ML17275A208
| ML17275A208 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/29/2017 |
| From: | Jim Barstow Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-17-0093 | |
| Download: ML17275A208 (10) | |
Text
Exelon JAFP-17-0093 September 29, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRG Docket No. 50-333 200 rxelon Way Ke Square. PA. 19348 exeloncc r p.com 10 CFR 50.55a
Subject:
Submittal of Relief Request [[::JAF-15R-05|JAF-15R-05]] Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702) In accordance with 1 O CFR 50.55a, "Codes and standards," paragraph (z)(1 ), 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 lnservice Inspection of Nuclear Power Plant Components." Relief Request [[::JAF-15R-05|JAF-15R-05]] proposes an alternative to the requirements contained in Table IWB-2500-1 concerning nozzle-to-vessel weld and nozzle inner radii examination requirements.
We request your review and approval by September 10, 2018. No regulatory commitments are contained in this letter. Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.
Sincerely, James Barstow Director -Licensing
& Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Relief Request [[::JAF-15R-05|JAF-15R-05]] to Utilize ASME Code Case N-702 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, JAFNPP Project Manager [JAFNPP] USNRC Attachment Relief Request [[::JAF-15R-05|JAF-15R-05]] to Utilize ASME Code Case N-702 Relief Request [[::JAF-ISR-05|JAF-ISR-05]] to Utilize ASME Code Case N-702 in Accordance with 10 CFR 50.55a(z)(1) (Page 1 of 8) 1. ASME CODE COMPONENTS AFFECTED Code Class: 1 Component Numbers: See Enclosure 1 for complete list of nozzle identifications Examination Category:
8-D Item Number: 83.90 and 83.100
Description:
Alternative to ASME Section XI, Table IWB-2500-1
- 2. APPLICABLE CODE EDITION AND ADDENDA The fifth 10-year lnservice Inspection (ISi) program at the James A. FitzPatrick Nuclear Power Plant (JAFNPP) is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (8&PV) Code,Section XI, 2007 Edition through the 2008 Addenda. Additionally, for ultrasonic examinations, ASME Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the Section XI, 2007 Edition through the 2008 Addenda is implemented.
- 3. APPLICABLE CODE REQUIREMENTS The applicable requirements are contained in Table IW8-2500-1, "Examination Category 8-D, Full Penetration Welded Nozzles in Vessels." Class 1 nozzle-to-vessel weld and nozzle inner radii examination requirements are delineated in Item Number 83.90, "Nozzle-to-Vessel Welds," and 83.100, "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.
Additionally, for ultrasonic examinations, ASME Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," is implemented.
All of the nozzle assemblies identified in Enclosure 1 are full penetration welds. The plant, interval, ASME Section XI Code Edition and Addenda, interval start date and interval end date are provided in the table below. PLANT INTERVAL EDITION START END James A. FitzPatrick Nuclear 2007 Edition, through Power Plant Fifth 2008 Addenda August 1, 2017 June 15, 2027 This relief request will remain in effect for the remainder of the 10-year intervals and the remaining term of JAFNPP renewed operating license, which currently expires on October 17, 2034.
Relief Request [[::JAF-15R-05|JAF-15R-05]] to Utilize ASME Code Case N-702 in Accordance with 1 O CFR 50.55a(z)(1) (Page 2 of 8) 4. REASON FOR REQUEST NRC Regulatory Guide 1.147, Revision 17 conditionally accepts the use of Code Case N-702. This code case provides an alternative to performing examination of 100% of the vessel welds and inner radii for Examination Category 8-D nozzles with the exception of the Feedwater and Control Rod Drive Return Line (CRDRL) nozzles. The alternative is to perform examination of 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, excluding the Feedwater and CRDRL Nozzles. 5. PROPOSED ALTERNATIVE AND BASIS FOR USE In accordance with 10 CFR 50.55a(z)(1
), relief is requested from performing the required examinations on 100 percent of the nozzle assemblies identified in Table 1 below (see Enclosure 1 for the list of Reactor Pressure Vessel (RPV) nozzles applicable to this relief request).
