Text

Response to Request for Additional Information for Pressurized Thermal Shock Evaluation
	ML11145A180
Person / Time
Site:	Palisades
Issue date:	05/24/2011
From:	Dotson B; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PNP 2011-044, TAC ME5263
	Download: ML11145A180 (182)
	v • d • e

Entergy Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel 269 764 2000 Barbara E. Dotson Licensing Manager PNP 2011-044 May 24, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Response to Request for Additional Information for Pressurized Thermal Shock Evaluation (ME5263)

Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Reference:

1. Entergy Nuclear Operations, Inc. letter, "Updated Palisades Reactor Vessel Pressurized Thermal Shock Evaluation", dated December 20, 2010 (ADAMS Accession No. ML110060692)

2. NRC e-mail dated April 7, 2011, Palisades - PTS Evaluation -

ME5263 - Request for Additional Information

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. (ENO) submitted an updated reactor vessel pressurized thermal shock evaluation for the Palisades Nuclear Plant on December 20, 2010 (Reference 1). ENO received an electronic request for additional information (RAI) from the Nuclear Regulatory Commission (NRC) concerning the submittal on April 7, 2011 (Reference 2). ENO and the NRC held a conference call on May 3, 2011, to clarify the RAI.

The enclosure contains the ENO response to the RAI. Attachment 1 of the enclosure contains BAW-2341, "Test Results Capsule SA-60-1," and Attachment 2 of the enclosure contains BAW-2398, "Test Results for Capsule SA-240-1." These two documents were requested by the NRC during the conference call.

Document Control Desk Page 2 This letter contains no new or revised commitments.

Sincerely, bed/jse

Enclosure:

RAI Response on Updated Palisades Reactor Vessel Pressurized Thermal Shock Evaluation cc:

Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC

ENCLOSURE RAI RESPONSE ON UPDATED PALISADES REACTOR VESSEL PRESSURIZED THERMAL SHOCK EVALUATION Request for additional information (RAI) received by electronic mail on April 7, 2011.

Nuclear Regulatory Commission (NRC) Request : Report 0901132.401, "Evaluation of Surveillance Data for Weld Heat No. W5214 for Application to Palisades PTS Analysis"

1.

It is stated in Section 4.0 under Data Evaluation Results that, "[tfhe new data survey was performed to gather all the unirradiated and irradiated capsule test results for the Palisades limiting weld material." Briefly describe this new data survey to demonstrate that no relevant data could have been missed during the survey.

Entergy Nuclear Operations, Inc. (ENO) Response

1.

The new data survey to gather all the unirradiated and irradiated capsule test results for the Palisades Nuclear Plant (PNP) limiting weld materials consisted of discussions with vendors and reviews of applicable databases and reports to ensure that all relevant data had been identified for the pressurized thermal shock evaluation. The focus of the surveying process was to identify and verify:

sister plants containing the same heats of weld material, capsules containing weld metal heat W5214 and 27204 that have been removed and tested to date, capsule initial properties, capsule irradiation temperature, and capsule fluence.

The following sister plants, vendors, and consultants were contacted for information:

sister plants: Fort Calhoun, Indian Point Units 2 and 3, and Robinson fabricating vendor: Combustion Engineering testing vendor: The Babcock and Wilcox Company, AREVA, and Westinghouse Electric Company fluence analysis vendor: Westinghouse Electric Company consultant: ATI Consulting and Structural Integrity Associates, Inc.

Page 1 of 5

The following documentation was reviewed during the initial information gathering process:

1.

Reactor Vessel Integrity Database Version 2.0.1 (NRC database).

2.

Reactor Vessel Materials Database (RPVDATA) Version 2 (EPRI database).

3.

EPRI, Materials Reliability Program letter 2010-001, Technical Report 51-9107111-000, "Coordinated U.S. PWR Reactor Vessel Surveillance Program (DRAFT 2)," September 2010.

4.

"Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds," CE NPSD-1039, Revision 2, Combustion Engineering Owners Group, June 1997 [referenced in Structural Integrity Associates, Inc. (SIA) Report No. 1000915.401, Revision 1].

5.

"Updated Analysis for Combustion Engineering Fabricated Reactor Vessel Welds Best Estimate Copper and Nickel Content,"

Combustion Engineering Owners Group, CEOG Task 1054, CE NPSD-1 119, Revision 1, July 1998 [referenced in SIA Report No.

0901132.401, Revision 0, and SIA Report No. 1000915.401, Revision 1].

6.

Letter from NRC to Palisades Plant, "Palisades Plant - Pressurized Thermal Shock Safety Evaluation (TAC No. M83227)," April 12, 1995.

7.

CNS-04-02-01, Constellation Nuclear Services Report, Revision 1, June 2004, "Evaluation of Palisades Nuclear Plant Reactor Pressure Vessel Through the Period of Extended Operation"

[referenced in SIA Report No. 0901132.401, Revision 0, and SIA Report No. 1000915.401, Revision 1].

8.

WCAP and BAW/BWXT reports referenced in SIA Report No.

0901132.401, Revision 0, and SIA Report No. 1000915.401, Revision 1.

9.

EPRI, Reactor Vessel Embrittlement Management Handbook, Volume 6, "Vessel Design and Fabrication," EPRI TR-101975-T2, December 1993.

Page 2 of 5

Through discussions with Westinghouse Electric Company and AREVA, ENO was able to confirm which surveillance capsules containing weld metal heats W5214 and 27204 have been removed and tested to date.

In addition, ENO retained Westinghouse Electric Company to review Structural Integrity Associates (SIA), Inc. Report No. 0901132.401 and Report No.

1000915.401 prior to transmittal of the pressurized thermal shock evaluation to the NRC to ensure that the reports contain all relevant information.

In summary, an exhaustive search confirmed that all reactor vessels made by Combustion Engineering containing these weld metal heats were identified. For the sister plants containing these same heats of weld material in surveillance capsules, the most up-to-date information had been gathered and there was no additional relevant data available.

NRC Request

2.

It is stated in Section 4.0 that, "there are two capsules from the Palisades supplemental surveillance program that were previously unreported."

A review of the BA W-2398 report, "Test Results of Capsule SA-240-1,"

indicated that the upper shelf energy values were determined in accordance with American Society for Testing and Materials (ASTM) Standard E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels." However, it did not mention whether the two supplemental capsules also comply with other aspects of the ASTM E 185-82. Discuss whether the supplemental capsule weld test data were obtained in accordance with the ASTM E 185-82 regarding test specimens, irradiation requirements, measurement of mechanical properties, and determination of irradiation effects.

ENO Response The PNP supplemental surveillance capsules SA-60-1 and SA-240-1 were designed in accordance with ASTM El 85-82, which was the version of ASTM El 85 that was accepted by the NRC at that time.

Due to space limitations in the capsules and the need for a sufficient number of specimens to monitor irradiation effects, annealing recovery and re-embrittlement 18 mm x 10 mm x 10 mm Charpy inserts for each of the three weld metal heats in the beltline region (W5124, 34B009, and 27204) were inserted in the capsules, as follows:

Page 3 of 5

Weld Metal Heat Capsule SA-60-1 Capsule SA-240-1 W5124 39 Charpy inserts 42 Charpy inserts 34B009 39 Charpy inserts 36 Charpy inserts 27204 36 Charpy inserts 36 Charpy inserts These inserts were to be reconstituted into full size Charpy specimens after irradiation following the guidance in ASTM E1253-88, "Standard Guide for Reconstitution of Irradiated Charpy Specimens." Both SA-60-1 and SA-240-1 capsules contained equivalent dosimetry and melt wires, like other surveillance capsules in the PNP surveillance program. Additionally, 12 correlation monitor material (heavy-section steel technology (HSST) Plate 02) Charpy specimens were included in each of these supplemental capsules as well as 12 full size Charpy specimens and three tensile specimens for weld metal heat 27204. Both supplemental surveillance capsules, SA-60-1 and SA-240-1, were installed into original surveillance capsule locations that were vacated during prior capsule removals.

Additional information on reconstitution of Charpy specimens is documented in BAW-2184, "Verification of Reconstituted Charpy V-Notch Test Values," dated May 1993. The dosimetry evaluations for capsule SA-60-1 were documented in WCAP-1 5353, Revision 0, "Palisades Reactor Pressure Vessel Neutron Fluence Evaluation," (ADAMS Accession No. ML003686582). The dosimetry analysis for capsule SA-240-1 was transmitted to Consumer Energy Company (former PNP license holder) via Westinghouse Project Letter CPAL-01 -009, "Neutron Fluence Analysis for Palisades Surveillance Capsule SA-240-1," dated April 30, 2001. The irradiation assessments for SA-60-1 and SA-240-1 have been updated under WCAP-1 5353, Supplement 1. Note that all mechanical property testing was done in accordance with ASTM El 85-82 requirements.

Test results for SA-60-1 are included in BAW-2341, Revision 2, (provided in to this enclosure) and test results for SA-240-1 are included in BAW-2398 (provided in Attachment 2). The latest determinations of irradiation effects are summarized in SIA Report No. 1000915.401, "Revised Pressurized Thermal Shock Evaluation for the Palisades Reactor Pressure Vessel," and WCAP-1 7341-NP, "Palisades Nuclear Power Plant Heatup and Cooldown Limit Curves for Normal Operation and Upper-Shelf Energy Evaluation."

WCAP-17341 -NP was provided to the NRC in ENO submittal, "License Amendment Request for Primary Coolant System Pressure-Temperature Limits,"

dated March 7, 2011.

Page 4 of 5

NRC Request

2. (continued)

Provide information about the reconstituted full size Charpy V-notch specimens using weld metal inserts. Cite studies and demonstrate that the Charpy data obtained this way is equivalent to those from conventional weld metal specimens.

ENO Response ASTM E1253 provides guidance on reconstitution of Charpy specimens, as mentioned in the previous response. This standard guidance was used in the preparation of all reconstituted Charpy specimens of the irradiated welds from the two supplemental capsules. Confirmation that equivalent results are obtained from reconstituted Charpy specimens as compared to full size Charpy specimens is documented in BAW-2184. Extensive studies also have been conducted, including an ASTM round robin in which many United States and international laboratories participated (including the laboratory that produced these reconstituted specimens), that further support the guidance in ASTM E1253. This ASTM round robin is documented in NUREG/CR-6777 (ORNL/TM-2001/34),

"Results and Analysis of the ASTM Round Robin on Reconstitution," August 2002

[ML022540225].

NRC Request

2. (continued)

Discuss whether the Palisades surveillance program augmented with two supplemental capsules was reviewed by the NRC.

ENO Response The PNP surveillance program augmented with the two supplemental capsules, SA-60-1 and SA-240-1, has not been previously reviewed by the NRC.

The supplemental capsules are discussed in the PNP Final Safety Analysis Report (FSAR). FSAR Section 4.5.3, "Surveillance Program" describes the supplemental capsules, and references the aforementioned BAW-2341 and BAW-2398, which contain the test results for these capsules.

In addition, the dosimetry results from capsule SA-60-1 are included in WCAP-1 5353, Revision 0, which has been reviewed by the NRC.

Page 5 of 5

ATTACHMENT 1 TEST RESULTS CAPSULE SA-60-1 BAW-2341 REVISION 2 MAY 2001 93 Pages Follow

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~- 1.Li BAW-2341, Revision 2 May 2001 Test Results of Capsule SA-60-1 Consumers Energy Palisades Nuclear Plant

-- Reactor Vessel Material Surveillance Program --

by LI VI Li B

LI LI Li LI El Li M. J. DeVan FTI Document No. 77-2341-02 (See Section 7 for document signatures.)

Prepared for Consumers Energy Prepared by Framatome ANP, Inc.

3315 Old Forest Road P. 0. Box 10935 Lynchburg, Virginia 24506-0935 fFRAMATOME ANP

Executive Summary This report describes the results of the test specimens from the first supplemental capsule (Capsule SA-60-1) of the Consumers Energy Palisades Nuclear Plant as part of their reactor vessel surveillance program. The objective of the program is to monitor the effects of neutron irradiation on the mechanical properties of the reactor vessel materials by testing and evaluation Fof Charpy impact specimens.

Supplemental Capsule SA-60-1 was removed from the Palisades reactor vessel at the end-of-cycle 13 (EOC-13) for testing and evaluation. The capsule contents were removed from Capsule SA-60-1 for testing and examination. The test specimenis included modified 18mm Charpy V-1notch inserts for three weld metals fabricated with weld wire heats W5214, 34B009, and 27204 and standard Charpy V-notch specimens fabricated from the correlation monitor plate material, r)HSST Plate 02. The weld metal Charpy inserts were reconstituted to full size Charpy V-notch specimens. The reconstituted weld metals along with HSST Plate 02 material were Charpy iimpact tested.

Following the initial Charpy V-notch impact testing, the laboratory performed a calibration of 1the temperature indicator used in the Palisades Capsule SA-60-1 testing. The results of the laboratory calibration indicated the instrument was out-of-tolerance. Based on the results of this calibration test, the laboratory revised the Charpy impact test temperatures accordingly. Revision 1 corrects the test temperatures for the Supplemental Capsule SA-60-1 reconstituted weld metal Charpy V-notch impact specimens and the HSST Plate 02 Charpy V-notch impact specimens.

Revision 2 provides an update to the hyperbolic tangent curve fits of the Charpy impact curves by restraining the upper-shelf energy. For these curve fits, the lower-shelf energy was fixed at 2.2 ft-lbs for all cases, and for each materials the upper-shelf energy was fixed at the average of all test energies exhibiting 100% shear, consistent with ASTM Standard E 185-82.

LI 13ii f~lRAMATOME ANP

I Acknowledgement I

31 3

The author would like to thank Kevin Hour of the McDermott Technology, Inc. Lynchburg Technology Center for his efforts and expertise in specimen testing and Hongqing Xu of Framatome Technologies, Inc. for his work on the Charpy specimen reconstitution. The efforts by both these individuals contributed greatly to the success of this project.

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Record of Revisions Date Revision No.

Description March 1999 0

Original Issue May 1999 1

Executive Summary - Revision statement added.

I Section 1 - Revision statement added.

Section 4 - Added paragraph referencing laboratory test report.

Table 4-2. - Corrected Specimen iDs.

Table 4-3. - Revised test temperatures.

Table 4-4. - Revised test temperatures.

Table 4-5. - Revised test temperatures.

Table 4-6. - Revised test temperatures.

Table 4-7. - Revised test temperatures.

-]

Table 4-8. - Revised test temperatures.

Table 4-9. - Revised test temperatures.

Table 4-10. - Revised test temperatures.

Table 4-11. - Revised coefficients based on revised test temperatures.

Table 4-12. - Revised Figure 4-2. - Revised figure based on revised test temperatures.

Figure 4-3. - Revised figure based on revised test temperatures.

Figure 4-4. - Revised figure based on revised test temperatures.

Figure 4-5. - Revised figure based on revised test temperatures.

Figure 4-6. - Removed reported test temperature.

LI Figure 4-7. - Removed reported test temperature.

Figure 4-8. - Removed reported test temperature.

Figure 4-9. - Removed reported test temperature.

Section 6. - Revised transition temperatures in items 3 through 6 based on revised test temperatures.

Section 7. - New signatures added.

Section 8. - Revised reference.

-iiv

Record of Revisions (continued)

Date May 2000 Revision No.

2 Description Executive Summary - Revision statement added.

Section 1 - Revision statement added.

Section 3 - Corrected typo.

Section 4.1 - Corrected typo.

Section 4.5 - Added paragraph describing the method used for the hyperbolic tangent curve fitting of the Charpy impact data.

Table 4-2. - Changed "width" and "thickness" tolerance from +/-0.001" to +/-+0.003".

Table 4-11. - Revised coefficients for Absorbed Energy based on fixing the upper-shelf energy at the average of all test energies exhibiting 100% shear.

Table 4-12. - Revised.

Figure 4-2. - Revised figure.

Figure 4-3. - Revised figure.

Figure 4-4. - Revised figure.

Figure 4-5. - Revised figure.

Section 6. - Revised transition temperatures in items 3 through 6 based on revised hyperbolic tangent curve fit coefficients.

Section 7. - New signatures added.

Table A-1. - Revised table to be consistent with the NRC's RVID2 database.

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IFRAMATOME ANP v

Table of Contents 1.0 Introduction......................................................................................................................

1-1

[4 2.0

Background

2-1 3.0 Surveillance Program D escription...................................................................................

3-1

., 1 4.0 Post-Irradiation Testing....................................................................................................

4-1 4.1.

Visual Examination and Inventory.......................................................................

4-1 4.2.

Therm al M onitors.................................................................................................

4-1 4.3.

Tension Test Specim ens.......................................................................................

4-1 4.4.

Reconstitution of Irradiated Charpy Inserts.........................................................

4-1 J

4.5.

Charpy V-Notch Impact Test Results 4-3 5.0 D osim eter M easurem ents.................................................................................................

5-1 5.1.

Introduction..........................................................................................................

5-1 5.2.

D osim eter Preparation.........................................................................................

5-1 5.3.

Quantitative Gamma Spectrometry..............................

5-1 5.4.

D osim eter Specific Activities...............................................................................

5-2 6.0 Summary of Results.............................................

6-1 7.0 Certification 7-1 8.0 R eferences........................................................................................................................

8-1

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Appendices A.

Reactor Vessel Surveillance Program Background Data and Information............... A-1 B.

Instrumented Charpy V-Notch Specimen Test Results Load-Time Traces............. B-1 lid

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Ai ARAMATOME ANP

List of Tables Table Pg 3-1.

Test Specimens Contained in Palisades Capsule SA-60-1...............................................

3-3 3-2.

Chemical Composition of Palisades Capsule SA-60-1 Surveillance Materials............... 3-4 3-3.

Heat Treatment of Palisades Capsule SA-60-1 Surveillance Materials........................... 3-5 4-1.

Conditions of Palisades Capsule SA-60-1 Thermal Monitors.........................................

4-5 4-2.

Dimensions of Reconstituted Charpy Specimens for Palisades Capsule SA-60-1.......... 4-6]

4-3.

Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Weld Metal W 52 14..............................................................................................................................

4-7 4-4.

Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Weld Metal

,1 34B 009............................................................................................................................

4-8 4-5.

Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Weld Metal

§1 27204................................................................................................................................

4-9 4-6.

Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02) Heat No. A 1195-1.........................................

4-10

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4-7.

Instrumented Charpy Impact Properties for Palisades Capsule SA-60-1 Irradiated W eld M etal W 5214........................................................................................................

4-11 4-8.

Instrumented Charpy Impact Properties for Palisades Capsule SA-60-1 Irradiated W eld M etal 34B 009.......................................................................................................

4-12 4-9.

Instrumented Charpy Impact Properties for Palisades Capsule SA-60-1 Irradiated W eld M etal 27204..........................................................................................................

4-13 4-10. Instrumented Charpy Impact Properties for Palisades Capsule SA-60-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02) Heat No. Al 195-1...................... 4-14 4-1i.

Hyperbolic Tangent Curve Fit Coefficients for the Palisades Capsule SA-60-1 Surveillance M aterials....................................................................................................

4-15 4-12. Summary of Charpy Impact Test Results for the Palisades Capsule SA-60-1 Surveillance M aterials....................................................................................................

4-16 5-1.

Quantifying Gam m a Rays......................................................

.................................... 5-3 J

5-2.

Isotopic Fractions and Weight Fractions of Target Nuclides...........................................

5-4 5-3.

Specific Activities for Palisades Capsule SA-60-1 Dosimetry........................................

5-5 A-1.

Description of the Palisades Reactor Vessel Beltline Region Materials......................... A-3 v

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vii ARAMATOME ANP i]

LI lList of Figures 5lFiur Page 3-1.

Reactor Vessel Cross Section Showing Location of Palisades Original RVSP C apsules...........................................................................................................................

3-6 r]

3-2.

Reactor Vessel Cross Section Showing Location of Palisades Supplemental L..1 Surveillance C apsules......................................................................................................

3-7 3-3.

Supplemental Surveillance Capsule Assembly Showing Location of Specimens and M onitors....................................................................................................................

3-8 3-4.

Temperature, Flux, and Tensile (TFI') Capsule Compartment Assembly....................... 3-9 3-5.

Standard Charpy Impact and Flux Capsule Compartment Assembly (Two Per C apsule)............................................................................................................................

3-9 3-6.

Standard Charpy Impact Capsule Compartment Assembly...........................................

3-10 VI 3-7.

Typical 18mm Charpy Impact Capsule Compartment Assembly (Three Per C apsule...........................................................................................................................

3-10 4-1.

Photographs of Thermal Monitors Removed from Palisades Capsule SA-60-I............ 4-17

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4-2.

Charpy Impact Data for Irradiated Weld Metal W5214................................................

4-18 4-3.

Charpy Impact Data for Irradiated Weld Metal 34B009................................................

4-19 4-4.

Charpy Impact Data for Irradiated Weld Metal 27204..................................................

4-20 4-5.

Charpy Impact Data for Irradiated Correlation Monitor Plate Material (H SST Plate 02).............................................................................................................

4-21 4-6.

Photographs of Charpy Impact Specimen Fracture Surfaces, W eld M etal W 5214.......................................................................................................

4-22 4-7..

Photographs of Charpy Impact Specimen Fracture Surfaces,

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W eld M etal 34B009.......................................................................................................

4-23 4-8.

Photographs of Charpy Impact Specimen Fracture Surfaces, El W eld M etal 27204..........................................................................................................

4-24 4-9.

Photographs of Charpy Impact Specimen Fracture Surfaces, Correlation Monitor Plate Material (HSST Plate 02).....................................................

4-25

/

5-1.

Photographs of Shielded Uranium Dosimeters Removed from Capsule SA-60-1.......... 5-6 A-1.

Location and Identification of Materials Used in the Fabrication of Palisades Reactor Pressure V essel..................................................................................................

A -4 B-1.

Load-Time Trace for Charpy V-Notch Impact Specimen AA2......................................

B-2 B-2.

Load-Time Trace for Charpy V-Notch Impact Specimen AWl.....................................

B-2 B-3.

Load-Time Trace for Charpy V-Notch Impact Specimen AW2.....................................

B-3 J

B-4.

Load-Time Trace for Charpy V-Notch Impact Specimen 2AF5....................................

B-3 B-5.

Load-Time Trace for Charpy V-Notch Impact Specimen AL3......................................

B-4 B-6.

Load-Time Trace for Charpy V-Notch Impact Specimen AA4...................................

B-4 viii ARAMATOME AMP

I List of Figures (continued)

Figu-re Page

-B-7.

Load-Time Trace for Charpy V-Notch Impact Specimen 2AL6....................................

B-5 B-8.

Load-Time Trace for Charpy V-Notch Impact Specimen 2AE2..............................

B-5 B-9.

Load-Time Trace for Charpy V-Notch Impact Specimen 2AH6....E..........................

B-6 B-10. Load-Time Trace for Charpy V-Notch Impact Specimen AR94....................................

B-6 B-11. Load-Time Trace for Charpy V-Notch Implpact Specimen AV4...............................

B-7 B-1i. Load-Time Trace for Charpy V-Notch Impact Specimen AW5...............

B-7 B-13. Load-Time Trace for Charpy V-Notch Impact Specimen BO2...................................

B-B-12. Load-Time Trace for Charpy V-Notch Impact Specimen ABV5............................. B-B-13. Load-Time Trace for Charpy V-Notch Impact Specimen BD2...............................

B-S B-14. Load-Time Trace for Charpy V-Notch Impact Specimen 2BK5.............

W..................B-9 B-15. Load-Time Trace for Charpy V-Notch Impact Specimen 3B02...................................

