 RMI 2.6675 SS STD N/A 12" 00 INSULATION D LOWHEAD SAFETY INJECTION Itom 376 630 16 0600200-09-01 ACCUMULATOR ROOM 1 716' 663 2.17 RMI 8,6875 SS STD NIA 246 O0 INSULATION D LOWHEAD SAFETY INJECTION Item 377 1.93 16 0600200-09-Ol ACCUMULATOR ROOM 1 716' 2.38 616 RMI 2.3125 SS, STD N/A 7' OD INSULATION D LOWHEAD SAFETY INJECTION Item 376 005 16 0600200-09-01 ACCUMULATOR ROOM 1 716' 1.05 0.43 RMI 1.8125 S.& STD NIA 6" OD INSULATION D LOWHEAD SAFETY INJECTION Item 379 001 16 0500200-09-01 ACCUMULATOR ROOM 1 716' 105 084 MIN-K 025 S.S STD N/A 25" THK MIN- INSULATION D LOWHEAD SAFETY INJECTION Item 380 006 16 0600200-09-01 ACCUMULATOR ROOM 1 716' 105 040 MIN-K 2.2 S.S STD N/A 326' O MIN K INSULATION D RESIDUAL HEAT REMOVAL Item 381 506 16 N/A ACCUMULATOR ROOM 1 716' 863 1992 RMI 1.1675 SS STD N/A 11" OD INSULAT7ON E RESIDUAL HEAT REMOVAL Item 382 400 16 N/A ACCUMULATOR ROOM 1 716' 6.3 2.25 RMI 569 S.S STD NIA 20" OD INSULATION E RESIDUAL HEAT REMOVAL Item 383 1.00 16 N/A ACCUMULATOR ROOM 1 716' 863 264 RMI 1.6875 S.S. STD N/A 12' OD INSULATION E RESIDUAL HEAT REMOVAL Item 384 047 16 N/A ACCUMULATOR ROOM 1 716' 2.36 450 RMI 1.31 S.S STD WA 5' 00 INSULATION E RESIDUAL HEAT REMOVAL Item 385 021 16 N/A ACCUMULATOR ROOM 1 716. 2.38 068 RMI 2.31 S.S STD N/A 7COD INSULATION E RESIDUAL HEAT REMOVAL Item 386 0.14 16 N/A ACCUMULATOR ROOM 1 716' 1.06 0.71 RMI 247 S.S STD N/A 6" OD INSULATION E RESIDUAL HEAT REMOVAL Item 387 3.70 16 N/A ACCUMULATOR ROOM 1 716' 863 14056 RI 1.1675 S.S STD NWA 11 OD INSULATION F LOWHEAD SAFETY INJECTION Item 386 4.30 16 0600200-09-02 ACCUMULATOR ROOM 1 716' 8.63 1692 RMI 1.1675 S.S. STO N/A I YOD INSULATION G 3" AUXILIARY SPRAY LINE Item 389 0.17 17 0600200 13-02 ACCUMULATOR ROOM 2 716' 3.50 126 RMI 1 25 S.S. STD N/A 6" OD INSULATION A 3" AUXILIARY SPRAY LINE Item 390 6.59 17 0600200-13-02 ACCUMULATOR ROOM?2 716' 350 22.91 RMI 2.75 S.S. STD N/A 9' OD INSULATION A 3" AUXILIARY SPRAY LINE Item 391 0.11 17 0600200.13-02 ACCUMULATOR ROOM 2 716' 3.50 0.66 MIN-K 15 S.S STO N/A 6.5" GO INSULATION A 3 AUXILIARY SPRAY LINE Item 392 0.78 17 0600200-13-02 ACCUMULATOR ROOM 2 716' 3.50 109 RMi 4.25 S.S. STD N/A 12" OD INSULATION A LOWHEAD SAFETY INJECTION Iter 393 3.73 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 6.63 1642 RMI 1.1875 S.S STO N/A 9" OD INSULATION B LOWHEAD SAFETY INJECTION Item 394 3.73 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 6.63 1.92 RMI 66675 S.S. STO NIA 20" 00 INSULATION B LOWHEAD SAFETY INJECTION Item 395 3.45 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 8.63 13.59 RMI 1.1675 S.S STO N/A 1" OD INSULATION B LOWHEAD SAFETY INJECTION Ionm 31 6 0.08 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 2.38 1.34 MIN-K 06125 S.S STO NIA 4" OD MIN-K INSULATION B LOWHEAD SAFETY INJECTION Item 397 0.03 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 2.38 0.78 RMI 0.5625 S.S STD NIA 3`5 0OD INSULATION B LOWHEAD SAFETY INJECTION Item 398 003 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 2.36 092 .MIN-K 05625 S.S STD N/A 3.5" G0 MIN-K INSULATION B LOWHEAD SAFETY INJECTION It.e 399 005 17 0600200 09-02 ACCUMULATOR ROOM 2 716' 2.36 050 MIN-K 1.3125 S.S STD N/A 5* OD MIN K INSULATION B LOWHEAD SAFETY INJECTION It.. 400 045 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 2.38 4.29 RMI 1.3125 S'S STD NIA 5 OD INSULATION B LOWHEAD SAFETY INJECTION Item 401 236 17 0600200-09-02 ACCLMULATOR ROOM 2 716' 2.38 10.00 RMI 2.3125 S'S STD N/A 7" 00 INSULATION B LOWHEAD SAFETY INJECTION 11- 402 059 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 236 1.15 RMI 3.8125 SS STD N/A 10OD INSULATION B LOWHEAD SAFETY INJECTION Item 403 0.75 17 0606200 09,02 ACCUMULATOR ROOM 2 716' 238 1.45 RMI 3.8125 SS. STD N/A 6" 00 INSULATION B LOWHEAD SAFETY INJECTION Item 4.4 0.4 17 0600200-09.02 ACCUMULATOR ROOM 2 716' 1.05 051 RMI 1.475 S 6 STD N/A l GO INSULATION R LOWHEAD SAFETY INJECTION Item 405 0.96 17 0600200-09-02 ACCUMULATOR ROOM 2 716' 1.05 367 NRMI 2.975 S.S. STO I WA 7" OD INSULATION ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-10 of 1-12 N umb r NFT3) AREA PROBLEM NUMBER LOCATION ELEV. 0O (IN) LENGTH (FT) INSULTYPE THICKNESS IN) MATERIAL BUCKLE TYPE TYPE COMMENTS PACKET LETTER DSRPIN Line ton, INStiL. VOLUME TICNESULAION MATKErISAL NORMAL CHARGING 11- tm410 03S 17 0600200-08-11 ACCUMULATOR ROOM 2 716' 3.50 096 RMI 2.75 S'S TO N/A S OD INSULATION D EXCESS LETDOWN Ite m 411 2.07 17 0600200-06-12 ACCUMULATOR ROOM 2 716' 1.32 11.09 RMI 2,34 S.S. STD WA 6OD INSULATION E EXCESS LETDOWN Item 412 025 17 0600200 08-12 ACCUMULATOR ROOM 2 716 ` 1.32 2.00 RMI 7.64 B.S. STD NIA 5" O INSULATION E EXCESS LETDOWN Item 413 0.14 17 0600200-08-12 ACCUMULATOR ROOM 2 776e 1.05 1.07 RMI 1.975 S'S STD WA _"500 INSULATION E EXCESS LETDOWN Item 414 0.75 17 0600200-08-12 ACCUMULA70R ROOM 2 710' 1.05 067 RMI 2.975 S.S STD N/A 7" O INSULATION (VALVE) E 3" ALTERNATE CHARGING item 415 444 17 0600200 11 ACCUMULATOR ROOM 2 716 -3.50 71. 54 RMI 2.75 S.S STO N/A 9V 0 ) INSULATION F 3" ALTERNATE CHARGING Item 416 0.36 17 0600200 08-11 ACCUMULATOR ROOM 2 716' 350 275 RMI 1,25 SS STO WA 6"SO INSULATION F 3" ALTERNATE CHARGING It.. 417 0.66 17 0600200-0.-11 ACCUMULATOR ROOM 2 71' 350 234 RMI 2.25 SS STD WA 6" OD INSULATION F TAGS & LABELS t em418 N/A 19 N/A ACCUMULATOR ROOM 4 716' N/A N/A N/A WA N/A N/A N/A SEE REPORT FOR COMMENTS A TAGS & LABELS Item 417 N/A 19 N/A ACCUMULATOR ROOM 4 716' N/A " N/A N/A NA NIA N/A NVA SH/OW RUBBER GASKETS B TAGS & LABELS Itnn 420 N/A 19 N/A ACCUMULATOR ROOM 4 7106 N/A N/A N/A NA N/A N/A N/A SEE REPORT FOR COMMENTS C PENETRATIONS It.. 421 N/A 19 NWA ACCUMULATOR ROOM 4 716' NIA N/A N/A NIA N/A N/A NA NO POTENTIAL DEBRIS FROM THESE D LETDOWN LINE It.. 422 3.83 19 0600270 008-09 ACCUMULATOR ROOM 4 716 ` 2 36 23.17 RMI 1.81 S.S. ST D N A W A E LOWHEAD SAFETY INJECTION Item 423 317 19 0600200-09-01 ACCUMULATOR ROOM 4 718- 6.63 15.67 RMI 1.1675 S.S STD NIA 9" 0O INSULATION F LO W H/EAD SAFETY IN JECTIO N Ite m 424 7.46 19 0600200-09-01 ACCU M ULATO R RO O M 4 716' 6.63 2.17 RM I 9.6875 S .S STD W A 26"00 INSULATION F LOWHEAD SAFETY INJECTION Item 425 692 10 0U002.0-0 9,01 ACCUMULATOR ROOM 4 716' 6.63 35.09 RMI 1.1675 S. STO WA 11D0 INSULATION F LOWHEAD SAFETY INJECTION Item 426 0.37

• 10 0600200.0 9,01 ACCUMULATOR ROOM 4 716' 163 053 RM7 2.6187 S.S. STD WA 13" OD INSULATION F LOWHEAD SAFETY INJECTON Item 427 1.70 19 0600200-09-01 ACCUMULATOR ROOM 4 718' 1 05 86.92 RMI 2475 S.S STO NIA 6" 0 INSULATION F LOWHEAD SAFETY INJECTION

[tn, 426 0.03 19 0600200-09-01 ACCUMULATOR ROOM4 716' 105 0.90 MIN-K 0.726 S.S STD NWA 245* OD MIN-K INSULATION F LOWHEAD SAFETY INJECTION Item 429 0.32 19 0600200-08-0 1 ACCUMULATOR ROOM 4 716' 1.05 094 RMI 3475 S0S. ST D WA 6" 00 INSULATION F LOWHEAD SAFETY INJECTION Item 430 148 19 0600200.09-01 ACCUMULATOR ROOM 4 718' 2.38 625 RMI 2.31 S ,S. STO WA I DD INSULATION F LOWHEAD SAFETY INJECTION Ite m 431 045 19 0600200 .09-01 ACCUMULATOR ROOM 4 710' 2.38 071 RM. 43125 S.S. STD WA 11" O0 INSULATION F LOW NEAD SAFETY INJECTION Item 432 0.34 19 0600200-09-01 ACCUMULATOR ROOM 4 716' 1.05 IS0 RMI 2.475 S.S. STE WA 6" OD INSULATION LOWHEAD SAFETY INJECTION Ite m 433 045 19 0600200-09-01 ACCUMULATOR ROOM 4 716' 1.05 342 RMI 1.975 S.S, STO NIA 5"00 INSULATION LOW HEAD SAFETY INJECTION Item 434 0.55 19 0600200-09-01 ACCUM ULA TO R RO OM 4 7 t6' 1.05 .06 4 RM I 4.975 S.S STO W A I I" O INSULA TIO N F RESIDUAL HEAT REMOVAL Item 435 13.11 19 N/A ACCUMULATOR ROOM 4 71S' 663 51.59 RMI 11875 S.S. STD N/A Il" 00 INSULATION G RESIDUAL HEAT REMOVAL Item 436 0.20 19 N/A ACCUMULATOR ROOM 4 716E 8.63 1.00 MIN-K 0.935 S'S STD N/A 10.5" OD INSULATION G RESIDUAL HEAT REMOVAL It.. 437 0.35 19 N/A ACCUMULATOR ROOM 4 716' B.63 2,52 RMI 06675 S9S STD N/A 10" D0 INSULATION G RESIDUAL HEAT REMOVAL item 43 5 7.46 19 NIA ACCUMULATOR ROOM 4 716 ` 12.75 21.92 RMI 1.125 SS STD WA 15" 0O INSULATION G G RESIDUAL HEAT REMOVAL item 439 1.32 19 N/A ACCUMULATOR ROOM 4 716 ` 12.75 1.50 RMI 2.625 SUS STD WA 18" 00 INSULATION G RESIDUAL HEAT REMOVAL Itemm440 033 19 N/A ACCUMULATOR ROOM 4 716E 1,05 1.75 RMI 2475 SS. STD N/A 6"OD INSULATION G RESIDUAL HEAT REMOVAL Item 641 007 19 N/A ACCUMULATOR ROOM 4 716' 1.05 080 RMI 1.475 SS STD NWA 4 OD INSULATION G RESIDUAL HEAT REMOVAL It.. 642 006 19 N/A ACCUMULATOR ROOM 4 716- 2.88 084 RMi 1.06 S.S. STD WA 5" OD INSULATION (TIEBACK G_______________

______SUPPORTI RESIDUAL HEAT REMOVAL It. 443 006 19 N/A ACCUMULATOR ROOM 4 716- 105 046 RMI 17975 S.S. STD WA 5 OD INSULATION G R E S IDU AL NEA T R EM O V AL ite m 444 0.08 79 N /A A CC U M U LA T O R R O O M 4 716 ` 268 0.53 R M I 17 56 S ,S .ST D NW A 5" O0 IN S U LA T IO N (TIEBA C K G-OS ISSUPPORT)

RESIDUAL HEAT REMOVAL Item 445 0.90 19 N/A ACCUMULATOR ROOM 4 7160 1.05 11.09 RMI 1475 S'S STD WA 4" CO INSULATION (DRAIN LINE) G RESIDUAL HEAT REMOVAL Itemn 4 46 014 19 N/A ACCUMULATOR ROOM 4 7160 -1.05 1.07 RMI 1.975 SS STO NWA 5 " O0 INSULATION DRAIN VALVE) G RESIDUAL HEAT REMOVAL item 447 7.33 19 0600200 03-01 ACCUMULATOR ROOM 4 710" 14.00 10.50 RM/ 2 SS STD 0 WA 18"OD INSULATiON H RESIDUAL HEAT REM OVAL Ite m 448 358 19 0600200-0801 ACCUMULATOR ROOM 4 716' 10.75 600 RMI 2.125 SS STO WA 15 -OD INSULATION H RESIDUAL HEAT REMOVAL Item 449 1515 19 0600200-03-01 ACCUMULATOR ROOM 4 716' 14.00 311 RMI 95 S.S. STD NWA 33" OD NSULATION (VALVE) H RESIDUAL HEAT REMOVAL I tem4450 992 19 0600200-03-01 ACCUMULATOR ROOM 4 716' 10.75 272 RMI 86 625 S.0 STO W A 20" OD NSULAT ION (VALVE)RESIDUAL HEAT REMOVAL Item 451 007 19 0600200-03-01 ACCUMULATOR ROOM 4 716' 350 034 RMI 1.75 S.S STE) WA 7 "00 INSULATION H RESIDUAL NEAT REMOVAL Item 452 0.04 19 0600200.03-01 ACCUMULATOR ROOM 4 716' 105 0682 RM0 0.975 S.S ST7D NA 3" 00 INSULAT7ON H LOWHEAD SAFETY INJECTION

