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| issue date = 12/09/2011 | | issue date = 12/09/2011 | ||
| title = Request for Approval of Proposed Changes to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules | | title = Request for Approval of Proposed Changes to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules | ||
| author name = Mims D | | author name = Mims D | ||
| author affiliation = APS, Arizona Public Service Co | | author affiliation = APS, Arizona Public Service Co | ||
| addressee name = | | addressee name = | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:10 CFR 50, Appendix H A W A | {{#Wiki_filter:10 CFR 50, Appendix H A W A subsidiaryof Pinnacle West CapitalCorporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Senior Vice President Tel. 623-393-5403 P. 0. Box 52034 Generating Station Nuclear Regulatory and Oversight Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06447-DCM/GAM December 09, 2011 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | ||
==Dear Sirs:== | ==Dear Sirs:== | ||
==Subject:== | ==Subject:== | ||
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Request for Approval of Proposed Changes to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Arizona Public Service Company (APS) is requesting approval of proposed changes to the PVNGS Units 1, 2, and 3 reactor pressure vessel surveillance capsule withdrawal schedules in the Updated Final Safety Analysis Report. The proposed changes are submitted pursuant to Title 10 of the Code of | Palo Verde Nuclear Generating Station (PVNGS) | ||
The proposed changes to the reactor pressure vessel surveillance capsule withdrawal schedules are consistent with the recommendations specified in American Society for Testing and Materials (ASTM) Standard Practice E 185-82, as referenced by the requirements of 10 CFR Part 50, Appendix H. In addition, the proposed changes are consistent with Commitment No. 17 in Table A4-1 in the PVNGS license renewal application submitted in APS letter no. 102-05937, dated December 11, 2008 (ADAMS Accession No. ML083510627), and Appendix A in the related NRC Safety Evaluation Report, NUREG-1 961 (ADAMS Accession No. | Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Request for Approval of Proposed Changes to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Arizona Public Service Company (APS) is requesting approval of proposed changes to the PVNGS Units 1, 2, and 3 reactor pressure vessel surveillance capsule withdrawal schedules in the Updated Final Safety Analysis Report. The proposed changes are submitted pursuant to Title 10 of the Code of FederalRegulations (10 CFR) Part 50, Appendix H, Section III.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation. | ||
The proposed changes to the reactor pressure vessel surveillance capsule withdrawal schedules are consistent with the recommendations specified in American Society for Testing and Materials (ASTM) Standard Practice E 185-82, as referenced by the requirements of 10 CFR Part 50, Appendix H. In addition, the proposed changes are consistent with Commitment No. 17 in Table A4-1 in the PVNGS license renewal application submitted in APS letter no. 102-05937, dated December 11, 2008 (ADAMS Accession No. ML083510627), and Appendix A in the related NRC Safety Evaluation Report, NUREG-1 961 (ADAMS Accession No. ML11095A011). | |||
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway | |||
* Comanche Peak | * Comanche Peak | ||
* Diablo Canyon | * Diablo Canyon | ||
* Palo Verde -San Onofre -South Texas | * Palo Verde - San Onofre - South Texas | ||
* Wolf Creek ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Request for Approval of Proposed Changes to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Page 2 No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.Sincerely, fc'e p. c, /,./,,,45 DCM/RAS/GAM/gat | * Wolf Creek | ||
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Request for Approval of Proposed Changes to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Page 2 No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111. | |||
Sincerely, fc'e p. c, /,./,,,45 DCM/RAS/GAM/gat | |||
==Enclosure:== | ==Enclosure:== | ||
Proposed Changes to the Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules cc: E. E. Collins Jr. NRC Region IV Regional Administrator L. K. Gibson NRC NRR Project Manager for PVNGS J. R. Hall NRC NRR Senior Project Manager M. A. Brown NRC Senior Resident Inspector for PVNGS | |||
Enclosure Proposed Changes to the Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules | |||
==1.0 INTRODUCTION== | |||
==2.0 REGULATORY EVALUATION== | |||
2.1 License Renewal Commitment 3,0 TECHNICAL EVALUATION 3.1 Evaluation Criteria of ASTM Standard Practice E 185-82 3.2 Changes Proposed to the Withdrawal Schedule for PVNGS Units 1, 2, and 3 | |||
==4.0 CONCLUSION== | |||
5,0 REFERENCES ATTACHMENT Updated Final Safety Analysis Report Markups | |||
Proposed Changes to the | Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules | ||
==1.0 INTRODUCTION== | ==1.0 INTRODUCTION== | ||
Arizona Public Service Company (APS) is requesting approval of proposed changes to the Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 reactor pressure vessel (RPV) surveillance capsule withdrawal schedules. The proposed changes are submitted pursuant to Title 10 of the Code of FederalRegulations (10 CFR) Part 50, Appendix H, Section III.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation, The proposed changes to the RPV surveillance capsule withdrawal schedules are consistent with the recommendations specified in American Society for Testing and Materials (ASTM) Standard Practice E 185-82, as referenced by the requirements of 10 CFR Part 50, Appendix H. In addition, the proposed changes are consistent with Commitment No. 17 in Table A4-1 in the PVNGS license renewal application submitted in APS letter no. 102-05937, dated December 11, 2008 (ADAMS Accession No. ML083510627), as reflected in Appendix A in the related NRC Safety Evaluation Report, NUREG-1961 (ADAMS Accession No. ML11095AO11). | |||
2. | ==2.0 REGULATORY EVALUATION== | ||
Appendix H to 10 CFR Part 50 requires nuclear power plant licensees to implement reactor pressure vessel (RPV) surveillance programs to "monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region... which result from the exposure of these materials to neutron irradiation and the thermal environment." Section III.B.1 of Appendix H states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the American Society for Testing and Materials (ASTM) E 185, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," | |||
that is current on the issue date of the American Society of Mechanical Engineers (ASME) Code to which the RPV was purchased. The rule permits the use of later editions of ASTM E 185, but including only those editions through 1982 (i.e., ASTM E 185-82). The current PVNGS Units 1,2, and 3, RPV surveillance programs and the withdrawal schedules meet the requirements of ASTM E 185-82. | |||
Appendix H to 10 CFR Part 50, Section III.B.3, requires prior NRC approval of all RPV surveillance capsule withdrawal schedule changes. Further, NRC Administrative Letter 97-04, "NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules," dated September 30, 1997, specifies that changes to RPV surveillance capsule withdrawal schedules that do not conform to ASTM E 185 require approval by the license amendment process, whereas changes that conform to the ASTM standard require only staff verification of such conformance. The proposed changes to the PVNGS Units 1, 2, and 3 RPV surveillance capsule withdrawal schedules conform to ASTM E 185-82, and, therefore, a license amendment is not required for these proposed changes. | |||
1 | |||
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules 2.1 License Renewal Commitment The PVNGS Units 1,2, and 3 license renewal application (Ref. 5.1) contained the following item in Commitment No. 17 in Table A4-1, as reflected in Appendix A of the related NRC Safety Evaluation Report, NUREG-1961, April 2011 (Ref. 5.2): | |||
Priorto the period of extended operation: | |||