3B-10 B-16. Load-Time Trace for Charpy V-Notch Impact Specimen 2B5.............................. B-1 B-17. Load-Time Trace for Charpy V-Notch Impact Specimen 2BJ.............................

B-10 B-28. Load-Time Trace for Charpy V-Notch Impact Specimen BL2..............................

B-10 B-21B"2.

Load-Ti°medime Tracreae for Charpy V-NofrthapyVNtch Impac~mtat Specimen PBR91..................................SecmnP6.................

BI

-12 B-272.

Load-Time Traace for Charpy V-Notch Impamct Spcimen PB B_-1 B-29. Load-Time Trace for Charpy V-Notch Impact Specimen B3K1......................... B-1i B-20. Load-Time Trace for Charpy V-Notch Impact Specimen BWL............................ B-1i B-21. Load-Time Trace for Charpy V-Notch Impact Specimen PBR8.............................

B-12 4 B-22. Load-Time Trace for Charpy V-Notch Impact Specimen PBU2...................................

B-12 B-23.

Load-Time Trace for Charpy V-Notch Impact Specimen PB15...............

B-15 B-24. Load-Time Trace for Charpy V-Notch Impact Specimen PBL2...............................

B-13 B-25. Load-Time Trace for Charpy V-Notch Impact Specimen PB93.......................... B-14 B-3-.

Load-Time Trace for Charpy V-Notch Impact Specimen PB95........................

3 B-1 B-3-.

Load-Time Trace for Charpy V-Notch Impact Specimen P328.......................

3 B-1 2. Load-Time Trace for Charpy V-Notch Impact Specimen P378...................B-1 B3-2.

Load-Time Trace for Charpy V-Notch Impact Specimen P393.........................

3B-168 B-30. Load-Time Trace for Charpy V-Notch Impact Specimen PB15..........................3B-1687 B-35. Load-Time Trace for Charpy V-Notch Impact Specimen P3428.........................3B-17 3-32. Load-Time Trace for Charpy V-Notch Impact Specimen PB96.........................

3B-17 B-34. Load-Time Trace for Charpy V-Notch Impact Specimen P2D2-9.......................

B-i0 3-38. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-3......................3B-20 ix AFRAMATOME AMP]

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List of Figures (continued)

.m Figure Page B-39. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-1..............................

B-21 B-40. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-7............................ B-21 B-41. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-18............................

B-22 B-42. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-21............................ B-22 B-43. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-14............................ B-23 B-44. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-16............

B-23 B-45. Load-Time Trace for Charpy V-Notch Impact Specimen 02D24..............................

B-24 B-46. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-6.............

B-24 B-47. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-12............................ B-25 13-48. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-20

............ B-25 x

fARAMATOME AN P

1.0 Introduction 71 Two supplemental surveillance capsules were fabricated containing the three weld metals found in the core region of the Palisades reactor vessel. The supplemental capsules were prepared to obtain 71 information on the effects of irradiation on the mechanical properties of weld metals fabricated using the same weld wire heats and weld procedures as was used in the Palisades reactor vessel beltline region. Supplemental Capsules SA-60-1 and SA-240-1 were inserted in the Palisades reactor vessel at the end-of-cycle 11 (EOC-11) in locations near the outer wall of the core support barrel for accelerated exposure. Supplemental Capsule SA-60-1 was removed from the Palisades reactor vessel at the end-of-cycle 13 (EOC-13) for testing and evaluation.

This report describes the specimen testing and the post-irradiation results from the first I

supplemental surveillance capsule (Capsule SA-60-1) for the Consumers Energy's Palisades Nuclear Plant.

Following the initial Charpy V-notch impact testing, the laboratory performed a calibration of the temperature indicator used in the Palisades Capsule SA-60-1 testing. The results of the laboratory calibration indicated the instrument was out-of-tolerance. Based on the results of this calibration test, the laboratory revised the Charpy impact test temperatures accordingly. Revision 1 corrects the test temperatures for the Supplemental Capsule SA-60-1 reconstituted weld metal Charpy V-notch impact specimens and the HSST Plate 02 Charpy V-notch impact specimens.

Revision 2 provides an update to the hyperbolic tangent curve fits of the Charpy impact curves by restraining the upper-shelf energy. For these curve fits, the lower-shelf energy was fixed at 2.2 ft-lbs for all cases, and for each materials the upper-shelf energy was fixed at the average of 2

all test energies exhibiting 100% shear, consistent with ASTM Standard E 185-82.

iA 1-1 A*_RAMATOME ANP j]

I

2.0 Background

The ability of the reactor vessel to resist fracture is a primary factor in ensuring the safety of the primary system in light water-cooled reactors. The reactor vessel beltline region is the most critical region of the vessel because it is exposed to the highest level of neutron irradiation. The general effects of fast neutron irradiation on the mechanical properties of low-alloy ferritic steels used in the fabrication of reactor vessels are well characterized and documented. The low-alloy ferritic steels used in the beltline region of reactor vessels exhibit an increase in ultimate and yield strength properties with a corresponding decrease in ductility after irradiation. The most significant II mechanical property change in reactor vessel steels is the increase in the ductile-to-brittle transition temperature accompanied by a reduction in the Charpy upper-shelf energy (CVUSE) value.

Code of Federal Regulations, Title 10, Part 50, (10 CFR 50) Appendix G,1 "Fracture Toughness Requirements," specifies minimum fracture toughness requirements for the ferritic materials of the 3

pressure-retaining components of the reactor coolant pressure boundary (RCPB) of light water-cooled power reactors and provides specific guidelines for determining the pressure-temperature limitations for operation of the RCPB. The fracture toughness and operational requirements are specified to provide adequate safety margins during any condition of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected over its service lifetime. Although the requirements of 10 CFR 50, Appendix G, became effective on August 16, 1973, the requirements are applicable to all boiling and pressurized J

water-cooled nuclear power reactors, including those under construction or in operation on the effective date.

10 CFR 50, Appendix H,2 "Reactor Vessel Materials Surveillance Program Requirements," defines the material surveillance program required to monitor changes in the fracture toughness properties

}

of ferritic materials in the reactor vessel beltline region of water-cooled reactors resulting from exposure to neutron irradiation and the thermal environment. Fracture toughness test data are obtained from material specimens contained in capsules that are periodically withdrawn from the reactor vessel. These data permit determination of the conditions under which the vessel can be operated with adequate safety margins against non-ductile fracture throughout its service life.

2 2-1 AAMATOEANP

A method for guarding against non-ductile fracture in reactor vessels is described in Appendix G to L

the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section 1],3 "Nuclear Power Plant Components" and Section XI,4 "Rules for Inservice Inspection."

This method uses fracture mechanics concepts and the reference nil-ductility temperature, RTNrT, which is defined as the greater of the drop weight nil-ductility transition temperature (in accordance r_

with ASTM Standard E 208-815) or the temperature that is 60°F below that at which the material exhibits 50 ft-lbs and 35 mils lateral expansion. The RTNDT of a given material is used to index that 3material to a reference stress intensity factor curve (KmR curve), which appears in Appendix G of ASME B&PV Code Section Ell and Section XI. The Km curve is a lower bound of dynamic and crack arrest fracture toughness data obtained from several heats of pressure vessel steel. When a given material is indexed to the Km curve, allowable stress intensity factors can be obtained for the material as a function of temperature. The operating limits can then be determined using these allowable stress intensity factors.

F_]

The RTNDT and, in turn, the operating limits of a nuclear power plant, are adjusted to account for the effects of irradiation on the fracture toughness of the reactor vessel materials. The irradiation eml'rittlement and the resultant changes in mechanical properties of a given pressure vessel steel can be monitored by a surveillance program in which surveillance capsules containing prepared specimens of the reactor vessel materials are periodically removed from the operating nuclear 3

reactor and the specimens are tested. The increase in the Charpy V-notch 30 ft-lb temperature is added to the original RTNDT to adjust it for irradiation embrittlement. The adjusted RTNDT is used to I rindex the material to the Km curve which, in turn, is used to set operating limits for the nuclear power plant. These new limits take into account the effects of irradiation on the reactor vessel U

materials.

10 CFR 50, Appendix G, also requires a minimum initial Charpy V-notch upper-shelf energy (CUSE) of 75 ft-lbs for all beltline region materials unless it is demonstrated that lower values of upper-shelf fracture energy will provide an adequate margin of safety against fracture equivalent to those required by ASME Section XI, Appendix G. No action is required for a material that does not meet the initial 75 ft-lbs requirement provided that the irradiation embrittlement does not cause the CVUSE to drop below 50 ft-lbs. The regulations specify that if Ithe CvUSE drops below 50 ft-lbs, it must be demonstrated, in a manner approved by the Office of Nuclear Reactor Regulation, that the lower values will provide adequate margins of safety.

L i.L j2-2 AERAMATOME AMP

3.0 Surveillance Program Description The original reactor vessel surveillance program (RVSP) for the Palisades Nuclear Plant was designed and furnished by Combustion Engineering, Inc.6 The program was designed to the requirements of ASTM Standard E 185-66,7 "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors." The Palisades RVSP includes ten capsules designed to monitor the effects of neutron and thermal environments on the materials of the reactor pressure vessel core region. These capsules were inserted into the reactor vessel before initial plant startup.

Six capsules were positioned such that they were located near the inside surface of the reactor 1

vessel wall adjacent to the core, and two capsules were positioned closer to the core located on the outer wall of the core support barrel for accelerated exposure. Two capsules, designed for monitoring the effects of operating temperature on the surveillance materials, were located above the core such that the exposure was in a low flux region of the reactor vessel. The locations of the 3'-

Palisades surveillance capsules within the reactor vessel are shown in Figure 3-1.

In addition to the above ten surveillance capsules, two supplemental surveillance capsules were 3'

fabricated containing three weld metals representative of those found in the core region of the Palisades reactor vessel. These capsules were installed at the end-of-cycle I I (EOC-1 1) in locations near the outer wall of the core support barrel for accelerated exposure. The locations of the two supplemental surveillance capsules within the Palisades reactor vessel are shown in Figure 3-2.

Supplemental surveillance Capsule SA-60-1 was removed from the Palisades reactor vessel at the end-of-cycle 13 (EOC-13). The capsule contained standard Charpy V-notch impact test specimens fabricated from a submerged-arc weld metal (weld wire heat number 27204) and a correlation monitor plate material (HSST Plate 02). In addition, the Capsule SA-60-1 contained modified 18mm Type A Charpy V-notch specimens fabricated from three submerged-arc weld metals (weld wire heat numbers W5214, 34B009, and 27204); the 18mm Type A Charpy V-notch specimens are

]

available for reconstitution such that full size Charpy V-notch impact specimens can be fabricated.

The tension test specimens included in Capsule SA-60-l were fabricated from a submerged-arc weld metal (weld wire heat number 27204). The number of specimens of each material contained in supplemental surveillance Capsule SA-60-1 is described in Table 3-1, and the locations of the individual specimens within the capsule are shown in Figures 3-3 through 3-7. The chemical

]

3-1 AFRAMATOME ANP

I Li Li Li a

]

fill composition and heat treatment of the surveillance materials in Capsule SA-60-1 are described in Tables 3-2 and 3-3 respectively.

The weld metal Charpy V-notch and tensile specimens were machined throughout the thickness of the weldment and were oriented with the longitudinal axis of the specimen either parallel or perpendicular to the welding direction.

There are three sets of nine dosimeter monitors in Capsule SA-60-1; one each located in the top, middle, and bottom of the capsule. The dosimeter monitors included in each set consist of shielded copper, shielded nickel, unshielded iron, unshielded titanium, shielded and unshielded aluminum-cobalt, shielded and unshielded neptunium-237 (237Np), and shielded and unshielded uranium-238 2 38m Thermal monitors fabricated from four low-melting alloys were included in Capsule SA-60-1, and were located in the middle of the capsule. The eutectic alloys and their melting points are listed below:

1]

LL 80% Au, 20% Sn 5% Ag, 5% Sn, 90% Pb 2.5% Ag, 97.5% Pb 1.75% Ag, 0.75% Sn, 97.5% Pb Melting Point 536°F Melting Point 558°F Melting Point 580°F Melting Point 590°F Li FRAMATOME ANP 3-2

Table 3-1. Test Specimens Contained in Palisades Capsule SA-60-1 Number of Test Specimens Standard 18amm Charpy V-Notch Charpy V-Notch Material Description Tension Impact Inserts Weld Metal W5214 39 Weld Metal 34B009 39 Weld Metal 27204 3

12 36 Correlation Monitor Material, 12 HSST Plate 02 (Heat No. A 1195-1)

FRAMATOME ANP 3-3 ii

FI r

11 Table 3-2. Chemical Composition of Palisades Capsule SA-60-1 Surveillance Materials Chemical Composition, wt%

Weld Metal Weld Metal Weld Metal Correlation Monitor Plate Element W5214(3' 34B009 (a) 27204(,)

Heat No. Al1 95-1(c)

C 0.094 0.110 0.142 0.23 Mn 1.161 1.269 1.281 1.39 P

0.009 0.012 0.009 0.013 S

0.012 0.016 0.008 0.013 Si 0.252 0.181 0.217 0.21 Ni 1.045(b) 1.121(b) 1.067 0.64 Cr 0.040 0.040 0.071 Mo 0.510 0.543 0.525 0.50 Cu 0.307()

0. 18 5(b) 0.194 0.17 (a) AEA Technology analysis.8 (b) Analysis provided by Consumers Energy.9 (c) ORNL analysis.' 0 r]

Li LI Ji tFRAMATOME AMP 3-4

ii Table 3-3. Heat Treatment of Palisades Capsule SA-60-1 Surveillance Materials Material Heat Description Treatment Weld Metal W5214 Post weld heat treatment: >1 100*F for 25 hrs, cooled at 8°F/hr for 24 hrs.(a)

Re-post weld heat treatment: 1 1500F for 2 hrs, with 100°F/hr heatingfcooling rates (above 500°F)ob)

Weld Metal 34B009 Post weld heat treatment: >1 1000F for 16 hrs, cooled at 7°F/hr for 27 hrs.(a)

Re-post weld heat treatment: 1150*F for 2 hrs, with 1000F/hr heating/cooling rates (above 500°F)(b)

Weld Metal 27204 Post weld heat treatment: >1100°F for 40 hrs.(c)

Correlation Monitor Plate, 1675 +/- 25'F for 4 hrs., air cooled ISST Plate 02 1600 +/- 25*F for 4 hrs., water quenched to 300'F (Heat No. A1195-1) 1225 +/- 25'F for 4 hrs., furnace cooled to 500°F 1150 +/- 250F for 40 hrs., furnace cooled to 600'F (a) Original post weld heat treatment."1 (b) Post weld heat treatment performed on retired steam generator material to ensure that the material would be as close as possible to the original start-of-life condition.!

(c) Post weld heat treatment provided by Consumers Energy.9 r -,

LI C

21 I

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C 12

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ii

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ii j

'II C

A RAMATOME ANP 3-5

LI LJ LI Figure 3-1. Reactor Vessel Cross Section Showing Location of Palisades Original RVSP Capsules I

I

/

I 3

Enlarged Plan View oo Elevation View

/RAMATOME ANP I

3-6

Figure 3-2. Reactor Vessel Cross Section Showing Location of Palisades Supplemental Surveillance Capsules 3ORAMATOME ANP 3-7

7]

LI LI LI El JI LI a

LI a

Li' LI ri LI U]

CLI U

j Figure 3-3. Supplemental Surveillance Capsule Assembly Showing Location of Specimens and Monitors Standard Charpy Impact

& Flux Compartment Temperature, Flux, & Tensile Compartment Standard Charpy Impact

& Flux Compartment Lock Assembly I

Wedge Coupling Assembly I

Extension Assembly 18mm Charpy Impact Compartment 18mm Charpy Impact Compartment Standard Charpy Impact Compartment AR'AMATOME ANP 3-8

3-4. Temperature, Flux, and Tensile (TFT) Capsule Compartment Assembly Temperature Monitor Tensile Housing

/-

Specimen Dosimeter Housing 3-5. Standard Charpy Impact and Flux Capsule Compartment Assembly (Two Per Capsule)

Temperature SMonitor IO m M d~

Housig

/--18rmm Modified Charpy Insert Dosimeter ZCharpy V-Notch Housing Specimen 3-9 ARAMATOME ANP

3-6. Standard Charpy Impact Capsule Compartment Assembly Standard Charpy V-Notch Specimen 3-7. Typical 18mm Charpy Impact Capsule Compartment Assembly (Three Per Capsule) 18mm Modified Charpy Insert pIFRAMATOME AMP 3-10

4.0 Post-Irradiation Testing The post-irradiation testing of the Charpy V-notch impact specimens, thermal monitors, and dosimeters for the Palisades Capsule SA-60-1 was performed at the B&W Services Inc. (BWSI)

Lynchburg Technology Center (LTC).18 4.1. Visual Examination and Inventory I

After capsule disassembly, the contents of Capsule SA-60-1 were removed, inspected, and inventoried. The capsule contained a total of 24 standard Charpy V-notch specimens, 114 modified ii 18mm Charpy inserts, three tension test specimens, three dosimetry blocks, and four temperature monitors, which is consistent with the manufacturing report inventory.

12]

4.2. Thermal Monitors The four low-melting point eutectic alloys contained in Capsule SA-60-1 were examined for evidence of melting. The results of the thermal monitor examination are tabulated in Table 4-1.

Photographs of the monitors are shown in Figure 4-1.

Only the thermal monitor with complete melting was the monitor with the melting point at 5360F, and the remaining thermal monitors with melting points at 558°F, 580'F and 590°F had no evidence of melting. Based on these observations, it can be concluded that the capsule did not exceed a maximum irradiation temperature of 558°F.

4.3. Tension Test Specimens The tension test specimens removed from Capsule SA-60-1 were not tested at the request of Consumers Power Company. The specimens are to be held for testing at a future date.

4.4. Reconstitution of Irradiated Charpy Inserts Pre-machined 18mm Charpy inserts fabricated from three submerged-arc weld metals (weld wire heat numbers W5214, 34B009, and 27204) were included in Capsule SA-60-1 for reconstitution of

]

full size Type A Charpy V-notch impact specimens. Each 18mm weld metal Charpy insert included a centrally located V-notch that was machined prior to capsule irradiation. The j

reconstitution technique was performed by stud welding steel end tabs onto the irradiated modified 18mm Charpy inserts and machining full size Type A Charpy V-notch impact 7f 4-1 A

RAMATOME ANP

LI specimens to the dimensional requirements of ASTM Standard E 23-91.12 The proof-of-principal and validation test results for the FTI Charpy reconstitution process is documented in BAW-2184.13 The reconstitution of the irradiated weld metal 18mm modified Charpy inserts was performed in accordance with ASTM Standard E 1253-88,14 "Standard Guide for vil Reconstitution of Irradiated Charpy Specimens."

Sixteen (16) modified 18mm Charpy inserts were selected from weld metal 34B009, and fifteen

](15) modified 18mm Charpy inserts were selected from each of the weld metals W5214 and 27204 for reconstitution to full size Charpy V-notch specimens. Prior to welding the irradiated 18mm Charpy inserts, the reconstitution process was performed on two mockup inserts to assure that the reconstitution welding process would produce quality welds. A steel end tab was stud welded to each end of the mockup insert, and each weldment was visually inspected for good

]fillet formation resulting from the stud welding process. In addition, each mockup specimen was subjected to a 45-degree bend test, to determine acceptance of the stud weld. An acceptable

[weld is one that did not fracture in the weld fusion zone resulting from the stud welding process.

Once acceptable welds were established on the mockup inserts, reconstitution of the irradiated 18mm Charpy inserts could begin. Using the same welding parameters used to reconstitute the mockup inserts, a steel end tab was stud welded to each end of the selected weld metal 18mm Charpy inserts irradiated in Capsule SA-60-1.

The ASTM Standard E 1253-88 specifies that temperature records be made during the welding on the first and last specimens of each set of Charpy specimens or on dummy specimens LI proceeding and following welding of the set. Prior to performing the reconstitution of the Capsule SA-60-1 modified 18mm Charpy inserts, temperatures were recorded on dummy

I specimens in the central test section. The amperage setting used in the stud welding process for these dummy specimens was significantly greater than the setting used to reconstitute the

ii Capsule SA-60-1 modified 18mm Charpy inserts. The greater amperage results in a greater heat input to the central portion of the reconstituted specimen, however the maximum recorded temperature using this greater amperage was approximately 500VF which is less than the Palisades reactor vessel cold-leg temperature and meets the temperature requirement of ASTM Standard E 1253-88. Following the reconstitution of the Capsule SA-60-1 18mm Charpy inserts, 0a dummy specimen was reconstituted using the similar welding parameters to determine the maximum temperature at the center position of the Charpy insert section. The maximum Fl temperature observed on the dummy specimen was 423°F for the first weld and 414°F for the second weld which again meets the temperature requirement of ASTM Standard E 1253-88.

LFourteen (14) stud-welded inserts were then selected from weld metal 34B009, and thirteen (13) stud-welded inserts were selected from each of the weld metals W5214 and 27204 for machining 4-2 FRAMATOME ANP

of full size Type A Charpy V-notch specimens in accordance with ASTM Standard E 23-91.

j The reconstituted Charpy specimen dimensions for each specimen are shown in Table 4-2. Upon completion of the machining of the reconstituted Charpy specimens, twelve (12) specimens were I

selected from each weld metal for Charpy impact testing.

4.5. Charpy V-Notch Impact Test Results The Charpy V-notch impact testing was performed in accordance with the applicable requirements of ASTM Standard B 23-91. Impact energy, lateral expansion, and percent shear fracture were measured at numerous test temperatures and recorded for each specimen. The impact energy was measured using a certified Satec SI-1K Impact tester (traceable to NIST Standard) with 240 ft-lb

]

of available energy. The lateral expansion was measured using a certified dial indicator. The specimen percent shear was estimated by video examination and comparison with the visual standards presented in ASTM Standard E 23-91. In addition, all Charpy V-notch impact testing was performed using instrumentation to record a load-versus-time trace and energy-versus-time trace for each impact event. The load-versus-time traces were analyzed to determine time, load, and impact energy for general yielding, maximum load, fast fracture, and crack arrest properties during the test. The dynamic yield stress is calculated from the three-point bend formula:

U a-y= 33.33 * (general yielding load)

The dynamic flow stress is calculated from the average of the yield and maximum loads, also using the three-point bend formula:

a flow = 33.3

((generalyielding load + maximum load))U The results of the Charpy V-notch impact testing are shown in Tables 4-3 through 4-10 and Figures 4-2 through 4-5, and the individual load-versus-time traces for the instrumented Charpy V-notch impact tests are presented in Appendix B. The curves were generated using a hyperbolic tangent curve-fitting program to produce the best-fit curve through the data. The hyperbolic tangent (TANH) function (test response, i.e., absorbed energy, lateral expansion, and percent U

shear fracture, "R," as a function of test temperature, "T") used to evaluate the surveillance data is as follows:

U]

4-3 ARAMATOME ANPj

F-L.1 j

F]

[1

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Li

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F]

LI F]

LI Li ci LI Cl ii For the absorbed (impact) energy curves, the lower-shelf energy was fixed at 2.2 ft-lbs for all materials, and the upper-shelf energy was fixed at the average of all test energies exhibiting 100 percent shear for each material, consistent with the ASTM Standard E 185-82. The lateral expansion curves were generated with the lower-shelf mils lateral expansion fixed at I mil and the upper-shelf mils lateral expansion not constrained (i.e., not fixed). The percent shear fracture curves for each material were generated with the lower-shelves and upper-shelves fixed at 0 and 100 respectively.

