ML18198A119

Attachment 5 to 18-233, ANP-3467NP, Rev. 0, North Anna Fuel-Vendor Independent Small Break LOCA Analysis Licensing Report

ML18198A119
Person / Time
Site:	North Anna
Issue date:	05/31/2018
From:	Framatome
To:	Office of Nuclear Reactor Regulation
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ML18198A133	List: ML18198A118 ML18198A119
References
18-233 ANP-3467NP, Rev. 0
Download: ML18198A119 (64)

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Serial No .18-233 LAR - SBLOCA Methodology Addition to COLR References Attachment 5 ANP-3467NP, Revision 0 North Anna Fuel-Vendor Independent Small Break LOCA Analysis Licensing Report (NON-Proprietary)

Virginia Electric and Power Company (Dominion Energy Virginia)

North Anna Power Station Units 1 and 2

Controlled Docu ent framatome ANP-3467NP North Anna Fuel-vendor Independent Revision 0 Small Break LOCA Analysis Licensing Report May 201 8 Framatome Inc.

(c) 2018 Framatome Inc.

C ntrolled Docun1ent ANP-3467NP Revision 0 Copyright© 2018 Framatome Inc.

All Rights Reserved

Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page i Nature of Changes Section(s)

Item or Page(s) Description and Justification 1 All Initial Issue

\.JUllllU Iv' LI \,.,UII Clll Framatome Inc. ANP-3467NP Revision 0 North Ann a Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page ii Contents Page

1.0 INTRODUCTION

.. .... ....... .. .. .. .... .... ... .. ... ... ...... ......... .... ... ... ........ .... .. .. .. ........ ...... 1-1 2.0

SUMMARY

OF RESULTS ..... ........ .. ..... ..... .. ..... ......... ....... ....... .. ... ... ...... ...... .. .. .. 2-1

3.0 DESCRIPTION

OF ANALYSIS ... .... .... ....... ..... ........... .... ... ..... ... .... ... ..... ..... ... .. ... 3-1 3.1 Description of an SBLOCA Event ... ........... .. ........ .. ..... ... .. ........ ... .. ........ .. 3-1 3.2 Method of Analysis ..... ........... ... ...... .... .... ... ..... ... ... .. ... ............. .. ... ... ... .... . 3-3 3.2 .1 Approved Analytical Method ........ ....... ... ...... .. ... .... ........ .... ..... ... .. . 3-3 3.2.2 Fuel-vendor Independent Appl ication .. ... ... .. ... ..... .. ..... .... .... ... ...... . 3-5 3.2.3 Deviations from Approved Analytical Method .... .... .. ..... .... ... .. .. .... . 3-8 3.2.4 SE Compliance ....... ....... ....... ....... .. .... ..... ... .... .. ..... .... ..... ...... ........ 3-9 3.3 Plant Description and Summary of Analysis Parameters ...... ..... ... ...... .. 3-10 4.0 ANALYTICAL RESULTS ... ... ... .. ......... .. ......... .... .. ...... ... ... ......... ... .. .... .... ........ .. .. 4-1 4.1 Break Spectrum Results .................. ... ..... ........ .... ..... ...... .. ... .. ... .. ... ....... .. 4-1 4.2 Discussion of Limiting PCT Break Transient.. .. .... ..... .... ...... .. ... .... .......... . 4-2 4.3 Additional Studies ... .. ...... .... .......... .... .. .. ...... ... ... .... .. ... ........... .. ... .... .... .... . 4-3 4.3 .1 Delayed RCP Trip ...... ..... .... ...... ......... .... .. ... ..... .... .... .. .... .... .... .... .. 4-3 4.3.2 Attached Pipe Breaks ..... ... .... ...... .... ... .... ..... ... .. .... .. ....... ... ... ... ... ... 4-4 4.3.3 ECCS Temperature Sensitivity .... .... .. ..... ....... .. .... ... .. ....... ..... .. ...... 4-5

5.0 REFERENCES

..... .... ............. .......... ... .............. .. ... ...... ..... .. ......... .... .... .. ........ .. .. 5-1 The specifi c reason(s) for claiming the information annotated herein as proprietary, as delineated in the Affidavit executed by the owner of the information, are provided as follows :

• Use of the information by a competitor would perm it the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar produ ct or service .

• The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of wh ich provides a competitive advantage for Framatome Inc. in product optimization or marketabil ity.

• The information is vital to a competitive advantage held by Framatome Inc., would be helpful to competitors to Framatome Inc., and would likely cause substantial harm to the competitive position of Framatome Inc.