o The [reactorpressure vessel surveillance program]schedule will be revised to withdraw the next capsule at the equivalent clad-base metal exposure of approximately 54 effective full power years (EFPY)expected for the 60-year period of operation, and to withdraw remaining standby capsules at equivalent clad-base metal exposures not exceeding the 72 EFPY expected for a possible 80-year second period of extended operation. This withdrawalschedule is in accordance with NUREG-1801 | |||
[GenericAging Lessons Learned (GALL) Report], Section XI.M31, item 6, and with the ASTM E 185-82 criterion which states that capsules may be removed when the capsule neutron fluence is between one and two times the limiting fluence calculated for the vessel at the end of expected life. | |||
This schedule change must be approved by the NRC, as required by 10 CFR 50 Appendix H. | |||
This request to revise the PVNGS Units 1, 2, and 3 RPV surveillance capsule withdrawal schedules will address this commitment. | |||
== | ==3.0 TECHNICAL EVALUATION== | ||
3.1 Evaluation Criteria of ASTM Standard Practice E 185-82 Table 1 of ASTM Standard Practice E 185-82 requires that either a minimum of three, four, or five surveillance capsules be removed from the vessels, as based on the limiting amount of reference temperature for nil-ductility transition shift (limiting RTNDT) that is projected to occur at the clad-vessel interface location of the RPV at the end-of-licensed plant life (EOL). For plants with projected RTNDT shifts (i.e., ARTNDT) less than 100 OF (56 0C), three capsules are required to be removed from the RPV. | |||
For the renewed operating license operating terms, the PVNGS RPVs have limiting ARTNDT values of less than 100 OF. At 60 years (54 EFPY), the maximum shift in reference temperature for pressurized thermal shock (ARTPTS) is 57.7 OF for Unit 1, the maximum ARTPTS is 54 OF for Unit 2, and the maximum ARTPTS is 40.7 °F for Unit 3 (Ref. 5.1, License Renewal Application Tables 4.2-6, 7, and 8). In this context, ARTPTS is equivalent to ARTNDT. Therefore APS is required, as a minimum, to remove three capsules from each reactor during the current operating period. | |||
2 | |||
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Table 1 of ASTM Standard Practice E 185-82 also provides specific criteria for removal of surveillance capsules. The criteria are that the surveillance capsules be removed after a certain amount of power operation has elapsed or at various times when the RPV shell is projected to achieve certain levels of neutron fluence. The intent of the Standard Practice is to achieve a set of testing data over a range of neutron fluences for the RPV that bounds the current life of the plant. Of key importance are the removal criteria for the second to last and final capsules required for capsule withdrawal. For the second-to-last required capsule in a withdrawal schedule, the ASTM standard requires that the capsules be pulled at either 13 effective full power years (EFPYs) or at the time when the capsule is equivalent to the limiting fluence projected for the clad-based metal interface of the RPV at EOL, whichever time comes first. For the final capsule that is required for removal, ASTM E 185-82 requires that the capsule be removed at a time when the neutron fluence projected for the capsule is between the limiting fluence value projected for the RPV at the EOL and two times that value. | |||
3.2 Changes Proposed to the Withdrawal Schedule for PVNGS Units 1, 2, and 3 The proposed changes to the PVNGS Units 1, 2, and 3 RPV surveillance capsule withdrawal schedule are shown in the attached markups of UFSAR Tables 5.3-18, 5.3-19, 5.3-19A, 5.3-13, 5.3-14, and 5.3-15. | |||
For the final capsule that is required for removal, ASTM E 185-82 requires that the capsule be removed at a time when the neutron fluence projected for the capsule is between the limiting fluence value projected for the RPV at the EOL and two times that value. The limiting fluence values projected for the RPVs at the EOL for the final capsule required for removal from each unit, Capsule 6 (3100), are shown in Tables 3.2-1, 3.2-2, and 3.2-3 below. | |||
3 | |||
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Table 3.2-1 PVNGS Unit I Reactor Pressure Vessel Surveillance Capsule Withdrawalma) | |||
Capsule No. | |||
CapsuleWihrwlIM Location Location_____ Lead Factor EFPY(b) | |||
Withdrawal Fune(lm Fluence (n 3 1370 1.34 4.57 3.65E18 1 380 1.33 9.76 6.28E18 5 2300 1.35 13.83 8.76E18 6 3100 1.35 40OC) 2.56E19(O) 2 430 1.35 Standby 4 1420 1.35 Standby (a) Based on Table 7-1 in WCAP-16374-NP, "Analysis of Capsule 2300 from the Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program," February 2005 (Ref. 5.3). | |||
(b) Effective full power years (EFPY) from plant startup. | |||
(c) Equivalent to capsule accumulating a fluence equal to 54 EFPY. | |||
(d) Calculated at reactor vessel clad-to-metal interface. (Source: Table 1-2 of WCAP-1 6835-NP [Ref. | |||
5.6]. This value was calculated for the current maximum licensed power of 3990 MWt, whereas the 2.51 E19 value shown in Table 6-2 in WCAP-1 6374 [Ref. 5.3] and in Section 4.2.1 of the PVNGS License Renewal Application [Ref. 5.1] was calculated for the previous maximum licensed power of 3876 MWt prior to implementation of the Unit 1 power uprate license amendment.) | |||
Table 3.2-2 PVNGS Unit 2 Reactor Pressure Vessel Surveillance Capsule Withdrawal(a) | |||
(a) Based on Table 7-1 in WCAP-16524-NP, "Analysis of Capsule 2300 from the Arizona Public Service Company Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program," February 2006 (Ref. 5.4). | |||
(b) Effective full power years (EFPY) from plant startup. | |||
EFPY(b) Fune(lm 3 1370 1.34 4.57 3.65E18 1 380 1.33 9.76 6.28E18 5 2300 1.35 13.83 8.76E18 6 3100 1.35 40OC) 2.56E19(O) 2 430 1.35 Standby 4 1420 1.35 Standby (a) Based on Table 7-1 in WCAP-16374-NP, "Analysis of Capsule 2300 from the Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program," February 2005 (Ref. 5.3).(b) Effective full power years (EFPY) from plant startup.(c) Equivalent to capsule accumulating a fluence equal to 54 EFPY.(d) Calculated at reactor vessel clad-to-metal interface. (Source: Table 1-2 of WCAP-1 6835-NP [Ref.5.6]. This value was calculated for the current maximum licensed power of 3990 MWt, whereas the 2.51 E19 value shown in Table 6-2 in WCAP-1 6374 [Ref. 5.3] and in Section 4.2.1 of the PVNGS License Renewal Application | (c) Equivalent to capsule accumulating a fluence equal to 54 EFPY. | ||
[Ref. 5.1] was calculated for the previous maximum licensed power of 3876 MWt prior to implementation of the Unit 1 power uprate license amendment.) | (d) Calculated at reactor vessel clad-to-metal interface. (Source: Table 1-3 of WCAP-16835-NP [Ref. | ||
Table 3.2-2 PVNGS Unit 2 Reactor Pressure Vessel Surveillance Capsule Withdrawal(a)(a) Based on Table 7-1 in WCAP-16524-NP, "Analysis of Capsule 2300 from the Arizona Public Service Company Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program," February 2006 (Ref. 5.4).(b) Effective full power years (EFPY) from plant startup.(c) Equivalent to capsule accumulating a fluence equal to 54 EFPY.(d) Calculated at reactor vessel clad-to-metal interface. (Source: Table 1-3 of WCAP-16835-NP | 5.6]. This value was calculated for the current maximum licensed power of 3990 MWt, and is the same as shown in Table 6-2 in WCAP-1 6524 [Ref. 5.4] and in Section 4.2.1 of the PVNGS License Renewal Application [Ref. 5.1], reflecting the Unit 2 power uprate license amendment.) | ||
[Ref.5.6]. This value was calculated for the current maximum licensed power of 3990 MWt, and is the same as shown in Table 6-2 in WCAP-1 6524 [Ref. 5.4] and in Section 4.2.1 of the PVNGS License Renewal Application | 4 | ||
[Ref. 5.1], reflecting the Unit 2 power uprate license amendment.) | |||
4 | |||
==4.0 CONCLUSION== | Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Table 3.2-3 Pressure Vessel Surveillance PVNGS Unit 3 ReactorCapsule Capsule Withdrawal(a) | ||
WithdrawalM2 Capsule__No. | |||
Capsule No. Location ca LaFctrEFPY(b) | |||
