PLA-6847, Proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program

Proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program

ML12115A200
Person / Time
Site:	Susquehanna
Issue date:	04/24/2012
From:	Helsel J Susquehanna
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
PLA-6847
Download: ML12115A200 (13)

Text

Jeffrey M. Helsel PPLSusquehanna,LLC Nuclear Plant Manager 769 Salem Boulevard Berwick, P A 18603 Tel. 570.542.3510 Fax 570.542.1504 jmhelsel@ pplweb.com U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Stop 0-Pl-17 Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED RELIEF REQUEST NO. 3RR-19 TO THE THIRD 10-YEAR INSERVICE INSPECTION PROGRAM FOR SUSQUEHANNA SES UNITS 1 AND 2 Docket No. 50-387 PLA-6847 and No. 50-388 PPL Susquehanna, LLC (PPL) requests approval of proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program for Susquehanna SES Units 1 and 2.

This proposed relief request requests the use of ASME Code Case N-702.

Pursuant to 10CFR50.55a(a)(3)(i) relief is requested from the requirements of the ASME Section XI, 1998 Edition, 2000 Addenda, Code Category B-D, Item Nos. B3.90 and B3.100 on the basis that the proposed alternative will provide an acceptable level of quality and safety.

In accordance with ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds" and the Boiling Water Reactor Vessel Internals Project (BWRVIP) report BWRVIP-108, "BWR Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," report BWRVIP-108, PPL Susquehanna, LLC requests relief from examination of 100% of the inlet nozzles under Examination Category B-D, Item Nos. B3.90 and B3.100 to a minimum of 25% of the nozzle inner-radii and nozzle-to-shell welds, including at least one nozzle from each system and nominal pipe size.

As an alternative, for all welds and nozzle inner radius section, PPL proposes to examine a minimum of 25% of the nozzle-to-vessel shell welds and nozzle inner radius section to include at least one nozzle from each system and nominal pipe size, in accordance with Code Case N-702.

PPL Susquehanna, LLC requests that this relief request be approved by June 1, 2012, in order to support the Unit 2 16th Refuel Outage Planning milestone date.

2 Document Control Desk PLA-6847 If you have any questions or require additional information, please contact Ms. Brenda O'Rourke (570) 542-1791.

Sincerely, C)~~dd~

J. M. Helsel

Attachment:

Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program for Susquehanna SES Units 1 and 2 Copy: NRC Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. R. R. Janati, DEP/BRP Ms. C. J. Sanders, NRC Project Manager

ATTACHMENT TO PLA-6847 RELIEF REQUEST NO. 3RR-19 TO THE THIRD 10-YEAR INSERVICE INSPECTION PROGRAM FORSUSQUEHANNASESUNITS1AND2

Attachment to PLA-6847 Page 1 of 10 RELIEF REQUEST NO. 3RR-19 TO THE THIRD 10-YEAR INSERVICE INSPECTION PROGRAM FOR SUSQUEHANNA SES UNITS 1 AND 2 Component Identification:

Code Class: 1 Examination Category: B-D Item Numbers: B3.90 and B3.100

==

Description:==

Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds" and the Boiling Water Reactor Vessel Internals Project (BWRVIP) report BWRVIP-108, "BWR Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii" Component Numbers: Reactor Nozzle Assemblies as defined below in Table 1.

TABLEt Affected Components Component ASME ASME Description Category Item Number N1AIR B-D B3.100 NOZ-IR N1BIR B-D B3.100 NOZ-IR N2AIR B-D B3.100 NOZ-IR N2BIR B-D B3.100 NOZ-IR N2CIR B-D B3.100 NOZ-IR N2DIR B-D B3.100 NOZ-IR N2EIR B-D B3.100 NOZ-IR N2FIR B-D B3.100 NOZ-IR N2GIR B-D B3.100 NOZ-IR N2HIR B-D B3.100 NOZ-IR N2JIR B-D B3.100 NOZ-IR N2KIR B-D B3.100 NOZ-IR N3AIR B-D B3.100 NOZ-IR N3BIR B-D B3.100 NOZ-IR