/to. 453 10.11 19 0600200-09-02 ACCUMULATOR ROOM 4 716' 8.63 39.75 RMI 1.1875 S.S STD NWA 11" V0 INSULATION LOWHEAD SAFETY INJECTION Item 454 1.01 19 0600200-0.-02 ACCUMULATOR ROOM 4 716- 8.63 5417 MIN-K 0.9375 &.S STO WA 10 5" OD MIN-K INSULATION SEAL WATER RETURN LINE Item 455 350 19 0600200-08-06 ACCUMULATORROOM4 776' 4.50 14.67 RMI 1.70 SS STO WA 6 O [) INSULATION K SEAL WATER RETURN LINE Item 456 1.12 19 0600200-06-06 ACCUMULATOR ROOM 4 716' 4.50 1.17 RMI 4.75 SS STO WA 14" OD INSULATION K SEAL WATER RETURN LINE Item 457 054 19 0600200-08-06 ACCUMULATOR ROOM 4 716' 4.50 080 RMI 3.75 S.S STO N/A 12"OD INSULATION K SEAL WATER RETURN LINE ltem458 031 19 0600200.08-06 ACCUMULATOR ROOM 4 7160 1.06 360 RMI 1.47 S.S STD NWA 4' 00 INSULATION K SEAL WATER RETURN LINE Item 459 0.33 19 0600200-08-06 ACCUMULATOR ROOM 4 716" 1.06 7.71 RMI 2.47 S.S STD NWA " O0 INSULATION K SEAL WATER RETURN LINE It/, 440 0.19 19 0600200-08.06 ACCUMULATOR ROOM 4 7160 2.38 1683 RM/ 1.31 S.S STD NIA 5" 00 INSULATION K SEAL WATER RETURN LINE It. e 461 0.11 19 0600200-08-06 ACCUMULATOR ROOM 4 717' 2.38 0.26 RMI 331 S.S STD N/A 9" 00 INSULATION K MIN-K item 462 0.04 09 N/A ACCUMULATOR ROOM 4 7160 N/A N/A M7N-K 0.72 N/A NWA NWA WA L GLYCOLR N/SU463 7022 20 K/A UPPER CONTAINMENT 756 ` 2.38 29.03 FOAMGLASS 3 SS WA STE EL 756' TO EL 769'-0 5/8" A LINES IteLY 4_3_102_20_NAUPPRCONTINMEN GLYCOLRETURNWLPPLY Ite m 464 356 20 NIA UPPER CONTAINMENT 756' 2.38 10.10 FOASIPLASTIC 3 N/A NWA WA EL. 771'-6" A GLYCOL RETURN/UPPLY Item 445 1.57 20 N/A UPPER CONTAINMENT 756" 064 625 FOAMPLASTIC 3 WA WA WA EL. 771'-6 A LINES GLYCOL RETIUN/SUPPLY UPPERCNTANMENT 755' 2.3. 14.70 FOAMPLASTIC 3 WA WA WA EL 775-0 A LIELINES__

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ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-11 of 1-12 DESCRIPTION Lln,~me flare INSUL VOLUME 1HCNs SLTON MTRA AKTSTRAPTP COMNSPCKTLTE

[ECITO AREA PROBLEM NUMBER LOCATION ELEV. OD (IN) LENGTH (FT) INSUL. TYPE INSULATION JACKET PACKET LETTER Number PET3) __________

_____ ______ THICKNESS (IN) MATERIAL BUKEYE TYPE ______________

______GLYCOL RETURN/SUPPLY LINES Item 467 2.20 20 N/A UPPER CONTAINMENT 756' 0.84 875 FOAMPLASTIC 3 SS N/A NIA A GLYCOL RETURN/SUPPLY GLCLRTRtUPY Item 458 0.63 20 N/A UPPER CONTAINMENT 756' 0,14 2.50 FOAMGLASS 3 SS N/A STD CHC AVSA LINES L INES It.. 469 1.65 20 N/A UPPER CONTAINMENT 755' SEE CALC SEE CALC FOAMPLASTIC I N/A N/A N/A AT SUPPORTS A LINES VENT-CURTAINS Item 470 2.20 21 N/A ICE CONDENSER 803' N/A SEE CALC SEE CALC SEE CALC N/A NWA N/A N/A A SEAL FRAME & VESSEL SHELL Item 471 8.38 21 N/A ICE CONDENSER 803' N/A SEE CALC SEE CALC SEE CALC N/A N/A NWA W/A A GLYCOLRETURN/SUPPLY Item 472 111,97 21 N/A ICE CONDENSER 758' 2.38 318.05 EOASIGLASS 3 S.S N/A NA B LINES GLYCOL RETURN/SUPPLY Item 473 6998 21 N/A ICE CONDENSER 756' 1,05 264.00 EOAMGLASS 3 SSN WA STD NIA a LINES DRAIN LINES item 474 262.88 21 N/A ICE CONDENSER 756' 12.75 25500 FOAMGLASS 3 SS N/A STD N/A B TOP DECK BLANKET Item 475 44400 21 NIA ICE CONDENSER 819'-7 1/20 SEE CALC SEE CALC SPONGE 0.75 SS N/A STITCHES 2 BLANKET LAYERS C ASSEMBLY END WALLS/DOORS Item 478 4020 21 N/A ICE CONDENSER 803' SEE CALC SEE CALC FOAM RUBBER I N/A N/A N/A N/A D S.S. JACKETING USED ON SOME GLYCOL SUPPLY LINE Item 477 18.78 21 N/A ICE CONDENSER 803' 683 28.81 FOAMGLASS 3 NIA N/A N/A PIPING OUTSIDE OF ICE CONDENSER E BAY 5.0 JACKETING USED ON SOME GLYCOL SUPPLY LINE Item 478 7.52 21 N/A ICE CONDENSER 803' 4.50 14.30 FOA-GLASS 3 N/A N/A NIA PIPING OUTSIDE OF ICE CONDENSER U BAY SS JACKETING USED ON SOME GLYCOL SUPPLY LINE It.n 479 211.31 21 N/A ICE CONDENSER 803' 4.50 553347 FOAMPLASTIC 2.5 N/A NA N/A PPI NG OUTSIDE OF ICE CONDENSER BAY S.S. JACKETING USED ON SOME GLYCOL RETURN LINE Item 480 830 21 N/A ICE CONDENSER 803' 8.83 1000 FOAMGLASS 3 NIA N/A N/A PIPING OUTSIDE OF [CE CONDENSER E BAY S.S. JACKETING USED ON SOME GLYCOL RETURN LINE 1Ie- 481 14.56 21 N/A ICE CONDENSER 803' 4.50 29.67 FOAMGLASS 3 N/A NA N/A PIPING OUTSIDE OF ICE CONDENSER E BAY S.S. JACKETING USED ON SOME GLYCOL RETURN LINE IN/. 482 201.97 21 N/A ICE CONDENSER 803' 4.50 $29.00 FOAMPLASTIC 2.5 NIA N/A N/A PIPING OUTSIDE OF ICE CONDENSER E BAY GLYCOL SUPPLY BYPASS Item 483 1.31 21 N/A ICE CONDENSER 603' 084 7.17 FOAMPLASTIC 2.5 N/A N/A N/A N/A F LINE0 GLYCOL SUPPLY BY-PASS Ion, 484 013 21 N/A ICE CONDENSER 803' 084 0.50 FOAMGLASS 3 N/A N/A N/A VALVE E LINE LINEI485 1.51 21 N/A ICE CONDENSER 853' 084 827 FOAMPLASTIC 2.5 N/S N/A NA N/A LIRE ItBP 486 0.13 21 NIA ICE CONDENSER 803' 0.84 050 FOAMGLASS 3 N/A N/A N/A VALVE LINE GLYCOL EXPANSION TANK Itn,487 0.19 21 N/A ICE CONDENSER 803' 3.50 0.59 FOAMPLASTIC 2.5 NIA N/A N/A N/A E LINES GLYCOLEXPANSION TANK 11..488 8.82 21 N/A ICE CONDENSER 803' 1.32 32.72 FOAMPLASTIC 2.5 N/A N/A N/A N/A LINESA GLYCOL S~L7,rLoIURN, Ionm 489 15626 21 LINES TO AHUS N/A ICE CONDENSER 803' 1.32 750.00 FOAMPLASTIC 2.5 N/A IN/A N/Al N/A E 3' AUXILIARY SPRAY LINE Item 5-7 003 23 0600200-1302 0.0u PRESSURIZER PRESSURIZER PRESSURIZER PRESSURIZER 728'729'729'729'350 1.34 MIN-K 05I SS STO 4 02' ODINSULATION N/A Volme n hanged par TVA calculation Re. 0 B 3' AUXILIARY SPRAY LINE Ioen 510 0 11 23 1 80 200.13102 3.50 0.70 MIN-K 1.5 S'S. STD 6.5" OD INSULATION N/A Dou, banded pe0 1. TVA calculmion MDO0010632007115 R-. 0 B ALION-CAL-TVA-2739-03 Revision 3 Appendix 1 1-12 of 1-12 DSRPIN Line Iterm INSUL.VOLUME INSULATON JCE STRAP Number (FT3) AREA PROBLEM NUMBER LOCATION ELEV. 0O (IN) LENGTH (FT) INSUL TYPE BSION JACKET BUCKLE TYPE COMMENTSPPACKET LETTER Nlm I VO THICKNESS (IN) MATERIAL TYPE TYPE_ C_______PACKETLETTE PRESSURE RELIEF Item 514 3.79 23 NIA PRESSURIZER 729' 3.50 267 RMI 6.5 S.S S7D NIA 1658' O INSULATION 0 PRESSURE RELIEF 1te1 515 1.60 23 N/A PRESSURIZER 729' 3.50 427 RM$ 2.75 S.S ST0 NIA 9' 0O INSULATION D PRESSURE RELIEF WI.n 516 0.68 23 N/A PRESSURIZER 729' 12.00 111 RMI 2 S.S STO NWA 16' 0O INSULATION (FLANGE) D PRESSURE RELIEF item 517 0.99 23 N/A PRESSURIZER 729' 350 1.67 RMI 3.75 SS. STO N/A 11 OD INSULATION D PRESSURE RELIEF Item 518 0.18 23 N/A PRESSURIZER

.729' 3.50 064 RM I 2.25 SS. STO WN/A WOO INSULATION D PRESSURE RELIEF Sonm 519 0.78 23 N/A PRESSURIZER 729' 12.00 1.11 RMI 2.25 SS. STO N/A 13.5 OD INSULATION (FLANGE) D PRESSURE RELIEF Ion. 520 0.52 23 N/A PRESSURIZER 729' 106 1 go RMI 2.97 5S. STO WA 7 OD INSULATION D LETDOWN LINE Iteum 521 7.98 24 0600200-0B-10 INSTRUMENT ROOM 716' 350 1867 RMI 325 US. STO WA N/A A LETDOWN LINE Ionm 522 14.76 24 N/A INSTRUMENT ROOM 716' 350 30W4 RMI 3.25 &S. STO WA N/A B REGENERATIVE HEAT RECNER Itor 523 45.63 24 N/A INSTRUMENT ROOM 716' 1090 SEE CALC RMI 305 S.S STO WA NIA B EXCHANGERI LETDOWN LINE Iaen 524 3405 24 3600200-06-09 INSTRUMENT ROOM 716' 353 15.34 RMI 574 .S STO NWA NWA C NORMAL CHARGING LINE Item 525 8.88 24 0600200.06-11 INSTRUMENT ROOM 716' 350 2367 RMI 2,75 S.S STD NWA AT 9"OD INSULATION D NORMAL CHARGING LINE ten, 526 0.16 24 0600200O-0&

11 INSTRUMENT ROOM 716' 3.50 124 RMI 125 S.S STO NWA AT 6OD INSULATION D NORMAL CHARGING LINE Rtam 527 0.57 24 0600200-06-11 INSTRUMENT ROOM 716' 3.53 2.82 RMI 1.75 S.S STD WA AT 7"OD INSULATION 0 ALTERNATE CHARGING LINE Item 528 044 24 0900200-08-11 INSTRUMENT ROOM 716' 3.50 .191 RMI 2.75 S4S S7T NWA AT 9 OD INSULATION D ALTERNATE CHARGING LINE ton. 529 0.48 24 0600200-08-11

.INSTRUMENT ROOM 716' 3.50 1.69 RMI 225 SS STD NWA AT OD INSULATION 0 NORMAL CH/ARGING BYPASS lo50D LINE l~n 2 .9 24 0600200.06-11 INSTRUMENT ROOM 716' 1.09 3.34 RMI 1.975 '.S. STO WA AT 500D INSULATION D NORMAL CHARGING BYPASS It.. 531 006 24 0600200-08-I1 INSTRUMENT ROOM 716' 1.05 1.80 RMI 0.975 SS. STO) NWA AT 0 O INSULATION D LINE I_ _AUXILIARY SPRAY LINE Io.. 532 345 24 0600200.08-11 INSTRUMENT ROOM 716' 2.38 1084 RMI 2.81 USS STD NIA AT 8* 00 INSULATION D AUXILIARYSPRAYLINE it.. 533 039 24 0600200w-1302 INSTRUMENT ROOM 716' 1350 1.05 RMI 2.75 SS. STO WA AT 9' OD INSULATION 0 AUXILIARY SPRAY LINE Ito, 53 4 002 24 0600200.1102 INSTRUMENT ROOM 716' 3.50 0.84 RMI 0.25 SS. STO WA AT 48 OD INSULATION D AUXILIARY SPRAY LINE It.. 535 039 24 0600200-13-02 INSTRUMENT ROOM 716' 350 059 RMI 0275 SO. STO NWA AT 59 O INSULATION 0 AUXILIARY SPRAY LINE item 539 010 24 0600200.13-02 INSTRUMENT ROOM 716' 350 2.25 RMI 0.5 SS. N/A ST AT 4.5 00 INSULATION D RESIDUAL HEAT REMOVAL Item 537 14.07 24 N0 A INSTRUMENT ROOM 716' 893 5534 RMI 11975 U.S. STO WA 1 V O INSULATION E LOWHEAD SAFETY INJECTION Iton 53M 16.47 24 0600200-09-02 INSTRUMENT ROOM 716' 6863 72.67 RMI 1.1575 S.S STO NWA I" 030 INSULATION F EXCESS LETDOWN Item 539 3.11 24 0600200-08-12 INSTRUMENT ROOM 716' 132 16.67 RMI 234 S.S STO WA 6 O INSULATION G EXCESS LETDOWN Item 540 0.09 24 0600200.0U-12 INSTRUMENT ROOM 716' 1 32 117 MIN-K 134 S.S TSD N/A 4' O INSULATION G EXCESS LETDOWN item 541 0.09 24 0600200.08-12 INSTRUMENT ROOM 716' 1.32 072 RMI 184 S.S STO NA 5'OD INSULATION G EXCESS LETDOWN Item 542 0.22 24 0600200-06-12 INSTRUMENT ROOM 716' 1.05 093 RMI 2.64 S.S. STD NWA 7' O INSULATION G CONDUIT 3M.M2OC Itell 543 2.19 24 N/A INSTRUMENT ROOM 720.737 1.90 50.00 3M-M20C 0,1675 N/A N/A NWA SEE CALCULATION H CONDUIT3.2CSPOTLATION E CONDUIT 3M-M20C Item 544 1.00 24 N/A INSTRUMENT ROOM 720-737 0.6/ 50.00 3M.M20C 0.1875 NWA NWA NWA SEE CALCULATION INSULATION CONDUIT 3M-M20C Item 545 1454 24 N/A INSTRUMENT ROOM 720-737 N/A N/A 3M-M20C 091875 NIA NIA NIA SUPPORT INSULATION SEEA INSULATION CALCULATION MIN-K INSULATION It.. 546 106 24 N/A INSTRUMENT ROOM 720-737. 0.68 20.00 MN-K 0.75 N/A WA NIA SEE CALCULATION H EXCESS LETDOWVN NEAT E ESCSANGER It.. 547 402 24 NIA INSTRUMENT ROOM 716' 18.75 SEE CALC RMI SEE CALC S.S ST N/A 25" 00 INSULATION J EXCESS LETDOWN 1 te4 549 1.12 24 N/A INSTRUMENT ROOM 718' 1.32 600 RMI 2.34 S.S STO WA 6"O INSULATION K EXCESS LETDOWN Ion, 549 0.34 24 N/A INSTRUMENT ROOM 716' I 32 1.32 RMI 254 S.S. DT I WA 1 7OD INSULATION K EXCESS LETDOWN Iton 560 045 24 NIA INSTRUMENT ROOM 716' 1.32 0.84 RMI 434 S.S STO N/A 10"OD INSULATION K

Watts Bar Reactor Building GSI-191 Debris Generation Calculation il:ON Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 2-1 of 2-7 APPENDIX 2 -RMI WORKSHEETS This Appendix contains the RMI worksheets which identify which RMI debris sources terms are included for each break location.

The line item column provides a reference back to Appendix 1, which can be used as a reference back to the Enercon provided Watts Bar insulation spreadsheet in Attachment A.

