Text

Rev 0 to Perry Unit 1 RPV Surveillance Matls Testing & Analysis
	ML20134M751
Person / Time
Site:	Perry
Issue date:	11/30/1996
From:	Branlund B, Sleight E, Tilly L; CENTERIOR ENERGY
To:	;
Shared Package
ML20134M755	List: B130179, Rev 0 to Perry Unit 1 RPV Surveillance Matls Testing & Analysis;
References
	GE-NE-B1301793, GE-NE-B1301793-01-R0, GE-NE-B1301793-1-R, NUDOCS 9702200396
	Download: ML20134M751 (104)
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Enclosure PY-CEWtR-2129L Page 1 of 104

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GE NuclearEnergy TechnicalServices Business GE-NE-B1301793-01 GeneralElectric Company Revision 0 j

175 Curtner Avenue, San Jose, CA 95125 November 1996 1

i PERRY UNIT 1 RPV SURVEILLANCE MATERIALS J

TESTING AND ANALYSIS a

O Prepared by:

k L. J. Tilly, Engm)eer v

c Engineering Services Verified by: % Ws E.s/. S b;S -

k%

E. W. Sleight, Engineer Engineering Seivices

.., proved byQ Thd.

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x B. J. Branlund, Project Manager Engineering Services 9702200396 970218" PDR ADOCK 05000440 p

PDR.

Enclosure i

PY-CEI/NRR-2129L Page 2 of104 GE-NE-B 1301793-01 Revision 0 IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT l

PLEASE READ CAREFULLY This report was prepared by General Electric solely for the use of Cleveland Electric Illuminating Company. The information contained in this report is believed by General Electric to be an accurate and true representation of the facts knovm, obtained, or provided to General Electric at the time this report was prepared.

The only undertakings of the General Electric Company respecting information in this document are contained in the contract between the customer and General Electric Company, identified in the purchase order for this report and nothing.:ontained in this document shall be construed as changing the contract. The use of this information by anyone other than the customer or for any purpose other than that for which it is intended, is not authorized; and with respect to any unauthorized use, General Electric Company makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.

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Enclosure PY-CEI/NRR 2129L Page 3 of 104 GE-NE-B1301793-01 4

Revision 0 TABLE OF CONTENTS 9b i

eaa F

ABSTRACT vii i

ACKNOWLEDGMENTS viii 1.

INTRODUCTION

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1 2.

SUMMARY

AND CONCLUSIONS 2

2.1 Summary ofResults 2

2.2 Conclusions 5

4 3.

SURVEILLANCE PROGRAMBACKGROUND 6

1 3.1 Capsule Recovery 6

3.2 RPVMaterials and Fabrication 6

i 3.2.1 FabricationHistory 6

3.2.2 Material Properties ofRPV at Fabrication 7

l 3.2.3 Surveillance Capsule Specimen Chemical Composition 7

}

3.3 Specimen Description 7

1 3.3.1 Charpy Specimens 7

1 4.

PEAK RPV FLUENCE EVALUATION 15 i

4.1 Flux Wire Analysis 15 4.1.1 Procedure 15 i

4.1.2 Results 16 O

4.2 Determination ofLead Factor 16

,O 4.2.1 Procedure 17 4.2.2 Results 18 4.3 Estimate of 32 EFPY Fluence 19 5.

CHARPY V-NOTCHIMPACT TESTING 26 5.1 Impact Test Procedure 26 5.2 Impact Test Results 27 5.3 Irradiated Versus Unirradiated Charpy V-Notch Properties 27 5.4 Comparison to Predicted Irradiation Effects 28 5.4.1 Irradiation Shift 28 5.4.2 ChangeinUSE 29 6.

ADJUSTED REFERENCE TEMPERATURE AND 49 UPPER SHELF ENERGY 6.1 Adjusted Reference Temperature at 32 EFPY 49 6.2 Upper ShelfEnergv at 32 EFPY 50 l

7.

PRESSURE-TEMPERATURE CURVE 53

7.1 Background

53 7.2 Non-Beltline Regions 54 7.3 Core Beltline Region 55 7.4 Closure Flange Region 55 7.5 Core Critical Operation Requirements of 10CFR50, Appendix G 56 8

REFERENCES 72 O.

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t Enclosure PY.CE1/NRR-2129L i

p,g,4 or go4 GE-NE-B1301793-01 Revision 0 TABLE OF CONTENTS iO 3

APPENDICES A.

IRRADIATED CHARPY SPECIMEN FRACTURE SURFACE A-1

-PHOTOGRAPHS 9'

4 B.

PRESSURE TEMPERATURE CURVES VALID FOR UP TO 9 EFPY AND 18 EFPY B-1

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Enclosure PY-CEI/NRR-2129L Page 5 of 104 GE-NE-B1301793-01 Revision 0 TABLES A) l M

11112 j n Pagn a

3-1 Chemical Composition ofRPV Beltline Materials from 9

Fabrication CMTR Records 3-2 Mechanical Properties ofBeltline and Other Selected 10 RPV Materials 3-3 Chemical Composition ofPerry Unit 1 Surveillance Materials From Surveillance Specimen Chemical Tests 11 4-1 Summary ofDaily Power History 20 4-2 Summary ofPerry Unit 1 Irradiation Periods 21 4-3 Surveillance Capsule Flux and Fluence for Irradiation from Start-up to 1/27/96 (3 Azimuth Capsule at 5.5 EFPY) and Measured Flux vs. Theoretical Flux at 3 Azimuth Dosimeter and Capsule 22 1

5-1 Vallecitos Qualification Test Results Using NIST Standard 30 Reference Specimens 5-2 Irradiated Charpy V-Notch Impact Test Results 31 5-3 Unirradiated Charpy V-Notch Impact Test Results 32 5-4 Significant Results ofIrradiated and Unirradiated Charpy 34 V-Notch Data 6-1 Beltline ART Values for Perry Unit 1 51 6-2 Upper ShelfEnergy Analysis for Perry Unit 1 Beltline Material 52 7-1 Perry Unit 1 P-T Curve Values 57 Required Temperatures at 100'F/hr for Figures 7-1 through 7-3 7-2 Perry Unit 1 P-T Curve Values 62 Required Temperatures at 200 F/hr for Figures 7-4 through 7-5 O

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Enckswe l

PY-CEI/NRR-2129L Page 6 of 104 GE-NE-B1301793-01 Revision 0 i

ILLUSTRATIONS 4

Figure litic P_ags v

3-1 Surveillance Capsule Holder Recovered from Peny Unit 1 12 l

3-1(a)

Charpy Specimen Capsule Identification 13

)

3-2 Schematic of the RPV Showing Identification 14 ofVessel Beltline Plates and Welds s

9 4-1 Schematic ofModel for Azimuthal Vlux Distribution Analysis 23 1

4-2 Relative Flux vs. Angle at RFV Inside Surface 24 4-3 Relative Flux vs. Elevation at RPV Inside Surface 25 5-1 Peny Unit 1 Unirradiated Charpy Base Metal Impact Energy 35 5-2 Perry Unit 1 Unitradiated Charpy Base Metal Lateral Expansion 36 5-3 Perry Unit 1 Irradiated Charpy Base Metal Impact Energy 37 5-4 Perry Unit 1 Irradiated Charpy Base Metal Lateral Expansion 38 5-5 Perry Unit 1 Unirradiated Charpy Weld Metal Impact Energy 39 5-6 Perry Unit 1 Unitradiated Charpy Weld Metal Lateral Expansion 40 5-7 Perry Unit 1 Irradiated Charpy Weld Metal Impact Energy 41 5-8 Perry Unit 1 Irradiated Charpy Weld Metal Lateral Expansion 42 5-9 Perry Unit 1 Irradiated Charpy HAZ Metal Impact Energy 43 5-10 Perry Unit 1 Irradiated Charpy HAZ Metal Lateral Expansion 44 5-11 Perry Unit 1 Unirradiated and Irradiated Charpy Base Metal Impact Energy 45 5-12 Perry Unit 1 Unirradiated and Irradiated Charpy Base Metal Lateral Expansion 46 5-13 Perry Unit 1 Unirradiated and Irradiated Charpy Weld Metal Impact Energy 47 5-14 Perry Unit 1 Unirradiated and Irradiated Charpy Weld Metal Lateral Expansion 48 7-1 Pressure Test Curve (Curve A) 67 7-2 Non-Nuclear Heatup/Cooldown (100 F/hr) (Curve B) 68 i

7-3 Core Critical Operation (100 F/hr) (Curve C) 69 7-4 Non-Nuclear Heatup/Cooldown (200 F/hr) (Curve B) 70 7-5 Core Critical Operation (200 F/hr) (Curve C) 71 i

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Enclosure PY-CE!/NRR-2129L Page 7 of 104 GE-NE-B1301793-01 Revision 0

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3 ABSTRACT The surveillance capsule at the 3' azimuthal location was removed at 5.5 EFPY at full power of 3579 MW from the Perry Unit I reactor in February 1996. The capsule contained flux t

wires for neutron fluence measurement and Charpy test specimens for material property I

l evaluations. The flux wires were evaluated to determine the fluence experienced by the test specimens. Charpy V-Notch impact testing was performed to establish the properties of the irradiated surveillance materials.

i r

The irradiated Charpy data for the weld specimens were compared to the unirradiated data to determine the shift in Charpy curves due to irradiation. The results are within the predictions of the Regulatory Guide 1.99 Revision 2.

The flux wire results combined with the lead factor were used to estimate the 32 EFPY O

fluence.

O The resulting estimate was in good agreement with analytical results and the previous l

nominal 32 EFPY fluence estimate.

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Enclosure PY-CEI/NRR-2129L Page 8 of 104 GE-NE-B1301793-01 Revision 0 ACKNOWLEDGMENTS The author gratefully acknowledges the efforts of other people towards completion of the contents of this report.

Capsule shipping and disassembly was performed by J.B. Myers. Charpy testing was completed by G. E. Dunning and B. D. Frew. Chemical composition analysis was performed by 1

P. Wall. Flux wire testing and analysis were performed by L. Kessler, R. Kruger and R. Reager.

Fluence and lead factor calculations were performed by D. Rogers, S. Wang and H.A. Careway.

Project management was conducted by Betty Branlund.

.A,

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Enclosure PY-CEI/NRR-2129L Page 9 0f l04 GE-NE-B1301793-01 Revision 0 e']

1. INTRODUCTION v

l Part of the effort to assure reactor vessel integrity involves evaluation of the fracture toughness of the vessel ferritic materials. The key values which characterize a material's fracture toughness are the reference temperature of nil-ductility transition (RTwr) and the upper shelf energy (USE). These are defined in 10CFR50 Appendix G [1] and in Appendix G of the ASME Boiler and Pressure Vessel Code,Section XI [2].

Appendix H of 10CFR50 [3] and ASTM E185-73 [4] establish the methods to be used for surveillance of the Perry Unit I reactor vessel materials.

In addition, compliance with ASTM E185-73 has been addressed in the Updated Safety Analysis Report [5]. The first vessel surveillance specimen capsule required by 10CFR50 Appendix H [3] was removed from Perry Unit 1 in February 1996. The irradiated capsu'e was sent to the GE Vallecitos Nuclear Center (VNC) for testing. The surveillance capsule contained flux wires for neutron flux monitoring and Charpy V-Notch impact test specimens fabricated using materials from the vessel materials within the core beltline region. The impact specimens were tested to establish properties for the irradiated materials.

j O

V The results of the surveillance specimen testing are presented in this report, as required per 10CFR50 Appendices G and H [1 & 3]. The irradiated material properties are compared to the unirradiated properties to determine the effect ofirradiation on material toughness for the base and weld materials, through Charpy testing.

Pressure-temperature (P-T) curves are included in this repon which have been developed to present steam dome pressure versus minimum vessel metal temperature incorporating appropriate non-beltline limits and irradiation embrittlement effects in the beltline. The P-T curves are established to the requirements of 10CFR50, Appendix G [1] to assure that brittle fracture of the reactor vessel is prevented.

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Enclosse I

PY-CEI/NRR-2129L Page 10 of104 GE-NE-B1301793-01 Revision 0

2.

SUMMARY

AND CONCLUSIONS V

2.1

SUMMARY

OF RESULTS The 3' azimuth position surveillance capsule was removed and shipped to VNC. The flux wires and Charpy V-Notch test specimens removed from the capsule were tested according to ASTM E185-82 [6]. The methods and results of the testing are presented in this report as

{

follows:

1 Section 3:

Surveillance Program Background RPV Materials and Fabrication I

e Material Properties e

Surveillance Specimen Chemical Composition Specimen Description e

I Section 4:

Peak RPV Fluence Evaluation Section 5:

Charpy V-NotchImpact Testing Section 6:

Adjusted Reference Temperature and Upper ShelfEnergy Section 7:

Pressure-Temperature Cmves The significant results ofthe evaluation are below:

The 3* azimuth position capsule was removed from the reactor after 5.5 EFPY a.

(Effective Full Power Years at 3579 MW ) of operation. The capsule contained t

4 flux wires: 2 copper (Cu) and 2 iron (Fe). There were 36 Charpy V-Notch specimens in the capsule: 12 each of plate material, weld material, and heat affected zone (HAZ) material.

b.

The chemical composition of copper (Cu) and nickel (Ni) for the irradiated surveillance materials was determined from a chemical composition analysis. The best estimate values for the surveillance material chemistries were calculated as averages of the available baseline and irradiated data. The best estimate values for 2

l Enclosure PY-CEI/NRR 2129L Page 11 of 104 GE-NE-B1301793-01 Revision 0 l

L the surveillance plate are 0.054% Cu and 0.62% Ni, and are 0.025% Cu and

/_)

L (/

0.91% Ni for the surveillance weld.

c.

The purpose of the flux wire testing was to determine the neutron flux at the suneillance capsule location. The flux wire results show that the fluence (from E >l MeV flux) received by the surveillance specimens was 3.53x1017 n/cm2 at removal (5.5 EFPY).

d.

A neutron transport computation had been performed based on the performance of the first fuel cycle. Relative flux distributions in the azimuthal and axial directions were previously developed in Reference 8. The lead factor was 0.40, relating the surveillance capsule flux to the peak inside surface flux. The lead factor was also calculated after the first capsule was removed at 5.5 EFPY, and determined to be 0.42, which was used for all calculations in this report.

The surveillance Charpy V-Notch specimens were impact tested at temperatures e.

selected to define the upper shelf energy (USE) and the transition of the Charpy V-Notch curves for the plate, weld, and HAZ materials. Measurements were b) y taken of absorbed energy, lateral expansion and percentage shear. From absorbed j

energy and lateral expansion curve-fit results, the "alues of USE and of index l

temperature for 30 ft-lb, 50 ft-lb and 35 mils lateral expansion (MLE) were obtained (see Table 5-4). Fracture surface photographs of each specimen are presented in Appendix A.

f.

The curves ofirradiated and unirradiated Charpy specimens established the 30 ft-lb shifts. The weld material showed a -14.7*F shift and a 3.2 n-lb decrease in USE (3.5% decrease). The plate material showed a -6.3 F shift and a 21.6 ft-lb increase in USE (25.2% increase).

g.

The measured shifts of-6.3 F for plate material and -14.7 F for weld material, for a fluence of 3.53x1017 2

n/cm, were within the Reg. Guide 1.99 [7] range predictions (ARTan12c) of-26 F to 42 F and -48 F to 64 F for plate and weld material, respectively. The best estimate chemical composition for the surveillance materials was used for this calculation.

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Enclosure PY-CE!/NRR-2129L Page 12 of 104 GE-NE-B1301793-01 i

Revision 0 1

h.

q The 32 EFPY RPV ID surface peak fluence prediction is 4.9x1018 n/cm2 at the

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vessel wall, based on the flux wire test and lead factor. This is about 14% higher than the previously established nominal 32 EFPY at 3579 MW fluence prediction t

(4.3x1018 n/cm2 [8]). The 32 EFPY fluence prediction is 3.42x1018 n/cm2 at 1/4 T.

t i.

The adjusted reference temperature (ART = Initial RTer + ARTwr + Margin) was predicted for each beltline material, based on the methods ofReg. Guide 1.99, Rev. 2. The ART for the limiting material, weld heat 627260, at 32 EFPY is 83.8 F and is lower than the 200 F requirement of Reg. Guide 1.99, Rev. 2 [7]

and 10CFR50 Appendix G [1].

j.

An update of the beltline material USE values at 32 EFPY was performed using the Reg. Gu'de 1.99, Rev. 2 methodology. The irradiated USE for all beltline materials vill remain above 50 ft-lbs through 32 EFPY as required in 10CFR50 Appendix G [1].

k.

P-T curves were developed for three reactor conditions: pressure test (Curve A),

C) non-nuclear heatup and cooldown (Curve B), and core critical operation (Curve C) which are valid for 32 EFPY of operation. The beltline curve is more limiting for Curve A at pressures above approximately 550 psig. For Curves B and C, the beltline curves are limiting for pressures above approximately 410 psig and 312 psig, respectively. The P-T curves as shown in Figures 7-1 through 7-5 include a set of B and C curves evaluated at heatup/cooldown rates of 100*F/hr and 200 F/hr.

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Encloswe PY-CEI/NRR-2129L Page 13 of 104 GE-NE-B1301793-01 Revision 0

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2.2 CONCLUSION

S

[.h v

The requirements of 10CFR50 Appendix G [1] deal with vessel design life conditions and with limits of operation designed to prevent brittle fracture. Based on the evaluation of surveillance testing results, and the associated analyses, the following conclusions are made:

The 30 ft-lb shifts and changes in USE are consistent with Regulatory Guide 1.99 a.

Revision 2 predictions.

b.

The values of ART and USE for the reactor vessel beltline materials are expected to remain within the limits of Reg. Guide 1.99, Rev. 2 [7] and Appendix G of 10CFR50 [1] (< 200 F and > 50 ft-lbs, respectively) for at least 32 EFPY of operation.

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Enclosure PY-CEI/NRR-2129L Page 14 of 104 GE-NE-B1301793-01 Revision 0

3. SURVEILLANCE PROGRAM BACKGROUND 3.1 CAPSULE RECOVERY i

The reactor pressure vessel (RPV) surveillance program consists of three surveillance capsules at 3,177, and 183 azimuths at the core midplane. The specimen capsules are held against the RPV inside surface by a spring loaded specimen holder. Each capsule is expected to I

receive equal irradiation because of core symmetry. During the January 1996 outage (5.5 EFPYj the surveillance capsule was removed from the 3 azimuthallocation. The capsule was shipped by cask to the GE Vallecitos Nuclear Center (VNC), where testing was performed.

Upon arrival at VNC, the capsule was examined for identification. The identification i

number stamped on the capsule corresponded to reactor number 70, as specified by GE drawings 131C8981G001 (Specimen Holder) and 105D5691 (Surveillance Program), for the Perry Unit 1 3 surveillance materials. The general condition of the capsule as received is shown in Figure 3-1.

