ML13074A794

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Amendment I Operational Assessment for Songs Unit 2 Steam Generators for Tube-To-Tube Wear Degradation 100% Power Operation Case
ML13074A794
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 03/31/2013
From:
Intertek APTECH
To:
Office of Nuclear Reactor Regulation
References
TAC ME9727 1814-AG117-M0026, Rev 0, AES 13018304-2Q-1, Rev 0
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ENCLOSURE 1 Amendment I Operational Assessment for SONGS Unit 2 Steam Generators for Tube-to-Tube Wear Degradation 100% Power Operation Case

Intertek AES 13018304-2Q-1 Controlled Document 1-8 Revision 0 March 2013 Amendment I OPERATIONAL ASSESSMENT FOR SONGS UNIT 2 STEAM GENERATORS FOR TUBE-TO-TUBE WEAR DEGRADATION 100% POWER OPERATION CASE Prepared By Intertek APTECH 601 West California Avenue Sunnyvale, California 94086-4831 Supplier Status Stamp VPL 1814-AG117-M0026 Rev 0 IQc: N/A No: No:

E-DESIGN DOCUMENT ORDER NO. 800918458

_[,REFERENCE DOCUMENT-INFORMATION ONLY E-VIRP IOM MANUAL MFG MAY PROCEED: OYES f"NO9 XNIA STATUS - A status is required for design documents and is optional for reference documents. Drawings are reviewed and approved for arrangements and conformance to specification only. Approval does not relieve the submvter from the responsibilit,./of adequacy and suitability of design. materials. and/or equipment represented.

1. APPROVED
2. APPROVED EXCEPT AS NOTED - Make changes and resubmiL

.NOT APPROVED -Correct and resubmit for review. NOTifor field use.

APPROVAL: (PRINT ISIGN BATE)

FLSthe 3113 1I Other.

SCE DE(123) 5 REV. 3 07/11

REFERENCE:

SO 123-XXIV-37.8.26 Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 I-i 1814-AG117-M0026, REV. 0 Page 1 of 41 COLOR IS RELEVANT

This report was preparedby Intertek APTECH as an account of work sponsored by the organization named herein.

Neither Intertek APTECH nor any person acting on behalf of Intertek APTECH: (a) makes any warranty, express or implied, with respect to the use of any information, apparatus,method, or process disclosed in this report or that such use may not infringe privately owned rights; or (b) assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information,apparatus,method, or process disclosed in this report.

Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1814-AG117-M0026, REV. 0 Page 2 of 41

APPROVAL RECORD SHEET Report No.: AES 13018304-2Q-1 Rev.: 0 Date: March 2013 Report

Title:

"Amendment I- Operational Assessment for SONGS Unit 2 Steam Generators for Tube-to-Tube Wear Degradation - 100% Power Operation Case" Originated By:

Project Engineer Date Reviewed By:

Project Engineer Date Approved By: c3i / 2 /'2L.

Project Manager Date Verified By: I*A,*-4 24(3

'Verifier Date QA Approved By:

QA Manager D te Intertek APTECH Southern California Edison AES 13018304-20-1 March 2013 I-iii 1814-AG117-M0026, REV. 0 Page 3 of 41

TABLE OF CONTENTS Section Page Executive Sum m ary ........................................................................................................ I-v 1.1 Introduction ............................................................................................................... 1.1-1 1.2 Structural Requirem ents ................................................................................................. 1.2-1 1.2.1 Structural and Leakage Integrity ......................................................................... 1.2-1 1.2.2 Assessment Overview ........................................................................................ 1.2-2 1.2.3 Probabilistic Model ............................................................................................. 1.2-3 1.2.3 Tube Burst Model ................................................................................................ 1.2-4 1.2.4 Leak Rate Calculation ......................................................................................... 1.2-5 1.3 Assum ptions and Conditions ......................................................................................... 1.3-1 1.4 Analysis Input Param eters ............................................................................................. 1.4-1 1.4.1 Tubing Properties ................................................................................................ 1.4-1 1.4.2 Operating Parameters ......................................................................................... 1.4-1 1.4.3 Degradation Characterization .............................................................................. 1.4-2 1.4.4 State of Degradation - W ear Index ..................................................................... 1.4-3 1.4.5 Tube Support Distributions .................................................................................. 1.4-4 1.4.6 Probability of Detection ....................................................................................... 1.4-5 1.4.6.1 Inspected Population .................................................................................. 1.4-5 1.4.6.2 Undetected Population ............................................................................... 1.4-6 1.4.7 Tube-to-Tube W ear Initiation ............................................................................... 1.4-7 1.4.8 Degradation Growth Rates .................................................................................. 1.4-8 1.4.8.1 AVB and TSP Growth Models .................................................................... 1.4-8 1.4.8.2 TTW Growth Model .................................................................................... 1.4-9 4.9 Measurement Uncertainty ...................................................................................... 1.4-9 1.5 Operational Assessm ent ................................................................................................. 1.5-1 1.5.1 Analysis Cases .................................................................................................... 1.5-1 1.5.2 Structural Margin Evaluation ............................................................................... 1.5-1 1.5.3 Leakage Evaluation ............................................................................................. 1.5-2 1.6 Analysis Verification and Validation .............................................................................. 1.6-1 1.7 References ............................................................................................................... 1.7-1 1.8 Nom enclature ............................................................................................................... 1.8-1 Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 I-iv 1814-AG1 17-M0026, REV. 0 Page 4 of 41

EXECUTIVE

SUMMARY

The San Onofre Unit 2 (Unit 2) plant has two new steam generators that replaced the original CE-70 design. The replacement steam generators are MHI Model 116TT1 and began operation in Year 2010. The generators have completed one cycle of operation (Cycle 16) with duration of 1.718 years at power (20.6 months). In the first cycle of operation, the Unit 2 tubing has experienced wear degradation at points of contact with anti-vibration bar (AVB) U-bend supports. There were 4348 indications detected at AVB contact points with a maximum Non-Destructive Examination (NDE) depth of 35%TW found during the end-of-cycle (EOC) 16 tube examinations. To a much lesser extent, wear at tube support plates (TSP) was also detected (364 indications) with a maximum NDE depth of 20%TW.