Lead Factor Fluence (n/cm2 ) | |||
4 1370 1.28 4.44 3.48E18 5 2300 1.31 13.75 9.07E18 6 3100 1.31 42(c) 2.99E19(d) 2 430 1.30 Standby 3 1420 1.28 Standby 1 380 1.28 Standby (a) Based on Table 7-1 in WCAP-16449-NP, "Analysis of Capsule 2300 from the Arizona Public Service Company Palo Verde Unit 3 Reactor Vessel Radiation Surveillance Program," August 2005 (Ref. 5.5). | |||
(b) Effective full power years (EFPY) from plant startup. | |||
(c) Equivalent to capsule accumulating a fluence equal to 54 EFPY. | |||
(d) Calculated at reactor vessel clad-to-metal interface. (Source: Table 1-4 of WCAP-16835-NP [Ref. | |||
5.6]. This value was calculated for the current maximum licensed power of 3990 MWt, whereas the 2.93E19 value shown in Table 6-2 in WCAP-16449 [Ref. 5.5] and in Section 4.2.1 of the PVNGS License Renewal Application [Ref. 5.1] was calculated for the previous maximum licensed power of 3876 MWt prior to implementation of the Unit 3 power uprate license amendment.) | |||
==4.0 CONCLUSION== | |||
The proposed changes to the PVNGS RPV surveillance capsule withdrawal schedules will continue to meet the RPV surveillance capsule withdrawal schedule criteria in ASTM E 185-82 for the renewed licensed periods of PVNGS Units 1, 2, and 3. | The proposed changes to the PVNGS RPV surveillance capsule withdrawal schedules will continue to meet the RPV surveillance capsule withdrawal schedule criteria in ASTM E 185-82 for the renewed licensed periods of PVNGS Units 1, 2, and 3. | ||
==5.0 REFERENCES== | ==5.0 REFERENCES== | ||
5.1 Letter no. 102-05937, from APS to the NRC, "License Renewal Application," | |||
December 11, 2008 (ADAMS Accession No. ML083510627) 5.2 NUREG-1961 "Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Units 1,2 and 3." (ADAMS Accession No. ML11095A011) 5.3 Letter no. 102-05242 from APS to the NRC, "Palo Verde Nuclear Generating Station Unit 1 Reactor Vessel Material Surveillance Capsule at 230','' April 5, 2005 (transmittal of WCAP-16374-NP, "Analysis of Capsule 230' from Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program," February 2005) (ADAMS Accession No. not publicly available). | |||
5 | |||
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules 5.4 Letter no. 102-05457 from APS to the NRC, "Palo Verde Nuclear Generating Station Unit 2 Reactor Vessel Material Surveillance Capsule at 2300,' April 4, 2006 (transmittal of WCAP-16524-NP, "Analysis of Capsule 230' from Arizona Public Service Company Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program," February 2006) (ADAMS Accession No. ML061040586). | |||
5.5 Letter no. 102-05348 from APS to the NRC, "Palo Verde Nuclear Generating Station Unit 3 Analysis of Reactor Vessel Material Surveillance Capsule at 2300," | |||
September 26, 2005 (transmittal of WCAP-16449-NP, "Analysis of Capsule 2300 from Arizona Public Service Company Palo Verde Unit 3 Reactor Vessel Radiation Surveillance Program," August 2005) (ADAMS Accession No. ML053390139). | |||
5.6 Westinghouse Report WCAP-16835-NP, "Palo Verde Nuclear Generating Station Units 1, 2, and 3; Basis for RCS Pressure and Temperature Limits Report," June 2008 (ADAMS Accession No. ML090641016). This report was submitted with letter no. 102-05960 from APS to the NRC, "Request for Technical Specification Amendment and Exemption from 10 CFR 50, Appendix G, to Relocate the Reactor Coolant System Pressure and Temperature Limits and the Low Temperature Overpressure Protection Enable Temperatures," February 19, 2009 (ADAMS Accession No. ML090641014). | |||
6 | |||
ATTACHMENT Updated Final Safety Analysis Report Markups Page No. | |||
5.3-27 (no changes - for information only) 5.3-28 (no changes - for information only) 5.3-29 (no changes - for information only) 5.3-30 5.3-31 (no changes - for information only) 5.3-32 (no changes - for information only) 5.3-33 5.3-34 (no changes - for information only) 5.3-35 (no changes - for information only) 5.3-36 (no changes - for information only) 5.3-37 5.3-46 5.3-47 | |||
No changes to this page - | |||
for information only Table 5.3-13 C- PVNGS UNIT 1 SURVEILLANCE PROGRAM (Sheet 1 of 4) | |||
(D r') | |||
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY") Factor Material Origins No. Type Orientation 1 380 8-10 1.0<LF<I.5 Base metal 15 C, Trans. | |||
PC, lower shell plate 9 PC, Trans. | |||
M-4311-I1*' 9 PCv Long. | |||
3 Tension Trans. | |||
9 Cv Long. | |||
Weld metalb 3 Tension Trans. 1-3 M-4311-2/M-4311-3('1 15 C, Trans. | |||
weld wires tl) | |||
(-n B-4 heat/lot 90071 9 PC, Trans. | |||
Flux Linde 0091/1054 HAZ metal 12 C, Trans. | |||
Lower shell plate M-4311-1 SRM HSST plate 01d) 9 Cý Long. | |||
0 | |||
: a. See table 5.3-1 for chemistry of plate code No. M-4311-1 (lower shell plates). | |||
C') | |||
: b. See table 5.3-2 for chemistry of weld code No. 101-142 A-C (lower shell long seams). Wl (D c. Surveillance weld metal between plates m-4311-2 and M-4311-3 (long seams). | |||
: d. See ORNL-4315, dated February 1968 for chemistry of SRM (HSST-01 Ppate). | |||
H" e. See table 5.3-1 for chemistry of plate code No. M-6701-2 (intermediate shell plate). | |||
0 | |||
: f. Effective full power years. | |||
o- | |||
No changes to this page - | |||
for information only Table 5.3-13 C- PVNGS UNIT 1 SURVEILLANCE PROGRAM (Sheet 2 of 4) | |||
(D C) Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY"' Factor Material Origins No. Type Orientation 2 430 Standby 1.0<LF<I.5 Base metal 15 C, Trans. | |||
CT Inter. shell plate 10 1/2t CT Trans. z M-6701-2 e( 3 Tension Trans. | |||
U) | |||
Weld metal(b) 3 Tension Trans. | |||
M-4311-2/M-4311-3(o 15 C, Trans. | |||
Weld wires B-4 heat lot 90071 10 1/2t CT Trans. H Flux Linde 0091/1054 I-zj Cn HAZ metal 12 C, Trans. U) | |||
Lower shell plate M-4311-1(" | |||
co SRM HSST plate 01d 9 C, Long. | |||
3 1370 4-5 1.0<LF<l.5 Base metal 15 C, Trans. | |||
PC, Inter shell plate 9 PC, Trans. | |||
M-6701-2"'e 9 PC, Long. C) 3 Tension Trans. | |||
9 C, Long. 0 Weld metalb 3 Tension Trans. | |||
M-4311-2/M-4311-3(ý) 15 C, Trans. | |||
Weld wire W) | |||
U/) | |||
B-4 heat/lot 90071 9 PC, Trans. no Flux Linde 0091/1054 t-i (D | |||
HAZ metal 12 C, Trans. | |||
Lower shell plate M-4311-1 0 | |||
SRM HSST plate 01d 9 C, Long. | |||
I-. | |||
No changes to this page - | |||
for information only Table 5.3-13 PVNGS UNIT 1 SURVEILLANCE PROGRAM (Sheet 3 of 4) | |||
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY'f Factor Material Origins No. Type Orientation 4 1420 Standby 1.0<LF<1.5 Base metal 15 C0 Trans. | |||
CT Lower shell plate 10 1/2t CT Trans. | |||
M-4311-1"a' 3 Tension Trans. G') | |||
C/) | |||
Weld metallbI 3 Tension Trans. | |||
0 M-4311-2/M-4311-3( ) 15 C0 Trans. | |||
Weld wires B-4 heat lot 90071 10 1/2t CT Trans. C: | |||
Flux Linde 0091/1054 3 Tension Trans. | |||
HAZ metal 12 C0 Trans. | |||
Lower shell plate M-4311-1"' | |||
SRM HSST plate 01dl 9 C, Long. | |||
5 2300 12-15 1.0<LF<I.5 Base metal 15 C0 Trans. | |||
PC, Inter shell plate 9 PC, Trans. | |||
M-6701-2") 9 PC, Long. | |||
3 Tension Trans. | |||
9 C0 Long. 0 Weld metallb 3 Tension Trans. | |||
0 M-4311-2/M-4311-3( ) 15 C0 Trans. | |||
Weld wire B-4 heat/lot 90071 9 PC0 Trans. t7' Flux Linde 0091/1054 HAZ metal 12 C0 Trans. | |||
Lower shell plate M-4311-1") 12 C0 Trans. | |||
SRM HSST plate 01(d) 9 C0 Long. | |||
Table 5.3-13 PVNGS UNIT 1 SURVEILLANCE PROGRAM (Sheet 4 of 4) | |||
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY") Factor Material Origins No. Type Orientation 6 3100 I 1.0<LF<I.5 Base metal 15 C, Trans. | |||
CD PC, 4 Lower shell plate 9 PCv Trans. | |||
M-4311-1'a 9 PC, Long. | |||
F044 3 Tension Trans. C') | |||
WI- 9 C, Long. | |||
Weld metal bI 3 Tension Trans. | |||
M-4311-2/M-4311-3(') 15 Cý Trans. | |||
Weld wires B-4 heat/lot 90071 9 PCý Trans. | |||
Flux Linde 0091/1054 C/) | |||
(C) HAZ metal 12 C, Trans. | |||
Lower shell plate M-4311-1") | |||
SRM HSST plate 01d) 9 C, Long. | |||
0 1l (D | |||
H-00' | |||
No changes to this page - | |||
r-I for information only CD Table 5.3-14 N) PVNGS UNIT 2 SURVEILLANCE PROGRAM (Sheet 1 of 3) | |||
C) | |||