The specimen holder contained 4 flux wires (two iron and two copper) and 36 Charpy specimens, 12 each of plate, weld, and HAZ materials in a sealed helium environment.

g.

1.

3.2 RPVMATERIALS ANDFABRICATION 3.2.1 Fabrication History The Perry Unit 1 RPV is a 238 inch diameter BWR/6 design.

Construction was performed by CBI Nuclear Company (CBIN) under the 1971 edition of the ASME Code through the 1972 Winter Addenda. The shell and head plate materials are ASME SA533, Grade B, Class I low alloy steel (LAS). The nozzles and closure flanges are ASME SA508 Class 2 LAS, and the closure flange bolting materials are ASME SA540 Grade B23 or B24 LAS [9].

Submerged arc or shielded metal arc welding of plates was followed by post-weld heat treatment at 1150*F. The fabrication impact test specimens were given a simulated post weld heat treatment at 1150*F plus 25 F minus 50 F, held 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months followed by furnace cooling to below 600'F, then air cooled. The identification of plates and welds in the beltline region is shown in Figure 3-2.

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_._.. _._ _ _._~ __.__ ___ ___ _ _ _ _.- _

Enclosure PY-CEI/NRR-2129L Page 15 of 104 GE-NE-B1301793-01 Revision 0 3.2.2 Material Properties of RPV at Fabrication Material certification records were retrieved from GE Quality Assurance (QA) records to determine chemical and mechanical properties of the vessel materials. The retrieved information l

for the beltline materials is documented in the USAR [5]. Table 3-1 shows the chemistry data for l

the beltline materials.. Properties of the beltline materials and materials at other locations of i

interest are presented in Table 3-2.

3.2.3 Surveillance Caosule Specim;n Chemical Comoosition i

Samples were taken from the irradiated base and weld specimens after they were tested.

l Chemical analyses were performed using a Spectraspan III plasma emission spectrometer. Each sample was dissolved in an acid solution to a concentration of 40 mg steel per mi solution. The spectrometer was calibrated for determination of Mn, P, Ni, Mo, V, Cr, Si and Cu by diluting National Institute of Standards and Technology (NIST) Spectrometric Standard Solutions. The 1

phosphorus calibration involved analysis of five reference materials from NIST with known i

phosphorus levels. Analysis accuracies are 10.005% (absolute) of reported value for phosphorus O

and iS% (relative) of reported value for o'.ner elements. 'Ihe chemical composition results are V

given in Table 3-3 for both irradiated and baseline surveillance plate and weld materials.

The baseline data were taken from CBIN material certification records as documented in the USAR

[5] for the plate and weld surveillance specimens.

i 3.3 SPECIMENDESCRIPTION The surveillance capsule holder contained 36 Charpy specimens: base metal (12), weld l

metal (12), and HAZ (12). The holder contained 4 flux wires: 2 iron and 2 copper. The chemistry and fabrication history for the Charpy specimens are described in this section.

3.3.1 Charov Soecimens The fabrication of the Charpy specimens is described in the CBIN drawings of the surveillance test program. All materials used for surveillance were fabricated from material of the same heat as one of the beltline plates (5].

The base metal specimens were cut from Heat C2557-1. The test plates received the same O

g heat treatment as the fabrication specimens for Heat C2557-1, including the post-weld heat y

Encic sure PY-CEI/NRR-2129L Pag: 16 of 104 GE-NE-B1301793-01 Revision 0 treatment for 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months at 1150 F +25 F/-50 F.

The Charpy specimens were removed from

()

Heat C2557-1 and machined from the 1/4 T and 3/4 T positions in the plate, in the transverse orientation (long axis nonnal to the rolling direction). The Charpy specimens had been stamped on one end with the fabrication codes as listed in CE surveillance program drawings for Perry Unit 1.

The weld metal and HAZ Charpy specimens were fabricated by welding together two pieces of the surveillance test plate Heat C2557-1 with the same weld procedure used to produce welds in the beltline region. Welding records obtained from CBIN show the surveillance weld to be submerged arc weld with Heat SP6214B, Linde 124 Flux, and Lot 0331. The welded test plates received stress reliefheat treatment at 1150 F +25 F/-50'F to simulate the RPV fabrication conditions. The weld and HAZ specimens were cut from the material avoiding the volume near the root of the welds. The base metal orientation in the weld and HAZ specimens was transverse.

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O GE-NE-131301793-01 Revision 0

??E Table 3-1 5I 5

g Chemical Composition of RPV Beltline Materials from Fabrication CMTR Recordsa g

5 t-Composition by Weight Percent Identification

IIcat/ Lot No.

Cu-Ni C

Mn P.

S Si

'Mo PLATF6:

e Lower-Intermediate Shell Plates:

22-1-1 C2557-lb 0.06 0.61 0.23 1.32 0.010 0.025 0.27 0.54 22-I-2 B6270-1 0.06 0.63 0.20 1.28 0.012 0.015 0.23 0.53 22-1-3 Al155-1 0.06 0.63 0.20 1.33 0.010 0.013 0.28 0.54 WELDS:

Lower-Intermediate Venical:

13D,BF 627260 / B322A27AE 0.06 1.08 0.040

!.25 0.02 0.022 0.56 0.64 BD,BE,BF 626677 / C301 A27AF 0.01 0.85 0.048

!.10 0.015 0.022 0.45 0.45 BD,BE,BF SP6214Bc /

0.02 0.82 0.051 1.39 0.013 0.017 0.53 0.52 Flux 124, Lot 033 i BE 624063 / D228A27A 0.03 1.00 0.041 1.12 0.009 0.018 0.41 0.54 DE 627069 / C312A27A 0.01 0.94 0.037 1.07 0.013 0.019 0.60 0.52 a Data from GE QA Records and USAR [5]

b Surveillance Plate c Surveillance Wcld L

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Enclosure PY-CEI/NRR-2129L Page 18 of 104 GE-NE-B1301786-01 Revision 0 Table 3-2 Mechanical Properties of Beltline and Other Selected RPV Materialsa

-Location Identification -

Heat Numter:

' Initial RTwor:'

(op)

Lower-Intennediate Beltline 22-1-1 C2557-1 10 ShellPlates Beltline 22-1-2 B6270-1

-30 Beltline 22-1-3 A1155-1

-10 Vertical Welds Beltline BD, BF 627260

-30 Beltline BD, BE, BF 626677

-20 Beltline BD, BE, BF SP6214B

-40 Beltline BE 624063

-50 Beltline BE 627069

-60

/m

)

Upper Shell Non-Beltline 24-1-1 C2451-1 10 Head Flange Non-Beltline 32-1 48D1278-1-1

-30 Feedwater Nozzle Non-Beltline 59-1 Q2055W

-20 Bottom Head Non-Beltline 13-2 C2469-2 10 Closure Boltsb Non-Beltline 83833 70 a Test data information from GE QA Records b LST = 10 F (the lowest CVN test temp.) + 60 F

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O Gil-N!!-B 1301793-0 I Revision 0 Tahic 3-3 dk Chemical Composition of Perry Unit i Surveillance Materials from Surveillance Specimen Chemical Tests 2s 5

r-Metal Sampic ID Metal SamplS Mn'(wt%)..Ni(wt%)

Cu (wt%) Mo (wt%)

Si (wt%):.Cr (wt%),

V.(}vt%); [P (wt%)

l Type-28983 13ase 1.29 0.63 0.052 0.56 0.25 0.059 0.0073 0.011 28984 Ilasc 1.30 0.65 0.054 0.58 0.26 0.062 0.0080 0.014 28985 Base 1.20 0.61 0.050 0.55 0.22 0.059 0.0064 0.015 Ilaselinea Base I.32 0.61 0.060 0.54 0.27 n/a 0.0010 0.010 Data Avg.

I.28 0.62 0.054 0.56 0.25 0.060 0.0060 0.010 Std. Dec.

0.05 0.02 0.004 0.02 0.02 0.002 0.0030 0.000 28971 Weld 1.25 0.89 0.024 0.49 0.46 0.136 0.0049 0.013 28972 Weld 1.36 0.97 0.027 0.54 0.50 0.149 0.0081 0.014 28973 Weld 1.35 0.97 0.031 0.56 0.45 0.I46 0.0062 0.015 13asclinea Weld 1.39 0.82 0.020 0.52 0.53 n/a 0.0040 0.013 Data Avg.

l.34 0.91 0.025 0.53 0.49 0.I44 0.006 0.014 Std. Dec.

0.06 0.07 0.004 0.03 0.04 0.007 0.002 0.00I a Sec Table 3-1 1I

l Enclosure

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PY-CEl/NRR-2129L Page 20 of 104 GE-NE-B1301793-01 j

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Enclosure PY-CEI/NRR-2129L Page 21 of 104 GE-NE-B1301793-01 Revision 0 i

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q c;.l,h;m..:;=a,IC *

e

., 3r; m

=s : ;.

~

- ~. ~.. j '.

L'

..Q;: HiL 7, _m:.4 g(y p.-

w%3%^y /

e./ 2',

c.d,

,t*;

/!

irs 2 e.-

s.. /,

.wr

p,arv+-

.rmj ge,

r% g e

,,-4

. _.,......mdg.

s

_ gg - :-.

a-*

_e...nz,a.4;a

.:s:z e,

x "s~.

' ' C.. ^.. -

- ::4Wp + ~

.5

w m a

~% usa;y=b

-r'.::..).=,.la.*:f y.J*,5, :j w m. 'w,4 ~n.+ ;7, r,, _,,

% k:"'s

_QQql.;".kv.'..<w an:%

r

, %.m i a m-3

. a=. _ n. u 2..-

_.-.w'a n,:w p

w

.sp,7,., :a -

n ~.

07 f.: +

c.

g,.7., -

a. ~ ? "T,l<h.. a..'

Figure 3-1(a): Charpy Specimen Capsule Identification (3 AzimuthalLocation capsule) 13

Enclosure PY-CEI/NRR-2129L 4

Page 22 of 104 GE-NE-B1301793-01 Revision 0 O

4 j

Vessel Flange 4

ummmmmmmmmmmmun summmmmmmmmmmm-f 1

Upper Shell Girth Welds f

(#4 Shell Ring) e

=

l 7

Longitudinal Welds f

E s

N intermediate Shell

,_f-(#3 Shell Ring)

N

[>

n

2 Shell Ring Shell Belt ine

= instrumentation (4) 2 1-1 C255 -1

(#2 Sh I ng)

O,,

Region 22-1-2 B6270-1 V

22-1-3 A1155-1 Lower Shell N

Recirc. iniet (to)

Recirc. f

(#1 Shell Ring)

{ Jet Pump Inst. (2) outiet (2) f Bottom Head Enclosure Figure 3-2. Schematic of RPV Showing Identification of Vessel Beltline Plates and Welds O

14

l Enclosure i

PY-CEI/NRR-2129L Page 23 of 104 GE-NE-B1301793-01 Revision 0

4. PEAK RPV FLUENCE EVALUATION ym) v Flux wires removed from the 3 location capsule were analyzed, as described in Section 4.1, to determine flux and fluence received by the surveillance capsule. The lead factor, determined as described in Section 4.2, was used to establish the peak vessel fluence from the flux wire results. Section 4.3 includes 32 EFPY peak fluence estimates. All references to EFPY in this report are defined as effective full power years at 3579 MW -t 4.1 FLUX WIRE ANALYSIS 4.1.1 Procedure The surveillance capsule contained 4 flux wires: 2 iron and 2 copper. Each wire was removed from the capsule, cleaned with dilute acid, weighed, mounted on a counting card, and analyzed for its radioactivity content by gamma spectrometry. Each iron wire was analyzed for Mn-54 content and each copper wire for Co-60 at a calibrated 4-cm source-to-detector distance with 170-ce Ge and 100-cc Ge(Li) gamma spectrometers.

OQ To properly predict the flux and fluence at the surveillance capsule from the activity of the flux wires, the periods of full and partial power irradiation and the zero power decay periods were considered. Operating days for each fuel cycle and the reactor average power fraction were derived from records provided by Cleveland Electric Illuminating Company and are shown in Tables 4-1 and 4-2 respectively.

From the flux wire activity measurements and power history, reaction rates for Fe-54 (n,p) Mn-54 and Cu-63 (n,ct) Co-60 were calculated. The E >l MeV fast flux reaction cross sections were determined using multiple dosimeter and spectrum unfolding techniques (11].

The cross sections for the iron and copper wires are 0.156 barn and 0.00264 barn, respectively.

These values are consistent with other measured cross section functions determined at GE's Vallecitos Nuclear Center from more than 65 spectral determinations for BWRs and for the General Electric Test Reactor using activation monitors and spectmm unfolding techniques.

These data functions are applied to BWR pressure vessel locations based on water gap (fuel to vessel wall) distances. The cross sections for > 0.1 MeV flux were determined from the measured 0.1 to 1 MeV cross section ratio of 1.6 [11].

AV 15

l Enc.losure PY-CEl/NRR-2129L Page 24 of104 GE-NE-B1301793-01 Revia, ion 0 4.1.2 Results The measured activity, reaction rate and full-power flux results for the 3 location surveillance capsule are given in Table 4-3.

The E > 1 MeV flux values were calculated by dividing the wire reaction rate measurements by the corresponding cross sections, factoring in the local power history for each fuel cycle. The fluence result, 3.53x1017 n/cm2 (E > 1 MeV), was obtained by using the following equation:

O. = *r, tpi (4-1) c i

where, @c. = fluence measured by the Cu dosimeters Gr, = full power flux value for Cu ti

= operating time pi

= full power fraction as shown in Tables 4-1 and 4-2. Virtually identical results were obtained for Fe. The accuracies of the values in Tables 4-3 for a 2e deviation are influenced by the following sources of error:

11%

counting rates 15 %

power history i 10 %

cross sections The overall 2a error is estimated to be about 20%.

4.2 DETERMINATION OF LEAD FACTOR The flux wires detect flux at the location of the surveillance capsule. The wires will reflect the power fluctuations associated with the operation of the plant. However, the flux wires are not at the location of peak vessel flux. A lead factor is required in order to relate the flux at

)

the location of the wires to the peak flux. The lead factor is the ratio of the flux r. the surveillance capsule to the peak flux at the vessel inside surface. The lead factor is a functbn of the core and vessel geometry and depends on the distributions of power density and coolant voids in the core. The lead factor was calculated for the Perry Unit 1 geometry, using data for a typical operating cycle to determine power shape and void distribution. The methods used to calculate the lead factor are discussed below.

16

4 Encloswe n

-2 N i

Page 25 of104 GE-NE-B1301793-01 i

Revision 0 4.2.1 Procedure i

i The lead factor for the RPV inside wall was determined by using a combination of two separate two-dimensional neutron transport computer analyses. The first of these established the

]i azimuthal and radial variation of flux in the vessel at the fuel midplane elevation. The second analysis determined the relative variation of flux with elevation.

The azimuthal and axial distribution results were combined to provide a simulation of the three-dimensional distribution of flux. The ratio of fluxes, or lead factor, between the surveillance capsule location and the peak flux locations was obtained from this distribution.

1 The DORT computer program, which utilizes the discrete ordinates method to solve the

- Boltzmann transport equation in two dimensions, was used to calculate the spatial flux 4

distribution produced by a fixed source of neutrons in the core region. The azimuthal distribution i

was obtained with a model speci6ed in (R,0) geometry, assuming eighth-core symmetry with t

4 l

reflective boundary conditions at 0* and 45. A schematic of the (R,0) vessel model is shown in Fi ure 4-1. The model incorporates inner and outer core regions, the shroud, water regions inside

{

E 4

j and outside the shroud, and the vessel wall. A spatial mesh consisting of 131 radial intervals and i

)

90 azimuthal intervals was used. The core region material compositions and neutron source densities were representative of conditions et the core midplane elevation (75 inches above the i

bottom of active fuel), which is near the elevation of the wires. Neutron cross-sections were specified for a 26 energy group set, with angular dependence of the scattering cross-sections f

approximated by a third-order Legendre polynomial expansion. The output of this calculation l

provided the distribution of flux as a function of azimuth and radius at reactor midplane. The l

azimuth of the peak flux and its magnitude relative to the flux at the 3 azimuth, which is the azimuth of the flux wires, were determined from this distribution.

f 1

The calculation of the axial flux distribution was performed in (R,Z) geometry, using a simplified cylindrical representation of the core configuration and realistic simulations of the axial variations of power density and coolant mass density. The core description was based on i

conditions near the azimuth angle of 21.8 where the edge of the core is closest to the vessel wall.

The elevation of the peak flux was determined, as well as its magnitude relative to the flux at the surveillance capsule elevation.

~ O 4

17 i

,,. ~. -

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

Enclosure PY-CEI/NRR-2129L Page 26of104 GE-NE-B1301793-01 Revision 0 4.2.2 Results V

The two-dimensional transport calculations indicate that flux maxima occur at azimuthal i

locations which are displaced by 25.75 from the RPV quadrant references (0, 90, etc.), at an elevation about 100 inches above the bottom of the active fuel. The capsule from which the j

surveillance samples and flux wires were retrieved was located at 3 The flux peak closest to this location occurs at the 25.75' azimuth, as shown in Figure 4-2. The relative distribution of flux versus elevation at the RPV inside surface is shown in Figure 4-3. The calculated core midplane flux at the (R,0) coordinates corresponding to the capsule position was multiplied by the ratio of flux at the capsule elevation to flux at midplane, as determined from the (R,Z) calculation. The resulting flux at the surveillance capsule is 1.6x10 n/cm2-s. The peak flux at the vessel surface 9

was similarly obtain~ed by multiplying the midplane flux at the peak azimuth by an axial adjustment factor derived from the (R,Z) calculation. The resulting peak flux is 3.8x10 n/cm2-s. Therefore, 9

the lead factor is 1.6/3.8=0.42.

The transport calculation of surveillance capsule flux,1.6x109 n/cm -s, is about 20%

2 lower than the dosimetry result of 2.0x10 n/cm -s.

This is considered to be good agreement in 9

2 view of the significant uncertainties in the analytical model and in the experimental results. The difference may, in part, result from the use of nominal rather than as-built vessel radius.

However, it should be noted that the lead factor is not as sensitive to these differences as the magnitude of the flux. A difference in vessel radius has little, if any, effect on the calculated lead factor, since the difference would affect both capsule radius and vessel radius and would not significantly alter the ratio of fluxes at the two locations.

