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{{#Wiki_filter:NMC Committed to Nuclear Ex ce >2~Palisades Nuclear Plant Operated by Nuclear Management Company, LLC August 2, 2006 ASME, Section Xl, Article IWA-6000 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 ASME Section XI Inservice Inspection 90-Day Report Nuclear Management Company, LLC (NMC) is enclosing the 90-day report for the Palisades Nuclear Plant (PNP) Inservice Testing Program. The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Article IWA-6000, requires that inservice inspection reports be submitted within 90 days following the completion of the most recent refueling outage. PNP completed a refueling outage on May 10, 2006.Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. | {{#Wiki_filter:NMC Committed to Nuclear Ex ce >2 ~ | ||
Paul A. Harden Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway a Covert, Michigan 49043-9530 Telephone: | Palisades Nuclear Plant Operated by Nuclear Management Company, LLC August 2, 2006 ASME, Section Xl, Article IWA-6000 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 ASME Section XI Inservice Inspection 90-Day Report Nuclear Management Company, LLC (NMC) is enclosing the 90-day report for the Palisades Nuclear Plant (PNP) Inservice Testing Program. The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Article IWA-6000, requires that inservice inspection reports be submitted within 90 days following the completion of the most recent refueling outage. PNP completed a refueling outage on May 10, 2006. | ||
269.764.2000 01 ENCLOSURE 1 NUCLEAR MANAGEMENT COMPANY PALISADES NUCLEAR PLANT DOCKET 50-255 August 2, 2006 INSERVICE INSPECTION (ISI) OF CLASS 1, 2 AND 3 SYSTEMS ISI Report 3-9 123 Pages Follow PALISADES NUCLEAR PLANT ENGINEERING PROGRAMS DEPARTMENT Review and Approval Summary TITLE: ISI REPORT 3-9 ISI Engineer / MWAcker Date ASME Programs d V es Supervisor | Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. | ||
/ B fanW gner Date Engineering Progr6s Manager / THFouty Date PALISADES NUCLEAR PLANT 2006 INSERVICE INSPECTION REPORT Submitted in accordance with the American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel (B&PV) Code, Section Xl, Article IWA-6000, 1989 Edition.1. Date: August 2, 2006 2. Plant Owner: Consumers Energy 212 West Michigan Avenue Jackson, Michigan 49201 3. Plant: Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 4 | Paul A. Harden Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway a Covert, Michigan 49043-9530 Telephone: 269.764.2000 01 | ||
: 8. Code Inspector: | ENCLOSURE 1 NUCLEAR MANAGEMENT COMPANY PALISADES NUCLEAR PLANT DOCKET 50-255 August 2, 2006 INSERVICE INSPECTION (ISI) OF CLASS 1, 2 AND 3 SYSTEMS ISI Report 3-9 123 Pages Follow | ||
: 9. Authorized Inspection Agency: 10. Abstract: | |||
2006 INSERVICE INSPECTION 3-9 PALISADES NUCLEAR PLANT Summary Inservice Inspection 3-9 was conducted during the period of November 18, 2004, through May 10, 2006, in accordance with Section 5.5.7 of the Palisades Nuclear Plant Technical Specifications. | PALISADES NUCLEAR PLANT ENGINEERING PROGRAMS DEPARTMENT Review and Approval Summary TITLE: ISI REPORT 3-9 ISI Engineer / MWAcker Date ASME Programs d V es Supervisor / B fanW gner Date Engineering Progr6s Manager / THFouty Date | ||
The American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel (B&PV) Code, Section XI, 1989 Edition controlled the inspections and provided the acceptance criteria for these examinations. | |||
Included in this report are three sections. | PALISADES NUCLEAR PLANT 2006 INSERVICE INSPECTION REPORT Submitted in accordance with the American Society of Mechanical Engineers (ASME) | ||
Section 1 details the examinations that were performed and provides the final inspection results. Section 2 provides a listing of the repairs and replacements that have been performed over the last operating cycle and during the refueling outage. The attached NIS-2 forms document these repairs and replacements. | Boiler and Pressure Vessel (B&PV) Code, Section Xl, Article IWA-6000, 1989 Edition. | ||
Section 3 contains the documentation for acceptance, by analysis, for porosity which was found in a three-inch service water system weld.Inspection Activities This was the second examination of the third period of the third inspection interval.Areas examined during this inspection included A" | : 1. Date: August 2, 2006 | ||
The examinations were conducted by the Consumers Energy non-destructive testing (NDT) services department, Westdyne, and Lambert MacGill Thomas examination personnel, using site-approved procedures. | : 2. Plant Owner: Consumers Energy 212 West Michigan Avenue Jackson, Michigan 49201 | ||
: 3. Plant: Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 | |||
: 4. Unit No: 1 | |||
: 5. Commercial Service Date: December 31, 1971 | |||
: 6. Major Components Inspected: | |||
Mfci National Component Manufacturer Serial No. State No. Board No. | |||
Steam Generator Combustion Eng CE-70277-1 M358176M NB22864 RPV Head Combustion Eng CE-66110 M96725M NB20827 | |||
: 7. Completion Date for Inspections: May 10, 2006 | |||
: 8. Code Inspector: Kenneth L Blake | |||
: 9. Authorized Inspection Agency: Hartford Steam Boiler | |||
: 10. Abstract: See ISI Report | |||
2006 INSERVICE INSPECTION 3-9 PALISADES NUCLEAR PLANT Summary Inservice Inspection 3-9 was conducted during the period of November 18, 2004, through May 10, 2006, in accordance with Section 5.5.7 of the Palisades Nuclear Plant Technical Specifications. The American Society of Mechanical Engineers (ASME) | |||
Boiler and Pressure Vessel (B&PV) Code, Section XI, 1989 Edition controlled the inspections and provided the acceptance criteria for these examinations. Included in this report are three sections. Section 1 details the examinations that were performed and provides the final inspection results. Section 2 provides a listing of the repairs and replacements that have been performed over the last operating cycle and during the refueling outage. The attached NIS-2 forms document these repairs and replacements. | |||
Section 3 contains the documentation for acceptance, by analysis, for porosity which was found in a three-inch service water system weld. | |||
Inspection Activities This was the second examination of the third period of the third inspection interval. | |||
Areas examined during this inspection included A"Nsteam generator and regenerative heat exchanger welds. Various components of the primary coolant system, engineered safeguards system, main steam system, main feedwater system and support systems, as identified in the attached Non-destructive Examination (NDE) Results Summary Report, were also examined. | |||
The examinations were performed using ultrasonic (UT), liquid penetrant (PT), | |||
radiographic (RT), and visual techniques. The examinations were conducted by the Consumers Energy non-destructive testing (NDT) services department, Westdyne, and Lambert MacGill Thomas examination personnel, using site-approved procedures. | |||
Examinations were performed by personnel qualified in the NDT process used, in accordance with the requirements of ASME Section XI, IWA-2300. | Examinations were performed by personnel qualified in the NDT process used, in accordance with the requirements of ASME Section XI, IWA-2300. | ||
SECTION 1 EXAMINATION DETAILS AND FINAL INSPECTION RESULTS FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 1. Owner CON-iw~e~r-3's | |||
\-et-AA | SECTION 1 EXAMINATION DETAILS AND FINAL INSPECTION RESULTS | ||
: 5. Commercial Service Date 1 41 L 6. National Board Number for Unit NB elnl,.a 1 7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.Sv.E "N~sr- Re'sI3iL"! | |||
FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 1.Owner CON-iw~e~r-3's v SA 2 \4k | |||
\-et-AA _*-- | |||
, a J ] | |||
4~~I~ | |||
17-01 (Name aM Address of Owner) U | |||
: 2. PlantPlAnalg5 T7180 Bite- | |||
% 1AW3'CW--rk4KI 41OR3 S., | |||
(Namrn and Address of Plant) | |||
: 3. Plant Unit 4. Owner Certificate of Authorization (if required)___ | |||
: 5. Commercial Service Date 1 41 L 6. National Board Number for Unit NB elnl,.a 1 | |||
: 7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No. | |||
Sv.E "N~sr- Re'sI3iL"! VsyrvsP _____ | |||
4 4 4. 4. | |||
: 4. 4. I. | |||
.1. | |||
* __________ | * __________ | ||
Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y in. x I I in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(12/82)This Form (E00029) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017 FORM NIS-1 (Back)8. Examination Dates 2IhsIzM4Zo | Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y in. x I I in., | ||
.to 5.kZfz9. Inspection Interval from S71)~Sto 12- 1Z Iac.V 10. Abstract of Examinations. | (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. | ||
Include a list of examinations and a statement concerning status of work required for current interval. | (12/82) This Form (E00029) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017 | ||
_. ,. a ."3 | |||
* | FORM NIS-1 (Back) | ||
~4~4 Commissions | : 8. Examination Dates 2IhsIzM4Zo . to 5.kZfz9. Inspection Interval from S71)~Sto 12- 1Z Iac.V | ||
PALISADES NDE RESULTS | : 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. _. ,. a sIt . "3 | ||
: 11. Abstract of Conditions Noted | |||
: 12. Abstract of Corrective Measures Recommended and Taken We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code, Section XI. | |||
Certificate of Authorization No. (if applicable) rt K Expiration Date " I'* | |||
Date ilM 2 fi 1v ZOc.- Signed COrnSVIi'KPg- t 3 By 4 ~ ASLV% | |||
Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the Nlational Board of Boiler and Pressure Vessel Inspectors and the State or Province of *tCX1%x*L6o. *andemployed by H- - C.-! of CCovCC.k %C¢.O*c- have inspected the components described in this Owner's Report during the period W1_w&C,- 1-94 !Ito Mwhl Ws 20-, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. | |||
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personaltinjury or property damage or a loss of any kind arising from or connected with this inspection. | |||
~4~4 Commissions 3cc "4 | |||
-lff Inspector's Signature National Board, State, Province, and Endorsements Date -- L.Y 7 V' 2oo(P | |||
. (12/82) | |||
PALISADES NDE RESULTS | |||
==SUMMARY== | ==SUMMARY== | ||
NIS I Category System Component ID Disposition Exam Comments Aug ESS ESS-24-SIS-SH1-207 Acceptable UT/PT ESS-24-SIS-SH2-207 Acceptable UT/PT ESS-6-SIS-2A1-21 Acceptable UT/PT ESS-6-SIS-2B1-27 Acceptable UT/PT FWS FWS-18-FWL-1SI-245 Acceptable UT/PT FWS-18-FWL-1SI-257 Acceptable UT/PT FWS-18-FWL-1SI-258 Acceptable UT/PT FWS-18-FWL-1S1-261 Acceptable UT/PT FWS-18-FWL-2S1-262 Acceptable UT/PT MSS MSS-36-MSL-1Si-216 Acceptable UT/PT MSS-36-MSL-1S1-216LDI Acceptable UT/PT MSS-36-MSL-1S1-216LDO Acceptable UT/PT MSS-36-MSL-1S1-216LU Acceptable UT/PT MSS-36-MSL-1S1-217 Acceptable UT/PT MSS-36-MSL-1S1-2117LD Acceptable UT/PT MSS-36-MSL-1S1-217LUI Acceptable UT/PT Page 1 of 33 | |||
Category System Component ID Disposition Exam Comments MSS-36-MSL-1 Sl-217LUO Acceptable UT/PT MSS-36-MSL-2S1-218 Acceptable UT/PT MSS-36-MSL-2S1-218LDI Acceptable UT/PT MSS-36-MSL-2S1-218LDI Acceptable UT/PT MSS-36-MSL-2S1-218LU Acceptable UT/PT MSS-36-MSL-2S1-219 Acceptable UT/PT MSS-36-MSL-2S1-219LD Acceptable UT/PT MSS-36-MSL-2S1-219LUD Acceptable UT/PT MSS-36-MSL-2S1-219LUO Acceptable UT/PT MSS-6-RVR-2S4-203 Acceptable UT/PT MSS-6-RVR-2S4-203 Acceptable UT/PT MSS-6-RVR-2S4-203 Acceptable UT/PT MSS-6-RVR-2S6-203 Acceptable UT/PT MSS-8-MSV-1S1-212 Acceptable UT/PT PCS Bowl Plug SGA-1 Acceptable BM Visual Bowl Plug SGA-2 Acceptable BM Visual Bowl Plug SGB-1 Acceptable BM Visual Bowl Plug SGB-2 Acceptable BM Visual Cold Leg Charging A #1 Acceptable BM Visual Page2 of 33 | |||
Category System Component ID Disposition Exam Comments Cold Leg Charging B #2 Acceptable BM Visual Cold Leg Spray CV-1057 #1 Acceptable BM Visual Cold Leg Spray CV-1057 #2 Acceptable BM Visual Cold Leg Spray CV-1059 #1 Acceptable BM Visual Cold Leg Spray CV-1059 #2 Acceptable BM Visual DPT-01a12A Acceptable BM Visual DPT-01 12A/C Acceptable BM Visual DPT-01 12A/C Acceptable BM Visual DPT-01 12B Acceptable BM Visual DPT-01 12BID Acceptable BM Visual DPT-01 12BID Acceptable BM Visual DPT-01 12C Acceptable BM Visual DPT-01 12D Acceptable BM Visual DPT-0122A Acceptable BM Visual DPT-0122A/C Acceptable BM Visual DPT-0122A/C Acceptable BM Visual DPT-0122B Acceptable BM Visual DPT-0122B/D Acceptable BM Visual DPT-0122B/D Acceptable BM Visual DPT-0122C Acceptable BM Visual Page 3 of 33 | |||
Category System Component ID Disposition Exam Comments DPT-0122D Acceptable BM Visual PCS-011 Weld 1 (DPT-O112A/C) Acceptable BM Visual PCS-011 Weld 15 (DPT-0112A) Acceptable BM Visual PCS-01 1 Weld 22 (DPT-01 12AJC) Acceptable BM Visual PCS-01 1 Weld 8 | |||
: 8. Construction Code used for repairs, replacements: | : 8. Construction Code used for repairs, replacements: | ||
(edition) (addenda) (Code Case(s)) | |||
: 9. Design responsibilities: n/a | |||
: 10. Opening pressure: 2485 psig | |||
... Set-pressure adjustment made at NWS Technologies, LLC using steam | |||
: 11. Description of work (Include name and Identifying | |||
: 1. The service life is assumed to be 40 years from the date of this evaluation (40 years + 20 years license extension). | : 1. The service life is assumed to be 40 years from the date of this evaluation (40 years + 20 years license extension). | ||
: 2. For this evaluation is assumed that the location of the flaw will experience 400 cycles of the combined maximum load (Pressure | : 2. For this evaluation is assumed that the location of the flaw will experience 400 cycles of the combined maximum load (Pressure + Deadweight + Seismic + Thermal) which correspond to 40 years of original plant life plus 20 years of license extension. | ||
+ Deadweight | |||
+ Seismic + Thermal) which correspond to 40 years of original plant life plus 20 years of license extension. | |||
: 3. The piping material per the piping specification can be ASTM A-106 Grade B or A53 Grade B or SA-106 Grade B. While the mechanical properties of these materials are identical, ASTM A-106 Grade B will be assumed for this evaluation. | : 3. The piping material per the piping specification can be ASTM A-106 Grade B or A53 Grade B or SA-106 Grade B. While the mechanical properties of these materials are identical, ASTM A-106 Grade B will be assumed for this evaluation. | ||
5 CALCULATIONS 5.1 Allowable Flaw Size Calculation The material of the flaw is assumed to be ferritic steel SA-106 Grade and the maximum operating temperature of the CSW line is 170'F. Therefore, as determined from the screening criteria, the LEFM methodology described in ASME Code, Section XI, Appendix H [1] is used in this evaluation in lieu of the other two failure modes (EPFM and limit load). The technical approach consists of determining the critical flaw size in the pipe which corresponds to a stress intensity factor equal to the material fracture toughness. | 5 CALCULATIONS 5.1 Allowable Flaw Size Calculation The material of the flaw is assumed to be ferritic steel SA-106 Grade and the maximum operating temperature of the CSW line is 170'F. Therefore, as determined from the screening criteria, the LEFM methodology described in ASME Code, Section XI, Appendix H [1] is used in this evaluation in lieu of the other two failure modes (EPFM and limit load). The technical approach consists of determining the critical flaw size in the pipe which corresponds to a stress intensity factor equal to the material fracture toughness. | ||
The allowable flaw size is derived from the critical flaw by applying the code specified safety factors.In this evaluation, default ASME Code Section XI, Appendix H material properties at lower shelf temperature are conservatively used. The evaluation was performed using SI's computer program pc-CRACKTm [8].The pc-CRACK" output file for the analysis is presented in Appendix A. It shows that for the observed flaw length, the allowable flaw depth is 75% of wall thickness, which is greater than the depth of the observed flaw of 65% of wall thickness. | The allowable flaw size is derived from the critical flaw by applying the code specified safety factors. | ||
5.2 Stress Intensity Factors Calculation A linear elastic fracture mechanics and fatigue crack growth evaluation is performed for the observed indication using pc-CRACKTm. | In this evaluation, default ASME Code Section XI, Appendix H material properties at lower shelf temperature are conservatively used. The evaluation was performed using SI's computer program pc-CRACKTm [8]. | ||
The fracture mechanics model of an elliptical surface flaw in an infinite plate, as illustrated in Figure 2, is conservatively used in this evaluation. | The pc-CRACK" output file for the analysis is presented in Appendix A. It shows that for the observed flaw length, the allowable flaw depth is 75% of wall thickness, which is greater than the depth of the observed flaw of 65% of wall thickness. | ||
The model with a flaw aspect ratio of 0.5 is used in the evaluation since the actual ratio is 0.53 for the pipe weld indication under evaluation. | 5.2 Stress Intensity Factors Calculation A linear elastic fracture mechanics and fatigue crack growth evaluation is performed for the observed indication using pc-CRACKTm. The fracture mechanics model of an elliptical surface flaw in an infinite plate, as illustrated in Figure 2, is conservatively used in this evaluation. The model with a flaw aspect ratio of 0.5 is used in the evaluation since the actual ratio is 0.53 for the pipe weld indication under evaluation. | ||