ALI ON-CAL-TVA-2739-03 Revision 3 Appendix 2 2-2 of 2-7 DESCRIPTION Line Item INSUL. INSULATION RMI Surface Break 1 Break 2 Break 3 Break 4 NumberAREA LOCATION ELEV. OD (IN) LENGTH () INSUL. TYPE THICKNESS (IN) Area RC INTERIM LEG Item 46 88.62 2 LOOP 1 702' SEE CALC SEE CALC RMI SEE CALC 3190.32 x x x REACTOR COOLANT PUMP Item 47 63.45 2 LOOP 1 702' SEE CALC SEE CALC RMI SEE CALC 2284.20 x x x INTERIM LEG DRAIN Item 48 0.45 2 LOOP 1 702' 2.38 0.88 RMI 3.8125 16.30 x a x INTERIM LEG DRAIN Item 49 4.46 2 LOOP 1 702' 2.38 14.00 RMI 2.8125 160.42 x x x INTERIM LEG DRAIN Item 50 0.13 2 LOOP 1 702' 2.38 0.55 RMI 2.3125 4.68 x X x INTERIM LEG DRAIN Item 51 0.05 2 LOOP 1 702' 2.38 0.50 RMI 1.3125 1.90 x x x RC INTERIM LEG Item 53 86.81 3 LOOP 2 702' SEE CALC SEE CALC RMI SEE CALC 3125.16 x x x REACTOR COOLANT PUMP Item 54 63.45 3 LOOP 2 702' SEE CALC SEE CALC RMI SEE CALC 2284.20 x x a INTERIM LEG DRAIN Item 55 0.45 3 LOOP 2 702' 2.38 0.88 RMI 3.8125 16.30 x x x INTERIM LEG DRAIN Item 56 4.46 3 LOOP 2 702' 2.38 14.00 RMI 2.8125 160.42 x x x RC INTERIM LEG Item 58 85.43 4 LOOP 3 702' SEE CALC SEE CALC RMI SEE CALC 3075.48 x x INTERIM LEG DRAIN Item 59 0.99 4 LOOP 3 702' 2.38 1.92 RMI 3.8125 35.57 x x INTERIM LEG DRAIN Item 60 3.02 4 LOOP 3 702' 2.38 9.50 RMI 2.8125 108.86 x x LETDOWN LINE Item 61 6.34 4 LOOP 3 702' 3.50 13.25 RMI 3.25 228.29 x x REACTOR COOLANT PUMP Item 62 63.45 4 LOOP 3 702' SEE CALC SEE CALC RMI SEE CALC 2284.20 x x RC INTERIM LEG Item 64 85.05 5 LOOP 4 702' SEE CALC SEE CALC RMI SEE CALC 3061.80 x I x REACTOR COOLANT PUMP Item 65 63.45 5 LOOP 4 702' SEE CALC SEE CALC RMI SEE CALC 2284.20 x x INTERIM LEG DRAIN Item 66 0.99 5 LOOP 4 702' 2.38 1.92 RMI 3.8125 35.57 x x INTERIM LEG DRAIN Item 67 4.11 5 LOOP 4 702' 2.38 12.92 RMI 2.8125 148.05 x x RESIDUAL HEAT REMOVAL Item 70 41.02 5 LOOP 4 702' 14.00 58.75 RMI 2 1476.55 x x RESIDUAL HEAT REMOVAL Item 71 1.64 5 LOOP 4 702' 14.00 5.00 RMI 1 58.90 x x RESIDUAL HEAT REMOVAL Item 72 1.10 5 LOOP 4 702' 14.00 1.83 RMI 1.75 39.61 x x RESIDUAL HEAT REMOVAL Item 73 9.35 5 LOOP 4 702' 10.75 15.67 RMI 2.125 336.72 x x RESIDUAL HEAT REMOVAL Item 74 21.31 5 LOOP 4 702' 14.00 3.13 RMI 12 766.99 x x RESIDUAL HEAT REMOVAL Item 75 14.60 5 LOOP 4 702' 10.75 2.75 RMI 11.125 525.62 x x RESIDUAL HEAT REMOVAL Item 76 0.09 5 LOOP 4 702' 1.05 1.13 RMI 1.475 3.31 x x RESIDUAL HEAT REMOVAL Item 77 0.42 5 LOOP 4 702' 1.05 2.21 RMI 2.475 15.14 x x RESIDUAL HEAT REMOVAL Item 78 0.32 5 LOOP 4 702' 6.63 2.91 RMI 0.6875 11.49 x x RESIDUAL HEAT REMOVAL Item 79 5.95 5 LOOP 4 702' 6.63 2.05 RMI 8.6875 214.18 x x STEAM GENERATOR Item 80 215.60 6 LOOP 1 716' SEE CALC SEE CALC RMI SEE CALC 7761.60 x x I STEAM GENERATOR Item 81 0.66 6 LOOP 1 716' SEE CALC SEE CALC RMI SEE CALC 23.76 x x FEEDWATER Item 82 24.32 6 LOOP 1 716' 16.00 24.10 RMI 2.5 875.42 x 544.87 x Loop 2 -15ft FEEDWATER Item 83 1.91 6 LOOP 1 716' 16.00 10.59 RMI 0.5 68.62 x x FEEDWATER Item 84 0.42 6 LOOP 1 716' SEE CALC SEE CALC RMI SEE CALC 15.12 x x FEEDWATER Item 85 0.26 6 LOOP 1 716' SEE CALC SEE CALC RMI SEE CALC 9.36 x x 4" PRESSURIZER SPRAY LINE Item 94 18.88 6 LOOP 1 716' 4.50 43.40 RMI 2.75 679.60 x x x 4" PRESSURIZER SPRAY LINE Item 95 0.10 6 LOOP 1 716' 4.50 1.21 RMI 0.75 3.74 x x x 4" PRESSURIZER SPRAY LINE Item 97 2.51 6 LOOP 1 716' 4.50 1.21 RMI 7.75 90.22 x x x 3/4"PRESSURIZER SPRAY Item 98 1.35 6 LOOP 1 716' 1.05 5.17 RMI 2.975 x x x BYPASS LINE 48.62 3/4"PRESSURIZER SPRAY Item 99 0.35 6 LOOP 1 716' 1.05 4.34 RMI 1.475 12.70 BYPASS LINE 12.70 3/4"PRESSURIZER SPRAY Item 100 0.16 6 LOOP 1 716' 1.05 0.50 RMI 3.35 x x BYPASS LINE 1 1 5 a79 HOT LEG Item 101 69.55 6 LOOP 1 716' SEE CALC SEE CALC RMI SEE CALC 2503.-80 x x COLD LEG Item 102 55.34 6 LOOP 1 716' SEE CALC SEE CALC RMI SEE CALC 1992.24 x x x BORON INJECTION Item 103 1.40 6 LOOP 1 716' 1.90 5.65 RMI 2.55 50.35 x x x BORON INJECTION Item 104 1.51 6 LOOP 1 716' 1.90 0.96 RMI 7.6 54.44 x x x ACCUMULATOR INJECTION Item 105 0.47 6 LOOP 1 716' 10.75 2.36 RMI 0.795 17.01 x x x ACCUMULATOR INJECTION Item 106 15.53 6 LOOP 1 716' 10.75 16.42 RMI 3.125 559.17 x x x ACCUMULATOR INJECTION Item 108 21.81 6 LOOP 1 716' 10.75 5.09 RMI 9.635 785.18 x x x ACCUMULATOR INJECTION Item 109 1.29 6 LOOP 1 716' 10.75 0.57 RMI 6.126 46.28 x x x LOWHEAD SAFETY INJECTION Item 110 4.34 6 LOOP 1 716' 6.63 7.94 RMI 2.6875 a a x____________

__________

_____ _________

_____156.07

___ _______

ALION-CAL-TVA-2739-03 Revision 3 Appendix 2 2-3 of 2-7 RESIDUAL HEAT REMOVAL Item 111 2.90 6 LOOP 1 716' 6.63 3.50 RMI 3.6875 104m53 x x RESIDUAL HEAT REMOVAL Item 112 0.23 6 LOOP 1 716' 6.63 2.09 RMI 0.6875 8.25 x X RESIDUAL HEAT REMOVAL Item 113 7.48 6 LOOP 1 716' 6.63 2.17 RMI 9.6875 269.33 x x RESIDUAL HEAT REMOVAL Item 114 102.56 6 LOOP 1 716' 8.63 26.50 RMI 9.6875 3692.28 x 2925.96 x Loop 2 -21 ft NORMAL CHARGING Item 116 20.44 6 LOOP 1 716' 3.50 54.50 RMI 2.75 735.70 x x x NORMAL CHARGING Item 117 0.15 6 LOOP 1 716' 3.50 0.89 RMI 1.5 5.24 x X x NORMAL CHARGING Item 118 0.60 6 LOOP 1 716' 3.50 2.50 RMI 2 21.60 x X X STEAM GENERATOR Item 119 11.76 6 LOOP 1 716' 3.50 41.67 RMI 2.25 X X B L O W D O W N 1 4 2 3 .4 1 'STEAM GENERATOR Item 120 9.53 6 LOOP 1 716' 4.50 28.75 RMI 2.25 3 X BLOWDOWN 1 342.94 STEAM GENERATOR Item 121 0.26 6 LOOP 1 716' 4.50 3.01 RMI 0.75 x x BLOWDOWN 9.31 STEAM GENERATOR Item 122 0.20 6 LOOP 1 716' 1.35 0.59 RMI 3.325 x x BLOWDOWN 7.20 STEAM GENERATOR Item 123 0.41 6 LOOP 1 716' 1.33 1.22 RMI 3.335 x x BLOWDOWN 14.91 STEAM GENERATOR Item 124 0.14 6 LOOP 1 716' 1.31 0.75 RMI 2.345 x x SLOWDOWN 5.05 STEAM GENERATOR Item 125 0.38 6 LOOP 1 716' 1.30 1.13 RMI 3.35 x C BLOWDOWN 13.831 STEAMOG N Item 126 0.06 6 LOOP 1 716' 2.91 0.29 RMI 2.045 2.31 X X BSLOWDOWN GENER 3" ALTERNATE CHARGING Item 128 16.53 6 LOOP 1 716' 3.50 44.09 RMI 2.75 595.17 x x x STEAM GENERATOR Item 130 215.60 7 LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC 7761.60 X _STEAM GENERATOR Item 131 0.67 7 LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC 24.12 x X PRESSURIZER SURGE LINE Item 135 62.48 7 LOOP 2 716' 14.00 34.40 RMI 4.5 2249.22 x x X PRESSURIZER SURGE LINE Item 136 1.21 7 LOOP 2 716' 14.00 7.67 RMI 0.5 43.67 x x x PRESSURIZER SURGE LINE Item 137 1.09 7 LOOP 2 716' 14.00 3.34 RMI 1 39.35 x x x PRESSURIZER SURGE LINE Item 138 2.71 7 LOOP 2 716' 14.00 3.01 RMI 2.5 97.52 x x x PRESSURIZER SURGE LINE Item 139 4.40 7 LOOP 2 716' 14.00 8.67 RMI 1.5 158.32 x x X FEEDWATER Item 140 18.67 7 LOOP 2 716' 16.00 18.50 RMI 2.5 672.01 544.87 x x Loop 1 -15ft FEEDWATER Item 141 0.63 7 LOOP 2 716' 16.00 0.80 RMI 2 22.62 x x FEEDWATER Item 143 1.95 7 LOOP 2 716' 16.00 10.84 RMI 0.5 7024 x X FEEDWATER Item 144 0.42 7 LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC 15.12 x x FEEDWATER Item 145 0.27 7 LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC 9.72 x x 4" PRESSURIZER SPRAY LINE Item 147 14.21 7 LOOP 2 716' 4.50 32.67 RMI 2.75 511.58 x X x 4" PRESSURIZER SPRAY LINE Item 148 2.51 7 LOOP 2 716' 4.50 1.21 RMI 7,75 90.22 x x X BYPASSUINE Item 149 0.11 7 LOOP 2 716' 1.05 0.42 RMI 2.975 x X X BYPASS LINE 3.95 314" PRESSURIZER SPRAY 3/"PESRZRSRY Item 150 0.68 7 LOOP 2 716' 1.05 8.42 RMI 1.475 263 X x C BYPASS LINE 24.63___ _ _ _ _ _ __ _ _ _ _ _ _ _ _ __ _ _ __ __ _ _ _ _ _HOT LEG Item 151 74.60 7 LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC 2685.60 x x HOT LEG Item 152 8.15 7 LOOP 2 716' SEECALC SEECALC RMI SEE CALC 293.40 x x COLD LEG Item 153 55.42 7 LOOP 2 716' SEE CALC SEE CALC RMI SEE CALC 1995.12 x x x BORON INJECTION Item 154 0.98 7 LOOP 2 716' 1.90 3.94 RMI 2.55 35.11 x x x BORON INJECTION Item 155 1.70 7 LOOP 2 716' 1.90 1.08 RMI 7.6 61.24 x x x ACCUMULATOR INJECTION Item 156 16.79 7 LOOP 2 716' 10.75 17.75 RMI 3.125 604.47 x x x ACCUMULATOR INJECTION Item 157 21.31 7 LOOP 2 716' 10,75 4.98 RMI 9.625 767.04 x x x _ACCUMULATOR INJECTION Item 158 0.15 7 LOOP 2 716' 10.75 0.96 RMI 0.625 5.36 x x x ACCUMULATOR INJECTION Item 159 0.54 7 LOOP 2 716' 10.75 1.24 RMI 1.625 19.58 x x x LOWHEAD SAFETY INJECTION Item 160 5.32 7 LOOP 2 716' 6.63 9.75 RMI 2.6875 191.65 x x x RESIDUAL HEAT REMOVAL Item 161 7.94 7 LOOP2 716' 8.63 31.25 RMI 1.1875 285.99 192.19 x x Loop 1 -21 ft NORMAL CHARGING Item 163 10.09 7 LOOP 2 716' 350 26.92 RMI 2.75 363.39 x x X NORMAL CHARGING Item 164 0.08 7 LOOP 2 716' 3.50 1.92 RMI 0.5 3.02 x x x ALION-CAL-TVA-2739-03 Revision 3 Appendix 2 2-4 of 2-7 NORMAL CHARGING Item 165 0.08 7 LOOP 2 716' 3.50 0.84 RMI 1 2.97 x x x NORMAL CHARGING Item 166 0.22 7 LOOP 2 716' 3.50 3.17 RMI 0.75 7.94 x x x EXCESS LETDOWN Item 167 7.41 7 LOOP 2 716' 1.32 39.67 RMI 2.34 266.84 x x x EXCESS LETDOWN Item 169 0.86 7 LOOP 2 716' 1.32 6.75 RMI 1.84 30.82 x x x EXCESS LETDOWN Item 170 0.02 7 LOOP 2 716' 1.32 0.59 RMI 0.84 0.84 x x x STEAM GENERATOR BLOWDOWN Item 171 9.95 7 -LOOP 2 716' 3.50 35.25 RMI 2.25 3510 X x STEAM GENERATOR S LE WDOWN Item 172 9.47 7 LOOP 2 716' 4.50 28.59 RMI 2.25 x X BLOWDOWN I1341.031 STEAM GENERATOR Item 173 0.55 7 LOOP 2 716' 4.50 3.50 RMI 1.25 x x BLOWDOWN 1 19.76 STEAM GENERATOR Item 174 0.43 7 LOOP 2 716' 1.31 1.67 RMI 2.845 x x BLOWDOWN t5.5 STEAM GENERATOR Item 176 0.14 7 LOOP 2 716' 1.31 0.73 RMI 2.345 x x BLOWDOWN 4.91 STEAM GENERATOR Item 176 0.20 7 LOOP 2 716' 1.31 0.59 RMI 3.345 x X x BLOWDOWN 7.221 STEAM GENERATOR B L W O NIte m 177 0 .0 6 7 LO O P 2 7 16' 2.88 0 .28 R M I 2 .06 2 .2 Xx LETDOWN LINE Item 180 1.56 7 LOOP 2 716' 3.50 2.17 RMI 4.25 56.16 x x LETDOWN LINE Item 181 22.73 7 LOOP 2 716' 3.50 47.50 RMI 3.25 818.28 473.74 x x Loop 1 -27.5 ft LETDOWN LINE Item 182 1.21 7 LOOP 2 716' 3.50 4.29 RMI 2.25 43.56 x x x LETDOWN LINE Item 183 0.51 7 LOOP 2 716' 3.50 3.09 RMI 1.5 18.36 x x x 3" ALTERNATE CHARGING Item 185 9.41 7 LOOP 2 716' 3.50 25.09 RMI 2.75 338.69 x x x 3" ALTERNATE CHARGING Item 186 0.05 7 LOOP 2 716' 3.50 1.25 RMI 0.5 1.96 x x x 3" ALTERNATE CHARGING Item 187 0.21 7 LOOP 2 716' 3.50 3.04 RMI 0.75 7.61 x x x STEAM GENERATOR Item 188 215.60 8 LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC 7761.60 x x STEAM GENERATOR Item 189 0.62 8 LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC 22.32 x x FEEDWATER Item 190 19.60 8 LOOP 3 716' 16.00 19.42 RMI 2.5 705.42 x x FEEDWATER Item 191 0.86 8 LOOP 3 716' 16.00 1.09 RMI 2 30.82 x x FEEDWATER Item 192 1.14 8 LOOP 3 716' 16.00 6.34 RMI 0.5 41.08 x x FEEDWATER Item 193 0.35 8 LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC 12.60 x9 FEEDWATER Item 194 0.24 8 LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC 8.64 X x LETDOWN LINE Item 196 18.43 8 LOOP 3 716' 3.50 38.50 RMI 3.25 663.34 x x HOT LEG Item 197 49.89 8 LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC 1796.04 x x COLD LEG Item 198 54.98 8 LOOP 3 716' SEE CALC SEE CALC RMI SEE CALC 1979.28 x x BORON INJECTION Item 199 1.29 8 LOOP 3 716' 1.90 5.20 RMI 2.55 46.34 x x BORON INJECTION Item 200 1.51 8 LOOP 3 716' 1.90 0.96 RMI 7.6 54.44 x x ACCUMULATOR INJECTION Item 201 16.32 8 LOOP 3 716' 10.75 17.25 RMI 3.125 587.44 x x ACCUMULATOR INJECTION Item 202 22.16 8 LOOP 3 716' 10.75 5.18 RMI 9.625 797.84 x x ACCUMULATOR INJECTION Item 203 0.17 8 LOOP 3 716' 10.75 1.07 RMI 0.625 5.97 x x ACCUMULATOR INJECTION Item 204 0.17 8 LOOP 3 716' 10.75 1.82 RMI 0.375 5.96 x x LOWHEAD SAFETY INJECTION Item 205 1.38 8 LOOP 3 716' 6.63 2.53 RMI 2.6875 C x LOWHEAD SAFETY INJECTION Item 206 0.47 8 LOOP 3 716' 6.63 4.26 RMI 0.6875 16.82 C x RESIDUAL HEAT REMOVAL Item 207 1.55 8 LOOP 3 716' 8.63 6.09 RMI 1.1875 55.73 x x RESIDUAL HEAT REMOVAL Item 208 7.48 8 LOOP 3 716' 6.63 2.17 RMI 9.6875 269.33 x x RESIDUAL HEAT REMOVAL Item 209 0.41 8 LOOP 3 716' 6.63 3.75 RMI 0.6875 14.81 x x RESIDUAL HEAT REMOVAL Item 210 2.22 8 LOOP 3 716' 6.63 2.67 RMI 3.6875 79.74 x x EXCESS LETDOWN Item 211 8.00 8 LOOP 3 716' 1.32 42.84 RMI 2.34 288.16 x x EXCESS LETDOWN Item 212 0.16 8 LOOP 3 716' 1.32 0.63 RMI 2.84 5.85 x x EXCESS LETDOWN Item 213 0.78 8 LOOP 3 716' 1.32 6.17 RMI 1.84 28.18 x x EXCESS LETDOWN Item 214 0.10 8 LOOP 3 716' 1.05 0.78 RMI 1.975 3.66 x x EXCESS LETDOWN Item 215 0.09 8 LOOP 3 716' 1.05 0.46 RMI 2.475 3.15 x x ALION-CAL-TVA-2739-03 Revision 3 Appendix 2 2-5 of 2-7 STEAM GENERATOR Item 216 12.68 8 LOOP 3 716' 3.50 44.92 RMI 2.25 x X BLOWDOWN _ 1 456.44 STEAM GENERATOR STEAM G N Item 217 7.10 8 LOOP 3 716' 450 21.42 RMI 2.25 255.50 X X BLOWDOWN 255_________________50____