The fracture toughness analysis is based on a 1/4 T depth flaw in the beltline region, so the attenuation of the flux to that depth is considered. This attenuation is calculated according to Reg. Guide 1.99 requirements, as shown in the next section.

pJ l

l8

Enclosure PY-CEI/NRR-2129L Page 27 of104 GE-NE-B1301793-01 Revision 0 4.3 ESTIMATE OF 32 EFPY FLUENCE

- (G

)

The inside surface fluence (fsurf) at 32 EFPY at 3579 MW is determined from the flux t

wire fluence at a particular EFPY and lead factor according to f rf * (f su cap

32 EFPY)/(LF

CEFPY)

(4-2) where, fsurf = 32 EFPY fluence at the peak vesselinside surface fcap = capsule fluence measured at the CEFPY 32 EFPY = end oflife EFPY based on a 40-year operation at an 80% capacity factor CEFPY = the current EFPY for the capsule LF

= lead factor The surveillance capsule was removed from Perry Unit 1 at 5.5 EFPY as calculated in Table 4-2. The fluence at 5.5 EFPY was determined to be 3.53x1017 n/cm2 using Equation 4-1, and ;he lead factor was determined to be 0.42 as discussed in Section 4.2.

Using this information with Equation 4-2, the resulting 32 EFPY fluence value at the peak vessel inside surface is:

{

fsurf= (3.53x1017

32)/(0.42

5.5) = 4.9x1018 n/cm2 at the peak location.

The peak surface fluence at 32 EFPY is about 14% higher than the nominal value (4.3x1018 n/cm ) that was calculated from the first cycle dosimetry as reponed in GE report [8).

2 This is well within the 20% accuracy expected as reported in Section 4.1.2.

The 1/4 T fluence (f) is calculated according to the Reg. Guide 1.99 [7] equation:

f = fsurf(e-0.24x),

(4-3) where x = distance, in inches, to the 1/4 T depth. The vessel beltline lower-intermediate shell ring is 6.23 inches thick ordered,6.0 inches minimum requirement. The corresponding depth, x, taken from the minimum required thickness is 1.5 inches. Equation 4-3 evaluated for this value of x gives the 1/4 T value of 32 EFPY fluence, f = 3.42x1018 n/cm2 for the lower-intermediate shell ring.

Ab 19

Enclosure PY-CEI/NRR-2129L Page 28 of 104

,p Table 4-1 Summary of Daily Power Ilistory

' Cycle Date On Date Off Days On mwd (t)

Cycle Date On Date Off Days On mwd (t)

(t ) ~

(t) i 1

6/6/86 7/28/86 53 3774 12/1/93 12/2/93 2

4994 7/28/86 3/24/87 240 26628 12/14/93 12/31/93 18 59853 i

4/28/87 6/30/87 64 80170 1/1/94 181/94 31 99512 8/21/87 1/3/88 136 235097 2/1/94 2/5/94 5

13214 1/29/88 5/18/88 111 337679 5

7/25/94 7/27/94 3

752 5/30/88 9/16/88 110 309440 8/1/94 8/31/94 31 55697 9/29/88 10/21/88 23 69722 9/1/94 9/30/94 30 105893 11/4/88 2/22/89 111 368666 10/1/94 10/31/94 31 110497 2

7/24/89 9n/90 411' 1345154 11/1/94 11/30/94 30 107324 3

1/4/91 1/31/91 28 89705 12/1/94 12/31/94 31 95245 1

2/1/91 2/28/91 28 91513 1/1/95 1/31/95 31 110080 3/1/91 3/31/91 31 107279 2/1/95 2/28/95 28 96620 4/1/91 4/2/91 2

3254 3/1/95 3/31/95 31 104382 4/18/91 4/30/91 13 43474 4/1/95 4/17/95 17 60351 5/1/91 5/31/91 31 108915 4/27/95 4/30/95 4

4295

^

6/1/91 6/30/91 30 106233 5/1/95 5/31/95 31 109779 7/1/91 7/31/91 31 101815 6/1/95 6/30/95 30 106760

(~'

8/1/91 8/31/91 31 108924 7/1/95 7/31/95 31 110036 N.

9/1/91 9/30/91 30 107107 8/1/95 8/31/95 31 108890 10/1/91 10/31/91 31 95057 9/2/95 9/30/95 29 74190 11/1/91 1160/91 30 105587 10/1/95 10/31/95 31 110673 12/1/91 12/22/91 22 75434 11/1/95 11/11/95 11 34008 1/5/92 181/92 27 93158 11/19/95 1180/95 12 38377 2/1/92 2/29/92 29 103585 12/1/95 12/31/95 31 101609 3/1/92 3/21/92 21 70454 1/1/96 1/27/96 27 75282 4

6/13/92 6/30/92 18 44040 7/1/92 7/31/92 31 107547 TotalDays Sum 8/1/92 8/31/92 31 108450 2614 7.18E+06 9/1/92 9B0/92 30 90400 10/1/92 10/31/92 31 81910 11/1/92 1180/92 30 102213 12/1/92 12/31/92 31 108955

' For Cycle 2, specific on/off dates are not 1/1/93 1/9/93 9

28182 pressted, simply the total number of days in 3n/93 3/26/93 20 44396 the cycle.

6/2/93 6/30/93 29 94537 7/1/93 7/9/93 9

29453 7/27/93 7Bl/93 5

6001 8/1/93 8/31/93 31 99547 9/1/93 980/93 30 105938 10/1/93 10/3/93 3

6227 11/16/93 11/30/93 15 37155 20 l

Enclosure PY-CEl/NRR-2129L Page 29 of104 GE-NE-B1301793-01 5-Revision 0 hU i

k i

Table 4-2 i

Summary of Perry Unit 1 Irradiation Periods l

Cycle t 10n:~ * ' ' ' Off '

Days One mwd JFull_ Power

. Full Power' 7

. Days i Fradtioni a

1 6/6/86 2/22/89 993 1431176 399.9 0.40 2

7/24/89 9/7/90 411 1345154 375.8 0.91 3

1/4/91 3/21/92 443 1411493 394.4 0.89 4

i 4

6/13/92 2/5/94 603 1272523 355.6 0.59 5

7/25/94 1/27/96 552 1720738 480.8 0.87 TOTAL (EFPD) = 2006.5 j

TOTAL (EFPY) =

5.5 i

1 a Full Power Days based on thermal power of 3579 MWt 4O 1

?

l a

a 4

4 P

V 21

Gli-Nii-ill301793-01 Itevision 0 Tahic 4-3 g[

Surveillance Capsule Irlux and Fluence bf' for Irradiation from Start-up to 1/27/96 (3 Azimuth Capsule at 5.5 EFPY)

Eg is 8

> Average

Full Power Fluxb Full Power Fluk6 Fluence.

Fluenecc Wire Average -

a (lilement) -

dps/g Element

... I{cactioit Rate (n/cn1-s);

2 2

(ii/cm -s).

(n/cm )

(n/cm )-

(at end ofirradiation) :

. [diis/ nucleus (saturated)l' vE>I McVT E>0.1 McV E>l McV E>0.1 M eV Copper 1.55E04 5.38E-18 2.04E09 3.26E09 3.531117 5.65I117 Iron I.461i05 3.I8E-16 2.041!09 3.261?09 3.531117 5.651!!7 l

a Obtained by R.D Reager and LK. Kessler b Full power flux, based on thermal powcr of 3579 MWt C 1.6 times the E >l McV result Measured Flux vs. Theoretical Flux at 3 Azimuth Dosimeter and Capsule E>l MeV -

l EFPY* '

Measured Flux Theofblical Flux **:-

2 (n/cm -s)

(n/cm2.3) 1989 liOC1 Dosimeter [8]

l.09 1.7x109 not available 1996 EOCS Flux Wires 5.5 2.0x109 1.6x109 6

liffective Full Power Years at 3579 MW t

9 2

- Design Value = 2.6x10 n/cm.s calculated from the original design lluence of 6.5x1018 2

n/cm and lead factor of 0.4 22

Enclosure PY-CEI/NRR-2129L Page 31 of 104 GE-NE-B1301793-01 Revision 0 0

a

/1 l 1

A ilil l

l1 l1l1 l 1

f1f1 f 1

1 1

1f1l1f1 l 1 1

If1 i1l1f1 I

f1 1

1l1f1 f1[1 l1 1k1f1 f1l1 I

I Il 1 1

REFLECTIV:

2l2 1l1]1 1

BOUNDARh 2

2h2f1 1l1l1 3l3 (,

i 2l2l2l1l1l1l1l1 l1

{!N R!OR 2l2l2 l

2l2l2l2 2

57

/"]

2 j 2l2 f 2 f 2 f2

'p' -X RIOR C AL

-Q WATER,

, REGION

/ SHROUD: 10 INTERVALS

, WATER REGION:

44 INTERVALS 90 INTERVALS VESSEL WALL:

IN AZ1MUTHAL 20 WWALS DIRECTION Il = CORE INTERIOR FUEL

[2. CORE EXTERIOR FUEL c-Figure 4-1. Schematic of Model for Azimuthal Flux Distribution Ana O

23 J

. ~..

O O

O GE-NE-B 1301793-01 Revision 0 Nkbf FIGURE 4-2 RELATIVE FLUX VS. ANGLE AT RPV INSIDE SURFACE 1.00 E

0.90 0.80 g

W 0.70 A

0.60 u.z

@ 0.50 7

0.40 5

h 0.30 m:

O.20 0.10 O.00 0

5 10 15 20 25 30 35 40 45 ANGULAR POSITION (DEGREES) 24

O O

O GE-NE-B 1301793-01 Revision 0Nk ir FIGURE 4-3 y

g RELATIVE FLUX VS. ELEVATION AT RPV INSIDE SURFACE C

E 4 1'00

/[

f N

0.90 0'80

/

B

/

2 0.70 f

3 0.60 u.

z 0.50 a

0.40 g

?

h 0.30 m

0.20 i

0.10 0.00 15 25 35 45 55 65 75 85 95 105 115 125 135 DISTANCE FROM BAF (INCHES) 25

Enclosure PY-CD/NRR-2129L Page 34 oflos GE-NE-B1301793-01 Revision 0

~ q( v j

5. CHARPY V-NOTCH IMPACT TESTING The 36 Charpy specimens recovered from the surveillance capsule were impact tested temperatures selected to establish the toughness transition and upper shelf of the irradiated RPV materials. Testing was conducted in accordance with ASTM E23-94b [12].

5.1 IMPACT TEST PROCEDURE The Vallecitos testing machine used for irradiated specimens was a Riehle Model PI-2 impact machine, serial number R-89916. The maximum energy capacity of the machine is 240 ft-lb, which produces a test velocity at impact of 15.44 ft/sec.

The test apparatus (Riehle machine) and operator were qualified using NIST standard reference material specimens. The Standard Reference Materials (SRMs) consist of three sets of specimens which cover the energy range of the apparatus. Each set has a designated failure energy and a standard test temperature. According to ASTM E23-94b [12], the test apparatus averaged results must reproduce the NIST standard values within an accuracy of 5% or (D

11.0 ft-lb, whichever is greater. The results of the qualification are summarized in Table 5-1.

U Charpy V-Notch tests were conducted at temperatures between -100 F and 300 F. The cooling fluid used for irradiated specimens tested at temperatures at or below 60 F was ethyl alcohol.

At temperatures between 60 F and 200 F, water was used as the temperature conditioning fluid. The specimens were heated in silicon oil for test temperatures above 200 F.

Cooling of the conditioning fluids was done by heat exchange with liquid nitrogen through a copper coil; heating was done by an immersion heater. The bath of fidd was mechanically stirred to maintain uniform temperatures. The fluid temperature was mer.5ured with a calibrated Type K thermocouple positioned near the impact samples. After equili'> ration at the test temperature for at least 5 minutes, the specimens were manually transferred with centering tongs to the Charpy test machine and impacted in less than 5 seconds.

For each Charpy V-Notch specimen the test temperature, energy absorbed, lateral expansion, and percent shear were determined.

In addition, for the irradiated specimens, photographs were taken of fracture surfaces. Lateral expansion and percent shear were measured according to specified methods [12]. Percent shear was determined using method number 1 of f]

Subsection 11.2.4.3 of ASTM E23-94b [12], which involved measuring the length and width of v

26

- - - =.

- - - - - - - ~ "

~^~^"~~^]

Enclosse l

PY-CEl/NRR-2129L j

Page 35 of104 GE-NE-B1301793-01 Revision 0 l

the cleavage surface in inches and determining the percent shear value from Table 2 -of 3

l ASTM E23-94b [12].

l 5.2 IMPACT TEST RESULTS J

i

{

Twelve Charpy V-Notch specimens each ofirradiated base, weld, and HAZ material i

were tested at temperatures (-100 F to 300 F) selected to define the toughness transition and upper shelf portions of the fracture toughness curves. The absorbed energy, lateral expansion, i

and percent shear data are listed for each material in Table 5-2. Plots of absorbed energy and j

lateral expansion for base, weld, and HAZ materials are presented in Figures 5-1 through 5-10.

l The irradiated plate and weld metal curves are plotted along with the corresponding unirradiated curves in Figure 5-11 through Figure 5-14. The fracture surface photographs and a summary of the test resuhs for each specimen are contained in Appendix A.

The irradiated plate, weld and HAZ energy and lateral expansion data are fit with the hyperbolic tangent function developed by Oldfield for the EPRIIrradiated Steel Handbook [13];

Y = A + B

TANH [( T - To )/C],

where Y = impact energy or lateral expansion T = test temperature, and A, B, To and C are determined by non-linear regression.

The TANH function is one of the few continuous functions with a shape characteristic oflow alloy steel fracture toughness transition curves.

5.3 IRRADIATED VERSUS UNIRRADIATED CHARPY V ' NOTCH PROPERTIES A shift in RTan is established by comparing the irradiated Charpy specimen data to baseline unirradiated Charpy data. This has been done for the Perry Unit I surveillance weld material (Heat 5P6214B, Linde 124 Flux, Lot 0331) and surveillance plate material (Heat C2557-1), where enough fabrication Charpy data exists to develop a full Charpy curve.

The.unirradiated data was fit to a -TANH function as described in the previous section.

Transverse data provided in Table 5-3 was used for the plate material. The single wire test data provided in Table 5-3 was used in the weld material plots to be consistent with the surveillance weld material.

27

. _ =

Enclosure PY-CEI/NRR-2129L Page 36 of 104 GE-NE-B1301793-01 Revision 0 5.4 COMPARISON TO PREDICTED IRRADIATION EFFECTS

.s

[V\\

\\

5.4.1 Irradiation Shift The measured transition temperature shifts for the plate and weld materials were compared to the predictions calculated according to Regulatory Guide 1.99, Revision 2 (Reg. Guide)[7]. The inputs and calculated values for irradiated shift for the plate and weld materials based upon measurements taken from the 3 azimuth capsule at 5.5 EFPY at 3579 MW t

are as follows:

Plate:

Copper =

0.054 %

Nickel =

0.62 %

i CF =

33 fluence =

3.53x1017 n/cm2 Reg. Guide 1.99 ARTmr =

8F l

Reg. Guide 1.99 ARTer 2cA(34 F)= 42 F max,-26 F min Measured 30 ft-lb shift =

-6.3 *F Weld:

Copper =

0.025 %

Nickel =

0.91 %

CF =

34 fluence =

3.53x1017 n/cm2 Reg. Guide 1.99 ARTmr =

5*F Reg. Guide 1.99 ARTeri 2cA(56 F) = 64 F max, -48*F min Measured 30 ft-lb shift =

-14.7 F The weight percents of Cu and Ni are best estimates based on averaging (see Table 3-3).

The CF values shown above are the chemistry factors for the materials obtained from Table 1 of Reg. Guide 1.99. The fluence factor for the Reg. Guide calculation of 30 fi-lb shift may either be calculated according to the Reg. Guide definition fluence factor = f(0.28 - 0.10 log f)

(5-1) or it may be obtained from the Reg. Guide Figure 1 [7]. Using equation 5-1, the fluence factor was calculated to be 0.24.

These values are used to calculate the Reg. Guide prediction for J

30 ft-lb shift and USE decrease for comparison to the measured shift and USE decrease for the 28

Enclosme PY-CEl/NRR-2129L -

Page 37 of104 GE-NE-B1301793-01 i

Revision 0 irradiated surveillance materials. The predicted 30 ft-lb temperature shift (ARTsm) was also calculated according to the Reg. Guide using the equation

)

ARTer = (CF) f(0.28 - 0.10 log f)

(5-2) 4 1

The measured 30 ft-lb temperature shifts (Table 5-4) of-6.3'F for the plate material and -14.7*F for the weld material are within the bounds of the Reg. Guide prediction with the uncertainty of f

20.

l 5.4.2 Channe in USE t

J Using the copper and fluence data above with Figure 2 of the Reg. Guide, decreases in USE of approximately 6% and 7.3% are predicted for the plate and weld materials, respectively.

l 4

The actual impact energy curves show an increase in the USE value of 25% for the plate material and a decrease of 3.5% in the USE value for the weld material.

4 i

Upper ShelfEnergy is expected to decrease due to irradiation. The amount of expected decrease is related to both copper content and fluence, which is relatively low (about an order of magnitude less than in PWRs) in BWRs. Both the copper content in the Perry Unit 1 I

vessel (0.06%) and the fluence (3.53x1017 n/cm2) are relatively low, and therefore, materials may not experience significant decreases in USE. Experience has shown that, at relatively low fluence and considering typical scatter in Charpy data, BWR vessel material USE test results may show an increase. Given the typical scatter in Charpy data and the low fluence of the irradiated specimens, the increase in USE in the Perry Unit 1 plate material is not unexpected.

a O

29

-~

l Enclosure PY-CE!/NRR-2129L Page 38 of104 GE-NE-B1301793-01 Revision 0 j

q Table 5-1 V

Vallecitos Qualification Test Results Using NIST Standard Reference Specimens

_7 Test;..

jl=rgy1 i Acceptable :

. 1Spe;z.g; cunent lBith;

,T 4 emperature; /Absorbe&

" Range; 41dentifisationk 4MediumJ -

F( F) 4 3 (f14b)1 f(ft-lb)?

1 Vallecitos HH-461 Ethyl Alcohol

-40 74

{

Riehle Machine IIH-46 2 Ethyl Alcohol

-40 72.5 (tested 8/95)

HH-46 3 Ethyl Alcohol

-40 75.5 HH-46 4 Ethyl Alcohol

-40 73 HH-46 5 Ethyl Alcohol

-40 77 A/erage 74.4 74.3 3.7 pass LL-451 Ethyl Alcohol

-40 13 LL-45 2 Ethyl Alcohol

-40 13 LL-45 3 Ethyl Alcohol

-40 13 LL-45 4 Ethyl Alcohol

-40 13 LL-45 5 Ethyl Alcohol

-40 13 Average 13 12.8 1.0 pass SH-51 Ethyl Alcohol 70 170 SH-5 2 Ethyl Alcohol 70 170 l

SH-5 3 Ethyl Alcohol 70 162.5 SH-5 4 Ethyl Alcohol 70 161.5 SH-5 5 Ethyl Alcohol 70 156 Average 164 164.118.2 pass i

O 30

..__.._..______._._.__.._...m._.