While Unit 2 was in refueling, San Onofre Unit 3 (Unit 3) had a forced outage due to a leak in one of the steam generators after 338 days (0.926 years at power or 11.1 months). The leak was due to tube-to-tube wear (TTW) at freespan locations within the U-bend region. Tube-to-tube wear in Unit 3 was caused by in-plane motion of tubes within a defined region of the bundle. The in-plane motion was due to conditions that created fluid-elastic instability (FEI) of one or more tubes. Subsequent examination of Unit 2 steam generators specifically looking for TTW revealed two indications in steam generator (SG) 2E089. Because of the generic designs of both units, and the nature of the FEI, the possibility of having further initiation and progression of TTW in Unit 2 is addressed.

This report describes the Operational Assessment (OA) performed for the limiting steam generator (SG 2E-089) in Unit 2 for a simulated population of TTW degradation indications under 100% power operation. The original Unit 2 OA was for reduced power operation at 70%.

This report is Amendment I to the original OA. A full description of the 70% power OA is given in Ref. 1.

In Ref. 1, a probabilistic model representing the high-wear region of the tube bundle was used to evaluate TTW for the next inspection interval. Calculated tube burst and leakage probabilities Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 I-v 1814-AG117-M0026, REV. 0 Page 5 of 41

were obtained by Monte Carlo simulation for initiation and growth of TTW. The results for burst and leakage were compared with the structural and leakage performance margin requirements of Nuclear Energy Institute (NEI) 97-06. The performance standards for assessing tube integrity to the required margins are delineated in the Electric Power Research Institute (EPRI) Integrity Assessment Guidelines (Ref. 2). This assessment established the probability of burst for the worst-case tube due to TTW predicted for the defined high-wear region.

The Unit 3 wear behavior was used to establish the initiation and growth of TTW indications in Unit 2 steam generators. An empirical correlation based on a wear index parameter (measure of the state of wear degradation in each tube) provided the method for scaling the Unit 3 wear behavior to Unit 2. Modifications were made to the original OA model to include a revised TTW growth rate distribution that incorporates the estimated initiation times associated with each occurrence of TTW in Unit 3 steam generators.

Two OA analysis cases were evaluated based on the sizing techniques used to define the Unit 3 TTW depths. Case 1 evaluated the situation where voltage based sizing for Eddy Current Testing Examination Sheet (ETSS) 27902.2 was used to establish the TTW depth distributions and the correlated wear rate with wear index. The results for Case 1 indicate that the Structural Integrity Performance Criteria (SIPC) margin requirements are satisfied for an inspection interval length of 0.94 years at 100% power level. For Case 2, where the TTW depths were resized by AREVA using a more realistic calibration standard, the SIPC margins will be met for an inspection interval length of 1.04 years at 100% power level. The plan for Unit 2 is to operate for an inspection interval of 5 months at a 70% power to provide additional margin to the industry requirements for tube integrity.

Tube burst at 3xNOPD (Normal Operating Pressure Differential) is the limiting requirement for inspection interval length. Therefore, the accident-induced leakage requirements will be satisfied provided that burst margins at 3xNOPD are maintained during the inspection interval.

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1.1 INTRODUCTION

An Operational Assessment (OA) is a forward-looking evaluation of the steam generator (SG) tube conditions that is used to ensure that the structural integrity and accident leakage performance will not be exceeded during the next inspection interval. The OA projects the condition of SG tubes to the time of the next scheduled inspection outage and determines their acceptability relative to the tube integrity performance criteria.

San Onofre Unit 2 (Unit 2) OA for the next inspection interval is documented in the original OA (Ref. 1). The original OA was completed for 70% power level using operating parameters for temperature, flow, and normal operating pressure differential (NOPD) for the tubes after plugging (Ref. 1). The degradation mechanism evaluated is tube-to-tube wear (TTW). Tube-to-tube wear is caused by in-plane motion of tubes. The in-plane motion is due to conditions that created fluid-elastic instability (FEI).

San Onofre Unit 2 has two new steam generators that replaced the original CE-70 design. The replacement steam generators are MHI Model 116TT1 and began operation in 2010. The generators have completed one cycle of operation (Cycle 16) with duration of 1.718 years at power. In the first cycle of operation, the Unit 2 tubing has experienced wear degradation at anti-vibration bar (AVB) U-bend supports. Wear at tube support plates (TSP) was also detected during the end-of-cycle (EOC) 16 tube examinations. A schematic illustration of the tube supports, AVBs labeled B01 through B12 and TSPs labeled 01C through 07C on the cold-leg side and labeled 01H through 07H on the hot-leg side, is shown in Figure 1.1-1.

This report serves as an amendment to the original OA. The analysis in this report performs an OA for 100% power. Similar to the original OA, probabilistic simulation methods were used.

These methods establish the tubing structural and leakage margins following standard industry guidelines. These margins are compared with the structural integrity and leakage performance criteria requirements of Nuclear Energy Institute (NEI) 97-06. The performance standards for assessing tube integrity to the required margins are provided in the Electric Power Research Institute (EPRI) Integrity Assessment Guidelines (Ref. 2). This approach established the probability of burst (POB) for the worst-case tube due to TTW.

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07H - -43.66-06H0C I I 43.G6' 05H - 05C 43.66" 02H 02C 43.661 I *1 TSH 01H T - H l TS0C 03C 43.GG" 4342A" TEHS TEC ___

Figure 1.1-1 SONGS Steam Generator Tube Support Structure Schematic (Ref. 1)

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1.2 STRUCTURAL REQUIREMENTS An OA projects the condition of the steam generator tubes and establishes the allowable inspection interval over which tube integrity performance criteria will be satisfied. In this OA, the TTW degradation mechanism is evaluated for 100% power operation.