__STEAM GENERATOR STEAM G N Item 218 0.50 8 LOOP 3 716' 4.50 3.17 RMI 1.25 x x BLOWDOWN ________________

______ 17.89 _______STEAMIENERATOR Item 219 0.45 8 LOOP 3 716' 1.31 1.75 RMI 2.845 x x BLOWDOWN 16.25____STEAM GENERATOR STEAMGEN Item 220 0.14 8 LOOP 3 716' 1.31 0.75 RMI 2.345 5.05 X x BLOWDOWN 5_______ ___ ______________5_

______STEAM GENERATOR STEAMGEN Item 221 0.38 8 LOOP 3 716' 1.31 1.11 RMI 3.345 1357 X X B LOWDOWN 13___ ___ ____ ___57 ______ __STEAM GENERATOR STEAM G N Item 222 0.06 8 LOOP 3 716' 2.88 0.28 RMI 2.06 x x BLOWDOWN ____2.24 _______STEAM GENERATOR Item 223 215.60 9 LOOP4 716' SEE CALC SEE CALC RMI SEE CALC 7761.60 x X STEAM GENERATOR Item 224 0.58 9 LOOP 4 716' SEE CALC SEE CALC RMI SEE CALC 20.88 x x FEEDWATER Item 225 20.25 9 LOOP4 716' 16.00 20.07 RMI 2.5 729.04 x x FEEDWATER Item 226 1.22 9 LOOP4 716' 16.00 6.78 RMI 0.5 43.93 x x FEEDWATER Item 227 0.35 9 LOOP4 716' SEE CALC SEE CALC RMI SEE CALC 12.60 x x FEEDWATER Item 228 0.14 9 LOOP 4 716' SEE CALC SEE CALC RMI SEE CALC 5.04 x x HOT LEG Item 230 72.51 9 LOOP 4 716' SEE CALC SEE CALC RMI SEE CALC 2610.36 x x COLD LEG Item 231 54.86 9 LOOP 4 716' SEE CALC SEE CALC RMI SEE CALC 1974.96 x x BORON INJECTION Item 232 1.10 9 LOOP4 716' 1.90 4.45 RMI 2.55 39.66 x X BORON INJECTION Item 233 1.42 9 LOOP4 716' 1.90 0.90 RMI 7.6 51.04 x x ACCUMULATOR INJECTION Item 234 24.83 9 LOOP 4 716' 10.75 26.25 RMI 3.125 893.93 x x ACCUMULATOR INJECTION Item 235 23.19 9 LOOP4 716' 10.75 5.42 RMI 9.625 834.81 X X LOWHEAD SAFETY INJECTION Item 236 1.43 9 LOOP4 716' 6.63 7.04 RMI 1.1875 x x STEAM GENERATOR Item 239 9.95 9 LOOP 4 716' 3.50 35.25 RMI 2.25 X X BLOWDOWN 358.18 STEAM GENERATOR STEAM G N Item 240 12.21 9 LOOP4 716' 4.50 36.84 RMI 2.25 X X B LOWDOWN ___39_____44__

STEAM GENERATOR STEAM G N Item 241 0.12 9 LOOP 4 716' 4.50 0.79 RMI 1.25 4.46 X X STEAM GENERATOR Item 242 0.42 9 LOOP 4 716' 1.32 1.63 RMI 2.84 1.2 X X BLOWDOWN 15.121 STEAM GENERATOR STEAM G N Item 243 0.14 9 LOOP 4 716' 1.32 0.75 RMI 2.34 x x BLOWDOWN 1____ _______ ____5.04_2__

STEAM GENERATOR BLOWDOWN Item 24 0.20 9 LOOP 4 716' 1.32 0.59 RMI 3.34 7.21 X X STEAM GENERATOR Item 245 0.10 LOOP 4 716' 2.88 0.34 RMI 2.56 x x BLOWDOWN 7.21_ ___ ____Item 245 0.10 9 LOOP 4 716' 2.88 3.34 RM 2.6xx 3" ALTERNATE CHARGING Item 246 24.65 9 LOOP 4 716' 3.50 65.75 RMI 2.75 887.56 x X 3- ALTERNATE CHARGING Item 247 0.66 9 LOOP 4 716' 3.50 2.34 RMI 2.25 23.78 x X 3" ALTERNATE CHARGING Item 248 4.39 9 LOOP 4 716' 3.50 2.91 RMI 6.75 158.13 x X MAIN STEAM Item 249 171.24 10 LOOP 1 745' 32.00 63.17 RMI 3.5 2220.08 4098.60 Below745 22.75ft_ 6164.491 In Loop 4 ZOI = 42 ft MAIN STEAM Item 251 3.10 10 LOOP 1 745' 32.00 2.83 RMI 1.5 111.69 x x MAIN STEAM Item 252 1.48 10 LOOP 1 745' SEE CALC SEE CALC RMI SEE CALC 53.28 MAIN STEAM Item 253 0.34 10 LOOP 1 745' SEE CALC SEE CALC RMI SEE CALC 12.24 MAIN STEAM Item 254 1.34 10 LOOP 1 745' SEE CALC SEE CALC RMI SEE CALC 48.24 STEAM GENERATOR Item 255 451.03 10 LOOP 1 745' SEE CALC SEE CALC RMI SEE CALC 12989.66 811884 Loop 1 -80%16237.08 Loop 4 -50%AUXLILIARY FEEDWATER Item 256 4.24 10 LOOP 1 745' 6.63 3.17 RMI 5.1875 152.56 x _AUXLILIARY FEEDWATER Item 257 32.21 10 LOOP 1 745' 6.63 59.00 RMI 2.6875 1159.73 x 265.36 below 745 = 13.5 ft ALION-CAL-TVA-2739-03 Revision 3 Appendix 2 2-6 of 2-7 AUXLI AUXLI Item 258 1.10 10 LOOP 1 745' 6.63 3.01 RMI 2.8125 39.60 x X Item 259 044 10 LOOP 1 745' &663 1.43 RMI 1.6875 15.75 x X AUXLILIARY I-EEDWATER I Item 260 1 0.31 10 I LOOP 1 I 745' 1 131 1.20 RMI 2845 11.14 X X MAIN STEAM Item 265 182.97 11 LOOP 2 745' 32.00 67.50 RMI 3.5 448894Below 745 = 22.75 ft M 6587.04 In Loop 4 ZOI = 46 ft MAIN STEAM Item 266 3.01 11 LOOP 2 745' 32.00 2.75 RMI 1.5 108.53 x x MAIN STEAM Item 267 1.63 11 LOOP 2 745' SEE CALC SEE CALC RMI SEE CALC 58.68 MAIN STEAM Item 268 0.37 11 LOOP 2 745' SEE CALC SEE CALC RMI SEE CALC 13.32 MAIN STEAM Item 269 1.41 11 LOOP 2 745' SEE CALC SEE CALC RMI SEE CALC 50.76 STEAM GENERATOR Item 270 451.03 11 LOOP 2 745' SEE CALC SEE CALC RMI SEE CALC 12989.66 8118.54 Loop 3 -50%1 16237.08 18.4Loop 2 -80%AUXLILIARY FEEDWATER Item 271 4.68 11 LOOP 2 1 745' 6.63 3.50 RMI 5.1875 168.44 x AUXLILIARY FEEDWATER Item 272 1.89 11 LOOP 2 745' 6.63 2.28 RMI 3.6875 68.10 x AUXLILIARY FEEDWATER Item 273 27.69 11 LOOP 2 745' 6.63 50.72 RMI 2.6875 996.97 x 245.71 below 745 = 12.5 ft AUXLILIARY FEEDWATER Item 274 0.64 11 LOOP 2 745' 6.63 2.10 RMI 1.6875 23.14 X x AUXLILIARY FEEDWATER Item 276 8.24 11 LOOP 2 745' 6.63 15.09 RMI 2.6875 296.62 x AUXLILIARY FEEDWATER Item 277 11.35 11 LOOP 2 745' 4.50 26.09 RMI 2.75 408.54 x 313.18 below 745 = 20 ft AUXLILIARY FEEDWATER Item 278 4.71 11 LOOP 2 745' 4.50 2.84 RMI 6.75 169.38 x x AUXLILIARY FEEDWATER Item 279 0.08 11 LOOP 2 745' 1.31 0.45 RMI 2.345 3.03 X X AUXLILIARY FEEDWATER Item 280 0.29 11 LOOP 2 745' 1.31 1.11 RMI 2.847 10.32 x x Below 745 = 22.75 ft MAIN STEAM Item 281 180.80 12 LOOP 3 745' 32.00 66.70 RMI 3.5 2220.08 4391.36 Inloo 3 Z 2245 ft 16508.97 In Loop 3 ZOI = 45 ft MAIN STEAM Item 282 3.40 12 LOOP 3 745' 32.00 3.10 Transco RMI 1.5 122.35 x X MAIN STEAM Item 283 1.42 12 LOOP 3 745' SEE CALC SEE CALO RMI SEE CALC 51.12 MAIN STEAM Item 284 0.38 12 LOOP 3 745' SEE CALC SEE CALC RMI SEE CALC 13.68 MAIN STEAM Item 285 1.35 12 LOOP 3 745' SEE CALC SEE CALC RMI SEE CALC 48.60 STEAM GENERATOR Item 286 451.03 12 LOOP 3 745' SEE CALC SEE CALC RMI SEE CALC 8118.54 12989.66 Loop 3 -80%1116237-081 Loop 2 -50%AUXLILIARY FEEDWATER Item 287 4.68 12 LOOP 3 745' 6.63 3.50 RMI 5.1875 168.441 X AUXLILIARY FEEDWATER Item 288 2.22 12 LOOP 3 745' 6.63 2.67 RMI 3.6875 79.74 x AUXLILIARY FEEDWATER Item 289 26.59 12 LOOP 3 745' 6.63 48.70 RMI 2.6875 957.27 255.53 x below 745 -13 ft AUXLILIARY FEEDWATER Item 290 0.92 12 LOOP 3 745' 6.63 3.00 RMI 1.6875 33.05 X AUXLILIARY FEEDWATER Item 291 0.21 12 LOOP 3 745' 6.63 1.92 RMI 0.6875 7.58 x AUXLILIARY FEEDWATER Item 292 10.10 12 LOOP 3 745' 6.63 18.50 RMI 2.6875 363.64 x AUXLILIARY FEEDWATER Item 293 8.92 12 LOOP 3 745' 4.50 20.50 RMI 2.75 321.01 x x AUXLILIARY FEEDWATER Item 294 0.41 12 LOOP 3 745' 4.50 1.72 RMI 1.75 14.78 x x AUXLILIARY FEEDWATER Item 295 6.17 12 LOOP 3 745' 4.50 3.32 RMI 7.25 222.13 x x AUXLILIARY FEEDWATER Item 296 0.41 12 LOOP 3 745' 1.31 2.18 RMI 2.345 14.67 x x MAIN STEAM Item 298 171.02 13 LOOP 4 745' 32.00 63.09 RMI 3.5 2220.08 4098.60 Below 745 = 22.75 ft 6156.68 In Loop 4 ZOI = 42 It MAIN STEAM Item 300 3.48 13 LOOP 4 745' 32.00 3.17 Transco RMI 1.5 125.11 x x MAIN STEAM Item 301 1.45 13 LOOP 4 745' SEE CALC SEE CALC RMI SEE CALC 52.20 MAIN STEAM Item 302 0.35 13 LOOP 4 745' SEE CALC SEE CALC RMI SEE CALC 12260 MAIN STEAM Item 303 1.13 13 LOOP 4 745' SEE CALC SEE CALC RMI SEE CALC 40.68 STEAM GENERATOR Item 304 451.03 13 LOOP 4 745' SEE CALC SEE CALC RMI SEE CALC 8118.54 12989.66 Loop 4 -80%16237.08 Loop 1 -50%AUXLILIARY FEEDWATER Item 305 4.47 13 LOOP 4 745' 6.63 3.34 RMI 5.1875 160.74 x AUXLILIARY FEEDWATER Item 306 26.86 13 LOOP 4 745' 6.63 49.20 RMI 2.6875 967.10 255.53 x below 745-13 ft AUXLILIARY FEEDWATER Item 307 0.99 13 LOOP 4 745' 6.63 3.01 RMI 2.8125 35.64 x x AUXLILIARY FEEDWATER Item 308 0.36 13 LOOP 4 745' 6.63 1.18 RMI 1.6875 13.00 x x AUXLILIARY FEEDWATER Item 309 0.43 13 LOOP 4 745' SEECALC SEECALC RMI SEE CALC 15.48 x x I PRESSURIZER Item 499 449.41 23 PRESSURIZE 729' SEE CALC SEE CALC RMI SEE CALC 16178.76 4666.95 4666.95 4666.95 below 745 -15 ft 6" PRESSURIZER SPRAY LINE Item 500 0.58 23 PRESSURIZE 729' 5.56 0.29 RMI 7.22 21.02 6" PRESSURIZER SPRAY LINE Item 501 0.14 23 PRESSURIZE 729' 5.56 0.38 RMI 2.22 5.15 6"PRESSURIZER SPRAYLINE Item52 0.34 23 PRESSURIZE 729' 4.50 0.79 RMI 2.75 12.37 6" PRESSURIZER SPRAY LINE Item 503 26.96 23 PRESSURIZE 729' 6.62 49.34 RMI 2.69 970.49 242.62 242w62 242.62 below 745- 13 ft ALION-CAL-TVA-2739-03 Revision 3 Appendix 2 2-7 of 2-7 6" PRESSURIZER SPRAY LINE Item 504 0.24 23 PRESSURIZE 729' 6.62 0.65 RMI 2 8.80 x x x 6" PRESSURIZER SPRAY LINE Item 505 0.27 23 PRESSURIZE 729' 105 1.05 RMI 2975 9.87 x X X 3"AUXILIARY SPRAY LINE Item 506 6.28 23 PRESSURIZE 729' 3.50 16.75 RMI 2.75 226.11 x X X 3" AUXILIARY SPRAY LINE Item 508 0.09 23 PRESSURIZE 729' 3.50 1.30 RMI 0.75 3.25 x x x 3"AUXILIARY SPRAY LINE Item 509 194 23 PRESSURIZE 729- 3.50 1.46 RMI 6.25 69.88 x x X 3/4" INSTRUMENTATION Item 511 3.83 23 PRESSURIZE 729' 1.05 5.84 RMI 4.98 137.74 x x x 3/4" INSTRUMENTATION Item 512 0.64 23 PRESSURIZE 729' 1.05 1.46 RMI 3.98 22.96 x x x PRESSURE RELIEF Item 513 5.37 23 PRESSURIZE 729' 6.63 9.84 RMI 2.6875 193.42 1 1 PRESSURE RELIEF Item 514 3.79 23 PRESSURIZE 729' 3.50 2.67 RMI 6.5 136.311 PRESSURE RELIEF Item 515 1.60 23 PRESSURIZE 729' 3.50 4.27 RMI 2.75 57.64 PRESSURE RELIEF Item 516 0.68 23 PRESSURIZE 729' 12.00 1.11 RMI 2 24.41 PRESSURE RELIEF Item 517 0.99 23 PRESSURIZE 729' 3.50 1.67 RMI 3.75 35.66 PRESSURE RELIEF Item 518 0.18 23 PRESSURIZE 729' 3.50 0.64 RMI 2.25 6.50 PRESSURE RELIEF Item 519 0.78 23 PRESSURIZE 729' 12.00 1.11 RMI 2.25 27.95 PRESSURE RELIEF Item 520 0.52 23 PRESSURIZE 729' 1.06 1.98 RMI 2.97 18.61 Watts Bar Reactor Building GSI-191 Debris Generation Calculation

' I' 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 3-1 of 3-20 APPENDIX 3 -DEBRIS SOURCE

SUMMARY

SHEETS This Appendix contains a summary spreadsheet and the debris source worksheets for each of the 4 break locations.

