RA-21-0249, Subsequent License Renewal Application Supplement 1
| ML21302A208 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/28/2021 |
| From: | Snider S Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-21-0249 | |
| Download: ML21302A208 (170) | |
Text
Steven M. Snider Vice President Oconee Nuclear Station RA-21-0249 October 28, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, Maryland 20852
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Oconee Nuclear Station (ONS), Units 1, 2, and 3 Docket Numbers 50-269, 50-270, 50-287 Renewed License Numbers DPR-38, DPR-47, DPR-55 Subsequent License Renewal Application Supplement 1
References:
Duke Energy ON01VP l 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3478 f: 864.873.5791 Steve.Snider@duke-energy.com 10 CFR 50.4 10 CFR Part 54
- 1. Duke Energy Letter (RA-21-0132) dated June 7, 2021, Application for Subsequent Renewed Operating Licenses, (ADAMS Accession Number ML21158A193)
- 2. NRC Letter dated July 22, 2021, Oconee Nuclear Station, Units 1, 2, and 3 - Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding Duke Energy Carolinas Application for Subsequent License Renewal (ADAMS Accession Number ML21194A245)
- 3. NRC Letter dated July 23, 2021, Oconee Nuclear Station, Units 1, 2, and 3 - Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review, (ADAMS Accession Number ML21196A076)
Ladies and Gentlemen:
By letter dated June 7, 2021 (Reference 1), Duke Energy Carolinas, LLC (Duke Energy) submitted an application for the subsequent license renewal of Renewed Facility Operating License Numbers DPR-38, DPR-47, and DPR-55 for the Oconee Nuclear Station (ONS), Units 1, 2, and 3 to the U.S. Nuclear Regulatory Commission (NRC). On July 22, 2021 (Reference 2), the NRC determined that ONS subsequent license renewal application (SLRA) was acceptable and sufficient for docketing. By letter dated July 23, 2021 (Reference 3), the NRC issued the regulatory audit plan for the aging management portion of the SLRA review. During the audit being conducted July 26, 2021 - October 8, 2021, Duke Energy agreed to supplement the SLRA with new or clarifying information. This letter provides the NRC staff with additional information in support of the development of the safety evaluation report.
The Enclosure to this letter provides the index of topics to be supplemented. For each Attachment to this letter, changes are described along with the affected section(s), page number(s), and affected document mark-ups. For clarity, deletions are indicated by strikethrough and inserted text by underlined red font. Also, there are three commitment changes provided in Table A6.0-1 for Attachments 9, 16 and 17.
U.S. Nuclear Regulatory Commission October 28, 2021 Page 2 Should you have any questions regarding this submittal, please contact Paul Guill at (704) 382-4753 or by email at paul.guill@duke-energy.com.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October 28, 2021.
Sincerely, Steven M. Snider Site Vice President Oconee Nuclear Station
Enclosure:
Enclosure:
Index of Attachment Topics Involving SLRA Supplement Attachments:
Resolution of Administrative Discrepancies :
Clarification of Reactor Pressure Vessel Extended Beltline Welds and Shell Components :
Correction of Aging Management Review Line Items Associated with Buried Stainless Steel Piping and Valves :
Clarification of Underground Environment for the Diesel Engine Fuel Oil Storage Tank :
Update to add aging effects and a Raw Water (Internal) Environment :
Update to the Chlorine Tank Aging Management Review :
Update to NUREG-2191 Consistency Statement for Water Chemistry Aging Management Program :
Update to Steam Generator component Aging Management Review line items for the Water Chemistry Aging Management Program :
Caulking/Sealant of Outdoor and Large Atmospheric Metallic Storage Tanks Program 0:
Update of SLRA Table 3.1.2-4, Reactor Vessel, Reactor Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation 1:
Revision to SLRA Tables 2.3.1-4 and 3.1.2-4 2:
Update to Appendix B2.1.10 Program Description 3:
Update of HPSW Boundary Drawing to remove CT-5 Sprinkler System 4:
Clarification on the materials of construction of the fire damper assemblies and the applicable aging affects for the fire damper assemblies 5:
Revised Scoping and Screening Determination for the Letdown Coolers 6:
Added training and qualification requirements to Fire Water System Aging Management Program 7:
Added new enhancement to prevent the use of high strength bolting 8:
Resolution of Standard Industry Note B for Copper Alloy > 15% Zinc 9:
Update to Flow-Accelerated Corrosion Aging Management Program
U.S. Nuclear Regulatory Commission October 28, 2021 Page 3 CC: W/O
Enclosures:
Laura A. Dudes Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Angela X. Wu, Project manager (by electronic mail only)
U.S. Nuclear Regulatory Commission Mail Stop 11 G3 11555 Rockville Pike Rockville, Maryland 20852 Shawn A. Williams, Project Manager (by electronic mail only)
U.S. Nuclear Regulatory Commission Mail Stop 8 B1A 11555 Rockville Pike Rockville, Maryland 20852 Jared Nadel (by electronic mail only)
NRC Senior Resident Inspector Oconee Nuclear Station Anuradha Nair-Gimmi, (by electronic mail only: naira@dhec.sc.gov)
Bureau Environmental Health Services Department of Health & Environmental Control 2600 Bull Street Columbia, South Carolina 29201
U.S. Nuclear Regulatory Commission October 28, 2021 Page 4 BCC: W/O
Enclosures:
T.P. Gillespie K. Henderson S.D. Capps T.M. Hamilton P.V. Fisk H.T. Grant D.A. Wilson M.C. Nolan S.M Snider R.K. Nader G.D. Robison T.M. LeRoy P.F. Guill R.V. Gambrell File: (Corporate)
Electronic Licensing Library (ELL)
ENCLOSURE OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION INDEX OF ATTACHMENT TOPICS INVOLVING SLRA SUPPLEMENTS
INDEX OF ATTACHMENT TOPICS INVOLVING SLRA SUPPLEMENTS Attachment Number Topics 1
Resolution of Administrative Discrepancies 2
Clarification of Reactor Pressure Vessel Extended Beltline Welds and Shell Components 3
Correction of Aging Management Review Line Items Associated with Buried Stainless Steel Piping and Valves 4
Clarification of Underground Environment for the Diesel Engine Fuel Oil Storage Tank 5
Update to add aging effects and a Raw Water (Internal) Environment 6
Update to the Chlorine Tank Aging Management Review 7
Update to NUREG-2191 Consistency Statement for Water Chemistry Aging Management Program 8
Update to Steam Generator component Aging Management Review line items for the Water Chemistry Aging Management Program 9
Caulking/Sealant of Outdoor and Large Atmospheric Metallic Storage Tanks Program 10 Update of SLRA Table 3.1.2-4, Reactor Vessel, Reactor Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation 11 Revision to SLRA Tables 2.3.1-4 and 3.1.2-4 12 Update to Appendix B2.1.10 Program Description 13 Update of HPSW Boundary Drawing to remove CT-5 Sprinkler System 14 Clarification on the materials of construction of the fire damper assemblies and the applicable aging affects for the fire damper assemblies 15 Revised Scoping and Screening Determination for the Letdown Coolers 16 Added training and qualification requirements to Fire Water System Aging Management Program 17 Added new enhancement to prevent the use of high strength bolting 18 Resolution of Standard Industry Note B for Copper Alloy > 15% Zinc 19 Update to Flow-Accelerated Corrosion Aging Management Program
ATTACHMENT 1 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES RESOLUTION OF ADMINISTRATIVE DISCREPANCIES
Resolution of Administrative Discrepancies Affected SLRA Sections:
No SLRA Sections are affected by changes 1 through 8. Portions of the Application for the Renewed Facility Operating License are revised.
SLRA Section 4.2.3 SLRA Appendix A4.2.5 SLRA Page Numbers:
Not Applicable for Changes 1 through 8 4-39 A-60 Description of Change:
The Titles of documents listed on the dividers/separators for Enclosures and Attachments were revised to correct typographical errors. Specifically:
- 1. Revised the title of the document listed in Enclosure 2, Attachment 3 on Page 4 of the cover letter.
- 2. Revised the title of the document listed in Enclosure 2, Attachment 1 on Enclosure Summary page.
- 3. Revised the title of the document listed in Enclosure 2, Attachment 2 on Enclosure Summary page.
- 4. Added document title in Enclosure 2 as Attachment 3 on Enclosure Summary page.
- 5. Revised the title of the document listed in Enclosure 4, Attachment 1 on Enclosure Summary page.
- 6. Revised the title of the document listed in Enclosure 5, Attachment 1 on Enclosure Summary page.
- 7. Revised the title of the document on Enclosure 2, Attachment 3 Divider page.
- 8. Revised the title of the document on Enclosure 5, Attachment 1 Divider page.
Affected application page is revised as follows:
U.S. Nuclear Regulatory Commission June 7, 2021 Page 4
Enclosures:
- Oconee Nuclear Station Subsequent License Renewal Application Enclosure Summary : Application for Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390 : Affidavit for Framatome Topical Reports ANP 3898P, Revision 0 and ANP 3899P, Revision 0 : Framatome Affidavit for SLR-ONS-TLAA-0306P, Revision 0 : Duke Energy Affidavit for SLR-ONS-TLAA-0306P-NP, Revision 0 : Oconee Nuclear Station Subsequent License Renewal Application : Subsequent License Renewal Application (Safety Report) : Subsequent License Renewal Application, Appendix E, Environmental Report : Non-proprietary Reference Documents and a Redacted Version of a Proprietary Reference Document (Public Version) : Framatome Topical Report ANP 3898NP, Revision 0 : Framatome Topical Report ANP 3899NP, Revision 0 : SLR-ONS-TLAA-0306NP, Revision 0 : 10 CFR 2.390 Withheld Proprietary Reference Documents (Non-Public Version) : Framatome Topical Report ANP 3898P, Revision 0 : Framatome Topical Report ANP 3899P, Revision 0 : SLR-ONS-TLAA-0306P, Revision 0
Affected application page is revised as follows:
ENCLOSURE
SUMMARY
Oconee Nuclear Station Subsequent License Renewal Application Enclosure Summary : Application for Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390 : Affidavit for Framatome Topical Reports ANP 3898P, Revision 0 and ANP 3899P, Revision 0 : Framatome Affidavit for SLR-ONS-TLAA-0306P, Revision 0 : Duke Energy Affidavit for SLR-ONS-TLAA-0306P, Revision 0 : Oconee Nuclear Station Subsequent License Renewal Application : Subsequent License Renewal Application (Safety Report) : Subsequent License Renewal Application, Appendix E, Environmental Report : Non-proprietary Reference Documents and a Redacted Version of a Proprietary Reference Document (Public Version) : Framatome Topical Report ANP 3898NP, Revision 0, Framatome Reactor Vessel and RCP TLAA and Aging Management Review Input to the ONS SLRA, May 2021 : Framatome Topical Report ANP 3899NP, Revision 0, Framatome Reactor Vessel Internals TLAA Input to the ONS SLRA, May 2021 : SLR-ONS-TLAA-0306NP, Revision 0, Environmentally-Assisted Fatigue Oconee Subsequent License Renewal Application Supplemental Section 4.3.4 : 10 CFR 2.390 Withheld Proprietary Reference Documents (Non-Public Version) : Framatome Topical Report ANP 3898P, Revision 0,Framatome Reactor Vessel and RCP TLAA and Aging Management Review Input to the ONS SLRA, May 2021 : Framatome Topical Report ANP 3899P, Revision 0, Framatome Reactor Vessel Internals TLAA Input to the ONS SLRA, May 2021 : SLR-ONS-TLAA-0306P, Revision 0, Environmentally-Assisted Fatigue Oconee Subsequent License Renewal Application Supplemental Section 4.3.4
Affected application page is revised as follows:
ENCLOSURE 2 ATTACHMENT 3 OCONEE NUCLEAR STATION DUKE ENERGY AFFIDAVIT FOR SLR-ONS-TLAA-0306P-NP, REVISION 0
Affected application page is revised as follows:
ENCLOSURE 5 ATTACHMENT 1 OCONEE NUCLEAR STATION Framatome Topical Report ANP 3898P, Revision 0, Framatome Reactor Vessel and RCP TLAA and Aging Management Review Input to the ONS SLRA, May 2021 PROPRIETARY INFORMATION - WITHHOLD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390
SLRA Section 4.2.3 (Page 4-39) is revised as follows:
245.1°F (screening criterion of 300°F). For Unit 3, the limiting material is circumferential weld WF-67 with a projected value of RTPTS at 72 EFPY of 240.2°F (screening criterion of 300°F).