1.2.1 Structural and Leakage Integrity The structural integrity performance criteria (SIPC) and accident-induced leakage performance criteria (AILPC) applicable to any degradation mechanism including TTW are as follows (Ref. 2):

Structural Integrity - "All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads."

Accident-Induced Leakage - "The primary to secondary accident leakage rate for the limiting design basis accident shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all steam generators and leakage rates for an individual steam generator."

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For SONGS, the accident-induced leak rate is 0.5 gallons per minute (gpm) per generator cumulative for all degradation mechanisms.

The acceptance performance standard for structural integrity is (Ref. 2):

The worst-case degraded tube shall meet the SIPC margin requirements with at least a probability of 0.95 at 50% confidence.

The worst-case degraded tube is established from the estimation of lower extreme values of structural performance parameters (e.g., burst pressure) representative of all degraded tubes in the bundle for a specific degradation mechanism.

The acceptance performance standard for accident leakage integrity is (Ref. 2):

The probability for satisfying the limit requirements of the AILPC shall be at least 0.95 at 50% confidence.

The analysis technique for assessing the above conditions for TTW is a fully probabilistic assessment of the Unit 2 steam generators.

1.2.2 Assessment Overview A probabilistic OA involves the analytical evaluation of inspection data in conjunction with a structural (burst) model for comparing the likelihood of tube burst with the SIPC margin requirements. Through-wall leakage probabilities must satisfy the accident-induced leak rate limits. An allowable inspection interval is established by demonstrating the SIPC and AILPC standards will be satisfied for the inspection interval.

For the probabilistic OAs for TTW degradation, the probability of detection (POD), the wear rate, and initiation function for creating new wear indications are explicitly treated by statistical distributions for direct input to the structural model. In addition, distributions for tubing strength and relational uncertainties on the tube burst model are addressed in accordance with industry guidelines.

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The OA for TTW is performed with a single-cycle model applied to a defined region where TTW is assumed active. The models for TTW initiation and the determination and assignment of TTW growth rates are critical input variables to the OA.

1.2.3 Probabilistic Model A Monte Carlo simulation process was used to solve the probabilistic model for TTW. The simulation process is shown in Figure 1.2-1, which illustrates one Monte Carlo trial. The probabilistic model includes TTW initiation, growth, and structural integrity analysis for the degraded tubes projected to the next inspection. Tubes that have been preventatively plugged based on wear patterns and other attributes have been removed from the population. This includes Tubes R1 13 C81 and R1 11 C81 in SG-2E089 with detected TTW. The population of tubes at the start of the next inspection interval includes inservice tubes that have detected AVB and TSP wear and tubes with No Detectable Degradation (NDD) within the high wear region.

Wear degradation of the steam generator tubing is simulated in the model for the population of indications in the high wear region. The attributes assigned to each degraded tube are the depth and length of the indications, material properties, and the degradation growth rate. These parameters are treated randomly and the calculation of burst pressure is made for each indication in the population.

The major steps in the process are:

1) TTW initiations are predicted based on the wear degradation state. This is accomplished with the total wear index parameter calculated from existing AVB and TSP wear. The initiation of TTW and initial depth is based on total wear index values calculated during operation as a result of further growth of AVB and TSP wear.
2) Attributes are randomly defined for each degraded tube for a single trial representing one inspection interval. These include tube strength properties, the TTW degraded length, and the TTW indication shape factor. The population of degraded tubes at the beginning of the inspection interval contains the tubes with potential undetected TTW.
3) Growth of the TTW degradation for the inspection interval is established by sampling from the Unit 3 wear rate distribution dependent on the total wear index at the time of initiation. The TTW growth model differs from the version used in the original OA (as Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.2-3 1814-AG117-M0026, REV. 0 Page 11 of 41

discussed in section 1.4.8). The size distribution of the TTW degradation is defined in this step.

4) The population of TTW indications is evaluated for burst pressure and leakage at the end of the inspection interval. The degraded tube with the lowest burst pressure is recorded for each trial to establish the distribution of worst case values for comparing with the SIPC margin requirements and acceptance standards. Likewise, the leakage probabilities for each trial are recorded to determine the 95% probability with 50%

confidence (95-50) leak rate for comparison with AILPC.

The simulation process generates a record of the results of all trials performed from which overall burst and leakage probabilities are calculated and appropriate distributional information obtained.

The OA methodology is discussed in Sections 3 and 5 of the original OA. The same fully probabilistic modeling approach and numerical algorithm was followed for computing tube burst probabilities for TTW degradation.

1.2.4 Tube Burst Model TTW indications are characterized by axial volumetric degradation with limited circumferential extent. The burst pressure for TTW is computed from the burst relationship for length and depth dimensions of axial wear given in Ref. 3:

Pb = 0.58(Sy +Su)(t/Ri)1 SL+2t _ +L(d/t)+291 Psi+ZOB (1.2-1) where:

Pb is the estimated burst pressure SY is the yield strength Su is the ultimate tensile strength t is the wall thickness R, is the tube inner radius Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.2-4 1814-AG117-M0026, REV. 0 Page 12 of 41

L is the characteristic degradation length d is the characteristic wear depth d/t is the fractional normalized depth Relational uncertainty in Eq. 1.2-1 is represented by the standard normal deviate, Z, (-oo < Z <oo),

and GB, the standard error of regression (GB = 282 psi). The burst equation, when used with the structural significant dimensions (LST and dsT), produces consistently conservative burst pressure estimates compared with tube burst data (Ref 3).

1.2.5 Leak Rate Calculation Leakage predictions for wear-related degradation are subject to large uncertainties. Wear profiles at incipient leakage can vary significantly from simple slits to large holes caused by the blowout of thin membranes. For these situations, absolute leakage rates are not generally computed. Rather, the probability of through-wall penetration is established from projected maximum depths and ligament rupture calculations. A ligament rupture is where the indication pops through the remaining wall without causing tube burst. For TTW, leakage at limiting accident conditions (i.e., main steam line break) will not be controlling on inspection interval length. The depths required for burst at SIPC are much smaller (bounding) than the depths necessary to produce ligament rupture (pop-through) events under accident pressures. SIPC is therefore the controlling criteria.