StructuralIntegrity File No.: PAL-09Q-301 Revision: 1 Associates, Inc. Page 5 of 10 | |||
1 Associates, Inc. Page 5 of 10 Using the applied stresses presented in Section 3.5, the stress intensity factors due to the different load combinations are determined. | |||
In the calculation of stress intensity factors, the pressure stress is taken as the membrane stress, which is constant across the wall thickness. | Using the applied stresses presented in Section 3.5, the stress intensity factors due to the different load combinations are determined. In the calculation of stress intensity factors, the pressure stress is taken as the membrane stress, which is constant across the wall thickness. The stresses from the deadweight, seismic and thermal expansion moment loads are taken as linearly varying through-wall bending stresses. | ||
The stresses from the deadweight, seismic and thermal expansion moment loads are taken as linearly varying through-wall bending stresses.The calculated stress intensity factors are presented in Figure 3.5.3 End of Life Fatigue Crack Growth Analysis Since the indication is assumed to be surface connected, the end of life flaw size due to fatigue crack growth is calculated using the fatigue crack growth rate for ferritic steels exposed to water environments. | The calculated stress intensity factors are presented in Figure 3. | ||
The fatigue crack growth rate for carbon and low alloy steel in water environment is given by Appendix A of ASME Code, Section XI as: da/dN = CL | 5.3 End of Life Fatigue Crack Growth Analysis Since the indication is assumed to be surface connected, the end of life flaw size due to fatigue crack growth is calculated using the fatigue crack growth rate for ferritic steels exposed to water environments. | ||
The fatigue crack growth rate for carbon and low alloy steel in water environment is given by Appendix A of ASME Code, Section XI as: | |||
da/dN = CL | |||
* SL | * SL | ||
* dKA5.95 for dK < dKtran da/dN = CU | * dKA5.95 for dK < dKtran da/dN = CU | ||
* SU | * SU | ||
* dKA1.95 for dK >= dKtran where, dK = Kmax -Kmin R = Kmin /Kmax for R <= 0.25: SL = 1.0 SU = 1.0 dKtran = 17.74 for 0.25 < R <= 0.65: SL = 26.9* R -5.725 SU = 3.75 | * dKA1.95 for dK >= dKtran | ||
: where, dK = Kmax - Kmin R = Kmin /Kmax for R <= 0.25: | |||
SL = 1.0 SU = 1.0 dKtran = 17.74 for 0.25 < R <= 0.65: | |||
SL = 26.9* R - 5.725 SU = 3.75 | |||
* R + 0.06 dKtran = 17.74*{(3.75 | * R + 0.06 dKtran = 17.74*{(3.75 | ||
* R + 0.06)/(26.9 | * R + 0.06)/(26.9 | ||
* R -5.725))AO.25 for 0.65 < R: SL = 11.76 SU = 2.5 dKtran = 12.04 where, CL = 1.0200e-012 CU = 1.01OOe-007 for the selected units of force, kip, and length, inch.The fatigue crack growth is performed for the assumed number of 400 cycles of the maximum combined loading. The initial flaw depth of 0.14 inches is used.The results of the fatigue crack growth evaluation show that the flaw in the CSW pipe weld does not grow after 400 cycles of the maximum combined loading range. This is because the stress range and, therefore, the corresponding stress intensity factor range are relatively small.The pc-CRACK T h output file for the crack growth analysis is presented in Appendix A. | * R - 5.725))AO.25 for 0.65 < R: | ||
SL = 11.76 SU = 2.5 dKtran = 12.04 | |||
The allowable flaw depth for the observed combined flaw length is 75% of pipe wall thickness. | : where, CL = 1.0200e-012 CU = 1.01OOe-007 for the selected units of force, kip, and length, inch. | ||
The fatigue crack growth is performed for the assumed number of 400 cycles of the maximum combined loading. The initial flaw depth of 0.14 inches is used. | |||
The results of the fatigue crack growth evaluation show that the flaw in the CSW pipe weld does not grow after 400 cycles of the maximum combined loading range. This is because the stress range and, therefore, the corresponding stress intensity factor range are relatively small. | |||
The pc-CRACK T h output file for the crack growth analysis is presented in Appendix A. | |||
Revision: I StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page 6 of 10 | |||
6 CONCLUSIONS AND DISCUSSIONS Based on the results of the evaluation presented in this calculation package, the indications found during the inservice inspection of the CSW system Line are acceptable for continued operation based on the requirements of ASME Code, Section XI, IWB-3650. The allowable flaw depth for the observed combined flaw length is 75% of pipe wall thickness. | |||
A fatigue crack growth analysis performed using a conservative fracture mechanics model and 400 cycles of the maximum combined loading shows that crack propagation by fatigue is not a concern as the flaw growth did not grow. This indicates that the allowable flaw depth will not be reached during plant operation including 20 years of life extension. | A fatigue crack growth analysis performed using a conservative fracture mechanics model and 400 cycles of the maximum combined loading shows that crack propagation by fatigue is not a concern as the flaw growth did not grow. This indicates that the allowable flaw depth will not be reached during plant operation including 20 years of life extension. | ||
Revision: I StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page 7 of 10 | |||
: 1. ASME Boiler and Pressure Vessel Code, Section XI, 1989 Edition with Addenda through 1990.2. Nuclear Management Company (NMC), Palisades Nuclear Plant Piping Class Summary, SI File No.PAL-09Q-201. | 7 REFERENCES | ||
: 3. Consumers Energy, Palisades Plant Stress Isometric 03316, Drawing No. VEN-M-101, Sheet No.2746, Rev. 6, "Service Water From Engineered Safeguards Cooler V-27 C &D West," SI File No.PAL-09Q-202. | : 1. ASME Boiler and Pressure Vessel Code, Section XI, 1989 Edition with Addenda through 1990. | ||
: 4. NMC Radiographic Examination Report, Sheet Number P-6-8001, dated 4/5/06, SI File No. PAL-09Q-203.5. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Appendices, 1989 Edition.6. NMC Ultrasonic Thickness Examination Report, Sheet Number MAO-01, dated 4/27/06, SI File No.PAL-09Q-204. | : 2. Nuclear Management Company (NMC), Palisades Nuclear Plant Piping Class Summary, SI File No. | ||
PAL-09Q-201. | |||
: 3. Consumers Energy, Palisades Plant Stress Isometric 03316, Drawing No. VEN-M-101, Sheet No.2746, Rev. 6, "Service Water From Engineered Safeguards Cooler V-27 C &D West," SI File No. | |||
PAL-09Q-202. | |||
: 4. NMC Radiographic Examination Report, Sheet Number P-6-8001, dated 4/5/06, SI File No. PAL-09Q-203. | |||
: 5. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Appendices, 1989 Edition. | |||
: 6. NMC Ultrasonic Thickness Examination Report, Sheet Number MAO-01, dated 4/27/06, SI File No. | |||
PAL-09Q-204. | |||
: 7. Partial ADLPIPE Stress Analysis Output for CSW System Piping Analysis, EA-03316, 1/9/1995, SI File No. PAL-09Q-205. | : 7. Partial ADLPIPE Stress Analysis Output for CSW System Piping Analysis, EA-03316, 1/9/1995, SI File No. PAL-09Q-205. | ||
: 8. pc-CRACKTM for Windows, Version 3.1-98348, Structural Integrity Associates, 1998. | : 8. pc-CRACKTM for Windows, Version 3.1-98348, Structural Integrity Associates, 1998. | ||
1 Associates, Inc. Page 8 of 10 | StructuralIntegrity File No.: PAL-09Q-301 Revision: 1 Associates, Inc. Page 8 of 10 | ||
I | C = C0+ C1X+C 2X2 +C X3 C0 CO: surface stress (I=O) | ||
-- | |||
'84 -'98 Structural Integrity Associates, Inc.3315 Almaden Expressway, Suite 24 San Jose, CA 95118-1557 Voice: 408-978-8200 Fax: 408-978-8964 E-mail: pccrack@structint.com Allowable Flaw Size Evaluation Using ASME Section XI, IWB-3640/50 Procedures and Criteria For Circumferential Crack in Carbon Steel Piping Date: Mon May 01 12:29:13 2006 Input Data and Results File: PAL_ALW.CNS Title: PALISADES, ESW PIPE, CRITICAL FLAW EVALUATION Material: | * x A | ||
Seamless/Welded Wrought CS Pipe and Pipe Fitting, YS<=40ksi (Category 1)Material properties: | Section A-A Calculated K is the maximum of K at points 1 and 2 at each crack depth (a) | ||
Design stress = 18.1000 Flow stress = 43.4400 Elastic modulus = 26000.0000 Poisson ratio = 0.3000 Yield stress = 27.1000 JIc: Lower shelf = 45.0000 Upper shelf = 600.0000 The evaluation assumes default material properties for a lower shelf temperature Pipe geometry: Outer diameter = 3.5000 Wall thickness | Ref:, REQUIRED INPUTS: | ||
= 0.2160 Crack geometry: Crack depth = 0.1400 Crack length = 0.2650 Kr' = 0.0256 Sr' = 0.0134 Sc = 1.9077 The flawed pipe is assumed to fail by brittle fracture(LEFM). | ASME Section t: plate thickness XI, 95SEd.ci a: nrximum crack depth (a*x <O.8t) | ||
The allowable flaw size is determined using code formulas.Default safety factors for normal operating (incl. upset and test) condition. | (flaw shape parameter without plastic zone correction factor) | ||
Membrane stress (Pm) 0.5710 (safety factor = 2.7700)Bending stress (Pb) = 0.4480 (safety factor = 2.7700)Expansion stress (Pe) = 0.0020 (safety factor = 1.0000) | Figure 1: Elliptical Crack in Infinite Plate Model Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page 9 of 10 | ||
I Associates, Inc.Page A2 of A15 Design stress -(Pm + Pb) / Sm= 0.0563 KIr (residual stress) =Nominal pipe size= 3. | |||
= 0.024: allowable a/t = 0. | Stress Intensity Factors 0.8 C | ||
0.5 | |||
'84 -'98 Structural Integrity Associates, Inc.3315 Almaden Expressway, Suite 24 San Jose, CA 95118-1557 Voice: 408-978-8200 Fax: 408-978-8964 E-mail: pccrack@structint.com Linear Elastic Fracture Mechanics Date: Mon May 01 12:30:50 2006 Input Data and Results File: PAL_FCG1.LFM Title: PALISADES, ESW PIPE, FATIGUE CRACK GROWTH ANALYSIS Load Cases: Stress Coefficients Case ID CO C1 C2 C3 Type Total 0.965-4.148 0 0 Coeff------ Through | *0.4- | ||
'*0.3-00.2 0.1o 0 9 0.02 0.04 0.06 0.08 0.1 0.12 0.04 0.16 0.18 0.2 C il Crack Depth (in.) | |||
Figure 2: Applied Stress Intensity Factor StructuralIntegriy [File No.: PAL-09Q-301 Revision: I Associates, Inc. Page 10 of 10 | |||
APPENDIX A pc-CRACK OUTPUT FILES Filename Description Pages PALALW.OUT Allowable Flaw Size Calculation A2 - A3 PALFCG1.OUT Fatigue Crack Growth Analysis A4 - A15 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page Al of A15 | |||
pc-CRACK Output File for Allowable Flaw Evaluation tm pc-CRACK for Windows Version 3.1-98348 (C) Copyright '84 - '98 Structural Integrity Associates, Inc. | |||
3315 Almaden Expressway, Suite 24 San Jose, CA 95118-1557 Voice: 408-978-8200 Fax: 408-978-8964 E-mail: pccrack@structint.com Allowable Flaw Size Evaluation Using ASME Section XI, IWB-3640/50 Procedures and Criteria For Circumferential Crack in Carbon Steel Piping Date: Mon May 01 12:29:13 2006 Input Data and Results File: PAL_ALW.CNS | |||
==Title:== | |||
PALISADES, ESW PIPE, CRITICAL FLAW EVALUATION Material: Seamless/Welded Wrought CS Pipe and Pipe Fitting, YS<=40ksi (Category 1) | |||
Material properties: | |||
Design stress = 18.1000 Flow stress = 43.4400 Elastic modulus = 26000.0000 Poisson ratio = 0.3000 Yield stress = 27.1000 JIc: | |||
Lower shelf = 45.0000 Upper shelf = 600.0000 The evaluation assumes default material properties for a lower shelf temperature Pipe geometry: | |||
Outer diameter = 3.5000 Wall thickness = 0.2160 Crack geometry: | |||
Crack depth = 0.1400 Crack length = 0.2650 Kr' = 0.0256 Sr' = 0.0134 Sc = 1.9077 The flawed pipe is assumed to fail by brittle fracture(LEFM). | |||
The allowable flaw size is determined using code formulas. | |||
Default safety factors for normal operating (incl. upset and test) condition. | |||
Membrane stress (Pm) 0.5710 (safety factor = 2.7700) | |||
Bending stress (Pb) = 0.4480 (safety factor = 2.7700) | |||
Expansion stress (Pe) = 0.0020 (safety factor = 1.0000) | |||
StructuralIntegrity File No.: PAL-09Q-301 Revision: I Associates, Inc.Page A2 of A15 | |||
Design stress - 18.1000 (Pm + Pb) / Sm= 0.0563 KIr (residual stress) = 0.0000 (safety factor = 1.0000) | |||
Nominal pipe size= 3.00100 a/t = 0.648:1 l/circumference = 0.024:1 allowable a/t = 0.75040 End of pc-CRACK Output Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A3 of A15 | |||
pc-CRACK Output File for Fatigue Crack Growth Analysis tm pc-CRACK for Windows Version 3.1-98348 (C) Copyright '84 - '98 Structural Integrity Associates, Inc. | |||
3315 Almaden Expressway, Suite 24 San Jose, CA 95118-1557 Voice: 408-978-8200 Fax: 408-978-8964 E-mail: pccrack@structint.com Linear Elastic Fracture Mechanics Date: Mon May 01 12:30:50 2006 Input Data and Results File: PAL_FCG1.LFM | |||
==Title:== | |||
PALISADES, ESW PIPE, FATIGUE CRACK GROWTH ANALYSIS Load Cases: | |||
Stress Coefficients Case ID CO C1 C2 C3 Type Total 0.965 -4.148 0 0 Coeff | |||
------ Wall Through Stresses for Load Cases With Stress Coeff ------- | |||
Wall Case Depth Total 0.0000 0.965 0.0173 0.893323 0.0346 0.821645 0.0518 0.749968 0.0691 0.67829 0.0864 0.606613 0.1037 0.534935 0.1210 0.463258 0.1382 0.39158 0.1555 0.319903 0.1728 0.248226 Crack Model: Elliptical Surface Crack in an Infinite Plate (a/1=0.5) | |||
==Reference:== | ==Reference:== | ||
ASME Boiler and Pressure Vessel Code, Section XI, '95 Ed. | |||
Flaw shape parameter is without plastic zone correction. | |||
WARNING: The stress intensity factor (K) is the maximum of K at the surface and K at the deepest point at each crack depth. | |||
Crack Parameters: | |||
Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A4 of A15 | |||
Plate width: 0.2160 Max. crack size: 0.1728 | |||
-------------------- Stress Intensity Factor ....... | |||
Crack Case Size Total 0.0035 0.0730043 0.0069 0.1031 0.0104 0.126088 0.0138 0.145373 0.0173 0.162275 0.0207 0.177471 0.0242 0.191585 0.0276 0.204768 0.0311 0.217127 0.0346 0.228793 0.0380 0.239861 0.0415 0.250408 0.0449 0.260663 0.0484 0.270693 0.0518 0.280372 0.0553 0.289731 0.0588 0.298798 0.0622 0.307594 0.0657 0.316243 0.0691 0.324987 0.0726 0.333532 0.0760 0.34189 0.0795 0.35007 0.0829 0.358083 0.0864 0.365936 0.0899 0.374191 0.0933 0.382319 0.0968 0.390326 0.1002 0.398215 0.1037 0.405992 0.1071 0.413659 0.1106 0.421651 0.1140 0.4297 0.1175 0.437667 0.1210 0.445556 0.1244 0.453367 0.1279 0.461103 0.1313 0.469093 0.1348 0.477352 0.1382 0.485553 0.1417 0.493699 0.1452 0.50179 0.1486 0.509825 0.1521 0.517955 0.1555 0.526485 0.1590 0.534972 0.1624 0.543417 0.1659 0.551819 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A5 of A15 | |||
0. | 0.1693 0.560177 0.1728 0.568493 Crack Growth Laws: | ||
Law ID: CSteelinWater Model: ASME Section XI - ferritic steel in water environment da/dN = CL | |||
* SL | * SL | ||
* dK^5.95 for dK < dKtran CU | * dK^5.95 for dK < dKtran da/dN = CU | ||
* SU | * SU | ||
* dK-1.95 for dK >= dKtran where dK= Kmax - Kmin R= Kmin / Kmax for R <= 0 .25: | |||
SL = |
Latest revision as of 02:47, 14 March 2020
ML062230275 | |
Person / Time | |
---|---|
Site: | Palisades ![]() |
Issue date: | 08/02/2006 |
From: | Harden P Nuclear Management Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
IWA-6000 | |
Download: ML062230275 (125) | |
Text
NMC Committed to Nuclear Ex ce >2 ~
Palisades Nuclear Plant Operated by Nuclear Management Company, LLC August 2, 2006 ASME, Section Xl, Article IWA-6000 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 ASME Section XI Inservice Inspection 90-Day Report Nuclear Management Company, LLC (NMC) is enclosing the 90-day report for the Palisades Nuclear Plant (PNP) Inservice Testing Program. The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Article IWA-6000, requires that inservice inspection reports be submitted within 90 days following the completion of the most recent refueling outage. PNP completed a refueling outage on May 10, 2006.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Paul A. Harden Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway a Covert, Michigan 49043-9530 Telephone: 269.764.2000 01
ENCLOSURE 1 NUCLEAR MANAGEMENT COMPANY PALISADES NUCLEAR PLANT DOCKET 50-255 August 2, 2006 INSERVICE INSPECTION (ISI) OF CLASS 1, 2 AND 3 SYSTEMS ISI Report 3-9 123 Pages Follow
PALISADES NUCLEAR PLANT ENGINEERING PROGRAMS DEPARTMENT Review and Approval Summary TITLE: ISI REPORT 3-9 ISI Engineer / MWAcker Date ASME Programs d V es Supervisor / B fanW gner Date Engineering Progr6s Manager / THFouty Date
PALISADES NUCLEAR PLANT 2006 INSERVICE INSPECTION REPORT Submitted in accordance with the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel (B&PV) Code, Section Xl, Article IWA-6000, 1989 Edition.
- 1. Date: August 2, 2006
- 3. Plant: Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043
- 4. Unit No: 1
- 5. Commercial Service Date: December 31, 1971
- 6. Major Components Inspected:
Mfci National Component Manufacturer Serial No. State No. Board No.
Steam Generator Combustion Eng CE-70277-1 M358176M NB22864 RPV Head Combustion Eng CE-66110 M96725M NB20827
- 7. Completion Date for Inspections: May 10, 2006
- 8. Code Inspector: Kenneth L Blake
- 9. Authorized Inspection Agency: Hartford Steam Boiler
- 10. Abstract: See ISI Report
2006 INSERVICE INSPECTION 3-9 PALISADES NUCLEAR PLANT Summary Inservice Inspection 3-9 was conducted during the period of November 18, 2004, through May 10, 2006, in accordance with Section 5.5.7 of the Palisades Nuclear Plant Technical Specifications. The American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel (B&PV) Code,Section XI, 1989 Edition controlled the inspections and provided the acceptance criteria for these examinations. Included in this report are three sections. Section 1 details the examinations that were performed and provides the final inspection results. Section 2 provides a listing of the repairs and replacements that have been performed over the last operating cycle and during the refueling outage. The attached NIS-2 forms document these repairs and replacements.
