ML110250147: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(3 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 01/24/2011
| issue date = 01/24/2011
| title = Submittal of Relief Request 14R-52 Concerning Nozzle-to-Vessel Weld and Inner Examinations (Use of Code Case N-702)
| title = Submittal of Relief Request 14R-52 Concerning Nozzle-to-Vessel Weld and Inner Examinations (Use of Code Case N-702)
| author name = Helker D P
| author name = Helker D
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:Exel n Nuclear 10 CFR 50.55a January 24, 2011 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos.DPR-44 and DPR-56 NRC Docket Nos.50-277 and 50-278  
{{#Wiki_filter:I    ii I  I Exel Exelnn I Ion t
Nuclear N uci ear I  kU UIUlFk 8A      8                                                                          10 1 0 CFR C FR 50.55a
: 50. 55a January 24, January           24, 2011 2011 U.S. Nuclear U.S.          Nuclear Regulatory Regulatory Commission Commission Attn: Document Attn:        Document Control Control Desk Desk Washington, DC Washington,             DC 20555-0001 20555-0001 Peach Bottom Peach   Bottom Atomic Atomic Power Power Station, Station, Units Units 2 and 3 Renewed Facility Renewed            Operating License Facility Operating  License Nos.
Nos. DPR-44 DPR-44 and DPR-56 NRC Docket NRC    Docket Nos.
Nos. 50-277 and 50-278


==Subject:==
==Subject:==
Submittal of Relief Request 14R-52 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)In accordance with 10 CFR 50.55a,"Codes and standards," paragraph (a)(3)(i), Exelon Generation Company, LLC (Exelon), is requesting relief from the American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel (B&PV)Code, Section XI,"Rules for Inservice Inspection of Nuclear Power Plant Components.'1 Relief Request 14R-52 proposes an alternative to the requirements contained in Table IWB-2500-1 concerning nozzle-to-vessel weld and nozzle inner radii examination requirements.
 
This relief applies to the fourth 10-year Inservice Inspection (lSI)interval.The fourth interval for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 began on November 5,2008, and will conclude November 4, 2018.The fourth 10-year lSI interval complies with the ASME B&PV Code, Section XI, 2001 Edition through 2003 Addenda.We request your review and approval by January 24, 2012.No regulatory commitments are contained in this letter.Should you have any questions concerning this letter, please contact Tom Loomis at (610)5510.Sincerely, David P.Helker Manager-Licensing&Regulatory Affairs Exelon Generation Company, LLC  
==Subject:==
Submittal of Submittal    Relief Request of Relief Request 14R-52 Concerning Nozzle-to-Vessel Nozzle-to-Vessel Weld and Inner and  Inner Radii Radii Examinations Examinations (Use of Code Case N-702)
In accordance In       accordance with 10    10 CFR 50.55a, "Codes Codes and standards,"
standards, paragraph (a)(3)(i), Exelon Generation Company, LLC (Exelon), is requesting relief from the American Society of Mechanical Engineers Mechanical            Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl,        XI, "Rules Rules for Inservice Inspection of Nuclear Power Plant Components.'1 Inservice                                                Components. Relief Request 14R-52  l4R-52 proposes an alternative to the requirements contained in Table IWB-2500-1 concerning nozzle-to-vessel    nozzle-to-vessel weld and nozzle inner radii examination requirements. requirements.
This relief applies to the fourth 10-year Inservice lnservice Inspection (lSI)
(ISI) interval. The fourth interval for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 began on November 5,                        5,2008, 2008, and will conclude November 4, 2018. The fourth 10-year lSl              lSI interval complies with the ASME B&PV Code, Section XI,        Xl, 2001 Edition through 2003 Addenda.
We request your review and approval by January 24, 2012.
No regulatory commitmentscommitments are contained in this letter.
Should you have any questions concerning this letter, please contact Tom Loomis at (610)               (610) 765-765-5510.
Sincerely, David P. Helker Manager - Licensing & Regulatory Affairs Exelon Generation Company, LLC


==Attachment:==
==Attachment:==
 
Relief Request l4R-52        14R-52 cc:             USNRC Region I, Regional Administrato Administratorr USNRC Senior Resident Inspector, Inspector, PBAPS PBAPS USNRC USNRC Project Manager, Manager, PBAPS PBAPS R. R. Janati, Janati, Bureau Bureau of Radiation Protection Protection S. T. Gray, State of Maryland Maryland
Relief Request 14R-52 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPSR.R.Janati, Bureau of Radiation Protection S.T.Gray, State of Maryland  


ATTACHMENT Relief Request I4R-52
ATTACHMENT Relief Request I4R-52


Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 1 of 12)  
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
: 1. ASME CODE COMPONENTS AFFECTED Code Class: 1  
(Page 1 of 12)
: 1. ASME CODE COMPONENTS AFFECTED Code Class:               1 Component Numbers:        Reactor Vessel Nozzles: N2, N3, N5, N6, N8 (See Enclosure 1 for complete list of nozzle identifications)
Examination Category:      B-D (Inspection Program B)
Item Number:              B3.90 and B3.100


Component Numbers: Reactor Vessel Nozzles: N2, N3, N5, N6, N8 (See Enclosure 1 for complete list of nozzle identifications)
== Description:==
Examination Category: B-D (Inspection Program B)  
Alternative to ASME Section XI, Table IWB-2500-1
: 2. APPLICABLE CODE EDITION AND ADDENDA The fourth 10-year Inservice Inspection (ISI) program at Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, 2001 Edition through the 2003 Addenda. Additionally, for ultrasonic examinations, ASME Section XI, Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems, of the 2001 Edition is implemented, as required and modified by 10 CFR 50.55a(b)(2)(xv).
: 3. APPLICABLE CODE REQUIREMENTS The applicable requirements are contained in Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels - Inspection Program B.
Class 1 nozzle-to-vessel weld and nozzle inner radii examination requirements are delineated in Item Number B3.90, Nozzle-to-Vessel Welds, and B3.100, Nozzle Inside Radius Section. The required method of examination is volumetric. All nozzles with full penetration welds to the vessel shell (or head) and integrally cast nozzles are examined each interval.
All of the nozzle assemblies identified in Enclosure 1 are full penetration welds.
: 4. REASON FOR REQUEST Enclosure 1 provides a complete listing of the applicable Reactor Pressure Vessel (RPV) nozzles for PBAPS, Units 2 and 3.
The proposed alternative provides an acceptable level of quality and safety, and the reduction in scope could provide a dose savings of as much as 26 Person-Rem for Unit 2 and 27 Person-Rem for Unit 3 over the remainder of the interval.


Item Number: B3.90 and B3.100
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
(Page 2 of 12)
: 5. PROPOSED ALTERNATIVE AND BASIS FOR USE In accordance with 10 CFR 50.55a(a)(3)(i), relief is requested from performing the required examinations on 100 percent of the nozzle assemblies identified in Tables 5-1 and 5-2 below (see Enclosure 1 for the list of RPV nozzles applicable to this relief request). As an alternative, for all welds and inner radii identified in Tables 5-1 and 5-2, Exelon Generation Company, LLC (Exelon) proposes to examine a minimum of 25 percent of the PBAPS, Units 2 and 3 nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with Code Case N-702 (Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds Section XI, Division 1). For the nozzle assemblies identified in Enclosure 1, this would mean 25 percent from each of the groups identified below:
Table 5-1 PBAPS, Unit 2 Summary Group 1,2            Total    Minimum Number Number        to be Examined Recirculation Inlet        10              3 (N2)
Main Steam                4              1 (N3)
Core Spray                2              1 (N5)
Nozzles On Top              2              1 Head (N6)
Jet Pump                2              1 Instrument (N8)
Notes to Table 5-1:
1 The nozzle-to-vessel weld and inner radius examinations are performed together.
2 The N6 is the only Unit 2 nozzle that has been inspected to date in the fourth ISI interval.


==
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
Description:==
(Page 3 of 12)
Alternative to ASME Section XI, Table IWB-2500-1
Table 5-2 PBAPS, Unit 3 Summary Group 1,2           Total     Minimum Number Number       to be Examined Recirculation Inlet       10                3 (N2)
: 2. APPLICABLE CODE EDITION AND ADDENDA The fourth 10-year Inservice Inspection (ISI) program at Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, 2001 Edition through the 2003 Addenda. Additionally, for ultrasonic examinations, ASME Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the 2001 Edition is implemented, as required and modified by 10 CFR 50.55a(b)(2)(xv).
Main Steam             4                1 (N3)
: 3. APPLICABLE CODE REQUIREMENTS The applicable requirements are contained in Table IWB-2500-1, "Examination Category B-D, Full Penetration Welded Nozzles in Vessels - Inspection Program B."
Core Spray             2                1 (N5)
Class 1 nozzle-to-vessel weld and nozzle inner radii examination requirements are delineated in Item Number B3.90, "Nozzle-to-Vessel Welds," and B3.100, "Nozzle Inside Radius Section."  The required method of examination is volumetric. All nozzles with full penetration welds to the vessel shell (or head) and integrally cast nozzles are examined each interval.
Nozzles On Top           2                1 Head (N6 )
 
Jet Pump              2               1 Instrument (N8)
All of the nozzle assemblies identified in Enclosure 1 are full penetration welds.
Notes to Table 5-2:
: 4. REASON FOR REQUEST Enclosure 1 provides a complete listing of the applicable Reactor Pressure Vessel (RPV) nozzles for PBAPS, Units 2 and 3.
 
