Text

Nondestructive Bone Exam & Condition Assessment of Gec Alstrom HP Rotor Enrico Fermi Fermi Nuclear Station,Unit 2 Detriot Edison Co
	ML20095L403
Person / Time
Site:	Fermi
Issue date:	06/27/1994
From:	; AFFILIATION NOT ASSIGNED, SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	;
Shared Package
ML20095L359	List: ML20095L355; ML20095L362; ML20095L372; ML20095L386; ML20095L403; ML20095L413;
References
	FOIA-94-507, FOIA-95-A-2 NUDOCS 9601030119
	Download: ML20095L403 (100)
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NONDESTRUCTIVE BORE EXAMINATION AND CONDITION ASSESSMENT OF GEC ALSTROM HP ROTOR ENRICO FERMI NUCLEAR STATION, UNIT 2 DETROIT EDISON COMPANY June 27,1994 Prepared By WESDYNE INTERNATIONAL INC.

Murry Corporate Park 1002 Corporate Drive Export, PA 15632 and SIEMENS POWER CORPORATION Fossil Division 1040 South 70th Street Milwaukee, WI 53214 g

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TABLE OF CONTENTS 1.0

SUMMARY

AND CONCLUSIONS 1

t 2.0 RECOMMENDATIONS

3.0 INTRODUCTION

4.0 INSPECTION METHODOLOGY 5.0 CONDITION ASSESSMENT METHODOLOGY 6.0 RESULTS APPENDICES A

MATERIAL PROPERTIES DATA B

NASCRAC" FRACTURE MECHANICS COMPUTER PROGRAM C

NONDESTRUCTIVE EXAMINATION RESULTS D

CONDITION ASSESSMENT RESULTS Y

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1.0

SUMMARY

AND CONCLUSIONS The HP rotor of Unit #2 at the Enrico Fermi Nuclear Power Station #2 was nondestructively examined by WesDyne international Inc. (WDI) at the station during June 1994. The examinations included rotor bore diameter measurements, visual and magnetic particle 1

inspection of the bore surfaces and ultrasonic inspection of the near bore regions.

Engineering condition assessments were made by Siemens Power Corporation (SPC).

These tasks included a sizing of potential flaws from examination results, estimation of material properties, and stress and fracture mechanics analyses. The purpose of the assessment was to determine the suitability of the rotors for continued operation and recommend a future inspection schedule.

The specific results are summarized as follows.

HP ROTOR:

l The bore diameters before and after honing are as follows.

Bore Diameter, in.

Axial Ranoe, In.

Before Honina After Honina 0-4" Plug Bore Plug Bore 4 - 226" 9.964 - 9.980 9.985 - 9.988 226 - 234" Transition Transition j

234 346" 6.013 - 6.027 6.044 - 6.049 i

i The visual examination showed five areas of dimpled regions.

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The magnetic particle examinations did not reveal any flaw like indications including the dimpled regions.

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The ultrasonic examination usin( UDRPS^ system resulted 13 centroids of indications. A linkup analysis of these indications yielded 3 potentially linked up flaws.

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Engineering condition assessment analysis showed that the rotor can be returned e

to service but future inspections are recommended.

2.0 RECOMMENDATIONS The HP rotor can be returned to service. It is recommended, however, that this rotor be inspected within 2000 starts or 80,000 hours0 days 0 hours 0 weeks 0 months which-ever comes first.

3.0 INTRODUCTION

During ' June 1994, WesDyne Intemational Inc. (WD1) performed nondestructive examinations of the subject HP rotor at the Enrico Fermi Nuclear Generating Station.

Siemens Power Corporation (SPC) performed the engineering condition assessment based on WDl's inspection results.

The purpose of this study was to detect any potential flaws in or near the bore and evaluate their significance on the reliability of the rotors during future operation. These flaws could grow by fatigue and/or creep to critical sizes when a burst condition would occur. Remaining life estimates are made using fracture mechanics and a recommended future inspection interval is developed.

The unit was manufactured by GEC Alstrom and placed in service in 1975. The unit is rated at about 1200 MW, with the inlet steam at 544eF and 991 PSIG.

Section 4.0 of this r port includes a description of the inspection methodolog) Section 5.0 includes a discussion of the condition assessment methodology. Section 6.0 includes a discussion of the specific analysis and results.

4.0 NONDESTRUCTIVE EXAMINATION METHODOLOGY The typical procedure includes, removal of bore plug (s), bore surface preparation by power honing, bore diameter measurements, visual and magnetic particle inspections of the bore surface, ultrasonic inspection from the bore and real time data acquisition, "deworming"

O analysis of the ultrasonic data to determine the hypothetical flaws and finalinstallation of the new bore plug /s (after the flaws are not found to be harmful as determined by condition assessment).

4.1 Bore Preoaration and Measurements The bore surface is power honed to obtain a finish suitable for the magnetic particle

[and ultrasonic examinations. The bore diameter is measured to the nearest 0.00 at every 2" axially and at transitions when more than one size bore is present.

4.2 Visual Examination The primary purpose of the visual examination (VT)is to detect flaws that may be open to, or present at, the bore surface he secondary purpose of the visual examination is to determine if the bore surface finish is acceptable for conducting magnetic particle and ultrasonic examinations of the rotorh A visual examination of the entire rotor surface is performed using a borescope) fThis examination utilizes a conventional 2X magnification borescope that is bmanually rotated along the bore. Sketches and/or photographs of the indications I

are provided with appropriate axial and circumferential locations.

4.3 Maonetic Particle Examination A magnetic particle examination (MT) of the bore surface is performed to locate significant surface breaking flaws. The bore surface is visually examined after proper application of a wet magnetic particle solution to the magnetized surface Magnetization is achieved by a central conductor rod either grounded at the end of Jhe blind bore to the rotor or run th ough the bore if possible. A large magnetiQ l

bower supply (480 VAC, single phase)is used to deliver 200 amperes of current per inch of bore diameter. The magnetic field is checked by an independent gauge, i

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l The magnetic particles are suspended in a solvent. Checks are made on particle concentration with care taken to prevent particle settling. The solution is sprayed pnto the bore surface with the magnetic field on. Afterwards the bore is examine $[

l bwith a borescope with a white light source and then cleaned.

Significant I

indications and their location are recorded by the technician, s

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4.4 Ultrasonic Examination Rotorsonic System WesDyne has developed a state-of-the-art Mitrasonic Qata Becording and l Erocessing System (UDRPS).This system is a field deployable, multi-channel, production oriented data acquisition and analysis system. The UDRPS has been successfully used at several commercial operating plants to detect, size and characterize various types of flaw indications including intergranular stress corrosion cracking.

The UDRPS has been developed to do, in real time, what a trained examiner does to discriminate flaws from other UT responses.

That is, to discriminate a consistent signal moving in time (depth) relative to search unit position. This fundamental goal precipitated development of extremely fast electronics and several sophisticated mathematical processes which together form the unique technology of the UDRPS.

The UDRPS is a high-speed, ultrasonic data recording, processing and analysis system. The system is capable of performing automatic flaw detection and location and can accommodate longitudinal, shear and dual element transducers.

The UDRPS processes ultrasonic response signals in a manner that provides up to J

twenty to-one improvement in signal-to-noise ratio over conventional analysis, while directly correcting for search unit characteristics such as beam spread. It generates images from the data so that the operator can "see" defects and size those defects accurately.

Although a significant increase in examination sensitivity has been demonstrated in several applications, it is also important to note that increased reliability of examination also is realized.

The location of an individual target return is calculated from time of flight (i.e.,

metal path) and transducer position and angle. This location is transformed and displayed in the coordinates of the material being inspected.

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Sizing is pGrformed interactively using scaled orthogonal or perspective views of sound field images displayed on a color graphics monitor.

System hardware consists of multiple, automatic detection channels. Each channel is a network of computers including an ultra high speed data stream computer, an array processor, and digital storage medium. Channels can be added or deleted from the UDRPS configuration to match the application.

Each transducer search unit is energized separately, never more than one at a time by the use of a multiplexing scheme and in a fixed sequence. Further the time separation between pulses is jittered randomly, thus eliminating any possibility of t

cross talk between transducers leading to false calls. All transducers used during the examination are of the non-focused, pulse / echo type.

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UDRPS provides for a signal to noise ratio improvement, the objective of focused h probe scanning, without the use of narrow beam profiles. This is achieved by the use of a line SAFT (Synthetic Aperture Focusing Technique) digital signal processing calculation performed in real time by UDRPS. This technique allows wide beam transducers to be focused to smaller beam widths while maintaining the wide coverage and more rapid scan rates not generally available with focused probes.

Although 1/16" and 1/8" side drilled holes are used for calibration, a specific i

reference level is not used to record data. Rather all ultrasonic targets, including noise, are recorded. Since this technique is much less sensitive to the amplitude calibration, it is more repeatable for futuo inspections. Furthermore, the high sen-sitivity and the signal to noise processing employed allows surface flaws to be detected.

f It should be noted that this method of inspection produces substantially more data for analysis than other single gate ultrasonic acquisition systems which record data above a certain percentage of calibration level. Therefore, the number of targets recorded is not meaningful since the majority of the targets are from insignificant point source reflectors.

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r Transducers /Seannino Pattern The frequency of the transducer search units used during the examinations are 3.5 MHz for the angle beam circumferential scans, 3.5 MHz for the Oo longitudinal beam scans, and 2.25 MHz for the angle beam axial scans. The transducers are f

mounted in plexiglass shoes which are coupled to the bore by a continuous flow of light turbine oil force fed to oil outlets on the bottom of the shoe Radial shear wave search units in the clockwise and counterclockwise direction are used.

The scanning pattern used for the examination involves circumferential motion in a clockwise then counterclockwise direction with indexing in the axial direction 2down the bore. Axial index increment is.25" for a total scan section of 15".

Additional lengths of the bore are examined by adding extension tubes. A dedicated, high precision computer controlled scanner has been constructed for bore inspection.

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UDRPS Analysis /Outout A

During the examination, UDRPS provides:

Coniplete recording of each entire A-scan, pulse by pulse on an uptical disk.

Target detection on a well proven, highly reliable, amplitude insensitive, signal to noise ratio and pattern recognition algorithm performed in real time as data are taken.

A, B, C and D scan data presentations.

Three dimensional target displays of the inspected volume of material.

Spatial and temporal averaging of data for enhanced signal to noise.

t Multiple B scan views at near motion picture framing rates.

Edge enhancement routines to improve signal to noise.

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Spatial correlation routines for the separation of significant from benign indications, i.e. "deworming" techniques.

This technique is used to

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formulate potential flaw sizes. All indications that appear to be real and meet certain criteria within the UDRPS detection algorithm are centroided (flagged). These centroids are compiled in the data files and are available for further processing. Next the UDRPS uses a data processing program called "deworming". The UDRPS will go through all the raw centroids and

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look for consistency from one centroid to the next. It also looks for centroids that fall within the boundaries set by the operator. If centroids {

are found that meet the criteria, then it links 'them together into groups.

All examination data are recorded in real time and reviewed for accuracy and validity at the end of each scan section. All structurally significant indications detected during the examination are documented by hard copy display, which can be found in later sections of this report.

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5.0 CONDITION ASSESSMENT METHODOLOGY The SPC condition assessment includes reviewing reported flaw sizes and/or formulating potential flaw sizes from inspection data, performing stress analyses, material data evaluation and fracture mechanics analysis to determine how detrimental the present flaws are for operation of the rotor and to establish the next inspection interval.

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j 5.1 Crack Size Determination 9

If a magnetic particle inspection is conducted, it is usually assumed that the radial depth of the indication is one half of its axiallength unless proven otherwise by the boresonic inspection.

7 Surface and subsurface flaw sizes are provided by WesDyne from the ultrasonic [

l examination, and when necessary they are derived by performing a "3 D Computer Linkup Analysis" of the ultrasonic data by SPC. Although the ultrasonic indications may show a relatively small amplitude, it is possible for larger flaws to be present due to reflection uncertainty associated with flaw shape and orientation.

Furthermore, it is possible to have ligament yielding between indications without J

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5 being detected. To reduce these uncertainties and to define the size of potential flaws a linkup analysis is conducted utilizing an ellipsoid surface criterion wherein 4

i the radial, circumferential and axial radii can be varied (Reference 1). The 3-D istance between indications is calculated and if this distance is less than a critical /

/ Gistance, the indications are linked together. A potential flaw is formed wherb sufficient indications can be linked or clustered together. This critical distance is

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in general a function of the size of the neighboring indications, the plastic zone size, the fracture toughness, the stress level and the yield strength of the material.

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5.2 Stress Analyses Stress analyses are normally conducted with in house computer programs using classical formulation and in certain cases the finite element method is utilized.

For a turbine rotor, the circumferential mechanical stress profile as a function of the radial distance from the bore surface due to rotation and blade load is calculated at the potential flaw locations. An appropriate thermal stress is added to account i

for the start up transient at cold starts.

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For a generator rotor, the circumferential stress profile about the bore in the main?

body is calculated based on a solid ring of dead weight, which represents the copper coils, acting on a bored shaft with a diameter equal to the bottom of the coil slots. The distance from the bore surface to the bottom of the coil slots is measured ultrasonically.

Since the overspeed stress in addition to the running speed stress is considered in e fracture mechanics analysis, this stress prof:!e is also calculated.

5.3 Material Evaluation Typically fracture toughness, K, and crack growth data are estimated from available known mechanical properties and chemical composition for the rotor, or when data are not available the SPC database, which includes both published and i

unpublished in house data for vintage rotors, are used. When possible, drilling chips are removed from the rotor for chemical analysis and correlation with fracture toughness (Reference 2).

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Fracture toughnsss data normally us2d for these analys:;s are provided in Appendix 4

A; Figure A-1 shows lower bound K data for embrittled and unembrittled rotors, and Figure A-2 shows K. versus operating temperature minus FATT. If a need is indicated, then core samples such as radial or axial trepans, or ring samples from the bore region are removed from the rotor and actual K, data are obtained in accordance with ASTM E-813. Fracture toughness and chemical composition correlations are also provided in Appendix A (as Attachment A) are also utilized when appropriate.

5.4 Fracture Mechanics Analyses Since fracture mechanics deals with cracks, the visual, magnetic particle and ultrasonic indications are usuaCy considered to be cracks unless proven otherwise; this is a conservative approach.

P Critical Crack Size The burst condition for the rotor occurs when the stress intensity factor, K,,

l corresponding to the present crack size is equal to or exceeds the current fracture toughness, K., of the material. The crack size corresponding to this situation is said to be critical. The stress intensity factor is a function of the applied stress and k crack size and increases with either of these values. The critical crack size, a,,, is a function of the ratio uf the fracture toughness, K., to the applied stress, a. The f

/ racture toughness is a function of the temperature and generally increases with it.

g if the current stress intensity factor is less than the fracture toughness, then the /

current crack size is suberitical. However, this suberitical crack could grow by fatigue due to start stop cyclic operation of the rotor and/or by creep due to steady operation at high enough temperature. By performing a crack growth analysis, the remaining life to reach the burst condition is estimated.

The burst condition, depicted in Appendix A, Figure A-3, corresponds to the minimum critical crack size which occurs when the ratio of fracture toughness to stress is minimum. Therefore, the burst condition occurs sometime during a cold start when K,/ais minimum. Since a detailed analysis is beyond the scope of this i

study, the burst condition and the associated critical crack size are evaluated from minimum estimated fracture toughness and maximum estimated stress.

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l Fatiaue Crack Growth ASCRAC (TI@g Th t:omputer program, described in Appendix B, is used to calculate the stress intensity factors for the hypothetical crack, and to determine the number of load blocks required for the crack to grow by start-stop cycling to a critical size. A load block consists of a number of normal start stop cycles and one overspeed cycle.

As a conservative estimate hot and warm starts are considered to be the same as a cold start. Upper bound fatigue crack growth rate data are used for the calculations and it is considered that the rotor will fail during an overspeed test. Crack growth rate data are provided in Appendix A, Figure A 4.

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Since the NASCRAC program allows stress profiles to be input, it is especiallyg i

jsuited to rotor bore analysis. If the circumferential stress is held constant with' dial distance from the bore, the critical crack size calculated is too conservative (too small). Therefore, more realistic results can be obtained using the actual stress profile.

L e NASCRAC output tabulates crack sizes, stress intensity factors based on overspeed stress, and load blocks for small increments of crack growth. To account for uncertainty in the stress analysis, fracture toughness, crack size, etc.,

the number of calculated load blocks is reduced by a factor of ten Ithough the results may show that it would take more than 2000 start stop cycles for the crack to reach the critical size, it is SPC policy to recommend no more than 2000 starts-stops before the next bore inspection.

Creco Fatiaue Crack Growth An in house computer program is used to calculate c*ack growth for cyclically loade rMo tors subjected to hold time at high temperature (Reference 3).

Essentially, a load block consisting of one start followed by a number of steady-state running hours (usually 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months or one month) is used to calculate the number of starts and operating hours required for a preexisting flaw to grow to the critical size based on start-up transient and steady state stress profiles.

Appropriate safety factors are then employed to determine an inspection interval.

5.5 Referenc_g1 t

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D. R. McCann, J. Zhang, H. M. Snapp and H. R. Jhansale, " Formulating Potential Flaws From Boresonic Data", EPRI Computer Assisted Technologies For NDE and Plant Monitoring Workshop, Philadelphia, PA, August 10 13,1992.

2.

R. Viswanathan and S. Gehl, "A Method for Estimation of the Fracture Toughness of CrMoV Rotor Steels Based on Composition", Journal of i

Engineering Materials and Technology, April 1991, Vol.113, P. 263-270.

3.

R. Viswanathan, " Damage Mechanism and Life Assessment of High Temperature Components", ASM International, Metals Park, OH,1989, P.

170 172.

6.0 RESULTS The nondestructive examination results are provided in Appendix C, and the condition assessment results are presented in Appendix D.

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A Method for Estimation of the Fracture Toughness of CrMoV Rotor Steels Based on Composition Assessment-of the remaining Itfe ofsteam turbine rotors in the presence of bore

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R* Viswanathan procedures for estimating the Kg involve two steps; as a f'irst step, the fracture appearance transition temperature (FATT) at the criticallocation is determined; the FATT value is then used to estimate the Kg, based on published correlations g, gg between the eccess temperature (T-FATT) and Kn Some problems arise in im.

piementing both of these steps. To determine the FA TTof the material large piec of material have to be removed, machined into charpy specimens and tested; this y

procedure is often time consuming and expensive and sometimes notfeasible. The excess temperatures versus the Kgcorrelation that is used to derive the K c t values from the FATT data is based on a variety of low alloy steels and is therefore characterized by a large sattler band, thus leading to considerable uncertainty o the estimated Ke In Ihis work. FA TTand Koc data reportedfor a number ofietired CrMo Vrotors wre gathered andanalyzedandcorrelationsspecific to CrMo Vrotor>

were developed. Based on these correlations, a methodfor estimating Koe ith grea w

accuracy, based on a knowledge of the steel chemistry alone, is proposed. The method offers the adsentage that very small samples removed from nontritical locations in the rotor would be sufficient to get the desired data.

Journal of Engineering Materials and T=chnology APRIL 1991. Vol.1131263

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NASCRACS FRACTURE MECHANICS COMPUTER PROGRAM l

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NASCRAC " COMPUTER CODE l

The NASCRAC Code is a computer program for performing state of-the art fracture mechanics calculations. It utilizes influence functions, a prior stress analysis of the uncracked structure, and previously developed crack stress intensity solutions to calculate the crack induced redistribution of the elastic stress field. The program has a library of different crack configurations for which 1

K solutions are provided, and has the ability to analyze a spectrum of different loads. In addition to the linear elastic fracture mechanics capabilities. the program has provisions for the evaluation of J-integrals, elastic-plastic stress redistribution, and creep crack growth.

The most common models used in the program are a semi elliptical surface crack (702) and a buried elliptical crack (502) shown on the next pages. Both models contain correction factors to the stress intensity factor for the crack tip approaching a free surface.

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I NASCRAC is a trademark of THE FAILURE GROUP, INC.

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Crack Front Shape Semi Dliptical Finite Width EKects Yes influence Function Yes Variable Thickness EKects IVTHIC No No J Integral Solutions Data Input Description FORTRAN Input Input Description Variable Format Rema.rks variable Thickness IVTHIC Tabular Not Available Initial Crack Size al AINITL(1)

Constant a2 AINITL(2)

Constant a3 AINITL(3)

Constant Body Widths W1 WIDTHS (1)

Constant W2 WIDTHS (2)

Constant W3 WIDTHS (3)

Constant Crack Position Xc CENTER (1)

Constant Ye CENTER (2)

Constant Crack Orientation 4 CRKANG Constant Stress input a,(z)

Equational Tabular a,,(z, y)

Equational Tabular K.Solutiene Limits : (as+c3)/ai>2 Accuracy : Approximately 10% for ci/W < 0.8 and 15 (o + e3)/a, 5 6 ;

n ai/W <1 Unknown outside this range.

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4 a,.-

a, y

r-i W 3 Tc - -,

a m

a I

X l

NASCR AC Usu's Mseest ya,,,, g,2 Y

A

1 Burind Elliptical Cr.ek FORTRAN Optis i Variable Featured Model Feature L

Model Index Number KRKTYP 502 Number of Degrees of Freedom KRKDOF 4

A Crack Front Shape Elliptical Finite width Effects Yes Innuence Function Yes Variable Thickness Effects IVTHIC No J Integral Solutions No Data input Description FORTRAN Input input Description Variable Format Remarks Variable Thickness IVTHic Tabular Not Available Initial Crack Size al AINITL(1)

Constant a2 AINITL(2)

Constant a3 AINITL(3)

Constant a4 AINITL(4)

Constant Body Widths W1 WIDTHS (1)

Constant W2 WIDTHS (2)

Constant W3 WIDTHS (3)

Constant W4 WIDTHS (4)

Constant Crack Position Xe CENTER (1)

Constant Yc CENTER (2)

Constant j

. Crack Orientation d CREANC Constant Stress Inpt.t a,,(z)

Equational Tabular

)

a. (z,y)

Equational

)

Tabular K Solutions:

Limits : unknown Accuracy : unknown (better accuracy for smaller cracks)

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~.

g.

s uI'*Ii c

x/~%r

+

.,'. t /

l

/

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w 4

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c.