The Charpy V-notch data was entered, and the coefficients A, B, To, and C are determined by the program minimizing the sum of the errors squared (least-squares fit) of the data points about the fitted curve. Using these coefficients and the above TANH function, a smooth curve is

..-. generated through the data for interpretation of the material transition region behavior. The coefficients determined for irradiated materials in Capsule SA-60-1 are shown in Table 4-11.

The transition temperature shifts and upper-shelf energy decreases for the Capsule SA-60-1 materials with respect to the unirradiated material properties are summarized in Table 4-12.

Photographs of the Charpy V-notch specimen fracture surfaces are presented in Figures 4-6

- through 4-9.

4-4 ARAMATOME ANP 2

Li"

Table 4-1. Conditions of Palisades Capsule SA-60-1 Thermal Monitors Capsule Melt Post-Irradiation Segment Temperature Condition Middle 5360F Melted Middle 558°F Unmelted Middle 580OF Unmelted Middle 590OF Unmelted tFRAMATOME ANP 4-5

Table 4.2. Dimensions of Reconstituted Charpy Specimens for Palisades Capsule SA-60-1 ii LI LI LI a

U LI Ti a

'LI U

Weld Spcimen Width Thickness Length Notch Depth IComm Metal ID 0.394 i'0.003" 0.394 _+0.003" 2.165 +0, -0.100" 0.079 +/-+0.001" Comments Wel 11pcmn WdhTikes egh jNthDph W5214 AA4 0.394 0.395 2.160 Acceptable 2AHI 0.394 0.395 2.160 Acceptable 2AE2 0.394 0.394 2.155 Acceptable 2AH6 0.394 0.394 2.157 Acceptable AA2 0.393 0.393 2.156 Acceptable AV4 0.394 0.394 2.159 Acceptable AT2 0.393 0.394 2.158 Acceptable AR94 0.394 0.394 2.159 Acceptable AW2 0.393 0.395 2.160 Acceptable AWL 0.394 0.393 2.157 Acceptable 2AF5 0.393 0.394 2.160 Acceptable AL3 0.392 0.392 2.149 0.078 Acceptable 2AL6 0.396 0.395 2.158 Acceptable 34B009 BR91 0.395 0.395 2.160 Acceptable BW5 0.393 0.394 2.160 Acceptable BW1 0.394 0.394 2.160 Acceptable 2BKI 0.394 0.395 2.157 Acceptable BU2 0.394 0.394 2.160 Acceptable BL2 0.394 0.393 2.155 Acceptable 2BF5 0.392 0.394 2.160 0.079 Acceptable 2BK5 0.393 0.394 2.160 Acceptable BD2 0.393 0.394 2.157 Acceptable 2BJ2 0.393 0.394 2.160 Acceptable BV5 0.394 0.394 2.157 Acceptable B02 0.393 0.393 2.159 Acceptable 2BH2 0.393 0.393 2.158 Note b 2BH5 0.391 0.391 2.160 Note b 27204 PB15 0.394 0.393 2.160 Acceptable PB42 0.394 0.393 2.155 Acceptable PB91 0.394 0.394 2.160 Acceptable PB96 0.393 0.393 2.155 Acceptable PB94 0.394 0.393 2.158 Acceptable PB78 0.393 0.392 2.155 Acceptable PB95 0.393 0.394 2.155 Acceptable PB28 0.394 0.393 2.154 Acceptable PB93 0.393 0.394 2.158 Acceptable PB68 0.393 0.393 2.160 Acceptable PB92 0.392 0.392 2.158 0.08 Note b PB8I 0.392 0.392 2.155 0.08 Acceptable PB56 0.393 0.393 2.158 Acceptable Notes:

a. Notch depth only checked when depth of the notch was suspected to be changed by the machining process.

b. Specimen squareness unacceptable.

4-6 ARAMATOME ANP LI LI LI LI

Table 4-3. Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Weld Metal W5214 Test Impact Lateral Shear Specimen Temperature,

Energy, Expansion,

Fracture, ID OF ft-lbs mil AA2 74 10 4

0 AWl 129 24 15 5

AW2 154 23.5 15 15 2AF5 204 30 16 50 AL3 229 33.5 23 65 AA4 254 28 19 60 2AL6 279 43.5 35 80 2AE2 279 48.5 38 90 2AH6 329 47.5 35 90 AR94 404 51.5*

43 100 2AHI 454 55*

47 100 AV4 479 57*

46 100

Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.15

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11

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a I]

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'~**1 OI'RAMATOME ANP 4-7

1 LI a

ii a

Table 4-4. Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Weld Metal 34B009 Test Impact Lateral Shear Specimen-Temperature,

Energy, Expansion,

Fracture, ID OF ft-lbs rail BD2 74 18 8

5 BW5 129 21.5 13 30 B02 154 23.5 13 40 2BK5 179 32 18 50 2BJ2 204 36.5 25 50 2BF5 229 40 32 75 2BK1 254 46.5 41 90 BWl 279 51 42 95 BR91 329 57*

50 100 BU2 404 53*

44 100 BV5 454 58*

50 100 BL2 479 53*

49 100

Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.'1 LI tFRAMATOME ANP 4-8

Table 4-5. Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Weld Metal 27204 Test Impact Lateral Shear Specimen Temperature,

Energy, Expansion,

Fracture, ID

°F ft-lbs mil.

PB68 74 12.5 7

0 PB56 129 16.5 13 40 PB81 154 17 10 30 PB78 204 25 19 45 PB93 229 28 27 70 PB91 254 39.5 35 85 PB28 279 44.5 39 95 PB96 329 52.5*

48 100 PB94 329 52*

50 100 PB15 404 57*

53 100 PB42 454 55*

49 100 PB95 479 48.5*

43 100 LO'n I

71 I

I 7!

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71 Value used to determine upper-shelf energy with ASTM Standard E 185-82.15 (USE) in accordance OI'RAMATOME ANP 4-9

Li Fi Table 4-6. Charpy Impact Results for Palisades Capsule SA-60-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02) Heat No. A1195-1 Test Impact Lateral Shear Specimen Temperature,

Energy, Expansion,

Fracture, ID OF ft-lbs mil 02132-9 74 8

3 5

02D2-3 104 20.5 16 10 02D2-1 129 24.5 18 20 02D2-7 154 26.5 23 40 02D2-18 179 35.5 28 45 OCD2-21 204 48.5 40 70 02D2-14 229 53.5 43 65 02D2-16 229 51.5 43 70 02D2-4 254 73.5 65 80 02D2-6 279 85*

70 100 02D2-12 329

.87.5*

74 100 02D2-20 404 86.5*

77 100 Value used to determine upper-shelf energy with ASTM Standard E 185-82.'

El

[1 LI LI Li LI (USE) in accordance ARAMATOME ANP 4-10

Table 4-7. Instrumented Charpy Impact Properties for Palisades Capsule SA-60-1 Irradiated Weld Metal W5214 Propagation Maximum Load Properties Load Total Load Test Charpy Yield Properties Fast Fracture Properties Crack Arrest Properties Properties Properties Yield Flow Specimen Temp Energy Time Load Energy Time Load Energy Time Load Encrgy Time Load IEnergy Load jEnergy Time Energy Stress Stress ID

() _

(ft-lbf)

(psec)

(Ibf) I (ft-bf)

(itsec)

(lbf)

(ft-lbf)

(gsec)

(Ib1)

(ft-lbf) 1sec)

(Ibf)

(ft-lbf)

Ibf I (ft-lbf)

(1tsce)[ (ft-lbf)

(ksi)

AA2 74 10 166 4043 5.8 188 4050 7.3 188 4050 7.3 243 5

9.5 4046 2.2 243 9.5 134.8 134.9 AWl 129 24 168 3820 6.1 376 4409 20.5 376 4409 20.5 440 0

23.3 4430 2.8 440 23.3 127.3 137.1 AW2 154 23.5 176 3820 5.8 378 4382 19.7 389 4375 20.4 452 12 23 4363 3.3 452 23.0 127.3 136.7 2AF5 204 30 169 3726 5.8 418 4421 22.8 418 4421 22.8 541 1012 26.6 3409 6.3 1217 29.1 124.2 135.8 AL3 229 33.5 168 3485 5.5 439 4368 23.8 439 4368 23.8 553 1605 28.4 2762 9.6 1555 33.4 116.2 130.9 AA4 254 28 178 3643 5.8 344 4195 16.7 344 4195 16.7 460 1727 21.4 2468 11.1 1556 27.8 121.4 130.6 2AL6 279 43.5 178 3600 5.8 440 4262 23.2 528 4119 29.1 666 1999 35.5 2120 19.3 1766 42.5 120.0 131.0 2AE2 279 48.5 180 3558 5.8 440 4267 22.9 N/A N/A N/A N/A N/A N/A 0

25.3 1848 48.2 118.6 130.4 2AH6 329 47.5 172 3531 5.7 430 4168 22.4 N/A N/A N/A N/A NIA N/A 0

25.2 1778 47.6 117.7 128.3 AR94 404 51.5 168 3374 5.4 425 3997 21.4 N/A N/A NIA N/A N/A N/A 0

29.4 2056 50.8 112.5 122.8 2AHl 454 55 182 3328 5.8 444 3958 21.9 N/A N/A N/A N/A N/A N/A 0

32.8 2060 54.7 110.9 121.4 AV4 479 57 170 3188 5.2 530 3889 26.7 N/A N/A N/A N/A N/A N/A 0

28.9 2148 55.6 106.3 117.9 4*t 0

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~

)

r 1

~

r

.-*--~

I------'Ijnm r

Kl EC Ld LI]

EL I

I Table 4-8. Instrumented Charpy Impact Properties for Palisades Capsule SA-60-1 Irradiated Weld Metal 34B009 Propagation Maximum Load Properties Load Total Load Test Charpy Yield Properties Fast Fracture Properties Crack Arrest Properties Properties Properties Yield Flow ID

(')

(ft-lbf)

(le)I (Ibf)

,fsec) (1W)

(ft(b bf)-

(psec) [ (Ibf)

(ft-lbf)

(gsec) I (lbf)

(ft-lbf)

(Ibf) j (ft.lbf)

(psec)

(ft-lbf)

(ksi)

BD2 74 18 161 4016 5.6 303 4391 15.5 303 4391 15.5 357 0

17.8 4411 22 357 17.8 133.9 140.1 BW5 129 21.5 166 3710 5.4 336 4287 16.7 336 4287 16.7 448 653 19.9 3634 4.1 719 20.9 123.7 133.3 B02 154 23.5 163 3758 5.1 348 4349 17.5 348 4349 17.5 472 736 21.4 3613 5.1 738 22.6 125.3 135.1 2BKS 179 32 170 3705 5.2 442 4398 23.6 448 4388 24 567 1208 28 3181 7.7 1566 31.2 123.5 135.0 2BJ2 204 36.5 167 3678 5.2 444 4409 23.9 469 4375 25.7 592 1789 30.6 2585 12.4 1673 36.4 122.6 134.8 2BF5 229 40 178 3604 5.4 456 4338 23.9 517 4260 28.1 634 2088 33 2171 15.9 1570 39.8 120.1 132A 2BKI 254 46.5 170 3577 5.5 438 4239 23.2 524 4101 28.9 N/A N/A N/A 4101 23.3 1854 46.4 119.2 130.3 BWI 279 51 170 3432 5.5 432 4112 22.2 N/A N/A N/A N/A N/A N/A 0

28.8 2024 51.0 114.4 125.7 BR91 329 57 180 3404 5.2 454 4080 22.4 N/A NIA N/A N/A N/A NIA 0

34.4 2248 56.8 113.5 1243 BU2 404 53 164 3275 5.0 434 3931 21.4 N/A N/A N/A N/A N/A N/A 0

31.7 2018 53.1 109.2 120.1 BV5 454 58 168 3202 5.3 526 3882 26.8 N/A N/A N/A N/A NfA N/A 0

30.1 2242 56.8 106.7 118.1 BL,2 479 53 170 3213 5.1 438 3293 21.0 N/A N/A N/A N/A N/A N/A 0

31.5 2210 52.4 107.1 108.4 I-.

0 z

Table 4-9. Instrumented Charpy Impact Properties for Palisades Capsule SA-60-1 Irradiated Weld Metal 27204 Propagation Maximum Load Properties Load Total Load Test Charpy Yield Properties Fast Fracture Properties Crack Arrest Properties Properties Properties Yield Flow Speci__men

_Energy Time MLoadaxergy Time Ly TiPoerte ime Load Lo Eergy Time Loerd Stress Stress ID M

(ft-lbf)

.(psec)

(Ibf)

(ft-lbf)

(psec) Ilbf)

(ft-lbf)

(gsec)

Wbf) (ft-lb)

( ec)

(lbf)

(ft-lbf)

(1bf)

(ft-lbf)

(psec)

(ft-lbf)

(ksi)

PB68 74 12.5 158 3922 4.9 229 4080 9.6 229 4080 9.6 279 20.7 11.5 4060 1.9 279 11.5 130.7 133.4 PB56 129 16.5 173 3629 5.4 230 3813 8.9 230 3813 8.9 343 1242 12.2 2571 6.6 1005 15.5 121.0 124.0 PBSI 154 17 167 3696 5.3 248 4016 10.5 248 4016 10.5 366 1099 14.1 2916 5.9 915 16.4 123.2 128.5 PS78 204 25 167 3498 4.9 264 3841 10.8 264 3841 10.8 389 2095 16.1 1746 13.4 1480 24.2 116.6 122.3 PB93 229 28 164 3466 5.3 292 3807 13.1 292 3807 13.1 409 2040 17.8 1766 14.6 1843 27.7 115.5 121.2 PB91 254 39.5 172 3367 5.1 356 3853 16.2 404 3827 19.2 690 1746 31.9 2082 22.9 1932 39.1 112.2 120.3 PB28 279 44.5 170 3399 4.9 442 3968 21.6 N/A N/A N/A N/A N/A N/A 0

22.6 2062 44.2 113.3 122.8 PB96 329 52.5 160 3268 4.6 430 3774 20.5 N/A N/A N/A N/A N/A N/A 0

32.1 2068 52.6 108.9 117.4 PB94 329 52 168 3280 5.0 432 3809 20.7 N/A N/A N/A N/A N/A N/A 0

30.8 2086 51.5 109.3 118.1 PBI5 404 57 170 3158 4.9 532 3765 26.1 N/A NIA N/A NIA N/A N/A 0

29.8 2324 55.9 105.3 115.4 PB42 454 55 156 3225 4.3 440 3795 20.8 N/A N/A N/A NIA NJA N/A 0

33.9 2120 54.6 107.5 117.0 PB95 479 48.5 168 3036 4.9 428 3514 19.2 N/A N/A N/A N/A N/A N/A 0

29.0 2022 48.3 101.2 109.2

-I z

-1

-j 'L r

r r

Table 4-10. Instrumented Chaorly Impact Properties for Palisades Capsule SA-60-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02)

Heat No. A1195-1 Propagation Maximum Load Properties Load Total Load Test Chapy Yield Properties Fast Fracture Properties Crack Arrest Properties:

Pro m~ies Properties Yield Flow Specimen Temp Energy Time Load Energy Time Load Energy Time Load Energy Time Load Energy Load Energy Time Energy Stress Stress ID (F)

(ft-lbf)

(tsec) J (Ibf) f (ft-lbf)

(/.sec)

(Ibf)

(ft-lbf)

(1sec)

(lbf)

(ft-lb)

(sec)

([bf)

(ft-lbf)

(lbf)

(ft-lbf)

(pec)

(ft-lbf)

(ksi)

(ksi) 02D2-9 3574 1.9 182 5.7 119.6 119.6 02D2-3 104 20.5 169 3558 5.5 345 4262 17.0 345 4262 17 409 2

19.4 4260 2.4 409 19.4 118.6 130.3 02D2-1 129 24.5 159 3528 4.9 385 4292 19.6 385 4292 19.6 459 5

22.2 4287 2.6 459 22.2 117.6 130.3 02D2-7 154 26.5 173 3413 5.5 375 4186 18.4 375 4186 18.4 498 1210 22 2976 6.8 1167 25.1 113.8 126.6 02D2-18 179 35.5 160 3427 5.1 520 4428 28.7 520 4428 28.7 629 1157 32.2 3271 6.1 1310 34.8 114.2 130.9 02D2-21 204 48.5 172 3312 5.4 538 4352 29.1 614 4333 34.2 728 2116 39.1 2217 19.0 2630 48.0 110.4 127.7 02D2-14 229 53.5 184 3303 5.5 548 4313 29.0 628 4262 34.4 812 2445 43.9 1817 23.0 1916 51.9 110.1 126.9 02D2-16 229 51.5 174 3275 5.6 538 4313 28.9 592 4276 32.6 706 2519 37.9 1757 21.2 2724 50.1 109.2 126.5 02D2-4 254 73.5 168 3241 5.0 620 4349 34.1 712 4296 40.3 1176 1753 59.6 2544 37.6 3204 71.7 108.0 126.5 02D2-6 279 85 172 3192 4.7 626 4329 33.5 N/A N/A N/A NIA NIA N/A 0

49.0 3174 82.5 106.4 125.3 02D2-12 329 87.5 168 3123 4.7 538 4207 27.3 N/A N/A N/A N/A NIA N/A 0

57.5 3252 84.8 104.1 122.2 02D2-20 404 86.5 140 2916 3.6 614 4080 32.1 N/A N/A N/A N/A N/A N/A 0

51.6 3704 83.7 97.2 116.6 A..

I-.

0

>1 10

Table 4-11. Hyperbolic Tangent Curve Fit Coefficients for the Palisades Capsule SA-60-1 Surveillance Materials Material Hyperbolic Tangent Curve Fit Coefficients Description Absorbed Energy Lateral Expansion Percent Shear Fracture Weld Metal A:

28.4 A:

25.0 A:

50.0 W5214 B:

26.2 B:

24.0 B:

50.0 C:

158.1 C:

160.0 C:

80.5 TO:

188.8 TO: 239.6 TO: 214.9 Weld Metal A:

28.7 A:

25.3 A:

50.0 34B009 B:

26.5 B:

24.3 B:

50.0 C:

123.8 C:

97.6 C:

89.6 TO:

161.8 TO:

196.4 TO:

179.6 Weld Metal A:

27.6 A:

25.9 A:

50.0 27204 B:

25.4 B:

24.9 B:

50.0 C:

111.4 C:

101.8 C:

92.1 TO:

201.4 TO: 214.4 TO:

187.1 Correlation A:

44.3 A:

41.3 A:

50.0 Monitor Plate, B:

42.1 B:

40.3 B:

50.0 HSST Plate 02 C:

95.1 C:

104.9 C:

85.2 (Heat No. A1195-1)

TO:

193.0 TO: 208.6 TO:

183.7 71 71 71 71 a

I I

71 71 Li j

71

]

I]

FRAMATOME AN P 4-15

L L=

LLD.

L.72j Lý3 Lý Lm*

L=2 Table 4-12. Summary of Charpy Impact Test Results for the Palisades Capsule SA-60-1 Surveillance Materials 30 ft-lb Transition Temperature, 50 ft-lb Transition Temperature, 35 mil Lateral Expansion Material OF OF Transition Temperature, °F Upper-Shelf Energy, ft-lb Descripion Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated Decrease Weld Metal

-60.2(0) 198.8 259.0

-17.4(a) 375.6 393.0

-29.614) 310.1 339.7 102.7(s) 54.5 48.2 W5214 Weld Metal

-82.0(4 167.8 249.8

-45.0(")

298.6 343.6

-51.61a) 237.5 289.1 113.9(a) 55.25 58.65 34B009 Weld Metal

-4 1.2(b) 211.9 253.1

-6.l1b) 355.6 361.7 Not 249.4 108.4b) 53.0 55.4 27204 available.

HSST Plate 02 45.7(c) 159.4 113.7 78.31c) 206.0 127.7 Not 187.9 120.3(c) 86.3 34.0 Heat No At 195-1 available.

2 0%

(a) Data reported in AEA Technology Report AEA-TSD-0774.'

(b) Data reported in CE Report No. TR-MCC-189.16 (c) Data reported in NUREG/CR-6413. 10 Xl 0

z VU

Figure 4-1. Photographs of Thermal Monitors Removed from Palisades Capsule SA-60-1

]

3]

I q]

I I

fFRAMATOME AN P 4-17

]

71

.71 71 71 F) j 71 71 I

71 71 71 71 1]

71 El U]

71 Figure 4-2. Charpy Impact Data for Irradiated Weld Metal W5214 Lw ii.

Lw Lw a,

100 75 50 25 0

-100 100 80 60 0

100 200 300 400 Temperature, F 500 600

.2 CL x

LW 40 20 0

-10

............................ I 1 111111111,0:.....................

10 0

100 200 300 Temperature, F 400 500 600 2

120 100 Lw 0

LU ULw a.

2 80 60 40 20 0

T35&" :

-,,310.1 F Tw

+375.6 F T30:

+198.8F CvUSE:545f-00 ater eld Metal Heat Number: W5214

-100 0

100 200 300 Temperature, F 400 500 600 FRAMATOME ANP 4-18

Figure 4-3. Charpy Impact Data for Irradiated Weld Metal 34B009 0-1 U.

100 75 50 25 0-

-100 0

100 200 300 Temperature, F 400 500 600 100

.2 3 80 00 x

40 w

~20*

o

-10C

)0 l

I l

l I

I I

1 P

0 100 200 300 Temperature, F 400 500 120 100 C.0 a,

80 60F TwMLE :

+237.5 F Tso:

+298.6 F T30

+167.8F CRUSE: 5,5f-At

m=.=.....*..J

................... i..............2 1 Material:

Weld Metal Heat Number: 34B009 Boo 00

7 I

I

]

40.

20 F 0

-100 0

100 200 300 Temperature, F 400 500 6

FRAMATOME Ai 4-19

Figure 4-4. Charpy Impact Data for Irradiated Weld Metal 27204 LI IZ1 LI LI

]

LI LI LI

'LI Li LI Li Li LI "U

u-U=

Oa 100 75 50 25 0

-1 S

S C0 0

100 200 300 Temperature, F 400 500 600 100 E

e 80 60 C 40 20

~ 0*

-10 120 100 O0 I

I i

i J

I I

I 0

100 200 300 Temperature, F 400 500 600 2

T25MLE :

+253.4 F T~o:

+355.6 F TCU:

+211.

CvUSE:

53 ft-lb C

E 80 [

60 1 0

40 F 20 Material:

Weid Metal Heat Number. 27204 0

-100 0

100 200 300 Temperature, F 400 500 600 LI 4fFRAMATOME ANP 4-20

Figure 4-5. Charpy Impact Data for Irradiated Correlation Monitor Plate Material (HSST Plate 02), Heat No. A1195-1 100

f.

75 1

50 U-25 0

= 100 E

CF80 60 260 0.

1 40

- 20

-10 00 0

100 200 300 400 500 Temperature, F 600 O0 0

100 200 300 Temperature, F 400 500 600 I]

I I

I

]

21 I

]

I I]

]

Li I

'p ]

120 100 t

80

.0 60 00 LU 40 20 0 L

-100 0

100 200 300 400 500 600 Temperature, F I' FAMATOME AN 4-21

Figure 4-6. Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal W5214 I

LI LI

]

I I

LI I

LI Li LI I

7]

I

]T

$pe-dwee NA. AA2, Sperticn N*. L,*C6 SJO,[LhIm9 No. A'NV 1, Spcbimenm Nth 2AF2.2 S~demI~em r'xo AW21 Specienta No. 2MiM, Sp~drneai Speebimiat N-o. A*.,

Spe,"imCIN

o. AVW.