The Oconee Units 1, 2, and 3 reactor pressure vessel materials remain below the 10 CFR 50.61 screening criteria at 72 EFPY.
TLAA Disposition: 10 CFR 54.21(c)(1)(ii):
The Oconee Units 1, 2, and 3 PTS analyses, utilizing 10 CFR 50.61 for traditional and extended beltline locations have been projected to the end of the SPEO. Therefore, this TLAA is dispositioned in accordance with 10 CFR 54.21(c)(1)(ii).
SLRA Appendix A4.2.5 (Page A-60) is revised as follows:
A4.2.5 Low Temperature Overpressure Protection overpressure enable temperature and power operated relief valve setpoint will be submitted to the NRC for approval prior to exceeding the period of applicability for Units 1, 2, and 3. Since the low temperature overpressure enable temperature, power operated relief valve setpoint will be updated through the 10 CFR 50.90 process at a later, appropriate date, the effects of aging on the intended function(s) of the Oconee reactor vessels will be adequately managed for the SPEO and are dispositioned in accordance with 10 CFR 50.5454.21(c)(1)(iii).
ATTACHMENT 2 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES CLARIFICATION OF REACTOR PRESSURE VESSEL EXTENDED BELTLINE WELDS AND SHELL COMPONENTS
Clarification of Reactor Pressure Vessel Extended Beltline Welds and Shell Components Affected SLRA Sections:
- 1. SLRA Section 2.3.1.1
- 2. SLRA Table 3.1.2-1
2-50, 2-52, 3-81, 3-99 through 3-109 (includes 2 new pages), 4-12, 4-13, 4-14 Description of Change:
SLRA Table 2.3.1-1 is being revised to include both Beltline Welds and Non-Beltline Welds, fluence information, new note, and new component items and their intended function to address fabrication differences between Unit 1 and Units 2 and 3.
SLRA Table 3.1.2-1 is being revised to update the Notes Column for several line items, to add fluence information, new note, and to include additional line items for new Components to address fabrication differences between Unit 1 and Units 2 and 3. The Components added to the table are:
Non-Beltline Welds Intermediate Shell Plate (Unit 1)
Intermediate Shell Plate (Unit 2 and 3)
Lower Shell Forging (Units 2 and 3)
Lower Shell Plate (Unit 1)
Upper Shell Forging (Units 2 and 3)
Upper Shell Plate (Unit 1)
The phrase Beltline and Extended Beltline in SLRA Section 4.2, (Pages 4-12, -13, and -14) is being revised to read Traditional Beltline and Extended Beltline.
SLRA Table 2.3.1-1 (Page 2-50) is revised as follows:
Since systems share drawings, system flow paths can be depicted on flow diagrams not labeled with the system in the title. This would be an example of a secondary drawing.
To ensure an entire system has been analyzed, both primary and secondary drawings are displayed for the given systems below:
P rimary Drawings OSLRD-100A-1.1 OSLRD-100A-2.1 OSLRD-100A-3.1 Secondary Drawings None The SLR evaluation boundaries of the reactor vessel include the components located within the flow diagram system boundary flags, or as modified by SLR system boundary flags.
C omponents Subject to Aging Management Review The component types subject to AMR are indicated in Table 2.3.1-1, Reactor Vessel.
Table 2.3.1-1 Reactor Vessel Component/Commodity Group Intended Functions Beltline Welds 2)(Note 1)
Pressure Boundary Bottom Head Pressure Boundary Structural Support Closure Head Dome and Flange Pressure Boundary Structural Support Closure Head Lifting Lugs Pressure Boundary Structural Support Closure Head Stud Assembly Pressure Boundary Control Rod Drive Mechanism Closure Insert and Vent Assemblies Pressure Boundary
SLRA Table 2.3.1-1 (Page 2-52) is revised as follows:
Table 2.3.1-1 Reactor Vessel Component/Commodity Group Intended Functions Intermediate Shell Plate (Unit 1)
Pressure Boundary Lower Nozzle Belt Forging Pressure Boundary Lower Shell Forging (Units 2 and 3)
Pressure Boundary Structural Support Lower Shell Plate (Unit 1)
Pressure Boundary Structural Support Non-Beltline Welds (<1E17 n/cm2)
Pressure Boundary Support Skirt Structural Support Transition Forging Pressure Boundary Structural Support Upper Nozzle Belt Forging Pressure Boundary Upper Shell Flange Pressure Boundary Upper Shell Forging (Units 2 and 3)
Pressure Boundary Upper Shell Plate (Unit 1)
Pressure Boundary Vessel Flange Leak Detection Line Structural Integrity Vessel Flange Leak Detection Line Tap Weld Structural Integrity Note 1: The definition of the beltline, including clarification of the traditional and extended beltlines, is provided in Section 4.2.
The AMR results for these component types are indicated in Table 3.1.2-1, Reactor Vessel, Reactor Internals and Reactor Coolant System - Reactor Vessel - Aging Management Evaluation.
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-81) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Beltline Welds n/cm2)
(Note 2)
Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Bottom Head Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.RP-379 3.1.1- 048 A
Cracking of Nickel Alloy Components and Loss of Material due to Boric Acid-Induced Corrosion in RCPB Components (B2.1.5)
IV.A2.RP-379 3.1.1- 048 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Instrument Tubes (bottom head)
Pressure Boundary Nickel Alloy Air with Borated Water Leakage (External)
None None IV.E.RP-378 3.1.1-106 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-59 3.1.1- 045 A
Cracking of Nickel Alloy Components and Loss of Material due to Boric Acid-Induced Corrosion in RCPB Components (B2.1.5)
IV.A2.RP-59 3.1.1- 045 A
Water Chemistry (B2.1.2)
IV.A2.RP-59 3.1.1- 045 A
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Intermediate Shell Plate (Unit 1)
Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Intermediate Shell Plate (Unit 1)
Pressure Boundary Steel (with Stainless Steel Cladding)
Reactor Coolant (Internal)
Cracking Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Lower Nozzle Belt Forging Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 A
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 A
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Lower Nozzle Belt Forging Pressure Boundary Steel (with Stainless Steel Cladding)
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Lower Shell Forging (Units 2 and 3)
Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Steel with Nickel Alloy Cladding Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Lower Shell Forging (Units 2 and 3)
Pressure Boundary Steel with Nickel Alloy Cladding Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Structural Support Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Lower Shell Forging (Units 2 and 3)
Structural Support Steel (with Stainless Steel Cladding)
Reactor Coolant (Internal)
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Steel with Nickel Alloy Cladding Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Lower Shell Forging (Units 2 and 3)
Structural Support Steel with Nickel Alloy Cladding Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Lower Shell Plate (Unit 1)
Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Steel with Nickel Alloy Cladding Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Lower Shell Plate (Unit 1)
Pressure Boundary Steel with Nickel Alloy Cladding Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Structural Support Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation 3
SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Lower Shell Plate (Unit 1)
Structural Support Steel (with Stainless Steel Cladding)
Reactor Coolant (Internal)
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Steel with Nickel Alloy Cladding Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation 3
SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Lower Shell Plate (Unit 1)
Structural Support Steel with Nickel Alloy Cladding Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Non-Beltline Welds
(<1E17 n/cm2)
(Note 2)
Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Support Skirt Structural Support Steel Air - Indoor Uncontrolled (External)
Cumulative Fatigue Damage TLAA IV.A2.R-70 3.1.1- 004 A
Loss of Material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
None None None None J, 1 Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation 108 SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Upper Nozzle Belt Forging Pressure Boundary Steel (with Stainless Steel Cladding)
Reactor Coolant (Internal)
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Upper Shell Flange Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.R-87 3.1.1- 037 A
Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Upper Shell Forging (Units 2 and 3)
Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Upper Shell Forging (Units 2 and 3)
Pressure Boundary Steel (with Stainless Steel Cladding)
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Upper Shell Plate (Unit 1)
Pressure Boundary Steel (with Stainless Steel Cladding)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.A2.R-17 3.1.1- 049 A
Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.A2.RP-55 3.1.1- 047 C
TLAA IV.A2.R-85 3.1.1- 018 A
Water Chemistry (B2.1.2)
IV.A2.RP-55 3.1.1- 047 C
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Upper Shell Plate (Unit 1)
Pressure Boundary Steel (with Stainless Steel Cladding)
Reactor Coolant (Internal)
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Reactor Coolant and Neutron Flux (Internal)
Loss of Fracture Toughness Neutron Fluence Monitoring (B3.2)
IV.A2.RP-229 3.1.1- 014 A
Reactor Vessel Material Surveillance (B2.1.19)
IV.A2.RP-229 3.1.1- 014 B
TLAA IV.A2.R-84 3.1.1- 013 A
Vessel Flange Leak Detection Line Structural Integrity Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
IV.A2.R-74a 3.1.1-139 A
Loss of Material One-Time Inspection (B2.1.20)
IV.C2.R-452a 3.1.1-136 A
Air with Borated Water Leakage (External)
None None IV.E.RP-05 3.1.1-107 A
Reactor Coolant (Internal)
Cracking One-Time Inspection (B2.1.20)
IV.A2.R-74a 3.1.1-139 A
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Vessel Flange Leak Detection Line Tap Weld Structural Integrity Nickel Alloy Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
IV.A2.R-74a 3.1.1-139 A
Table 3.1.2-1 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Reactor Vessel - Aging ManagementEvaluation SLRA Table 3.1.2-1 (Page 3-99 through 109, plus 2 new pages) is revised as follows Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Vessel Flange Leak Detection Line Tap Weld Structural Integrity Nickel Alloy Air - Indoor Uncontrolled (External)
Loss of Material One-Time Inspection (B2.1.20)
IV.C2.R-452a 3.1.1-136 A
Air with Borated Water Leakage (External)
None None IV.E.RP-378 3.1.1-106 A
Reactor Coolant (Internal)
Cracking One-Time Inspection (B2.1.20)
IV.A2.R-74a 3.1.1-139 A
Cumulative Fatigue Damage TLAA IV.A2.R-219 3.1.1- 010 A
Loss of Material Water Chemistry (B2.1.2)
IV.A2.RP-28 3.1.1- 088 A
Plant Specific Notes:
- 1. The RPV support skirt is the critical location of the RPV support assembly and is not susceptible to irradiation embrittlement based on the NDT evaluation reported. The RPV support intended function will be maintained consistent with the CLB during the SPEO when considering damage due to irradiation.
2.
The definition of the beltline, including clarification of the traditional and extended beltlines, is provided in Section 4.2.
SLRA Section 4.2 (Page 4-12) is revised as follows:
26, 2021, ADAMS Accession Number ML20335A001 [Reference 4.2-5 and4.2-33, respectively].
Reduces the applicability for the reactor coolant system heatup and cooldown limit curves from 54 EFPY to 44.6 EFPY for Unit 1, to 45.3 EFPY for Unit 2, and to 43.8 EFPY for Unit 3 based on updated reactor vessel material evaluations discussed in Section IV.1 of the measurement uncertainty recapture submittal.
Maintains RTPTS and underclad cracking at 48 EFPY and upper-shelf energy at 54 EFPY for all three units.
- 6.
All TLAA for subsequent license renewal reported in this Chapter consider the revised operating conditions (i.e, 1.64% increase in power) associated with measurement uncertainty recapture as reported in References 4.2-5 and 4.2-33. Measurement uncertainty recapture is assumed at the beginning of Cycle 30 for ONS Unit 1, Cycle 29 for ONS Unit 2, and Cycle 29 for ONS Unit 3. At present, measurement uncertainty recapture has not been implemented. Each unit is currently operating in Cycles 32, 30, and 31, respectively. The effects of the measurement uncertainty recapture were considered and found to have no impact on SLR.
