ML20083N860
| ML20083N860 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 07/28/1994 |
| From: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20071L473 | List: |
| References | |
| CAW-94-699, NUDOCS 9505230355 | |
| Download: ML20083N860 (9) | |
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q Nuclear Technolop Division Westinghouse Energy Systems - Electric Carperstlen go,333 Pritsburgh Pennsylvanla 15230-0355 July 28,1994 CAW-94-699 Dhment Control Desk US Nuclear Regulatory Commission Washington, DC 20555 Attention: . Mr. William T. Russell, Director APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
"Braidwood Unit 1 Technical Support for Cycle 5 Steam Generator Interim Plugging Criteria" (WCAP-14046) go-i$b .
Dear Mr. Russell:
De proprietary information for which withholding is being requested is further identified in Affidavit CAW-94499 signed by the owner of the proprietary information, Westinghouse Electric Corporation. We affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.790 of the Commission's regulations. I Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Commonwealth Edison Company. Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-94499, and should be addressed to the undersigned. Very truly yours, N. J. Liparu o, k anager Enclosures Nuclear Safety Regulatory and Licensing Activities cc: Kevin Bohrer/NRC (12H5) e 9505230355 940001 4 DR ADOCK 0500
CAW-94-699 AFFIDAVrr COMMONWEALTH OF PENNSYLVANIA: ss COUNTY OF ALLEGHENY: Before me, the undersigned authority, personally appeared Henry A. Sepp, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief: i h , M, Henry A. Sepp, Manager Regulatory and Licensing Initiatives Sworn to and subscribed before me this M day of J u fa4 ,1994 _, O Denke K Hannamon.Nowy Ndo MycommesionM2Ns
)) y Notary Public l
l uenc-amierJens
CAW-94-699 I (1) I am Manager, Regulatory and Licensing Initiatives, in the Nuclear Technology Division, of the Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceMings, and am authorized to apply for its withholding on behalf of the Westinghouse Energy Systems Business Unit. (2) I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit. (3) I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Business Unit in designating information as a trade secret, privileged or as confidential commercial or financial information. (4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information' sought to be withheld from public disclosure should be withheld. (i) De information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse. (ii) ne information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence, ne application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required. Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows: 132SC-suh62Sf2sN
CAW-94-699 (a) De information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of - Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies. (b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability. (c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product. (d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers. (e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse. , (f) It contains patentable ideas, for which patent protection may be desirable. Dere are sound policy reasons behind the Westinghouse system which include the following: (a) He use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors, it is, therefore, withheld from disclosure to protect the Westinghouse competitive position. (b) It is information which is marketable in many ways. He extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information, monmenm
4- CAW-94-699
-(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of prcprietary information pertinent to a particular
- competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving l Westinghouse of a competitive advantage.
(e) Unrestricted disclosure w.uld jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries. (f) De Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage. ; I (iii) De information is being transmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission. _ (iv) De information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief. (v) The proprietary information sought to be withheld in this submittal is that which is , appropriately marked in "Braidwood Unit 1 Technical Support for Cycle 5 Steam Generator Interim Plugging Criteria", WCAP-14046 (Proprietary), May,1994 for Byron Unit 1, being transmitted by Commonwealth Edison Company letter and Application for Withholding Proprietary Information from Public Disclosure, to Document Control Desk, Attention William T. Russell. The proprietary information as submitted for use by Commonwealth Edison Company for Byron Unit 1 is expected to be applicable in other licensee submittals in response to certain NRC requirements for justification of steam generator tube interim plugging criteria. m ens = e --- ., _ - - . < +_.c
CAW-94-699 3 i This information is part of that which will enable Westinghouse to: ; (a) Provide documentation for steam generator tube interim plugging criterion. (b) Provide a basis for the form of the steamline break (SLB) leak rate correlation. , t (c) Provide SLB leak rate analyses. (d) Assist the customer in obtaining NRC approval. Further this information has substantial commercial value as follows: (a) Westinghouse plans to sell the use of similar information to its customers for purposes of meeting requirements for licensing documentation. (b) Westinghouse caa sell support and defense of the technology to its customers in the licensing prxess. Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar methodologies and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure , ,c of the information would enable others to use the information to meet NRC , requirements for licensing documentation without purchasing the right to use the information. De development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money. In order for competitors of Westinghouse to duplicate this information, similar i technical programs would have to be performed and a significant manpower effort, nece m nsu
4- CAW-94-699 having the requisite talent and experience, would have to be expended for developing testing and analytical methods and performing testing. Further the deponent sayeth not. t t tzuc aw+enom e
. . .-. .. - . . . - . , - _ , - _ . m--,. . _ , . ,-c-_, . - e r . . , . .
Proprietary Information Notice Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval. In order to conform to the requirements of 10 CFR 2.790 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the
~
proprietar[v$ ions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) contained within parentheses located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to , 10 CFR 2.790(b)(1). c==xum 1 I
Copyright Notice The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted te make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary. M.MIM
I 1
. WESTINGHOUSE CLASS 3 ,
l WCAP-14047 SG-94-06-002 l l BRAIDWOOD UNIT 1 TECHNICAL SUPPORT FOR CYCLE 5 STEAM GENERATOR INTERIM PLUGGING CRITERIA MAY 1994 Approved by:
. Esposito,Nanager
/ team Generator Technology & Engineering WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR SERVICES DIVISION . !
P. O. BOX 158 MADISON, PENNSYLVANIA 15663-0158 C 1994 Westinghouse Electric Corporation All Rights Reserved
, ~ u 7x n/ f
- WUJ'OA -
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4 [ BRAIDWOOD UNIT 1: TECHNICAL SUPPORT FOR CYCLE 5 STEAM GENERATOR INTERIM PLUGGING CRITERIA TABLE OF CONTENTS SECTION PAGE 1.0 Introduction 1-1 2.0 Summary and Conclusions 2-1 2.1 Overall Conclusions 2-1 2.2 Summary 2-2. 3.0 Crack Morphology 3-1 3.1 General Discussion 3-1 4.0 Accident Considerations 41 4.1 General Considerations 41 4.2 Thermal Hydraulic Loads on TSP in a SLB Event 4-2 4.3 Structural Modeling for SLB TSP Displacement Analyses 45 4.4 Results of SLB TSP Displacement Analyses ' 4-10 4.5 SLB TSP Displacements by Tube Location 4 13 4.6 SLB Frequency at Hot Standby and Full Power Conditions 4 15 4.7 Tubes Subject to Deformation in a SSE + LOCA Event 4 16 4.8 Allowable SLB Leakage l'imit 4-18 4.9 Acceptability of the Use of TRANFLO Code 4 20 4.10 References 4 24 5.0 Database Supporting Altemate Repair Criteria 5-1 5.1 Data Outlier Evaluation 51 5.2 Database for ARC Correlations 5-6 5.3 NDE Uncertainties 5-6 5.4 References 57 6.0 Burst and SLB Leak Rate Correlations 6-1 6.1 EPRI ARC Correlations 61 6.2 Burst Pressure vs. Bobbin Voltage Corelation 61 6.3 Burst Pressure vs. Throughwall Crack Length Correlation 6-2 6.4 NRC Draft NUREG-1477 SLB Leak Rate POD and Uncerninty 6-5 Methodology 6.5 Probability of Leakage Correlations 65 6.6 SLB Leak Rate vs. Voltage Correlation for 3/4" Tubes 69 6.7 SLB Leak Rate Analysis Methodology 6 11 6.8 Simulation of Equation Parameter Uncertainties 6 '3 i
.=. - -
BRAIDWOOD UNIT 1: TECHNICAL SUPPORT FOR CYCLE 5 STEAM GENERATOR INTERIM PLUGGING CRITERIA TABLE OF CONTENTS (Continued) SECTION PAGE 7.0 . Braidwood l Eddy Current Inspection Results 7.1 7-1 General 7.2 Inspection Results 71 7.3 Voltage Growth Rates 72 7-3 7.4 Historical Operating Chemistry 7-5 7.5 Relation Between Operating Chemistry and ODSCC Growth 76 7.6 Pulled Tube Eddy Current Data 77 8.0 Braidwood l IPC Criteria and Evaluation 81 8.1 General Approach to IPC Assessment 81 8.2 IPC Repair Criteria Implemented at Braidwood-l 8-2 8.3 Operating Leakage Limit 8-3 8.4 Projected EOC-5 Voltage Distributions 8.5 SLB Leakage Analyses 85 8.5.1 8-6 Reference SLB Leakage Analyses (Log logistic POL) 86 8.5.2 SLB Leak Rate Sensitivity to POL Correlations 8.6 87 Assessment of SLB Burst Margins and Probability of Burst 87 8.6.1 Deterministic Burst Margin Assessment 8.6.2 87 Method of Analysis for SLB Tube Burst Probability 8-8 8.6.3 Demonstration of Method for SG D at EOC-4 8 11 8.6.4 Conservative Burst Probability for SLB at Normal Operating 8-11 Conditions 8.6.5 Burst Probability for SLB at Hot Standby Conditions 8.6.6 8 12 Braidwood l Frequency of SLB Event with a Tube Rupture 8-13 8.7 Summary of Results 8 13 ii
y 4 BRAIDWOOD UNIT 1: TECHNICAL SUPPORT FOR CYCLE 5 I STEAM GENERATOR INTERIM PLUGGING CRITERIA
1.0 INTRODUCTION
Following the completion of Cycle 4 operation, eddy current inspections of the tube support . plate (TSP) intersections of the steam generator (S/G) tubes have identified 2733 bobbin coil { indications of which 1566 were confirmed as being axial crack-like ODSCC indications using RPC inspection techniques. The size and number ofindications could result in significant ' ' tube repairs with current plugging criteria and repairs that are not required to meet NRC Regulatory Guide 1.121 guidelines for tube repair. Braidwood Station has therefore requested a Technical Specification change to implement an interim plugging criteria (IPC) for ODSCC at TSP intersections. The requested IPC repair limits and inspection requirements have been based on the Catawba 1 NRC SER which approved a 1.0 volt repair limit. The methodology . to support the Braidwood-l IPC differs from previously approved IPCs in that it applies the EPRI data outlier evaluation methodology and SLB leak rate versus voltage correlation based 4 on the NRC guidance of the February 8,1993 NRC/ industry meeting on resolution of comments on draft NUREG-1477. In addition, Braidwood-l IPC analyses demonstrate limited TSP displacement relative to the tube in a SLB event, and show structural integrity with respect to tube burst considerations. The evaluations supporting the Braidwood l IPC are based upon bobbin coil voltage amplitude which is correlcted with tube burst capability and leakage potential. Detailed analyses provided in this report (Section 4) have demonstrated limited relative tube support - plate to tube movement which minimizes the potential for significant leakage or tube burst - during both normal and accident conditions. For SLB leakage analyses, the tube support plate crevices are assumed to be free span or open crevices, which lead to more conservative Icak ; rates compared to the expected packed crevices under normal and accident conditions. The j analyses for demonstrating limited TSP displacement utilize thermal hydraulic loads for a postulated SLB at normal operating conditions and for a SLB at hot standby conditions. The loads utilize existing analyses and the hot standby loads are very conservative as the initial conditions include low water level combined with an excess feedwater transient, both of ; which tend to increase the loads. The dynamic structural analyses yield TSP displacements as a function of tube location. Tube burst analyses performed for the crack length exposed by the TSP displacements have been conservatively performed by assuming that the exposed crack length is throughwall. Even with these conservative assumptions, it is demonstrated that Braidwood-1 has adequate tube burst margin. i In accordance with draft NUREG-1477, SLB leak rates were calculated for a total of six ; probability of leak (POL) correlations including the EPRI reference leg logistic correlation. i 1-1 !
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~ The six correlations (Section 6) evaluated included linear and log voltage formulations for logistic, normal and Cauchy cumulative distribution functions. The reference leak rate with the log logistic correlation and five additional leak rates for assessing the sensitivity to the POL correlation are given in this report (Section 8). He SLB leak rate analyses utilize voltage distributions consistent with the draft NUREG-1477 guidance including adjustme for probability of detection.
The plugging criteria were developed from testing of tube specimens with laboratory-ODSCC, extensive examination of pulled tubes from operating S/Gs and field experien leakage due to indications at TSPs. The recommended criteria represent conserva based upon Electric Power Research Institute (EPRI) and industry-supported develop programs that are continuing to further refme the plugging criteria. At the end of Cycle 4, four tube:; with 13 intersections and 6 RPC confirmed indications were pulled at Braidw for future enhancement of the EPRI database and validate the industry developed EP and burst correlations applied in this report. Implementation of the tube plugging criteria was supplemented by 100% bobbin coil inspection requirements at TSP elevations having ODSCC indications, reduced leakage requirements, inspection guidelines to provide consistency in the voltage normalization, and rotating pancake coil (RPC) inspection requirements to establis requirements for indications above the 1.0 volt repair limit and to characterize th 1 degradation mechanism as ODSCC. In addition, potential SLB leakage was calculate tubesiswith leakage indications less than left the allowable limits. in service at TSPs to demonstrate that the c I i e 1-2 I i
2.0
SUMMARY
AND CONCLUSIONS This report documents the technical support for a Braidwood Unit 1, Cycle 5 Interim Plugging Criteria (IPC) of 1.0 volt for ODSCC indications at TSPs. 2.1 Overall Conclusions An IPC with a 1.0 bobbin voltage repair limit has been developed for Braidwood-1, Cycle 5 operation. Inspection requirements typical ofIPC practice, such as the guidelines of the Catawba-1 NRC SER, were applied at the Cycle 4 refueling outage to support implementation of the IPC. These requirements include eddy current analysis guidelines, training of analysts, cross calibration of ASME standards to a reference standard, use of probe wear standards, 100% bobbin probe inspection and RPC inspection of bobbin indications above 1.0 volt together with a sample of dented TSP intersections R.G.1.121 guidelines for tube integrity are conservatively satisfied at end-of cycle five (EOC-5) conditions for the 1.0 volt IPC. The results of the Braidwood-l assessment can be summarized as follows: The projected EOC-5 SLB leakage is 3.1 gpm for the limiting SG, which is !ess than the allowable limit of 9.1 gpm for Braidwood 1. The SLB leak rate was evaluated for the six altemate formulations of the probability ofleak versus voltage correlation identified in draft NUREG-1477 and found to be essentially (within 0.1 gpm) independent of the correlation applied in the analysis. The SLB leak rates were obtained by applying the leak rate versus voltage correlation based on the EPRI database and outlier evalua: ion consistent with the NRC guidance of the February 8,1994, NRC/ industry meeting on resolution of draft NUREG 1477 comments. The tube burst probabihties estimated at EOC-5 are 5x104 for a SLB at normal operating conditions and 8x10" for a SLB at hot standby conditions. Weighting these probabilities - by the relative operating ames leads to a combined burst probability of 3.1x10 4 These burst probabilities are significantly lower than the IPC acceptance guideline of 2.5x10'2 shown to be acceptable in NUREG-0844. When combined with the corresponding SLB event frequencies, the frequency of a postulated SLB event with a subsequent tube 4 rupture is very low at 5 5x10 per year. The tube burst probabilities are developed based on limited TSP displacements calculated during a SLB event for the Braidwood-l S/Gs, even when applying very conservative load conditions for the hot standby SLB. Deterministic tube burst analyses show that the projected EOC-5 voltage obtained with voltage growth rates up to 99% cumulative probability on the Cycle 4 measured growth distribution, is less than the R.G.1.121 structural limit of 4.54 volts for a 1.43xAP a 2-1
. . - -~ . - __- . . . . - - .
s' accident condition burst margin. The R.G.1.121 structural limit guideline of three' times normal operating pressure differential is inherently satisfied by the tube constraint provided by the tube support plates at normal operating conditions. 1
. The modest SLB leakage, acceptable tube burst margins and low tube burst probabilities presented in this report support full cycle operation for Cycle 5 at Braidwood-l following implementation of the 1.0 volt IP'C. ;
2.2 Summary Braidwood-1 Interim Plueeine Criteria I The implementation of the IPC at Braidwood-l for ODSCC at TSPs can.be summarized as follows: Tube Pluneing. Criteria Tubes with bobbin flaw indications exceeding the 1.0 volt IPC voltage repair limit and i. 52.7 volts are plugged or repaired if confirmed as flaw indications by RPC inspection. Bobbin flaw indications >2.7 volts attributable to ODSCC are repaired independent ofi RPC confirmation. Insnection_Reauirements A 100% bobbin coil inspection was performed for all TSP intersections. All bobbin 1 flaw indications greater than the 1.0 volt repair limit were RPC inspected and.the RPC - inspection included a sample of dented TSP intersections. i Ooeratine Leaknes Limits Plant S G. shutdown will be implemented if normal operating leakage exceeds 150 gpd 1 SLB Leakane Criterion Predicted end of cycle SLB leak rates from tubes left in service, including a POD = 0.6 ' adjustment and allowances for NDE uncertainties and ODSCC growth rates, must be less than 9.1 gpm for the S/G in the faulted loop. Exclusim from Iub.f Plunnine Criteria Certain tube locations, as identified in Section 4 of this report, are excluded from application of the IPC repair limits. The analyses indicate that these tubes may potentially deform or collapse following a postulated LOCA + SSE event. 2-2 t
4 1 EOC-4 Insocction Results Eddy cunent inspection at EOC-4 resulted in the identification of 2733 bobbin indications at the TSP intersections and 1566 or 57% of the bobbin indications were confirmed by RPC inspection. The indicanons ranged from 272 in S/G B to 1061 in S/G C. To evaluate Cycle 4 voltage growth, all indications of ODSCC ~at TSP interse/:tions at EOC-4 had the EOC-3 bobbin data reevaluated to obtain Cycle 4 growth rates. In addition, Braidwood-l had a 100% inspection of S/G C during October,1993 as the result of a primary to secondary tube leak unrelated to ODSCC at the TSPs. This allowed a growth evaluation for S/G C from October 1992 to October 1993, a S/G C evaluation from November 1993 to March 1994 and a growth evaluation on S/Gs A, B and D for the entire Cycle 4. The results of this growth rate analysis were conservatively applied to the BOC-5 indications left in service to project the EOC-5 voltage distabutions for tube integrity analyses. The average growth for all 4 S/Gs over Cycle 4 was 0.23 volts per EFPY or 48% of the BOC-4 average voltage amplitudes. The average growth for S/G C over the first part of Cycle 4 was 0.19 volts per EFPY (48%) and was 011 volts per EFPY (16%) over the second part of Cycle 4. A few indications (-l%) showed larger than typical growth with the largest growth rate being 9.76 volts. The Braidwood-1, RPC confirmed TSP bobbin indications show axially oriented indications that are typical of those of other plants which have been confirmed as having ODSCC; i.e., the Braidwood l results are consistent ,with axial ODSCC as the degradation mechanism and the associated EPRI daubase is applicable for the Braidwood-l IPC. Four tubes including 13 TSP intersections and sa RPC confirmed bobbin indications ranging from 1.0 to 10.4 volts were pulled during the cutage for subsequent laboratory testing and destructive examination. The results from these pulled tube examinanons will be used to enhance the EPRI database and leakage / burst correiznons. The effect of these data on the correlations and results of this report will be assessed upon completion of the destructive examinations. . 4 Correlations of bobbin vcltage to burst pressure and to SLB leakage and a correlation for the < probabihty of SLB leakage are provided which are consistent with NUREG-1477 and the Catawba 1 SER. These correlations form the basis for determining repair limits and the , corresponding margins i:r burst and leakage as summarized below. Structura! Intenrity Assessment To support the Cycle 5 :.:be integnty assessment under the conservative assumptions of the larger Cycle 4 growth ra:es reoccurring in Cycle 5 and a probability of detection of 0.6 (draft NUREG 1477 guidance, additional analyses were performed to demonstrate limited TSP displacement in a postu:::ed SLB event. With limited displacement, the part of the overall 2-3 ) _-m,.-
1 l ODSCC crack length covered by the TSP is constrained against burst and the burs of the indication is that associated with the exposed crack length. Thus, limited relative displacement of the tubes and TSPs results in increased tube burst margins and an associate low probability of tube burst. The two sets of Model D4 S/G thermal-hydraulic loads available for this report are (a) for a SLB at normal full power operating conditions and (b) those for a very conservative ; SLB at hot standby conditions with low water level combined with an excess feedwater transient. 'Ihe initial conditions for the latter hot standby SLB event are excessively conservative as shown by comparison with a Model D3 S/G, hot standby SLB event with normal water levels and no feedwater transient. TSP displacements for each TSP and each tube location were obtained by dynamic, fmite element analyses for each of the aforementioned SLB loading conditions. The results of the Model D4 S/G SLB analyses at normal operating conditions and for th Model D3 S/G at hot standby conditions show maximum TSP displacements at tube lo of <0.44 inch. These displacements expose a crack length less than the 0.51 inc crack length that satisfies R.G 1.121 criteria for the structural3. limit of 1.43xAP .. The estimated tube burst probability for the SLB at normal operating conditions, very , conservatively assuming a throughwall crack equal to the exposed crack4 length, is 5x10 which is negligible for tube integrity considerations. Thus structural integrity is mainta sroughout Cycle 5 for a SLB at normal operating conditions. Since the time at pow operation is typically 96% of the operating cycle for Braidwood-1, large structural m exist for the dominant part of the operating cycle. Even for the very conservative Model D4 hot standby loads, TSP displacements are
- ess than 0.35 inch for all TSPs having bobbin indications at Braidwood-l except fo '
ud 7. At plate 3, the maximum TSP displacement at a tube location is 0.57 inch which is
-ell less than the 0.75 inch length for burst at the SLB pressure differential of 2560
=bes with LTL material properties. The probability of tube burst for an assumed 0 57 inc .
nroughwall crack is about 6x10" which is negligible compared to allowables since onl
- .26% of TSP intersections) tube locations on plate 3 have TSP displacements greater t ne 0.51 inch structural limit.
At the EOC-4 inspection, only 1 indication was found on plate 3 at a location with displacements >0.5 inch. This indication had a small 0.59 volt am e a tube location with 0.51 inch TSP displacement. Thus the number and voltage ampl F indications found at plate 3 locations with significant TSP displacements is negligible ube integrity considerations. Since maximum TSP displacements maintain adequate tube
- sst margins even if throughwall cracks are assumed and since the larger tube displacements evolve only a few tubes, it is concluded that adequate structural margins are maintained for Cycle 5 operation for all potential indications at plate 3.
2-4 l l r . , , , - - , - - - - - - _----------------_------------1
Only plate 7 has significant tube-to-TSP displacements which provide potential concerns for exceeding EOC-5 structural integrity considerations. At plate 7,124 tubes (2.6% of TSP intersections) have TSP displacements exceeding 0.5 inch corresponding to the R.G.1.121 structural margin for throughwall cracks and the maximum TSP displacement at any tube location is 0.87 inch. Based on the EOC-4 inspection results of plate 7 locations, only 8 indications in any one S/G, and a total of 20 indications in all 4 S/Gs (0.7% of all in'dications) have SLB displacements exceeding 0.5 inch. The maximum bobbin voltage at any tube location with SLB displacements exceeding 0.35 inch was 1.24 volts and the maximum voltage indication found in any S/G at plate 7 was 2.74 volts. This is well below the 4.54 volts corresponding to R.G.1.121 margins against burst for free span indications. Thus it is concluded that only a few, relatively low voltage indications are likely to occur at the plate 7 locations with significant SLB displacements at hot standby conditions. A statistical assessment is necessary to assess the potential for a structurally significant indication to occur at a plate 7 location with relatively large TSP displacements. A tube burst probability assessment was performed for SLB hot standby conditions (conservative Model D4 loads) and the resulting probability of a tube burst at EOC-5 conditions was only 8x10"; 4 this is negligible compared to IPC acceptance guidelines of 2.5x10 . The burst probability for an SLB during power operation at EOC-5 is 5x10 4 Since only about 3.8% of the Braidwood l operating time is at hot standby (Mode 3) conditions, the combined burst probability is only about 3x10 4 The Braidwood l SLB event frequencies and conditional tube rupture probabilities described 4 above have been combined to obtain a frequency of 5.5x10 per year for a SLB event with a subsequent tube rupture. This very low frequency has negligible influence on the core damage frequency and supports full cycle operation at Braidwood l for Cycle 5. Leakace Intecrity Based on sensitivity analyses for SLB leakage, it was concluded that S/G D is the most limiting S/G and was analyzed for potential SLB leak rates at EOC-5. The analysis utilized the EPRI IPC database, probability of leakage correlation and SLB leak rate versus voltage correlation following the NRC guidance at the February 8,1994, meeting on resolution of draft NUREG 1477 comments. Projected EOC-5 bobbin voltage distributions were obtained including a POD adjustment of 0.6, an allowance for NDE uncertainties, and an allowance for voltage growth based on the S/G D voltage growth distribution obtained for Cycle 4 The resulting SLB leak rate for the limitmg SG at EOC-5 was 3.1 gpm, which is significantly less than the allowable leak rate of 9.1 gpm obtained for Braidwood-1. Based on draft NUREG 1477 guidance, the SLB leak rate was assessed for six attemate formulations of the probability ofleakage correlation including linear and log voltage forms 2-5
for logistic, normal and Cauchy distributions. A negligible leak rate dependence on the probability ofleakage form was found, with a variation of only 0.1 gpm between the six distributions. 4 e l 2-6 l I
3.0 CRACK MORPHOLOGY
~3.1 General Discussion Four tubes were pulled from Braidwood-l including 13 TSP intersections with 6 reported !
bobbin and RPC indications. The resulting tube examinations will confirm the crack morphology for indications at the tube support intersections. The schedule for the tube exams will be based on obtaining the appropriate technical results and the results will be available for review after the tests are completed. In the interim period, comparisons of RPC data from the current Braidwood-l inspection are compared in Section 3.2 below with RPC results for pulled tubes with known morphology of dominantly axial ODSCC typical of the EPRI database. With the performance of the tube metallography on the pulled tube specimens from Braidwood *., the 3/4" database will be expanded by 6 TSP intersections with clearly identifiable degradation and 7 other intersections for w'ich a EC interpretation guidelines, as practiced in the field, did not find a basis for reporting as possible flaws; these NDD specimens will help to define the extent of ODSCC which may be present at such locations. : The Braidwood .' pulled tubes can be expected to demonstrate a crack morphology of dominantly axial ODSCC typical of the EPRI database. Together with leak and burst testing, the ground truth provided from these samples is expected to support the detection probability conceming the adequaev of bobbin EC testing of non-dented TSPs as the appropriate NDE technique for TSP interim plugging criteria. The bobbin results from the SH level of R37C34 in panicular are suggestwe of possible flaw conditions, but both the bobbin and the RPC field analyses were reported as NDD; the metallography results could confirm the sensitivity of the bobbin probes' integration cf many small cracks, producing a detectable signal, while the RPC probe response ; is too'small .o distinguish a signal produced from only a fraction of the total cracks present in. its helical pzi at any instant. In either case, the voltage range of 1.0 to 10.4 volts for the Braidwood . pulled tubes will enhance the EPRI database and resulting correlations while the
? NDD intersections will supplement the bobbin and RPC detectability data.
3.2 Craci Morphology Inferred from Inspection Data Comparison :f typical MRPC pseudo-isometric graphics (C-scans) for some of TSP indications which were :enfirmed shows that the Braidwood-l TSP degradation is enveloped by examples from other r.ints and that the condition represented by the C-scans is quite consistent with - ODSCC Fipres 7-1 to 7-6 in Section 7 illustrate the distributions of axial indications, all confined wit.:n the edges of the support plates; the distributions of bobbin indications with elevation an: voltage are similar to that found in plants with axial indications verified by , previous inve:mgations to be ODSCC by metallographic studies of pulled tubts. 3-1 1
The intersections pulled during the EOC-4 inspection which exhibited Ed indications were R37C34-3H and SH and R16C42-3H from SG D, followed by R27C43 3H and R42C44-3H and SH, both from SG A; these MRPC indications are shown in Figures 7-42 to 7-47 and are typical of the variety of TSP ODSCC in Braidwood-l confirmed bobbin indications from 1.04 volts to 10.4 volts. Comparable C-scan results from Plant R and Plant S, both with SG's of similar design to the Braidwood-l SGs, shown in Figures 3-1 to 3-5, confirm the appropriateness of the judgment that all of these indications represent TSP ODSCC within the definition relevant to the IPC. O e 1 4 3-2
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_ _. .. - ~ - - 4.0 ACCIDENT CONSIDERATIONS t 4.1 Gentral Considerations for Accident Condition Analyses The approach being applied to demonstrate tube integrity at Braidwood-l is based on applying , SLB analyses demonstrating limited TSP displacement to reduce the likelihood of a tube burst in a'SLB event to negligible levels. In addition, it is demonstrated that the SLB leak rate, even under the conservative assumption ofleak rates for free span indications, is within
^
acceptable limits. The allowable limit on the SLB leak rate is developed in Section 4.8. Section 4.2 develops the SLB thermal hydraulic loads on the TSPs which are used in the structural analyses of Sections 4.3 to 4.5 to obtain TSP displacements. At this time, Model , D4 S/G loads are available for an SLB at normal operating conditions and for a very conservative SLB at hot standby conditions. The hot standby loads include conservatisms based on low water levels (at level of the top TSP) and include a simultaneous feedwater transient. The potential level of conservatism in the Model D4 hot standby loads is demonstrated by comparing the loads with those obtained from a Model D3 S/G analysis w.6 normal water level and no feedwater transient.' Both SLB analyses, at normal operating conditions and at conservative hot standby conditions, for TSP displacements developed in . this section are applied in Section 8 to develop tube burst margins. The TSP displacements are calculated relative to the tube location at the start of the transient, as discussed in Section 4.5. Section 4.4 includes an assessment of the structural integrity of the TSPs and their supports (bar, wedge welds). Section 4.6 develops the frequencies of occurrence for t-SLB at Braidwood-l at both normal operating and hot standby (Mode 3) conditions. It is shown that the frequency of an SLB at hot standby conditions, for which the TSP displacements are higher, is significantly lower than that for an SLB at normal operating conditions. For a postulated accident condition combining a LOCA simultaneously with a SSE, it is possible to have some tubes near TSP wedges deformed by the resulting loading condition. Due to the potential for secondary to primary leakage in the combined LOCA plus SSE, the , tubes subject to significant tube deformation near the wedges are excluded from application :f the IPC repair limits. The analyses describing this consideration are described in Section 4 - l l Some of the analyses described in this section use the Westinghouse labeling system for numbering TSPs which differs from that applied at Braidwood-1. The following relates the i Westinghouse and Braidwood-l nomenclatures for hot leg TSP identification: I 4-1 i
,~, - - - - -
l ' We.stinnhouse ISE Braidwood-LTSP A 1 l, C 3 F 5 J 7 L 8 M. 9 N 10 l P
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11 TSP 1 is the Flow Distribution Baffle (FDB). The FDB has large tube to plate clearances (nominal [ J' diameter) in the central region of the plate and radialized holes (nominal [ ]* width) in the outer region. No indications have been found at the FDB in the l
' Braidwood-l SGs. For comparison, the Model D3 SG, for which indications have been found at the FDB, has a nominal hole diameter of [ ]*.
l 4.2 Thermal Hydraulic Loads on TSP in a SLB Event 4.2.1 Introduction A postulated steam line break (SLB) event results in blowdown of steam and water. The I fluid blowdown leads to depressurization of the secondary side fluid. Pressure drop develops l and exerts hydraulic loads on the tube support plate (TSP) or flow baffle. These hydraulic loads were determined for the Model D4 and D3 steam generator using the TRANFLO Code. This code is a network flow based code that can model the thermal and hydraulic characteristics of fluid through the steam generator intemals. TRANFLO code p'ledicts the transient flow rate, pressures and pressure drops. The hydraulic loads vary with initial conditions and boundary conditions of the SLB event. The significant initial conditions are mode of operation and water level. The important boundary conditions are those associated with feedwater nozzle and steam nozzle; these include the' size and location of break, and flow rate through the feedwater nozzle during the event. The most likely initial conditions are of full power operation with a normal water level. When fluid moves in the tube bundle, water will exert a higher pressure drop across the TSP when compared to steam. Hot standby at zero power provides a solid water pool in the tube
' bundle while power operation generates a steam and water mixture. Thus, hot standby would '
be conservative in estimating the hydraulic loads on the TSPs, although the most likely mode of operation is power operation if a SLB event occurred. Previous studies confirmed that the 4-2
bot standby yields the largest hydraulic loads when compared to full or partial power } operation. Once a SLB event begins, it triggers a rapid depressurization, which leads to water flashing across the water level. The rapid water flashing generates water motion, and the closer the TSP to the water level the higher the flow rate, and thus the larger the pressure drop. . Previous parametric evaluations indicate that a lower water level tends to yield higher hydraulic loads on the tube support plates or baffles. It would be ideal to calculate the hydraulic loads on the TSPs of the Model D4 steam generator under the no load, hot standby conditions. Although there are currently no such calculations, there are other calculations of Model D3 and D4 for developing conservative, bounding loads for the Model D4. This section presents such a task. These bounding loads for the Model D4 and the more applicable Model D3 loads at hot standby with normal water level. 4.2.2 Hydraulic Loads of Model D3 under No Load, Hot Standby with Norma] Water Level In 1993, a TRANFLO calculation of hydraulic loads on the TSP under a SLB event was made for a Model D3 steam generator. He calculation considers the initial conditions of zero load, hot standby and a water level at about normal setting. The following describes the calculation model. - L i The Model D3 steam generator maintains a normal water level of [ T above the top of the tubesheet during no load, hot standby. He computational model considers a water level of [ T above the top of the tubesheet. Use of the no load, hot standby and a water level of [ T is thus conservative in estimating the pressure loads to tube support plates. Water amt steam temperature is initially at 557'F, and primary coolant pressure is at 2350 psia. and secondary side steam pressure is at 1106 psia, and feedwater j temperature at 75'F. ' I A network of nodes and connectors was created to represent the secondary side f;uid, tube metal heat transfer and primary coolant. Figures 4-1 and 4-2 show the nodal laycut of the secondary side of the Model D3 steam generator. Figures 4-3 and 4-4 present the nodal j network of the secondary fluid, primary fluid and tube metal. In the tube bundle area, the space between support plates or baffles forms a fluid node, and a flow connector links the adjacent nodes. Pressure drops through support plates or baffles are calculated by the code for each flow connector, which represent a plate or baffle. Blowdown flow induces fluid flow in the secondary side, and thus pressure loads to various i TSPs and baffle plates. Figures 4 5 through 4-7 show pressure loads through TS?s and baffle 4-3 1
c . plates outside the preheater. The peak of pressure loads across TSP or baffle plates develops within one second, and it then drops to a small value or becomes a quasi-steady state. The flow splits take place in the lower tube bundle; it occurs at about TSP L (see Figure 4-1). Plates A, C and G experience downward flow because the fluid leaves in a downward direction from the tube bundle up into the downcomer. Plates above TSP L experiences upward flow as the fluid leaves in the upward direction through the tube bundle. Maximum loads occur at TSPs A, B and T; about [ J' at the peak for TSP B on the cold leg, [ ]* for TSP A on the hot leg, and [ ]* for TSP T (i.e., the uppermost TSP). . 4.2.3 Hydraulic Loads of Model D4 under Full Power with Normal Water Level Although there are differences in the preheater design between the Model D3 and D4 steam generator, it is judged that there would be no significant differences in the hydrsu!ic loads on the TSPs outside the preheater. It would be ideal to have a TRANFLO calculation for the Model D4 steam generator with initial conditions and boundary conditions like Case 1 for the Model D3. However, no such run is currently available. Calculations are available for hydraulic loads on the TSPs for the Model D4 steam generator under full power operation with a normal water level when a SLB begins. Figure 4 8 illustrates the nodal layout of the secondary side of the Model D4 steam generator, which is similar to Figure 41 for the Model D3. The calculation was made for design analyses in the 1970's. Table 4-1 lists the initial and boundary conditions for three cases for t which SLB loads are available; Case 3 will be discussed later. Results of Case 2 are presented in Figures 4-9 through 411. As discussed earlier, hydraalic loads for a steam and water mixture in the tube bundle are less than a solid water pool. Therefore, hydraulic loads of Case 2 for the Model D4 is less than those of Case 1 for the Model D3. When a SLB event initiates from a power operation, the blowdown flow path is essentially in the upward direction from the tubesheet towards the riser barrels. Therefore, hydraulic loads tend to be higher at the upper TSPs, as shown in the above figures. Since the event begins from full power operation, the steam content increases with the bundle height. The uppermost TSP is thus lower in water content, and the resulting hydraulic load is less than the N plate below it. In addition, the highest loads occurs at the TSP L on the hot leg because the flow area is half of a whole TSP and the majority of flow is passing through the hot leg side. Compared to Case 1 for the Model D3, which experiences flow splits, loads of Case 2 for Model D4 are less even under the situation of no flow splits. The reason for this is because of its relatively mild initial coniitions. 4-4
4 t t 4.2.4 Hydraulic leads of Model D4 under No Load, Hot Standby with a Water Level at the Uppermost TSP and an Excessive Feedwater Flow Transient The TRANFLO computational model for this case is identical to Case 2 except for its initial and boundary conditions. This calculation of Case 3 uses extremes of both initial and boundary conditions. No load at hot standby is already conservative compared to a most likely mode of full power operation; it considers a water level at the uppermost TSP, which is by itself a very rare transient. In addition, it imposes an excessive feedwater flow transient. As discussed already, a water level at the uppermost TSP generates higher hydraulic loads than a normal water level. An excessive feedwater flow introduces more solid water into the tube bundle, which provides additional source of water for flashing action to trigger more water motion. Figures 4-1.2 through t-14 presents hydraulic loads on various TSPs. Like Case 1, flow splits take place for Case 3 since both cases initiate from a no load, hot standby condition. However, Case 3 yie'ds much higher loads than case 1 because of severe initial and boundary conditions discussed above. 4.2.5 Summary Table 4 2 summarizes the key parameters regarding the loads. As far as the maximum peak load is concemed Cue 2 for Model D4 yields slightly higher loads than Case i for Model D3. This is because de flow area for the plate with maximum load is half of the whole plate only, and there is no f.ow split. The lower TSPs of Case 2 experience hydraulic loads much less than those of Case 1, because there is almost no downward flow split for Case 2. Peak loads of Case 3 tre more than twice those of Case 2. Use ofloads of Case 3 is conservative. It is bi.;eved that loads for Model D4 would be about the same as those of Case 1 for Model D3. if the same initial and boundary conditions are used in the computational model 4.3 Structural Mo:eling for SLB TSP Displacement Analyses This section summan:es the structural modeling of the Model D4 tube bundle region. A finite element model :f the hot leg region of the tube bundle is prepared, and corresponding mass and stiffness mz .ces are generated. The mass and stiffness matrices are then used in a subsequent dynamic t .slysis to determine TSP displacements under SLB loads. Structural 4-5
. - ~ - - - _ - . , -
members included in the model include all TSPs, the tierods and spacers.' Since the present analysis considers only the response of the hot leg to the SLB loading, the finite element model includes 90* of the tube bundle. I 4.3.1 Material Properties A summary of component materials is contained in Table 4-3, with the corresponding material properties summarized in Tables 4-4 through 4-6. The propetties are taken from the 1971 edition (through summer 1972 addenda) of the ASME Code, which is the applicable code edition for Braidwood Unit 1. Since temperature dependent properties cannot be used in substructures, properties for the finite element model correspond to the values at 550'F. The material properties for the tube support plates are modified to account for the tube penetrations and flow holes. 'Ihe density of the TSPs is also modified to account for the added mass of the secondary side fluid. 4.3.2 TSP Support System The support system for the TSPs is a combination of several support mechanisms A schematic of the tube bundle region is shown in Figure 4-15, with each of the plates identified. [ l'
' For the analysis of the Model D3 steam generators under SLB loads, the finite element codel a included the shell, wrapper, partition plate, and channel head. Except for the tubedeet, these structures were included to account for support locations for the TSPs and baffle plates. However, compared to the stiffness of the TSPs, baffle plates, and tierods, these structures are essentially infinitely stiff and have insignificant displacements (<0.010) under SLB loads. Therefore, it is acceptable to treat these structures as points of rigid support for the plates, and not in:lude them explicitly in the model.