AFRAMATOME ANP 4-22

7' Figure 4-7. Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal 34B009 Lmu~.i.~4 Spednctin Nep 2UK1, Specimen1 Na& D2.

]

Spe

-im&

No, BW1, u

6suchrvni No. B02, Sxiiien N K 8.R9I,

.1 U

I I

I I:]

]r1

-'411tvimen INV. AwA.

"VVVFImC L-,06 Dvz',

Sperlm-n No, lops.

bplctmen no, 151L,*

j_

]

Ii f'FRAMATOME ANP 4-23

71

]

71

]

71 U]

I 71 71 El

]

I

[1 LI L]

Li I]

Figure 4-8. Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal 27204 I

Specimen No. PMR68, Specimen No. PB28.

Speciten No. PB96L Spociweit No. P581 I.Spedinen NoQ.

PB9J, Spechien hNZO. PB78.

5elntcln No. PS 15, ripecIllel! NO. 'iSJJ, Speclnewn No. P94'..

bpecwtelk NO. I5-1, SpRO[iminm NNo Pi95.

4FRAMATOME ANP 4-24

Figure 4-9. Photographs of Charpy Impact Specimen Fracture Surfaces, Correlation Monitor Plate Material (HSST Plate 02) sivednen 'N'M 02D. 2-9,

p*ewIemm~li *'tO U--DZ-E4 1 Specinen No. 02I2-3.

zilleurnen Iva, ULVA-.16, Specimen No. 02D2-I.

S5pccimce No. 021)2-7:

Spcvimen No. 0 ZD2 -06.

Specimecn No,. 02D)2-18, Speciimvu No. 02D1-1 2:.

~rcu~n 70242I

'-f1I3n L44

["0 UWA-i 1'.

fFRAMATOME ANP 4-25

5.0 Dosimeter Measurements 5.1. Introduction Three dosimeter sets were located in blocks that were installed in top, middle, and bottom positions of the Capsule SA-60-1 assembly. Each dosimeter, set consisted of dosimeters made up of shielded and unshielded cobalt/aluminum and uranium dosimeters, shielded copper, nickel, and neptunium

]

dosimeters, and unshielded iron and titanium dosimeters. The dosimeters were stored in vials identified by labels consisting of the position of the dosimeter holder block within the capsule assembly and the location from where the dosimeters where recovered.

5.2. Dosimeter Preparation Vials were prepared for the dosimeters by labeling them with identifications that indicated their types and positions in the holder blocks. For example, the one top block shielded cobalt/aluminum dosimeter was labeled Palisades T (or TOP) Sh Co/Al. The analyte nuclides were verified during gamma scanning.

]

The dosimeter wires were washed in reagent grade acetone and blotted dry with a laboratory towel.

Each dosimeter wire was then measured with a certified micrometer caliper and weighed on a certified analytical balance. Each wire was then mounted in the center of a PetriSlideTO with double-sided tape.

5.3. Quantitative Gamma Spectrometry Several of the dosimeters, placed in the PetriSlideTM, were given a 300 second preliminary count on the 31% PGT gamma spectrometer. This provided information to best judge the distance at which to count the dosimeter to obtain a minimum of 10,000 counts in the photopeak of interest while keeping the counter dead time below 15%. It also provided qualitative identification of the dosimeters. This identification was made from the presence of the gamma rays in Table 5-1. The spectra were used to confirm the identities of the dosimeters.

The spectra were then measured quantitatively at the appropriate counting positions and for the appropriate count times determined from the preliminary counts.

.1 5-1 ER-AMATOMEANP

F]

Li

]

IL J l Jl El UF 5.4. Dosimeter Specific Activities The associated elemental weight fractions of the dosimeters and the isotopic fractions of the target nuclides are listed in Table 5-2. The isotopic fractions of the target nuclides were obtained from the CRC Handbook of Chemistry and Physics, 632d Edition. 7 The dosimeter specific activities were calculated by dividing the corrected activity of the analyte nuclide by the target nuclide mass, and the results are shown in Table 5-3.

The shielded uranium dosimeter identified as "Palisades, SA-60-1 161T Sh U" is considered to be invalid since this dosimeter has a bright shiny color and a non-wire shape. This non-wire shape was different from the other shielded uranium dosimeters removed from the other capsule locations (i.e., compartments 164T and 167T). Photographs of the shielded uranium dosimeters removed from compartments 161T and 164T are shown in Figure 5-1.

5-2 ARAMATOME AN P

Table 5-1. Quantifying Gamma Rays Dosimeter Analyte Iron 54Mn @ 834 keV from 54Fe Co/Al 6°Co @ 1332 keV from "9Co Nickel 58Co @ 811 keV from 51Ni Titanium 4Sc@ 1121 keV from 4Ti Copper

'"Co @ 1332 keV from 63Cu, very low activity compared to Co wires, wire has coppery color 237 Np 137Cs @ 662 keV 238u

' 37Cs @ 662 keV I FRAMATOME ANP 5-3

1 LI I

I Li LI

ii I

I LI

]

El

[1 I

LI Li ii]

LI Table 5-2. Isotopic Fractions and Weight Fractions of Target Nuclides OI'RAMATOME ANP 5-4

Table 5-3. Specific Activities for Palisades Capsule SA-60-1 Dosimetry Specific Dosimeter Shielded Target Analyte Activity

% Error Identification (Yes/No)

Nuclide Nuclide (jtCi/gm Target)

(%)

-I-Palisades, SA-60-1 161T Sh Co Yes Co-59 Co-60 3.638E+04 7-51 Palisades, SA-60-1 161T Co No Co-59 Co-60 1.065E+05 6.93 Palisades, SA-60-1 164T Sh Co Yes Co-59 Co-60 3.760E+04 6.58 Palisades, SA-60-1 164T Co No Co-59 Co-60 9.600E+04 6.70 Palisades, SA-60-I 167T Sh Co Yes Co-59 Co-60' 3.489E+04 6.64 Palisades, SA-60-I 167T Co No Co-59 Co-60 9.682E+04 6.75 Palisades, SA-60-1 161T Sh Cu Yes Cu-63 Co-60 14.07 5.24 Palisades, SA-60-1 164T Sh Cu Yes Cu-63 Co-60 13.87 5.25 Palisades, SA-60-1 167T Sh Cu Yes Cu-63 Co-60 13.79 5.24 Palisades, SA-60-1 161T Sh Ni Yes Ni-58 Co-58 7458 5.24 Palisades, SA-60-1 164T Sh Ni Yes Ni-58 Co-58 7184 5.24 Palisades, SA-60-1 161T Sh Ni Yes Ni-58 Co-58 7238 5.24 Palisades, SA-60-1 161T Fe No Fe-54 Mn-54 4921 5.68 Palisades, SA-60-1 164T Fe No Fe-54 Mn-54 4886 5.77 Palisades, SA-60-1 167T Fe No Fe-54 Mn-54 4970 5.68 Palisades, SA-60-1 161T Ti No Ti-46 Sc-46 1165 5.89 Palisades, SA-60-1 164T Ti No Ti-46 Sc-46 1173 6.33 Palisades, SA-60-1 167T Ti No Ti-46 Sc-46 1168 6.12 Palisades, SA-60-1 161T S U Yes U-238 Cs-137 NA Palisades, SA-60-1 161T U No U-238 Cs-137 27.81 8.11 Palisades, SA-60-1 164T Sb U Yes U-238 Cs-137 22.71 8.13 Palisades, SA-60-1 164T U No U-238 Cs-137 NA*

NA*

Palisades, SA-60-1 167T Sh U Yes U-238 Cs-137 22.41 8.11 Palisades, SA-60-1 167T U No U-238 Cs-137 27.97 8.07 Palisades, SA-60-1 161T Sh Np Yes Np-237 Cs-137 145.7 8.08 Palisades, SA-60-1 164T Sh Np Yes Np-237 Cs-137 2263*

8.16*

Palisades, SA-60-1 167T Sh Np Yes Np-237 Cs-137 765.3*

8.16*

I 3]

I Li Li I

LI I

ii I]

Data were not available due to the fact that only a small amount of the dosimeter was recovered and the uncertainty of the dosimeter weight measurement was high (see Reference 18).

]

5-5 A*RAMATOME ANP j

L'i1 Li

[1 El Li

[3 El 3

Li El LI.

L]

LI Ii LI LI III Li Li Figure 5-1. Photographs of Shielded Uranium Dosimeters Removed from Capsule SA-60-1 Shielded Uranium Dosimeter Removed from Compartment 161T Shielded Uranium Dosimeter Removed from Compartment 164T FRAMATOME ANP 5-6

6.0 Summary of Results The investigation of the post-irradiation test results of the materials contained in the first supplemental surveillance capsule, Capsule SA-60-1, removed from the Consumers Power Company Palisades reactor vessel, led to the following conclusions:

1. Observation of the Capsule SA-60-1 thermal monitors indicated that the irradiated

]

test specimens were exposed to a maximum irradiation temperature no greater than 5580F.

2. Thirty-six pre-machined irradiated 18mm Charpy inserts were successfully reconstituted and machined to Type A Charpy impact specimens. Upon completion of the machining of the reconstituted Charpy specimens, the specimens were impact tested.

3. The 30 ft-lb transition temperature for the weld metal W5214 increased 259.0'F, and the 50 ft-lb transition temperature increased 393.0°F. In addition, the CVUSE for this material decrease 46.9%.

4. The 30 ft-lb transition temperature for the weld metal 34B009 increased 249.8°F, and the 50 ft-lb transition temperature increased 343.6°F. In addition, the CVUSE for this material decrease 51.5%.

2

5. The 30 ft-lb transition temperature for the weld metal 27204 increased 253. 1°F, and the 50 ft-lb transition temperature increased 361.7°F. In addition, the CRUSE for this material decrease 51.1%.

]

6. The correlation monitor plate demonstrated similar behavior with an increase in the 30 ft-lb transition temperature of 113.7°F, and an increase in the 50 ft-lb transition temperature of 127.7°F. The percent decrease in the CVUSE for this material is 28.3%.

1 6-1

/RAMATOME AMPj

LI LF1 7.0 Certification The'specimens obtained from the Consumers Energy's Palisades first supplemental surveillance capsule (Capsule SA-60-1) were tested and evaluated using accepted techniques and established standard methods and procedures in accordance with the requirements of 10 CFR 50, Appendices G and H.

M. J.

eVan, Engineer IV Date Materials & Structural Analysis Unit This report has been reviewed for technical content and accuracy.

Materials & Structural Analysis Unit Verification of independent review.

I

i.

ore, Manager D e Materials & Structural Analysis Unit This report is approved for release.

D. L. Howell Program Manager Date YFFRA MATO ME T& CH."OfL 00It 7-1

Revision 1 The revisions to this report were made as stated in accordance with the standard methods and procedures for the original report.

.11 j]

1 M. J. 15eVan, Engineer IV Date Materials & Structural Analysis Unit This report has been reviewed for technical content and accuracy.

.H: Xu, Ergineyf II Materials & Structural Analysis Unit Verification of independent review.

3 3

~1 I

11 I

I I

I K. E. Moore, Date Materials & Structural Analysis Unit This report is approved for release.

D. L. Howell Program Manager v

Date fFRAMATOME T K CI1440LOO I

S 7-2

r]

Revision 2 The revisions to this report were made as stated in accordance with the standard methods and procedures for the original report.

M. J. DeVan, Supervisory Engineer Date Materials & Structural Analysis Unit This report has been reviewed for technical content and accuracy.

/K. E. Moore, Advisory Engineer Date Materials & Structural Analysis Unit F]

113 LI LI El El I]

LI

[11

[I

[1

[I LI LI Verification of independent review.

A. D. McKim, StUnt Manager Date Materials & Struclu 'al Analysis Unit This report is approved for release.

D. L. Howell Program Manager Szz2o I Date fFRAMATOME ANP 7-3

ri JI 8.0 References

1. Code of Federal Regulation, Title 10, Part 50, "Domestic Licensing of Production and C]

Utilization Facilities, " Appendix G. Fracture Toughness Requirements.

2. Code of Federal Regulation, Title 10, Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix H, Reactor Vessel Material Surveillance Program Requirements.

3. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, "Nuclear Power Plant Components, " Appendix G, Protection Against Nonductile Failure, 1989 Edition.

C4.

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XM, "Rules for biservice Inspection of Nuclear Power Plant Components," Appendix G. Fracture Toughness Criteria for Protection Against Failure, 1989 Edition.

5. ASTM Standard E 208-81, "Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels," American Society for Testing and Materials, Philadelphia, Pennsylvania.

6. R. C. Groeschel, "Summary Report on Manufacture of Test Specimens and Assembly of Capsules for Irradiation Surveillance of Palisades Reactor Vessel Materials," CE Report No. P-NLM-019, Combustion Engineering, Inc., Windsor, Connecticut, April 1, 1971.

7. ASTM Standard E 185-66, "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors, " American Society for Testing and Materials, Philadelphia, C]

Pennsylvania.

8. G. Gage, R. J. McElroy, and C. A. English, "Evaluation of Weldmetalsfrom Retired I-Palisades Steam Generators," AEA-TSD-0774, AEA Technology, November 23, 1995.

9. Letter from J. R. Kneeland to D. L. Howell (FTI), FTG Document No. 38-1247683-00, Creleased March 9, 1999.

10. J. A. Wang, "Analysis of the Irradiation Data for A302B and A533B Correlation Monitor Materials," NUREG/CR-6413 (ORNLTTM-13133), Prepared for U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tennessee, April 1996.

11. Letter from R. A. Fenech (CPCo) to NRC, "Docket 50-255 - License DPR Palisades Plant Response to Request for Additional Information, Revision 1 - 10 CFR 50.61 Screening Crtierion (RE: TAC No. M8322 7)," dated December 28, 1994.

8-1 A RAMATOME ANP

12. ASTM Standard E 23-9 1, "Standard Test Methods for Notched Bar Impact Testing of Metallic Materials," American Society for Testing and Materials, Philadelphia, Pennsylvania.

13. L. B. Gross, "Verification of Reconstituted Charpy V-Notch Test Values, " BAW-2184, B&W Nuclear Technologies, Inc., Lynchburg, Virginia, May 1993.

14. ASTM Standard E 1253-88, "Standard Guide for Reconstitution of Irradiated Charpy Specimens," American Society for Testing and Materials, Philadelphia, Pennsylvania.

15. ASTM Standard E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706 (IF)'" American Society for Testing and Materials, Philadelphia, Pennsylvania.

16. "Baseline Charpy Test Data for Weld Heat No. 27204," CE Report No. TR-MCC-189, Combustion Engineering Inc., Windsor, Connecticut.

17. R. C. Weast and M. J. Astle, Eds., "CRC Handbook of Chemistry and Physics, 6 3rd Edition,"

CRC Press, Boca Raton, Florida, 1982.

18. K. Y. Hour, "Evaluation of Consumers Power Company's Palisades SA-60-1 Capsule,"

00:475-0165-01:02 (FTG Document No. 31-1023260-01), B&W Services, Inc., Lynchburg, Virginia, May 1999.

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I A.1.

Palisades Reactor Pressure Vessel The Palisades reactor pressure vessel was fabricated by Combustion Engineering, Inc. (CE). The Palisades reactor vessel beltline region consists of two shells, containing six heats of base metal plate, six longitudinal weld seams, and two circumferential weld seams. Table A-1 presents a description of the Palisades reactor vessel beltline materials including their copper and nickel chemical contents and their unirradiated mechanical properties. The locations of the materials within the reactor vessel beltline region are shown in Figure A-1.

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Table A-1. Description of the Palisades Reactor Vessel Beltline Region Materials Chemical Fabricator Comp osition Toughness Properties Material Code eaMaterial~o Material~p RgnBeltlineoato

wtCu, Ni,wt 30 ft-lb,F 50 ft-lb,F 35 WIE,

CRUSE, TF t-bs

',_ RTNDTF Heat No.

Type J Region Location wt%

wt%

F F

F___

F__

F_

D-3803-1 C1279-3 A 302 Gr. B Mod.

Intermediate Shell 0.24 0.51 102

-30

-5 D-3803-2 A0313-2 A 302 Gr. B Mod.

Intermediate Shell 0.24 0.52 87

-30

-30 D-3803-3 C1279-1 A 302 Gr. B Mod.

Intermediate Shell 0.24 0.50 102

-30

-5 D-3804-1 C1308-1 A 302 Gr. B Mod.

Lower Shell 0.19 0.48 72

-30 0

D-3804-2 C1308-3 A 302 Or. B Mod.

Lower Shell 0.19 0.50 76

-40

-30 D-3804-3 B5294-2 A 302 Gr. B Mod.

Lower Shell 0.12 0.55 73

-30

-25 2-112A, B, C W5214/

ASA Weld/

Intermediate Shell 0.213 1.01 118

--56 3617*

Linde 1092 Longitudinal Welds 9-112 27204/

ASA Weld/

Intermediate to Lower 0.203 1.018 98

-56 3687*

Linde 124 Shell Circ. Weld 3-112A, B, C

34B009, ASA Weld/

Lower Shell 0.192/

0.98/

111/

-56 W5214/

Linde 1092 Longitudinal Welds 0.213 1.01 118 3692*

2

Weld wire heat number and flux lot identifiers.

0 V:

Figure A-1. Location and Identification of Materials Used in the Fabrication of Palisades Reactor Pressure Vessel REACTOR VESSEL BELTLINE MATERIALS NOITSHOWN INTERMEDIATE SHELL WELD SEAM No. 2-112C LOWER SHELL WELD SEAM No. 3-112B WELD SEAM No. 3-112C PLATE No. 0-304-0 42" ID OUTLET NOZZLE UPPER TO INTERMEDIATE SHELL GIRTH SEAM WELD No. 8-112 INTERMEDIATE SHELL PLATE No. D.3803.1 II Z]

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30" ID INLET NOZZLE INTERMEDIATE SHELL LONGITUDINAL WELD SEAM No. 2-112B INTERMEDIATE SHELL PLATE No. 0-3803-3 INTERMEDIATE TO LOWER SHELL GIRTH SEAM WELD No. 9-112 LOWER SHELL PLATE No. D-3804-2 INTERMEDIATE SHELL LONGITUDINAL WELD SEAM No. 2-112A INTERMEDIATE SHELL PLATE No. D-3503-2 LOWER SHELL PLATE No. D-3804-1 LOWER SHELL LONGITUDINAL WELD SEAM No. 3.112A REACTOR VESSEL a

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APPENDIX B Instrumented Charpy V-Notch Specimen Test Results Load-Time Traces AF-RAMATOME ANP B-1

Figure B-1. Load-Time Trace for Charpy V-Notch Impact Specimen AA2 PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECDIEN AA2 MOW 4=

3WN MO

-400 ii TI TI I

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Figure B-3. Load-Time Trace for Charpy V-Notch Impact Specimen AW2 PROJ. NO. 0165 QA NO. 95006 LOAD - TIME TRACE FOR SPECIMEN ;.,*e..

F(" ý'tll C3 CL

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-lo

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NO. 0165 GA NO. 98006 LOAD - TINE TRACE FOR SPECIMEN HAF M-IAf0* r '1's se Al No 200

-. 75

.0498

.8495 1.549 2.44g MILLISECONDS 3.249 O

RAMATOME ANP B-3

Figure B-5. Load-Time Trace for Charpy V-Notch Impact Specimen AL3 PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN -PA6 AL q, I o' I

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C. 200

, 14W

>00

-M0

-. 75

.0498

.8498

1.B49 2.449 MILLI.ECON13S 3.249 Figure B-6. Load-Time Trace for Charpy V-Notch Impact Specimen AA4 PROJ.

NO. 0155 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN PAA4-A A*

4f11 NE.

MW 4400 sm

-I 2OO A00

-400

-000 C

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Figure B-7. Load-Time Trace for Charpy V-Notch Impact Specimen 2AL6

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U PROJ. NO. 0165 0A NO. 98006 LOAD - TINE TRACE FOR SPECIMEN PPk& -ALb 1't' ý'kiw MM C-ii CL d

.C'4

_JQ 200

_4w

,.t

3.,99 4.799 6.398 1MLLISECCNDS

7. 998 Figure B-8. Load-Time Trace for Charpy V-Notch Impact Specimen 2AE2 PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN 1 PAEF8 E r?" 'kPi Ii.

MW 44M MG MW

-400

-1.5 1.699 3.M99 MILL'rECOCCS

4. B96 5.498 Ui

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Figure B-9. Load-Time Trace for Charpy V-Notch Impact Specimen 2AH6 PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN a.

/A",'

j jt4 +21(1 I!'7 3=

-4W

-1.5

.0995 1,599 3.299 4.898 MILLISECONDS 5.499 Figure B-10. Load-Time Trace for Charpy V-Notch Impact Specimen AR94 I

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FROJ. NO. 0165 GA NO. 98005 LOAD - TIME TRACE FOR SPECIMEN P"4-01 A

r&9 V",4

'7 3w 1MW M9

-. 75

.0495

.8496 2.49 2.449 MILLISECGODB 3.249 fFRAMATOME ANP B-6

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Figure B-11. Load-Time Trace for Charpy V-Notch Impact Specimen 2AHl PROJ.