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4 g

-W

=

2 1

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y g'b e e h

uscuc u,., w,.a vm. u L-

N',

l M

i t

Type of analysis Ii i

l

,r 1r p

,r 3r 1r K vs. e J vs.s Elastic-Critical Suberitical Proof test calculation calculation plastic stress crack size crack growth logic redistribution l

l f

,r ir 3r 1r 3r

-Generation Use of Generation Use of Creep Fatigue t

of new existInD of new existing crack crack Influence solution J-solution solution Growth Crowth l

function a

h h

l 1

1 1

I Inco tion i

I 1

atton i

Use of Use of No Retardation 3

o new I

C(t)

Cy retardation

- Wheeler o new I

I>

- Willentng

~~

~

solution into solution into

~

I y

(elastic only)

[

existing existing library library l

Creep l

lifetime l'

Crack Crowth law

- Paris

- Modified Forman

- Colliptiest l'

- Walker IExceedance Elastic Elastic stic

- General Tabulated of Ke taarin tea

'"*'g*

BLOCK DIAGRAM -

Transition THE CRACK GROWTH

d'*d" ANALYSIS FORTION OF Faugue i

THE NASCRAC~ CODE-lifetime

'l Failure l

Analysis Associates *",""

l y

-m-

~

_4--

0 l

APPENDIX C NONDESTRUCTIVE EXAMINATION RESULTS

?,

i'

.~.

I DIMENSIONAL PROFILE 4

A bore profile was made at 2.0" Intervals down the bore after power honing. See detailed results.

L.

BORE PROFILE SHEET

/

CUSTOMER D E.I.O STATION / UNIT EE.R Ms & /__

JOB NO."DGkVloo

~

HP

/ IP LP GEN ROTOR MEASURED FROM

(, e o Eon Boro Before After Bore Before After Bore Before After Dnpth Honing Honing Depth Honing Honing Depth Honing Honing o

yA g

44 9.9H 9.985-88 9.%E 9.966 2

QA Qg 46 g,q(q q,qgg 90 q,qq q,ggg 92 9.90 9.996 9.980 9.98G 48 9.965-9.985 4

9.980 q.qgg so 9.903 9.985 94 9.9G7 9.q 06 6

8 9.9(7 98eg s2 i q,qw q 9ef 96 q,qg q,qg6 1

9.966 9.985-54 q.gy q,qgg 98 q,qqq q,q g6 ss 9.965 9.9 86 100 9.%7 9896 12 9.90 9.9 85-14 9.90 9.9 85' 58 9.%G 9.966 102 9.967 9.996 6

9. %0 9.985 60 9.%G 9.9 86 104 9.9n 9.986 18 9.%E 9.985 s2 q.qct q q66 106 980 9.986 1a q,ga q886 q.%G 9.986 20 q, qty q.qe5 64 22 q,qcg q.985-66 9.96G 9.98s' lio 9.90 9.9 86 24 g,qqg 9.965 68 9.%g 9.98G 112 9.9G 9.9 86 7o 9.965 4.9 86 114 9.H7 9 886 2s 9.965 9.985-72 q,q(5 q,qgg 11s 9.qn 9885 28 q,gg g,qgg 74 9%

9.986 118 9.% 1 988l 3o 9.966 9.985-76 9.%~1 9886 120 q,gg go86 32 9.90 9.9 85-34 9.96E-9 986 78 9.%F 9886 122 9.966 9886 36 q,q6{

q,9Bh so 9,q(~]

q,9@(

124 g,g(g q,ggg 38 9.%5' 9.98G 82 q,g, q.986 12e 9.%E 9 986 4o 9.%E 9885 84 9.90 9.q8g 128 q qc5-qR86 42 qqg gags-as 9.965' 9 8BC 13o 9.965' 9886

)

i j;*

E' dw/y_

oxrE c-n-s4 g

D1xtuS10nS TAxtn av

/

CUSTOMER D EC.O STATION / UNIT Fenos, tz: 1 JOB NO.T. E M "240 j

HP s/ IP LP GEN ROTOR MEASURED FROM 6,e.o EOD Bore Before After Bore Before After Bore Before After Depth Honing Honing Depth Honing Honing Depth Honing Honing 132 q,q(c q,986 176 q,qc, q,qgg 220 q,q1l q,et go

/\\

Ib 222 g,97q q,qly 134 q,qQ 178 g,9($

136 9 96G 18o 9,9 L5 224 q,qm q, cf y-138 9,g(,

182 q,q(c 22s q,q(g q,q (,g TAAg*4 5

140 9,9((

184

%,9(q 228 hgo hj'k-142 q,q((

186 q,911 230 144 g,g((

188 g,q(g 232 hgA*8 tag ** l 145 T,966 1So 9.9G8 234 c,og3 c,0+c 148 q,qQ 192 q,966 236

(,0\\'l

(,0 %

150 q,q(g 194 g,96(

238

(,0 l 5 152 g,q({

196 q,q(6 240

(,015 154 9;q(6 198 g,qqg 242

(,ogy 200 q,q(g 244

(,0\\f 156 9,q(y 158 g,qgg 202 9,97[

246

(,O gg 204 g,q69 248

(,ogg 160 9,q((

g 162 9,965 q,qgl 206 q,qqg 250

(,ots 164 9,q69 208 g,96]

252

(,015 254

(,Ogg 166 q,g(L 210 q,qqf y

168 9,9(,5-212 q,qcl q,qgc 256

(,o tr 170 q,q(,]

214 q,q((

9,98{

258

(,Og g 216 9,qbl q,qgq 260

(,Qlf j

172 q,q (,]

q 174 q,q(7 g,qgg 218 q,q(q q,98h 262 6.O t $

y b

DIMENSIONS TAxEN sy 10 % _ _ _ _

DATE (-u-

~

A

,K BORE PROFILE CONTINUATION SHEET 3

CUSTOMER O

S T A T I o N / u N I T F c e a s v ~/._Jos no DEuCOc HP IP LP GEN ROTOR MEASURED FROM h r:.o E n n Bore Before After Bore Before After Bore Before After Depth Honing Honing Depth Honing Honing Depth Honing Honing 308 352 264 6.01T (M

LO\\N

(,My b

266

(,o g g 354 310 b.O \\ q 268

(,,oty 312

(,,ogg 356 358 270

(,.O I T 314

(,0 t%

MO 272

6. ole 316

(,ogy 362 274

(,on E 318

(.O G 276

(.. ole 320

(,o gg 364 278

(,0 lg 322 C.Oli 366 280

.G.015 324

(,o gq 368 282 6,0)E 326 l..Ol4 370 284

(..O l f 328 C.O t3 372 286

(,,O g g 330

(,Ogg 374 288

(,,0 l g 332

(,o gg y

376 378 290 G,ogg 334 6.015

(,04y 380 292 -

G.015 336 b.Ol5

(.W6 294

(.015 338 G.Ot5

(,oq-)

382 384 296 G.016 340

(..O t E (m

386 298

(. 015-342

(,og ;

(,og-)

344

(,.010 C.6 %

39 3 0 C.Q L 5 302

(,otg 346

(,op

(,oqq 392

(,D } g 348 394 304 306 b.O lE y

350 396

/

DIMENSIONS TAKEN BY / M_ _ _

D ATE (,- Il - 9 '

l r

VISUAL INSPECTION The visual examination was conducted using a borescopic probe. The borescope allowed for the complete viewing of the visual examination. See detailed results.

L....

1 1

4

c a

}

INDICATION DATA SHEET Paga l' of 2 7

i CUSTOMER FERMI STATION / UNIT _

~~t JOB NO. D F H7 i

H.P. ROTOR V

I. P. ROTOR A//A

,L.P.

ROTOR N/A GENERATOR N/A MAGNETIC PARTICLE M/A VISUAL

/

PRELIMINARY

/

FINAL N/A BORE DIA.9.7fW4BZERO DEG.REF.

A BOLT HOLE FIELD OF VIEW 525/3 0

)

i i

Ind. #_

1 Deg.[4o 366 Ind.#

Deg.

Ind.#

Deg.

Axini Start fUL L ( f~ETH Axial Start Axial Start Length __ N/A Length Length Dascription MEDRM L6RRfiJ#, Description Description i

/Y/

Y f

Ind.#

Deg.

Ind.#

Deg.

Ind.#

Deg.

Axial Start Axial Start Axial Start Length Length Length Description Description Description REMARKS:

~1 i,

J

}

/) / / 7

~

Paga 2' of' 2 4

CUSTOMER [O[N[

2 STATION / UNIT 2

JOB NO.OEME H.P. ROTOR

[

I.P. ROTOR N/A L.P. ROTOR /V/A GENERATOR N/R MAGNETIC PARTICLE _ #/A VISUAL

/

i PRELIMINARY #/A FINAL

/

BORE DIA.7f/N4.8kERO DEG.REF.8ClT NdlE.I s

FIELD OF VIEW 5.2 SN.E' g-g,

,+

g Ind.#_.I Deg. 34'5" Ind.#

2 Dag. 795*

Ind.# 1 Deg. /,0

1 Axial Start NF Longth _ vx2^

Axial Start /F3.S

Axial Start /f05 Length

'3 ' r /

Length /, S ' # / '-

Description #7xrzt Description _ M Mr4E Description ST&LE N

y

,.s-Ind. #_ 4' Deg. 2 00' Ind.#

5 Deg. 2 40*

Ind.#_

Deg.

Axial Start / '74. 5 '

Langth_ 3 x/.5

Axial Start _/f9t.7'-

Axial Start Description prMPLE Length J,sy /.v*

Length Description _D7nFi.E Description REMARKS:

1 9,

... =

l ExAMIurR

/ hs._

LEVEL DATE t-# /' r e-w-win

MAGNETIC PARTlCLE EXAMINATION A magnetic particle examination was performed. A borescopic probe was utilized to allow complete viewing of the examination. See detailed results.

l 0

.y

-.' {. '

n... n,

r. -

c t

,y e

L v.....

! CUSTOMER FE t\\mL STATION / UNIT _.

1 JOB NO._DE H )'

(

.P.

ROTOR

/

I.P. ROTOR _U/b L.P. ROTOR _ N/A GENERATOR N/A H

MAGNETIC PARTICLE _

/

VISUAL N/S PRELIMINARY N/A FINAL

/

BORE DIA.SMEhbd~ZERO DEG.REF.#

1 BBLT HDLE

_ FIELD OF VIEWS 25/3 0 b

,q

/;

J, Ind.#__

Deg.

Axial Start Ind.#_

Deg.

Ind. /_

Deg.

Length _

Axial Start Description Length Axial Start Description _

Length _

Description g

g M

A A

A Ind.#__

Deg.

Ind.#_

Deg.

Axial Start

~

Axial Start Ind.#_

Deg.

Lnngth Description _

Length _

Axial Start Description _

Length _

Description REMARKS:

flg gf((Qfjf fyff( ATf0y$

[0()l\\)Q t

-a

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t j

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G

.,,A m

ULTRASONIC EXAMINATION Calibrations 9

A dynamic calibration designed to establish udrps detection parameters was performed.

This sensitivity reference standard is made from a block of material acoustically similar to the rotor forging material. The block contains a bore with a radius similar to the radius of the forging. Each block contains small diameter reference reflectors at different depths radially outward from the bore surface.

Results of the dynamic calibrations and examination para, meters are permanently stored on optical disk for future reference.

t

\\

/

1 Figure 1 is a view of the 12" Calibration block with the clockwise radial search unit.

Figure 2 is a counterclockwise view of the 12" Calibration block with the other radial search unit.

Figure 3 is a clockwise view of the 6.25' Calibration block with the clockwise radial search unit.

j Figure 4 is a counterclockwise veiw of the 6.25" Calibration block with the other radial search unit.

2 e'

1 mfd E

LE ES)

E BORE IT CAtlBRATION DATA SilEET 'A' b Eb 7' Ob CUSTOMER: DETROITEDISQV STATION %TT; FER3f/ / 2 JOB NO.:

HP ROTOR SN. EERF/2133 BORE DIAMETER. 7 78E CAL BWCx DR:!2' TRANSDUCER SHOE SIZI:

EC CIRC. SHEAR AXIAL SHEAR ZERO DEGREE CW CCW OLT IN NS FS TRANSDeCERSw C lllLE C l ll t,Y P 0 3'D 2 D03972 60791'?

607727 LT INSTRntENT DY.VAFUL5ER LH I 0 %VA FULSF K C H 2 PYNAFULSER CN 3 j

MODEL NO. s SEn u.NO WCM 10711 WEM 10711 WEm 10712 SENSITIVITv 35 30 3O SKETCH OF CALIBRATION BLOCK AND HOLES USED HOLE /DEPTII

.25 A

/* O DE ROn B

MO OD C

3.9 to oc o,

D

2. 5 ko ea on

.25

___________g_o eA E

r

.50 OF 0

1. 0 1.0 y

i 3.0

.35

/.0 x

t 2.0 u I. 0 N

0 P

Q ODrSxNO W.3 -7 2 - Pr 3 DEGREES CCw Orr.SE7 NOTES:

t i

MA E.TUUNER

~ ~

EVEL DATE

N s WmS

=

^

M M

l It i 4 II et A 1 iO es A L BORE IT CALIBRATION DATA SIIEET T CUSTOMEn DETROITED/ SOY STATIONUNIT. FER3f/ 2 JOB NO. p riq y -20c HP ROTOR SN EERF12133 BORE DIANETER: [. O/

CAL BLOCK DIA: d. 26 ULANSDL'CER SilOE SIZE. - d. O '

CIRC. SHEAR ANIAL S!! EAR ZERO DEGREE CW CCW OLT IN NS FS rnxNSot CER S s

[ll145 Cll/4 Y 003772 D03772 60M9 407U7 LT INSTRL'hENT OYA/R$$$(8 (Nl 0Nb'$llSf8 (H2 DYNRPa S E R CH 3 "i'ENE' WU? 1077.2 WEM ID 772 IJ9: 10 7'12 ER SENSITI\\'ITY

[E 24 8.2 SKETCH OF CALIBRATION BLOCK AND IIOLES USED IIOLE/DEITil A _,25 B l 00 ~

c

.2. 0 0 '

o 3.00 '

E 25

-~~~~-----~~-------~~~----------

F. 50 O

l. 0 0

E' o H Jl 06 ^

Fo I 3. C C IO Co 3

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J. 00,

kO 4o o c t.2. 0 0

LO 1o M

N O

P Q

O. DISK NO YV-7I-8 CCW OFT. SET 4

e,'

NOTES:

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hstrNER IML DATE

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DATA ANALYSIS The data files were dewormed and analyzed for real targets that correlated perpendicular to the principal stress direction (radial axial near bore).

The following tables provide a listing of the indications found in the HP rotor. The contents of the tables (c file) are as follows:

r--

-m Column 1 Rmin Minimum distance that the indication is located below the bore's inner surface.

- f Column 2 Delta R Total through wall dimension of the indication.

Column 3 Zmin Minimum axial distance the indication is located from the coupling face, r Column 4 Delta Z Total axial length of the indication.

kolumn 5 Tmin Minimum circumferential location of the indication measured in degrees from a fixed datum point.

Typically bolt hole one.

Column 6 Delta R Total circumferential length of the indication.

l Column 7 AMPmin Minimum amplitude of the indication. Amplitudz 1

ranges are from 0 255.

Column 8 AMPmax Maximum amplitude of the indication.

w

PERCY FILE AXIAL LENGTH RANGE FROM 2.750" TO 0.250" Rain Delta-R Zain Delta-Z Tmin Delta-T AMPain AMPaax 1.930 0.420 320.5 2.75 12.780 3.280 19.0 255.0*

2.140 0.260 321.4 0.50 12.640 1.150 30.0 108.0**

NOTE: only indications of lengths >.25" are listed.

p

= CW INDICATION

- = CCW INDICATION

\\

SUMMARY

OF INFORMATIG.

FILE NAME LIST : CF17CW + CF17CCW TURBINE NAME.................. FERMI-f2-HP COORDINATE ZERO LOCATION...... f1-BOLT-HOLE DELTA Z PER SWEEP.............

0.25" TRANSDUCER DIAMETER...........

0.50" TRANSDUCER TYPE............... RADIAL SHEAR BORE DIAMETER.................

6.01" W

2.790 M;1 -

i q g{g iit\\gijkh7..dU'd i '

...a.+

~

0 i

l APPENDIX D 1

CONDITION ASSESSMENT RESULTS O ~700 AAAT.~.O!A1:

V.y

?

'?

I p,.,. c, g.J

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-. 4.C w ut V

'llusiw.a 6...

CONDITION ASSESSMENT RESULTS:

1.

HP ROTOR:

Figure D1 shows a cross-section of the HP rotor. The axial zero reference was from the generator end. The angular measurements were referenced from the No.1 bolt hole on the coupling.

Bore Measurements.

Bore diameter measurements were made at 2" intervals axially and are included in Appendix C. The bore diameters before and after honing were respectively as follows.

P Bore Diameter, In.

Axial Ranae. In.

Egigre Hon..in After Honina

/

0 - 4" Plug Bore Plug Bore s

s 1

4 - 226" 9.964 - 9.980 9.985 - 9.988 i

s 226 - 234" Transition Transition 234 - 346" 6.013 - 6.027 6.044 - 6.049 Visual and Mannetic Particle Framinations:

The visual and magnetic particle examinations did not reveal any reportable flaw like indications, except for five dimpled areas.

Ultrasonic Examination:

The ultrasonic examination of the near bore region using thil UDRPS}ystem revealed 13 centroids of indications. Figures 32-D6 show two dimensional plots of these indications in three views. Figures D2 D3 show plots over the entire length of the rotor, while Figures D4 05 show a closer view of the same plots over a shorter section of the rotor. A 3D linkup analysis of these indications resultad in 3 potentially linked flaws. Figure D7 includes a listing of these linkup flaws.

Crack Sizes Analvred:

All three linkup flaws are located outside the last stage blade row on the governor side, which is a low stressed region. However, Linkup #2 which is the worst is considered for 0

a f,

e,,e **

}

1 analysis. Also, a default surf:ce flaw 0.25" long and 0.125' drep is assumid to be present in the highest stressed section and analyzed.

Stress Analysis:

Circumfsrential mechanical stresses were calculated at the inlet and exhaust stages.

Appropriate thermal stresses based on previous analyses data were added to these values to develop total stresses corresponding to running and 10% overspeed conditions. Figure D8 shows these stresses under the last stage.

Material Pronerties:

No material properties were available. Typically, nuclear HP turbine rotors are made of iCrMoV ste hich has good fracture toughness properties. However, for the purpose of the present enalysis a fracture toughness of 35 ksidin will be assumed.

Fracture Mechanics Analysis:

Figures D8 and D9 show the fatigue crack growth analysis results for the default flaw and linkup #2 respectively. The number of blocks to reach the critical fracture toughness of 35 ksiVin for the two cracks analyzed ar M767 and 2050 ' espectively. However, it is SPC policy to limit the number of starts and the hours before the next inspection to 2000 and 70,000 hours0 days 0 hours 0 weeks 0 months . Creep crack growth damage is not a problem since the operating temperature is well below 8000F.

3

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m A AXlAL VS RADIAL PLOT OF ULTRASONIC DATA FROM WESDYNE SYSTEMS DETROIT EDISON, FERMI 2 NUCLEAR GEC ALSTROM HP WERTDYN-D, SONIC 457.6/94 AXIAL ZERO. GENERATOR END, THETA ZERO: NO.1 BOLT HOcE THETA RANGE: 0.0 to 360.0 Degrees 8~

W S

t 8

-..............................B..o...r.e..............................................................

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0.0 50.0 100.0 150.0 200.0 250.0 300.0 350.0 AXIAL - lN.

SPC, SONIC 457,6/13/94 w

l\\

f b-AXIAL VS CIRCUMFERENTIAL PLOT OF ULTRASONIC DATA FROM WESDYNE SYSTEMS DETROIT EDISON, FERMI 2, NUCLEAR GEC ALSTROM,HP,WESTDYN-D, SONIC 457,d/94 AXIAL ZERO: GENERATOR END, THETA ZERO: NO.1 BOLT HOLE DEPTH RANGE: 0 to 10 "

o 8

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AXIAL - IN SPC, SONIC 457, 6/13/94 a ~

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F AXIAL VS RADIAL PLOT OF ULTRASONIC DATA FROM WESDYNE SYSTEMS DETROIT EDISON, FERMI 2, NUCLEAR GEC ALSTROM,HP.WESTDYN-D SONIC 457,B/94 AXIAL ZERO: GENERATOR END THETA ZERO: NO.1 BOLT HOLE THETA RANGE: 0.0 to 60.0 Degrees 8

vi 1I g

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..........................B..o..r.e................................................................................................

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310.0 314.0 31 8.0 322.0 326.0 330.0 l

AXlAL - IN.

SPC, SONIC 457,6/13/94 l

4 1

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y 1

5 D'

AXIAL VS CIRCUMFERENTIAL PLOT OF ULTRASONIC DATA FROM WESDYNE SYSTEMS DETROIT EDISON, FERMI 2, NUCLEAR GEC ALSTROM,HP,WESTDYN-D, SONIC 457,b/94 AXIAL ZERO: GENERATOR END, THETA ZERO: NO.1 BOLT HOLE DEPTH RANGE: 0 to 10 "

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322.0 326.0 330.0 AXIAL - IN SPC, SONIC 457, 6/13/94

_ v;r4 Y

o s N-

P%

j AXIAL VIEW PLOT OF ULTRASONIC DATA FROM WESDYNE SYSTEMS.

DETROIT EDISON, FERMI 2, NUCLEAR GEC ALSTROM,HP.WESTDYN-D, SONIC 457,6/94 AXIAL ZERO: GENERATOR END, THETA ZERO: NO.1 BOLT HOLE ODEGREES

.i AXIAL RANGE: 310.0" to 330.0" F

's

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1 SPC, SONIC 457,6/13/94

, gg

(

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k

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DETROIT EDISON, FERMI #2, NUCLEAR GEC ALSTROM, Hp, WESTDYN-D, SONIC 457, 6/94 s

bore diameter = 9.976 from 0.000 to 225.000 6.047 from 234.000 to 346.000 f

\\

Entered Ellipse Parameters

- Zone #

Depth a

b c

1 2.000

.100

.150 2

2.000

.100

.150 3

2.000

.100

.150 4

2.000

.100

.150 5

2.000

.100

.150 mm dynacon threshold =

0

- no. of data points =

13

- search units selected: 1

Petition ---------------------------

linkup no.

axial, in.

circus. deg.

in.

radial, in.

no.

pts.

x dx theta dtheta mean r

dr start diff start diff width start diff 1

2 320.25

.25 12.78

.11

.010 2.30

.03 2

8 321.00 1.25 13.13 1.58

.140 2.00

.35 3

2 323.25

.25 15.03 1.03

.089 1.93

.02 total no. of linkups =

3 RESULTS OF LDEUP ANALfSIS FIGURE D7 e **

p

-. _ ~.