Subsequent License Renewal Reactor vessel beltline items must comply with the requirements of 10 CFR 50, Appendices G and H, and 10 CFR 50.61 for SLR. The reactor vessel beltline is defined by 10 CFR 50 Appendix G, II., F, and 10 CFR 50.61(a)(3) in accordance with the following definition: the region of the reactor vessel (shell material, including welds, heat-affected zones, and plate or forgings) that directly surrounds the effective height of the active core and the adjacent regions of the reactor vessel that are predicted to experience sufficient neutron irradiation damage to be considered in the selection of the most limiting material with regard to radiation damage during the licensed period.
For SLR, the NRC staff has directed applicants to consider additional reactor vessel items (i.e.,
extended beltline) that may be subject to reduction of fracture toughness as defined in RIS 2014-11 [Reference 4.2-6]. Specifically, extended beltline means the region of the reactor vessel (shell material, including welds, heat-affected zones, and plate or forgings) adjacent to the traditional beltline region that will have associated fluence values projected to exceed 1.0E+17 n/cm2 (E >
1.0 MeV) at end of license to experience sufficient neutron damage to be included in the beltline.
In accordance with RG 1.99, Revision 2 [Reference 4.2-12], Figure 1, the fluence threshold of 1.0E+17 n/cm2 (E > 1.0 MeV) reported in RIS-2014-11 is assumed to be at the inside wetted surface of the reactor vessel. The 72 EFPY fluence projections used to establish ONS reactor vessel traditional beltline and extended beltline locations are discussed in Section 4.2.1.
Based on accrued EFPY through Cycles 31, 29 and 30 for Oconee Units 1 through 3 and assuming breaker-to-breaker operation and no outages per cycle (Capacity Factor = 1), the bounding projected EFPY for 80 years for each Oconee unit is less than 72 EFPY. Therefore, for Oconee, TLAA evaluations are completed to 80 years. A measurement uncertainty capture
SLRA Section 4.2 (Page 4-13) is revised as follows uprate is conservatively factored in at 2% for all TLAA evaluations that utilize neutron fluence as an input.
Adjusted Reference Temperatures Adjusted reference temperatures, as defined by Regulatory Guide 1.99, Revision 2, Position 1.1, and 2.1, are utilized in the calculation of upper-shelf energy/equivalent margins (Section 4.2.2),
pressurized thermal shock (Section 4.2.3), pressure-temperature limits (Section 4.2.4), low temperature overpressure (Section 4.2.5), and underclad cracking (Section 4.7.2). As such, adjusted reference temperatures are discussed in the applicable SLRA sections.
Description of Reactor Vessels: Oconee Units 1, 2, and 3 A schematic of the reactor vessel shell and closure head that applies to all 3 ONS units is provided in Figure 4.2-1. The reactor vessel shells for all three units are shown in Figure 4.2-2 for Unit 1, Figure 4.2-3 for Unit 2, and Figure 4.2-4 for Unit 3. Extended beltline items are identified with a (superscript 1) and include the reactor vessel inlet/outlet nozzles and associated welds, and the transition forging (dutchman forging) for all three units; material properties for these items have not been previously reviewed and accepted by the NRC. The remaining reactor vessel items are all considered traditional beltline items, have been reviewed previously by the NRC, and are available through the 60-year reactor vessel integrity TLAA evaluations cited above. Material properties that are required for reactor vessel integrity TLAA evaluations (traditional beltline and extended beltline) required by 10 CFR 50 Appendix G and 10 CFR 50.61 for SLR are reported in Section 4.2.2, Upper Shelf Energy, Section 4.2.3, Pressurized Thermal Shock, and Section 4.2.4, Pressure-Temperature limits.
ONS Unit 1 Traditional Beltline and Extended Beltline Reactor Vessel Items (Figure 4.2-2)
- 1.
Forgings are ASTM A 508 Class 2 Reactor vessel outlet nozzles (2) and reactor vessel inlet nozzles (4)1 Lower nozzle belt forging (AHR 54: ZV 2861)
Transition forging (122S347VA1)1
- 2.
Plates are ASTM A 302B, Modified Intermediate shell (C2197-2)
Upper shell (C3265-1 and C3278-1)
Lower shell (C2800-1 and C2800-2)
- 3.
Linde 80 Welds Reactor vessel inlet and outlet nozzle to nozzle belt forging welds1 Lower nozzle belt forging to intermediate shell circumferential weld (SA-1135)
Intermediate shell axial welds (SA-1073)
SLRA Section 4.2 (Page 4-14) is revised as follows:
Intermediate shell to upper shell circumferential weld (SA-1229, 61% ID; WF 25, 39%
OD)
Upper shell axial welds (SA-1493)
Upper Shell-to-lower shell circumferential weld (SA-1585)
Lower shell axial welds (SA-1430 and SA-1426)
Lower shell forging to transition forging circumferential weld (WF-9)
ONS Unit 2 Traditional Beltline and Extended Beltline Reactor Vessel Items (Figure 4.2-3)
- 1.
Forgings are all ASTM A 508 Class 2 Reactor vessel outlet nozzles (2) and reactor vessel inlet nozzles(4)1 Lower nozzle belt forging (AMX 77: 123T382)
Upper shell forging (AAW 163:3P2359)
Lower shell forging (AWG 164: 4P1885)
Transition forging (122T293VA1)1
- 2.
Linde 80 Welds Reactor vessel inlet and outlet nozzle to nozzle belt forging welds1 Lower nozzle belt forging to upper shell forging circumferential weld (WF-154)
Upper shell forging to lower shell forging circumferential weld (WF-25)
Lower shell forging to transition forging circumferential weld (WF-112)
ONS Unit 3 Traditional Beltline and Extended Beltline Reactor Vessel Items (Figure 4.2-4)
- 1.
Forgings are all ASTM A 508 Class 2 Reactor vessel outlet nozzles (2) and reactor vessel inlet nozzles(4)1 Lower nozzle belt forging (4680)
Upper shell forging (AWS 192: 522314)
Lower shell forging (ANK 191:522194)
Transition forging (417543-1)1
- 2.
Linde 80 Welds Reactor vessel inlet and outlet nozzle to nozzle belt forging welds1 Lower nozzle belt forging to upper shell forging circumferential weld (WF-200)
Upper shell forging to lower shell forging circumferential weld (WF-67, 75% ID; WF-70, 25% OD)
Lower shell forging to transition forging circumferential weld (WF-169-1)
Note 1: Extended beltline items
ATTACHMENT 3 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES CORRECTION OF AGING MANAGEMENT REVIEW LINE ITEMS ASSOCIATED WITH BURIED STAINLESS STEEL PIPING AND VALVES
Correction of Aging Management Review Line Items Associated with Buried Stainless Steel Piping and Valves (TRP-14)
Affected SLRA Section:
Table 3.3.2-24 Table 3.3.2-48 Table 3.3.2-51 SLRA Page Numbers:
3-727 3-922 3-968 Description of Changes:
An aging management review line item identifying a stainless steel valve with an external soil environment was inadvertently included in Table 3.3.2-24. There are no buried stainless steel valves in the high pressure service water system at Oconee. Table 3.3.2-24 is revised to delete this aging management review line item.
Stress corrosion cracking was inadvertently omitted as an aging effect requiring management for stainless steel buried piping in the condenser circulating water system and siphon seal water system. Table 3.3.2-48 and Table 3.3.2-51 are revised to add stress corrosion cracking as an aging effect requiring management for stainless steel piping with a soil external environment.
SLRA Table 3.3.2-24 (page 3-727) is revised as follows:
Table 3.3.2-24 Auxiliary Systems - High Pressure Service Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Valve Body Pressure Boundary Stainless Steel Condensation (External)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
Raw Water (Internal)
Loss of Material, Flow Blockage Fire Water System (B2.1.11)
VII.G.A-55 3.3.1- 066 B
Soil (External)
Loss of Material Buried and Underground Piping and Tanks (B2.1.26)
VII.I.AP-137 3.3.1-107 B
Underground (External)
Cracking One-Time Inspection (B2.1.20)
VII.I.A-714a 3.3.1-146 A
Loss of Material One-Time Inspection (B2.1.20)
VII.I.A-775a 3.3.1-246 A
SLRA Table 3.3.2-48 (page 3-922 ) is revised as follows:
Table 3.3.2-48 Auxiliary Systems - Condenser Circulating Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping Pressure Boundary Stainless Steel Condensation (External)
Cracking One-Time Inspection (B2.1.20)
VII.I.A-734b 3.3.1-205 A
Loss of Material One-Time Inspection (B2.1.20)
VII.I.A-761b 3.3.1-232 A
Raw Water (Internal)
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-54 3.3.1- 040 B
Soil (External)
Loss of Material Buried and Underground Piping and Tanks (B2.1.26)
VII.I.AP-137 3.3.1-107 B
Cracking Buried and Underground Piping and Tanks (B2.1.26)
VII.I.A-425 3.3.1-144 B
Underground (External)
Cracking One-Time Inspection (B2.1.20)
VII.I.A-714a 3.3.1-146 A
Loss of Material One-Time Inspection (B2.1.20)
VII.I.A-775a 3.3.1-246 A
Waste Water (Internal) Loss of Material, Flow Blockage Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.E5.AP-278 3.3.1- 095 A
SLRA Table 3.3.2-51 (page 3-968) is revised as follows:
Table 3.3.2-51 Auxiliary Systems - Siphon Seal Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping Pressure Boundary Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
Air - Outdoor (External)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
Condensation (External)
Cracking One-Time Inspection (B2.1.20)
VII.I.A-734b 3.3.1-205 A
Loss of Material One-Time Inspection (B2.1.20)
VII.I.A-761b 3.3.1-232 A
Raw Water (Internal)
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-54 3.3.1- 040 B
Soil (External)
Loss of Material Buried and Underground Piping and Tanks (B2.1.26)
VII.I.AP-137 3.3.1-107 B
Cracking Buried and Underground Piping and Tanks (B2.1.26)
VII.I.A-425 3.3.1-144 B
Underground (External)
Cracking One-Time Inspection (B2.1.20)
VII.I.A-714a 3.3.1-146 A
Loss of Material One-Time Inspection (B2.1.20)
VII.I.A-775a 3.3.1-246 A
ATTACHMENT 4 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES CLARIFICATION OF UNDERGROUND ENVIRONMENT FOR THE DIESEL ENGINE FUEL OIL STORAGE TANK
Clarification of Underground Environment for the Diesel Engine Fuel Oil Storage Tank (TRP-14)
Affected SLRA Section:
Table 3.3.2-56 SLRA Page Numbers:
3-1002 3-1004 Description of Change:
Table 3.3.2-56 is revised to add a plant-specific note to clarify the Underground (External) environment for the buried standby shutdown facility fuel oil system diesel engine fuel oil storage tank.
SLRA Table 3.3.2-56 (pages 3-1002) is revised as follows:
Table 3.3.2-56 Auxiliary Systems - Standby Shutdown Facility Fuel Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Tank (diesel engine fuel oil storage)
Pressure Boundary Steel Fuel Oil (Internal)
Loss of Material Fuel Oil Chemistry (B2.1.18)
VII.H1.AP-105a 3.3.1- 070 A
Soil (External)
Loss of Material Buried and Underground Piping and Tanks (B2.1.26)
VII.I.AP-198 3.3.1-109 B
Underground (External)
Loss of Material Buried and Underground Piping and Tanks (B2.1.26)
VII.I.AP-284 3.3.1-109 D, 3 SLRA Table 3.3.2-56 (page 3-1004) is revised as follows:
Plant Specific Notes:
- 1. Component is constructed of the same material as the fuel oil storage tank. The fuel oil storage tank is not coated on its internal surface. One-time inspection of this component is not required per GALL AMP XI.M30, Element 4.
- 2. Stainless steel piping embedded in concrete exits the building above grade level. Concrete is not subject to soil or groundwater.
- 3. The Underground (External) environment was included to account for the air space in the manhole that provides access to the tank manway. There is no air-to-soil interface as would be seen with a partially buried tank. The bottom, top and sides of the external surface of the tank are exposed to soil except for the area of the tank within the manhole.