NO. 0165 DA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN -P

-AU I yfs" '9"1 Si 1400

-o M00

-1.5

.0998 1.299 3.299

4. B98 i1iLUiSECONDS 6.498 Figure B-12. Load-Time Trace for Charpy V-Notch Impact Specimen AV4 PROJ. NO. 0165 GA NO. 98005 LOAD - TIME TRACE FOR SPECIMEN P-V4 Avf 0'b i"

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Figure B-13. Load-Time Trace for Charpy V-Notch Impact Specimen BD2 PROJ. NO. 0165 GA NO. 58008 LOAD - TINE TRACE FOR SPECIMEN BD2 ii L40 svo 200

-. 75

.0498

.8498 1.U49 2.449 MILLISECONDS 3.249 Figure B-14. Load-Time Trace for Charpy V-Notch Impact Specimen BW5

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PROJ. NO. 0155 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN-PSNI#-- gt r

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-. 78

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.8496 1.549 2.442 MILLISECONDS 3.249 fFRAMATOME AN P B-8

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, qPfP Z-1 3M 14W so

_4W

.0498

.8498 I.B49 2.449 MILLISECONDS 3.249 Figure B-16. Load-Time Trace for Charpy V-Notch Impact Specimen 2BKs PROJ. NO. 0165 GA NO. 98006 LOAD - TINE TRACE FOR SPECIMEN PP9 (

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1 1( "'1I' 5M0 C

9J 0

.7898 1.0 2.399

3. 390 MILL!SECOND5

3. 99 I'

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Figure B-17. Load-Time Trace for Charpy V-Notch Impact Specimen 2BJ2 PRDj. NO. 0165 9h NO. 98006 LOAD - TINE TRACE FOR SPECIHEN PfB

>61X KqF 044j Ii 3=O 5"

WO0 200

-400

-. 75

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.8495

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Figure B-18. Load-Time Trace for Charpy V-Notch Impact Specimen 2BF5 PROJ. NO. 0165 GA NO. 98006 LOAD - TINE TRCE FOR SPECINEN P8F6 A4Si rf"t bi Ri 2W 4400 No

-4K

-. 75

.049B

.8498 1.549 2.449 KILLISECODS 3.249

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ILI Figure B-19. Load-Time Trace for Charpy V-Notch Impact Specimen 2BKI PROJ. NO. 0165 GA NO. 98006 LOAD TiHE TRACE FOR SPECINEN -PHi "_4KI

ý10 ý-M 17 4400 MW 1400 4000

.0996 1.699 3.289 MILLISEOMNDS

5. 498 Figure B-20. Load-Time Trace for Charpy V-Notch Impact Specimen.BWl 1 -

PROJ. NO. 0165 GA NO. 96006 LOAD - TIME TRACE FOR SPECIMEN *i

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rj fj Li j

MW 2M 200

-ft0

-55

.0995 1.699 3.299 H41LLISECWES 8.490 IFRAMATOME ANP B-I1

Figure B-21. Load-Time Trace for Charpy V-Notch Impact Specimen BR91 PROJ. NO. 0155 OA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN BR91 I

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Um No am

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.0995 1.599 3.299 4.B98 MILLISECOICS 5.498 Figure B-22. Load-Time Trace for Charpy V-Notch Impact Specimen 1BU2 PROJ. NO. 0165

[*A NO. 98006 LOAD

- TIME TRACE FOR SPECIMEN4-P*. *J-I

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.0995 1.E99 3.299 4.898 MILLISECON13S 8.498 AIFRAMATOME AN P B-12 Ii

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TIME TRACE FOR SPECIMEN 9BYf-SIN

"'*M ""

1WN

-WO

-15 098 1.819 3.299 4.B989 MILLISECONDS B.498 Figure B-24. Load-Time Trace for Charpy V-Notch Impact Specimen BL2 PROJ. NO. 0165 QA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN-NRL2 E-.

lqt4

'7 Ii 44W sm C14W Noo no

-4W

-1.5

.0995 1.599 3.299 4.998 MILLISECONDS 5,499 fRAMATOME ANP B-13

Figure B-25. Load-Time Trace for Charpy V-Notch Impact Specimen PB68 PROJ. NO. 0165 GA NO. 9B006 LOAD - TIME TRACE FOR SPECIMEN PB68 U

I flu MW 4400

=0

-,J

-low

-. 75

.0496

.8496 1,549 MILL!SECONDB

2. 4A9 3.249 Figure B-26. Load-Time Trace for Charpy V-Notch Impact Specimen PB56 I

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3Mm 220) 2w0

-. 75

.0495

.8498 1.149 2.449 04ILLISECOM1S 3.249 fFRAMATOME AN P B-14

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U.'

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-. 75

.0498

.8495 1.049 2.449 14ILLIGECDMVS 3.249 Figure B-28. Load-Time Trace for Charpy V-Notch Impact Specimen PB78 PM,.

NO. 0165 DA NO. 99008 LOAD - TIME TRACE FOR SPECIMEN P878 3$ii to 2M 41Mo

_4w

-. 75

.0499

.8499 1.549 2.449 MILLISEMNOIS 3.249 fFRAMATOME AN P B-15

Figure B-29. Load-Time Trace for Charpy V-Notch Impact Specimen PB93 PROJ. NO. 0165 G1 NO. 98006 LOAD - TIME TRACE FOR SPECIMEN PB93 44W ODi 2w

-lo

-. 73

.0498

.8495 1.B49 2.449 3.249 MILLISECONDS Figure B-3D. Load-Time Trace for Charpy V-Notch Impact Specimen PB91 PROJ. NO. 0165 GA NO. 98006 LOAD

- TIME TRACE FOR SPECIMEN PB9I I

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'7 BOW 44M am 0GO S1400

-j 000 MO

-4W0

-I 095 1.699 3.299 4.1998 MILLISECONDS 6.498

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IL Figure B-31. Load-Time Trace for Charpy V-Notch Impact Specimen PB28 PROJ. NO. 0165 Gh NO. 98006 LOAD - TIME TRACE FOR SPECIMEN PB28 4400

=0(X Ii-g 14W

.J 2M 2MO

-4W

]

7]

ar ra

-1.6

.0998

1. B99 3.299 4.898 MILLISECON1D 6.498 Figure B-32. Load-Time Trace for Charpy V-Notch Impact Specimen PB96 PPOJ. NO, 0155 GA NO. 9806 LDAD - TIME TRACE FOR SPECIMEN PB96 BUG ow Mc 2M 2w0

_4w2

1.

3.199 4.799 5.399 MILLISEcCONS 7.999 L J I,

RAMATOME ANP B-17

Figure B-33. Load-Time Trace for Charpy V-Notch Impact Specimen PB94 PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN PB94 me Ii, Ii 326M U.

-I BoO tOO

.-4A I

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.0295 1.599 3.299 4.998 MILLISECONDS 5.499 Figure B-34. Load-Time Trace for Charpy V-Notch Impact Specimen PB15 PROJ. NO. 01685 A NO. 98005 LOAD - TIME TRACE FOR SPECIMEN PBi5 IT Ii MW 4400 am

-3m

.L B. 496

-1

-1.5

.098 1.699 3.290 4.9He MILLISECONDS I

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Figure B-35. Load-Time Trace for Charpy V-Notch Impact Specimen PB42 PROJ. NO. 0255 CA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN PB42 as MOW 4M0 no A

AJ

-1.5

.0998 1.899 3.299 4.509 MILLISECONDS 5.490 Figure 13-36. Load-Time Trace for Charpy V-Notch Impact Specimen.PB95 PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN PB95 C-asii 2Mc am

-1.5

.0998 1.599 3.299 4.096 MILLISECWS C5 6.498 Cf

RAMATOME AN P B-19

Figure B-37. Load-Time Trace for Charpy V-Notch Impact Specimen O2D2-9 PROJ.

NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN 02D29 200

-4m

-1000 t

I i

-. 75

.0495

.849B 1.549 2.449 3.249 MILLISECONDC Figure B-38. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-3 PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN 02023

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Figure B-39. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-1 PROJ. NO, 0165 GA NO. 98905 LOAD - TINE TRACE FOR SPECIMEN 02021

,,I

-. 75

.0495

.8495

".549 2.449 MILL*SECONDS 3, 249 Figure B-40. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-7 PROJ. NO. 0165 GA NO. 98006 LOAD - TINE TRACE FOR SPECIMEN 02D27 Ii.Pu 14

_MO

-. 771

.0280 a82ap

1. 528 2.428 MILLISECONDS 3 228 IfFRAMATOME ANP B-21

Figure B-41. Load-Time Trace for Charpy V-Notch Impact Specimen O2D2-18 PROJ. NO. 0155 GA NO. 95006 LOAD - TIME TRACE FOR SPECIMEN 02112i8 Is Ii.

am 20 a 143

_j

-. 75

.049a

.8495

1. S49 2.44A HILLISECONOS 3.249 Figure B-42. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-21 I

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Il PROJ. NO. 0i65 GA NO. 98006 LOAD - TINE TRACE FOR SPECIMEN 021221 moo 4M

moo 4MO 23

-1.5

.0998 1.599

3. 299 4.990 4ILLISECONDS 5.498 fFRAMATOME ANP B-22

Figure B-43. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-14 PROJ. NO. 0165 GA NO. 9B006 LOAD - TIME TRACE FOR SPECIMEN 0U214 8O00

-100_

I.

I

-15 0595 1,599 3.299 4.e99 6.4913 MILLISECONDS:

Figure B-44. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-16 R0OJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN O2B~f6 St Ii 4400 no

-400

1.

657 3.257 4.B56 MILLISECONDS 6.45, fFRAMATOME ANP B-23

Figure B-45. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-4 PROJ. NO. 0165 9A NO. 98006 LOAD - TINE TRACE FOR SPECIMEN 02024 SC 3s 44W 2M 2X0

-4W

-1.542

.0575 1.657 3.257 4.855 MILL ISECONOS 5.450 Figure B-46. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-6 I

PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN 020*3 K

Mu 44M 20W No

-4M0

-1.542

.0575 1.*57 3.257 4.858 MILLISECONDS 5.455 FRAMATOME ANP B-24

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Figure B-47. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-12 PROJ. NO. 0165 GA NO. 98006 LOAD - TIME TRACE FOR SPECIMEN 02W2O2 Iiz CL

-400

-1.542

.0575 1,557 3.257 4.956 M4ILLISECONDS 5.45S Figure B-48. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-20 PROJ. NO. 0165 GA NO. 88006 LOAD - TIME TRACE FOR SPECIMEN 02D220 Ii.1/4 200

-W

-1.5

,0995 1.B99 3.299 4.B98 MILLISECONDS 5.498 Li C]

El OIFRAMATOME AN P B-25

ATTACHMENT 2 TEST RESULTS CAPSULE SA-240-1 BAW-2398 MAY 2001 84 Pages Follow

BAW-2398 May 2001 Test Results of Capsule SA-240-1 Consumers Energy Palisades Nuclear Plant

-- Reactor Vessel Material Surveillance Program --

by M. J. DeVan FfI Document No. 77-2398-00 (See Section 7 for document signatures.)

Prepared for Consumers Energy Prepared by Framatome ANP, Inc.

3315 Old Forest Road P. 0. Box 10935 Lynchburg, Virginia 24506-0935 fRAMATOME AMP

Executive Summary This report describes the results of the tests performed on the specimens contained in the second supplemental reactor vessel surveillance capsule (Capsule SA-240-1) from the Consumers Energy Palisades Nuclear Plant. The objective of the program is to monitor the effects of neutron irradiation on the mechanical properties of the reactor vessel materials by testing and evaluation of Charpy impact specimens.

Supplemental Capsule SA-240-1 was removed from the Palisades reactor vessel at the end-of-cycle 14 (EOC-14) for testing and evaluation. The test specimens included modified 18mm Charpy V-notch inserts for three weld metals fabricated with weld wire heats W5214, 34B009, and 27204 and standard Charpy V-notch specimens fabricated from the correlation monitor plate material, HSST Plate 02. The weld metal Charpy inserts were reconstituted to full size Charpy V-notch specimens. The reconstituted weld metals along with HSST Plate 02 material were Charpy-impact tested. The results of these tests are presented in this document.

f MRAMATOME ANP

Acknowledgement The author would like to thank Kevin Hour of the BWXT Services, Inc. Lynchburg Technology Center for his efforts and expertise in specimen testing and Hongqing Xu of Framatomne ANP, Inc. for his work on the Charpy specimen reconstitution. The efforts by both these individuals contributed greatly to the success of this project.

i FRAMATOME ANP iii

Table of Contents Page 1.0 Introduction......................................................................................................................

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

2-1 3.0 Surveillance Program Description...................................................................................

3-1 4.0 Post-Irradiation Testing....................................................................................................

4-1 4.1.

Visual Exam ination and Inventory.......................................................................

4-1 4.2.

Therm al M onitors.................................................................................................

4-1 4.3.

Tension Test Specimens.......................................................................................

4-1 4.4.

Reconstitution of Irradiated Charpy Inserts.........................................................

4-1 4.5.

Charpy V-Notch Im pact Test Results..................................................................

4-3 5.0 Dosim eter M easurem ents.................................................................................................

5-1 5.1.

Introduction.....................................................................................................

5-1 5.2.

Dosim eter Preparation..........................................................................................

5-1 5.3.

Quantitative Gam m a Spectrom etry......................................................................

5-1 5.4.

Dosim eter Specific Activities...............................................................................

5-2 6.0 Sum m ary of Results.........................................................................................................

6-1 7.0 Certification......................................................................................................................

7-1 8.0 References........................................................................................................................

8-1 Appendices A.

Reactor Vessel Surveillance Program Background Data and Information.................

A-1 B.

Instrumented Charpy V-Notch Specimen Test Results Load-Time Traces................ B-1 ivRAMATOME ANP

List of Tables Table Page 3-1.

Test Specimens Contained in Palisades Capsule SA-240-1.............................................

3-3 3-2.

Chemical Composition of Palisades Capsule SA-240-1 Surveillance Materials............. 3-4 3-3.

Heat Treatment of Palisades Capsule SA-240-1 Surveillance Materials......................... 3-5 4-1.

Conditions of Palisades Capsule SA-240-1 Thermal Monitors.......................................

4-5 4-2.

Dimensions of Reconstituted Charpy Specimens for Palisades Capsule SA-240-1........ 4-6 4-3.

Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Weld Metal W 52 14..............................................................................................................................

4-7 4-4.

Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Weld Metal 34B 00 9.............................................................................................................................

4 -8 4-5.

Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Weld Metal 27 204................................................................................................................................

4 -9 4-6.

Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02) Heat No. Al 195-1.........................................

4-10 4-7.

Instrumented Charpy Impact Properties for Palisades Capsule SA-240-1 Irradiated W eld M etal W 5214...................................................................................................

4-l1 4-8.

Instrumented Charpy Impact Properties for Palisades Capsule SA-240-1 Irradiated W eld M etal 34B 009.......................................................................................................

4-12 4-9.

Instrumented Charpy Impact Properties for Palisades Capsule SA-240-1 Irradiated W eld M etal 27204..........................................................................................................

4-13 4-10. Instrumented Charpy Impact Properties for Palisades Capsule SA-240-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02) Heat No. Al 195-1...................... 4-14 4-11.

Hyperbolic Tangent Curve Fit Coefficients for the Palisades Capsule SA-240-1 Surveillance M aterials....................................................................................................

4-15 4-12. Summary of Charpy Impact Test Results for the Palisades Capsule SA-240-1 Surveillance M aterials....................................................................................................

4-16 5-1.

Q uantifying G am m a R ays................................................................................................

5-3 5-2.

Isotopic Fractions and Weight Fractions of Target Nuclides...........................................

5-4 5-3.

Specific Activities for Palisades Capsule SA-240-1 Dosimetry......................................

5-5 A-1.

Description of the Palisades Reactor Vessel Beltline Region Materials......................... A-3 v

ARAMATOME AN P

List of Figures Figure Page 3-1.

Reactor Vessel Cross Section Showing Location of Palisades Original RVSP C apsules...........................................................................................................................

3-6 3-2.

Reactor Vessel Cross Section Showing Location of Palisades Supplemental Surveillance C apsules......................................................................................................

3-7 3-3.

Supplemental Surveillance Capsule Assembly Showing Location of Specimens and M onitors....................................................................................................................

3-8 3-4.

Temperature, Flux, and Tensile (TFT) Capsule Compartment Assembly....................... 3-9 3-5.

Standard Charpy Impact and Flux Capsule Compartment Assembly (Two Per C apsule)............................................................................................................................

3-9 3-6.

Standard Charpy Impact Capsule Compartment Assembly...........................................

3-10 3-7.

Typical 18mm Charpy Impact Capsule Compartment Assembly (Three Per C apsule...........................................................................................................................

3-10 4-1.

Photographs of Thermal Monitors Removed from Palisades Capsule SA-240-1.......... 4-17 4-2.

Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Weld Metal W 52 14............................................................................................................................

4-18 4-3.

Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Weld Metal 34B 009...........................................................................................................................

4 -19 4-4.

Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Weld Metal 27 204..............................................................................................................................

4 -20 4-5.

Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Correlation Monitor Plate Material (HSST Plate 02), Heat No. A 1195-1.......................................

4-21 4-6.

Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal W5214 from Palisades Capsule SA-240-1.................................................

4-22 4-7.

Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal 34B009 from Palisades capsule SA-240-1.................................................

4-23 4-8.

Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal 27204 from Palisades Capsule SA-240-1...................................................

4-24 4-9.

Photographs of Charpy Impact Specimen Fracture Surfaces, Correlation Monitor Plate Material (HSST Plate 02) from Palisades Capsule S A -240-I........................................................................................................................

4-25 A-1.

Location and Identification of Materials Used in the Fabrication of Palisades R eactor Pressure V essel..................................................................................................

A -4 B-I.

Load-Time Trace for Charpy V-Notch Impact Specimen 2ALI....................................

B-2 B-2.

Load-Time Trace for Charpy V-Notch Impact Specimen 2AH3....................................

B-2 B-3.

Load-Time Trace for Charpy V-Notch Impact Specimen AW5................................

B-3 B-4.

Load-Time Trace for Charpy V-Notch Impact Specimen 2AJ1.....................................

B-3 vi ARAMATOME ANP

List of Figures (continued)

FigIr.

Page B-5.

Load-Time Trace for Charpy V-Notch Impact Specimen AU4.............................. B-4 B-6.

Load-Time Trace for Charpy V-Notch Impact Specimen 2AL3....................................

B-4 B-7.

Load-Time Trace for Charpy V-Notch Impact Specimen API.................

B-5 B-8.

Load-Time Trace for Charpy V-Notch Impact Specimen AU5...................................

B-5 B-9.

Load-Time Trace for Charpy V-Notch Impact Specimen 2AE5....................................

B-6 B-10. Load-Time Trace for Charpy V-Notch Impact Specimen 2AK5....................................

B-6 B-1i.

Load-Time Trace for Charpy V-Notch Impact Specimen APS.....................................

B-7 B-12. Load-Time Trace for Charpy V-Notch Impact Specimen AS2......................................

B-7 B-13. Load-Time Trace for Charpy V-Notch Impact Specimen BTI.....................................

B-8 B-14. Load-Time Trace for Charpy V-Notch Impact Specimen 2BJ5.....................................

B-8 B-15. Load-Time Trace for Charpy V-Notch Impact Specimen BL5....................................

B-9 B-16. Load-Time Trace for Charpy V-Notch Impact Specimen 2BG5............................ B-9 B-17. Load-Time Trace for Charpy V-Notch Impact Specimen 2BFG.......................... B-10 B-18. Load-Time Trace for Charpy V-Notch Impact Specimen 2BG4................................

B-10 B-19. Load-Time Trace for Charpy V-Notch Impact Specimen 2BJ2.............................. B-i1 B-20. Load-Time Trace for Charpy V-Notch Impact Specimen 2B14.............................. B-1l B-21. Load-Time Trace for Charpy V-Notch Impact Specimen 2BIl...................................

B-12 B-22. Load-Time Trace for Charpy V-Notch Impact Specimen BVDI..................................

B-12 B-23. Load-Time Trace for Charpy V-Notch Impact Specimen 2BDG..................................

B-13 B-24. Load-Time Trace for Charpy V-Notch Impact Specimen 2BG2..................................

B-13 B-25. Load-Time Trace for Charpy V-Notch Impact Specimen PB45..............................

B-14 B-26. Load-Time Trace for Charpy V-Notch Impact Specimen PB62........................... B-14 B-27. Load-Time Trace for Charpy V-Notch Impact Specimen PB71.............................. B-15 B-28. Load-Time Trace for Charpy V-Notch Impact Specimen PB54...............................

B-15 B-29. Load-Time Trace for Charpy V-Notch Impact Specimen PBO7...................................

B-16 B-30. Load-Time Trace for Charpy V-Notch Impact Specimen PB73.............................

B-16 B-31. Load-Time Trace for Charpy V-Notch Impact Specimen PB52.................................

B-17 B-32. Load-Time Trace for Charpy V-Notch Impact Specimen PB35..................................

B-17 B-33. Load-Time Trace for Charpy V-Notch Impact Specimen PBO6.............................. B-18 B-34. Load-Time Trace for Charpy V-Notch Impact Specimen PB58................................

B-18 B-35. Load-Time Trace for Charpy V-Notch Impact Specimen PB57..................................

B-19 B-36. Load-Time Trace for Charpy V-Notch Impact Specimen PB61............................ B-19 B-37. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-1 B-20 viiAO E

N

List of Figures (continued)

Figue Pi.ge B-38. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-13............................ B-20 B-39. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-23............................ B-21 B-40. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-17............................ B-21 B-41. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-2............................

B-22 B-42. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-22............................

B-22 B-43. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-19............................ B-23 B-44. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-8..............................

B-23 B-45. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-5............................

B-24 B-46. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-15............................ B-24 B-47. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-24............................ B-25 H-8. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-1 B-25 viii ARAMATOME ANP

1.0 Introduction Two supplemental surveillance capsules were fabricated containing the three weld metals found in the core region of the Palisades reactor vessel. The supplemental capsules were prepared to obtain information on the effects of irradiation on the mechanical properties of weld metals fabricated using the same weld wire heats and weld procedures as was used in the Palisades reactor vessel beltline region. These supplemental Capsules, SA-60-1 and SA-240-1, were inserted in the Palisades reactor vessel at the end-of-cycle 11 (EOC-I 1) in locations near the outer wall of the core support barrel for accelerated exposure. At the end-of-cycle 13 (EOC-13), supplemental Capsule SA-60-1 was removed from the Palisades reactor vessel, tested, and evaluated."' The supplemental Capsule SA-240-1 was removed from the Palisades reactor vessel for testing at the end-of-cycle 14 (EOC-14).

This report describes the results of the testing performed on the specimens from the Palisades second supplemental surveillance capsule (Capsule SA-240-1).

1-1

/ FRAMATOME ANP

2.0 Background

The ability of the reactor vessel to resist fracture is a primary factor in ensuring the safety of the primary system in light water-cooled reactors. The reactor vessel beltline region is the most critical region of the vessel because it is exposed to the highest level of neutron irradiation. The general effects of fast neutron irradiation on the mechanical properties of low-alloy ferritic steels used in the fabrication of reactor vessels are well characterized and documented. The low-alloy ferritic steels used in the beltline region of reactor vessels exhibit an increase in ultimate and yield strength properties with a corresponding decrease in ductility after irradiation. The most significant mechanical property change in reactor vessel steels is the increase in the ductile-to-brittle transition temperature accompanied by a reduction in the Charpy upper-shelf energy (CRUSE) value.

Code of Federal Regulations, Title 10, Part 50, (10 CFR 50) Appendix G E2) "Fracture Toughness Requirements," specifies minimum fracture toughness requirements for the ferritic materials of the pressure-retaining components of the reactor coolant pressure boundary (RCPB) of light water-cooled power reactors and provides specific guidelines for determining the pressure-temperature limitations for operation of the RCPB. The fracture toughness and operational requirements are specified to provide adequate safety margins during any condition of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected over its service lifetime. Although the requirements of 10 CFR 50, Appendix G, became effective on August 16, 1973, the requirements are applicable to all boiling and pressurized water-cooled nuclear power reactors, including those under construction or in operation on the effective date.

10 CFR 50, Appendix H,(3l "Reactor Vessel Materials Surveillance Program Requirements," defines the material surveillance program required to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region of water-cooled reactors resulting from exposure to neutron irradiation and the thermal environment. Fracture toughness test data are obtained from material specimens contained in capsules that are periodically withdrawn from the reactor vessel. These data permit determination of the conditions under which the vessel can be operated with adequate safety margins against non-ductile fracture throughout its service life.

2-1 MRAMATOME ANP

A method for guarding against non-ductile fracture in reactor vessels is described in Appendix G to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section rn,141 "Nuclear Power Plant Components" and Section XI,E51 "Rules for Inservice Inspection." This method uses fracture mechanics concepts and the reference nil-ductility temperature, RTNDT, which is defined as the greater of the drop-weight nil-ductility transition temperature (in accordance with ASTM Standard E 208-81 [6]) or the temperature that is 60'F below that at which the material exhibits 50 ft-lbs and 35 mils lateral expansion. The RTNrDr of a given material is used to index that material to a reference stress intensity factor curve (Kim curve), which appears in Appendix G of ASME B&PV Code Section III and Section XI. The KI curve is a lower bound of dynamic and crack arrest fracture toughness data obtained from several heats of pressure vessel steel. When a given material is indexed to the Km curve, allowable stress intensity factors can be obtained for the material as a function of temperature. The operating limits can then be determined using these allowable stress intensity factors.