7 N

DETROIT EDISON, FERMI #2, GEC HP, DEFAULT FLAW, 6/94

\\

Stress distribution used for calculating K1 values OVERSPEED RUNNING Distance-in Transient Stress-ksi Steady State Stress-ksi

.00 45.900 40.500 1.00 41.200 36.600 2.00 38.400 34.300 3.00 36.600 32.900 5.00 34.600 31.200 Entered fracture toughness = 60.0 Flaw Dim: dx:

.250; dr=

.125; r=

.000 ELLIPTIC SURFACE CRACK GROWIH ANALYSIS FOR LINKUP NO. default No. of cold starts /overspeed run = 10 al a3 SIF1 SIF3 NO. BIDCES

.1250

.1250 19.1298 20.1586

.0000E+00

.1361

.1375 20.0379 21.0550

.2452E+03

.1483

.1511 20.9786 21.9910

.4874E+03

.1616

.1659 21.9537 22.9681

.7265E+03

.1762

.1821 22.9653 23.9881

.9630E+03

.1922

.1997 24.0154 25.0527

.1197E+04

.2097

.2190 25.1057 26.1636

.1428E+04

.2288

.2399 26.'2380 27.3226

.1657E+04

.2498

.2628 27.4142 28.5314

.1883E 04

.2726

.2878 28.6361 29.7919

.2107E+04

.2976

.3150 29.9053 31.1061

.2329F+04 j"3

.3248

.3448 31.2237 32.4759

.2549E+04 MJ1

.3546

.3773 32.5930 33.9034

.2767E+04 +

b

.3871

.4127 34.0152 35.3910

.2982E+04

.4225

.4514 35.4921 36.9408

.3196E+04 p':

.4612

.4937 37.0257 38.5555

.3408E+04

.5033

.5398 38.6181 40.2377

.3618E+04

[

.5493

.5901 40.2715 41.9904

.3826E+04 t.

.5994

.6451 41.9883 43.8170

.4033E+04 i

.6539

.7050 43.7712 45.7210

.4237E+04 s

.7133

.7704 45.6232 47.7066

.4440E+04

[_

.7780

.8417 47.5478 49.7786

.4641E+04

.8483

.9195 49.5490 51.9424

.4840E+04 C

.9248 1.0044 51.6312 54.2042

.5037E+04

(

ls 3

FATIcUE CRACK GROWTH ANALYSIS RESULTS FOR THE DEFAULT FLAN p\\

FicUmE D8

.E.

A m

.~

_. _ _ _ _ _ _._..__.~ _

i q'

Stress distribution used for calculating K1 values OVERSPEED RUNNING Distance-in Transient Stress-ksi Steady State Stress-ksi l

.00 45.900 40.500 l

1.00 41.200 36.600 1

2.00 38.400 34.300 3.00 36.600 32.900 5.00 34.600 31.200 Entered fracture toughness = 60.0 Flaw Dim: dx= 1.250; dr=

.350; r=-

2.000 BURIED ELLIPTIC CRACK GR0im! ANALYSIS FOR LI!OUP NO. 2 no. cold starts /overspeed run = 10 al a2 a3 SIF1 SIF2 SIF3 NO. BUXlKS

.1750

.6250 24.0119 24.1802 18.5627

.0000E+00

.1923

.1925

.6347 24.9455 25.1978 19.4727

.2220E+03

.2112

.2118

.6455 25.8886 26.2399 20.4203

.4447E+03

.2318

.2329

.6575 26.8391 27.3067 21.4059

.6683E+03

.2543

.2562

.6710 27.7947 28.3983 22.4299

.8933E+03

.2788

.2818

.6862 28,7536 29.5158 23.4923

.1120E+04

.3055

.3100

.7031 29.7144 30.6608 24.5932

.1349E+04

.3346

.3410

.7220 30.6765 31.8360 25.7323

.1580E+04

.3662

.3751

.7433 31.6399 33.0450 26.9094

.1814E+04

.4005

.4126

.7670 32.6057 34.2930 28.1240

.2050E+04 C

.4376

.4539

.7936 33.5757 35.5861 29.3760

.2290E+04

.4779

.4993

.8233 34.5528 36.9324 30.6651

.2533E+04

.5214

.5492

.8564 35.5405 38.3416 31.9911

.2779E+04

.5683

.6041

.8933 36.5428 39.8259 33.3540

.3028E+04

.6188

.6646

.9343 37.5636 41.4004 34.7539

.3280E+04

.6732

.7310

.9797 38.6064 43.0845 36.1908

.3534E+04

.7314

.8041 1.0298 39.b734 44.9043 37.6641

.3790E+04

.7936

.8845 1.0849 40.7647 46.8957 39.1725

.4048E+04

.8598

.9730 1.1450 41.8778 49.1100 40.7131

.4305E+04

.9297 1.0703 1.2102 43.0055 51.6218 42.2799

.4561E+04 1.0030' 1.1773 1.2801 44.1349 54.5422 43.8633

.4814E+04 1.0787 1.2950 1.3542 45.2454 58.0385 45.4473

.5060E+04 s

FATIGUE CRACK GROWTH ANALYSIS RESULTS FOR LINKUP #2 FIGURE D9

)

7

-e-~--**y

(

y w......

]

_ _. _.. _ _ _ _. _ _ _.... _. _ ~ __

v.'

q C * "l'N"W j% le.

r, n v,,, n,, v,.,,,

er j

f g;/jy 'D C C o wvu-s -r u n a snu W

l h

J2C F d #

0801.21 s-l Date:

July 21,1994 i

TMTB-94-00ll

]

To:

W. D. Romberg Assistant Vice President and Manager, Technical i

From:

L. C. Fron Director, Turbine & Special Projects

Subject:

LP Turbines Operated With 7th and 8th Stage Pressure Plates 2

His memo is being written to assemble, organize and summarize documents applicable to the above subject. The EF2 Main Turbine Generator has experienced problems with the LP 7th and 8th stages of rotating blades. Due to this fact, reviews were performed to determine the safety and reliability of operating the Main Turbine Generator with the airfoils removed from the 7th and 8th stages of rotating blades and pressure plates installed in place of the 7th and 8th stage diaphragms. Results of these reviews show that the turbine can be operated safely and reliably in this modified configuration. The plan is to run for one cycle in this modified configuration and then to install new LP rotors and diaphragms.

He following actions were taken to investigate and determine the safety and reliability of i

operating in this modified configuration.

l

1. De pressure plates were designed by the original equipment manufacturer (O.E.M.), GEC.

De basis for the GEC design is documented in a memo from A. Holmes to L. R. Gobbett, dated 7/26/94, which is included as Attachment 1. T11e pressure plates were designed to replicate the pressure drops exhibited by the stationary and rotating blades they are replacing. GEC provided a review of their experience in designing pressure plates and the operating experience with those installations. The applicability of this experience to the proposed design and installation at Fermi 2 was also documented. His document is included as Attachment 2.

2. Westinghouse provided a summary of their design experience for pressure plates, and the operating experience with those plates. Dey pres ~ nted this experience and its applicability e

to their review of the GEC design to site personnel. His is included as Attachment 3. As can be seen from this attachment, Westinghouse has a significant amount of experience in designing and operating with pressure plates.

u......

s_

.v

.... v Shv

CONFIDENTI AL &Ny q

\\

1-1

3. Westinghouse performed a detailed review of the GEC proposed pressure plate design using their own design methodology and verification process (Attachment 4). They have concluded that the GEC design is adequate and, indeed, conservative.

4. Technical and Engineering Services (DECO) provided detailed review of the operational experience with pressure plates designed by GEC at Fermi 2. No adverse operational or vibration effects were identified. This review is included as Attachment 5.

5. MPR Associates performed a survey (Attachment 6) of domestic Westinghouse and GE turbines that have operated with pressure plates installed. This survey specifically requested 1

operational limitations and adverse operational effects experienced. The period covered begins in 1970, with more than twelve nuclear plants identified. Experience supports the installation of pressure plates at Fermi, with several plants identified that also installed pressure plates in the last two stages of the LP turbine (s).

6. Failure Prevention International (FPI) performed:

an independent study utilizing their own experience, a.

b. a review of the GEC and Westinghouse identified relevant experience summaries, a review of the Westinghouse conclusions of the GEC design review, and c.

d. a review of the MPR industry experience survey.

FPI concluded that their experience, the Westinghouse design review of GEC design (in light of Westinghouse's experience), and the identified operational experience supports the prudency and viability ofinstalling pressure plates. Their report is included as Attachment 7.

7. A Safety Evaluation (SE) was performed in accordance with 10CFR50.59 and site procedures and it determined that there would be no unreviewed safety question and that operation in this modified configuration would reduce the probability of a turbine missile 9

a.ccident. For additional details, ese Attachment 8 (SE 94-0073).

8. An Engineering Design Package (EDP) has been prepared in accordance with site procedures to document the design and installation of these pressure plates. EDP 26726 is included as.

9. GEC has revised the heat balance for EF2 (Drawing TS 24122) with these pressure plates installed and it is included as Attachment 10.

10. Westinghouse has reviewed the GEC revised heat balance as it affects operability of the pressure plates and faard there are no significant differences from their initial evaluation. 1 documents this review.

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11. The fabrication drawing for the pressure plates, Drawings TI-3687, are included as 2.

4

12. Heat Exchanger Systems, Inc. performed an analysis of the effects on the condenser from operating the turbine with these pressure plates installed and determined that the condenser will operate satisfactorily. This review is included as Attachment 13.

j In summary, these reviews clearly show that the EF2 Main Turbine Generator can be safely and reliably operated with these pressure plates installed.

b I

Attachments i

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GECALSTHOM EMN MEMORANDUM I

To: Mr L.R.Gobbert.

From: Mr A.Hohra:s.

Construction & Service.

P.C.D.G.

Rugby Rugby j

i i

Date: 26 July,1994 Tel: 531(4)946 l

Copy To: File Fax:

I Ref:

i i'

Enrico Fermi Pressure Plates for Stages LP7 & 8 i

With regard to the request by Mr L.Fron for dengn r=h=J for the design of Enrico LP7 &

8 pressure plates we would reply as follows :-

l Tbc Design C=hans for the design of drillaip-plares to replace a tur$ine stage are :-

I

1. To provide a flow area that will maintain the design p-diniiinaion in the ttirbine. *nds will ensure that the turbine cycle remains close to design and in the case of replacing Emico LP7 & 8 that stage w,rmy on stage LP 6 remain as design.

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2. To size the holes so that thejet issuing from the plate will decay mfRdmtly before reachmg the f next stage, (normally a <hn%m) in the case of Em2co LP7 the adT1M plate for LPS and in the p case of Fnrim LP8 the cone of the *e hood.

X

]. To arrange the holes wrthin the annulus of the removed stage.

s

4. To size the thickness of the plate so that it is *% ady strong and deflections are kept within av_hle lizmts (this is done by use of an in house -

-i @ t g= -).

Using the above design <=<ided-we have provided and fitted drh! pressure plates on a MImber of occasions which have emhlM a m ' I # 10 femain Mhly in serv'u:e I

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Large 5emen Twbines l

[

Mr L.c. Fron section Head - Turbine Fermi 2 1

i 10th June 1994 OPERATTON OF FERMT 2 WTTE PRE 85URE PLATES Following telephone conversations with George Trahey and Brian stone, please find attached a statement regarding GEC ALSTHOM cxperience of operating with pressure plates, i

Regards

.,. y P A McCUIRE 1

Copy:

Mr G. Trahey, Farmi 2' l

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NewbeW Reed,Rugbr,Wr ':' 'r.CY212NM,faglend Tif.;;. 0738577111 Telem 314Q GALTO O Feu 0738531700 OEC ALSTHOM TUR8tNE GENERATORS UMffED Regnesered OEm. Newbold Reed, Rugby, Warweks. Vee. "-7: Min EnglandNo.N1951

r Ih certain circumstancas it may a noccosary to operate turbinos for limitad period Lvith a completo stago of fixed and moving bledas removed.

On such cases pressure plates are often installed to avoid"over oading other stages, particularly the j

immediata upstraan stage.

The pressura plata has a large number of small holes of suffic ant area to ensure that the normal stage i

pressura drop and flow rata are maintained. Mne holes are distributed uniformly to minimise flow perturbations and are mised to allow sufficient jet mi before inlet to the next staga}

xing and velocity reduction The first significant use of pressura plates was in the early 1970's when a major rehabilitation exercise was carried out on LP rotors of 60MW turbines.

since t ti e assure lates been fitted to a numbar of turbine

[

Normally the time of operation with pressure plates has been for periods of 6 - 24 months until permanent remedial action could i

be carried out.

In most cases the turbines have been operated without restriction after the installation of the pressure plate and we have no experience of any consequential problems with pressure plates of this type.

There is therefore no reason which would have prevented operation for longer periods.

At Fermi 2 DECO have decidad to remove the last two stagas of LP blading and to instal pressure plates, f which relevant des details have a

been rovidad.

i f

zn espects the sence of any stage owns a

plates represents a less onerous condition.

e pressure i

With the pressure pictes installed the turbine can be operated in accordance with normal procedures and there are no additional restrictions.

cnthalpy of the exhaust steam to the condensar will be greater The than under normal conditions and as a consequanca there vill be o olight increase in condansar back pressure but there should be no adverse effect on the safe operation of tha~ turbina.

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WESTINGHOUSEWOCEEAFI AND FOSSIL ~ BAFFLE

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EXPERIENCE

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BB STAGE

GENERAL COMMENT

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81 L-0 Used at Indian Point # LP3 in 8/86, removal date unknown.

Nuclear L-L-1 Not used yet L-2 Used at Palisades in 2/80, removal date unknown.

T L-3 Used at urry #1 LP#1 and LP#2 from 3/80 to 4/81.

Used a alem # n LP #3 in 4/81, removal date unknown.

Used in Ya 0/81, removal date unknown.

Used a alisade in 1/80, removal date unknown.

Used at ndian P nt #3 1/79, removal date unknown.

Used at ndian Point # from 2/80 to 2/81.

Used a oope}in 6/80, removal date unknown.

L-4 Used at Surry #[LP#1 from 7/78 to 4/81.

above.[,alem, Cooper, and Indian Poi [the sam Used at Used at Palisades 'in 1/80, removal date unknown.

~

L-5 Used aflndian oin3 rom 3/80 to 3/82.

L-6 Used atTalem 6/81 ta12/81.

L-7 Used at}ali in 1/80, removal date unknown.

dce Used at[Haddern Neck}n 3/86, removal date unknown.

Ran with[ Coop rom 3/80 to 4/81. Removed in early '82 4, L-8 L-9 iaJr RAY 80 L-0 Used at Prairie island in 74, removal date unknown. h """"

Nuclear m p,f,

{ Used atjPraine Island #1 fro,)m 74 to L,L-1 Designed for San Onofore.

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( Used aQinn] rom 7 to 78.

Uk L-1 Not used yet.

Used afPrairie Islanhoj. 2 rom 74 to 78.

L-2 Used a inna] rom 76 to 78.

Used at inShan #1 and #2 n 5/80, removal date unknown.

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PRRIANT

~ ' WESTINUMUU5t: NUCLEAR AND POUMIL BArrLE

' ~ ~ '

EXPERIENCE

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L-3 Not used yet.

L-4 Not used yet.

281 L-0 Not used yet.

Nuclear L-1 Not used yet.

MUD} 7/75, removal date unknown.

L-2 Used a Used at Zion) rom 12/79 to 3/81.

L-5 L-6 Used at flus'slesvillejrom 1/80 to 1/81.

L-7 Used a MUD}n 5/81, removal date unknown.

280 L-0 Not used yet.

- Nuclear L-1 Not used yet.

L-2 Not used yet.

73 L-0 Not used yet.

Fossil Used at Sutto}n rom 8/74 to '76. Installed in Summer - S L-1 82.

hWagner4 nnin with L-2. Stage Baffle from 4/79 to '85.

L-2 Used ly # 2 n 4/79, removal date unknown.

Used a tee n 1/85, removal date unknown.

L-3 Used at Horseshoe Lake rom 1979 to 1972.

Used at' Hubba om 1970 to 1972.

Used at]agner 4} rom 8/79 to 3/81.

Used in{CFE Mexic}o n 7/78, removal date unknown 72 L-0 Fossil l

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L-1 Used at

' son rom 9/82 to 12/84. Four ends arrison 1 i

remov n mid L-1C & 2C Not used yet.

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EXPERIENCE

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88111-126 L-1 Not used yet.

RT-2566 L-1 Not used yet. Special Design must be redesigned.

Used ag(Lake Cree]d n 1977, remo L-2 Used at von 8}n 4/85, removal date unknown.

Used atha}removaldate unknown.

1st IP Row Cygn} rom 7/79 to 1/80.

57 L-3, L-4 Used a RST-2566 L-2, L-3 Used athvon 8]n 8/80, removal date unknown.

44 L-2, L-3 (HP)

Used at BoardmaTfrom 6/81 to 5/82.

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IP-13th Used a oardma rom 6/81 to 5/82.

L-0, L-1 (HP)

AB 240 L-2 Used at Somisa m 10/79, removal date unknown.

L-BB46 HP 11C Used at anal 1, Commonwealth Electn[

Replace {d 3 stagesUsed or VEPCO's 10 9 RT-1606G IP,1,2,3 Indian Point.]

dson 1, PSE&G of N.[11/30/83, removal date BB72 L-2 Used at unknow.

BBS1 R3 Used at ncaid #2 n 2/84, removal date unknown.

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PRRh241

Juns 10, 1994 Date:

To:

G. Trahey Fermi 2 Power Plant L. G. Fron From:

Technical and Engineering Services Fermi 2 Main Turbine - Generator Vibration During Operation with Blades Removed and Pressure Plates

Subject:

Inst'alled This memorandum is written in response to our telephonethe subject of w conversation on June 10, 1994; Turbine - Generator (MTG) shaft lateral vibration during operation with pressure plates in place of Low Pressure (LP)

Turbine blade rows.

During Fermi 2 refueling outage RF01, the fifth stage rota MTG operated in this condition from late December 1989 to late November 1990.

In late November 1990, an outage was required to disassemble LP Turbine 3 to confirm fourth stage blade failures predicted by vibration analysis. During this forced outage the LP Turbine 3 fourth stage rotating blades were removed and pressure plates were installed in both flows of LP Turbine 3. The MTG was returned to service on January 1, 1991. The plant operated at 80%

(

power from January 1991 to March 1991 (to refueling o stage blades ~ removed from both flows of LP Turbine 3, and pressure plates installed in both flows of LP Turbine 3 bet with pressure plates in LP Turbine 3, no abnormal shaft lateral vibration was observed. MTG shaft vibration amplitudes were less than 6.5 mils P-P at each bearing at approximately 800 Mw.

As we discussed, if uniform axisymmetric flow is maintained by the pressure plates, shaft lateral excitation should not result.

I am not aware of a situation where two pressure plates were utilized in one flow of a turbine. My arperience of pressure plates effect on shaft vibration is limited to that described above for the Fermi 2 LP Turbine 3.

Rotordynamic characteristics of a rotor will change as a result of removing blades (mass) from the rotor. Reduction in rotor mass results in increasing the critical speeds (shaft lateral vibration natural frequencies) of the rotor.

Removing the eighth and seventh stage blades from both flows of an LP Turbine rotor results in an approximate 7% reduction in rotor weight. Simple rotating beam model calculations predict a less than 5% increase in critical speed due to a 74 decrease in k

7-v-

m

w31ght. Tha LP Turbins rotors op3rsta vary clo30 to th2ir cacond critical cpacds which complicatoo field balancing. Howsysr, balancing characteristics have been established from exParienca

/

and successful balancing has been performed. Therefore,it is anticipated that an increase in the critical speeds on the order of less than 5% will not result in amplified shaft lateral vibration that cannot be dealt with by field balancing.

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MPR ASSOCIATES, INC.

^b# I r

i 320 King street Alexandria, VA 22334-3238 l

(703)519-0200 (703)519-0224 Fax m aber FAX TRANSNITTAL COVER SHEET DATE:

June 13. 1994 70s Brian Stone FRON:

L. Demiek COMPANY: Detroit Edison LOCATION:

FAX NUMBER:

313-586-1772 VERIFICATION No.:

NO. OF PAGES: _I _ INCLUDING C0VER RACHINE: ONNIFAX 893 NE55 AGES t

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MPR ASSOCIATES, INC.

320 Kin Street

/r Alexandfia,VA 22314-3238 (703)519-0200 4 ' "' "',,. /,.. u (703) 519-0224 Fax Ittaiber FAX TRANSNITTAL COVER SHET DATE:

June 13. 1994 70s Brian Stone FRON:

L. Demiek COMPANY: Detroit Edison LOCATION:

FAX NUMBER:

313-586-1772 YERIFICATION NO.:

NO. OF PAGES:

B__ INCLUDING C0VER RACHINE: ONNIFAK 893 RESSAGES o

a ei e.4...

.+

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Table 1 Plants With Operating Experience with j(

Pressure Plates Installed in Place of LP Turbine Stages l

GENERAL ELECTIC PIANTS I

Plant Affected Power Diemian Stage (s)

I.oss (MW)

Brunswick 4TA 15 Installed pressure plate in 1993. Have not 2

inggi.4 since installation. Intend to um.is until outage in 1996. Have no operating restrictions and have not noted any change in vibration or feed system operation.

Nine Mile N/A 22 Installed in the Fall of 1993. No adverse impact of Point 2 inentiation other than loss of power noted. Will be replacing the rotors with monoblocks the next refueling outage.

Oyster SGB' 10 Installed /n 1993. Will inW. in September 1994 Creek when long shank buckets will be installed. No vibration problems noted and there are no Wing restrictions.