As an alternative, for all welds and inner radii identified in Table 1, Exelon Generation Company, LLC (Exelon) proposes to examine a minimum of 25 percent of the 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 remaining term of the JAFNPP renewed operating license. For the nozzle assemblies identified in Enclosure 1, this would mean 25 percent from each of the groups identified below: Table 1 James A. FitzPatrick Nuclear Power Plant Summary* Identification Description Size Total Minimum Number Inches Number Number to be Examined N1 Recirculation Outlet 28 2 1 N2 Recirculation Inlet 12 10 3 N3 Main Steam Outlet 24 4 1 NS Core Spray 10 2 1 N-TH-A/C Closure Head Instrumentation 6 2 1 N-TH-B Closure Head Vent 4 1 1 NB Jet Pump Instrumentation 4 2 1 *The nozzle-to-vessel weld and inner radius examinations are performed together.
The exams in Table 1 will be scheduled in accordance with Table IWB-2411-1.
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. 83.100, "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 "). If a VT-1 is performed, the conditions specified in Code Case N-648-1 will be utilized.
Exelon will perform either volumetric examination or VT-1 examination of the inner radius as required by Code Case N-702.
Relief Request [[::JAF-ISR-05|JAF-ISR-05]] to Utilize ASME Code Case N-702 in Accordance with 10 CFR 50.55a(z)(1) (Page 3 of 8) 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 1 o-s for 40 years) with or without inservice inspection.
The report concludes that inspection of 25 percent of each nozzle type is technically justified.
EPRI Report BWRVIP-241 received a final NRG Safety Evaluation Report on April 19, 2013 (ML 13071A240).
In the NRG Safety Evaluation Report, Section 5.0, "Conditions and Limitations" indicates that each licensee who plans to request relief from the ASME Code,Section XI requirements for RPV nozzle-to-vessel shell welds and nozzle inner radius sections may reference the BWRVIP-241 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 of the BWRVIP-241 report as discussed below. The analyses in BWRVIP-108 and BWRVIP-241 are based on the assumption that fluence at the nozzles is negligible because the analysis is for the initial 40 years of plant operation.
JAFNPP is starting the 5th interval (extended period of operation);
however, none of the nozzles applicable to this request will exceed a fluence of 1x10 17 and the assumptions used in BWRVIP-108 and BWRVIP-241 regarding fluence remain valid. The analyses in BWRVIP-108 and BWRVIP-241 were based on predicted fatigue crack growth over the initial licensed operating period and assumed additional fatigue cycles in evaluating fatigue crack growth. The probability of failure per reactor year for the nozzle-to-shell-weld and nozzle blend radii in JAFNPP's N2 nozzles are below the acceptance criterion of 5 x 1 o-s per year. An evaluation was performed, which showed that, after consideration of the additional thermal cycles and fluence at the end of the period of extended operation, the N2 nozzles (and thus any other applicable nozzle), are qualified for reduced inspection using ASME Code Case N-702 through the end of the period of extended operation.
Based on the two analyses (BWRVIP-108 and BWRVIP-241), the failure probabilities due to a low temperature overpressure event at the nozzle blend radius region and the vessel shell weld for JAFNPP recirculation inlet and outlet nozzles, and all other nozzles listed in Table 1, are very low and meet the NRG safety goal of 5 x 1 o-6* Regulatory Guide 1.147, Revision 17 conditionally accepts the use of Code Case N-702 with the following condition: "The applicability of Code Case N-702 must be shown by demonstrating that the criteria in Section 5.0 of NRG Safety Evaluation regarding BWRVIP-108 dated December 18, 2007 (ML073600374) or Section 5.0 of NRG Safety Evaluation regarding BWRVIP-241 dated April 19, 2013(ML13071A240) are met." Section 5.0 of the NRG Safety Evaluation for BWRVIP-241 states: Licensees who plan to request relief from the ASME Code,Section XI requirements for RPV nozzle-to-vessel shell welds and nozzle inner radius sections may reference the BWRVIP-241 report as the technical basis for use of ASME Code Case N-702 as an alternative.