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F-K" Figure 1.2 Operational Assessment Logic Flowchart (One Monte Carlo Trial Illustrated)

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1.3 ASSUMPTIONS AND CONDITIONS The following are the major assumptions and analysis conditions used in this and the original OA model for TTW and input parameters:

1) TTW is analyzed as a stochastic process of independent events based on the state of tube support wear degradation of each individual tube in the high wear region at any point in time during the inspection interval.
2) The critical region for evaluation is assumed as a box area defined by Rows 70 to 140 and Columns 60 to 120. This region bounds the high-wear region in the U-bends.
3) The state of wear degradation at tube supports for a given tube is assumed to be characterized by the summation of NDE depths at AVBs and TSPs wear locations. This is defined as the "wear index" for a degraded tube. This is the same index definition as used in the original OA as described in Ref. 1.
4) The Unit 3 data for TTW is used to define the likelihood of initiating TTW and what will be the TTW growth rate. These data are used to establish the probability of initiation and growth of TTW in Unit 2 through the wear index parameter.
5) The wear rate is based on constant growth on depth rather than constant wear volume basis. This assumption is conservative since wear generally evolves on a constant volume rate basis where the rate of change in depth will decrease as wear progresses.
6) It is assumed at the start of Cycle 17, that any tube within the high wear region can initiate TTW including tubes with no detected support wear at the beginning of the cycle.

This is a conservative assumption.

A key analysis condition in the probabilistic model is a measurable amount of AVB and TSP wear precedes tube instability and subsequent tube-to-tube contact.

The assumptions and conditions below are used only in this OA:

1) A variable non-zero initiation-time analysis is used to establish TTW growth rates.
2) The NOPD for Cycle 17 is based on TCOLD restoration implementation with 3% plugging.

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1.4 ANALYSIS INPUT PARAMETERS The input parameters for the OA for TTW by fully probabilistic methods are discussed in this section. Much of this information is given in the original OA but is summarized below for completeness.

1.4.1 Tubing Properties Each Unit 2 steam generator has 9727 tubes. The steam generator tubing has an outside diameter of 0.75 inch and a nominal wall thickness of 0.043 inch. The tube material is Alloy 690 thermally treated (A690 TT). The mechanical properties corrected to a temperature of 650°F were provided by AREVA with the following parameters for Sy + Su:

Tubing Yield plus Ultimate Strength Values (psi)

Parameter S/G 88 S/G 89 SY + Su (mean) 115,361 116,633 SY + Su (St. Dev) 2,023 2,504 Sy+ Su (min) 108,700 109,900 Sy+ Su (max) 121,600 123,900 These values were obtained from the certified material test report (CMTR) data sheets for the supplied tubing. A plot of the distribution is shown in Figure 1.4-1.

1.4.2 Operating Parameters Tube pressure differential under normal operating conditions during Cycle 16 was 1430 psi (Ref. 4). The operating conditions assumed for the next cycle of operation for 100% power conditions after plugging are listed below (Ref. 5).

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Cycle 17 Operating Parameters Parameter 100% Power Thermal power (MWt)/SG 1729 Tcold, (F) 550 RCS pressure, (psia) 2250 Steam pressure, (psia) 926 NOPD, (psi) 1324 Note: NOPD with TCOLD restoration implemented at 100% w/3% plugging Three times normal operating pressure (3xNOPD) for the inspection interval is 3972 psi. For accident conditions, maximum steam line break pressure is assumed at 2560 psi (Ref. 1). The limiting SIPC requirement is 3xNOPD.

1.4.3 Degradation Characterization Tubes assumed to be susceptible to TTW are located in the high wear region. Wear patterns for AVB and TSP wear were within a region of tubes defined by rows 70 to 140, and columns 60 to 120. The table below shows the nature of degradation within the defined high-wear region.

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Summary of Degraded Tubes in the SG 2E-089 Steam Generator High Wear Region at BOC 17 (Ref. 1)

Description (High Wear Region) SG 2E-089 Total Number of Tubes 2121 Tubes Plugged* 211*

Number of TTW Indications 2 Number of AVB Indications 2537 Number of TSP Indications 90 TSP Indications with No AVB wear 11 BOC Tubes with Wear Degradation 560 BOC NDD Tubes 1350

  • Note: Three additional tubes were preventatively plugged after the original OA.

They were conservatively treated as in-service tubes in this analysis for consistency with the original OA.

Previously undetected wear indications at AVB and TSP supports are randomly assigned to the NDD tubes using the cumulative distributions developed from past observed active wear for SG 2E-089 as shown in Figure 1.4-2. Depths for these wear indications are defined by the POD performance for the bobbin probe (see Section 1.4.6).

The shapes of the TTW indications were determined by line-by-line +PointTM sizing for Unit 3 tubes. The shape factor parameter (F) is defined as the ratio of maximum depth of the indication to the structural average depth of the indication, dMAx/dsT. The shapes were relatively flat (F=1.0) with long structural lengths. The structural lengths (LsT) as determined by the structural-minimum method using the profile data from Unit 3 is shown in Figure 1.4-3 (Ref. 1).

The cumulative distribution function (CDF) of these data is fitted to a log-normal model.

1.4.4 State Of Degradation - Wear Index TTW is assumed to initiate when the tube becomes unstable in the in-plane direction under local fluid-elastic conditions. TTW is analyzed as a random process of independent events based on the state of degradation of each individual tube in the high wear region during the inspection interval. This OA uses wear degradation at tube supports (AVBs and TSPs) as a direct indicator of both the likelihood of occurrence and severity of TTW during the inspection interval.