Monticello STA N/A Cm.i 4 for a couple of years in the early 1980's with a pressure plate in STA stage. No problems encountered except loss of MW (ActspMess not r

b_nx! but is indicated by GE to be "minimmt"). No' damage was found to downstream stages when rotor was replaced. Stage s.-m.sares at the pressure plate were monitomi to ensure the startup tunsients did not exceed design ramp rates for the plates and that the plates produced the desired pressure ratios. The pressure ratios were -W~y. nis is believed to be the first GE installation of pressure plates in a nuclear turbine.

Millstone N/A N/A We were not able to contact Millstone, however 1

they are,5.4 to have w.isd with pressure plates.

1 Table 2 l

WESTINGHOUSE TURBINES i

l Plant Affected Power Discussion Stage (s)

Imus (MW)

Prahie L-1/L-2 100 The 7.-- plates were instaBed in the 1970s. Tbc j

island 17% power loss was attributed to reduced reactor power (80%) stenuning from flow restrictions acmss the pressure plates. 3,-3=ny, the design pressme drop was not achieved resulting in signi5 cant stress on l

the pressure plates. It was reported that the holes in the pressure plates were not large enough to achieve the desired pressure drop. & station tried to incrisse back pressure but this had no sigam==* e5 set. Tbs j

heater drain temperature increased slishtly.

t l

Surry N/A -

N/A We were not able to contact p-a==f familiar with operation with removed stages. We were informed that l

operating esperience from a decade ago would be unretrievable. However, they are.#ned to have l

operated with removed stage (s).

l Salem 1 2*d N/A We were not able to contact g--

==f fandliar with operation with removed stages. However, they are reported to have operated with removed stage (s).

i

}

Ginna 1 L 001/L.2 e

The unk is rated at 470 MW but generaDy runs at

--490MW (less in summer amonths). The plates were instaBed in 1974 in one of the LP turbines (both barmis) and ran with this con 5guration forshout two j

years untu reblading. The crossover line between mah mones was blanked out during this operation period. No hathat deviation was observed in the feedwater train. There were no limiting condhions for operation and, as such, remetor power was not reduced.

Maine L.2 30 m unit operated at two separate times with pressure Yankee 1 L 2/L.3 do plates installed. The original Westinghouse steam path was.M after the second period ('88) with an ABB design. The pressure plates were approsimately 1 inch thick. The blades were cut off such that the soots r== lad There is no recoDestion of torsional vibtstion analyssa being ML r.d or of any torsional problems during operation with stages removed.

Page 1 of 2 j

s n.

..~..L-.

Toble 2 (continued)

(

WESTINGHOUSE TURBINES Plant A!Escted Power Discussion stsp(s)

Ims:

(MW)

Indian Point 14 15 The pressure plates were used in the mid 1980s widle 3

procuring a new steam path. He actual unit desate was skre to that predicted by Westinghouse. No mI=that deviation was observed in the feedwater train. Ders were no limiting conditions for operetion and, as such, ruector power was not reduced. The blads were cut off such that the roots r-'ah 4

i Page 2 of 2

June 13,199i 021-004 3

i TF7. ECON MEMORANDUM i

Date: June 13,1994 satdeet:

Turbine Pressure 11 ate - Operating Experience Person Called:

Carl Jacobs [ India;, Point 3] (914) 681-6262 4

Person Calling:

D. Lutchenkov The unit has three LP turbines and was operated with pressure plate (s) installed in the I-2 stage (both barrels of one LP turbine only) in the early 1980s. The L 0 was also removed.

The unit lost about 7%MW per stage removed (15MW total) which was the predicted value by Westinghouse. No signi5 cant deviation was observed in the feedwater train. 'Ihere were no limiting conditions for operation and, as such, reactor power was not reduced. However, the blades were cut offjust above the root which, due to SCC in some locations, broke apart sending damaging fragments into the condenser tube bundle.

No problems were reported with pressure plate operation. The plates were about an inch thick.

The original Westinghouse steam path has been replaced with an ABB design. The steam path replacement took 76 days. Signi5 cant effort (~S300K) was expended in sw.ilug the condenser tube bundles with platforms to preclude tube damage from above. Herculized, fire retardant wood was used.

Mr. Jacobs wrote the pim.-6.r-.m M= tion (-60 pages) for the replacement steam path. The spahtion required numerous documentation regarding material composition

..ymi., vibration test results and stress analyses. The sp+"" cation also included the foBowing:

o replacement of Won bellows (the inner cylinder was replaced) o expansion beBows e Hay o

hydraulic bolting replacement of all asbestas gaskets with graphite fiDed o

o June 13,1994 021 004 L

TELECON MEMORANDUM Date: June 10,1994 Sabject:

Turbine Pressure Phte - Operating Experience Person Called:

. Hunter GDpatrick [ Maine Yankee) (207) 882 6321 Person Calling:

D. Lutchenkrvy The unit has two If turbines and was operated with pressure plate (s) instaDed in the LP turbine twice with the Westinghouse steam path as follows:

Early in the 1980s the L3 stage was removed in both barrels (for b= haag) with a total of 30 MW derate. The blades were cut off but the root was retained.

In 1987 the L2 and L3 stages were removed in both barrels i- "" ig in a derate of e

60 MW. Operation was maintained in this configuration for a year untD the steam path was rephced in 1988 with an ABB design. De were cut off but the root was retained. The steam path replacement took 55 days.

No problems were reported with pressure plate operation. The phtes were about an inch thick.

Mr. GDpatrick recommended caning Clayton Giggey (performance,x5604) to discuss detailed impact on operation whDe pressure phtes were installed. Talked to Mr. Giggey on 6/13/94.

He only has experience with the 1987 y.-w plate operation. He indicated that Westinghouse predicted 58 MW derate with the L2 and b3 stages removed. They could not monitor the pressure drop across the plates but did monitor extraction pressures to verify satisfactory operation. No significant deviation was observed in the feedwater train.

There were no luulia.g conditions for operation and, as such, reactor power was not reduced. Mr. Giggey will forward any operating data avanable which spanned this period of operation.

~+

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June 13,1994 021-004

(

TELECON MEMORANDUM Date: June 9,1994 Sahject:

Turbine Pressure Plate - Operating Lperiesce Person Caned:

Joe Eastwood [ Surrey) (804) 273-2730 Person Cauing:

D.Lmtchenkay Mr. Eastwood does not recaB operation with pressure plates instaBed. In addition, any infonnation concerning this operation would be unretrievable. He could not offer any additional help or leads.

e 6

June 13,1994 021 004 TELECON MEMORANDUM Date: June 13,1994 Sutdect:

Turbine Pressure Plate - Operating Experience Person Called:

Paul Detwiler [GINNA) (315) S24-4446 x8306 Dennis Grandjean [ Rochester gas & Sectric) (716) 724-8062 Person M =-:

D. lartchenkov w,mt, ;. me.a., nn uw hiit yn.-N nm.., ~donuw n e...mm.e man +he) m plates were instaDed in 1974 in one of the LP turbines (both barrels) and ran with this configuration for about two years until reblading. The stages were removed from LP2 due to failure of a blade in the I-2 stage. The crossover line between condenser zones was blanked out during this operation period. There were no limiting conditions for operation and, as such, reactor power was not reduced.

No problems were reported with pre ute plate operation. The plates were about an inch thick.

Note: Originally called Jeff Wayland (Rochester Gas & Bectric) who referred me to Barry Ketchmaryk (x215) who is a performance engineer at the station. Mr. Ketchmaryk referred me to Paul Detwiler who a maintenance engineer at the station. Mr.

Detwiler referred me to his supervisor Mr. Dennis Grandjean at the main office for more detailed information.

i j

June 13,1994 021-004 j

TELECON MEMORANDUM Date: June 9,1994 subject:

Turbine Pressure Plate - Operating Experience Person Called:

Bernie Hang [SAGM] (609) 339-1790 Mark Moncourtois (609) 935 6000 (x2065)

Person Calling:

D. Lutchenkov Mr. Haug recalls that Salem 1 operated with pressure plates instaBed in the 2nd stage (from front) in the early 1980s. He does not have any specific details about operation with this con 5guration.

e N

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TUTAL P.09

_ _ _ _ _ _ _ _ _l Gi3MPR A s s O C I AT E S I N C.

l ENOINEERs

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June 14,1994 021004-03 Brian Stone Fermi Unit 2 Detroit Edison Company 6400 North Dixie Highway Newpon,MI 48166

Subject:

Pressure Plate Ynd=Hations at Prairie Island and Ginna

Dear Mr. Stone:

As a follow up to our telephone conversation June 14,1994, the foBowing summarizes the results of our review to date on the use o.! pressure plates at Prairie Island and Ginna. This summary is based on review of the " Grey Books" (Nureg 0020,

" Operating Units Status Repon for Licensed Generating Reactors" for the period January 1974 through November 1978. De grey books were not published prior to January 1974.

i Prairie Island 1 Prairie Island I went critical in December 1973. On 3/9/74 a turbine blade failure was reponed. The plant was operated to m91% reactor power. The report does not indicate the status of the.faned turbine stage. Possibly a pressure plate was instaned. On 4/27/94 another turbine blade faDure was reported. Three stages of LP blading were replaced with pressure plates (called bafDes in the grey books). The unit was then restricted to 85% power.

On September 5,1974 the unit was shutdown to repair the turbine, i.e., replace the blading. De unit was returned to fuH power in October 1974. Maximum dependable power rating was 520 Mwe. The electrical rating was 530 MWe.

ASME turbine cycle best rate tests were performed in November 1974.

No other problems with the turbine or derates due to turbine problems are reported through November 1978. In early 1977 the marimum dependable capacity (MDC) of the unit was decreased to 507 MWe I don't believe that was related to turbine problems because the electrical rating was still 530 MWe.

330 EsteG 5t.ttf ALEEA880em, VA 22314 3888 708 419 4300 sat: 703 519 0234

j Prairie Island 2-The first rsw.ds for Pnirie Island 2 begin in May 1975. Turbine bearing

(

problems required a shutdown of the unit that month.

1 An 1-1 blade failed in the No. 2 LP turbine in December 1975. The last three L

i rows of blading in LP2 were replaced with bafiles. The unit was restricted to j

445 MWs at 100% power.

New LP turbine rotors were installed in December 1976 and the 100% power rating was 1.rmoed to 520 MWe.

He MDC for this unit was also reduced to 507 MWe with an electrical rating of 530 MWe in early 1977. No turbine problems were reported through November 1778.

i Ginna Ginna' began commercial operation in March 1970. A turbine blade failure in the No. 2 LP turbine is reported in the February 1974 status report. ne unit was in an outage for turbine repair. De nature of the repair was not i

described. The plant was returned to 70% power in AprB 1974 "to evaluate turbine blade failures in simDar turbine units". In August and September 1974 power was increased to 91%. In October power was increased to 100%.

On January 19,1976 another blade faBure sused in the No. 2 LP turbine.

Apparently ym.rure plates were installed, because the 100% power rating of the unit was reduced from 470 MWe (MDC) to 415 MWe, The electrical rating of the plant was 490 MWe, Another blade faBure in the No. 2 LP turbine was reported on August 7,1976.

No details on the repair to retan to service are provided.

The plant remained at 415 MWe 100% power rating untB May 1978 when a new rotor was lastaDed in the No. 2 LP turbine. Tbc 200% power rating was returned to 470 MWe. No turbine problems were noted through November 1978.

% have enclosed copies of those pages of the grey books for the pertinent events in cach plant. If you have any questions please give me a cab.

'l S* cerely, l

E. Demick

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y l -4r. m p. w m. g CONHDIEUAL ~ ~ Westinghouse Power Generation 5% ) Electric CEpeen Business Unit CM, j l i l July 13.1994 Detroit Edison Company i Enrico Fermi 2 i 6400 Dixie Highway Newport. Michigan 48166 Attention: I en C. Fron. Sr.

Subject:

Pressure Plating Evaluation Report

Dear Mr. Fron:

Attached is the final report for the Westinghouse evaluation of the pressure plates. I hope that we have providd all of the information that you need. If you have any questions. please call me h07) 28l-5640. Thank you. J Sincerely. -/ A- " Phillip R. RatDff \\ Manager. Turbine Service Programs ( f. ! ' ' " y W M i M....r.

4 Westinghouse Evaluation of GEC Pressure Plates for DECO Fermi 2 Prepared bv1 f Brad A.Steinebronn \\ MatthewTremmel f Larry Fowles Phil R. Ratliff -:,. s,- %h%...w.... .= Westinghouse Proprietary Information P CF

l ? I

1. Introduction in instances, it may be necessary to operate turbines with a complete stue of blades rem

) This plate is designed with a large number of small hoics to ensure that the pressure drop is maintEned at the same level, thus allows for temporary operation. 'de safe and reliable operation the pressure plates must: 1 II. Statement.of Mission When blades in the Fermi 2 Low Pressure turbines failed, the utilization of pressure plates the last two stages of blading was considered as a temporary method for retum to senice. DE decided that OEM should be responsible for any modifications to the turbine, and thus GEC's pressu plate design was conducted. At the request of Detroit Edison. Wrstinghouse rev the L-D and L-1 stage pressure plates. This review focused on the capability of the pressure to duplicate the turbine thermodynanue conditions and the mechanical adequacy of the pres structure. This review was prudent to assure that the plates operate with complete reliability a III. Pressure Plate Experience i Westingbouse has utilized pressure plates in many different steam turbines in the 19 fossil and nuclear low pressure steam turbmes. During this time span, many unprovement on the specific designs and design methodology. Westinghouse's most relevant ex ~ with Northe;m States Power and Rochester Gas and Electnc. reed outage because of blade fa 74horthern States Prairie Island #1)ncounteredwere useTacross the bladi L and L-1 stages. unit tan at MWt. pressure drop to Rochester Gas and Electne Ginna $ After tesung, the In 1976, pressure p tes were i is adv'ancement was significan allowable e drop was raised These tests have shown the turbine can cal operating condiuons. operate at 100% MWt. iwhile staying well below theThis most relevant e for the design of pressure plates. These tools have been compared to actual unn opera performance of the pressure pistes. Specifically. there is egerience in the des wet steam applications in nuclear low pressure steam turbines as exzsts in Fermi 2. Ed 't. I 't

N E"***W Withhold from Fuuu m

1 i IV. Design Evaluation i Utilizing the above mentioned knowledge base. Westinghouse has evaluated the GEC design for the Ferns 2 low pressure turbine pressure plates. Although there are construction differences in design of the pressure plates between GEC and Westinghouse, the applicaten of our tools and experi:nec was jud ed F to be relevam.

1. Thermodynamic Evaluation 1.1 Westinghouse Mmm ofFlow Area

{ De inajority of Westmghouse pressure plates were designed with the aid of an in-hous elo d ^ s e r code. This code has been extensively verifie h field and laboratory te ) ~ i I l I .I, e i( - l { Table I shows the flow condmons used for the Westinghouse evaluation as supplied by GEC (Attachment 1). Because this is not a Westinghouse unit accuracy of these numbers was not verifiable. s- ' ~ .x L.. ...2%p ~- + i I g ....w.o,..a .'../.,..:. :wy m

W e <. p <,

..,,;... 3 P.. ~ J .... J n.... Table 2 shows the resuks of the Westinghouse computer program. All areas include the designed leakage area. _,.7 ..C:, T. ' ,2 + ..s, s.- ., j ; -,, ". - h z s w. .,'.. c. H. T-f. : ^ :'.l.,..- s Q.. ; g.h . 'W l.' 3 -, ...; ; "c C c , C 7,[ While there is me difference in the flow areas, the first pressure plate (which is ' cal) is sized adequatel w e l,ogreary w - es. y..

4 1.2 Estimate ofinlet Total Pressure Because the pressure ratio across both pressure plates is greater than the critical pressure ratio. the flow is choked through the holes. The critical flow equation was applied to estimate the inlet total pressure to each pressure p] ate. Table 3 presents the Westingbouse estimate ofinlet total pressures. ~. y _ 4. o., c., ;yz. 3 . ? s I,,.;. 's e. I y & ';.3..,g. ..,. );. 2 ,.. s :.... w...... ~ a m v. +.....;...,.. . ~..;.- .g L .f. f 1.3 Discussion of Resuks The hole area and subsequent inlet pressure to the lates, as determined Westmghouse. considers the OEC design to be a conservative desi An estanate o ss inpower from last rotating row due to the increase in total pressure was made. Based on the DECO supplied expansion line data (Attachment 2L Table 4 shows the resulting loss in power from stage 6. The additional loss in power is 2.7 MW per end for a total loss of 16.2 MW from the LP due to the change in stage 6 exit conditions only. ? w w. ._ v. ? _,;...; .~ '.. ~

N'.,1-

, ;. e), -

.g ~u 1 ,t,,'.o..,* y

n. t. & s:

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2. MechanicalEvaluation diff

~ m, e.., s'w. used b GEC differs from th 6 esiw used. Westinghouse. The i j e l r,.. _,,. 4 .s . e q -

n L

[ '. ; ; ; p.', ;. N.w e.... r.,9-y ' P c. ...~ :. ,,. m, h 4, ~ ' Y' U-.:. '. g>-.t o Wesinghouse Propneuryide ,, n ~,

.= The GEC method of pressure bame design seems to be sound. although somewhat more conservative than that used by Westinghouse. One concern is the fact that the OEC design requires adequate axial clearance between the rotor disc's and the bam: plate for operation. These axial cicarance concems would not be present in the Weninghouse design. This design type requires the axial clearances should be opened up enough to pmide extra margin due to the deflection of the pressure bames. GEC has stated that the axial clearances as established are sumcient. However. Westinghouse deflection calculations indicate that smaller deflections than the OEC axial clearances should be adequate. The methods for calcu ating maximum seasses and deflections in unifonnly loaded, semicircular 7 _. 7-plates was developed b Arn O. Karamaman and reported in Westinghouse ineerin rt EM-,f y 116 e formulas found.in the were developed based o ' w./.,, e pramanan's} report the methods were checked b te element processes available to ven t a assumptions were valid. This method has been used by Wesnnghouse since the early 70's for pressure bame design. calculation metho minimum safety factor of 2 based on yield strength is used. l ne operaung stresses determmed in the evaluation were within our design allowables for the materia used. The following table shows approximations determmed usmg our design techniques and their value relative to allowables. Stare 7 Pressure Plate V I m-e Mb. N s- -umr-e 'ML 4 .y,;;.. 'l " g g .:... * ; -.,...i.., gle, . j'[ .J:. - L. l,- 41_ ; . o mg ..,. _.. 3 ; g ME y L_ .M 4 ~.-:. ..q ~.

r...n.,,,,

.V. '; - - Wesungbouse Propnetaryinformanon y-. __,-y .,_s

Stare 8 Pressure Plate t i c A V. Design Review The design review was held on 6/14/94 (following Westmghouse Des' As nee Policy)to review the Westingbouse effort of the GEC-Alsthom design of ich would repbce the darnaged seventh and eight stages in the GEC-Alsthoni machine at the Detroit ison Company's Fermi Pha 7 g In general. the review panel felt that the flow areas of _were s!fghtlylower than what was required for Westinghouse's design which had generat Tood fieldorperience at Ginna and Prairie bland However, the difference in area was not great enough to reject the design, as some assumptions had to be made within the calculation procedure. However it was thought prudent to inform Detron Edison of this fact and note to them that the effect on the unit cycle could be a, higher mimmum extracnon pressure and might tmload the sixth stage. These effects were not considered entical to the accomplishmem of the overall task. Other concerns recorded for this review involved the impact on the condenser of an increase best load imposed by dtunping 200 MW into the condenser and subsequently into the environment and the fact that the higher energy last 'on woul e the beater steam teqturements and subsequently increase flow through thelast stag o a manufacunbility concern was recorded. The following concerns were recorded for the review: Contem Wl: Can the condenser handle the increased best load (approximately 200 MW) without any dernmental effects in:)udmg the enviromnental impact. Resoonse: This is a concern to be addressed by DECO, however initial customer feedback is that the condenser has the capacity to handle the additional heat load. Ed.ht:. '9':' '. Wesunghouse Propnetaryinformanon I i

________c_. l Contem #2: Consider itoring the. stage extraction pressure to assure ourselves of proper i operationalimpact of th l Resnonse: he conclusi t th ill cause a higher than designed pressure at the stag: aeven and eight inlets is a co appro relative to blade loading. Based on this conservattsrn. monitoring of the last stage extraction pressure is not necessary. Con-ero #3: Consider runnmg a GPHB to assess the cycle effects of higher energy steam being extracted to the lowest pressure heater. De scope of work to perform a GPHB model was outside the realm of the pressure plate Resnonse: i _ evaluation study purchased by DECO. Considering the conservatism of the GEC design. it was not l necessary toperform this analysis to form conclusions on the GEC pressure plate designs. i e program documentation f Con-em 84 is better than most but the recorded lumtations can be subject to mterpretauon. Resoonse: Abbough the limitations of the subject computer analysis are not well documented the 7 i engineer performed other calculation methods in addition to the computer program to assure the validity of the resubs. i Concern #5: Attemptingto dril j could proven be a difficuk ma cturmg chal The need to ven ill drift could make th' lg costly designtom a manufacturing pomt of vie id be the preferred method ifitzan be accommodated. j Resnonse: Danew of the ma=f=* ability of the GEC pressure plate design with the Pensacola factory revealed tharsleill drift would not be a problem. Pensacola has successfully drilled smaller diameter i bones throug'hibicker steel plate without occurrence of drill drift. f concem #6: As Westinghouse would prefer to use larger d$tmeter holes in their design, we should check to see whatase holes they have used in the 4th and 5th stage baffle plate. i Resnonse: Tk concemis irrelevant. as the GEC specific hole Amater was accepted by DECO. Coneem e7: As a check on our results we should check the stage flows and enthalpies and see if we approxanatette mated 200 MW loss. This would be a quick look check. Response: lined on expansion line data provided by DECO / Fermi the 200 MW estanated loss is correct i for thelossdsinges seven and eight. l coneem 8E: Ewe the seventh stage stationary gaging, we could get a better feel for the accuracy l efou tion and verify some of the assumption we made. Remme: E!!C not provide the seventh stage stationary gaging. so the validity of the assumption ] could notMM i d be concemed if we designed a baffle application that changed an j Concern #9: ouse i extncion pressu 'fied the deviation in extraction pressure that is caused by the GEC Resnonse: W u vuse l thermaldesip .htnhc: i. k. 1 E'nD, Wesunghouse'?ugmesaryinf ~ J

e P Concern $10: We should calculate thi bottoms out in the mounting groove. i n1 think we have a concem here but we shou check. The data was checked, and this does not seem to be a concern. ~ Resnonse: sk GEC if they have checked the ability of the cylinder to pick up th j 1 We dont have enough dunensionalinformation to do this ourselves ny f accuracy. Right now thE doesnt look like a problem but we should ask. A bounding calculation of the cylinder loads imposed by the pressuie plates was perfor Resnonse: by Westinghouse. Dese resuhs were found to be within allowabic values. Concem *12: ne plate support pockets have been damaged (especially in LP3). Will they be clea up and if they are, will they be restored to drawing. Any differences will have to be picked up design of the support keys. Remonse: This concern will be identified in the final report to DECO Fermi for identification and attention during unit restoration No open concerns cust from the design review. VI. Conclusion The technical review of tht pressure plates does not identify any significant deficiencies in the design The application of the Westinghouse knowledge base to the evaluation of the GEC pressure plate that the design satisfies the basic thermodynamic and mechanical strength requirements with ampic conservansm. The turbine should perform safely without operating restrictions. e Ethhoit ::=.. T.#. '. We$lin(boubC PTUpneta!y informanOn

c Drvness Fraction x ) ,e 4 i .a.S l 4 l .l n p. e& g u;;-e .b.*J Attachment #1 m

y l '*

D'**

Wesunghouse Power Generation Electnc Corporation Business Unit in,am, 4400 Atatsys Itail Dun 00 fonda 32826 2339 August 4,1994 Detroit Edison Company Enrico Fermi 2 6400 Dixie Highway Ne@rt, Michigan 48166 Attenuon: Brian Stone