Section 3 contains the documentation for acceptance, by analysis, for porosity which was found in a three-inch service water system weld.
Inspection Activities This was the second examination of the third period of the third inspection interval.
Areas examined during this inspection included A"Nsteam generator and regenerative heat exchanger welds. Various components of the primary coolant system, engineered safeguards system, main steam system, main feedwater system and support systems, as identified in the attached Non-destructive Examination (NDE) Results Summary Report, were also examined.
The examinations were performed using ultrasonic (UT), liquid penetrant (PT),
radiographic (RT), and visual techniques. The examinations were conducted by the Consumers Energy non-destructive testing (NDT) services department, Westdyne, and Lambert MacGill Thomas examination personnel, using site-approved procedures.
Examinations were performed by personnel qualified in the NDT process used, in accordance with the requirements of ASME Section XI, IWA-2300.
SECTION 1 EXAMINATION DETAILS AND FINAL INSPECTION RESULTS
FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 1.Owner CON-iw~e~r-3's v SA 2 \4k
\-et-AA _*--
, a J ]
4~~I~
17-01 (Name aM Address of Owner) U
- 2. PlantPlAnalg5 T7180 Bite-
% 1AW3'CW--rk4KI 41OR3 S.,
(Namrn and Address of Plant)
- 3. Plant Unit 4. Owner Certificate of Authorization (if required)___
- 5. Commercial Service Date 1 41 L 6. National Board Number for Unit NB elnl,.a 1
- 7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
Sv.E "N~sr- Re'sI3iL"! VsyrvsP _____
4 4 4. 4.
- 4. 4. I.
.1.
- __________
Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y in. x I I in.,
(2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00029) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-1 (Back)
- 8. Examination Dates 2IhsIzM4Zo . to 5.kZfz9. Inspection Interval from S71)~Sto 12- 1Z Iac.V
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. _. ,. a sIt . "3
- 11. Abstract of Conditions Noted
- 12. Abstract of Corrective Measures Recommended and Taken We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code,Section XI.
Certificate of Authorization No. (if applicable) rt K Expiration Date " I'*
Date ilM 2 fi 1v ZOc.- Signed COrnSVIi'KPg- t 3 By 4 ~ ASLV%
Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the Nlational Board of Boiler and Pressure Vessel Inspectors and the State or Province of *tCX1%x*L6o. *andemployed by H- - C.-! of CCovCC.k %C¢.O*c- have inspected the components described in this Owner's Report during the period W1_w&C,- 1-94 !Ito Mwhl Ws 20-, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personaltinjury or property damage or a loss of any kind arising from or connected with this inspection.
~4~4 Commissions 3cc "4
-lff Inspector's Signature National Board, State, Province, and Endorsements Date -- L.Y 7 V' 2oo(P
. (12/82)
PALISADES NDE RESULTS
SUMMARY
NIS I Category System Component ID Disposition Exam Comments Aug ESS ESS-24-SIS-SH1-207 Acceptable UT/PT ESS-24-SIS-SH2-207 Acceptable UT/PT ESS-6-SIS-2A1-21 Acceptable UT/PT ESS-6-SIS-2B1-27 Acceptable UT/PT FWS FWS-18-FWL-1SI-245 Acceptable UT/PT FWS-18-FWL-1SI-257 Acceptable UT/PT FWS-18-FWL-1SI-258 Acceptable UT/PT FWS-18-FWL-1S1-261 Acceptable UT/PT FWS-18-FWL-2S1-262 Acceptable UT/PT MSS MSS-36-MSL-1Si-216 Acceptable UT/PT MSS-36-MSL-1S1-216LDI Acceptable UT/PT MSS-36-MSL-1S1-216LDO Acceptable UT/PT MSS-36-MSL-1S1-216LU Acceptable UT/PT MSS-36-MSL-1S1-217 Acceptable UT/PT MSS-36-MSL-1S1-2117LD Acceptable UT/PT MSS-36-MSL-1S1-217LUI Acceptable UT/PT Page 1 of 33
Category System Component ID Disposition Exam Comments MSS-36-MSL-1 Sl-217LUO Acceptable UT/PT MSS-36-MSL-2S1-218 Acceptable UT/PT MSS-36-MSL-2S1-218LDI Acceptable UT/PT MSS-36-MSL-2S1-218LDI Acceptable UT/PT MSS-36-MSL-2S1-218LU Acceptable UT/PT MSS-36-MSL-2S1-219 Acceptable UT/PT MSS-36-MSL-2S1-219LD Acceptable UT/PT MSS-36-MSL-2S1-219LUD Acceptable UT/PT MSS-36-MSL-2S1-219LUO Acceptable UT/PT MSS-6-RVR-2S4-203 Acceptable UT/PT MSS-6-RVR-2S4-203 Acceptable UT/PT MSS-6-RVR-2S4-203 Acceptable UT/PT MSS-6-RVR-2S6-203 Acceptable UT/PT MSS-8-MSV-1S1-212 Acceptable UT/PT PCS Bowl Plug SGA-1 Acceptable BM Visual Bowl Plug SGA-2 Acceptable BM Visual Bowl Plug SGB-1 Acceptable BM Visual Bowl Plug SGB-2 Acceptable BM Visual Cold Leg Charging A #1 Acceptable BM Visual Page2 of 33
Category System Component ID Disposition Exam Comments Cold Leg Charging B #2 Acceptable BM Visual Cold Leg Spray CV-1057 #1 Acceptable BM Visual Cold Leg Spray CV-1057 #2 Acceptable BM Visual Cold Leg Spray CV-1059 #1 Acceptable BM Visual Cold Leg Spray CV-1059 #2 Acceptable BM Visual DPT-01a12A Acceptable BM Visual DPT-01 12A/C Acceptable BM Visual DPT-01 12A/C Acceptable BM Visual DPT-01 12B Acceptable BM Visual DPT-01 12BID Acceptable BM Visual DPT-01 12BID Acceptable BM Visual DPT-01 12C Acceptable BM Visual DPT-01 12D Acceptable BM Visual DPT-0122A Acceptable BM Visual DPT-0122A/C Acceptable BM Visual DPT-0122A/C Acceptable BM Visual DPT-0122B Acceptable BM Visual DPT-0122B/D Acceptable BM Visual DPT-0122B/D Acceptable BM Visual DPT-0122C Acceptable BM Visual Page 3 of 33
Category System Component ID Disposition Exam Comments DPT-0122D Acceptable BM Visual PCS-011 Weld 1 (DPT-O112A/C) Acceptable BM Visual PCS-011 Weld 15 (DPT-0112A) Acceptable BM Visual PCS-01 1 Weld 22 (DPT-01 12AJC) Acceptable BM Visual PCS-01 1 Weld 8 (DPT-01 12C) Acceptable BM Visual PCS-012 Weld i (DPT-0112B) Acceptable BM Visual PCS-012 Weld 15 (DPT-0112D) Acceptable BM Visual PCS-012 Weld 22 (DPT-01 12BID) Acceptable BM Visual PCS-012 Weld 8 (DPT-O112B1/) Acceptable BM Visual PCS-013 Weld 1 (DPT-0122A/C) Acceptable BM Visual PCS-013 Weld 15 (DPT-0122C) Acceptable BM Visual PCS-01 3 Weld 22 (DPT-01 22A/C) Acceptable BM Visual PCS-013 Weld 8 (DPT-0122A) Acceptable BM Visual PCS-014 Weld I (DPT-0122B/D) Acceptable BM Visual PCS-014 Weld 13 (DPT-01 22B1/) Acceptable BM Visual PCS-014 Weld 20 (DPT-0122B) Acceptable BM Visual PCS-014 Weld 6 (DPT-0122D) Acceptable BM Visual PCS-015 Weld I Drain Acceptable BM Visual PCS-015 Weld 1 Drain Acceptable BM Visual PCS-01 6 Weld I Drain Acceptable BM Visual Page 4 of 33
Category System Component ID Disposition Exam Comments PCS-016 Weld 1 Drain Acceptable BM Visual PCS-017 Weld 1 Drain Acceptable BM Visual PCS-017 Weld 1 Drain Acceptable BM Visual PCS-018 Weld 1 Drain Acceptable BM Visual PCS-018 Weld 1 Drain Acceptable BM Visual PCS-023 Weld 1 Acceptable BM Visual PCS-023 Weld 1 Acceptable BM Visual PCS-026 Weld 1 (SX-01 12) Acceptable BM Visual PCS-027 Weld I (SX-1023A) Acceptable BM Visual PCS-035 Weld 11 Acceptable BM Visual PCS-035 Weld 12 Acceptable BM Visual PCS-036 Weld 14 Acceptable BM Visual PCS-036 Weld 15 Acceptable BM Visual PCS-037 Weld 15 Acceptable BM Visual PCS-037 Weld 16 Acceptable BM Visual PCS-038 Weld 14 Acceptable BM Visual PCS-038 Weld 15 Acceptable BM Visual PCS-040 Weld 17 Acceptable BM Visual PCS-041 Weld 48 Acceptable BM Visual PCS-042 Weld 1 Acceptable BM Visual Page 5 of 33
Category System Component ID Disposition Exam Comments PCS-042 Weld 10 Acceptable BM Visual PCS-042 Weld 2 Acceptable BM Visual PCS-042 Weld 3 Acceptable BM Visual PCS-042 Weld 4 Acceptable BM Visual PCS-042 Weld 5 Acceptable BM Visual PCS-042 Weld 6 Acceptable BM Visual PCS-042 Weld 7 Acceptable BM Visual PCS-042 Weld 8 Acceptable BM Visual PCS-042 Weld 9 Acceptable BM Visual PCS-043 Weld 1 Acceptable BM Visual PCS-043 Weld 10 Acceptable BM Visual PCS-043 Weld 11 Acceptable BM Visual PCS-043 Weld 12 Acceptable BM Visual PCS-043 Weld 2 Acceptable BM Visual PCS-043 Weld 3 Acceptable BM Visual PCS-043 Weld 4 Acceptable BM Visual PCS-043 Weld 5 Acceptable BM Visual PCS-043 Weld 6 Acceptable BM Visual PCS-043 Weld 7 Acceptable BM Visual PCS-043 Weld 8 Acceptable BM Visual Page 6 of 33
Category System Component ID Disposition Exam Comments PCS-043 Weld 9 Acceptable BM Visual PCS-12-PSL-1H1-7 Acceptable UT PCS-12-PSL-1H1-7 Acceptable BM Visual PCS-12-PSL-iH1-8 Acceptable BM Visual PCS-12-PSL-iH1-8 Acceptable UT PCS-12-SCS-2H1-l Acceptable BM Visual PCS-12-SCS-2H1-2 Acceptable BM Visual SX-0112 Acceptable BM Visual SX-1023A Acceptable BM Visual PZR PCS-12-PSL-IH1-1 Acceptable UT PCS-12-PSL-1Hi-i Acceptable BM Visual PCS-12-PSL-1H1-2 Acceptable BM Visual PCS-12-PSL-1Hi-2 Acceptable UT PCS-4-PSS-1 P1-20 Acceptable BM Visual PCS-4-PSS-1P1-21 Acceptable BM Visual Pressurizer Heater Sleeves Acceptable BM Visual RVH 119-01-A Acceptable BM Visual 119-01-A Acceptable UT 119-01-B Acceptable BM Visual Page 7 of 33
Category System Component ID Disposition Exam Comments 119-02-A Acceptable BM Visual 119-02-A Acceptable UT 119-02-B Acceptable BM Visual 119-03-A Acceptable BM Visual 119-03-A Acceptable UT 119-03-B Acceptable BM Visual 119-04-A Acceptable BM Visual 119-04-A Acceptable UT 119-04-B Acceptable BM Visual 119-05-A Acceptable UT 119-05-A Acceptable BM Visual 119-05-B Acceptable BM Visual 119-06-A Acceptable UT 119-06-A Acceptable BM Visual 119-06-B Acceptable BM Visual 119-07-A Acceptable UT 119-07-A Acceptable BM Visual 119-07-B Acceptable BM Visual 119-08-A Acceptable BM Visual 119-08-A Acceptable UT Page 8 of 33
Category System Component ID Disposition Exam Comments 119-08-B Acceptable BM Visual 119-09-A Acceptable BM Visual 119-09-A Acceptable UT 119-09-B Acceptable BM Visual 119-1 0-A Acceptable BM Visual 119-10-A Acceptable UT 119-10-B Acceptable BM Visual 119-11-A Acceptable BM Visual 119-11-A Acceptable UT 119-11-B Acceptable BM Visual 119-12-A Acceptable BM Visual 119-12-A Acceptable UT 119-12-B Acceptable BM Visual 119-13-A Acceptable BM Visual 119-13-A Acceptable UT 119-13-B Acceptable BM Visual 119-14-A Acceptable BM Visual 119-14-A Acceptable UT 119-14-B Acceptable BM Visual 119-15-A Acceptable UT Page 9 of 33
Category System ComponentID Disposition Exam Comments 119-15-A Acceptable BM Visual 119-15-B Acceptable BM Visual 119-16-A Acceptable BM Visual 119-16-A Acceptable UT 119-16-B Acceptable BM Visual 119-17-A Acceptable UT 119-17-A Acceptable BM Visual 119-17-B Acceptable BM Visual 119-18-A Acceptable UT 119-18-A Acceptable BM Visual 119-18-B Acceptable BM Visual 119-19-A Acceptable BM Visual 119-19-A Acceptable UT 119-19-B Acceptable BM Visual 119-20-A Acceptable UT 119-20-A Acceptable BM Visual 119-20-B Acceptable BM Visual 119-21-A Acceptable UT 119-21-A Acceptable BM Visual 119-21-B Acceptable BM Visual Page 10 of 33
Category System Component ID Disposition Exam Comments II I mile 119-22-A Acceptable UT 119-22-A Acceptable BM Visual 119-22-B Acceptable BM Visual 119-23-A Acceptable UT 119-23-A Acceptable BM Visual 119-23-B Acceptable BM Visual 119-24-A Acceptable UT 119-24-A Acceptable BM Visual 119-24-B Acceptable BM Visual 119-25-A Acceptable BM Visual 119-25-A Acceptable UT 119-25-B Acceptable BM Visual 119-26-A Acceptable BM Visual 119-26-A Acceptable UT 119-26-B Acceptable BM Visual 119-27-A Acceptable BM Visual 119-27-A Acceptable UT 119-27-B Acceptable BM Visual 119-28-A Acceptable BM Visual 119-28-A Acceptable UT Page 11 of 33
Category System Component ID Disposition Exam Comments 119-28-B Acceptable BM Visual 119-29-AR Acceptable UT 119-29-AR Acceptable BM Visual 119-29-B Acceptable BM Visual 119-30-AR Acceptable UT 119-30-AR Acceptable BM Visual 119-30-B Acceptable BM Visual 119-31-A Acceptable UT 119-31-A Acceptable BM Visual 119-31-B Acceptable BM Visual 119-32-A Acceptable UT 119-32-A Acceptable BM Visual 119-32-B Acceptable BM Visual 119-33-A Acceptable UT 119-33-A Acceptable BM Visual 119-33-B Acceptable BM Visual 119-34-A Acceptable UT 119-34-A Acceptable BM Visual 119-34-B Acceptable BM Visual 119-35-A Acceptable UT Page 12 of 33
Category System Component ID Disposition Exam Comments 119-35-A Acceptable BM Visual 119-35-B Acceptable BM Visual 119-36-A Acceptable UT 119-36-A Acceptable BM Visual 119-36-B Acceptable BM Visual 119-37-A Acceptable UT 119-37-A Acceptable BM Visual 119-37-B Acceptable BM Visual 119-38-A Acceptable UT 119-38-A Acceptable BM Visual 119-38-B Acceptable BM Visual 119-39-A Acceptable UT 119-39-A Acceptable BM Visual 119-39-B Acceptable BM Visual 119-40-A Acceptable UT 119-40-A Acceptable BM Visual 119-40-B Acceptable BM Visual 119-41-A Acceptable BM Visual 119-41-A Acceptable UT 119-41-B Acceptable BM Visual Page 13 of 33
Category System Component ID Disposition Exam Comments 1 19-42-A Acceptable BM Visual 119-42-A Acceptable UT 119-42-8 Acceptable BM Visual 119-43-A Acceptable UT 119-43-A Acceptable BM Visual 119-43-B Acceptable BM Visual 119-44-A Acceptable BM Visual 119-44-A Acceptable UT 119-44-B Acceptable BM Visual 119-45-A Acceptable BM Visual 119-45-A Acceptable UT 119-45-B Acceptable BM Visual 119-46 Acceptable BM Visual 119-46 Acceptable UT 119-46-A Acceptable BM Visual 119-47 Acceptable BM Visual 119-47 Acceptable UT 119-47-A Acceptable BM Visual 119-48 Acceptable BM Visual 119-48 Acceptable UT Page 14 of 33