The line item column provides a reference back to Appendix 1, which can be used as a reference back to the Enercon provided Watts Bar insulation spreadsheet in Attachment A.

ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-2 of 3-20 c~~~eblis

~~~ ~ & G~~to eut _________

ae 1il. ase ?= M[_asel3 Case 4'Debris Type Debris Size Debris Quantity Debris Quantity Debris Debris Small Pieces (<4") 75901.59 ft 2 75219.51 ft 2 63864.92 ft 2 63482.95 ft 2 Stainless Steel RMI (ft 2) Large Pieces (>4") 25300.53 ft 2 25073.17 ft 2 21288.31 ft 2 21160.98 ft 2 Total 101202.12 ft 2 100292.68 ft 2 85153.23 ft 2 84643.93 ft 2 3M-M20C Individual Fibers/Particulate 5.87 ft 3 8.45 ft 3 1.67 ft 3 1.67 ft 3 Min-K -Fiber Fines 4.03 lb 6.30 lb 2.56 lb 6.35 lb Min-K -Si02 Fines 13.10 lb 20.46 lb 8.32 lb 20.63 lb Min-K -TiO2 Fines 3.02 lb 4.72 lb 1.92 lb 4.76 lb I Total 20.16 lb 31.48 lb 12.80 lb 31.74 lb ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-3 of 3-20 IBreak Description I Case I Loop 1 Crossover Leg at base of steam generator Debris Gen6ration Results Debris Type Debris Size Debris Quantity Small Pieces (<4") 75901.59 ft2 Stainless Steel RMI (ft 2) Large Pieces (>4") 25300.53 ft 2 Total 101202.12 ft2 3M-M20C Individual Fibers/Particulate 5.87 ft 3 Min-K Fines 1.26 ft 3 Debris Generation Inventory:

_______....__________________.....

.Debris Type linventory Detaiis I I uantit I ines I mall Large Intact.-- --p y ~ -Y I p -5.79E+0O 1 .45E+00 3/4" PRESSURIZER SPRAY BYPASS LINE Item 100 5.79E+00 4.34E+00 1.45E+00 HOT LEG Item 101 ft' 2.50E+03 1.88E+03 6.26E+02 COLD LEG Item 102 f 1.99E+03 1.49E+03 4.98E+02 BORON INJECTION Item 103 Ft 3 5.04E+01 3.78E+01 1.26E+01 BORON INJECTION Item 104 f 5.44E+01 4.08E+01 1.36E+01 ACCUMULATOR INJECTION Item 105 7f 1.70E+01 1.28E+01 4.25E+00 ACCUMULATOR INJECTION Item 106 ft' 5.59E+02 4.19E+02 1.40E+02 ACCUMULATOR INJECTION Item 108 ft* 7.85E+02 5.89E+02 1.96E+02 ACCUMULATOR INJECTION Item 109 4.63E+01 3.47E+01 1.16E+01 LOWHEAD SAFETY INJECTION Item 110 ftF 1.56E+02 1.17E+02 3.90E+01 RESIDUAL HEAT REMOVAL Item 111 '7' 1.05E+02 7.84E+01 2.61E+01 RESIDUAL HEAT REMOVAL Item 112 It' 8.25E+00 6.19E+00 2.06E+00 RESIDUAL HEAT REMOVAL Item 113 ft' 2.69E+02 2.02E+02 6.73E+01 RESIDUAL HEAT REMOVAL Item 114 ftV 3.69E+03 2.77E+03 9.23E+02 Item 116 ft' 7.36E+02 5.52E+02 1.84E+02 NORMAL CHARGING Item 117 7t 5.24E+00 3.93E+00 1.31E+00 NORMAL CHARGING Item 118 ftF 2.16E+01 1.62E+01 5.40E+00 STEAM GENERATOR BLOWDOWN Item 119 ft* 4.23E+02 3.18E+02 1.06E+02 STEAM GENERATOR BLOWDOWN Item 120 7t 3.43E+02 2.57E+02 8.57E+01 STEAM GENERATOR BLOWDOWN Item 121 ftV 9.31E+00 6.98E+00 2.33E+00 STEAM GENERATOR BLOWDOWN Item 122 tV 7.20E+00 5.40E+00 1.80E+00 STEAM GENERATOR BLOWDOWN Item 123 tV 1.49E+01 1.12E+01 3.73E+00 STEAM GENERATOR BLOWDOWN Item 124 ftV 5.05E+00 3.79E+00 1.26E+00 STEAM GENERATOR BLOWDOWN Item 125 ft- 1.38E+01 __1.04E+01 3.46E+00 ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-4 of 3-20 Debris Type lInventory Details Quantity I ines I mall large ntac I- Y 'p -I I I -U -I STEAM GENERATOR BLOWDOWN Item 126 ft, 2.31 E+00 1.73E+00 5.77E-01 3" ALTERNATE CHARGING Item 128 ftý 5.95E+02 4.46E+02 1.49E+02 PRESSURIZER SURGE LINE Item 135 ftK 2.25E+03 1.69E+03 5.62E+02 PRESSURIZER SURGE LINE Item 136 f 4.37E+01 3.28E+01 1.09E+01 PRESSURIZER SURGE LINE Item 137 ft 3.93E+01 2.95E+01 9.84E+00 PRESSURIZER SURGE LINE Item 138 ft' 9.75E+01 7.31E+01 2.44E+01 PRESSURIZER SURGE LINE Item 139 ft' 1.58E+02 1.19E+02 3.96E+01 FEEDWATER Item 140 F 5.45E+02 4.09E+02 1.36E+02 4" PRESSURIZER SPRAY LINE Item 147 ft 5.12E+02 3.84E+02 1,28E+02 4" PRESSURIZER SPRAY LINE Item 148 ft 9.02E+01 6.77E+01 2.26E+01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 149 ft 3.95E+00 2.96E+00 9.87E-01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 150 ft' 2.46E+01 1.85E+01 6.16E+00 COLD LEG Item 153 ft 2.00E+03 1.50E+03 4.99E+02 BORON INJECTION Item 154 ft" 3.51E+01 2.63E+01 8.78E+00 BORON INJECTION Item 155 ft 6.12E+01 4.59E+01 1,53E+01 ACCUMULATOR INJECTION Item 156 ft 6.04E+02 4.53E+02 1.51E+02 ACCUMULATOR INJECTION Item 157 ft' 7.67E+02 5.75E+02 1.92E+02 ACCUMULATOR INJECTION Item 158 ft7 5.36E+00 4.02E+00 1.34E+00 ACCUMULATOR INJECTION Item 159 f 1.96E+01 1.47E+01 4.90E+00 LOWHEAD SAFETY INJECTION Item 160 F 1.92E+02 1.44E+02 4.79E+01 RESIDUAL HEAT REMOVAL Item 161 ft 1.92E+02 1.44E+02 4.80E+01 NORMAL CHARGING Item 163 ftz 3.63E+02 2.73E+02 9.08E+01 NORMAL CHARGING Item 164 f 3.02E+00 2.26E+00 7.54E-01 NORMAL CHARGING Item 165 ft' 2.97E+00 2.23E+00 7.42E-01 NORMAL CHARGING Item 166 f 7.94E+00 5.95E+00 1.98E+00 EXCESS LETDOWN Item 167 f 2.67E+02 2.00E+02 6.67E+01 EXCESS LETDOWN Item 169 ft' 3.08E+01 2.31E+01 7.71E+00 EXCESS LETDOWN Item 170. ft' 8.41E-01 6.31E-01 2.10E-01 LETDOWN LINE Item 181 f 4.74E+02 3.55E+02 1.18E+02 LETDOWN LINE Item 182 ft' 4.36E+01 3.27E+01 1.09E+01 LETDOWN LINE Item 183 f 1.84E+01 1.38E+01 4.59E+00 3" ALTERNATE CHARGING Item 185 f 3.39E+02 2.54E+02 8.47E+01 3" ALTERNATE CHARGING Item 186 ft' 1.96E+00 1.47E+00 4.91E-01 3" ALTERNATE CHARGING Item 187 f 7.61E+00 5.71E+00 1.90E+00 STEAM GENERATOR Item 223 f 7.76E+03 5.82E+03 1.94E÷03 STEAM GENERATOR Item 224 f 2.09E+01 1.57E+01 5.22E+00 FEEDWATER Item 225 f 7.29E+02 5.47E+02 1.82E+02 FEEDWATER Item 226 ft' 4.39E+01 3.29E+01 1.10E+01 FEEDWATER Item 227 ftz 1.26E+01 9.45E+00 3.15E+00 FEEDWATER Item 228 ft- 5.04E+00 3.78E+00 1.26E+00 ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-5 of 3-20 Debris Type Inventory Details Quantity I ines I mall Large Intact F p q q Y -W -q.HOT LEG Item 230 ft' I 2.61E+03 1.96E+03 6.53E+02 Stainless Steel RMI (ft2)COLD LEG Item 231 ft? 1.97E+03 1.48E+03 4.94E+02 BORON INJECTION Item 232 F 3.97E+01 2.97E+01 9.91E+00 BORON INJECTION Item 233 F 5.10E+01 3.83E+01 1.28E+01 ACCUMULATOR INJECTION Item 234 F 8.94E+02 6.70E+02 2.23E+02 ACCUMULATOR INJECTION Item 235 ft 8.35E+02 6.26E+02 2.09E+02 LOWHEAD SAFETY INJECTION Item 236 ft' 5.13E+01 3.85E+01 1.28E+01 STEAM GENERATOR BLOWDOWN Item 239 ft' 3.58E+02 2.69E+02 8.95E+01 STEAM GENERATOR BLOWDOWN Item 240 ft' 4.39E+02 3.30E+02 1.10E+02 STEAM GENERATOR BLOWDOWN Item 241 ft' 4.46E+00 3.34E+00 1.11E+00 STEAM GENERATOR BLOWDOWN Item 242 ft' 1.51E+01 1.13E+01 3.78E+00 STEAM GENERATOR BLOWDOWN Item 243 ft' 5.04E+00 3.78E+00 1.26E+00 STEAM GENERATOR BLOWDOWN Item 244 ft' 7.21 E+00 5.41E+00 1.80E+00 STEAM GENERATOR BLOWDOWN Item 245 ft 3.72E+00 2.79E+00 9.30E-01 3" ALTERNATE CHARGING Item 246 f7 8.88E+02 6.66E+02 2.22E+02 3" ALTERNATE CHARGING Item 247 F7 2.38E+01 1.78E+01 5.94E+00 3" ALTERNATE CHARGING Item 248 ft' 1.58E+02 1.19E+02 3.95E+01 MAIN STEAM Item 249 F7 2.22E+03 1.67E+03 5.55E+02 MAIN STEAM Item 251 ft 1.12E+02 8.38E+01 2.79E+01 STEAM GENERATOR Item 255 ft 1.30E+04 9.74E+03 3.25E+03 AUXLILIARY FEEDWATER Item 256 ft 1.53E+02 1.14E+02 3.81E+01 AUXLILIARY FEEDWATER Item 257 ft' 1.16E+03 8.70E+02 2.90E+02 AUXLILIARY FEEDWATER Item 258 Ft 3.96E+01 2.97E+01 9.90E+00 AUXLILIARY FEEDWATER Item 259 7' 1.58E+01 1.18E+01 3.94E+00 AUXLILIARY FEEDWATER Item 260 Ft 1.11E+01 8.36E+00 2.79E+00 MAIN STEAM Item 298 ft 2.22E+03 1.67E+03 5.55E+02 MAIN STEAM Item 300 7't 1.25E+02 9.38E+01 3.13E+01 STEAM GENERATOR Item 304 ft' 8.12E+03 6.09E+03 2.03E+03 AUXLILIARY FEEDWATER Item 306 " 2.56E+02 1.92E+02 6.39E+01 AUXLILIARY FEEDWATER Item 307 ft 3.56E+01 2.67E+01 8.91E+00 RC INTERIM LEG Item 46 " 3.19E+03 2.39E+03 7.98E+02 REACTOR COOLANT PUMP Item 47 f 2.28E+03 1.71 E+03 5.71E+02 INTERIM LEG DRAIN Item 48 'ff 1.63E+01 1.22E+01 4.08E+00 INTERIM LEG DRAIN Item 49 ft' 1.60E+02 1.20E+02 4.01E+01 PRESSURIZER Item 499 ft' 4.67E+03 3.50E+03 1.17E+03 INTERIM LEG DRAIN Item 50 't7 4.68E+00 3.51E+00 1.17E+00 6" PRESSURIZER SPRAY LINE Item 503 ff 2.43E+02 1.82E+02 6.07E+01 6" PRESSURIZER SPRAY LINE Item 504 ftR 8.80E+00 6.60E+00 2.20E+00 6" PRESSURIZER SPRAY LINE Item 505 Ft 9.87E+00 7.41 E+00 2.47E+00 3" AUXILIARY SPRAY LINE Item 506 ft- 2.26E+02 1.70E+02 5.65E+01 ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-6 of 3-20 Debris Type Inventory Details Quantity Pines Small Large In act 3" AUXILIARY SPRAY LINE Item 508 ftz 3.25E+00 2.44E+00 8.1 4E-01 3" AUXILIARY SPRAY LINE Item 509 ft' 6.99E+01 5.24E+01 1.75E+01 INTERIM LEG DRAIN Item 51 ft' 1.90E+00 1.43E+00 4.75E-01 3/4" INSTRUMENTATION Item 511 ft 1.38E+02 1.03E+02 3.44E+01 3/4" INSTRUMENTATION Item 512 ft' 2.30E+01 1.72E+01 5.74E+00 RC INTERIM LEG Item 53 t 3.13E+03 2.34E+03 7.81E+02 REACTOR COOLANT PUMP Item 54 7t' 2.28E+03 1.71E+03 5.71E+02 INTERIM LEG DRAIN Item 55 ft' 1.63E+01 1.22E+01 4.08E+00 INTERIM LEG DRAIN Item 56 -F 1.60E+02 1.20E+02 4.01E+01 RC INTERIM LEG Item 64 'Ft 3.06E+03 2.30E+03 7.65E+02 REACTOR COOLANT PUMP Item 65 -F 2.28E+03 1.71 E+03 5.71E+02 INTERIM LEG DRAIN Item 66 '-F 3.56E+01 2.67E+01 8.89E+00 INTERIM LEG DRAIN Item 67 ft' 1.48E+02 1.11E+02 3.70E+01 RESIDUAL HEAT REMOVAL Item 70 f 1.48E+03 1.11E+03 3.69E+02 RESIDUAL HEAT REMOVAL Item 71 f 5.89E+01 4.42E+01 1.47E+01 RESIDUAL HEAT REMOVAL Item 72 ft 3.96E+01 2.97E+01 9.90E+00 RESIDUAL HEAT REMOVAL Item 73 ft" 3.37E+02 2.53E+02 8.42E+01 RESIDUAL HEAT REMOVAL Item 74 ft' 7.67E+02 5.75E+02 1.92E+02 RESIDUAL HEAT REMOVAL Item 75 ftI 5.26E+02 3.94E+02 1.31E+02 RESIDUAL HEAT REMOVAL Item 76 ft' 3.31E+00 2.48E+00 8.26E-01 RESIDUAL HEAT REMOVAL Item 77 ft 1.51E+01 1.14E+01 3.79E+00 RESIDUAL HEAT REMOVAL Item 78 1.15E+01 8.62E+00 2.87E+00 RESIDUAL HEAT REMOVAL Item 79 t 2.14E+02 1.61 E+02 5.35E+01 STEAM GENERATOR Item 80 fti 7.76E+03 5.82E+03 1.94E+03 STEAM GENERATOR Item 81 ftI 2.38E+01 1.78E+01 5.94E+00 FEEDWATER Item 82 ft' 8.75E+02 6.57E+02 2.19E+02 FEEDWATER Item 83 '7' 6.86E+01 5.15E+01 1.72E+01 FEEDWATER Item 84 f 1.51E+01 1.13E+01 3.78E+00 FEEDWATER Item 85 ft ; 9.36E+00 7.02E+00 2.34E+00 4" PRESSURIZER SPRAY LINE Item 94 f 6.80E+02 5.10E+02 1.70E+02 4" PRESSURIZER SPRAY LINE Item 95 ft' 3.74E+00 2.81E+00 9.35E-01 4" PRESSURIZER SPRAY LINE Item 97 ft 9.02E+01 6.77E+01 2.26E+01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 98 ft' 4.86E+01 3.65E+01 1.22E+01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 71 ttI 1.Z7E+01 9.52E+00 3.17E+00 hfI- -1I 1.29 5EUF2E+00 3 17E+00l 3M-M20C See 3M Appendix ft° 5.87 5.87E+00 Ift- 0.00E+00 ALIO N-CAL-TVA-2739-03 Revision 3 Appendix 3 3-7 of 3-20 lDebris Type inventory IDetails i Quantity I t-ines I Small I Large I Intact Totals ."T-+UO .blt + I 0.00E+00 ACCUMULATOR INJECTION Item 107 0.13 1.30E-01 RESIDUAL HEAT REMOVAL Item 115 Wf 0.08 8.OOE-02 3" ALTERNATE CHARGING Item 129 ft 0.08 8.00E-02 Mn-K AUXLILIARY FEEDWATER Item 258 7f 0.87 8.70E-01 3" AUXILIARY SPRAY LINE Item 507 ft- 0.03 3.OOE-02 AUXLILIARY FEEDWATER Item 275 f 0.07 7.OOE-02 O.OOE+00 Totals I I.:eb t÷U I 1.2 L+uu I ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-8 of 3-20 IBreak Description I Case 2 Loop 2 Crossover Leg at base of steam generator Debris Generation Results Debris Type Debris Size Debris Quantity Small Pieces (<4") 75219.51 ft2 Stainless Steel RMI (ft 2) Large Pieces (>4") 25073.17 ft2 Total 100292.68 ft2 3M-M20C Individual Fibers/Particulate 8.45 ft 3 Min-K Fines 1.97 ft 3 Debris Generation Inventory