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A key assumption in the probabilistic model is that a measurable amount of AVB and TSP wear precedes tube instability and subsequent tube-to-tube contact.

The total wear index is used to define the state of degradation of individual tubes. The total wear index parameter relates the observed AVB and TSP wear states of each tube in the high-wear region to both TTW initiation and growth rate. The same total wear index model used in the original OA is used in this analysis. The total wear index model is based on the summation of AVB and TSP wear depths in a given tube.

Total Wear Index = AVB Wear + TSP Wear WI [AVB depth]i + I" [TSP depth], (1.4-1) where the total wear index is defined in %TW.

This measure was chosen to capture both the total amount of wear as well as the loss of effective support, both of which are assumed to be precursors to in-plane tube instability and the initiation of TTW for a given tube. The total wear index measures the loss of wall thickness due to the vibratory activity of the tube. This loss of wall thickness can adversely affect support effectiveness from changes in tube to support gaps.

1.4.5 Tube Support Distributions The model considers two cases which assume additional support wear in tubes located in the high wear region:

1) Tubes with no detected wear that may have low level of wear at tube supports
2) Tubes that have detected support wear but may develop additional wear at tube supports during the next inspection interval The number of affected supports is reflected in the wear index on a tube-by-tube basis. The number of affected tube supports used in this analysis for Unit 2 is shown in Figure 1.4-2.

The Unit 2 data shown in Figure 1.4-2 for the number of affected wear locations was used to assign wear at support locations in those tubes with no detected wear in the most recent Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-4 1814-AG117-M0026, REV. 0 Page 19 of 41

inspection. All tubes with no detected wear within the high wear region are conservatively assumed to have wear at an assigned number of AVB and TSP locations at the start of the next inspection interval. The number of tube support locations assigned with AVB and TSP wear is determined by sampling from the cumulative distributions derived from Figure 1.4-2. On average, each tube with no detected wear is assigned five tube support locations with wear.

Wear depths are assigned at these wear locations based on the POD for the bobbin probe as discussed in Section 1.4.6.

For tubes in the high wear region with detected support wear, additional support wear locations were assigned. Operating experience (OE) for a similar replacement steam generator provides data on the evolution of tube support wear after two cycles of operation. The number of additional AVB supports that developed wear in the second cycle of operation depends on the number of first cycle detected AVB wear locations in each tube. The OE data were used in the OA to add AVB wear locations at the start of the Cycle 17 inspection interval using a statistical representation. Since the number of TSP wear locations in the OE data did not increase, only the increase AVB wear locations was modeled in the OA. When new AVB wear locations are added to a given tube, wear is assumed to start at the beginning of the inspection interval from an initial zero depth.

Wear from all AVB and TSP supports (including the newly added AVB support locations) are used in the total wear index for the tube.

1.4.6 Probability of Detection 1.4.6.1 Inspected Population The probability of detection performance of the bobbin probe demonstrates it is capable of reliably detecting AVB wear, TSP wear, and TTW indications in the U-bend region. The probability of detection for eddy current test techniques has been established from industry data and made available through published Examination Technique Specification Sheet s (ETSS).

For ETSS 96004.1, Rev. 13, the POD function is shown as a log-logistic function in Figure 1.4-4.

For comparison, the POD function for +PointTM inspection (ETSS 27902.2) is also plotted in this figure. The log-logistic model for POD and the parameters for the examination techniques used for support and TTW, are given below:

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POD(h) 1 + exp[A + B Log(h)]j (1.4-2)

Probe ETSS Intercept (A) Slope (B)

Bobbin 96004.1 10.61 -11.20

+PointTM 27902.2 14.24 -17.22 where h = d/t and is the degradation depth in % TW. The parameters for ETSS 96004.1 were derived from hit-miss ECT data used to establish the ETSS data statistics.

Tubes within the high-wear region that had significant AVB and TSP wear in Unit 2 had received bobbin probe examination. Subsequent to the Unit 3 inspection findings, supplemental +PointTM inspections were performed in Unit 2 to look for TTW with an improved POD. Two TTW indications were found in SG 2E-089 and no indications were detected in SG 2E-088. The most susceptible group of tubes within the high-wear region has been examined with a more sensitive inspection with an improved POD.

1.4.6.2 Undetected Population The POD function is used to define the population and depth of the undetected AVB, TSP, and TTW indications at the start of the inspection interval.

For the tubes with no detected wear within the high-wear region, wear sites are assigned at AVB and TSP locations that are assumed to develop wear during the inspection interval (discussed in section 1.4.5). The wear depths are defined by the bobbin probe POD performance for an assumed threshold level (POD < 0.05).

I' 1 1 Ln[ (POD) -

Logl 0 (h)= RN (OD) (1.4-3) where:

Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-6 1814-AG117-M0026, REV. 0 Page 21 of 41

h is the wear depth equal to (d/t), expressed as % TW POD is the assumed threshold level for NDD (POD < 0.05)

RN is a randomly selected number between 0 and 1 A and B are constants (intercept and slope) in the log-logistic function for the bobbin probe POD The wear depths are determined by a random process with equation 1.4-3 used for each assigned support wear location in the 1350 tubes without detected wear. The bobbin probe POD is used in this process.

1.4.7 Tube-To-Tube Wear Initiation The initiation of TTW was established through an empirical model relating the probability of initiation (POI) for TTW to the total wear index parameter. The same POI model developed for the original Unit 2 OA (Ref. 1) is used in this OA (see Figure 1.4-5). This model is based on the total wear index value for each tube within the high-wear region. The total wear index parameter relates the observed AVB and TSP wear states of each tube in the high-wear region to the POI function. Further details on the benchmarking process to obtain the POI model parameters for Unit 2 are discussed in Ref. 1.

The Unit 2 initiation model is implemented such that both the POI and the time when initiation occurs can be established. It is possible undetected TTW may exist in some tubes at the start of the inspection interval or may initiate during the inspection interval. The initiation model includes these possibilities, which are illustrated in Figure 1.4-6. In the figure, the total wear index for an example tube at BOC and EOC for the Cycle 17 inspection interval is shown. The initiation of TTW is evaluated using a random process. TTW does not initiate when the combination of the EOC total wear index and the random sample produces a value greater than POI curve.