Category System Component ID Disposition Exam Comments 119-48-A Acceptable BM Visual 119-49 Acceptable UT 119-49 Acceptable BM Visual 119-49-A Acceptable BM Visual 119-50 Acceptable UT 119-50 Acceptable BM Visual 119-50-A Acceptable BM Visual 119-51 Acceptable BM Visual 119-51 Acceptable UT 119-51-A Acceptable BM Visual 119-52 Acceptable BM Visual 119-52 Acceptable UT 119-52-A Acceptable BM Visual 119-53 Acceptable UT 119-53 Acceptable BM Visual 119-53-A Acceptable BM Visual PCS-034A Weld 1 Acceptable BM Visual RPV Vent Line Acceptable UT RPV Vent Line Acceptable BM Visual B-B Page 15 of 33
Category System Component ID Disposition Exam Comments PZR Pressurizer T-72 Weld 2-982A Acceptable UT RGA Regen Heat Exchanger Weld E- Acceptable UT 56A-03 Regen Heat Exchanger Weld E- Acceptable UT 56A-04 SGI SG No.1 E-50A Weld 1-101-251 Acceptable UT SG No.1 E-50A Weld 1-1402-271 Acceptable UT SG No.1 E-50A Weld 1-1404-271 Acceptable UT B-D RGA Regen Heat Exchanger Weld E- Acceptable UT 56A-05 Regen Heat Exchanger Weld E- Acceptable UT 56A-05-IRS Regen Heat Exchanger Weld E- Acceptable UT 56A-07 RGB Regen Heat Exchanger Weld E- Acceptable UT 56B-05 Regen Heat Exchanger Weld E- Acceptable UT 56B-05-IRS Regen Heat Exchanger Weld E- Acceptable UT 56B-07 SGI SG No.1 E-50A Weld 1-102-251A Acceptable UT SG No. 1 E-50A Weld 1-102-251A- Acceptable UT IRS SG No.1 E-50A Weld 1-102-251B Acceptable UT SG No.1 E-50A Weld 1-102-251B- Acceptable UT IRS Page 16 of 33
Category System Component ID Disposition Exam Comments SG No.1 E-50A Weld 1-104-251 Acceptable UT SG No.1 E-50A Weld 1-104-251- Acceptable UT IRS B-G-1 RPV RPV-Ligaments Acceptable UT RVH RPVCH SIN 37 Nut Acceptable MT RPVCH S/N 37 Stud Acceptable UT/MT RPVCH S/N 37 Washer Acceptable VT7-1 RPVCH S/N 38 Nut Acceptable MT RPVCH SIN 38 Stud Acceptable UT/MT RPVCH SIN 38 Washer Acceptable VT7-I RPVCH S/N 39 Nut Acceptable MT RPVCH SIN 39 Stud Acceptable UT/MT RPVCH S/N 39 Washer Acceptable VTI-I RPVCH SIN 40 Nut Acceptable MT RPVCH SIN 40 Stud Acceptable UT/MT RPVCH SIN 40 Washer Acceptable VT-1 RPVCH S/N 41 Nut Acceptable MT RPVCH S/N 41 Stud Acceptable UT/MT RPVCH SIN 41 Washer Acceptable VT-1 Page 17 of 33
Category System Component ID Disposition Exam Comments RPVCH S/N 42 Nut Acceptable MT RPVCH SIN 42 Stud Acceptable UT/MT RPVCH SIN 42 Washer Acceptable VT-1 RPVCH S/N 43 Nut Acceptable MT RPVCH S/N 43 Stud Acceptable UT/MT RPVCH S/N 43 Washer Acceptable VT-I RPVCH SIN 44 Nut Acceptable MT RPVCH SIN 44 Stud Acceptable UT/MT RPVCH SIN 44 Washer Acceptable VT-1 RPVCH SIN 45 Nut Acceptable MT RPVCH SIN 45 Stud Acceptable UT/MT RPVCH SIN 45 Washer Acceptable VT-I RPVCH SIN 46 Nut Acceptable MT RPVCH SIN 46 Stud Acceptable UT/MT RPVCH SIN 46 Washer Acceptable VT-1 RPVCH SIN 47 Nut Acceptable MT RPVCH SIN 47 Stud Acceptable UT/MT RPVCH SIN 47 Washer Acceptable VT-1 RPVCH SIN 48 Nut Acceptable MT RPVCH SIN 48 Stud Acceptable UT/MT Page 18 of 33
Category System Component ID Disposition Exam Comments RPVCH SIN 48 Washer Acceptable VT-1 RPVCH S/N 49 Nut Acceptable MT RPVCH S/N 49 Stud Acceptable UT/MT RPVCH SIN 49 Washer Acceptable VT-1 RPVCH SIN 50 Nut Acceptable MT RPVCH SIN 50 Stud Acceptable UT/MT RPVCH SIN 50 Washer Acceptable VT-1 RPVCH SIN 51 Nut Acceptable MT RPVCH SIN 51 Stud Acceptable UT/MT RPVCH SIN 51 Washer Acceptable VT-1 RPVCH S/N 52 Nut Acceptable MT RPVCH SIN 52 Stud Acceptable UT/MT RPVCH SIN 52 Washer Acceptable VT-1 RPVCH S/N 53 Nut Acceptable MT RPVCH S/N 53 Stud Acceptable UT/MT RPVCH SIN 53 Washer Acceptable VT-1 RPVCH SIN 54 Nut Acceptable MT RPVCH SIN 54 Stud Acceptable UT/MT RPVCH S/N 54 Washer Acceptable VT-1 B-G-2 Page 19 of 33
Category System Component ID Disposition Exam Comments ESS CK3118-BT Acceptable VT-1 PIA Primary Coolant Pump P-50A 1A- Acceptable VT-I 2BT-B-1-16 Primary Coolant Pump P-50A 1A- Acceptable VT-1 2BT-W-1-16 PIB 1B-2BT-B-1-16 Acceptable VT-1 I B-2BT-W-I -16 Acceptable VT-1 PCs M03016-BT Acceptable VT-1 PCS-4-PRS-1P2-3BT Acceptable VT-1 PCS-4-PRS-1 P3-8BT Acceptable VT-1 SGI SG No.2 E-50B Primary Manway Acceptable VT-1
- 1 Studs SG No.2 E-50B Primary Manway Acceptable VT-i
- 2 Studs SG2 SG No.1 E-50A Primary Manway Acceptable VT-1
- 1 SG No.1 E-50A Primary Manway Acceptable VT-i
Category System Component ID Disposition Exam Comments 1-102-221 Acceptable UT 1-201-246 Acceptable UT C-B SGI 1-104-221 Acceptable UT 1-105-201-IRS Acceptable MT 1-1510-271 Acceptable PT C-C ESS ESS-1 2-SIS-1A1-3PL1-4(H739) Acceptable PT ESS-1 2-SIS-1 BI-7PL1-4(H728) Acceptable PT ESS-6-LTC-1A-203PL1 -4(H726) Acceptable PT ESS-6-LTC-1A-218PL1-4(H722) Acceptable PT FWS FWS-18-FWL-2S1-257PL1- Acceptable PT 4(H32A)
MSS MSS-36-MSL-1S1-210PL Acceptable MT MSS-36-MSL-2S1-212PL Acceptable MT SGI 1-A Acceptable MT 1-B Acceptable MT 1-C Acceptable MT 1-D Acceptable MT Page 21 of 33
Category System Component ID Disposition Exam Comments 1-E Acceptable MT 1-F Acceptable MT D-B CCS CCS-10-RWS-1P1-PR1-DB(H8) Acceptable VT-3 CCS-16-CPU-1 PA-PS(H323) Acceptable VT-3 CCS-20-CPU-1PA-PS(H303.2) Acceptable VT-3 FWS FWS-6-AWS-SLC-PS Acceptable VT-3 SwS SWS-10-CRS-RLI-PS(H302) Acceptable Vr-3 SWS-10-CRS-RL1 -PS1 Acceptable VT-3 SWS-10-CRS-RL3-PS5 Acceptable VT-3 SWS-10-CRS-RL4-PR1-DB Acceptable VT-3 SWS-10-CRS-SL3-PS4 Acceptable vr-3 SWS-10-CRS-SL3-PS5 Acceptable VT-3 SWS-16-CRS-SH1-PR-DB Acceptable VT-3 SWS-16-SWP-OLA-PS(H9) Acceptable Vr-3 SWS-24-CSW-SH1-PSA1 Acceptable VT-3 SWS-6-CRS-2S1-PS(H297) Acceptable vr-3 SWS-6-CRS-2S2-PS1 (H28) Acceptable VT-3 Page 22 of 33
Category System Component ID Disposition Exam Comments SWS-6-CRS-3S1 -PSI (H27) Acceptable VT-3 SWS-6-CRS-4R2-PS3(HI8) Acceptable VT-3 SWS-6-CRS-4S1-PSI(Hi 1) Acceptable VT-3 SWS-6-CRS-4S2-PS1 (HI 0) Acceptable Vr-3 SWS-6-EPS-SLB-PR3B- Acceptable VT-3 DB(H67.1)
SWS-8-CRS-RL2-PS2(H39) Acceptable VT-3 F-A CCS CCS-1O-RWS-1P1-PR1 (H8) Acceptable Vr-3 CCS-16-CPU-I PA-PSS(H323) Acceptable VT-3 CCS-20-CPU-1PA-PSS(H303.2) Acceptable Vr-3 CSA P-54A-02 Acceptable V'-3 ESS ESS-10-SDC-XIA-202PR(H 120.1) Acceptable VT-3 ESS-12-SIS-1B1-7PR(H728) Acceptable VT-3 ESS-12-SIS-1LP-219PR(R143.1) Acceptable VT-3 ESS-14-SIS-HPA-207PR1 Acceptable VT-3 ESS-14-SIS-HPA-207PR2 Acceptable VT-3 ESS-24-SIS-SH1-203PR(H169.1) Acceptable VT-3 ESS-24-SIS-SH1-209PR1(H 169) Acceptable VT-3 Page 23 of 33
Category System Component ID Disposition Exam Comments 77777-=
ESS-6-SIS-2B1-16PR(R-770.1) Acceptable Vr-3 ESS-6-SIS-2B 1-20PR(H-767) Acceptable VT-3 ESS-8-SIS-HPB-207PR(H1 79) Acceptable VT-3 FWS FWS-18-FWL-1Si - Acceptable VT-3 256APR(R32.1)
FWS-6-AWS-OLC-PR2 (H4) Acceptable Vr-3 FWS-6-AWS-SLC-PSS (H4) Acceptable Vr-3 HSB P-66B-02 Acceptable VT-3 LSB P-67B-02 Acceptable VT-3 PCs PCS-4-PSS-1PI-5PR(H-22A) Acceptable VT-3 PZR Pressurizer T-72 Weld 4-984/5- Acceptable VIT-3 984-SS RGA Regen Heat Exchanger Weld E- Acceptable VT-3 56A-S-01 SGI I-A-SS Acceptable V17-3 1-B-SS Acceptable Vr-3 1-c-SS Acceptable Vr-3 1-D-SS Acceptable VT-3 I-E-SS Acceptable VT-3 Page24 of 33
Category System Component ID Disposition Exam Comments 1-F-SS Acceptable VT-3 SG No.1 E-50A 1-SK-SS Acceptable VT-3 SiS ESS-6-SIS-2HP-216PRA(R203.1) Acceptable Vr-3 SwS SWS-10-CRS-RL1-PSS(H302) Acceptable VT-3 SWS-10-CRS-RL1-PSS1(H48) Acceptable VT-3 SWS-10-CRS-RL3-PSS5(H264) Acceptable VT-3 SWS-10-CRS-RL4-PRi(H275) Acceptable VT-3 SWS-10-CRS-SL3-PSS4(H254) Acceptable VT-3 SWS-10-CRS-SL3-PSS5(H256) Acceptable VT-3 SWS-16-CRS-SH 1-PR(H284) Acceptable Vr-3 SWS-16-SWP-OLA-PSS(H9) Acceptable Vr-3 SWS-24-CSW-SH1- Acceptable VT-3 PSSA1(H281.1)
SWS-6-CRS-2S1-PSS(H297) Acceptable V'-3 SWS-6-CRS-2S2-PSSI(H28) Acceptable V'-3 SWS-6-CRS-3S1-PSS 1(H27) Acceptable VT-3 SWS-6-CRS-4R2-PSS3(H 18) Acceptable VT-3 SWS-6-CRS-4S1-PSS1(HI1) Acceptable VT-3 SWS-6-CRS-4S2-PSSI(H1O) Acceptable Vr-3 SWS-6-EPS-SLB-PR3B(H67.1) Acceptable VT-3 Page25 of 33
Category System Component ID Disposition Exam Comments SWS-8-CRS-RL2-PSS2(H39) Acceptable VT-3 VAS VAS-8-CPU-RL1-205PR(H1) Acceptable VT-3 R-A AFW Segment AFW-010 Acceptable VT-2 Segment AFW-01 1 Acceptable VT-2 Segment AFW-012 Acceptable VT-2 Segment AFW-016 Acceptable VT-2 Segment AFW-018 Acceptable VT-2 BLD Segment BLD-003 Acceptable VT-2 Segment BLD-004 Acceptable VT-2 Segment BLD-005A Acceptable VT-2 Segment BLD-006A Acceptable VT-2 CBA Segment CBA-012 Acceptable VT-2 CDS CDS-014 Weld 12 Acceptable UT CSW CSW-006B Weld 4 Acceptable UT CSW-007 Weld 7 Acceptable UT CSW-008 Weld 5 Acceptable UT Page 26 of 33
Category System Component ID Disposition Exam Comments CSW-009 Weld 1 Acceptable UT CSW-016 Weld 2 Acceptable UT CSW-017 Weld 2 Acceptable UT CwS Segment CWS-01 1 Acceptable V17-2 Segment CWS-012 Acceptable VT-2 FWS AFW-010 Weld 4 Acceptable UT AFW-012 Weld 9 Acceptable UT HED HED-001 Weld 5 Acceptable UT HED-002 Weld 3 Acceptable UT HED-005 Weld 20 Acceptable UT LPI LPI-002 Weld 12 Acceptable UT LPI-002 Weld 13 Acceptable UT LPI-002A Weld 19 Acceptable UT LPI-002A Weld 21 Acceptable UT LPI-004 Weld 12 Acceptable UT LPI-004 Weld 13 Acceptable UT LPI-004A Weld 26 Acceptable UT Page27 of 33
Category System Component ID Disposition Exam Comments LPI-004A Weld 27 Acceptable UT Segment LPI-001A Acceptable VT-2 Segment LPI-002A Acceptable VT-2 Segment LPI-003A Acceptable VT-2 Segment LPI-004A Acceptable VT-2 MSS MSS-027 Weld 3 Acceptable UT MSS-041 Weld 2 Acceptable UT MSS-047 Weld 25 Acceptable UT MSS-048 Weld 5 Acceptable UT MSS-049 Weld 8 Acceptable UT MSS-059 Weld 41 Acceptable UT MSS-060 Weld 36 Acceptable UT MSS-067 Weld 2 Acceptable UT MSS-069 Weld 2 Acceptable UT MSS-071 Weld 5 Acceptable UT MSS-076 Weld 3 Acceptable UT Segment MSS-048 Acceptable VT-2 Segment MSS-049 Acceptable VT-2 NSW NSW-001 Weld 38 Acceptable UT Page28 of 33
Category System Component ID Disposition Exam Comments NSW-004 Weld 6 Acceptable UT NSW-005 Weld 45 Acceptable UT NSW-01 OA Weld 23 Acceptable by RT See Section 3 Analysis EC-7950 NSW-01 OC Weld 6 Acceptable UT Segment NSW-005 Acceptable VT-2 PCs PCS-036 Weld 14 Acceptable UT PCS-036 Weld 15 Acceptable UT Segment PCS-01 1 Acceptable Vr-2 Segment PCS-012 Acceptable Vr-2 Segment PCS-013 Acceptable VT-2 Segment PCS-014 Acceptable Vr-2 Segment PCS-015 Acceptable VT-2 Segment PCS-016 Acceptable VT-2 Segment PCS-017 Acceptable VT-2 Segment PCS-018 Acceptable VT-2 Segment PCS-019A Acceptable VT-2 Segment PCS-019B Acceptable VT-2 Segment PCS-020A Acceptable VT-2 Segment PCS-020B Acceptable Vr-2 Page 29 of 33
Category System Component ID Disposition Exam Comments Segment PCS-021A Acceptable VT-2 Segment PCS-021 B Acceptable VT-2 Segment PCS-022A Acceptable VT-2 Segment PCS-022B Acceptable VT-2 Segment PCS-023 Acceptable VT-2 Segment PCS-026 Acceptable VT-2 Segment PCS-027 Acceptable VT-2 Segment PCS-034A Acceptable VT-2 Segment PCS-040 Acceptable VT-2 Segment PCS-041 Acceptable VT-2 Segment PCS-042 Acceptable VT-2 Segment PCS-043 Acceptable VT-2 PZR PZR-001 Weld I Acceptable UT PZR-001 Weld 2 Acceptable UT PZR-001 Weld 7 Acceptable UT PZR-001 Weld 8 Acceptable UT PZR-016 Weld 14 Acceptable UT PZR-017 Weld 22 Acceptable UT Segment PZR-002 Acceptable Vr-2 Page30 of 33
Category System Component ID Disposition Exam Comments Segment PZR-003 Acceptable VT-2 Segment PZR-004 Acceptable VT-2 Segment PZR-005 Acceptable VT-2 Segment PZR-006 Acceptable VT-2 Segment PZR-007 Acceptable VT-2 Segment PZR-008 Acceptable VT-2 Segment PZR-009 Acceptable VT-2 Segment PZR-010 Acceptable VT-2 Segment PZR-014A Acceptable VT-2 Segment PZR-015 Acceptable VT-2 Segment PZR-018 Acceptable VT-2 Segment PZR-019 Acceptable VT-2 Segment PZR-020 Acceptable VT-2 SDC SDC-002B1 Weld 26 Acceptable UT SDC-002B1 Weld 26LDI Acceptable UT SDC-002B1 Weld 26LDO Acceptable UT SDC-002B1 Weld 26LU Acceptable UT SDC-002B2 Weld 9 Acceptable UT SDC-002B2 Weld 9LD Acceptable UT Page 31 of 33
Category System Component ID Disposition Exam Comments SDC-002B2 Weld 9LUI Acceptable UT SDC-002B2 Weld 9LUO Acceptable UT SDC-005 Weld 3 Acceptable UT SDC-005 Weld 3LDI Acceptable UT SDC-005 Weld 3LDI Acceptable UT SDC-005 Weld 3LU Acceptable UT SDC-011A1 Weld 2 Acceptable UT SDC-011A1 Weld 2LD Acceptable UT SDC-01 1A2 Weld 5 Acceptable UT SDC-012A1 Weld 2 Acceptable UT Segment SDC-002B1 Acceptable VT-2 Segment SDC-005 Acceptable VT-2 Segment SDC-006 Acceptable VT-2 Segment SDC-009 Acceptable VT-2 Segment SDC-011A2 Acceptable VT-2 Segment SDC-012A2 Acceptable VT-2 Segment SDC-021 B Acceptable VT-2 SSS Segment SSS-001A Acceptable VT-2 Segment SSS-001 B Acceptable V17-2 Page 32 of 33
Category System Component ID Disposition Exam Comments Segment SSS-002A Acceptable VT-2 Segment SSS-002B Acceptable VT-2 Segment SSS-005A Acceptable VT-2 Segment SSS-006A Acceptable VT-2 Segment SSS-007 Acceptable VT-2 Segment SSS-008A Acceptable VT-2 Segment SSS-009 Acceptable VT-2 SSS-007 Weld 2 Acceptable RT SSS-007 Weld 22 Acceptable RT SSS-007 Weld 3 Acceptable RT SSS-007 Weld 32 Acceptable RT SSS-007 Weld 66 Acceptable RT SSS-007 Weld 69 Acceptable RT Page33 of 33
SECTION 2 ASME SECTION XI REPAIRS AND REPLACEMENTS
ASME Section XI Repairs and Replacements The following is a list of the repairs or replacements which have been performed through the restart from the 2006 refueling outage for which NIS-2 forms are attached.