___..._ ..._ .. ..____..__.._....__.....

Debris Type Inventory IDetals I I Quantity I ines I mall Large Intact 4i' U 1 , , I U I 3/I4 PRESS~URIZER~

SPR-AY BiYP-ASS~

LINE item 100 IL 0. / lr-tUU"1.45E-+00 COLD LEG Item 102 ft' 1.99E+03 1.49E+03 4.98E+02 BORON INJECTION Item 103 ftF 5.04E+01 3.78E+01 1.26E+01 BORON INJECTION Item 104 TF 5.44E+01 4.08E+01 1.36E+01 ACCUMULATOR INJECTION Item 105 TF 1.70E+01 1.28E+01 4.25E+00 ACCUMULATOR INJECTION Item 106 t 5.59E+02 4.19E+02 1.40E+02 ACCUMULATOR INJECTION Item 108 ft' 7.85E+02 5.89E+02 1.96E+02 ACCUMULATOR INJECTION Item 109 ft 4.63E+01 3.47E+01 1.16E+01 LOWHEAD SAFETY INJECTION Item 110 t 1.56E+02 1.17E+02 3.90E+01 RESIDUAL HEAT REMOVAL Item 114 f 2.93E+03 2.19E+03 7.31 E+02 NORMAL CHARGING Item 116 t 7.36E+02 5.52E+02 1.84E+02 NORMAL CHARGING Item 117 ft' 5.24E+00 3.93E+00 1.31 E+00 NORMAL CHARGING Item 118 7t 2.16E+01 1.62E+01 5.40E+00 3" ALTERNATE CHARGING Item 128 ft 5.95E+02 4.46E+02 1.49E+02 STEAM GENERATOR Item 130 7t 7.76E+03 5.82E+03 1.94E+03 STEAM GENERATOR Item 131 ft 2.41 E+o1 1.81E+01 6.03E+00 PRESSURIZER SURGE LINE Item 135 ft' 2.25E+03 1.69E+03 5.62E+02 PRESSURIZER SURGE LINE Item 136 ft' 4.37E+01 3.28E+01 1.09E+01 PRESSURIZER SURGE LINE Item 137 ftF 3.93E+01 2.95E+01 9.84E+00 PRESSURIZER SURGE LINE Item 138 t 9.75E+01 7.31E+01 2.44E+01 PRESSURIZER SURGE LINE Item 139 t 1.58E+02 1.19E+02 3.96E+01 FEEDWATER Item 140 ft' 6.72E+02 5.04E+02 1.68E+02 FEEDWATER Item 141 ft' 2.26E+01 1.70E+01 5.65E+00 FEEDWATER Item 143 ft- 7.02E+01 5.27E+01 1.76E+01 ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-9 of 3-20 BORON INJECTION Item 104 5.44E+01 4.08E+01 I 1.36E+01 ACCUMULATOR INJECTION Item 105 W 1.70E+01 1.28E+01 4.25E+00 FEEDWATER Item 144 f 1.51 E+01 1.13E+01 3.78E+00 FEEDWATER Item 145 t 9.72E+00 7.29E+00 2.43E+00 4" PRESSURIZER SPRAY LINE Item 147 7' 5.12E+02 3.84E+02 1.28E+02 4" PRESSURIZER SPRAY LINE Item 148 ftP 9.02E+01 6.77E+01 2.26E+01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 149 7' 3.95E+00 2.96E+00 9.87E-01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 150 ft' 2.46E+01 1.85E+01 6.16E+00 HOT LEG Item 151 f 2.69E+03 2.01 E+03 6.71E+02 HOT LEG Item 152 f 2.93E+02 2.20E+02 7.34E+01 COLD LEG Item 153 f 2.OOE+03 1.50E+03 4.99E+02 BORON INJECTION Item 154 IF 3.51E+01 2.63E+01 8.78E+00 BORON INJECTION Item 155 ft' 6.12E+01 4.59E+01 1.53E+01 ACCUMULATOR INJECTION Item 156 ft' 6.04E+02 4.53E+02 1.51E+02 ACCUMULATOR INJECTION Item 157 7ft 7.67E+02 5.75E+02 1.92E+02 ACCUMULATOR INJECTION Item 158 7f 5.36E+00 4.02E+00 1.34E+00 ACCUMULATOR INJECTION Item 159 ftF 1.96E+01 1.47E+01 4.90E+00 LOWHEAD SAFETY INJECTION Item 160 ft' 1.92E+02 1.44E+02 4.79E+01 RESIDUAL HEAT REMOVAL Item 161 _F 2.86E+02 2.14E+02 7.15E+01 NORMAL CHARGING Item 163 7ft 3.63E+02 2.73E+02 9.08E+01 NORMAL CHARGING Item 164 7f 3.02E+00 2.26E+00 7.54E-01 NORMAL CHARGING Item 165 IFt 2.97E+00 2.23E+00 7.42E-01 NORMAL CHARGING Item 166 Wf 7.94E+00 5.95E+00 1.98E+00 EXCESS LETDOWN Item 167 'f7 2.67E+02 2.OOE+02 6.67E+01 EXCESS LETDOWN Item 169 7f 3.08E+01 2.31E+01 7.71E+00 EXCESS LETDOWN Item 170 ft7 8.41E-01 6.31E-01 2.10E-01 STEAM GENERATOR BLOWDOWN Item 171 IfF 3.58E+02 2.69E+02 8.95E+01 STEAM GENERATOR BLOWDOWN Item 172 ft' 3.41E+02 2.56E+02 8.53E+01 STEAM GENERATOR BLOWDOWN Item 173 f 1.98E+01 -E __5_1_1.48E+01 4.94E+00 STEAM GENERATOR BLOWDOWN Item 174 IF 1.55E+01 1.16E+01 3.88E+00 STEAM GENERATOR BLOWDOWN Item 175 IF 4.91E+00 3.69E+00 1.23E+00 STEAM GENERATOR BLOWDOWN Item 176 ft' 7.22E+00 5.41E+00 1.80E+00 STEAM GENERATOR BLOWDOWN Item 177 ft' 2.24E+00 1.68E+00 5.59E-01 LETDOWN LINE Item 180 ft 5.62E+01 4.21E+01 1.40E+01 LETDOWN LINE Item 181 ft 8.18E+02 6.14E+02 2.05E+02 LETDOWN LINE Item 182 ft` 4.36E+01 3.27E+01 1.09E+01 LETDOWN LINE Item 183 ft 1.84E+01 1.38E+01 4.59E+00 3" ALTERNATE CHARGING Item 185 ft' 3.39E+02 2.54E+02 8.47E+01 3" ALTERNATE CHARGING Item 186 ft' 1.96E+00 1.47E+00 4.91E-01 3" ALTERNATE CHARGING Item 187 ftF 7.61E+00 5.71E+00 1.90E+00 STEAM GENERATOR Item 188 ft 7.76E+03 5.82E+03 1.94E+03 STEAM GENERATOR Item 189 ft' 2.23E+01 1.6TE+01 5.58E+00 I AL ION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-10 of 3-20 BORON INJECTION Item 104 5.44E+01 4.08E+01 I 1.36E+01 I Stainless Steel RMI (ft2)ACCUMULATOR INJECTION Item 105 ft' 1.70E+01 1.28E+01 4.25E+00 FEEDWATER Item 190 7' 7.05E+02 5.29E+02 1.76E+02 FEEDWATER Item 191 '7' 3.08E+01 2.31E+01 7.70E+00 FEEDWATER Item 192 f 4.11E+01 3.08E+01 1.03E+01 FEEDWATER Item 193 f 1.26E+01 9.45E+00 3.15E+00 FEEDWATER Item 194 ft' 8.64E+00 6.48E+00 2.16E+00 LETDOWN LINE Item 196 tW 6.63E+02 4.98E+02 1.66E÷02 HOTLEG Item 197 f 1.80E+03 1.35E+03 4.49E+02 COLD LEG Item 198 1.98E+03 1.48E+03 4.95E+02 BORON INJECTION Item 199 ft 4.63E+01 3.48E+01 1.16E+01 BORON INJECTION Item 200 ft' 5.44E+01 4.08E+01 1.36E+01 ACCUMULATOR INJECTION Item 201 ft 5.87E+02 4.41E+02 1.47E+02 ACCUMULATOR INJECTION Item 202 ft' 7.98E+02 5.98E+02 1.99E+02 ACCUMULATOR INJECTION Item 203 ft 5.97E+00 4.48E+00 1.49E+00 ACCUMULATOR INJECTION Item 204 f 5.96E+00 4.47E+00 1.49E+00 LOWHEAD SAFETY INJECTION Item 205 ft' 4.97E+01 3.73E+01 1.24E+01 LOWHEAD SAFETY INJECTION Item 206 '7' 1.68E+01 1.26E+01 4.21E+00 RESIDUAL HEAT REMOVAL Item 207 ft' 5.57E+01 4.18E+01 1.39E+01 RESIDUAL HEAT REMOVAL Item 208 ft' 2.69E+02 2.02E+02 6.73E+01 RESIDUAL HEAT REMOVAL Item 209 f 1.48E+01 1.11E+01 3.70E+00 RESIDUAL HEAT REMOVAL Item 210 ft' 7.97E+01 5.98E+01 1.99E+01 EXCESS LETDOWN Item 211 't' 2.88E+02 2.16E+02 7.20E+01 EXCESS LETDOWN Item 212 f 5.85E+00 4.38E+00 1.46E+00 EXCESS LETDOWN Item 213 f 2.82E+01 2.11E+01 7.04E+00 EXCESS LETDOWN Item 214 7' 3.66E+00 2.74E+00 9.15E-01 EXCESS LETDOWN Item 215 ft' 3.15E+00 2.36E+00 7.88E-01 STEAM GENERATOR BLOWDOWN Item 216 ft' 4.56E+02 3.42E+02 1.14E+02 STEAM GENERATOR BLOWDOWN Item 217 ft' 2.56E+02 1.92E+02 6.39E+01 STEAM GENERATOR BLOWDOWN Item 218 't' 1.79E+01 _E_011.34E+01 4.47E+00 STEAM GENERATOR BLOWDOWN Item 219 F 1.62E+01 1.22E+01 4.06E+00 STEAM GENERATOR BLOWDOWN Item 220 F 5.05E+00 3.79E+00 1.26E+00 STEAM GENERATOR BLOWDOWN Item 221 ft4 1.36E+01 1.02E+01 3.39E+00 STEAM GENERATOR BLOWDOWN Item 222 ft 2.24E+00 1.68E+00 5.59E-01 MAIN STEAM Item 265 'ft 4.49E+03 3.37E+03 1.12E+03 MAIN STEAM Item 266 ft 1.09E+02 8.14E+01 2.71E+01 STEAM GENERATOR Item 270 t 1.30E+04 9.74E+03 3.25E+03 AUXLILIARY FEEDWATER Item 271 ft' 1.68E+02 1.26E+02 4.21E+01 AUXLILIARY FEEDWATER Item 272 t 6.81E+01 5.11E+01 1.70E+01 AUXLILIARY FEEDWATER Item 273 ft 9.97E+02 7.48E+02 2.49E+02 AUXLILIARY FEEDWATER Item 274 ft 2.31E+01 1.74E+01 5.78E+00 AUXLILIARY FEEDWATER Item 276 ft 2.97E+02 2.22E+02 7.42E+01 AL 0 N-CAL-TVA-2739-03 Revision 3 Appendix 3 3-11 of 3-20 BORON INJECTION Item 104 Ft 5.44E+01 4.08E+01 I 1.36E+01 ACCUMULATOR INJECTION Item 105 ft' 1.70E+01 1.28E+01 4.25E+00 AUXLILIARY FEEDWATER Item 277 f 4.09E+02 3.06E+02 1.02E+02 AUXLILIARY FEEDWATER Item 278 f 1.69E+02 1.27E+02 '4.23E+01 AUXLILIARY FEEDWATER Item 279 f 3.03E+00 2.27E+00 7.57E-01 AUXLILIARY FEEDWATER Item 280 ft 1.03E+01 7.74E+00 2.58E+00 MAIN STEAM Item 281 ft' 2.22E+03 1.67E+03 5.55E+02 MAIN STEAM Item 282 f 1.22E+02 9.18E+01 3.06E+01 STEAM GENERATOR Item 286 f 8.12E+03 6.09E+03 2.03E+03 AUXLILIARY FEEDWATER Item 289 ft 2.56E+02 1.92E+02 6.39E+01 AUXLILIARY FEEDWATER Item 293 f7 3.21 E+02 2.41E+02 8.03E+01 AUXLILIARY FEEDWATER Item 294 f 1.48E+01 1.11E+01 3.69E+00 AUXLILIARY FEEDWATER Item 295 f 2.22E+02 1.67E+02 5.55E+01 AUXLILIARY FEEDWATER Item 296 f 1.47E+01 1.10E+01 3.67E+00 AUXLILIARY FEEDWATER Item 308 f 1.30E+01 9.75E+00 3.25E+00 AUXLILIARY FEEDWATER Item 309 fT5 1.55E+01 1.16E+01 3.87E+00 Item 46 ft 3.19E+03 2.39E+03 7.98E+02 REACTOR COOLANT PUMP Item 47 ft' 2.28E+03 1.71E+03 5.71E+02 INTERIM LEG DRAIN Item 48 F 1.63E+01 1.22E+01 4.08E+00 INTERIM LEG DRAIN Item 49 f 1.60E+02 1.20E+02 4.01E+01 PRESSURIZER Item 499 f 4.67E+03 3.50E+03 1.17E+03 INTERIM LEG DRAIN Item 50 f 4.68E+00 3.51E+00 1.17E+00 6" PRESSURIZER SPRAY LINE Item 503 ft' 2.43E+02 1.82E+02 6.07E+01 6" PRESSURIZER SPRAY LINE Item 504 f 8.80E+00 6.60E+00 2.20E+00 6" PRESSURIZER SPRAY LINE Item 505 ft7 9.87E+00 7.41E+00 2.47E+00 3" AUXILIARY SPRAY LINE Item 506 F 2.26E+02 1.70E+02 5.65E+01 3" AUXILIARY SPRAY LINE Item 508 F 3.25E+00 2.44E+00 8.14E-01 3" AUXILIARY SPRAY LINE Item 509 ft' 6.99E+01 5.24E+01 1.75E+01 INTERIM LEG DRAIN Item 51 ft 1.90E+00 1.43E+00 4.75E-01 3/4" INSTRUMENTATION Item 511 Ft7 1.38E+02 1.03E+02 3.44E+01 3/4" INSTRUMENTATION Item 512 ft' 2.30E+01 1.72E+01 5.74E+00 RC INTERIM LEG Item 53 f7 3.13E+03 2.34E+03 7.81E+02 REACTOR COOLANT PUMP Item 54 ft' 2.28E+03 1.71 E+03 5.71E+02 INTERIM LEG DRAIN Item 55 f 1.63E+01 1.22E+01 4.08E+00 INTERIM LEG DRAIN Item 56 f 1.60E+02 1.20E+02 4.01E+01 RC INTERIM LEG Item 58 fT 3.08E+03 2.31 E+03 7.69E+02 INTERIM LEG DRAIN Item 59 Ft 3.56E+01 2.67E+01 8.89E+00 INTERIM LEG DRAIN Item 60 ft' 1.09E+02 8.16E+01 2.72E+01 LETDOWN LINE Item 61 f 2.28E+02 1.71 E+02 5.71E+01 REACTOR COOLANT PUMP Item 62 f 2.28E+03 1.71E+03 5.71E+02 FEEDWATER Item 82 F 5.45E+02 4.09E+02 1.36E+02 4" PRESSURIZER SPRAY LINE Item 94 ft' 6.80E+02 5.10E+02 1.70E+02 ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-12 of 3-20 BORON INJECTION Item 104 Ft 5.44E+01 4.08E+01 1.36E+01 ACCUMULATOR INJECTION Item 105 ft' 1.70E+01 1.28E+01 4.25E+00 4" PRESSURIZER SPRAY LINE Item 95 F 3.74E+00 2.81 E+00 9.35E-01 4" PRESSURIZER SPRAY LINE Item 97 9.02E+01 6.77E+01 2.26E+01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 98 ftj 4.86E+01 3.65E+01 1.22E+01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 99 ft' 1.27E+01 9.52E+00 I 3.17E+00 ft-0.00E+00 0.00E+00 Totals [102I I *04 2.1 I 3M-M20C See 3M Calculation Appendix ft° 8.45 8.45E+00 It 0 2_.00E+00 Totals U ]8.45+00 U8.41+00 0.OOE+00 ACCUMULATOR INJECTION Item 107 f 0.13 1.30E-01 RESIDUAL HEAT REMOVAL Item 115 f 0.08 8.OOE-02 3" ALTERNATE CHARGING Item 129 f 0.08 8.OOE-02 FEEDWATER Item 142 f 0.58 5.80E-01 RESIDUAL HEAT REMOVAL Item 162 ft. 0.12 1.20E-01 EXCESS LETDOWN Item 168 f 0.72 7.23E-01 LETDOWN LINE Item 184 f 0.04 4.OOE-02 AUXLILIARY FEEDWATER Item 275 Ft 0.07 7.OOE-02 3" AUXILIARY SPRAY LINE Item 507 f 0.03 3.OOE-02 3" AUXILIARY SPRAY LINE Item 510 f 0.11 1.15E-01 __ft 110.00E+00 Totals I Tota+ls I I I II ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-13 of 3-20 IBreak Description I Case 3 Loop 3 Crossover Leg at base of steam generator Debris Generation Resujlts Debris Type Debris Size Debris Quantity Small Pieces (<4") 63864.92 ft2 Stainless Steel RMI (ft 2) Large Pieces (>4") 21288.31 ft2 Total 85153.23 ft2 3M-M20C Individual Fibers/Particulate 1.67 ft 3 Min-K Fines 0.80 ft 3 Debris Generation Inventory