Relief Request [[::JAF-15R-05|JAF-15R-05]] to Utilize ASME Code Case N-702 in Accordance with 1 O CFR 50.55a(z)(1) (Page 4 of 8) However, each licensee should demonstrate the plant-specific applicability of the BWRVJP-241 report to their units in the relief request by demonstrating all of the following:
Criterion 1: The maximum RPV heatup/coo/down rate is limited to Jess than 115°F/hour; The JAFNPP Technical Specification Surveillance Requirement 3.4.9.1, limits the maximum heatup and cooldown rates to less than or equal to 100°F in any one hour period and thus meets the requirement of Criterion
- 1. Evaluation of JAFNPP aqainst Criterion 2, 3, 4, and 5 contained in NRC SER for BWRVIP-241 Recirculation Inlet Nozzles (N2) Recirculation Outlet Nozzles (N1) Criterion 2: Criterion 4: (pr/t)/CRPv:S,1
.15 (pr/t)/CRPV
- £ 1.15 p = RPV normal operating 1040 psig p = RPV normal operating 1040 psig pressure pressure r = RPV inner radius 110.375" r = RPV inner radius 110.375" t = RPV wall thickness 6.875" t = RPV wall thickness 6.875" Ci-RPV 19332 Co-RPV 16171 0.86 < 1.15 1.03 < 1.15 Criterion 3: Criterion 5: [p(ro 2 + r?) I (ro 2 -n 2)]/CNOZZLE s 1.47 [p(ro 2 + r?) I (ro 2 -r?)]/CNoZZLE S 1.59 p = RPV normal operating 1040 psig p = RPV normal operating 1040 psig pressure pressure r o = nozzle outer radius 10.22" ro =nozzle outer radius 21.66" n = nozzle inner radius 6.19" n = nozzle inner radius 12.69" Ci-NOZZLE 1637 Co-NOZZLE 1977 1.37 < 1.47 1.08 < 1.59 Based on the above information, all JAFNPP RPV nozzle-to-vessel shell penetration welds and nozzle inner radii sections meet the general and nozzle-specific criteria in BWRVIP-241.
Therefore, ASME Code Case N-702 is applicable.
Relief Request [[::JAF-15R-05|JAF-15R-05]] to Utilize ASME Code Case N-702 in Accordance with 10 CFR 50.55a(z)(1) (Page 5 of 8) The results of the last examination performed on each nozzle-to-vessel weld and nozzle inner radii are included in Enclosure
- 1. ASME Code Case N-702 provides an acceptable level of quality and safety in accordance with 1 O CFR 50.55a(z)(1) for the RPV nozzle-to-vessel shell full penetration welds and nozzle inner radii section. 6. DURATION OF PROPOSED ALTERNATIVE This relief request will remain in effect for the remainder of the 10-year intervals and the remaining term of the renewed operating license, which currently expires on October 17, 2034. 7. PRECEDENTS
- 1. "Columbia Generating Station -Relief Request for Alternative 41Sl-04 Applicable to the Fourth 10-Year lnservice Inspection Program Interval (CAC No. MF7331)," October 5, 2016 (ML 16263A233)
- 2. "LaSalle County Station, Units 1 and 2, Relief from the Requirements of the ASME Code RE: RR 13R-14, Proposed Alternative To The Examination Requirements For Vessel Welds and Inner Radii Sections in Accordance with 10 CFR 50.55a(z)(1) (TAC Nos. MF5654 and MF5655)," October 30, 2015(ML15226A412}