Capsule Assembly Withdrawal Specimens No. and Azimuthal Schedule Lead Surveillance Type Location EFPY") Factor Material Origins No. Type Orientation 1 380 Standby 1.0<LF<I.5 Base metal 15 C, Trans CT Lower shell plate 10 1/2t CT Trans F-773-1. 3 Tension Trans Weld metalc'c 15 C, Trans F-773-2/F-773-3(ý) 10 1/2t CT Trans F-3 Weld wires 3 Tension Trans B-4 heat/lot 3P7317 Flux Linde 124/0662 Cl) | |||
Cn HAZ metal 12 C, Trans Lower shell plate Cd Id F_ 773-IbI SRM HSST plate 01"e' 9 C, Long. | |||
2 430 Standby 1.0<LF<l.5 Base metal 15 Cv Trans CT Lower shell plate 10 1/2t CT Trans F- 7 7 3-I'b) 3 Tension Trans Weld metal"c) 15 Cv Trans F-773-2/F-773-3(d) 10 1/2t CT Trans Weld wire 3 Tension Trans B-4 heat/lot 3P7317 Flux Linde 124/0662 0 HAZ metal 12 C, Trans Lower shell plate (D F-773-11b) | |||
Cl) | |||
SRM HSST plate 01 9 C, Trans t7-1 01(e) 0 | |||
: a. Effective full power years. | |||
: b. See tables 5.3-3 for chemistry of plates. | |||
: c. See tables 5.3-4 for chemistry of weld code No. 101-142 A-C (lower shell long seams). | |||
: d. Surveillance weld metal formed between designated plates | |||
: e. See ORNL-4315 dated February 1968 for chemistry of SRM (HHST-01 plate). | |||
No changes to this page - | |||
for information only C-4 (D Table 5.3-14 PVNGS UNIT 2 SURVEILLANCE PROGRAM (Sheet 2 of 3) | |||
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY'*' Factor Material Origins No. Type Orientation 3 1370 4-6 1.0<LF<I.5 Base metal 15 Cv Trans PCý Lower shell plate 9 PCý Trans N) F-773-1IbI 9 PC, Long. | |||
3 Tension Trans 0 9 CQ Long. | |||
Weld metal'c' 15 C, Trans F-773-2/F-773-3(ý) 9 PC, Trans Weld wires 3 Tension Trans B-4 heat/lot 3P7317 cl) | |||
Flux Linde 124/0662 HAZ metal 12 C, Trans Lower shell plate F-773-I'0 ' | |||
SRM HSST plate 01'* 9 C, Long. | |||
4 142' Standby 1.0<LF<I.5 Base metal 15 C, Trans CT Lower shell plate 10 1/2T CT Trans F-773-1Ib 3 Tension Trans Weld metal"c) 15 C, Trans F-773-2/F-773-3'd) | |||
Weld wire 10 1/2t CT Trans 0 B-4 heat/lot 3P7317 Flux Linde 124/0662 3 Tension Trans HAZ metal 12 C, Trans Cf) | |||
(D Lower shell plate 0 F-773- _IbI 02 SRM HSST plate 01"' 9 C Long. | |||
O | |||
C-4 Table 5.3-14 (D PVNGS UNIT 2 SURVEILLANCE PROGRAM (Sheet 3 of 3) | |||
N) | |||
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY W Factor Material Origins No. Type Orientation 5 2300 12-15 1.0<LF<I.5 Base metal 15 C0 Trans PC, Lower shell plate 9 PC, Trans 0 | |||
F-773-1' ' 9 PC0 Long. z 3 Tension Trans Cl) 9 C, Long. | |||
Weld metal"'l 15 C0 Trans '-0 0 | |||
F-773-2/F-773-3' ' 9 PC, Trans Weld wires 3 Tension Trans | |||
'-3 B-4 heat/lot 3P7317 Flux Linde 124/0662 4::, | |||
CA ITj HAZ material 12 Cv Trans Cl) | |||
Lower shell plate F-773-1I'b SRM HSST plate 01 9 C, Long. | |||
6 310' 1.0<LF<I.5 Base metal 15 C0 Trans PC, Lower shell plate 9 PC, Trans F-773-1I~b 9 PC, Long. | |||
3 Tension Trans 9 C0 Long. '-3 Weld metal"'* 15 C, Trans 0 0 | |||
F-773-2/F-773-3' ' Tension Trans Weld wire 9 PC0 Trans B-4 heat/lot 3P7317 Flux Linde 124/0662 (D HAZ metal 12 C0 Trans Lower shell plate F-773-1 0 SRM HSST plate 01"' 9 C0 Long. | |||
for changes to only No information this page - | |||
Table 5.3-15 CA PVNGS UNIT 3 SURVEILLANCE PROGRAM (Sheet 1 of 4) | |||
(D N) Capsule Specimens I-, | |||
Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPYle, Factor Material Origins No. Type Orientation 1 380 Standby 1.0<LF<I.5 Base metal 15 Cv Trans. | |||
CT Lower shell plate 10 1/2t CT Trans. | |||
F-6411-2 a) 3 Tension Trans. 0 U) | |||
Weld metal1b, 15 C, Trans. | |||
F-6411-1 to 3(C) 10 1/2t CT Trans. | |||
Weld wires 3 Tension Trans. | |||
B-4 heat lot 4P7869 H Flux Linde 124/0281 | |||
'-Il HAZ metal 12 Cv Trans. Cl) | |||
Lower shell plate F-6411-2"' | |||
SRM HSST plate 01l 9 Cv Long. | |||
2 430 Standby 1.0<LF<I.5 Base metal 15 Cv Trans. | |||
CT Lower shell plate 10 1/2t CT Trans. | |||
F-6411-2"a 3 Tension Trans. | |||
0 | |||
: a. See table 5.3-5 for chemistry of plates. | |||
: b. See table 5.3-6 for chemistry of weld code No. 101-142 A-C (lower shell long seams). CO W) | |||
C. Surveillance weld metal formed between designated plates. | |||
(D | |||
: d. See ORNL-4315 dated February 1968 for chemistry of SRM (HSST-01 plate). | |||
O e. Effective full power years. | |||
:o3 | |||
No changes to this page - | |||
for information only Table 5.3-15 PVNGS UNIT 3 SURVEILLANCE PROGRAM (Sheet 2 of 4) | |||
(D C) Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY"' Factor Material Origins No. Type Orientation 2 Weld metal bI 15 C, Trans. | |||
CT F-6411-1 to 3"C' 10 1/2t CT Trans. | |||
(Cont.) Weld wires 3 Tension Trans. C) | |||
B-4 heat lot 4P7869 U) | |||
I-Flux Linde 124/0281 '-0 Trans. U HAZ metal 4 12 C, al Lower shell plate F-6411-2 H U | |||
SRM HSST plate 01 l 9 Cv Long. | |||
'-Il CI) | |||
C-n 3 1420 Standby 1.0<LF<I.5 Base metal 15 Cv Trans. | |||
PC, Lower shell plate 9 PC, Trans. | |||
F-6411-2"' 9 PC, Long. | |||
3 Tension Trans. | |||
9 C, Long. | |||
Weld metalc 15 C, Trans. | |||
F-6411-1 to 3(C' 9 PC, Trans. | |||
Weld wire 3 Tension Trans. | |||
0 B-4 heat/lot 4P7869 Flux Linde 124/0281 HAZ metal 12 C, Trans. Cn Lower shell plate F-6411-2c tzl (D | |||
SRM HSST plate 01' 9 Cv Long. | |||
H-0 0H | |||
No changes to this page - | |||
for information only Table 5.3-15 PVNGS UNIT 3 SURVEILLANCE PROGRAM (Sheet 3 of 4) | |||
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY(e) Factor Material Origins No. Type Orientation 4 1370 4-6 1.0<LF<l.5 Base metal 15 C0 Trans. | |||
CT Lower shell plate F-6411-2"'e 10 1/2t CT Trans. | |||
3 Tension Trans. Cl) | |||
Weld metal(b) 15 C, Trans. | |||
F-6411-1 to 3(0) | |||
Weld wire 10 1/2t CT Trans. Lii B-4 heat lot 4P7869 tJ2 Flux Linde 124/0281 3 Tension Trans. | |||
HAZ metal 12 C0 Trans. | |||
Lower shell plate F-6411-2a SRM HSST plate 01(d) 9 C, Long. | |||
5 2300 12-15 1.0<LF<1.5 Base metal 15 C0 Trans. | |||
PC, Lower shell plate 9 PC, Trans. | |||
F-6411-2"' 9 PC, Long. | |||
3 Tension Trans. F-3 9 C0 Long. | |||
Cf) | |||
Weld metal 0 bI 15 C0 Trans. | |||
F-6411-1 to 3C) 9 PC, Trans. | |||
Weld wire 3 Tension Trans. | |||
Cl) | |||
B-4 heat/lot 4P7869 NI Flux Linde 124/0281 HAZ material 12 C0 Trans. | |||
Lower shell plate F-6411-2' SRM HSST plate 01(dl 9 C0 Long. | |||
C-4 Table 5.3-15 PVNGS UNIT 3 SURVEILLANCE PROGRAM (Sheet 4 of 4) | |||
F-. | |||
I-, | |||
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY"' Factor Material Origins No. Type Orientation 6 3100 1_P-2_4 1.0<LF<I.5 Base metal 15 C, Trans. | |||
PC, Lower shell plate 9 PC, Trans. | |||
F-6411-2"' 9 PC, Long. | |||
3 Tension Trans. | |||
9 C, Long. | |||
C" Weld metalb 15 C, Trans. | |||
F-6411-1 to 3(C) 9 Tension Trans. | |||
Weld wire 3 PC, Trans. | |||
B-4 heat/lot 4P7869 I-Cl Flux Linde 124/0281 HAZ metal 12 C, Trans. | |||
Lower shell plate F-6411-2"' | |||
Cn SRM HSST plate 01(dl 9 Cý Long. | |||
0 o- t7-' | |||
PVNGS UPDATED FSAR REACTOR VESSEL Table 5.3-18 PVNGS UNIT 1 CAPSULE ASSEMBLY REMOVAL SCHEDULE Azimuthal Removal Base Metal Capsule Locations Time Material Included 1 380 8-10 EFPY Lower shell PCv 2 430 Standby Intermediate shell CT 3 1370 4-5 EFPY Intermediate shell PCv 4 1420 Standby Lower shell CT 5 2300 12-15 EFPY Intermediate shell PCv 6 3100 I- 4 EFPY Lower shell PCv Note: Schedule may be odified to coincide with those refueling o ages or scheduled shutdowns most closely approximat g the withdrawal schedule. | |||
140-44 Table 5.3-19 PVNGS UNIT 2 CAPSULE ASSEMBLY REMOVAL SCHEDULE Azimuthal Removal Base Metal Capsule Locations Time Material Included 1 380 Standby Lower shell CT 2 430 Standby Lower shell CT 3 1370 4-6 EFPY Lower shell PCv 4 1420 Standby Lower shell CT 5 2300 12-15 EFPY Lower shell PCv 6 3100 1-94 EFPY Lower shell PCv Note: Schedule may be odified to coincide with those refueling ou ages or scheduled shutdowns most closely approximatig the withdrawal schedule. | |||
139 -43 | |||
* June 2011 5.3-46 Revision 16 | |||
PVNGS UPDATED FSAR REACTOR VESSEL Table 5.3-19A PVNGS UNIT 3 CAPSULE ASSEMBLY REMOVAL SCHEDULE Azimuthal Removal Base Metal Capsule Locations Time Material Included 1 380 Standby Lower shell CT 2 430 Standby Lower shell CT 3 1420 Standby Lower shell PCv 4 1370 4-6 EFPY Lower shell CT 5 2300 12-15 EFPY Lower shell PCv 6 3100 - EFPY Lower shell PCv Note: Schedule may be modified to *ncide with those refueling outages or scheduled utdowns most closely approximating the withdrawal sched | |||