The RTNDT and, in turn, the operating limits of a nuclear power plant, are adjusted to account for the effects of irradiation on the fracture toughness of the reactor vessel materials. The irradiation embrittlement and the resultant changes in mechanical properties of a given pressure vessel steel can be monitored by a surveillance program in which surveillance capsules containing prepared specimens of the reactor vessel materials are periodically removed from the operating nuclear reactor and the specimens are tested. The increase in the Charpy V-notch 30 ft-lb temperature is added to the original RTNDT to adjust it for irradiation embrittlement. The adjusted RTNDT is used to index the material to the Km curve which, in turn, is used to set operating limits for the nuclear power plant. These new limits take into account the effects of irradiation on the reactor vessel materials.

10 CFR 50, Appendix G, also requires a minimum initial Charpy V-notch upper-shelf energy (CvUSE) of 75 ft-lbs for all beltline region materials unless it is demonstrated that lower values of upper-shelf fracture energy will provide an adequate margin of safety against fracture equivalent to those required by ASME Section XI, Appendix G. No action is required for a material that does not meet the initial 75 ft-lbs requirement provided that the irradiation embrittlement does not cause the CVUSE to drop below 50 ft-lbs. The regulations specify that if the CXUSE drops below 50 ft-lbs, it must be demonstrated, in a manner approved by the Office of Nuclear Reactor Regulation, that the lower values will provide adequate margins of safety.

2-2 fARAMATOME ANP

3.0 Surveillance Program Description The original reactor vessel surveillance program (RVSP) for the Palisades Nuclear Plant was designed and furnished by Combustion Engineering, Inc.J71 The program was designed to the requirements of ASTM Standard E 185-66,1s' "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors." The Palisades RVSP includes ten capsules designed to monitor the effects of neutron and thermal environments on the materials of the reactor pressure vessel core region. These capsules were inserted into the reactor vessel before initial plant startup.

Six capsules were positioned such that they were located near the inside surface of the reactor vessel wall adjacent to the core, and two capsules were positioned closer to the core located on the outer wall of the core support barrel for accelerated exposure. Two capsules, designed for monitoring the effects of operating temperature on the surveillance materials, were located above the core such that the exposure was in a low flux region of the reactor vessel. The locations of the Palisades surveillance capsules within the reactor vessel are shown in Figure 3-1.

In addition to the above ten surveillance capsules, two supplemental surveillance capsules were fabricated containing three weld metals representative of those found in the core region of the Palisades reactor vessel. These capsules were installed at the end-of-cycle 11 (EOC-1 1) in locations near the outer wall of the core support barrel for accelerated exposure. The locations of the two supplemental surveillance capsules within the Palisades reactor vessel are shown in Figure 3-2.

Supplemental surveillance Capsule SA-240-1 was removed from the Palisades reactor vessel at the end-of-cycle 14 (EOC-14). The capsule contained standard Charpy V-notch impact test specimens fabricated from a submerged-arc weld metal (weld wire heat number 27204) and a correlation monitor plate material (HSST Plate 02). In addition, the Capsule SA-240-1 contained modified 18mm Type A Charpy V-notch specimens fabricated from three submerged-arc weld metals (weld wire heat numbers W5214, 34B009, and 27204); the 18mm Type A Charpy V-notch specimens are available for reconstitution such that full size Charpy V-notch impact specimens can be fabricated.

The tension test specimens included in Capsule SA-240-1 were fabricated from a submerged-arc weld metal (weld wire heat number 27204). The number of specimens of each material contained in supplemental surveillance Capsule SA-240-1 is described in Table 3-1, and the locations of the individual specimens within the capsule are shown in Figures 3-3 through 3-7. The chemical 3-1

& FRAMATOME AN P

composition and heat treatment of the surveillance materials in Capsule SA-240-1 are described in Tables 3-2 and 3-3 respectively.

The weld metal Charpy V-notch and tensile specimens were oriented with the longitudinal axis of the specimen either parallel or perpendicular to the welding direction.

There are three sets of nine dosimeter monitors in Capsule SA-240-1; one set each located in the top, middle, and bottom of the capsule. The dosimeter monitors included in each set consist of shielded copper, shielded nickel, unshielded iron, unshielded titanium, shielded and unshielded aluminum-cobalt, shielded and unshielded neptunium-237 (237Np), and shielded and unshielded uranium-238 (239U).

Thermal monitors fabricated from four low-melting alloys were included in Capsule SA-240-1, and were located in the middle of the capsule. The eutectic alloys and their melting points are listed below:

80% Au, 20% Sn 5% Ag, 5% Sn, 90% Pb 2.5% Ag, 97.5% Pb 1.75% Ag, 0.75% Sn, 97.5% Pb Melting Point 536°F Melting Point 558°F Melting Point 580OF Melting Point 590°F 3-2 AIFRAMATOME ANP

Table 3-1. Test Specimens Contained in Palisades Capsule SA-240-1 Number of Test Specimens Standard 18rmm MateialDesripionCharpy V-Notch Charpy V-Notch Material Description Tension Impact Inserts Weld Metal W5214 42 Weld Metal 34B009 36 Weld Metal 27204 3

12 36 Correlation Monitor Material, 12 HSST Plate 02 (Heat No. A1195-1) fRAMATOME AN P 3-3

Table 3-2. Chemical Composition of Palisades Capsule SA-240-1 Surveillance Materials Chemical Composition, wt%

Weld Metal Weld Metal Weld Metal Correlation Monitor Plate Element W521421) 34B009'2' 272041bI Heat No. Al1195-11c)

C 0.094 0.110 0.142 0.23 Mn 1.161 1.269 1.281 1.39 P

0.009 0.012 0.009 0.013 S

0.012 0.016 0.008 0.013 Si 0.252 0.181 0.217 0.21 Ni 1.045 b) 1.1 2 1lb) 1.067 0.64 Cr 0.040 0.040 0.071 Mo 0.510 0.543 0.525 0.50 Cu 0.3071b) 0.1851b) 0.194 0.17 (a) AEA Technology analysis.1 91 (b) Analysis provided by Consumers Energy.1101 (c) ORNL analysis."ill 3FRAMATOME ANP 3-4

Table 3-3. Heat Treatment of Palisades Capsule SA-240-1 Surveillance Materials Material Heat Description Treatment Weld Metal W5214 Post weld heat treatment: >1 100*F for 25 hrs, cooled at 8°F/hr for 24 hrs.(a)

Re-post weld heat treatment: 11 50°F for 2 hrs, with 100°F/hr heating/cooling rates (above 5000F)(b)

Weld Metal 34B009 Post weld heat treatment: >1 100'F for 16 hrs, cooled at 7°F/hr for 27 hrs.(a)

Re-post weld heat treatment: 1150'F for 2 hrs, with 100°F/hr heating/cooling rates (above 5000F)(b)

Weld Metal 27204 Post weld heat treatment: >1 100°F for 40 hrs.(c)

Correlation Monitor Plate, 1675 +/- 25'F for 4 hrs., air cooled HSST Plate 02 1600 +/- 25'F for 4 hrs., water quenched to 300'F (Heat No. A 1195-1) 1225 +/- 25°F for 4 hrs., furnace cooled to 500WF 1150 +/- 25'F for 40 hrs., furnace cooled to 600'F (a) Original post weld heat treatment.[121 (b) Post weld heat treatment performed on retired steam generator material to ensure that the material would be representative of the reactor vessel beltline materials. 91 (c) Post weld heat treatment provided by Consumers Energy. [ 0]

FRAMATOME ANP 3-5

Figure 3-1. Reactor Vessel Cross Section Showing Location of Palisades Original RVSP Capsules Thermal Capsules Assembly Accelerated Capsule Assembly Wall Capsule Assembly Reactor Vessel Core Support Barrel Elevation View fFRAMATOME ANP 3-6

Figure 3-2. Reactor Vessel Cross Section Showing Location of Palisades Supplemental Surveillance Capsules 14 FRAMATOME ANP 3-7

Figure 3-3. Supplemental Surveillance Capsule Assembly Showing Location of Specimens and Monitors 4".- Lock Assembly

}Wedge Coupling Ass I!

Extension Assembly embly Standard Charpy Impact

& Flux Compartment 18mm Charpy Impact Compartment Temperature, Flux, & Tensile Compartment Standard Charpy Impact

& Flux Compartment 18mm Charpy Impact Compartment Standard Charpy Impact Compartment 3FRAMATOME ANP 3-8

3-4. Temperature, Flux, and Tensile (TFT) Capsule Compartment Assembly Temperature Monitor Housing

.E.0 Tensile Z Dosimeter Housing 3-5. Standard Charpy Impact and Flux Capsule Compartment Assembly (Two Per Capsule)

Temperature SMonitor lm oife Housing

/Charpy Insert a I.

r.llll.Z SDosimeter Standard HousingCherpy V-Notch HousingSpecimen 3-9 ARAMATOME AN P

3-6. Standard Charpy Impact Capsule Compartment Assembly Standard Charpy V-Notch Specimen 3-7. Typical 18mm Charpy Impact Capsule Compartment Assembly (Three Per Capsule) 18mm Modified Charpy Insert f-FRAMATOME ANP 3-10

4.0 Post-Irradiation Testing The post-irradiation testing of the Charpy V-notch impact specimens, thermal monitors, and dosimeters for the Palisades Capsule SA-240-1 was performed at the BWXT Services Inc.

(BWXT) Lynchburg Technology Center (LTC).'131 All equipment and instruments used in conducting the post-irradiation testing and measurements are calibrated annually using standards traceable to the National Institute for Standards and Technology (NIST).

4.1. Visual Examination and Inventory After capsule disassembly, the contents of Capsule SA-240-1 were removed, inspected, and inventoried. The capsule contained a total of 24 standard Charpy V-notch specimens, 114 modified 18mm Charpy inserts, three tension test specimens, three dosimetry blocks, and four temperature monitors, which is consistent with the manufacturing report inventory.

4.2. Thermal Monitors The four low-melting point eutectic alloys contained in Capsule SA-240-1 were examined for evidence of melting. The results of the thermal monitor examination are tabulated in Table 4-1.

Photographs of the monitors are shown in Figure 4-1.

Only the 536'F thermal monitor exhibited complete melting. The remaining thermal monitors with melting points at 5580F, 580OF and 590'F had no evidence of melting. Based on these observations, it can be concluded that the capsule did not exceed a maximum irradiation temperature of 558'F.

4.3. Tension Test Specimens The tension test specimens removed from Capsule SA-240-1 were not tested as part of this capsule work effort at the request of Consumers Energy Company. However, these specimens were inadvertently tested under a separate work effort sponsored by the Electric Power Research Institute (EPRI) Reactor Vessel Issue Task Group (RV-ITG) and are no longer available for future testing.

4-1 FRAMATOME ANP

4.4. Reconstitution of Irradiated Charpy Inserts Pre-machined 18mm Charpy inserts fabricated from three submerged-arc weld metals (weld wire heat numbers W5214, 34B009, and 27204) were included in Capsule SA-240-1 for reconstitution of full size Type A Charpy V-notch impact specimens. Each 18mm weld metal Charpy insert included a centrally located V-notch that was machined prior to capsule irradiation. Reconstitution was performed by stud welding steel end tabs onto the irradiated modified 18mm Charpy inserts and machining full size Type A Charpy V-notch impact specimens to the dimensional requirements of ASTM Standard E 23-91.1'43 The proof-of-principal and validation test results for the Framatome ANP Charpy reconstitution process is documented in BAW-2184.J'5 The reconstitution of the irradiated weld metal 18mm modified Charpy inserts was performed in accordance with ASTM Standard E 1253-88,[I63 "Standard Guide for Reconstitution of Irradiated Charpy Specimens."

Fifteen (15) modified 18mm Charpy inserts were selected from each of the weld metals W5214 and 34B009, and fourteen (14) modified 18mm Charpy inserts were selected from the weld metal 27204 for reconstitution to full size Charpy V-notch specimens. Prior to the welding of the irradiated 18mm Charpy inserts, the reconstitution process was performed on mockup inserts to assure that the reconstitution welding process would produce quality welds. A steel end tab was stud welded to each end of the mockup insert, and each weldment was visually inspected for good fillet formation resulting from the stud welding process. In addition, two mockup specimens (minimum) were subjected to a 45-degree (minimum) bend test, to determine acceptance of the stud weld. An acceptable weld is one that did not fracture in the weld fusion zone resulting from the stud welding process. Once acceptable stud welds were established, reconstitution of the irradiated capsule 18mm Charpy inserts could begin. Using the same welding parameters used to reconstitute the mockup inserts, a steel end tab was stud welded to each end of the selected weld metal 18mm Charpy inserts irradiated in Capsule SA-240-1.

The ASTM Standard E 1253-88 specifies that temperature records be made during the welding on the first and last specimens of each set of Charpy specimens or on dummy specimens proceeding and following welding of the set. The welding temperature verification is performed using identical welding parameters as those in the actual reconstitution process except the mockup insert was not clamped by the movable jaw due to the obstruction by the thermocouple.

Since the movable jaw acts as a heat sink during the welding process, the measured temperatures are expected to be higher than the irradiated inserts. A certified thermocouple was connected to the midsection of the mockup insert and connected to a certified measuring temperature device.

Temperature measurements are recorded after stud welding a steel end tab to each end of the mockup insert. A total of four welding temperature verifications were performed, one preceding and following the reconstitution stud welding of each weld series. The recorded temperatures at 4-2 fRAMATOME ANP

the center position of the temperature verification mockup insert ranged from 3470F to 51 10F, which is less than the Palisades reactor vessel cold-leg temperature and meets the temperature requirement of ASTM Standard E 1253-88.

Twelve (12) stud-welded inserts were then selected from each of the weld metals W5214, 34B009, and 27204 for machining of full size Type A Charpy V-notch specimens in accordance with ASTM Standard E 23-91. The reconstituted Charpy specimen dimensions for each specimen are shown in Table 4-2.

4.5. Charpy V-Notch Impact Test Results The Charpy V-notch impact testing was performed in accordance with the applicable requirements of ASTM Standard E 23-91. Prior to testing, the specimens were temperature-controlled in liquid immersion baths, capable of covering the temperature range -100°F to +550'F. Specimens remain immersed in the liquid medium at the test temperature +/-2°F for at least 10 minutes before testing to assure achievement of thermal equilibrium. A certified Omega Model 462 device was used to measure the temperature. Impact energy, lateral expansion, and percent shear fracture were measured at numerous test temperatures and recorded for each specimen. The impact energy was measured using a certified Satec S 1-1K Impact tester (traceable to NIST Standard3 ) with a striker velocity of 16.90 ft/sec and 240 ft-lb of available energy. The lateral expansion was measured using a certified dial indicator. The specimen percent shear was estimated by video examination and comparison with the visual standards presented in ASTM Standard E 23-91. In addition, all Charpy V-notch impact testing was performed using instrumentation to record a load-versus-time trace and energy-versus-time trace for each impact event. The load-versus-time traces were analyzed to determine time, load, and impact energy for general yielding, maximum load, fast fracture, and crack arrest properties during the test. The dynamic yield stress is calculated from the three-point bend formula:

cry = 33.33 * (general yielding load)

The dynamic flow stress is calculated from the average of the yield and maximum loads, also using the three-point bend formula:

Each year, two sets of Charpy specimens are purchased from NIST and tested on the Charpy test machine. The results are then sent to NIST for evaluation. A letter is then issued by NIST certifying the calibration of the Charpy test machine. The accuracy of the Charpy tester is +/-1 ft-lb or 5% of the dial reading whichever is greater.

4-3 0RAMATOME ANP

The results of the Charpy V-notch impact testing are shown in Tables 4-3 through 4-10 and Figures 4-2 through 4-5, and the individual load-versus-time traces for the instrumented Charpy V-notch impact tests are presented in Appendix B. The curves were generated using a hyperbolic tangent curve-fitting program to produce the best-fit curve through the data. The hyperbolic tangent (TANH) function (test response, i.e., absorbed energy, lateral expansion, and percent shear fracture, "R," as a function of test temperature, "T") used to evaluate the surveillance data is as follows:

R =A +B *tanh[I(T To)]

For the absorbed (impact) energy curves, the lower-shelf energy was fixed at 2.2 ft-lbs for all materials, and the upper-shelf energy was fixed at the average of all test energies exhibiting 100 percent shear for each material, consistent with the ASTM Standard E 185-82. The lateral expansion curves were generated with the lower-shelf mils lateral expansion fixed at 1 mil and the upper-shelf mils lateral expansion not constrained (i.e., not fixed). The percent shear fracture curves for each material were generated with the lower-shelves and upper-shelves fixed at 0 and 100 respectively.

The Charpy V-notch data was entered, and the coefficients A, B, To, and C are determined by the program minimizing the sum of the errors squared (least-squares fit) of the data points about the fitted curve. Using these coefficients and the above TANH function, a smooth curve is generated through the data for interpretation of the material transition region behavior. The coefficients determined for irradiated materials in Capsule SA-240-1 are shown in Table 4-11.

The transition temperature shifts and upper-shelf energy decreases for the Capsule SA-240-1 materials with respect to the unirradiated material properties are summarized in Table 4-12.

Photographs of the Charpy V-notch specimen fracture surfaces are presented in Figures 4-6 through 4-9.

4-4 14FRAMATOME ANP

Table 4-1. Conditions of Palisades Capsule SA-240-1 Thermal Monitors Capsule Melt Post-Irradiation Segment Temperature Condition Middle 5360F Melted Middle 558OF Unmelted Middle 580OF Unmelted Middle 590OF Unmelted 4RAMATOME ANP 4-5

Table 4-2. Dimensions of Reconstituted Charpy Specimens for Palisades Capsule SA-240-1 Weld Specimen Width f Thickness Length Metal ID 0.394 +/-+0.003" 0.394 +0.003" 2.165+0,-0.100" Comments Mea0 00" Co W5214 2AE5

.394 0.394 2.163 Acceptable 2AK5 0.394 0.394 2.163 Acceptable 2AJI 0.395 0.392 2.162 Acceptable AU5 0.395 0.392 2.162 Acceptable AW5 0.393 0.392 2.163 Acceptable 2AL1 0.393 0.394 2.163 Acceptable AS2 0.394 0.393 2.163 Acceptable AU4 0.393 0.392 2.163 Acceptable AP5 0.393 0.393 2.163 Acceptable API 0.394 0.393 2.164 Acceptable 2AL3 0.393 0.392 2.163 Acceptable 2AH3 0.393 0.393 2.163 Acceptable 34B009 BV1 0.394 0.392 2.163 Acceptable 2H14 0.393 0.392 2.163 Acceptable 2BFI 0.393 0.393 2.163 Acceptable BTI 0.393 0.394 2.162 Acceptable 2BG5 0.393 0.394 2.163 Acceptable 21311 0.391 0.393 2.163 Acceptable BL5 0.392 0.393 2.163 Acceptable 2BJ 1 0.392 0.394 2.164 Acceptable 2BG4 0.393 0.393 2.163 Acceptable 2BJ2 0.394 0.392 2.163 Acceptable 2BDI 0.392 0.394 2.162 Acceptable 2BG2 0.395 0.394 2.162 Acceptable 27204 PB58 0.395 0.395 2.163 Acceptable PB07 0.394 0.393 2.162 Acceptable PB45 0.393 0.393 2.162 Acceptable PB71 0.393 0.393 2.163 Acceptable PB 35 0.393 0.393 2.163 Acceptable P1306 0.393 0.392 2.163 Acceptable PB54 0.392 0.392 2.162 Acceptable PB62 0.393 0.392 2.162 Acceptable PB52 0.393 0.394 2.163 Acceptable PB61 0.392 0.393 2.162 Acceptable PB57 0.392 0.394 2.162 Acceptable PB73 0.392 0.394 2.162 Acceptable fFRAMATOME ANP 4-6

Table 4-3. Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Weld Metal W5214

Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.1"3 4-7 IRAMATOME ANP

Table 4-4. Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Weld Metal 34B009 Test Impact Lateral Shear Specimen Temperature,

Energy, Expansion,

Fracture, ID OF ft-lbs mil BT1 70 6.5 4

0 2B J1 125 20.5 11 30 BL5 150 23.5 11 45 2BG5 175 32 23 35 2BF1 200 33 30 50 2BG4 225 37.5 31 55 2BJ2 250 47.5 35 75 2BI4 300 53 40 95 2BI1 350 54*

47 100 BVI 400 59.5*

49 100 2BD1I 450 61.5*

43 100 2BG2 500 54.5*

42 100 Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82.117I 4-8 AFRAMATOME ANP

Table 4-5. Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Weld Metal 27204 Test Impact Lateral Shear Specimen Temperature,

Energy, Expansion,

Fracture, ID OF ft-lbs mil

-15

ý PB45 70 5.5 3

0 PB62 125 16.5 12 10 PB71 175 16 18 30 PB54 200 26.5 29 55 PB07 200 33.5 27 60 PB73 225 29 24 65 PB52 250 34.5 26 55 P1335 300 36 32 65 PB06 350 44.5 43 95 PB58 400 49.5*

42 100 PB57 450 59*

52 100 PB61 500 53*

47 100 Value used to determine upper-shelf energy (USE) in accordance with ASTM Standard E 185-82. 171 4-9

&RAMATOME ANP

Table 4-6. Charpy Impact Results for Palisades Capsule SA-240-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02) Heat No. A1195-1 Test Impact Lateral Shear Specimen Temperature,

Energy, Expansion,

Fracture, ID

[

F ft-lbs mil

-I-02D2-10 70 6.5 4

0 02D2-13 125 15.5 10 20 02D2-23 175 27.5 24 30 02D2-17 200 26 19 35 02D2-2 200 44.5 29 55 OCD2-22 225 44.5 30 55 02D2-19 240 54 40 70 02D2-8 250 70 50 80 02D2-5 300 83*

66 100 02D2-15 350 82.5*

72 100 02D2-24 400 89.5*

67 100 02D2-11 500 82.5*

65 100

Value used to determine upper-shelf energy with ASTM Standard E 185-82.t'*7 (USE) in accordance FRAMATOME ANP 4-10

Table 4-7. Instrumented Charpy Impact Properties for Palisades Capsule SA-240-1 Irradiated Weld Metal W5214 Propagation Maximum Load Properties Load Total Load Test Charpy Yield Properties Fast Fractur Properties Crack Arrest Properties Properties Properties Yield Flow Specimen Temp Energy Time Load Energy Time Load Energy Time Load r Energy Time Load Energy Load Energy Time Energy Stress Stress ID (F)

(ft-lbW)

(Asec)

(Ibf)

(ft-lbf)

(pasec)

(lbf)

(ft-lbo (Lsec)

(Ibf)

(ft-lbf)

(Asec)

(Nb)

(fl-lbf)

(lbf)

(ft-Ibf)

(Pec)

(ft-lbt)

(ksi)

(ksi) 2ALI 70 14 168 4122 6.28 234 4444 11.00 234 4444 11.00 284 0

13.11 4444 2.11 284 13.11 137.4 142.8 2AH3 125 15.5 165 3887 4.87 260 4333 11.33 260 4333 11.33 344 0

15.10 4345 3.77 344 15.10 129.6 137.0 AW5 175 24.5 162 3680 5.33 344 4294 17.72 391 4276 21.13 456 0

23,71 4290 5.99 456 23.71 122.7 132.9 2AJI 200 13 166 3733 5.60 166 3733 5.60 166 3733 5.60 294 1019 9.96 2714 6.74 956 12.34 124.4 124.4 AU4 200 26.5 165 3682 5.01 355 4273 17.79 405 4225 27.38 526 941 24.62 3284 8.39 769 26.18 122.7 132.6 2AL3 225 25 173 3692 4.58 270 4129 10.82 327 4110 14.74 440 1638 19.77 2473 13.49 1253 24.31 123.1 130.3 API 250 40 170 3593 4.74 442 4276 23.10 442 4276 23.10 548 2569 28.58 1707 17.27 1648 40.36 119.8 131.1 AUS 300 54.5 172 3505 5.69 438 4181 23.33 N/A N/A N/A N/A N/A N/A 0

33.81 1922 57.15 116.8 128.1 2AE5 350 49 164 3519 4.73 442 4110 22.97 N/A N/A N/A N/A N/A N/A 0

27.17 1844 50.14 117.3 127.1 2AK5 400 50.5 174 3436 5.62 438.