The proposed alternative provides an acceptable level of quality and safety, and the reduction in scope could provide a dose savings of as much as 26 Person-Rem for
 
Unit 2 and 27 Person-Rem for Unit 3 over the remainder of the interval.
 
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 2 of 12)  
: 5. PROPOSED ALTERNATIVE AND BASIS FOR USE In accordance with 10 CFR 50.55a(a)(3)(i), relief is requested from performing the required examinations on 100 percent of the nozzle assemblies identified in Tables 5-1 and 5-2 below (see Enclosure 1 for the list of RPV nozzles applicable to this relief request). As an alternative, for all welds and inner radii identified in Tables 5-1
 
and 5-2, Exelon Generation Company, LLC (Exelon) proposes to examine a minimum of 25 percent of the PBAPS, Units 2 and 3 nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with Code Case N-702 ("Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds Section XI, Division 1"). For the nozzle assemblies identified in Enclosure 1, this would mean 25 percent from each of the groups identified below:
 
Table 5-1 PBAPS, Unit 2 Summary Group 1,2 Total Number Minimum Number to be Examined Recirculation Inlet (N2) 10 3 Main Steam (N3) 4 1 Core Spray (N5) 2 1 Nozzles On Top Head (N6) 2 1 Jet Pump Instrument (N8) 2  1  Notes to Table 5-1:
1 The nozzle-to-vessel weld and inner radius examinations are performed together.
1 The nozzle-to-vessel weld and inner radius examinations are performed together.
2 The N6 is the only Unit 2 nozzle that has been inspected to date in the fourth ISI interval.
2 None of the above Unit 3 nozzles have been examined to date in the fourth ISI interval.
 
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in  Accordance with 10 CFR 50.55a(a)(3)(i) (Page 3 of 12)
Table 5-2 PBAPS, Unit 3 Summary Group 1,2 Total Number Minimum Number to be Examined Recirculation Inlet (N2) 10 3 Main Steam (N3) 4 1 Core Spray (N5) 2 1 Nozzles On Top Head (N6 ) 2 1 Jet Pump Instrument (N8) 2 1  Notes to Table 5-2:
1  The nozzle-to-vessel weld and inner radius examinations are performed together.
2  None of the above Unit 3 nozzles have been examined to date in the fourth ISI interval.
The exams in Tables 5-1 and 5-2 will be scheduled in accordance with Table IWB-2412-1, Inspection Program B.
The exams in Tables 5-1 and 5-2 will be scheduled in accordance with Table IWB-2412-1, Inspection Program B.
Code Case N-702 stipulates that a VT-1 examination may be used in lieu of the volumetric examination for the inner radii (i.e., Item No. B3.100, "Nozzle Inside Radius Section"). This VT-1 examination is outlined in Code Case N-648-1  
Code Case N-702 stipulates that a VT-1 examination may be used in lieu of the volumetric examination for the inner radii (i.e., Item No. B3.100, Nozzle Inside Radius Section). This VT-1 examination is outlined in Code Case N-648-1 (Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles Section XI, Division 1). However, Exelon is not currently using Code Case N-648-1 at PBAPS for the identified components utilizing enhanced magnification visual examination, and has no plans of using Code Case N-648-1 on those components in the future. Volumetric examinations of all selected nozzle inside radius sections will be completed.
("Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles Section XI, Division 1"). However, Exelon is not currently using Code Case N-648-1 at PBAPS for the identified com ponents utilizing enhanced magnification visual examination, and has no plans of using Code Case N-648-1 on those components in the future. Volumetric examinations of all selected nozzle inside radius sections will be completed.  
Electric Power Research Institute (EPRI) Technical Report 1003557, BWRVIP-108:
BWR Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii, provides the basis for Code Case N-702. The evaluation found that failure probabilities at the nozzle blend radius region and nozzle-to-vessel shell weld due to a Low Temperature Overpressure event are very low (i.e., <1 x 10-6 for 40 years) with or without inservice inspection. The report concludes that inspection of 25 percent of each nozzle type is technically justified.
This EPRI report was approved by the NRC in a Safety Evaluation (SE) dated December 19, 2007 (i.e., ADAMS Accession No. ML073600374). Section 5.0,


Electric Power Research Institute (EPRI) Technical Report 1003557, "BWRVIP-108: BWR Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," provides the basis for Code Case N-702. The evaluation found that failure probabilities at the nozzle blend radius region and nozzle-to-vessel shell weld due to a Low Temperature Overpressure event are very low (i.e., <1 x 10
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
-6 for 40 years) with or without inservice inspection. The report concludes that inspection of 25 percent of each nozzle type is technically justified.
(Page 4 of 12)
 
Plant-Specific Applicability, of the SE indicates that each licensee who plans to request relief from ASME Code, Section XI requirements for RPV nozzle-to-vessel shell welds and nozzle inner radii sections may reference the BWRVIP-108 report as the technical basis for the use of ASME Code Case N-702 as an alternative.
This EPRI report was approved by the NRC in a Safety Evaluation (SE) dated December 19, 2007 (i.e., ADAMS Accession No. ML073600374). Section 5.0, Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 4 of 12)  
However, each licensee should demonstrate the plant specific applicability criteria from the BWRVIP-108 report to its units in the relief request by showing that all the general and nozzle-specific criteria addressed below are satisfied (i.e., as described in Enclosure 2 to this relief request).
  "Plant-Specific Applicability," of the SE indicates that each licensee who plans to request relief from ASME Code, Section XI requirements for RPV nozzle-to-vessel shell welds and nozzle inner radii sections may reference the BWRVIP-108 report as the technical basis for the use of ASME Code Case N-702 as an alternative. However, each licensee should demonstrate the plant specific applicability criteria from the BWRVIP-108 report to its units in the relief request by showing that all the general and nozzle-specific criteria addressed below are satisfied (i.e., as described in Enclosure 2 to this relief request).  
(1)     The maximum RPV heatup/cooldown rate is limited to less than 115&deg;F/hour.
(1) The maximum RPV heatup/cooldown rate is limited to less than 115&deg;F/hour.  
PBAPS, Units 2 and 3 Technical Specification (TS) Surveillance Requirement (SR) 3.4.9.1, RCS Pressure and Temperature (P/T) Limits, provides a Reactor Coolant System (RCS) heatup/cooldown rate of less than or equal to 100&deg;F in any 1-hour period. The heatup/cooldown rate is also referenced in the PBAPS operating procedures.
 
(2)     For the Recirculation Inlet Nozzles, the following criteria must be met:
PBAPS, Units 2 and 3 Technical Specification (TS) Surveillance Requirement (SR) 3.4.9.1, "RCS Pressure and Temperature (P/T) Limits," provides a Reactor Coolant System (RCS) heatup/cooldown rate of less than or equal to 100&deg;F in any 1-hour period. The heatup/cooldown rate is also referenced in the PBAPS operating procedures.  
: a. (pr/t)/CRPV<1.15; the calculation for the PBAPS, Units 2 and 3 N2 Nozzle results in 1.097, which is less than 1.15.
 
: b. [p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE<1.15; the calculation for the PBAPS, Units 2 and 3 N2 Nozzle results in 0.977, which is less than 1.15.
(2) For the Recirculation Inlet Nozzles, the following criteria must be met: a. (pr/t)/C RPV<1.15; the calculation for the PBAPS, Units 2 and 3 N2 Nozzle results in 1.097, which is less than 1.15. b. [p(r o 2 +r i 2)/(r o 2-r i 2)]/C NOZZLE<1.15; the calculation for the PBAPS, Units 2 and 3 N2 Nozzle results in 0.977, which is less than 1.15.  
(3)     For the Recirculation Outlet Nozzles, the following criteria must be met:
(3) For the Recirculation Outlet Nozzles, the following criteria must be met: a. (pr/t)/C RPV< 1.15; the calculation for the PBAPS, Units 2 and 3 N1 Nozzle results in 1.311, which is higher than 1.15 and does not meet the requirements. b. [p(r o 2+r i 2)/(r o 2-r i 2)]/C NOZZLE<1.15; the calculation for the PBAPS, Units 2 and 3 N1 Nozzle results in 0.853, which is less than 1.15.
: a. (pr/t)/CRPV< 1.15; the calculation for the PBAPS, Units 2 and 3 N1 Nozzle results in 1.311, which is higher than 1.15 and does not meet the requirements.
Based upon the above information, all PBAPS RPV nozzle-to-vessel shell full penetration welds and nozzle inner radii sections, with the exception of the Recirculation Outlet Nozzles, meet the general and nozzle-specific criteria in BWRVIP-108. The Recirculation Outlet (N1) Nozzles are not included in this relief request, and both nozzles will be examined during the fourth ISI interval.  
: b. [p(ro2+ri2)/(ro2-ri2)]/CNOZZLE<1.15; the calculation for the PBAPS, Units 2 and 3 N1 Nozzle results in 0.853, which is less than 1.15.
Based upon the above information, all PBAPS RPV nozzle-to-vessel shell full penetration welds and nozzle inner radii sections, with the exception of the Recirculation Outlet Nozzles, meet the general and nozzle-specific criteria in BWRVIP-108. The Recirculation Outlet (N1) Nozzles are not included in this relief request, and both nozzles will be examined during the fourth ISI interval.
Therefore, the use of Code Case N-702 provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i) for all the RPV nozzle-to-vessel shell full penetration welds and nozzle inner radii sections, with the exception of the Recirculation Outlet Nozzles.
In the response to a request for additional information for Limerick Generating Station (LGS), Units 1 and 2 (letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information - Submittal of Relief Request I3R-14 Concerning Nozzle-to-Vessel Weld