"".42_-46I 5.3.1.6.7 Irradiation Effects Prediction Basis The design curve used to predict the radiation induced increase in transition temperature is shown in figure 5.3-5. Predicted changes in the transition temperature are used to select the surveillance materials (paragraph 5.3.1.6.1) and to formulate the initial heatup and cooldown limit curves for plant operation. Once actual post-irradiation surveillance data become available, these data will be used to adjust plant operating limit curves. | |||
Figure 5.3-5 was conservatively drawn using the data given in table 5.3-20 including SA533B, Class 1, plate and weld zone material typical of that used in the fabrication of the Palo Verde reactor vessel beltline materials. The curve is applicable for materials with copper contents of 0.10 w/o or June 2011 5.3-47 Revision 16}} | |||
Once actual post-irradiation surveillance data become available, these data will be used to adjust plant operating limit curves.Figure 5.3-5 was conservatively drawn using the data given in table 5.3-20 including SA533B, Class 1, plate and weld zone material typical of that used in the fabrication of the Palo Verde reactor vessel beltline materials. | |||
The curve is applicable for materials with copper contents of 0.10 w/o or June 2011 5.3-47 Revision 16}} | |||
Latest revision as of 19:24, 6 February 2020
| ML11356A086 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/09/2011 |
| From: | Mims D APS, Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-06447-DCM/GAM | |
| Download: ML11356A086 (23) | |
Text
10 CFR 50, Appendix H A W A subsidiaryof Pinnacle West CapitalCorporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Senior Vice President Tel. 623-393-5403 P. 0. Box 52034 Generating Station Nuclear Regulatory and Oversight Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06447-DCM/GAM December 09, 2011 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Request for Approval of Proposed Changes to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Arizona Public Service Company (APS) is requesting approval of proposed changes to the PVNGS Units 1, 2, and 3 reactor pressure vessel surveillance capsule withdrawal schedules in the Updated Final Safety Analysis Report. The proposed changes are submitted pursuant to Title 10 of the Code of FederalRegulations (10 CFR) Part 50, Appendix H,Section III.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation.
The proposed changes to the reactor pressure vessel surveillance capsule withdrawal schedules are consistent with the recommendations specified in American Society for Testing and Materials (ASTM) Standard Practice E 185-82, as referenced by the requirements of 10 CFR Part 50, Appendix H. In addition, the proposed changes are consistent with Commitment No. 17 in Table A4-1 in the PVNGS license renewal application submitted in APS letter no. 102-05937, dated December 11, 2008 (ADAMS Accession No. ML083510627), and Appendix A in the related NRC Safety Evaluation Report, NUREG-1 961 (ADAMS Accession No. ML11095A011).
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde - San Onofre - South Texas
- Wolf Creek
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Request for Approval of Proposed Changes to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Page 2 No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.
Sincerely, fc'e p. c, /,./,,,45 DCM/RAS/GAM/gat
Enclosure:
Proposed Changes to the Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules cc: E. E. Collins Jr. NRC Region IV Regional Administrator L. K. Gibson NRC NRR Project Manager for PVNGS J. R. Hall NRC NRR Senior Project Manager M. A. Brown NRC Senior Resident Inspector for PVNGS
Enclosure Proposed Changes to the Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules
1.0 INTRODUCTION
2.0 REGULATORY EVALUATION
2.1 License Renewal Commitment 3,0 TECHNICAL EVALUATION 3.1 Evaluation Criteria of ASTM Standard Practice E 185-82 3.2 Changes Proposed to the Withdrawal Schedule for PVNGS Units 1, 2, and 3
4.0 CONCLUSION
5,0 REFERENCES ATTACHMENT Updated Final Safety Analysis Report Markups
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules
1.0 INTRODUCTION
Arizona Public Service Company (APS) is requesting approval of proposed changes to the Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 reactor pressure vessel (RPV) surveillance capsule withdrawal schedules. The proposed changes are submitted pursuant to Title 10 of the Code of FederalRegulations (10 CFR) Part 50, Appendix H,Section III.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation, The proposed changes to the RPV surveillance capsule withdrawal schedules are consistent with the recommendations specified in American Society for Testing and Materials (ASTM) Standard Practice E 185-82, as referenced by the requirements of 10 CFR Part 50, Appendix H. In addition, the proposed changes are consistent with Commitment No. 17 in Table A4-1 in the PVNGS license renewal application submitted in APS letter no. 102-05937, dated December 11, 2008 (ADAMS Accession No. ML083510627), as reflected in Appendix A in the related NRC Safety Evaluation Report, NUREG-1961 (ADAMS Accession No. ML11095AO11).
2.0 REGULATORY EVALUATION
Appendix H to 10 CFR Part 50 requires nuclear power plant licensees to implement reactor pressure vessel (RPV) surveillance programs to "monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region... which result from the exposure of these materials to neutron irradiation and the thermal environment."Section III.B.1 of Appendix H states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the American Society for Testing and Materials (ASTM) E 185, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels,"
that is current on the issue date of the American Society of Mechanical Engineers (ASME) Code to which the RPV was purchased. The rule permits the use of later editions of ASTM E 185, but including only those editions through 1982 (i.e., ASTM E 185-82). The current PVNGS Units 1,2, and 3, RPV surveillance programs and the withdrawal schedules meet the requirements of ASTM E 185-82.
Appendix H to 10 CFR Part 50, Section III.B.3, requires prior NRC approval of all RPV surveillance capsule withdrawal schedule changes. Further, NRC Administrative Letter 97-04, "NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules," dated September 30, 1997, specifies that changes to RPV surveillance capsule withdrawal schedules that do not conform to ASTM E 185 require approval by the license amendment process, whereas changes that conform to the ASTM standard require only staff verification of such conformance. The proposed changes to the PVNGS Units 1, 2, and 3 RPV surveillance capsule withdrawal schedules conform to ASTM E 185-82, and, therefore, a license amendment is not required for these proposed changes.
1
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules 2.1 License Renewal Commitment The PVNGS Units 1,2, and 3 license renewal application (Ref. 5.1) contained the following item in Commitment No. 17 in Table A4-1, as reflected in Appendix A of the related NRC Safety Evaluation Report, NUREG-1961, April 2011 (Ref. 5.2):
Priorto the period of extended operation:
o The [reactorpressure vessel surveillance program]schedule will be revised to withdraw the next capsule at the equivalent clad-base metal exposure of approximately 54 effective full power years (EFPY)expected for the 60-year period of operation, and to withdraw remaining standby capsules at equivalent clad-base metal exposures not exceeding the 72 EFPY expected for a possible 80-year second period of extended operation. This withdrawalschedule is in accordance with NUREG-1801
[GenericAging Lessons Learned (GALL) Report],Section XI.M31, item 6, and with the ASTM E 185-82 criterion which states that capsules may be removed when the capsule neutron fluence is between one and two times the limiting fluence calculated for the vessel at the end of expected life.