Enclosure PY-CE!/NRR-2129L Page 39 of 104 GE-NE-B1301793-01 Revision 0 Table 5-2 l

l I

Irradiated Charpy V-Notch Impact Test Results Test

Fracture Lateral :

Percent. Shear Specimen Temperature

' Energy '

l 4 Identification

(*F)

- (ft-lb) -

' Expansion (Meth6d 1)7 (mils)

' (%) '

Base:

28994

-60 8

6 8

Heat C2557-1, 28988

-20 13.5 14 15 Transverse 28985 10 28 26 28 28989 20 36 26 26 28983 40 52.5 42 40 28990 60 55 48 46 28991 80 79.5 56 59 28992 108 87 70 73 28987 120 83 61 54 28986 150 111.5 78 85 28984 200 106.5 72 100 28993 300 108 76 100 i

Weld:

Heat 5P6214B, 28979

-100 7.5 7

1 Lot 0331, 28972

-60 32.5 26 23 Linde 124 Flux 28977

-50 38 22 43 (Single Wire) 28973

-20 50 41 35 1

28981 0

45.5 37 49 l-28976 20 44 39 50 28971 30 63.5 51 46 l'

28980 60 68 56 80 28974 108 78.5 64 96 28975 120 90 61 100 28982 200 84.5 68 100 i

28978 300 90 77 100 HAZ:

28960

-60 20 12 24 28959

-50 67.5 42 49 28962

-20 29.5 19 28 28968 0

38.5 31 41 28966 20 62 38 47 28963 30 76 53 49 28970 60 99 63 76 28967 80 90 61 97 28964 108 110 76 98 28965 120 109.5 73 100 28961 200 123.5 71 100 28969 300 112 76 100

O 31

Enclo6we PY-CEI/NRR-2129L Page 40 of 104 GE-NE-B1301793-01 Revision 0 i

Table 5-3 Unirradiated Charpy V-Notch Impact Test Results Test Fracture

Lateral.

Percent Shear Specimen a Temperature.

Energy Expansion Identification

(*F)

(ft-lb)

'(mils):

.(%)

Plate: b 1

40 50 47 40 Heat C2557-1 2

40 53 44 40 (Longitudinal) 3 40 50 44 40 4

40 64 54 50 f

5 40 54 54 50 6

40 65 43 50 Plate: b 1

40 32 31 30 Heat C2557-1 2

40 32 34 30 (Transverse) 3 40 36 28 30 4

60 40 38 40 5

60 46 38 40 6

60 44 40 40 7

70 52 42 40 8

70 50 46 40 i

9 70 52 42 40 10 40 44 48 40 9

11 40 51 39 40 12 40 40 40 40 13 60 54 63 60 14 60 64 53 60 15 60 76 46 60 16 212 86 74 99 17 212 84 72 99 18 212 87 74 99 19 70 60 50 50 20 70 62 52 50 21 70 58 53 50 22 40 40 36 30 23 40 46 36 30 24 40 40 41 30 25 0

23 17 20 26 0

20 23 20 27 0

18 22 20 28

-20 19 11 10 29

-20 23 17 10 30

-20 13 18 10 31

-50 9

9 1

32

-50 6

10 1

33

-50 11 8

1 i

a I.D.'s are listed for numbering only, i.e. I.D.'s were not preassigned b abrication Charpy specimen data from Materials Certification Reports F

32

Enclosure PY-CEI/NRR-2129L

-I Page 41 of104 GE-NE-B1301793-01 Revision 0 Table 5-3, Continued bV Unirradiated Charpy V-Notch Impact Test Results i

Test; Fracture Lateral

. Percent Shear.

4 Specimen a-l Temperature Energy -

FExpansion -

~ Identification i(*F)

' (ft-lb) E i(mils)

(%);

Weld: b 1

70 22 17 2

Heat 5P6214B, 2

-70 13 10 2

i Lot 0331, 3

-70 11 9

2 Linde 124 Flux 4

-50 42 34 15 (Single Wire) 5

-50 13 11 5

6

-50 34 26 10 7

10 56 45 25 8

10 50 41 20 9

10 54 46 30 10 40 76 66 75 11 40 66 52 45 12 100 87 70 95 13 100 89 64 90 14 120 96 68 100 4

15 120 90 61 100 16 120 88 71 100 Weld; b 1

30 17 14 2

Heat 5P6214B, 2

-80 21 17 2

Lot 0331, 3

-40 25 20 5

Linde 124 Flux 4

-40 37 29 5

(Tandem Wire) 5

-40 29 28 5

6 10 50 46 50 7

10 61 50 40 8

10 64 52 35 9

20 75 53 55 10 20 69 47 60 11 20 78 55 55 1

12 40 82 65 75 13 40 80 62 75 14 120 100 60 100 15 120 96 81 100 16 120 97 57 100 a, I.D.'s ate listed for numbering only, i.e. I.D.'s were not preassigned D Fabrication Charpy specimen data fiom Materials Cenification Reports 4

33

Enclosure 1

I PY-CEI/NRR-2129L Page 42 of 104 GE-NE-B1301793-01 Resision 0 a

,m Table 5-4 U

Significant Results ofIrradiated and Unirradiated Charpy V-Notch Data for 3 Azirnuth Surveillance Capsule at 5.5 EFPY 4

(Index Temp (*F)

Index Temp ( F)

!Index Temp (*F)

?USE, Material 1 E=30 ft-lb E=50 ft-lbl

- "MLE=35 rnil i(ft-lb)1 1

PLATE: Heat C2557-1 Unitradiated 18.4 56.7 36.4 85.7 l

Lradiated 12.1 43.8 32.5 107.3 Difference

-6.3

-12.9

-3.9 21.6 (+25%)

Reg. Guide 1.99, Rev 2 ARTmr :

gop a

Reg. Guide 1.99, Rev 2 (Ai2c) a:

-26'F to 42 F b

Reg. Guide 1.99, Rev 2 Decrease in USE :

6%

index Temp.('F); *IndexTsmp39);

IndexTemp ( F)'

"iUSE

~ E=50ftM

/MLs=35 mil i(fNb)

,-:. Materials L E=30 ft-lb E

HAZ:

q D

Unitradiated not available not available not available not available Irradiated

-21.7 5.4 7.7 115.0 Index Temp (*F)

Index Temp (?F)

!IndexTelnp (@)?

USE-Material.

. 05f3D fN1b E=50 ftM EMLE=35 mil

/(fNIb) -

WELD: Heat 5P6214B Unirradiated

-39.4

-1.9

-16.2 91.3 Irradiated

-54.1 0.7

-14.1 88.2 i

Difference

-14.7 2.6 2.1

-3.2 (-3.5%)

Reg. Guide 1.99, Rev 2 ARTmr ':

8F Reg. Guide 1.99, Rev 2 (AI2c)3:

-48'F to 64'F b

Reg. Guide 1.99, Rev 2 Decrease in USE ;

7.3%

a Determined in Section 5.4.1 b Determined in Section 5.4.2 O

34

O

- O O

GE-NE-B 1301793-01 Revision 0 N.

k._

Figure 5-1 D

UNIRRADIATED CHARPY Perry Unit 1, Base Metal Impact Energy R

Heat C2557-1 120 gg r

110 100 90 80

^

s 70 -.-

i

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60 g

m 5

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O GE-NE-BI30I793-0I Revision og g

Figure 5-3 1

{

IRRADIATED CHARPY 2

Perry Unit 1, Base Metal impact Energy Heat C2557-1 from 3* Capsule at 5.5 EFPY 120

@r 110 -

a Ik

[

100

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37

O O

O GE-NE-B1301793-01 Revision 0?$

a Figure 5-4 IRRADIATED CHARPY h

Perry Unit 1, Base Metal Lateral Expansion 2g Heat C2557-1 from 3* Capsule at 5.5 EFPY

3 120 p

110 100 90 80 -

g

=

n

5. '

r u

7

^

60 a

3 50 5

40 30 A

20 10 0

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o O

O GE-NE-BI301793-01 Revision 0 2'KW oa Figure 5-5 1

{

UNIRRADIATED CHARPY y

Perry Unit 1, Weld Metal Impact Energy 2

Heat SP6214B Flux 124 Lot 0331 E k 120 E

i-t-

110 100 i

i y

t 80 E

A i

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A aE 60

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40 A

30 20 gA 10 0

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O O

O GE-NE-B1301793-01 Revision 0 3'

L" ao M

Figure 5-6 1

{

UNIRRADIATED CHARPY y

Perry Unit 1, Weld Metal Lateral Expansion 2

Heat 5P6214B Flux 124 Lot 0331 2,

4 120 g

110 100-90 80 7

t 7 70 -

O A

A g 60 -

/

W 50

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A 30 A

20 t

4 1

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O O

O GE-NE-B1301793-01 Revision 0kk Figure 5-8 g

~

IRRADIATED CHARPY 5

Perry Unit 1, Weld Metal Lateral Expansion 2

Heat 5P6214B Flux 124 Lot 0331 from 3* Capsule at 5.5 EFPY E h 120

@r 110 100 90 n

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7 70

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O GE-hT-B 1301793-01 Revision 0

?$

Fign u 6-11 bk UNIRRf AT* D AND IRRADIATED CHARPY.

SL 3

Perr) - M;1 9ase Metal impact Energy y$

Heat C2557-1 120 8

110 laa iated 100_

imm 3* Capsule

/

at 5.5 EFPY

/

90

/

80

/

70

/

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Im 40 f'

30

[j USE Increase: 21.6 ft-lbs.

/

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100 200 300 400 500 Test Temperature, 'F 45

O O

O GE-NE-B1301793-01 Revision 0Nk Figure 5-12 g$7 UNIRRADIATED AND IRRADIATED CHARPY e

Perry Unit 1, Base Metal Lateral Expansion 2

Heat C2557-1 A h 120 g

r-110 100 Irradiated from 3' Capsule at 5.5 EW 90 80 1

f,,.

7

{ 60 Unirradiated 0

l f

50 5

J 40-

/

30 -

/

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100 200 300 400 500 Test Temperature *F 46

GE-NE-B1301793-01 Revision 0 dk o

Figure 5-13 S

UNIRRADIATED AND IRRADIATED CHARPY Perry Unit 1, Weld Metal impact Energy 2g Heat SP6214B Flux 124 Lot 0331 g

120 110-Unirradiated 1

100 90

/

80-

/

f E

Irradiated b

70 from 3* Capsule

/

at 5.5 EFPY g

60

,l, w

U f/

g 50 5

40

/

30 7

USE Decrease: 3.2 ft-Ibs.

30 ft-Ib RTndt Shift: -14.7'F 20

/

g 10 0

-200

-100 0

100 200 300 400 500 Tert Temperature, 'F 47

O O

O GE-NE-B1301793-01 Revision 0

?W Figue 5-14 hf UNIRRADIATED AND 1RRADIATED CHARPY C

3 Perry Unit 1, Weld Metal Lateral Expansion y,

Heat 5P6214B Flux 124 Lot 0331 M

120 (8

e-110 Irradiated 100 from 3' Capsule at 5.5 EFPY 90 80 g

s? 70 -

E 60 E

/

W 50 7

40 -

l 30 20

[7 Unirradiated 10 0

-200

-100 0

100 200 300 400 500 Test Temperature, 'F 48

Encicrure PY-CEI/NRR-2t29L Page 57 of 104 GE-NE-B1301793-01 Revision 0 b

6. ADJUSTED REFERENCE TEMPERATURE AND UPPER SHELF ENERGY v

The 32 EFPY peak fluence value of 4.9x1018 n/cm2 defined in Section 4.3 is used to calculate the 32 EFPY 1/4 T fluence value oi3.42x1018 n/cm2. The 32 EFPY 1/4 T fluence used in this section to calculate adjusted reference temperatures (ARTS) and upper shelf energy (USE) decrease for the. beltline materials. All references to EFPY in this report are defined as effective full power years at 3579 MW -t 6.1 ADJUSTED REFERENCE TEMPERATURE AT 32 EFPY The effect on adjusted reference temperature (ART) due to irradiation in the beltline materials is determined according to the methods in Reg. Guide 1.99, Rev. 2 [7], as a function of neutron fluence and the element contents of copper (Cu) and nickel (Ni).

The specific relationship from Reg. Guide 1.99, Rev. 2 [7] is:

ART = Initial RTer + ARTer + Margin (6-1) where:

ARTer = CF f @2841 i s 0 (6-2)

Margin = 2]o,y,2 (6-3) 2 CF = chemistry factor from Tables 1 or 2 ofReg. Guide 1.99, Rev. 2 [7],

f=

1/4 T fluence (n/cm2) divided by 1019, c1 =

standard deviation on initial RTer which is taken to be O'F, cA = standard deviation on ARTer,28 F for welds and 17 F for base material, except that ca need not exceed 0.50 times the ARTer value.

The ART values are calculated based upon chemistry data as described in Table 6-1.

The chemistry for weld Heat SP6214B is 0.02% Cu and 0.82% Ni, which has a corresponding chemistry factor of 27. The chemistry for plate Heat C2557-1 is 0.06% Cu and 0.61% Ni, which has a chemistry factor of 37.

l Each beltline plate and weld ARTmr value is determined by multiplying the CF from Reg. Guide 1.99, Rev. 2 determined for the Cu-Ni content of the material, by the fluence factor

'A for the EFPY being evaluated. The Initial RTmr, ARTmr and Margin are added to get the ART d

t i

49

1 Enclosure PY CC1/NRR-2129L Page 58 of104 GE-NE-B1301793-01 Revision 0

(

of the material. The 32 EFPY ART values for all of the beltline plates and welds are shown in Table 6-1. Surveillance plate and weld ART values are included for information. The ART for the limiting beltline material, weld Heat 627260, at 32 EFPY is 83.8 F.

6.2 UPPER SHELF ENERGY AT 32 EFPY Paragraph IV.B of 10CFR50 Appendix G [1] sets limits on the upper shelf energy (USE) of the beltline materials. The USE must be above 50 ft-lb at all times during plant operation, assumed here to be up to 32 EFPY. Calculations of 32 EFPY USE, using Reg. Guide 1.99, Rev. 2 methods, are summarized in Table 6-2. The values for initial USE were obtained from [5]

for all materials.

The USE decrease prediction values from Reg. Guide 1.99 [7] were used for the beltline plates and welds in Table 6-2. Based on the above results, the beltline materials will have USE values above 50 ft-lb at 32 EFPY, as required in 10CFR50 Appendix G [1]. The lowest USE predicted for 32 EFPY is 75 ft-lb (for plate Heat C2557-1).

D(&

Since USE and ART requirements are met, irradiation effects are not severe enough to necessitate additional analyses. Suflicient data is available to establish that the actual 32 EFPY USE values will be above 50 ft-lb, demonstrating acceptability.

l

"%e) 50

Enclosure PY-CEI/NRR-2129L Page 59 of 104 GE-NE-B1301793-01 Revision 0 Table 6-1 Beltline ART Values for Perry Unit 1 PLATE Thickness:

6 inches 32 EFPYPeakID Fluence:

4.90E+18 32 EFPY Peak 1/4T Fluence:

3.42E+18 WELD Thickness:

6 inches 32 EFPY PeakID Fluence:

4.90E+18 32 EFPY Peak 1/4T Fluence:

3.42E+18 32 EFPY

~32 32-Initial Delta:

EFPY EFPY Component '

. Heat '

%Cu;

%Ni

.CF RTmr RTmr Margin 5 Shift ART

'F '

F.

F-

F

'F PLATES:

Shell Ring

2 22-1-1 C2557-1 0.06 0.61 37 10 26.1 26.1 52.1 62.1 22-1-2 B6270-1 0.06 0.63 37

-30 26.1 26.1 52.1 22.1 22-1-3 A1155-1 0.06 0.63 37

-10 26.1 26.1 52.1 42.1 Surveillance Platea 0.054 0.62 33 10 23.2 23.2 46.5 56.5 WELDS:

Lower-Intermediate BD, BF 627260 0.06 1.08 82

-30 57.8 56.0 113.8 83.8 BD, BE, BF 626677 0.01 0.85 20

-20 14.1 14.1 28.2 8.2 BD, BE, BF SP6214B 0.02 0.82 27

-40 19.0 19.0 38.0

-2.0 BE 624063 0.03 1.00 41

-50 28.9 28.9 57.8 7.8 BE 627069 0.01 0.94 20

-60 14.1 14.1 28.2

-31.8 Surveillance Weldb 0.025 0.91 34

-40 23.9 23.9 47.9 7.9 a

Surveillance Plate (Best Estimate Chemistry, Table 3-3) b Surveillance Weld (Best Estimate Chemistry, Table 3-3)

O 51

Fxiosure PY-CEI/NRR-2129L Page 60 of 104 GE-NE-B1301793-01 Revision 0 Table 6-2 O

Upper Shelf Energy Analysis for Perry Unit 1 Beltline Material LOCATION 3 HEAT ETEST INITIAL

% Cu '

32

. TEMP USEa

. DECREASE '

EFPY.

J 'c

.USEb USEc3 PLATES Shell Ring #2 i

22-1-1 C2557-1 70 84

.06 11 75 22-1-2 B6270-1 30 94

.06 11 84 1

22-1-3 A1155-1 50 114

.06 11 101 WELDS Lower-Intermediate BD,BF 627260 30 104

.06 15.5 88 BD,BE,BF 626677 40 90

.01 10.5 81 I

BD,BE,BF SP6214B 10 88

.02 12 77

]

BE 624063 10 105

.01 10.5 94 BE 627069 0

112

.02 12 99 O

a Values obtained from [5]

b Values obtained from Figure 2 of[7] for 32 EFPY 1/4 T fluence = 3.42x1018n/cm2 e 32 EFPY Trans USE = Initial Trans USE * (1 - (% Decrease USE /100)}

I O

52

Enclosure PY-CEl/NRR-2129L Page 61 of 1(M GE-NE-B 1301793-01 Revision 0

7. PRESSURE-TEMPERATURE CURVES N]

7.1 BACKGROUND

Operating limits for pressure and temperature are required for three categories of operation: (a) hydrostatic pressure tests and leak tests, referred to as Curve A; (b) non-nuclear heatap/cooldown and low-level physics tests, referred to as Curve B; and (c) core critical operation, referred to as Curve C. There are three vessel regions that affect the operating limits:

the closure flange region, the core beltline region, and the remainder of the vessel, or non-beltline regions. The closure flange region limits are controlling at lower pressuies primarily because of 10CFR50 Appendix G [1] requirements. The non-beltline and beltline region operating limits are evaluated according to procedures in 10CFR50 Appendix G [1], ASME Code Appendix G [2],

and Welding Research Council (WRC) Bulletin 175 [10], with the beltline region minimum temperature limits adjusted to account for vesselirradiation. Ahhough not required, bottom head curves were also provided; the limits for the bottom head curves are evaluated the same as the other non-beltline regions.