Attachment to PLA-6847 Page 2 of 10 Component ASME ASME Description Category Item Number N3CIR B-D B3.100 NOZ-IR N3DIR B-D B3.100 NOZ-IR N5AIR B-D B3.100 NOZ-IR N5BIR B-D B3.100 NOZ-IR N6AIR B-D B3.100 NOZ-IR N6BIR B-D B3.100 NOZ-IR N7 IR B-D B3.100 NOZ-IR N8AIR B-D B3.100 NOZ-IR N8BIR B-D B3.100 NOZ-IR NlA B-D B3.90 NOZ-SCl NlB B-D B3.90 NOZ-SCl N2A B-D B3.90 NOZ-SCl N2B B-D B3.90 NOZ-SCl N2C B-D B3.90 NOZ-SCl N2D B-D B3.90 NOZ-SCl N2E B-D B3.90 NOZ-SCl N2F B-D B3.90 NOZ-SCl N2G B-D 133.90 NOZ-SCl N2H B-D B3.90 NOZ-SCl N2J B-D B3.90 NOZ-SCl N2K B-D B3.90 NOZ-SCl N3A B-D B3.90 NOZ-SC5 N3B B-D B3.90 NOZ-SC5 N3C B-D B3.90 NOZ-SC5 N3D B-D B3.90 NOZ-SC5 N5A B-D B3.90 NOZ-SC3 N5B B-D B3.90 NOZ-SC3 N6A B-D B3.90 TPHEAD-NOZ N6B B-D B3.90 TPHEAD-NOZ N7 B-D B3.90 TPHEAD-NOZ N8A B-D B3.90 NOZ-SCl N8B B-D B3.90 NOZ-SCl Applicable ASME Code Edition and Addenda:

The Susquehanna Steam Electric Station is currently in its Third 10-Year Inservice Inspection interval and is required to follow the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for Inservice

Attachment to PLA -6847 Page 3 of 10 Inspection of Nuclear Power Plant Components, (ASME Section XI), 1998 edition through the 2000 Addenda.

Code Requirement:

ASME Section XI, Table IWB-2500, Category B-D, Item No. 3.90 requires examination of 100% of nozzles with full penetration welds to vessel shell (or head) and integrally cast nozzles. In addition, Table IWB-2500-1, Category B-D, Item No. B3.100 requires examination of the inner radius of these same nozzles.

Basis for Relief:

Pursuant to 10CFR50.55a(a)(3)(i) relief is requested from the requirements of the ASME Section XI, 1998 Edition, 2000 Addenda, Code Category B-D, Item Nos. B3.90 and B3.100 on the basis that the proposed alternative will provide an acceptable level of quality and safety.

In accordance with ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds" and the Boiling Water Reactor Vessel Internals Project (BWRVIP) report BWRVIP-108, "BWR Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," report BWRVIP-108, PPL Susquehanna, LLC requests relief from examination of 100% of the inlet nozzles identified in Table 1 above under Examination Category B-D, Item Nos.

B3.90 and B3.100 to a minimum of 25% of the nozzle inner-radii and nozzle-to-shell welds, including at least one nozzle from each system and nominal pipe size.

Proposed Alternative Examinations:

Pursuant to 10CFR50.55a(a)(3)(i), relief is requested from performing the required examinations on 100% of the identified nozzle assemblies identified in Table 1. As an alternative, for all welds and nozzle inner radius section identified in Table 1, PPL Susquehanna, LLC proposes to examine a minimum of 25% of the nozzle-to-vessel shell welds and nozzle inner radius section to include at least one nozzle from each system and nominal pipe size, in accordance with Code Case N-702. For the nozzle assemblies indentified this would mean that PPL Susquehanna, LLC would perform the number of examinations identified in Table 2 below:

Attachment to PLA-6847 Page 4 of 10 Table 2 Summary of SSES Reactor Vessel Nozzles for Unit 1 and Unit 2 Component ID Total Number of Nozzles Total Number to be Examined*

Recirculation Outlet-N1 2 2 (does not pass criteria)

Recirculation Inlet-N2 10 3 Main Steam-N3 4 1 Feedwater-N4 (not 6 6 allowed by Code Case)

Core Spray-N5 2 1 Head Nozzles N6 & N7 3 1 Jet Pump-N8 2 1 CRD Return-N9 (not 1 1 allowed by Code Case)

• Code Case N-702 stipulates that the VT-1 examination may be used in lieu of the volumetric examination for the nozzle inner radius sections (Code Item B3.100).

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

Boiling Water Reactor Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirement for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," provides the bases for the use of Code Case N-702. The evaluation found that failure probabilities at the nozzle blend radius region and nozzle-to-vessel shell welds due to a Low Temperature Overpressure event are very low (Less than 1E-6 for 40 years) with or without inservice inspection. The report concludes that inspection of 25% of each nozzle type is technically justified.