This schedule change must be approved by the NRC, as required by 10 CFR 50 Appendix H.
This request to revise the PVNGS Units 1, 2, and 3 RPV surveillance capsule withdrawal schedules will address this commitment.
3.0 TECHNICAL EVALUATION
3.1 Evaluation Criteria of ASTM Standard Practice E 185-82 Table 1 of ASTM Standard Practice E 185-82 requires that either a minimum of three, four, or five surveillance capsules be removed from the vessels, as based on the limiting amount of reference temperature for nil-ductility transition shift (limiting RTNDT) that is projected to occur at the clad-vessel interface location of the RPV at the end-of-licensed plant life (EOL). For plants with projected RTNDT shifts (i.e., ARTNDT) less than 100 OF (56 0C), three capsules are required to be removed from the RPV.
For the renewed operating license operating terms, the PVNGS RPVs have limiting ARTNDT values of less than 100 OF. At 60 years (54 EFPY), the maximum shift in reference temperature for pressurized thermal shock (ARTPTS) is 57.7 OF for Unit 1, the maximum ARTPTS is 54 OF for Unit 2, and the maximum ARTPTS is 40.7 °F for Unit 3 (Ref. 5.1, License Renewal Application Tables 4.2-6, 7, and 8). In this context, ARTPTS is equivalent to ARTNDT. Therefore APS is required, as a minimum, to remove three capsules from each reactor during the current operating period.
2
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Table 1 of ASTM Standard Practice E 185-82 also provides specific criteria for removal of surveillance capsules. The criteria are that the surveillance capsules be removed after a certain amount of power operation has elapsed or at various times when the RPV shell is projected to achieve certain levels of neutron fluence. The intent of the Standard Practice is to achieve a set of testing data over a range of neutron fluences for the RPV that bounds the current life of the plant. Of key importance are the removal criteria for the second to last and final capsules required for capsule withdrawal. For the second-to-last required capsule in a withdrawal schedule, the ASTM standard requires that the capsules be pulled at either 13 effective full power years (EFPYs) or at the time when the capsule is equivalent to the limiting fluence projected for the clad-based metal interface of the RPV at EOL, whichever time comes first. For the final capsule that is required for removal, ASTM E 185-82 requires that the capsule be removed at a time when the neutron fluence projected for the capsule is between the limiting fluence value projected for the RPV at the EOL and two times that value.
3.2 Changes Proposed to the Withdrawal Schedule for PVNGS Units 1, 2, and 3 The proposed changes to the PVNGS Units 1, 2, and 3 RPV surveillance capsule withdrawal schedule are shown in the attached markups of UFSAR Tables 5.3-18, 5.3-19, 5.3-19A, 5.3-13, 5.3-14, and 5.3-15.
For the final capsule that is required for removal, ASTM E 185-82 requires that the capsule be removed at a time when the neutron fluence projected for the capsule is between the limiting fluence value projected for the RPV at the EOL and two times that value. The limiting fluence values projected for the RPVs at the EOL for the final capsule required for removal from each unit, Capsule 6 (3100), are shown in Tables 3.2-1, 3.2-2, and 3.2-3 below.
3
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Table 3.2-1 PVNGS Unit I Reactor Pressure Vessel Surveillance Capsule Withdrawalma)
Capsule No.
CapsuleWihrwlIM Location Location_____ Lead Factor EFPY(b)
Withdrawal Fune(lm Fluence (n 3 1370 1.34 4.57 3.65E18 1 380 1.33 9.76 6.28E18 5 2300 1.35 13.83 8.76E18 6 3100 1.35 40OC) 2.56E19(O) 2 430 1.35 Standby 4 1420 1.35 Standby (a) Based on Table 7-1 in WCAP-16374-NP, "Analysis of Capsule 2300 from the Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program," February 2005 (Ref. 5.3).
(b) Effective full power years (EFPY) from plant startup.
(c) Equivalent to capsule accumulating a fluence equal to 54 EFPY.
(d) Calculated at reactor vessel clad-to-metal interface. (Source: Table 1-2 of WCAP-1 6835-NP [Ref.
5.6]. This value was calculated for the current maximum licensed power of 3990 MWt, whereas the 2.51 E19 value shown in Table 6-2 in WCAP-1 6374 [Ref. 5.3] and in Section 4.2.1 of the PVNGS License Renewal Application [Ref. 5.1] was calculated for the previous maximum licensed power of 3876 MWt prior to implementation of the Unit 1 power uprate license amendment.)
Table 3.2-2 PVNGS Unit 2 Reactor Pressure Vessel Surveillance Capsule Withdrawal(a)
(a) Based on Table 7-1 in WCAP-16524-NP, "Analysis of Capsule 2300 from the Arizona Public Service Company Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program," February 2006 (Ref. 5.4).
(b) Effective full power years (EFPY) from plant startup.
(c) Equivalent to capsule accumulating a fluence equal to 54 EFPY.
(d) Calculated at reactor vessel clad-to-metal interface. (Source: Table 1-3 of WCAP-16835-NP [Ref.
5.6]. This value was calculated for the current maximum licensed power of 3990 MWt, and is the same as shown in Table 6-2 in WCAP-1 6524 [Ref. 5.4] and in Section 4.2.1 of the PVNGS License Renewal Application [Ref. 5.1], reflecting the Unit 2 power uprate license amendment.)
4
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Table 3.2-3 Pressure Vessel Surveillance PVNGS Unit 3 ReactorCapsule Capsule Withdrawal(a)
WithdrawalM2 Capsule__No.
Capsule No. Location ca LaFctrEFPY(b)
Lead Factor Fluence (n/cm2 )
4 1370 1.28 4.44 3.48E18 5 2300 1.31 13.75 9.07E18 6 3100 1.31 42(c) 2.99E19(d) 2 430 1.30 Standby 3 1420 1.28 Standby 1 380 1.28 Standby (a) Based on Table 7-1 in WCAP-16449-NP, "Analysis of Capsule 2300 from the Arizona Public Service Company Palo Verde Unit 3 Reactor Vessel Radiation Surveillance Program," August 2005 (Ref. 5.5).
(b) Effective full power years (EFPY) from plant startup.
(c) Equivalent to capsule accumulating a fluence equal to 54 EFPY.
(d) Calculated at reactor vessel clad-to-metal interface. (Source: Table 1-4 of WCAP-16835-NP [Ref.
5.6]. This value was calculated for the current maximum licensed power of 3990 MWt, whereas the 2.93E19 value shown in Table 6-2 in WCAP-16449 [Ref. 5.5] and in Section 4.2.1 of the PVNGS License Renewal Application [Ref. 5.1] was calculated for the previous maximum licensed power of 3876 MWt prior to implementation of the Unit 3 power uprate license amendment.)
4.0 CONCLUSION
The proposed changes to the PVNGS RPV surveillance capsule withdrawal schedules will continue to meet the RPV surveillance capsule withdrawal schedule criteria in ASTM E 185-82 for the renewed licensed periods of PVNGS Units 1, 2, and 3.
5.0 REFERENCES
5.1 Letter no. 102-05937, from APS to the NRC, "License Renewal Application,"
December 11, 2008 (ADAMS Accession No. ML083510627) 5.2 NUREG-1961 "Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Units 1,2 and 3." (ADAMS Accession No. ML11095A011) 5.3 Letter no. 102-05242 from APS to the NRC, "Palo Verde Nuclear Generating Station Unit 1 Reactor Vessel Material Surveillance Capsule at 230', April 5, 2005 (transmittal of WCAP-16374-NP, "Analysis of Capsule 230' from Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program," February 2005) (ADAMS Accession No. not publicly available).
5
Proposed Changes to the PVNGS Units 1, 2, and 3 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules 5.4 Letter no. 102-05457 from APS to the NRC, "Palo Verde Nuclear Generating Station Unit 2 Reactor Vessel Material Surveillance Capsule at 2300,' April 4, 2006 (transmittal of WCAP-16524-NP, "Analysis of Capsule 230' from Arizona Public Service Company Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program," February 2006) (ADAMS Accession No. ML061040586).
5.5 Letter no. 102-05348 from APS to the NRC, "Palo Verde Nuclear Generating Station Unit 3 Analysis of Reactor Vessel Material Surveillance Capsule at 2300,"
September 26, 2005 (transmittal of WCAP-16449-NP, "Analysis of Capsule 2300 from Arizona Public Service Company Palo Verde Unit 3 Reactor Vessel Radiation Surveillance Program," August 2005) (ADAMS Accession No. ML053390139).
5.6 Westinghouse Report WCAP-16835-NP, "Palo Verde Nuclear Generating Station Units 1, 2, and 3; Basis for RCS Pressure and Temperature Limits Report," June 2008 (ADAMS Accession No. ML090641016). This report was submitted with letter no. 102-05960 from APS to the NRC, "Request for Technical Specification Amendment and Exemption from 10 CFR 50, Appendix G, to Relocate the Reactor Coolant System Pressure and Temperature Limits and the Low Temperature Overpressure Protection Enable Temperatures," February 19, 2009 (ADAMS Accession No. ML090641014).