Therefore, the use of Code Case N-702 provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i) for all the RPV nozzle-to-vessel shell full penetration welds and nozzle inner radii sections, with the exception of the Recirculation Outlet Nozzles.
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
In the response to a request for additional information for Limerick Generating Station (LGS), Units 1 and 2 (letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information - Submittal of Relief Request I3R-14 Concerning Nozzle-to-Vessel Weld Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 5 of 12) and Inner Radii Examinations," dated July 27, 2010) the NRC had requested a synopsis of the inspections that have been performed on the components for which the alternative was requested and the indications that were found and how these indications were dispositioned. This information for PBAPS, Units 2 and 3 is included in Enclosure 3 to this relief request. As also provided in this response for LGS, Units 1 and 2, the NRC requested that LGS, Units 1 and 2 confirm that the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.) used in the BWRVIP-108 computation are correct and applicable to both LGS, Units 1 and 2. In the case of PBAPS, Units 2 and 3, the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.) in Enclosure 2 ("Plant Specific Applicability") are correct and applicable to PBAPS, Units 2 and 3. These values are minimum design values.
(Page 5 of 12) and Inner Radii Examinations," dated July 27, 2010) the NRC had requested a synopsis of the inspections that have been performed on the components for which the alternative was requested and the indications that were found and how these indications were dispositioned. This information for PBAPS, Units 2 and 3 is included in Enclosure 3 to this relief request. As also provided in this response for LGS, Units 1 and 2, the NRC requested that LGS, Units 1 and 2 confirm that the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.) used in the BWRVIP-108 computation are correct and applicable to both LGS, Units 1 and 2. In the case of PBAPS, Units 2 and 3, the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.) in Enclosure 2 (Plant Specific Applicability) are correct and applicable to PBAPS, Units 2 and 3. These values are minimum design values.
: 6. DURATION OF PROPOSED ALTERNATIVE The fourth interval for PBAPS, Units 2 and 3 began on November 5, 2008 and will conclude November 4, 2018. The proposed alternative will be used for the remainder of the fourth 10-year interval of the PBAPS ISI program.
: 6. DURATION OF PROPOSED ALTERNATIVE The fourth interval for PBAPS, Units 2 and 3 began on November 5, 2008 and will conclude November 4, 2018. The proposed alternative will be used for the remainder of the fourth 10-year interval of the PBAPS ISI program.
: 7. PRECEDENTS
: 7. PRECEDENTS
: 1. Letter from H. K. Chernoff (U.S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), "Limerick Generating Station, Units 1 and 2  
: 1. Letter from H. K. Chernoff (U.S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), "Limerick Generating Station, Units 1 and 2
- Proposed Alternative Request RR-I3R-14, Nozzle-to-Vessel Weld and Inner Radii Examinations (TAC NOS. ME3306 and ME3307)," dated September 9, 2010.
      - Proposed Alternative Request RR-I3R-14, Nozzle-to-Vessel Weld and Inner Radii Examinations (TAC NOS. ME3306 and ME3307)," dated September 9, 2010.
: 2. Letter from L. James (U.S. Nuclear Regulatory Commission) to R. L. Anderson (Duane Arnold Energy Center), "Duane Arnold Energy Center - Safety  
: 2. Letter from L. James (U.S. Nuclear Regulatory Commission) to R. L. Anderson (Duane Arnold Energy Center), Duane Arnold Energy Center - Safety Evaluation for Request for Alternative to Reactor Pressure Vessel Nozzle to Vessel Weld and Inner Radius Examinations (TAC NO. MD8193), dated August 29, 2008.
: 3. Letter from R. Gibbs (U.S. Nuclear Regulatory Commission) to M. B. Bezilla (FirstEnergy Nuclear Operating Company), Perry Nuclear Power Plant, Unit No.
1 - Request for Relief Related to Inservice Inspection Relief Request IR-054 (TAC NO. MD8458), dated December 29, 2008.


Evaluation for Request for Alternative to Reactor Pressure Vessel Nozzle to Vessel Weld and Inner Radius Examinations (TAC NO. MD8193)," dated August 29, 2008.  
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
: 3. Letter from R. Gibbs (U.S. Nuclear Regulatory Commission) to M. B. Bezilla (FirstEnergy Nuclear Operating Company), "Perry Nuclear Power Plant, Unit No.
(Page 6 of 12)
1 - Request for Relief Related to Inservice Inspection Relief Request IR-054 (TAC NO. MD8458)," dated December 29, 2008.  
Enclosure 1 Applicable PBAPS, Unit 2 Nozzles Component ID    Category    Item              System                  Nominal Number    Number                                    Pipe Size N2A                B-D      B3.90      Recirc Inlet                        12 N2A-IRS            B-D      B3.100    Recirc Inlet                        12 N2B                B-D      B3.90      Recirc Inlet                        12 N2B-IRS            B-D      B3.100    Recirc Inlet                        12 N2C                B-D      B3.90      Recirc Inlet                        12 N2C-IRS            B-D      B3.100    Recirc Inlet                        12 N2D                B-D      B3.90      Recirc Inlet                        12 N2D-IRS            B-D      B3.100    Recirc Inlet                        12 N2E                B-D      B3.90      Recirc Inlet                        12 N2E-IRS            B-D      B3.100    Recirc Inlet                        12 N2F                B-D      B3.90      Recirc Inlet                        12 N2F-IRS            B-D      B3.100    Recirc Inlet                        12 N2G                B-D      B3.90      Recirc Inlet                        12 N2G-IRS            B-D      B3.100    Recirc Inlet                        12 N2H                B-D      B3.90      Recirc Inlet                        12 N2H-IRS            B-D      B3.100    Recirc Inlet                        12 N2J                B-D      B3.90      Recirc Inlet                        12 N2J-IRS            B-D      B3.100    Recirc Inlet                        12 N2K                B-D      B3.90      Recirc Inlet                        12 N2K-IRS            B-D      B3.100    Recirc Inlet                        12 N3A                B-D      B3.90      Main Steam                          26 N3A-IRS            B-D      B3.100    Main Steam                          26 N3B                B-D      B3.90      Main Steam                          26 N3B-IRS            B-D      B3.100    Main Steam                          26 N3C                B-D      B3.90      Main Steam                          26 N3C-IRS            B-D      B3.100    Main Steam                          26 N3D                B-D      B3.90      Main Steam                          26 N3D-IRS            B-D      B3.100    Main Steam                          26 N5A                B-D      B3.90      Core Spray                          10 N5A-IRS            B-D      B3.100    Core Spray                          10 N5B                B-D      B3.90      Core Spray                          10 N5B-IRS            B-D      B3.100    Core Spray                          10 CH-NA (N6A)       B-D      B3.90      Head Spray                          6 CH-NA-IRS (N6A)    B-D      B3.100    Head Spray                          6 CH-NC (N6B)       B-D      B3.90      Head Spray                          6 CH-NC-IRS (N6B)    B-D      B3.100    Head Spray                          6 N8A                B-D      B3.90      Jet Pump Instrumentation            4 N8A-IRS            B-D      B3.100    Jet Pump Instrumentation            4 N8B                B-D      B3.90      Jet Pump Instrumentation            4 N8B-IRS            B-D      B3.100    Jet Pump Instrumentation            4 Note: The N6A (CH-NA and CH-NA-IRS) was examined in the fourth ISI interval.
* IRS - Inner Radius Section


Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 6 of 12)
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
Enclosure 1 Applicable PBAPS, Unit 2 Nozzles Component ID Category Number Item Number System Nominal Pipe Size N2A B-D B3.90 Recirc Inlet 12" N2A-IRS B-D B3.100 Recirc Inlet 12" N2B  B-D B3.90 Recirc Inlet 12" N2B-IRS B-D B3.100 Recirc Inlet 12" N2C  B-D B3.90 Recirc Inlet 12" N2C-IRS B-D B3.100 Recirc Inlet 12" N2D B-D B3.90 Recirc Inlet 12" N2D-IRS B-D B3.100 Recirc Inlet 12" N2E  B-D B3.90 Recirc Inlet 12" N2E-IRS B-D B3.100 Recirc Inlet 12" N2F  B-D B3.90 Recirc Inlet 12" N2F-IRS B-D B3.100 Recirc Inlet 12" N2G  B-D B3.90 Recirc Inlet 12" N2G-IRS B-D B3.100 Recirc Inlet 12" N2H  B-D B3.90 Recirc Inlet 12" N2H-IRS B-D B3.100 Recirc Inlet 12" N2J  B-D B3.90 Recirc Inlet 12" N2J-IRS B-D B3.100 Recirc Inlet 12" N2K  B-D B3.90 Recirc Inlet 12" N2K-IRS B-D B3.100 Recirc Inlet 12" N3A  B-D B3.90 Main Steam 26" N3A-IRS B-D B3.100 Main Steam 26" N3B  B-D B3.90 Main Steam 26" N3B-IRS B-D B3.100 Main Steam 26" N3C  B-D B3.90 Main Steam 26" N3C-IRS B-D B3.100 Main Steam 26" N3D B-D B3.90 Main Steam 26" N3D-IRS B-D B3.100 Main Steam 26" N5A  B-D B3.90 Core Spray 10" N5A-IRS B-D B3.100 Core Spray 10" N5B  B-D B3.90 Core Spray 10" N5B-IRS B-D B3.100 Core Spray 10" CH-NA (N6A) B-D B3.90 Head Spray 6" CH-NA-IRS (N6A) B-D B3.100 Head Spray 6" CH-NC (N6B) B-D B3.90 Head Spray 6" CH-NC-IRS (N6B) B-D B3.100 Head Spray 6" N8A  B-D B3.90 Jet Pump Instrumentation 4" N8A-IRS B-D B3.100 Jet Pump Instrumentation 4" N8B  B-D B3.90 Jet Pump Instrumentation 4" N8B-IRS B-D B3.100 Jet Pump Instrumentation 4" Note: The N6A (CH-NA and CH-NA-IRS) was examined in the fourth ISI interval.
(Page 7 of 12)
* IRS - Inner Radius Section Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in  Accordance with 10 CFR 50.55a(a)(3)(i) (Page 7 of 12)
Enclosure 1 Applicable PBAPS, Unit 3 Nozzles Component ID     Category   Item             System         Nominal Number  Number                              Pipe Size N2A               B-D     B3.90     Recirc Inlet                 12 N2A-IRS           B-D     B3.100   Recirc Inlet                 12 N2B               B-D     B3.90     Recirc Inlet                 12 N2B-IRS           B-D     B3.100   Recirc Inlet                 12 N2C               B-D     B3.90     Recirc Inlet                 12 N2C-IRS           B-D     B3.100   Recirc Inlet                 12 N2D               B-D     B3.90     Recirc Inlet                 12 N2D-IRS           B-D     B3.100   Recirc Inlet                 12 N2E               B-D     B3.90     Recirc Inlet                 12 N2E-IRS           B-D     B3.100   Recirc Inlet                 12 N2F               B-D     B3.90     Recirc Inlet                 12 N2F-IRS           B-D     B3.100   Recirc Inlet                 12 N2G               B-D     B3.90     Recirc Inlet                 12 N2G-IRS           B-D     B3.100   Recirc Inlet                 12 N2H               B-D     B3.90     Recirc Inlet                 12 N2H-IRS           B-D     B3.100   Recirc Inlet                 12 N2J               B-D     B3.90     Recirc Inlet                 12 N2J-IRS           B-D     B3.100   Recirc Inlet                 12 N2K               B-D     B3.90     Recirc Inlet                 12 N2K-IRS           B-D     B3.100   Recirc Inlet                 12 N3A               B-D     B3.90     Main Steam                   26 N3A-IRS           B-D     B3.100   Main Steam                   26 N3B               B-D     B3.90     Main Steam                   26 N3B-IRS           B-D     B3.100   Main Steam                   26 N3C               B-D     B3.90     Main Steam                   26 N3C-IRS           B-D     B3.100   Main Steam                   26 N3D               B-D     B3.90     Main Steam                   26 N3D-IRS           B-D     B3.100   Main Steam                   26 N5A               B-D     B3.90     Core Spray                   10 N5A-IRS           B-D     B3.100   Core Spray                   10 N5B               B-D     B3.90     Core Spray                   10 N5B-IRS           B-D     B3.100   Core Spray                   10 CH-NA (N6A)       B-D     B3.90     Head Spray                   6 CH-NA-IRS (N6A)   B-D     B3.100   Head Spray                   6 CH-NC (N6B)       B-D     B3.90     Head Spray                   6 CH-NC-IRS (N6B)   B-D     B3.100   Head Spray                   6 N8A               B-D     B3.90     Jet Pump Instrumentation     4 N8A-IRS           B-D     B3.100   Jet Pump Instrumentation     4 N8B               B-D     B3.90     Jet Pump Instrumentation     4 N8B-IRS           B-D     B3.100   Jet Pump Instrumentation     4
Enclosure 1 Applicable PBAPS, Unit 3 Nozzles Component ID Category Number Item Number System Nominal Pipe Size N2A B-D B3.90 Recirc Inlet 12" N2A-IRS B-D B3.100 Recirc Inlet 12" N2B B-D B3.90 Recirc Inlet 12" N2B-IRS B-D B3.100 Recirc Inlet 12" N2C B-D B3.90 Recirc Inlet 12" N2C-IRS B-D B3.100 Recirc Inlet 12" N2D B-D B3.90 Recirc Inlet 12" N2D-IRS B-D B3.100 Recirc Inlet 12" N2E B-D B3.90 Recirc Inlet 12" N2E-IRS B-D B3.100 Recirc Inlet 12" N2F B-D B3.90 Recirc Inlet 12" N2F-IRS B-D B3.100 Recirc Inlet 12" N2G B-D B3.90 Recirc Inlet 12" N2G-IRS B-D B3.100 Recirc Inlet 12" N2H B-D B3.90 Recirc Inlet 12" N2H-IRS B-D B3.100 Recirc Inlet 12" N2J B-D B3.90 Recirc Inlet 12" N2J-IRS B-D B3.100 Recirc Inlet 12" N2K B-D B3.90 Recirc Inlet 12" N2K-IRS B-D B3.100 Recirc Inlet 12" N3A B-D B3.90 Main Steam 26" N3A-IRS B-D B3.100 Main Steam 26" N3B B-D B3.90 Main Steam 26" N3B-IRS B-D B3.100 Main Steam 26" N3C B-D B3.90 Main Steam 26" N3C-IRS B-D B3.100 Main Steam 26" N3D B-D B3.90 Main Steam 26" N3D-IRS B-D B3.100 Main Steam 26" N5A B-D B3.90 Core Spray 10" N5A-IRS B-D B3.100 Core Spray 10" N5B B-D B3.90 Core Spray 10" N5B-IRS B-D B3.100 Core Spray 10" CH-NA (N6A) B-D B3.90 Head Spray 6" CH-NA-IRS (N6A) B-D B3.100 Head Spray 6" CH-NC (N6B) B-D B3.90 Head Spray 6" CH-NC-IRS (N6B) B-D B3.100 Head Spray 6" N8A B-D B3.90 Jet Pump Instrumentation 4" N8A-IRS B-D B3.100 Jet Pump Instrumentation 4" N8B B-D B3.90 Jet Pump Instrumentation 4" N8B-IRS B-D B3.100 Jet Pump Instrumentation 4"
* IRS - Inner Radius Section
* IRS - Inner Radius Section Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in  Accordance with 10 CFR 50.55a(a)(3)(i) (Page 8 of 12)
Enclosure 2 Plant Specific Applicability (1) The maximum Reactor Pressure Vessel (RPV) heatup/cooldown rate is limited to less than 115 F/hour. PBAPS, Units 2 and 3 Technical Specification (TS) Surveillance Requirement (SR) 3.4.9.1, "RCS Pressure and Temperature (P/T) Limits," provides a Reactor Coolant System (RCS) heatup/cooldown rate of less than or equal to 100&deg;F in any 1-hour period. The heatup/cooldown rate is also referenced in the PBAPS operating procedures.


Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
(Page 8 of 12)
Enclosure 2 Plant Specific Applicability (1) The maximum Reactor Pressure Vessel (RPV) heatup/cooldown rate is limited to less than 115&deg;F/hour.
PBAPS, Units 2 and 3 Technical Specification (TS) Surveillance Requirement (SR) 3.4.9.1, RCS Pressure and Temperature (P/T) Limits, provides a Reactor Coolant System (RCS) heatup/cooldown rate of less than or equal to 100&deg;F in any 1-hour period. The heatup/cooldown rate is also referenced in the PBAPS operating procedures.
For Recirculation Inlet Nozzles (N2)
For Recirculation Inlet Nozzles (N2)
  (2) (pr/t)/C RPV< 1.15 p=RPV Normal Operating Pressure 1035 psi r=RPV inner radius 125.5 in.
(2)     (pr/t)/CRPV< 1.15 p=RPV Normal Operating Pressure       1035 psi r=RPV inner radius                   125.5 in.
t=RPV wall thickness 6.125 in.
t=RPV wall thickness                 6.125 in.
C RPV= 19332 (pr/t)/C RPV = 1.097 <1.15 (3) [p(r o 2 +r i 2)/(r o 2-r i 2)]/C NOZZLE< 1.15 p=RPV Normal Operating Pressure 1035 psi r o=nozzle outer radius 12.5 in.
CRPV=                                 19332 (pr/t)/CRPV = 1.097 <1.15 (3)     [p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE< 1.15 p=RPV Normal Operating Pressure       1035 psi ro=nozzle outer radius               12.5 in.
r i=nozzle inner radius 5.784 in.
ri=nozzle inner radius               5.784 in.
C NOZZLE 1637 [p(r o 2 +r i 2)/(r o 2-r i 2)]/CNOZZLE = 0.977 <1.15 For Recirculation Outlet Nozzles (N1)
CNOZZLE                              1637
  (4) (pr/t)/C RPV< 1.15 p=RPV Normal Operating Pressure 1035 psi r=RPV inner radius 125.5 in.
[p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE = 0.977 <1.15 For Recirculation Outlet Nozzles (N1)
t=RPV wall thickness 6.125 in.
(4)     (pr/t)/CRPV< 1.15 p=RPV Normal Operating Pressure       1035 psi r=RPV inner radius                   125.5 in.
C RPV= 16171 (pr/t)/C RPV = 1.311 >1.15 Note: Requirement not satisfied for the PBAPS N1 Nozzles, which are not included in this relief request.  
t=RPV wall thickness                 6.125 in.
(5) [p(r o 2 +r i 2)/(r o 2-r i 2)]/C NOZZLE< 1.15 p=RPV Normal Operating Pressure 1035 psi r o=nozzle outer radius 26.5 in.
CRPV=                                 16171 (pr/t)/CRPV = 1.311 >1.15 Note: Requirement not satisfied for the PBAPS N1 Nozzles, which are not included in this relief request.
r i=nozzle inner radius   12.97 in.
(5)     [p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE< 1.15 p=RPV Normal Operating Pressure       1035 psi ro=nozzle outer radius               26.5 in.
C NOZZLE 1977 [p(r o 2 +r i 2)/(r o 2-r i 2)]/CNOZZLE = 0.853 <1.15
ri=nozzle inner radius               12.97 in.
CNOZZLE                              1977
[p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE = 0.853 <1.15


Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 9 of 12)
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
Enclosure 3 PBAPS, Unit 2 Nozzle-to-Vessel and Nozzle Inner Radius Inspection Results The following tables identify the inspection results (Recordable Indications (RI) and No-Recordable Indications (NRI)). All the indications were evaluated as acceptable per ASME Section XI.  
(Page 9 of 12)
Enclosure 3 PBAPS, Unit 2 Nozzle-to-Vessel and Nozzle Inner Radius Inspection Results The following tables identify the inspection results (Recordable Indications (RI) and No-Recordable Indications (NRI)). All the indications were evaluated as acceptable per ASME Section XI.
Unit  Component ID        Outage  Interval Period  Results 2    CH-NA (N6A)          2R14      3      1      NRI 2    CH-NA (N6A)          2R18      4      1      NRI 2    CH-NA-IRS (N6A)      2R14      3      1      NRI 2    CH-NA-IRS (N6A)      2R18      4      1      NRI 2    CH-NC (N6B)          2R14      3      1      NRI 2    CH-NC-IRS (N6B)      2R14      3      1      NRI 2    N2A                  2R14      3      1      NRI 2    N2A-IRS              2R14      3      1      NRI 2    N2B                  2R14      3      1      NRI 2    N2B-IRS              2R14      3      1      NRI 2    N2C                  2R14      3      1      NRI 2    N2C-IRS              2R14      3      1      NRI 2    N2D                  2R15      3      2      NRI 2    N2D-IRS              2R15      3      2      NRI 2    N2E                  2R16      3      3      NRI 2    N2E-IRS              2R16      3      3      NRI 2    N2F                  2R15      3      2      NRI 2    N2F-IRS              2R15      3      2      NRI 2    N2G                  2R16      3      3      NRI 2    N2G-IRS              2R16      3      3      NRI 2    N2H                  2R15      3      2      NRI 2    N2H-IRS              2R15      3      2      NRI 2    N2J                  2R16      3      3      NRI 2    N2J-IRS              2R16      3      3      NRI 2    N2K                  2R16      3      3      NRI 2    N2K-IRS              2R16      3      3      NRI 2    N3A                  2R17      3      3      NRI 2    N3A-IRS              2R17      3      3      NRI 2    N3B                  2R17      3      3      NRI 2    N3B-IRS              2R17      3      3      NRI 2    N3C                  2R16      3      3      NRI 2    N3C-IRS              2R16      3      3      NRI 2    N3D                  2R16      3      3      NRI 2    N3D-IRS              2R16      3      3      NRI 2    N5A                  2R17      3      3      NRI 2    N5A-IRS              2R17      3      3      NRI 2    N5B                  2R17      3      3      NRI


Unit Component ID Outage Interval PeriodResults 2 CH-NA (N6A) 2R14 3 1 NRI 2 CH-NA (N6A) 2R18 4 1 NRI 2 CH-NA-IRS (N6A) 2R14 3 1 NRI 2 CH-NA-IRS (N6A) 2R18 4 1 NRI 2 CH-NC (N6B) 2R14 3 1 NRI 2 CH-NC-IRS (N6B) 2R14 3 1 NRI 2 N2A 2R14 3 1 NRI 2 N2A-IRS 2R14 3 1 NRI 2 N2B 2R14 3 1 NRI 2 N2B-IRS 2R14 3 1 NRI 2 N2C 2R14 3 1 NRI 2 N2C-IRS 2R14 3 1 NRI 2 N2D 2R15 3 2 NRI 2 N2D-IRS 2R15 3 2 NRI 2 N2E 2R16 3 3 NRI 2 N2E-IRS 2R16 3 3 NRI 2 N2F 2R15 3 2 NRI 2 N2F-IRS 2R15 3 2 NRI 2 N2G 2R16 3 3 NRI 2 N2G-IRS 2R16 3 3 NRI 2 N2H 2R15 3 2 NRI 2 N2H-IRS 2R15 3 2 NRI 2 N2J 2R16 3 3 NRI 2 N2J-IRS 2R16 3 3 NRI 2 N2K 2R16 3 3 NRI 2 N2K-IRS 2R16 3 3 NRI 2 N3A 2R17 3 3 NRI 2 N3A-IRS 2R17 3 3 NRI 2 N3B 2R17 3 3 NRI 2 N3B-IRS 2R17 3 3 NRI 2 N3C 2R16 3 3 NRI 2 N3C-IRS 2R16 3 3 NRI 2 N3D 2R16 3 3 NRI 2 N3D-IRS 2R16 3 3 NRI 2 N5A 2R17 3 3 NRI 2 N5A-IRS 2R17 3 3 NRI 2 N5B 2R17 3 3 NRI Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 10 of 12)
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
Unit Component ID Outage Interval PeriodResults 2 N5B-IRS 2R17 3 3 NRI 2 N8A 2R14 3 1 NRI 2 N8A-IRS 2R14 3 1 NRI 2 N8B 2R16 3 3 NRI 2 N8B-IRS 2R16 3 3 NRI  
(Page 10 of 12)
Unit Component ID     Outage Interval Period Results 2   N5B-IRS           2R17       3     3     NRI 2   N8A               2R14       3     1     NRI 2   N8A-IRS           2R14       3     1     NRI 2   N8B               2R16       3     3     NRI 2   N8B-IRS           2R16       3     3     NRI


Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 11 of 12)
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
(Page 11 of 12)
Enclosure 3 PBAPS Unit 3, Nozzle-to-Vessel and Nozzle Inner Radius Inspection Results The following tables identify the inspection results (Recordable Indications (RI) and No-Recordable Indications (NRI)). All the indications were evaluated as acceptable per ASME Section XI.
Enclosure 3 PBAPS Unit 3, Nozzle-to-Vessel and Nozzle Inner Radius Inspection Results The following tables identify the inspection results (Recordable Indications (RI) and No-Recordable Indications (NRI)). All the indications were evaluated as acceptable per ASME Section XI.
Unit Component ID Outage Interval PeriodResultsMisc. 3 CH-NA (N6A) 3R13 3 1 NRI     3 CH-NA-IRS (N6A)  3R13 3 1 NRI     3 CH-NC (N6B) 3R13 3 1 NRI     3 CH-NC-IRS (N6B) 3R13 3 1 NRI     3 N2A 3R14 3 2 NRI     3 N2A-IRS 3R14 3 2 NRI   3 N2B 3R14 3 2 RI Recordable indications identified - acceptable per ASME Section XI. 3 N2B-IRS 3R14 3 2 NRI 3 N2C 3R14 3 2 NRI  3 N2C-IRS 3R14 3 2 NRI 3 N2D 3R13 3 1 NRI 3 N2D-IRS 3R13 3 1 NRI 3 N2E 3R13 3 1 NRI 3 N2E-IRS 3R13 3 1 NRI 3 N2F 3R13 3 1 NRI 3 N2F-IRS 3R13 3 1 NRI  3 N2G 3R14 3 2 RI Recordable indication identified - acceptable per ASME Section XI.
Component Unit     ID       Outage   Interval Period  Results                        Misc.
3 N2G-IRS 3R14 3 2 NRI 3 N2H 3R16 3 3 NRI 3 N2H-IRS 3R16 3 3 NRI 3 N2J 3R16 3 3 NRI 3 N2J-IRS 3R16 3 3 NRI 3 N2K 3R16 3 3 NRI 3 N2K-IRS 3R16 3 3 NRI 3 N3A 3R13 3 1 NRI 3 N3A-IRS 3R13 3 1 NRI 3 N3B 3R13 3 1 NRI 3 N3B-IRS 3R13 3 1 NRI 3 N3C 3R16 3 3 NRI 3 N3C-IRS 3R16 3 3 NRI 3 N3D 3R16 3 3 NRI Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) (Page 12 of 12)
3   CH-NA         3R13       3       1       NRI (N6A) 3   CH-NA-IRS     3R13       3       1       NRI (N6A) 3   CH-NC         3R13       3       1       NRI (N6B) 3   CH-NC-IRS     3R13       3       1       NRI (N6B) 3   N2A           3R14       3       2       NRI 3   N2A-IRS       3R14       3       2       NRI 3   N2B           3R14       3       2       RI   Recordable indications identified - acceptable per ASME Section XI.
Unit Component ID Outage Interval PeriodResultsMisc. 3 N3D-IRS 3R16 3 3 NRI 3 N5A 3R14 3 2 NRI 3 N5A-IRS 3R14 3 2 NRI 3 N5B 3R15 3 3 NRI  3 N5B-IRS 3R15 3 3 NRI 3 N8A 3R13 3 1 NRI  3 N8A-IRS 3R13 3 1 NRI  3 N8B 3R16 3 3 NRI  3 N8B-IRS 3R16 3 3 NRI}}
3   N2B-IRS       3R14       3       2       NRI 3   N2C           3R14       3       2       NRI 3   N2C-IRS       3R14       3       2       NRI 3   N2D           3R13       3       1       NRI 3   N2D-IRS       3R13       3       1       NRI 3   N2E           3R13       3       1       NRI 3   N2E-IRS       3R13       3       1       NRI 3   N2F           3R13       3       1       NRI 3   N2F-IRS       3R13       3       1       NRI 3   N2G           3R14       3       2       RI   Recordable indication identified - acceptable per ASME Section XI.
3   N2G-IRS       3R14       3       2       NRI 3   N2H           3R16       3       3       NRI 3   N2H-IRS       3R16       3       3       NRI 3   N2J           3R16       3       3       NRI 3   N2J-IRS       3R16       3       3       NRI 3   N2K           3R16       3       3       NRI 3   N2K-IRS       3R16       3       3       NRI 3   N3A           3R13       3       1       NRI 3   N3A-IRS       3R13       3       1       NRI 3   N3B           3R13       3       1       NRI 3   N3B-IRS       3R13       3       1       NRI 3   N3C           3R16       3       3       NRI 3   N3C-IRS       3R16       3       3       NRI 3   N3D           3R16       3       3       NRI
 
Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)
(Page 12 of 12)
Component Unit     ID     Outage   Interval Period  Results                  Misc.
3   N3D-IRS     3R16       3       3       NRI 3   N5A         3R14       3       2       NRI 3   N5A-IRS     3R14       3       2       NRI 3   N5B         3R15       3       3       NRI 3   N5B-IRS     3R15       3       3       NRI 3   N8A         3R13       3       1       NRI 3   N8A-IRS     3R13       3       1       NRI 3   N8B         3R16       3       3       NRI 3   N8B-IRS     3R16       3       3       NRI}}

Latest revision as of 07:42, 11 March 2020

Submittal of Relief Request 14R-52 Concerning Nozzle-to-Vessel Weld and Inner Examinations (Use of Code Case N-702)
ML110250147
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/24/2011
From: David Helker
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML110250147 (14)
v • d • e


Text

I ii I I Exel Exelnn I Ion t

Nuclear N uci ear I kU UIUlFk 8A 8 10 1 0 CFR C FR 50.55a

50. 55a January 24, January 24, 2011 2011 U.S. Nuclear U.S. Nuclear Regulatory Regulatory Commission Commission Attn: Document Attn: Document Control Control Desk Desk Washington, DC Washington, DC 20555-0001 20555-0001 Peach Bottom Peach Bottom Atomic Atomic Power Power Station, Station, Units Units 2 and 3 Renewed Facility Renewed Operating License Facility Operating License Nos.

Nos. DPR-44 DPR-44 and DPR-56 NRC Docket NRC Docket Nos.

Nos. 50-277 and 50-278

Subject:

Subject:

Submittal of Submittal Relief Request of Relief Request 14R-52 Concerning Nozzle-to-Vessel Nozzle-to-Vessel Weld and Inner and Inner Radii Radii Examinations Examinations (Use of Code Case N-702)

In accordance In accordance with 10 10 CFR 50.55a, "Codes Codes and standards,"

standards, paragraph (a)(3)(i), Exelon Generation Company, LLC (Exelon), is requesting relief from the American Society of Mechanical Engineers Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, XI, "Rules Rules for Inservice Inspection of Nuclear Power Plant Components.'1 Inservice Components. Relief Request 14R-52 l4R-52 proposes an alternative to the requirements contained in Table IWB-2500-1 concerning nozzle-to-vessel nozzle-to-vessel weld and nozzle inner radii examination requirements. requirements.

This relief applies to the fourth 10-year Inservice lnservice Inspection (lSI)

(ISI) interval. The fourth interval for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 began on November 5, 5,2008, 2008, and will conclude November 4, 2018. The fourth 10-year lSl lSI interval complies with the ASME B&PV Code,Section XI, Xl, 2001 Edition through 2003 Addenda.

We request your review and approval by January 24, 2012.

No regulatory commitmentscommitments are contained in this letter.

Should you have any questions concerning this letter, please contact Tom Loomis at (610) (610) 765-765-5510.

Sincerely, David P. Helker Manager - Licensing & Regulatory Affairs Exelon Generation Company, LLC

Attachment:

Relief Request l4R-52 14R-52 cc: USNRC Region I, Regional Administrato Administratorr USNRC Senior Resident Inspector, Inspector, PBAPS PBAPS USNRC USNRC Project Manager, Manager, PBAPS PBAPS R. R. Janati, Janati, Bureau Bureau of Radiation Protection Protection S. T. Gray, State of Maryland Maryland

ATTACHMENT Relief Request I4R-52

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 1 of 12)

1. ASME CODE COMPONENTS AFFECTED Code Class: 1 Component Numbers: Reactor Vessel Nozzles: N2, N3, N5, N6, N8 (See Enclosure 1 for complete list of nozzle identifications)

Examination Category: B-D (Inspection Program B)

Item Number: B3.90 and B3.100

Description:

Alternative to ASME Section XI, Table IWB-2500-1

2. APPLICABLE CODE EDITION AND ADDENDA The fourth 10-year Inservice Inspection (ISI) program at Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 2001 Edition through the 2003 Addenda. Additionally, for ultrasonic examinations, ASME Section XI, Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems, of the 2001 Edition is implemented, as required and modified by 10 CFR 50.55a(b)(2)(xv).
3. APPLICABLE CODE REQUIREMENTS The applicable requirements are contained in Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels - Inspection Program B.

Class 1 nozzle-to-vessel weld and nozzle inner radii examination requirements are delineated in Item Number B3.90, Nozzle-to-Vessel Welds, and B3.100, Nozzle Inside Radius Section. The required method of examination is volumetric. All nozzles with full penetration welds to the vessel shell (or head) and integrally cast nozzles are examined each interval.

All of the nozzle assemblies identified in Enclosure 1 are full penetration welds.

4. REASON FOR REQUEST Enclosure 1 provides a complete listing of the applicable Reactor Pressure Vessel (RPV) nozzles for PBAPS, Units 2 and 3.

The proposed alternative provides an acceptable level of quality and safety, and the reduction in scope could provide a dose savings of as much as 26 Person-Rem for Unit 2 and 27 Person-Rem for Unit 3 over the remainder of the interval.

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 2 of 12)

5. PROPOSED ALTERNATIVE AND BASIS FOR USE In accordance with 10 CFR 50.55a(a)(3)(i), relief is requested from performing the required examinations on 100 percent of the nozzle assemblies identified in Tables 5-1 and 5-2 below (see Enclosure 1 for the list of RPV nozzles applicable to this relief request). As an alternative, for all welds and inner radii identified in Tables 5-1 and 5-2, Exelon Generation Company, LLC (Exelon) proposes to examine a minimum of 25 percent of the PBAPS, Units 2 and 3 nozzle-to-vessel welds and inner radii sections, including at least one nozzle from each system and nominal pipe size, in accordance with Code Case N-702 (Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell WeldsSection XI, Division 1). For the nozzle assemblies identified in Enclosure 1, this would mean 25 percent from each of the groups identified below:

Table 5-1 PBAPS, Unit 2 Summary Group 1,2 Total Minimum Number Number to be Examined Recirculation Inlet 10 3 (N2)

Main Steam 4 1 (N3)

Core Spray 2 1 (N5)

Nozzles On Top 2 1 Head (N6)

Jet Pump 2 1 Instrument (N8)

Notes to Table 5-1:

1 The nozzle-to-vessel weld and inner radius examinations are performed together.

2 The N6 is the only Unit 2 nozzle that has been inspected to date in the fourth ISI interval.

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 3 of 12)

Table 5-2 PBAPS, Unit 3 Summary Group 1,2 Total Minimum Number Number to be Examined Recirculation Inlet 10 3 (N2)

Main Steam 4 1 (N3)

Core Spray 2 1 (N5)

Nozzles On Top 2 1 Head (N6 )

Jet Pump 2 1 Instrument (N8)

Notes to Table 5-2:

1 The nozzle-to-vessel weld and inner radius examinations are performed together.

2 None of the above Unit 3 nozzles have been examined to date in the fourth ISI interval.

The exams in Tables 5-1 and 5-2 will be scheduled in accordance with Table IWB-2412-1, Inspection Program B.