ATTACHMENT 5 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES UPDATE TO ADD AGING EFFECTS AND A RAW WATER (INTERNAL) ENVIRONMENT
Update to add aging effects and a Raw Water (Internal) Environment (TRP-38)
Affected SLRA Section:
Table 3.3.2-16 Section 3.3.2.1.16 SLRA Page Numbers:
3-625 through 3-629 3-348 through 3-349 Description of Change:
Revised the aging effects to add flow blockage due to fouling in a raw water environment for all components that provide a pressure boundary function to align with GALL-SLR recommendations. Added a Raw Water (Internal) environment and applicable aging effects for the Essential Siphon Vacuum Pump Casing and the Pump Separator.
SLRA Table 3.3.2-16 (pages 3-625 through 3-629) is revised as follows:
Table 3.3.2-16 Auxiliary Systems - Essential Siphon Vacuum System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Piping Pressure Boundary Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
VII.I.A-734b 3.3.1-205 A
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
VII.I.A-761b 3.3.1-232 A
Air (Internal)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
Raw Water (Internal)
Loss of Material, Flow Blockage Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-727 VII.C1.A-54 3.3.1-134 3.3.1-040 A,2 B
Soil (External)
Cracking Buried and Underground Piping and Tanks (B2.1.26)
VII.I.A-425 3.3.1-144 B
Loss of Material Buried and Underground Piping VII.I.AP-137 3.3.1-107 B
SLRA Table 3.3.2-16 (pages 3-625 through 3-629) is revised as follows:
Table 3.3.2-16 Auxiliary Systems - Essential Siphon Vacuum System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Pump Casing (essential siphon vacuum)
Pressure Boundary Gray Cast Iron Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A
Air (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.D.A-26 3.3.1- 055 A
Raw Water (Internal)
Loss of Material Selective Leaching (B2.1.21)
VII.C1.A-51 3.3.1- 072 A
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VII.C1.A-532 3.3.1-193 A
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-194 3.3.1 - 037 B
Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
SLRA Table 3.3.2-16 (pages 3-625 through 3-629) is revised as follows:
Table 3.3.2-16 Auxiliary Systems - Essential Siphon Vacuum System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Pump Casing (essential siphon vacuum)
Pressure Boundary Stainless Steel Air - Indoor Uncontrolled (External)
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
Air (Internal)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
Raw Water (Internal)
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-54 3.3.1-040 B
SLRA Table 3.3.2-16 (pages 3-625 through 3-629) is revised as follows:
Table 3.3.2-16 Auxiliary Systems - Essential Siphon Vacuum System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Separator (essential siphon vacuum air-water)
Pressure Boundary Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A
Air (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.D.A-26 3.3.1- 055 A
Raw Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VII.C1.A-532 3.3.1-193 A
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-194 3.3.1 - 037 B
SLRA Table 3.3.2-16 (pages 3-625 through 3-629) is revised as follows:
Table 3.3.2-16 Auxiliary Systems - Essential Siphon Vacuum System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Sight Glass Pressure Boundary Stainless Steel Raw Water (Internal)
Loss of Material, Flow Blockage Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-727 VII.C1.A-54 3.3.1-134 3.3.1-040 A,1,2 B,1 Silencer Structural Integrity Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A Air (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.D.A-26 3.3.1- 055 A Tank (essential siphon vacuum receiver)
Pressure Boundary Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 C Loss of Material One-Time Inspection (B2.1.20)
VII.I.A-751b 3.3.1-222 A Raw Water (Internal)
Loss of Material, Flow Blockage Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-727 VII.C1.A-54 3.3.1-134 3.3.1-040 C,2 B
SLRA Table 3.3.2-16 (pages 3-625 through 3-629) is revised as follows:
Table 3.3.2-16 Auxiliary Systems - Essential Siphon Vacuum System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Stainless Steel Air (Internal)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
Raw Water (Internal)
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-54 3.3.1-040 B
Underground (External)
Cracking One-Time Inspection (B2.1.20)
VII.I.A-714a 3.3.1-146 A
Loss of Material One-Time Inspection (B2.1.20)
VII.I.A-775a 3.3.1-246 A
Plant Specific Notes:
- 1. The ESV vacuum tank level gauge is a magnetic float type indicator with no glasselement.
- 2. Flow blockage due to fouling is not a concern for components that perform a structural integrity function. Flow blockage is not a concern in the ESV system as the raw water environment is only present in drain piping which is not part of the main flowpath.
SLRA Section 3.3.2.1.16 (pages 3-348 and 3-349) is revised as follows:
Section 3.3.2.1.16 Essential Siphon Vacuum System Aging Effects Requiring Management Components in the Essential Siphon Vacuum System require aging management to address the following aging effects:
Cracking Flow Blockage Long-Term Loss of Material Loss of Material Loss of Preload Aging Management Programs The aging effects for components in the Essential Siphon Vacuum System are managed by the following Aging Management Programs:
Bolting Integrity (B2.1.9)
Buried and Underground Piping and Tanks (B2.1.26)
External Surfaces Monitoring of Mechanical Components (B2.1.23)
Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
One-Time Inspection (B2.1.20)
Open-Cycle Cooling Water System (B2.1.11)
Selective Leaching (B2.1.21)
ATTACHMENT 6 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES UPDATE TO THE CHLORINE TANK AGING MANAGEMENT REVIEW
Update to the Chlorine Tank Aging Management Review (TRP-38)
Affected SLRA Section:
Table 3.3.2-25 Table 3.3.1 Section 3.3.2.1.15 SLRA Page Numbers:
3-732 3-491 3-366 Description of Change:
Revised the aging effects used to manage the polymeric Chlorine Tank in the Keowee Service Water System to align with GALL-SLR recommendations.
SLRA Table 3.3.2-25 (SLRA page 3-732) is revised as follows:
Table 3.3.2-25 Auxiliary Systems - Keowee Service Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Tank (chlorine)
Structural Integrity Polymeric Condensation (External)
Hardening or Loss of Strength, Loss of Material, Cracking or Blistering External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-797a 3.3.1-263 C
Raw Water (Internal)
Cracking, Blistering Hardening or Loss of Strength, Loss of Material, Cracking or Blistering Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.C1.A-739 VII.C1.A-797b 3.3.1-210 3.3.1 - 263 C, 1 SLRA Table 3.3.1 (SLRA page 3-491) is revised as follows:
Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL-SLR Report Item Number Component Aging Effect/
Mechanism Aging Management Program Further Evaluation Recommended Discussion 3.3.1-210 HDPR HDPE piping, piping components exposed to raw water (for components not covered by NRC GL 89-13)
Cracking, blistering; flow blockage due to fouling AMP XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components No Consistent with NUREG-2191.
Not Applicable. ONS has no HDPE piping, piping components exposed to raw water.
The associated NUREG-2191 aging items are not used.
SLRA Section 3.3.2.1.15 (SLRA page 3-366) is revised as follows:
Section 3.3.2.1.15 Keowee Service Water System Aging Effects Requiring Management Components in the Keowee Service Water System require aging management to address the following aging effects:
Cracking Cracking or Blistering Cracking, Blistering Hardening or Loss of Strength Long-Term Loss of Material Loss of Material Loss of Preload
ATTACHMENT 7 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES UPDATE TO NUREG-2191 CONSISTENCY STATEMENT FOR WATER CHEMISTRY AGING MANAGEMENT PROGRAM
Update to NUREG-2191 Consistency Statement Water Chemistry Aging Management Program (TRP-2)
Affected SLRA Section:
Appendix B, Section B2.1.2 SLRA Page Numbers:
B-30 Description of Change:
The following editorial correction is made to the NUREG-2191 Consistency statement in SLRA Section B2.1.2 for the Water Chemistry aging management program: Delete the phrase with enhancements described below.
SLRA Section Appendix B2.1.2 (Page B-30) is revised as follows B2.1.2 WATER CHEMISTRY NUREG-2191 Consistency The Water Chemistry AMP is an existing program that is consistent with the ten elements of NUREG-2191,Section XI.M2, Water Chemistry, as modified by SLR-ISG-Mechanical-2021 MECHANICAL Updated Aging Management Criteria for Mechanical Portions of the SLR Guidance with enhancements described below.
ATTACHMENT 8 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES UPDATE TO STEAM GENERATOR COMPONENT AGING MANAGEMENT REVIEW LINE ITEMS FOR THE WATER CHEMISTRY AGING MANAGEMENT PROGRAM
Update to Steam Generator component Aging Management Review line items for the Water Chemistry Aging Management Program (TRP-2)
Affected SLRA Section:
Table 3.1.2-4 SLRA Page Numbers:
3-202, 3-204 Description of Change:
SLRA Table 3.1.2-4 is being revised to modify Steam Generator component Aging Management Review line items for the Water Chemistry Aging Management Program.
Items revised are as follows:
The environment of Treated Water is equal to the environment of Secondary Feedwater for the Tube Support Plate Assembly (support rods). A plant specific note was added to clarify that these environments are the same.
The environment of Treated Water (Internal) was revised to Treated Water (External) for the applicable line items associated with the Tube Support Plate Assembly (support rods).
The environment of Treated Water is considered the same as Secondary. A plant specific note was added for clarity for the Tube Support Plate Assembly (tube support plates).
The internal environment for tube-to-tubesheet weld was revised to Secondary Feedwater (Internal).
The external environment of the tube-to-tubesheet weld was revised to Reactor Coolant (External)
SLRA Table 3.1.2-4 (Page 3-202) is revised as follows:
Table 3.1.2-4 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Tube Support Plate Assembly (support rods)
Structural Support Stainless Steel Secondary Feedwater (External)
Cracking Water Chemistry (B2.1.2)
Treated Water (External)
Cumulative Fatigue Damage TLAA IV.C2.R-18 3.1.1-005 C, 1 Treated Water (Internal)
(External)
Loss of Material Steam Generators (B2.1.10)
None None J, 1 Water Chemistry (B2.1.2)
None None J, 1 Tube Support Plate Assembly (tube support plates)
Structural Support Stainless Steel Secondary Feedwater (External)
Cracking Steam Generators (B2.1.10)
Water Chemistry (B2.1.2)
Cumulative Fatigue Damage TLAA IV.C2.R-18 3.1.1-005 C
Treated Water (Internal)
Loss of Material Steam Generators (B2.1.10)
None None J, 2 Water Chemistry (B2.1.2)
None None J, 2 Tubes Heat Transfer Nickel Alloy Secondary Feedwater (External)
Reduction of Heat Transfer Steam Generators (B2.1.10)
IV.D2.R-407 3.1.1-111 A
Water Chemistry (B2.1.2)
IV.D2.R-407 3.1.1-111 A
Pressure Boundary Nickel Alloy Reactor Coolant (Internal)
Cracking Steam Generators (B2.1.10)
IV.D2.R-44 3.1.1-070 A
Plant Specific Notes:
- 1. The environment of Treated Water is equal to the environment of Secondary Feedwater for the Tube Support Plate Assembly (support rods).