6
ATTACHMENT Updated Final Safety Analysis Report Markups Page No.
5.3-27 (no changes - for information only) 5.3-28 (no changes - for information only) 5.3-29 (no changes - for information only) 5.3-30 5.3-31 (no changes - for information only) 5.3-32 (no changes - for information only) 5.3-33 5.3-34 (no changes - for information only) 5.3-35 (no changes - for information only) 5.3-36 (no changes - for information only) 5.3-37 5.3-46 5.3-47
No changes to this page -
for information only Table 5.3-13 C- PVNGS UNIT 1 SURVEILLANCE PROGRAM (Sheet 1 of 4)
(D r')
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY") Factor Material Origins No. Type Orientation 1 380 8-10 1.0<LF<I.5 Base metal 15 C, Trans.
PC, lower shell plate 9 PC, Trans.
M-4311-I1*' 9 PCv Long.
3 Tension Trans.
9 Cv Long.
Weld metalb 3 Tension Trans. 1-3 M-4311-2/M-4311-3('1 15 C, Trans.
weld wires tl)
(-n B-4 heat/lot 90071 9 PC, Trans.
Flux Linde 0091/1054 HAZ metal 12 C, Trans.
Lower shell plate M-4311-1 SRM HSST plate 01d) 9 Cý Long.
0
- a. See table 5.3-1 for chemistry of plate code No. M-4311-1 (lower shell plates).
C')
- b. See table 5.3-2 for chemistry of weld code No. 101-142 A-C (lower shell long seams). Wl (D c. Surveillance weld metal between plates m-4311-2 and M-4311-3 (long seams).
- d. See ORNL-4315, dated February 1968 for chemistry of SRM (HSST-01 Ppate).
H" e. See table 5.3-1 for chemistry of plate code No. M-6701-2 (intermediate shell plate).
0
- f. Effective full power years.
o-
No changes to this page -
for information only Table 5.3-13 C- PVNGS UNIT 1 SURVEILLANCE PROGRAM (Sheet 2 of 4)
(D C) Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY"' Factor Material Origins No. Type Orientation 2 430 Standby 1.0<LF<I.5 Base metal 15 C, Trans.
CT Inter. shell plate 10 1/2t CT Trans. z M-6701-2 e( 3 Tension Trans.
U)
Weld metal(b) 3 Tension Trans.
M-4311-2/M-4311-3(o 15 C, Trans.
Weld wires B-4 heat lot 90071 10 1/2t CT Trans. H Flux Linde 0091/1054 I-zj Cn HAZ metal 12 C, Trans. U)
Lower shell plate M-4311-1("
co SRM HSST plate 01d 9 C, Long.
3 1370 4-5 1.0<LF<l.5 Base metal 15 C, Trans.
PC, Inter shell plate 9 PC, Trans.
M-6701-2"'e 9 PC, Long. C) 3 Tension Trans.
9 C, Long. 0 Weld metalb 3 Tension Trans.
M-4311-2/M-4311-3(ý) 15 C, Trans.
Weld wire W)
U/)
B-4 heat/lot 90071 9 PC, Trans. no Flux Linde 0091/1054 t-i (D
HAZ metal 12 C, Trans.
Lower shell plate M-4311-1 0
SRM HSST plate 01d 9 C, Long.
I-.
No changes to this page -
for information only Table 5.3-13 PVNGS UNIT 1 SURVEILLANCE PROGRAM (Sheet 3 of 4)
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY'f Factor Material Origins No. Type Orientation 4 1420 Standby 1.0<LF<1.5 Base metal 15 C0 Trans.
CT Lower shell plate 10 1/2t CT Trans.
M-4311-1"a' 3 Tension Trans. G')
C/)
Weld metallbI 3 Tension Trans.
0 M-4311-2/M-4311-3( ) 15 C0 Trans.
Weld wires B-4 heat lot 90071 10 1/2t CT Trans. C:
Flux Linde 0091/1054 3 Tension Trans.
HAZ metal 12 C0 Trans.
Lower shell plate M-4311-1"'
SRM HSST plate 01dl 9 C, Long.
5 2300 12-15 1.0<LF<I.5 Base metal 15 C0 Trans.
PC, Inter shell plate 9 PC, Trans.
M-6701-2") 9 PC, Long.
3 Tension Trans.
9 C0 Long. 0 Weld metallb 3 Tension Trans.
0 M-4311-2/M-4311-3( ) 15 C0 Trans.
Weld wire B-4 heat/lot 90071 9 PC0 Trans. t7' Flux Linde 0091/1054 HAZ metal 12 C0 Trans.
Lower shell plate M-4311-1") 12 C0 Trans.
SRM HSST plate 01(d) 9 C0 Long.
Table 5.3-13 PVNGS UNIT 1 SURVEILLANCE PROGRAM (Sheet 4 of 4)
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY") Factor Material Origins No. Type Orientation 6 3100 I 1.0<LF<I.5 Base metal 15 C, Trans.
CD PC, 4 Lower shell plate 9 PCv Trans.
M-4311-1'a 9 PC, Long.
F044 3 Tension Trans. C')
WI- 9 C, Long.
Weld metal bI 3 Tension Trans.
M-4311-2/M-4311-3(') 15 Cý Trans.
Weld wires B-4 heat/lot 90071 9 PCý Trans.
Flux Linde 0091/1054 C/)
(C) HAZ metal 12 C, Trans.
Lower shell plate M-4311-1")
SRM HSST plate 01d) 9 C, Long.
0 1l (D
H-00'
No changes to this page -
r-I for information only CD Table 5.3-14 N) PVNGS UNIT 2 SURVEILLANCE PROGRAM (Sheet 1 of 3)
C)
Capsule Assembly Withdrawal Specimens No. and Azimuthal Schedule Lead Surveillance Type Location EFPY") Factor Material Origins No. Type Orientation 1 380 Standby 1.0<LF<I.5 Base metal 15 C, Trans CT Lower shell plate 10 1/2t CT Trans F-773-1. 3 Tension Trans Weld metalc'c 15 C, Trans F-773-2/F-773-3(ý) 10 1/2t CT Trans F-3 Weld wires 3 Tension Trans B-4 heat/lot 3P7317 Flux Linde 124/0662 Cl)
Cn HAZ metal 12 C, Trans Lower shell plate Cd Id F_ 773-IbI SRM HSST plate 01"e' 9 C, Long.
2 430 Standby 1.0<LF<l.5 Base metal 15 Cv Trans CT Lower shell plate 10 1/2t CT Trans F- 7 7 3-I'b) 3 Tension Trans Weld metal"c) 15 Cv Trans F-773-2/F-773-3(d) 10 1/2t CT Trans Weld wire 3 Tension Trans B-4 heat/lot 3P7317 Flux Linde 124/0662 0 HAZ metal 12 C, Trans Lower shell plate (D F-773-11b)
Cl)
SRM HSST plate 01 9 C, Trans t7-1 01(e) 0
- a. Effective full power years.
- b. See tables 5.3-3 for chemistry of plates.
- c. See tables 5.3-4 for chemistry of weld code No. 101-142 A-C (lower shell long seams).
- d. Surveillance weld metal formed between designated plates
- e. See ORNL-4315 dated February 1968 for chemistry of SRM (HHST-01 plate).
No changes to this page -
for information only C-4 (D Table 5.3-14 PVNGS UNIT 2 SURVEILLANCE PROGRAM (Sheet 2 of 3)
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY'*' Factor Material Origins No. Type Orientation 3 1370 4-6 1.0<LF<I.5 Base metal 15 Cv Trans PCý Lower shell plate 9 PCý Trans N) F-773-1IbI 9 PC, Long.
3 Tension Trans 0 9 CQ Long.
Weld metal'c' 15 C, Trans F-773-2/F-773-3(ý) 9 PC, Trans Weld wires 3 Tension Trans B-4 heat/lot 3P7317 cl)
Flux Linde 124/0662 HAZ metal 12 C, Trans Lower shell plate F-773-I'0 '
SRM HSST plate 01'* 9 C, Long.
4 142' Standby 1.0<LF<I.5 Base metal 15 C, Trans CT Lower shell plate 10 1/2T CT Trans F-773-1Ib 3 Tension Trans Weld metal"c) 15 C, Trans F-773-2/F-773-3'd)
Weld wire 10 1/2t CT Trans 0 B-4 heat/lot 3P7317 Flux Linde 124/0662 3 Tension Trans HAZ metal 12 C, Trans Cf)
(D Lower shell plate 0 F-773- _IbI 02 SRM HSST plate 01"' 9 C Long.