The Nuclear Regulatory Commission issued a Safety Evaluation Report (SER) dated December 19, 2007 approving the use of BWRVIP-108 as a basis for using Code Case N-702. In the SER, Section 5.0, "Plant Specific Applicability" states that licensees who plan to request relief from the ASME Code Section XI requirements for reactor pressure vessel (RPV) nozzle-to-shell welds and nozzle inner radius 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 for the BWRVIP-108 report to its units in the relief request by showing that all the general and nozzle specific criteria are satisfied:

Attachment to PLA-6847 Page 5 of 10 Maximum RPV Heatup/Cooldown Rate (1) the maximum RPV heatup/cooldown rate is limited to less than 115°F The reactor heatup/cooldown rate for Susquehanna is limited to 100°F per Technical Specifications Section 3.4.10.

For recirculation inlet nozzles (N2-Nozzles, Criteria (2) and (3) of the SER apply):

(2) (pr/t)/CRPv<1.15 where:

p=RPV normal operating pressure (1035 psig) r=RPV inner radius (126.5 inches based upon diameter provided in Table 3-1 of BWRVIP-108) t=RPV wall thickness (6.16 inches per Table 3-1 of BWRVIP-108)

CRPv=19332(per BWRVIP-108)

The PPL result is 1.10, which meets the criteria of being less than 1.15; therefore criterion 2 is met.

(3) [p(ro2 + ri2)/(ro2 - ri2 )]/Cnozzle <1.1 5 w h .

ere.

p=RPV normal operating pressure ( 1035 psig) ri=N2 nozzle inner radius (11.625 inches) r 0 = N2 nozzle outer radius (26.125 inches)

Cnozzle- 1637 per BWRVIP-108 The PPL result is 0.944, which meets the criteria of being less than 1.15; therefore criterion 3 is met. With both criteria 2 and 3 being met, the recirculation inlet nozzles are bound by Code Case N-702 and BWRVIP-108.

For recirculation outlet nozzles (N1-Nozzles, Criteria (4) and (5) of the SER apply):

(4) (pr/t)/CRPv<1.15 where:

p = RPV normal operating pressure (1035 psig) r = RPV inner radius 126.5 inches based upon diameter provided in Table 3-1 of BWRVIP-108) t=RPV wall thickness (6.16 inches per Table 3-1 of BWRVIP-108)

CRPv = 16171 based upon B WRVIP-1 08 recirculation outlet nozzle/RPV FEM model The PPL result is 1.314. This criterion is not met.

2 2 2 (5) (5) [p(ro + ri )/(r0 - r?)J/Cnozzle <1.15 where:

p=RPV normal operating pressure ( 1035 psig) ri~N2 nozzle inner radius (25.832 inches)

Attachment to PLA-6847 Page 6 of 10 r 0 = N2 nozzle outer radius (45.75 inches)

Cnozzle- 1977 per BWRVIP-108 The PPL result is 1.01, which meets the criteria.

Based upon the above information, all RPV nozzle-to-shell welds and nozzle inner radius sections, with the exception of the Recirculation Outlet Nl Nozzles and those that are specifically excluded from the Code Case (N4 and N9 nozzles), meet the criteria.

Therefore, Code Case N-702 is applicable. Since the recirculation outlet nozzles do not meet all of the criteria, Code Case N-702 will not be applied to these nozzles (Nl Nozzles).

Table 3 Completed Nozzle Exams for Third 10-Year Inspection Interval Unitl Code Code Inspection Inspection Category Item Component Description Outage Date Method Ul-B-D B3.90 NlA NOZ-SCl 14RIO 3/9/2006 UT Ul-B-D B3.100 NlAIR NOZ-IR 14RIO 3/8/2006 UT Ul-B-D B3.90 NIB NOZ-SCl 14RIO 3/8/2006 UT Ul-B-D B3.100 NlBIR NOZ-IR 14RIO 3/8/2006 UT Ul-B-D B3.90 N2A NOZ-SCl 14RIO 3/13/2006 UT Ul-B-D B3.100 N2AIR NOZ-IR 14RIO 3/13/2006 UT Ul-B-D B3.90 N2F NOZ-SCl 14RIO 3/15/2006 UT Ul-B-D B3.100 N2FIR NOZ-IR 14RIO 3/15/2006 UT Ul-B-D B3.90 N3A NOZ-SC5 15RIO 3/18/2008 UT Ul-B-D B3.100 N3AIR NOZ-IR 15RIO 3/18/2008 UT Ul-B-D B3.90 N3B NOZ-SC5 15RIO 3/17/2008 UT Ul-B-D B3.100 N3BIR NOZ-IR 15RIO 3/18/2008 UT