O Figure 7-1 is Curve A for 32 EFPY; the bottom head limits are shown separately. This G

curve is valid for heatup/cooldown rates less than or equal to 20 F/hr. Curve B (100 F/hr heatup/cooldown) is shown in Figure 7-2; again the bottom head temperature limits are presented separately from the remainder of the vessel. Curve C (100 F/hr heatup/cooldown) is shown in

{

Figure 7-3. A separate bottom head curve is not shown, since the bottom head does not have a l

significant temperature variation from the remainder of the vessel during core critical operation.

The data tabulation for Figure 7-1 through Figure 7-3 is presented in Table 7-1. Similar curves with data tabulation which are valid for up to both 9 EFPY and 18 EFPY are provided in Appendix B.

If the heatup/cooldown rate is increased to 200 F/hr, then Figure 7-4 is the result for Curve B at up to 32 EFPY. Similarly, Curve C at up to 32 EFPY and a 200 F/hr heatup/cooldown rate is presented in Figure 7-5.

The data tabulation for Hee 7-4 and Figure 7-5 is presented in Table 7-2.

(Curve A data is unaffected by a increased j

heatup/cooldown rate.) Since there are RPV calculations that are limited to the 100 F/hr limits (such as vessel fatigue and piping), the 200 F/hr curves are provided for information only.

O LJ 53

Enclosure l

PY-CEI/NRR-2129L l

Page 62 of 104 GE-NE-B1301793-01 Revision 0 7.2 NON-BELTLINE REGIONS qb

)

Non-beltline regions are those locations that receive too little fluence to cause any RTer shift. Non-beltline components include the nozzles, the closure flanges, some shell plates, the top and bottom head plates and the control rod drive (CRD) penetrations. Detailed stress analyses of the non-beltline components were performed for the BWR/6 specifically for the purpose of fracture toughness analysis. The analyses took into account all mechanical loading and thermal transients anticipated.

Transients considered included 100 F/hr and 200 F/hr startup and shutdown, SCRAM, loss of feedwater heaters or flow, loss of recirculation pump flow, and all transients involving emergency core cooling injections. Primary membrane and bending stresses and secondary membrane and bending stresses due to the most severe of these transients were used according to [2] to develop plots of allowable pressure (P) versus temperature relative to the reference temperature (T - RTer). Plots were developed for the two most limiting BWR/6 components; the feedwater nozzle and the CRD penetration. All other components in the non-beltline regions are categorized under one of these two components.

The initial RTer values for non-beltline components are listed in Table 3-2. The basis for the feedwater nozzle limits was an initial RTer of-20 F for the Perry Unit I feedwater nozzle.

7V The bottom head toms initial RTer of 10 F was used as a basis for the CRD penetration limits.

Under certain conditions, the minimum bottom head temperature can be significantly cooler than the beltline or closure flange region.

These conditions can occur when the recirculation pumps are operating at low speed (or off), and during water injection through the control rod drives.

To account for these circumstances, individual temperature limits for the bottom head were established.

For pressures below 20% of preservice hydrostatic test pressure (312 psig) and with full bolt preload, the closure flange region metal temperature is required to be at RTer or greater [2].

The limiting flange region RTwr is 10 F, from the upper shell plate material. At low pressure, AShE Code Appendix G allows the beltline and bottom head regions to experience even lower metal temperatures than the flange region RTer.

However, temperatures should not be permitted to reach this limit for the reason discussed below.

The shutdown margin is calculated for a water temperature of 68 F. Shutdown margin is l

the quantity of reactivity needed for a reactor core to reach criticality with the strongest-worth l

control rod fully withdrawn and all other control rods fully insened. Although it may be possible O

lQ to safely allow the water temperature to fall below this 68 F limit, funher extensive calculations 54

Enclosure PY-CEI/NRR 2129L Page 63 of IM GE-NE-B1301793-01 Revision 0 3

{

would be required to justify a lower temperature. For Perry, since the boltup temperature is at U

70 F and to avoid confusion, the shutdown margin temperature will conservatively be set at 70*F.

Because the water temperature is currently limited to a minimum of 70'F, the metal temperature should not fall below this limit while fuel is in the vessel. The 70 F limit applies when the head is on and tensioned, and also when the head is off. (When fuel has been removed from the vessel, the head is tensioned, and the pressure is below 60 psig, the limiting vessel temperature is equal to the limiting RT ur of the vessel materials. This limiting RTwor is 10 F.) When the head is not N

tensioned and fuel is not in the vessel, the requirements of 10CFR50 Appendix G do not apply, and there are no limits on the vessel temperatures.

7.3 CORE BELTLINE REGION The pressure-temperature (P-T) limits for the beltline region are determined according to the methods in AShE Code Appendix G [2]. As the belt.line fluence increases during operation, these curves shift by an amount as discussed in Section 6.1. For the Perry Unit I vessel, the beltline curves were more limiting through 32 EFPY at typical operating pressures.

(]

The stress intensity factors (K), calculated for the beltline region according to AShE i

V Code Appendix G procedures, were based on a combination of pressure and thermal stresses for a 1/4 T flaw in a flat plate. The pressure stresses were calculated using thin-walled cylinder equations. Thermal stresses were calculated assuming the through-wall temperature distribution of a flat plate; values were calculated for both 100 F/hr and 200 F/hr thermal gradient. The shift value of the most limiting ART material from Table 6-1 was used to adjust the RTwor alues for v

the P-T limits. Since there are RPV calculations that are limited to the 100 F/hr limits (such as vessel fatigue and piping), the 200 F/hr curves are provided for information only.

7.4 CLOSURE FLANGE REGION 10CFR50 Appendix G [1] sets several minimum requirements for pressure and temperature, in addition to those outlined in the ASME Code, based on the closure flange region RTwor. In some cases, the results of analysis for other regions exceed these requirements and closure flange limits do not affect the shape of the P-T curves. However, some closure flange requirements do impact the curves.

(v3 55

Enclosure PY-CEI/NRR 2129L Page 64 of104 GE-NE-B1301793-01 Revision 0 The ASME Code [2] requirement for boltup was at qualification temperature (Tun) plus 60 F. Current ASME Code requirements state in Paragraph G-2222(c), that for application of full bolt preload and reactor pressure up to 20% of hydrostatic test pressure, the RPV metal temperature must be at RTer or greater. The approach used for Peny Unit 1 for the boltup temperature was based on a more conservative value of(RTmr + 60), or the LST of the bolting materials, whichever is greater. The limiting initial RTer for the closure flange region was the upper shell plate material at 10 F and the LST of the closure studs was 70 F; therefore the boltup temperature value used was 70'F. This conservatism is appropriate because boltup is one of the more limiting operating conditions (high stress and low temperature) for brittle fracture.

10CFR50 Appendix G, paragraph IV.A.2 including Table 1, sets minimum temperature requirements for pressure above 20% hydrotest pressure based on the RTer of the closure region. Curve A temperature must be no less than (RTer + 90 F) and Curve B temperature no less than (RTer + 120*F). The Curve A requirement causes a 30 F shift at 20% hydrotest pressure (312 psig) as shown in Figure 7-1. Similarly, the Curve B requirements cause a 30*F shift at 312 psig as shown in Figure 7-2.

7.5 CORE CRITICAL OPERATION REQUIREMENTS OF 10CFR50, APPENDIX G Curve C, the core critical operation curve shown in Figure 7-3, is generated from the requirements of 10CFR50 Appendix G [1], Table 1. Essentially Table 1 requires that core critical P-T limits be 40 F above any Cuwe A or B limits when pressure exceeds 20% of the preservice system hydrotest pressure. Curve B is more limiting than Curve A, so limiting Curve C values must be at least Curve B plus 40 F above 312 psig.

Table 1 of[1] indicates that for BWR's with water level within normal range for power operation, the allowed initial criticality at the closure flange region is (RTer + 60 F) at pressures below 312 psig. This requirement makes the minimum criticality temperature 70'F, based on a RTmr of10 F. In addition, above 312 psig, the Curve C temperature must be at least the greater of RTer of the closure region + 160 F or the temperature required for the hydrostatic pressure test (Curve A at 1100 psig). Therefore, the Curve C requirement causes a 47 F shift at 20%

hydrostatic test pressure (312 psig) as shown in Figure 7-3.

56

Enclosure PY-CEl/NRR 2129L Page 65 of104 GE-NE-B1301793-01 Revision 0 Table 7-1 Perry Unit 1 P-T Curve Values Required Temperatures at 100 'F/hr for Curves B & C and 20 F/hr for Cune A For Figures 7-1 Through 7-3 i

BOTTOM l RPV &

BOTTOM JRPV & s 3 RPV & -.

PRESSURE

.HEADL

32 EFPY HEAD?

32 EFPY 32 EFPY-CURVE AV

" RPV &-

-CURVE B

- RPV &-

, CURVE C BELT A.

EBELT B-

(PSIG)

( F) -

- ('F) -

(*F).

(*F)

SDF) n; O

70.0 70.0 70.0 70.0 70.0 t

10 70.0 70.0 70.0 70.0 70.0 20 70.0 70.0 70.0 70.0 70.0 30 70.0 70.0 70.0 70.0 70.0 40 70.0 70.0 70.0 70.0 70.0 50 70.0 70.0 70.0 70.0 70.0 60 70.0 70.0 70.0 70.0 70,0 70 70.0 70.0 70.0 70.0 70.0 80 70.0 70.0 70.0 70.0 70.0 90 70.0 70.0 70.0 70.0 70.0 100 70.0 70.0 70.0 70.0 74.8 110 70.0 70.0 70.0 70.0 80.4 120 70.0 70.0 70.0 70.0 85.3 130 70.0 70.0 70.0 70.0 90.1 140 70.0 70.0 70.0 70.0 94.7 150 70.0 70.0 70.0 70.0 99.0 160 70.0 70.0 70.0 70.0 102.9 170 70.0 70.0 70.0 70.0 106.3 180 70.0 70.0 70.0 70.0 109.3 190 70.0 70.0 70.0 72.1 112.1 200 70.0 70.0 70.0 74.8 114.8 210 70.0 70.0 70.0 77.5 117.5 220 70.0 70.0 70.0 80.1 120.1 230 70.0 70.0 70.0 82.4 122.4 240 70.0 70.0 70.0 84.7 124.7 250 70.0 70.0 70.0 86.9 126.9 260 70.0 70.0 70.0 89.0 129.0 270 70.0 70.0 70.0 91.0 131.0 57

Enclosure

)

PY-CEI/NRR-2129L Page 66 of 104 GE-NE-B1301793-01 Revision 0 Table 7-1, Continued I

Perry Unit 1 P-T Curve Values Required Temperatures at 100 F/hr for Curves B & C and 20 *F/hr for Curve A 1

For Figures 7-1 Through 7-3

. BOTTOMS'

RPV &

BOTTOM RPV & -

RPV &

PRESSURE

' HEAD 32 EFPY

' HEAD, 32 EFPY. ' 32 EFPY-CURVE An RPV&

T CURVEB fRPV &-

CURVE C BELT A-BELT B ~

(PSIG).

(T)5

.- (T)

~.(T)c f(T)

NTj -

280 70.0 70.0 70.0 93.0 133.0 290 70.0 70.0 70.0 94.9 134.9 300 70.0 70.0 70.0 96.7 136.7 310 70.0 70.0 70.0 98.5 138.5 312.5 70.0 70.0 70.0 98.9 138.9 312.5 70.0 100.0 70.0 130.0 186.0 320 70.0 100.0 70.0 130.0 186.0 330 70.0 100.0 70.0 130.0 186.0 340 70.0 100.0 70.0 130.0 186.0 350 70.0 100.0 70.0 130.0 186.0 360 70.0 100.0 70.0 130.0 186.0 k

370 70.0 100.0 70.0 130.0 186.0 380 70.0 100.0 70.0 130.0 186.0 390 70.0 100.0 70.0 130.0 186.0 400 70.0 100.0 70.0 130.0 186.0 j

410 70.0 100.0 70.0 130.9 186.0 420 70.0 100.0 70.0 133.5 186.0 430 70.0 100.0 70.2 136.0 186.0 440 70.0 100.0 73.2 138.4 186.0 450 70.0 100.0 76.1 140.7 186.0 460 70.0 100.0 78.8 143.0 186.0 470 70.0 100.0 81.5 145.2 186.0 480 70.0 100.0 84.0 147.3 187.3 490 70.0 100.0 86.5 149.3 189.3 500 70.0 100.0 88.8 151.3 191.3 510 70.0 100.0 91.1 153.3 193.3 520 70.0 100.0 93.3 155.1 195.1 530 70.0 100.0 95.5 157.0 197.0 540 70.0 100.0 97.5 158.8 198.8 550 70.0 100.5 99.6 160.5 200.5 58

Enclosure PY-CEI/NRR-2129L Page 67 of 104 GE-NE-B1301793-01 l

Resision 0 Table 7-1, Continued Perry Unit 1 P-T Curve Values Required Temperatures at 100 *F/hr for Curves B & C and i

l 20 F/hr for Curve A For Figures 7-1 Through 7-3 BOTTOM

!RPV &

! BOTTOM RPV &

RPV &.

PRESSURE HEAD.

32 EFPY.

HEAD'

'32 EFPY 32'EFPY CURVE A

' RPV &

! CURVE B RPV &

CURVE C i

3 BELTA BELT B l

(PSIG)1

s.(T)

.(F).

(F)

L(F)

L('F) 4 560 70.0 103.5 101.5 162.2 202.2 i

570 70.0 106.4 103.4 163.8 203.8 580 71.8 109.2 105.3 165.5 205.5 590 74.0 111.8 107.1 167.0 207.0 600 76.1 114.4 108.9 168.6 208.6 610 78.2 116.9 110.6 170.1 210.1 620 80.2 119.3 112.3 171.6 211.6 630 82.1 121.6 113.9 173.0 213.0 i

640 84.0 123.8 115.5 174.4 214.4

{

650 85.9 126.0 117.0 175.8 215.8 660 87.7 128.0 118.6 177.2 217.2 O

670 89.4 130.1 120.1 178.5 218.5 680 91.1 132.1 121.5 179.8 219.8 690 92.8 134.0 123.0 181.1 221.1 700 94.4 135.8 124.4 182.4 222.4 710 96.0 137.7 125.7 183.6 223.6 720 97.6 139.4 127.1 184.9 224.9 730 99.1 141.2 128.4 186.0 226.0 740 100.6 142.8 129.7 187.2 227.2 750 102.0 144.5 131.0 188.4 228.4 760 103.5 146.1 132.2 189.5 229.5 770 104.8 147.7 133.5 190.6 230.6 780 106.2 149.2 134.7 191.7 231.7 790 107.6 150.7 135.9 192.8 232.8 800 108.9 152.2 137.0 193.9 233.9 810 110.2 153.6 138.2 194.9 234.9 820 111.4 155.0 139.3 196.0 236.0 830 112.7 156.4 140.4 197.0 237.0 840 113.9 157.8 141.5 198.0 238.0 850 115.1 159.1 142.6 199.0 239.0 O

l l

59

Enclosure PY-CEl/NRR-2129L Page 68 of 104 GE-NE-B1301793-01 Revision 0 Ts ble 7-1, Continued

)

Perry Unit 1 P-T Curve Values v

Required Temperatures at 100 F/hr for Curves B & C and 20 'F/hr for Curve A ForFigures 7-1 Through 7-3 i

BOTTOM.

RPV & l

' BOTTOM RPV &

RPV &

PRESSURE HEAD

.32 EFPYJ HEAD 32 EFPY-..

' 32 EFPY'-

CURVE As, lRPVh?

CURVE B RPV&'

CURVE C BELT.A.

BELT B -

(PSIG) -

('F).

?('F)

(7)

(*F),

(F)l i

860 116.3 160.4 143.6 200.0 240.0 870 117.5 161.7 144.7 200.9 240.9 880 118.6 162.9 145.7 201.9 241.9 890 119.7 164.2 146.7 202.8 242.8 900 120.8 165.4 147.7 203.7 243.7 910 121.9 166.6 148.7 204.6 244.6 920 123.0 167.7 149.7 205.5 245.5 930 124.0 168.9 150.6 206.4 246.4 940 125.1 170.0 151.6 207.3 247.3 950 126.1 171.1 152.5 208.2 248.2 960 127.1 172.2 153.4 209.0 249.0 Os.

970 128.1 173.3 154.3 209.9 249.9 980 129.1 174.4 155.2 210.7 250.7 990 130.0 175.4 156.1 211.5 251.5 1000 131.0 176.4 157.0 212.4 252.4 1010 131.9 177.5 157.8 213.2 253.2 i

1020 132.9 178.5 158.7 214.0 254.0 1030 133.8 179.4 159.5 214.7 254.7 1040 134.7 180.4 160.3 215.5 255.5 1050 135.6 181.4 161.2 216.3 256.3 1060 136.5 182.3 162.0 217.1 257.1 1070 137.3 183.2 162.8 217.8 257.8 1080 138.2 184.2 163.6 218.5 258.5 1090 139.0 185.1 164.3 219.3 259.3 1100 139.9 186.0 165.1 220.0 260.0 1110 140.7 186.9 165.9 220.7 260.7 1120 141.5 187.7 166.6 221.4 261.4 1130 142.3 188.6 167.4 222.2 262.2 1140 143.1 l

189.4 168.1 222.9 262.9 1150 143.9 l

190.3 168.9 223.5 263.5 O

60

. -. ~.

Enclosure PY CEl/NRR-2129L Page 69 of 104 GE-NE-B1301793-01 l

Revision 0 l

Table 7-1, Continued Perry Unit 1 P-T Curve Values Required Ternperatures at 100 F/hr for CurTes B & C and 20 F/hr for Curve A For Figures 7-1 Through 7-3 BOITOM-

' RPV &-

BOTIOM RPV &

.RPV &.

PRESSURE

HEAD;,

. 32 EFPY '

. HEAD' 32 EFPY t32 EFPY CURVE A RP.V & -

. CURVE B RPV &'

CURVE C..