____________________Fn sIm llL rg_____Debris Type Inventory Dtis uantity ines ma arge ntac I -- I~Y I I I STEAM GENERATOR Item 130 ft-7.76E+03 5.82E+03 1.94E+03 STEAM GENERATOR Item 131 ft' 2.41E+01 1.81E+01 6.03E+00 PRESSURIZER SURGE LINE Item 135 ft' 2.25E+03 1.69E+03 5.62E+02 PRESSURIZER SURGE LINE Item 136 F 4.37E+01 3.28E+01 1.09E+01_47 PRESSURIZER SURGE LINE Item 137 F 3.93E+01 2.95E+01 9.84E+00 PRESSURIZER SURGE LINE Item 138 ft' 9.75E+01 7.31E+01 2.44E+01 PRESSURIZER SURGE LINE Item 139 ft' 1.58E+02 1.19E+02 3.96E+01 FEEDWATER Item 140 ft" 6.72E+02 5.04E+02 1.68E+02 FEEDWATER Item 141 F 2.26E+01 1.70E+01 5.65E+00 FEEDWATER Item 143 ft' 7.02E+01 5.27E+01 1.76E+01 FEEDWATER Item 144 F 1.51E+01 1.13E+01 3.78E+00 FEEDWATER Item 145 ft' 9.72E+00 7.29E+00 2.43E+00 4" PRESSURIZER SPRAY LINE Item 147 7' 5.12E+02 3.84E+02 1.28E+02 4" PRESSURIZER SPRAY LINE Item 148 F 9.02E+01 6.77E+01 2.26E+01 Item 149 ft' 3.95E+00 2.96E+00 9.87E-01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 150 ft' 2.46E+01 1.85E+01 6.16E+00 HOT LEG Item 151 ft' 2.69E+03 2.01 E+03 6.71 E+02 HOT LEG Item 152 'Ft 2.93E+02 2.20E+02 7.34E+01 COLD LEG Item 153 Ft 2.00E+03 1.50E+03 4.99E+02 BORON INJECTION Item 154 Ft 3.51 E+01 2.63E+01 8.78E+00 BORON INJECTION Item 155 ftW 6.12E+01 4.59E+01 1.53E+01 ACCUMULATOR INJECTION Item 156 Ft 6.04E+02 4.53E+02 1.51E+02 ACCUMULATOR INJECTION Item 157 ft- 7.67E+02 5.75E+02 1.92E+02 ACCUMULATOR INJECTION Item 158 ft, 5.36E+00 4.02E+00 1.34E+00 ALIO N-CAL-TVA-2739-03 Revision 3 Appendix 3 3-14 of 3-20 PRESSURIZER SURGE LINE Item 136 ft' 4.37E+01 3.28E+01 1.09E+01 PRESSURIZER SURGE LINE Item 137 ft 3.93E+01 2.95E+01 9.84E+00 ACCUMULATOR INJECTION Item 159 ft' 1.96E+01 1.47E+01 4.90E+00 LOWHEAD SAFETY INJECTION Item 160 ft' 1.92E+02 1.44E+02 4.79E+01 RESIDUAL HEAT REMOVAL Item 161 f7' 2.86E+02 2.14E+02 7.15E+01 NORMAL CHARGING Item 163 ft' 3.63E+02 2.73E+02 9.08E+01 NORMAL CHARGING Item 164 ft' 3.02E+00 2.26E+00 7.54E-01 NORMAL CHARGING Item 165 t 2.97E+00 2.23E+00 7.42E-01 NORMAL CHARGING Item 166 ft' 7.94E+00 5.95E+00 1.98E+00 EXCESS LETDOWN Item 167 7f 2.67E+02 2.00E+02 6.67E+01 EXCESS LETDOWN Item 169 ft' 3.08E+01 2.31E+01 7.71E+00 EXCESS LETDOWN Item 170 Ft 8.41E-01 6.31E-01 2.10E-01 STEAM GENERATOR BLOWDOWN Item 171 ft' 3.58E+02 2.69E+02 8.95E+01 STEAM GENERATOR BLOWDOWN Item 172 ft' 3.41E+02 2.56E+02 8.53E+01 STEAM GENERATOR BLOWDOWN Item 173 ft 1.98E+01 1.48E+01 4.94E+00 STEAM GENERATOR BLOWDOWN Item 174 ft' 1.55E+01 1.16E+01 3.88E+00 STEAM GENERATOR BLOWDOWN Item 175 ft' 4.91E+00 3.69E+00 1.23E+00 STEAM GENERATOR BLOWDOWN Item 176 f 7.22E+00 5.41E+00 1.80E+00 STEAM GENERATOR BLOWDOWN Item 177 ft' 2.24E+00 1.68E+00 5.59E-01 LETDOWN LINE Item 180 ft' 5.62E+01 4.21E+01 1.40E+01 LETDOWN LINE Item 181 ft' 8.18E+02 6.14E+02 2.05E+02 LETDOWN LINE Item 182 ft' 4.36E+01 3.27E+01 1.09E+01 LETDOWN LINE Item 183 t .84E+01 1.38E+01 4.59E+00 3" ALTERNATE CHARGING Item 185 3.39E+02 2.54E+02 8.47E+01 3" ALTERNATE CHARGING Item 186 ft' 1.96E+00 1.47E+00 4.91E-01 3" ALTERNATE CHARGING Item 187 'ft 7.61E+00 5.71E+00 1.90E+00 STEAM GENERATOR Item 188 ft' 7.76E+03 5.82E+03 1.94E+03 STEAM GENERATOR Item 189 7' 2.23E+01 1.67E+01 5.58E+00 FEEDWATER Item 190 ft' 7.05E+02 5.29E+02 1.76E+02 FEEDWATER Item 191 Ft 3.08E+01 2.31E+01 7.70E+00 FEEDWATER Item 192 ft' 4.11E+01 3.08E+01 1.03E+01 FEEDWATER Item 193 ft 1.26E+01 9.45E+00 3.15E+00 FEEDWATER Item 194 ft' 8.64E+00 6.48E+00 2.16E+00 LETDOWN LINE Item 196 ft' 6.63E+02 4.98E+02 1.66E+02 HOT LEG Item 197 ft' 1.80E+03 1.35E+03 4.49E+02 COLD LEG Item 198 ft' 1.98E+03 1.48E+03 4.95E+02 BORON INJECTION Item 199 It' 4.63E+01 3.48E+01 1.16E+01 BORON INJECTION Item 200 f7' 5.44E+01 4.08E+01 1.36E+01 ACCUMULATOR INJECTION Item 201 ft' 5.87E+02 4.41E+02 1.47E+02 ACCUMULATOR INJECTION Item 202 ft' 7.98E+02 5.98E+02 1.99E+02 ACCUMULATOR INJECTION Item 203 ft- 5.97E+00 4.48E+00 1.49E+00 Stainless Steel RMI (ft2)JACCUMULATOR INJECTION Item 204 ft, 5.96E+00 4.47E+00 1.49E+00 ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-15 of 3-20 PRESSURIZER SURGE LINE Item 136 ft' 4.37E+01 3.28E+01 1.09E+01 PRESSURIZER SURGE LINE Item 137 ftý 3.93E+01 2.95E+01 9.84E+00 LOWHEAD SAFETY INJECTION Item 205 F 4.97E+01 3.73E+01 1.24E+01 LOWHEAD SAFETY INJECTION Item 206 F 1.68E+01 1.26E+01 4.21E+00 RESIDUAL HEAT REMOVAL Item 207 f 5.57E+01 4.18E+01 1.39E+01 RESIDUAL HEAT REMOVAL Item 208 ft' 2.69E+02 2.02E+02 6.73E+01 RESIDUAL HEAT REMOVAL Item 209 ft' 1.48E+01 1.11E+01 3.70E+00 RESIDUAL HEAT REMOVAL Item 210 ft' 7.97E+01 5.98E+01 1.99E+01 EXCESS LETDOWN Item 211 ft7 2.88E+02 2.16E+02 7.20E+01 EXCESS LETDOWN Item 212 ft7 5.85E+00 4.38E+00 1.46E+00 EXCESS LETDOWN Item 213 'ft 2.82E+01 2.11E+01 7.04E+00 EXCESS LETDOWN Item 214 V 3.66E+00 2.74E+00 9.15E-01 EXCESS LETDOWN Item 215 f 3.15E+00 2.36E+00 7.88E-01 STEAM GENERATOR BLOWDOWN Item 216 ft' 4.56E+02 3.42E+02 1.14E+02 STEAM GENERATOR BLOWDOWN Item 217 '7t 2.56E+02 1.92E+02 6.39E+01 STEAM GENERATOR BLOWDOWN Item 218 F 1.79E+01 1.34E+01 4.47E+00 STEAM GENERATOR BLOWDOWN Item 219 F 1.62E+01 1.22E+01 4.06E+00 STEAM GENERATOR BLOWDOWN Item 220 7 5.05E+00 3.79E+00 1.26E+00 STEAM GENERATOR BLOWDOWN Item 221 ft' 1.36E+01 1.02E+01 3.39E+00 STEAM GENERATOR BLOWDOWN Item 222 7f 2.24E+00 1.68E+00 5.59E-01 MAIN STEAM Item 265 '7' 2.22E+03 1.67E+03 5.55E+02 MAIN STEAM Item 266 '7t 1.09E+02 8.14E+01 2.71E+01 STEAM GENERATOR Item 270 f7t 8.12E+03 6.09E+03 2.03E+03 AUXLILIARY FEEDWATER Item 273 ft' 2.46E+02 1.84E+02 6.14E+01 AUXLILIARY FEEDWATER Item 274 ft7 2.31E+01 1.74E+01 5.78E+00 AUXLILIARY FEEDWATER Item 277 F 3.13E+02 2.35E+02 7.83E+01 AUXLILIARY FEEDWATER Item 278 F 1.69E+02 1.27E+02 4.23E+01 KAUXLILIARY FEEDWATER Item 279 t 3.03E+00 2.27E+00 7.57E-01 AUXLILIARY FEEDWATER Item 280 ft' 1.03E+01 7,74E+00 2,58E+00 MAIN STEAM Item 281 ft' 4.39E+03 3.29E+03 1.10E+03 MAIN STEAM Item 282 7' 1.22E+02 9.18E+01 3.06E+01 STEAM GENERATOR Item 286 ft 1.30E+04 9.74E+03 3.25E+03 AUXLILIARY FEEDWATER Item 287 ft' 1.68E+02 1.26E+02 4.21E+01 AUXLILIARY FEEDWATER Item 288 ft7 7.97E+01 5.98E+01 1.99E+01 AUXLILIARY FEEDWATER Item 289 F 9.57E+02 7.18E+02 2.39E+02 AUXLILIARY FEEDWATER Item 290 ft' 3.31E+01 2.48E+01 8.26E+00 AUXLILIARY FEEDWATER Item 291 f 7.58E+00 5.69E+00 1.90E+00 AUXLILIARY FEEDWATER Item 292 f 3.64E+02 2,73E+02 9.09E+01 AUXLILIARY FEEDWATER Item 293 ft' 3.21E+02 2.41E+02 8.03E+01 AUXLILIARY FEEDWATER Item 294 ft 1.48E+01 1.11E+01 3.69E+00 AUXLILIARY FEEDWATER Item 295 ft7 2.22E+02 1.67E+02 5.55E+01 AUXILILIARY IFEEDWATER Item 296 ftz 1 .47E+01 1.10E+01 3.67E+00 1.47E+01 ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-16 of 3-20 PRESSURIZER SURGE LINE Item 136 ft' 4.37E+01 3.28E+01 1.09E+01 PRESSURIZER SURGE LINE Item 137 f 3.93E+01 2.95E+01 9.84E+00 PRESSURIZER Item 499 t 4.67E+03 3.50E+03 1.17E+03 6" PRESSURIZER SPRAY LINE Item 503 t 2.43E+02 1.82E+02 6.07E+01 6" PRESSURIZER SPRAYLINE Item 504 7' 8.80E+00 6.60E+00 2.20E+00 6" PRESSURIZER SPRAY LINE Item 505 ft' 9.87E+00 7.41E+00 2.47E+00 3" AUXILIARY SPRAY LINE Item 506 ft' 2.26E+02 1.70E+02 5.65E+01 3" AUXILIARY SPRAY LINE Item 508 f -3.25E+00 2.44E+00 8.14E-01 3" AUXILIARY SPRAY LINE Item 509 6.99E+01 5.24E+01 1.75E+01 3/4" INSTRUMENTATION Item 511 1.38E+02 1.03E+02 3.44E+01 3/4" INSTRUMENTATION Item 512 ft' 2.30E+01 1.72E+01 5.74E+00 RC INTERIM LEG Item 53 f 3.13E+03 2.34E+03 7.81E+02 REACTOR COOLANT PUMP Item 54 ft !2.28E+03 1.71E+03 5.71E+02 INTERIM LEG DRAIN Item 55 f -1.63E+01 1.22E+01 4.08E+00 INTERIM LEG DRAIN Item 56 1.60E+02 1.20E+02 4.01E+01 RC INTERIM LEG Item 58 ft' 3.08E+03 2.31E+03 7.69E+02 INTERIM LEG DRAIN Item 59 ft' 3.56E+01 2.67E+01 8.89E+00 INTERIM LEG DRAIN Item 60 ft' 1.09E+02 8.16E+01 2.72E+01 LETDOWN LINE Item 61 ft 2.28E+02 1.71E+02 5.71E+01 REACTOR COOLANT PUMP Item 62 ftI 2.28E+03 1.71 E+03 5.71E+02 ft1 0-nnE+O0 0 f0fl+flf Totals _ ____ I II 1 u4 I ft_- 0.OOE+00 3M-M20C See 3M Calculation Appendix ftI 1.67 1.67E+00 ft-_ 0.00E+00 Totals I./L+UU l I_ [ IUI FEEDWATER Item 142_ft° 0.58 5.80E-01 RESIDUAL HEAT REMOVAL Item 162 ft° 0.12 1.20E-01 Min-K AUXLILIARY FEEDWATER Item 275 7' 0.07 7.00E-02 3" AUXILIARY SPRAY LINE Item 507 W 0.03 3.00E-02 ft_ 0.00E+00 Totals ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-17 of 3-20 m IBreak Description I Case 4 Loop 4 Crossover Leg at base of steam generator Debris Generation Results ________,-___;,__

Debris Type Debris Size Debris Quantity Small Pieces (<4") 63482.95 ft2 Stainless Steel RMI (ft 2) Large Pieces (>4") 21160.98 ft2 Total 84643.93 ft2 3M-M20C Individual Fibers/Particulate 1.67 ft 3 Min-K Fines 1.98 ft 3.F-Debrs Generation Inventory

_________.

...__.. ..............