4046 22.77 N/A N/A N/A N/A N/A N/A 0

29.75 1806 52.52 114.5 124.7 AP5 450 52.5 162 3335 4.56 438 3894 21.58 N/A N/A N/A N/A N/A N/A 0

32.43 1878 54.01 111.2 120.5 AS2 500 54.5 160 3271 4.50 436 3940 21.38 N/A N/A NN/A

/A N/A N/A 0

34.99 1832 56.37 109.0 120.2 3:

03:

z v

Table 4-8. Instrumented Charpy Impact Properties for Palisades Capsule SA-240-1 Irradiated Weld Metal 34B009 Propagation Maximum Load Properties Load Total Load Test Charpy Yield nies Fast Fracture Properties Crack Arrest Properties Properties Properties Yield Flow Specimen

Temp, Energy Time Load jEnergy Time Load Energy Time Lead Energy Time LWad Energy Load Energy Time Energy Stress Stress ID (F)

(ft-2bf)

(A-tec)

(Ib)

(ft-r)o (gsec)

(lbf)

(ft-Ibf) 0tsec)

(1bf)

(ft-lbf)

(tsec)

(1Wf)

(ft-lbf)

(1bf)

(ft-lW)

(gisec)

(ft-lb)

(ksi)

BTI 70 6.5 138 3873 4.48 138 3873 4.48 138 3873 4.48 188 0

6.30 3889 1.82 188 6.30 129.1 129.1 21J1 125 20.5 167 3809 5.01 324 4303 15.82 324 4303 15.82 394 0

18.33 4310 3.46 624 19.27 127.0 135.2 BL5 150 23.5 162 3797 5.10 342 4453 17.60 350 4439 18.20 464 678 21.54 3761 5.07 730 22.67 126.6 137.5 2BG5 175 32 159 3648 5.11 434 4382 24.11 471 4296 26.84 603 775 30.47 3521 7.32 746 31.43 121.6 133.8 2BFI 200 33 162 3646 5.04 432 4303 23.57 432 4303 23.57 558 1755 29.17 2548 9.78 1244 33.35 121.5 132.5 2BG4 225 37.5 169 3623 4.96 443 4352 23.69 506 4200 28.25 623 1723 32.72 2477 13.85 1617 37.54 120.8 132.9 2BJ2 250 47.5 164 3560 4.80 440 4172 23.15 522 4037 28.81 618 2730 34.11 1306 26.35 1730 49.51 118.7 128.9 2B14 300 53 168 3448 5-50 434 4115 22.91 N/A N/A N/A N/A N/A N/A 0

32.40 1792 55.31 114.9 126.0 2B11 350 54 164 3342 4.75 442 3997 22.37 N/A N/A N/A N/A N/A N/A 0

33.48 1918 55.85 111.4 122.3 BVI 400 59.5 166 3353 5.63 518 4034 28.44 N/A N/A N/A N/A N/A N/A 0

31.78 2058 60.21 111.8 123.1 28DI 450 61.5 158 3312 4.60 436 3986 21.85 N/A N/A N/A N/A N/A N/A 0

40.36 2128 62.20 110.4 121.6 2BG2 500 54.5 160 3317 4.48 438 3963 21.68 N/A N/A N/A N/A N/A N/A 0

35.66 1922 57.35 110.6 121.3 t,,

3:

In1 z

I I

(

I I

i I

Table 4-9. Instrumented Charpy Impact Properties for Palisades Capsule SA-240-1 Irradiated Weld Metal 27204 Propagation Maximum Load Properties Load Total Load Spcmn Temp Energy Time Load Energy Time ILoad Energy Time Load 1Energy Time Load Energy Load Energy Time Energy Srs Stress Test Charpy ield Proprtie Fast Fracture Properties Crack Arrest Properties Properties Properties Yield Flow ID (F)

(ft-lbf (Lsec)

I bf)

(ft-lbf)

(psec)

(Ibf)

(ft-lbf)

(gisec)

(Ibf)

(ft-lbf)

(psec)

(bfI)

(ft-lbf)

(Ibf)

(ft-tbf)

(psec)

(ft-lbf)

(ksi)

(csi)

P045 70 5.5 138 3689 4.00 138 3689 4.00 138 3689 4.00 182 0

5.47 3680 1.48 182 5.47 123.0 123.0 PB62 125 16.5 158 3678 4.89 251 4039 10.87 251 4039 10.87 365 646 13,93 3393 4.77 802 15.65 122.6 128.6 PB71 175 16 161 3634 4.73 220 3657 8.32 220 3657 8.32 335 980 11.17 2677 6.57 1237 14.88 121.1 121.5 PB54 200 26.5 162 3563 5.12 252 3919 10.76 284 3903 12.89 402 2036 12.90 1868 15.38 1486 26.15 118.8 124.7 PB07 200 33.5 172 3512 4.75 336 3977 15.07 336 3977 15.07 436 2627 20.39 1350 19.14 1850 34.21 117.1 124.8 PB73 225 29 164 3473 5.44 238 3797 9.96 238 3797 9.96 331 3004 15.11 794 18.63 1649 28.59 115.8 121.2 PB52 250 34.5 164 3443 4.41 346 3974 15.67 346 3974 15.67 448 2767 21.37 1208 18.75 1572 34.42 114.8 123.6 PB35 300 36 166 3393 4.90 350 3892 16.27 390 3809 18.88 592 1927 28.19 1881 19.78 1724 36.06 113.1 121.4 PB06 350 44.5 168 3275 5.24 334 3761 15.23 N/A N/A N/A N/A N/A N/A 0