Nozzle ID Nozzle-to-Vessel (NV) Inner Radius (IR} N1A (NV) N1A (IR} N18 (NV} N18 (IR) N2A (NV) N2A (IA) N28 (NV) N28 (IA) N2C (NV) N2C (IA) N2D (NV) N2D (IR) N2E (NV) N2E (IR) N2F (NV} N2F (IR) N2G (NV) N2G (IA) N2H (NV) Relief Request [[::JAF-ISR-05|JAF-ISR-05]] to Utilize ASME Code Case N-702 in Accordance with 10 CFR 50.55a(z)(1) (Page 6 of 8) Enclosure 1 Applicable James A. FitzPatrick Nuclear Power Plant Nozzles CategoQL Item Nominal Pige Number Number System Size (Inches) 8-D 83.90 Recirculation (Outlet) 28 8-D 83.100 Recirculation (Outlet) 28 8-D 83.90 Recirculation (Outlet) 28 8-D 83.100 Recirculation (Outlet) 28 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 Last AQQendix VI 11 Examination Results Exam RF0-17 Accept Yes RF0-17 Accept Yes RF0-20 Accept Yes RF0-20 Accept Yes AF0-13 Accept No 1 RF0-13 Accept No 1 RF0-18 Accept Yes RF0-18 Accept Yes AF0-17 Accept Yes RF0-17 Accept Yes AF0-17 Accept Yes RF0-17 Accept Yes RF0-18 Accept Yes RF0-18 Accept Yes RF0-18 Accept Yes RF0-18 Accept Yes RF0-17 Accept Yes RF0-17 Accept Yes RF0-20 Accept Yes Nozzle ID Nozzle-to-Vessel (NV) Inner Radius (IA) N2H (IA) N2J (NV) N2J (IA) N2K (NV) N2K (IA) N3A (NV) N3A (IA) N38 (NV) N38 (IA) N3C (NV) N3C (IA) N3D (NV) N3D (IA) NSA (NV) NSA (IA} N58 (NV) N58 (IA) N-TH-A (NV) N-TH-A {IA) Relief Request [[::JAF-15R-05|JAF-15R-05]] to Utilize ASME Code Case N-702 in Accordance with 1 O CFR 50.55a(z)(1) (Page 7 of 8) Enclosure 1 Applicable James A. FitzPatrick Nuclear Power Plant Nozzles Catego!Y Item Nominal PiQe System Number Number Size (Inches} 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Recirculation (Inlet) 12 8-D 83.100 Recirculation (Inlet) 12 8-D 83.90 Main Steam 24 8-D 83.100 Main Steam 24 8-D 83.90 Main Steam 24 8-D 83.100 Main Steam 24 8-D 83.90 Main Steam 24 8-D 83.100 Main Steam 24 8-D 83.90 Main Steam 24 8-D 83.100 Main Steam 24 8-D 83.90 Core Spray 10 8-D 83.100 Core Spray 10 8-D 83.90 Core Spray 10 8-D 83.100 Core Spray 10 8-D 83.90 Head Instrumentation 6 8-D 83.100 Head Instrumentation 6 Last AQpendix VIII Results Examination Exam RF0-20 Accept Yes RF0-17 Accept Yes RF0-17 Accept Yes RF0-20 Accept Yes RF0-20 Accept Yes RF0-17 Accept Yes RF0-17 Accept Yes RF0-17 Accept Yes RF0-17 Accept Yes RF0-13 Accept No 1 RF0-13 Accept No 1 RF0-18 Accept Yes RF0-18 Accept Yes RF0-18 Accept Yes RF0-18 Accept Yes RF0-17 Accept Yes RF0-17 Accept Yes RF0-18 Accept Yes RF0-18 Accept Yes Nozzle ID Nozzle-to-Vessel (NV) Inner Radius (IR) N-TH-C (NV) N-TH-C (IR) N-TH-8 (NV) N-TH-8 (IR) NBA (NV) NBA (IR) NB8 (NV) NB8 (IR) Relief Request [[::JAF-ISR-05|JAF-ISR-05]] to Utilize ASME Code Case N-702 in Accordance with 1 O CFR 50.55a(z)(1) (Page 8 of 8) Enclosure 1 Applicable James A. FitzPatrick Nuclear Power Plant Nozzles Catego!'.Y Item Nominal Pige Number Number System Size {Inches} 8-0 83.90 Head Instrumentation 6 8-D 83.100 Head Instrumentation 6 8-D 83.90 Head Vent 4 8-D 83.100 Head Vent 4 8-0 83.90 Jet Pump 4 Instrumentation 8-D 83.100 Jet Pump 4 Instrumentation 8-D 83.90 Jet Pump 4 Instrumentation 8-D 83.100 Jet Pump 4 Instrumentation Last Examination Results RF0-17 Accept RF0-17 Accept RF0-22 Accept RF0-22 Accept RF0-17 Accept RF0-17 Accept RF0-1B Accept RF0-1B Accept Note: (1) These nozzles have not had an Appendix VIII examination.
The specific nozzles will be included in the selected nozzles for examination during the 5th ISi interval.
Aggendix VI 11 Exam Yes Yes Yes Yes Yes Yes Yes Yes