Work Order Description of Work
- 1. 19400 Rebuilt Service Water Pump P-7C
- 2. 26320 Replaced Snubber SNB-38
- 3. 16739 Replaced Valve MV-SW1 36
- 4. 21496 Replaced SIRW Tank Recirc Pump P-74
- 5. 27257 Replaced Valve CV-0826
- 6. 27405 Replaced Valve CV-0823
- 7. 25184 Replaced Valves CV-0821/MV-SW769
- 8. 25693 Replaced Valves CV-0822/MV-SW770
- 9. 29819 Repaired VHX-4
- 10. 26963 Plugged 22 tubes in the "A" Steam Generator
- 11. 26964 Plugged 10 tubes in the "B" Steam Generator
- 12. 20457 Replaced Valve CV-3070
- 13. 270650 Installed Weldolet and Cap on CSW Line
- 14. 25456 Replaced Steam Generator Studs
- 15. 269848 Repaired RV-0703
- 16. 269853 Repaired RV-0705
- 17. 267581 Repaired RV-0706
- 18. 269856 Repaired RV-0707
- 19. 269857 Repaired RV-0715
- 20. 26379 Repaired RV-0716
- 21. 269863 Repaired RV-0721
- 22. 269864 Repaired RV-0722
- 23. 26226 Repaired RV-1041
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM C
- 1. Owner Consumers Energy Company Date 6126/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO# 19400 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Nuclear Management Company, LLC Type Code Symbol Stamp N/A Name 27780 Blue Star Hwy, Covert, M!49043 Authorization N/A Address Expiration Date N/A
- 4. Identification of System SWS Code Class Class 3
- 5. (a) Applicable Construction Code B31.1 1955 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None
- 6. Identification of Components
- 7. Description of Work Rebuild Service Water Pump P-7C Using Rebuilt Bowl Assembly per EAR-2001-0542
- 8. Tests conducted: Hydrostatic -- Pneumatic[] Nominal Operating Pressure Exempt[]
Other [] Pressure psi Test Temp. 0F Other: N/A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 112 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Authorization No. N/A Expiration Date N/A Signed ASME Program Engineer Date _____ ___ ,' _____
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HS13-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
_-_______ __ _ Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date , aw&
I rPALISADES NUCLEAR POWER PLANT ACTIVITY FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ITEM
- 1. Owner Consumers Energy Company Date 511/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO# 26320 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Name Typo Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A
- 4. Identification of System ESS Code Class Class 2
- 5. (a) Applicable Construction Code B31.1 1989 Edition Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
Snubber Anchor Darling ADH-1000-2487 n/a PO#GO284322 1999 Installed No 4 4. 4. 4. 4.~t~ I 4 4. 4 4. 4 4. I 1 4. 4 4 4 4.
- 4. 4. t 4. 4. 1 7.
Description of Work 1 1 1 11 Replaced Snubber SNB-38 per Snubber Program
- 8. Tests conducted: Hydrostatic [] Pneumatic [] Nominal Operating Pressure [] Exempt E]
Other F1 Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
Ems I
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks I
n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Aut izationl.o. N/A Expiration Date N/A Signed /,$J *. , ASME Program Engineer Date 14'" ... 2J , ZOO-CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB-CT of Connecticut have inspected the components described in this Owners Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
t , Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date . obo(o
IPALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 612612006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 Of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO# 16739 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A
- 4. Identification of System SWS Code Class Class 3
- 5. (a) Applicable Construction Code ASME B31.1 1955 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
MV-SW136 Crane Nuclear Model 143 1/2 XU n/a PO#G0309185 2006 Installed No Flanges Energy Steel n/a n/a PO#P807305 2006 Installed No 4" 300# Supply No Studs 5/8" -11 Muskon Inc n/a n/a PO#P805467 2006 Installed No UNC X4" Long Hex Nuts 5/8"- Muskon Inc n/a n/a PO#P805467 2006 Installed No 11
- 7. Description of Work Replace Valve MV-SW136
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure Exempt []
Other 0] Pressure psi Test Temp. aF Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings maybe used, provided (1) size is 8 1 /2 in. x 1I in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of AuthorizatioDNo. N/A Expiration Date N/A Signed ASMEProgram Engineer Date , .( .
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSR-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date Date E.oc
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#21496 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp Name Same Authorization Expiration Date Address
- 4. Identification of System Code Class Class 2
- 5. (a) Applicable Construction Code ASME B31.1 1955 Edition Addenda n/a Code C. ase n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
P-74 SIRW Chesterton 3247GS n/a PO#G0195946- 1996 Installed No Recirc Pump CQ No 4"xl 1/2" Conc Energy & n/a n/a PO# 2006 Installed No Reducer Process Corp P00002253 No 4" Flange Energy & n/a n/a PO# 2006 Installed No Process Corp P00002253
- 7. Description of Work Replaced SIRW Tank Recirculation Pump P-74 per EAR-2003-0270
- 8. Tests conducted: Hydrostatic [] PneumaticE] Nominal Operating Pressure R] Exempt E]
Other [] Pressure psi Test Temp.
Other: NIA NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of AuthorizatioD. N/A Expiration Date N/A Signed ____ ____
____ ASMEProgram
___ Engineer
________ Date Z4 ____ Za3 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSR-CT of Connecticut have inspected the components described in this Owners Report during the period November 18,2004 to May 10,2006 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
____ Commissions Ma 300762 Inspectors Signature National Board, Province and Endorsements Date t, oe
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/2612006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#27257 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Enertech Type Code Symbol Stamp N/A Name 2950 Birtch Street,Brea,CA 92821 Authorization N/A Address Expiration Date N/A
- 4. Identification of System CCW Code Class Class 3
- 5. (a) Applicable Construction Code ANSI B16.4 1981 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
CV-0826 CCW Enertech SIN 10315 n/a PO#2276 2006 Corrected N Heat N Exchanger Control Valve
- 7. Description of Work Installed hard stop and repaired areas of Erosion/Cavitation on ID of Valve Body
- 8. Tests conducted: Hydrostatic Li Pneumatic- Nominal Operating Pressure 0 Exempt El Pressure NOP psi Test Temp. 0 Other [l NOT F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM I
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Authori ation No. N/A Expiration Date N/A Signed 6, X/ , ASME Program Engineer Date " 6 2k 2cor CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
Commissions MI 300762 Inspector's Signature National Board, Province and Endorsements Date D ae?004
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet I of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#27405 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A
- 4. Identification of System CCW Code Class Class 3
- 5. (a) Applicable Construction Code ANSI B16.4 1981 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
CV-0823 CCW Enertech S/N 11524 n/a PO#P808270 2006 Installed No Heat No Exchanger Control Valve
- 7. Description of Work Installed hard stop and repaired areas of Erosion/Cavitation on ID of Valve Body
- 8. Tests conducted: Hydrostatic [] Pneumatic--] Nominal Operating Pressure Exempt Ej Other n Pressure psi Test Temp. 0 F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Auth w'ation No. .. EExpiration Date N/A Signed , ASME Program Engineer Date , V. , "
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSR-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
__ _ _ _ Commissions MI 300762 Inspector's Signature National Board, Province and Endorsements Date Dat ,J s 0 S..
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO# 25184 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Nuclear Management Company, LIC Type Code Symbol Stamp N/A Name 27780 Blue Star Hwy, Covert, MI 49043 Authorization N/A Address Expiration Date N/A
- 4. Identification of System SWS Code Class Class 3
- 6. (a) Applicable Construction Code ASME B31.1 1973 Edition Edition Addenda 1974 Addend Code Case n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xi Code Cases n/a
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
CV-0821 Fisher S/N17545158 n/a PO#P806452 2006 Installed No MV-SW769 Velan S/N6615405-02 n/a OP#P806519 2006 Installed No
- 7. Description of Work Replaced Valve CV-0821 and Installed new Isolation Valve MV-SW769
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure S6 Exempt E]
Other LI Pressure psi Test Temp.
Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
ý111 I
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks ITEM I
n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Autho 'ation No. N/A Expiration Date N/A Signed ASMEProgram Engineer Date __U_ _ _" _ , ZOO~,
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
Commissions M1300762 Inspector's Signature National Board, Province and Endorsements Date _____L__V___ ____ Roo(.
I PALISADES NUCLEAR POWER PLANT ACTIVITY FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 Of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO# 25693 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Nuclear Management Company, LLC Name Type Code Symbol Stamp N/A 27780 Blue Star Hwy, Covert, MI 49043 Authorization N/A Address Expiration Date N/A
- 4. Identification of System SWS Code Class Class 3
- 5. (a) Applicable Construction Code ASME B31.1 1973 Edition Edition Addenda 1974 Addend Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases n/a
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
CV-0822 Fisher S/N17545159 n/a PO#P806452 2006 Installed No MV-SW770 Velan Model F12-11X13- n/a PO#P806519 2006 Installed BC2A No
- 7. Description of Work Replaced Valve CV-0822 and Installed new Isolation Valve MV-SW770
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure 66 Exempt []
Other [] Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 1I in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM I I
- 9. Remarks n/a CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Authorizati No N/A Expiration Date NWA Signed ASME Program Engineer Date . , '2O*:.
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michi-gan and employed by HSB-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
-60" Inspector's Signature Commissions MI300762 National Board, Province and Endorsements Date
IPALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet I of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#2981 9 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Ownerbner Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A
- 4. Identification of System VAS Code Class Class 3
- 6. (a) Applicable Construction Code ASME B31.1 1955 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
Tube Plugs Heat Exchanger n/a n/a PO#663 2005 Installed No Prod Corp No
- 7. Description of Work Plugged tube inVHX-4 Heat Exacanger
- 8. Tests conducted: Hydrostatic [] Pneumatic[o Nominal Operating Pressure Exempt D1 Other [] Pressure psi Test Temp. aF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Authorization No. N/A Expiration Date N/A Signed '$,*d '/A 6 , ASME Program Engineer Date T -4'-- z-1 ,
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
,I* , . Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date ..'" s, U v
IPALISADES NUCLEAR POWER PLANT ACTIVITY FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ITEM
- 1. Owner Consumers Energy Company Date 612612006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#26963 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date NIA
- 4. Identification of System PCS Code Class Class 1
- 5. (a) Applicable Construction Code ASME Section I11 1977 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
Tube Plugs Westinghouse n/a n/a PO#1281 2005 Installed Electric Company No
- 7. Description of Work -Plugged 22 tubes in the "A"Steam Generator
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure R] Exempt[]
Other LI Pressure psi Test Temp. *F Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PALISADES NUCLEAR POWER PLANT EFOR:MV NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Authorization No. N/A Expiration Date N/A Signed ASME Program Engineer Date ,l Zfo , _" _____
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michi-gan and employed by HSR-CT of Connecticut have inspected the components described in this Owners Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
-e o'" Commissions Ml100762 Inspector's Signature National Board, Province and Endorsements Date A* 0&44.2 &
V 1%
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet I Of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#26964 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Name Type Code Symbol Stamp NIA Same Authorization NIA Address Expiration Date N/A
- 4. Identification of System PCS Code Class Class 1
- 5. (a) Applicable Construction Code ASME Section III 1977 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
Tube Plugs Westinghouse n/a n/a PO#1281 2005 Installed No Electric Company No
- 7. Description of Work Plugged 10 tubes in the "B" Steam Generator
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure Sd Exempt[]
Other [] Pressure psi Test Temp. *F Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings maybe used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PALISADES NUCLEAR POWER PLANT FRM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Authoyation No. N/A Expiration Date N/A Signed 144--& ASME Pro(gram Engineer Date it,- 2. , '2,06 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSS-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
____ Commissions M1 300762 Inspectors Signature National Board, Province and Endorsements Date " , V(X Id V
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#20457 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp Name Same Authorization N/A Address Expiration Date N/A
- 4. Identification of System ESS Code Class Class 2
- 5. (a) Applicable Construction Code ASME B31.1 1955 Ed ition Edition Addenda n/a Code Caase n/a (b) Applicable Edition of Section Xi Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases N-416-1
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
CV-3070 Aloyco Inc 68-Mi 13-1 n/a PO#4838 2006 Installed No
- 7. Description of Work Replaced HPSI Pump P-66B subcooling valve CV-3070
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure W Exempt []
Other Rl Pressure psi Test Temp.
Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks ITEM I
None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp NIA Certificate of Authorztion No. N/A Expiration Date N/A Signed , ASME Program Engineer Date *'%Tk)- 2:1 , W--
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HS4-CT of Connecticut have inspected the components described in this Owners Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
" Commissions MI 300762 Inspector's Signature National Board, Province and Endorsements Date Ja4J-" .2:F o-,
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/2612006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#270650 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A
- 4. Identification of System CSW Code Class Class 3
- 5. (a) Applicable Construction Code ASME B31.1 1955 Edition Edition Addenda nra Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases N-416-1
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No) 3" Weldolet Dubose n/a n/a PO#5457 2006 Installed No 3" Pipe Cap Dubose n/a n/a PO#5457 2006 Installed No I INI
- 7. Description of Work Installed weldolet and cap on servive water pipe
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure 6d Exempt []
Other R] Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information In items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks ITEM i-ý'a"Wov I
None CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Authoriz n No. N/A Expiration Date N/A Signed ,'ý ASMEIVI Program Engineer Date "Q46 . .1,"
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB-.T of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
"KM_ k Commissions MI 300762 Inspectors Signature National Board, Province and Endorsements Date
PALISADES NUCLEAR POWER PLANT ACTIVITY FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 Of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#25456 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Name Type Code Symbol Stamp N/A Same Authorization N/A Address Expiration Date N/A
- 4. Identification of System PCS Code Class Class 1
- 5. (a) Applicable Construction Code ASME Serction ll 1989 Edition Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
Studs Westinghouse n/a n/a PO# n/a Installed No G0201602 No Nuts Westinghouse n/a n/a PO# n/a Installed G78219 No Helicoil Westinghouse n/a n/a PO# n/a Installed No G0318552
- 7. Description of Work Replace stuck stud & studs #1008B and Stud #14 lB3
- 8. Tests conducted: Hydrostatic 0 PneumaticE] Nominal Operating Pressure g Exempt f]
Other F] Pressure NOP psi Test Temp. NOT 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 112 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PALISADES NUCLEAR POWER PLANT
- FOR:MV NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks None CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this conforms to the requirements of the ASME Code, Section Xl.
Type Code Symbol Stamp N/A Certificate of Autization-No. N/A Expiration Date N/A Signed ASMEProgram Engineer Date " -c .- * ,
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSR-CT of Connecticut have inspected the components described in this Owners Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
-*A 3* 4 Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date ___.__ _
_o__, ,
U -,
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/2612006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, Ml 49043 WO#269848 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS TechnologiesLLC Type Code Symbol Stamp VR I NR Name 131 Venture Bivd, SpartanburgSC 29301 Authorization 632 /81 Address Expiration Date 4/312009 4/9/2009
- 4. Identification of System MSS Code Class
- 5. (a) Applicable Construction Code ASME Section III 1968 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-0703 See Attached Form NVR-1
- 7. Description of Work Repaired Relief Valve
- 8. Tests conducted: Hydrostatic E] Pneumatic [- Nominal Operating Pressure 0 Exempt E]
Other LI Pressure psi Test Temp.
Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM I
- 9. Remarks See Attached Form NVR-1 for RV-0703 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of AuthorizonNo. N/A Expiration Date NIA Signed iQ- ASME Program Engineer Date 'T M 7--C-7
, Z.004C CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and ennployed by HSR-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date ,Aor W V'
FORM NVR-1 REPORT OF REPAIR I] REPLACEMENT El OF NUCLEAR PRESSURE RELIEF DEVICES C 1.Work performed by: NWS Technologies, LLC Purchase Order# 00004610 131 Venture Boulevard, Spartanburg, SC 29306
- 2. Work performed for. Nuclear Management Company - Palisades Nuclear Plant 3/4. Owner - name, address and identification of nuclear power plant Nuclear Management Company - Palisades Nuclear Plant, 27780 Blue Star Memorial Hwy, Covert, MI 49043
- 5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer. Anderson Greenwood I Crosby c: Identifying nos.
HA 55 RV-0703 n/a steam 6Q8 n/a (type) (mfes S"N) (NB#) (service) (size) (yr.built) d: Construction Code: ASME Sec. III 1968 n/a n/a 1 (name/section/division) (edition) (addenda) (Code Cases(s)) (Code Class)
- 6. ASME Code Section Xl. applicable for inservice Inspection: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 7. ASME Code Section Xi used for repairs, replacements: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 8. Construction Code used for repairs, replacements: 1968 n/a n/a (edition) (addenda) (Code Case(s))
- 9. Design responsibilities: n/a
____10.Qpenng pressure: 1025 psig Set-pressure a djustnent-m-en " -a . -- - NWS Technoogies LLC- -using..,steani_
C I11. Description of work (include name and identifying number of replacement parts): As-found steam test. Disassembled, inspected, modified guide and upper spring washer per Palisades Modification EAR-2005-0043, replaced spindle, lapped seats. Certified set-pressure using steam. Jacked & Lapped. Certified seat tightness using steam.
- 12. Remarks: NWS Traveler #: 06-127. Replaced spindle.
CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section X! of the ASME Code and the National Board Inspection Code "VR and "NR" rules.
National Board Certificate of Authorization No. 632 to use the "'VR" stamp expires April 3, 2009.
Nati/nal Board Certificate of Authorization No. 81 /to use t "NR" sta expires April 9, 2009.
NWS Technologies, LLC Manager, QA Date Repair Organization Aforized r entative Title CERTIFICATE OFINSPECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described Inthis report on v/)HT40 and state that to the best of my knowledge and belief, this repair, modification or replacement has t3eenkompleted in accordance with Section XI of the of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected Is *sp n.
Y,.,e in o.,, -t C oNB#8462, A,(N,I NC# 1073 1ae_" lnspdtol 5 natuy I Commissions (NB (minendorsemen'ts). Iurisdiction,& no.)
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#269853 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS Technologies,LLC Type Code Symbol Stamp VR I NR Name 131 Venture Blvd, Spartanburg,SC 29301 Authorization 632/81 Address Expiration Date 4/3/2009 4/9/2009
- 4. Identification of System MSS Code Class
- 6. (a) Applicable Construction Code ASME Section 1II 1968 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-0705 See Attached Form NVR-1
- 7. Description of Work Repaired Relief Valve
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure Exempt i]
Other R Pressure psi Test Temp. aF Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks See Attached Form NVR-1 for RV-0705 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Aut 9 zation NO. N/A Expiration Date N/A Signed-, ASME Program Engineer Date *zk'.jie. , ,
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by H,4R-rT of Connecticut have inspected the components described in this Owners Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
_ _ __ _ _ Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date " o , e9OO&,
FORM NVR-1 REPORT OF REPAIR EN REPLACEMENT I0 OF NUCLEAR PRESSURE RELIEF DEVICES C 1.Work performed by: NWS Technologies, LLC Purchase Order# 00004610 131 Venture Boulevard, Spartanburg, SC 29306
- 2. Work performed for: Nuclear Management Company - Palisades Nuclear Plant 3/4. Owner - name, address and Identification of nuclear power plant Nuclear Management Company - Palisades Nuclear Plant, 27780 Blue Star Memorial Hwy, Covert, MI 49043
- 5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer Anderson Greenwood I Crosby c: Identifying nos.