^

BELTA

. BELT B (PSIG)j

'(T)F

. (Y)3

- (T)

-(T)

(T) 1160 144.7 191.1 169.6 224.2 264.2 1170 145.5-191.9 170.3 224.9 2 64.9 1180 146.2 192.8 171.0 225.6 265.6 1190 147.0 193.6 171.7 226.2 266.2 1200 147.7 194.3 172.4 226.9 266.9 1210 148.5 195.1 173.1 227.6 267.6 1220 149.2 195.9 173.8 228.2 268.2

_ 1230 149.9 196.7 174.5 228.8 268.8 1240 150.6 197.4 175.1 229.5 269.5 1250 151.3 198.2 175.8 230.1 270.1 0-1260 152.0 198.9 176.4 230.7 270.7 1270 152.7 199.7 177.1 231.4 271.4 1280 153.4 200.4 177.7 232.0 272.0 1290 154.1 201.1 178.4 232.6 272.6 1300 154.8 201.8 179.0 233.2 273.2 1310 155.4 202.5' 179.6 233.8 273.8 1320 156.1 203.2 180.3 234.4 274.4 1330 156.8 203.9 180.9 234.9 274.9 1340 157.4 204.6 181.5 235.5 275.'

1350 158.1 205.3 182.1 236.1 276.1 1360 158.7 205.9 182.7 236.7 276.7 1370 159.3 206.6 183.3 237.2 277.2 1380 159.9 207.3 183.9 237.8 277.8 1390-160.6 207.9 184.4 238.4 278.4 1400 161.2 208.6 185.0 238.9 278.9 O

61

-. ~

Enclosure PY-CEI/NRR-2129L Page 70 of 104 GE-NE-B1301793-01 Revision 0 Table 7-2 Perry Unit 1 P-T Curve Values Required Temperatures at 200 *F/Hr for Curves B & C and 20 oF/Hr for Curve A For Figures 7-4 And 7-5

. BOTIOM.

. RPV &.

BOTTOM RPV &

RPV &

PRESSURE HEAD 32 EFPY-L. HEAD 32 EFPY 32 EFPY ;

CURVE A RPV & '

CURVE B RPV & -

CURVE C BELT A BELT.B (PSIG)

(*F)

( F)8 J(F)

.,(( F) c

.(F)'

O 70.0 70.0 70.0 70.0 70.0 10 70,0 70.0 70.0 70.0 70.0 20 70.0 70.0 70.0 70.0 70.0 30 70.0 70.0 70.0 70.0 70.0 40 70.0 70.0 70.0 70.0 70.0 50 70.0 70.0 70.0 70.0 70.0 60 70.0 70.0 70.0 70.0 70.0 i

70 70.0 70.0 70.0 70.0 70.0 80 70.0 70.0 70.0 70.0 70.0 90 70.0 70.0 70.0 70.0 70.0

/~N 100 70.0 70.0 70.0 70.0 74.8 v

.110 70.0 70.0 70.0 70.0 80.7 120 70.0 70.0 70.0 70.0 89.6 130 70.0 70.0 70.0 70.0 97.5 140 70.0 70.0 70.0 70.0 104.6 i

j 150 70.0 70.0 70.0 71.0 111.0 l

160 70.0 70.0 70.0 76.9 116.9 170 70.0 70.0 70.0 82.3 122.3 180 70.0 70.0 70.0 87.4 127.4 190 70.0 70.0 70.0 92.0 132.0 200 70.0 70.0 70.0 96.4 136.4 210 70.0 70.0 70.0 100.6 140.6 4

220 70.0 70.0 70.0-104.4 144.4 l

230 70.0 70.0 70.0 108.1 148.1

]

240 70.0 70.0 70.0 111.6 151.6

~

250 70.0 70.0 70.0 115.0 155.0

)

260 70.0 70.0 70.0 118.1 158.1 270 70.0 70.0 70.0 121.2 161.2 280 70.0 70.0 70.0 126.1 166.1 290 70.0 70.0 70.0 128.9 168.9 1

62

Enclosure l

PY-CEI/NRR-2129L Page 71 of 104 GE-NE-B1301793-01 Resision 0 Table 7-2, Continued t

Perry Unit 1 P-T Curve Values Required Temperatures at 200 F/Hr for Cunes B & C and 20 oF/Hr for Curve A For Figures 7-4 And 7-5 BOTTOM RPV &

BOTTOM RPV &

RPV &

PRESSURE HEAD.-

32 EFPY HEAD 32 EFPY 32 EFPY CURVE A RPV &

CURVE B

RPV &

LCURVE C

. BELT A BELT B :

(PSIG)

(*F)

(F)

(*F) :

. (*F)

-(F)f 300 70.0 70.0 70.0 131.5 171.5 310 70.0 70.0 70.0 134.1 174.1 312.5 70.0 70.0 70.0 134.7 174.7 312.5 70.0 100.0 70.0 134.7 186.0 320 70.0 100.0 70.0 136.6 186.0 330 70.0 100.0 70.0 139.0 186.0 340 70.0 100.0 70.0 141.3 186.0 350 70.0 100.0 70.0 143.5 186.0 360 70.0 100.0 70.0 145.7 186.0 370 70.0 100.0 70.0 147.8 187.8

/]

380 70.0 100.0 70.0 149.8 189.8 D

390 70.0 100.0 70.0 151.8 191.8 400 70.0 100.0 70.0 153.7 193.7 410 70.0 100.0 70.0 155.6 195.6 420 70.0 100.0 70.0 157.4 197.4 430 70.0 100.0 70.2 159.2 199.2 440 70.0 100.0 73.2 160.9 200.9

~

450 70.0 100.0 76.1 162.6 202.6 460 70.0 100.0 78.8 164.2 204.2 470 70.0 100.0 81.5 165.8 205.8 480 70.0 100.0 84.0 167.4 207.4 490 70.0 100.0 86.5 168.9 208.9 500 70.0 100.0 88.8 170.4 210.4 510 70.0 100.0 91.1 171.9 211.9 520 70.0 100.0 93.3 173.4 213.4 530 70.0 100.0 95.5 174.8 214.8 540 70.0 100.0 97.5 176.2 216.2 550 70.0 100.5 99.6 177.5 217.5 560 70.0 103.5 101.5 178.8 218.8 570 70.0 106.4 103.4 180.1 220.1 63

Enclosure I

PY-CEI/NRR-2129L Page 72 of 104 GE-NE-B1301793-01 l

Revision 0 Table 7-2, Conlinued

~

Perry Unit 1 P-T Cune Values Required Temperatures at 200 'FSr for Curves B & C and 20 FMr for Cune A For Figures 7-4 And 7-5

. BOTTOM.

. R P V &.-

-BOTTOM; fRPV &

. RPV &

2 PRESSURE HEADf i32 EFPY

' HEAD ^

732 EFPYJ

32. EFPY, CURVE A

.:RPV &

CURVEB

. RPV &

. CURVE C :

3

BELT A; BELT B -

(PSIG)?

( F)

.('F);

(*F)

(*F))

' ' $(*F);,

580 71.8 109.2 105.3 181.4 221.4 i

l 590 74.0 111.8 107.1 182.7 222.7 600 76.1 114.4 108.9 183.9 223.9 610 78.2 116.9 110.6 185.1 225.1 620 80.2 119'.3 112.3 186.3 226.3 1

630 82.1 121.6 113.9 187.5 227.5

^

640 84.0 123.8 115.5 188.6 228.6 650 85.9 126.0 117.0 189.8 229.8 660 87.7 128.0 118.6 190.9 230.9 i

670 89.4 130.1 120.1 192.0 232.0

'/~N 680 91.1 132.1 121.5 193.1 233.1

.b 690 92.8 134.0 123.0 194.1 234.1 700 94.4 135.8 124.4 195.2 235.2 j

710 96.0 137.7 125.7 196.2 236.2 j

720 97.6 139.4 127.1 197.2 237.2 730 99.1 141.2 128.4 198.2 238.2 j

740 100.6 142.8 129.7 199.2 239.2 750 102.0 144.5 131.0 200.2 240.2 760 103.5 146.1 132.2 201.1 241.1

}

770 104.8 147.7 133.5 202.1 242.1 j

780 106.2 149.2 134.7 203.0 243.0 i

790 107.6 150.7 135.9 204.0 244.0 1

800 108.9 152.2 137.0 204.9 244.9 1

810 110.2 153.6 138.2 205.8 245.8 l

820 111.4 155.0 139.3 206.6 246.6 j

830 112.7 156.4 140.4 207.5 247.5 840 113.9 157.8 141.5 208.4 248.4

)

850 115.1 159.1 142.6 209.2 249.2 860 116.3 160.4 143.6 210.1 250.1 870 117.5 161.7 144.7 210.9 250.9 1

64

Enclosure a

4 PY-CEI/NRR-2129L Page 73 of 104 GE-NE-B1301793-01 Revision 0 Table 7-2, Continued Perry Unit 1 P-T Curve Values Required Temperatures at 200 F/Hr for Curves B & C and d

20 *F/Br for Curve A For Figures 7-4 And 7-5

' BOTTOM -

' RPV &

LBOTTOM RPV &

RPV&c

}

PRESSURE

.THEID,-

132EFPY?

. {HEADI 32 EFPY 3'2 EFPY. -

i

CURVE A 1RPK&L

. CURVE B RPV&

CURVE C LBELT A :

BELTB --

- (PSIG)

/(*F) s'FE

(*F)?

[(F)!

. ( F) 4 l

880 118.6 162.9 145.7 211.7 251.7 890 119.7 164.2 146.7 212.5 252.5 I

900 120.8 165.4 147.7 213.3 253.3 l

910 121.9 166.6 148.7 214.1 254.1

^

920 123.0 167.7 149.7 214.9 254.9 930 124.0 168.9 150.6 215.7 255.7

}

940 125.1 170.0 151.6 216.5 256.5 950 126.1 171.1 152.5 217.2 257.2 j

960 127.1 172.2 153.4 218.0 t

258.0 970 128.1 173.3 154.3 218.7 258.7 l('

980 129.1 174.4 155.2 219.5 259.5

!\\

990 130.0 175.4 156.1 220.2 260.2 l

1000 131.0 176.4 157.0 220.9 260.9 l

1010 131.9 177.5 157.8 221.6 261.6 4

1020 132.9 178.5 158.7 222.3 262.3 3

?

1030 133.8 179.4 159.5 223.0 263.0 1040 134.7 180.4 160.3 223.7 263.7 1050 135.6 181.4 161.2 224.4 264.4 1060 136.5 182.3 162.0 225.1 265.1 1070 137.3 183.2 162.8 225.7 265.7 1080 138.2 184.2 163.6 226.4 266.4 1090 139.0 185.1 164.3 227.1 267.1 1100 139.9 186.0 165.1 227.7 267.7 1110 140.7 186.9 165.9 228.4 268.4 3

1120 141.5 187.7 166.6 229.0 269.0 i

1130 142.3 188.6 167.4 229.6 269.6 1140 143.1 189.4 168.1 230.3 270.3 1150 143.9 190.3 168.9 230.9 270.9 l

1160 144.7 191.1 169.6 231.5 l

271.5 1170 145.5 191.9 170.3 232.1 l

272.1 1

65

Enclosure PY-CEUNRR-2129L Page 74 of 104 GE-NE-B 1301793-01 Revisior 0 Table 7-2, Continued

' [

Perry Unit 1 P-T Curve Values

\\

Required Temperatures at 200 oF/Hr for Curves B & C and 20 F/Ilr for Curve A For Figures 7-4 And 7-5 4 BOTTOM

.RPV &

BOTTOM RPV &

RPV &

PRESSURE

HEAD, f 32 EFPY HEAD 32 EFPY 32 EFPY CURVE AL RPV &

CURVEB RPV &

CURVE C BELT A.

BELT B (PSIG)[

(F)?

('F)

[(*F)

(F) 3( F) 1180 146.2 192.8 171.0 232.7 272.7 1190 147.0 193.6 171.7 233.3 273.3 1200 147.7 194.3 172.4 233.9 273.9 1210 148.5 195.1 173.1 234.5 274.5 1220 149.2 195.9 173.8 235.1 275.1 1230 149.9 196.7 174.5 235.7 275.7 1240 150.6 197.4 175.1 236.2 276.2 1250 151.3 198.2 175.8 236.8 276.8 1260 152.0 198.9 176.4 237.4 277.4 1270 152.7 199.7 177.1 237.9 277.9

('

1280 153.4 200.4 177.7 238.5 278.5

\\.

1290 154.1 201.1 178.4 239.0 279.0 1300 154.8 201.8 179.0 239.6 279.6 1310 155.4 202.5 179.6 240.1 280.1 1320 156.1 203.2 180.3 240.7 280.7 1330 156.8 2 03.9 180.9 241.2 281.2 1340 157.4 204.6 181.5 241.7 281.7 1350 158.1 205.3 182.1 242.3 282.3 1360 158.7 205.9 182.7 242.8 282.8 1370 159.3 206.6 183.3 243.3 283.3 1380 159.9 207.3 183.9 243.8 283.8 1390 160.6 207.9 184.4 244.3 284.3 1400 161.2 208.6 185.0 244.8 284.8

}

O 66

Enclosure PY-CEI/NRR-2129L Page 75 of 104 GE-NE-B1301793-01 Revision 0 0) v.

1400 I

i T,

INITIAL RTndt VALUES I

ARE -30*F FOR BELTLINE,

-20'F FOR UPPER 1200 VESSEL, AND 10'F FOR l

BOTTOM HEAD

{

HEATUP/COOLDOWN RATE 20'F/HR 1000

/

W I

a R

800

/,'

BOTTOM BELTINE CURVES

{

E HEAD 70'F 8

ADJUSTED AS SHOWN:

EFPY SHIFT ('F) j UP TO 32 113.8 K

600 s

l E

t-b

=

1 S

400 fu' I

E e

1 312 PSIG l UPPER VESSEL AND BELTINE LIMITS

- - BOTTOM HEAD 200 FLANGE LIMITS REGION 70*F 0

0 100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

Figure 7-1: Pressure Test Curve (Curve A)

O 67

}

Enclosure PY-CEI/NRR-2129L i

Page 76 of 104 GE-NE-B1301793-01 1

Revision 0 1400 7

I 8

INITIAL RTndt VALUES f

ARE -30*F FOR BELTLINE, f

-20'F FOR UPPER 1200 VESSEL, AND 10'F FOR f

BOTTOM HEAD HEATUP/COOLDOWN f

RATE 100*F/HR

_.?

E g 1000 j

b I

8 I

~

800

[

BELTINE CURVES

/

E O

ADJUSTED AS SHOWN:

EFPY SHIFT (*F)

D UP TO 32 113.8 W

BOTTOM g

600 gggo 7o.F 5

l' u

S 400 e

i E

UPPER VESSEL AND l

BELTINE LIMITS

- - BOTTOM HEAD 200 r

LIMITS FLANGE REGION 70*F l

0 0

100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 7 2: Non-Nuclear Heatup/Cooldown (Curve B)

I O

l!

68

Enclosure PY-CEI/NRR-2129L Page 77 of 104 GE-NE-B1301793-01 Revision 0 1400 INITIAL RTndt VALUES ARE -30'F FOR BELTLINE,

-20*F FOR UPPER 1200 VESSEL, AND 10'F FOR BOTTOM HEAD HEATUP/COOLDOWN f

RATE 100*F/HR

?

h1000

)

5 I

oe ibg 800 BELTINE CURVES E

ADJUSTED AS SHOWN:

b' k

EFPY SHIFT (*F)

UP TO 32 113.8 E

600 i!E e

S 400 0

E Minimum Criticality BELTLINE AND Temperature NON-BELTLINE 200 70'F LIMITS

/

s 0

0 100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 7-3: Core Critical Operation (Curve C)

O 69 1

Enclosure PY-CEI/NRR-2129L Page 78 of 104 GE-NE-B1301793-01 Revision 0 0

1400 I

INITIAL RTndt VALUES l

ARE -30*F FOR BELTLINE,

{

20'F FOR UPPER 1200 VESSEL, AND 10*F FOR f

BOTTOM HEAD HEATUP/COOLDOWN

.9 7

RATE 200*F/HR E.

j g 1000 j

6 I

8 I

800

[

BELTINE CURVES

/

E

[

O ADJUSTED AS SHOWN:

EFPY SHIFT ('F) k Ug f

UP TO 32 113.8 m

BoTTou 1

2 600 HEAD 70*F a

o

.J E

S 400 I

E" l

UPPER VESSEL AND BELTINE LIMITS

- - BOTTOM HEAD l/

200 LIMITS FLANGE REGloN 70*F l 0

0 100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

Figure 7-4: Non-Nuclear Heatup/Cooldown (Curve B) 70 A

Enclosure PY-CEI/NRR-2129L Page 79 of104 GE-NE-B 1301793-01 Resision 0

O 1400 l

i INITIAL RTndt VALUES ARE -30*F FOR BELTLINE,

-20'F FOR UPPER 1200 VESSEL, AND 10'F FOR BOTTOM HEAD a

HEATUP/COOLDOWN RATE 200'F/HR

.!?

E.g 1000 5

I i

o>

d g

800 BELTINE CURVES E

ADJUSTED AS SHOWN:

1 O

EFPY SHIFT (*F)

UP TO 32 113.8 E

600 iE 5a g

i 400 7

E Minimum BELTLINE AND Criticality NON-BELTLINE 200 Temperature LIMITS 70'F 1

0 0

100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

Figure 7-5: Core Critical Operation (Curve C)

O 71

____.____.._._._.._.._____.______.___.._...m.______.__..

~

Enclosure PY-CEI/NRR-2129L Ne 0m GE-NE-B1301793-01 Revision 0

)

8. REFERENCES

[1]

" Fracture Toughness Requirements," Appendix G to Part 50 of Title 10 of the Code of Federal Regulations, December 1995.

[2]

" Protection Ag'ainst Non-Ductile Failure," Appendix G to Section XI of the 1989 ASME Boiler & Pressure Vessel Code.

I

[3]

" Reactor Vessel Material Surveillance Program Requirements," Appendix H to Part 50 i

of Title 10 of the Code ofFederal Regulations, July 1983.

[4]

" Surveillance Tests for Nuclear Reactor Vessels,' Annual Book of ASTM Standards, E185-73, March 1973 i

[5]

Perry Nuclear Power Plant Units 1 & 2 Updated Safety Analysis Repon for Unit 1,.

Section 5.3

[6]

" Conducting Surveillance Tests for Light Water Cooled Nuclear Power Reactor Vessels," Annual Book of ASTM Standards, E185-82, July 1982.

[7]

" Radiation Embrittlement ofReactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988.

[8]

T. A. Caine, " Implementation ofRegulato y Guide 1.99 Revision 2 for Perry Nuclear Power Plant Unit 1", GENE, San Jose, CA, November 1989, (GE Report SASR 89-76).

[9]

Perry Nuclear Power Plant Units 1 & 2 Updated Safety Analysis Report for Unit 1, Section 5.2.

[10]

"PVRC Recommendations on Toughness Requirements for Ferritic Materials", Welding Research Council Bulletin 175, August 1972.

[11]

Martin, G.C., " Fast Neutron Cross-Section Determination for BWR's Using Neutron Dosimeters," November 11,1993 (FMT Transmittal 93-212-0045).