Regarding the tubesheet, although not considered explicitly in the finite element model, tubesheet displacements are considered in the analysis. Due to similarities in geometry of the tubedeet, s and channel head, displacements are scaled from the Model D3 analysis. The tubesheet displacements are quite small relative to the TSP displacements, and scaling of Model D3 displacements is an acceptable approximation. Further discussion of the tubesheet dis;!acements is provided in Section 4.4. . The Model D3 analysis also considered the non-linear interaction between tubes and T5? due to TSP rotation. The present analysis has not incorporated this effect, primarily due to the 1:=tted time available to develop the system model. This effect may be considered in subsequent e,aluations to limit plate displacements. i 4-6
i
- 6:
[ t
).
The lack of a rigid link' between the spacers and TSPs for the outer tierods / spacers results in a non-linear dynamic' system. However, the nature of the SLB transient results in an essentially linear system response. During installation a small positive preload is introduced into the tierod/ spacer system. As shown in Section 4.2, the plates are subject either to an upward or downward pressure loading, with the exception being Plate J, which sees a both a significant upward and downward loading. Thus, the response is essentially linear either upward or downward. The tierods/ spacers have a different stiffness characteristic for upward and downward loads. These differences have been incorporated into the model. For Plate J, the weaker of the two stiffnesses has been incorporated to provide a conservative response. I 1' I 1' 4-7 l
The various support locations for the plates are shown in Figures 4-16 through 4-24. Figure 4-16 shows the locations of the tierods and spacers. Plate / wrapper support locations are shown in Figures 4-17 through 4-24. The finite element model representation of the plates and tierods/ spacers is shown in Figure 4 25. 4.3.3 Revised Material Properties As noted earlier, the material properties for the tubesheet and tube support plates are modified to accoQnt for the tube penetrations, flow holes, and various cutouts. The properties that must be modified are Young's modulus, Poisson's ratio, and the material density. The density must be additionally modified to account for the added mass of the secondary side fluid. i e In calculating revised values for Young's modulus and Poisson's ratio, separate formulations are used for plates with and without flow holes. Due to square penetration patterns, different properties exist in the pitch and diagonal directions. The first step is to establish equivalent parameters for Young's modulus and Poisson's ratio in the pitch and diagonal directions (E,*/E, E,*/E, v/, v,*), respectively. The equivalent Young's modulus for the overall plate is taken as the average of the pitch and diagonal directions. The next step in the process is to determine an equivalent value for the shear modulus, G'/G, for the plate. This is done in a similar manner as for Young's modulus, starting with values in the pitch and diagonal directions, and then taking an average of the two values. The final equivalent value for Poisson's ratio is determined from the relationship between Young's modulus and the shear modulus. A summary of the revised values for Young's modulus and Poisson's ratio is provided in Table 4-7. ' There are.two aspects to revising the plate density. The first is based on a ratio of solid area i to the modeled area. The second aspect corresponds to the plate moving through the secondary side fluid, displacing tha: fluid, and creating an "added mass" effect. The added hydrodynamic mass is a direct function of the fluid density. Because the dynamic analysis ' cannot account for the change in fluid density with time, the analysis uses the average density value for the duration of the transient. Results of the calculations to determine effective plate , densities are summarized in Table 4-8. This table provides a summary of the actual (structural) and modeled plate arets, the metal and added fluid masses, and the final effective ' plate densities. The fluid densities correspond to SLB events initiating from hot shutdown conditions (as opposed to full power operation). Calculations were also performed for densities corresponding to full power operation. The change in effective plate densities did not have a significant effect on the dynamic response of the plates. 4-8 I
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F 4.3.4 Dynamic Degrees of Freedom In setting up the dynamic substnactures, it is necessary to define the dynamic degrees of : freedom. In order to define dynamic degrees of freedom for the TSPs, two sets of modal , calculations are performed for each of the plates. The first set of calculations determine plate i mode shapes and frequencies using a large number of degrees of freedom (approximately 120 per plate). The second set of calculations involves repeating the modal analysis, using a , significantly reduced set of degrees of freedom (DOF). 'Ihe reduced DOF are selected to predict all frequencies for a given plate below 50 hertz to within 10% of the frequencies for ; the large set of DOF. A frequency of 50 hertz was selected as a cutoff, as it is judged that higher frequencies will have a small energy content compared to the lower frequencies. This ; can be confirmed by noting that the highest frequency content in the first one and a half i seconds of the pressure drop time history input loadingc is typically less than 10 hertz. For , each of the modal runs, in addition to symmetry boundary conditions along the "Y-axis", and vertical restraint at vertical bar locations, all the plates are assumed to be constrained vertically at tierod/ spacer locations. A sample set of mode shape plots is provided for Plate A. Mode shape plots for the full set of DOF are shown in Figures 4 26 through 4-28, while mode shapes for the reduced set of - DOF a're shown in Figures'4-29 through 4-31. A comparison of the natural frequencies for the full and reduced sets of DOF for the plates is provided in Table 4-9. Based on the tabular summary, the reduced set of DOF are concluded to provide a good approximation of the plate response. Note that for Plate P, the frequency for Modes 3 and 5 for the reduced set of DOF . slightly exceeds the 10% objective for matching frequencies. These variations are not considered to be significant, and the selected DOF are judged to give an acceptable ' representation of the Plate P response. The reduced set of DOF consists of 8 - 10 DOF for each of the plates. 4.3.5 Displacement Boundary Conditions The displacement boundary cond::ons for the substructure generation consist primarily of 1 prescribing symmetry conditions along the "Y" axis for each of the components. Vertical constraint is provided where the plates are constrained by the vertical bars welded to the partition plate and wrapper, and to the tierods at there bottom end. For the TSPs, rotations normal to the plate surface are aise constrained, as required by the stiffness representation for the plate elements. 4-9
-e, ---- -~,. - - , ------e.- - -,- -- - - -
' 1 4.3.6 Application of Pressure Loading The SLB pressure loads act on each of the TSPs. To accommodate this, load vectors are prescribed for each of the plates using a reference load of 1 psi. The reference loads are scaled during the dynamic analysis to the actual time-history (transient) loading co defined in Section 4.2.
The transient pressures summarized in Section 4.2 are relative to the control volum - thermal hydraulic analysis. The area over which the hydraulic pressure acts cor the area inside the wrapper minus the tube area. nese pressures must be scaled b ratio of the plate area in the structural model to the control volume area in the hydra model. A summary of the transient pressure drops is given in Section 4.2. These p drops were modified as discussed above and applied to the structural model for analysis. 4.4 Results of SLB TSP Displacement Analyses As discussed in Section 4.2, several sets of SLB loads were considered in perfo analysis. hi addition to the system analysis, some preliminary single-plate evaluation performed to estimate the plate response to the applied loadings. Calculations were als performed using the single plate models to estimate the effects of expanding tubes locations in the tube bundle to limit glate motions. The results for each set of ca summarized within this section of the report. An overall summary of the limiting displacements for each of the plates for the var considered is provided in Table 4-10. The displacements in this table are relative to th initial starting plate positions. The magnitude of the tubesheet displacements an on these results is discussed below. The first two sets of results in Table 4-10 are for the most limiting SLB loading (SLB simultaneous Feedwater Transient) using the single plate models, with and without tub expansion. These results show that tube expansion significantly reduces plate displac , for all of the plates. The third set of results is again for the limiting SLB transient for system model. Comparing these results to the single plate models shows that the sin models provide a good indication of the relative plate motions, but that plate interaction result in an increase in the plate responses, more for some plates than others. , Comparing the results for the three SLB sets of loads using the system model shows th the limiting SLB loads, Plates A (IH), C (3H), and J (7H) experience displacements. 4 - 10
than 0.350 inch. For a transient initiating from normal operation that only Plate J (7H) sees any significant motions, and for the Model D3 SLB loads case, only Plates A (lH) and C (3H) show any significant response. Based on the single plate response to the limiting load with expanded tubes, it is concluded that expansion of a limited number of tubes would be effective in reducing the response of each of these plates to very low levels. The limiting plate displacements in all cases are limited to a small region of the plate at their outer edge near the tube lane, where the distance between vertical supports is greatest. Displaced geometry plots for Plates A (lH), C (3H), and J (7H) for the limiting set of SLB loads are shown in Figures 4 32 through 4-35. The consistent displacement pattem is apparent for the three plates. Displacement time histories for each of the plates for the limiting transient loads are provided in Figures 4-36 and 4-37. The bottom four plates are shown in Figure 4 36 and the upper four plates in Figure 4-37. As discussed previously, tubesheet displacements are not significant and were scaled from the Mode: D3 analysis. The geometry of the tubesheet and supporting structures for the two designs is nearly identical. A summary of key dimensions for the two models of steam generators is provided in Table 4-11. Displacement resuhs for the tubesheet from the Model D3 analysis as a function of distance frem plate center for several transient times are summarized in Table 4-12. At the bottom of this table a summary of the tubesheet displacements relative to tirne zero are presented. The relative displacements are shown to be quite small relative to the p; ate displacements. This is especially true at the outer edge of the tubesheet where the plate d:splacements are a maximum. Since se dynamic analysis :s based on elastic response, calculations were performed to assure that the tierods, a significant support element for the plates remain elastic throughout the transient. The dynamics anz2ysis results establish that the stayrods do, in fact, remain elastic throughout the transient. [
]* In both instances, these elongations are well below the yield point f:: the stayrods.
Also relevant in assessing the appropriateness of the elastic solution, are the stresses in the plates Thus, in conjunction with the displacement results from the dynamic analysis, stresses are ca':ulated for the hot le; plates at the times corresponding to the maximum plate displa:ements. The stresses are calculated by extracting displacements from the dynamic analys:s for each plate degree of freedom, and then applying those displacements to the finite eleme-: model. The finite e.ement code then back calculates the displacements and stresses for the overall plate rr.odel 1 4 - 11 l l 1
l l In order to extract the appropriate displacements from the tape created by the dynamic analysis, a special purpose computer program is used. This program extracts the ' 4 ' displacements for a given plate at specific transient times and writes the resulting nodal ; displacements to output in a form that can be input directly to the WECAN program as t displacemant boundary conditions. Using this program, displacement boundary conditions are extracted at the times of maximum relative displacement for Places'A (1H), C (3H), and ' J (7H) at the critical times for the SLB + Excess Feedwater transient an and C (3H) for the Model D3 transient. Note that for Plate J for the SLB + Exc transient, stresses are calculated for the times corresponding to both the maximum upwar , displacement and also for the maximum downward displacement. These are the transients i and plates that are judged to be limiting based on the plate displacement results. ' Additional boundary conditions corresponding to lines of symmetry and appropriate rotational constraints are also applied to the model. The finit. element results give a set of displacement and stress results for the overall plate. The resulting plate stresses, how I correspond to the effective Young's modulus, and must be multiplied by the inverse ratio of effective-to actual Young's modulus to get the correct plate stresses. The stress multipli is performed by another special purpose computer program, SRATIO. i In order to interpret the stress results, stress contour plots for the maximum and mmimum ! stress intensities have been made for each plate. The limiting stresses for each of the pl! ' occur for the SLB + Excess Feedwater transient.Plots showing the maximum and minimum stress intensities for Plates A(lH), C(3H), and J(7H) are shown in Figures 4-38 to 4 45, j
- sspectively. These plots show the distribution of stress throughout the plate. As expectei
- he maximum stresses occur near the locations of vertical support, the tierod / spacers an vertical bars. He ASME Code minimum yield strength for the TSP material is 23.4 ksi.
Except for one very local area for Plate J corresponding to the upward loading on th iTigure 4-42), the stresses are elastic throughout the plate. Recalling that the presen des not account for either the wedge support for Plate J at the 10* location, or the potentia for tube / plate interaction due to plate rotation, the stresses in Figures 4-42 and 4-43 for
- are judged to be conservative. nus, it is judged that the effective plate stresses will be
;;dged to be elastic for all transient cases.
~
ae plate stresses cannot be compared directly to the material yield strength, as these stresses correspond to an equivalent solid plate. In order to arrive at the plate ligament stresses, additional detailed stress analysis of the plates is required. Such an analysis is outside the uope of this program. The equivalent plate stresses do provide a general guideline as to t .ose areas of the plate that are most limiting from a stress viewpoint. The plate stresses are meaningful in that they indicate that the stresses are generally low throughout the plate, and
- t. it the elastic analysis is a good approximation of the transient plate response. I i
4 - 12 i 1 m -- ,__ - . . . . . _ _ _ _ _ _ - - - _ _ ~ . _ . . . _ . . - _ . , _ _ , . . - _ , -
- m. ..- . -_ , . -_. .-. - . - _ . .~ ..
Calculations have also been performed to determine the stresses in the welds between the vertical bars and the partition plate and wrapper. The loads at the various support points are I extracted from the static WECAN runs in the form of reaction forces at the times of I maximum plate deflection. Loads have been extracted for the limiting plates (based on plate motions) for each of the SLB load cases, and for Plate P, which experiences the highest l pressure loads, for the SLB + Excess Feedwater transient. l l I [ ll twice the shear stress. A summary of the reaction forces and corresponding stresses for each of the bar locations for the locations considered is provided in Table 4-13. The results show all of the stresses to be low (<2 ksi) for a faulted event. The allowable stress for the welds is based on 2.4S,, x 1.5 x 0.35 (for fillet welds with visual examination) for carbon steel S at 550'F is 15.5 ksi. The resulting allowable stress intensity is 19.53 ksi, and the weld stresses are acceptable. Overall, it is concluded that the elastic. analysis provides a good approximation of the dynamic response of the TSPs to the applied loading. 4.5 SLB Displa:ements By Tube Location 4 In order to establish probabilities for tube burst as a result of relative plate / tube movement, calculations are performed to determine how many tubes are associated with a given displacement magnitude for a given plate. The plate displacements are categorized into groups, starting at 0.35 inch, and increasing in 0.05 inch increments to a maximum displacement > 0.80 inch. It is the relative plate / tube displacement that is of interest, with the tube and plate positions at the start of the SLB transient defined as the reference position. At hot standby, the TSP positions relative to cracks inside the TSP are essentially the same as at cold shutdown. Every known S/G cold condition inspection shows ODSCC cracks within the non-dented TSP with a trend towards being centered within the TSP. Therefore, the cold condition TSP location relative to the tubes is ecsentially the same as for the full power i condition where the cracks formed, which is also the position during hot shutdown. These inspections indicate that there is little relative movement between the tubes and plates throughout the operating cycle. Thus, this analysis calculates relative tube / TSP motions based on the tube / plate positions at the initiation of the SLB transient. 4 4 - 13 I 1
e . i l l The algorithm for calculating the relative displacements is as follows: e AD = (D . r - D, . . ),,,, - (D, . 7 - D, . . )1,,,,,,,, , d ere D,,,, = Plate Displacement Dr.,,,w = Tubesheet Displacement e T = Time of maximum displacement from dynamic analysis In order to calculate the relative displacements across the full plate, displacement (stress) solutions are performed for the limiting plates at the times of. maximum displacement. Calculations were performed for each set of transient loads for those plates where the maximum absolute displacement exceeded 0.350 inch. The displacement solutions are performed using the finite element representations for the j plates. Displacements for the dynamic degrees of freedom for the limiting plates are l extracted at the times ofinterest from a file containing the DOF displacements for the full transient. These displacements are applied to the finite element model as boundary conditionI: (along with any other appropriate boundary conditions representing symmetry or ground locations),'and displacements for the entire plate are then calculated. These results are then combined with the scaled tubesheet displacements, to arrive at a combined relative displacement between the tubes and plates. The combined relative displacements are then ' superimposed on a tube bundle map, and the results interpolated to arrive at a displacemen value for each tube location. A summary of the number of tubes falling into each of the displacement groupings for the limiting plates is provided in Table 4-14. Note that the numbers of tubes in Table 4-14 correspond to the full plate. The number of tubes in each plate quadrant is one half of the j values listed. A summary of the total number of tubes having displacements > 0.35 inch for each of the SLB loads is provided in Table 4-15. Note that at the top of Table 4-14, the limiting displacements as reported in Table 4-10 are repeated, while the number of tubes where the relative plate / tube displacements exceed 0.350 inch are summarized at the bottom of the table. Summarized in Table 4-16 is a comparison of the maximum plate displacement to the plate displacement at the limiting tube location (the tube having the highest displacement), RIC1. As can be observed in the displaced geometry plots in Figures 4 4 35, the displacement gradients at the comer of the plate are high, so the maximum differential displacement at RICI is less than the maximum plate displacement reported in Table 4-15. 4 - 14 ,
l 4.6 SLB Frequency at Hot Standby and Full Power Conditions In order to identify the frequency of main steamline break in both the hot standby and full power conditions to support the steamline break tube support plate displacement analysis for Braidwood Unit 1, a review of References 4-1 and 4-2 for the Byron Nuclear Power Station
, Units 1 and 2 was completed. 1 4.6.1 Secondary Side Breaks Two main feedline pipe breaks have occurred on Westinghouse designed PWRs. The feedline breaks were downstream of the main feedwater isolation valves (MFWIVs), outside containment. The number of years at criticality calculated for all Westinghouse designed PWRs is 1370 years (Reference 4-1).
Using the Bayes theorem, the mean frequency of occurrence may be determined (Reference 4-2) by: mean = where r is the number of failures and t is the time interval. Substituting r = 2 and t = 1370, mean = 2A + 1, 23 = 1.8E-03/ year 2(1370) 1370 Since no secondary side breaks have occurred, other than these two main feedline breaks, the mean of the frequency for this event is 1.8E-03/ year (Reference 4-1). Based on the plant response to steamline/feedline breaks, this event is split into two initiators: (1) secondary side breaks downstream of the main steam isolation valves (MSIVs) or upstream of the MFWIVs and (2) secondary side breaks upstream of the MSIVs or downstream of the MFWIVs. The same frequency is used for both types of steamline/feedline breaks. That is, Secondary side breaks upstream of MSIVs or downstream of MFWIVs = 1.8E-03/ year Secondary side breaks downstream of MSIVs or upstream of MFWIVs = 1.8E-03/ yea.r. 4 - 15
4.6.2 Hot Standby and Full Power Conditions Evaluations A review of the operating histories for Braidwood Unit 1 Cycle 3 and 4 was completed to 1 determine the amount of time spent in Mode 3 versus full power operation. The result of this evaluation is shown in Table 4-17. The frequency of Mode 3 operation is defined as: Frequency of Mode 3, M M Mode 3 ,36.1 ,g,n3g Days in Cycles 3 & 4 959 Frequency of Mode 1 = 1 -Mode 3 = 0.962 The results of these calculations show a frequency in Mode 3 of 0.038 and frequency of Mode 1 of 0.962. Combining these frequencies with the IPE frequency of secondary side break upstream of the MSIVs gives a frequency of secondary side break upstream of the MSIVs in the Mode 3 condition and in the Mode 1 condition of: Mode 3 Secondary Side Break = (1.8E-03l year)x0.038 = 6.8E-05lyr. Mode 1 Secondary Side Break ='(1.8E-03l year) x 0.962 = 1.7E-03lyr. 4.7 Tubes Subject to Deformation in a SSE + LOCA Event This section deals with accident condition loadings in terms of their effects on tube deformation. The most limiting accident conditions relative to these concems are seismic (SSE) plus loss of coolant accident (LOCA). For the combined SSE + LOCA loading condition, the potential exists for yielding of the tube support plate in the vicinity of the wedge groups, accompanied by deformation of tubes and subsequent loss of flow area and a postulated in leakage. Tube deformation alone, although it impacts the steam generator cooling capability following a LOCA, is small and the increase in PCT is acceptable. Consequent in-leakage, however, may occur if axial cracks are present and propagate throughwall as tube deformation occurs. This deformation may also lead to opening of pre-existing tight through wall cracks, resulting in primary to secondary leakage during the SSE + LOCA event, with consequent in-leakage following the event. In leakage is a potential concern, as a small amount ofleakage may cause an unacceptable increase in the core PCT. Thus, any tubes that are defined to be potentially susceptible to deformation under SSE + LOCA loads are excluded from consideration under the IPC. 4 - 16
In the absence of plant specific LOCA and SSE loads for Braidwood Unit 1, a conservative upper bound estimate was made of the maximum number of tubes that would be affected at each wedge location. Using the results of an analysis for another plant having the same model steam generators, a conservanve upper bound of ( ]' per wedge group was established for the Braidwood Unit 1 steam generators. A summary of the applicable tubes for each of the wedge locations is provided in accompanying tables and figures. Braidwood Unit 1 is a four-loop plant. As such, there are two loops with "left-hand" steam generators and two loops with "right hand" steam generators. These designations refer to the orientation of the nozzles and mannys on the channel head. For the purpose of this analysis, "left-hand" units are defined to be those loops where the primary fluid flows from the reactor to the steam generator to the pump and back to the reactor vessel in a counter-clockwise direction. Conversely, for the "right hand" units, the flow is in the clockwise direction. The left- versus right hand designation rifects the location of the nozzles and manways, and the manner in which the columns are numbered for tube identification purposes. Reference configur.ations used in identifying wedge locations are shown in Figures 4-46 and 4-47 for the left-hand and right-hand units, respectively. As shown in the figures, for left hand units, the nozzle and tube column 1 are lo:ated at 0*, while for right-hand units they are located at 180*. Tabular. summaries of the tubes tha are potentially susceptible to collapse and subsequent in-leakage are summarized in Tables t-18 to 4-23 for the left hand units, and in Tables 4 24 to 4-29 for the right-hand units. Fc: the Braidwood Unit I steam generators there is a flow distribution baffle, seven tube supp: plates, and three baffle plates. The plate configuration is shown in Figure 4-15. Plate A c: responds to the flow distribution baffle, Plates B, E, and H are the flow baffles, and Plates C 3, F/G, J/K, and L, M, N, and P are the tube support plates. 1 Prior analysis for steam generators ci similar design show the flow distribution baffle to not impact the wrapper /shell under seis ne loads. Thus, it is judged that there will not be any tubes at the flow distribution baffle ~.: cation that are potentially susceptible to collapse unde.- combined LOCA+SSE. It will be n::ed that separate summary tables are provided for the lower TSPs, B-K (except E and H were a table common to both is used), and a single table for the upper TSPs L P. This is due to the orientation of wedge groups for each of the TSP. For the lower TSPs, the wedge groc s are rotated in some instances relative to the other TSPs, while for the upper TSPs, the wedge groups have the same angular orientation. Maps showing the location of the p:antially susceptible tubes are provided in Figures 4-48 to 4-57. The maps provide row and c:. mn designations relative to the left hand units. Column , numbers for the right hand units are shown in brackets. Identification of the potentially l susceptible tubes is based on crush us: results for both Model D and Series 51 steam 4 - 17
I 4 generators. For both sets of tests, however, wedge / tube configurations identical to those for the Braidwood Unit I steam generators were not tested. As such,it was not possible to identify exactly the [
)* that might be limiting at each wedge group. Thus, due to the uncertainties involved, there are generally (
being limiting. )* identified at each wedge group as i Finally, Table 4-30 provides an index of the applicable tables and figures identifying potentially susceptible tubes for each TSP. 4.8 Allowable SLB Leakage Limit An evaluation has been performed to determine the maximum permissible steam gene primary to secondary leak rate during a steam line break for the Braidwood Nuclear Pla Unit 1. The evaluation considered both pre-accident and accident initiated iodine results of the evaluation show that the accident initiated spike yields the limiting leak This case was based on a 30 rem thyroid dose at the site boundary and initial p secondary coolant iodine activity levels of 1 pCi/gm and 0.1 pCi/gm I-131, respectiv leak rate of 9.1 gpm was determined to be the upper limit for allowable prima
. leakage in the SG in the faulted loop. The SG in each of the three intact loops wa to leak at a rate of 150 gpd (approximately 0.1 gpm), the proposed Technical Specif LCO for implementation ofIPC. The allowable leak rate will increase in inverse p to a reduenon in the primary and secondary equilibrium coolant activity.
Thirty rem was selected as the thyroid dose acceptance criteria for a steam line brea assumed a:cident initiated iodine spike based on the guidance of the Standard Review Pla (NUREG 0800) Section 15.1,5, Appendix A. Only the release ofiodine and the re thyroid dose was considered in the leak rate determination. Whole-body doses due to gas immersion have been determined, in other evaluations, to be less limiting than the correspondmg thyroid doses. The salien: assumptions follow. m Initial primary coolant iodine activity - 1 pCi/gm DE I-131 The ca):ulation of primary coolant DE I-131 is based on a mixture of 5 iodine nuclides (1-131 through I-135) and the dose conversion factors of TID-14844, consistent with the Braidwood Technical Specification definition of DE I-131. 4 - 18 l l l
l + m Initial secondary coolant iodine activity - 0.1 pCi/gm I-131 The calculation of secondary coolant iodine activity is based on actual I-131 activity rather than DE I-131. Although, this is somewhat more conservative than the Technical Specification LCO which is based on DE I-131, secondary coolant activity still accounts for less than 6% (1.75 rem) of the allowable offsite dose. m Steam released to the environment (0 to 2 hours) from 3 SGs in the intact loops,416,573 lb from the affected SG,96,000 lb (the entire initial SG water mass)
- e Iodine partition coefficients for primary-secondary leakage SGs in intact loops,1.0 (leakage is assumed to be above the mixture level)
SG in faulted loop,1.0 (SG is assumed to steam dry) e Iodine partition coefficients for activny relean due to steaming of SG water SGs in intact loops, 0.1 SG in faulted loop,1.0 (SG is assumed to steam dry) e Atmospheric dispersion factor (SB 0 to 2 hours),7.70E-4 sec/m' s Thyroid dose conversion factors (I-131 through I-135) utilized in offsite dose calculation, ICRP-30 The activity released to the environment due to a main steam line break can be separated into two distinct releases: the release of the iodine activity that has been established in the secondary coolant prior to the accident and the release of the primary coolant iodine activity that is transferred by tube leakage during the accident. Based on the assumptions stated previously, the release of the activity initially contained in the secondary coolant (4 SGs) l results in a site boundary thyroid dose of approximately 1.75 rem. The dose contribution I from I gpm of primary to-secondary leakage (4 SGs) is approximately 3 rem. With the thyroid dose limit of 30 rem and with 1.75 rem from the initial activity contained in the secondary coolant, the total allowable primary to , secondary leak rate is (30 rem - 1.75)/3 rem per gpm, or 9.4 gpm. Allowing 0.1 gpm per each of the 3 intact SGs leaves (9.4 - 0.3) or 9.1 gpm for the SG on the faulted loop. 4 - 19
t
- 4.9 Acceptability of the Use of TRANFLO Code 4.9.1 Background In the early 1970's, there was a need to accurately predict the steam generator behavior under transient conditions, such as a steam line break (SLB) event; a transient can develop thermal hydraulic loads on the intemal components and shell of the steam generator. Structural analyses are required to analyze the adequacy of the individual components and the whole steam generator under various thermal and hydraulic loads. With the assistance of MPR Associates, Westinghouse developed and verified the TRANFLO computer code to conservatively model the thermal and hydraulic conditions within the steam generator under transient conditions.
The secondary side of the steam generator involves water boiling under high pressure during normal operating conditions. During a transient such as a SLB event, it may be subject to vapor generation due to rapid depressurization. Therefore, analysis methods have to recognize this characteristic of two-phase fluid behavior. In the early stake of the computer code development and technology of two phase flow, a homogeneous model was used. For current analyses, a more accurate slip flow model is used which takes into consideration the relative velocity between the liquid and vapor phases. Development of the TRANFLO code reflects this general trend of the two-phase flow modeling. The first version of TRANFLO was a homogeneous model, and it was later updated to a drift flux model to simulate the effect of two-phase slip. Since the original issue of the code, Westinghouse has made several l enhancements to the code and has performed the appropriate verification and validation of these changes. These changes do not significantly affect the calculated pressure drops across the steam, generator tube support plates. 4.9.2 Acceptability of Application of TRANFLO The original version of the TRANFLO code (Reference 4-3) was reviewed and approved by the NRC in Reference 4-4. TRANFLO was used as part of the Westinghouse mass and energy release / containment analysis methodology. Specifically, the code was used to predict steam generator (SG) secondary side behavior following a spectrum of steam line breaks. Its output was the prediction of the quality of the steam at the break as a function of time. The quality is calculated as a function of power level, as well as break size. In order to assure that the TRANFLO code evaluates a conservatively high exit quality, Reference 4-4 states that the calculational sequences were reviewed for the determination of " conditions prior to entering into the separation stages. The calculated rate, quality and energy content of the two phase mixture entering the separation stages must be evaluated conservatively". This review was completed and found to be acceptable, as the NRC staff concludes in 4 - 20 i
I Reference 4-4 that the TRANFLO code is an acceptable code for calculating mass and energy i release data following a postulated MSLB. Therefore, it is concluded that the TRANFLO model is appropriate for predicting SG behavior (including tube bundle region) under the range of SLB conditions. For the current application, TRANFLO is used in conjunction with a structural analysis code to predict TSP movement following the same SLB event. The key data transferred between the transient code and the structural code is the pressure drop across the TSP as a function of . time. This pressure drop calculation depends on the fluid conditions in the steam generator
- and on the adequacy of the loss coefficients along the flow paths. The conditions in the tube bundle as calculated by TRANFLO have been previously reviewed. Furtherjustification of the adequacy of the pressure drop calculation is discussed in Section 4.9.4.