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North An na Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page iii List of Tables Table 3-1 System Parameters and Initial Conditions .... ..... ... .......... ..... ... ... .. .. ....... ... 3-12 Table 3-2 HHSI Flow Rates .. .... .... ........... ... .................... ........... ... .. ............ ..... ... ... .. . 3-13 Table 3-3 LHSI Flow Rates ..... .. .... ..... ...... .. .. .. .. ..... ..... ..... ..... .. ..... ...... ..... ......... ...... ... 3-14 Table 4-1 Summary of SBLOCA Break Spectrum Results ......... .. ..... ... .......... .. .. ... ..... 4-6 Table 4-2 Event Times for Break Spectrum (seconds) ...... .... .... ........... ... ................... 4-8 Table 4-3 6.5 Inch Break - Sequence of Events .. ... ... ....... ....... ... .. .. .. ... ... .. .... ... ... .... . 4-10

cu Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page iv List of Figures Figure 3-1 Generic W3 Plant Primary System Nodalization .. ..... .. ... ..... ..... ... .. .. .... ... . 3-15 Figure 3-2 Generic W3 Plant Secondary System Nodalization ....... .... ... ... ... ..... .... ... 3-16 Figure 3-3 Generic W3 Reactor Vessel Nodalization .... .. .... ... .. ... .... .. .. ... ... ... .. ... ..... .. 3-17 Figure 3-4 Axial Power Distribution ..... ..... ....... ... .... ... ... ...... .. ... ....... ... .. .. ........ ... ... ... .. 3-18 Figure 3-5 ] ....... .. ......... ...... .... . 3-19 Figure 4-1 PCT vs. Break Size for Break Spectrum .. ...... .... ........ .. .... ....... .. .. ... ... ...... 4-11 Figure 4-2 6.5 Inch Break - Cladding Temperature at PCT Node .. .. .. .. ... ... .. ..... ...... . 4-12 Figure 4-3 6.5 Inch Break - Break Flow Rate .... .......... .... .... .... .... .. ... ... ..... .. .... .. ....... 4-13 Figure 4-4 6.5 Inch Break- Break Void Fraction .... ... .. ... ... ...... ..... .. ... .... ... ... ..... .. .. .. . 4-14 Figure 4-5 6.5 Inch Break - System Pressures ....... ............. ..... .. .. .... ....... ..... .... ...... . 4-15 Figure 4-6 6.5 Inch Break - Reactor Power ..... .. .. .. ........... .... .. ...... ... .. ... ... ..... ... ..... ... 4-16 Figure 4-7 6.5 Inch Break - RCS and RV Masses ...... ... ... ...... ..... .... ..... ... .. ... ... .... .... 4-17 Figure 4-8 6.5 Inch Break - Downcomer Level .... ...... ...... ....... ...... ... .. ... ....... ........ .... 4-18 Figure 4-9 6.5 Inch Break - Hot Assembly Collapsed Level ....... ...... .... .... .... .. .. .... ... 4-19 Figure 4-10 6.5 Inch Break - Hot Assembly Mixture Level. .......... .... ....... .. ...... ...... ... 4-20 Figure 4-11 6.5 Inch Break - Cold Leg Mass Flow Rates ... .... .... .. ...... ........ .. .. ..... .... 4-21 Figure 4-12 6.5 Inch Break - HHSI Mass Flow Rates .... .. .. .. ..... ... ... ... .... .... .... .... ... ... 4-22 Figure 4-13 6.5 Inch Break - LHSI Mass Flow Rates ....... ....... ........ ...... ... ..... .. ....... .. 4-23 Figure 4-14 6.5 Inch Break - Accumulator Mass Flow Rates .. .... ... .... ...... ... .... ... ... ... 4-24 Figure 4-15 6.5 Inch Break - Loop Seal Upside Collapsed Levels .... ..... .......... ... .... 4-25 Figure 4-16 6.5 Inch Break- SG Upside Tube Collapsed Level , Broken Loop ........ 4-26 Figure 4-17 6.5 Inch Break - Secondary Mass ...... ..... ... ... ..... ... .......... ........ ......... ... . 4-27 Figure 4-18 6.5 Inch Break - MFW Mass Flow Rates ... .... ......... .... .... ..... ...... .. ... .... .. 4-28 Figure 4-19 6.5 Inch Break - AFW Mass Flow Rates .... ..... ....... ...... ... ..... ......... ... .... . 4-29 Figure 4-20 6.5 Inch Break - MSSV Mass Flow Rates ..... ....... .. ..... .. ... .. .... .......... .... 4-30 Figure 4-21 ] ..... ..... .... ... ...... 4-31 Figure 4-22

] ........ ......... ....... .. ... .... .. .. .. ... ...... .... .... .... ..... .. .... .... ...... .. 4-32 Figure 4-23

] ***** ***** **** **** ***** *** ************ ** **** ********** ******** **** **** ** ******** *** ** 4-33 Figure 4-24 ] ... ... .... 4-34

Controlled Docun1ent Framatome Inc. ANP-3467NP Revision 0 North An na Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page v Nomenclature Acronym Definition AFW Auxiliary Feedwater BOC Beginning-of-Cycle cwo Core Wide Oxidation CFR Code of Federal Regulations DC Down comer ECCS Emergency Core Cooling System EOG Emergency Diesel Generator EM Evaluation Model EOC End-of-Cycle FVI Fuel Vendor Independent HHSI High Head Safety Injection LHGR Linear Heat Generation Rate LSC Loop Seal Clearing LHSI Low Head Safety Injection LOCA Loss of Coolant Accident LOOP Loss of Offsite Power MFW Main Feedwater MLO Maximum Local Oxidation MSSV Main Steam Safety Valve NRC Nuclear Regulatory Commission RCP Reactor Coolant Pump RCS Reactor Coolant System RV Reactor Vessel PCT Peak Cladding Temperature PWR Pressurized Water Reactor PZR Pressurizer SBLOCA Small Break Loss of Coolant Accident SE Safety Evaluation SG Steam Generator SI Safety Injection SIAS Safety Injection Actuation Signal TT Turbine Trip w Westinghouse W3 Westinghouse 3-loop plant