O

\\

72

Encloswe PYM-2129L Page 81 of104 GE-NE-B 1301793-01 Revision 0

[12]

" Standard Methods for Notched BarImpact Testing ofMetallic Materials," Annual Book ofASTM Standards, E23-94b

[13]

" Nuclear Pir.nt Irradiated Steel Handbook," EPRI Report NP-4797, September 1986

~O i

)

O 73

Enclosure PY-CEI/NRR-2129L Page 82 of104 GE-NE-B1301793-01 Revision 0 APPENDIX A 1

IRRADIATED CHARPY SPECBIEN FRACTURE SURFACE PHOTOGRAPHS j

Photographs of each Charpy specimen fracture surface were taken per the requirements of ASTM E185-82. The'pages following show the fracture surface photographs along with a summary of the Charpy test results for each irradiated specimen. The pictures are arranged in the

.i l

order of base, weld, and HAZ matedals.

4 i

i d

i j

fO i

1 i

k l

i 4

O A-1 i

]

Enclosure PY-CEl/NRR-2129L Page 83 or 104 GE-NE-B1301793-01 Revision 0 BASE:28994 BASE: 28988 Temp: -60 F

Temp: -20 'F Energy: 8 ft-lb Energy: 13.5 ft-lb MLE: 6 mils

^

MLE: 14 mils Shear: 7.6 %

i_ 2d L_ ]

Shear: 15.4 %

BASE: 28985 9'

"r Shear: 27.7 %

~ M._c_.. J; Temp: 10 F

/ :~=Tq BASE: 28989 Temp: 20 F Energy: 28 ft-lb Energy: 36 ft-Ib MLE: 26 mils MLE: 26 mils Sim: 25.5 %

i BASE: 28983 i

BASE: 28990 l

Temp: 40 F

}c f.,f:

%.,.~'~

Temp: 60 F h/I*T,/!N 4j T$ '

Energy: 55 ft-lb l

Energy: 52.5 ft-lb MLE: 42 mils U. ' M L '.

'i~N I'.' $

MLE: 48 mils e.

.:s u

'l Shear: 40 %

Shear: 45.7 %

BASE: 28991 BASE: 28992 Temp: 80 F

.tA7

3. 3wr, Temp: 108 *F

@3., f:

. p f; 1

Energy: 79.5 ft-lb

- I;f '

t y

j, Energy: 87 ft-lb i

MLE: 56 mils "j

n+y :) ;..' h MLE: 70 mils o.,. ' 1 L;.L:

1.s u Shear: 58.8 %

Shear: 72.8 %

l l

4 A-2 4

l Enclosure PY-CEI/NRR 2129L Page 84 of104 GE-NE-B1301793-01 Revision 0 lO l

BASE: 28987 BASE: 28986

[

I k{.1 Temp: 120 F p

sp ;- [

Temp: 150 'F Energy: 83 ft-lb

,y Jj

>g

~

MLE 78 mils Energy: 111.5 fi-lb 9

~7 MLE: 61 mils EIA ' '

" M. -

w Shear: 54.1 %

Shear: 85.2 %

BASE:28984 BASE: 28993 l

Temp: 200 F Temp: 300 F 5

i

. L Energy: 106.5 ft-lb

'M y

Energy: 108 fi-lb I

.d *:$i.

MLE: 76 mils 4

n I

MLE: 72 mils

r. " '

u l

Shear: 100 %

i l

l lO WELD: 28979

~ '-

WELD: 28972 l

Temp: -100 F Temp: --60 F Energy: 7.5 ft-lb Energy: 32.5 fi-lb l

MLE: 7 mils MLE: 26 mils i

j Shear: 1 %

.ggy

, {:{, '

Shear: 23 %

I i

-~

l WELD: 28977

~" 27 f' '

f-

~. ~ ' '

WELD: 28973 l

Temp: -50 F Temp: -20 F Energy: 38 ft-lb Energy: 50 ft-lb MLE: 22 mils MLE: 41 mils Shear: 42.5 %

~

Shear: 34.5 %

i I

}

2 O

4 A-3

1 Enclosure PY-CEl/NRR-2129L Page 85 of 104 GE-NE-B1301793-01 Revision 0 O

WELD: 28981 x

WELD: 28976 Temp: 0F Energy: 45.5 ft-lb Temp: 20'F Energy: 44 ft-lb MLE: 37 mils MLE: 39 mils Shear: 49.2 %

i ggg

~

T Shear: 50.1 %

[

I WELD: 28971

~

WELD: 28980 Temp: 30 F Temp: 60 F l

Energy: 63.5 ft-lb Energy: 68 ft-lb MLE: 51 mils

^

MLE: 56 mils Shear: 46.4 %

4:

Shear: 79.6 %

i O l

WELD: 28974 WELD: 28975 j

Temp: 108 F

~

Temp: 120*F Energy: 78.5 fi-lb Energy: 90 ft-Ib MLE: 64 mils MLE: 61 mils Shear: 95.8 %

~

Shear: 100 %

I WELD: 28982 WELD: 28978 Temp: 200 *F ew

'9~g; Temp: 300 F Energy: 84.5 fi-lb MLE: 68 mils i

Energy: 90 ft-lb MLE: 77 mils l

Shear: 100 %

~

Shear: 100 %

i O

f A-4

Enclosure f

PY.CEI/NRR-2129L l

Page 86 of 104 GE-NE-B1301793-01 l

Revision 0 I

l l

t j

HAZ: 28960 HAZ 28959

{

j Temp: -60 F Energy: 20 ft-lb Temp: -50 F Energy: 67.5 ft-lb MLE: 12 mils MLE: 42 mils i

i Shear: 23.5 %

Shear: 48.9 %

l

~

C _." is l

...s.-

HAZ 28962

~

- 7 JO

'... g% ]

HAZ 28968 Temp: -20 F

~

Temp: 0 F Energy: 29.5 ft-lb Energy: 38.5 ft-lb MLE: 19 mils MLE: 31 mils Shear: 27.5 %

~

~'

Shear: 41.1 %

i j

HAZ: 28966 HAZ 28963 Temp: 20 F Temp: 30 F 1

. ? e' ;

.i j

Energy: 62 ft-lb

{Q. '

f'

(,

Energy: 76 f!-lb

ji h;.,,.i,%

~

I

[

MLE: 38 mils MLE: 53 mils Shear: 47.4 %

{

p $l4 j Shear: 49.1 %

Q HAZ 28970 HAZ: 28967 Temp: 60'F Temp: 80 F fg Energy: 99 ft-lb g,Jw.(

t.!i Energy: 90 ft-lb

?+fcy.

s ~,

vu j

MLE: 63 mils

1..-

,,. p:.;j :

-,.,. :.Ua MLE: 61 mils A. t i

s v1 Shear: 97.3 %

Shear: 75.9 %

. W 1

4 1

1

?

l 1

i A-5 1

J Enclosure PY-CEI/NRR-2129L Page 87 of 104 GE-NE-B1301793-01 l

Revision 0 O

l HAZ 28964

' J-HAZ 28965 i

j Temp: 108 *F Temp: 120 F Energy: 110 n-lb Energy: 109.5 n-lb i

MLE: 76 mils MLE: 73 mils Shear: 98.1 %

r.

Shear: 100 %

i HAZ 28961 HAZ 28969 Temp: 200 F

-- 1..- '

Temp: 300 F Energy: 123.5 n-lb Energy: 112 R-lb MLE: 71 mils MLE: 76 mils Shear: 100 %

Shear: 100 %

iO i

l l

I i,

!O l

l 4

A-4

~~ - _..

Enclosure PY CEI/NRR 2129L Page 88 of 104 GE-NE-B1301793-01 Revision 0 fm APPENDIX B

(

PRESSURE TEMPERATURE CURVES VALID FOR UP TO 9 EFPY AND 18 EFPY i

This appendix contains pressure temperature curves as defined in Section 7 of this report, which are valid up to 9 EFPY and 18 EFPY. Figures B-1 through B-3 present the curves for up to 9 EFPY, with data tabulation contained in Table B-1. Figures B-4 through B-6 present the curves for up to 18 EFPY, with data tabulation contained in Table B-2.

i 4

i J

s l

J e

i i

i t

)

1

)

I B-1

Enclosure PY-CEI/NRR-2129L Page 89 of 104 GE-NE-B1301793-01 Revision 0 1 O 4"O Table B-1 Perry Unit 1 P-T Curve Values for Up to 9 EFPY Required Temperatures at 100 F/hr for Cun es B & C and 20 CF/hr for Curve A for Figures B-1 through B-3

]

1 BOTTOM.

RPV &;

cBOTTOM

RPV &

RPV & ~

PRESSURE HEAD-

- 9 EFPYs HEAD-

~ 9 EFPY "

19 EFPYR

~

CURVE A RPV & -

CURVE B RPV &'-

CURVE C

~

j BELTA

' BELT B 1(PSIG) 2(F).

( F).

. (*F)

(*F)

~(F) 0 70.0 70.0 70.0

}

70.0 70.0 l

10 70.0 70.0 70.0 l

70.0 70.0 i

20 70.0 70.0 70.0 l

70.0 70.0 i

30 70.0 70.0 70.0 70.0 70.0 40 70.0 70.0 70.0 70.0 70.0 2

l 50 70.0 70.0 70.0 70.0 70.0 60 70.0 70.0 70.0 70.0 70.0 1

70 70.0 70.0 70.0 70.0 70.0 i

80 70.0 70.0 70.0 70.0 70,0 f (

90 70.0 70.0 70.0 70.0 70.0

\\

100 70.0 70.0 70.0 70.0 74.8

^

110 70.0 70.0 70.0 70.0 80.4 i

120 70.0 70.0 70.0 70.0 85.3 l

130 70.0 70.0 70.0 70.0 90.1 j

140 70.0 70.0 70.0 70.0 94.7 l

150 70.0 70.0 70.0 70.0 99.0 j

160 70.0 70.0 70.0 70.0 102.9 1

170 70.0 70.0 70.0 70.0 106.3 180 70.0 70.0 70.0 70.0 109.3 190 70.0 70,0 70.0 72.1 112.1 j-200 70.0 70.0 70.0 74.8 114.8 210 70.0 70.0 70.0 77.5 117.5 220 70.0 70.0 70.0 80.1 120.1 2

230 70.0 70.0 70.0 82.4 122.4 240 70.0 70.0 70.0 84.7 124.7 250 70.0 70.0 70.0 86.9 126.9 260 70.0 70.0 70.0 89.0 129.0 4

1 270 70.0 l

70.0 70.0 91.0 131.0

)

280 70.0 l

70.0 70.0 93.0 133.0 i

B-2

Enclosure PY-CEI/NRR-2129L 1

i Page 90of104 GE-NE-B 1301793-01 Revision 0 i

Table B-1, Continued Perry Unit 1 P-T Curve Values for Up to 9 EFPY Required Temperatures at 100 oF/hr for Cun'es B & C and 20 F/hr for Curve A for Figures B-1 through B-3 l

TBOTTOM :

RPV &.

BOTTOM RPV &

.RPV &

l PRESSURE

'HEADf.

9 EFPY HEAD

9 EFPY

'9 EFPY p

l

. CURVE A ~

- RPV~& ;

CURVE B RPV &

CURVE C BELTAf

. BELTB.;

(PSIG)

..(*F)

.;(*F)?

(F)i 1.(*F[

l(F) 290 70.0 70.0 70.0 94.9 134.9 300 70.0 70.0 70.0 96.7 136.7 310 70.0 70.0 70.0 98.5 138.5 312.5 70.0 70.0 70.0 98.9 138.9 j

312.5 70.0 100.0 70.0 130.0 170.0 i

320 70.0 100.0 70.0 130.0 170.0 330 70.0 100.0 70.0 130.0 170.0 340 70.0 100.0 70.0 130.0 170.0 350 70.0 100.0 70.0 130.0 170.0 360 70.0 100.0 70.0 130.0 170.0 0

370 70.0 100.0 70.0 130.0 170.0 380 70.0 100.0 70.0 130.0 170.0 390 70.0 100.0 70.0 130.0 170.0 400 70.0 100.0 70.0 130.0 170.0 f

410 70.0 100.0 70.0 130.0 170.0

{

420 70.0 100.0 70.0 130.0 170.0 430 70.0 100.0 70.2 130.0 170.0 440 70.0 100.0 73.2 130.0 170.0 450 70.0 100.0 76.1 130.0 170.0 460 70.0 100.0 78.8 130.0 170.0 470 70.0 100.0 81.5 130.0 170.0 480 70.0 100.0 84.0 130.0 170.0 490 70.0 100.0 86.5 130.0 170.0 500 70.0 100.0 88.8 130.0 170.0 510 70.0 100.0 91.1 130.0 170.0 520 70.0 100.0 93.3 130.0 170.0 530 70.0 100.0 95.5 130.0 170.0 540 70.0 100.0 97.5 130.0 170.0 550 70.0 100.0 99.6 131.0 171.0 560 70.0 100.0 101.5 132.0 172.0 i

B-3

Enclosure PY-CEl/NRR-2129L Page 91 of 104 GE-NE-B1301793-01 Revision 0 Table B-1, Continued

)

Perry Unit 1 P-T Curve Values for Up to 9 EFPY Required Temperatures at 100 CF/hr for Curves B & C and 20 F/hr for Curve A for Figures B-1 through B-3 LBOTTOM RPV&'

BOTTOM RPV &

RPV &

PRESSURE

HEAD, 9 EFPY-HEAD 9 EFPY 9 EFPY CURVE A ~

RPV &

CURVE B RPV &

CURVE C'

- BELT A BELT B (PSIG)

'( F)

(*F)

_(F)

('F)

( F).

570 70.0 100.0 103.4 132.9 172.9 580 71.8 100.0 105.3 133.8 173.8 590 74.0 100.0 107.1 134.7 174.7 600 76.1 100.0 108.9 135.5 175.5 610 78.2 100.0 110.6 136.3 176.3 620 80.2 100.0 112.3 137.1 177.1 630 82.1 100.0 113.9 137.8 177.8 640 84.0 100.0 115.5 138.5 178.5 650 85.9 100.0 117.0 139.2 179.2 660 87.7 100.0 118.6 139.8 179.8

("]

670 89.4 100.0 120.1 140.4 180.4 V

680 91.1 100.0 121.5 141.0 181.0 690 92.8 100.0 123.0 i

141.5 181.5 700 94.4 100.0 124.4 142.0 182.0 710 96.0 100.0 125.7 142.5 182.5 720 97.6 100.0 127.1 143.0 183.0 730 99.1 100.0 128.4 143.4 183.4 740 100.6 100.6 129.7 143.9 183.9 750 102.0 102.0 131.0 144.9 184.9 760 103.5 103.5 132.2 146.0 186.0 770 104.8 104.8 133.5 147.1 187.1 780 106.2 106.2 134.7 148.2 188.2 790 107.6 107.6 135.9-149.3 189.3 800 108.9 108.9 137.0 150.4 190.4 810 110.2 110.2 138.2 151.4 191.4 820 111.4 111.5 139.3 152.5 192.5 830 112.7 112.9 140.4 1

153.5 193.5 840 113.9 114.3 141.5 l

154.5 l

194.5 850 115.1 115.6 142.6 l

155.5 195.5 860 l

116.3 116.9 143.6 l

156.5 196.5 V

B-4

Enclosure PY-CEI/NRR-2129L Page 92 of104 GE-NE-B1301793-01 Revision 0 Table B-1, Continued C)

Perry Unit 1 P-T Curve Values for Up to 9 EFPY Required Temperatures at 100 oF/hr for Curves B & C and 20 F/hr for Curve A for Figures B-1 through B-3 BOTTOM.

RPV &

. BOTTOM RPV &

.- RPV &

PRESSURE

' HEAD, 9 EFPY -

HEAD 9 EFPY 9 EFPY CURVE A

.RPV &

CURVE B RPV &

CURVE C BELT A BELT B

-(PSIG)[

( F)

(*F)

.(*F) 870 117.5 118.2 144.7 157.4 197.4 880 118.6 119.4 145.7 158.4 198.4 890 119.7 120.7 146.7 159.3 199.3 900 120.8 121.9 147.7 160.2 200.2 910 121.9 123.1 148.7 161.1 201.1 920 123.0 124.2 149.7 162.0 202.0 930 124.0 125.4 150.6 162.9 202.9 940 125.1 126.5 151.6 163.8 203.8 950 126.1 127.6 152.5 164.7 204.7 960 127.1 128.7 153.4 165.5 205.5 O

970 128.1 129.8 154.3 166.4 206.4 980 129.1 130.9 155.2 167.2 207.2 990 130.0 131.9 156.1 168.0 208.0 1000 131.0 132.9 157.0 168.9 208.9 1010 131.9 134.0 157.8 169.7 209.7 1020 132.9 135.0 158.7 170.5 210.5 1030 133.8 135.9 159.5 171.2 211.2 1040 134.7 13 6.9 160.3 172.0 212.0 1050 135.6 137.9 161.2 172.8 212.8 1060 136.5 138.8 162.0 173.6 213.6 1070 137.3 139.7 162.8 174.3 214.3 1080 138.2 140.7 163.6 175.0 215.0 1000 139.0 141.6 164.3 175.8 215.8 1100 139.9 142.5 165.1 176.5 216.5 1110 140.7 143.4 165.9 177.2 217.2 1120 141.5 144.2 166.6 177.9 217.9 1130 142.3 145.1 167.4 178.7 218.7 1140 143.1 145.9 168.1 179.4 219.4 1150 143.9 146.8 168.9 180.0 220.0 A

1160 144.7 147.6 169.6 180.7 220.7 U

B-5

Encicrure PY-CEl/NRR-2129L Page 93 of 104 GE-NE-B1301793-01 Revision 0 Table B-1, Continued (O

Perry Unit 1 P-T Curve Values for Up to 9 EFPY Required Temperatures at 100 F/hr for Curves B & C and 20 F/hr for Curve A for Figures B-1 through B-3 BOTTOM RPV &

BOTTOM RPV &

RPV & -

PRESSURE

HEAD, 9 EFPY HEAD 9 EFPY.

L 9 EFPY CURVE A iRPV &~

CURVE B RPV &

CURVE C BELT A.