For cases where initiations are predicted to occur during the inspection interval, the point of initiation is determined by the intersection of the random sample with the POI value for the model function as shown by the "X"on the middle dashed line. In this case, initiation is calculated to occur at a wear index between the inspection interval BOC and EOC values. The initiation time is determined by linear interpolation of the total wear index over time. The TTW Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-7 1814-AG117-M0026, REV. 0 Page 22 of 41

indication is assumed to start growing at the time of initiation with an initial depth of zero and at a wear rate determined from the total wear index value at the time of initiation.

The bottom horizontal dashed line in Figure 1.4-6 shows the case when initiation was calculated to occur during the prior inspection interval (Cycle 16). In this case, TTW initiation is determined to have occurred during Cycle 16. Because the tube had no detected TTW at EOC 16, the TTW indication is assumed to continue to grow from the beginning of the Cycle 17 inspection interval.

The starting depth is determined by a random selection process from the lower 5% detection level of the +PointTM POD curve, with a wear rate determined from the Cycle 17 BOC total wear index value. The time of growth is the inspection interval length.

1.4.8 Degradation Growth Rates Wear rates for three mechanisms are required for the OA of TTW. The required wear rate distributions are for AVB wear, TSP wear, and TTW. All wear rates are conservatively based on a constant growth in depth.

1.4.8.1 AVB and TSP Growth Models The AVB and TSP wear rates are used to evaluate the increase in total wear index for each tube during the inspection interval. The increase in total wear index is due to the individual growth in AVB and TSP wear depths. The wear rates for AVB degradation were developed from Unit 2 EOC 16 NDE data (Ref. 1). The distribution of wear depths at each of the 12 AVB and 14 TSP tube intersections for Unit 2 is shown in Figure 4-8 of the original OA (Ref. 1). AVB and TSP wear rates used in this OA are the same as those used in the original OA.

The wear rate distributions for AVB and TSP wear are shown in Figure 1.4-7. The AVB wear rate distribution was developed using conservative wear data (AVBs 4 to 9 as discussed in Ref.

1 for Group 3) from both steam generators. The TSP wear rate distribution uses all the data from both steam generators. The two functions are based on a lognormal statistical model for sampling in the simulation.

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1.4.8.2 TTW Growth Model The TTW growth rates for Unit 2 were developed from the TTW wear depth data observed in Unit 3. To establish TTW growth rates for 100% power operation for Unit 2, a variable initiation-time model was used to estimate the time at which TTW began in each affected tube in Unit 3.

This approach differs from that used in the original OA (Ref 1) for 70% power where TTW initiation was assumed to occur at beginning of Cycle 16 for Unit 3 (i.e., zero initiation time).

The development of the variable initiation-time model is discussed in Ref. 6.

The results of the variable initiation-time model on TTW growth rate is shown in Figure 1.4-8.

The two OA cases for ETSS 27902.2 sizing and AREVA resizing model of the TTW depths are discussed in the original OA (Ref 1). The TTW growth rates were calculated and the regression lines shown in Figure 1.4-8 for the two sizing cases yields the following parameters for 100%

power:

Case Intercept Slope Error

(%TW) Slope (%TW)

ETSS Sized 30.565 0.0594 13.93 AREVA Resized 23.072 0.06416 14.16 The residuals from the regression analysis are well modeled by a normal distribution over the range of interest for wear index. The relational error for both regression models is normally distributed with a mean of zero and a standard deviation as given in the above table.

1.4.9 Measurement Uncertainty Measurement uncertainty for sizing of indications is defined in the ETSS for estimating actual (true) structural parameters (depth and length) from NDE wear size data. The 70% and 100%

power OA total wear index was based on NDE measured data for both the correlation and predictive models so that adjusting for measurement error was not required.

The need for including measurement uncertainty was assessed for assigning TTW wear depth and growth rates. Initial TTW depths were assigned at beginning of the interval based on Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-9 1814-AG117-M0026, REV. 0 Page 24 of 41

+PointTM POD which has negligible measurement error. Growth applied during the inspection interval was derived from Unit 3 +PointTM depth sizing (ETSS 27902.2) where the systematic error from linear regression is very small. Therefore, sizing uncertainty is not significant for estimating TTW growth rates.

Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-10 1814-AG117-M0026, REV. 0 Page 25 of 41

1.0 SONGS-2 Tubing Strength at 650°F 0.9 -.- 2SG88 2SG89 2---

0.8 U-0.7 0.6

.-0 0.5 E* 0.4 0

0.3 U.. _ _ _

0.2 0.1 0.0 1106 108 110 112 114 116 118 120 122 124 126 128 Sy + SU, (ksi)

Figure 1.4-1 - Distribution of Tubing Strength Properties at 650°F Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-11 1814-AG117-M0026, REV. 0 Page 26 of 41

SONGS-2 Distribution of Wear at AVB Supports 280 U12SG88 02SG89 240 220 200 180-160-140-120-E z 100-80-60-40-20-U]

0- [! nR I 0 1 2 3 4 5 6 7 8 9 10 11 12 Number of Affected Supports SONGS-2 Distribution of Wear at TSP Supports 0

E z

0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Number of Affected Supports Figure 1.4 Support Locations per Tube Exhibiting AVB and TSP Wear in Unit 2 Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-12 1814-AG117-M0026, REV. 0 Page 27 of 41

TTW Structural Length Distribution 1.0 0.9 0.8 0.7

.2 O.6 00.5 00.4 0.3 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 Structural Length,LST (inches)

Figure 1.4 Structural Length Distribution for TTW in Unit 3 Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-13 1814-AG117-M0026, REV. 0 Page 28 of 41