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 1-1

1.0 INTRODUCTION

This report summarizes the fuel-vendor independent small break loss-of-coolant accident (SBLOCA) analysis for North Anna Units 1 and 2. The purpose of the analysis is to provide the transient results which will support the demonstration of acceptable emergency co re cooling system (ECCS) design performance against the 10 CFR 50.46 criteria. The analysis was performed in accordance with the Nuclear Regulatory Commission (NRC)-approved S-RELAP5 methodology described in Reference 1 and as supplemented by Reference 2. This report justifies the use of the methodology for a fuel-vendor independent (FVI) SBLOCA analysis.

The analyzed North Anna plant is a 3-loop , Westinghouse (W)-designed pressurized water reactor (PWR) with an upflow barrel baffle configuration and 17x17 fuel assembl ies. The analysis supports operation at a core power level of 2951 MWt; an Fa of 2.5 which includes uncertainties and K(z)=1 ; radial peaking , Ft>H , of 1.65; 7% steam generator (SG) tube plugging in each SG ; and a total initial core bypass of 6.5% .

A complete spectrum of cold leg break sizes was considered , ranging from 1.0 inch diameter to 8.7 inch diameter. In addition , sensitivity studies were performed to consider delayed reactor coolant pump (RCP) trip , attached piping breaks , and ECCS fluid temperature.

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 2-1 2.0

SUMMARY

OF RESULTS The limiting Peak Clad Temperature (PCT) from the break spectrum occurs in the 6.5 inch break with a PCT of 1705°F. The maximum value from the break spectrum for the transient maximum local oxidation (MLO) is 1.18%. The transient MLO does not include the pre-transient oxidation which is dependent on cladding type . The maximum core-wide oxidation (CWO) is less than 0.04%.

Consistent with the additional prescriptions of the evaluation model (EM) supplement in Reference 2, a delayed RCP trip study, an attached pipe break study, and an ECCS temperature sensitivity study were performed. The delayed RCP trip study analyzed both cold leg and hot leg break spectrums with a trip time of five minutes after the loss of hot leg subcooling . The attached pipe break study analyzed a break in both the pumped safety injection (SI) line connection and the accumulator line. The ECCS temperature study analyzed the sensitivity to temperatures different than those prescribed in the break spectrum analysis. The conclusions of these studies support the break spectrum analysis as the licensing basis.

cu Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-1

3.0 DESCRIPTION

OF ANALYSIS Section 3.1 of this report provides a brief description of the postulated SBLOCA event.

Section 3.2 describes the analytical methods used in the analysis. That section contains a discussion of the application of the approved EM , the justification of the approved EM to fuel-vendor independent applications, any deviations , and compliance with the NRC's final Safety Evaluation (SE) of the EM . Section 3.3 presents a description of the analyzed North Anna plant and outlines the system parameters used in the SBLOCA analysis.

3.1 Description of an SBLOCA Event The postulated SBLOCA is defined as a break in the Reactor Coolant System (RCS) pressure boundary for which the break area is up to approximately 10% of a cold leg pipe area. The most limiting break location is in the cold leg pipe on the discharge side of the RCP. This break location results in the largest amount of RCS inventory loss and the largest fraction of ECCS fluid ejected out through the break. This produces the greatest degree of core uncovery, the longest fuel rod heatup time , and consequently ,

the greatest challenge to the 10 CFR 50 .46 criteria (Reference 3).

The SBLOCA event progression develops in the following distinct phases: (1) subcooled depressurization (also known as blowdown) , (2) natural circulation , (3) loop seal clearing, (4) core boil-off (5) core recovery and long-term cooling . The duration of each of these phases is break size and system dependent.

Following the break, the RCS rapidly depressurizes to the saturation pressure of the hot leg fluid. During the initial depressurization phase, a reactor trip is generated on low pressurizer pressure ; the turbine is tripped on the reactor trip. The assumption of loss-of-offsite-power (LOOP) concurrent with the reactor scram results in RCP trip.

CL1 Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-2 In the second phase of the transient, the RCS transitions to a quasi-equilibrium condition in which the core decay heat, leak flow , steam generator heat removal , and system hydrostatic head balance combine to control the core inventory. During this period, the RCPs are coasting down and the system drains top down with voids beginning to form at the top of the SG tubes and continuing to form in the reactor vessel upper head and at the top of the reactor vessel upper plenum region . The loop seals remain plugged during this phase, trapping vapor generated by the core in the RCS ,

and resulting in a low quality flow at the break.

The third phase in the transient is characterized by loop seal clearing. During this phase, the loop seal , which is liquid trapped in the RCP suction piping, can prevent steam from venting via the break. When a sufficient pressure difference between the reactor vessel upper head and downcomer is reached , liquid in the loop seal is displaced, clearing the loop seal, and allowing the trapped steam to be vented to the break. For a small break, the transient develops slowly, and liquid level in the RCS may drop to the loop seal level prior to establishing a steam vent. The core can become tempora rily uncovered in this loop seal clearing process. Following loop seal clearing ,

the break flow transitions to primarily steam and the core recovers to approximately the cold leg elevation, as the pressure imbalances throughout the RCS are relieved .