Dear Mr. Stone:

In reference to questions of today, table for Sta 7 Pressure Plate Steam Analysis indica calculate 'al load force 's was an increased by 10% to a n analysis to conservatism to the calculation. The value o calcula non considered the load to be a str.ady load situation, no impact loading considered. Sincerely, I% S. % ) / <h / 'Phillip R. RatlifT V ~ W::.' m e i NN O '.'... NAM 7/.alor N as heiPW

f/ opf ! 'W2"/')l w l \\A International / \\ The Leading Experts sr: Failure Prevenhon & Investigatiott i June 15, 1994 1 Mr. Len Fron j Turbine Supervisor Detroit Edison Company Fermi-2 6400 N. Dixie Highway Newport, MI 48166

Subject:

FPI Review of Pressure Plate Use on Fermi-2 Dear Mr. Frta Par your vernal request of June 11, 1994, FPI has conducted a rcview of various subjects regarding use of pressure plates in 1rrge neam turbines. This review is organized based on discussions with Mr. Brian Stone into the following areas. 1. Experience / perspective on operation with pressure plates / baffles. 2. Review of industry experience as provided by Westinghouse. 3. Review of Westinghouse evaluation for Fermi-2 pressure plates. This review does not attempt to provi(.e an in-depth evaluation of whether FPI would recommend pressure plates versus other turbine repair possibilities such as reblading. It is understood that this analysis has been conducted and the determination has been made to use pressure plates in all three LP rotors fer all L-0 and L-1 rows provided the technical analysis of this installation does not jeopardize turbine operation. The primary purpose of this assessment therefore, is to provide an independent review of current industry experience using pressure plates and review the evaluations conducted by Westinghouse and others for Detroit Ed$ son. This is to support the Detroit Edison Company in ensuring all consideration is given to arrive at the best overall dacision regarding the return to service of the Fermi - 2 turbine. 112 W. Caneda

San Clemente, Calitomse 92672 PhoneiFax:V14) 361-5479 Messages:714) 361 5474

~ 1 Mr. Len Fron-June 14,1994 k FPI Review of Pressure Plate Use on Fermi Page 2 of 4 1. Experience / perspective on operation with pressure plates / baffles. The primary purpose for installing pressure plates is to prevent overloading upstream and downstream stages when it becomes necessary to operate a turbine with rotor blade stage (s) removed. The theory is that the pressure drop through the installed pressure plate is designed to replicate the expected pressure drop exhibited by the stage diaphragm and rotating blading it is replacing. Therefore, surrounding stages continue to have the same pressure forces exerted on them as if the rotating blades wsre installed. The typical industry use for pressure plates has been in reaction stages, usually L.P. exhaust stages for example L-4,L-3,L-2,L-1, and L-0 stages. The industry experience has been good with respect to pressure plate applications. Frthlems which might occur due to improperly designed or Iwcalled pressure plates are: rotor vibration, excessive blade vibration upstream or downstream, excessive noise emissions, overheating of

exhaust, casing distortion (not expected in diaphragm type construction), overheating of condenser expansion

joint, excessive rotor thrust (not expected in double flow design), failure or distortion of pressure plates, unacceptable changes in rotor torsional frequency to name a few.

Certain cperating limitations could be experienced with pressure plates installed such as: reduced generator output, rotor vibration

limits, reduced steam

flow, additional exhaust temperature control requirements, for example: capacity of exhaust sprays, capacity of exhaust cooling water system, condenser heat removal

capacity, cooling water system capacity.

The above must be considered when installing pressure plates.

However, pertinent experience in the use of pressure plates occurred at the Southern California Edison Mohave Generating Station.

Mohave Generating Station is a 790 megawatt coal fired supercritical unit using General Electric double flow L.P. steam turbines. These are 1800 FPM turbines with L-0 blades of 52", L-1 = 34", and L-2 = 22.5". Both units have experienced problems on different stages resulting from disc cracking and both required the use of pressure plates. Unit 1, L-2 stage cracks ware in the rotor dovetail. Unit 2, L-1 stage had a disc bore crack at a keyway. These units are similar to the Fermi 2 turbine in that they both employ diaphragms. No operational problems were experienced with either Mohave unit which were N wI \\1 I b International m --.4

e k Mr.Im Fron. June 14.1994 FPI Review of Pressure Plate Use on Fermi Page 3 of 4 2 operated with pressure plates for over 1 year. Therefore, based on the above discussion and knowledge that pressure plates have been used throughout the industry on numerous occasions without adverse consequences, it is our conclusion that pressure plates are a suitable alternative for the Fermi - 2 turbine. This similar question was posed to FPI personnel during a recent presentation to the Detroit Edison Board of Directors. When asked if FPI personnel thought pressure plates were a viable alternative it was stated that after hearing the entire presentation by Fermi personnel we would concur with the decision to install pressure plates for one operating cycle. 2. Review of. industry experience as provided by Westinghouse. FPI reviewed a series of documents that were prepared for Detroit Edison personnel by GEC Alstrom and MPR Associates. These documents provide the results of industry use by the three major turbine vendors: GEC, G.E., and Westinghouse, of pressure plates. FPI's conclusion based on the review of this industry data compilation is that it supports our conclusion expressed in item 1 above that the industry experience concerning use of pressure plates has been successful. Therefore, this reinforces FPI's overall conclusion that use of pressure plates for the Fermi 2 turbine is a suitable alternative solution. 3. Review of Westinghouse evaluation for Fermi-2 pressure plates. FPI reviewed a draft memo Willip R.

Ratliff, Ngr.

Turbine Sarvic'e Programs of Westinghouse Electric Corporation to Len

Fron, Sr.

of Detroit Edison

Company,

Subject:

Westinghouse Evaluation of GEC Design Pressure Plates for Fermi 2, dated June 14, 1994. This document presents Westinghouse Electric ' Corporations technical assessment of the GEC design for Fermi 2 turbine pressure plates. This points to the facts that Wastinghouse has utilized pressure plates successfully in many cpplications in the past 20 years which is important from a practical industry experience standpoint. In addition they have d2veloped tools which have provided them both analytical and ermirical design basis for reviewing pressure plate designs. They express confidence in their capability of reviewing the GEC f \\ \\ wf \\ international

( Mr.1 m Fron-June 14.1994 FPI Review of Pressure Plate Use on Fermi Page 4 of 4 design using their tools and have done this through their design review process. The Westinghouse review process concludes that the thermodynamic design of the GEC pressure plates closely matches the Westinghouse predictions. The memo also goes on to describe other evaluations that were performed to validate the sdequacy of the GEC design for the pressure plates. Thus, the FPI review of the Westinghouse analysis concludes that the Westinghouse review and validation process adequately considers those parameters necessary for pressure plate design and that the GEC design meets those requirements. In conclusion, FPI conducted an independent review based on the decision by Detroit Edison to install pressure plates for L-0 and L-1 turbine blades. This review determined that although there are certain special considerations as described. above which chould be considered prior to installing pressure plates it was demonstrated that Detroit Edison took the necessary prudent steps to examine those considerations to allow installation of pressure plates for the Fermi-2 turbine. In fact, multiple independent analysis were conducted to provide assurance that this is a prudent and intelligent decision based on facts available at tais time. Please feel free to contact me regarding any questions you might have regarding'"the above subject. Sincerely, ) ec r Codcurre/ce: Mr. Ra ph Ortolano ec: Dr. Chung Chiu \\ W ! \\ 4 International

-y EDP - 2672i) Type [X] 1 {] 11 index itim No.1 l l Rrv 0 Pace 1 of 1 !Nig?-pO" . ' MQ.j!EA1tTh3DElmPr==NJEYb_., 4$.hd:.li I A) Title ELIMINATION OF THE 7TH AND 8TH STAGE LP TURBINE BLADES AND PRESSURE PLATES INSTALLATION B) System PIS Number (c) N3011C001 C) Commitment References D) Responsible Group E) Responsible Engineer F) QA Level MECHANICAL R.TASSELL [] 1 [] 1M [X] Non-O G) Selamic Category H) Piping [] A [] B I) Simulator impact [] l [] II/I Groups [} C [] D [X] Yes [] No [X] None [] D+ [X) NA J) Trainingimpact K) Change Paper CECO L) EQ Central File /EQ M&S [X] Yes [] No [X) Yes [] No Requirements impact [] Yes [X] No M) DVRP Required N) Spare Parts impact O) SE Required [] .No [] Yes [X) No [X] Yes [] No [X] Yes, SE Numbeg 94-0073 '., ' ~ PART2: ENGINEERING OPEftABil(( b6NSTFbdNTShkMY;)Q[" " A) leaued with EOC B) Revised to Remove EOC [] No [ lif Yes, EOC No.: [] Yes '[ ] No C) EOC Description / Removal Explanation [] NA WART 3 SIGNATdR5' N%iT 2 ~ S A) Prepared By R. L.TASSELL Print & Sion 8 -/ # Date 6-/ 7t' B) Checked By Print & Sion A.AN .O# Date Id/5 Y C) Approved By Project Engineer (Support Organization only) [X] NA Print & Sion Date f-2-W D) Concigrred By PMRG (PMRG Leader) [X] NA Print & Sion Date NM T-2-9 Y 4 Print & Sion Y '44W F..sc#ur4MAA/ E) Approved By fot C: E //eu!An Date S-)~$Y F) Approved By OSRO'(OSRO Che n) [] NA Print & Sion d.#.AtowA m - 2 1 //.7 % Date 8/e /r < / / / ARMS -INFORMATION DSN %"77_[o.Ol l Rev @ l Dete D-3-9k DTC: TCEDP l File-1801 l DECOM Related: I X 1 Yes l Recipient 1[d J Form FIP-CM1 12 Att 1 Pg 1/1060394 i t. = - - -

EDP -26726 index lt m N o. 2

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Rev 0 Page 1 of 1 w-e r a.. T5 Y S S.$$$iG5k. :$,$.m.i._.. ,- -hm tvew$.z < -N ~m * ~ item No. Item Description item Rev. Remarks 1 EDP COVER SHEET O 2 EDP INDEX SHEET O 3 LtST OF BCDD'S TO BE REVISED 0 4 SCOPE OF EDP O A) PURPOSE /OBJECTIVG B) GENERAL DESCRIPTIOrJ C) FUNCTIONAL DESCRIPTION D) JUSTIFICATION E) DESIGN INPUT

1) DESIGN BASIS

2) ALARA

3) FIRE PROTECTION

[

4) SECURITY

5) HUMAN FACTORS F) NUCLEAR TRAINING /

SIMULATOR IMPACT G) UFSAR IMPACT 5 PRELIMINARY EVALUATION O 6 REFERENCES O 7 LIST OF MATERIAL .O 8 INSTALLATION INSTRUCTIONS O 9 PMT/ DESIGN CHANGE O ACCEPTANCE TEST (DCAT) O 10 Pressure Plate Mxlifications to O j Drawings R LA 94 04766 (T1-3687), R200 A15462 (T13668) & R265 A3

- a 3077 (T13689) 11 TURBINE DESCRIPTION CHAPTER O

7/ LP. TURBINE (VMT1 1.1.7) 12 Mse. Vendor Drawings 0 = il h h L.Q.,J.g. d.i:: igd;stPART.2: SIGNATU_RES w. A) Prer,ared By R. L.TASSELL []NA B) Checkey [p [] NA Sion 6P/M Date #67v Sion S W r7/ Date N7y A RMS -INFORM AT!ON SERVICEG tirc:7(Erjp DSN:37&Q%),REv: p %..s.51P-CM1-12 Att 2 Pg 1/1 D50793 DATE:6-S-Q 4 RECIPIENT NO: c3 M

' ARMS -INFORMAT!ON SERVICEG gop,.2s726 ( DTC: 77"pDp DSNM7XCDSREV:g, Inder ttom N3. 3 DATE: 6 1).CJ4 RECIPlENT NO: MQ Rev 0 Page 1 of 3 i MI ,bN [h[ I ARMS ARMS ARMS. Description or Description of Change / DTC DSN Rev Other identification Affected CECO P!S No. TMINSL VMT1-1.1.7 B TURBINE DESCRIPTION See Index item 11 CHAPTER 7/ LP. TURBINE DDVEND LA 146X69 K LP 3 SHAFT AND BODY See index flem 12 GROOVING (T1569) DDVEND LA 231X69 M LP 2 SHAFT AND BODY See index Item 12 GROOVING (T1568) DDVEND LA 230X69 L LP 1 SHAFT AND BODY See index hem 12 GROOVING (T1567) DDVEND R277A874 H LP 1 CYLINDER ARRGT. & See index ltem 12 PG.1 RECORD OF CLEARANCE (T1 1187) DDVEND R277A874 J LP 1 CYLINDER ARRGT. & See index item 12 PG. 2 RECORD OF CLEARANCE (T1-1187) DDVEND R277A875 H LP 2 CYLINDER ARRGT. & See index item 12 PG.1 RECORD OF CLEARANCE (T1 1264) DDVEND R277A875 L LP 2 CYLINDER ARRGT. & See Index item 12 PG.2 RECORD OF CLEARANCE (T1 1264) DDVEND R277A876 H LP 3 CYLINDER ARRGT. & See Index Item 12 PG.1 RECORD OF CLEARANCE (T1-1265) DDVEND R277A876 J LP 3 CYLINDER ARRGT. & See index item 12 PG. 2 RECORD OF CLEARANCE (T1-1265) DDVEND TS 17280 B DIAGRAM SHOWING See inclex item 12 OPERATING CONDITION UFSAR FIG.10.1 1 (T1 1598) LCR-94149-UFS }& DDVEND R LA 94 A LP STAGE 7 & 8 PRESSURE See index item 10 >D 04766 g]S{1pB7) DDVEND R200 A15462 G SPECIAL SOCKET HEADED See index item 10 SCREWS (WAISTED) B.S. FINE (T1-3688) DDVEND R265 A3 3077 M LOCATING PEG FOR See index item 10 DIAPHRAGM (T13689) m fC..T.C.... T. : 9t.'C..'.Q..9Wh. PARI.2GSIGNA, TUF-

C 3

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A) Propered By R.L.TASSELL [] NA B) Checked y [] NA Sion f f k // Date 9-/ 7'/' Sign J t'24 Date ik/gs. BCDDs TO BE POSTED / REVISED Form RP-CM1-l? w 5 Pg 1/1050793 r* ~ t

j EDP -26726 i [ index Item N3. 3 j Rev 0 Page 2 of 3 FART 1: CONTENT ARMS ARMS ARMS Description or Description of Changel DTC DSN Rev Other identification Affected CECO PiS No. l TLEQlP CECO O CENTRAL COMPONENT (CECO) PIS # N30110001 DATABASE (Electronic CECO) 1 l l l l I l l 1 PART2: SIGNATURES A) Prr.. pared By R. L. TASSELL M NA B) Checked By N NA l Sign Date Sign Date ~ ~ ~ - -. ~, _,,. Form FIP-CM1 12 Att 3 Pg 1/10%is3 ...,3

(R;ferences on ARMS) j l I ~ EDP 26726 ( index item No. 3 Rev 0 i Page 3 of 3 l Im:rd << 'y,js- > r -y-g-y 1 ))_ ARMS ARMS ARMS Document Deecription Description of Change DTC DSN Rev VSSERC SE-S4-0073 SAFETY EVALUATION FOR ISSUED TO SUPPORT THIS EDP EDP 26726 TDLCR 94-149-UFS LICENSING CHANGE REQUEST ISSUED TO SUPPORT THIS EDP TDFSAR UFSAR 6A UPDATED FINAL SAFETY SEE LCR-94149-UFS FOR ANALYSIS REPORT CHANGES DDVEND R LA 94 A LP STAGE 7 & B PRESSURE ISSUED TO SUPPORTTHIS EDP 04766 PLATES (T13687) DDVEND R200 A1 S462 G SPECIAL SOCKET HEADED ISSUED TO SUPPORT THIS EDP SCREWS (WAISTED) B.S. FINE (T13688) DDVEND R265 A3 3077 M LOCATING PEG FOR ISSUED TO SUPPORT THIS EDP DIAPHRAGM (T1-3689) DDVEND TS 24122 A DIAGRAM SHOWING ISSUED TO SUPPORT THIS EDP OPERATING CONDITIONS AT 105% REACTOR FLOW - LP STAGES 7 & 8 REPLACED WITH DRILLED PLATES f e;- :w y--- 'MPA.R..T,2.:.'.SI.GN.X..T..URES*Mf_ _ Y D._ -- - - -- -a.u .-2 ,e-A) Prepared By R. L. TASSEL.L )(NA B) Checked By N NA Sion Date Sign Date T Form FIP-CM1-12 Att 3 Pg 1/1 D50793

EDP -26726 Index item ND. 4 '( R5v 0 Page 1 of 2 SCOPE OF WORK A. PURPOSE / OBJECTIVE. Due to the failure on December 25,1993 of an eighth stage blade on the number three Low Pressure Turbine (LP3) and the resultir.g damage found during investigation, this EDP allows the operation of all three LPs without their j seventh and eighth stage blades for one fuel cycle or until new LP Turbine sectons are available for installation. The new LP sechons are expected to be delivered in early 1996 and installed during RFOS, B. GENERAL DESCRIPTION. This EDF includes removal of all the seventh and eighth stage blades on three LP's. The disc blade serrabons will i be protected by root blocks, which are fabncated by cutting the blades at the bottom of the airfoil. For those 7th a { 8th stage blades, which had destructive testing done or an unacceptable NDE of the roots, a root block will be fabricated and installed by Westinghouse during straightening and balancing of the rotors at the factory. To account for the removal of the blades, the 7th and 8th stage diaphragms will be removed and pressure plates will be iristalled. ) C. FUNCTIONAL DESCRIPTION: With this modification installed, the turbine / generator output will be reduced by approximately 200 megawatts during the next fuel cycle, per discussions with the Turbine manufacturer, GEC/Alsthom. Feedwater heaters 1 and 2, located in the neck of the condenser under each LP, receive their steam from extrachon points before stage 8 and stage 7 blades respectively and the steam after the 8th stage is exhausted directly into the condenser. The pressure plates are designed to restore the pressure drops across stages 7 & 8 to values similar to having the blades and diaphragms installed. Thus, stage 6 blades will not be overstressed and the thermodynamic effects on the feedwater heaters and the condenser will be minimal. D. JUSTIFICATION. Remov5L1 of the LP 8th stage blades eliminates the potential of on 8th stage blade penetrating an LP hood which is what occurred in the December 25th incident. The LP 7th stage blades are being tornoved due to indications found during inspection of some of their roots. Management's decison is to remove these blades and replace them with pressure plates until RFOS, at which time newly designed LP rotors and blade sechons will be installed. The pressure plates have t>sen designed by the turbine manufacturer, GEC/Alsthom, with an inuependent review performed by Westinghouse Electric Corporation Turbine Services group and found to be acceptable as an interim measure until the newly designed rotors and blades can be installed. ARMS-!NFORMATION SERVICES DTC:7CW) DSN:MQ,.@4CEV:@ DATE: d-Q-Q 4. RECIPIENT NO:M g( 79 av, sy, ~ 'SKnNATURESM jp MMpME A) Prepared By R. L.TASSELL B) Checked Sign f/ M/ Date to-/-rf Sign Date 1/t/s y ~ Form FIP-CM1 12 Att 6 Pg 1/1050793 g... 9 ...J L...

EDP.26726 ind';x Item N3. 4 R'.y 0 ( Page 2 cf 2 SCOPE OF WORK (Continued) E DESIGN INPUT.

1) DESIGN BASIS Per GEC/Alsthom, the plates are designed to provide a similar pressure drop for the blades and diaphragms they are replacing. The revised heat balance provided by GEC/Alsthom (Edison File # T1-3690) indicates approximately 17% reduction in rnegawatts, approx.10% increase in condenser heat load and only minor changes in the balance of the thermal cycle conditions. See SE 94-0073 for a detail evaluation of the j

changes.

2) ALARA The turbine is typically a low radiation, contaminated area during outages. All work should be in accordance with normal radiation protection requirements.

Removing the LP's 7th & 8th stage blades and replacing them with pressure plates results in an insignificant change in the steam conditions (pressure & temperature) to the feedwater heaters or condenser. Therefore, this change does not affect any radiation assessment calculations or exposure dnses.

3) FIRE PROTECTION This design change conforms with, and does not adversely affect, the plant Fire Protection Program. The modification is all within the LP turbine casings. There are no additional combustibles being added or any fire bamer penetrations being breached as the result of this EDP.