HA 55 RV-0705 n/a steam 6Q8 nra (type) (mrfs S/N) (NB#) (service). (size) (yr.built) d: Construction Code: ASME Sec. 1II 1968 n/a n/a 1 (namelsectionrddvisfon) (edition) (addenda) (Code Cases(s)) (Code Class)
- 6. ASME Code Section XI applicable for Inservice Inspection: 1989 nra nra (edition) (addenda) (Code Case(s))
- 7. ASME Code Section XI used for repairs, replacements: 1989 nra n/a (edition) (addenda) (Code Case(s))
- 8. Construction Code used for repairs, replacements: 1968 n/a na (edition) (addenda) (Code Case(s))
- 9. Design responsibilities: n/a 10- Openlng-pressure:-- -1025-pslg ............
Set-pressure adjustment made at NWS Technologies, LLC using steam (3 11. Description of work (Include name and Identifying number of replacement parts): As-found steam test Disassembled, Inspected, modified guide and upper spring washer per Palisades Modification EAR-2005-0043, replaced spindle, lapped seats. Certified set-pressure using steam. Jacked & Lapped. Certified seat tightness using steam.
- 12. Remarks: NWS Traveler#: 06-128. Replaced spindle.
CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
Iiational Board Certificate of Authorization No. 632 to use the 'VR" stamp expires April 3, 2009.
Naional Board Certificate of Authorization No. 81 to use th NR" stami expires April 9, 2009.
______ NWS Technologies, LLC gW Manager, QA Date Repair Organization A. horized repry ntative Tit'e CERTIFICATE OF INSPECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on Y/11/od_, and state that to the best of my knowledge and belief, this repair, modification or replacement has lden 4ompleted In accordance with Section XI of the of the ASME Code and the National Board Inspection Code WVR" and "NRn rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising from or connected-th thil Insp tioq.
A Ze -NB ANl n8462, NC#1073
-7Dite - ins%:~o~s~ignattrr I Commissions (NB (mInendorsements), jurisdiction,& no.)
m I
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#267581 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS Technologies,LLC Type Code Symbol Stamp VR / NR Name 131 Venture Blvd, Spartanburg,SC 29301 Authorization 632 /81 Address Expiration Date 4/312009 4/912009
- 4. Identification of System MSS Code Class S. (a) Applicable Construction Code ASME Section III 1968 Edition Addenda n/a Code Ca se n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-0706 See Attached Form NVR-1
- 7. Description of Work Repaired Relief Valve
- 8. Tests conducted: Hydrostatic [] PneumaticE] Nominal Operating Pressure W Exempt I]
Other [] Pressure psi Test Temp.
Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information In items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM I
- 9. Remarks See Attached Form NVR-1 for RV-0706 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Auth ization No. NIA Expiration Date N/A Signed /'"/'I ,, , ASME Program Engineer Date zrJ 200(a CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSR-rT of Connecticut have inspected the components described in this Owners Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
Commissions M1 300762 Inspectors Signature National Board, Province and Endorsements Date '4 OrT
FORM NVR-1 REPORT OF REPAIR [] REPLACEMENT [3 OF NUCLEAR PRESSURE RELIEF DEVICES
- 1. Work performed by: NWS Technologies, LLC Purchase Order# 00004610 131 Venture Boulevard, Spartanburg, SC 29306
- 2. Work performed for: Nuclear Management Company - Palisades Nuclear Plant 314. Owner - name, address and identification of nuclear power plant Nuclear Management Company - Palisades Nuclear Plant, 27780 Blue Star Memorial Hwy, Covert, MI 49043
- 5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer. Anderson Greenwood I Crosby c: Identifying nos.
HA 55 RV-0706 ri/a steam 6C n/a (type) (m"s S) (N13#) (servioe)- (S,X) (yr.bullt) d: Construction Code: ASME Sec. III 1968 n/a n/a I (name/sectlonldivision) (edition) (addenda) (Code Cases(s)) (Code Class)
- 6. ASME Code Section XI applicable for inservice inspection: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 7. ASME Code Section XI used for repairs, replacements: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 8. Construction Code used for repairs, replacements: 1968 rna n/a (edition) (addenda) (Code Case(s))
- 9. Design responsibilities: n/a
- 11. Description of work (Include name and ldentii4ng number of replacement parts): As-found steam test Disassembled, inspected, modified guide and upper spring washer per Palisades Modification EAR-2005-0043, lapped seats. Certified set-pressure and seat tightness using steam.
- 12. Remarks: NWS Traveler #: 06-129.
CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code "VRn and "NR" rules.
National Board Certificate of Authorization No. 632 to use the "VR" stamp expires Apnrl 3, 2009.
Nat'nal Board Certificate of Authorization No. 81 7J, se the wNsXtgmp e ires April 9, 2009.
7 7RZ; Date NWS Technalogies, LItC Repair Organization
&vTManager, Autiirjfted mepreserndWie Title i
I, Charles F. Toegel Jr. holding a valid commission Issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT - . of Hartford, CT have Inspected the repair, modification or replacement described in this report on ,and state that to the best of my knowledge and belief, this repair, modification or replacement has be~n ýhmpleted in accordance with Section XI of the of the ASME Code and the National Board Inspection Code wVR" and NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected thisspe n
-P/ ,, D a Inslt*-&- / t C #8462,
,n(NBA, N,I NCO 1073 Dfiv Ins& cte fgnarrY Commissions (NS (inci endorsements), jurisdiction.& no.)
PALISADES NUCLEAR POWER PLANT EORM NIS-2 OWNER'S REPORT FOR REPAIR/TREPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 Of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#269856 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS Technologies,LLC Type Code Symbol Stamp VR I NR Name 131 Venture Blvd, Spartanburg,SC 29301 Authorization 632/81 Expiration Date 4/3/2009 4/912009 Address
- 4. Identification of System MSS Code Class
- 5. (a) Applicable Construction Code ASME Section III 1968 Edition Addenda nla Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-0707 See Attached Form NVR-1
- 7. Description of Work Repaired Relief Valve
- 8. Tests conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure W Exempt []
Other 0 Pressure psi Test Temp.
Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks See Attached Form NVR-1 for RV-0707 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Au.rization No. NIA Expiration Date N/A 7
Signe /AS,/ iMi E Program Engineer Date wo W- 7,- 5 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
_ _60 " Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date _ ___ V V __O___
FORM NVR-1 REPORT OF REPAIR Da REPLACEMENT [3 OF NUCLEAR PRESSURE RELIEF DEVICES
§ 1. Work performed by: NWS Technologies, LLC Purchase Order# 00004610 131 Venture Boulevard, Spartanburg, SC 29306
- 2. Work performed for Nuclear Management Company - Palisades Nuclear Plant 3/4. Owner - name, address and identification of nuclear power plant: Nuclear Management Company - Palisades Nuclear Plant, 27780 Blue Star Memorial Hwy, Covert, MI 49043
- 5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer Anderson Greenwood I Crosby c: Identifying nos.
HA 55 RV-0707 n/a steam 6Q8 n/a (type) (mfe's SIN) (NB#) (service). (size) (yr.buil) d: Construction Code: ASME Sec. I1I 1968 n/a n/a 1 (namelsectionldivision) (edition) (addenda) (Code Cases(s)) (Code Class)
- 6. ASME Code Section XI applicable for Inservice inspection: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 7. ASME Code Section XI used for repairs, replacements: 1989 nra n/a (edition) (addenda) (Code Case(s))
- 8. Construction Code used for repairs, replacements: 1968 n/a nra (edition) (addenda) (Code Case(s))
- 9. Design responsibilities: n/a i--lOW.Open1ng pressure s te25psi_
Set-pressure adjustment made at NWS Technologies, LLC using steam
- 11. Description of work (nclude name and identifying number of replacement parts): Disassembled, Inspected, modified guide and upper spring washer per Palisades Modification EAR-2005-0043, lapped seats. Certified set-pressure using steam. Jacked & Lapped. Certified seat tightness using steam.
- 12. Remarks: NWS Traveler#: 06-130.
CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code "aR" and "NR" rules.
National Board Certificate of Authorization No. 632 to use the "stamp expires April 3, 2009.
Nalynal Board Certificate of Authorization No. 81 touse the "stamp eypires April 9, 2009.
'q/I /,*I, NWS Technologies, LIC _______________ Manager, QA Date Repair Organization Autho=ed represe tive TWie CERTIFICATE OF INSPECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on j////OA, and state that to the best of my knowledge and belief, this repair, modification or replacement has bain cdmpleted in accordance with Section XI of the of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning this repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising om or connected wifthis I specon,
-A,7? *nat*-
- oN1398462, A,N,I NC# 1073 o te Insm = = IaV Commissions (N9 find endorsements). jurlsdkcton.& no.)
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet I of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#269857 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS Technologies,LLC Type Code Symbol Stamp VR / NR Name 131 Venture Blvd, Spartanburg,SC 29301 Authorization 632/81 Expiration Date 4/3/2009 4/9/2009 Address
- 4. Identification of System MSS Code Class
- 6. (a) Applicable Construction Code ASME Section III 1968 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-0715 See Attached Form NVR-1
- 7. Description of Work Repaired Relief Valve
- 8. Tests conducted: Hydrostatic LI Pneumatic-- Nominal Operating Pressure 0 Exempt 1]
Other f-1 Pressure psi Test Temp.
Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x II in., (2)
Information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets Is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks ITEM I
See Attached Form NVR-1 for RV-0715 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Auth*ation No. N/A Expiration Date N/A Signed /A 6 , ASME Program Engineer Date ,, . , woe*
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
_ _"____ Commissions MI 300762 Inspector's Signature National Board, Province and Endorsements Date .02006 Date
FORM NVR-1 REPORT OF REPAIR M REPLACEMENT I3
- OF NUCLEAR PRESSURE RELIEF DEVICES
- 1. Work performed by: NWS Technologies, LLC Purchase Order # 00004610 131 Venture Boulevard, Spartanburg, SC 29306
- 2. Work performed for Nuclear Management Company - Palisades Nuclear Plant 3/4. Owner - name, address and identification of nuclear power plant Nuclear Management Company - Palisades Nuclear Plant. 27780 Blue Star Memorial Hwy, Covert, MI 49043
- 5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer Anderson Greenwood / Crosby c: Identifying nos.
HA 55 RV-0715 1/a steam 6Q8 n/a (type) (mfs S" () 139) (service). (size) (yr.bullt) d: Construction Code: ASME Sec. Ill 1968 n/a n/a I (namelsectlon/dlvislon) (edition) (addenda) (Code Cases(s)) (Code Class)
- 6. ASME Code Section XI applicable for inservice Inspection: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 7. ASME Code Section Xl used for repairs, replacements: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 8. Construction Code used for repairs, replacements: 1968 n/a n/a (edition) (addenda) (Code Case(s))
- 9. Design responsibilities: n/a Mae
- -. * *
- W, r , t-, -. W ,.
Set-pressure adjustment made at NWS Technologies, LLC using steam
- 11. Description of work (Indude name and identifying number of replacement parts): As-found steam test. Disassembled, Inspected, modified guide and upper spring washer per Palisades Modification EAR-2005-0043, lapped seats. Certified set-pressure using steam. Jacked & Lapped. Certified seat tightness using steam.
- 12. Remarks: NWS Traveler#: 06-131.
CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
National Board Certificate of Authorization No. 632 to use the "VRO stamp expires April3, 2009.
N~jnlBoard Certificate of Authorization No. 81 jo use theVANR" stam' expires April 9,2009.
1 , NWS Technologies, LLC Manager, QA Date Repair Organization Auyodzed reprentative TItle I. Charles F. Toegel Jr. holding a valid commission Issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described in this report on .I/L4_O*,_and state that to the best of my knowledge and belief, this repair, modification or replacement has Ieninbmpleted In accordance with Section XI of the of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any persona! injury, property damage or loss of any kind ani g fom or connecte.plth- n, ,
iae - Ins.A N 13 8462, A N. , I N C# 1073
-7oake 3 gnatire Commissions (NB Ond endorsements). jurisdiction.& no.)
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#26379 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS Technologies,LLC Type Code Symbol Stamp VR / NR Name 131 Venture Blvd, Spartanburg,SC 29301 Authorization 632/81 Address Expiration Date 4/3/2009 4/9/2009
- 4. Identification of System MSS Code Class
- 5. (a) Applicable Construction Code ASME Section eII 1968 Edition Addenda nIa Code Case nla (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-0716 See Attached I Form NVR-1 I
- 4. 4 I I 4 4 4 4 4 I I 4 4 4
- 4. 4 I I 4 4 4
- 4. 4 I I 4-4 4
- 4. 4 1 I 1 .1
- 7. Description of Work Repaired Relief Valve
- 8. Tests conducted:
Hydrostatic [] Pneumatic[] Nominal Operating Pressure Rj Exempt E]
Other El Pressure psi Test Temp.
Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 In. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks ITEM I
See Attached Form NVR-1 for RV-0716 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section X1.
Type Code Symbol Stamp N/A Certificate of Authoriation No. N/A Expiration Date NIA Signed ASME Program Engineer Date *'oiJu z., , _____
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSR-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
Commissions M1300762 Inspector's Signature National Board, Province and Endorsements Date ". 05"
FORM NVR-1 REPORT OF REPAIR 0 REPLACEMENT El OF NUCLEAR PRESSURE RELIEF DEVICES
- 1. Work performed by: NWS Technologies, LLC Purchase Order # 00004610 131 Venture Boulevard. Spartanbur-, SC 29306
- 2. Work performed for: Nuclear Management Company - Palisades Nuclear Plant 3/4. Owner - name, address and identification of nuclear power plant: Nuclear Management Company - Palisades Nuclear Plant, 27780 Blue Star Memorial Hwy, Covert, MI 49043
- 5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer: Anderson Greenwood / Crosby c: Identifying nos.
HA 55 RV-( )71 6 n/a steam 6Q8 n/a (type) (mfrs SIN1
- 1) (NB#) (service) (size) (yr.built) d: Construction Code: ASME Sec. III 1968 n/a n/a 1 (name/sectlonldlvision) (edition) (addenda) (Code Cases(s)) (Code Class)
- 6. ASME Code Section XI applicable for inservice inspection: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 7. ASME Code Section Xl used for repairs, replacements: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 8. Construction Code used for repairs, replacements: 1968 n/a n/a (edition) (addenda) (Code Case(s))
- 9. Design responsibilities: n/a
- 0. etpenngpreadjuste nt. made sg a -
Set-pressure adjustment made at: NWS Technologies, LLC using steam
- 11. Description of work (include name and Identifying number of replacement parts): Disassembled, inspected, modified guide and upper spring washer per Palisades Modification EAR-2005-0043, replaced disc, lapped seats.
Certified set-pressure and seat tightness steam.
- 12. Remarks: NWS Traveler#: 06-132. Replaced disc.
CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacemtn of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'R/R" and "NR" rules.
National Board Certificate of Authorization No. 632 to use the 'R'R" stamp expires April 3, 2009.
Nati nal Board Certificate of Authorization No. 81 tuse the "NR" tamp expires April 9, 2009.
/7 NWS Technologies, LLC _ /_ ,______ Manager, QA Date Repair Organization AuthorizecAepresentatlvYf Title CERTIFICATE OF INSPEr'IION I, Carl R. Enos holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of Tennessee and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described in this report on l/'zo/ld and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the of the ASME Code and the National Board Inspection Code '"VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Futhermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection.
Date Inspectors Sig NBC#8460, ANI TN# 2236 Date Inspector's Signature Commissions (NB (mnci endorsements), jurisdiction,& no.)
PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 6/2612006
- 1. Owner Consumers Energy Company Date Name
- 2. Plant Palisades Nuclear Power Plant Sheet I Of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#269863 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS Technologies,LLC Type Code Symbol Stamp yR / NR Name 131 Venture Blvd, Spartanburg,SC 29301 Authorization 632/81 Address Expiration Date 4/3/2009 4/9/2009
- 4. Identification of System MSS Code Class Class 2
- 5. (a) Applicable Construction Code ASME Section III 1968 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-0721 See Attached Form NVR-1
- 7. Description of Work Repaired Relief Valve
- 8. Tests conducted: Hydrostatic [] Pneumatic-- Nominal Operating Pressure Exempt [D Other ED Pressure psi Test Temp. 0F Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM I
- 9. Remarks See Attached Form NVR-1 for RV-0721 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section X1.
Type Code Symbol Stamp N/A Certificate of Authoriwtion No. N/A Expiration Date N/A Signed ,2.( ASME Program Engineer Date ,24-w -
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michi-gan and employed by HSR-QT of Connecticut have inspected the components described in this Owners Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
,..* t44 Commissions MI 300762 Inspector's Signatuire National Board, Province and Endorsements Date V" V 0 , oOO 6
FORM NVR-1 REPORT OF REPAIR Ea REPLACEMENT 10 OF NUCLEAR PRESSURE RELIEF DEVICES
( 131 Venture Boulevard, Spartanburg, SC 29306
- 2. Work performed for: Nuclear Management Company - Palisades Nuclear Plant 314. Owner - name, address and identification of nuclear power plant Nuclear Management Company - Palis*
Nuclear Plant, 27780 Blue Star Memorial Hwy, Covert, MI 49043
- 5. a: Repaired pressure relief device: Main Steam SafetY Valve b: Name of manufacturer:. Anderson Greenwood I Crosby c: Identifying nos.
HA 55 RV-C721 n/a steam 608 n/1 (type) (rfns S/N) (NB#) (service). (size) (yr.b d: Construction Code: ASME Sec. Ill 1968 n/a- n/a 1 (namelsection/divislon) (edition) (addenda) (Code Cases(s)) ( 'ode Clas
- 6. ASME Code Section XI applicable for inservice inspection: 1989 n/a n/a (edition) (addenda) (Code Case(
- 7. ASME Code Section XI used for repairs, replacements: 1989 n/a n/a (edition) (addenda) (Code Casef
- 8. Construction Code used for repairs, replacements: 1968 n/a n/a (edition) (addenda) (Code Case;
- 9. Design responsibilities: n/a
- 11. Description of work (Include name and Identifying number of replacement parts): As-found steam test Dis--sse-dm-b1-d C>* ,. Inspected, modified oulde and upper sring washer per Palisades Modification EAR-2005-0043. replaced
(.. spindle, lapped seats. Certified set-pressure using steam. Jacked & Lapped. Certified seat tightness using' steam.