. BELT B (PSIG)-

-(F)

( F)

. ( F)

(F) 4(*FI 1170 145.5 148.4 170.3 181.4 221.4 1180 146.2 149.3 171.0 182.1 222.1 1190 147.0 150.1 171.7 182.7 222.7 1200 147.7 150.8 172.4 183.4 223.4 1210 148.5 151.6 173.1 184.1 224.1 1220 149.2 152.4 173.8 184.7 224.7 1230 149.9 153.2 174.5 185.3 225.3 1240 150.6 153.9 175.1 186.0 226.0 1250 151.3 154.7 175.8 186.6 226.6 1260 152.0 155.4 176.4 187.2 227.2 m

1270 152.7 156.2 177.1 187.9 227.9 1280 153.4 156.9 177.7 188.5 228.5 1290 154.1 157.6 178.4 189.1 229.1 1300 154.8 158.3 179.0 189.7 229.7 1310 155.4 159.0 179.6 190.3 230.3 1320 156.1 159.7 180.3 190.9 230.9 1330 156.8 160.4 180.9 191.4 231.4 1340 157.4 161.1 181.5 192.0 232.0 1350 158.1 161.8 182.1 192.6 232.6 1360 158.7 162.4 182.7 193.2 233.2 1370 159.3 163.1 183.3 193.7 233.7 1380 159.9 163.8 183.9 194.3 234.3 1390 160.6 164.4 184.4 194.9 234.9 1400 161.2 165.1 185.0 195.4 235.4 Od B-6

Enclosure PY-CEI/NRR-2129L Page 94 of 104 GE-NE-B1301793-01 Revision 0

[')

Table B-2 V

Perry Unit 1 P-T Curve Values for Up to 18 EFPY Required Temperatures at 100 *F/hr for Curves B & C and 20 oF/hr for Curve A For Figures B-4 through B-6 BOTTO}f TRPV &

BOTTOM cRPV &.

RPV&

PRESSURE

~ HEAD 18 EFPY HEAD?

18 EFPY 18 EFPY CURVE A RPV &

CURVE B

' RPV &

CURVE C BELT A -

BELT B (PSIG)

_ ( F)

.(?F).

.(F)

(F)

( F) 0 70.0 70.0 70.0 70.0 70.0 10 70.0 70.0 70.0 70.0 70.0 20 70.0 70.0 70.0 70.0 70.0 30 70.0 70.0 70.0 70.0 70.0 40 70.0 70.0 70.0 70.0 70.0 50 70.0 70.0 70.0 70.0 70.0 60 70.0 70.0 70.0 70.0 70.0 70 70.0 70.0 70.0 70.0 70.0 80 70.0 70.0 70.0 70.0 70.0 l

90 70.0 70.0 70.0 70.0 70.0 p)

(

100 70.0 70.0 70.0 70.0 74.8 110 70.0 70.0 70.0 70.0 80.4 120 70.0 70.0 70.0 70.0 85.3 130 70.0 70.0 70.0 70.0 90.1 140 70.0 70.0 70.0 70.0 l

94.7 150 70.0 70.0 70.0 70.0 99.0 160 70.0 70.0 70.0 70.0 102.9 170 70.0 70.0 70.0 70.0 106.3 180 70.0 70.0 70.0 70.0 109.3 190 70.0 70.0 70.0 72.1 112.1 200 70.0 70.0 70.0 74.8 114.8 210 70.0 70.0 70.0 77.5 117.5 220 70.0 70.0 70.0 80.1 120.1 230 70.0 70.0 70.0 82.4 122.4 240 70.0 70.0 70.0 84.7 124.7 250 70.0 70.0 70.0 86.9 126.9 260 70.0 70.0 70.0 89.0 129.0 270 70.0 70.0 70.0 91.0 131.0 280 70.0 70.0 70.0 93.0 133.0 v

B-7

Encic:ure PY-CEI/NRR-2129L Page 95 of 104 GE-NE-B 1301793-01 Resision 0 Table B-2, Continued l

Perry Unit 1 P-T Curve Values for Up to 18 EFPY Required Temperatures at 100 cF/hr for Curves B & C and 20 'F/hr for Curve A For Figures B-4 through B-6

-BOTTOM.

SRPV &T

- BOTTOM

' RPV & -

2 RPV &

PRESSURE

$HEADj (18 EFPYJ

! HEAD 18 EFPY.

18 EFPYi JCURVE A

' RPV &

CURVE B RPV-&-:

CURVE C' BELT A BELTB 3(PSIG)r

!( F)

NT

( F).

~ (*F)

' ( F)r 290 70.0 70.0 70.0 94.9 134.9 300 70.0 70,0 70.0 96.7 13 6.7 310 70.0 70.0 70.0 98.5 138.5 312.5 70.0 70.0 70.0 98.9 138.9 312.5 70.0 100.0 70.0 130.0 170.0 320 70.0 100.0 70.0 130.0 170.0 330 70.0 100.0 70.0 130.0 170.0 340 70.0 100.0 70.0 130.0 170.0 350 70.0 100.0 70.0 130.0 170.0 360 70.0 100.0 70.0 130.0 170.0 p

370 70.0 100.0 70.0 130.0 170.0 380 70.0 100.0 70.0 130.0 170.0 390 70.0 100.0 70.0 130.0 170.0 400 70.0 100.0 70.0 130.0 170.0 410 70.0 100.0 70.0 130.0 170.0 420 70.0 100.0 70.0 130.0 170.0 430 70.0 100.0 70.2 130.0 170.0 440 70.0 100.0 73.2 130.0 170.0 450 70.0 100.0 76.1 130.0 170.0 460 70.0 100.0 78.8 130.0 170.0 470 70.0 100.0 81.5 130.0 170.0 480 70.0 100.0 84.0 130.0 170.0 490 70.0 100.0 86.5 130.0 170.0

{

500 70.0 100.0 88.8 130.0 170.0 i

510 70.0 100.0 91.1 131.4 171.4 520 70.0 100.0 93.3 133.2 173.2 530 70.0 100.0 95.5 135.1 175.1 1

540 70.0 100.0 97.5 136.9 176.9 550 70.0 100.0 99.6 138.6 178.6 p

560 70.0 100.0 101.5 140.3 180.3 b

B-S

Enclosure PY-CEI/NRR-2129L Page 96 of 104 GE-NE-B1301793-01 Revision 0 l

Table B-2, Continued (U)

Perry Unit 1 P-T Curve Values for Up to 18 EFPY Required Temperatures at 100 F/hr for Curves B & C and 20 F/hr for Curve A For Figures B-4 through B-6 BOTTOM

. R P V &'.

BOTTOM RPV &.

RPV &

PRESSURE

' HEAD,

.18 EFPY l HEAD:

18 EFP 18 EFPY C.URVE A i RPV &-

CURVE B RPV &

CURVE C

- BELT A BELT B f(PSIG)

(F)

--- (*F).

(*F)

(*F)-

(F)L 570 70.0 100.0 103.4 141.9 181.9 580 71.8 100.0 105.3 143.6 183.6 590 74.0 100.0 107.1 145.1 185.1 600 76.1 100.0 108.9 146.7 186.7 610 78.2 100.0 110.6 148.2 188.2 620 80.2 100.0 112.3 149.7 189.7 630 82.1 100.0 113.9 151.1 191.1 640 84.0 101.9 115.5 152.5 192.5 650 85.9 104.1 117.0 153.9 193.9 660 87.7 106.1 118.6 155.3 195.3 p

670 89.4 108.2 120.1 156.6 196.6 V

680 91.1 110.2 121.5 157.9 197.9 690 92.8 112.1 123.0 159.2 199.2 700 94.4 113.9 124.4 160.5 200.5 710 96.0 115.8 125.7 161.7 201.7 720 97.6 117.5 127.1 163.0 203.0 i

730 99.1 119.3 128.4 164.1 204.1 740 100.6 120.9 129.7 165.3 205.3 750 102.0 122.6 131.0 166.5 206.5 760 103.5 124.2 132.2 167.6 207.6 770 104.8 125.8 133.5 168.7 208.7 780 106.2 127.3 134.7 169.8 209.8 790 107.6 128.8 135.9 170.9 210.9 800 108.9 130.3 137.0 172.0 212.0 810 110.2 131.7 138.2 173.0 213.0 820 111.4 133.1 139.3 174.1 214.1 830 112.7 134.5 140.4 l

175.1 215.1 840 113.9 l

135.9 141.5 176.1 216.1 850 115.1 137.2 l

142.6 177.1 217.1 A

860 116.3 138.5 143.6 178.1 218.1 V

B-9

~ _ _. -. _ _. _ _ _. _ _ _ _ _ _ _ _ _.. - _

Enclosure PY-CEI/NRR 2129L

^

Page 97 of 104 GE-NE-B1301793-01 Revision 0 Table B-2, Continued Perry Unit 1 P-T Curve Values for Up to 18 EFPY Required Temperatures at 100 oF/hr for Cun es B & C and 20 'F/hr for Curve A 4

For Figures B-4 through B-6

[

' BO'ITOM;

. RPV&'.

BOTTOM RPV &

" RPV &

}

PRESSURE HEAD.(

L18 EFPY-

HEAD 18 EFPY:

18 EFPY

]

. CURVE A RPV &

CURVE B RPV &:

CURVE C I'

' BELT A L BELT B l(PSIG):

i (?F).

( F) x

(*F)

(*F) j ( F) -

870 117.5 139.8 144.7 179.0 219.0 880 118.6 141.0 145.7 180.0 220.0 890 119.7 142.3 146.7 180.9 220.9 900 120.8 143.5 147.7 181.8 221.8 910 121.9 144.7 148.7 182.7 222.7 920 123.0 145.8 149.7 183.6 223.6 930 124.0 147.0 150.6 184.5 224.5 940 125.1 148.1 151.6 185.4 225.4 950 126.1 149.2 152.5 186.3 226.3 960 127.1 150.3 153.4 187.1 227.1

{',

970 128.1 151.4 154.3 188.0 228.0 980 129.1 152.5 155.2 188.8 228.8 990 130.0 153.5 156.1 189.6 229.6 1000 131.0 154.5 157.0 190.5 230.5 1010 131.9 155.6 157.8 191.3 231.3 1020 132.9 156.6 158.7 192.1 232.1 1030 133.8 157.5 159.5 192.8 232.8 1040 134.7 158.5 160.3 193.6 233.6 1050 135.6 159.5 161.2 194.4 234.4 1060 136.5 160.4 162.0 195.2 235.2 t

1070 137.3 161.3 162.8 195.9 235.9 1080 138.2 162.3 163.6 196.6 236.6 1090 139.0 163.2 164.3 197.4 237.4 1100 139.9 164.1 165.1 198.1 238.1 1110 140.7 165.0 165.9 198.8 238.8 1120 141.5 165.8 166.6 199.5 239.5 1130 142.3 166.7 167.4 200.3 240.3 1140 143.1 167.5 168.1 1

201.0 241.0 1150 143.9 168.4 168.9 l

201.6 241.6 1160 144.7 169.2 169.6 l

202.3 242.3 O

B-10

Enclosure PY-CD/NRR-2129L Page 98 of 104 GE-NE-B1301793-01 Revision 0 Table B-2, Continued Perry Unit 1 P-T Curve Values for Up to 18 EFPY Required Temperatures at 100 oF/hr for Curves B & C and 20 F/hr for Curve A For Figures B-4 through B-6 1 BOTTOMS

RPV & -

. BOTTOM

RPV &'

(RPV &

PRESSURE JHEAD]

l18 EFPYi

~ HE'ADL l18 EFPY-'

i 18 EFPY. :

CURVE A-:

~RPV &

. CURVE B

RPV &

CURVE C -

JBELT A EBELT B (PSIG);

l(*F) ?

(:( F)s 1( F)

(*F).

"$( F) l 1170 145.5 170.0 170.3 203.0 243.0 1180 146.2 170.9 171.0 l

203.7 243.7 1190 147.0 171.7 171.7 204.3 244.3 1200 147.7 172.4 172.4 205.0 245.0 1210 148.5 173.2 173.1 205.7 245.7 1220 149.2 174.0 173.8 206.3 246.3 1230 149.9 174.8 174.5 206.9 246.9 1240 150.6 175.5 175.1 207.6 247.6 1250 151.3 176.3 175.8 208.2 248.2 1260 152.0 177.0 176.4 208.8 248.8 O

1270 152.7 177.8 177.1 209.5 249.5 1280 153.4 178.5 177.7 210.1 250.1 1290 154.1 179.2 178.4 210.7 250.7 1300 154.8 179.9 179.0 211.3 251.3 1310 155.4 180.6 179.6 211.9 251.9 1320 156.1 181.3 180.3 212.5 252.5 1330 156.8 182.0 180.9 213.0 253.0 1340 157.4 182.7 181.5 213.6 253.6 1350 158.1 183.4 182.1 214.2 254.2 1360 158.7 184.0 182.7 214.8 254.8 1370 159.3 184.7 183.3 215.3 255.3 1380 159.9 185.4 183.9 215.9 255.9 1390 160.6 186.0 184.4-216.5 256.5 1400 161.2 186.7 185.0 217.0 257.0 0

B-11

Enclosure PY-CEI/NRR-2129L Page 99 of 104 GE-NE-B1301793-01 Revision 0 tO

' V i

l 1

1400 INITIAL RTndt VALUES J

ARE 10*F FOR BELTLINE,

-20*F FOR UPPER 1200 i

VESSEL, AND 10*F FOR

f BOTTOM HEAD HEATUP/COOLDOWN

,f RATE 20*F/HR f

g 1000 6x 8s idg 800 BOTTOM T

BELTINE CURVES es E

HEAD 70*F J

O ADJUSTED AS SHOWN:

{

f I

s EFPY SHIFT (*F) f UP TO 9 30.3 E

600 2

"3 g

I S

400 e

I l 2 PSIG l UPPER VESSEL AND BELTINE LIMITS

- - BOTTOM HEAD 200 FLANGE LIMITS REGION 70*F 0

0 100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

,e Figure B-1: Pressure Test Curve (Curve A) Valid Up to 9 EFPY

,e B-12

Enclosure PY-CEI/NRR 2129L Page 100 of 104 GE-NE-B1301793-01 Revision 0 O

1400 I

8 INITIAL RTndt VALUES f

ARE 10*F FOR BELTLINE,

-20*F FOR UPPER 1200 VESSEL, AND 10*F FOR r

/

BOTTOM HEAD

,j HEATUP/COOLDOWN RATE 100'F/HR jl

_.9 i

jl E 1000 6

I:

8 I

~

dg 800

.I 7

'T BELTINE CURVES

/

ADJUSTED AS SHOWN:

R:

O EFPY SHIFT ('F)

. 'O UP TO 9 30.3 E

I 600

}

f E

F BOTTOM g

HEAD 70*F

_J E

S 400 l

E UPPER VESSEL AND l

BELTINE LIMITS

- - BOTTOM HEAD 200 LIMITS y

FLANGE REGION 70*F l

0 0

100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

Figure B-2: Non Nuclear Heatup/Cooldown (Curve B) Valid Up to 9 EFPY O

B-13

Enclosure PY-CE!/NRR-2129L Page 101 of 104 GE-NE-B1301793-01 Revision 0 f)

\\

1 s/

1400 7

l INITIAL RTndt VALUES ARE 10*F FOR BELTLINE,

-20'F FOR UPPER 1200 VESSEL, AND 10*F FOR BOTTOM HEAD HEATUP/COOLDOWN 3

RATE 100*F/HR

'Ec.

2 1000 5

I o-dg 800 m>

BELTINE CURVES ADJUSTED AS SHOWN:

-Q EFPY SHIFT ('F) g UP TO 9 30.3 E

600 i

j E

f H

E

~]

w 5

g 400 E

o.

Minimum Criticality BELTLINE AND Temperature NON-BELTLINE i

200 - 70*F LIMITS

/

4 0

0 100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure B-3: Core Critical Operation (Curve C) Valid Up to 9 EFPY V

B-14

Enclosure PY-CEl/NRR-2129L Page 102 of 104 GE-NE-B1301793-01 i

Revision 0 o

1400 7

I e

INITIAL RTndt VALUES l

ARE -30'F FOR BELTLINE,

-20*F FOR UPPER 1200 VESSEL, AND 10*F FOR l

BOTTOM HEAD HEATUP/COOLDOWN RATE 20*F/HR 1

~ 1000

/

o!

g

/

i n

800 BOTTOM BELTINE CURVES l,

/3 E

HEA0 70*F ADJUSTED AS SHOWN-I h

a EFPY SHIFT ('F)

UP TO 18 91.9 w

E 600 2

E I

a g

I i

S 400 I

UPPER VESSEL AND BELTINE LIMITS

- - BOTTOM HEAD 200 FLANGE LIMITS REGION 70*F 0

0 100 200 300 400 M,NIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

O Figure B-4: Pressure Test Curve (Curve A) Valid Up to 18 EFPY b

B-15

Enclosure PY-CEI/NRR-2129L Page 103 of104 GE-NE-B1301793-01 Revision 0 1400

'I e

INITIAL RTndt VALUES l

ARE -30*F FOR BELTLINE,

-20'F FOR UPPER j

1200 VESSEL, AND 10'F FOR f

BOTTOM HEAD HEATUP/COOLDOWN RATE 100*F/HR 3

/

a 1000 f-a m

l

/

8

/

v

~

800 f

y BELTINE CURVES

/

ADJUSTED AS SHOWN:

E EFPY SHIFT ('F) v Q

UP TO 18 91.9 j

W BOTTOM E

600 HEAD 70*F a

N

}

a b

400 Fu i

tc" UPPER VESSEL AND l

BELTINE LIMITS

- - BOTTOM HEAD 200 L.lMITS r

FLANGE REGION 70*F l

0 0

100 200 300 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F) h Figure B-5: Non-Nuclear Heatup/Cooldown (Curve B) Valid Up to 18 EFPY v

B-16

Encloswe PY-CEI/NRR-2129L 4

Page 104 of 104 GE-NE-B1301793-01 Revision 0 s

O 1400 INITIAL RTndt VALUES ARE -30*F FOR BELTLINE,

-30'F FCR UPPER i

1200 VESSEL, AND 10*F FOR BOTTOM HEAD d

HEATUP/COOLDOWN f

RATE 100*F/HR

.9 j

E l

g 1000 5I j

o>

wg 800 BELTINE CURVES pg g

ADJUSTED AS SHOWN:

gj g

EFPY SHIFT (*F)

UP TO 18 91.9 m

l E

600 3

z t-lE3

$=

y 400 i

l Minimum BELTLINE AND Criticality NON BELTLINE Temperature LIMITS 200

/[

j 70'F i

O O

100 200 300 400 MINnMUM REACTOR VESSEL METAL TEMPERATURE (*F) 1 Figure B-6: Core Critical Operation (Curve C) Valid Up to 18 EFPY l

B-17

.

B130179, Rev 0 to Perry Unit 1 RPV Surveillance Matls Testing & Analysis

Contents

Text

SUMMARY

7.1 Background

SUMMARY

SUMMARY

2.2 CONCLUSION

7.1 BACKGROUND

Navigation menu

B130179, Rev 0 to Perry Unit 1 RPV Surveillance Matls Testing & Analysis

Text

SUMMARY

7.1 Background

SUMMARY

SUMMARY

2.2 CONCLUSION

7.1 BACKGROUND

Navigation menu

Search