- 2. The environment of Treated Water is equal to the environment of Secondary Feedwater for the Tube Support Plate Assembly (tube support plates)
SLRA Table 3.1.2-4 (Page 3-204) is revised as follows:
Table 3.1.2-4 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Tubesheet Pressure Boundary Steel with Nickel Alloy Cladding Reactor Coolant (Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
IV.D2.RP-47 3.1.1- 042 A
Water Chemistry (B2.1.2)
IV.D2.RP-47 3.1.1- 042 A
Cumulative Fatigue Damage TLAA IV.D2.R-222 3.1.1- 008 C
Loss of Material Steam Generators (B2.1.10)
IV.D2.R-440 3.1.1-127 A
Water Chemistry (B2.1.2)
IV.D2.R-440 3.1.1-127 A
Tube-to-Tube Sheet Welds Structural Support Nickel Alloy Reactor Coolant (External)
Cracking Water Chemistry (B2.1.2)
IV.D2.RP-185 3.1.1- 025 A
Reactor Coolant (Internal)
Secondary Feedwater (Internal)
Cracking Steam Generators (B2.1.10)
IV.D2.RP-185 3.1.1- 025 A
Cumulative Fatigue Damage TLAA IV.D2.R-46 3.1.1- 002 A
Loss of Material Water Chemistry (B2.1.2)
IV.C2.RP-23 3.1.1- 088 A
Secondary Feedwater (External)
Reactor Coolant (External)
Cracking Steam Generators (B2.1.10)
IV.D2.R-47 3.1.1- 069 A
Water Chemistry (B2.1.2)
IV.D2.R-47 3.1.1- 069 A
Loss of Material Steam Generators (B2.1.10)
IV.D2.RP-233 3.1.1- 077 A
ATTACHMENT 9 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES CAULKING/SEALANT OF OUTDOOR AND LARGE ATMOSPHERIC METALLIC STORAGE TANKS PROGRAM
Caulking/Sealant of Outdoor and Large Atmospheric Metallic Storage Tanks Program (TRP-29)
Affected SLRA Section:
A2.17 Table A6.0-1 B2.1.17 SLRA Page Numbers:
A-19 A-84 B133-134 Description of Change:
The Oconee Outdoor and Large Atmospheric Metallic Storage Tanks Aging Management Program is revised to require installation of a sealant or caulking to the base of each BWST at the concrete-component interface and periodic inspections of the sealant or caulking.
SLRA Section A2.17 page A-19 is revised as follows:
Program Description The Outdoor and Large Atmospheric Metallic Storage Tanks AMP is a new condition monitoring program that manages loss of material on the external surfaces of the Unit 1, 2, and 3 borated water storage tanks and ensures there is no significant degradation of the tank bottom. These are indoor large volume tanks that contain water and are designed with internal pressures approximating atmospheric that are sited on concrete. This program includes preventive measures to mitigate corrosion by protecting the external surfaces of steel components consistent with standard industry practices. Sealant or caulking will be applied to each tank at the concrete-component interface. The borated water storage tanks are internally coated and protected by missile barriers.
The program manages loss of material by conducting external visual surface inspections.
Inspections of the sealant or caulking will be supplemented with physical manipulation.
Thickness measurements of the tank bottoms are conducted to ensure that significant degradation is not occurring. Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (A2.27) AMP will manage the internally coated surfaces of the borated water storage tanks. The Structures Monitoring AMP (A2.33) will manage the tank concrete foundations and the borated water storage tank superstructures that serve as missile barriers. Cracking is not a predicted aging effect due to the carbon steel construction.
Inspections not conducted in accordance with ASME Code,Section XI requirements are conducted in accordance with plant-specific procedures that include inspection parameters such as lighting, distance, offset, and surface conditions.
Industry and plant-specific OE will be considered in the development and implementation of this program.
Enhancements None
SLRA Section A6.0-1 page A-84 is revised as follows:
Table A6.0-1: Subsequent License Renewal Commitments Program Commitment AMP Implementation 17 Outdoor and Large Atmospheric Metallic Storage Tanks program The Outdoor and Large Atmospheric Metallic Storage Tanks AMP is a new condition monitoring program that manages loss of material on the external surfaces of the Unit 1,2 and 3 borated water storage tanks and ensures there is no significant degradation of the tank bottoms. Sealant or caulking will be applied to the base of each tank at the concrete-component interface. These are indoor large volume tanks that contain water and are designed with internal pressures approximating atmospheric that are sited on concrete. This program includes preventive measures to mitigate corrosion by protecting the external surfaces of the steel components in accordance with standard industry practices.
B2.1.17 The program for SLR will be implemented six months prior to the SPEO or no later than the last refueling outage prior to the SPEO.
SLRA Section B2.1.17 (page B133-134) is revised as follows:
Program Description The Outdoor and Large Atmospheric Metallic Storage Tanks AMP is a new condition monitoring program that manages loss of material on the external surfaces of the Unit 1,2 and 3 borated water storage tanks and ensures there is no significant degradation of the tank bottoms. These are indoor large volume tanks that contain water and are designed with internal pressures approximating atmospheric that are sited on concrete. This program includes preventive measures to mitigate corrosion by protecting the external surfaces of the steel components in accordance with standard industry practices.
Oconee has no outdoor aboveground tanks constructed on concrete or soil, and no indoor tanks that sit on, or are embedded in, concrete where specific OE indicates that the tank surfaces are periodically exposed to moisture.
These tanks contain treated borated water, are constructed of carbon steel, are coated both internally and externally as a preventive measure to mitigate corrosion, and are supported on a concrete foundation, such that the bottoms of the tanks are inaccessible for direct visual inspection. Each borated water storage tank is surrounded by two external layers of metal siding that house fiberglass insulation in between. Between the tank surface and the inner metal siding there is a 6 air gap. Around the bottom portions of the tank in the air gap, there are two 1 thick Tempmat insulation blankets pressed against the tank surface. A sealant or caulking will be applied to each tank at the concrete-component interace. There is no sealant or caulking at the tank and concrete interface as the tank is located indoors.
This program manages loss of material by conducting periodic external surface visual inspections, and tank bottom volumetric inspections on a frequency of ten years or less. Visual inspections of sealant or caulking will be supplemented with physical manipulation every refueling outage. Cracking is not a predicted aging effect due to the carbon steel construction.
These inspections ensure significant degradation is not occurring. The periodic inspection results are compared to the acceptance criteria to allow corrective actions to be taken prior to loss of intended function.
The Outdoor and Large Atmospheric Metallic Storage Tanks AMP does not manage loss of coating integrity for internal coating or linings. The activities to manage the aging effects for internal coatings or linings is managed by the Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.27) AMP. The Structures Monitoring AMP (A2.33) will manage the tank concrete foundations and the borated water storage tank superstructures that serve as missile barriers.
The Outdoor and Large Atmospheric Metallic Storage Tanks AMP will perform the following activities:
Conduct external tank surface inspections on a minimum of 20% of the tank on a ten year frequency.
Conduct subsequent visual inspections every refueling outage. These inspections consist of a visual examination of the outer protective metal siding around the tank to identify indications of siding damage or water intrusion. If this inspection reveals new damage or water intrusion, then the shielding will be removed around that location to
ensure no damage to the tank has occurred. If no new damage is identified, then the inspection is complete.
Conduct subsequent visual inspections supplemented with physical manipulation every outage of the sealant or caulking applied at the tank concrete-component interface.
Perform a volumetric inspection of the borated water storage tank bottom, at least once every 10 years during the SPEO.
ATTACHMENT 10 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES UPDATE OF SLRA TABLE 3.1.2-4, REACTOR VESSEL, REACTOR INTERNALS, AND REACTOR COOLANT SYSTEM - STEAM GENERATORS - AGING MANAGEMENT EVALUATION
Update of SLRA Table 3.1.2-4, Reactor Vessel, Reactor Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation (TRP-19)
Affected SLRA Section:
Table 3.1.2-4 SLRA Page Numbers:
3-193 Description of Change:
- 1. A plant specific note was added for the auxiliary feedwater nozzle flange line items to clarify that these nozzle flanges are insulated.
- 2. SLRA Table 3.1.2-4 cites Aging Management Review Items 3.4.1-103 and 3.4.1-104 for managing loss of material and cracking of the stainless-steel auxiliary feedwater nozzle flanges exposed externally to indoor uncontrolled air by the One-Time Inspection program and these Aging Management Review items are for insulated stainless steel piping, piping components, etc.
- 3. Note A was changed to a Note F for the Auxiliary Feedwater Nozzle Flange lines associated with cracking.
SLRA Table 3.1.2-4 (Page 3-193) is revised as follows Table 3.1.2-4 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG
- 2192 Table 1 Not es Auxiliary Feedwater and Main Feedwater Closure Bolting Pressure Steel Air - Indoor Uncontrolled (External)
Loss of Material Bolting Integrity (B2.1.9)
IV.D2.RP-166 3.1.1-064 Loss of Preload Bolting Integrity (B2.1.9)
IV.D2.RP-46 3.1.1-067 Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.D2.R-17 3.1.1-049 Auxiliary Feedwater Nozzle Flanges Pressure Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VIII.H.S-452b 3.4.1-104 A, 1 Loss of Material One-Time Inspection (B2.1.20)
VIII.H.S-451b 3.4.1-103 A, 1 Air with Borated Water Leakage (External)
None None IV.E.RP-05 3.1.1-107 Treated Water (Internal)
Cracking One-Time Inspection (B2.1.20)
Water Chemistry (B2.1.2)
None None Cumulative Fatigue Damage TLAA IV.C2.R-18 3.1.1-005 Loss of Material One-Time Inspection (B2.1.20)
VIII.G.SP-87 3.4.1-085 Water Chemistry (B2.1.2)
VIII.G.SP-87 3.4.1-085 Plant Specific Notes:
- 1. The Auxiliary Feedwater Nozzle Flanges are insulated with stainless steel metal reflective insulation (
Reference:
Drawing OM 241-37 Sheet 1 and OSS-0241.00-00-0005).
ATTACHMENT 11 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES REVISION TO SLRA TABLES 2.3.1-4 AND 3.1.2-4
Revision to SLRA Tables 2.3.1-4 and 3.1.2-4 (TRP-19)
Affected SLRA Section:
Table 2.3.1-4 Table 3.1.2-4 SLRA Page Numbers:
2-67 3-195 Description of Change:
SLRA Table 2.3.1-4 was modified to include flow distribution as an intended function for the baffle assemblies to be consistent with SLRA Table 3.1.2-4 and Section 2.3.1.4.
Note A was changed to Note C for line items matching to IV.D2.R-33 and IV.D2.RP-162.
SLRA Table 2.3.1-4 (page 2-67) is revised as follows:
Table 2.3.1-4 Steam Generators Component/Commodity Group Intended Functions Auxiliary Feedwater and Main Feedwater Closure Bolting Pressure Boundary Auxiliary Feedwater Nozzle Flanges Pressure Boundary Auxiliary Feedwater Nozzle Inlet Header Pressure Boundary Auxiliary Feedwater Nozzle Thermal Sleeves Thermal Resistance Baffle Assemblies Structural Support Flow Distribution Base Support Structural Support Main Feedwater Nozzle Inlet Headers Pressure Boundary Main Feedwater Nozzle Spray Plates Pressure Boundary Main Feedwater Spray Nozzle Flanges Pressure Boundary Primary Manway and Inspection Opening Bolting Pressure Boundary Primary Manway and Inspection Opening Covers and Backing Plates Pressure Boundary Primary Nozzles Pressure Boundary Secondary Manway and Handhole Opening Bolting Pressure Boundary Secondary Manway and Handhole Opening Covers Pressure Boundary Secondary Side Nozzles (vent, drain, and instrumentation)
Pressure Boundary Shell Assembly Pressure Boundary
SLRA Table 3.1.2-4 (page 3-195) is revised as follows:
Table 3.1.2-4 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Baffle Assemblies Flow Steel Secondary Feedwater (External)
Cumulative Fatigue Damage TLAA IV.D2.R-33 3.1.1- 005 Loss of Material Steam Generators (B2.1.10)
IV.D2.RP-162 3.1.1- 072 Water Chemistry (B2.1.2)
IV.D2.RP-162 3.1.1- 072 Support Steel Secondary Feedwater (External)
Cumulative Fatigue Damage TLAA IV.D2.R-33 3.1.1- 005 Loss of Material Steam Generators (B2.1.10)
IV.D2.RP-162 3.1.1- 072 Water Chemistry (B2.1.2)
IV.D2.RP-162 3.1.1- 072 Base Support Support Steel Air - Indoor Uncontrolled (External)
Cumulative Fatigue Damage TLAA IV.A2.R-70 3.1.1- 004 Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
V.E.E-44 3.2.1- 040 Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.D2.R-17 3.1.1- 049 Main Feedwater Nozzle Inlet Headers Pressure Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
V.E.E-44 3.2.1- 040 Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
IV.D2.R-17 3.1.1- 049
ATTACHMENT 12 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES UPDATE TO APPENDIX B2.1.10 PROGRAM DESCRIPTION
Update to Appendix B2.1.10 Program Description (TRP-19)
Affected SLRA Section:
Appendix B, Section B2.1.10 SLRA Page Numbers:
B-93 and B-94 Description of Change:
Revised the Steam Generators AMP Program Description in SLRA Section B2.1.10 to add detail to address the following items:
- a. Corrective actions will be taken in accordance with the corrective action program during the subsequent period of extended operation for tube integrity not being maintained for the operating interval before the next inspection, non-conservative operational assessments, and acceptance criteria not being met.