4) SECURITY This EDP does not involve any safeguard information, nor does it impact any Physical Security Plans, Systems or Facilities.

5) HUMAN FACTORS The modifications in this EDP replaces the LP's 7th & 8th stage blades and dephragms. There is no impact on any control center components or local controls. Therefore, human factors are ne',.fected.

F_ NUCLEAR TRAINING / S!MULATOR IMPACT The training material should be revowed and changed as required to address the removal of the LP 7th & 8th stage blades & diaphragms and the replacement with pressure plates. The only change to the simulator, if any, would be the slight change in the operating conditions of the condenser, heater drains and number 1& 2 heaters. as well as MW Output These changes can be seen by reviewing the new hest balance provided by GEC/Alsthom (Edison Fiie # T1-3C90) against the previous one shown in UFSAR fig 10.1 1 (Edision File # T1-1598). G.UFSARIMPACT

1) Fig.10.1 Heat Balance at 100 Percent Reactor Flow, temporarily replaced with a new heat balance.

2) Sections 10.1,10.2,10.3, and 10.4 will also require changes.

c;y.e ud @ :, M ATURESl yg#(. N @ N .a5 ^ 7 A) Prepared By R. L TASSELL B) Checked y Sign f.f%// Datep+7Y Sign 1 Date V2h s. Y Form FIP CM1-12 Att 6 Pg 1/1050793

y curwan n-dtC:-ppg DSNMU"' NEE Rv0 [DATE:g,3 Q RECipl:tn tiO: $M PRELIMINARY EVALUATION Page 1 of 3 PART1: DESCRIPTION OFCHANGE(Preparer) A) Documentidentification B) Revision if Approved C) PiS Number EDP 26726 0 N3011C001 D) Desenption of Change Replace all three LPs 7m & Sm tage blades and diaphragms with pressure plates. s PART2: PREUnflNARYEVALUATION(Preparer, Approver) A) Review of Commitments [] No commstments [X) Commitments Exist (Identify in accordance with 6.1.4.5) See name 2 [X) Commitments Met - none negated [] Commitments need changing - Describe and justify commitment changes on continuation sheet [] Safety Engineenng and/or Nuclear Licensing have been contacted to make changes B) Impact on License, Plans, or Programs [ Check box (es) rf no impact] No No No impact impact impact [X) Operating License [X) Quality Assurance [X) Offsite Dose Calculation [X) Technical Specifications Program Manual (ODCM) (including Bases) [X) Radiological Emergency [X) Process Control Program [X) Environmental Protection Response Preparedness (PCP) Plan Plan (RERP) [X) Inservice inspection - [X) Core Operating Limits [X) Physical Security Plan Inservice Testing Program Report (COLR) [X) Safeguards Contingency (ISI-IST) [] UFSAR Plan [X) inservice inspection - [X) Fire Protection Program [X) Security PersonnelTraining Non-Destructive and Qualification F!!an Examination (ISI-NDE) [] License Change Request (LCR) required List LCR(s): 94-149-UFS C) Effect on Environment [X) No effect on environment [] Environment affected - contact Fermi Environmental Engineer and indicate resolution l D) Need for Safety Evaluation (check appropnate answer) Safety Evaluation No. (rf required) Yes No [X) [] 1. Is this a change to the facility, including assumptions, as described in the UFSAR? [] [X)

2. is this a change to a procedure, including assumptions, as described in the UFSAR?

[] [X) 3. Does this change constitute a Special Test? if any answers are "yes" and the NRC Safety Evaluation Report as available, attach NRC Safety Evaluation. If any answers are "yes" and no NRC Safety Evaluation Report is available, initiate a Safety Evaluation. If all answers are "no". provide the basis to support that determination on a continuation sheet. E) Prepared by R. SSELL F) pr ved b jj f{& Date 9-/- t Y y, c n. f** nm - Date f*2 ~W "Y LMHt1 E. ScHUEAMAN Form FIP-SRI-01 Att 1 Pl/l 051794 File: 0923.02 f l 1

andex Item N*. 5 Rev 0 ( PRELIMINARY EVALUATION CONTINUATION SHEET Pace 2 of 3 ~ A) Documentidentification B) RevWonif Approved i EDP-26726 0 l PART 2A) REVIEW OF COMMITMENTS (Continued) [X) Commitments Exist (list) CECO RACT 89630,89633,90436,91211,92074,91248 DER 88 2122,89 0245,92-0195 MISC OTH-89-004, SEN 057, NOTE 89-042 i NOIMPACT ALL AFFECTED DDVEND DRAWINGS No Commitments UFSAR RACT 204, 4113,1527, 2156, 2157, 2123, 87288, 3263, 2597, 5851, 4144, 5212, 3756, 3757, 89292,89613,89069,1498,88432,90381 DER 90 0453,92 0497,90-0509 i MISC MISC 032-SUP 1, MISCO32, NOTE 82-003, SOER90-002 RC01 NOIMPACT N3000 RACT 204,1016,1501,6107,7916,90383,90384,91101,91103,94023,94024,94025,94026, 94072,9074,94119,94129 OER DER's 86-044,071,076,079 87-033,065 NO-85 701, NP-84-012 NP-85-061, 438, 499, 546, 593, 635, 654, 701 MISC MISC 044 NOTE 79-037, 80-003, 91 -083, O&MR256, 262, 268, 284, 337 OTH 91-017-LIC9,92 049-AIT,92-054-INPO, SEN 084, SOER-84-006,84-006-RC1 RC7 ~ SER 84-035,84-091,85-006,86 007,91004,91-012,91-016,91018,92-021 SOER-84-006,84-006 r,C1 thru RC7 NO IMPACT f N3011 RACT No Commitments MISC SER 87-005 NO IMPACT ~$ Form FIP SR1-01 Au 2 Pl/l 051794 Fik: 0923.02 .a o 60e %=

index item No. 6 Riv 0 ( PRELIMINARY EVALUATION CONTINUATION SHEET Page 3 of 3 A) Documentidentification B) Revisionif Approved EDP 26726 0 PART 2D) NEED FOR SAFETY EVALUATION (Continued) Response to Questions: 1. This modification is considered a change to the facility, including assumptions, as descrbed in the UFSAR, see Safety Evaluation 94-0073 2. This modification replaces the 7th & 8th stage blades and diaphragms of all three LP turbines with i pressure plates and as stated above is a change to the facility. The effect on the system results in a loss of approximately 200 megawatts at 100 % reactor power and a very slight change in the thermodynamics after the 6th stage thru the number 1 and 2 heatem. This does not change the function of any equipment or system as defined in the UFSAR. Therefore, this is not a change to any procedure, including assumptions, as described in the UFSAR. 3. Due to the major repair work and modifications, including this EDP, as the result of the D6 comber j 25th incident, additional start-up testrng and monitoring will be performed, including the completion of the power up-rate testing that could not be completed last cycle. However, replacing the LP 7th & 8th stage blades and diaphragms with pressure plates does not require a Special Test, as ) described in the UFSAR, the SER, or the Fermi 2 Technical Specifications. The Special Test Section,4.8, described in FMD-CT1 has been reviewed. l 1 Forrn FIP-SRI-01 Att 2 Pl/l 051794 File: 0923.02 w v----- a -m w

EDP -26726 index it:m No. 6 -( Rev 0 Page 1 of 21

REFERENCES:

1. Work Requests for this EDP ARMS-INFORMATION SERVICrts i W.R. 000Z940425 - LP 1 Installation DTC:7PFDp DSNZ7.b.d5REV;@ i W.R. 000Z940426 - LP 2 Installation DATE: 8 a,-Q4 RECIPIENT NO: 'M l W.R. 000Z940423 - LP 3 installation 2. EDP-10533, Turbine LP Blading Row #S npple spring modification performed in 1989. 3. Temporary Modification 940015 / W.R. 00Z942362 - Monitonng of the Extrachon Steam lines in the condenser. 4. Temporary Modification 940016 / W. R. 000Z942363 - Monitoring equipment for piping outside the condenser in the Turbine Bldg. 5. Fax from Mills Alloy Steel Company to G. Kulju, dated 6/8/94 - Material Quostions - Copy attached. 6. Fax from Phillip R. Ratliff, Westinghouse, to G. Kulju, dated 6/9/94 - Response to Material Questions in item 5 - Copy attached. 7. Memo dated 6/9/94 from P. Temple and approved by K. Howard, which was provided to Purchasing (G. Kulju) providing additional guidance in the response to Material Questions in item 5 - Copy attached. 8. Memo to G. Kulju from P. Tracy, dated 6/29/94 - Documenting informaton provided to Westinghouse and Ort Tool on design changes to the fabncation drawings and/or clarification - Copy attached. 9. Memo to G. Kulju from P. Tracy, dated 7/1/94 - Clarificaton of Technical issues related to manufacturing of the pressure plates provided to Westinghouse and Ort, Tool-Copy attached 10. Fax to R. Wynn, Westinghouse and L. Weber, Ort Tool from P. Tracy, dated 7/5/94 - Clarificaten of info provided under item 9 - Copy attached. 11. Fax to R. Wynn, Westinghouse and L. Weber, Ort Tool from P. Tracy, dated 7/6/94 - Clarificaton of orrussions on fabricaton drawing - Copy attached 12. Memo to G. Kulju from P. Tracy, dated 7/7/94 - Documenting informaton pronded to Westinghouse and Ort Tool on design changes to the fabricaton drawmps and/or clarification - Copy attached. 13. Memo to G. Kulju from P. Tracy, dated 7/8/94 - Documenting informabon provided to Westinghouse, Ort Tool and PX Engineering on design changes to the fabncation drawngs and/or clarification '- Copy attached. 14. Westinghouse letter, dated 7/13/94 to L. Fron - Pressure Plate Evaluaton Report. 15. PX Engineering letter, dated 7/14/94 to Gary Kulju LP Stage 8 Pressure Plates 4..cs.

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EDP 4t6726 index kom N3. 4 ~ Rev 0 Page 4 of go t y,,., Facsimile Cover Sheet To: Mr. Gary Kulju companr. Detmh Edson Company Phone: 313 586 4096 Fax: 315-68tM306 Q From:..Phillip R. Ratliff 3 / Company:1 Westophouse Electric Corporation / Phone:f 407 281-5640 Fax: 407-281 5047 d Oste: OIWD944 Pages including this cover pege: 3 Comments: 1he following transmission is in 'esponse to your r request for assistance and approvsf in the disposition of the. defects in the pressure plate matorist. Please call if anything in this response is unclear. I =mm e 1 L. Form FIP-CM1-12 Att 6 Pg 1/1050793 sww

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i d s' EDP.as726 ) index b m ND.6 j R:V0 '( Page 5 of g a % l l euer

e Wesengboues Electic Carpersuen Dear Mr.Kahr i

" and J- ' 7 appnnel fe apeir of 6e defuetrve Thislenar is e convey the._ pnesse plate material es deemibed in our selephone i sbat funber volumseric NDE does act reves! intener defects, Wesunghouse agrees to and approves of abc weld mpair, stress relief and NDE pmosas as a means a sepai 1 W pcovided estpropersepair f The weld repair of te baffle plate is oppoved and W procedwas are folkmed. As part of a proper supeir pmoodse and prior to teinstio 1 sepair,we sogene that 6e veuler esaduer ehresseic tespesh h are presset, advise Wesungbouse i====&ssely before % repeles. If vobenetnc soundsees is haani-t prossed wish pmoussing regered sepair peosedure infonnenen m Waa=pa=== Por final appnnel of 6is repair to be given by Watingbosse, k is segelred abet 6e venj their wel&eg proonderes. l.a. WPS, pQR, qualined in socordemos wie ASME Session IX soview. la addaan, so &is inAmassies, we iogeiro tot the vender psovies a esteiled ese she sovity evesussion (bles&as). MT hopeseios of sevby,wetens, post weld best einenset (PWHT) and flaal aussest Ur inspeceios of Amsbed weld repair. Onse this informsma sensived, Wasaleshomas wcl parvule flest eppmval efIbs repair if the W is found so be anospuble. If the informseiis is famed o k desasst in anyway, spadne snes er _ _. _- " wg1he pnyvidedso DEOD. I hope het you wRI Sed Ibis suspense so be assapenble to bolk DSOD and the ases The Westingbosse appmeabis tseseded e aanse that psoper repair procednes are i foDowed to yield on eenspeabic mesuriel for use b enestrenden af the peensee plass. ..q I t 3 I,.a.. .. ~.. I Form FIP-CM1-12 Att 6 Pg 1/1050793 w w y rwmww mi e,- rwr-v

---w-NWy'

EDP.26726 index item N3. 6 ( Rev 0 Page & of g g Menee have the vender supply aD m, sired h-to : PhillipRsths l Manager. Turbine Service hogranu Westinghouse E3 scene Corpossman MC 101 4400 Alebysthil {MFlorida NM n Ahernetely, tbs respdred sueerial sesy be Faamd to407 281 5047, J a- - i Sincerely yours, -N,E Ky PhilhpR.Railin j ms-Q ec. 'Dat;y Nelson, Westinghouse MC403 Jun Moon, Wanglum=,Dansk \\ l i l I ,,......-q t, " J '...r.... 5. Form FIP-CM112 A* 3 PG 1/1050793 l { l ~ w

1 EDP.28726 index nem Ns 8 Rev 0 k Page 7 of W 21 m FERMI 2 JUNE 9,11194

SUBJECT:

Dakot Edson Pwehsee Drder Det.291082, PLATE WELD REPAIR TECteeCAL REQUIREMENT 5 Redwennes.

1. June 9,1994 Wesenghouse (P. Rartif) ter to Detret Edson (G. IQ4u)

2. June 8,1994 Mas Amoy mool Co. tax to Doest Reson (G. $h4u)

Wilmen ty: P.L Tenpie, Plant Engineertrig [), / / Approved By: K E.Monard, Sipenrisor, Plant Enghoorbis [ Wald repair of to enqA387. Grade 22, Casselh descrbed h 9ts June 8,1994 ter torn Mas Aloy Steel Company r ty be undertaken perufr~ig sansp!ance of tie totomns ortwrie and sie completon of the inwrmooiew asses. These are exposined betow. The end use of these passes requires that they be drmed weh severe! thousand holes and through weiuises integray is very Imperient The repair of sus pises is enneneent ipon seawanos that the pasie has the bespray A Prior to beginning repairs pleses complete the beowing;

1. Repers trey be compisted using the guidenes of ASTM Specfnesten A20 and to toRowing requesmetC. Please submit Die weldin0 procedures Sie weisnB procedure alueencelan repos, and welder quouncolions for review and approval

2. Psesse subma she nondeseuceve exerrunston procat;res and omsasseans of en eneminers who ut perterm pie summinstons. These shalinset tie seguirements of ASNT

( seendard SNT TC 1A,

3. The eutgeot plate shsE be enemined t3 asseritance wlm ASTM am A578.

The scanning penem and exemwiston venuts using Level 1 acceptance artens shal be feported to Detron Edson for approval prior e indhobnB weld sepairs

4. The June s deconenuity seecnpton is interpested a to the owtsas dimensions and does not renset the ech.et depth of each. Please escrete each covby and proport them ter welding. The Snelihmensions of each cavity and to loceton on the plate (merked so tot R con be locawd later) is to also to bmished ter approvet Each sever is e be amones, wunout eherp somers, permRbnD bI baion in tw sevhes. '

5. Magnetic pertels (MT) nondestrucWve eneminsten of each sevty shes be porturmed to ensure that the remoning meterief is sound. A sk (5) hch demeter area beyond the edge of each sevey shes be key econned using ereight besm ieremonic enemnshan techniques to answo tot no emer undetecsed escoreuhes aunt Amospen me einerie ter the momenseone is Leveli of ASTM W AS78.

Re, wire may in hasted tonowine compleson of these noms and e,, rover tem Deben Emmon,

s. weid repair requiremanes:

1. weisne le to be eenvisted using thepeedne procedwes and welders approved by Delreit Edisert Fotowing compiston of was see plate is to be enhor er nomaked and terryered to the original

'-%~.W _ theasseris porturmed the weids must be queened for Wiese heat treatmores. I

2. The Anel wold eurtsono shal be propered tor WT and UT eneminsterL The weeds and one (1) inch around each shal be AAy exemned, haluding a bR acen of the eres by em UT method. The weld and base motorial ehet be sound, wthout sing, porosuy, orsaks, er nonfunkm, and blended unieomey has the pines owtmos.

an End .-t ~~' .M ci s 1 ,e y'.. Form FIP-CM112 Att 6 Pg 1/1050793 u

5.wnw-*

e ,we.

e EDP 28726 Index Item No. 8 Rev 0 Page e of # 2.\\ u s NUCLEAR GENERATION MEMORAhTUM Date: June 29,1994 To: OsryKulju m) )] From: PsulR.Tracy t

Subject:

LP TJ2== - 7th & Rth S*=ee Pr**==e Pl=*e

Reference:

GEC Drawings R-LA-94 04766 Shts 1,2, & 3. A number of technical issues have arisen relative to the fabrication of the subject =am*= Iisted below are the issues and corresponding responses. In eddition, all unresolved issues are also listed. As per our discussion, this memorandum will be faxed duecGy to our suppliers, Ort Tool and Westinghouse. L Resolved Issues A. 'Ihreadedfasteners 1. The refd drawings specify Bntish standard threads and fasteners. 2. The use ofunified iy 0;;dNC or UNB' appropriate,is acceptable. AB bolting shaB be KSTM A193 Grade supplierwillbe j required to have senples of aB bohing used, to be provided to a DECO Quahty Assurance R.,,. t.ative on toquest. 3. AB bolting used to attach the half rings to the pressure plate shall be staked aAer Snal asemaMy. 4. AB other bolting used to attached key, supports, etc., shall RQ1 be =*=kad. B 1. 'Ibe only speci5ed swface Bush, 2 RMSjspp key 6t areas. This Saishis to be==' M j 2. AB other --AM surfaces @ould be EniM to " norma!" =Ml=4 Enish quahry,approximateki25 RMS) fesae/ /adre,see i ncl ex rN.-~ lo, po 3. [ a+11 - e g .... J my

EDP.26726 index Item No. 8 Rev 0 ( _Pageq of ig's m Page 2 C. Stress alief ofpressure plates. 1. The question was raised concerning the need to stress relieve the P ates aAer cutting to preclude the possW ofmacking durms l machining operstmas. 2. Based upon discussions with DECO Metalhrsist, John E. Schaefer, on 6-29-93, oer prstion is: 8

a. Platemateriah:6S_TM A387 87 Grade 22 Class 2,is a low carbon

b. 'Ibe DECO ped, hence,is not prone to excessive hardening material, <0.159 and=+iaa is to as stress relieve the plates, with the following oceditions:

1) R-=and*A cutting process ipplasma are; cutting should be done to aBow the machinin= reinovel of epp.v :..mely signi6 cant effects of the bea$' Ibis should remov I/4" ofmaterial aAerthe cu t affected ene. 2) Flame cutting is as recommended due to the pa*at of additional distortion. If the supplier plans on using this process, a&btional dar===iaan and approval are required. I D. Overall surface machining 1. DECO daa< =at require that the entire perforated surface area be machiaad Only O.D. and I.D. areas are required, with appropriate surface cleaning and de-scalmd i 2. Should the supplier elect to not machine the entire surface, than steps shall be taken to assure that no significant discontinuities exist when the upper and lower halves are fitted together. R +9f="y, any i discontinuities, or steps, should be dressed out at a rate of p.iy

3. %"Aer aD machin}ag is complete,' all surfaces must b per 1/16" step A

cleaned and completely free of all oil and grease. All surfaces should .be wiped down with alcohol anakad line free rags. '!his should be done during each phase of the assembly process. II. UnresolvedIssues A. Mnimmn allowable plate thickness. B. NDE erami==tian of plates. ...e.an --1 .. 3 Form FIP-CM112 Att 6 Pg 1/1050793 ,,,_,,,j

~ EDP.26726 Index Rom Na.6 Rev c Page to of iff <D m Page 3 cc: L.Fron J.Drolz F.Wszelaki P. Hudson N.Kepler J J. Loner R Szkotnicki D.DiAntonio i R Wynn-Westingbouse Fax (407)281-3171 2330 L. Weber-Ort Tool D.Pickard - Ort Tool i Fax (313) 848-4308 I f I 1 e i l i j h 1 ,--e? g c;....._.. Farm FIP-CM112 Att 6 Pg 1/1050793

a' EDP -26726 index kom No. 4 Rev 0 Page it of 18I '2.\\ w 9 9 Lf.M %tc 9 Aft. ,I, sof 4 a.... um l'. a w u a A c.A,vm. i L - an- -- s sg = 4 0 N / \\. Jl L ~' o e m p = = - / k' J *'"' f .nua. \\, c' eM' 'l l T s- \\ I 1 LOme*LS,k % f* 1 6 tDb d&1 j 1 "9A4't..[ sag 7994 Y j ~ ? I .~9 ~' ' a Form FIP-CM1-12 Att 6 Pg 1/1050793 i

_ _ ~ __. _ _ _ _ __ EDP.3872s Index Item No. g Rev 0 Page 12 of 9 q) m NUCLEAR GENERATION MEMORANDUM Duse Ady 1,1994 To: OuryKulu Df Frout PaulTracyT Sulsest LP T.--. Test Teh. and 8th. E ee ?. _.e ?'=c=.

Reference:

GEC Drawing R4.A.94 04766 5471.1.83. The purpose of this====-andua ls to enemnue to clarify Technical issues related to their Waem-e. L Resolvmilssues A. Stress relierand cutting ofpressure passes.

1. This memorandum charses direction provuled in the 6 29 94 item.

2. Flarne aussag is acceptable, but must be preceded by ;;n '

-5 00*F

3. am sist series relieris not rap =.d and could potenuany amuse piste datormon If the supplier shooses to mress relief pinses sAer cuttag, the procedure must be provided to DECO for approval B. NDE saaminados ofpine prior to, or during, manuencem wW mot be requesd

{ C. Stk. Stage pressure passe desalis. Sheet 2.

1. LJAng bok holes around shamuserenas.

r

a. As holes are ariamed radidy som esser line.

b. The drawing ineerrnedy sped 5ss six (6) holes on the top half and four (4) holesonthebottomhaE Thegan3g "; - ='--- is four (4) holes on q

s/\\ the top halfand two (2) holes on the hoetom half as denensioned on Shost 2. /

2. On the cross escuom view, the O.D. aba-far on the pier : side is 1 1/4' x 45*. The chamfer en the half ring side is 115* x 45*.