4.9.3 Diffprent Versions of TRANFLO The original version of the TRANFLO code has been reviewed and approved by the NRC. Westinghouse has continued to update the code with new models that more accurately predict steam generator behavior. Four versions of TRANFLO have been used in calculation. The following are descriptions of each of them. The Orininal yersion (Aoril 1974) This is the original homogeneous model, which MPR Associates developed in April 1974. The code predicts mass flow rate, pressure, pressure drop, fluid temperature, steam quality and void fraction. The code document includes results of TRANFLO calculations for a 51 Series steam genera:or subject to water and steam blowdown due to an SLB event. The document also presents code verification using blowdown test data from pressurized vessels. Westinghouse documer.ted this version in detail in September 1976, including code verification using vesse' blowdown data. Sensitivity analyses were also performed and documented to show that the modelling was conservative. This included sensitivities te loss coefficient. The TRANFLO code uses an elemental control volume approach to calculate the thermal. hydraulics of a steam and water system undergoing rapid changes. Fluid conditions may be subcooled, two phase or superheated. The code considers fluid flows being one dimensional. Control volumes simula:e the geometrical model, and flow connectors allow mass and energy exchange between conrol volumes. Each nodal volume has mass and energy that are homogeneous throughou: the volume. Flow connectors account for flow and pressure crops. The system model allows flow entering or leaving any control volume. This then allom that 4 - 21 l l
feedwater flows into a steam generator and steam flows out ofit. The system models also permit a heat source, which then can simulate the tube bundle with hot water flow. TRANFLO solves for system conditions by satisfying mass, momentum and energy equations for all control volumes. It models the effects of two-phase flows on pressure losses. The code allows a variety of heat transfer correlations for the tube bundle. It covers all regimes from forced convection to subcooled liquid through boiling and forced convection to steam. The Drift Flux Version (November IPJ.Q) This version implements a drift flux model to better simulate relative flow velocity between water and steam. For example, it allows a realistic simulation of counter-current flow of steam and water. It required modification of the mass, momentum and energy equations of the two-phase flo.w. A capability is provided for monitoring calculated variables for convenient examination of results. TRANFLO Version 1.0 (November 1991) This version accepts transient data of parameters as direct inputs, rather than supplying input subroutines, as used in the drift-flux version. It also improves printouts and plots. This version maintains the drift-flux model, and includes the addition of thermal conductivity of Alloy 690 tubing. TRANFLO Version LQ Danuary 1993)
- This version provides an option for two inlets of feedwater flow into the steam generator. It involves minor changes to a subroutine for specifying feedwater flow. This version is used for separate inlets of simultaneous feedwater flow from main and auxiliary feedwater nozzle.
4.9.4 Verification of Loop Pressure Drop Correlations As discussed earlier, an accurate prediction of mass and energy release from the vessel means that the TRANFLO code properly calculates local thermal hydraulics in various nodes (i.e., elemental control volume and flow connector). It is critical to accurately simulate the pressure drop inside a steam generator that consists of various components, such as the tube bundle with tube support plates, moisture separators, and downcomer. Hydraulic loads on various components depend on accurate pressure drop calculations. Thus, it is important to verify the pressure drop calculations through the circulation loop. The TRANFLO code uses the same pressure drop correlations as the Westinghouse GENF code, which is a performance program. The GENF code predicts one-dimensional steady 4 - 22
state conditions, which include pressure drops along the circulation flow loop. Both laboratory tests and field data validate the accuracy of the GENF code, ne GENF code is used extensively for steam generator performance analysis and has been shown to accurately predict operating steam generator conditions. When provided with all geometrical input and operating conditions, GENF calculates the steam pressure, steam flow rate, circulation ratio, pressure drops, and other thermal hydraulic data. He circulation ratio is a ratio of total flow through the tube bundle to feedwater flow. For a dry and saturated steen generator, there exists a hydrostatic head difference between the downcomer and the tube bundle. This head difference serves as the driving head to circulate flow between them (see Figure 4-58). The driving head is constar.t for given operating specifications, such as power level and water level. The total pressure drop through the circulation loop is equal to the driving head. Pressure drops depend on loss coefficient and flow rate (i.e., velocity). Loss coefficient consists of friction loss and form loss; the majority of the loss is due to the form loss in the steam generator. Since the driving head is constant, a higher loss coefficient means a lower circulation flow rate and a lower circulation ratio. A lower loss coefficient yields a higher circulation ratio. Therefore, an accurate prediction of the circulation ratio depends on an accurate loss coefficient. - Model boiler and field tests are used in qualifying the loss coefficients in the flow loop of the steam generator. For example, the major contributors of the pressure drop are the primary separator and tube support plates. The loss coefficient of the primary separator has been verified usmg model boilers and field steam generators (Reference 4-5). Similarly, loss coefficients of tube support plates have been developed using test data; Figure 4 59 presenu the correlation of the loss coefficient and test data. Figure 4-60 shows a typical comparison between predicted and actual measured circulation ratio. There is good agreement in circulation ratio between the prediction and measurement The TRAhTLO model uses the same loss coefficient correlations as GENF code. This provides assurance in properly calculating the pressure drops throughout the steam generater 4.9.5 Summary This section presents a summary of the adequacy of the TRANFLO code for its current applications Blowdown test data of simulated reactor vessels validate the adequacy of the code in predicting the steam and water blowdown transient. The NRC has accepted the TRANFLO code in calculating mass and energy release to the containment during a steam generator blowdown due to feed or steam line break. 4 - 23
As part ofits review, the NRC accepted the code's ability to accurately predict local thermal-hydraulics in the vessel. The calculated pressure agrees well with the measured vessel pressure. Flow through the internals of the steam generator depends on accurate prediction of pressure drops, which relies on the accuracy of the loss coefficients along the flow paths. Test data of pressure drops from model boiler and field steam generators have been applied to verify the correlations for the loss coefficients. Westinghouse has made modifications to the code to better predict steam generator behavior following a SLB event. Westinghouse has performed the verification and validation consistent with the methods approved by the NRC staff for the original version. In conclusion, the TRANFLO code is a verified program for adequately predicting thermal-hydraulic conditions during the blowdown transient of a steam generator due to a feed or steam line break. 4.10 References 4-1.
"Quantification of Byron IPE Steamline/Feedline Break Frequency",
CN-COA-92 537-R1, Appendix RI-B, April 1993. 4-2.
" Byron IPE Initiating Event Calculations and Notebook - Draft",
CN COA-92-537-RO, December 1993. 4-3. R. E. Land, "TRANFLO Steam Generator Code Description", Westinghouse Nuclear Energy System, WCAP-8821, September 1976. 4-4. Memo from C. O. Thomas to E. P. Rahe, " Proprietary Content Review of SER on WCAP-8821 and WCAP-8822", October 14, 1982. 4-5. P. W. Bird and P. J. Prabhu, " Review of Primary Separator Loss Coefficient", WTD TH-80-010, July 1980. l 4 - 24
l l l Table 4-1 Initial and Boundary Conditions of the TRANFLO Calculation Models ' for Model D3 and D4 Steam Generator l Initial Conditions Boundary Conditions l SG Mode of Steam Nozzle
.Cass Model Ooeration Water Level Flow Limiter FeedwaterFlow 1 D3 Hot Standby @ ~ Normal Setting Yes Small 2 D4 Full Power @ Normal Setting Yes Full Flow 3 D4 Hot Standby @ Uppermost TSP Yes Excessive l
I l 4 - 25 1
. Table 4-2 Peak Pressure Drop at Different Tube Support Plates (Hot Leg Only for Half Plate) '
SG & Case SG & Case SG & Case Palamatat Dl. .1 DJ4. _2 DA. _1 Flow splits within tube bundle Yes No Yes TSP with max peak Dp 'a Peak Dp @ uppermost TSP Max peak Dp, psi Peak max Dp @ bottom Plate i Dp @ Hot Leg Top TSP l _ i l l l 4 - 26 l re-
l
- l Table 4-3 Summary of Component Materials l C-t Material ll Tube Support Plate SA-285 Grade C Stayrod SA-106 Grade B Spacer SA-106 Grade B Tube Inconel600
)
e 4 - 27 DISK 215 - BRDWDTBL431 - 04/18/94
i i{ i Table 4-4 1 Summary of Material Properties SA-285, Gr. C l[ TEMPERATURE I PROPERTY CODE ED. 70 200 300 400 500 600 1 Young's Modulus 71 700 27.90 27.70 27.40 27.00 26.40 25.70 24.80 Coemeient ofThermal 71 6.07 6.38 6.60 6.82 7.02 7.23 Expansion 7.44 Density - 0.284 0.283 0.283 0.282 0.281 0.281 0.280 7.35 7.33 7.32 7.30 7.28 7.26 7.25 l l PROPERTY UNITS l Young's Modulus psi x 1.0E06 Coemeient ofThermal in/in/deg. F x 1.0E 06 Expansion Density Ib/in^3 lb sec^2hn^4 x 1.0E-4 4 - 28 DISK 215 - BRDWD'iTBL432 04/19/94 l
Table 4-5 Summary of Material Properties SA-106, Gr. B ll TEMPERATURE PROPERTY CODE ED. 70 200 300 i 400 ' 500 '600 700 'i Young's Modulus 71 27.90 27.70 27.40.- 27.00 26.40 25.70 24.80,. Cocilicient of Thermal 71 6.07 6.38 6.60 6.82 7.02 7.23 7.44 Expansion
; Density - 0.284 0.283 0.283. 0.282 0.281 0.281 0.280 7.35 7.33 7.32 7.30 7.28 7.26 7.25 i
PROPERTY UNITS l
. Young's Modulus psi x 1.0E06 i
i Coefficient of Tnmnal in/in/deg. F x 1.0E-06 Expansion Density lb/m'3 l lb sec^2/m^4 x 1.0E-4 4 - 29 DLSK 215 BRDWD\TBl.A32 - 04/19/94
Table 4-6 Summary of Material Properties SB-166 ll TEMPERATURE l PROPERTY CODE ED. 70 200 300 400 ' Young's Modulus 500 600 700 i 71 31.70 30.90 30.50 30.00 29.60 29.20 28.60 Coefficient ofThermal 71 7.13 7.40 7.56 7.70 7.80 Expansion 7.90 8.00 Density - - 0.306 0.305 0.305 0.304 0.303 0.302 7.923 7.905 7.886 7.867 7.847 7.828. I PROPERTY l UNITS l Young's Modulus psi x 1.0E06 CoeDicient of Thennal in/in/deg. F x 1.0E 06 Expansion Density Ib/in^3 lb sec^2/in^4 x 1.0E-4
.L 4 - 30 DISK 215 - BRDWD\TBL432 - 04/19/94
a l l Table 4-7 Summary of Equivalent Plate Properties Reference Effective Effective Young's Young's Poisson's Plate Modulus Modulus Ratio A -Inside 32" Radius 2.605E+07 4.810E+06 0.2466 l A - Outside 32" Radius ;! 2.605E+07 5.850E+06 0.2654 C. F. J. L M. N. P* 2.605E+07 2.470E+06 0.6445
* - These plates have flow holes, resulting in a significantly reduced value for Young's Modulus 4-31 DISK 215 - BRDWD\TBL435 - 04/18/94
Table 4 8 Summary of Effective Plate Densities - R 4
' mes M
i 9 e DISK 215 - BRDWD\TBL436 04/18/94 4 - 32
Table 4 9 Comparison of Natural Frequencies Full Versus Reduced DOF
=a b
e e e
- 4 - 33 l
DISK 215. BRDWD\TBL437 04/19/94 I l i
l Table 4-10 Summary of TSP Displacements for
.. Postulated SLB Events for Model D3 and D4 Steam Generators * '
-a I
J 4 l 1 l 4 4 - 34 DISK 215 - BRDWDiTBL441 - 04/18/94
i I I Table 4-11 l Comparison of Component Dimensions Model D3 versus Model D4 Steam Generators l Dimension Model D3 Model D4 l
~ ~
ShellID a ShellThichess Channel Head Bowl Radius Channel Head Tnickness Tubesheet Thi:kness Hole Diamem
- Number Hdes Tube Pit:h .
4 - 35 DISPs 215 - BRDWD\TBL442 - 04/19/94
e Table 4-12. Summary of Tubesheet Displacements m Model D3 SLB Analysis a-e l a 9 e I i 4 4 - 36 DISK 215 -BRDWD\TBL443 - 04/19/94 i _ _ m,, -._ , .m+ s- ~ ' '"-' #---*
,,.,_,-,ewrw-y V "" "
Table 4-13 Summary of Vertical Bar Stresses
, Model D4 Steam Generators i 9
9 4 4
?
E M 4 - 37 DISE 215 BRDWD\TBL444 04/20/94
3 Table 414 Summary of Number of Tubes Having Different Displacement Magnitudes Model D4 Steam Generator , - Steam Line Break Load Cases L f
'N t
4 - 38 DISK 215 BRDWIATBL451 - 0,is9S4
Table 4-15 Summary of Tubes Having Relative Tube / Plate Displacements That Exceed 0.400 inch g. O e WIMI 4 - 39 DISK 215 -BRDMTBIA52 - 04/19/94
i . . T t Table 4-16 Comparison of Maximum Displacement at Plate Edge and at Limiting Tube Location a r J t 4 - 40 DISK 215 - BRDWif.., WINP\TBIA53 - 04/19/94
,,.-r- - - r - - __y . . .
a Table 4-17 Braidwood Unit 1 Mode 3 Durations Hours in Event Offline Date Mode 3 Online Date J
' Online Days Cycle 3 AIR 02 N/A 360
- 5/18/91 AIF19 7/16/91 0 7/27/91 60 AIF20 10/9/91 0 10/14/91 74 l AIF21 11/6/91 54 11/11/91 24 A1F22 2/5/92 62 20/92 86 i ! AIF23 3/21/9 8 3/21/92 43
} AIR 03 9/1/92 26' N/A 165 Hours in Mode 3 = 510 Onime Days = 452 '
Days in Mode 3 = 21.2 Days m Cycle = 472 l Cycle 4 A1R03 N/A 56* 11/3/92 j I A1M03 11/20/92 124 ' 11/25/92 18 AIF24 in/93 38 1/14/93 44 AIM 04 5/29/93 35 5/30/93 136 1 A1F25 6/2/93 65 i 6n/93 4 ' AIF26 10/24/93 < 21 11/11/93 140 A1R04 3/4/94 18' N/A 114 Hours in Mode 3 = 357 Onlir.e Days = 456 j Days in Mode 3 = 14.9 Days e Cycle = 487 i l 1 ,
- Mode 3 times associated with planned refueling outages.
Cycle 3 percent of time spent in Mode 3 = 4.50% Cycle 3 percent of time spent in Mode 3 minus Refuelling Mode 3 houn = 1.09% Cycle 4 percent of time spent in Mode 3 = 3.05% Cycle 4 percent of time spent in Mode 3 minus Refuelling Mode 3 houn = 2.42% 4 4 - 41
.m ,
i i l i Table 4-18 Tubes Potentially Susceptible to Coll' apse and In-Leakage TSP C, D Left-Hand Unit
., a 1
e P , f 4 - 42 DISK 215- BRDWD\TBL42 - 04/19/94
. = - .-
Table 4-19 Tubes Potentially Susceptible to Collapse and In-Leakage TSP F, G Left-Hand Unit _ a 6 I I I e t e JM M 4 - 43 DISK 215 - BRDWD\TBL42- 04/19/94 L -_ _ _ - ,_ _ _
e Table 4-20 Tubes Potentially Susceptible to Collapse and In-Leakage TSP J, K Left-Hand Unit a M l 4 - 44 DISK 215 - BRDWD\TBL42- 04/19/94
Table 4-21 Tubes Potentially Susceptible to Collapse and In-Leakage TSP L-P Left-Hand Unit
= a k
w M k 4 - 45 DISK 215 - BRDWD ~3L42 - 04n 9/94 I
. - . l
i Table 4-22 Tubes Potentially Susceptible to Collapse and In-Leakage TSP B Left Hand Unit 4 t 6 m 4 - 46 DISK 215 - BRDWD\TBL42- 04/19/94 !
3 f Table 4-23 Tubes Potentially Susceptible to Collapse and In-Leakage TSP E, H Left-Hand Unit a 4 . 4 - 47 DISK 215 - BRDWDiTBL42 - 04/19/94 1
Table 4-24 Tubes Potentially Susceptible to Collapse and In-Leakage TSP C, D Right-Hand Unit A 6 e 9 m W l 4 - 48 DISK 215- BRDWD\TBL42- 04/19/94
l l l Table 4-25 l Tubes Potentially Susceptible to Collapse and In-Leakage TSP F, G Right-Hand Unit
- a 4
4 4
/
O
' amet smagni a 4 - 49 DISK 215 - BRDWD\TBL42- 04/19/94
Table 4-26 Tubes Potentially Susceptible to Collapse and In-Leakage TSP J, K Right-Hand Unit 4 l - 4 - 50 DISK 215 - BRDWDiTBL42 - 04/19/94
J Table 4-27 Tubes Potentially Susceptible to Collapse and In-leakage TSP L-P Right-Hand Unit a 4 tuim 4 - 51 l DISK 215 - BRDWD\TBL42 - 04/19/94 {
i Table 4-28 Tubes Potentially Susceptible to Collapse and In-Leakage
-TSP B Right-Hand Unit a
I unsa M l 4 - 52 DISK 215- BRDWD\TBL42- 04/19/94
Table 4-29 Tubes Potentially Susceptible to Collapse and In-Leakage TSP E H Right-Hand Unit 1 e t l l 1 4 - 53 DISK 215 - BRDWD\TBL42 - 04/19/94
- 1
Table 4-30
, Table and Figum Index for TSP Row / Column Identification Summary Tables Tube Map Left-Hand SG Right-Hand SG I" "'
B 4-22 4-28 4-48, 4-49 C .4-18 4-24 4-48, 4-49 D 4-18 4-24 4 50, 4-51 E 4-23 4-29 452,453 F 4-19 4-25 454,455 G 4-19 4-25 4 30, 4-51 H 4-23 4-29 452,453 J 4-20 4-26 4-48, 4-49 K 4-20 4-26 4 48,4-49 L 4-21 4-27 4 56, 4-57 l M 4-21 4-27 4 56, 4-57 N 4-21 4-27 4 56, 4-57 P 4-21 4-27 4 56, 4-57 l l l 4 - 54 l l
,-w. y - ... - . - -_m..7-,,,, ,. __,m ,, ,. . _ . _ _ , _ . - - . , _ _ , . _ _ _ _
-a 1
Figure 4-1. Secondary Side Nodes, and Tube Support Plate Identification (See Figure 4-2 for Preheater Detail) J 4 - 55
~
-a 4
t i i l l Figure 4-2. Preheater Nodes, and Bame Identification of Model D3 Steam Generator I 1 4 - 56
'* -es--n
- 1. , -.
- a l
l l l I 1 Figure 4-3. Secondary Side Fluid Nodes and Flow Connectors for Model D3 Steam I' Generator 4 - 57
-- ---w -- w k ww-r -- v--umy-we w er -
- ,7T-
1 a 1 l l 4 8 Figure 4-4. Primary Fluid Nodes and its Flow Connectors, Metal Heat Nodes and Its Heat Transfer Connectors, and Secondary Fluid Modes Within Tube Bundle 4 - 58
4 . t
- a A
Figure 4-5. Pressure drop through tube support plates T. S and R during steam line break of a Model D3 (Case 1; 5 - TSP T, O - TSP S, + - TSP R) _. a a Figure 4-6 Pressure drop through tube support plates Qhot, L and G during steam line break of a Model D3 (Case 1; 5 - TSP Qhot, Q TSP L, + - TSP G) 4 59
- a l
o l i l 1 Figure 4-7. Pressure drop through tube suppon plates Qhot. L and G during steam line break of a Model D3 (Case 1; E - TSP C, Q- TSP A) 4 4 - 60 1 i l
l 1 l I l 1
-a a
l' l Figure 4-8. Secondary Side Nodes and Tube Support Plates identification of TRANFLO Model for Model D4 Steam Generator 4 - 61 1
1 l a Figure 4-9. Pressure drop through tube support plates M, N and P during steam line break of a Model D4 (case 2; O - TSP N, E - TSP P, + - TSP M)
, _a Figure 4 10.
Pressure drop through tube support plates L, J and F during steam line break of a Model D4 (Case 2; O - TSP J, E - TSP L, + - TSP Fi 4 - 62
i
, I i
l I 1 L a :
~
Figure 4-11 Pressure drop through tube support plates A and C during steam line break of a Model D4 (Case 2; Q- TSP A, E - TSP C)
-a ;
- 2. Figure 412 Pressure drop through tube support plates M, N and P during steam line break of a Model D4 (Case 3; 5 - TSP P, - TSP N, + - TSP M) 4 - 63
_ a Figure 4-13. Pressure drop through tube support plates M N and P during steam line , break of a Model D4 (Case 3; E - TSP L, O - TSP J, + - TSP F) a a Figure 414. Pressure drop through tube support plates M, N and P during steam line - break of a Model D4 (Case 3; E - TSP C, O - TSP A) 4 - 64 l l
m 1
-a ,
l s i L
?
d Figun 4-15. Tube Bundle Geometry 4 - 65
..., . , . , , ._,. _ _ . - , _ . . . - , . _ ..._. ,.__, -.._, _ ,, ~ .. - - _ . _ . . ,. - , . - - - . . - , . . . . . . .
l 1 1
-a I
i 1
)
a l t t i l l Figure 4-16. Tierod / Spacer Locations 4-66 l
1.. - , s
, i 4 ,a i a
d f I L
.Ic t.
i
+
4 Figure 417. Plate A (IH) Support Locations 4 - 67 ! 1
- ., . .- . - - . . . , _ _ _ . _ - . _ . _ _ _ _ _ . , _ _ , , , , . _ _ . . _ _ _ _ . - _ . _ , _ . . . . . , ~ . , _ . _ ,, _. , . . , . , _ . _ _ _ , -,, . , < . . , -
, . . . . , ~ . ,
-a 4
1W Figure 4-18. Plate C (3H) Support Locations 4 - 68
-A t t 1
a ik i e Figure 4-19. Plate F (SH) Support Locations 4 - 69 I
L
~a l
I l i I 5 F Figure 4 20. Plate ,1 (7H) Support Locations 4 - 70
j
)
I
- a t
i f P
.i h
t i 6 1 ( f r 9 i i I s f
<m e I
Figure 4-21. Plate L (8H) Support Locations . 1 4 - 71 '
a t l l . I Figure 4-22. Plate M (9H) Support Locations 4 - 72 1
~~a i
I t
?
?
I I Figurt 4-23 Plate h (10H) Support Locations i 4 - 73
-a Figure 4-24. Plate P (11H) Support Locations i
\
4 - 74 l t l [ l l
i y
$W -
l I t W NP
-n ll l WD i 1
4 Figure 4-25. Overall Finite Element Model Geometry 4 - 75
i l i i
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Figure 4-26. Mode Shape Plot - Plate A Full Set of DOF Mode 1 4 76
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, . . . $,?h' ya ' ' - ,
, '^',,,l' .,',} ' ' < : ,
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Figure 4 27. Mode Shape Plot - Plate A Full Set of DOF Mode 2 4 - 77
4
. . ~ . . .,- . . . ... ......m . ,_
p - , N ' ~ n s,
-~
, ,; ;, ',,'~ .
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Figure 4 28. Mode Shape Plot - Plate A Full Set of DOF Mode 3 4 - 78
[ l I l i
/ . - s . /
, p.
- ,# a- , - 1. /~
* , ,a
~ a- ~. ~ M~ f's .><.
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Figure 4-29. Mode Shape Plot - Plate A Reduced Set of DOF Mode 1 4-79 l *
'~~ .. . n:n :: :- '***
, , ,,f %,- ~, , , ', , ',x', V', 'x' ,,'] s 9
, . ,, , , ,#, A ,,
,',x,. .
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I i 1 1 1 l Figure 4 30. Mode Shape Plot - Plate A Reduced Set of DOF Mode 2 4 80
f
\
. ,, . . . ;. ~:: .,
* - N ' 'y n
.. p - . ,- ,, , 'v , , ..
;a, - .
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,- / ..e, ..,- _
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. . ,-. . . y, l
l l Figure 4 31. Mode Shape Plot - Plate A Reduced Set of DOF Mode 3 4 - 11
. . . . .y :: :r ' '.: ~~
,..:n* -~ ,
,,,- ~, - '. -
' ~~. ,,
,, - ,,, ,,, ,x ~. :.~n.. >..
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x:v;;:'),.,,6. 3
~ , . ..
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. ,, /, , -
- NT
~' , XRN \
;< N N ,.
.- /,*
Figure 4-32. Displaced Geometry Plate A(1H) : Time = 0.902 see SLB + Excess Feedwater Transient 4 - 82
,, N ','.,,~,, ,., , , ,.. . . ;;. . .- ,
. ..9^*.- N,- -
~... ,,
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r
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Figure 4 33. Displaced Geometry Plate C(3H) : Time = 1.886 see SLB + Excess Feedwater Transient 4 - 83
c
- J
- < ~ .% -
_ _ ~
,_ ,' NN-g %
gf ww _,..,. A gwm ,
- f
. , s n . s, - ,
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. , u., , , , ,. ,
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x u,- se .y -~
. s w. ,.s.k. . g,~,
- u. ..u.
.w. ~,.y ,
., a. . .
.....u..
~
,s Figure 4 34. Displaced Geometry Plate J(7H) : Time = 0.264 see SLB + Excess Feedwater Transient
. . 84
b l i f' 1 K
.ff-e '*
. . ..is* % * %,... '~ =+ f ,-..' W ,, ,'" ' %,
. c, - . , ., . .
',..~.
**.'9c'
.**,'R,
',,9 " ** .
f,, , ', % .% , - l ' ,,
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-. x, .,
., N*
- ~~ > n, - ' ', f ' . .
. ' , ,,v, ' ,';, ,-
~
3
. + ,.. .- .. .->. . .. . . .c
* .5' * . ~
'{ .' . >. X %' E'.
~-
y
.x..; q . ,ML . ' ; .
; ; e \..;,,.
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.s s sw %,-
N
,4,y a
s ,, -
,. s , .
.' f -
~.-- e
'%f' .
s
/ N Figure 4-35. Displaced Geometn Plate J(7H) : Time = 1.926 sec SLB + Excess Feedwater Transient I
4 - 85 l I i I
, - . - - - , ~,_ .-___..-__'
)
1
. 1 a
- a 4
Figure 4 36. Displacement Time History Response SLB + Excess Feedwater Transient Plates A(IH), C(3H), F(5H), J(7H) 4 - 86
9 I I W l
, a )
l l 4 i e t
~
Figure 4-37. Displacement Time History Response SLB + Excess Feedwater Transient I Plates L(8H), M(9H), N(10H), P(11H) l l 4 - 87
=
a l
\
a
~ .
Figure 4-38 ~ Maximum Stress Intensity - SLB + Excess Feedwater Transient Plate A (1H) 4 88
)
t
* .q
-a l
l
~
Figure 4 39 Minimum Stress Intensity SLB + Excess Feedwater Transient Plate A (1H) 4 - 89 i
1 I
~
l
-a l l
i
. l i
e Figure 4-40 - Maximum Stress Intensity SLB + Excess Feedwater Transient Plate C (3H) 4 - 90 l l l l
I
- a t
l Figure 4-41 Minimum Stress Intensity SLB + Excess Feedwater Transient Plate C (3H) 4 - 91
r
.a 0
l i l Figure 442 Maximum Stress Intensity SLB + Excess Feedwater Traasient Plate J (7H) (Maximum Upward Response) 4 - 92
l
)
-a w
~
~
Figure 4-43 Minimum Stress intensity SLB + Excess Feedwater Transient Plate J (7H) (Maximum Upward Response) 4 93
-.. a 4
4 Figure 4-44 Maximum Stress Intensity SLB + Excess Feedwater Transient Plate J (7H)(Maximum Downward Response) i 4 )
l
~
~a 4
~
Figure 4-45 Minimum Stress Intensity SLB + Excess Feedwater Transient Plate J (7H)(Maximum Downward Response) 4 - 95
7 90 Quadrant 2 - Quadrant 1 Hot Leg DMder Plate Manway o Nottle e 180
- 0 360' Counn 114 Colen 1 Quadrant 3 4 Colo Leg Quaarant 4 .
270 Figure 4 46. Reference Configuration ' Looking Down on Steam Generator Left Hand Unit 4 96
- SK 215 - @ABar.emwacu a<= - ^-
l 7,.
- p. .
L 4. 90* Quadrant 2 Quadrant 1 - Hot Leg DMder Plate ManwsY Nottle 180~ 0: 360' Coksnn 114 Cola-- 1 Quadrant 3 Cold Leg Quadrant 4 o 270 i Figure 4 47. Reference Configuration Looking Down on Steam Generator Right Hand Unit i 4 - 97 r ~w -s** 9 ' ' ' ' ' ' * '* ~ ' ' ' ' ' ' ' ~ ~ - ' ^ ~ ~
. . _- -. .- = . _ -- ,
4 a 5 l . ( ) i i } l i I Figure 4-48. Tubes Potentially Susceptible to Collapse and In-Lesk-( ~ Braidwood Unit 1 TSP C, J Quadrant 1 4 - 98 4
, _ _ , , .._.-,--.--n~w - - , - - ' ' - -'-' '
~ , l a 1 h Figure 4-49. Tubes Potentially Susceptible to Collapse and In-Leakage Braidwood Unit 1 TSP C, J Quadrant 2 4 - 99 f
l l i
- a i
't e f
'~
Figure 4 50. Tubes Potentially Susceptible to Collapse and In-Leakage - Braidwood Unit 1 TSP D, G Quadrant 3 4 - 100
l l l i
-a i
1 i l l ~ l
~
Figure 4-51. Tubes Potentially Susceptible to Collapse and In-Leakage Braidwood Unit 1 TSP D. G Quadrant 4 4 101
1 l
. 1
.I
,a
. i l
?
ligure 4 52. Tubes Potentially Susceptible to Collapse.and In-Leakage
~
Braidwood Unit 1 TSP E,11 Quadrant 3 4 - 102 I l l l I
F.', .,
- a e
1 l Figure 4 53. Tubes Potentially Susceptible to Collapse and in-Leakage Brandwood Unit 1 TSP E, H Quadrant 4 4 - 103 I
a
~
~
Figurr 4-54. Tubes Potentially Susceptible to Collapse and In-Leakage Braidwood Unit 1 TSP F Quadrant 1 4 -104
-e - _ , - _ - ,__ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ - . _ - _ . _ _ . . _ . . . . _ _ _ _ _ _ _ _ _ - .- - , _ . , - _ . -
+
\
l i
- a i
l I f t
~
Figure 4-55. Tubes Potentially Susceptible to Collapse and In Leakage Braidwood Unit 1 TSP F Quadrant 2 4 - 105
a 9 l
. I, t
P 4 i k Figure 4-56. Tubes Potentially Susceptible to Collapse and In-Leakage Braidwood Unit 1 TSP L, M, N, P Quadrant 1 4 - 106 t
- - , - , - , , - , - - ....n. - , . , , - - - - - . - - - - ~ --
l
)
1 1
-a l
i
~
Figure 4 57. Tubes Potentially Susceptible to Collapse and In Leakage Braidwood Unit 1 TSP L, M, N, P Quadrant 2 4 - 107
. . _ . . _ . . .. . - - - . - ... ~ - - .
Steam Flow ak ! i 4 h ! 4 Steam o o h _
.o Primary Separator N ec e
- o :o Water
}o" / Level
~- . r -- ,
- p o' ~~
'o '
'-_-~
--> ] o' '4k 'I _ Recirculated os L, , Water Feedwater o a
Flow u o oo ooc - ! oe o 1 og ,o oo o oo o'o a ** j! Tube [ so
% oo ', oo ao o o*p- / Support Plate oc o e o Downcomer :- o' o ',f,o ,
.n.* -
o e o 0 L e* O V i, o oo ' e -Tube Bundle 1 _ o o oe o, s ke IV o o o el MI '
< I
!M hM N 3
Coolant in Coolant Out Figure 4 58. Diagram of Flow Circulation During Power Operation 4 - 108
1 1 4 i l l
-a !
l i P i i i d Figure 4-59. Counterbored Structural Quatrefoil Loss CoefTicients i 4 - 109 1 1 I
- l
k
~
n J 1 4 Figure 4-60. GENF Verification, Circulation Ratio Versus Lead 4 - 110 1
4 4 5.0 DATABASE SUPPORTING ALTERNATE REPAIR CRITERIA ~ This section describes the database supporting the altemate repair criteria (ARC) burst snd leak rate correlations. The database for 3/4 inch diameter tubing is described in EPRI Report NP-7480 L, Volume 2 (Reference 51). However, at the February 8,1994 NRC/ Industry
- meeting, the NRC presented resolution ofindustry comments on draft NUREG-1477. The NRC identified guidelines for application of leak rate versus voltage correlations and for removal of data outliers in the burst and leak rate correlations. This section applies the NRC guidance on removal of outliers to update the database for the 3/4 inch tubing correlations.
5.1 Data Outlier Evaluation At the February 8 meeting, the NRC provided the following guidance for removal of data outliers:
- Data can be deleted in case of an invalid test.
- Any morphology criteria for deleting outliers must be rigorously defined and applied to all the data.
Criteria for deleting outliers must be able to be unambiguously applied by an independent observer. '
- It is acceptable to modify data or a model in a conservative manner.
Based on the above NRC guidance, the outlier evaluation of Reference 5-1 is updated in this section. Consistent mth the NRC guidance, criteria for removal of outliers are defined in this section and applied to the database. These criteria were developed and approved by the EPRI Adhoc Alternate Repur Criteria (ARC) Committee. Consistent with Reference 5-1, only conservative outliers which are high on the burst correlation or low on the leak rate correlation are evaluted for removal from the database. Although the outliers are conservative in this manner, their retention in the database can increase the uncertainties from the regression analyses such that their removal from the database can lead to non-conservatisms m anrjyses applying uncertainties at upper or lower tolerances.
. Criterion 1 for outlier removal applies to invalid data including unacceptable specimens, invalid measuremenu, etc. To describe the invalid ' test condition, Criteria la to le are defined as described m Table 51. Table 5-1 provides examples of invalid data that are applicable to the EPRI database.