The fou rth phase is characterized as core boil-off. With the loop seal cleared , the venting of steam through the break causes a rapid RCS depressurization below the secondary pressure. As boiling increases in the core , the core mixture level decreases.

The core mixture level will reach a minimum, in some cases resulting in deep core uncovery. The boil-off period of the transient ends when the core liquid level reaches this minimum . At this time, the RCS has depressurized to the point where ECCS flow into the reactor vessel matches the rate of boil-off from the core.

Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-3 The last phase of the transient is characterized as core recovery and long-term cooling.

The core recovery period extends from the time at which the core mixture level reaches a minimum in the core boil-off phase, until all parts of the core are quenched and covered by a low quality mixture. Core recovery is provided by pumped injection and passive accumulator injection when the RCS pressure decreases below the accumulator pressure.

The SBLOCA transient progression is dependent on the size of break and is typically broken into three different break size ranges. For break sizes towards the larger end of the break spectrum, significant primary system inventory loss results in larger primary system depressurization and rapid accumulator injection. For break sizes in the middle of the spectrum, the rate of inventory loss from the primary system is such that the HHSI pumps cannot preclude significant core uncovery. The primary system depressurization rate is slow, extending the time required to reach the accumulator injection pressure or to recover core liquid level on HHSI flow. This tends to maximize the heatup time of the hot rod and produce the maximum PCT and local cladding oxidation. For very small break sizes, the primary system pressure does not reach the accumulator injection pressure; however, primary system inventory loss is not significant and typically within the means of HHSI makeup capacity such that core uncovery is minimal if not precluded.

3.2 Method of Analysis 3.2.1 Approved Analytical Method This analysis was performed in accordance with the NRG-approved S-RELAP5 methodology described in Reference 1 and as supplemented by Reference 2. This section describes the application of the approved methodology to the North Anna plant.

This application of the method to a non-Framatome fuel core is described in Section 3.2 .2. Deviations from the method are described in Section 3.2.3. Compliance with the SE is described in Section 3.2.4 .

lled Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-4 The EMF-2328 SBLOCA evaluation model for event response of the primary and secondary systems and the hot fuel rod used in this analysis is based on the use of two computer codes . The appropriate conservatisms, as prescribed by Appendix K of 10 CFR 50 (Reference 6) , are incorporated .

Two computer codes were used in this analysis:

1. The RODEX2-2A code (References 4 and 5) was used to determine the burnup-dependent initial fuel rod conditions for the system calculations.

2. The S-RELAP5 code was used to predict the thermal-hydraulic response of the primary and secondary sides of the reactor system and the hot rod response .

Representative system nodalization figures for a Westinghouse 3-loop plant are shown in Figure 3-1 (RCS) , Figure 3-2 (Secondary System) , and Figure 3-3 (Reactor Vessel) .

As noted in Figure 3-3 , the upper plenum noding is variable. [

]

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-5 3.2.2 Fuel-vendor Independent Application The fou ndation of the FVI-SBLOCA application is the NRC-approved SBLOCA methodology contained in EMF-2328 (Reference 1) and its supplement (Reference 2) .

The methodology incorporates the appropriate conservatisms, as prescribed by Append)x K of 10 CFR 50 (Reference 6) and is applicable to Wand CE-designed plants . It is typically used to analyze Framatome fuel products. A fuel-vendor independent application inherently must use representative fuel design and material characteristics. [

]

for a 17x17 assembly, and non-fuel related plant-specific details.

Controlled D0cun1 Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-6

[

] The general SBLOCA event progression is described in Section 3.1. [

] Consequently, these inputs are all plant-specific.

[

] Important system parameters and initial conditions used in the analysis are given in Table 3-1 , Table 3-2 and Table 3-3. [

]

cu Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-7

[

] The Framatome fuel product is designed so that it can be a replacement to the resident fuel and therefore is functionally very similar to other vendor fuel designs. The application was reviewed in light of the current assembly design and

[

] the analysis herein is applicable to use for 17x17 fuel products with ZIRLO and Optimized ZIRLO cladding . Any changes in the fuel assembly design or cladding material would need to be evaluated for continued applicability of the method and analyses results .

Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-8

[

] The results of the SBLOCA analysis described herein can therefore be used to support North Anna Units 1 and 2 with a non-Framatome core.

3.2.3 Deviations from Approved Analytical Method A deviation from the modeling approach is applied to better represent the primary system mass distribution during a specific period of the SBLOCA transient:

.,..:.,,*. ~ $

\¢,lA Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensin Re ort Pa e 3-9 3.2.4 SE Compliance The supplemented EMF-2328 method (Reference 1 and Reference 2) contains no restrictions. Except as indicated in Section 3.2.3, the analysis was performed in accordance with the approved methodology.

d c:u Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-10 3.3 Plant Description and Summary of Analysis Parameters The North Anna plant is a W-designed PWR with three loops. Each loop contains a hot leg , a U-tube SG , an RCP, and a cold leg. A pressurizer is connected to the hot leg of one of the loops . The reactor has a core power level of 2951 MWt (including measurement uncertainty) . The reactor vessel contains a downcomer, upper and lower plenums, and a reactor core containing 157 fuel assemblies. The ECCS contains two centrifug al charging/HHS! pumps, two low head safety injection (LHSI) pumps, and three accumulators.