- b. Evaluations for continued acceptability will be performed for steam generator components such as, tube-to-tubesheet welds, heads, tubesheets, and secondary side internals during the subsequent period of extended operation.
SLRA Section Appendix B2.1.10 (Pages 93 and 94) is revised as follows:
B2.1.10 STEAM GENERATORS Program Description The aging effects managed by the Steam Generators AMP include cracking, loss of material (e.g., wall thinning), and reduction of heat transfer for the steam generators. The scope of the program includes primary-side components (e.g., tubes, plugs, lower/upper heads, tubesheet, etc.), and secondary-side components that are contained within the steam generator. The program uses volumetric inspections for the tubes, and visual inspections for the other primary-side and secondary-side components. The visual inspections of steam generator components are performed in accordance with the degradation assessment that is prepared as each steam generator is scheduled for examination, including steam generator head primary side stainless steel cladding surfaces. The primary side surfaces of Oconee replacement once through steam generator tubesheets are clad with nickel alloy and the Alloy 690 thermally treated tubes are joined to the tubesheet with autogenous welds. General steam generator inspection activities are credited to identify rust stains indicative of degradation (loss of material) of tubesheet or tube-to-tubesheet weld primary side surfaces.
Depending on the results of the visual examinations, more detailed inspections may be performed. A condition report is generated in the corrective action program to address any indications of degradation on steam generator components. Steam generator components such as degraded plugs, tube-to-tubesheet welds, heads (interior surfaces), tubesheets (primary side), and secondary side internals are evaluated for continued acceptability on a case-by-case basis as part of the ONS Steam Generators aging management program.
Similarly, inspection/maintenance activity events that potentially damage tubesheet and tube-to-tubesheet weld primary side surfaces are also addressed on a case-by-case basis through entry into the corrective action program. Evaluations are performed using industry guidance contained in NEI 97-06 and the associated EPRI Steam Generator Guidelines. These evaluations for continued acceptability will be performed during the subsequent period of extended operation for steam generator components such as tubes, plugs, secondary side components, sleeves, tube supports, primary side cladding of heads (interior surfaces),
tubesheets and tube-to-tubesheet welds.
The Steam Generators AMP includes preventive measures to mitigate aging related degradation through foreign material exclusion as a means to inhibit tube degradation due to wear. Identification of deposits on the secondary side of the steam generator, and the subsequent removal of sludge deposits helps prevent tube degradation. As an additional preventive measure, the Water Chemistry program monitors and controls reactor water chemistry and secondary water chemistry for the steam generators consistent with EPRI 3002000505, PWR Primary Water Chemistry Guidelines, and EPRI 3002010645, PWR Secondary Water Chemistry Guidelines.
Oconee Technical Specifications include the following requirements which have been incorporated in the Steam Generators program:
Conducting condition monitoring assessments for each refueling outage during which steam generator tubes are inspected or plugged.
Maintaining steam generator tube integrity bymeeting performance criteria for tube structural integrity, accident-induced leakage, and operational leakage.
Installing plugs in tubes found by inservice inspection to contain flaws with a depth equal to, or exceeding, 40% of the nominal tube wall thickness.
Performing periodic inspections of steam generator tubes. Inspection scope, methods, and interval ensure that tube integrity is maintained until the next planned inspection.
Monitoring primary-to-secondary leakage.
Monitoring secondary water chemistry to ensure controls are in place to inhibit steam generator tube degradation.
Non-destructive examination techniques are used to inspect tubing materials in order to identify tubes that may need to be removed from service in accordance with technical specifications. The Steam Generators program utilizes volumetric examination techniques for the tubes, and visual examinations for other primary-side and secondary-side components.
The Steam Generators program defines specific examination techniques, and describes criteria for the qualification of personnel, and for the acquisition and analysis of data.
Assessment of tube integrity and plugging criteria of flawed tubes is in accordance with the technical specifications and the Steam Generators program implementing procedures. Tube plugs with indications of aging are evaluated for corrective actions in accordance with the corrective action program and the Steam Generators program.
Condition monitoring assessments are performed to determine whether structural and accident leakage criteria have been satisfied during the previous operating cycle(s). Operational assessments are performed after inspections are completed to verify that structural and leakage integrity will be maintained for the operating interval between inspections, which is selected performed in accordance with Technical Specifications and EPRI Steam Generator Integrity Assessment Guidelines. Comparison of the results of the condition monitoring assessment with the predictions of the previous operational assessment provides feedback for evaluation of the adequacy of the operational assessment and additional insights that can be incorporated into the next operational assessment. If the operational assessment was significantly non-conservative, corrective actions are initiated in accordance with the corrective action program. The condition monitoring, and performance monitoring methods, are effective in detecting the applicable aging effects, and the frequency of monitoring is adequate to prevent significant age-related degradation.
Corrective actions will be taken in accordance with the corrective action program during the subsequent period of extended operation if acceptance criteria are not met. This includes, but is not limited to, inspection results indicating tube integrity may not be maintained for the operating interval until the next inspection or if operational assessments are significantly non-conservative.
ATTACHMENT 13 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES UPDATE OF HPSW BOUNDARY DRAWING TO REMOVE CT-5 SPRINKLER SYSTEM
Update of HPSW Boundary Drawing to remove CT-5 Sprinkler System (Fire Protection Scoping and Screening)
Affected SLRA Section:
SLRA Section 2.3.3.4.1 SLRA Page Numbers:
2-144 Description of Change:
Transformer CT-5 sprinkler system is not credited for a3 Fire Protection. Removing the highlighting on CT-5 sprinkler drawing resulted in no other components highlighted on the drawing. Therefore, that drawing is no longer a SLR boundary drawing and the SLRA will be revised accordingly.
SLRA Section 2.3.3.4.1 (Page 2-144) is revised as follows:
Subsequent License Renewal Boundary Drawings Primary Drawings
- OSLRD-124C-1.1
- OSLRD-124C-1.2
- OSLRD-124C-1.3
- OSLRD-124C-1.4
- OSLRD-124C-1.5
- OSLRD-124C-1.6
- OSLRD-124C-1.7
- OSLRD-124C-1.8
- OSLRD-124C-1.9
- OSLRD-124C-1.10
- OSLRD-124C-2.2
- OSLRD-124C-2.3
- OSLRD-124C-2.7
- OSLRD-124C-2.8
- OSLRD-124C-3.2
- OSLRD-124C-3.3
- OSLRD-124C-3.7
ATTACHMENT 14 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES CLARIFICATION ON THE MATERIALS OF CONSTRUCTION OF THE FIRE DAMPER ASSEMBLIES AND THE APPLICABLE AGING AFFECTS FOR THE FIRE DAMPER ASSEMBLIES
Clarification on the materials of construction of the fire damper assemblies and the applicable aging affects for the fire damper assemblies (TRP-26)
Affected SLRA Section:
SLRA Table 2.3.3.5-3 and SLRA Table 3.3.2-29 SLRA Page Numbers:
2-163 3-776 3-777 3-778 3-791 Description of Change:
Revised Component name from Damper housing to Damper assembly. Updated SLRA Table 2.3.3.5-3 to include fire barrier as an intended function for damper assembly.
Updated SLRA Table 3.3.2-29 to include the material of construction for the fire damper assemblies, the environments that the material is exposed to, the aging effect for the material and environment, and the programs to manage these aging effects. A plant specific note was added.
SLRA Table 2.3.3.5-3 (Page 2-163) is revised as follows:
Table 2.3.3.5-3 Ventilation System Component/Commodity Group Intended Functions Damper Housing Assembly Fire Barrier Pressure Boundary Drain Pan Structural Integrity
SLRA Table 3.3.2-29 (Pages 3-776 through 3-778, and 3-791) is revised as follows:
Table 3.3.2-29 Auxiliary Systems - Ventilation Systems - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Damper Assembly Housing Fire Barrier Galvanized Steel Air - Indoor Uncontrolled (External)
Loss of Material Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A,2 Air - Indoor Uncontrolled (Internal)
Loss of Material Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A,2 Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.A-79 3.3.1- 009 A
Stainless Steel Air - Indoor Uncontrolled (External)
Loss of Material, Cracking Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A,2 Air - Indoor Uncontrolled (Internal)
Loss of Material, Cracking Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A,2 Air with Borated Water Leakage (External)
None None VII.J.AP-18 3.3.1-120 C
Steel Air - Indoor Uncontrolled (External)
Loss of Material Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A,2 Air - Indoor Uncontrolled (Internal)
Loss of Material Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A,2 Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.A-79 3.3.1- 009 A
Pressure Boundary Galvanized Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A
Air - Indoor Uncontrolled (External)
Loss of Material Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A
SLRA Table 3.3.2-29 (Pages 3-776 through 3-778, and 3-791) is revised as follows:
Table 3.3.2-29 Auxiliary Systems - Ventilation Systems - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1
Notes Damper Assembly Housing Pressure Boundary Galvanized Steel Air - Indoor Uncontrolled (Internal)
Loss of Material Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A
Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.F1.A-08 3.3.1- 090 A
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.A-79 3.3.1- 009 A
Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VII.F1.A-781a 3.3.1- 094a A
Loss of Material One-Time Inspection (B2.1.20)
VII.F1.AP-99a 3.3.1- 094 A
Loss of Material, Cracking Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A
Air - Indoor Uncontrolled (Internal)
Cracking One-Time Inspection (B2.1.20)
VII.F1.A-781a 3.3.1- 094a A
Loss of Material One-Time Inspection (B2.1.20)
VII.F1.AP-99a 3.3.1- 094 A
Loss of Material, Cracking Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A
Air - Outdoor (External)
Cracking One-Time Inspection (B2.1.20)
VII.F1.A-781a 3.3.1- 094a A
Loss of Material One-Time Inspection (B2.1.20)
VII.F1.AP-99a 3.3.1- 094 A
SLRA Table 3.3.2-29 (Pages 3-776 through 3-778, and 3-791) is revised as follows:
Table 3.3.2-29 Auxiliary Systems - Ventilation Systems - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Damper Assembly Housing Pressure Boundary Stainless Steel Air - Outdoor (Internal)
Cracking One-Time Inspection (B2.1.20)
VII.F1.A-781a 3.3.1- 094a A
Loss of Material One-Time Inspection (B2.1.20)
VII.F1.AP-99a 3.3.1- 094 A
Air with Borated Water Leakage (External)
None None VII.J.AP-18 3.3.1-120 C
Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A
Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A
Air - Indoor Uncontrolled (Internal)
Loss of Material Fire Protection (B2.1.15)
VII.G.A-789 3.3.1-255 A
Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.F1.A-08 3.3.1- 090 A
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.A-79 3.3.1- 009 A
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. Damper assemblies that perform a fire barrier function do not contain elastomeric parts. Hardening, loss of strength, and shrinkage is not an aging mechanism requiring management.
ATTACHMENT 15 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES REVISED SCOPING AND SCREENING DETERMINATION FOR THE LETDOWN COOLERS
Revised Scoping and Screening Determination for the Letdown Coolers (TRP-1)
Affected SLRA Sections:
SLRA Table 2.3.2-3 SLRA Table 3.2.2-3 SLRA Section 3.3.2.2.2 SLRA Page Numbers:
2-76 2-77 3-284 3-285 3-435 Description of Change:
The letdown cooler tubes were added to the scope of SLR for meeting the (a)(1) scoping criteria. The letdown cooler heat exchanger assembly are replaced on a specified frequency and are not subject to aging management review in accordance with 10CFR54.21(a)(1)(ii).