5-1 > l
1 i Criterion 2 for outlier removal applies to specimens with atypical or non-prototypic crack s morphology. Criterion 2a applies to specimens with atypical ligament morphology while 1 Criterion 2b applies to severe degradation significantly exceeding the EPRI database. The specific criteria for deleting outliers based on morphology considerations are given in Table 5 2. Table 5 2 also includes the indications excluded from the correlations based on Criterion 2b. No 3/4" indications were removed from the database based on Criterion 2a. Specimen 598-1 is excluded by Criterion 2b. His data point's voltage is more than 40 volts higher than the next largest specimen. There is insufficient data at the high voltage (64.9 volts) to assess the protypicality of the specimen or applicability to the database. This singular point may unduly influence the correlations without comparable voltage data to define the appropriate trend in the data at these high voltages. Based on destructive examination results providing identification of remaining uncorroded ligaments, the criteria of Table 5-2 can be unambiguously applied by an independent observer and thus satisfies the NRC guidance for removal of data outliers. Criterion 3 for outlier removal applies to specimens with abnormal leakage behavior due to a suspected test problem. In the performance ofleak tests, the crack can become plugged by deposits resulting in abnormally low leak rates or a measurement error could occur. For these cases, the cause for the measurement error is not as apparent as for Category I and the test results must be evaluated for apparent errors. It is not appropriate to include the spread in leak rates resulting from plugging of cracks in leak tests in the leak rate correlation and each leak rate measurement should be evaluated against the criteria of this section before inc the data in the database. Table 5-3 dermes Criterion 3 provides for either SLB leak rates insignificantly greater than normal operating leak rates or for leak rates much lower than expected for the throughwall crack length found by destructive examination as a basis for ' excluding data from the correlations. Also included in Table 5-3 are the 3/4" tubing specimens excluded from the database by this criterion and the basis for exclusion. Criterion 3 applies to extreme cases oflow leak rate outliers, such as more than a factor of 50 lower than predicted by verified analytical models. In addition, the factor of 50 criterion applies only to specimens which have no remaining uncorroded ligaments within the throughwall length of the crack. ne principal effects causing lower than expected variation
- in leak rates are remaining ligaments in the crack face, tortuosity (oblique steps in the crack surface irregularities) and presence of deposits. These effects tend to lower leakage for modest throughwall crack lengths. All three effects become smaller as crack length increases and crack opening increases. Longer throughwall cracks tend to have lost the ligaments by corrosion; the wider crack openings reduce the influence of surface irregularities and reduce
' the potential for deposits plugging the crack. From the database, "long" cracks appear to be about > 0.3" throughwall as above this length, the variability from predicted leak rates as a , function of length appears to be smaller (see Figure 5-1). For 0.3" throughwall cracks, the t l 1 1 5-2 l i
I crack width is about I mil at 2560 psid and increases to about 10 mils for a 0.5" long crack. Thus, crack lengths < 0.3" are more susceptable to plugging from deposits. From Figure 5-1, it is seen that model boiler specimens 598-3 and 604-2 have very low leak rates for their respective throughwall crack lengths. The remaining data are reasonably ) clustered with trends similar to that expected as shown for the CRACKFLO analyses in Figure 5-1. There is no indication through spread in the data that other specimens are significantly influenced by probable deposits in the crack face. Criterion 3 has been applied to specimen 598-3 to eliminate this indication from the leak rate correlation, as this specimen is more than a factor of 100 lower than the mean of the other data at about the 0.27" crack length of this specimen. Criterion 3 has not been rpplied to specimen 604-2, as this specimen is not clearly a factor of 50 less than the mean of the data, although the leak rate is apparently affected by deposits. Criterion 3 can be unambiguously applied by an independent observer to all measured leak rates given the results from leak rate measurements and/or destructive examinations and thus satisfies the NRC guidance for removal of outliers. This criterion is applied only to low leak rate measurements. For conservatism, high leak rate measurements are not considered for removal from the database. Based on Criteria 1 to 3 as described in Tables 5-1 to 5 3, the EPRI database of Reference 5-1 was reviewed for identification of data outliers to be removed from the database. Tables 5-4 to 5-6 summarize the data points removed from the database applied to the burst, leak rate and probability of leak correlations, respectively. Data were removed from the EPRI database in Reference 5-1 based on the same technical considerations, although less formal, as the criteria of Tables 5-1 to 5-3. However, the updated criteria lead to no changes from Reference 5-1. Plant S pulled tube R28C41 was deleted from the database of Reference 5-1 and would also be deleted by the more explicit criteria of this section. However, special considerations have been applied to this indication as described below. Special Consideration for Plant S Pulled Tube R28CH Plant S pulled tube R28C41 had leak rates exceeding the initial hot cell leak rate facility capacity at pressure differentials near SLB conditions. Test results are given in Table 5-7. Mea:ured leak rates of 43.4 and 95.11/hr at 2335 and 2650 psid, respectively, exceeded facility capacity and are not valid measurements. At 1500 pJd, a measured leak rate of 12.31/hr was within the facility capability (- 251/hr) and repreents a valid measurement. The facility capacity was increased and attempts to reach 2650 psid for a valid leak rate measurement (i.e., without hysteresis effects) were not successful as the leakage exceeded the 5-3
new facility capacity. At the first 2650 psi unsuccessful leak test, the cracks were plastically deformed such that succeeding tests below 2650 psi are not directly applicable due to the crack epening or hysteresis effect. As a consequence of not having an acceptable SLB leak rate measurement, this data point was not included in the EPRI leak rate database of Ref. 5-1. This indication is given special consideration, per NRC request, because of the crack morphology for this indication. He crack face had a 5% ID ligament about 0.31" long separating throughwall cracks in an overall, near throughwall crack length of 0.67" and a total crack length of 0.80". Destructive examination results for the crack length versus depth are given in Table 5-8. The uncorroded ligaments where the crack depth is 95% (Ligaments 1 and 2) include the widest (0.013") ligament and tend to reinforce the remaining 5% wall 1 thickness against tearing. Based on the increase in voltage after the tube pull, it is known that some ligaments were torn as a result of the tube pull. The initial leak rate was measured at 1500 psid. A pressurization to 2650 psi followed, but leak rates were too high to be measured in that facility. Leak rate tests performed in a facility with larger flow capacity can be used to estimate the effective through wall crack length and the leak rate at steam line break conditions. The method applied herein was developed by Paul Hemalsteen of Laborelec. He general methodology is based on the fact that the initial pressurization to 2650 results in a crack opening that has a significant plastic opening component. Subsequent ( measured leak rates, performed at lower pressure differentials, are affected by the plastic deformation which resulted from the pressurization to 2650 psid. The evaluations described below are based on crack opening areas calculated by the CRACKFLO Code. SLB leak rates calculated for R28C41 by CRACKFLO are in very good agreement with results obtained by Hernalsteen using the LABOLEAK Code. Differences in crack openings calculated by the two codes are small. l i The process used for the evaluation of the test results on the pulled tube included the following steps. These steps are summarized in Table 5-9 and use the test results from ! Table 5-7. For each step, the plastic and elastic crack opening widths are presented in Table 5-9 along with the crack lengths and leak rate. I
- 1. Figure 5-2 shows CRACKFLO leak rates at the conditions of Test 1. Based on the measured leak rate for this test,12.31/hr, a crack length of 0.38 inches is inferred. This length is greater than the 0.26 inch length of 100% depth (Table 5-8) determined assuming that ligaments 3 and 4 were tom during the tube pull. Thus, tearing of ligaments with modest throughwall crack extension was probable from the tube pulling operations.
- 2. The pressurization to 2650 psid (Test 3) is assumed to have introduced an irreversible minimum plastic opening in the existing crar.k. Using CRACKFLO, the plastic opening 5-4
area was calculated as a function of crack length. These results are presented in Figure 5 3, along with a curve fit < > the calculations. The curve fit was used to develop a modified version of CRACKFI's which maintains the minimum plastic opening resulting from the pressurintion to 2650 psid and combines it with an additional elastic opening due to the pressure differential of subsequent tests.
- 3. Using the modified CRACKFLO code with plastic crack opening at 2650 psid, the leak rate as a function of crack length was determined for the conditions of Test 4, Table 5-7. De results are presented in Figure 5-4. The figure shows that a crack length of 0.42 inch is inferred from the measured leak rate of 79.81/hr. Some additional tearing of the ligaments and throughwall crack extension from the 2650 psid pressurintion is suggested by the throughwall crack length increase from 0.38 to 0,42
[ inch between Tests 1 to 3 and Test 4.
- 4. The modified code, a 0.42 inch crack length and the conditions for Test 6 give a leak rate of 1141/hr at 1615 psid. This is substantially less than the 4481/hr measured for this test, suggesting significant tearing of the crack has occurred from thermal cycling and pressurintion between Tests 4 and 6.
- 5. Destructive examination of the tube after a tube burst test indicated a crack length up to 0.67 inches was possible. Using this crack length, a leak rate of 3751/hr is obtained for the conditions of Test 6. This value is reasonably close to the measured leak rate of 4481/hr. For this calculation CRACKFLO was used since the plastic opening area,' ,
2.0x10 3 inch, was greater than the 1.5x10' inch calculated to be present after the pressurintion to 2650 psid. Thus it is expected that complete tearing of all ligaments and the 5% wall thickness occurred between Tests 4 and 6.
- 6. 'Using the desired steam line break conditions (2560 psid and 616'F primary temperature) for the EPRI database, the as-pulled crack length of 0.38 inch (Step 1) is expected to have torn to 0.42 inch and a leak rate of 1111/hr is calculated.
The estimated leak rate for Plant S tube R28C41 at SLB conditions (2560 psid) is therefore 111 1/hr. This result is reasonably consistent with Plant S tube R33C20, which was measured in the large capacity facility. Tube R33C20 had a throughwall corrosion length of 0.33", j i compared to the 0.26" continuous length for R28C41. Both indications likely had ligament tearing and crack extension from tube pulling and pressurization to 2560 psid. The measured leak rate for R33C20 at 2560 psid was 1371/hr, compared to the estimate of 1111/hr for R28C41. Based on similar analyses using a few runs with the LABOLEAK code and analytical ratios of crack areas between 2650 and 1200 psid, Paul Hernalsteen of Laborelee estimated a 5-5 l
, ,v.-
r ,+cy- ,-,c .,n.-~.
R28C41 throughwall crack length of 0.475 inch at 2650 psid and predicted a leak rate of 1231/hr at 2560 psid. This result is in very good agreement with the CRACKFLO estimate
' of 1111/hr.
To bound the CRACKFLO and LABOLEAK analyses, a SLB leak rate of 1251/hr at 2560 psid is assigned to R28C41 for the EPRI database. 5.2 Database for ARC Correlations No new data for 3/4 inch diameter tubing has been obtained since the preparation of { j l Reference 5-1. The data of Reference 5-1 are updated for the present application based on the outlier evaluation of Section 5.1 above. Table 5-10 summarizes the data having burst j pressure and leak rate tests. Table 5-11 summarizes the data for use in the probability ofleak correlation. 5.3 NDE Uncertainties l For IPC applications, NDE uncertainties are required to support projections of EOC voltage i distributions, SLB leak rates and SLB tube burst probabilities as discussed in Section 8.0. The database supporting NDE uncertainties is described in Reference 5-1, and NDE uncertainties for IPC/APC applications are given in the EPRI repair criteria report (Reference : 5-2). From Reference 5-2, the NDE uncertainties are comprised of uncertainties due to the data acquisition technique, which is based on use of the probe wear standard, and due to - analyst interpretation, which is sometimes called the analyst variability uncertainty. l The data acquisition (probe wear) uncertainty has a standard deviation of 7.0% about a mean of zero and has a cutoff at 15%, with implementation of the probe wear standard requiring probe replacement at 15% differences between new and wom probes. ASME standards cross-calibrated against the reference laboratory standard and the probe wear standard were implemented in the Braidwood l EOC-4 inspection. l The analyst interpretation (analyst variability) uncertainty has a standard deviation of 10.3% about a mean of zero. Typically, this uncertainty has a cutoff at 20% based on requiring resolution of analyst voltage calls differing by more than 20%. However, as of the February 8,1994 meeting, the NRC has not accepted the 20% cutoff on the analyst interpretation uncertainty. Pending a further resolution of this issue with the NRC, the analyst interpretation uncertainty was applied for Braidwood-l without a cutoff. For EOC voltage projections, separate distributions are applied for probe wear with a cutoff at 15% and the analyst interpretation with no cutoff. 5-6 i
I 4 5.4 References
- 51. " Steam Generator Tubing Outside Diameter Stress Corrosion Cracking at Tube Suppon Plates - Database for Alternate Repair Criteria, Volurne 2: 3/4 Inch Diameter Tubing",
NP-7480 L, Volume 2, October 1993. 5-2. "PWR Steam Generator Tube Repair Limits - Technical Support Document for Outside Diameter Stress Corrosion Cracking at Tube Support Plates", TR 100407, Revision 1, Draft Report, August 1993. 5-7 l l
Table 5-1 Criteria la to le for Excluding Data from Correlations Criterion la: Unacceptable Bobbin Voltage Measurement Excludes specimen from all applications
' Examples: Welded specimen extension influences voltage measurement, specimen damage prior to test completion Criterion Ib: Unacceptable Burst Test Excludes specimen only from burst correlation .
Examples: Incomplete burst test (e g. leak but not burst), test malfunction, burst inside TSP Criterion Ic: Unacceptable Leak Test Excludes specimen from leak rate correlation and requires prob. ofleak evaluation Examples: Leak rate exceeded facility capacity, test malfunction Criterion Id: Unacceptable Leak Data Due to Tube Pull Damage Excludes specimen from leak rate correlation and requires prob. ofleak evaluation
. Requires analyses to demonstrate uncorroded ligament would not have torn at accident conditions Example ID ligament tom during tube pull as demonstrated by post pull voltage and higher than expected leak rates at or below normal operating conditions. Structural analysis shows uncorroded ligament would not be expected to tear at accident concittoas.
Criterion le: Unacceptable Data for Estimating Probability of Leak Prob. of leak (yes/no) cannot be confidently estimated from destructive exam crack morphology and leak test not performed Examples: Short TW corrosion cracks such as < 0.1" which normally do not leak at SLB conditions No destructive exam data available for estimating prob. ofleak 5-8
Table 5-2 Criteria 2a and 2b for Excluding Data from Correlations Criterion 2a: Atypical ljgament Morphology
- Cracks having s 2 uncorroded ligaments in shallow cracks < 60% maximum depth should be excluded from the database as having bobbin voltages significantly higher than the dominant database which shows more uncorroded ligaments in shallow cracks Results in aypical voltages and associated specimens are excluded from all corr.
No 3/4" specim' ens are excluded from the database due to this criterion Criterion 2b: Severe Degradation
. Exclude data points having bobbin voltages > 20 volts larger than next data point from correlations, as singular data points at the tail of distributions can have undue influence on regression correlation. In this case, there is insufficient data at comparable voltages to assess the prototypicality of the. crack morphology and applicability to the database.
Results in atypica! voltages and associated specimens are excluded from all corr.
- Excludes 3/4" model boiler specimen 598-1 (64.9 volts) which is > 40 volts larger than the next highest voltage point (22 volts) 5-9
Table 5-3 Criterion 3 for Excluding Data from Correlations Criterion 3: Suspected Test Error Data are excluded from only the SLB leak rate versus voltage correlation if either or both of the following criteria are satisfied
. Leak rates at SLB pressure differentials should be at least 10% higher than that measured at normal operating pressure differentials for free span leak tests
- No 3/4" specimens are excluded from the database for this criterion For throughwall cracks with no ligaments, the measured leak rate should be within a factor ofless than about 50 of the mean measured leak rate at the associated throughwall crack length For:3/4" tubing, this criterion excludes model boiler specimen 598-3 (0.27" TW,0.02 1/hr leak rate). The measured leak rate for this specimen with no remaining ligamen is more length than a factor of 100 less than the mean measured leak rate for The most limiting specimen compared to this criteria retained in the database is .
model boiler specimen 604-2 (0.19"TW,0.051/hr), for which the mean measured leak rate is about 0.2 to 0.31/hr 5 - 10
f l Table 5-4 Basis for Excluding Data from the 3/4" Burst Correlation Basis for Excluding Indications EPRI* Tube TSP from Tube Burst Correlation Exclusion , Category . Tort Section Plant E-4 R19C35 2 Burst inside TSP. Yields much higher burst Ib 4.4 pressure than free span burst tests of ARC data base. R45C54 2 Burst inside TSP lb R47C66 2 Burst inside TSP lb Plant S ' R28C41 1 Incomplete burst test - burst opening length Ib 2.5,4.5 less than macrocrack length (no tearing) Plant R 1 R7C71 3 Test recorder malfunction Ib 2.2,4.3 RSCll2 2,3 Incomplete burst test Ib R10C6 2,3 Incomplete burst test Ib R10C69 2,3 Incomplete burst test Ib R20C46 2,3 Incomplete burst test Ib R7C47 3 Incomplete burst test Ib Model Boiler Specimens 591-3 Unacceptable specimen preparation due to la 5.6 bobbin voltage influenced by cracks in model boiler Teflon spacer below TSP as well as cracking within TSP. This results in two bands of cracks. 598-1 Bobbm voltage (64.93 volts) and three large 2b 5.6 throughwall indications not prototypic of field indications and single data point >20 volts unduly influences burst correlation 593-4,595-4, These bobbin NDD specimens all burst at a Ib 596 1, 597-4, welded joint made to extend the specimen 603-4, 604-4 length for burst testing and are not valid tests. ; These data have been excluded fro = the 3/4 l inch data base discussed in the EPRI report. { EPRI Report NP-7480-L, Vol. 2 (Reference 5-1) l 5 - 11
Table 5-5 Basis for Excluding Data from the 3/4" Leak Rate Correlation Basis for Eacluding Indications Tube TSP Exclusion
, from Leak Rate Correlation Report Category 3
Plant R-1 RSCI12 3 Max. corrosion depth of 97% Remaining TW Id 2.2,4.3 ligament tom during tube pull as indicated by post-pull voltage and leak at 500 psi. Analyses indicate ligament would not have tom at accident conditions. Plant B-1 R4C61 5 No leakage identifiable during pressure test le 2.2,4.3 above SLB conditions. Test accuracy not sufficient to conclude no leakage. - Model Boiler Specimens 591-3 Unacceptable specimen preparation due to la 5.6 bobbin voltage influenced by cracks in model boiler Teflon spacer below TSP as well as cracking within TSP. This results in two bands of cracks. 598-1 Bobbin voltage (64.93 volts) and three large 2b 5.6 throughwall indications not prototypic of field indications and single data point >20 volts unduly influences correlation. 598-3 Specimen had no operating leakage and 0.02 3 1/hr at SLB conditions. Crack was found to be 0.27" TW with no ligaments for which leak rate of 5 to 201/hr would be expected, based on the mean of the measured data. It is concluded that crack became plugged by deposits or a measurement error was made.
- EPRI Report NP-7480 L, Vol. 2 (Reference 5-1) 5 - 12
i l l i Table 5-6 Basis for Excluding Data from the 3/4" Prob. of Leak Correlation Basis for Excluding Indications . EPRI* Tube TSP from Prob. of Leak Correlation Report Category 3 Plant R-1 R7C47 2 No destructive exam data or burst test to le 4.3 estimate probability of leakage. R5Cll2 3 Max. corrosion depth of 97%. Remaining TW id 2.2,4.3 ligament torn during tube pull as indicated by post pull voltage and leak at 500 psi. Analyses indicate ligament would not have torn at accident conditions. Plant B-1 R4C61 5 No leakage idenafiable during pressure test le 2.2, 4.3 above SLB conditions. Test accuracy not sufficient to conclude no leakage. Model Boiler Specimens 591-3 Unacceptable specimen preparation due to la 5.6 bobbin voltage influenced by cracks in model boiler Teflon spacer below TSP as well as cracking within TSP. This results in two bands of cracks. 598-1 Bobbin voltage (64.93 volts) and three large 2b 5.6 throughwall indications not prototypic of field indications and single data point >20 volts unduly influences correlation
- EPRI Report NP-7480-L, Vol. 2 (Reference 51) 5 - 13 l
l I J
l Table 5-7 l Plant S R28C41 Leak Rate Tests Primary Conditions Differential Secondary Istl Ternoerature Pressure Pressure Pressure LnalLBas (*F) (psia) (psid) (psia) (1/hr) Ininalsenes 1 612 2000 1500 500 12.3 2 2650 2335 315 > 43
- 3 2850 2650 200 > 96
- Second Senes 4 550 1930 1200 730 78.9 5 560 2375 1535 840 321 6 580 2550 1615 935 448 7 550 2500 , 1375 1125 4 78 **
Leak rate exceeded facility capacity.
** Note increase in leak rate at low pressure differential which indiates additional deformation of crack opening.
1 e 5 - 14
R , Table 5-8 Plant S SG Tube Macrocrack Profile for R28C41 Length vs. Depth Ductile Ligament Tube. Locati911 (inch /% throunhwall) Location R28C41, FDB 0.00 / 0 0.07 / 100 O.13 / 100 0.19 / 95
- Ligament 1,0.013" wide 0.25 / 95 0.32 / 95
- Ligament 2,0.004" wide 0.38 / 95 0.44 / 100 0.52 / 100
- Ligament 3,0.007" wide 0.60 / 100 2
0.70 / 100
- Ligament 4,0.008" wide 0.75 / 70 0.80 / 0 i
5 15
Table 5-9 Evaluation Summary, R28C41 Tube leak Rate Tests Crack Opening Crack Case Plastic Elasts Length Leak Rats ( x 10 5 in) (in.) (1/hr) Before Pressurizing to 2650 psi AP S.lfA.1 Crack Length inferred from 0.12 0.65 0.38 12.3* measured leak rate at AP=150 psi After Pressurizing to 2650 psi AP SitP_1 Crack Length inferred from 1.5 0.65 0.42 79.8* measured leak rate a: AP=1200 psi and $50 'F SitD.! Leak rate for a crack 1.5 0.86 length of 0.42" at 0.42 114 AP=1615 psi & 580 7 Measured leak rate 448* SitP_1 Crack Length = 0.67 m. se 2.0 2.6 0.67 3 75 AP=1615 psi & 5807 assumed Calculated Leak Rate at 2560 psi AP (Step 3 len'gth of 0.42") l SitP_6 l Leak rate for a crack length of 1.4 1A 0.42 111 0.42" at AP=2560 ps: & 616 7 i
- Measured leak rates see TaEe 5 7 l
5 - 16
I a Table 5-10 . Burst Pressure and Leak Rate Data Base for 3/4 Inch Tubing Adjusted Correlation (4) Row / Col or Destructive Exam St.B Leak (2) Burst (3) Application Bobbin Bobbin RPC Plant Specimen No. Max. Rate (1/hr) Pressure TSP Volts Depth Leak Volts Depth length (1) 2560 psid I (ksil Rate . Burst -l
- t 9
R O L e ~ + --e ,- -e - w _m _w..m
TeMe 5-10 (continued) Burst Pressure and Leak Rate Data Bose for 3/4 Inch Tubing Adjusted Row / Col or Bobbin Destructive Exam Correlation (4) Plant Specimen No. Bobbin - RPC SLB Leak (2) Burst (3) Application TSP Max. Volts Depth Volts Rate Ultw) Pressure Leek Depth Length (1) 2560 psid (ksii Rete Burst e i W 6 '
i Table 5-10 (continued) Burst Pressure and Leak Rate Data Base for 3/4 inch Tubing Adjusted Correlation (4) Row / Col or Destructive Exam SLB Leak (2) Bobbin Bobbin HPC Burst (3) Application Plant Specimen No. Max. - Rete ll/tw) TSP Volts Depth Pressure Leek Volts Depth Length (1) 2560 psid
' (ksil ' Rate Burst e
M 4
Tcble 5-11: Database for Probability of r ak for3/4" Diameter Tubes Plant or Model Bobbia Boiler Sample Amplitude P biU W Plant or Model Bobbin buipf bak Boiltf 58mP lc Amplitude
- Number (V) Number g
(V)
~ c l
t
' nam M
tMSUuOAT R $) L eon
- eon ack 5Z W *4'ou
Figure 5-1 Comparison of 3/4" Leak Test Data with CRACKFLO Predictions ! _ a,e i 4 m e l l
l i 1 Figure 5-2 : As Pulled Tube Leak Rate 1500 psi Pressure Drop y e 0 W G m
7_ ' ' 4 Figure 5-3 Plastic Correction Area _ 2650 psi Pressure Difference _y i
i l Figure 5-4 1 Modified Code Leak Rate
- 1200 psi Pressure Drop
_ R,c 0 4 P I O 9 l
6.0 BURST AND SLB LSAK RATE CORRELATIONS 6.1 EPRI ARC Correlations As part of the development of alternate repair criteria (ARC), correlations have been developed for tubes containing ODSCC indications at TSP locations between the bobbin amplitude, expressed in volts, of those indications and the free-span burst pressure, the probability ofleak, and the free-span leak rate for indications that leak, References 6.1 and 6.2. The database used for the development of the correlations is presented and discussed in Reference 6.2. Guidelines for the identification and exclusion 'of inappropriate data, termed outlien, are provided in Reference 6.3. In addition to the aforemersned, an empirical correlation curve for the burst pressure as a function of crack length has been developed for tubes with free-span, through-wall, axial cracks. In 1993, the NRC issued draft NUREG-1477, Reference 6.4, for public comment. The draft NUREG delineated a set of guidelines for criteria to be met for the application ofInterim Plugging Criteria (IPC) for ODSCC indications. The criteria guidelines permitted the use of, with adequate justification, a burst pressure to bobbin amplitude correla-tion and a probability ofleak to bobbin amplitude correlation. The criteria guidelines did not permit the use of a leak rate to bobbin amplitude correlation for the estimation of end of cycle (EOC) total leak rates. In essence, References 6.1 and 6.2.provided comments on the Reference 6.4 guidelines. Reference 6.5 provided an NRC response and position relative to resolving the differences between References 6.1 & 6.2 and Reference 6.4, along with responses to other public comments. Of significance to this report,is that Reference 6.5 indicated that a correlation between leak rate and bobbin amplitude could be employed if the correlation could be sta:istically justified at a 95% confidence lent, and provided direction for the development of guidelines, e.g., Reference 6.3, that could then be employed for the identification and exclusion of outlying experimental data. Subsequent discussions with NRC personnel have revealed potential issues associated with the man:er in which the leak rate to bobbin amplitude correlation is used, thus, the potential leak rate during a postulated steam line break (SLB) is herein estimated by alternate Monte Carlo and de:erministic methods to demonstrate that either method yields acceptable results. The purpose of this section is to provide information and justifica: ion for all of the correlations developed in support of the application of an IPC for the Braidwood 1 nuclear power plant. Information is first presented relative to the correlation of burst pressure to bobbin amplitude and to through-wall cra:k length, followed by a discussion of the correlation between the probability ofleak and th- bobbin amphtude, and lastly a discuss:on of the correlation of leak rate to bobbin amplitude The use of each of the correlations is also documented. 6-1
l 6.2 Burst Pressure versus. Bobbin Voltage Correlation 1 The bobbin coil voltage amplitude and burst pressure data presented in the EPRI database report for 3/4" tubes, Reference 6.2, were used to estimate the degree of correlation between the burst pressure and bobbin voltage amplitude. The details of performing the correlation analysis, and subsequent regression analysis to estimate the parameters of a log-linear relation- i ship between the burst pressure and the bobbin amplitude, are provided in the EPRI database report. He evaluations examined the scale factors for the coordinate system to be employed, the detection and treatment of outliers, the order of the regression equation, the potential for measurement errors in the variables, and the evaluation of the residuals following the develop-ment of a relation by least squares regression analysis. The results of the analyses indicated that an optimum linear, first order relation could be obtained from the regression of the burst pressure on the common logarithm (base 10) of the bobbin amplitude voltage. A linear, first order equation relating the burst pressure to the logarithm of the bobbin amplitude was developed. Examination of the residuals from the regression analysis indicated that they are normally distributed, thus verifying the assumption of normality inherent in the use of least squares regression. The regression curve (line)is given by P,' = a, +a, log (V,) ! (6.1) l
= 7.822 -3.077 log (V,),
)
where the burst pressure is measured in ksi an'd the bobbin amplitude is in volts. The ind determinanon for the regression was 80.7%, thus the correlation coefficient is 0.90, which is significant at a >99.999% level. This means that the p-value for the slope of the line is ,
< 0.001%
ne estimated standard deviation of the residuals, i.e., the error of the estimate, e s, of the burs: pressure was 0.95 ksi. A summary of the results from the regression analysis is provided m Table 6-1. The data base and the regression curve are illustrated on Figure 61. Using the regression relationshg. a lower 95% prediction bound for the burst pressure as a function of bobbin amplitude was developed. These values were further reduced to account for the lower 95%/95% tolerance bound for the Westinghouse data base of tubing material properties at 650*F. Bo:h of these are also depicted on Figure 6-1. Using this reduced lower prediction bound, the bobbin amplitude corresponding to afree-span burst pressure of 3657 psi was found ' to b; 4.54 V. The value of 3657 psi results from considering a SLB differential pressure of 25o0 psi dmded by 0.7 in accord with the guidelines of RG 1.121, Reference 6.6. 6-2
6.3 Burst Pressure versus Through-Wall Crack Length Correlation For a tube with a mean radius of r., and a thickness t, the normalized burst pressure as a function of the actual burst pressure, P,, is given by P,r" P ,,= (Sr + 8v )' . (6.2) Thus, P ,is the ratio of the maximum Tresca stress intensity, taking the average compressive stress in the tube to be P,/2, to twice the fiow strength of the material. The normalizing parameter for crack length, a, is given by a
}" '
(6.3)
/ r,i a form which arises in the theoretical solu::ns. The burst pressure as a funcuan of axial crack length for a specific tube size is then easily obtained from the non dimensionahzed relation-ship.
Examination of the normalized burst press'.: e data indicated that a variety of f=>ctional forms would result in similar fit characteristics. .e exponential function, i.e., x P ,, = b, + b, e I, (6 4) was bnally selected based on the combinan:c of maximizing the goodness of 5:, and minim ing the number of coefficients in the funct>:c Equation (6.4) was also found :: be advanta. geous in that it can easily be inverted to yield 1 as a function of P.,,. For the d.ata analyzed. the coefficients of equation (6.4) were found to be x P,,, = 0.0f '. 5 + 0.534 e ' un (6.5) The index of determination for the fit was si 3%, with a standard error of the es-imate of 0.015. The F distribution statistic for the repession, the ratio of the mean squre due to the regression to the mean square due to the rer.iuals, was 4625. Thus, the fit of de equation to the data is excellent. Note that this does n:: mean that equation (6.4)is the true form of a 6-3
functional relationship between the two variables, only that it provides an exce of the relationship. Equation (6.4) was then rearranged to yield the inverse relation r , A = - 3.611 in P**' - 0.0615
, (6'6)
, 0.534 s for the normalized crack length as a function of normalized burst pressure.
In order to present the results in a form directly applicable to the Braidwood I normalized relationships were converted for 0.750" diameter by 0.043" thick t flow stress of 71.6 ksi, the average of the Westinghouse database. The converted the regression curve, and the regression curve adjusted for lower 95%/95% tole material properties are shown on Figure 6-2. Using the regression results, the probability of burst during SLB was estimat crack length. The mean estimate of the burst pressure is given by the regress P, = P,,, t S, +y S ) . (6.7) An unbiased estimate of the variance of P, which atcounts forthe
,, about the variation in regression curve and the variation fin Su +S can be calculated as
( , V(P,) = P,',,V(Sf ) + 1f
- V(P,,,) - C 'P,,,) V(S ) , (6.8)
, =, f where V is used to represent an unbiased estimate of the variance of the respec parentheses,f and S , the flow stress for Alloy 600 material, is one half of the and ultimate strengths. Taking the standard deviation of the burst pressure as of the estimated variance allows for the estimation of the probability of burst u t distribution. Specifically, the difference between the estimated burst given pressure for a crack length, a, and the SLB pressure is divided by the estimated standard deviatio burst pressure to obtain a t deviate. The probability of occurrence of the value estimate of the probability of burst for that crack length during a SLB. The n of freedom used in estimating the probability of occurrence of a t deviate greater conservatively taken as the lesser of the number of degrees of ffreedom An of P ., or S alternate estimate of the probability of burst can be obtained by simulating P ., and f
independently, in this case, a large number off values of P,,, and S are indepe 6-4
- calculated using randomly generated independent t variates and the respective estimated standard deviations of Pu, about the regression curve and Sf about the mean of the database.
These are then combined using equation (6.7) to obtain a burst pressure for a single simulation. The number of occurrences of the calculated burst pressure being less than the SLB pressure is then an estimate of the probability of burst. Based on the specific simulation results, an upper bound for the estimate of the probability of burst may then be made using non parametric methods. The results of the calculational and the Monte Carlo simulation determinations are depicted on Figure 6-3 Also shown are the 99% upper confidence bounds for the Monte Carlo estimated values. The calculational procedure is seen to lead to a ccnservative estimate of the probability of burst for a given crack length. An examination of the distribution of the burst pressures from the Monte Carlo simulations reveals that is skewed right. Thus, the tail of the distribution is shorter for the lower burst pressures, hence the lower probabilities of burst. 6.4 NRC Draft NUREG 1477 SLB Leak Rate POD and Uncertainty Methodology The NRC methodology of draft NUREG 1477 obtains the number of ind: cations that are to be considered as being returned to service, N, as: l N, N = N, + N,, - N, = N, + 1 - POD y# _ g' , , _ y' , (6.9) POD POD where, N, = number of detected bobbin indications N, = number of repaired indications N,,, = number of indications not detected by the bobbin inspe:non ' POD = probability of detection (0.6 for NRC methodology). The above adjustments for POD have been incorporated in the BOC and EOC voltage distribunons so that no further adjustments are required for the leakage cQulation. Secton 3.3 of draft NUREG 1477 states that the total leak rate, T, should be determined as: T=pP+2 cP+pP-2 2 (N, P,2 ) ' , (6.10) where, p = mean of the leak rate data independent of voltage c = standard denation of the leak rate data independent of witage P, = probability that a tube leaks for the " voltage bin N, = number of indications (after POD adjustment) in the i* voltage bin P = I(N,P,) = expected number of indicanons that leak sum =ed over all vchage bins 2 = standard normal distribution deviate (establishes level of confidence on leakage). 6-5
. . . . - . . . ._ . = _ - . - - . .