- 12. Remarks: NWS Traveler #: 06-133. Replaced spindle.
CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
National Board Certificate of Authorization No. 632 to use the 'VR" stamp expires April 3, 2009.
Nayonai Board Certificate of Authorization No. 81 to use the "Ne='stamp expires April 9, 2009.
-fll/*" NWS Technologies, LLC . - Manager, QA Date Repair Omanizatlon Authorized representaPe Title
-- I7 I CERTIFICATE OF INSPECTION I, Charles F. Toegel Jr. holding a valid commission Issued by The National Board of Boiler and Pressuri Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have Inspected the repair, modifica or replacement described In this report on #/4'4, and state that to the best of my knowledge and belie this repair, modification or replacement has len 6ompleted in accordance with Section XI of the of the ASME Code and the National Board Inspection Code "vR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied concerning this repair, modification or replacement described in this report. Furthermore, neither the undersign.
nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising from or connected it this Inspe ion.
,I
-- 7n,,-,,r-- NSomissons8462, A, N, I NCd 1073 I eI ns (o~I sna, r re Commissions (NB (mci endorsements). jurisdiction.& no
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1 of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#269864 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS TechnologiesLLC Type Code Symbol Stamp VR / NR Name 131 Venture Blvd, Spartanburg,SC 29301 Authorization 632/81 Address Expiration Date 4/3/2009 4/9/2009
- 4. Identification of System MSS Code Class
- 5. (a) Applicable Construction Code ASME Section III 1968 Edition Addenda n/a Code Case n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section Xl Code Cases None
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-0722 See Attached Form NVR-1
- 7. Description of Work -Repaired Relief Valve
- 8. Tests conducted: Hydrostatic [] Pneumatic- Nominal Operating Pressure &6 Exempt (D Other 0 Pressure psi Test Temp.
Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks ITEM I
See Attached Form NVR-1 for RV-0722 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Autoization No. NIA Expiration Date N/A Signed - - (. , ASME Program Engineer Date Mj.e-"O *C CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michi-gan and employed by HSR-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
-560'd-'l Inspector's Signature Commissions M1300762 National Board, Province and Endorsements Date ,Z4 cia V1 N
FORM NVR-1 REPORT OF REPAIR tM REPLACEMENT 03 OF NUCLEAR PRESSURE RELIEF DEVICES
- 1. Work performed by: NWS Technologies, LLC Purchase Order# 00004610 131 Venture Boulevard. SDartanburo. SC 29306
- 2. Work performed for Nuclear Management Company - Palisades Nuclear Plant 314. Owner - name, address and identification of nuclear power plant Nuclear Management Company - Palisades Nuclear Plant. 27780 Blue Star Memorial Hwy, Covert. Mi 49043
- 5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer Anderson Greenwood / Crosby c: Identifying nos.
HA 55 RV-0722 1/a steam 60 8 n/a (type) (rns S/N) (P (B#) (servlceý (siz:e) (yr.buift) d: Construction Code: ASME Sec. III 1968 . n/a 1 (namelsectlon/division) (edition) (adder nda) (Code Cases(s)) (Code Class)
- 6. ASME Code Section XI applicable for inservice Inspection: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 7. ASME Code Section Xi used for repairs, replacements: 1989 n/a n/a (edition) (addenda) (Code Case(s))
- 8. Construction Code used for repairs, replacements: 1968 n/a n/a (edition) (addenda) (Code Case(s))
- 9. Design responsibilities: n/a
-1`-.l3-s-cption of work oncude name ard men-awn-g-erua w rotiptacementparts. --As-foundstearn-test- Dlsassembled-- -..
Inspected, modified guide and upper spring washer per Palisades Modification EAR-2005-0043, lapped seats. Certified set-pressure and seat tightness using steam.
- 12. Remarks: NWS Traveler#: 06-134.
CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.
National Board Certificate of Authorization No. 632 to use the "VRW stamp expires April 3, 2009.
Nati!nal Board Certificate of Authorization No. 81 to use theI"R"stamp expires April 9, 2009.
,,,NWS Technologies, LLC ,,,, o Manager, QA Date Repair Organization Authorized rei,*6sentative WTe
/ "7, CERTIFICATE OO1NSPECTION I, Charles F. Toegel Jr. holding a valid commission Issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the Jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford. CT have inspected the repair, modification or replaement described In this report on '/1/41*,h and state that to the best of my knowledge and belief, this repair, modification or replacement has I~entompleted in accordance with Section XI of the of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning this repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising from or conne this.
AI , " " NB # 8462, A, N, I NC# 1073 IOetspectlsiafr j Commissions (N8 (mInendorsements), Jurisdiction.& no.)
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM M
- 1. Owner Consumers Energy Company Date 6/26/2006 Name
- 2. Plant Palisades Nuclear Power Plant Sheet 1Of 2 Name 27780 Blue Star Highway, Covert, MI 49043 WO#26226 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by NWS Technologies,LLC Type Code Symbol Stamp VR I NR Name 131 Venture Blvd, Spartanburg,SC 29301 Authorization 632/81 Address Expiration Date 4/3/2009 4/9/2009
- 4. Identification of System PCs Code Class Class 1
- 6. (a) Applicable Construction Code ASME Section IlII 1965 Edition Addenda Winter 1965 Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1989 With No Addenda (c) Applicable Section XI Code Cases None'
- 6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)
RV-1041 See Attached Form NVR-1
- 7. Description of Work Repaired Pressurizer Relief Valve
- 8. Tests conducted: Nominal Operating Pressure R Exempt []
Hydrostatic [] Pneumatic[]
Other [] Pressure psi TestTemp.
Other:
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I PALISADES NUCLEAR POWER PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM
- 9. Remarks See Attached Form NVR-1 for RV-1 041 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp N/A Certificate of Authorion No. N/A Expiration Date N/A Signed ASME Program Engineer Date _______o CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HS13-CT of Connecticut have inspected the components described in this Owner's Report during the period November 18,2004 to May 10,2006 ,
and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
1&?0_---" Commissions M1 300762 Inspector's Signature National Board, Province and Endorsements Date Tc7.L ( ?&
FORM NVR-1 REPORT OF REPAIR 0. REPLACEMENT 99 OF NUCLEAR PRESSURE RELIEF DEVICES
- 1. Work performed by: NWS Technologies, LLC Purchase Order # 00002497 131 Venture Boulevard, Spartanburg, SC 29306
- 2. Work performed for Consumers Energy - Palisades Nuclear Plant 3/4. Owner - name, address and identification of nuclear power plant Consumers Energy - Palisades Nuclear Plant, 27780 Blue Star Memorial Hwy, Covert, Mi 49043
- 5. a: Repaired pressure relief device: Pressurizer Safety Valve b: Name of manufacturer. Consolidated - Dresser c: Identifying nos.
31739A-1 BL011390 n/a steam 3'I n/a (type) (mfes S/N) (NB#) (service) (slZe) (yr.built) 1965 W'65a n/a 1 d: Construction Code: ASME Sec. III (namelsection/dlvision) (edition) (addenda) (Code Cases(s)) (Code Class) 1989 n/a n/a
- 6. ASME Code Section XI applicable for Inservice inspection:
(edition) (addenda) (Code Case(s))
1989 n/a nra
- 7. ASME Code Section Xl used for repairs, replacements: (Code Case(s))
(edition) (addenda) 1965 W '65a n/a
- 8. Construction Code used for repairs, replacements:
(edition) (addenda) (Code Case(s))
- 9. Design responsibilities: n/a
- 10. Opening pressure: 2485 psig
... Set-pressure adjustment made at NWS Technologies, LLC using steam
- 11. Description of work (Include name and Identifying number of replacement parts): As-found test, disassembled,
- j inspected, replaced disc, lapped, assembled, certified set-pressure and seat tightness.
- 12. Remareks: NWS Traveer# 06-118. Replaced disc and 4 body gaskets CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.
National Board Certificate of Authorization No. 632 to use the 'VR" stamp expires April 3, 2009.
Nationaloard Certificate of Authorization No. 81 tA use the " mp expires April 9, 2009.
itl'91 NWS Technologies, LLC Repair Organization Authtiz.ed reprel.ntative
_Manager, Title QA Date CERTIFICATE OF INV.ECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described inthis report on -1111142& and state that to the best of my knowledge and belief, this repair, modification or replacement has Ibencompleted in accordance with Section XI of the of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning this repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or loss of any kind arising from or connected ith thi ins /
17'a . uJTIA, NB#8462, A,N,I NC#1073
-/"date - i-(*p~oF ~re-"/ " Commissions (NB (ind endorsements), Jurisdiction,& no.)
SECTION 3 ASME SECTION XI ANALYSIS OF WELD NSW-010A23
QF-0549 (FP-E-CAL-01), Rev. 0 rM Calculation Signature Sheet Document Information NMC Calculation (Doc) No: EC-7950 T Revision: 0
Title:
Flaw Evaluation of Palisades CSW Piping Weld NSW-010A23 Facility: [I DA E-1 MT I-7 PB -I PI Z PL El HU/FT -] Unit: [1-2 Safety Class: [K] SR El Aug Q El Non SR Special Codes: [] Safeguards El Proprietary Calc Type (PassPort DOC-DESC-CODE): DOC (ifapplicable)
Major Revisions EC Number: 7950 I*Vendor Calc Vendor Name or Code:SIA Vendor Doc No: PAL-090-301 Description of Revision: Initial issue Prepared by: A:s$-.-(_,
c&,3--
" Date: t/o co Reviewed by: t*
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Structural Integrity CALCULATION File No.: PAL-09Q-301 Associates, Inc. PACKAGE Project No.: PAL-09Q PROJECT NAME: Flaw Evaluation of Palisades CSW Piping Weld NSW-010A23 Contract No: N/A CLIENT: Nuclear Management Company PLANT: Palisades CALCULATION TITLE: ASME Code Section XI Flaw Evaluation of Indications in CSW Piping Weld NSW-010A23 Project Mgr. Preparer(s)
Document Affected Pages Revision Description Approval & Checker(s)
Revision Signature & Signatures &
Date Date 0 1 - 10 Original Issue Al - A15 Computer Files PH 5/04/06 GAM 5/02/06 NGC 5102/06 1 - 10 Revised ASME Code At A - A15 l Sectionevaluation XI used for the PH 5/04/06 Computer Files GAM 5/02/06 NGC 5/02/06 Page 1 of 10 SI Form F200 IR2a
Table of Contents 1 INTRODU CTIO N ............................................................................................................ 3 2 TECHN ICAL APPROACH ................................................................................................. 3 3 D ESIGN INPUT ....................................................................................................................... 3 3.1 D esign and Operating Conditions ......................................................................................... 3 3.2 Pipe Dim ensions ....................................................................................................................... 4 3.3 M aterial Properties ............................................................................................................ 4 3.4 Flaw Characterization ........................................................................................................ 4 3.5 Applied Stresses ........................................................................................................................ 4 4 A SSUM PTIO N S ....................................................................................................................... 5 5 CA LCU LA TIO NS ............................................................................................................ 5 5.1 Allowable Flaw Size Calculation .......................................................................................... 5 5.2 Stress Intensity Factors Calculation ..................................................................................... 5 5.3 End of Life Fatigue Crack G rowth Analysis ....................................................................... 6 6 CO N CLU SIO N S A ND D ISCU SSION S .............................................................................. 7 7 REFEREN CES .......................................................................................................................... 8 APPEND A pc-CRA CK OUTPUT FILES .....................................................................................
IX Al List of Figures Figure 2: Circum ferential Crack in Cylinder M odel ............................................................................ 9 Figure 3: Applied Stress Intensity Factor ............................................................................................ 10 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page 2 of 10
I INTRODUCTION During routine inservice inspection in the 2006 refueling outage, two rounded indications were identified in Weld NSW-010A23 of the critical service water (CSW) system Line HB-23 at Palisades Nuclear Plant (Palisades). These indications were identified using radiographic examinations. The rounded indications measured 0.140 and 0.125 inches.
The piping is a 3-inch NPS assumed to be fabricated from ASTM A106 Grade B carbon steel. An evaluation performed by NMC personnel indicates that the observed flaws do not meet the ASME Code,Section XI acceptance standards of Table IWB-3514-4. Consequently, per IWA-3300, the indications were combined into a single subsurface flaw and evaluated per the guidelines of ASME B&PV Code, Section Xl, IWB-3650, which include acceptance criteria based on the failure mode. A conservative fatigue crack growth evaluation is then performed to determine the adequacy of continued operation of the piping system with the observed indications.
2 TECHNICAL APPROACH The flaw evaluation consists of the following tasks:
" Perform a flaw evaluation based on the guidelines of ASME B&PV Code,Section XI, IWB-3650 to calculate the allowable flaw size for the CSW pipe weld. Applied stresses due to the moment loading from the piping design analysis are used. Given that the material of the pipe elbow is carbon steel, the flaw acceptance criteria of Paragraph IWB-3650 of Reference 1 are used. This paragraph requires the use Appendix H of ASME Code,Section XI, which has screening criteria for determining the failure mode (linear elastic fracture mechanics (LEFM), elastic-plastic fracture mechanics (EPFM) or limit load).
- Determine the stress intensity factors at the flaw and perform a fatigue crack growth analysis to compare end-of-evaluation period flaw size to the allowable flaw size computed above.
" The ASME Section XI Code of record at Palisades is the 1989 Edition. However, for this evaluation the Addenda through 1990 will be used since prior to this Addenda, there were no provisions in the Code for performing flaw evaluation for ferritic piping and alternate means had to be used to meet the safety margins in the Code.
3 DESIGN INPUT 3.1 Design and Operating Conditions The design and operating conditions of the CSW system are provided by Reference 2. The pressure and temperature data for CSW Line HB-23 is as follows:
StructuralIntegrity File No.: PAL-09Q-301 Revision: I Associates, Inc. Page 3 of 10
" Design Temperature = 300'F
- Design Pressure = 100 psig
- Maximum Operating Temperature = 170'F
" Maximum Operating Pressure = 125 psig
- Normal Operating Temperature = 114°F
" Normal Operating Pressure = 65 psig 3.2 Pipe Dimensions The CSW pipe where the indication was discovered is an 3-inch Schedule 40 pipe [3]. The nominal dimensions of the pipe are:
- Nominal Outer Diameter = 3.5 in.
- Nominal Wall Thickness = 0.216 in.
3.3 Material Properties The CSW system pipe containing the indication is assumed to be fabricated from ASTM A106 Grade B carbon steel per Reference 3. The design allowable stress, Sm, of the weld metal is taken to be the same as that of the base metal of the pipe. At the normal operating temperature of 65°F [2], Sm is equal to 20,000 psi [5]. Therefore, the flow stress, o"f, defined as 2.4 S., is equal to 48,000 psi. However, conservative default values derived from Appendix H of ASME Code,Section XI (Sm = 18,100 psi) are used in the evaluation.
3.4 Flaw Characterization The indications are rounded indications located in the lower vertical elbow weld NSW-010A23 on Line HB-23 of the CSW system [4]. The inspection results summarized in References 4 and 6 show that the largest indication is 0.14 inches diameter rounded, centered near the neutral axis, 0.1 inches from the outer surface of the weld. The other indication is 0.125 inches in diameter. Using the flaw characterization rules of ASME Section XI, IWA-3300, this flaw is classified as a subsurface flaw. Per ASME Code,Section XI, IWA-3370, indications detected by radiographic examinations shall be considered to be linear indications. Hence, the lengths of the flaws are combined to give a total length of 0.265 inches. The depth of the combined flaw is the maximum diameter of the two indications, which is 0.14 inches. If the flaw is conservatively considered a surface flaw, the flaw depth to thickness ration is 0.65.
3.5 Applied Stresses The applicable stresses at the location of the indication are provided by Reference 7 which contains stress results from a piping analysis of the CSW piping system. Maximum stresses due to pressure, deadweight, seismic loadings and thermal expansion are extracted from the piping analysis at the node representing the weld (Node 115) for use in this evaluation.
The following maximum stress values at Node 115 (beginning of elbow) are used herein:
- Pressure + Deadweight, P + DW = 0.517 ksi Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page 4 of 10
- Pressure + Deadweight + Seismic, P+DW+SEIS = 0.965 ksi
- Thermal Expansion, T = 0.002 ksi 4 ASSUMPTIONS
- 1. The service life is assumed to be 40 years from the date of this evaluation (40 years + 20 years license extension).
- 2. For this evaluation is assumed that the location of the flaw will experience 400 cycles of the combined maximum load (Pressure + Deadweight + Seismic + Thermal) which correspond to 40 years of original plant life plus 20 years of license extension.
- 3. The piping material per the piping specification can be ASTM A-106 Grade B or A53 Grade B or SA-106 Grade B. While the mechanical properties of these materials are identical, ASTM A-106 Grade B will be assumed for this evaluation.
5 CALCULATIONS 5.1 Allowable Flaw Size Calculation The material of the flaw is assumed to be ferritic steel SA-106 Grade and the maximum operating temperature of the CSW line is 170'F. Therefore, as determined from the screening criteria, the LEFM methodology described in ASME Code,Section XI, Appendix H [1] is used in this evaluation in lieu of the other two failure modes (EPFM and limit load). The technical approach consists of determining the critical flaw size in the pipe which corresponds to a stress intensity factor equal to the material fracture toughness.
The allowable flaw size is derived from the critical flaw by applying the code specified safety factors.
In this evaluation, default ASME Code Section XI, Appendix H material properties at lower shelf temperature are conservatively used. The evaluation was performed using SI's computer program pc-CRACKTm [8].
The pc-CRACK" output file for the analysis is presented in Appendix A. It shows that for the observed flaw length, the allowable flaw depth is 75% of wall thickness, which is greater than the depth of the observed flaw of 65% of wall thickness.
5.2 Stress Intensity Factors Calculation A linear elastic fracture mechanics and fatigue crack growth evaluation is performed for the observed indication using pc-CRACKTm. The fracture mechanics model of an elliptical surface flaw in an infinite plate, as illustrated in Figure 2, is conservatively used in this evaluation. The model with a flaw aspect ratio of 0.5 is used in the evaluation since the actual ratio is 0.53 for the pipe weld indication under evaluation.
StructuralIntegrity File No.: PAL-09Q-301 Revision: 1 Associates, Inc. Page 5 of 10
Using the applied stresses presented in Section 3.5, the stress intensity factors due to the different load combinations are determined. In the calculation of stress intensity factors, the pressure stress is taken as the membrane stress, which is constant across the wall thickness. The stresses from the deadweight, seismic and thermal expansion moment loads are taken as linearly varying through-wall bending stresses.
The calculated stress intensity factors are presented in Figure 3.
5.3 End of Life Fatigue Crack Growth Analysis Since the indication is assumed to be surface connected, the end of life flaw size due to fatigue crack growth is calculated using the fatigue crack growth rate for ferritic steels exposed to water environments.