SLRA Table 2.3.2-3 (Pages 2-76 and 2-77) is revised as follows:
Table 2.3.2-3 High Pressure Injection System Component/Commodity Group Intended Functions Flow Element Flow Restriction Pressure Boundary Structural Integrity Heat Exchanger (letdown cooler) Head Structural Integrity Heat Exchanger (letdown cooler) Shell Structural Integrity Heat Exchanger (reactor coolant seal return cooler) Head Structural Integrity
SLRA Table 3.2.2-3 (Page 3-284) is revised as follows Table 3.2.2-3 Engineered Safety Features - High Pressure Injection System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Heat Exchanger (letdown cooler)
Head Structural Integrity Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
V.A.EP-103b 3.2.1- 007 C
Loss of Material One-Time Inspection (B2.1.20)
V.C.EP-107a 3.2.1- 004 C
Air with Borated Water Leakage (External)
None None V.F.EP-19 3.2.1- 063 C
SLRA Table 3.2.2-3 (Page 3-285) is revised as follows Table 3.2.2-3 Engineered Safety Features - High Pressure Injection System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1
Notes Heat Exchanger (letdown cooler)
Head Structural Integrity Stainless Steel Treated Borated Water (Internal)
Loss of Material One-Time Inspection (B2.1.20)
V.A.EP-41 3.2.1- 022 A
Water Chemistry (B2.1.2)
V.A.EP-41 3.2.1- 022 A
Treated Borated water
>60°C (>140°F)
(Internal)
Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)
VII.E1.AP-119 3.3.1- 008 A
One-Time Inspection (B2.1.20)
V.A.E-12 3.2.1- 020 C
Water Chemistry (B2.1.2)
V.A.E-12 3.2.1- 020 C
Heat Exchanger (letdown cooler)
Shell Structural Integrity Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
V.E.E-44 3.2.1- 040 A
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
V.E.E-28 3.2.1- 009 A
Closed-Cycle Cooling Water (Internal)
Loss of Material Closed Treated Water System (B2.1.12)
V.A.EP-92 3.2.1- 030 A
SLRA Section 3.3.2.2.2 (Page 3-435) is revised as follows:
3.3.2.2.2 Cracking Due to Stress Corrosion Cracking and Cyclic Loading Evaluation:
[3.3.1-003] [3.3.1-003a] - Not applicable. The ONS high pressure injection system letdown coolers and seal return coolers function as nonregenerative heat exchangers. The letdown coolers are replaced on a specified time period and are short-lived components not subject to aging management per 10 CFR 54.21(a)(1)(ii). The tubes on these the seal return coolers heat exchangers perform no intended function and are not in the scope of SLR. Therefore, cracking due to stress corrosion cracking and cyclic loading of stainless steel PWR nonregenerative heat exchanger tubing exposed to treated borated water greater than 60 °C (Celsius) [140 °F (Fahrenheit)] is not an aging effect requiring management for ONS.
ATTACHMENT 16 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES ADDED TRAINING AND QUALIFICATION REQUIREMENTS TO FIRE WATER SYSTEM AMP
Added training and qualification requirements to Fire Water System Aging Management Program (TRP-15 and TRP-27)
Affected SLRA Sections:
SLRA Appendix A2.16 SLRA Table A6.01 SLRA Appendix B2.1.16 SLRA Page Numbers:
A-19 A-84 B-127 Description of Change:
AMP XI.M42 of GALL-SLR, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks, states that when the fire water storage tank internals are coated, the Fire Water System program is used to manage the aging effects. The FSAR Summary Description of the Fire Water System program needs to be enhanced to include the recommendations from XI.M42 on training and qualification of personnel performing inspection of the internal coatings of the elevated water storage tank.
The Oconee SLRA is being revised to add an enhancement for personnel training and qualifications to Sections A2.16 and B2.1.16 and Table A6.0 item # 16 for the Fire Water System program.
SLRA Appendix A2.16 (Page A-19) is revised as follows:
A2.16 Fire Water System Enhancements The Fire Water System AMP will be enhanced to:
- 10. Acceptance criteria and corrective actions for internal inspections of the elevated water storage tank will be in accordance with the Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers and Tanks program. Tank wall thickness measurements will be conducted if interior pitting or general corrosion (beyond minor surface rust) is detected.
- 11. Personnel involved with inspection of the internal coatings of the elevated water storage tank and evaluation of degraded conditions will be trained and qualified in accordance with an ASTM international standard endorsed in Regulatory Guide 1.54, including NRC staff limitations associated with a particular standard.
SLRA Table A6.0-1 (Page A-84) is revised as follows:
Table A6.0-1: Subsequent License Renewal Commitments Program Commitment AMP Implementation 16 Fire Water System program
- 10. Acceptance criteria and corrective actions for internal inspections of the elevated water storage tank will be in accordance with the Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers and Tanks program. Tank wall thickness measurements will be conducted if interior pitting or general corrosion (beyond minor surface rust) is detected.
- 11. Personnel involved with inspection of the internal coatings of the elevated water storage tank and evaluation of degraded conditions will be trained and qualified in accordance with an ASTM international standard endorsed in Regulatory Guide 1.54, including NRC staff limitations associated with a particular standard.
B2.1.16 Program enhancements for SLR will be implemented 6 months prior to the SPEO.
Inspections or tests that are to be completed prior to SPEO are completed 6 months prior to the SPEO or no later than the last refueling outage prior to the SPEO.
SLRA Section B2.1.16 (Page B-127) is revised as follows:
B2.1.16 FIRE WATER SYSTEM Enhancements The following enhancements shall be implemented in the respective program elements:
Parameters Monitored or Inspected (Element 3), Detection of Aging Effects (Element 4),
Monitoring and Trending (Element 5), Acceptance Criteria (Element 6), and Corrective Actions (Element 7)
- 10.
Acceptance criteria and corrective actions for internal inspections of the elevated water storage tank will be in accordance with the Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers and Tanks program. Tank wall thickness measurements will be conducted if interior pitting or general corrosion (beyond minor surface rust) is detected.
- 11.
Personnel involved with inspection of the internal coatings of the elevated water storage tank and evaluation of degraded conditions will be trained and qualified in accordance with an ASTM international standard endorsed in Regulatory Guide 1.54, including NRC staff limitations associated with a particular standard.
ATTACHMENT 17 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES ADDED NEW ENHANCEMENT TO PREVENT THE USE OF HIGH STRENGTH BOLTING
Added new enhancement to prevent the use of high strength bolting (TRP-18)
Affected SLRA Sections:
Sections A2.9, B2.1.9, Table A6.0-1 SLRA Page Numbers:
A-10 A-76 B-89 Description of Change:
- 1. Clarify the description of Enhancement #5.
- 2. Add new enhancement to address GALL-SLR preventative measure related to the use of high strength bolting.
- 3. Updated Commitment Table A6.0-1
SLRA Appendix A2.9 (Page A-10) is revised as follows:
A2.9 Bolting Integrity Enhancements The Bolting Integrity AMP will be enhanced to:
- 1. Revise applicable procedures and specifications to include reference to EPRI Report 1015336, EPRI Report 1015337, and NUREG-1339, as appropriate.
- 2. Revise procedures governing the direct visual examination of bolted joints to include inspection parameters such as lighting, distance, and offset.
- 3. Perform volumetric inspections of non-ASME high strength bolting greater than 2 inches in diameter in accordance with the method described in ASME Code Section XI, Table IWB-2500-1, Examination Category B-G-1.
- 4. Perform visual inspections of a representative sample of 20 percent of closure bolting where leakage is difficult to detect such as submerged connections or systems containing air/gas or a maximum of 17 bolts for each material and environment population per unit, whichever is less, during each ten year period. If the minimum sample size is not achieved during a ten year period, then alternative inspections may be performed. For submerged bolting, alternative inspections may include (a) diver inspections or (b) remote video inspections. For systems containing air/gas, alternative inspections may include (a) visual inspection for discoloration when leakage from inside the piping system would discolor the external surfaces of the component; (b) monitoring and trending of pressure decay when the bolted connection is located within an isolated boundary; (c) soap bubble testing on the external mating surface of the bolted component; or (d) thermography, when the temperature of the process fluid is higher than ambient conditions around the component.
- 5. Perform additional inspections of a minimum of 20% of similar bolting or five additional inspections, whichever is less, when sample based inspections do for each sample based inspection (each bolt, etc.) that does not meet acceptance criteria. If the additional inspections identify bolting that does not meet acceptance criteria, then an extent of condition and extent of cause analysis will be conducted to determine the further extent of inspections. Additional inspections of similar bolting (same material, environment, and aging effect (s)) will be performed at all three units and will occur within the same interval in which the original inspection was conducted. The corrective action program will be used to determine if changes to inspection frequency is appropriate if any inspection results indicate that loss of function will occur prior to the next scheduled inspection.
- 6. Revise applicable procedures and specifications to ensure that the use of bolting with measured yield strength greater than or equal to 150 kilo-pounds per square inch (ksi) or 1,034 megapascals (MPa) in newly designed applications is avoided when practical engineering design considerations allow.
SLRA Appendix B2.1.9 (Page B-89) is revised as follows:
B2.1.9 BOLTING INTEGRITY Enhancements
- 5. Perform additional inspections of a minimum of 20% of similar bolting or five additional inspections, whichever is less, when sample based inspections do for each sample based inspection (each bolt, etc.) that does not meet acceptance criteria. If the additional inspections identify bolting that does not meet acceptance criteria, then an extent of condition and extent of cause analysis will be conducted to determine the further extent of inspections. Additional inspections of similar bolting (same material, environment, and aging effect (s)) will be performed at all three units and will occur within the same interval in which the original inspection was conducted. The corrective action program will be used to determine if changes to inspection frequency is appropriate if any inspection results indicate that loss of function will occur prior to the next scheduled inspection. (Element 7)
- 6. Revise applicable procedures and specifications to ensure that the use of bolting with measured yield strength greater than or equal to 150 kilo-pounds per square inch (ksi) or 1,034 megapascals (MPa) in newly designed applications is avoided when practical engineering design considerations allow. (Element 2)
Operating Experience Based on a broad search of pertinent Oconee OE, the following examples provide objective evidence that the Bolting Integrity AMP will continue to be effective in managing aging effects for SSCs within the scope of the program so that intended functions will be maintained consistent with the current licensing basis for the SPEO. This broad search included the corrective action program, metallurgical laboratory reports, programmatic inspection results and effectiveness reviews for existing AMPs.
SLRA Table A6.0-1 (Page A-76) is revised as follows:
Table A6.0-1: Subsequent License Renewal Commitments Program Commitment AMP Implementation 9
Bolting Integrity program
- 5. Perform additional inspections of a minimum of 20%
of similar bolting or five additional inspections, whichever is less, when sample based inspections do for each sample based inspection (each bolt, etc.)
that does not meet acceptance criteria. If the additional inspections identify bolting that does not meet acceptance criteria, then an extent of condition and extent of cause analysis will be conducted to determine the further extent of inspections. Additional inspections of similar bolting (same material, environment, and aging effect(s)) will be performed at all three units and will occur within the same interval in which the original inspection was conducted. The corrective action program will be used to determine if changes to inspection frequency is appropriate if any inspection results indicate that loss of function will occur prior to the next scheduled inspection.
- 6. Revise applicable procedures and specifications to ensure that the use of bolting with measured yield strength greater than or equal to 150 kilo-pounds per square inch (ksi) or 1,034 megapascals (MPa) in newly designed applications is avoided when practical engineering design considerations allow.
Steam Generators program The existing Steam Generators program is credited.