For the total leakage, the first term of the above equation represents a mean expected leak rate while the square root term is an effective standard deviation for the total leakage based on the variance of the product of the probability ofleak and the predicted leak rate. Draft NUREG. 1477 recommends that 2 be applied as 2, which corresponds to a level of confidence of 98%, while Reference 6.5 indicates that 2 may be taken as 1.645, corresponding to a confidence level of 95%. 6.5 Probability of Leakage Correlations Historically, the probability ofleakage has been evaluated by segregating the model boiler and field data into two categories, i.e., specimens that would not leak during a SLB and those that would leak during a SLB. These data were analyzed to fit a sigmoid type equation to establish an algebraic relationship between the bobbin amplitude and the probability ofleak. The specific algebraic form used to date has been the logistic function with the common logarithm of the bobbin amplitude employed as the regressor variable, i.e., letting P be the probab leak, and considering a logarithmic scale for volts, V, the logistic expression is: I P(leak l V) = 1 + e 'I M . (6.11) This is then rearranged as: In
# =
, + p, log ( V), (6.12)
,1-P, to permit an iterative, linear, least squares regression to be performed to fm' d the maximum >
likelihood estimators, b, and b,, of the coefficients, p, and p,. Reviews of those evaluations, e.g., NUREG-1477, have resulted in the NRC requesting th alternate sigmoid function forms be investigated, and that the evaluations also consider the potential dependence to be on the bobbin amplitude instead of the logarithm of the bobbin amplitude. NUREG 1477 specifically mentions that the cumulative normal, or Gaussian, distribution function and the Cauchy distribution function be investigated. Discussions with NRC persormel led to the stipulation that these functions be analyzed and used in predic the end-of cycle leak rate for the Braidwood I plant steam generator tube indications. Reference 6.7 has acknowledged that any non-conservatism associated with the exclusive use of the log logistic function would be expected to be small in comparison to the conservatism inherent in the methodology used to estimate the radiological consequences of leakage ~ associated with a postulated SLB. On this basis, the evaluation and results presented herein for attemative function forms is considered to be for information only. ' 6-6
, se i_ _, nA-m k A- i - J =A5- E A 4+u -,i e--4 hii GnhJ s 15a- - a1 2 4 g 4 --_r, 4J 4
The use of the logistic function for the analysis of dichotomous data si standard in many fields. The differential form assumes that the rate of change of the probability ofleak is proportional to the product of the probability ofleak and the probability of no leak. As noted, the function is sigmoidal in shape, and is similar to the cumulative normal function, and likewise similar to ' using a probit model (which is a normal function with the deviate axis shifted to avoid dealing with negative values). In principle, any distribution function that has a cumulative area of unity could be fit as the distribution function, a limitless number of possibilities. Trying to identify a latent, or physically based, distribution for the probability ofleak would be consid-ered to be unrealistic and unnecessary. For most purposes the logistic and normal functions will agree closely over the mid range of the data being fitted. The tails of the distributions do not agree as well, with the normal function approaching the limiting probabilities of 0 and 1 more rapidly than the logistic function. Thus, relative to the use of the normal distribution, the use of the logistic function is conservative. Given its wide acceptance in multiple fields it was judged that the logistic function would be suitable for use in determining a probability of leak as a function of voltage. In addition, consideration was given as to whether the bobbin amplitude or the logarithm of the bobbin amplitude should be used. Since the logistic, normal and Cauchy distribution functions are unbounded, the use of volts would result in a finite probability ofIcak from non degraded tubes, and would be zero only for V=-e. By contrast, the use of the logarithm of the voltage results in a probability ofleak for non-degraded tubes of zero. Clearly, the second situation is more realistic than the first, especially in light of the fact that a voltage threshold is a likely possibility. To comply with the NRC request, however, each distribution function was fitted to the data using the logarithm of the bobbin amplitude and the bobbin amplitude as the regressor. The three functions to be evaluated fall into a category of models referred to as Generalized LinearModels (GLMs). This simply means that the models can be transformed into a linear form, e.g., equation (6.12). The left side of equation (6.12) is referred to as the link function for the logistic model. For the normal or cumulative Gaussian distribution function, the model to be fitted is: 0, t,w) ,, I P(leak) =
- I e 7,d (6.13)
[27t . and the model to be fitted for the Cauchy distribution fun:: ion is: P(leak) = .I. + 1 tan]Q, -(log (P)]. (6.14) 2 n l 6-7
- 4 The link function for the Gaussian function is:
- 9 = @ ~'(P ) = p, + p, log (V), (6.15) h while the link function for the Cauchy function is
r q = tan x P ._3,- '
= p, + p, log (V) . (6.16)
,s 2,,
To fit the equation forms to the bobbin amplitude rather than log of the amplitude, Vis l substituted for log (V). Each equation was fitted to the data using an iterative least squares technique, which results in the maximum likelihood estimates of the parameters. The results of all of the regression analyses are summarized in Table 6-2. The' coefficients of 4 the equations are provided along with the elements of the variance covariance matrix for the coefficients. In addition, the deviance for each solution is also given. One accepted measure of the goodness of the solution or fit for GLMs is the deviance, given by, .I F P, in P' + (1 - P,)ln 1 - P' (6.17) D = 2 f..i , P(V,) , 1 -P(V,) ,, 1 l where P, is the probability associated with data pair / and P(V) is the calculated probabil from V,. - The deviance is used similar to the residual sum of squares in linear regression analysis and is equal to the error, or residual, sum of squares (SSE) for linear regression. For the probability of leak evaluation P, is either zero or one, so Equation (6.17) may be written D = -2 f.i . P,In[P(v,)] + (1 -P,)ln[1 -P(v,)]f. (6.18) . Since the deviance is similar to the SSE, lower values indicate a bener fit, i.e., the lower the
- residual sum of squares the more of the variation of the data is considered to be explained the regression equation. The smallest deviances,28.9, were obtained from the logistic and normal function fits. The deviances for the remaining four functions ranged from 32.5 to 33.8, about 12% to 17% higher than for the first two functions. For similar calculations performed
' using 7/8" tube data, the deviances obtained using either of the Cau:hy forms were about 15% to 20% higher than for the other four functions. These differences are not considered to be numerically significant in themselves relative to selecting the best form of a fitting function.
! 6-8 ~ _ _ _ . _ _ _ -
e The results of fitting each of the equations are depicted on Figures 6-4 and 6-5. A comparison of the results shown on Fipre 6-4 with those shown on Figure 6-5 indicates that the use of the logarithm of the volts results in a spreading of the functions with the probability of leak at, say,3 volts being higher for the logarithmic forms. In the very low voltage range, less than 1 volt, the probability of leak is lower for the logarithmic forms. This is because the tails must extend to -e. In general, the Cauchy cumulative distribution function has longer tails than either the logistic or normal functions. It also rises much more sharply in the middle of the data range. The regression results on Figure 6-2 illustrate the non realistic nature of the Cauchy fit for the non logarithmic form, in spite of its similar deviance value. Examination of the figures indicates that the Cauchy distribution is significantly less representative of the data in the regions where the no leak and leak test data overlap. A listing of probability ofleak results for selected volts is provided in Table 6 3. Up to a bobbin amplitude of 1 volt, predictions based on the log normal functon are less than predictions bas,ed on the log logistic function. For very high voltages the Cauchy distribution forms rise to a probability cf leak of one slower than the other distribution functions. Taken in conjunction with ti.e leak rate versus voltage correlation, the choice of a probability of leak function is relatively moot. The final total leak rate values tend to differ by only a few percent across the spectrum of POL functions 6.6 SLB Leak Rate Versus Voltage Correlation for 3/4" Tubes The bobbin coil and leakage data previously reported were used to de: ermine a correlation function between the SLB leak rate and the bobbin amplitude voltage Since the bobbin amplitude and the leak rate would be expected to be functions of the : rack morphology, it is to be expected that a correlation between these variables would exist. P evious plots of the data on linear and logarithmic scales indicated that a linear relationship be ween the logarithm of the leak rate and the logarithm of the bobbin amplitude would be an tepropriate choice for establishing a correlating function via least squares regression analysa Thus, the functional form of the correlation is log (G) = b3 + b, log (V), (6.19) I where G is the leak rate, V is the bobbin voltage, and b, and b, are es: mates ob:amed from the data of some coefficients, p, and p,. The final selection of the form :f the vanable scales, i.e., log log, was based on performing least squares regression analysu on each possible combination and examining the square of the correlation coefficient fe: each case The largest index of determination,58.2%, was found for the log (G) on log (P) reression. Tne second largest index, for G on V, was found to be on the order of 24%, clea5 mdican:; the appropriate choice of scales to be log log. ! 6-9
- l i
. , _ . _ _ - ~ . - _ _ , _ _ _ . _ . . _ . . .__ _ . _ _ _ . _ , .
A summary of the results of the regression analysis is provided in Table 6-4, and illustrated on Figure 6-6. The number of data points used for the above evaluations was 40 and the number of degrees of freedom (dof) 38. The obtained value of 2r of 58.2% is significant at a level of
>99.99999% based on an F distribution test of the ratio of the mean square of the regression to the mean square of the error. 'Ihis can also be interpreted as the probability that the log of the leak rate is correlated to the log of the bobbin amplitude. An altemate interpretation is that if the variables are really uncorrelated and the testing was repeated many times, an index of determination equal to or greater than that obtained from the analyzed data would be expected to occur randomly in only <0.000001% of those tests. The conclusion to be drawn from these results is that it is very likely that the variables are correlated.
At the February 8,1994, meeting between the NRC, EPRI, and NUMARC, information was presented by the NRC that the "use oflinear regression is acceptable if shown to be valid at a 5% level with [a] p value test." The p.value is the conditional probability of observing a computed statistic, e.g., the F distribution value reported above, as large or larger than the observed value, under the condition that there is no relationship. In this case, a small p value is evidence supporting the hypothesis that there is a correlation between log (G) and log (P). The p values for the estimated parameters of Equation (6.19) are also given in Table 6-4. For ' the slope of the regression equation, the conditional probability that the slope is zero is
<0.000001%
The conditional probability that the intercept is zero is 0.01%. The validity of the regression is judged by the p value associated with the slope. Since this is significantly less than the 5% value stipulated above the regression is concluded to be valid, and the use of linear regression is acceptable. . The expected, or arithmetic average (AA), leak rate, G, corresponding to a voltage level, V, was also determined from the above expressions. Since the regression was performed as log (G) on log (P) the regression line represents the mean oflog(G) as a function of bobbin amplitude. This is not the mean of G as a function of V. The residuals oflog(G) are expected to be normally distributed about the regression line. Thus, the median and mode of the log (G) residuals are also estimated by the regression line. However, G is then expected to be distributed about the regression line as a log normal distribution. The regression line still esumates the median of G, but the mode and mean are displaced. The corresponding adjust-ment to the normal distribution to obtain the AA of G for a log normal distribution is G -E(G lV) = 10 2 (6.20) for a given V, where c is the estimated variance oflog(G) about the regression line. The vanance of the expected leak rate about the regression mean is then obtained from Var (G) = G 2[e W - 1 ). (6.21) i 6 - 10 '
To complete the analysis for the leak rate, the expected leak rate as a function of log (V) was , determined by multiplying the AA leak rate by the probability ofleak as a function of log (V). I l The results of this calculation are also depicted on Figure 6-6 for a steam line break differential l- pressure of 2560 psi. 6.6.1 Analysis of Regression Residuals { l As previously noted, the correlation coefficients obtained from the analyses indicate that the i log log regressions at the various SLB APs are significant at a level greater than 99.8%. L Additional verification of the appropnateness of the regression was obtained by analyzing the regression residuals, i.e., the actual variable value minus the predicted variable value from the regression equation. A plot of the log (Q) residuals as a function of the predicted log (G) was found to be nondescript, indicating no apparent correlation between the residuals and the l predicted values. A cumulative probtbility plot of the residuals on normal probability paper approximated a straight line, thus veniying the assumption inherent in the regression analysis that the residuals are normally distrib:ted. Given the results of the residuals scatter plots and the normal probability plots, it is consdered that the regression curve and statistics can be used for the prediction of leak rate as a fu- tion of bobbin amplitude, and for the establishment of statistical inference bounds. 6.7 SLB Leak Rate Analysis Method: logy The leak rate versus voltage correlatec can be simulated in conjunction with the EOC voltage distributions obtained by Monte Carle methods, or by applying the POL and leak rate correlations to the EOC voltage distn:ction obtained by Monte Carlo methods as applied for the draft NUREG methodology. Thu second approach is a hybrid that joins Monte Carlo and deterministic calculations. Parallel ariyses verified that the full Monte Carlo leak rats and the direct application of the correlatio.s to the EOC voltage distribution yield essentially the same results Thus, it is adequate to eply the correlations to the EOC voltage distributions. l The determination of the end of cycle ;eak rate estimate proceeds as follows. The beginning of cycle voltages are estimated using the =ethodology provided in draft NUREG-1477. The distribution of indications is binned it.11V increments. The number ofindications in each bin is divided by 0.6 to account for POD The resulting number of indications in each bin is reduced by the number of indications -sugged in each bin. The f' mal result is the beginning of cycle distribution used for the Monte Carlo simulations. The NDE uncertainty and growth rate distributions are then independently st pled to estimate an end of cycle distribution, also reported in bins of 0.lv increment. C-ven the EOC voltage distribution the calculational steps to obtain an estimate of the total leak ste are as follows: (1) For each voltage bin, the leu rate versus bobbin amplitude correlation is used to estimate an expected, or average, leak rate for indications in that bin. 6-11
4 (2) The probability ofleakage correlation is then used to estimate the mean probability ofleak for the indications in each bin. (3) The relationships derived in Appendix C of draft NUREG-1477 for the variance of the product of the probability ofleak with the leak rate and for the total leak rate are then used to estimate the expected total leakage and variance for the sum of the indications in each bin as a function of the correlation means and estimated varianc. es for the leak rate and probability ofleak. To account for the variances of the coefficients of the regression equation for the leak rate, the o used in equations (6.20) and (6.21) is that from the predictive distribution for the logarithm of the leak rate as a function of bobbin amplitude, i.e., for each voltage, V, an effective standard deviation of the regression error, o,, is calculated as 3 108( V,) -lo8( V) e, = o* 1 + _1 + y 2 (6.22) log (Vj ) -log ( V) s . where N is the number of data pairs in the regression analysis, and o, is an unbiased estimate of c. The expected total leak rate from all of the indications in all of the bins is T= "' 10 2
, , , ; , , -l o, + +, v r.)1
, (6.23) where N, is the number of bins, and n, is the number of indications in the bin with bobbin amplitude V,.
Thus, the expected total leakage for the entire distribution is obtained as the sum of the expected leak rates for each bin. In order to estimate an upper confidence bound for the total leak rate an expression is needed for the variance of the total leak rate. There are two sources of variance to be considered, the variance about the predicted expected value and the variance of the predicted expected value; the estimated total variance about the predicted expected value being the sum of the two. The variance of the total leak rate about the predicted expected value is x, Y(T) = { n, }7P, G,* e **'-1 + G,' P, (1 - P,) , (6.24) where P, is the probability of leak from equation (6.11). As noted, an additional variance term is added in order to estimate the contribution to the variance from the correlation between th 6 - 12
individual leak rates, i.e., from the covariance, which arises as a consequence of using the regression equations. Bus, the second term accounts for the variances of the positions of the regression equations. A linearized approximation (via Taylor's Theorem) of the variance of the mean of the regression prediction, T,, is given by y ' [Cov(pi,p3)] O O T - T V(T,) = n, o [co,(p,,p,)] o
, (6.25) -
0 0 V(o,') , where the derivative of the total leak rate vector contains five elements forj=1,...,5, and the Covariance Matrix is a square 5x5 matrix consisting of the estimated variances and covariances of the estimated individual regression coefficients and c,. Note that here (Cov(pi, p2)] and [Cos(p3, p.)] are each 2x2 matrices, where the E's are estimated by b, through b,, and recall 1 that c,is an estimate of p3 The variance of the variance is estimated as 1 4 V(ol) = n-2, (6.26) where n is the number of data pairs used in the leak rate regression analysis. The standard deviation of the total leak rate is then taken as the square root of the variance of the total leak , rate. He upper bound 95% confidence limit on the total leak rate is then obtained as the expected total leak rate plus 1,645 times the standard deviation of the total leak rate. The resuhs obtained with this approach have been compared to results obtained from the Monte Carle simulation without significant differences being observed. For a calculation utilizing only equation (6.24), the total leak rate from SG "D" at the EOC is estimated to be 3.0 GPM. By i :luding the variance from equation (6.25), We estimated total leak rate was estimated to be 3 ! GPM. The value obtained from the Morue Carlo simulation of the total leak rate was 3.2 GPM, as described in Section 6.8.1 below. Rus, for the distribution analyzed, the contr.bution of terms associated with the covariance,i.e., the uncertainty of the prediction of the r ean total expected leak rate, is small (being on the order of 3%) when compared to the varia.:e of the total leak rate about the mean value. He results obtained provide independent verif::ation of the Monte Carlo and hybrid techniques. 6.8 Simulation of Equation Parameter Uncertainties The estimated, total end of cycle leak rate can also be calculated using Monte Carlo tech-niques, e.g., the method documented in the EPRI ODSCC report (TR-10047, Rev.1). In the Monte Carlo analysis the variation in the parameters, i.e., coefficients, and the variation of the depe.. dent variable about the regression line is simulated. A 95% confidence bound on the total leak rate from SG "D" of Braidwood I was calculated using a Monte Carlo simulation to 6 - 13 l
1
, a 1 verify the results from the deterministic analysis. The approach used for the simulation is different from that discussed in the EPRI ODSCC report. While both methods simulate variation of each parameter of the correlation equations, the metLd discussed herein also simulated the effect of the covariance of the individual indication leak methods is discussed herein in order to provide clarification regarding their use. In ordei simplify the discussion of the Monte Carlo techniques, different nomenclature is use of the previous section, i.e., Q, is used to represent the common logarithm of the V,is used to represent the common logarithm of the bobbin amplitude. Dus, th model is used to describe a working relationship between the logarithm of the leak logarithm of the bobbin amplitude, Q, = b3+ b, V, + c ,
(6.27) where c is the estimated error of the residuals, assumed to be from a population th mean, and a variance that is not dependent on the magnitude of V,. He coefficients, b, and b, are the estimates from the regression analysis of some true coefficients, E, a the intercept and slope of the equation, respectively. 6.8.1 Monte Carlo Simulation of the Total Leak Rate for Braidwood 1 The method used by Westinghouse for simulating the total leak rate is the outcom of technical discussions held with the NRC. De method differs from that repo WCAP reports, wherein the predictive distribution was simulated and covariance t ignored. It is noted that, although both methods yielded similar results (within - Braidwood I, the method described herein is more statistically accurate. This smal in the total leak rate results is because the contribution of the co variance terms is relatively small for the correlations used herein. In summary, rand versions of the POL and leak rate correlations are generated and used to calculate the leak rates for all of the indications in a SG to obtain a single simulated value o! leak rate. This process is repeated to obtain a distribution of the total leak rate fro simulations of the correlation equations. A non-parametric 95% confidence bound leak rate is then estimated from the distribution of total leak rates. At the start of each SG simulation, i.e., the calculation of a single total leak rate, a rando value for the standard deviation of the errorsfor the population is calculated from th distribution, the degrees of freedom from the data, and the standard deviation of errors. His is used to calculate random values for the parameters of the regression e which remain constant for the entire SG simulation. He variation of the regression pr are accounted for by randomly estimating the POL from a uniform distribution, and by the product of a random normal devit;e and the standard deviation of the errors for the population to the predicted logarithm of the leak rate, for each individual indication in the 6 - 14 .
i l distribution. The total leak rate for the SG simulation is calculated as the sum of the leak rates ' from all of the indications in the SG. The expression for the total leak rate is N T= R,(p ,, p,) O,(p,, p., ,), (6.28) where N = the total number ofindications in the SG at EOC, R,(pi, 2) = 0 or 1 is the POL from a single indication, i, in a tube, Q,( 3, A., p3) = is the conditional leak rate ofindication /, i.e., the leak rate if the indication is leaking, pi, p2 = the coemeients of the POL equation, p3, p, = the coefficients of the leak rate versus bobbin amplitude equation, and p3= the standard error of the lor of the leak rate about the correlation line, .t also referred to herein as c. To simulate the total leak rate from all of the indications in the generator, random coefficients for the probability ofleak, POL, and leak rate correlation equations are generated, and then those coefficients are used to simulate the POL and leak rate for each indication. The POL, R,, for each indication, i, is simulated as, , I R'(p ) . if U. < I Ki'(D+OI i 2 8( V,)) (6.29) O otherwise ' where U,is an independent draw from a uniform distribution. The step of determining an integer value for the POL accounts for the variation of the dismbution of probabilities abe a the log logistic regression line. Discussion of the generation of piand p2 is left until after the discussion of the coefficients for the leak rate equation. Leak Rate versus Bobbin Amplitude Simulation To simulate the leak rate from the regression line, random coefficients p3 and p, must be simulated. Each of these has a vanance that is dependent on the variance of the error of de log of the leak rate about the regression line. Thus, the first step is to simulate a random e ror 2 variance by picking a random x deviate for n-2 degrees of freedom and then calculating a 2 random error variance, c , for the correlanon equation from the regression error variance u c= 2 (n -2) 62 -f,. 6 2 , k,. - n. If 30)
~
6 - 15
where n is the number of data pairs used to calculate the regression coefficients, andfy is defined by equation (6.30). This is now one possible variance for the population oflog-leak rates about a correlation equation. Thus, it is appropriate to use the normal distribution to ) obtain random values for the parameters of the correlation equation. The distribution of p3 and ! D will be bivariate normal. Since they are correlated, although each is normally distributed marginally, they are not free to vary independently. If a value for the slope is determined first, then the distribution of the intercept values will be conditional on that value of the slope. The degree of correlation is indicated by the off-diagonal entry in the parameter covariance matrix calculated from the regression analysis. The entries of the covariance matrix of the parameters, V,,, V,,, and V,,, for the correlation equation to be used for a SG simulation are obtained from the corresponding estimated matrix obtained from the regression analysis as Vy -fy V,y (6.31) where the caret, "^", indicates an estimate from the regression data. A bivariate normal intercept as for the simulation correlation is then calculated from the regression equation inter E = b + Z, k , 3 3 (6.32) and the bivariate normal slope is calculated from the regression slope as y y2 ! p , = b, + 2, ["% +V,,-yI 2, n (6.33) i where 2, and 2, are random univariate normal deviates, i.e., from a population with a mean of zero and a variance of one. We now have Q3, D., and a for use in simulating all of the leak rates from each of the indications in the SG for one simulation of the total leak rate. F simulation of an individual indication, i, the leak rate will be G,( p ) = 108 '
- W"J , (6.34) with 2, representing the i* value from N independent draws from a standard normal distribu-tion.
Once the probabilities of leak have been calculated, the total lea? rate for one simulation is then calculated using equation (6.28). It is noted that each simulation: of T requires the generation of one p vector, N binomial variates R,, and a maximum of N log-normal variates 0, in practice, a value for the leak rate only needs to be generated for each indication that is leaking, i e., when R, = 1. 6 - 16
l Probability ofLeak Simulation The generation of the coefficients of the POL relation to be used in the simulation of the total I leak rate proceeds in the same manner as for the coefficients of the leak rate relation. 'Ihe elements of the covariance matrix are obtained from the GLM regression analysis and used with the esumated coefficients in equations like (6.32) and (6.33) to obtain Si and a for a random population POL equation. However, for the simulation of the POL, there is no term of the form 2,o in the simulation of the total leak rate. This exception is due to the fact that the data are binary. In effect, this additional term is being simulated through the use of the. I random sampling to deterinine if R, is 0 or 1 in equation (6.29). It is noted that the elements of the covariance matrix obtained from the GLM regression are ; scaled to a mean square error (mse) of 1. This is because the mse for the binary variables is asymptotically 1. A check of this assumption can be made by calculating an estimate of the
)
square root of the mse from the regression results as 6 => I (#'~#'} (6.35) l y n - 2 {, p,(1 p,) , 1 where the yls are the observed probabihties of leak, either zero or one, from the leak and burst ' testing, and the p,'s are the calculated probabilites of leak from the logistic regression equation. A significant departure from 1 for this quantity could be indicative of an inadequate l model. For de simulation of the POL data for 3/4" tubes the root mse was found to be 1.1. This is not s:gnificantly different from 1. A 95% confidence bound on the total leak rate from SG "D" a: the end of the fuel cycle was found to be 3 2 GPM. This is in very c.ose agreement with the value found using the determinisuc estimate. 6.8.2 EPRI Monte Carlo Simulations The simulatie methodology documented in the EPRI ODSCC report, Reference 6.1, was also used for the emmation of a EOC leak ra: for the Braidwood 1 SG "D" The resulting value, 3.1 GPM is provided for information s=:e this analysis was no: the reference methodology , employed fo: se evaluation of the Bra:dwood SGs Thus, the following discussion of the EPRI model :s also for information pur;oses to clarify how it relates to the methodology em-ployed. App:::ation of the EPRI mode mvolves two major steps. In the first step, an EOC leak rate table as a function of BOC vehs is generated from Monte Carlo simulations of NDE uncertamties, plant specific growth rates. and uncertainnes asso:iated with the correlation analyses in me second step, the total leak rate is estimated as the sum of the individual EOC leak rates frc= each indication usmg the tabulated leak versus BOC volts values. 6 - I *'
, ., , , . - _ - ~ - - - , .-, - - -
Using the EPRI methodology, the probe wear and analyst variability are randomly sam obtain a random DOC voltage corresponding to a measured BOC voltage. The growth cu then entered to obtain a random growth for the length of the cycle. This is then added to the ' BOC voltage to obtain a random EOC voltage. The POL and leak rate versus volts correls-tions are sampled to obtain a random POL and leak rate for that indication. The expected le rate from the indication is then taken as the POL times the leak rate. 'Ihe simulation repeated several thousand times to obtain an EOC distribution ofleak rate at each voltage level, typically in 0.1 volt increments. From the distribution, a non-parametric 95% confidence bound for 95% of the population of the leak rates is determined at each voltage level. Thes are then used to estimate the EOC leakage from the distribution of BOC indications. 1 The POL for a specified EOC indication voltage is obtained from the correlation equation a I R' =
] , g -if *8,30s i F )*2,q,) , (6.36) l l
where D, and D2 are the coefficients from the POL regression analysis,2,-N(0,1), and estimated standard deviation given by i l 9,=/Vn + [ 2 V,, + V,, log ( V,) ] log ( V,) , (6.37) where the F/s are the elements of the covariance matrix of the coefficients. For each indication simulated, the coefficients of the leak rate versus voltage equation are ' Eenerated. The slope of the regression equation is sampled using a random t variate, followed by simulation of the intercept. Finally, the regression residual error is sampled with a random t variate. Random t variates are used instead of random normal variates be deviation of the population of residuals is estimated, and not known, from the regression analysis. A two-sided 100-(1 a)% confidence band for the true slope, p., of the regression equation is given by c' p , = b,
- t,, %., , (6.38) where b,is the estimated slope from the regression analysis, v is the number of degrees of
' freedom used for the determination of o,, the estimated standard deviation of the residuals. Thus, by randomly sampling the t distribution with v degrees of freedom, t,, random values of 6 - 18
i
. the slope can be generated from equation (6.38), where the sign of the random t vanate i governs the sign of the second expression, i.e., .I o
. p, = b, + t, _ .
(6.39) [(V - V)* j The coefficients of the regression equation, i.e., equation (6.27), are not statistically indepen-dent. Thus, selecting a random value for the intercept must account for the already selected slope. In this case, a joint 100-(1-et)% confidence ellipse for the coefficients is given by (p3 -b3 )2 + 2 V(p3 -b )(p, -b ) + [ Y'# ( , - b,)22 sa' F2- ' 3 , (6.40) n n where S3 and p, are the true, but unknown, coefficients of the regression equation. Thus, given the random slope from equation (6.39), a random F-distribution value, F, for 2 and v degrees of freedom, is selected and equation (6.40) is solved (considering the equality) to obtain a random value for p3 Since there are multiple roots of equation (6.40), i.e., 8 p3 = 3b - V(p - b ) * (p, - b,)2 V'-[V n.
+
2o,*F8- ' n (6.41) an ad6tional random selection must be made to account for the sign of the radical it equation (6.41) It is also noted that the selection of a random F deviate may result in the ra6:al of (6.41) being imaginary. In this case, it is necessary to sample F until the radical is real To comple*,e the leak rate versus voltage correlation for the simulation, only the variatio: about the regresnon line remains. The standard error, o,, from the regression analysis has beet shown to be approximately normally distributed with a mean of zero. Since the true variance eithe residui population is estimated, the distribution is simulated using a random t variate. and the final leak rate for each simulation case is given by g, . i o 8, + 8. v. * *, e. , (6.42) It is no:ed that the method described in the EPRI ODSCC report indicates that the effective standard deviation of the residuals, o,, from equation (6.22) is to be used instead of the actual standard deviation of the residuals, o,, in equation (6.42). This is considered to be a . unnecessary conservatism because the variance of the coefficients would enter equane: (6.42) twice, i e , through the simulation of D3 :md p, and through o,. The net effect would be to L 6-19 '
l l slightly over estimate the leak rate for each individual indication. For the simulation result reported previously herein, equation (6.42) was used. In summary, the EPRI simulation essentially uses the predictive distribution to simulate the EOC leak rate. This ignores the potential contribution due to the covariance of the individual POL times leak rate values, however, this is likely compensated for by taking each individual EOC leak rate at a 95% confidence level, and the fact that the contribution from the covariance terms is small. Westinghouse has previously reported results, in prior WCAP reports, based on directly simulating the predictive distribution. Results obtained using this method,3.0 and 3.1 GPM for two in6endent simulations, were comparable to the result obtained using the methodology der,moed in Section 6.8.1. Thus, the EPRI methodology of Reference 6.1 results in a predicted total leak rate of 3.1 GPM, which is in excellent agreement with the 3.2 GPM result obtained by the Monte Carlo methods of Section 6.8.1, and the 3.1 GPM result from the hybrid method. In conclusion, either of the three methods is adequate for the SLB leak rate ar alysis. o9 References The references used in this report section are: 6.1 TR 100407, Revision 1 (draft), "PWR Steam Generator Tube Repair Limits - Technical Support Document for Outside Diameter Stress Corrosion Crack at Tube Support Plates," Electric Power Research Institute, August 1993. 6.2 NP 7480-L, Volume 2, " Steam Generator Tubing Outside Diameter Stress Corrosion Cracking at Tube Support Plates - Database for Alternate Repair Limits, Volume 2: 3/4 inch Diameter Tubing," Electric Power Research Institute, October,1993. 6.3 EPRI Letter, " Exclusion of Data from Altemate Repair Criteda (ARC) Databases Associated with 7/8 inch Tubing Exhibiting ODSCC," D. A. Stehinger (EPRI) to J. Strosnider (USNRC), April 22,1994 [to become Appendix E cf Reference 6.2]. 6.4 NUREG-1477 (draft), Voltage Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report," United States Nuclear Regulatory Commission (NRC), June 1,1993. 6.5 [ United States Nuclear Regulatory Commission] Meeting with EPRI, NUMARC, "Resolu-tion of Public Comments on Draft NUREG 1477," United States Nuclear Regulatory Commission, February 8,1994. 6 - 20
6.6 Regulatory Guide 1.121 (draft), " Bases for Plugging Degraded PWR Steam Generator Tubes," United States Nuclear Regulatory Commission, issued for comment in August, 1976. 6.7 Docket STM 50-456, " Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. to Facility Operating License No. NPF-72 Commonwealth Edison Company Braidwood Station, Unit No.1," United States Nuclear Regulatory Commission, May,1994. 'l 0 l 6 - 21
p, . i 4 Table 6-1: Regression Analysis Results - Burst Pressure vs. log (Bobbin Amplitude) 3/4" x 0.050" Alloy 600 MA SG Tubes q (Reference e, = 75 ksi) , Parameter Value Value Parameter 6, -3.077 7.822 b, SE b, 0.175 0.136 SE b,
. r' !
80.7% . 0.955 SE P, F 306.1 73 DoF S S,, 279.03 66.55 ' SS,,
, Pr(F) 8.0E-28 29.46 SS %g pi-value ' 8.GE-28 1.6E-62 po-value
{ l 4 I 6 - 22 P
o 1
. j s.. .
i I i Table 6-2: Results of Regression Fits of Logarithmic Forms l of POL Distribution Functions to 3/4" OD Tube Data
@ 620*F and AP = 2560 psi Prearneter Log-Logistic Log Normal Log Cauchy Values Values Values b, -5.5998 -2.7157 -13.8413 b, 9.1924 4.6317 21.3183 i
V,, 2.1145 0.3664 46.5125 V,, -2.9538 -04985 -71.2114. V,, 4.5779 0.7993 110.22 Dr.iance 32.52 33.84 32.43 Resi s of Regression Fits of Non-Logarithmic Forms of POL Distribution Functions to 3/4" OD Tube Data. ' Pra:neter Logistic Normal Cauchy Values Values Values 3, -5.3890 - 8544 -10.5327-b, 1.1945 0.6395 2.3085' P,, 1.4958 0.2905 24.4371 P., -0.3141 -00617 -5.3943 P., 0.0787 00169 1.2223 Dr. ance 28.87 25 94 32.47 i 6 - 23 1 l
I t 4 l 4 Table 6-3: Sample Results for Probability of Leak for 3/4" SG Tubes
@ 620*F and AP = 2560 psi Volts Log Logistic Log Normal Log Cauchy Logistic Normal Cauchy Function Function Function Function Function Function 0.1 3.77E-07 1.02E-13 9.05E-03 5.12E-03 2.63E-03 3.08E-02 .
0.2 5.99E-06 1.32E-09 1.11E-02 5.77E-03 3.20E-03 3.15E-02 . 0.3 3.02E-05 1.39E-07 1.27E-02 6.49E-03 3.88E 03 3.22E-02 0.4 9.53E-05 2.57E-06 1.42E-02 7.31E-03 4.68E 03 3.30E 02 0.5 2.32E-04 1.98E-05 1.57E 02 8.23E-03 5.63E-03 3.38E 02 0.6 4.81E-04 9.09E-05 1.71E-02 9.26E-03 6.74E-03 3.47E-02 0.7 8.90E-04 ' 2.98E-04 1.85E-02 1.04E-02 8.05E-03 3.55E-02 0.8 1.52E 03 7.77E-04 2.00E 02 1.17E-02 9.57E-03 3.65E-02 0.9 2.42E-03 1.71E-03 2.15E 02 1.32E-02 1.13E-02 3.75E-02 1.0 3.68E-03 3.31E-03 2.30E-02 1.49E-02 1.34E 02 3.85E-02 2.0 5.56E-02 9.32E-02 4.26E-02 4.74E-02 5.76E-02 5.33E-02 5.0 6.95E 01 6.99E-01 7.59E-01 6.42E-01 6.34E-01 7.52E-01 7.0 8.97E-01 8.85E-01 9.25E-01 9.51E-01 9.48E-01 9.44E-01 10.0 9.73E-01 9.72E-01 9.58E-01 9.99E-01 1.00E+00 9.75E-01 . 6 - 24 t
4 . .- a Table 6-4: Regression Analysis Results: log (Leak Rate) vs log (Volts) for 3/4" x 0.043" Alloy 600 SG Tubes
@ 620'F and AP = 2560 psi Prameter Value Value Parameter b, 3.132 -1.888 b, SE b, 0.431 0.425 SE b, 2
r 58.2 % 0.653 SE log (G) F 55.88 38 DoF ; 5 S,, 22.56 16.21 S S,,, l Pr(F) <0.000001% 2.300 SS #., !
; value <0.000001% 0.01% po-value - !
h 6 - 25 t
Figurt 6-1: Burst Press re vs Bobbia Amplitude s EPlu Database , @ 650*F, Reference Flow Stress = 75 ksi a,e Y a M M parvJmc xts) EPR P wV N M:4/1544.303 PM
Figun 6-2: Burst Pnssun vs. Crack length 0.750" x 0.043", Alloy 600 MA Steam Generator Tubes @ 650*F, Average Flow Stress S,6 e e ed [tw eunsixtsise cwve FFK- 4/1884,6 51 PM
Figure 6-3: Probability cf B:rst vs. Through-Wall Crack Imagth 3/4" x 0.043" Alloy 600 MA SG Tubes
,o l [EPROURS XLS) Pr Duest 34 TK 4/16/94. 6 de PM
Figure 6-4: Probability of Leak for3/4" SG Tubes Comparison of Logarithmic Forms of Logistic, Normal & Cauchy Funct
~
i useum M iso;nvEu xtstPos. %M m .. ._.