The fatigue crack growth rate for carbon and low alloy steel in water environment is given by Appendix A of ASME Code,Section XI as:
da/dN = CL
- dKA5.95 for dK < dKtran da/dN = CU
- SU
- dKA1.95 for dK >= dKtran
- where, dK = Kmax - Kmin R = Kmin /Kmax for R <= 0.25:
SL = 1.0 SU = 1.0 dKtran = 17.74 for 0.25 < R <= 0.65:
SL = 26.9* R - 5.725 SU = 3.75
- R + 0.06 dKtran = 17.74*{(3.75
- R + 0.06)/(26.9
- R - 5.725))AO.25 for 0.65 < R:
SL = 11.76 SU = 2.5 dKtran = 12.04
- where, CL = 1.0200e-012 CU = 1.01OOe-007 for the selected units of force, kip, and length, inch.
The fatigue crack growth is performed for the assumed number of 400 cycles of the maximum combined loading. The initial flaw depth of 0.14 inches is used.
The results of the fatigue crack growth evaluation show that the flaw in the CSW pipe weld does not grow after 400 cycles of the maximum combined loading range. This is because the stress range and, therefore, the corresponding stress intensity factor range are relatively small.
The pc-CRACK T h output file for the crack growth analysis is presented in Appendix A.
Revision: I StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page 6 of 10
6 CONCLUSIONS AND DISCUSSIONS Based on the results of the evaluation presented in this calculation package, the indications found during the inservice inspection of the CSW system Line are acceptable for continued operation based on the requirements of ASME Code,Section XI, IWB-3650. The allowable flaw depth for the observed combined flaw length is 75% of pipe wall thickness.
A fatigue crack growth analysis performed using a conservative fracture mechanics model and 400 cycles of the maximum combined loading shows that crack propagation by fatigue is not a concern as the flaw growth did not grow. This indicates that the allowable flaw depth will not be reached during plant operation including 20 years of life extension.
Revision: I StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page 7 of 10
7 REFERENCES
- 1. ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition with Addenda through 1990.
PAL-09Q-201.
- 3. Consumers Energy, Palisades Plant Stress Isometric 03316, Drawing No. VEN-M-101, Sheet No.2746, Rev. 6, "Service Water From Engineered Safeguards Cooler V-27 C &D West," SI File No.
PAL-09Q-202.
- 4. NMC Radiographic Examination Report, Sheet Number P-6-8001, dated 4/5/06, SI File No. PAL-09Q-203.
- 5. ASME Boiler and Pressure Vessel Code,Section III, Division 1, Appendices, 1989 Edition.
PAL-09Q-204.
- 7. Partial ADLPIPE Stress Analysis Output for CSW System Piping Analysis, EA-03316, 1/9/1995, SI File No. PAL-09Q-205.
- 8. pc-CRACKTM for Windows, Version 3.1-98348, Structural Integrity Associates, 1998.
StructuralIntegrity File No.: PAL-09Q-301 Revision: 1 Associates, Inc. Page 8 of 10
C = C0+ C1X+C 2X2 +C X3 C0 CO: surface stress (I=O)
--
- x A
Section A-A Calculated K is the maximum of K at points 1 and 2 at each crack depth (a)
Ref:, REQUIRED INPUTS:
ASME Section t: plate thickness XI, 95SEd.ci a: nrximum crack depth (a*x <O.8t)
(flaw shape parameter without plastic zone correction factor)
Figure 1: Elliptical Crack in Infinite Plate Model Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page 9 of 10
Stress Intensity Factors 0.8 C
0.5
- 0.4-
'*0.3-00.2 0.1o 0 9 0.02 0.04 0.06 0.08 0.1 0.12 0.04 0.16 0.18 0.2 C il Crack Depth (in.)
Figure 2: Applied Stress Intensity Factor StructuralIntegriy [File No.: PAL-09Q-301 Revision: I Associates, Inc. Page 10 of 10
APPENDIX A pc-CRACK OUTPUT FILES Filename Description Pages PALALW.OUT Allowable Flaw Size Calculation A2 - A3 PALFCG1.OUT Fatigue Crack Growth Analysis A4 - A15 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page Al of A15
pc-CRACK Output File for Allowable Flaw Evaluation tm pc-CRACK for Windows Version 3.1-98348 (C) Copyright '84 - '98 Structural Integrity Associates, Inc.
3315 Almaden Expressway, Suite 24 San Jose, CA 95118-1557 Voice: 408-978-8200 Fax: 408-978-8964 E-mail: pccrack@structint.com Allowable Flaw Size Evaluation Using ASME Section XI, IWB-3640/50 Procedures and Criteria For Circumferential Crack in Carbon Steel Piping Date: Mon May 01 12:29:13 2006 Input Data and Results File: PAL_ALW.CNS
Title:
PALISADES, ESW PIPE, CRITICAL FLAW EVALUATION Material: Seamless/Welded Wrought CS Pipe and Pipe Fitting, YS<=40ksi (Category 1)
Material properties:
Design stress = 18.1000 Flow stress = 43.4400 Elastic modulus = 26000.0000 Poisson ratio = 0.3000 Yield stress = 27.1000 JIc:
Lower shelf = 45.0000 Upper shelf = 600.0000 The evaluation assumes default material properties for a lower shelf temperature Pipe geometry:
Outer diameter = 3.5000 Wall thickness = 0.2160 Crack geometry:
Crack depth = 0.1400 Crack length = 0.2650 Kr' = 0.0256 Sr' = 0.0134 Sc = 1.9077 The flawed pipe is assumed to fail by brittle fracture(LEFM).
The allowable flaw size is determined using code formulas.
Default safety factors for normal operating (incl. upset and test) condition.
Membrane stress (Pm) 0.5710 (safety factor = 2.7700)
Bending stress (Pb) = 0.4480 (safety factor = 2.7700)
Expansion stress (Pe) = 0.0020 (safety factor = 1.0000)
StructuralIntegrity File No.: PAL-09Q-301 Revision: I Associates, Inc.Page A2 of A15
Design stress - 18.1000 (Pm + Pb) / Sm= 0.0563 KIr (residual stress) = 0.0000 (safety factor = 1.0000)
Nominal pipe size= 3.00100 a/t = 0.648:1 l/circumference = 0.024:1 allowable a/t = 0.75040 End of pc-CRACK Output Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A3 of A15
pc-CRACK Output File for Fatigue Crack Growth Analysis tm pc-CRACK for Windows Version 3.1-98348 (C) Copyright '84 - '98 Structural Integrity Associates, Inc.
3315 Almaden Expressway, Suite 24 San Jose, CA 95118-1557 Voice: 408-978-8200 Fax: 408-978-8964 E-mail: pccrack@structint.com Linear Elastic Fracture Mechanics Date: Mon May 01 12:30:50 2006 Input Data and Results File: PAL_FCG1.LFM
Title:
PALISADES, ESW PIPE, FATIGUE CRACK GROWTH ANALYSIS Load Cases:
Stress Coefficients Case ID CO C1 C2 C3 Type Total 0.965 -4.148 0 0 Coeff
Wall Through Stresses for Load Cases With Stress Coeff -------
Wall Case Depth Total 0.0000 0.965 0.0173 0.893323 0.0346 0.821645 0.0518 0.749968 0.0691 0.67829 0.0864 0.606613 0.1037 0.534935 0.1210 0.463258 0.1382 0.39158 0.1555 0.319903 0.1728 0.248226 Crack Model: Elliptical Surface Crack in an Infinite Plate (a/1=0.5)
Reference:
ASME Boiler and Pressure Vessel Code,Section XI, '95 Ed.
Flaw shape parameter is without plastic zone correction.
WARNING: The stress intensity factor (K) is the maximum of K at the surface and K at the deepest point at each crack depth.
Crack Parameters:
Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A4 of A15
Plate width: 0.2160 Max. crack size: 0.1728
Stress Intensity Factor .......
Crack Case Size Total 0.0035 0.0730043 0.0069 0.1031 0.0104 0.126088 0.0138 0.145373 0.0173 0.162275 0.0207 0.177471 0.0242 0.191585 0.0276 0.204768 0.0311 0.217127 0.0346 0.228793 0.0380 0.239861 0.0415 0.250408 0.0449 0.260663 0.0484 0.270693 0.0518 0.280372 0.0553 0.289731 0.0588 0.298798 0.0622 0.307594 0.0657 0.316243 0.0691 0.324987 0.0726 0.333532 0.0760 0.34189 0.0795 0.35007 0.0829 0.358083 0.0864 0.365936 0.0899 0.374191 0.0933 0.382319 0.0968 0.390326 0.1002 0.398215 0.1037 0.405992 0.1071 0.413659 0.1106 0.421651 0.1140 0.4297 0.1175 0.437667 0.1210 0.445556 0.1244 0.453367 0.1279 0.461103 0.1313 0.469093 0.1348 0.477352 0.1382 0.485553 0.1417 0.493699 0.1452 0.50179 0.1486 0.509825 0.1521 0.517955 0.1555 0.526485 0.1590 0.534972 0.1624 0.543417 0.1659 0.551819 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A5 of A15
0.1693 0.560177 0.1728 0.568493 Crack Growth Laws:
Law ID: CSteelinWater Model: ASME Section XI - ferritic steel in water environment da/dN = CL
- dK^5.95 for dK < dKtran da/dN = CU
- SU
- dK-1.95 for dK >= dKtran where dK= Kmax - Kmin R= Kmin / Kmax for R <= 0 .25:
SL = 1.0 SU = 1.0 dKtran = 17.74 for 0.25 < R <= 0.65:
SL = 26.9
- R - 5.725 SU = 3.75
- R + 0.06 dKtran = 17.74*{(3.75
- R + 0.06)/(26.9
- R - 5.725) }^0.25 for 0.6.5 < R:
SL = 11.76 SU = 2.5 dKtran = 12.04 where:
CL = 1.0200e-012 CU = 1.01OOe-007 are for the selected units of:
force: kip length: inch Material Fracture Toughness KIc:
Material ID: Carbon Steel Depth KIc 0.0000 36.2000 0.2160 36.2000 Initial crack size= 0.1400 Max. crack size= 0.1728 Number of blocks= 40 Print increment of block= 1 Cycles Calc. Print Crk. Grw. Mat.
Subblock /Time incre. incre. Law Klc Total 10 1 1 CSteelinWater Carbon Steel Kmax Kmin Subblock Case ID Scale Factor Case ID Scale Factor Total Total 1.0000 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A6 of A15
Crack growth results:
Total Subblock Cycles Cycles DaDn
/Time /Time Kmax Kmin DeltaK R /DaDt Da a a/thk Block:
1 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 2 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 3 3 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 4 4 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 5 5 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 6 6 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 7 7 4. 90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 8 8 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 9 9 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 10 10 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block:
11 1 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 12 2 4. 90e-001 0.00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 13 3 4. 90e-001 0.00e+000 4. 90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 14 4 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 15 5 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 16 6 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 17 7 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 18 8 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 19 9 4. 90e-001 0. 00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 20 10 4. 90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 Block:
21 1 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 22 2 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 23 3 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 24 4 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 25 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 26 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 27 7 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 28 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 29 9 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 30 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 Block: 4 31 1 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 32 2 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 33 3 4.90e-001 0. OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 34 4 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 35 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 36 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 37 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 38 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 39 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 40 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A7 of A15
Block: 5 41 1 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 42 2 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 43 3 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 44 4 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 45 5 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 46 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 47 7 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 48 8 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 49 9 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 50 10 4. 90e- 001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 Block: 6 51 1 4.90e-001 0.00e+000 4. 90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 52 2 4.90e-001 0. 00e+000 4. 90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 53 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 54 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 55 5 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 56 6 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 57 7 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 58 8 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 59 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 60 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 7 61 1 4. 90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 62 2 4. 90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 63 3 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 64 4 4. 90e- 001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 65 5 4. 90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 66 6 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 67 7 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 68 8 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 69 9 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 70 10 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 8 71 1 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 72 2 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 73 3 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 74 4 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 75 5 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 76 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 77 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 78 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 79 9 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 80 10 4.90e-001 0. OOe+O00 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 9 81 1 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 82 2 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 83 3 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 84 4 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 85 5 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 86 6 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 87 7 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 88 8 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 Revision:
StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A8 of A15
89 9 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 90 10 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 10 91 1 4.90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 92 2 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 93 3 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 94 4 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 95 5 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 96 6 4. 90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 97 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 98 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 99 9 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 100 10 4. 90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 Block: 11 101 1 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 102 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 103 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 104 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 105 5 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 106 6 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 107 7 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 108 8 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 109 9 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 110 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 Block: 12 111 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 112 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 113 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 114 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 115 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 116 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 117 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 118 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 119 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 120 10 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 13 121 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 122 2 4.90e-001 0.OOe+000 4. 90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 123 3 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 124 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 125 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 126 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 127 7 4.90e-001 0.OOe+600 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 128 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 129 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 130 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 14 131 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 132 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 133 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 134 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 135 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A9 of A15
136 6 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 137 7 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 138 8 4. 90e-001 0.00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 139 9 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 140 10 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 15 141 1 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 142 2 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 143 3 4.90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 144 4 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 145 5 4.90e-001 0.00e+000 4. 90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 146 6 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 147 7 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 148 8 4. 90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 149 9 4. 90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 150 10 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 16 151 1 4. 90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 152 2 4. 90e-001 0.00e+000 4. 90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 153 3 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 154 4 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 155 5 4. 90e-001 0.OOe+000 4. 90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 156 6 4. 90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 157 7 4. 90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 158 8 4. 90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 159 9 4. 90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 160 10 4.90e-001 0.00e+000 4. 90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 Block: 17 161 1 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 162 2 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 163 3 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 164 4 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 165 5 4.90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 166 6 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 167 7 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 168 8 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 169 9 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 170 10 4.90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 Block: 18 171 1 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 172 2 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 173 3 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 174 4 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 175 5 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 176 6 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 177 7 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 178 8 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 179 9 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 180 10 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 19 181 1 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 182 2 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page AlO of A15
183 3 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 184 4 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 185 5 4. 90e-001 0. OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 186 6 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 187 7 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 188 8 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 189 9 4.90e-001 0.OOe+O00 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 190 10 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 20 191 1 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 192 2 4.90e-001 0. OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 193 3 4.90e-001 0. OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 194 4 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 195 5 4.90e-001 0.OOe+000 4. 90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 196 6 4.90e-001 0.OOe+000 4. 90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 197 7 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 198 8 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 199 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 200 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 21 201 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 202 2 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 203 3 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 204 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 205 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 206 6 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 207 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 208 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 209 9 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 210 10 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 22 211 1 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 212 2 4. 90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 213 3 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 214 4 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 215 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 216 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 217 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 218 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 219 9 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 220 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 23 221 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 222 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 223 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 224 4 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 225 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 226 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 227 7 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 228 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 229 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 230 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page All of A15
Block: 24 231 1 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 232 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 233 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 234 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 235 5 4. 90e-001 0. OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 236 6 4. 90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 237 7 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 238 8 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 239 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 240 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 25 241 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 242 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 243 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 244 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 245 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 246 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 247 7 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 248 8 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 249 9 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 250 10 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 26 251 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 252 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 253 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 254 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 255 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 256 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 257 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 258 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 259 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 260 10 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 27 261 1 4.90e-001 0.OOe+O00 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 262 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 263 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 264 4 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 265 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 266 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 267 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 268 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 269 9 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 270 10 4. 90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 Block: 28 271 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 272 2 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 273 3 4.90e-001 O. OOe+O00 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 274 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 275 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 276 6 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 277 7 4.90e-001 0.OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 278 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A12 of A15
279 9 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 280 10 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 29 281 1 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 282 2 4. 90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 283 3 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 284 4 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 285 5 4. 90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 286 6 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 287 7 4. 90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 288 8 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 289 9 4. 90e-001 0. 00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 290 10 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 30 291 1 4.90e-001 0.00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 292 2 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 293 3 4. 90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 294 4 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 295 5 4. 90e-001 0.00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 296 6 4. 90e-001 0.00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 297 7 4. 90e-001 0. 00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 298 8 4. 90e-001 0. 00e+000 4. 90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 299 9 4.90e-001 0. 00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 300 10 4.90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 Block: 31 301 1 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 302 2 4.90e-001 0. 00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 303 3 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 304 4 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 305 5 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 306 6 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 307 7 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 308 8 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 309 9 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 310 10 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 32 311 1 4.90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 312 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 313 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 314 4 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 315 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 316 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 317 7 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 318 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 319 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 320 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 33 321 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 322 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 323 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 324 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 325 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 StructuralIntegrity File No.: PAL-09Q-301 Revision: 1 Associates, Inc. Page A13 of A15
326 6 4.90e-001 0. 00e+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 327 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 328 8 4. 90e-001 0. OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 329 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 330 10 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 Block: 34 331 1 4.90e-001 0.OOeO00 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 332 2 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 333 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 334 4 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 335 5 4. 90e-001 0.OOe+000 4. 90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 336 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 337 7 4.90e-001 0. OOe+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 338 8 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 339 9 4.90e-001 0.OOe+O000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 340 10 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 35 341 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 342 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 343 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 344 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 345 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 346 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 347 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 348 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 349 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 350 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 36 351 1 4. 90e-001 0.00e+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 352 2 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 353 3 4.90e-001 0. 00e+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 354 4 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 355 5 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 356 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 357 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 358 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 359 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 360 10 4. 90e-001 0.OOe+000 4. 90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 Block: 37 361 1 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 362 2 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 363 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 364 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 365 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 366 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 367 7 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 368 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 369 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 370 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 38 371 1 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 372 2 4.90e-001 0.00e+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A14 of A15
373 3 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 374 4 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 375 5 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 376 6 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 377 7 4. 90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 378 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 379 9 4.90e-001 0. OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 380 10 4.90e-001 0. OOe+000 4. 90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 39 381 1 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 382 2 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 383 3 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 384 4 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 385 5 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 386 6 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 387 7 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 388 8 4. 90e-001 0. 00e+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 389 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 390 10 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 Block: 40 391 1 4.90e-001 0. OOe+000 4. 90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 392 2 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1. 46e-014 0.14 0.65 393 3 4.90e-001 0.OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 394 4 4.90e-001 0. OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 395 5 4.90e-001 0. OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 396 6 4.90e-001 0. OOe+000 4.90e-001 0.00 1.46e-014 1.46e-014 0.14 0.65 397 7 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 398 8 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1.46e-014 0.14 0.65 399 9 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 400 10 4.90e-001 0.OOe+000 4.90e-001 0.00 1. 46e-014 1. 46e-014 0.14 0.65 End of pc-CRACK Output Revision: 1 StructuralIntegrity File No.: PAL-09Q-301 Associates, Inc. Page A15 of A15