SONGS ECT Techniques 1.0 0.9 0.8 0.7 0

IL C

.2 0.6 i 0.5

- 0.4

.0

a. 00.3 0.2

- Bobbin Probe (ETSS 96004.1) 0.1 -+Point (ETSS 27902.2) 0.0 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 Depth, dlt (%TW)

Figure 1.4 Probability of Detection for Tube Wear Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-14 1814-AG117-M0026, REV. 0 Page 29 of 41

TTW Initiation Model 1.0 0.9 0.8 0.7 0.6 C

0 0.5

.2 0.4 0.3 0.2

  • SONGS-3 Data 0.1 _ --Beta Distribution Fit

-B-Adjusted Distribution for SONGS-2

+- in I I I-0.0 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Total Wear Index, WI (%TW)

Figure 1.4 Tube-to-Tube Wear Initiation Model Based on Total Wear Index Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-15 1814-AG117-M0026, REV. 0 Page 30 of 41

SONGS-2 Tube-to-Tube Wear Initiation Model 1.0 BOC EO(

0.9-0.8-Non Initiation tNolnitiation Region 0.7 0.6-0 0.5 Initiation During I I Initiation Region 0

C.

0.4-0.3-6adNDD atI Cyl

',/

0.20 EOC 16 - SONGS-2 POI Model (100% Power) w Wear Index at BOC and EOC 0.1 K TTW Initiation AIn 00V 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Total Tube Wear Index, WI (% TW)

Figure 1.4 Illustration of TTW Initiation Model Estimation Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-16 1814-AG117-M0026, REV. 0 Page 31 of 41

AVB Wear Rate - Group 3 (Both SGs)

Li-

.2 E

0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Rate, WR (%TW per Years at Power)

TSP Wear Rate (Both SGs) 1.0 0.9 0.8 a

0.7 g

0.6 0

0.5 0

N 0.4 S

U 0.3 0.2 0.1 0.0 0 2 4 6 8 10 12 14 16 18 20 Wear Rate, WR (%TW per Years at Power)

Figure 1.4 Wear Rate Distributions for AVB and TSP Wear Mechanisms Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-17 1814-AG117-M0026, REV. 0 Page 32 of 41

ETSS 27902.2 Sizing 110 100 90 0.

- 80

' 70 2L 60 e 50

  • 40 30 20 10 0

0 50 100 150 200 250 300 350 400 450 500 550 600 650 Total Wear Index, WI (%TW)

AREVA Resized 110 100 90 80 m 70 1L60 e 50

. 40

.6 30 20 10 0

0 50 100 150 200 250 300 350 400 450 500 550 600 650 Total Wear Index, WI (%TW)

Figure 1.4 Tube-to-Tube Wear Rate as a Function of Wear Index Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.4-18 1814-AG117-M0026, REV. 0 Page 33 of 41

1.5 OPERATIONAL ASSESSMENT 1.5.1 Analysis Cases The OA for TTW degradation was performed by Monte Carlo simulation with 10,000 trials applied to produce the minimum burst pressure and maximum depth distributions at the completion of the inspection interval. Two cases were evaluated that look at the effect of TTW rate models as described below:

Case 1 - Tube-to-tube wear rate based on the Unit 3 wear depths sized with ETSS 27902.2 (Ref. 1)

Case 2 - Tube-to-tube wear rate based on the Unit 3 wear depths sized with AREVA hybrid voltage model (Ref. 1)

Each case was evaluated for 100% power operation. The planned inspection interval is 5 months.

The NOPD value is 1324 psi and includes 3% plugging and TcoLo restoration.

1.5.2 Structural Margin Evaluation The structural analysis to establish the margins to tube burst was performed for the two analysis cases. The parameters for the input distributions are given in Table 1.5-1.

The structural analysis for tube burst was completed for a range of inspection intervals. The POB was determined from the distribution of worst case burst pressures which is compared to the SIPC margin of 3xNOPD. The POB was determined as a function of inspection interval as shown in Figure 1.5-1. The performance standard for SIPC margin for the POB for the TTW mechanism is 5%.

The following allowable inspection interval lengths have been computed:

Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.5-1 1814-AG117-M0026, REV. 0 Page 34 of 41

Inspection Interval Lengths at POB = 5%

1 Years at Analysis Case Y P 1100% Power Case 1 - ETSS 27902.2 Sizing 0.94 Case 2 - AREVA Resized 1.04 The allowable inspection interval at 100% power is 11 months based on Case 1.

1.5.3 Leakage Evaluation Due to the long and flat nature of TTW degradation, the tube burst at 3xNOPD is more limiting than the accident-induced leakage criteria. The limiting condition for the inspection interval is based on the SIPC.

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Table 1.5-1 OPERATIONAL ASSESSMENT INPUT PARAMETERS TTW FOR Unit 2 Distribution Type Parameters S/G 89 (1) Basis (2)

Log- Intercept, A 10.61 ETSS 96004.1 Probability of Detection Logistic Slope, B -11.20 (Ref. 12)

Log- Intercept, A 14.24 ETSS 27902.2 Probability of Detection Logistic Slope, B -17.22 (Ref. 13)

Mean Ln(WR) 1.68 Unit 2 AVB Wear Rate (% TW per Years at Power) Log Normal Std Dev Ln(WR) 0.45 (Ref. 6b)

Max Rate 20 Mean Ln(WR) 1.71 TSP Wear Rate (% TW per Years at Power) Log Normal Std Dev Ln(WR) 0.26 Unit 2 Max Rate 20 (Ref. 6b)

Intercept 30.565 Unit 3 TTW Rate (% TW) (3) ETSS 27902.2 Normal Slope 0.0594 (Ref. 13)

Std Dev 13.93 (3 Intercept 23.072 Unit 3 TTW Rate (%TW) AREVA Resized Normal Slope 0.06416 (Ref. 14)

Std Dev 14.16 TTW Initiation Model Beta Shape 1 9.839 Unit 3 Shape 2 39.138 (Ref.1Oa & 16))