Fig:::re 6-5: Probability cf Leak for 3/4" SG Tubes Comparison of Non-Logarithmic Forms of Logistic, Normal & Cauchy Function y l a 6 d . tecunvE34 XLSIPolV ' RFK 44944.8 de PM
Figure 6-6: 2560 psi SLB Leak Rate vs. Bobbin Amplitude 3/4" x 0.043" Alloy 600 SG Tubes, Model Boiler & Field Data (EPRI) 1,C i i l l l 1 l l l l l l (340V CCE XLSI O vs V EPnt ww an am . .. r>.e
l 7.0 BRAIDWOOD 1 EDDY CURRENT INSPECTION RESULTS 7.1 General The March-April 1994 refueling shutdown was accompanied by 100% full length bobbin probe inspection of all four steam generators. In anticipation of the potential finding of significant ODSCC at support plate intersections, the ASME standards were calibrated to be consistent with IPC guidelines (such as incorporated into Appendix A of WCAP-13854), wear standards were employed to allow tracking of voltage measurement variation, and the eddy current analysts were required to demonstrate their capability to report and to measure indication voltages. TSP indications have been assessed against the prior inspection conditions at the corresponding locations to develop voltage growth rates fr the preceding periods of operation. Previous inspec't ions of the Braidwood l steam generator tubes were conducted in November 1993 during an unplanned outage (SG C only), in September 1992 (EOC 3), and in April 1991 (EOC-2); the EOC-1 inspection in September 1989 was not included in the growth rate studies. For each indication reported dunng the 1994 inspection, both the 1993 (SG C) and the 1992 (all SGs) data were reevaluated to determine, as far as possible, the pre existing signal amplitude which could be attribu:ed to any detectable precursor condition. Only if a possible flaw indication was observed in the earlier inspection was a growth point calculated for the particular 1994 indication; i.e. ne assumptions were made about prior year signal voltages. Because of the unplanned ouuge during Cycle 4, comparisons in SG C were made to both the 1993 and 1992 inspection results; furthermore,1992 data for tubes reported in 1993 were compared to obtain an estimz:e of the partial cycle (4a) growth rate. Cycle 4b growth was determined by comparing the 1993 and 1994 data for SG C only; an overall Cycle 4 growth rate based on comparise: of 1994 with 1992 data was also calculated. All the tubes plugged in 1992 were used to develop growth rate data for Cycle 3 by reanalyzing the 1991 data. Table 71 presents a sun. mary tabulation of all the growth rates on a per cycle as well as a per Effective Full Power Year (EFPY) basis; also shown for each case are the number of comparisons used, the average BOC voltages, the voltage growth (oV), and the lencth of the operating period in EFPY. For each cycle evaluated, the data was subdivided into indication populations less than 0.7! volt and those equal to or greater than 0.75 volt. This was done to demonstrate the consis ency in behavior with prior cases, which have consistently shown higher average perce:: age growth rates for low voltage indications. The distribution of the TSP ODSCC inci.:ations among the four SGs for the 1994 inspection is shown in Table 7 2, which tabulates t e number ofindications for each TSP elevation for which indications were observed For t.e D4 SGs of Braidwood 1, the IH level represents the Flow Distribution Baffle (FDB), a pmt:e with oversize tube holes and no flow holes; for this reason the incidence of ODSCC is expected to be low in the absence of unusual 7-1 1
l 3 circumstances. In fact, none of the indications reported in Braidwood l occur at this I elevation. The support levels above are numbered in the cold leg order; i.e., the next hot leg l l TSP is designated 3H since its height corresponds to the 3rd preheater plate. The remaining TSPs are designated SH,7H, SH,9H,10H, and 1IH. Thus, though some probability of encountering ODSCC signals at the upper plates exists, it is expected that most of the indications will be observed in TSPs 3H,5H, and 7H. These levels are in the relatively hotter' internal temperature zone of the tubes (maximum in the hot leg tubesheet and decreasing with elevation up to the apexes of the U bends, thereafter decreasing as the cold leg elevation decreases). 7.2 Inspection Results 7.2.1 March 1994 Inspection During the scheduled refueling outage (AIR 04), all tubes in service were tested full length with bobbin probes. Each distorted support plate indication (DSI) and all TSP indications , characterized as a percent (%) call were subjected to confirmatory MRPC testing to assess the consistency of the underlying tube condition with prior cases of TSP ODSCC, and to determine the severity of the indication with respect to the repair criteria. The TSP' bobbin indications confirmed by MRPC testing numbered 1567 among the four SGs,470 in SG A, 76 in SG B,642 in SG C, and 379 in SG D., The total number of TSP intersections subjecte to MRPC testing on the basis of possible ODSCC indications was 2733, distributed among the four SGs; this represents a 57% rate of confirmation of the bobbin calls. It is considered that only those intersections which exhibit detectable ODSCC with pancake coil inspections . warrant scrutiny with respect to plugging criteria, whether under Tech. Spec. criteria or under the attemate basis represented by the Interim Plugging Criteria. Two SG C bobbin field calls confirmed as NDD by RPC inspection are not included in the statistics These of this report. indications were more appropriately called permeability variations or residual signals and , i inclusion of these two indications would result in misleading growth data. The axial distribution of TSP ODSCC indications, as expected, exhibits the strong correlation with height above the tubesheet. ' With the exception of the IH level (FDB), a strong concentration of the bobbin and MRPC indications are observed at 3H (58%),5H (28%), and 7H (10%). Figure 7-1 presents the numerical distributions of the TSP ODSCC with respect to elevation in histogram form. The bobbin amplitude distributions associated with the ODSCC indications are presented together with the cumulative distribution curves in Figures 7-2 to 7-6 for the individual SGs and for the composite of all four SGs. Figure 7-7 gives the cumulative RPC confirmation fraction of the bobbin indications as a function of bobbin voltage. As expected, the probability that the RPC probe will detect degradation increases with the bobbin voltage, which increases with the depth and length and number of cracks Tablepresent. 7-3 7-2
provides detailed RPC confirmation statistics as a function of bobbin voltage for each of the individual SGs, as well as cumulative confirmation data for the four SG composite results. An RPC sampling plan was performed to inspect TSP intersections with dent signals greater than 5 volts and artifact / residual signals that could potentially mask bobbin indications of about 1.0 volt. Denting in Braidwood l is minor and most of the dents represent mechanical dings rather than corrosion induced denting. The RPC sampling plan was performed on all identified hot leg dents > 5.0 volts in SGs A and B. It included 21 dents (18 in SG A,3 in SG B) at TSP intersections. There are only 6 dents in SG C (one additional dent was in a tube plugged for other causes) and 2 in SG D left in service above 5 volts that were not RPC inspected. The RPC sample included 40 mix residuals in SG A and 41 in SG B. The mix residuals inspected had greater than a one volt signal and were manually selected to represent the larger residual signals. In addition to this RPC sampling plan,85 intersections with no bobbin indications were RPC inspected No RPC flaw indications were found in the RPC sampling plan. In both this RPC sample and the RPC inspection of bobbin flaw indications, no circumferential indications or indications extending outside of the TSP thickness were detected. Limiting the RPC sampling to only SGs A and B left only 8 dented TSP intersections uninspected in SGs C and D. Reviews of data from previous outages indicate that all 8 of these dent indications were present. Tne uninspected dent indications lead to a negligible risk of leakage or rupture due to the small number of dents, the fact that no flaw indications were found at the inspected dent locations and the fact that a conservative POD of 0.6, independent of voltage, is applied for the SLB leak rate and tube burst probability estimates. Similarly, uninspected mix residuals in SGs C and D would have negligible concem for leakage or burst consid,erations. The two dents in SG D have bobbin voltages of 19.1 and 5.1 volts. The bobbin data for these indications have been reviewed for the 1989,1991,1992 and 1994 inspections. There have been no discernable changes in the dent voltages or phase angles. In all inspections, the phase angles are within 3 degrees of the expected 180 degrees for a dent. If a flaw were present, some change to the voltage and phase angle would be expected. Thus, it is judged that the dents are not growing in size and there is a low likelihood of a flaw being present in the dents. SG D is the most limitmg SG for tube leakage and burst considerations. Since only two uninspected dents are present. even the assumption of a flaw being present in the dent (a flaw too small to influence the phase angle of the dent) would have negligible influence on leakage or burst. The POD = 0.6 adjustment results in 7.3 indications (actual indications plugged) above 2.7 volts lef:in service and 2 indications above 5.0 volts left in service. The contributions of these pos:ulated indications to leakage and burst probability would be expected to exceed that of a potential indication in the two dented intersections not RPC inspected SG C is not a limiting SG for leakage or burst considerations due to the 7-3
i e
- I
\
l lower voltages (maximum of 2.74 volts found in the 1994 inspection) and lower growth rates found for this SG compared to SG D. Even ifindications were postulated in the six 1 uninspected dents left in' service, the additional indications would be very unlikely to cause i the leakage or burst probability to approach that for SG D. It can be further noted that the t presence of a crack within a dented TSP would result in no or very small leakage due to the constraint provided by the dent, as shown by leak testing in the EPRI database report. If the postulated indication extended more than about 0.2" from the dent, the crack indication would be detectable by bobbin inspection. For these additional reasons, leakage or burst potent would be negligible for uninspected dents. 7.2.2 Prior Inspections: November 1993 and September 1992 The 1993 inspection of SG C was conducted in conjunction with an unplanned outage. Th 100% Nll length inspection with bobbin probes was conducted with 610 mil standard bobbin coils, t ,mg standards which were subsequently' normalized to the laboratory standard which serves as the reference for 3/4" alloy 600 tubing. Using the prevailing industry guidelines for reporting bobbin indications,116 percent type indications were reported, along with 300 DSIs The percent-type indications were removed from service after confirmation with MRPC, a the DSIs were continued in service without MRPC verification. This was considered in light of the AIR 04 refueling outage scheduled 4 months later. Since the November 1993 testing the was other SGs. not conducted as a Tech. Spec. inspection, there was no extension of the The 1993 bobbin indication distributions for number vs. TSP elevation and amplitude are given in Figure 7 8 and in Table 7-4. Once again, the temperature / elevation dependency of the ODSCC incidence is apparent, and the distribution of amplitudes show predominance amplitude signals. of low voltage (<!) signals accompanied by a low frequency tail of larger During AIR 03, the September 1992 inspection, all four SGs were subjected to 100% full length bobbin inspection, again using site-specific bobbin interpretation guidelines consist with the prevailing mdustry approach in plants not implementing the IPC. In this inspe as in AIR 04, all bobbin percent (%) and DSI indications reported were subjected to MRPC examination; 166 tubes with bobbin TSP indications confirmed by MRPC testing were removed from service. DSI signals reported on 79 intersections were continued in service after obtaining NDD (no detectable degradation) results from MRPC testing and analysis. The reported distribution of bobbin indications for AIR 03 are given in Table 7-5 and Figure 7-9 for the elevation dependency, and the amplitude spectrum of the plugged tube indications is shown in Figure 7-10. It is apparent that the bobbin inspection data for 1992 1993 and 1994 reflect similar pattems of tube degradation, proceeding for the most part a modest rates in terms of bobbin amplitudes, but progressively involving more tubes. 7-4
4 7.3 TSP Voltage Growth Rates The progression of ODSCC indicatio5s at the TSPs is determined by ic-evaluation of prior inspection EC records at the locations identified with indications in the 1994 inspection. In most cases, some element of the precursor is identified as corresponding to the flaw signal reported in 1994. However, it should be noted that rather conservative analysis criteria are invoked to accomplish this task. In this process analysts are required to forego the behavior criteria they may have employed to screen out low signal-to-noise indications, and to report possible flaw-like behavior in the TSP mix residual regardless of clarity. Review of the growth data identifies any anomalous growth data, and these are subjected to further scrutiny to eliminate spurious data. The evaluation of voltage growth based on reevaluating the prior inspection data for all indications found during the latest inspection is the same approach used for other IPC/APC evaluations. This method of growth evaluation includes the largest growth values (typically repaired at the EOC) for each cycle, and can result in large, conservative average growth values. However, because of tube repair and the occurrence of new indications, there are differences in the population of tubes when comparing growth rates between cycles. This introduces some uncertainty in assessing growth trends between cycles, such as those which may be due to chemistry improvements. A more desirable growth evaluation would track the same population ofindications for multiple cycles to more accurately assess growth trends. However, if the last inspection indications are tracked back in time, the larger prior cycle indications which were repaired are not included in the analysis and this method can lead to an underestimate of average prior cycle growth. This methc'd has been applied to SG C over the first and second parts of Cycle 4 as described below. A third option for evaluating growth would be to track the latest inspection results back in time and to add plugged tubes into the population evaluated for prior cycles. This method has not been systematically evaluated. A more systematic evaluation of these three options would be desirable to assess the best option for evaluating both cycle-to-cycle growth trends ano the influence of operational chemistry improvements. Such an evaluation has not been performed for Braidwood l in this report. The operational periods for which growth values were determined included Cycle 3 - plugged tubes only; Cycle 4a (9/92-10/93) - SG C only but in three subgroups: all plugged tubes at 10/93, all indications reported at 10/93, and all indications reported at 4/94; Cycle 4b (11/93-4/94) for SG C only for all indications reported in 4/94; and the overall Cycle 4 for all four S Gs. For each of these periods, growth data for indications <0.75 volt and those 20.75 volt were contrasted with the composite growth data for all indications. Table 7-6 shows a summary of the growth rates developed in this fashion for all four SGs. Figure 7-11 illustrates the overall growth / amplitude relationship for all the comparisons obtained in A 1 R04. 7-5
Figure 7-12 presents the same data combined with the elevation (temperature) effect.~ The i dominance reflected of therates. in the growth lower TSP levels in the incidence of the ODSCC indications is al The' distribution of the growth rate data, expressed as volts difference in the amplitude readings for 2 inspections, are tabulated (Table 7-6) in 0.1 volt bins up to 3 volts,0.2 volt bins fro' m 3 volts to 5 volts, and in 0.5 volt intervals up to the maximum observed change. For each bin the number ofindications is entered along with the corresponding' cumulative probability value. Voltage growth distributions are reported on a per EFPY basis. The voltage growth histograms for each of the operational periods evaluated are presented in Figures 7-13 to 7-18 on a composite basis for the prior cycles and on an individual SG basis for the Cycle 4 data. It is seen that for the AIR 04 inspection, the average voltage growth for the composite of four SGs is 49% per EFPY, or 0.24 volt average growth per EFPY on average BOC amplitude of 0.48 volt. The maximum growth was observed in SG A,76% p EFPY,0.36 volt growth on the average BOC amplitude of 0.47 volt.' The largest individual growth observations for Cycle 4 are listed in Table 7-7. For indications with appreciable BOC amplitude readings, i.e., those from 0.75 volt and up, average growth is but a fraction the composite,26% in SG A and approximately 16% for the overall population. These estimates are strongly weighted by the SG C results, which exclude the tubes plugged i 11/93 (EOC-4a), for which higher growth rates were observed. The decrease noted in the EOC-4 data and the EOC 4b data correlate with secondary system chemistry change implemented at Braidwood-l since the AIR 03, outage. ( While the voltage growth rates prior to 1993 appear to be larger than those observed in oth > domestic plants, they fall well below growth rates observed in European plants. Three cas , ef tube leakage attributable to TSP ODSCC have been reported in Europe, though none approached even Tech. Spec. leakage limits. None of the domestic plants affected by TSP ODSCC has experienced tube leakage in the absence of denting, notwithstanding indicati amplitudes as high as 10.5 volts, and one occurrence of 22 volts. t 7.4 Historical Operating Chemistry 1 Braidwood Unit 1 is currently in its fourth refueling outage. The unit has typically operate in the load follow manner of operation (Figures 7-19 through 7-21). Frequent changes in plant the output requirements have resulted in power swings and plant shutdowns on occasion in past. During periods of operation with chemistry imbalances, more frequent shutdowns ' with chemistry cleanup prior to restart can result in more limited accumulation of contaminan species in crevice regions subject to superheated conditions. Braidwood Unit I has experienced periods of elevated steam generator sodium to chloride molar ratios during prior operating cycles. Operating with these elevated ratios enhances the possibility of deve 7-6
i , s caustic crevice conditions conducive to initiation and propagation of Alloy 600 alkaline stress corrosion cracking. Figures 7-19 through 7-27 show the power history, steam generator blowdown sodium to chloride molar ratios, and steam generator blowdown sodium and chloride concentrations during power operation for Braidwood Unit I during Cycles 2 through 4. During Cycle 2, SG blowdown sodium to chloride molar ratios (Figure 7-22) were slightly higher than molar equivalency with ratios typically less than 2. These ratio values fluctuated along with variations in plant operating conditions and minor contaminant ingresses - condenser leakage and demineralizer leakage. It should be noted that ratios maintained in this range can lead to development of caustic conditions in steam generator crevice regions. During Cycle 3, SG blowdown sodium to chloride molar ratios (Figure 7-23) l were very elevated - both with respect to prior cycles of operation and with respect to good I ) operating chemistry conditions. It is believed that this notable increase is likely to primarily be due to increased attention paid to SG blowdown cation conductivity values and attempts to ! lower them. As chloride concentration affects cation conductivity, lower chloride concentratiohs resulted in lower cation conductivity and, consequently, higher sodium to chloride molar ratios. Sodium concentrations were elevated during the first half of Cycle 3 ' (Figure 7-26). As these concentrations were decreased during the latter part of the fuel cycle, l however, chloride concentrations were also decreased. Sodium to chloride molar ratios l typically in the range of 2 to 3 and up to 5, as observed during Cycle 3 are strongly indicative of potentially caustic environment development in SG crevice regions as described above. During Cycle 4, a period of operation with higher molar ratios around 2 to 3 was followed by attempts to control molar ratio by modification of blowdown demineralizer operation and, subsequently, ammonium chloride addition (Figure 7-24). Ammonium chloride addition has had the greatest effectiveness at Braidwood Unit 1 in controlling steam generator blowdown sodium to chloride molar ratios in the desired band. The success of this method controlling crevice chemistry appears to be positive as a result of shutdown hideout retum evaluations performed in May and at the end of the cycle. Hideout retum data obtained during Cycle 4 has been evaluated to ascertain the success of the molar ratio control program in modifying the steam generator crevice pH environment. Molar ratios of highly soluble species (sodium, potassium, and chloride) indicate a decreasing trend over the entire cycle (Figure 7-28). In addition, n us been reported that the crevice pH calculated by the MULTEQ program indicates an approximate 1.5 pH unit reduction to around 7.5 prior to the end of cycle shutdown. The end of cycle shutdown indicated more acidic conditions and lower molar ratio due to the occurrence of circulating water leakage. 7.5 Relationship Between Operating Chemistry and ODSCC Growth Corrective actions taken at Braidwood Unit I specifically to slow the progression of Alloy 600 tubing ODSCC include molar ratio chemistry control and boric acid addition beginning in ( 7-7 l l _, _
1 l April 1994. Molar ratio chemistry control was initiated during Cycle 4 in December 1992, following nearly two months of plant operation with elevated sodium to chloride molar ratios. Molar ratio control chemistry was begun by varying blowdown demineralizer operations to obtain greater breakthrough of anionic species. These operations have had some success in minimizing sodium leakage from the demineralizers; however, the operational sodium to chloride molar ratio was not able to be fully controlled. When it became apparent that ' operating in this manner was not achieving the desired degree of control, the decision was made to add ammonium chloride to adjust the sodium to chloride molar ratio in the steam generator blowdown. This method achieved a high degree of control over the operating steam generator blowdown sodium to chloride molar ratio. However, it was not apparent whether the desired result of neutral to slightly acidic hideout retum chemistry would be achieved by operating in the identified control band of Na/Cl = 0.3 - 0.6. Following a hideout retum evaluation at the end of May 1993, the Na/Cl control band was lowered to 0.2 to 0.4 to 3 further alter the steam generator operating environment. The result of this change is demonstrated in Figure 7-29. Hideout retum chemistry data reflect the success of the molar ratio control program in modifying the steam generator environment to the desired degree as indicated by the trends in hideout return chemistry.
\
l Boric acid addition has been identified as the next step to be employed at Braidwood Unit 1 to control Alloy 600 ODSCC progression. Boric acid will be used during the startup for the fifth fuel cycle in April,1994. Laboratory and operating PWR plant data indicate the { usefulness of boric acid as a contributor to the overall corrosion control program. It is { anticipated that the use of boric acid will take Braidwood Unit 1 one step further in their goal of minimizing ODSCC growth rates. ' Overall, the chemistry review indicates that the high molar ratios of Cycle 3 (4/91-9/92) and the early part of Cycle 4 (up to 1/93) are most likely to be associated with caustic crevice conditions and increased potential for ODSCC initiation and growth, Molar ratios since February 1993 and particularly since the May 1993 reduction in the control band are i supportive of reduced potential for ODSCC growth. Since voltage growth rates across the l i complete Cycle 4 operating period involve both high and low molar ratio operation, the growth rates cannot be readily related to chemistry improvements. However, the SG C growth data of Table 7-1 for Cycle 4a (includes high molar ratio period) and Cycle 4b (Iow molar ratio period) can provide some insight on the influence of reduced molar ratio on crack l { growth. SG C had an average growth rate of 39%/EFPY for Cycle 4a and 27%/EFPY for Cycle 4b. This reduction in growth rates for Cycle 4b is supportive of the chemistry k improvements in the reduction of growth rates. Cycle 5 experience, which will include boric {' acid addition, will provide more conclusive data for assessing the influence of chemistry enhancements on growth rates. 7-8
7.6 Pulled Tube Eddy Current Data TSP intersections from 4 tubes were removed from the Braidwood-1 SGs to provide the basis ' for application ofInterim Plugging Criteria and to demonstrate the consistency of the Braidwood-1 experience with other plants in which those criteria have been accepted. From SG A,2 tubes (R37C43 and R42C44) were pulled, and from SG D,2 tubes (R37C34 and R16C42). Tube R42C44 was cut above the 7H intersection, permitting the extraction of 4 intersections at the IH,3H, SH and 7H elevations. The three remaining tubes were cut below the 7H TSP level on inlet side, permitting the extraction of 9 additional intersections (total of 13),3 at each of the IH,3H, and SH elevations. Bobbin and RPC data were collected for each of the removed intersections, which resulted in 6 field bobbin indications with corresponding RPC confirmations and 7 NDD intersections. The bobbin field EC graphics for each of the intersections are given in Figures 7 30 to 7-42. The corresponding RPC field graphics for the tubes reported to have bobbin indications are given in Figures 7-43 to 7-48. Table 7-8 summarizes the field analysis results for each of the intersections. With ' the exception of the 1.04 volt indication at the 3H level on R37C34 and the 2.09 volt indication at TSP-SH on R42C44, the field calls represent voltages in excess of the full APC limit calculated for the 3/4" tubes in Braidwood-1. The SH level on R16C42 is consi representing a possible bobbin indication of 0.61 volt, but field RPC was reported as NDD, suggesting the absence of significant ODSCC; evaluation of the tube metallography for this tube may provide some insight into the relative sensitivities of the bobbin and RPC probes for the less developed areas of ODSCC. 7-9 i i
. - . . _ _ . . -- . _ . - ._ . - _ . = ,. .- . . . -
Table 7-1 Average Voltage Growth for Braidwood Unit 1 Cycle 4 9/92 -3/94 Average AV % Growth All S/G's # indications Average V see AV ofpy AV/efpy % percycle % perefpy Entire Voltage Range 2654 0.49 0.26 1.147 0.23 53 % 48% Vsoe<.75 2289 0.41 0.29 0.25 69% 60%
, V see 2 .75 365 0.94 0.13 0.11 14 % 16 %
S/G A Entire Voltage Rance 680 0.47 0.41
- 0.36 86 % 75 %
Vsee < .75 586 0.39 0.43 0.37 113 % 97% V see 2 .75 94 0.95 0.28 0.24 29% i 25% S/G B Entire Voltage Rance 261 0.48 0.17 0.15 36 % 31 % V see < .75 230 0.41 0.16 0.14 39% 34 % V noe 2 .75 31 0.94 0.22 0.19 23% 20% S/G C Entire Voltage Rance 1030 0.5 0.19 -0.17 38 % 34 % V soc < .75 876 0.42 0.24 0.21 57% 50 % V noe 2 .75 154 0.95 -0.06 -0.05 -6% 5% S/G D Entire Voltage Rance 683 0.49 0.27 0.24 55% 49% V ace < .75 597 0.43 0.27 0.24 63% 56 % V see 2 .75 86 0.92 0.29 0.25 31 % 27% Cycle 3 Plugged Tubes 4/91 to 9/92 All S/G's Entire Voltage Range 167 0.62 0.62 1.12 i O 55 100 % 89%I V see < .75 145 0.43 0.65 0.58 151 % 135% (V soe 2 .75 22 0.92 0.42 0.38 ' 46 % 41%
- Cycle da - Plugged Tubes j 9/92 to 10/93 S/G C Entire Voltage Range 128 0.71 0.67 0.852 0.79 94 % 141 %
V noe < .75 71 0.54 0.69 0.81 128% 191 % V noe 2 .75 57 0.92 0.65 0.76 71 % 105% Cycle 4a - AllIndications 9/92 to 10/93 S/G C Entire Voltage Range 428 0.62 0.33 0.852 0.39 53% 79 % Vmoe<.75 315 0.51 0.31 0.36 61 % 91 % V ace 2 .75 113 0.92 0.36 0.42 39% 58 % 9/92 to 10/93 to 3/94 - All 1994 Indications Cycle 4a and 4b S/G C - Cycle 4a Entire Voltage Range 1010 0.5 0.16 0.852 ' 0.19 32 % 48% V see < .75 857 0.42 0.19 0.22 45% 68% V soe 2 .75 153 0.95 0.01 -0.01 1% 2% S/G C - Cycle 4b i Entire Voltage Range 1069 0.66 0.03 0.295 0.10 5% 16% Veoe<.75 737 0.5 0.07 0.24 14% 46% V noe 2 .75 332 1.02 -0.04 -0.14 -4 % 13% l
Table 7-2. Braidwood #1 TSP ODSCC Indications (A1R04) March,1994 Steam Generstor A Steam Generstor S Steam Generator C Steam Generator D Att SesamiGenotetors volts volte Growth Volte volts Growth volte Volte Growth Volts Vetts Growth Volte Volte Growe TSP s Ma n. Ave. volts # Men. Ave. volte s Men. Ave. volts 8 Men. Ave. volts # Men. Ave. volts 1H 0 0 0 0 0 M4 344 4 oo DM 0 17 134 4 25 OM 0 13 Tim 2 3n 0 72 02t 401 a n2 0 82 03 15e0 8 82 0 7n 0 27 SH 236 8 33 0 95 05 - 116 2 75 0 50 0 23 235 2 46 0 62 0 16 180 10 44 0 75 0 26 770 10.44 0.75 0 26 TH 91 2 42 08 0 35 18 1.37 06 0 13 94 2 10 0 64 0 25 77 124 0 56 0.17 280 2.74 0 67 0.26 8H 28 3 46 0 63 0 44 3 0 44 0 41 0 00 20 0 92 0 55 0 24 23 1.59 0.57 0.25 74 3.46 0 86 0.31 9H 3 1 02 0 77 0 37 1 0 39 0 39 0 13 1 0 63 0 63 01 9 0 53 0.43 0.16 14 1.02 0 51 02 10H 2 0 76 0 63 0 22 0 1 0 45 0 45 0 18 1 0 67 0 67 0.43 4 0 76 06 0 26 1fH 0 0 0 1 0.52 0.52 1 0.52 0.52
,c . . m .. .