Code Case N-702 stipulates that a VT-1 examination may be used in lieu of the volumetric examination for the inner radii (i.e., Item No. B3.100, Nozzle Inside Radius Section). This VT-1 examination is outlined in Code Case N-648-1 (Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel NozzlesSection XI, Division 1). However, Exelon is not currently using Code Case N-648-1 at PBAPS for the identified components utilizing enhanced magnification visual examination, and has no plans of using Code Case N-648-1 on those components in the future. Volumetric examinations of all selected nozzle inside radius sections will be completed.

Electric Power Research Institute (EPRI) Technical Report 1003557, BWRVIP-108:

BWR Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii, provides the basis for Code Case N-702. The evaluation found that failure probabilities at the nozzle blend radius region and nozzle-to-vessel shell weld due to a Low Temperature Overpressure event are very low (i.e., <1 x 10-6 for 40 years) with or without inservice inspection. The report concludes that inspection of 25 percent of each nozzle type is technically justified.

This EPRI report was approved by the NRC in a Safety Evaluation (SE) dated December 19, 2007 (i.e., ADAMS Accession No. ML073600374). Section 5.0,

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 4 of 12)

Plant-Specific Applicability, of the SE indicates that each licensee who plans to request relief from ASME Code,Section XI requirements for RPV nozzle-to-vessel shell welds and nozzle inner radii sections may reference the BWRVIP-108 report as the technical basis for the use of ASME Code Case N-702 as an alternative.

However, each licensee should demonstrate the plant specific applicability criteria from the BWRVIP-108 report to its units in the relief request by showing that all the general and nozzle-specific criteria addressed below are satisfied (i.e., as described in Enclosure 2 to this relief request).

(1) The maximum RPV heatup/cooldown rate is limited to less than 115°F/hour.

PBAPS, Units 2 and 3 Technical Specification (TS) Surveillance Requirement (SR) 3.4.9.1, RCS Pressure and Temperature (P/T) Limits, provides a Reactor Coolant System (RCS) heatup/cooldown rate of less than or equal to 100°F in any 1-hour period. The heatup/cooldown rate is also referenced in the PBAPS operating procedures.

(2) For the Recirculation Inlet Nozzles, the following criteria must be met:

a. (pr/t)/CRPV<1.15; the calculation for the PBAPS, Units 2 and 3 N2 Nozzle results in 1.097, which is less than 1.15.
b. [p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE<1.15; the calculation for the PBAPS, Units 2 and 3 N2 Nozzle results in 0.977, which is less than 1.15.

(3) For the Recirculation Outlet Nozzles, the following criteria must be met:

a. (pr/t)/CRPV< 1.15; the calculation for the PBAPS, Units 2 and 3 N1 Nozzle results in 1.311, which is higher than 1.15 and does not meet the requirements.
b. [p(ro2+ri2)/(ro2-ri2)]/CNOZZLE<1.15; the calculation for the PBAPS, Units 2 and 3 N1 Nozzle results in 0.853, which is less than 1.15.

Based upon the above information, all PBAPS RPV nozzle-to-vessel shell full penetration welds and nozzle inner radii sections, with the exception of the Recirculation Outlet Nozzles, meet the general and nozzle-specific criteria in BWRVIP-108. The Recirculation Outlet (N1) Nozzles are not included in this relief request, and both nozzles will be examined during the fourth ISI interval.

Therefore, the use of Code Case N-702 provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i) for all the RPV nozzle-to-vessel shell full penetration welds and nozzle inner radii sections, with the exception of the Recirculation Outlet Nozzles.

In the response to a request for additional information for Limerick Generating Station (LGS), Units 1 and 2 (letter from D. P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information - Submittal of Relief Request I3R-14 Concerning Nozzle-to-Vessel Weld

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 5 of 12) and Inner Radii Examinations," dated July 27, 2010) the NRC had requested a synopsis of the inspections that have been performed on the components for which the alternative was requested and the indications that were found and how these indications were dispositioned. This information for PBAPS, Units 2 and 3 is included in Enclosure 3 to this relief request. As also provided in this response for LGS, Units 1 and 2, the NRC requested that LGS, Units 1 and 2 confirm that the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.) used in the BWRVIP-108 computation are correct and applicable to both LGS, Units 1 and 2. In the case of PBAPS, Units 2 and 3, the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.) in Enclosure 2 (Plant Specific Applicability) are correct and applicable to PBAPS, Units 2 and 3. These values are minimum design values.

6. DURATION OF PROPOSED ALTERNATIVE The fourth interval for PBAPS, Units 2 and 3 began on November 5, 2008 and will conclude November 4, 2018. The proposed alternative will be used for the remainder of the fourth 10-year interval of the PBAPS ISI program.
7. PRECEDENTS
1. Letter from H. K. Chernoff (U.S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), "Limerick Generating Station, Units 1 and 2

- Proposed Alternative Request RR-I3R-14, Nozzle-to-Vessel Weld and Inner Radii Examinations (TAC NOS. ME3306 and ME3307)," dated September 9, 2010.

2. Letter from L. James (U.S. Nuclear Regulatory Commission) to R. L. Anderson (Duane Arnold Energy Center), Duane Arnold Energy Center - Safety Evaluation for Request for Alternative to Reactor Pressure Vessel Nozzle to Vessel Weld and Inner Radius Examinations (TAC NO. MD8193), dated August 29, 2008.
3. Letter from R. Gibbs (U.S. Nuclear Regulatory Commission) to M. B. Bezilla (FirstEnergy Nuclear Operating Company), Perry Nuclear Power Plant, Unit No.

1 - Request for Relief Related to Inservice Inspection Relief Request IR-054 (TAC NO. MD8458), dated December 29, 2008.

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 6 of 12)

Enclosure 1 Applicable PBAPS, Unit 2 Nozzles Component ID Category Item System Nominal Number Number Pipe Size N2A B-D B3.90 Recirc Inlet 12 N2A-IRS B-D B3.100 Recirc Inlet 12 N2B B-D B3.90 Recirc Inlet 12 N2B-IRS B-D B3.100 Recirc Inlet 12 N2C B-D B3.90 Recirc Inlet 12 N2C-IRS B-D B3.100 Recirc Inlet 12 N2D B-D B3.90 Recirc Inlet 12 N2D-IRS B-D B3.100 Recirc Inlet 12 N2E B-D B3.90 Recirc Inlet 12 N2E-IRS B-D B3.100 Recirc Inlet 12 N2F B-D B3.90 Recirc Inlet 12 N2F-IRS B-D B3.100 Recirc Inlet 12 N2G B-D B3.90 Recirc Inlet 12 N2G-IRS B-D B3.100 Recirc Inlet 12 N2H B-D B3.90 Recirc Inlet 12 N2H-IRS B-D B3.100 Recirc Inlet 12 N2J B-D B3.90 Recirc Inlet 12 N2J-IRS B-D B3.100 Recirc Inlet 12 N2K B-D B3.90 Recirc Inlet 12 N2K-IRS B-D B3.100 Recirc Inlet 12 N3A B-D B3.90 Main Steam 26 N3A-IRS B-D B3.100 Main Steam 26 N3B B-D B3.90 Main Steam 26 N3B-IRS B-D B3.100 Main Steam 26 N3C B-D B3.90 Main Steam 26 N3C-IRS B-D B3.100 Main Steam 26 N3D B-D B3.90 Main Steam 26 N3D-IRS B-D B3.100 Main Steam 26 N5A B-D B3.90 Core Spray 10 N5A-IRS B-D B3.100 Core Spray 10 N5B B-D B3.90 Core Spray 10 N5B-IRS B-D B3.100 Core Spray 10 CH-NA (N6A) B-D B3.90 Head Spray 6 CH-NA-IRS (N6A) B-D B3.100 Head Spray 6 CH-NC (N6B) B-D B3.90 Head Spray 6 CH-NC-IRS (N6B) B-D B3.100 Head Spray 6 N8A B-D B3.90 Jet Pump Instrumentation 4 N8A-IRS B-D B3.100 Jet Pump Instrumentation 4 N8B B-D B3.90 Jet Pump Instrumentation 4 N8B-IRS B-D B3.100 Jet Pump Instrumentation 4 Note: The N6A (CH-NA and CH-NA-IRS) was examined in the fourth ISI interval.