O
C-4 Table 5.3-14 (D PVNGS UNIT 2 SURVEILLANCE PROGRAM (Sheet 3 of 3)
N)
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY W Factor Material Origins No. Type Orientation 5 2300 12-15 1.0<LF<I.5 Base metal 15 C0 Trans PC, Lower shell plate 9 PC, Trans 0
F-773-1' ' 9 PC0 Long. z 3 Tension Trans Cl) 9 C, Long.
Weld metal"'l 15 C0 Trans '-0 0
F-773-2/F-773-3' ' 9 PC, Trans Weld wires 3 Tension Trans
'-3 B-4 heat/lot 3P7317 Flux Linde 124/0662 4::,
CA ITj HAZ material 12 Cv Trans Cl)
Lower shell plate F-773-1I'b SRM HSST plate 01 9 C, Long.
6 310' 1.0<LF<I.5 Base metal 15 C0 Trans PC, Lower shell plate 9 PC, Trans F-773-1I~b 9 PC, Long.
3 Tension Trans 9 C0 Long. '-3 Weld metal"'* 15 C, Trans 0 0
F-773-2/F-773-3' ' Tension Trans Weld wire 9 PC0 Trans B-4 heat/lot 3P7317 Flux Linde 124/0662 (D HAZ metal 12 C0 Trans Lower shell plate F-773-1 0 SRM HSST plate 01"' 9 C0 Long.
for changes to only No information this page -
Table 5.3-15 CA PVNGS UNIT 3 SURVEILLANCE PROGRAM (Sheet 1 of 4)
(D N) Capsule Specimens I-,
Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPYle, Factor Material Origins No. Type Orientation 1 380 Standby 1.0<LF<I.5 Base metal 15 Cv Trans.
CT Lower shell plate 10 1/2t CT Trans.
F-6411-2 a) 3 Tension Trans. 0 U)
Weld metal1b, 15 C, Trans.
F-6411-1 to 3(C) 10 1/2t CT Trans.
Weld wires 3 Tension Trans.
B-4 heat lot 4P7869 H Flux Linde 124/0281
'-Il HAZ metal 12 Cv Trans. Cl)
Lower shell plate F-6411-2"'
SRM HSST plate 01l 9 Cv Long.
2 430 Standby 1.0<LF<I.5 Base metal 15 Cv Trans.
CT Lower shell plate 10 1/2t CT Trans.
F-6411-2"a 3 Tension Trans.
0
- a. See table 5.3-5 for chemistry of plates.
- b. See table 5.3-6 for chemistry of weld code No. 101-142 A-C (lower shell long seams). CO W)
C. Surveillance weld metal formed between designated plates.
(D
- d. See ORNL-4315 dated February 1968 for chemistry of SRM (HSST-01 plate).
O e. Effective full power years.
- o3
No changes to this page -
for information only Table 5.3-15 PVNGS UNIT 3 SURVEILLANCE PROGRAM (Sheet 2 of 4)
(D C) Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY"' Factor Material Origins No. Type Orientation 2 Weld metal bI 15 C, Trans.
CT F-6411-1 to 3"C' 10 1/2t CT Trans.
(Cont.) Weld wires 3 Tension Trans. C)
B-4 heat lot 4P7869 U)
I-Flux Linde 124/0281 '-0 Trans. U HAZ metal 4 12 C, al Lower shell plate F-6411-2 H U
SRM HSST plate 01 l 9 Cv Long.
'-Il CI)
C-n 3 1420 Standby 1.0<LF<I.5 Base metal 15 Cv Trans.
PC, Lower shell plate 9 PC, Trans.
F-6411-2"' 9 PC, Long.
3 Tension Trans.
9 C, Long.
Weld metalc 15 C, Trans.
F-6411-1 to 3(C' 9 PC, Trans.
Weld wire 3 Tension Trans.
0 B-4 heat/lot 4P7869 Flux Linde 124/0281 HAZ metal 12 C, Trans. Cn Lower shell plate F-6411-2c tzl (D
SRM HSST plate 01' 9 Cv Long.
H-0 0H
No changes to this page -
for information only Table 5.3-15 PVNGS UNIT 3 SURVEILLANCE PROGRAM (Sheet 3 of 4)
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY(e) Factor Material Origins No. Type Orientation 4 1370 4-6 1.0<LF<l.5 Base metal 15 C0 Trans.
CT Lower shell plate F-6411-2"'e 10 1/2t CT Trans.
3 Tension Trans. Cl)
Weld metal(b) 15 C, Trans.
F-6411-1 to 3(0)
Weld wire 10 1/2t CT Trans. Lii B-4 heat lot 4P7869 tJ2 Flux Linde 124/0281 3 Tension Trans.
HAZ metal 12 C0 Trans.
Lower shell plate F-6411-2a SRM HSST plate 01(d) 9 C, Long.
5 2300 12-15 1.0<LF<1.5 Base metal 15 C0 Trans.
PC, Lower shell plate 9 PC, Trans.
F-6411-2"' 9 PC, Long.
3 Tension Trans. F-3 9 C0 Long.
Cf)
Weld metal 0 bI 15 C0 Trans.
F-6411-1 to 3C) 9 PC, Trans.
Weld wire 3 Tension Trans.
Cl)
B-4 heat/lot 4P7869 NI Flux Linde 124/0281 HAZ material 12 C0 Trans.
Lower shell plate F-6411-2' SRM HSST plate 01(dl 9 C0 Long.
C-4 Table 5.3-15 PVNGS UNIT 3 SURVEILLANCE PROGRAM (Sheet 4 of 4)
F-.
I-,
Capsule Specimens Assembly Withdrawal No. and Azimuthal Schedule Lead Surveillance Type Location EFPY"' Factor Material Origins No. Type Orientation 6 3100 1_P-2_4 1.0<LF<I.5 Base metal 15 C, Trans.
PC, Lower shell plate 9 PC, Trans.
F-6411-2"' 9 PC, Long.
3 Tension Trans.
9 C, Long.
C" Weld metalb 15 C, Trans.
F-6411-1 to 3(C) 9 Tension Trans.
Weld wire 3 PC, Trans.
B-4 heat/lot 4P7869 I-Cl Flux Linde 124/0281 HAZ metal 12 C, Trans.
Lower shell plate F-6411-2"'
Cn SRM HSST plate 01(dl 9 Cý Long.
0 o- t7-'
PVNGS UPDATED FSAR REACTOR VESSEL Table 5.3-18 PVNGS UNIT 1 CAPSULE ASSEMBLY REMOVAL SCHEDULE Azimuthal Removal Base Metal Capsule Locations Time Material Included 1 380 8-10 EFPY Lower shell PCv 2 430 Standby Intermediate shell CT 3 1370 4-5 EFPY Intermediate shell PCv 4 1420 Standby Lower shell CT 5 2300 12-15 EFPY Intermediate shell PCv 6 3100 I- 4 EFPY Lower shell PCv Note: Schedule may be odified to coincide with those refueling o ages or scheduled shutdowns most closely approximat g the withdrawal schedule.
140-44 Table 5.3-19 PVNGS UNIT 2 CAPSULE ASSEMBLY REMOVAL SCHEDULE Azimuthal Removal Base Metal Capsule Locations Time Material Included 1 380 Standby Lower shell CT 2 430 Standby Lower shell CT 3 1370 4-6 EFPY Lower shell PCv 4 1420 Standby Lower shell CT 5 2300 12-15 EFPY Lower shell PCv 6 3100 1-94 EFPY Lower shell PCv Note: Schedule may be odified to coincide with those refueling ou ages or scheduled shutdowns most closely approximatig the withdrawal schedule.
139 -43
- June 2011 5.3-46 Revision 16
PVNGS UPDATED FSAR REACTOR VESSEL Table 5.3-19A PVNGS UNIT 3 CAPSULE ASSEMBLY REMOVAL SCHEDULE Azimuthal Removal Base Metal Capsule Locations Time Material Included 1 380 Standby Lower shell CT 2 430 Standby Lower shell CT 3 1420 Standby Lower shell PCv 4 1370 4-6 EFPY Lower shell CT 5 2300 12-15 EFPY Lower shell PCv 6 3100 - EFPY Lower shell PCv Note: Schedule may be modified to *ncide with those refueling outages or scheduled utdowns most closely approximating the withdrawal sched
"".42_-46I 5.3.1.6.7 Irradiation Effects Prediction Basis The design curve used to predict the radiation induced increase in transition temperature is shown in figure 5.3-5. Predicted changes in the transition temperature are used to select the surveillance materials (paragraph 5.3.1.6.1) and to formulate the initial heatup and cooldown limit curves for plant operation. Once actual post-irradiation surveillance data become available, these data will be used to adjust plant operating limit curves.
Figure 5.3-5 was conservatively drawn using the data given in table 5.3-20 including SA533B, Class 1, plate and weld zone material typical of that used in the fabrication of the Palo Verde reactor vessel beltline materials. The curve is applicable for materials with copper contents of 0.10 w/o or June 2011 5.3-47 Revision 16