The RCS was nodalized in the S-RELAP5 model with control volumes interconnected by flow paths or "junctions ." The model includes three accumulators, a pressurizer, and three SGs with both primary and secondary sides modeled . All of the loops were modeled explicitly to provide an accurate representation of the plant. A SG tube plugging level of 7% was modeled in each SG . Important system parameters and initial condition s used in the analysis are given in Table 3-1 . The heat generation rate in the S-RELAP5 reactor core model was determined from reactor kinetics equations with actinide and decay heating as prescribed by 10 CFR 50 Appendix K (Reference 6).

The analysis assumed LOOP concurrent with reactor scram , which is based on the low pressurizer pressure reactor trip and includes delays as stated in Table 3-1 . The assumption of LOOP results in RCP trip .

The single failure criterion requ ired by 10 CFR 50 Appendix K (Reference 6) was satisfied by assuming the loss of one emergency diesel generator (EOG). Thus , this results in the loss of one HHSI pump , one LHSI pump and one motor-driven AFW pump . The initiation of the HHSI and LHSI systems were delayed by 29 seconds, following safety injection actuation system (SIAS) activation . Table 3-2 and Table 3-3 show the minimum ECCS flow rates with EOG failure for HHSI and LHSI, respectively.

ntrol (J' Clt Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-11 Only two SGs were credited with receiving AFW. The AFW flow rates were minimized and were delayed 60 seconds beyond the time of the AFW system initiation on low-low SG level. The input model includes the main steam lines from the SGs to the turbine control valve , as well as the inlet piping to the MSSVs. The MSSVs were set to open at their nominal setpoints plus a 3% tolerance .

The axial power shape for this analysis is shown in Figure 3-4. [

]

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-12 Table 3-1 System Parameters and Initial Conditions Parameter Analysis Value 1

Reactor Power, MWt 2951 Axial Power Shape Figure 3-4 Peak LHGR, kW/ft 14.8 Total Peaking Factor, Fa 2.5 1

Radial Peaking Factor, F6 H 1.65 RCS Flow Rate, gpm 278 ,400 Pressurizer Pressure , psia 2250 RCS Average Temperature, °F 590.7 Accumulator Pressure , psia 590.4 Accumulator Fluid Temperature, °F 105 Accumulator Water Volume, ft 3 968.5 SG Tube Plugging Level per SG , % 7 SG Secondary Pressure , psia 847 MSSV Lift Pressure and Tolerance Nominal + 3% tolerance MFW Temperature, °F 449 AFW Flow Rate per fed SG , gpm 133.3 AFW Temperature, °F 100 Pressurizer Pressure - Low Reactor Trip Setpoint (RPS), psia 1845 Reactor Trip Delay Time on Low Pressurizer Pressure 2 , sec 2.0 Reactor Scram Delay Time, sec 0.0 SIAS Activation Pressurizer Pressure Setpoint, psia 1714.7 HHSI and LHSI Pump Delay Time on SIAS, sec 29.0 HHSI and LHSI Fluid Temperature, °F 72.0 Low-Low SG Level Setpoint, % Narrow Range Span 0.0 AFW Delay, sec 60.0 1

Includes associated measurement uncertainty 2

Includes scram delay

Co Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-13 Table 3-2 HHSI Flow Rates Pressure (psia) Intact Flow (lbm/sec) Broken Flow (lbm/sec) 0.0 22 .0 23.8 14.7 22 .0 23.8 64.7 21.8 23.6 114.7 21 .6 23.3 264.7 20.8 22.1 514.7 19.4 20.7 764.7 18.0 19.2 1014.7 16.6 18.1 1264.7 15.2 16.6 1514.7 13.6 14.8 1764.7 11 .8 12.9 2014.7 9.9 10.9 2114.7 8.9 \ 9.8 2114.8 0.0 0.0

C Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-14 Table 3-3 LHSI Flow Rates Pressure (psia) Intact Flow (lbm/sec) Broken Flow (lbm/sec) 0.0 153.1 153.1 14.7 153.1 153.1 24.7 143.5 143.5 34.7 133.6 133.6 44.7 123.4 123.4 54 .7 112.8 112.8 64.7 101.9 101 .9 74.7 89.8 89 .8 84 .7 77 .6 77 .6 94 .7 64 .7 64.7 104.7 50.8 50.8 114.7 35 .5 35.5 124.7 18.6 18.6 134.7 0.0 0.0

_J

Controlled Docun1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-15 Figure 3-1 Generic W3 Plant Primary System Nodalization

cu Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-16 Figure 3-2 Generic W3 Plant Secondary System Nodalization

ro-

._t ' !led Docu Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-17 Figure 3-3 Generic W3 Reactor Vessel Nodalization

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-18 Figure 3-4 Axial Power Distribution

nt Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 3-19 Figure 3-5 [ ]

CL!

Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 4-1 4.0 ANALYTICAL RES ULTS 4.1 Break Spectrum Results The North Anna break spectrum analysis for SBLOCA includes breaks of varying diameter up to 10% of the flow area for the cold leg. The break spectrum resolution follows that prescribed by the methodology and is refined to determine the limiting break size, identified as the case with the highest PCT, and the largest break size which depressurizes to a pressure just above the accumulator pressure . Figure 4-1 displays the PCT results as a function of break size. A summary of the results from each case of the break spectrum analysis is presented in Table 4-1. The event times for each case of the break spectrum are provided in Table 4-2. The limiting PCT case was determined to be the 6.5 inch break with a PCT of 1705°F. This case also resulted in the limiting transient MLO with a value of 1.18%. The largest break size which was resolved just above the accumulator setpoint is the 2.3 inch break.

C Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensin Re ort Pa e 4-2 4.2 Discussion of Limiting PCT Break Transient The limiting break from the break spectrum was determined to be the 6.5 inch break with a PCT of 1705°F. The transient progression is shown in Figure 4-2 through Figure 4-20 . The cladding temperature at the PCT location is shown in Figure 4-2. The sequence of events is shown in Table 4-3. The break opens at 0.0 seconds. The break size is relatively large and the fast depressurization (Figure 4-5) results in the low pressurizer setpoint being reached at 0.4 seconds. After the 2-second delay, the reactor trips (Figure 4-6) and , assumed coincident, the RCPs and turbine trip. The pressure in the secondary side begins to rise and is relieved via the MSSV (Figure 4-20). The low RCS pressure initiates the SI actuation signal at 8.1 seconds . Following the ECCS startup delays, the HHSI begins to inject at 38 seconds (Figure 4-12).

d Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 4-3 The core begins to uncover at 64 seconds (Figure 4-9, Figure 4-10) and reaches the bottom at 105 seconds. At this time though there is still a significant holdup of liquid in the SG tubes (Figure 4-16) . The three loop seals clear around 130 seconds. Along with the continued draining of the SG tubes, a temporary increase in the core level occurs , but the mixture level remains low with poor cooling in the upper regions (Figure 4-9 , Figure 4-10) and the clad temperature excursion proceeds (Figure 4-2).

The accumulators inject at 228 seconds (Figure 4-14). There is a time delay from the accumulator injection to the mixture level reaching sufficient levels to cool the upper locations in the core and as such , the hot rod ruptures at 240 seconds. The rupture allows for interior metal-water reaction thereby increasing the local oxidation at the rupture node . The cladding temperature excursion is terminated at 241 seconds with a PCT of 1705°F. The core is initially quenched at approximately 266 seconds. The pressure continues to fall and the accumulator injects again at 320 seconds. The pressure reduces such that the LHSI shutoff head is just reached and momentarily injects at 340 seconds (Figure 4-13), but this momentary injection of LHSI is not important in mitigation of the transient. The core is fully quenched around 344 seconds.

4.3 Additional Studies 4.3.1 Delayed RCP Trip The break spectrum analysis assume RCP trip coincident with reactor trip. For plants such as North Anna that do not have an automatic RCP trip , a delayed RCP trip can potentially result in a more limiting condition than tripping the RCPs at reactor trip .

Continued operation of the RCPs can result in earlier loop seal clearing with associated two-phase flow out the break, which would result in less inventory loss out the break early in the transient, but in the longer term could result in more overall inventory loss out the break. It has been postulated that tripping the pumps when the minimum RCS inventory occurs could cause a collapse of voids in the core , thus depressing the core level and provoking a deeper core uncovery, and a potentially higher PCT.

ment Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 4-4 Section 11. K.3.5 of NUREG-0737 (Reference 7) calls for the analysis of a delayed RCP trip for SBLOCA analyses . This was followed with specific recommendations for manual RCP trip in References 8 and 9 as NRC Generic Letters applicable to Westinghouse and CE plants. Based on indications/conditions consistent with the North Anna licensing basis and Emergency Operating Procedures, a spectrum of hot and cold leg breaks is analyzed to support the North Anna RCP trip procedu re. The assumed manual trip time in the analysis is five minutes after the loss of hot leg subcooling margin .

The studies demonstrated that the PCTs are over 150°F less in the delayed RCP , cold leg break study and 400°F less in the delayed RCP , hot leg break study than limiting PCT in the break analysis. In conclusion , the severity of RCP trip delayed until 5 minutes after the loss of hot leg subcooling , with a break in either location , is less than that of the break spectrum analysis with RCP trip coincident with the reactor trip .

4.3.2 Attached Pipe Breaks The ECCS must cope with ruptures of the main RCS piping and breaks in attached piping . To accomplish this , an evaluation is made of the ruptures in attached piping that also compromise the ability to inject emergency coolant into the RCS . When combined with a single failure , the ECCS capability is significantly compromised . The size of the rupture and the portion of ECCS lost directly to containment are dependent on the plant design . In order to assure acc~ptable ECCS performance , the scope of analysis includes accidents of this type .

The North Anna plant has a separate line for the accumulator and the pumped SI injection connected to each cold leg. The high head and low head system share a common short length of pipe before joining to the cold leg . Both the accumulator and SI line break are analyzed . The accumulator line break resulted in a PCT of 1505°F and a transient MLO of 0.17%. The SI line break resulted in a PCT of 1008°F and transient MLO of 0.01 %. The results are less limiting than those of the break spectrum analysis .