NOTE: The above details are based upon the masung ath. Stage Daphragms M ..:.J Fr. rP.CM112 Att 6 Pg 1/1050793

EDP 28726 Index Item Nn. 3 Rev 0 [ Page 13 of 3fr m s m s D. R Stage pressure plate details - Sheet 1.

1. IJAng bolt holes around cirsamnference

_ Some senuments as for eth. stage; refer to sheet I for coneet dunennens d,2. On the cross semon view, the O.D. chamfer on both the plate and half ring ddes / Lis 14' x 45*. Jf NOTE: The above datans are basal upon the seisting h Stage C 1 ;--- E. Minanum plate'h 1 AAer conferring with both EC and Wesunghouse, the following conchmans icve beenrieched th illate *Wan=== is preferred to maimise in service h l

2. No true value has been established to date.

3. Athsckness

.7 pk be acceptable, but DECO must be informed prior to machming thes' siue. In addition, the suppsn we be._; ~: for anstaang the overaB ring ana==Wy denensions. i E. IJaresolvedissues. ll None PRT/ par i I ac: L Fron J.9toir J. Andrew N. Kepler J.tener g, ten.-Ai D. DM R. Wynn-Wennghouse Fax (407)2313171 or Fax (407)2312330 L Weber-Ort Tool D.Pekard OrtTool Fax (313)548 4308 . n N ' r t, ,. n A Form FIP-CM112 Att 6 Pg 1/1050793 ~ ' ' " - -.... ~.

1 e EDP 26726 Index Item No. 8 Rev o Page f 4 of 16'u wp sco m e n u m a ass sus un e.e2 .u.-es-sea w s: 8 Detroit Edison Enttoo Form'!! POWRR GENERAT1ON-NUr'TFAR TURBINE RRPATR GROUP FACSTMT11 COVER RRDMT PAGES INCL. CDYR. 4 TO: 1.Jwwu L. J & a s.t. m.

st.*.A *
cxNrANY:

o e at. s 4. 4~ *a. 4 FHONE: ras (4 a7) 3 4e.3t If }* ,4 8 8-l FROM: h T s.Ag PHONE #: 013)SS6. tv s 9 FAX t. 0 13) 586 1671 COMMENTE: it.g : t.** e% 3. e d.43. eas % v c. hw eem

. esS e e (,te J. 4.aood, vde Omu (a r, s e,. w,F+u -

a,u. (v. ws.es 4" stte r. s*sa u ut -u,ui-de_Aos}. ,.. -- m. - ,m.....,, ....m.. "Ted4.E Aga. WY .G. Ca. E n hJea. 5 1DIR. P.31 e Form FIP-CM1-12 Att 6 Pg 1/10507S3 g ~ g.......

.~_ EDP.28726 Ind:x Item No. S Rev 0 ( Pageis of tggg ye GEC TOLERANCING STANDARDS l "Untoleranced decimal dimensions are to be within the following limits (tolerances must not be cumuluive!)>Bore diameters, slot & recess depths and widths: size to +.010". Shaft diameters and spigot heights: size to.010". Centre distances and centers to faces size +/.005" @ ^ l F N8 ~ a V =32 RNIS e c u,a \\~Tu <a M ,ue 10, Mt I e.t-sd. 1' r, e e _.,g ....__.s Form FIP-Ch I-12 Att 6 Pg 1/1050793

t s' i EDP -25726 l (.. Pege lio of tg t vws index item Nt. 4 Rev 0 i .sa. eP-sses sain sEcm usul'E se min 313 sus ss'rs P.e1 NUCLEAR GENERATION MEMORANDUM pense = perv em ewarnem anne turi kw a== = /

c. -

-- u -r,.9 .c .c m To: OuryEagu L em,1 h. t """" C Ma S 9 ~ ~ & u uM 6 WU y Smigest 12 Tartriman - Tak, and 8th. Bsame Fransmen Pimeen. I massemos: cac Drswes R4A4440ss shems 1,2, and 3. The Adkywhis kan require hi elartaastion_ 1 Rasemag to Sheets 1 and 2 there is a referunes mine t;beenug Peps per heirsecean. part member masszos77.3. These imens are no be - withshsPreman Phans,wth she hBowing desalt 9 A. Material m UNS DemonsmenK911SI (410 3.5.)

p. Use se remad meek and alweed as soeused.

} c. hans pegs and inhini machiens sesth amb ihme they protrude 0 tw above ashoe. /C a u rPrenane Phee, naar nins. and Leemans Pas The emel, overeE theksens e we he provided, based upon anual assise sroove width.

n. As pan ofiha Alwiedag somract, eneh SuppEer,womaghoum, Ort Tool, and FX Ragineenns is required = assembk the matrugs m ihe Presane risia and supply as essessary assemers. A has not.m ? "j heen miserty mased ihat aus work wui inchde-A. Fhish maahang erRaFRies mates e enabhah the overnE assanddy thisimons.

f y X j s. M shines erkey ways and immaning key h the rinne.naaraims Asm ehey C lastaEng and Snieb machinlag erLeemug Peps, reistred to b 1ssum 1 above. j FET4mr oc LPrem J.Dreis F.Weasleid P.Budson N.xapier J.1meer R.Saheemidd D.IkAmmonio P.Wynn Weebeghouse Paz(407)2813171 er 2330 L Weber-Ort Tool

- 3 D. Packard - Ort Tool

,,J Ps (313)S48430s g e "'"' ~.- Form FIP-CM1-12 Att 6 Pg 1/1050793 7

i EDP 26726 index Item N3. S I Rev 0 Page r7 of $ q_\\ v y o, MUC1E.AR GENERATION MD80RAMDUM Des: July s,19M To: GwyKasm j From: Pum!Tracyt / l ~ m.m.,s, 4 s. t Rsferumme GEC Drewsags R LA 94 04766, Shams 1,2 and 3 1 The followns imens clarify poism addressed in previous mesmorandums

1. Imesanspesleas and nasamen e

A. See mesmo dated July 7,1994; Refer a shoess 1 & 2. B. Based spen actual assing poove wides, tabuissed below by anses, me te rosynsed, ownH, m pine, half:=s, and lossnes pas esmessions. m _v y_= a-m anse from (ses); apper and lower 9475-i m mase toes (sam);i,per and somer s.249-M mase seer (son);apper and no or s.co3-se anse seer (son);appersadlower 9Ao6-mage nome (san);upperand ioner .24s-m anse tas (son);appnand is.or s.ms-M mase seer (sen); apper and lower 7.997- ) sib anse near(see);apperand lower 9A0$* LE1 se anse test (mm);apperandlower 9.2w m anse 6 ems (son);apper and lower a.244-m sense seer (sen);upperandlower 7.997-se sense seer (sea);syrerand somer 9A12" b IN %bb Mb% % N N M $s dellows:

1. m sense (Ebest 1) e fR hb$U Yh Ulsh WWWh{

L - - - fa q 90 8 e* H Form FIP-CM1-12 Att 6 Pg 1/1050793 '~ "~ ~ ~ - * * ' " " - ' ~ i i

i EDP 26T24 Index Item N3. 6 / Rev 0 Page @ of g' G.\\ w, July 7.199d Gary Kahu LP Tubmes - 7sb & teh Sr; e Pressee Phans Page 2 r

b. Peg ashassa e vernal esmerism (Dreweg Zeme B 2): abunge essa 1* m isA eresser nr.e nehr armsener

c. Saeemd peg show halfjoint (Drewsag Zone F 9) abange tems 27.5' m 2Li'.

The nanaming :=o pegs shall masemm ihe spaces or22.i' tem she essand pes.

2. th sage (5hast 2) a.

Peg agassa es halfjoint(Dreweg Zane K II) eksage $* as 2*. b' b. r Peg a4asms a vensal assentes (Drawing Zame 3 3) shaser tum 1.125* as ist of ) m s us m tre erammar c. sensed peg show harjaim(Dreweg Zane G-II): stange tem 1* m right d22P

==k

N

d. Thbd peg show halfjois (Drewhg Zane D4) desse tus l'as right d22.S' mark (malerar)=m esse,sg sh.n hairjoim(D weg Z.m s.4): shage t.m i m,ighi.r:2.5 ask (smal of 67.S*) m 2*Ja.ld.

R. EsyWayDamammans A. gasis tem Pum!Tsary,theadJuly6,1994;sederasanst3.

3. AI! keys are ' -

.Str assomsmedme Aming hmo the sambgs= Theofers, k k meessaary to rumow d$~aisses an of the key to 9: k isso the prussage plass. The keys sh==M be meshead maing the fauswhg guidsimas. ~ ,1. The up and besse hsys shrild est hast asaaltg en het sides se shst te key is esmeed. M

2. The side keys shemid be machimed se ese sier sah, sash that the smasas sessenal b em te side away tem the halfjoint (see smashed skaak ist ensreammens) 79tTAib ec D.DsAansano D.Puhard OrtTeel(Faz 313 448 00g) 3.Drote G. Bessee FX Eagnearks (Fan 6174464410)

LPnm m.askaakki P. Hadsen LWeber OrtTeel N.Espiar F. Wa=mamari J.Laimr R.Wyum W+(Fm 407-2313171/.2330) A.Rame -7 >r. Form FIP-CM1-12 Att 6 Pg 1/1050793 As...... '--..J

. -. -.. - - - -. - ~. -........ - EDP CONTINUATION SHEET 4 EDP 26726 Index item N 3. 6 Rev 0 Page Ft of 2.1 HINGHAM SHIPYRRD TEL 617-749-9410 Jul 14.94 16:21 No.003 P.02 1 e px engineering company, inc. ansLomme esent anos an

eenemm,

- eses: Tampampe 4817)744111 FeugB17)7 4 4610 Laur8ekoGPtW1. Pop 1er1 Thurseer, July 14,1994 Deerst Edison Conseny Fans Nudeer Generseng Staten 6400 Norm D6de HM Newport, MI 48106 j Amenton. Mr. Gary Kugu, Referanos-LP Stage S Pressure Pistes i

1. In referunas to yaw FAX of 7/11/94, Memo neced 7444 troen Pad Traor.

1.1 From peregrasm 1 A If it is e to our scope of work, please send j us e copy of " memo deled Ady 7,1904". 4.2 From peregraph 1.5 please ciertfy me 'We elege" pressure pistes you remare, Lo. steem or genensor end, LP1, LP2 1.3 Frern piirogrusm ilA N It is apptoeble to ow ecope of serk, pieces send us e copy of tax ested July 6,1984".

2. Inreferenos toyour FAXof 7/14 JD4,Memodated7/1494Irom PaulTraor.

\\ 2.1 Altsched 6 i sur weiding procoews SW-185 SR, autmaged der your approvet 2.2 The tength of me bare in our posessaan are not eng enegrito penst he tapfoerknp of altamseve No.2. Mmdryours, gineerin cornpony, inc. N ,7 .SonAon vlos-Premmeru of Enemoonne y& ' r. .. -q .O '~ g o'.. S * ~~ Fcrm FIP-CM1-12 Att 6 Pg 1/1050783

6 EDP.tsygg ind:x Item N3. 6 k Rev 0 Page to of g 16:23 No.003 P.03 Jul 24.94 TEL 617-749-9410 HINGHAM SHIPYARD PE Engineering causesryBingham, MA 03043 395 Liaeeln StNetWM233B F"'""" SPM2FICLTEM (Wpg) Dates 7/04/94 hevision No.: C NPS Re. a le=* "" - 1 Supper **** PMes W.166 .102NF (Op=403) Jettet design $-- - /ei9 iaer--- em 23 ShEB EEEht. (OIN403, OW-405) to F No. AL. Desting..... mi ** ae ** *

m *--* *==

7 No.t"A a_ anne

Beating Nota==1a=== =1 r e- ' as _4, Thieknees range. _e tave* ta ni Position (e).111 Fillet Wald sies ~~

**4

' 'n Progression.wa m a=8 metes possuBLD Este N (OW=407) notes t saa er + se ein Temperature rampe n.sa sie =<m. Pamesm' (08-406) mini-Temperature.,2gg pegrees F. Time range - 1 no hi /* m. Interpens toep. max. AAA Degrees F. notes --r*=-- Prehest maintemenes. Rene All peestes) i Whas / mamman i Passoas / type......... a nanne... Process thielmens Limit. f / ShS (05=408) m /A j

*1di"y Gee / CFE.....

(' m /i / / T.ra.ilias een /.c.F.E......- .,a me iog = / N SEREEL (Ge=4e4)

en t e.ast.

F# s..,,, F# .A.,, SFAft AWB eleasifiention....., _ M s SFA Spee. No. & F No.... SF 4 & Wo. se Chem. Comp..... are ~ /- Filler metal trade mess. w /A / 1 t l SAN fluir trade asse/ type __1/a j' a inn i - sna Eles./ Wire slee (in)... 1 er armemwna' (GD==400) solding esperage range., me.tae !

*e.**eI m

=w = re

== Waiting voltage range..._ v=e_ var. Travel speed (Ape)......_ w=e- ~ m ei / ' = is max. Best Empet (J/ia).. / Fuegeten Type / Sine...... _ m/A" - - e -- =. =me i Sorreset & polarity...... m it M (Gi>410) !== t 3 String / weave head..... m it 3rifice / gas esp....... u/a Seatest take te wort.... m ia m #A 3es111stion............. ~

- ==1=
1=---

amit./ Single electrees.. 3ther Technique potes...ealtiple er Staple Pass (per steep.... at t. (ni)_ ma - - t me - - n em *m t e -- u. ser* *11 l

*e +---

(m3 Lua w=. --ata, (n3)_ - e e. sa em .t (nel_ maar

e *** s t era 3

(as E --* en (me) (R7) e t' L. .. 9 ....'J Fctm FIP.CM1 12 Att 6 Pg 1/10507g3 \\ g......-

t EDP -26726 Ind:x Item N3. 6 ( Rev 0 Page 43 Of O M1NSHAM SHIPYARD TELtE17-749-9410 Jul 14.94 16:24 No.003 P.04 1 i n~ WEIaZ3G FADCEDIRE SPECIFIchTZW (WFS) Page 3 of 2 i i I WPS 30.3 es.tas.am Dates 7/D8/94 Revision 30s.: R, l l F.1ezur (gn-403) 1 single g geweve simple-assel grosse meeting a me h= awing naaming

as beating meet Opening: 3/1s* men.

seet openias 3/1s* max. eroeve Angles so degree sia. erwove Angle: 45 degree mia. aset Fame

1/s* mez.

aset Fees

1

......../8" mes. Single =W grosse N greeve Seeking a gouged & beak solded Becking a gouged & beak solded Root Opening: 1/4' mes. Reet Opening: 1/48 mes. Greeve Angles 50 degree mia. Greeve Angles 45 degree mia. Best Faos

3/16.................../168 Reet Fees

3 Wax.

.........." mes. Seeble d genove simple /Beeh&e F111st meeting

gauged & book solded maating Rest Openiag 1/48 max.

Root opening: 3/1s8 men. ereove Angles 45 degree min. Wald sise maquired tillet heet Fame

3/1s8 mes.

pies root spesia ....................................s... Speese p agenre grosse seeklag

T-$eint seekias We bookias

\\ Opening: 1/33* mes. Beet opening: 3/338 mes. ,e WEKA.10ZNT DESCRIFT20Its SIIDWN ARE IIDF ZEMASITE OF ALL OF TEISE FOtRD ON A ( j .105 BITE. WEta.70ZET DESIGN REFERENCE IN AN EI: SINE R1a5 SPEE FICSTICII OR DESIGN INIANZEIG 8E432. TAKE F3t3CEDENCE OTER WEIA.10ZIITS SEDIIN IN TEZ5 WPS. Initial sleening artem we,. _ et . s e L.a a 4 - me u 4ae.,. a11 m.8 2-. _ mem. - M gg haak gggg artswa messa11 (e) m en air.are is need, remove mil slag and earten assemelation try grinding, shipping, ama sire urushing. (b) palmi=== prehmet must be meistmi==8 during thermal settieg, taaking, and sending operatione. (e) De ro*ai==* will be need. 3 (d) Walde aball be cleaned becomen easd'. peas. Whom esopleted, resswo all alog and pre Z 8-- (e) park most be tree of euidae, dirt, sil, and meisture. es meetity that tihe etetamente in them reeerd are eerrest and in esserdense esta the receiramente of Sectione 11 and VIZZ of the AmIE Code. (*/ / 7 /7 D OC asamm9me 8 Prepared Dy: A a ..n Form FIP-CM1-12 Att 6 Pg 1/1050793

EDP CONTIN' ATION CHEET U i AF"3 - INFORMATION SERVICES x m NS. 7 "97Fr40 DON $714277REV:@ Rev 0 t. TE:b3 Q4 RECIP!ENTNO: $'d Paoe 1 of 1 LIST OF MATERIALS NOTE: For all this material refer to the following drawings, including the changes specified in this EDP, for specific details: R/LAS4A)4766 (T13687) Pressure Plates & Keys R200(A1)S462 (T1-3688)- Special Socket Headed Screws R265(A3)3077 (T1 3689) - Locating Pegs MM DESCRIPTION PURCHASE REO OA LEVEL 1 12 7th Stage Pressure Plate halves Non O 2 12 8th Stage Pressure Plate halves Non O 3 12 7th Stage Pressure Plate Half Rings NonO 4 12 8th Stage P sure Plate Half Rings NonO consisting quarter rings each due mitatiop to fabricatio 5 48 7th Stage Side Keys upplied 0.015' oversizeh Non O 8th Stage Side Keys [ applied 0.015' oversizh NonO 6 48 7 24 7th & 8th Stage Top & Bottom Keys 7: supplied 0.015' oversizy Non O 8 336 Special Socket Headed Screws for NonO installation of the Keys 9 216 Locating Pegs Non 0 10 120 7th Stage 7/8* Socket Headed Screws for Non O installation of Half Rings to Press. Plates 11 108 8th Stage 1' Socket Headed Screws for Non O installaton of Half Rings to Press. Plates All material purchased thmugh the Turbine Group. SPRSIW. PACT Add a note the following stock code items that all the LP's 7th & 8th stage blades and diaphragms have been replaced with pressure plates per EDP 26726: 450-3773,450 3774,482-9881,482-9882,482-9890 & 482-9891 fiifk B) Check @dG A _ [satef/t/h A) Prepared By R. L Tas/ sell Sion @ Sion F/sr:;h/ Date e-/'-ry' ~ ~ ~ ~ R n RP-CM1-12 Att 6 Pg 1/1050793 ~S D

.._. _..,..._ _....._._.... _...___ _...._ _.._._.. _.-.....__ _ _. _._ _.-. _ _.-.__ _ m i EDP CONTINUATION SHEET i EDP.26726 ( index Item No. 8 1 Rev 0 Page 1 of 1 INSTALLAT10N INSTRUCT 10NS 1. Verify that all the 7th & 8th stage disc serrations are protected with root blocks. During the work performed on the rotors by Westmghouse, the blades were to be cut at the bonom of the airfoils and the blade root sections used as a root blocks. Where necessary, new root blocks fabricated based on using the blade serratxms as a pattern, may also have been installed. 2. nis modification requires pressure plates to be fabncated along with new balf rings, keys and locatmg pegs. De intent is to have the pressure plate halves shipped assembled with their half rings, keys and locatmg pegs. 3. Check that the assembly dimensions are per the fabncation drawings, including the modifications identifwd in this EDP, to i'isure that the proper clearances will be achieved during and after installation. See ladex Item 10 for modifications / clarifications to the fabrication drawings. 4. Install the pressure plates into their respective diaphragm groove in the LP casings with clearances indicated in EDP Index Item 10 and fabrication drawings, Edison file numbers T13687,3688 & 3689. Adjust keys and pegs as necessary to achieve the proper fit-up. Note: Any deviations in the pressure plates, half rings, keys or locating pegs and/or installation clearances from the fabrication drawings and instructions shall be reviewed and approved by the Turbine Group and documented via a ECR or ABN to the EDP. - rt \\ - 'll ...3

e-

....) L...... - ARMS -INFORMATION SnVICI3 DTC:ppff DSNgyLMREV:O DATE: 4 %ECEEE R bk SIGNATURES R$d Mt J, ~ + A) Prepared By R. L.Ta sell B) Checked ly)gli' Date 9/1/y Sig 2 fff Date 9-2-N Snn f Form FIP-CM112 Att 6 Pg 1/1050793 n. -w e.- m -mg

~ _ -. - - - - - - -.. ~.. -.. EDP CONTINUATION SHEET EDP -26726 ( Index Item No. 9 Rev 0 ) Page 1 of 2 POST MODIFICATION TESTING (PMT) / DESIGN CHANGE ACCEPTANCE TESTING (DCAT) NOTE: This testing will be performed by the Performance Evaluation Group in conjunction with the Turbine Group. Plant Engineenng will be a consultant only.

1. During power ascension testing, monitoring the following data will establish a basis for the performance of the pressure plates at various power levels. 'Ihere is no acceptance criteria required for this data during ascension.

A. Feedwater heaters 1,2,3 & 4

1. Shell Pressure Heaters 1 North,1 Center,1 South,2 North,2 Center and 2 South shell pressure measurement may be unreliable. EDP-26841 written to modify the reference leg configuration, ifimplemented dunng RF-04, will allow for this measurement.

Heaters 3 and 4 shell pressure measurements are available.