30.67 1904 45.90 109.2 117.3 PB58 400 49.5 162 3255 4.58 436 3804 21.13 N/A N/A N/A N/A N/A N/A 0

30.41 1918 51.54 108.5 117.6 PB57 450 59 164 3165 5.07 428 3790 20.98 N/A N/A N/A N/A N/A N/A 0

38.41 2372 59.39 105.5 115.9 PB61 500 53 166 3172 4.04 446 3675 20.11 N/A N/A N/A N/A N/A N/A 0

34.24 1936 54.35 105.7 114.1

-~~

~~~~~~~

=_L.

0 z

Table 4-10. Instrumented Charpy Impact Properties for Palisades Capsule SA-240-1 Irradiated Correlation Monitor Plate Material (HSST Plate 02)

Heat No. A1195-1 Propagation Maximum Load Properties Load Total Load Test Charpy Yield Proper ies Fast Fracture Properties Crack Arrest Properties Properties Properties Yield Flow Spcie Tmp Eery ie oergy rg ie La nergy Time Load Energy Ti me Woad Energy Load Energy Time Energy tes Srs ID (F)

(ft-lbl)

(Wsec)

(Ibf)

(ft-lbf)

(ptsec)

(bf)

(ft-lbf)

(gtsec)

(bf)

(ft-lbI)

(.sec)

(lbf)

(ft-tbf)

(lbf)

(ft-rbf)

(1tsec)

(ft-lb)

(ksi)

(ksi) 02D2-10 70 6.5 128 3554 3.92 128 3554 3.92 128 3554 3.92 178 0

5.51 3616 1.59 178 5.51 118.5 118.5 02D2-13 125 15.5 165 3478 5.10 253 3887 10.53 253 3887 10.53 368 621 13.27 3266 3.54 621 14.07 115.9 122.7 02D2-23 175 27.5 156 3353 5.05 371 4078 18.83 371 4078 18.83 491 1343 22.73 2735 7.00 1023 25.84 111.8 123.8 02D2-17 200 26 138 3215 3.78 340 3993 16.23 340 3993 16.23 458 1589 20.55 2404 8.79 992 25.02 107.2 120.1 02D2-2 200 44.5 166 3372 5.48 532 4469 30.60 596 4432 35.42 708 1723 39.95 2709 14.14 1714 44.74 112.4 130.7 02D2-22 225 44.5 165 3264 5.16 534 4262 29.49 564 4200 31.65 672 2155 36.47 2045 15.11 2089 44.60 108.8 125.4 02D2-19 240 54 166 3312 5.21 612 4372 35.63 612 4372 35.63 756 2190 43.34 2183 19.91 2532 55.54 110.4 128.1 02D2-8 250 70 160 3202 5.04 530 4296 29.24 876 3880 53.66 976 2440 58.69 1440 43.43 2966 72.66 106.7 125.0 02D2-5 300 83 164 3167 5.05 612 4253 34.50 N/A N/A N/A N/A N/A N/A 0

53.65 3040 88.15 105.6 123.7 02D2-15 350 82.5 160 3080 4.85 532 4154 28.32 N/A N/A N/A N/A N/A N/A 0

58.45 3028 86.77 102.7 120.6 O2D2-24 400 89.5 162 3008 4.84 704 4066 39.42 N/A N/A N/A N/A N/A N/A 0

54.88 3156 94.30 100.3 117.9 02D2-11 500 82.5 170 2866 4.61 622 3896 31.79 N/A N/A N/A N/A N/A N/A 0

54.02 3130 85.81 95.5 112.7 4I-3:

'0 I

I I

t I

I I

I f

Table 4-11. Hyperbolic Tangent Curve Fit Coefficients for the Palisades Capsule SA-240-1 Surveillance Materials Material Hyperbolic Tangent Curve Fit Coefficients Description Absorbed Energy Lateral Expansion Percent Shear Fracture Weld Metal A:

27.4 A:

22.8 A:

50.0 W5214 B:

25.2 B:

21.8 B:

50.0 C:

111.6 C:

83.5 C:

72.5 TO:

208.1 TO: 231.7 TO:

223.2 Weld Metal A:

29.8 A:

22.9 A:

50.0 34B009 B:

27.6 B:

21.9 B:

50.0 C:

111.7 C:

88.0 C:

109.8 TO:

176.6 TO:

184.3 TO:

192.6 Weld Metal A:

28.0 A:

25.6 A:

50.0 27204 B:

25.8 B:

24.6 B:

50.0 C:

145.7 C:

169.2 C:

118.4 TO: 215.3 TO: 225.9 TO:

210.1 Correlation A:

43.3 A:

35.8 A:

50.0 Monitor Plate, B:

41.1 B:

34.8 B:

50.0 HSST Plate 02 C:

75.3 C:

83.1 C:

75.9 (Heat No. A1195-1)

TO:

211.8 TO: 222.2 TO:

206.5 fFRAMATOME ANP 4-15

Table 4-12. Summary of Charpy Impact Test Results for the Palisades Capsule SA-240-1 Surveillance Materials 30 ft-lb Transition Temperature, 50 ft-lb Transition Temperature, 35 mil Lateral Expansion Material TF OF Transition Temperature, *F Upper-Shelf Energy. ft-lb Description Unirradiated Irradiated ATi Unirradiated Irradiated AT Unirradiated I

Irradiated Decrease Weld Metal

-60.2(a) 219.9 280.1

-17.4(a) 372.7 390.1

-29.6(a) 284.3 313.9 102.7(')

52.5 50.2 W5214 Weld Metal

-82.0(a) 177.4 259.4

-45.0(2) 280.8 325.8

-51.6(a) 238.6 290.2 113.9(&)

57.4 56.5 34B009 Weld Metal

-41.2°)

226.6 267.8

-6.1'()

399.7 405.8 Not 293.7 108.4(")

53.8 54.6 27204 available.

HSST Plate 02 45.7(c) 186.6 140.9 78.3(c) 224.2 145.9 Not 220.3 120.3(c) 84.4 35.9 Heat No A 1195-1 available.

(a) Data reported in AEA Technology Report AEA-TSD-0774.1 91 (b) Data reported in CE Report No. TR-MCC-189.r1 81 (c) Data reported in NUREG/CR-6413. "

3:

0

'Ii 1

I I

(

I I

Figure 4-1. Photographs of Thermal Monitors Removed from Palisades Capsule SA-240-1 OIF'RAMATOME ANP 4-17

Figure 4-2. Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Weld Metal W5214 100 Bh LL 75 50 25 0

0 100 200 300 400 500 Temperature, F 600

.9 C

.9aC'U 0.

w U

a

-I 100 80 60 40 20 0

I I

I0 0

100 200 300 400 Temperature, F 500 600 120 100o aL

.0 80 1 601 T35LE :+8.

T50:

+372.7F TNo:

+219.f CvUSE:

52.5 ft-40 20 0

0 100 200 300 400 500 600 Temperature, F 8IRAMATOME ANp 4-18

~.C w

100 75 50 25 0

Figure 4-3. Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Weld Metal 34B009 66 0

0-0 S

S 0

100 200 300 400 500 Temperature, F 600 4

.2

,a.

w Ui 100 80 60 40 20 0

-0 0

100 200 300 400 500 Temperature, F 600 120 100 U

t U

U' UUa.

80 60 40 20 0

T3I5LE :

+238.6 F Tw:

+280.8 F To:

+177.4 F CvUSE:

57.4 ft-l

..........o

°...oo o

o

=

o Material:

Weld Metd Heat Number: 34BO9 0

100 200 300 400 Temperature, F 500 600 fI#

4-19

Figure 4-4. Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Weld Metal 27204 L6 100 75 50 25 0

0 100 200 300 Temperature, F 400 500 600 0.

-j 100 80 60 40 20 0

0 100 200 300 Temperature, F 400 500 600 120 100 T35LE :

+293.7F T~o

+~226.6 TvSE 532.8ft-l F~

CL f

80 60 -

40

.2............

0....................

0.....

20 M a e i lIed M etal IHeat Number: 27204 0

I I

I II 0

100 200 300 Temperature, F 400 500 600 A RAMATOME ANP 4-20

Figure 4-5. Palisades Capsule SA-240-1 Charpy Impact Data for Irradiated Correlation Monitor Plate Material (HSST Plate 02), Heat No. A1195-1 100 aR I.CU) 75 50 25 0

0 100 200 300 Temperature, F 400 500 600

- 100 E

d 8o c 60 K

40 2

20

~0 0

100 200 300 Temperature, F 400 500 600 120 100 1 a.

80 601 TwE:+220.3F Tso:

+224.2Z.

Tao:

+186.6 F OvUSE; 84.4 ft-lb Mateial:

HSS7 Pate oTI Orietaton:Longitudinal 40 20 0

0 100 200 300 Temperature, F 400 500 600 2fFRAMATOME ANP 4-21

Figure 4-6. Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal W5214 from Palisades Capsule SA-240-1 Specnimen No~AL, Tst'renperature 70'F Speciw~n.No. AI'1,TIest 11cwptaturc 2SOT1?

Spucizntn No. AU$.', Tv-Tamn praturr Wr~I Speciatut No. AWSi, Tis 'AmIKmJ.TJaurc 175*F S1wcirn'~iu N~AjI, T~t Tenaiii~roIimn~ ~OO5F Spei~snken N!Af'KS, TaqtTenmperuture 400F7 Specinmen No. AIJ4~ es(T 'i.persture 200"F Specimen No. AZ'S. T..st Temperature 4SOTF Specimen No. AS2. Test Tectnpeniur SWFI~

4'RAMATOME ANP 4-22

Figure 4-7. Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal 34B009 from Palisades Capsule SA-240-1 Specimen No BTI, Test Totperituart "I 0F SpeciweutnNd6Nj2 Tat Temhperatur~e 25OPF Speime~n No. RJU, TestTtkperature 125"F

$ptclren N. HLS, Test Twuenpmiure :150V SPEC11RCIL ING~F 1,es Fei tmpersture 35O*i Specimen~ N" IG5, TeSL Temperamtuew IWE*

Spedomcn No. HIi V1Tes Temperature 49 0OF fRAMATOME ANP 4-23

Figure 4-8. Photographs of Charpy Impact Specimen Fracture Surfaces, Weld Metal 27204 from Palisades Capsule SA-240-1 Speclimen No. P1145, Teoi Temperature 70OF Specimen No. VB52,'estTernptrature 250V1 Specbmen, No. P0162, TesidTemperature 325OFP Specimen No. 11135, t~t Temptraturv 3OW'1 Spedmcn No. P1171, TtsfTemperature 175*F Specinien No. P0106, Te4A Terntpurrtdire 350"F Spvweimen No. 1*0I4,TesCAt unperature 200b 1F Spet Jiun. N., L'3.8. TL~t Tenapuerawx*r 400V SpeeIhneis

. P0O7, Teo Temnperature 20lVF Specimen No". P1157, Test Tensperalure 4500V SpecJinen Na. I'N73, Test Tem perature 225*F Specimen N,. P1161, Test Temperature 500*'V fRAMATOME ANP 4-24

Figure 4-9. Photographs of Charpy Impact Specimen Fracture Surfaces, Correlation Monitor Plate Material (HSST Plate 02) from Palisades Capsule SA-240-1 S pccbncn N&o 02D210, rcst 'rmperaturOWI0F Spednmeen No. 021)219, Ted~ Temperature 2401F S peciuiata Nlo. 02D23)2 S.est. Tesnpierativr 1WF Specimen No. 020)18, Tont Temperature 254rF S pcciunuc No. 02J)W A T" Telov-dralurue I 7S*F Specimen No. (f02DZ5, Test Tempeval ure 300T Speelinem No. 020217, Tes't Temperature 2OI0?F SpeciInma No. 02D215, Tes Tauiperslure 3509F s peclmee No. 02D)221 Test 1'euperatume200OF SIpenimen No. 020)224, Text Temperature 4006F Specimen No. 02D1222. Test ITcmnpffatt~re 22SOI?

'Specknea No. 02D)211, TeatTemperature 5000F FRAMATOME AN P 4-25

5.0 Dosimeter Measurements 5.1. Introduction Three dosimeter sets were located in blocks that were installed in top, middle, and bottom positions of the Capsule SA-240-1 assembly. Each dosimeter set consisted of dosimeters made up of shielded and unshielded cobalt/aluminum and uranium dosimeters, shielded copper, nickel, and neptunium dosimeters, and unshielded iron and titanium dosimeters. The dosimeters were stored in vials identified by labels consisting of the position of the dosimeter holder block within the capsule assembly and the location from where the dosimeters where recovered.

5.2. Dosimeter Preparation Vials were prepared for the dosimeters by labeling them with identifications that indicated their types and positions in the holder blocks. For example, the one top block shielded cobalt/aluminum dosimeter was labeled Palisades SA-240-1 Il1T Sh Co. The analyte nuclides were verified during gamma scanning.

The dosimeter wires were washed in reagent grade acetone and blotted dry with a laboratory towel.

Each dosimeter wire was then measured with a certified micrometer caliper and weighed on a certified analytical balance. Each wire was then mounted in the center of a PetriSlideTM with double-sided tape.

5.3. Quantitative Gamma Spectrometry Several of the dosimeters, placed in the PetriSlideTM, were given a 300 second preliminary count on the 31% PGT gamma spectrometer. This provided information to best judge the distance at which to count the dosimeter to obtain a minimum of 10,000 counts in the photopeak of interest while keeping the counter dead time below 15%. It also provided qualitative identification of the dosimeters. This identification was made from the presence of the gamma rays in Table 5-1. The spectra were used to confirm the identities of the dosimeters.

The spectra were then measured quantitatively at the appropriate counting positions and for the appropriate count times determined from the preliminary counts.

5-1 YRAMATOME ANP

5.4. Dosimeter Specific Activities The associated elemental weight fractions of the dosimeters and the isotopic fractions of the target nuclides are listed in Table 5-2. The isotopic fractions of the target nuclides were obtained from the CRC Handbook of Chemistry and Physics, 63"' Edition."191 The dosimeter specific activities were calculated by dividing the corrected activity of the analyte nuclide by the target nuclide mass, and the results are shown in Table 5-3.

5-2

/FRAMATOME ANP

Table 5-1. Quantifying Gamma Rays Dosimeter Analyte Iron "Mn @ 834 keV from 'Fe Co/Al 6°Co @ 1332 keV from ' 9Co Nickel "8Co @ 811 keV from 5"Ni Titanium 46Sc@ 1121 keV from ¶6Ti Copper 6°Co @ 1332 keV from 63Cu, very low activity compared to Co wires, wire has coppery color 237Np 13 7Cs @ 662 keV 238u

'3'Cs @ 662 keV hRAMATOME ANP 5-3

Table 5-2. Isotopic Fractions and Weight Fractions of Target Nuclides fFRAMATOME ANP 5-4

Table 5-3. Specific Activities for Palisades Capsule SA-240-1 Doshnetry Specific Dosimeter Shielded Target Analyte Activity

% Error Identification (Yes/No)

Nuclide Nuclide (ltCi/gm Target)

(%)

1 IT Co I

Palisades, SA-240-1 11 IT Sh Co Yes Co-59 Co-60 5.659E+04 6.57 Palisades, SA-240-1 11IT Co No Co-59 Co-60 1.469E+05 6.58 Palisades, SA-240-1I 114T Sh Co Yes Co-59 Co-60 5.055E+04 6.70 Palisades, SA-240-1 I 14T Co No Co-59 Co-60 1.401E+05 6.53 Palisades, SA-240-1 117T Sh Co Yes Co-59 Co-60 5.167E+04 6.46 Palisades, SA-240- I IITT Co No Co-59 Co-60 2.454E+05 6.90 Palisades, SA-240-1 11IT Sh Cu Yes Cu-63 Co-60 2.039E+01 5.26 Palisades, SA-240-1 114T Sh Cu Yes Cu-63 Co-60 2.093E+01 5.25 Palisades, SA-240-1 117T Sh Cu Yes Cu-63 Co-60 2.109E+03 5.26 Palisades, SA-240-1 11lT Sh Ni Yes Ni-58 Co-58 8.671E+03 5.22 Palisades, SA-240-1 114T Sh Ni Yes Ni-58 Co-58 8.435E+03 5.23 Palisades, SA-240- 117T Sh Ni Yes Ni-58 Co-58 8.9614E+03 5.23 Palisades, SA-240-1 111T Fe No Fe-54 Mn-54 5.963E+03 5.65 Palisades, SA-240-1 114T Fe No Fe-54 Mn-54 6.067E+03 5.64 Palisades, SA-240-1 I 17T Fe No Fe-54 Mn-54 6.281E+03 5.59 Palisades, SA-240-1 114T Ti No Ti-46 Sc-46 1.315E+03 5.95 Palisades, SA-240-1 114T Ti No Ti-46 Sc-46 1.313E+03 5.98 Palisades, SA-240-1 117" Ti No Ti-46 Sc-46 1.4096E+03 5.92 Palisades, SA-240-1 I IIT Sb U Yes U-238 Cs-137 3.678E+01 7.12 Palisades, SA-240-1 11IT U No U-238 Cs-137 5.117E+01 7.59 Palisades, SA-240-1 114T Sb U Yes U-238 Cs-137 3.691E+01 7.48 Palisades, SA-240-1 114T U No U-238 Cs-137 4.954E+01 7.12 Palisades, SA-240-1 l17T ShU Yes U-238 Cs-137 3.765E+01 7.09 Palisades, SA-240-1 117T U No U-238 Cs-137 5.104E+01 7.18 Palisades, SA-240-1 11 IT Sh Np Yes Np-237 Cs-137 1.799E+02 8.08 Palisades, SA-240-1 114T Sh Np Yes Np-237 Cs-137 1.778E+02 8.09 Palisades, SA-240-1 117T Sh Np Yes Np-237 Cs-137 1.810E+02 8.09 fFRAMATOME ANP 5-5

6.0 Summary of Results The investigation of the post-irradiation test results of the materials contained in the second supplemental surveillance capsule, Capsule SA-240-1 removed from the Consumers Power Company Palisades reactor vessel, led to the following conclusions:

1. Observation of the Capsule SA-240-1 thermal monitors indicated that the irradiated test specimens were exposed to a maximum irradiation temperature less than 558'F.

2. Thirty-six pre-machined irradiated 18mm Charpy inserts were successfully reconstituted and machined to Type A Charpy impact specimens. The reconstituted Charpy specimens were subsequently impact tested.

3. The 30 ft-lb and 50 ft-lb transition temperatures for the weld metal W5214 increased 280.1F and 390.1'F, respectively. In addition, the CVUSE for this material decreased 48.9%.

4. The 30 ft-lb and 50 ft-lb transition temperatures for the weld metal 34B009 increased 259.4'F and 325.8'F, respectively. In addition, the CVUSE for this material decreased 49.6%.

5. The 30 ft-lb and 50 ft-lb transition temperatures for the weld metal 27204 increased 267.8*F and 399.7*F, respectively. In addition, the CVUSE for this material decreased 50.4%.

6. The correlation monitor plate demonstrated similar behavior with an increase in the 30 ft-lb and 50 ft-lb transition temperatures of 140.9 0F and 145.9°F, respectively.

The percent decrease in the CXUSE for this material is 29.8%.

6-1 fRAMATOME ANP

7.0 Certification This report is an accurate description of the testing and analysis of the Consumers Energy's Palisades Nuclear Plant second supplemental surveillance capsule (Capsule SA-240-1).

M.A

.Dean, Supervisory Engineer Date Materials & Structural Analysis Unit This report has been reviewed for technical content and accuracy.

SE. Moore, Advisory Engineer Materials & Structural Analysis Unit Date Verification of independent review.

A. t. McKim, S cana-y-Uaten MaEril & trctura *nalysis Unit This report is approved for release.

D. L. Howell Program Manager Date 7-I FAMTEAN 7-1

8.0 References

1. M. J. DeVan, "Test Results of Capsule SA-60-1 Consumers Energy Palisades Nuclear Plant Reactor Vessel Material Surveillance Program," BAW-2341, Revision 1, Framatome Technologies, Inc., Lynchburg, Virginia, May 1999.

2. Code of Federal Regulation, Title 10, Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix G. Fracture Toughness Requirements.

3. Code of Federal Regulation, Title 10, Part 50, "Domestic Licensing of Production and Utilization Facilities," Appendix H. Reactor Vessel Material Surveillance Program Requirements.

4. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, "Nuclear Power Plant Components," Appendix G. Protection Against Nonductile Failure, 1989 Edition.

5. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Appendix G. Fracture Toughness Criteria for Protection Against Failure, 1989 Edition.

6. ASTM Standard E 208-81, "Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels," American Society for Testing and Materials, Philadelphia, Pennsylvania.

7. R. C. Groeschel, "Summary Report on Manufacture of Test Specimens and Assembly of Capsules for Irradiation Surveillance of Palisades Reactor Vessel Materials," CE Report No. P-NLM-019, Combustion Engineering, Inc., Windsor, Connecticut, April 1, 1971.

8. ASTM Standard E 185-66, "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors," American Society for Testing and Materials, Philadelphia, Pennsylvania.

9. G. Gage, R. J. McElroy, and C. A. English, "Evaluation of Weldmetalsfrom Retired Palisades Steam Generators," AEA-TSD-0774, AEA Technology, November 23, 1995.

10. Letter from J. R. Kneeland to D. L. Howell (FTI), FTG Document No. 38-1247683-00, released March 9, 1999.

11. J. A. Wang, "Analysis of the Irradiation Data for A302B and A533B Correlation Monitor Materials, " NUREG/CR-6413 (ORNLfI'M-13133), Prepared for U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tennessee, April 1996.

8-1 ARAMATOM E AN P

12. Letter from R. A. Fenech (CPCo) to NRC, "Docket 50-255 - License DPR Palisades Plant Response to Request for Additional Information, Revision 1 - 10 CFR 50.61 Screening Crtierion (RE: TAC No. M8322 7)," dated December 28, 1994.

13. K. Y. Hour, "Evaluation of Consumers Power Company's Palisades SA-240-1 Capsule,"

1150:003-70-04:00 (FIG Document No. 31-1182295-00), BWXT Services, Inc., Lynchburg, Virginia, October 2000.

14. ASTM Standard E 23-91, "Standard Test Methods for Notched Bar Impact Testing of Metallic Materials, " American Society for Testing and Materials, Philadelphia, Pennsylvania.

15. L. B. Gross, "Verification of Reconstituted Charpy V-Notch Test Values," BAW-2184, B&W Nuclear Technologies, Inc., Lynchburg, Virginia, May 1993.

16. ASTM Standard E 1253-88, "Standard Guide for Reconstitution of Irradiated Charpy Specimens," American Society for Testing and Materials, Philadelphia, Pennsylvania.

17. ASTM Standard E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706 (IF)" American Society for Testing and Materials, Philadelphia, Pennsylvania.

18. "Baseline Charpy Test Data for Weld Heat No. 27204, " CE Report No. TR-MCC-189, Combustion Engineering Inc., Windsor, Connecticut.

19. R. C. Weast and M. J. Astle, Eds., "CRC Handbook of Chemistry and Physics, 63 rd Edition,"

CRC Press, Boca Raton, Florida, 1982.

8-2

/IRAMATOME ANP

APPENDIX A Reactor Vessel Surveillance Program Background Data and Information fFRAMATOME ANP A-1

A.1.

Palisades Reactor Pressure Vessel The Palisades reactor pressure vessel was fabricated by Combustion Engineering, Inc. (CE). The Palisades reactor vessel beltline region consists of two shells, containing six heats of base metal plate, six longitudinal weld seams, and two circumferential weld seams. Table A-I presents a description of the Palisades reactor vessel beltline materials including their copper and nickel chemical contents and their unirradiated mechanical properties. The locations of the materials within the reactor vessel beltline region are shown in Figure A-I.

A-2 ARAMATOME ANP

Table A-I. Description of the Palisades Reactor Vessel Beltline Region Materials Chemical Fabricator Composition Toughness Properties Material Code Material Material Beltlineo wCu' Ni, 30 ft-lb, 1 50 ft-lb, F

35 MLE, I CRUSE, I TFtls r, JRTNDT.

Heat No.

Type Region Locaton I%

wt%

F F

F ft-lbs F

F D-3803-1 C 1279-3 A 302 Gr. B Mod.

Intermediate Shell 0.24 0.51 102

-30

-5 D-3803-2 A0313-2 A 302 Gr. B Mod.

Intermediate Shell 0.24 0.52 87

-30

-30 D-3803-3 C 1279-1 A 302 Gr. B Mod.

Intermediate Shell 0.24 0.50 102

-30

-5 D-3804-1 C1308-1 A 302 Gr. B Mod.

Lower Shell 0.19 0.48 72

-30 0

D-3804-2 C1308-3 A 302 Gr. B Mod.

Lower Shell 0.19 0.50 76

-40

-30 D-3804-3 B5294-2 A 302 Or. B Mod.

Lower Shell 0.12 0.55 73

-30

-25 2-112A, B, C W5214/

ASA Weld/

Intermediate Shell 0.213 1.01 118

--56 3617*

Linde 1092 Longitudinal Welds 9-112 27204/

ASA Weld/

Intermediate to Lower 0.203 1.018 98

-56 3687*

Linde 124 Shell Circ. Weld 3-112A, B, C

34B009, ASA Weld/

Lower Shell 0.192/

0.98/

.-56 W5214/

Linde 1092 Longitudinal Welds 0.213 1.01 118 3692*

Weld wire heat number and flux lot identifiers.

3:

0 3:

M

Figure A-1. Location and Identification of Materials Used in the Fabrication of Palisades Reactor Pressure Vessel RPAClTOR VESSML BETUN MIATERIALW INTERMEDATE SHELL WELD SEAM No. 2-1120 LOWER SHELL WELD SEAM No. 3-112S WELD SEAM No. 3-1 2C PLATE No. D-3804-42" ID OUTLET NOZZLE UPPER TO INTERMEDIATE SHELL GIRTH SEAM WELD No. 8-112 INTERMEDIATE SHELL -

PLATE No. 0-3803.1 INTERMEDIATE &HELL LONGITUDINAL WELD SEAM No. 2-112A INTERMEDIATE SHELL PLATE No. D-38103.

LOWER SHELL PLATE No. D-3804.1 LOWER SHELL LONGITUDINAL WELD SEAM No. 3-112A REACTOR VESSEL fIFRAMATOME ANP A-4

APPENDIX B Instrumented Charpy V-Notch Specimen Test Results Load-Time Traces B-i RAMATOME ANP B-1

Figure B-1. Load-Time Trace for Charpy V-Notch Impact Specimen 2ALl PRO0J. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN-Ab* t kt 4200 in 2=0 200

-400 0

1.6 3.199 4.799 8.398 MILLISECONDS 7.990 Figure B-2. Load-Time Trace for Charpy V-Notch Impact Specimen 2AH3 PROJ.

NO. 1150-003 QA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN 43W A

IC Ii C.

M

_j

-. 4 3998 1.2

1. 9" 2.799 MILLISECONDS 3.599 M

'RAMATOME ANP B-2

Figure B-3. Load-Time Trace for Charpy V-Notch Impact Specimen AWS PROJ. NO, 1150-003 GA NO.

c9001 LOAD - TIME TRACE FODA ECIMEN AW5 E

U3 CL d

'01C 0

.799g 1.-

2.399 3.1g9 MILLISECONDS

3. H9 Figure B4.

.3 440 Load-Time Trace for Charpy V-Notch Impact Specimen 2AJ1 PROJ. NO. li00-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN4*dd-aC41ý agoo dt 1400 Boo

-400 1.5 3.199 4.799 5,396 MILLISECONDS 7.998 fFRAMATOME ANP B-3

Figure B-5. Load-Time Trace for Charpy V-Notch Impact Specimen AU4 PROJ.

NO. 1150-003 OA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN AU4

'7 Ii LA0R50 2WO 0

.116L 2.329 3.199 MILLISECONDS 3.99g Figure B-6. Load-Time Trace for Charpy V-Notch Impact Specimen 2AL3 PROJ. NO. 1150-003 GA NO.

99001 LOAD - TIME TRACE FOR SPECIMEN -ký IRL2 swoW 32M BOO 2w0

-4W0 0

7098B B

2. BW 3.099 MILLISECONDS 3.909 BRAMATOME ANP B-4

Figure B-7. Load-Time Trace for Charpy V-Notch Impact Specimen API PROJ. NO.

1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN API E

C,.

._J 131.

3.199 A.

799 5.396 M4ILLISECONDS5 7.89e Figure B-8. Load-Time Trace for Charpy V-Notch Impact Specimen AU5 PROJ. NO.

1150-003 GA NO. 9900i LOAD - TIME TRACE FOR SPECIMEN AL5 woo0 4400 am

-400 0

1.0 3.100 4-7B9 8.698 MILLISECOND~S 7.998 fRAMATOME ANP B-5

Figure B-9. Load-Time Trace for Charpy V-Notch Impact Specimen 2AE5 PROJ.

NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN A 2fL.

K 44GM S1400 BDO 200

-400 0

J.8 3.s099 4.799 HILL]SECUtCS

7. YB8 Figure B-10. Load-Time Trace for Charpy V-Notch Impact Specimen 2AK5 PROJ. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN *K-A

ý0&5 4400 (0O 26000 0

m 200

_4w0 a

3.133 4.799 34ILLISECONIMf 5.390 7.9M fI'RAMATOME ANP B-6

Figure B-11. Load-Time Trace for Charpy V-Notch Impact Specimen AP5 PROJ. NO. 1150-003 GA NO.

9o001 LOAD - TIME TRACE FOR SPECIMEN AP5 II U,-

C 0.

_j a

1.6 3.199 4.799 8.398 MILLISECONDS

7. 9N Figure B-12. Load-Time Trace for Charpy V-Notch Impact Specimen AS2 PROJ. NO.

1150-003 GA NO.

99001 LOAD - TIME TRACE FOR SPECIMEN AS2 h

.ziU La 0~

CL dC C

4

-.9

.7895 2.399 3.229 5.598 MILLISECONDS 7,195 FRAMATOME ANP B-7

Figure B-13. Load-Time Trace for Charpy V-Notch Impact Specimen BT1 PROJ. NO.

1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN BTI 5040 3JO 3M00

-400 a

3.190 4.799 MILLISECONDS 6.g98 7.1*8e Figure B-14. Load-Time Trace for Charpy V-Notch Impact Specimen 2BJ1 PROJ. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPEC]OEN,*l I

44MO 3=0 LQ 2

_j 2W10 AW

.4 1.2

.9 MILL ISECONDS BfRAMATOME ANP B-8

Figure B-15. Load-Time Trace for Charpy V-Notch Impact Specimen BL5 PROJ. NO.

1150-003 9A NO. 99001 LOAD -

TIME TPACE FOR SPECIOPN BL5 ah 44C0 ED*O A

0_3 1400 on 200

-4W0 ai'.79 L.399 3,1109 MILL ISECONDOS

3. 999 Figure B-16. Load-Time Trace for Charpy V-Notch Impact Specimen 2BGS PADJ. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN-'9 5

ý,S,5 In U,

C a-D4 C

-J 0

.799S 1.8 2.399 3.199 MILLISECONDS FRAMATOMIE AN P B-9

Figure B-17. Load-Time Trace for Charpy V-Notch Impact Specimen 2BF1 PROJ. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN-942 2BIl ow0 32M OUO 0

J.B 3.A99 4.790

.9 MILLISECONDS 7.M Figure B-18. Load-Time Trace for Charpy V-Notch Impact Specimen 2BG4 PJIOJ. NO.

1150-003 GA NO. g9ool LOAD - TIME TRACE FOR SPEC1MEN-H

Nd IT 100 ig 1400 0

.7999 1A8 2.399 3.199 M4ILLISECONDS 3.9ON B FAMATOME ANP B-10

Figure B-19. Load-Time Trace for Charpy V-Notch Impact Specimen 2BJ1 PGOJ. 1N1O.50-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN a8d:

.l, I 50000 3=a No 400 4

J~a 1.999 MILL ISECONDS 2.799 3.589 Figure B-20. Load-Time Trace for Charpy V-Notch Impact Specimen 2BI4 PROJ. NO.

1150-003 GA ND. 99001 LOAD - TIME TRACE FOR SPECIMEN-B

+

La I,

U3 0

d.

d C

a

.53.099 4.799 B.39e MILLISECONDS 7.99@

FPRAMATOME ANP B-1I

Figure B-21. Load-Time Trace for Charpy V-Notch Impact Specimen 2BI1 PROJ. No.

1150-003 GA NO. 9900f LOAD - TIME TRACE FOR SPECIMEN-8-Ir li\\

Ii.

CL a16319 4.799 6.329 MILLISECONDS 7.M Figure B-22. Load-Time Trace for Charpy V-Notch Impact Specimen BV1 PROJ. NO. J150-003 GA NO.

99O01 LOAD - TIME TRACE FOR SPECIMEN 8VI 4400 0 14DO

-j amO 200

_400 0

1.5 3.199 4.799 5.398 MILLISE0COMIS 7.098 fFRAMATOME ANP B-12

Figure B-23. Load-Time Trace for Charpy V-Notch Impact Specimen 2BD1 PROJ. NO.

1150-003 GA NO.

990o0 LOAD - TINE TRACE FOR SPECIMEN'ftl§ go'i II La 0

A

-J 0

1.0 3.189 4.799 5.398 MILLISECONDS

7. WSi Figure B-24. Load-Time Trace for Charpy V-Notch Impact Specimen 2BG2 PROJ. NO.

1150-003 QA NO.

gGaOI LOAD - TIME TRACE FOR SPECIMEN-BB*,,

QB&,"-

in 0

0a.

-I 01.0 3.11 4,7N 539 WILISECI3NDG 7.,99 fFRAMATOME ANP B-13

Figure B-25. Load-Time Trace for Charpy V-Notch Impact Specimen PB45 PROJ. NO. 1150-003 GA NO. 99001 W0AD - TIME TRACE FOR SPECIMEN PB45 ii ~.moo sw 2MFE CL 14W 01.5 3,192 4.799

.g9 MILLISECONDS 7,991 Figure B-26.

4000 6 M Iiu-Load-Time Trace for Charpy V-Notch Impact Specimen PB62 PROJ. NO, 1150-003 OA *O. 99001 LOAO - TIME TRACE FOR SPECIMEN P862 0002=

ED; 6

.j

.4.3998 1.25999 2.799 MILL I'SCONDS 3.!

f, B-14

Figure B-27. Load-Time Trace for Charpy V-Notch Impact Specimen PB71 PROJ.

NO.

1150-003 GA NO. 9*901 LOAD - TIME TRACE FOR SPECIMEN PB71 ii.

g. oo

-400 1

I I

0

.7996 1.5 2.399 3.199 MILLISECONDS 3.299 Figure B-28. Load-Time Trace for Charpy V-Notch Impact Specimen PB54 PROJ. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN P854 as 50O0 4400 3800 In2600 sL 2000 14DO

-J oN

-400 0.63.199 4.799 5.398 MILLISECONDS 7.M BRAMATOME ANP B-15

Figure B-29. Load-Time Trace for Charpy V-Notch Impact Specimen PB07 PROJ. NO, 1150-003 GA NO. 99001 LDAD - TIME TRACE FOR SPECIMEN PB07 re' 600 320 1400 a

1.6 3.199 4.799 619 MI!LL ISECONDOS

7. B3 Figure B-30. Load-Time Trace for Charpy V-Notch Impact Specimen PB73 PROJ. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FDR SPECI4EN PB73 Sc 4D00 44aO 3200 CL 0000 S1400

-400

.4.~9S1.2

1. 9" 2.799 MILLISECONDS 3.-w fRAMATOME ANP B-16

Figure B-31.

307 1

MO Load-Time Trace for Charpy V-Notch Impact Specimen PB52 PAO. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FMf SPECIMEN PB52

,,1400

.j 1 -

3.199 4,799 5.390 MILLiSMOO1C 7,098 Figure B-32. Load-Time Trace for Charpy V-Notch Impact Specimen PB35 PRUJ. NO. 1150-003 DA ND. 9*O01 LOAD - TIME TRACE FDR SPECIMEN PB35 3000 3M 2M i-40 0.53.199 4.799 6.390 MILL ISECONDS

7. OM8 B-7 RAMATOME ANP B-17

Figure B-33. Load-Time Trace for Charpy V-Notch Impact Specimen PB06 PROJ. HO. 1150-003 CA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN PBO6 0I a-0 40

-j 0

3.199 4,799 MILLI1SECONDS 0.39B 7.990 Figure B-34. Load-Time Trace for Charpy V-Notch Impact Specimen PB58 FIOJ. NO. 1J50-003 GA NO, 99001 LOAD - TIME TRACE FOR SPECINEN PB58

6I.

o

-J 1.5 3.199 4.799 5.398 MILLISECONDS6 7.190 f FRAMATOM ANP B-18

Figure B-35. Load-Time Trace for Charpy V-Notch Impact Specimen PB57 PROJ. NO. 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN PB57 F i

&i 0c

0.

3.199 4.799 6.396 MILL ISECONDS 7.990 Figure B-36. Load-Time Trace for Charpy V-Notch Impact Specimen PB61 PRiJ.

NO.

H50-003 GA NO. 99001 LOAD - TINE TRACE FDR SPECIMEN PBf6

.400

-.5

.799B 2.399 3.999

.0 MILL ISECONDS~

7.19G B-19I' FAMAkTOME AýN B-19

Figure B-37. Load-Time Trace for Charpy V.Notch Impact Specimen 02D2-10 PROJ. NO.

I511-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN 0D20 K

0CL 3200 M00 2000 1400 em 200 rI 1.8 MILLISECONDS B. 399 7.

Figure B-38. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-13 PqOJ. NO.

1150-W03 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN 02D2i3 Ii 44D0 3200 0

4 J

.46

-4.881.2 I.R99 272 MILL ISECONDS 3.599 fRAMATOME ANP B-20

Figure B-39. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-23 PROJ.

NO.

1150-003 GA NO.

g9001 LOAD - TIME TRACE FOR SPECIMEN 020223 0

.0.

-J 0

.7998 1.5 2.399 3.1g9 MILLISECONDS 3.999 Figure B-40. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-17 PfOJ. NO. t150-003 OA NO.

9O001 LOAD - TIME TRACE FOR SPECIMEN 020217 7

5000 40 0JL 2000 9N0 2we

-400 a

I.E 3.199 4.799 5.3m9 MILLI1SECONDS

7. WA BfRAMATOME ANP B-21

Figure B-41. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-2 PROJ.

NO. 1150-003 GA NO. 99001 LOAD - TIME ITACE FOR S'ECINEN 02022 I =

~1 I

U, 0

Q1.

_j 0

1.6 3.199 4.799 8.393 MILLISECONDS 7.996 Figure B-42. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-22 PROJ. NO. 1150-003 GA NO. gg990 LOAD - TIME TRACE FOR SPECIMEN 020222 I-o 4400 w 2600 C5

.400

-. 4

.3998 1.2

1. 99

2. ?9 MILLISECONDS 3, 99 RA B-22

Figure B-43. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-19 PROJ.

NO. 1150-003 GA NO. 99001 LOAD - TrME TRACE FOR SPECD4EN O**2i9 p

BO00 4400

=00 o1400 an 200

-490 1.5 3.199 4.799 5.389 MILL ISECONDS 7.gg8 Figure B-44. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-8 PROJ. NO, 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIHEN 02028 ii 8

a._j

?.a 2.9

.799 5.398 MILL15ECONDS 7.938 tRAMATOME ANP B-23

Figure B-45. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-5 P1IJ. NO, 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECINEN 02025 AL-C:

-I 1.6 3.199 4.799 5.398 MILLISECONDIS 7.183 Figure B-46. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-15 PRODJ.

NO.

1150-003 IA ND. 99001 LOAD -

TIME TRACE FOR SPECIMEN 02D215 I'

_j 44DO 1AM aco 400 3.199 4.799 8.3915 MILLISECONDOS 7.98

'F7RAMATOME ANP B-24

Figure B-47. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-24 PROJ.

NO.

1150-003 DA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN 02D224 I-a' o

0

-j a

3.199 4.799 MIUMlSCOtNCS B.3se 7.B991 Figure B-48. Load-Time Trace for Charpy V-Notch Impact Specimen 02D2-11 PROJ.

NO, 1150-003 GA NO. 99001 LOAD - TIME TRACE FOR SPECIMEN 020211 BM0 4400 100

-J 800 2D0

-4010

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.2 MILL ISECONDE 7.1g8 IfRAMATOME ANP B-25

v t e Letter Sequence Response to RAI
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Initiation Request Acceptance Administration Questions 7 April 2011 Answers 24 May 2011 Results Approval... Other: ML112870050, PNP 2013-046, Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation
MONTHYEAR2011-12-07 [Table View]

PNP 2011-044, Response to Request for Additional Information for Pressurized Thermal Shock Evaluation

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PNP 2011-044, Response to Request for Additional Information for Pressurized Thermal Shock Evaluation

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