___Debris Type linventory Details Quantity I ines Ismall Large In ac-I -I~. -- I I I -- I -Item 100 5.79E+00 ft 4.34E+00 3/4" PRESSURIZER SPRAY BYPASS LINE item 100 ft, 5.79E+00 4.34E+00 1.45E+00 HOT LEG Item 101 ft' 2.50E+03 1.88E+03 6.26E+02 COLD LEG Item 102 ft 7 1.99E+03 1.49E+03 4.98E+02 BORON INJECTION Item 103 ft 5.04E+01 3.78E+01 1.26E+01 BORON INJECTION Item 104 ft 5.44E+01 4.08E+01 1.36E+01 ACCUMULATOR INJECTION Item 105 ft' 1.70E+01 1.28E+01 4.25E+00 ACCUMULATOR INJECTION Item 106 ft* 5.59E+02 4.19E+02 1.40E+02 ACCUMULATOR INJECTION Item 108 ft* 7.85E+02 5.89E+02 1.96E+02 ACCUMULATOR INJECTION Item 109 ft 4.63E+01 3.47E+01 1.16E+01 LOWHEAD SAFETY INJECTION Item 110 ft* 1.56E+02 1.17E+02 3.90E+01 RESIDUAL HEAT REMOVAL Item 111 ft 1.05E+02 7.84E+01 2.61E+01 RESIDUAL HEAT REMOVAL Item 112 ft' 8.25E+00 6.19E+00 2.06E+00 RESIDUAL HEAT REMOVAL Item 113 F 2.69E+02 2.02E+02 6.73E+01 RESIDUAL HEAT REMOVAL Item 114 ft 3.69E+03 2.77E+03 9.23E+02 Item 116 ft 7.36E+02 5.52E+02 1.84E+02 NORMAL CHARGING Item 117 f7 5.24E+00 3.93E+00 1.31 E+00 NORMAL CHARGING Item 118 ft' 2.16E+01 1.62E+01 5.40E+00 STEAM GENERATOR BLOWDOWN Item 119 7f 4.23E+02 3.18E+02 1.06E+02 STEAM GENERATOR BLOWDOWN Item 120 7f 3.43E+02 2.57E+02 8.57E+01 STEAM GENERATOR BLOWDOWN Item 121 _F 9.31E+00 6.98E+00 2.33E+00 STEAM GENERATOR BLOWDOWN Item 122 7F 7.20E+00 5.40E+00 1.80E+00 STEAM GENERATOR BLOWDOWN Item 123 ft' 1.49E+01 1.12E+01 3.73E+00 STEAM GENERATOR BLOWDOWN Item 124 ft' 5.05E+00 3.79E+00 1.26E+00 STEAM GENERATOR BLOWDOWN Item 125 ft' 1.38E+01 1.04E+01 3.46E+00 AL ION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-18 of 3-20 BORON INJECTION Item 103 7t 5.04E+01 3.78E+01 1.26E+01 BORON INJECTION Item 104 ft' 5.44E+01 4.08E+01 1.36E+01 STEAM GENERATOR BLOWDOWN Item 126 ft' 2.31 E+00 1.73E+00 5.77E-01 3" ALTERNATE CHARGING Item 128 7f 5.95E+02 4.46E+02 1.49E+02 STEAM GENERATOR Item 223 ft 7.76E+03 5.82E+03 1.94E+03 STEAM GENERATOR Item 224 TFt 2.09E+01 1.57E+01 5.22E+00 FEEDWATER Item 225 ft' 7.29E+02 5.47E+02 1.82E+02 FEEDWATER Item 226 7t 4.39E+01 3.29E+01 1.10E+01 FEEDWATER Item 227 ft 1.26E+01 9.45E+00 3.15E+00 FEEDWATER Item 228 ft 5.04E+00 3.78E+00 1.26E+00 HOT LEG Item 230 f 2.61E+03 1.96E+03 6.53E+02 COLD LEG Item 231 ft' 1.97E+03 1.48E+03 4.94E+02 BORON INJECTION Item 232 'tF 3.97E+01 2.97E+01 9.91E+00 BORON INJECTION Item 233 f 5.10E+01 3.83E+01.

1.28E+01 ACCUMULATOR INJECTION Item 234 f 8.94E+02 6.70E+02 2.23E+02 ACCUMULATOR INJECTION Item 235 fT 8.35E+02 6.26E+02 2.09E+02 LOWHEAD SAFETY INJECTION Item 236 ft' 5.13E+01 3.85E+01 1.28E+01 STEAM GENERATOR BLOWDOWN Item 239 ft 3.58E+02 2.69E+02 8.95E+01 STEAM GENERATOR BLOWDOWN Item 240 F- 4.39E+02 3.30E+02 1.10E+02 STEAM GENERATOR BLOWDOWN Item 241 f 4.46E+00 3.34E+00 1.11E+00 STEAM GENERATOR BLOWDOWN Item 242 ft- 1.51E+01 1.13E+01 3.78E+00 STEAM GENERATOR BLOWDOWN Item 243 ft' 5.04E+00 3.78E+00 1.26E+00 STEAM GENERATOR BLOWDOWN Item 244 f 7.21E+00 5.41E+00 1.80E+00 STEAM GENERATOR BLOWDOWN Item 245 f 3.72E+00 2.79E+00 9.30E-01 3" ALTERNATE CHARGING Item 246 f7 8.88E+02 6.66E+02 2.22E+02 3" ALTERNATE CHARGING Item 247 f 2.38E+01 1.78E+01 5.94E+00 3" ALTERNATE CHARGING Item 248 ftý 1.58E+02 1.19E+02 3.95E+01 MAIN STEAM Item 249 ft 4.10E+03 3.07E+03 1.02E+03 MAIN STEAM Item 251 F 1.12E+02 8.38E+01 2.79E+01 STEAM GENERATOR Item 255 f 8.12E+03 6.09E+03 2.03E+03 AUXLILIARY FEEDWATER Item 257 Ft 2.65E+02 1.99E+02 6.63E+01 AUXLILIARY FEEDWATER Item 258 7ft 3.96E+01 2.97E+01 9.90E+00 AUXLILIARY FEEDWATER Item 259 ft' 1.58E+01 1.18E+01 3.94E+00 AUXLILIARY FEEDWATER Item 260 ft 1.11E+01 8.36E+00 2.79E+00 MAIN STEAM Item 298 ft 4.10E+03 3.07E+03 1.02E+03 MAIN STEAM Item 300 ft 1.25E+02 9.38E+01 3.13E+01 STEAM GENERATOR Item 304 ft 1.30E+04 9.74E+03 3.25E+03 AUXLILIARY FEEDWATER Item 305 7t 1.61 E+02 1.21E+02 4.02E+01 AUXLILIARY FEEDWATER Item 306 ft' 9.67E+02 7.25E+02 2.42E+02 AUXLILIARY FEEDWATER Item 307 f 3.56E+01 2.67E+01 8.91E+00 AUXLILIARY FEEDWATER Item 308 ft' 1.30E+01 9.75E+00 3.25E+00 AUXLILIARY FEEDWATER Item 309 ft 1.55E+01 1.16E+01 3.87E+00 Stainless Steel RMI (ft2)

ALION-CAL-TVA-2739-03 Revision 3 Appendix 3 3-19 of 3-20 BORON INJECTION Item 103 Ffq 5.04E+01 3.78E+01 1.26E+01 BORON INJECTION Item 104 ft' 5.44E+01 4.08E+01 1.36E+01 RC INTERIM LEG Item 46 7' 3.19E+03 2.39E+03 7.98E+02 REACTOR COOLANT PUMP Item 47 ft 2.28E+03 1.71E+03 5.71E+02 INTERIM LEG DRAIN Item 48 77 1.63E+01 1.22E+01 4.08E+00 INTERIM LEG DRAIN Item 49 7 1.60E+02 1.20E+02 4.01E+01 INTERIM LEG DRAIN Item 50 ft' 4.68E+00 3.51E+00 1.17E+00 INTERIM LEG DRAIN Item 51 7 1.90E+00 1.43E+00 4.75E-01 RC INTERIM LEG Item 64 f 3.06E+03 2.30E+03 7.65E+02 REACTOR COOLANT PUMP Item 65 ft 2.28E+03 1.71E+03 5.71E+02 INTERIM LEG DRAIN Item 66 7' 3.56E+01 2.67E+01 8.89E+00 INTERIM LEG DRAIN Item 67 ft' 1.48E+02 1.11E+02 3.70E+01 RESIDUAL HEAT REMOVAL Item 70 ft' 1.48E+03 1.11E+03 3.69E+02 RESIDUAL HEAT REMOVAL Item 71 ft 5.89E+01 4.42E+01 1.47E+01 RESIDUAL HEAT REMOVAL Item 72 'ft 3.96E+01 2.97E+01 9.90E+00 RESIDUAL HEAT REMOVAL Item 73 ft 3.37E+02 2.53E+02 8.42E+01 RESIDUAL HEAT REMOVAL Item 74 ft' 7.67E+02 5.75E+02 1.92E+02 RESIDUAL HEAT REMOVAL Item 75 f 5.26E+02 3.94E+02 1.31E+02 RESIDUAL HEAT REMOVAL Item 76 ft' 3.31E+00 2.48E+00 8.26E-01 RESIDUAL HEAT REMOVAL Item 77 ft' 1.51E+01 1.14E+01 3.79E+00 RESIDUAL HEAT REMOVAL Item 78 ft 1.15E+01 8.62E+00 2.87E+00 RESIDUAL HEAT REMOVAL Item 79 ft"2.14E+02 1.61 E+02 5.35E+01 STEAM GENERATOR Item 80 _Ft 7.76E+03 5.82E+03 1.94E+03 STEAM GENERATOR Item 81 ft' 2.38E+01 1.78E+01 5.94E+00 FEEDWATER Item 82 ft' 8.75E+02 6.57E+02 2.19E+02 FEEDWATER Item 83 't7 6.86E+01 5.15E+01 1.72E+01 FEEDWATER Item 84 ft2 1.51E+01 1.13E+01 3.78E+00 FEEDWATER Item 85 7' 9.36E+00 7.02E+00 2.34E+00 4" PRESSURIZER SPRAY LINE Item 94 f 6.80E+02 5.1OE+02 1.70E+02 4" PRESSURIZER SPRAY LINE Item 95 7 3.74E+00 2.81E+00 9.35E-01 4" PRESSURIZER SPRAY LINE Item 97 ft' 9.02E+01 6.77E+01 2.26E+01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 98 ft' 4.86E+01 3.65E+01 1.22E+01 3/4" PRESSURIZER SPRAY BYPASS LINE Item 99 1.27E+01 9.52E+00 3.17E+00 ft_ 0.OOE+00 0.O0E+00 TE 0.00E+00 0.00E+00 Totals I.4bt+u4 I I.1ILI ft° 0.OOE+00 3M-M20C See 3M Calculation Appendix ftj 1.67 1.67E+000.00E+00 I AL [ON-CAL-TVA-2739-03 Revision 3 Appendix 3 3-20 of 3-20 IBORONINJECTION It em 103 ft' 5.04E+01 _____J3.78E+01 1.26E+01 ____BORON INJECTION Item 104 5.44E+01 4.08E+01 1 .36E+01 Totals i.oto/p_.uu 1,/-U ftW 0.00E+00 ACCUMULATOR INJECTION Item 107 F 0.13 1.30E-01 RESIDUAL HEAT REMOVAL Item 115 W 0.08 8.O0E-02 Min-K MIN-K Item 127 ft 0.944 9.44E-01 3" ALTERNATE CHARGING Item 129 f7- 0.08 8.00E-02 AUXLILIARY FEEDWATER Item 307 ft, 0.75 7.50E-01 I,,- 0.00E+00 Totals I .8 +u I 1 8 +0 IIII Watts Bar Reactor Building GSI-191 Debris Generation Calculation Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-1 of 4-53 APPENDIX 4 -AUTOCAD FIGURES This attachment contains the print screens from AutoCAD that were used to calculate the paint surface areas.

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• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation I4NL I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-11 of 4-53 Figure 4.10 -Case 1 -Steel Intersected with IOD ZOI Sphere Within 6' of Floor 0 Watts Bar Reactor Building GSI- 191 Debris Generation Calculation SI O N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-12 of 4-53 SM N m*vc9 OICHN Douet oLO co w a ofM .3? (vOW9 in ~ M-4002 11 ).Fum Figure 4.11 -Case 2 -Concrete Subtracted from 1 OD ZOI Sphere 9 Watts Bar Reactor Building GSI- 191 Debris Generation Calculation L oN Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-13 of 4-53 I tIV ILt CfATW OftA CK I~)Ct~.jv

'*Abtt*Ct 1:q 'I"',~ "mII u~,. to (10161 I724*0 vqmawot oo..00 Figure 4.12 -Case 2 -Concrete Intersected with 1OD ZOI Sphere

• Watts Bar Reactor Building GSI-191 Debris Generation Calculation CE 0 041 Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-14 of 4-53 Figure 4.13 -Case 2 -Steel Subtracted from I OD ZOI Sphere

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation A L I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-15 of 4-53 WEc **O flcH.0 4, o cuetNoLO cill, I,"'t co~a jonat at IC .cl'~4i'SMKrCtj 0*U 010*'aW -*ftMV Id& *M 4 Figure 4.14 -Case 2 -Steel Intersected with 1 OD ZOI Sphere

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-16 of 4-53 scotmC( .* TLCMKOOGY Ct.Pt4 "~~1.was %a vwI *I7 i Psw1..%,4 J Figure 4.15 -Case 2 -Concrete Subtracted from 1 OD ZOI Sphere Within 6' of Floor

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation At. fLO G Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-17 of 4-53 sClt[ C[ 1 1 T9[C..O ., oumntNAL K A474 ast 07f) 09MI uvu. Pwaw Figure 4.16 -Case 2 -Concrete Intersected with I OD ZOI Sphere Within 6' of Floor

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation

/ E / I o N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-18 of 4-53**Pxc ,E TCW,0O0OY m ,*-oe "matI -)'A4*INt$6048 ". 1. (4401 00124" swaw Itt ýPr J Figure 4.17 -Case 2 -Steel Subtracted from IOD ZOI Sphere Within 6' of Floor

• Watts Bar Reactor Building GSI-191 Debris Generation Calculation AL.OI 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-19 of 4-53 VOrW $01*4 or 0 ,~ ~$ 402 wv'.. t (i ý ý407 bq'w (4 ) rwI.-tw -O-C MOV8 Figure 4.18 -Case 2 -Steel Intersected with I OD ZOI Sphere Within 6' of Floor

• Watts Bar Reactor Building GSI- 191 Debris Generation CalculationN Document No:ALION-CAL-TVA-2739-03 Rev:3 j Page: 4-20 of 4-53 s~tfuct &No 9tCR.OOGY Dcmn oLO I Z?0&01 VVM Aa * ( 46980 001t Wz It P) u..Figure 4.19 -Case 3 -Concrete Subtracted from 1 OD ZOI Sphere

• Watts Bar Reactor Building GSI- 191 Debris Generation CalculationI ON Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-21 of 4-53 scirIt[m ANO Ttc..4tOG, ouetNALO 74:.11 l~tcm M"c 4 .Figure 4.20 -Case 3 -Concrete Intersected with I OD ZOI Sphere

• Watts Bar Reactor Building GSI- 191 Debris Generation Calculation S09,.. aLm* ..O 06N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-22 of 4-53 Figure 4.21 -Case 3 -Steel Subtracted from I OD ZOI Sphere

• Watts Bar Reactor Building GSI- 191 Debris Generation CalculationI 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-23 of 4-53 cc.. 04, D~ocuetNoLO

• 1ow Pmaq tor 0 11044 oq*"* to aliks SM2 wsrww*i I~ ua I :C%,W0 A CC." Figure 4.22 -Case 3 -Steel Intersected with I OD ZOI Sphere

• Watts Bar Reactor Building GSI-191 Debris Generation Calculation A$ L I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-24 of 4-53 sctmlNot" OGY ouet oLO Figure 4.23 -Case 3 -Concrete Subtracted from 1OD ZOI Sphere Within 6' of Floor

• Watts Bar Reactor Building GSI-191 Debris Generation Calculation sct/ I 0 N Document No:ALION-CAL-TVA-2739-03 Rev:3 Page: 4-25 of 4-53 I**vw "" M1 I0StM~rhIG Figure 4.24 -Case 3 -Concrete Intersected with 1OD ZOI Sphere Within 6' of Floor