2. Extraction Steam Temperatures I

Heaters 1,2,3 and 4 ARMS -INFORMAT!ON SERVICES l B. Extraction Steam Pressure DTC: EE& cCsJic,%.Wr.Ev:(A DATE: h*3-Q h F:EC:PIENT NO: 12 Heaters 3 and 4 C. LP 1,2 and 3 inlet steam temperatures, LP 2 inlet pressure inlet temperatures for all three and only inlet pressure for LP 2 4 The only acceptance criteria during power ascension, related to this modification, is that the parameters being monitored under Temp. Mod /s 940015 (Strain and acceleration data of 3N,3S & 4N/S extraction steam lines within the condenser) & 940016 (Strain, acceleration or pressure data on steam supply to H.P. & L.P. turbines and feedwater heaters 3 & 4) remain within acceptable limits. In addition, the feedwater tempe 1,igits, as specified in enclosure A of General Operating Procedure 22.000.03, shall be maintained. ThesJterswi ad ssed under the main start-up testing prograrg=d i: p ~.,...,

.: -ir.. ;.; ::::.,_ J ;e ;e...f = i: M.W H, or - ~; ; :. _...

r 77' 1 SIGNATURES s A) Prepared By R. L. Tassell B) Checked Sign /jP f M'8 Date F-t N Sign J,A Date //s.M y Form FIP-CM1-12 Att 6 Pg 1/1050793

EDP CONTINUATION SHEET t EDP.26726 '( index it m Ns. 9 Rev 0 Page 2 of 2 POST MODIFICATION TESTING (PMT) / DESIGN CHANGE ACCEPTANCE TESTING (DCAT)

2. At 100% after uprate power level, monitor the following, to evaluate and reconcile against the new heat balance, reference Edison file T1 3690, to determine if any operational limitation are required. The evaluation and reconciliation will be part of the Start-up Testing Program and not a restraint to closing out this EDP.

a. Feedwater Heater #1 Drains leaving temperatures

b. LP Turbine Exhaust Condenser Heat Load - Using Process Computer Point C017

c. Condenser Hotwell Backpressure and hotwell temperature

d. Main Generator Output

c. Gross Heatrate Unit Heatrate - using Process Computer Point C099

f. Feedwater Heater #2 shell side r awade drain temperatures from heaters 3 North and 3 South to heaters 2 North,2 Center, and 2 South.

The preferred method of parameter measurement is the BOP log data of the process computer, but control room measurements may serve as a second check of the process computer points, or as the only source of data if the process computer crashes or a specific computer point experiences a malfunction. -e (.- - L......_.-..... --J _m .sy:, A) Prepared By R. L Tassell B) Check Sion .f'-//d Date 9-/-ty' Sion &hL. Date (bh y Form FIP-CM1-12 Att 6 Pg 1/1050793

EDP CONTINUATION CHEET \\ .e AF?MG - INFORMATION SERVICES EDp.2s72s DTC: 7'U:"$3fMh.0/O REV: $ Index Item N r.10 DATE: h*M4-RECIPIENT NO: %d 3 og 4 AFFECTED DOCUMENT DSN: R LA 94 04766 (T1-3687) L APPLICABLE TO ALL THREE SHEETS Add the following notes to drawings:

1. Where specify, the use of unified C or UN ds appropnate,is acceptable.

AllliAing eyesholes are to bph ~ m

2. All boking materal shall b5 }STM A193 Grade Bgq

3. All bohir.g used to attach the half rings to the pressure platpshall be stakQ EAer feal assembly.

i

4. All other bohing used to attached keys, supports, etc; hall not be stakeh

5. Overall surface enacharting Surface fm (125 RMS pplies only to the key fit areas, this shall be maintained.

other machined surfaces should be%ished to " normal" machmed fmish quality, approximatel 50 R The entire perforated surface area is not required to machinedhly O.D. and 1.D. area e with appropnate surface cleaning and de-scalin[ if the entire surface is not machined, then steps shall be taken to assure that no signifmant discontinuities e exist when the upper and lower halves are feed ether. Specifatally, any discontmuities, or steps, should be dressed out at a rate of approximatel " per 1/16" stepy AAer all machining is complete, all surfaces must be thoroughly cleaned and completely free of all oil e and grease All surfaces should be vnped down with alcohol soaked lint-free rags. This should be donc durmg each phase of the assembly process

6. Tolerances Untoleranced decimal dimensions are to be within the following limits (tolerances must not be cumulative!)

Bare diameters, slot & recess depths and widths: Plus 0.010" Le Shaft diameters and spigot beights Minus 0.010" yc e Center distances and centers to faces size: Plus/Minus 0.005" Pressure plate thickness Minimum is 4.75" with Edison approval e i

7. Flame cutting of the plates is acceptable, but must be proceded by pre-heatmg 00*bItress relieving is j

not to be performed without prior DECO approval. j r ' \\

p

w -

y+ %,g mgugngggg '}s}~}Q:ng m. ~ "

A) Prepared By R. L. Tassell

'8) Checked Sign fWJ Date p-/-N Sign N_ Date f/t/y Form FIP-CM112 Att 6 Pg 1/1050793

t EDP -26726 Index ttom NM.10 / Rev 0 Page 2 of 4 AFFECTED DOCUMENT DSN: R LA N 04766 (TI.3687) II. SHEET 1 A. Uffing bolt holes around circumference q

1. Al holes are onented rodolly from the center line.

t 7 '2. The drawing on,w-iir pect6es six (6) lifting bolt holes on the top half and four (4) holes on the s bottom half. The conect conAguro16cn is four (4) holes on the top half and two (2) holes on the bottom half as dimensoned

3. The holes are to be drilled 4.75' deep and topped 4' deep for a 2" x 8 UNC - ANS threads B. Chomfer Detail 8" GR00VE f

7.9" PL ATE-L OC ATION PEG 2'9" (GE N E N D'F OR See TO CYLINDER 5" ~ SHEET 3 CLEARANCE 0.005" &gg.ar STE AM E N 01 m d I ** C) i d o 4 I I b b o a e e 'e 8 8 8.o m o. o O

o...

S. s m 4 L W in m O 1 C. Assembly dimensions. based on octual casing groove widths required for overall pressure plate, hoff ring, and locatingpin dimension. M #pr e v 7th Stage LPs 1,2 & 3 F LP Required Dimension 1 Front (stm) upper and lower 8.264* 1 Rear (gen): upper andlower 7.997" p )( 2 Front (stm): upper andlower 8.249" 2 Rear (gen): upper andlower 8.003' 3 Front (stm) upper and lower 8.244' '~' 3 Rear (gen); upper and lower 7.997' " ' ~ ~' Form FIP-CM1 12 Att 6 Pg 1/1050793 (,. 5.....

t EDP -26726 i index Item Ns.10 l _[ Rev 0 Pace 3 of 4 i II. SHEET 2 A. Ufting bott holes around circurnference

1. AM holes are onented rodolly from the center kne.

J 7 x c

2. The drawng inconoc#y specifies six (6) lifting bott holes on the top half and four (4) holes on the bottom half. The conect conAgurallon is four (4) holes on the top half and two (2) holes on the f

bottornhalf asdrnenooned

3. The holes are to be drilled 4.75' deep and topped 4' deep for a 2" x 8 UNC - ANSI threads J

B. Charnfer Detail P \\ 1 R R AD 9" GR OOVE 3 8.9" PL ATE (GEN END SEE 5" 3.9 "# SWEET 3 FOR 0 5 E AM END) V ' ANCE O.OM" r r e r. a L i 5Q_l1 \\ l T 4.LJ t I" R g j yQ ,j i, 4 1 15 ' C. Anembly du -roicss. based on octual coming groove w6dths, required for overall pressure plate, hotf ring. and locating pin dirnension. f*>,er r-o-n 8th Stage LP's 1,2 & 3 1 LP Required Dimension 1 Front (stm): upper and lower 9.248' 1 Rear (gen): upper and lower 9.005" 2 Front (stm): upper andlower 9.675' N 2 Rear (gen): upper and lower 9.006' 3 Front (stm): upper and lower 9.249' O ~".J ~ ~' 3 Rear (gen): upper and lower 9.012' p. Form FIP-CM1-12 Att 6 Pg 1/1050793

.g. 1 EDP.26726 4 index Item No.10 l Rev 0 Page 4 of 4 l AFTECTED DOCUMENT DSN: R265 A3 3D77 (T3-3689) Matenalclanficanon-m, 1 l< g i Locating pegs areitem 3 - 3/4" 08 sad are to be fabncated frtd410 S.S/ laitial smachining length shall a: count for the fact that the installed pegs are y protrude 0.015" above the surf or actual counplete assembly widths with pegs, see pages 2 & 3 of this index hesn. / I l 1 l l 4 4 e , N. l . e.g s55 $..~ *, @@m>) %. M'.N._ W, ITc8f 7 SIGN. A. T.,URE. S17,$Ie$@f.%..,M.s?E.r, i,.d. W, ~ 7 A) Prepared By R. L. Tassell B) Check Sign p-/A/ Date S./-9y Sign Date /A/99 Form FIP CM1 12 Att 6 Pg 1/1050793 / i' .g

_.. _ _ _.. _.._.._ ~_. _._._._ __. _ _._ 4 EDP -26726 index Item No.11 Riv 0 Page 1 of 1 ) i Document to be Revised: DK: TMINSL DSN: VMTl11,1.7 Add the following note to this Vendor Manual: "Ihe 7thand 8th stage turbine blades and diaphragms have been removed and pressure plates installed. The pressure plates have been designed by the turbine manufacturer, GEC/Alsthom, with an independent review performed by Westinghouse Electne Corporation Turbine Services group and found to be acceptable as an interim measure until the newly designed rotors and blades can be installed. ARMS-INkORMAT!ON SERVICES ON' T !~fh L' & &.Offpgy; (y DAE 8.M 4 F'.201PIEN'T NO: $ A) Prepared By R.Y L Tassell B) Checke Sion -f 1'P Date 9-/-97 Sion hl Date 2b/% ~ Form FIP-CM1-12 Att 6 Pg 1/1050793 i t...

L4# mal'MIMDWCJ {$1Idzt/ 1 s EDP -26726 [ Index Item Ns.12 Rev 0 Paoe 1 of 1 Documents to be Posted. DTC DSN E& son Mie No. DDVEND LA 146X69 T1569 DDVEND LA 231X69 TI 568 DDVEND LA 2330X69 TI 567 ) DDVEND R277A874 PG 1 T1 1187 1 DDVEND R277A874 PG 2 TI 1187 DDVEND R277A875 PG 1 T1-1264 DDVEND R277A875 PG 2 T1-1264 DDVEND R277A876 PG 1 TI 1265 DDVEND R277A876 PG 2 TI-1265 DDVEND 'IS 17280 T1 1598 Add the following note to all above mentioned drawings: The 7th and 8th stage turbine blades and diaphragms have been removed and pressure plates installed. The pressure plates have been designed by the turbine manufacturer, GEC/Alsthom, with an 'Hnt review performed by Westinghouse Electric Corporation Turbine Services group and found to be acceptable as an interim measure until the newly designed rotors and blades can be installed. See Vendor Drawings R LA 94 04766 (Deco File No. TI 3687) for pressure plate design and information. ARMS-INFORMATION SERVICES

OTC:W p f ) F D S N S % D A' e v: G DATE:8-3N4RECIPlENT NO: %Q Form RP-CM1-12 Att 6 Pg 1/1050793

.s,

r ~ Heat Exchanger Systems, Inc. -r Consulting Engineers and Non-Destructive Examination -,l p-VL L .; D 374 Congress Suset, suite 60L Boston. M A 02210 TEL. (617) 335-6650 FAX (617) 426 7142 l 1 July 21,1994 Via Telecopier: 1 Mr. Mohan Deora ) Detroit Edison Company 6400 N. Dixie Highway ) Newport, MI 48166

Subject:

Condenser vibration / Performance Analysis - Fermillalll

Dear Mohan:

i Heat Exchanger Systems, Inc. (HES) has performed the subject analyses for the Fermi Unit j 2 condenser. i The analyses were performed in order to evaluate the effects of changes to the steam flow rate and enthalpy to the main condenser. The changes in steam conditions are caused by proposed modifications to the LP. turbine. The revised values used in the analyses are as follows: Steam Einw Ub/ht) Steam Enthalov fBtu/Lb) 8,129,928 1054.1 The analyses /results were as follows: Vibration Analysis Utilizing the HES tube sup > ort spacing analysis program and the new value for steam flow, the maximum allowa)le tube support spacmg was determined for the condenser tubed with 22 BWG titanium. The maximum allowable unsupported tube length is 31.19 inches at a condenser pressure of 1.48 inches HgA. Since the Fermi 2 condenser has anti-vibration staking installed in between the existing support plates for all tubes, the maximum unsupported tube length is less than 20 inches. Based upon the HES analysis, the increased steam flow to the condenser will not require any additional anti vibration staking. The analysis output from the tube support spacing program is attached.

s Thsrn.al Peri::rmance Analysis HES determined theoretical condenser pressure based upon the new steam flow rate and 0 enthalpy over a range of circulating water inlet temperature from 60.0 F to 87.5 F. The analysis was performed utilizing the HES proprietary performance prediction comput-er program. The analysis assumed 5 circulating water pumps in service and a cleanliness factor of 90%. 1 The predicted pressures are presented in the table below, along with predicted condensg pressures at the same CW inlet temperatures at the 105 percent power duty (7.79 x 10 BTU /HR). CONDENSER PRESSURE (INCHES HgA) QEI6') 105% POWER NEB' DUTY 60.0 1,46 1.61 62.5 1.56 1.71 65.0 1.66 1,82 67.5 1.78 1.94 70.0 1.90 2.07 72.5 2.03 2.22 75.0 2.18 2.37 77.5 2.33 2.53 80.0 2.49 2.71 82.5 2.67 2.90 85.0 2.86 3.10 87.5 3.06 3.32 The thermal performance analysis indicates that condenser pressure will increase 0.15-0.26 inches HgA, depending upon the circulating water inlet temperature. The condenser pressure performance prediction computer output sheets are attached, alone with the predicted condenser pressures in graphical form. Should you have any questions or require additional information, please advise. Sincerely, J Charles D. Hardy Senior Mechanical Engineer CDHitcl Attachment cc: HES File #711 Heat Exchanger Systems,Inc.

l Condenser Pressure <'hinches, HgA) f Fermi Unit 4.0 t x m i j 3.0 j e o 3 ,3 I 5 6 2.0 m o M 1 a ~ i 2 3 c 1.0 o x S t i E c i i 6 5 0.0 60.0 62.5 65.0 67.5 70.0 72.5 75.0 77.5 80.0 82.5 85.0 87.5 l Circulating Water Inlet Temperature,0 F _._ Without Plate _._. With Plate l n" i E s t w w

s TUBE SUPPORT SPACING CALC: DATE: 07-20-1994 CALCULATED BY: PLANT: FERNI UNIT 2 CHECKED BY: CLIENT: DETROIT EDISON GIVEN TUBE MATERIAL - TITANIUN 1.00 IN TUBE O.D. WALL THICKNESS -.028 IN 14.9 E6 PSI MODULUS OF ELASTICITY .163 LS/CU IN TUBE NATERIAL DENSITY 1.25 IN TUBE PITCH TURBINE EXHAUST AREA - 1074.7 SQ FT TURBINE FLOW RATE - 4.08 E6 LB/HR COOLING FLUID - LAKE ERIE COOLING FLUID DENSITY - 62.34 LB/CU FT l ( l 1.50 IN HGA CONDENSER BACK PRES. TUBE SUPPORT SPACING - 39.0 IN i RESULTS NAX SPAN $ GIVEN BACK PRESSURE - 31.44 IN MINIMUM PRESSURE FOR GIVEN SPACING - 2.75 IN HGA i i THE MINIMUM TUBE STAKE SPACING IS - 31 19 IN AND IT OCCURS AT A PRESSURE OF - 1.49 IN HGA 1 l (

u ( HEAT EXCHANGER SYSTEMS INC. BOSTON. MASS. f CONDENSER PERFORMANCE ANALYSIS DETROIT EDISON FERMI UNIT 2 105% POWER-5 CWP'S CONDENSER DATA TUDE DIAMETER (INS) a. 1.000 =22BWG. TITANIUM 59592 AVAILABLE TUDES FIRST MATERIAL SECONO MATER]AL =228WG, TITANIUM 0 AV AIL ABLE TUBES 776800.(SQ.FT) TOTAL DESIGN SURF ACE AREA = 776800.(SQ.FT) EFFECTI,VE SURFACE AREA = f CONDENSER PERFORMANCE l 1 2 3 4 RUN NUMBER f j CLEAN CONDENSER ( 1.38 1.47 1,57 1.63 SATURATION PRESSURE (INHG) 561 573 bek HEAT TRAN.COEFF.(BTU /HR FT2 F) 547 TERMINAL TEMP. DIFF.(F) 10.64 10.23 9.B7 9.56 60.00 62.50 65.00 67.50 INLET WATER TEMP.(F) 18.38 18.39 16.40 18.41 TEMPERATURE RISE (F) CIRCULATING WATER FLOW (GPM) 847500 847500 867500 847500 6.52 6.52 6.52 6.52 TUBE VELOCITY (FPS) 7790.00 7790.00 7790.00 7790.00 CONDENSER DUTY (MMBTU/HR) CLEANLINESS D ATA 1.46 1.56 1.66 1.18 SATURATION PRESSURE (INHG) 50h 516 576 HEAT TRAN.COEFF.(BTU /HR FT2 F) 492 12.52 12.06 11.66 11.31 TERMINAL TEMP. DIFF.(F) .90 .90 .90 .90 CLEANLINESS FACTOR CONDENSER PERFORMANCE 0 0 0 0 0 0 0-0- 0 f DATE DATA TAKEN O! 0 0: 0 0: 0 0: 0 TIME DAT A T AKEN .00 .00 .00 .00 SATURATION PRESSURE (INHG) -140 -135 -131 HEAT TRAN.COEFF.(BTU /HR FT2 F)-145 esses

- ces masse ssess TERMINAL TEMP. DIFF.(F) 10.38 18.39 18.40 18.41 TEMPERATURE RISE (F)

-26.6 -25.1 -23.7 -22.5 [ PERFORMANCE F ACTOR (5) SUBCOOLING (F) .00 .00 .00 .00 C D 0 0 VOL OXYGEN CONTENT PPB j

V o-( CONDENSER PERFORMANCE RUN NUMBER 5 6 7 8 CLEAN CONDENSER SATURATION PRESSURE (INHG) 1.80 1.93 2.07 2.22 HEAT TRAN.COEFF.(BTU /HR FT2 F) 594 603 611 618 TERMINAL TEMP. DIFF.(F) 9.30 9.06 8.87 8.70 INLET WATER TEMP.(F) 70.00 72.50 75.00 77.50 TEMPERATURE RISE (F) 18.42 18.43 18.44 18.45 CIRCULATING WATER FLOW (GPM) 847500 847500 847500 847500 TUBE VELOCITV(FPS) 6.52 6.52 6.52 6.52 CONDENSER DUTY (MMBTU/HR) 7790.00 7790.00 7790.00 7190.00 CLE'ANLINESS DATA SATURATION PRESSURE (INHG) 1.90 2.03 2.18 2.33 HEAT TRAN.COEFF.(BTU /HR FT2 F) 535 543 550 556 TERMINAL TEMP. DIFF.(F) 11.01 10.75 10.52 10.33 CLEANLINESS FACTOR .90 .90 .90 .90 t CONDENSER PERFORMANCE DATE DATA TAKEN 0-0- 0 0-0- 0 0-0- 0 0-0- 0 TIME DATA TAKEN 0: 0 0: 0 0: 0 02 0 SATURATION PRESSURE (INHG) .00 .00 .00 .00 HEAT TRAN.COEFF.(BTU /HR FT2 F)-127 -123 -119 -116

- A**

TERMINAL TEMP. DIFF.(F) TEMPERATURE RISE (F) 18.42 18.43 18.44 18.45 PERFORMANCE FACTOR (%) -21.4 -20.4 -19.5 -18.8 SUBCOOLING (F) .00 .00 .00 .00 VOL OXYGEN CONTENT PPB 0 0 0 0 TEMP. CORRECTION BASED ON HEI I l I i l

e CONDENSER PERFORMANCE 9 10 11 12 RUN NUMBER CLEAN CONDENSER SATURATION PRESSURE (INHG) 2.38 2.55 2.73 2.93 HEAT TRAN.COEFF.(BTU /HR FT2 F) 624 630 634 638 TERMINAL TEMP. DIFF.(F) 8.55 8.43 8.32 8.23 80.00 82.50 85.00 87.50 INLET WATER TEMP.(F) 18.46 18.47 18.68 18.49 TEMPERATURE RISE (F) CIRCULATING WATER FLOW (GPM) 847500 847500 847500 047500 6.52 6.52 6.52 6.52 [ TUBE VELOCITY (FPS) CONDENSER DUTY (MMBTU/HR) 7790.00 7790.00 7790.00 7190.00 e i CLEANLINESS DATA SATURATION PRESSURE (INHG) 2.49 2.67 2 8S 3.06 567 571 574 HEAT TRAN.COEFF.(BTU /HR FT2 F) 562 TERMINAL TEMP. DIFF.(F) 10.17 10.03 9.91 9.80 .90 .90 .90 .90 l CLEANLINESS FACTOR j CONDENSER PERFORMANCE 0 0 0 0 0 0 0 0 DATE DATA TAKEN 0: 0 0: 0 0: 0 0: O TIME DATA TAKEN .00 .00 .00 .00 SATURATION PRESSURE (INHG) -109 -106 -103 HEAT TRAN.COEFF.(BTU /HR FT2 F)-112

- 48s sesse esses sesse TERMINAL TEMP. DIFF.(F)

TEMPERATURE RISE (F) 18.46 18.k7 18.48 18.49 4 -18.1 -17.4 -16.8 -16.3 f PERFORMANCE FACTOR (%) SUBCOOLING (F) .00 .00 .00 .00 i 0 0 0 0 VOL OXYGEN CONTENT PPB TEMP. CORRECTION BASED ON HEI 4 p}}

ML20095L403

Contents

Text

SUMMARY

3.0 INTRODUCTION

SUMMARY

3.0 INTRODUCTION

SUMMARY

Subject:

GENERAL COMMENT

Subject:

Subject:

Dear Mr. Stone:

Subject:

Dear Mr. Fron:

Dear Mr. Stone:

Subject:

Subject:

REFERENCES:

nn==

---w-NWy'

SUBJECT:

Subject:

Reference:

Reference:

**4

Subject:

Dear Mohan:

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ML20095L403

Text

SUMMARY

3.0 INTRODUCTION

SUMMARY

3.0 INTRODUCTION

SUMMARY

Subject:

GENERAL COMMENT

Subject:

Subject:

Dear Mr. Stone:

Subject:

Dear Mr. Fron:

Dear Mr. Stone:

Subject:

Subject:

REFERENCES:

nn==

---w-NWy'

SUBJECT:

Subject:

Reference:

Reference:

**4

Subject:

Dear Mohan:

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