i Table 7-3 Braidwood Unit 11994 TSP Inspection Summary Soa sio e so c Bonem RPC sto o c Peowenen Gomem RPC Somem RPC Bemem RPC em Estem RPC Smd opdf Sees % Card. 8ed epdf pees % Cent. Smd epW Sees % Cent. Smd spW 8 ens % Cent. Sed opd sees %Cenf. 0 0 0.00 0 0 0.00 0 0.00 0 0.00 0 0.00 0 0.1 1 0.14 0 0.00 0 0.00 0 1 0.00 0 0.00 0 0.00 2 0.07 0 0.00 0.2 0 0.00 0 0.00 5 1.84 0 0.00 7 0.78 1 14.29 3 0.43 0 0.00 21 0.M 0.3 de 7.83 11 22.46 21 9.98 1 4.78 04 64 17.00 22 32.81 51 28J1 4 19.05 51 S.57 13 25.40 31 4,90 $ 18.13 182 8.41 33 21.71 0.8 92 30.03 48 47.83 43 44.12 8 11.78 124 17.28 41 33.08 83 18.88 13 15.88 322 1820 82 25.47 0 20.03 198 32.01 88 43.50 111 32.06 30 34.82 402 32.92 182 40.30 08 92 43.08 98 S8.70 48 81.78 18 33.33 100 47.12 Se 96.83 107 44.27 0.7 88 52.80 de 70.50 27 71.80 SG 52.34 407 47.82 217 S3.32 8 29.83 142 80.53 88 80.58 93 81.87 $1 4 24.00 117 71.58 88 73.50 84 71.47 41 S4.84 330 S0.00 194 98.79 O.8 46 S0.07 28 $7.78 25 00.08 7 30.43 92 80.24 74 90.43 38 78.06 28 73.88 256 80.24 150 82.35 0.9 51 88.29 98.42 41 80.30 23 59.34 1 44 72.52 30 88.38 3 80 44 204 78.71 190 73.53 1 33 2 84 88.31 57 08.08 34 81.84 29 85.29 146 82.02 125 88.21 1.1 34 77.34 25 73.53 8 92.85 5 83 2 41 90.18 31 75 81 1.2 25 80.88 41 87.75 38 87.00 122 88.40 57 79.51 22 88.00 8 N 85 4 88.87 31 93.11 29 93.56 18 90.35 1.3 25 84.42 25 100.00 18 100.00 80 30.42 73 91.25 2 96.S$ 0 0.00 18 94.81 17 94 44 14 02.38 1.4 14 88 40 14 100.00 2 98.32 13 92.88 Se 91.98 SS 83.22 1 S0.00 22 98.88 18 81.82 9 83.88 9 100.00 47 33.30 42 89.38 1.5 11 87.08 10 90.01 0 98.32 0 8 97.84 1.0 0 98.24 7 87.90 $ 94.52 5 83.33 25 94.21 22 88.00 0 100.00 2 97.08 2 100.00 7 98.30 8 85.71 1.7 13 91.08 13 100.00 4 08.10 3 75.00 22 95.02 20 90.91 0 07.08 0 3 98.98 3 100.00 8 96.97 1.4 8 92.21 8 100.00 2 97.79 8 100.0) 22 95.83 22 100.00 2 100.00 3 98.87 3 100.00 3 98 40 2 08.87 1.9 7 93.20 7 100.00 0 07.75 0 18 98.41 15 93.75 3 90.15 3 100.00 4 08 97 4 100.00 14 98.92 2 8 94 06 8 100.00 0 97.79 0 14 100.00 2 90.34 2 100.00 3 97.41 3 100.00 11 97.33 2.1 5 94.78 5 100 00 2 Se $3 1 S0.00 11 100.00 1 99 43 1 100.00 0 97.41 2.2 8 96.80 8 100.00 0 98.53 3 90 72 8 97.82 7 87.50 2.3 3 98.32 3 100.00 4 97.98 4 100.00 15 98.17 15 100.00 3 100.00 0 98.53 0 98.72 0 2.C 1 98 48 1 100.00 1 98.13 1 100.00 4 98.32 4 100.00 l 0 98.53 1 to 81 1 100.00 0 98.13 2.5 4 97.03 4 100 00 1 98 90 1 100.00 2 98.30 2 100.00 1 90 91 1 100.00 1 98.27 1 100.00 2.8 2 97.31 2 100.00 0 98 to 7 98.85 7 100.00 0 98.91 0 1 98 41 1 100.00 3 98.78 2.7 1 97.45 1 100 00 0 98 90 0 90 91 0 3 100.00 - 2.8 0 97.45 0 0 98.41 1 98.79 1 100.00 1 99.28 1 100.00 1 100.00 S0.00 1 98.58 2.0 0 97 45 .0 0 90.28 1 1 100.00 3 08.90 3 100 00 0 100.00 1 98.70 1 100.00 1 98.94 3 3 07.88 3 100 00 0 99.28 0 100.00 1 100.00 3.2 3 98.30 3 100.00 0 98.70 3 90.05 3 100.00 0 99.28 0 100.00 1 98.8$ 3C 2 98 SG 2 100 00 0 90.28 1 100.00 4 90.19 4 100 00 0 100.00 1 98.90 1 100.00 30 3 90.01 3 100 00 0 99.28 0 100.00 3 90.30 3 100.00 ' 38 1 901$ 1 100 00 1 90 83 0 98.99 3 90.41 3 100 00 1 100.00 0 100.00 1 90.14 1 100.00 4 2 99 43 2 100 00 0 99 83 3 99.S2 3 100.00 0 100.00 2 90 42 2 100.00 d2 1 99.58 1 100 00 0 99 83 4 30.87 4 100.00 l 0 100.00 0 90 42 44 0 90.58 0 1 100.00 1 100.00 1 90.71 1 100.00 0 100.00 1 99.57 1 100.00 44 0 Se 58 0 0 100 00 0 100.00 2 99.78 2 100.00 48 0 99.58 0 0 99.S7 0 90 78 0 0 100 00 0 100 00 : S 1 99.72 0 99.S7 0 99.78 0 1 100.00 0 100 00 0 100 00 1 95 0 99 72 0 0 99.57 1 99.82 1 100 00 0 100 00 0 100 00 8 1 99 08 1 100 00 1 99.71 1 100.00 1 99.85 1 100 00 0 100 00 0 100 00 85 0 99 88 0 0 99.71 1 90.89 1 100.00 0 100 00 0 100.00 7 0 99 88 0 0 90.71 0 90.89 0 0 100 00 0 100.00 7.5 0 Se se 0 0 99.71 0 30.89 0 0 100 00 0 100 00 8 0 90 88 0 0 90.71 0 Se Se 0 0 100 00 0 100.00 8$ 1 100 00 1 100 00 0 90.71 0 99 89 0 0 100 00 0 100.00 0 99.71 0 0 100 00 0 0 100 00 0 100.00 1 to 93 1 100 00 95 0 100 00 0 1 99 88 1 100.00 1 99 96 1 100 00 0 100 00 0 100 00 10 0 100 00 0 0 99 88 0 99.98 0 0 100 00 0 100 00 to S 0 100 00 0 0 100 00 0 99 to 0 99 98 0 0 100 00 1 100 00 1 100.00 706 470 2 72 76 1 100 00 1 100 00 1059 641 894 379 2731 7 - 12 I
l Table 7-4. Braidwood Unit 1 10/93 Inspection S/G C Only Elevation Number ofIndications lH 0 3H 346 5H 75 7H 23 8H 2 9H 1 10H I 11H I Note: All Bobbin in:: cations: No RPC Confirmations l CCEM 52 ALS
Table 7-5. Braidwood Unit 19/92 Inspection TSP Indication Distribution in Plugged Tubes Elevation A B C D Total 1H 0 0 0 0 0 3H 32 18 94 49 193 SH 14 5 15 15 49 7H 5 3 5 2 15 9 l centisexts
l 1 i Table 7-6 Braldwood Unit 1 Cumulative Probability Distributions for Voltage Growth (per EFPY) testsoleg2 ? 1982 a; 1953 1952 to 1 sed As ses SC C EdG A WW WC WD m usee Em acts esd eats I cyg sous cod sobs cod Sobs egg schs opp ecos egg 0 4 4 79 60 1402 161 23 SS 75 27.57 250 28.17 100 28.99 702 26 87 0.1 15 13 77 N 27.10 70 34 GS 70 $3 31 187 42 48 91 42 31 404 40 64 0.2 18 23 36 87 42.79 94 48 80 40 70.98 1H $8 01 121 to 03 422 M 10 03 21 35 93 64 S7.71 83 87.94 40 SS 98 157 73.34 M 72.82 348 88 10 04 21 48 S0 de 90.18 SS 08.42 14 91.54 97 0181 80 41.25 231 77 00 0.5 22 81 88 20 73.83 30 72.36 12 96.90 82 88 87 30 86 06 143 82.94 08 12 48 M 24 79 91 32 77.00 2 98 09 30 92.38 at 88 75 to 88 01 07 9 74 25 10 42.24 31 81 82 0 98 SS 32 98 S1 16 92 09 79 40 91 00 10 to24 14 45 61 23 85 00 0 98.00 18 97.07 12 03 to S1 92 25 09 8 43 83 14 88.79 21 88 09 1 97.00 8 97.00 9 M 17 37 94 03 1 3 45 $3 7 90A2 18 80 de 1 97.43 8 98 44 6 96 06 31 9514 11 4 43 22 5 91 90 17 92 94 1 97.70 5 08 03 0 98 93 29 96 48 1.2 6 ,92 22 7 93.22 4 93 82 0 97.79 2 90 12 4 97.S1 12 97 11 13 4 64 81 4 94 18 8 M 71 1 98 18 2 90 32 3 97.06 12 97 S9 14 1 M 21 1 95 33 4 95 29 1 98 53 3 90 81 0 97 95 8 07 77 1.5 1 M 81 3 98 03 4 95 M 0 98 83 1 99 71 2 M 24 7 M it 18 0 95 81 3 86 73 3 98 32 1 90 00 0 99 71 0 98 24 4 H 33 17 0 M 41 1 98 00 3 98 70 0 98 90 1 90 00 1 M 30 $ H $2 it 0 M 81 3 97.96 3 07.21 1 90 20 1 99 90 0 88 30 $ SS N 19 1 M 41 1 97.90 1 97.35 0 90 20 0 90 00 2 90 04 3 M 81 2 3 M 20 2 98 38 4 07 94 0 90 26 0 90 90 0 M SS 4 98 M 21 0 M 20 C 98 38 0 97 94 0 90 20 0 90 00 0 M SS 0 90 00 2.2 0 M 20 1 88 00 2 98 24 0 90 26 1 100 00 0 Se tt 3 99 07 23 0 M 20 0 90 00 1 98 38 1 90 83 0 100 00 2 88 00 4 99 22 24 0 M 20 C 90 00 2 98 8J 0 98 83 0 100 00 0 08 00 '2 99 30 25 1 N 00 C 94 40 1 98 82 0 90 63 0 100 00 0 98 08 i 90 37 28 0 St 80 C 90 00 0 ' 98 02 0 90 83 0 100 00 0 94 98 0 99 37 27 0 M 80 2 90 07 2 99 12 0 90 83 0 100 00 1 00 12 3 99 48 9 20 0 96 80 C. 90 07 0 9012 0 90 83 0 100 00 0 00 12 0 99 52 29 0 M 40 1! 99 30 0 99 12 0 99 83 0 100 00 1 9027 1 99 55 3 0 M ed 90 30 2 99 41 0 99 83 0 100 00 0 90 27 2 99 C3 32 0 91 80 Cl' i 99 53 1 99 58 0 99 83 0 100 00 1 99 41 2 99 70 34 0 N &* 0l 99 53 0 99 S8 1 100 00 0 100 00 1 DO SS 2 99 78 38 0 N 80 il 99 77 0 99 $8 0 100 00 0 100 00 0 99 98 0 99 78 38 0 98 80 C 90 77 0 00 $8 0 100 00 0 100 00 1 99 71 1 99 81 4 1 99 40 C; te n 0 90 $e 0 100 00 0 100 00 0 99 71 0 99 81 42 0 M dC 99 77 1 99 71 0 100 00 0 100 00 0 99 71 1 99 45 44 0 99 dC Cl'100 00 i 1 90 05 0 100 00 0 100 00 0 99 71 1 99 89 48 1 10C:C C' 100 00 0 90 45 0 100.00 0 100 00 0 99 71 0 99 89 de 0 10C X C' 100 00 0 00 0$ 0 100 00 0 100 00 0 99 71 0 99 49 5 0 10C :C C; 100 00 0 99 95 0 100 00 0 100 00 0 99 71 0 99 89 55 0 10C00 C. 100 00 0 99 05 0 100 00 0 100 00 0 99 71 0 99 89 6 0 10C:C C' 100 00 1 100 00 0 100 00 0 100 00 0 99 71 1 99 93 SS 0 10C X C 100 00 0 100 00 0 100 00 0 100 00 0 99 71 0 99 93 7 0 10C X C' 100 00 0 100 00 0 100 00 0 100 00 0 99 71 0 99 93 75 0 10C CC C. 100 00 0 100 00 0 100 00 0 100 00 1 90 0S 1 99 M 0 0 10C0C C 100 00 0 100 00 0 100 00 0 100 00 0 90 $$ 0 99 M 85 0 10C :C C 100 00 0 100 00 0 100 00 0 100 00 0 90 8S 0 99 M 9 0 10:CC C 100 00 0 100 00 0 100 00 0 100 00 1 100 00 1 100 00 95 0 10C lC C 900 00 0 100 00 0 100 00 0 100 00 0 100 00 0 100 00 10 0 10:X C 100 00 0 100 00 .0 100 00 0 100 00 0 100 00 0 100OC 10 5 0 90: X C '00 00 0 100 00 0 100 00 0 100 00 0 10300 0 10000 l
, l 1
Table 7-7. Braidwood Unit 1 Summary of Largest Bobbin Voltage Growth Rates for Cycle 4 Tube EOC4 SignalSize Boc4 S/G Row Col Elevation Bobbin RPC Bobbin Growth New Ind. D 37 34 5H 10.44 8.62 0.68 9.76 Yes D 23 12 3H 8.82 8.78 0.76 8.06 Yes A 45 415H 8.33 8.25 1.66 6.67 Yes A 18 23 5H 5.54 6.72 0.50 5.04 Yes A 27 43 3H 4.99 4.82 0.32 4.67 Yes D 12 9 3H 5.02 4.01 0.76 4.26 Yes D 11 9 3H 4.28 5.16 0.39 3.89 Yes B 7 9 3H 4.25 4.13 0.55 3.70 Yes D 19 7 3H 3.95 3.79 0.29 3.66 Yes A 6 91 SH 4.18 2.01 0.68 3.50 DSI 0.52V No RPC Conf. A 8 60 3H 3.91 3.29 0.47 3.44 Yes A 29 88 3H 3.91 1.55 0.49 3.42 Yes D 35 29 3H 3.62 1.21 0.32 3.30 Yes A 6 19 8H 3.46 3.05 0.41 3.05 Yes A 43 35 5H 3.52 3.53 0.49 3.03 Yes D 33 20 3H 3.83 3.68 0.80 3.03 A 3 13 SH DSI 0.73V No RPC Conf. 3.30 0.9 0.49 2.81 Yes A 37 88 3H 2.99 3.35 0.27 2.72 Yes A 30 24 5H 2.93 2.02 0.28 2.65 Yes B 15 88 3H 3.62 5.64 1.00 2.62 Yes A 42 44 3H 3.73 3.11 1.13 2.60 Yes D 11 12 3H 3.21 3.41 0.63 2.58 Yes D 16 42 3H 3.12 3.43 0.54 2.58 Yes A 45 55 3H 3.02 2.79 0.59 2.43 Yes A 33 75 3H 3.04 3.08 0.63 A 2.41 Yes 32 85 3H 2.46 1.62 0.21 2.25 Yes A 42 54 SH 2.56 2.31 0.34 2.22 Yes
.A 47 75 5H 3.44 0.4 1.23 2.21 Yes A 35 42 3H 2.96 3.07 0.76 2.2 Yes D 2 105 3H 2.84 2.32 0.67 2.17 Yes D 32 27 SH 248 2.52 0.36 2.12 Yes A 45 26 7H 2.42 2.32 0.34 2.08 Yes A 4 12 5H 3.06 3.19 1.01 2.05 Yes A 4 16 3H 3.23 2.08 1.18 2.05 Yes A 10 67 SH 2.48 1.56 0.43 2.05 Yes C 20 24 3H 2.38 1.56 0.35 2.03 Yes CCEWSCAS
1 Table 7-8 Braidwood Unit 1 A1RO4 Pulled Tube EC Results Tube I.D. Bobbin Bobbin RPC RPC Voltage Voltage Call Call SG A 1 R27C43 lH l ,- NDD NDD - 3H l 4.88 85 % SAI 5.28 SH l - NDD NDD - R42C44 1H l - NDD NDD - 3H l 3.73 68% MAI 3.24 max. l SH l 2.09 49% SAI 1,62 l 7H l - NDD ,NDD - SG D ' I { R37C34 lH l - NDD NDD - 3H l 1.04 92% SAI ' 0.31 SH l 10 44 82 % SAI 8.77 R16C42 lH l NDD NDD l 3H 3.12 70% MAI l 1.70 max SH 0.61
- NDD NDD l -
{
- Indication not reported in fie'd inspection I
7 17 e
Figure 7-1 Braidwood Unit 1 Number of Indications as Function of Elevation 800 700 -- - i l 600 - E 500 e g C D S/G A agg _
~
0 G S/G B E S/G C E e E S/G D j 300 - 200 l e
} F d ,
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l Numb:rcf observati:ns
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-::::::::::;...::::::::::::::::::: 100 60 90 .
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Figure 7-19 i ~ Braidwood Unit 1 . Cycle 2 120 Reactor Power Level I 100 .. y f.j w , y gr 9 r ~~ y-80 l lg f Ei ! ~ g 60 ;
- n. l r 40 !
\ l \
j 20 l j 3 O ' ' ' 8 i i 28-Nov-89 28-Mar-90 5 ' 26-Jul-90 27-Jan-90 27-May-90 23-Nov-90 24-Sep-90 Date 22-Jan-91 Power, %
~
l l M
Figure 7-20 Braidwood Unit 1 - Cycle 3 Reactor Power Level ' 120 --- - 100 qp A , ,7(gj ,ff ,i y g 7-]fyyp(vy 3 {3 \ rT ! r-80 l i l' g '
)
g 60 i 1 40 - 20 l . 0 ' - ! 03-Mar-91 03-Jul-91 02-Nov-91 03-Mar-92 03-Jul-92 02-Nov-92 l Date i Power, %
]
Figure 7-21 Braidwood Unit 1 - Cycle 4 Reactor Power Level 120 l l ..........__. 100
\l \q ,
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Figure 7-21 I Braidwood Unit 1 Cycle 2 Sodium to Chloride Molar Ratio 5; ' '
! i 4l l i i
~
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'1 28-Nov-89 27-Jan-90 28-Mar-90 27-May-90 26-Jul-90 24-Sep-90 23-Nov-90 22-Jan-91 Date
Figure 7-23 Braidwood Unit 1 - Cycle 3 1 _ SG Blowdown Sodium to Chloride. Molar Ratio 5 -
-g p '
j
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0 ' ' 03-Mar-91 ' 03-Jul-91 02-Nov-91 03-Mar-92 03-Jul-92 Date 02-Nov-92 O
O
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Figure 7-24 Braidwood Unit 1 - Cycle 4 SG Blowdown Sodium to Chloride Molar Ratio 5 - - 4
.a :
y3 Ni j D ' 2 ) f ) U 2
'iB Z h .
h I d 0 ' ' ' ' ' -- ------1 23-Oct-92 22-Nov-92 22-Dec-92 21-Jan-93 20-Feb-93 22-Mar-93 21-Apr-93 21-May-93 Date
l ! Figure 7-25 i i Braidwood Unit 1 - Cycle 2 i \ SG Blowdown Sodium & Chloride 10 es . . , , ..t v.
. --.----..e
.. .s
- s 8 .
.. s .
. . s . .
s ,. . .
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-- i 24-Sep-90 23-Nov-90 Date 22-Jan-91
' ~ ~
- Sodium. ppb
-- Chiofide[ ppd
Figure 7-26 Braidwood Unit 1 - Cycle 3 SG Blowdown Sodium & Chloride i 10 y ,. - i p i 8 : i 1 ; ,
' 9 i; :
o 6i I ll iJ .i j g
- fi :;. 1 E !
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i s Figure 7-27 { 1 Braidwood Unit 1 - Cycle 4 SG Bknvdown Sodom & Chionde 10 T i I 6 '. o
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a .: .
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23-Od-92 22-Nov-92 22-Dec-92 -- l ' 21-Jan-93 20-Feb-93 22-Mar-93 21-Apr-93 21-May-93 Date L Sodium, ppb -- chsonde, ppb l
l Figure 7-28 BrAchaeodthat 1 SGNaCRatio am am a , . E as i .
.g .. p.............._..............
5 am i f f ' y Q am -
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0 6, this me becomes very conservative for the BOC distnbution as it leaves 0.7 indication in service fo each indication found in the inspection, independent of the voltage level. 8.% IPC Repair Criteria Implemented at Braidwood-l This section describes the IPC implemented at the Cycle 4 refuel outage (EOC 4) and t inspection / analysis performed to support the IPC. Braidwood-1 Interim Pluneine Criteria The implementation of the IPC at Braidwood-l for ODSCC at TSPs can be summarized as follows:
- Tube Pluccine Cnteria Tubes with bobbin flaw indications exceedmg the 1.0 volt IPC voltage repair limit and
$2.7 volts are plugged or repaired if confirmed as flaw indications by RPC inspection. Bobbin flaw indications >2.7 volts attributable to ODSCC are repaired or plugged independent of RPC confirmation - + Operating Leakage Limi13 Plant shutdown will be implemented if normal operating leakage exceeds 150 gpd pe SG + SLILLeakage.Cptenon Predicted end of cycle SLB leak rates from tubes left in service, includmg a POD = 0 6 adjustment and allowances for NDE uncertainties and ODSCC growth rates, must be less than 9.1 gpm for the S/G in the faulted loop.
- Exclusions fam. Tube Pluccinn Cntena Certain tube locations, as identified in Section 4 of this report, are excluded from application of the IPC repair limits. The analyses indicate that these tubes may potentially deform or collapse following a postulated LOCA + SSE event 82 l
1 \ l l Braidwood-l EOC-4 Inscection . Eddy current analysis guidelines and voltage normalization consistent with the EPRI ISI guidelines and with prior IPC applications (typical of Appendix A for prior Westinghouse IPC WCAPs such as WCAP 13854). Eddy current analysts were trained specifically to voltage sizing per the analysis guidelines and 52% of the analysts were qualified to the industry standard Qualified Data Analysis program.
- Use of ASME calibration standards cross-calibrated to the reference laboratory standard and use of a probe wear standard requiring probe replacement at a voltage change of 15% from that found for the new probe.
a 100% bobbin coil, full length mspection of all active tubes with a 0 610 inch diameter bobbin probe for all straight length tubing a RPC inspection of all bobbin indications greater than the 1.0 volt repair limit (actual implemented was all bobbin indications). RPC inspections were performed with a 0 620 inch diameter,3 coil motorized RPC probe.
- RPC sample inspection of more than 100 TSP intersections with dents (at Braidwood 1, these are typically mechanically induced "dmgs") or artifact / residual signals that could potentially mask a 1.0 volt bobbin signal. Any RPC flaw indications in this sample will be plugged or repaired The NRC will be informed, prior to plant restart from the refueling outage, of any unexpected inspecuon findmgs relative to the assumed characteristics of the flaws at the TSP intersections. This includes any detectable circumferential indicanons or detectable indications extending outside the thickness of the TSP.
The IPC evaluations given in this report are based on the inspection results implementing the above guidelines and the 1.0 volt IPC repair limit. 8.3 Operatmg Leakage Limit Regulatory Guide 1.121 acceptance criteria for establishing operating leakage limits are based on leak.before break (LBB) considerations such that plant shutdown is ininated if the leakage associated with the longest permissible crack is exceeded The longest permissible crack length is the length that provides a factor of safety of 143 against burst at SLB conditions 8-3 since a factor of 3 against bursting at normal operating pressure differential is satisfied by the TSP constraint at normal operation. As noted previously, a vcitage amplitude of 4.54 volts for tvpical ODSCC cracks corresponds to meeting this tube burst requirement at the lower 95% pre &ction interval on the burst correlation. Alternate crack morphologies could correspond to 4.54 volts so that a unique crack length is not denned by the burst pressure to. voltage correlation. Consequently, typical burst pressure versus throughwall crack length correlations are used below to define the " longest permissible crack" for evaluating operating leakage limits. The CRACKFLO leakage model has been developed for single axial cracks and compared with leak rate test results from pulled tube and laboratory specimens. Fatigue crack and SCC leakage data have been used to compare pre &cted and measured leak rates Generally good agreement is obtained between calculation and measurement with the spread of the data being somewhat greater for SCC cracks than for fatigue cracks. Figure 81 shows normal operation leak rates inclu&ng uncertainties as a function of crack length. The throughwall crack lengths resultmg in tube burst at 1.43 times SLB pressure 6fferentials (3657 psi) and SLB con &tions (2560 psi) are about 0.51 and 0.75 inch, respectively, as shown in Figure 6-2. Nominal leakage at normal operating conditions for these crack lengths would range from about 0.24 to ~5 gpm while 95% confidence level leak rates would range from about 0 04 to 0.5 gpm. Leak rate hmits at the lower a ran ;e near 0 04 gpm would cause undue restrictions on plant operation and result in unnecessary plant outages, ra&ation exposure and cost of repair.- In addition, it is not feasible to satisfy LDB for all tubes by reducing the leak rate hmit. Crevice deposits, the presence of small ligaments and irregular fracture faces can, in some cases, reduce leak rates such that LDB cannot be satis 6ed for all tubes by lowering leak rate hmits t An operating leak rate of 150 gpd (-0.1 gpm) is implemented in conjunction with application of the tube pluggmg criteria As show in Figure 81 this leakage limit provides for detection i of rates 0 4 inch cracks at nominal leak rates and 0.6 inch cracks at the 95% confidenc Thus, the 150 gpd limit provides for plant shutdom pnor to reaching entical crack lengths for SLB con &tions (2560 psi) at leak rates less than a 95% confidence level and for 143 times SLB pressure &fferentials at less than nominalleak rates. The tube pluggmg hmits coupled with 100% inspection at affected TSP locations provide the principal protection agamst tube rupture. Consistent with a defense in depth approach, the 150 gpd leakage limit provides further protection agamst tube rupture. In addition the 150 gpd hmit provides the capabihty for detectmg a crack that might grow at greater than expected rates and thus provides additional margin against exceedmg SLB leakage hmits. 84 I i i i [V. W, . 8.4 Projected EOC-5 Voltage Distubutions ^ The BOC-5 voltage distributions are obtained by applying the draft NUREG 1477 POD = 0.6 i adjustment to all indicanons found in the EOC-4 inspection and subtracting the repaired indications. Data to develop the BOC-5 bobbin voltage distributions are given in Table 7.3. !' Monte Carlo analyses are then applied to develop the EOC-5 voltage distributions from the BOC distributions. The BOC voltages are increased by allowances for NDE uncertainties (Section 5.3) and voltage growth (Section 7.3) to obtain the EOC values. In the Monte Carlo analyses, each voltage bin of the BOC distributions (Figure 8-2 for S/G D, for example) is! increased by a random sample of the NDE uncertainty and growth distributions to obtain a EOC voltage sample. Each sample is weighted by the number ofindications in the voltage bin The sampling process is repeated 100,000 times for each BOC voltage bin and then repeated for each voltage bin of the voltage distribution. Since the Monte Carlo analyses yield a cumulative probability distribution of EOC voltages, a method must be defined to obtain a discrete maximum EOC voltage value. De method adopted in this report is to integrate the tail of the Monte Carlo distribution over the largest 1/3 of an indication to defin; a discrete value with an occurrence of 0.33 indication. ror N indications in the distribution this is equivalent to evaluating the cumulative probability of voltages at a probability of (N-0.33)/N. He largest voltages for all distributions developed by Monte Carlo in this rep have been obtained with this dermition for the maximum EOC discrete voltage. The next largest discrete EOC voltage indication is obtained by integrating the ta;! of the Monte Carlo distribution to one indication and assigning the occurrence of 0.67 indica' ion. This proces for developing the largest EOC voltage indications provides appropriate emphasis to . voltage tail of the distribution and permits discrete EOC voltages for deterministic tube integrity analyses. As described in Section 8.5 below, S/G D is the most limiting S/G for SLB leakage analysei and has been evaluated using final Braidwood-l inspection results and tube plugging data. The Cycle 4 voltage growth distribution of Table 7.6 for S/G D has been used to obtain the EOC voltages by Monte Carlo analyses as described above. The resulting BOC-5 and EOC 5 bobbin voltage distributions are shown in Figure 8 2. Based on applying the POD adjustment, the largest BOC voltage indication left in service is 0.7 indication at 10.4 volts. At EOC-5, the largest voltage indication is projected to be 11.2 volts. The EOC 5 distribution of Figure 8-1 is used for the S/G D SLB leakage analyses in Section 8.5 As shown in Table 7.3, the number ofindications found at EOC-4 in S/G B was 277 compared to 741 in S/G A,1062 in S/G C and 696 in S/G D. It is clear that S/G B is not limatmg for tube integrity considerauons and this S/C was not analyzed to obtain EOC ' distributions or leak rates. S/Gs A and C were analyzed using preliminary inspection results and growth rate data which have not had large changes in the final data. The voltage growth distribution for S/G A was applied in the Monte Carlo analyses for both S/Gs A and C. The 8-5 9 l 1 [ p e ? , o> % p> S/G C Cycle 4 growth distribution may have been influenced by tube repairs made in the October,1993 unplanned outage and thus could be an underestimate of the growth distribution. It is conservative to apply the S/G A growth distribution for S/G C since it has the largest Cycle 4 growth rates. Figures 8-3 and 8 4 show the BOC and EOC 5 voltage distributions obtained from the preliminary data. For S/G A, the largest POD adjusted BOC voltage is 8.33 volts and the largest projected EOC-5 voltage is 9.0 volts. For S/G C, the largest POD a4usted BOC voltage is 2.73 volts and the largest projected EOC-5 voltage is 7.2 volts. . ' 8.5 SLB Leakage Analyses This section summarizes the results of the projected EOC-5 SLB leak rate analyses applying the EPRI correlations for probability of leakage (POL) and the SLB leak rate versus voltage conelation. The EPRI methodology applies the 'og logistic form for the POL correlation and the leak rate results are given in Section 8.5.1 as the reference SLB leak rate. The NRC has requested leak rate results to be provided also for the log normal, log Cauchy, logistic, normal and Cauchy POL distributions and the results are also given in Section 8 5.2. The POL and leak rate correlations used for these analyses are described in Sections 6.4 and 6.5, respectively, ne SLB leak rate analysis methodology for applying the probability ofleakage and leak rate versus voltage correlations is described in Sections 6 6 to 6.8. SLB leak rates are provided at the upper, one-sided confidence of 95% based on the NRC guidance of the February 8,1994 NRC4ndustry meeting on resolution of draft NUREG 1477 comments. The EOC 5 voltage distributions have been descrit,ed above. SLB leak rate analyses were performed for S/Gs A, C and D using preliminary voltage indication, voltage growth and tube plugging distributions. As noted above, S/G B has fewer indications than the other S/Gs and is not a candidate for the limiting S/G for leakage considerations. The prelL,tinary leak rate analyses showed that S/G D had the highest projected EOC 5 SLB leak rate. He leak rate for S/G A was about half of that for S/G D and S/G C was only about one-third of the S/G D leak rate. Thus S/G D is the limiting S/G for SLB leakage analyses and the results for this generator are given in Section 8.5.1 for the reference EPRI methodology and in Section 8.5.2 for sensitivity to the attemate POL correlations 8.5.1 Reference SLB Leakage Analyses (Log logistic POL) The projected EOC 5 SLB leak rate for the limiting S/G D, as obtained with the reference EPRI correlations of Section 6,is 3.1 gpm. His leak rate is less than the allowable SLB leak of 9.1 gpm developed in Section 4.8 and thus is acceptable for the Braidwood-l IPC application. Table 81 provides details of the leak rate calculation. He column titled N.i 8-6 l provides the projected EOC-5 voltage distribution including the POD = 0.6 adjustment. He P.i and Q.i columns represent the POL and expected leak rate for each voltage bin. The remaining columns provide data for the upper bound confidence of 95% applied to the leak rate. Application of the POD adjustment to the EOC-4 voltage distribution leads to large voltage indications postulated to have been missed in the inspection and left in service at BOC 5. With the 1.0 volt repair hmit and only RPC NDD indications above 1.0 volt left in service, the expected SLB leakage at BOC-5 would be about zero The influence of the POD adjustment on predicted leakage values can be estimated by calculatmg the leak rate for the BOC-5 voltage distribution. De resulting SLB leak rate for S/G D at BOC-5 is 1.7 gpm compared to the expected near zero value. De leak rate thus increases only from 1.7 gpm at BOC to 3.1 gpm at EOC. Thus growth to the EOC only increases the SLB leak rate by about 1.4 gpm which would be near the projected leak rate assuming a POD of about 1.0. 8.5.2 SLB Leak Rate Sensanvity to POL Correlations ne NRC has requested that the projected EOC 5 SLB leak rate be provided for all six POL correlations 6scussed in draft NUREG-1477. These results provide sensinvity estimates to the form of the POL correlanon. As discussed in Section 6.4, the linear and log Cauchy distributions are iot consistent with the pulled tube database for low voltage (< 2.0 volt) probability of leakage and are not recommended for consideration as acceptable POL correlations. The esumated BOC 5 and EOC-5 SLB leak rates for all six POL correlations are given in Table 8-2. He results for the reference log logistic POL correlation have been desenbed above and are repeated in Table 8 2. It is se'en from Table B 2 that the SLB leak rates are essentially independent of the POL conelation applied to obtain the leak rates. The low leak rates for indications below I to 2 volts tend to offset the effects of the 6fferences in POL correlations. As seen in Table 8-1 for the column utled N.i'P.i'Qi, which gives the expected leak rate, the SLB leak rates are dommated by EOC in6 cations above about 3 volts even though only a small fracnon of the EOC indications are in this voltage range. 86 Assessments of SLB Burst Margms and Probability of Burst 8.6.1 Deterministic Burst Margin Assessments Although the technical support for the Braidwood l IPC is based on tube burst for limited TSP 6splacement, significant margins exist fer free span burst considerations for voltage growth in excess of 95% cumulative probabihty. Limited TSP displacement considerations 8-7 , o l l ) are necessary to accommodate only the largest few growth rates. A deterrainistic assessment of margins against assumed free span burst is given in Table 8-3. For the largest RPC confirmed indications of 1.0 volt left in service, the projected EOC-5 voltage at 95% growth ! is 2.8 volts compared to the 4.54 volts structural limit for free span burst at 1.43 x AP,w As ! shown in Table B-3, a burst margin in excess of one volt exists even for the largest unconfirmed bobbin indication left in service. Even at 99% cumulative probability, the 1 voltage growth is bounded by 2.7 volts (S/Gs A, D - Table 7.6) and the structural limit is satisfied for the 1.0 volt RPC confirmed indications left in service. Thus the evaluation , tube burst with limited TSP displacement is applied to accommodate only the largest 1% of ' the voltage growth distribution. As shown in Section 4. Table 4.5.1, TSP displacements for an SLB at normal operating conditions are small for most plates and bounded by a maximum TSP displacement of 0.45 inch. Only about 40 TSP intersections at the tubelane comers of the 7th TSP are subject to TSP displac'ements exceeding 0.35". As shown in Section 6, Figure 6 2, a throughwall crack length of about 0.51 inch (lower tolerance limit material properties LTL) corresponds to a ouru upability of 1.43 x APm = 3660 psi. Thus, for an SLB at normal operating conditions, the maximum exposed potential throughwall crack length of 0 45 inch is less than the RG.1.121 structural hmit of 0.51 inch. It is shown in Section 8.6.4 that this corresponds to an extremely low probability of burst. It can also be noted from Figure 6-2, that the free span throughwall crack length for burst at SLB conditions of 2560 psi i.t about 0.75 inch. Thus a free span throughwall crack the length of the TSP thickness is trquired for burst at SLB conditions. The exposed crack lengths associated with the maximum TSP displacements exceed the R G 1.121 structural limit of 0.51 inch only for a small number of TSP intersections for the conservative SLB at hot standby conditions. The remainder of this section emphasizes the probability of a SLB tube burst at hot standby conditions resulting from a potentially large indication at the TSP intersections where displacements are large. B 6.2 Method of Analysis for SLB Tube Burst Probability Assessment of the tube burst probabihty at SLB conditions for limited TSP displacement requires an estimate of the probability of a large indication occuring at the corners of tne TSP where the TSP 6splacements are significant Only plates 3 and 7 f. ave significant TSP displacements such that a burst assessment is appropriate. Although the flow distribution baffle (FDB, plate 1) has a few TSP intersections with significant displacements, no bobbin indications have been found at the FDB. The FDB in the Model D4 S/Gs has large tube to FDB gaps (nominally 100 mils diametral clearance toward the center of the plate ard 88 mils with radiahzed holes for the outer region). Thus there is a significantly lower likel. hood of 8B i i I l i 1 \ packed crevices with associated tube corrosion at the FDB intersections. Since no Braidwood-l indications at the FDB have been found, the FDB is not induded in the tube burst assessment. The projected EOC.5 voltage distributions of Secuon 8 4 above are total indications independent of TSP elevation and tube location. The EOC-4 inspection results can be used to develop the distribution ofindications between TSP clevations and the fraction ofin& cations occuring at tube locations where the TSP 6splacements are significant. TSP displacements as a function of tube location were developed from the analyses described in Section 4 and the number of tube locations as a function of displacement are summarized in Table 4.5.3. Table 8-4 provides the inspection results for S/Gs A, C and D as a function of TSP elevation and TSP displacement. S/G B is not included due to the smaller number of indicanons found in this S/G De table includes the fraction, Fo, ofindications found as a funcuon of . displacement. Also given in the table are the number and fractions ofindications for a ! uniform distribution of all tube intersections. Only 9 indications on plate 7 have been found in all S/Gs at tube locations having &splacements large enough (greater than about 0 6 inch) l to significantly influence the tube burst probability. The largest bobbin voltage for any of these 9 indications was 1.24 volts and the largest indication found anywhere on plate 7 was 2.74 volts Rese indications would have a high burst pressure even as free span indications i Thus, the inspection results indicate a low frequency ofindications and low voltages at tube locations subject to significant SLB TSP displacements. ) I The data of Table 8-4 can be used to dejine bounding distributions for indications as a function of TSP elevation and displacement The highest fraction ofindications at TSPs 3 I and 7 were 67% at TSP 3 in S/G C and 13% at TSP 7 in S/G A These values are used for the fraction of total indications at these TSP elevations He bounding distribution for the { i fraction of indications on the TSP as a function of TSP displacement is obtained as the larger ' found by inspection or the uniform distribunon, ne resulting boun&ng distributions for plates 3 and 7 are given in Table 8-4. Also given is the weighted sum for the fraction of TSP ) mdications as a function of displacement. This is obtained as the sum of the individual plate ' fractions multiplied by the fraction ofindications for the TSP elevation. This weighted sum ; of the boundmg &stributions is applied in the tube burst probability analyses as described below. j 1 The number of in& cations as a function of TSP &splacement can be obtamed as the product of the total number ofin& cations times the boundmg fractional distribution of Table 8 4. This product can be obtained as a function of bobbm voltage by applying the number of in& cations in each voltage bin The voltage bms and the number of EOC-5 indications in . each voltage bin are shown in Figure 8 2 and Table S 1 for S/G D, the most limmng S/G Conservatively assummg that the TSP d spiacements expose throughwall cracks, the 8-9 t probability of tube burst as a function of exposed crack length is given by the upper curve in Figure 6 3. The probability of tube burst (PRB) can then be obtained as: l PRB =[ PRB, =[ NY, f0.67 [ Fl,PRB o ,+ 0.13 o[ Fl,PRB (,8.1) i e s ) J PRB =[ NY, [{0.67 Fl,+0.13Fl} PRBo , (8.2) , i ) where i = i* witage bin j = j* 7SP displacement bin NY, = Number ofindications in the l' voltage bin Fl,,Fl, = Fraction ofindications at plates 3 and 7 havmg 75P displacement in bin J PRBo, = The smaller burst probability of either:
- PRB(V,) = Probability of burstfor afree span indication of voltage V,
- PRB(D,) = Prob. of burstfor throughm!! crack length equal to 75P disp. D, PRB, = Probability of burstfor the l* voltage bin The term in parentheses in Equation 2 is the weighted sum for the bounding distribution given in Table 8 4. Equation 2 is applied in Section 8.6.5 to estimate the burst probability at EOC-5.