Controlled Docun1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 4-5 4.3.3 ECCS Temperature Sensitivity

C ntrolled Framatome Inc. ANP-3467NP Revision 0 North Ann a Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 4-6 Table 4-1 Summary of SBLOCA Break Spectrum Results

C cu Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Licensing Report Page 4-7

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-8 Table 4-2 Event Times for Break Spectrum 5 (seconds)

on Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-9

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Ann a Fuel-vendor Independent Small Break LOCA Analysis Page 4-10 Table 4-3 6.5 Inch Break - Sequence of Events Event Time (sec)

Break Opening 0.0 Low PZR Pressure Trip 0.4 Reactor Scram , RCP and Turbine Trip 2.4 SIAS Issued 8.1 HHSI Flow: Loop 1/2/3, Broken 38/38/38 Core Uncovery 64 AFW: SG 1/2/3 701-/70 Loop Seal Clearing : Loop 3, Broken 131 Loop Seal Clearing: Loop 2 132 Loop Seal Clearing : Loop 1 132 Break Uncovery 134 Accumulator Flow: Loop 1/2/3 , Broken 228/228/228 Hot Rod Rupture Time 240 PCT Time 241 LHSI Flow: Loop 1/2/3, Broken 340/340/340 Approximate Core Quench 344

Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-11 Figure 4-1 PCT vs. Break Size for Break Spectrum

11ed Drici, i L. V ,',..

Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-12 Figure 4-2 6.5 Inch Break - Cladding Temperature at PCT Node Cladding Temperature 2000 .0 r------ ------------,-------,------~

1500.0

- HR201-44@ 10.875 ft G:'

~

~ 1000 .0

"'a.E

~

500 .0 Time(s}

Controlled Docun1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-13 Figure 4-3 6.5 Inch Break - Break Flow Rate Break Flow 5000 .0 ~ ~ - - ~ - ~ ~ - - ~ - ~ ~ - - ~ - - ~ - - ~ - - ~ - - ~ -

4000 .0

-a Break Flow

?., 3000 .0 iii 0::

~

u::

~ 2000 .0

1000.0 0 .0 ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - ~

0 200 400 600 800 1000 Time(s)

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analys is Page 4-14 Figure 4-4 6.5 Inch Break - Break Void Fraction Break Vapor Void Fraction 1 .0 -

{

0 .8 0 .6 C:

0 u

E u.

"O g

0.4

---

Void Fraction 0 .2

~

0 .0 0 200 400 600 800 1000 Time (s)

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-15 Figure 4-5 6.5 Inch Break - System Pressures System Pressures 2500.0 225 0.0 2000.0 1750 .0 - - a PZR

• .;

.e, 15 00 .0

~

• SG 1 A SG 2 SG3

~ 1250 .0

~

a..

1000 .0 750 .0 500 .0 250 .0 0 .0 0 200 400 600 800 1000 Time(s)

Controlled Docu n1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-16 Figure 4-6 6.5 Inch Break - Reactor Power Reactor Power 3000.0 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,

---

<11 Reactor Power 2000 .0 1000 .0 0.0 ~~-~~-~~-~~-~~-~~~~~~-~~-~~-~~

0 200 4 00 600 800 1000 Time(s)

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-17 Figure 4-7 6.5 Inch Break - RCS and RV Masses Mass 400000 .0 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~

300000 .0

- RCS

............. RV

}

';'

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0 200 400 600 800 1000 Time (s)

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-18 Figure 4-8 6.5 Inch Break - Downcomer Level Downcomer Level 30 .0 - - - - - - - - - -- -------------------

DC Level - Average

- 20 .0 s

~

.5 "O

• 5 O"

.:::;

al

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0 200 400 600 800 1000 Time(s)

Controlled D0cun1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-19 Figure 4-9 6.5 Inch Break - Hot Assembly Collapsed Level Hot Asse mbly Collapsed Level 15.0 ~ ~ - - ~ - - ~ - - ~ - - ~ - - ~ - - ~ - - - - - - - - ~ - - ,

--11 Liquid Level 10 .0 g

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a 200 400 soo soo 1 ooo Time (s)

Controlled Docun1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-20 Figure 4-10 6.5 Inch Break - Hot Assembly Mixture Level Hot Assembly Mixture Level 10.0 Mixture Level 5.0 0 .0 .___ _....._._.___,___.___ _ _ _,___ _ _ _ _,___ _ _ _ _.___ _ _ _ ~

0 200 400 600 800 1000 Time (s)

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-21 Figure 4-11 6.5 Inch Break - Cold Leg Mass Flow Rates RCS Loop Flow Rates 15000.0 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

10000.0 Loop 1

............. Loop 2

.. Loop 3

\

5000.0 \\

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0 200 400 600 800 1000 Time (s)

Controlled Docu n1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-22 Figure 4-12 6.5 Inch Break - HHSI Mass Flow Rates HHSI Mass Flow Rates 30 .0 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~

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0 200 400 600 800 1000 Time (s)

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-23 Figure 4-13 6.5 Inch Break - LHSI Mass Flow Rates LHSI Mass Flow Rates 80.0 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~

60.0 Loop 1

• • -********* Loop 2

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0 200 400 600 800 1000 Time(s)

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-24 Figure 4-14 6.5 Inch Break- Accumulator Mass Flow Rates Accumulator Injection 2000 .0 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

l L

i 1500 .0 /\

I. Lo op 1

Lo op 2 I!