Structural Length LST, (in.) Log Normal Mean Ln (LST) 1.28 Unit 3 Std Dev Ln (LsT) 0.26 (Ref. 11)

Shape Factor, F = dMAx/dsT Normal Mean (F) 1.00 Unit 3 Std Dev (F) 0.0 Ui Mean (Sy + Su) 116,633 Unit 2 Strength, Sy, + S, (psi) Normal Std Dev (Sy + Su) 2,504 CMTR Data Min (Sy + Su) 109,900 SG 2E-089 Max (Sy + Su) 123,900 (Ref. 1Ob) 1325 Normal Operating Pressure Differential, (psi) Constant NOPD at 100% 1305 (RefUnit7 2 1305 (Ref. 7 & 9)

Unit 23 Limiting Accident Pressure Differential, (psi) Constant LAPD 2560 (Ref (Ref. 3)

SCE RTS 4 Inspection Interval Length (Years at Power) Constant 0.42 Report( )

Notes (1) Wear in SG 2E-089 is limiting (2) Databases for Unit 2 and Unit 3 data and other listed references are from cited references in original OA (Ref. 1)

(3) TTW rates are shown in Figure 1.4-8 (4) Return to Service Report (Ref. 8)

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Operational Assessment for TTW for Cycle 17 at 100% Power 0.16 70% Power, Original OA, ETSS Sizing 70% Power, Original OA, AREVA Resizing I 0.14 E3 100% Power, NOPD=1 324 psi, ETSS Sizing

- 100% Power, NOPD=1324 psi, AREVA Resizing

- - - Mid-Cycle 17 (5 Months at Power) I

- Cycle 17 (1.578 Years at Power) 0.12

- SIPC Margin, POB < 0.05 -1

o. 0.1 l' I
  • ~0.08 j0.06 0

0.04

  • I 0.02

' I 0

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Inspection Interval, (Years at Power)

Figure 1.5 Probability of Burst at 70% and 100% Power Levels for TTW Growth Rate Models Based on Case I - ETSS 27902.2 Sizing and Case 2 - AREVA Resizing Models Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.5-4 1814-AG117-M0026, REV. 0 Page 37 of 41

1.6 ANALYSIS VERIFICATION AND VALIDATION A special-purpose computer program called TTWEARU2 Revision 1 (R1) was developed to perform the Monte Carlo simulation and required calculations as shown in Figure 1.2-1. This program is a revised version of the original program used for the 70% power OA. Verification and validation of TTWEARU2 Rev. 1 followed Intertek APTECH Quality Assurance Procedures for computer software and hardware systems as described in Section 3.5 of the original OA report (Ref. 1). The documentation of the verification and validation of TTWEARU2 R1 is given in Ref. 7.

Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.6-1 1814-AG117-M0026, REV. 0 Page 38 of 41

1.7 REFERENCES

1. "Operational Assessment for SONGS Unit 2 Steam Generators for Upper Bundle Tube-to-Tube Wear Degradation at End of Cycle 16," Intertek APTECH Report Number AES 12068150-2Q-1, (September 2012).
2. "Steam Generator Integrity Assessment Guidelines, Revision 3," Electric Power Research Institute, Steam Generator Management Program, EPRI Report 1019038, (November 2009)
3. "Steam Generator Degradation Specific Management Flaw Handbook, Revision 1,"

1019037, Electric Power Research Institute, Steam Generator Management Program (December 2009)

4. Letter from A. Matheny (SCE) to A. Brown (AREVA), "Numerical Values for the Steam Generator Operational Assessment San Onofre Nuclear Generating Station, Units 2 and 3," (February 8, 2012)
5. "Operating Parameters of Unit-2 RSGs for Various Power Levels after Plugging," MHI L5-04GA602, (January 23, 2013)
6. Calculation-C-8304-3, "initiation Time Model to Determine Tube-to-Tube Wear Rates for Unit 3 - RAI #2," Rev. 2, Intertek Project AES 13018304-2Q, (February 22, 2013)
7. "Verification of Program TTWEAR_U2 R1 for the Operational Assessment for SONGS Unit 2," Calculation No, AES-C-8304-5, Intertek APTECH, (March 2013)
8. Letter from Peter T. Dietrich (SCE) to Elmo E. Collins (NRC), Confirmatory Action Letter-Actions to Address Steam Generator Tube Degradation, San Onofre Nuclear Generating Station, Unit 2, October 3, 2012.

Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.7-1 1814-AG117-M0026, REV. 0 Page 39 of 41

1.8 NOMENCLATURE Acronym Description SG 2E-088 Unit 2 Steam Generator 88 SG 2E-089 Unit 2 Steam Generator 89 SG 3E-088 Unit 3 Steam Generator 88 SG 3E-089 Unit 3 Steam Generator 89 3xNOPD Three times normal operating pressure differential 95-50 95% probability at 50% confidence AILPC Accident Induced Leakage performance Criteria AVB Anti-vibration bar BOC Beginning of operating cycle CM Condition monitoring CYC Length of cycle EOC End of operating cycle EPRI Electric Power Research Institute ETSS Examination Technique Specification Sheets GPM Gallons per minute NDD No degradation detected NDE Non destructive examination NEI Nuclear Energy Institute OA Operational assessment POB Probability of burst POD Probability of detection POI Probability of initiation QA Quality assurance RAI Request for additional information RN Random number SG Steam generator Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.8-1 1814-AG117-M0026, REV. 0 Page 40 of 41

REPORT ACRONYMS (Cont'd)

Acronym Description SIPC Structural Integrity Performance Criteria SR Stability ratio TSP Tube support plate TTW Tube-to-tube wear TW Through wall Unit 2 San Onofre Unit 2 (also SONGS-2)

Unit 3 San Onofre Unit 3 (also SONGS-3)

WI Total wear index WR Wear rate Intertek APTECH Southern California Edison AES 13018304-2Q-1 March 2013 1.8-2 1814-AG117-M0026, REV. 0 Page 41 of 41

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