Attachment to PLA-6847 Page 7 of 10 Code Code Inspection Inspection Category Item Component Description Outage Date Method U1-B-D B3.90 N3C NOZ-SC5 15RIO 3/17/2008 UT U1-B-D B3.100 N3CIR NOZ-IR 15RIO 3/17/2008 UT U1-B-D B3.90 N3D NOZ-SC5 15RIO 3/17/2008 UT U1-B-D B3.100 N3DIR NOZ-IR 15RIO 3/17/2008 UT U1-B-D B3.90 N4A NOZ-SC3 14RIO 3/14/2006 UT U1-B-D B3.100 N4AIR NOZ-IR 14RIO 3/10/2006 UT U1-B-D B3.90 N4B NOZ-SC3 14RIO 3/11/2006 UT U1-B-D B3.100 N4BIR NOZ-IR 14RIO 3/11/2006 UT U1-B-D B3.90 N4C NOZ-SC3 14RIO 3/10/2006 UT U1-B-D B3.100 N4CIR NOZ-IR 14RIO 3/10/2006 UT U1-B-D B3.90 N4D NOZ-SC3 14RIO 3/11/2006 UT U1-B-D B3.100 N4DIR NOZ-IR 14RIO 3/11/2006 UT U1-B-D B3.90 N4E NOZ-SC3 14RIO 3/11/2006 UT U1-B-D B3.100 N4EIR NOZ-IR 14RIO 3/11/2006 UT U1-B-D B3.90 N4F NOZ-SC3 14RIO 3/11/2006 UT Ul-B-D B3.100 N4FIR NOZ-IR 14RIO 3/10/2006 UT TPHEAD- U1-B-D B3.90 N6A NOZ 15RIO 3/24/2008 UT U1-B-D B3.100 N6AIR NOZ-IR 15RIO 3/24/2008 UT TPHEAD- U1-B-D B3.90 N6B NOZ 15RIO 3/24/2008 UT U1-B-D B3.100 N6BIR NOZ-IR 15RIO 3/24/2008 UT

Attachment to PLA-6847 Page 8 of 10 Code Code Inspection Inspection Category Item Component Description Outage Date Method TPHEAD- U1-B-D B3.90 N7 NOZ 15RIO 3/24/2008 UT U1-B-D B3.100 N7 IR NOZ-IR 15RIO 3/24/2008 UT U1-B-D B3.90 N8A NOZ-SC1 15RIO 3/22/2008 UT U1-B-D B3.100 N8AIR NOZ-IR 15RIO 3/22/2008 UT U1-B-D B3.90 N8B NOZ-SC1 15RIO 3/21/2008 UT U1-B-D B3.100 N8BIR NOZ-IR 15RIO 3/23/2008 UT U1-B-D B3.90 N9 NOZ-SC3 15RIO 3/15/2008 UT U1-B-D B3.100 N9 IR NOZ-IR 15RIO 3/15/2008 UT Table 4 Completed Nozzle Exams for Third 10-Year Inspection Interval Unit2 Code Code Inspection Category Item Component Description Outage Inspection Date Method B-D B3.90 N1A NOZ-SC1 U2-13RIO 3/11/2007 UT B-D B3.100 NlAIR NOZ-IR U2-13RIO 3/11/2007 UT B-D B3.90 N2A NOZ-SC1 U2-13RIO 3/15/2007 UT B-D B3.100 N2AIR NOZ-IR U2-13RIO 3/15/2007 UT B-D B3.90 N2F NOZ-SC1 U2-13RIO 3/15/2007 UT B-D B3.100 N2FIR NOZ-IR U2-13RIO 3/15/2007 UT B-D B3.90 N2J NOZ-SC1 U2-13RIO 3/17/2007 UT B-D B3.100 N2JIR NOZ-IR U2-13RIO 3/17/2007 UT B-D B3.90 N2K NOZ-SC1 U2-13RIO 3/15/2007 UT B-D B3.100 N2KIR NOZ-IR U2-13RIO 3/15/2007 UT B-D B3.90 N3A NOZ-SC5 U2-15RIO 4/15/2011 UT B-D B3.100 N3AIR NOZ-IR U2-15RIO 4/15/2011 UT B-D B3.90 N3B NOZ-SC5 U2-15RIO 4/15/2011 UT B-D B3.100 N3BIR NOZ-IR U2-15RIO 4/15/2011 UT B-D B3.90 N3C NOZ-SC5 U2-15RIO 4/16/2011 UT B-D B3.100 N3CIR NOZ-IR U2-15RIO 4/16/2011 UT