1 8 - 10 i s.6.3 SLB Burst Probability for S/G D at EOC-4 The burst probability for S/G D at EOC-4 with limited TSP displacement can be obtained &rectly from the indications found and the TSP displacement at each specific indication. This application demonstrates the general methodology for the lir,.ied TSP displacement, burst probabilities without the need for distributing the indications as described in Section 8.6.2 above. Table 8 5 identifies the indications found in the inspection for the larger voltage indications and for indications at locations having the largest TSP displacements in the hot standby SLB event. The bobbin voltage and free span burst probability at the given voltage level are provided for each indication. Also given in the table are the local TSP e- displacement and the burst probability for a throughwall crack length equal to the TSP displacement (conservatively assumed exposed throughwall crack length) The applicable SLB burst probab3ity column shows the lower of the free span or throughwall burst probability for ese indication. The lower of the two burst probabilities is the appropriate value since the limiteo TSP 6splacement can reduce the free span burst probability but the free span probability camot be exceeded. The throughwall burst probability can exceed the free span value only because it is conservatively calculated for a throughwall crack while the free span value, based on bobbin voltage, is more realistically based on the actual crack morphology as reflected in the voltage amphtude. For the S/G D in& cations given in Table 8 5, the total burst probability calculated assuming free span (very large SLB TSP displacements) con &tions is 3.7 x 10'8 Accounting for the , hmited SLB TSP displacements at the locations of the indications, the total burst probability l is 1.7 x 104 Thus the limited TSP displacements reduce the burst probability by three orders j of magnitude It can be noted that none of the high voltage indications occurred at locations ; of high TSP &splacement and the TSP constramt reduces the burst probability for these high voltage in& cations to approximately zero. Only the small voltage indications found at the s corners of plate 7, where SLB &splacements are significant, contribute to the burst probability. The results of Table 8-5 show the effectiveness oflimited TSP esplacements in reducing the tube burst probability to small values and also show that Braidwood l had an acceptably low burst probability at EOC-4. l 8.6.4 Conservative Burst Probabihty for SLB at Normal Operstmg Conditions I For a SLB at normal operating conditions, it is shown in Section 4, Table 4.5.1 that TSP displacements are small and significantly less than that for an SLB at hot standby conditions. The ma'ximum TSP &splacement occurs for pla:e J and is hmited to 0 438 inch The maximum &splacements for all other plates are < 0.2 inch. An extremely conservative or bounding burst probabihty for this event can be obtained by assuming that the SLB B 11 ; 1 t l displacements expose a throughwall crack equal to the displacements at every TSP intersection on all seven bot leg TSPs above the FDB. He FD9 is excluded from the analysis as no indications have been found at this plate and the larger tube to TSP gap at the FDB would require supplemental burst tests to determine the intluence of the FDB constraint on the burst pressure. He throughwall crack assumption is approximately equivalent to assuming that a throughwall crack equal to the TSP thickness is present at every hot leg TSP ( intersecnon. i Table 8-6 summarizes the bounding analysis for the burst probability resulting from an SLB at normal operating conditions. He maximum TSP displacement column represents the l maximum displacement at any location on the plate except for plate 7 which is divided into three displacement magnitudes to permit separation of the number of TSP intersections subject to the larger TSP displacements. The number and maximum voltages for EOC-4 indications found at each plate are given in the table for general information. He number of tubes column represents' the number of TSP intersections with the maximum displacement of column 2, The exposed length burst probability is that associated with a throughwall crack length equal to the maximum TSP displacement. De last column provides the burst probability obtained by multiplying the exposed length probability by the number of tubes The total S/G burst probability for this conservative assumption of throughwall indications at each hot leg TSP intersection is < 5 x 10' This very low probability bounds all realistic potential indications at the TSP intersections.and demonstrates the effectiveness of modest TSP displacements under the SLB at normal operating conditions. As noted in Section 8.6 below, normal operating conditions dominate the operating time and the highest frequency an SLB event occurs at power conUms where the SLB loads on the TSPs and associated displacements are lower than for ao n,B at hot standby conditions. B.6.5 Burst Probabihty for a SLB at Hot Standby Conditions For Cycle 5 SLB leakage and bu st considerations, S/G D is the most limitinC and the projected EOC 5 voltage distribwion is given in Figure 8 2, The tube burst probability for S/G D at EOC 5, assuming an SLB at hot standby conditions, is evaluated in this section. The methodology of Equatica 8.2 given in Section B 6.2 is applied for this assessment. The total EOC 5 voltage distribuaon of Figure 8-2 is distnbuted as a function of TSP displacement usmg the weighted sum of the bounding distnbution of Table 8-4. Free span burst probabihties as a function of voltage are developed from the burst pressure versus bobbin voltage correlation of Section 6.1 and burst probabilities for exposed throughwall cracks are given in Figure 6-3. 1 The results of the burst probabihty analysis are summarized in Table 8 7. For each voltage bin of the projected EOC 5 voltage distribution (meluding POD = 0 6 adjustment), the number 8 - 12 ofindications, free span burst probability, the distribution ofindications and throughwall burst probability as a function of the SLB TSP displacement are given in Table 8 7. By applying Equation 2, the net probability of burst for each voltage level is obtained as given in the last column d of the table. The total limited TSP displacement burst probability is obtained as 8 = 10 . The influence of the limited TSP displacement can be seen by comparison with the estimated free span burst probability (column 3) of 9 = 10'8 The latter free span result is dominated by the large projected EOC-5 voltage indications up to 11.2 volts which are traceable to applying the POD adjustment to all indications found in the last inspection prior to reducing the population for tubes repaired at EOC-4. The estimated SLB tube burst probability of 8 m lod is significantly less than the acceptance guideline for IPC applications of 2.5 = 10, which was found acceptable in NUREG-0844. The normal operating and hot standby burst probabilities can be combined by weighting the separate burst probabilities by the fraction of operating time in each operating condition. Applying the Section 4.6 Braidwood I fractions of 0.962 for normal operation and 0.038 for hot standby, the combined burst probability is 3.1 = 10~5 8.6.6 Braidwood-l Frequency of SLB Event with a Tube Rupture in Section 4.6, Braidwood-l frequencies of occurrence were developed for an SLB at both normal operaung and hot standby (Mode 3) conditions. The frequencies are summarized in Figure B-5. The frequency for en SLB event at hot standby conditions is a factor of 25 lower than at operating conditiens and is only about 6.8 x 10' per year. Figure 8 5 includes the conditional probability of a tube rupture at normal operating and hot standby conditions as developed in Sections 8 6 4 and 8 6.5, respectively. The SLB event frequencies and conditional tube rupture probabihties are combined in Figure 8-5 to obtain a frequency of about 5.5 x 104 per year for a Braidwood 1 SLB event with a subsequent tube rupture This very low frequency has negligible influence on the core damage frequency and supports full cycle operation at Braidwood-l followmg implementation of the IPC for Cycle 5. 8.7 Summary of Results An IPC with a 1.0 bobbin voltage repair limit has been implemented for Braidwood-l Cycle 5 operation Inspection requirements typical ofIPC practice, such as 6e guidelmes of the Catawba-1 NRC SER, were apphed at the Cycle 4 refuelmg outar,*. to support implementation of the IPC. An operatmg leakage limit of 150 gpd is being applied for Cycle 5 operation The results of the Braidwood-1 IPC assessment can be summarized as follows- . The projected EOC-5 SLB leakage is 3.1 gpm which is less than the allowable limit of 9.1 gpm for Braidwood 1. The SLB leak rate was evaluated for the six alternate formulations of the probability ofleak versus voltage correlation identified in draft NUREG-1477 and 8 - 13 l i found to be essentially independent of the correlation applied in the analysis. The SLB leak rates were obtained by applying the leak rate versus voltage correlation based un the )' EPRI database and outlier evaluation consistent with the NRC guidance of the February 8, 1994 NRC/ industry meeting on resolution of draft NUREG 1477 comments. The tube burst probabilities estimated at EOC-5 are 5 x 10 d for a SLB at normal operating conditions and 8 x 10-' for a SLB at hot standby conditions. The combined probability of burst during a postulated SLB is then 3.1 x 10-' These burst probabilities are significantly lower than the IPC acceptance guideline of 2.5 x 10-8 When combined with the correspondmg SLB event frequencies, the frequency of a postulated SLB event l with a subsequent tube rupture is very low at 5.5 x lod per year. The tube burst analyses are developed based on limited TSP displacements predicted during an SLB event for the Draidwood-l S/Gs even when applying very conservative load conditions for the hot standby SLB. t l
- Deterministic tube burst analyses show that the projected EOC voltage, with voltage growth rates up to 99% cumulative probability on the Cycle 4 measured growth distribution,is less than the R.G.1.121 structural limit of 4.54 volts for a 1.43 x AP t, burst margin.
- The modest EOC-5 SLB leakkge and low tube burst probabilities strongly support full cycle operation for Cycle 5 at Braidwood-l following implementation of the 1.0 volt IPC.
0 1 1 l 1 I 8 - 14 1 j d Table 8-1: Braidwood 1. SG 'D*, pod m 0.6, EOC 5 Volte Cauchy E@ect*8 EOC Vone Cum Proe NJ PJ QJ Vertence QJ N#PpQJ Y @2500 psi p 0.2 0.0C0904 1016 00 1.0 3.11E42 S.17E44 s.15E45 1.e t E45 122E4e l 0.3 0.010827 1015.33 10.0 3.19E42 1.7eE43 3 49E44 5.87E44 1.12E 05 l 0.4 0.040213 100549 39 0 126E.02 4.12E43 122E43 8.24E43 4.02E45 l 0.5 0.123031 966.20 75.0 134E42 7.83E43 3.2sE43 1.96E42 1.11E44 1 0.4 0.222441 est.35 101.0 3.42E42 1.32E 02 7.40E43 4.56E 02 2.59E44 l 0.7 0.334646 700.25 114.0 151E42 2.04E 02 1.50E42 8.17E42 S.40E44 0.8 0.447835 875.79 115.0 3.a0E42 2.99E42 2.7eE42 1.24E 01 1.03E43 0.9 0.550197 881.22 104.0 3.70E42 4.18E 02 4 84E 02 1.81E41 1.85E43 1.0 0.839764 456.55 91.0 380E42 5.64E42 s.00E42 1.96E41 3.18E43 1.1 0.71250s 366.30 74 4 3.91E42 7.41E.02 1.27E41 2.14E41 5.16E43 i 1.2 0.771654 291.82 00.0 4.02E42 9.51E 02 1.94E41 129E41 8.13E43 1.3 0.817913 23132 47.0 4.14E42 1.20E41 2 57E41 133E41 1.25E42 1.4 0.853346 184.96 36.0 4.27E42 1.4eE41 4.15E41 2.27E 01 1.86E42 1 1.5 0.880908 144.83 28 4 4 40E42 1.81E41 5.86E41 123E41 2.72E42 1.6 0.002559 120.e9 22.0 4 55E42 2.18E41 a.12E41 118E 01 3 90E42 1.7 0.919291 99.09 17.0 4.70E42 2.60E41 1.11E+00 2.07E41 4 5 50E42 j 1.8 0.932007 62.01 13.0 4 86E42 3 06E41 1.46E+00 1.94E41 7.85E42 l 1A 0.042913 89 04 11.0 5 04E42 3 59E41 1.96E+00 1.99E41 145E41 l 2.0 0.950787 56.50 8.0 5.23E42 4.16E41 2.56E+00 1.74E41 1.42E41 1 2.1 0956693 50.34 6.0 5 43E42 4.80E41 330E+00 l 1.57E41 1.91E41 2.2 0.961614 43.66 5.0 566E42 5.50E41 4.22E+00 1.56E41 155E41 2.3 0.965551 38.83 4.0 5.89E42 8.27E 01 5.34E+00 1.48E41 136E41 2.4 0.966504 34.97 30 815E42 7.11E41 8.89E+00 1.31E41 4.41E41 j 2.5 0.971457 31S6 3.0 6 44E 02 5 01E 01 8.33 E+00 1.55E41 5.75E41 2.6 0.973425 29.39 2.0 6 75E42 9.00E41 1.03E+01 131E41 7.45E41 ' 2.7 0.975394 27.19 2.0 7.09E42 1.01E+00 1.26E+01 1.43E41 980E41 2.8 0.976378 25.24 1.0 7.47E42 1.12E+00 1.54E+01 8.36E42 123E 00 2.9 0.978346 23.55 2.0 7.00E42 1.24E+00 1.86E+01 1.96E41 1.58E+00 3.0 0.979331 21.99 1.0 8.35E42 1.37E+00 2.24E+01 1.15E41 2.01E+00 3.1 0.961299 20.58 2.0 8.86E42 1.52E+00 2.eeE+01 189E41 2.57E+00 3.2 0.962283 19.34 1.0 9.47E42 1.67E+00 3.19E+01 1.5eE-01 3.2eE+00 3.3 0.963268 1425 14 141E 01 1.83E+00 3.79E+01 1.35E 01 4.15E+00 34 0.964252 17.35 1.0 1.09E41 240E+00 4 47E+01 2.1eE 01 5.27E+00 3.8 0.965236 15.74 1.0 129E41 2.37E+00 6.15E+01 3.05E41 8.55E+00 3.7 0.966220 15.01 1.0 1.41E41 2.57E+00 7.18E+01 363E41 1.00E+01 3.9 0.967205 13.56
- 1.0 1.74E41 3.01E+00 967E+01 5.24E41 1.e1E+01 4.0 0.068189 12.83 1.0 1.96E41 3.25E+00 1.12E+02 8.37E41 2.35E+01 4.1 0.989173 12.00 1.0 2.23E41 3.50E+00 1.20E+02 7.83E41 300E+01 4.3 0.990157 10 55 1.0 3.01E41 4.05E+00 1.69E+02 1.22E+00 542E+01 4.4 0.991142 9.71 1.0 3.55E41 4.34 E+00 1.93E+02 1.54E+00 7.26E+01 4.5 0.992126 8.94 14 4.19E 01 4 64E+00 219E+02 1.95E+00 9.71E+01 4.7 0.993110 7.51 1.0 5 63E41 5.30E+00 2.82E+02 2 99E+00 1 e6E+02 4A 0.994094 6 90 10 6.30E41 5.65E+00 319E*02 3.56E+00 2.0eE+02 5.1 0995079 5 62 14 7.69E41 6 80E+00 4 54E+02 5.22E+00 3.57E+02 1 57 0.990063 4 60 1.0 8 79E41 9 55E+00 8.75E+02 8.40E+00 7.80E+02 l 7.4 0.997047 3.52 to 9 51E41 2.14E+01 4.24E+03 2.04E+01 4.05E+03 i 8.9 0.996031 2.52 1.0 9 6eE 01 3 81E+01 1.33E+04 3 69E*01 1.29E+04 9.7 0999016 1.58 1.0 0 73E41 5.00E+01 2.29E+04 (817E+01 2.24E *04 10.5 0.999705 0 65 07 9 77E41 6 43E+01 3 80E+04 4 CE+01
- 72E+04 11.2 1 000000 0 33 03 0 79E.o1 7 89E+01 57sE+04 2 32E+01 5 65E+M Regression Equations Analysis Sum [ Ni
- E(Qi)
- P6 j = 205.592 Sum [ Var + Cow ] = 0.17E+04 I Effective Standard Deviaton . 3.03E+02 Contdance. 95.0 % I Z Deviate = 1 645 Q. total (LPM) . 703.6 C. total (GPM) . 3 Des l
8 - 1$ mn==uasm o nac m sm.m. ; 1 1 l l .. p Table 8 2. Summary of Cycle 5 SLB Leak Rate Analyses for S/G D Method of Analysis BOC EOC EPRI SLB Leak Rate versus Voltage Correlation a POD = 0.6 a Leak rates based on EPRI voltage correlation a POL Correlation Reference SLB Leak Rate - Log logistic POL 1.71 3. I' . SLB Leak Rate Sensitivity to POL Correlation - Log normal POL 1.71 3.1 - Jeg Cauchy POL 1.69 3.1 - Logistic POL 1.73 3.1 - Normal POL 1.73 3.2 - Cauchy POL 1.70 3.1 4 8 - 16 p i l Table 8 3. Summary of Deterministic Margins Against Burst at SLB Conditions (95% Confidence) ! Parameter S/G A S/G B S/G C S/G D RPC Confirmed Indications Left in Service Largest bobbin voltage 1.00 1.00 1.00 1.00 i NDE uncertainty at 95% 0.20 0.20 0.20 l 0.20 ' confidence + 20% of bobbin voltage ! Voltage growth at 95% 1.40 0.50 1.40") 1.00 cumulanve probability Projected EOC-5 Voltage 2 60 1.7 2.60 2.20 Allowable EOC Voltage at 4.54 volt 1.43xaPit . Largest Bobbin Voltage, RPC NDD Left in Service Largest bobbin voltage 1.48 2.03 1.55 1.8 NDE uncertainty at 95% 0.30 0.41 0.31 0.36 confidence 20% of bobbin voltage Voltage growth at 95% 1.40 0.50 1.4 0"' l.00 cumulanve probability Projected EOC-5 Voltage 3.18 2.49 3.26 3.16 Allowable EOC Voltage at 4.54 143xoPit . Notes- 1. Growth rate for S/G A conservanvely applied to S/G C 8 - 17 I Table 8-4 Distributlen of Indicaflees as a Funcelen of liet $tsadby TSP Displacement and Elevottog Cycle 4 Number and Fraction ofImfientions as a Fenetion of TSP Displacement Indieatens < 045' 045*-050* 0.50* - 0.55' O.55* - 0 60* SO TSP 060* 065* 0 65* - 0.70* 0 70* - 0.75* No % No. > 0.75* F. No F. No. No F. F. No F. No A 3 F. No. F. No. F. 368 50*5 368 IO O O O O 5 248 3395 248 IO 7 93 13 % 86 0 924 2 0 0215 0 2 0 0215 1 0 0108 1 0 0108 I 0 0108 0 28 33 4% 33 10 C 3 713 67% 712 0 999 I 0 0014 0 0 0 5 237 22% 237 I0 - 7 94 9% 88 0 936 2 0 0283 3 0 0319 0 0 0 28 22 295 1 0 0106 0 22 10 D 3 404 58% 403 0 998 0 0 0025 1 0 0 5 181 26 % ISI 10 7 77 II% 66 0 857 3 0 0390 3 0 0390 0 1 0 0130 2 0 0260 1 0 0110 0 0130 28 34 5% 34 10 1 Uniform 3 4548 0 993 18 0 0039 to 00022 TSP Dist_ 2 0 00044 0 (4578 7 4346 0 934 48 0 0105 42 subes) 0 0092 34 0 0074 10 0 0066 22 0 0048 14 0 0031 22 0.0048 Bounding 3 67% 0.993 0 0039 0 0025 " 00004 0 7 13% 0 834 0 0190 0 0390 0 0215 0 0130 + Weighted 3*7 0 0260 0 0110 0 774 0 0110 Sum - 0 0077, 0 0067 0 0011 0 0017 0 0034 0 00l7 0 0017 , l _ _ __m-.------ "---- _- _ _ _ _ - - _ _ . - Table 8 5 Besidweed-1.SG D . Ese6mmeed Het Stand 6y SLB Beroe Probabluty as EOC-4 Tubs / Location Free spen Burst Listed TSP Disp. Bwst (1) - Apphcable SLB Row Col. TSP ' Volts Barst Pratt Local TSP Disp. Bws: Proh (2) TW Bws: Prob. 37 34 5 10.44 2.0E 02 < 0.12 < I.0E-12 - 0.0 23 12 3 8.82 12E 02 - < 0.35 < l.0E l1 - 0.0 12 9- 3 5.02 1.5E41 < 0.35 < l.0E Il - 0.0 11 9 3 4.28 8.0E 04 < 0.35 < l.0E Il -00 19 7 3 3.95 5.7E44 < 0.3 5 < l.0E 1I - 0.0 , 33 20 3 3.83 5.0E44 < 0.55 < l.0E l1 - 0.0 35 29 3 3.62 3.9E44 < 0.35 < l.0E Il -00 li 12 3 3.21 2.3E44 < 0 35 < l.0E f l - 0.0 16 42 3 3.12 2 0E-04 < 0.35 < l.0E f l ' -00 2 105 3 2 St 1.3E44 < 0.35 < l CE 11 -00 8 20 3 2.77 1.2E 04 < 0.3 5 < l.0E 11 - 0.0 43 56 3 2.60 8 8E 05 < 0.35 < l.0E 11 - 0.0 32 27 5 2 48 7.lE45 < 0.12 < l.0E 12 -00 45 $3 3 2.30 4.9E 05 < 0.35 < l 0E-Il - 0.0 31 20 3 2.20 4.0E45 < 0.35 < l.0E l1 - 0.0 27 35 3 2.18 38E45 < 0.35 < l.0E Il - 0.0 l i 41 $$ 3 2.16 3.7E45 < 0.35 < l .0E I l - 0.0 43 53 3 2.11 3.3E45 < 0.35 < 1.0E-Il - 0.0 2 113 3 0.59 2.2E47 0.514 1.9E 05 2.2E 07 3 110 0.58 3 2.lE 07 0 406 3SE49 3.5E49 2 113 7 0.56 1.9E 07 0 804 4.5E 01 1.9E 07 2 108 7 1.10 3.5E46 0 631 9 OE 03 3.5E46 2 105 7 0 64 35E47 0.530 5.3E45 3.5E47 2 11 7 0.72 5 6E47 0498 4 9E 06 5 6E47 4 106 7 0.52 14E-07 0.532 6.3E45 I 4E 07 4 112 7 1.24 6 0E-06 0.718 llE41 6.0E46 5 112 7 1.24 6 DE46 0.692 6 4E 02 6 OE 06 (continued on next pagel ._...g. i 1 o- . / Table 8 5 , Besidweed l.SG D . Essioneese Hee seemdby sLa nurse Probability et EOC4 Tubc/ Location Free Spaa Burst Linused TSP Bsp. Burst (1) Applicable SLB Row Col. TSP- Vohs Burst Prob. Local TSP Disp. TW Burst Prob. Burst Prob. (2) l 7 t 105 7- 0.59 2.2E47 ~ 0.4% 2.7E 07 2,2E47 13 110 7 0.88 1.3E46 0.417 ' 8 0E49 - 8.0E 09 Totel, Burst Probabihty 3.7E42 1.7E45 ; Notes: . I
- l. Analysis
~ displacement. conservatively assumes the TSP displacement exposes e throughwell crack length equj I
- 2. The applicable burst probability is the lower of the free span or TW burst probabihtes f
j b l ,_..,____,m. . , v'=* ' ' " ' 8 1 \ l Table 8-6. Bounding SLB Burst Probability at Normal Operating Conditions 1 EOC-4 Bounding SLB Burst Probability Indications Maximum TSP . TSP Max. Exposed Displacement Max. Volts Length (inch) Burst Prob. for No. Ind. at Number Burst Ind. at All at TSP TSP Tubes Prob.S - H.L. Int." yjg -a i 3/C 5/F 70 SL ' 1 9/M ' 10/N I1/P l _ 1 Total Burst <5 x 10 Probability 1 Notes:
- 1. Maximum number ofindications in any S/G st the noted TSP.
- 2. Burst probability for a throughwall crack length equal to the maximum TSP displacement of column 2.
- 3. Burst probability assummg all hot leg TSP intersections have a throughwall crack length at maximum TSP displacement.
8-21 l Table 8-7 Braldweed-l SC D: EOC-5 Burst Prebebility for Het Standby SLB with Lisetted TSP Displacesseet Free EOS W Plate 3 and 7 Contribution: F, and PRB, es a Functica of TSP Displac-No_ et Burst < 045* O 45*- 0 50* 0.50* - 0 55' 055*.060* O60*.065* 2065* (2) Net Prob. Voltage Ind. Prob. Bin of Burst NV. PRD(V,) F. PRB, F. PRD, F. PRB.M F. PRD " F. PRB," PRB,m F. PRB, I0 0 774 I .t E-8 0 0077 7 9E-7 0 0067 3 OE-3 0.0031 6 IE-4 0 0017 6.5E-3 0 0068 13 8E-2 1.1 74 0 3 5E4 0 774 1 1E-8 0 0077 7.9E-7 0 0067 3.5E4 0 0031 35E4 0 0017 3.5E-3 0 0068 53.5E-2 5.8E4 1.2 60 0 51E4 8 SE-9 (Note 3) 6 IE-9(Note 3) 0 0067 5. lE4 0 0031 5.lE4 0 0017 5.t E4 00068 5.lE4 6.5E4 1.3 47 0 7 3E4 8 5E-9 6 tE-9 0 0067 73E4 0 0011 7.3E4 0 0017 7.3E4 0.0068 7.3E4 7 0E4 , t4 36 0 I OE-5 8 SE-9 6 IE-9 0 0067 1.0E-5 0 0031 1 OE-5 0 00l? 1.0E-5 0 0068 1.0E-3 7.lE4 I l.5 28 0 14E-5 8SE-9 6 lE-9 0 0067 I 4E-5 0 0031 1.4E-5 0 0017 1.4E-3 0 0068 I4E-3 7.6E4 16 22 0 t RE-5 8 SE-9 6 IE-9 0 0067 1.8E-5 0 0011 1 SE-5 0 0087 1.8E-5 0 0068 1.8E-5 7.6E4 1.7 17 0 2.3E-5 8 5E-9 61E-9 0 0067 2.3E-5 0 0031 2.3E-5 0 0087 2.3E-5 0 0068 2 3E-5 7.4E4 18 13 0 3 0E-5 8 5E-9 6 tE-9 0.0067 3 0E 5 0 0011 3 0E-3 0 0017 3.0E-5 0 0068 3 0E-5 7.3E4 I9 IIO 3 8E-5 8 SE-9 6 IE-9 2 OE-7 (Note 3) 0 0011 3 8E-5 0 0017 3 SE-5 0 0068 3 BE-5 72E4 20 80 4 7E-5 8 SE-9 6.lE-9 2 0E-7 0 0038 4 7E-5 0 0017 4 7E-5 0 0068 4 7E-5 6IE4-2I 60 $ BE-5 8 SE-9 6.1 E-9 2 OE-7 0 0031 5 BE-5 0 0017 5 SE-5 0 0068 5 SE-5 S.Z 4 22 50 7 IE-5 8 SE-9 6 IE-9 2OE-7 ~, 0 0031 7 IE-5 0 0017 7.lE-5 0 0068 7 IE-5 5 2E4 i 23 40 8.5E-5 8 SE-9 6 lE-9 2.0E-7 0.0031 8.5E-5 0 0017 8SE-5 0 0068 8 SE-5 4SE4 24 30 i OE-4 8.5E-9 6 IE-9 2 OE-7 0 0011 1 CE-4 0 0017 i OE-4 0 0068 I OE-4 4IE4 25 30 I 2E-4 8.5E-9 6 IE-9 2 0E-7 0 0031 1.2 E-4 0 0017 12E-4 0 0068 1.2E-4 4SE4 26 20 14E-4 8 SE-9 6 lE-9 2DE-7 0 0011 14E-4 0 0087 I 4E-4 0 0068 I 4E-4 .t.71'4 f Table 8-7 Bral4=ee41 SC D: EOC-5 Beest Probability Ter flat Standby SLB with Lissited TSP Displaceneent Free EMS Sm Plate 3 and 7 Contribution: F, eral PRD, as a Function of TSP Displacement No. of Bunt < 045- o 45* - 0 50* 050*-055' Voltage truf o 55* - 0 60- 060*-065* Proh 2065* (2) l Net Prein. Dia NV, PRR(V,) F, lPRD, F, lPRB, of Burst F, l PRD." F. 2.7 PRB." F. PRB." F. PRB " PRB, 20 17E-4 8 5E-9 (Note 3) 6 lE-9 (Note 3) 2.0E-7 (Note 3) 0 0011 I.7E-4 0 0017 1.7E-4 28 10 0 0068 1.7E-4 4.4E4 2 0E-4 8 5E-9 61E-9 2 0E 7 0 0031 2.0E-4 0 0017 2 0E-4 29 20 0 0068 2 0E-4 2.5E4 2 3E-4 8 5E-9 61E-9 2 0E-7 0 0031 2.3E-4 0 0017 2.3E-4 30 10 0.0068 2 3E-4 5.8E4 2 6E-4 8 SE-9 6 IE-9 2.0E-7 0 0031 2 6E-4 0 0017 2 6E-4 31 20 0 0068 2 6E-4 3.2E4 3 DE-4 8 SE-9 6 IE-9 2 OE-7 0 0031 3 OE-4 0 0017 3 CE-4 32 IO 3 4E-4 0.0068 3 OE-4 7.4E4 8 SE 9 6 IE-9 2 OE 7 0 003I 3 4E-4 0 0017 3.4E-4 0.0068 3.3 10 3 8E-4 3 4E-4 4.2E4 8 SE-9 6. l E-9 2 DE-7 0 003I 3 SE-4 0 0017 3 SE-4 34 10 4 3E-4 8 SE-9 0 0068 3 SE-4 4.4E4 6 IE-9 2 0E-1 0 0031 4 3E-4 0 0017 36 10 4.3E-4 0 0068 4.3E-4 5.4E-4 8 5E-9 5.2E4 61E-9 2 0E-7 0 0031 5 4E-4 0 0017 3.7 10 5 4E-4 0 0068 5 4E-4 6 OE-4 8.5E-9 6.lE-9 6.5E4 2 OE-7 0 0031 6 OE-4 0 0017 6 DE-4 39 10 7 4E-4 8SE-9 0.0068 6 OE-4 7.2E4 6 IE-9 2 OE-7 0 0031 6 IE-4 0 0017 40 7.4E-4 0 0068 7 4E-4 I0 8 2E-4 8 SE-9 8 4E4 6 IE-9 2OE-7 I 9E4 (Nose 3) 0 0017 8.2E-4 0 0068
- 4. I IO 9 OE-4 M SE-9 8 2E-4 9.IE4 6 IE-9 2 OE-7 8 9E4 0 0017 9 DE-4 43 10 I IE-3 0.0068 9 OE-4 98E4 8 $E-9 6 IE-9 2 0E-7 19E4 44 - 0 0017 I IE-3 0 0068 t0 12E-3 8.5E-9 ' l. lE-3 1.lE-5 6 IE-9 2.0E-7 8 9E4 0 00l7 5 2E-3 45 10 13E-3 8 SE-9 0 0068 8.2E-3 1.2E-5 6 IE-9 2 OE-7 8 9E4 0 0017 47 10 1.5E-3 3 3E-3 0 0068 f 3E-3 f.3E-5 RSE-9 6 IE-9 2 CE 7 19E4 0 0017 1.5E-3 0 0068 1.5E-3 1.5E-5
Table 8-7 Braldweed-l SC D: EOC-5 Burnt Prebebility for liet Standby SLB with Limited TSP Displaceanent Free g,3 Piere 3 and 7 Contribution: F, and PRD, es e Function of TSP Displacement No of Darst < 045' O 45* - 0 50* 0.50* - 0 55' Voltage Ind O$$*- 060" 060"-065* Prob 2065* (2) Net Pratt Bin N V, of Burst PRB(V) F. PRD, F, PRD, F. PRD," F. PRB," 48 F. PRD/* F. PRB," PRD, I0 17E-3 8 SE-9 (Note 3) 6 lE-9 (Note 3) 2.0E-7 (Note 3) i %4 (Note 3) 0 0017 8.7E-3 5I 0.0068 f.7E 3 1.7E-5 I0 2. lE-3 8SE-9 6 lE-9 2 DE-7 1.9E4 0 0011 2 IE-3 0 0068 57 10 2 IE-3 2OE-5 3 IE 3 8 SE-9 6 IE-9 2 0E-7 8 9E4 0 0011 3 IE-3 0 0068 3 IE-3 7.4 10 7 8E-3 2.8E-5 8.5E 9 6. IE-9 2 0E-7 19E4 0 0017 6.5E-3 0 0068 7.8E-3 89 10 14E 2 6 6E-5 8 SE-9 6 IE-9 2 OE-7 8 9E4 97 1.lE.5 (Note 3) 0 0068 I 4E-2 1.lE I0 I 9E-2 8 SE-9 6 IE-9 2 OE-7 I.9E4 1.IE-5 0 0068 10 5 0.7 I 9E-2 1.4E4 2 4E-2 8 5E-9 6 f E-9 2 0E-7 19E4 1.IE-5 0 0068 2.4E-2 1.2E4 11.2 03 2 9E-2 8 5E-9 6 lE-9 2 OE-7 8 9E4 1.1E-5 0 0068 2 9E-2 6.3E-5 Net Free Sren Derst Probability 9:10' Net Lirnited TSP I NV,*PRD(V) Displacement Durst Sa10* Probabiliry, E PRB, Notes- 1) Initial colmna entry shows the burst probabdity for en esposed throughwell crack equel to the TSP displacement lower burst probebdiry for either free eran based en the bobbin voltage or a throughwell splacement crack at the length exposed 2) Forthe then TSP displacements 0 65 inch TSP displacement>0 65 inch, the free span burst probabihty for the EOC-5 veheses u e are e1=sys lower then for e t roughwellersch greater 3) Numerical value regvesents F,*PRB, for the TSP displacement bin. Selow this entry, the burst probability for en assu - displacement is always less then that for free span based on the v>ltsge level. roughwell crack et the given TSP 1 ' e Mi I se Figure 8-1. Irak Rate Under Ned %g, % mm Crack Length for 3/4 Inch Tubing _y i Figurt 8-2: Braidwood 1, SG "D" BOC & EOC 5 Indications BOC Indications Adjusted for pod = 0.6 200 - ] i . l 180 i a socs radiemions E EOC5 Indications 160 - 140 - - E .g 120 - - - U 9 ~ dO 100 - - -- s. .5 Z 9m _ _ _ Largest RPC NDD Indication Left in Service 60 - 40 - - - 20 - - f 0 1; , , , , . .. ; I ;' / / f f ; I ; W ;';W ,";=W";'; = Wo"'Wn;"; ,; s"^ a; n- ^ -' ' ; - ' -' ; ;s-' -' -' ;.-'e-;' y .6 . 6. 6o y W* =- o =o = v v , v vs as -'a-~d W W W N H H H Bobbin Amplitude (Volts) gressivoxtsisoc rocs NK:4% 791 PM _ -.- _ _ _ _ _ _ . - - - _ - _ - _ - - - _ _ _ _ . _ _ - _ - _ _ __- .--_n Figure 8-3: Braidwood I, SG "A" BOC & EOC 5 Indkations BOC Indications (Preliminary) Adjusted for pod = 0.6 160 ' 0 BOC5 Indications 140 - E EOC5 Indications 120 - 3 100 - - - 3 80 g - - - .E g Largest RPC NDD Z 60 - - _ _ indication Left in Service. 40 - - 20 - - - - - - - 0 ":- -
- lB;I ;I ;I ;I ; ; ; 1 ; !; !; I;rE EJ; 3;,3. m; m. m; m; , , , , _ , , , , , _ , _
UUUU332SDSUUUDDE2Q33 [3 ;a _;g,, ,, ,, ,,_ ,' ,,h' 3' g h 'g Bobbin Amplitude (Volts) fccessmsAxtst eoc roc s Figuur 8-4: Braldwood I, SG "C" BOC & EOC 5 Indications BOC Indications (Preliminary) Adjusted for pod = 0.6 300 0 BOC5 Indicatioins 250 '- E EOC5 Indications 200 - - - Note: Growth rate for SG y ' 'A' conservatively used to -8 simulate growth in SG "C'. .E 3 % 150 - - - - o 5 f gg Largest RPC NDD indication left in Service. 50 - - - - - - - - , .p, 9 9o 9o o 6
- 9 I L ,
9 9 h * * .. )] l 11 : u ; .m . . . . . .. . .. .. , .. o o. - - - - - c4 N N r46 e4* 9n n9 n9 nN *
- n ,9 9, , w9 w w o ei
. Bobbb Amplitude (Volts) ICCESSNC XLS]80C EOC S e FFlo erstpse. 7e7 Pas Figure 8-5. Esthmated Braidwood 1 EOC 5 Frequency of SLB Event with a Tub Breldweed-! SLB Freguesey !J s IM/yr P Fractles of Thee at Freetion of Timw as Nonnel Opereelen HetSamadby Mede3 ew s.am e .l . FuB Power SLB Frequency 1.7 30'/yr Het standby 512 Frequency 6Js18*/yr e LJunised T3P Displaceasst e Umehad 75F P' e Free spee e rwhat Prebebatry of e r=dhat Probabaky Rupeure for SLB of a chi Prebehaley of Rupeure for SIA ~ e Normal Operseine Codh Rapture for $La e HetSaeedby r w h <S:19# - e Het Standby Ceedissee Salt' 9:19 4 N/A For latermoeien Only l 8 ComMmed Frequency of $12 CaoMmed Frequency of SL3 as Normal Operaties and at Det Seandby and a Tube Rupture Tube Rupture SJalO*/yr SAal4*/yr Frequency of SLB and a Tube Rupeure S. Sal 0*/yr E - . , , e- - . - -_---n..-%-,w,.~ - -g-- - , , , - , f) . . i t i ATTACHMENT l i Byron /Braidwood Eddy Current inspection' Guidelines July 1994 i J 1 u l j. 't a -wm-+-vee-'ar,v%w,.--v-,-e-.se -*w---.....m. - .--.----w,- ---w----..,,-e.ev+%&>~me---w--------wr-,,-.-ewi.e ----. --- ,- - , , --- - ,}}