  • IRS - Inner Radius Section

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 7 of 12)

Enclosure 1 Applicable PBAPS, Unit 3 Nozzles Component ID Category Item System Nominal Number Number Pipe Size N2A B-D B3.90 Recirc Inlet 12 N2A-IRS B-D B3.100 Recirc Inlet 12 N2B B-D B3.90 Recirc Inlet 12 N2B-IRS B-D B3.100 Recirc Inlet 12 N2C B-D B3.90 Recirc Inlet 12 N2C-IRS B-D B3.100 Recirc Inlet 12 N2D B-D B3.90 Recirc Inlet 12 N2D-IRS B-D B3.100 Recirc Inlet 12 N2E B-D B3.90 Recirc Inlet 12 N2E-IRS B-D B3.100 Recirc Inlet 12 N2F B-D B3.90 Recirc Inlet 12 N2F-IRS B-D B3.100 Recirc Inlet 12 N2G B-D B3.90 Recirc Inlet 12 N2G-IRS B-D B3.100 Recirc Inlet 12 N2H B-D B3.90 Recirc Inlet 12 N2H-IRS B-D B3.100 Recirc Inlet 12 N2J B-D B3.90 Recirc Inlet 12 N2J-IRS B-D B3.100 Recirc Inlet 12 N2K B-D B3.90 Recirc Inlet 12 N2K-IRS B-D B3.100 Recirc Inlet 12 N3A B-D B3.90 Main Steam 26 N3A-IRS B-D B3.100 Main Steam 26 N3B B-D B3.90 Main Steam 26 N3B-IRS B-D B3.100 Main Steam 26 N3C B-D B3.90 Main Steam 26 N3C-IRS B-D B3.100 Main Steam 26 N3D B-D B3.90 Main Steam 26 N3D-IRS B-D B3.100 Main Steam 26 N5A B-D B3.90 Core Spray 10 N5A-IRS B-D B3.100 Core Spray 10 N5B B-D B3.90 Core Spray 10 N5B-IRS B-D B3.100 Core Spray 10 CH-NA (N6A) B-D B3.90 Head Spray 6 CH-NA-IRS (N6A) B-D B3.100 Head Spray 6 CH-NC (N6B) B-D B3.90 Head Spray 6 CH-NC-IRS (N6B) B-D B3.100 Head Spray 6 N8A B-D B3.90 Jet Pump Instrumentation 4 N8A-IRS B-D B3.100 Jet Pump Instrumentation 4 N8B B-D B3.90 Jet Pump Instrumentation 4 N8B-IRS B-D B3.100 Jet Pump Instrumentation 4

  • IRS - Inner Radius Section

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 8 of 12)

Enclosure 2 Plant Specific Applicability (1) The maximum Reactor Pressure Vessel (RPV) heatup/cooldown rate is limited to less than 115°F/hour.

PBAPS, Units 2 and 3 Technical Specification (TS) Surveillance Requirement (SR) 3.4.9.1, RCS Pressure and Temperature (P/T) Limits, provides a Reactor Coolant System (RCS) heatup/cooldown rate of less than or equal to 100°F in any 1-hour period. The heatup/cooldown rate is also referenced in the PBAPS operating procedures.

For Recirculation Inlet Nozzles (N2)

(2) (pr/t)/CRPV< 1.15 p=RPV Normal Operating Pressure 1035 psi r=RPV inner radius 125.5 in.

t=RPV wall thickness 6.125 in.

CRPV= 19332 (pr/t)/CRPV = 1.097 <1.15 (3) [p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE< 1.15 p=RPV Normal Operating Pressure 1035 psi ro=nozzle outer radius 12.5 in.

ri=nozzle inner radius 5.784 in.

CNOZZLE 1637

[p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE = 0.977 <1.15 For Recirculation Outlet Nozzles (N1)

(4) (pr/t)/CRPV< 1.15 p=RPV Normal Operating Pressure 1035 psi r=RPV inner radius 125.5 in.

t=RPV wall thickness 6.125 in.

CRPV= 16171 (pr/t)/CRPV = 1.311 >1.15 Note: Requirement not satisfied for the PBAPS N1 Nozzles, which are not included in this relief request.

(5) [p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE< 1.15 p=RPV Normal Operating Pressure 1035 psi ro=nozzle outer radius 26.5 in.

ri=nozzle inner radius 12.97 in.

CNOZZLE 1977

[p(ro2 +ri2)/(ro2-ri2)]/CNOZZLE = 0.853 <1.15

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 9 of 12)

Enclosure 3 PBAPS, Unit 2 Nozzle-to-Vessel and Nozzle Inner Radius Inspection Results The following tables identify the inspection results (Recordable Indications (RI) and No-Recordable Indications (NRI)). All the indications were evaluated as acceptable per ASME Section XI.

Unit Component ID Outage Interval Period Results 2 CH-NA (N6A) 2R14 3 1 NRI 2 CH-NA (N6A) 2R18 4 1 NRI 2 CH-NA-IRS (N6A) 2R14 3 1 NRI 2 CH-NA-IRS (N6A) 2R18 4 1 NRI 2 CH-NC (N6B) 2R14 3 1 NRI 2 CH-NC-IRS (N6B) 2R14 3 1 NRI 2 N2A 2R14 3 1 NRI 2 N2A-IRS 2R14 3 1 NRI 2 N2B 2R14 3 1 NRI 2 N2B-IRS 2R14 3 1 NRI 2 N2C 2R14 3 1 NRI 2 N2C-IRS 2R14 3 1 NRI 2 N2D 2R15 3 2 NRI 2 N2D-IRS 2R15 3 2 NRI 2 N2E 2R16 3 3 NRI 2 N2E-IRS 2R16 3 3 NRI 2 N2F 2R15 3 2 NRI 2 N2F-IRS 2R15 3 2 NRI 2 N2G 2R16 3 3 NRI 2 N2G-IRS 2R16 3 3 NRI 2 N2H 2R15 3 2 NRI 2 N2H-IRS 2R15 3 2 NRI 2 N2J 2R16 3 3 NRI 2 N2J-IRS 2R16 3 3 NRI 2 N2K 2R16 3 3 NRI 2 N2K-IRS 2R16 3 3 NRI 2 N3A 2R17 3 3 NRI 2 N3A-IRS 2R17 3 3 NRI 2 N3B 2R17 3 3 NRI 2 N3B-IRS 2R17 3 3 NRI 2 N3C 2R16 3 3 NRI 2 N3C-IRS 2R16 3 3 NRI 2 N3D 2R16 3 3 NRI 2 N3D-IRS 2R16 3 3 NRI 2 N5A 2R17 3 3 NRI 2 N5A-IRS 2R17 3 3 NRI 2 N5B 2R17 3 3 NRI

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 10 of 12)

Unit Component ID Outage Interval Period Results 2 N5B-IRS 2R17 3 3 NRI 2 N8A 2R14 3 1 NRI 2 N8A-IRS 2R14 3 1 NRI 2 N8B 2R16 3 3 NRI 2 N8B-IRS 2R16 3 3 NRI

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 11 of 12)

Enclosure 3 PBAPS Unit 3, Nozzle-to-Vessel and Nozzle Inner Radius Inspection Results The following tables identify the inspection results (Recordable Indications (RI) and No-Recordable Indications (NRI)). All the indications were evaluated as acceptable per ASME Section XI.

Component Unit ID Outage Interval Period Results Misc.

3 CH-NA 3R13 3 1 NRI (N6A) 3 CH-NA-IRS 3R13 3 1 NRI (N6A) 3 CH-NC 3R13 3 1 NRI (N6B) 3 CH-NC-IRS 3R13 3 1 NRI (N6B) 3 N2A 3R14 3 2 NRI 3 N2A-IRS 3R14 3 2 NRI 3 N2B 3R14 3 2 RI Recordable indications identified - acceptable per ASME Section XI.

3 N2B-IRS 3R14 3 2 NRI 3 N2C 3R14 3 2 NRI 3 N2C-IRS 3R14 3 2 NRI 3 N2D 3R13 3 1 NRI 3 N2D-IRS 3R13 3 1 NRI 3 N2E 3R13 3 1 NRI 3 N2E-IRS 3R13 3 1 NRI 3 N2F 3R13 3 1 NRI 3 N2F-IRS 3R13 3 1 NRI 3 N2G 3R14 3 2 RI Recordable indication identified - acceptable per ASME Section XI.

3 N2G-IRS 3R14 3 2 NRI 3 N2H 3R16 3 3 NRI 3 N2H-IRS 3R16 3 3 NRI 3 N2J 3R16 3 3 NRI 3 N2J-IRS 3R16 3 3 NRI 3 N2K 3R16 3 3 NRI 3 N2K-IRS 3R16 3 3 NRI 3 N3A 3R13 3 1 NRI 3 N3A-IRS 3R13 3 1 NRI 3 N3B 3R13 3 1 NRI 3 N3B-IRS 3R13 3 1 NRI 3 N3C 3R16 3 3 NRI 3 N3C-IRS 3R16 3 3 NRI 3 N3D 3R16 3 3 NRI

Relief Request I4R-52 to Implement an Alternative Concerning Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(a)(3)(i)

(Page 12 of 12)

Component Unit ID Outage Interval Period Results Misc.

3 N3D-IRS 3R16 3 3 NRI 3 N5A 3R14 3 2 NRI 3 N5A-IRS 3R14 3 2 NRI 3 N5B 3R15 3 3 NRI 3 N5B-IRS 3R15 3 3 NRI 3 N8A 3R13 3 1 NRI 3 N8A-IRS 3R13 3 1 NRI 3 N8B 3R16 3 3 NRI 3 N8B-IRS 3R16 3 3 NRI

Retrieved from "https://kanterella.com/w/index.php?title=ML110250147&oldid=2552371"