Attachment to PLA-6847 Page 9 of 10 Code Code Inspection Category Item Component Description Outage

• Inspection Date Method B-D B3.90 N3D NOZ-SC5 U2-15RIO 4/16/2011 UT B-D B3.100 N3DIR NOZ-IR U2-15RIO 4/16/2011 UT B-D B3.90 N4A NOZ-SC3 U2-13RIO 3/11/2007 UT B-D B3.100 N4AIR NOZ-IR U2-13RIO 3/11/2007 UT B-D B3.90 N4B NOZ-SC3 U2-13RIO 3/11/2007 UT B-D B3.100 N4BIR NOZ-IR U2-13RIO 3/11/2007 UT B-D B3.90 N4C NOZ-SC3 U2-13RIO 3/11/2007 UT B-D B3.100 N4CIR NOZ-IR U2-13RIO 3/11/2007 UT B-D B3.90 N4D NOZ-SC3 U2-13RIO 3/11/2007 UT B-D B3.100 N4DIR NOZ-IR U2-13RIO 3/11/2007 UT B-D B3.90 N4E NOZ-SC3 U2-13RIO 3/15/2007 UT B-D B3.100 N4EIR NOZ-IR U2-13RIO 3/15/2007 UT B-D B3.90 N4F NOZ-SC3 U2-13RIO 3/15/2007 UT B-D B3.100 N4FIR NOZ-IR U2-13RIO 3/15/2007 UT TPHEAD-B-D B3.90 N7 NOZ U2-14RIO 4/20/2009 UT B-D B3.100 N7IR NOZ-IR U2-14RIO 4/20/2009 UT B-D B3.90 N8A NOZ-SC1 U2-14RIO 4/24/2009 UT B-D B3.100 N8AIR NOZ-IR U2-14RIO 4/24/2009 UT B-D B3.90 N8B NOZ-SC1 U2-12RIO 3/7/2005 UT B-D B3.90 N8B NOZ-SC1 U2-14RIO 4/25/2009 UT B-D B3.100 N8BIR NOZ-IR U2-12RIO 3/7/2005 UT B-D B3.100 N8BIR NOZ-IR U2-14RIO 4/25/2009 UT B-D B3.90 N9 NOZ-SC3 U2-14RIO 4/19/2009 UT B-D B3.100 N9IR NOZ-IR U2-14RIO 4/19/2009 UT Comparing the examination completion information in Table 3 (Unit 1) and Table 4 (Unit 2) against the 25% examination requirement of Code Case N-702, the following summation can be made. For the remainder of the third 10-year Inservice Inspection Interval, PPL Susquehanna, LLC will complete the following nozzle examinations:

Attachment to PLA-6847 Page 10 of 10 For Unit 1 Weld Description Examination Method .

Recirculation Inlet Nozzle to Shell Weld UT N2(x)

Recirculation Inlet Nozzle IR Weld VT-1 N2(x)

Core Spray N5(x) Nozzle to Shell Weld UT Core Spray N5(x) Nozzle IR Weld VT-1 For Unit 2 Weld *. Description Examination Method Recirculation Outlet Nozzle to Shell Weld UT N1B Recirculation Outlet Nozzle IR Weld VT-1 N1B Core Spray N5(x) Nozzle to Shell Weld UT Core Spray N5(x) Nozzle IR Weld VT-1 The use of Code Case N-702 provides an acceptable level of quality and safety pursuant to 10CFR50.55a(a)(3)(i) for all RPV nozzle-to-vessel shell welds and nozzle inner radius section, with the exception of the Recirculation Outlet Nozzles.

Applicable Time Period:

Relief is requested for the remainder of the third ten-year inspection interval of the Inservice Inspection Program for SSES Units 1 and 2.