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0 200 400 600 800 1000 Time(s)

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis

• Page 4-25 Figure 4-15 6.5 Inch Break- Loop Seal Upside Collapsed Levels Loop Seal Upside Collapsed Liquid Level

\r"'1 g

.;

10.0

, I

. I Cl)

,,*5

...J er

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u 5 .0 Loop 1 Loop 2

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0 200 400 600 800 1000 Time(s)

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-26 Figure 4-16 6.5 Inch Break - SG Upside Tube Collapsed Level, Broken Loop Upside Tube Collapsed Liquid Level 30 .0 SG 1 Upside Tubes g **-* SG 2 Upside Tubes

.; - -.._ SG 3 Upside Tubes

...J "O

J

...J 20 .0 "O

~

a.

~

0

(.)

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0 200 400 600 800 1 000 Time (s)

Controlled Docun1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-27 Figure 4-17 6.5 Inch Break - Secondary Mass SG Total Mass 180000.0 . - - - - - - - - - - - - - - - - - - - - - - - - - - - - , . - - - - - - - - - - - ,

---

SG 1

---

* SG 2

• SG 3 160000.0

-;}

140000 .0

Time(s)

Controlled D0cun1ent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-28 Figure 4-18 6.5 Inch Break - MFW Mass Flow Rates SG MFW Flow Rates SG 1 1000 .0

• SG 2 U)

.0 v

& SG 3

~

0::

3:

0 u::

l

500 .0 0 .0 **********- )&*******' ************ -* ****$}*,.*** ********* **** *******£: ....... J. *** * ***"'******i& ****'** **** * *** *********>Ii** ******** * .......... , ** ******** * ....... .l .. * .... &***** .....,...* **** . . ;& *+ *****

0 200 400 600 800 1000 Time (s)

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-29 Figure 4-19 6.5 Inch Break - AFW Mass Flow Rates Auxiliary Feedwater Flow

.. a A . . . . . .. . ... . .

- - - 1 1 SG 1

---. SG2 15.0 .. SG 3 iii a:: 10.0

~

0 u::

l 5 .0 0 .0 ........... ,.... ;............ ........ ,............. 1.... ....................... , ..........J........ .................., ********** ************ 1 ********* * .... . .......... J. .........., ............, .................. .....

0 200 400 600 800 1000 Time (s)

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-30 Figure 4-20 6.5 Inch Break - MSSV Mass Flow Rates MSSV Flow SG 1 Total

-*---------* SG 2 Total

---

~ SG 3 Total 100 _0

.0

~

Cl::

~

U::

C1I

50 _0 o.o ..- ~ ... * .. . .... :,& ., ......... .. ... ........ :<< ........,. *** .,...... * .... , . ....... .. .... ;ik * ..... ** * *********" ~ -** ......... J. ** ....* . , . . . ........ ** *****' *.4.: + .. .

0 200 400 600 800 1 ODO Time(s}

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-31 Figure 4-21 [ ]

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-32 Figure 4-22 [

]

Controlled Docurnent Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-33 Figure 4-23 [

]

J

Controlled Document Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 4-34 Figure 4-24 [

]

L_

Controlled Docun1e,nt Framatome Inc. ANP-3467NP Revision 0 North Anna Fuel-vendor Independent Small Break LOCA Analysis Page 5-1

5.0 REFERENCES

1. EMF-2328(P)(A) Revision 0, "PWR Small Break LOCA Evaluation Model ,

S-RELAP5 Based ," March 2001 .

2. EMF-2328(P)(A) Revision O; Supplement 1(P)(A} , Revision O "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based ," September 2015.

3. Code of Federal Regulations, Title 10, Part 50, Section 46 , "Acceptance Criteria For Emergency Core Cooling Systems For Light-Water Nuclear Power Reactors ," January 2010 .

4. XN-NF-81 -58(P)(A) Revision 2, "Supplements 1 and 2, RODEX2 FUEL Thermal-Mechanical Response Evaluation Model ," Exxon Nuclear Company, March 1984.

5. ANF-81-58(P)(A) Revision 2, Supplements 3 and 4, "RODEX2 FUEL Thermal-Mechanical Response Evaluation Model ," Advanced Nuclear Fuels Corporation, June 1990.

6. Code of Federal Regulations, Title 10, Part 50 , Appendix K, "ECCS Evaluation Models," March 2000.

7. Office of Nuclear Reactor Regulation , NUREG-0737 "Clarification of TMI Action Plan Requirements" November 1980.

8. NRC Generic Letter 85-12 "Implementation of TMI Action Item 11.K.3.5,

'Automatic Trip of Reactor Coolant Pumps', (for Westinghouse NSSSs)"

June 1985.

9. NRC Generic Letter 86-06 "Implementation of TMI Action Item 11.K.3.5 ,

'Automatic Trip of Reactor Coolant Pumps', (for CE NSSSs, except Maine Yankee)," May 1986.