B2.1.10 Ongoing
ATTACHMENT 18 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES RESOLUTION OF STANDARD INDUSTRY NOTE B FOR COPPER ALLOY > 15% ZINC
Resolution of Standard Industry Note B for Copper Alloy > 15% Zinc (TRP-27)
Affected SLRA Section:
Table 3.3.2-4 Table 3.3.2-9 Table 3.3.2-11 Table 3.3.2-15 Table 3.3.2-18 Table 3.3.2-20 Table 3.3.2-21 Table 3.3.2-22 Table 3.3.2-24 Table 3.3.2-30 Table 3.3.2-31 Table 3.3.2-32 Table 3.3.2-40 Table 3.3.2-46 Table 3.3.2-49 Table 3.3.2-52 Table 3.3.2-54 Table 3.3.2-55 Table 3.3.2-57 Table 3.4.2-1 Table 3.4.2-2 Table 3.4.2-3 SLRA Page Numbers:
3-530 3-532 3-533 3-553 3-554 3-567 3-569 3-622 3-623 3-654 3-661 3-678 3-679 3-680 3-684 3-690 3-691 3-692 3-696
3-697 3-724 3-726 3-728 3-729 3-795 3-796 3-797 3-799 3-804 3-810 3-815 3-817 3-821 3-822 3-824 3-825 3-861 3-866 3-907 3-954 3-956 3-973 3-974 3-976 3-977 3-978 3-985 3-987 3-989 3-990 3-995 3-1011 3-1012 3-1116 3-1134 3-1144 3-1158 3-1164 3-1168 3-1176 3-1183
Description of Change:
Added a plant specific note to clarify the acceptability of matching components constructed of Copper Alloy >15% Zn to GALL SLR line items for Copper Alloy for specific aging effects.
The plant specific note states: Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-4 (page 3-530) is revised as follows:
Table 3.3.2-4 Auxiliary Systems - Instrument Air System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Copper Alloy Air - Dry (Internal)
Loss of Material Compressed Air Monitoring (B2.1.14)
VII.D.A-764 3.3.1-235 A
Air - Indoor Uncontrolled (External)
None None VII.J.AP-144 3.3.1-114 A
Condensation (Internal)
None None VII.J.AP-144 3.3.1-114 A
Copper Alloy
(>15% Zn)
Air - Dry (Internal)
Loss of Material Compressed Air Monitoring (B2.1.14)
VII.D.A-764 3.3.1-235 A
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Condensation (Internal)
None None VII.J.AP-144 3.3.1-114 A, 2,5
SLRA Table 3.3.2-4 ( page 3-532) is revised as follows:
Table 3.3.2-4 Auxiliary Systems - Instrument Air System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Structural Integrity Copper Alloy Air - Indoor Uncontrolled (External)
None None VII.J.AP-144 3.3.1-114 A
Condensation (Internal)
None None VII.J.AP-144 3.3.1-114 A
Copper Alloy
(>15% Zn)
Air - Dry (Internal)
Loss of Material Compressed Air Monitoring (B2.1.14)
VII.D.A-764 3.3.1-235 A
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Condensation (Internal)
None None VII.J.AP-144 3.3.1-114 A, 2,5
SLRA Table 3.3.2-4 (page 3-533) is revised as follows:
Plant Specific Notes:
Bubbler piping for fire water storage tank level indication has instrument air internal and raw water external within the tank. Flow blockage is not a concern for the internal air environment.
Cracking of copper alloy (>15% Zn) in indoor air could result from ammonia-based compounds conveyed to external surfaces from bolted joint leakage through insulation. However, cracking of internal surfaces is not expected as these surfaces are not exposed to contamination from external leakage sources.
Flow blockage due to fouling is not a concern for components that perform a structural integrityfunction.
The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g.
valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 5. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-9 (page 3-553) is revised as follows:
Table 3.3.2-9 Auxiliary Systems - Nitrogen Purge and Blanket System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Copper Alloy
(>15% Zn)
Gas (Internal)
None None VII.J.AP-9 3.3.1-114 A,1 Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VII.D.AP-209a 3.3.1- 004 A
Loss of Material One-Time Inspection (B2.1.20)
VII.D.AP-221a 3.3.1- 006 A
Air with Borated Water Leakage (External)
None None VII.J.AP-18 3.3.1-120 A
Gas (Internal)
None None VII.J.AP-22 3.3.1-120 A
Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.A-79 3.3.1- 009 A
Gas (Internal)
None None VII.J.AP-6 3.3.1-121 A
Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.AP-66 3.3.1- 009 A
Gas (Internal)
None None VII.J.AP-9 3.3.1-114 A,1 Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VII.D.AP-209a 3.3.1- 004 A
SLRA Table 3.3.2-9 (page 3-554) is revised as follows:
Plant Specific Notes:
- 1. None. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-11 (page 3-567) is revised as follows:
Table 3.3.2-11 Auxiliary Systems - Standby Shutdown Facility Fire Protection System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Nozzle Spray Pattern Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Condensation (Internal)
None None VII.J.AP-144 3.3.1-114 A,1,2
SLRA Table 3.3.2-11 (page 3-569) is revised as follows:
Plant Specific Notes:
- 1. Cracking of copper alloy (>15% Zn) in indoor air could result from ammonia-based compounds conveyed to external surfaces from bolted joint leakage through insulation. However, cracking of internal surfaces is not expected as these surfaces are not exposed to contamination from external leakage sources.
- 2. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-15 (page 3-622) is revised as follows:
Table 3.3.2-15 Auxiliary Systems - Demineralized Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Structural Integrity Copper Alloy
(>15% Zn)
Treated Water (Internal)
Loss of Material One-Time Inspection (B2.1.20)
VIII.F.SP-101 3.4.1- 016 A,4 Selective Leaching (B2.1.21)
VII.C2.AP-32 3.3.1- 072 A
Water Chemistry (B2.1.2)
VIII.F.SP-101 3.4.1- 016 A,4
SLRA Table 3.3.2-15 (page 3-623) is revised as follows:
Plant Specific Notes:
DW piping is Aluminum 6061-T6, which is not susceptible to SCC NUREG-2191 identifies no aging effects for PVC in a raw (potable) environment. The treated water environment is demineralized water that contains no additives. This environment is considered a match to raw (potable) for the subject material-environment-aging effect combination.
Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 4. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-18 (page 3-654) is revised as follows:
Table 3.3.2-18 Auxiliary Systems - Alternate Chilled Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Hose (stored equipment)
Pressure Boundary Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Air - Indoor Uncontrolled (Internal)
None None VII.J.AP-144 3.3.1-114 A, 1, 4
SLRA Table 3.3.2-18, (page 3-661) is revised as follows:
Plant Specific Notes:
Cracking of copper alloy (>15% Zn) in indoor air could result from ammonia-based compounds conveyed to external surfaces from bolted joint leakage through insulation. However, cracking of internal surfaces is not expected as these surfaces are not exposed to contamination from external leakage sources.
External surface of tank bladder is located inside of the tank. Therefore, the inspection is performed inside of the tank.
Hose is stored in a cabinet or trailer and protected from system leakage. Inspection of the external surface is representative of the internal surface.
- 4. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table (3.3.2-20 page 3-678) is revised as follows:
Table 3.3.2-20 Auxiliary Systems - Chilled Water (Non-Vital Loads) System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Copper Alloy Air with Borated Water Leakage (External)
None None VII.J.AP-11 3.3.1-115 A
Closed-Cycle Cooling Water (Internal)
Loss of Material Closed Treated Water System (B2.1.12)
VII.C2.AP-199 3.3.1- 046 A
Condensation (External)
None None VII.J.AP-144 3.3.1-114 A
Copper Alloy
(>15% Zn)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.AP-66 3.3.1- 009 A
Closed-Cycle Cooling Water (Internal)
Cracking Closed Treated Water System (B2.1.12)
VII.C2.A-473a 3.3.1-160 A
Loss of Material Closed Treated Water System (B2.1.12)
VII.C2.AP-199 3.3.1- 046 A,1, 3 Condensation (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
SLRA Table 3.3.2-20 (page 3-679) is revised as follows:
Table 3.3.2-20 Auxiliary Systems - Chilled Water (Non-Vital Loads) System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Stainless Steel Condensation (External)
Cracking One-Time Inspection (B2.1.20)
VII.I.A-734b 3.3.1-205 A
Loss of Material One-Time Inspection (B2.1.20)
VII.I.A-761b 3.3.1-232 A
Steel Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.A-79 3.3.1- 009 A
Closed-Cycle Cooling Water (Internal)
Loss of Material Closed Treated Water System (B2.1.12)
VII.C2.AP-202 3.3.1- 045 A
Condensation (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Structural Integrity Copper Alloy Air with Borated Water Leakage (External)
None None VII.J.AP-11 3.3.1-115 A
Closed-Cycle Cooling Water (Internal)
Loss of Material Closed Treated Water System (B2.1.12)
VII.C2.AP-199 3.3.1- 046 A
Condensation (External)
None None VII.J.AP-144 3.3.1-114 A
Copper Alloy
(>15% Zn)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.AP-66 3.3.1- 009 A
Closed-Cycle Cooling Water (Internal)
Cracking Closed Treated Water System (B2.1.12)
VII.C2.A-473a 3.3.1-160 A
Loss of Material Closed Treated Water System (B2.1.12)
VII.C2.AP-199 3.3.1- 046 A,1,3
SLRA Table 3.3.2-20 (page 3-680) is revised as follows:
Plant Specific Notes:
- 1. Material of construction is inhibited Brass which is not susceptible to selective leaching.
- 2. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 3. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-21 (page 3-684) is revised as follows:
Table 3.3.2-21 Auxiliary Systems - Recirculating Cooling Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (U0 recirculating cooling water A,B,C,D) Tubes Heat Transfer Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (External)
Reduction of Heat Transfer Closed Treated Water System (B2.1.12)
VII.C2.AP-205 3.3.1- 050 A,3 Raw Water (Internal)
Reduction of Heat Transfer Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-187 3.3.1- 042 B,3 Pressure Boundary Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (External)
Cracking Closed Treated Water System (B2.1.12)
VII.C2.A-473a 3.3.1-160 A
Loss of Material Closed Treated Water System (B2.1.12)
VII.F1.AP-203 3.3.1- 046 A,2, 3
Raw Water (Internal)
Cracking Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-473b 3.3.1-160 B
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-179 3.3.1- 038 B,2, 3
SLRA Table 3.3.2-21 (page 3-690) is revised as follows:
Table 3.3.2-21 Auxiliary Systems - Recirculating Cooling Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (Internal)
Loss of Material Closed Treated Water System (B2.1.12)
VII.C2.AP-199 3.3.1- 046 A,3 Selective Leaching (B2.1.21)
VII.C2.AP-43 3.3.1- 072 A
SLRA Table 3.3.2-21 (page 3-691) is revised as follows:
Table 3.3.2-21 Auxiliary Systems - Recirculating Cooling Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Structural Integrity Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (Internal)
Loss of Material Closed Treated Water System (B2.1.12)
VII.C2.AP-199 3.3.1- 046 A,3 SLRA Table 3.3.2-21, (page 3-692) is revised as follows:
Plant Specific Notes:
- 1. The heat exchanger plate performs the same function as a heat exchanger tube. Therefore, the component type is equivalent
- 2. Material of construction is inhibited Brass which is not susceptible to selective leaching.
- 3. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-22 (page 3-696) is revised as follows:
Table 3.3.2-22 Auxiliary Systems - Sample Cooling Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Structural Integrity Copper Alloy
(>15% Zn)
Raw Water (Potable)
(Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.E5.AP-271 3.3.1- 093 A,2 Selective Leaching (B2.1.21)
VII.G.A-47 3.3.1- 072 A
SLRA Table 3.3.2-22 (page 3-697) is revised as follows:
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-24 (page 3-724) is revised as follows:
Table 3.3.2-24 Auxiliary Systems - High Pressure Service Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Sprinkler Head Structural Integrity Copper Alloy
(>15% Zn)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.AP-66 3.3.1- 009 C
Condensation (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.G.A-649 3.3.1-197 A
Raw Water (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.C1.A-727 3.3.1-134 A,2,3 Selective Leaching (B2.1.21)
VII.C1.A-47 3.3.1- 072 C
SLRA Table 3.3.2-24 (page 3-726) is revised as follows:
Table 3.3.2-24 Auxiliary Systems - High Pressure Service Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Note s
Valve Body Pressure Boundary Copper Alloy
(>15% Zn)
Raw Water (Internal)
Loss of Material, Flow Blockage Fire Water System (B2.1.16)
VII.G.AP-197 3.3.1- 064 B,3
SLRA Table 3.3.2-24 (page 3-728) is revised as follows:
Table 3.3.2-24 Auxiliary Systems - High Pressure Service Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Structural Integrity Copper Alloy Condensation (External)
None None VII.J.AP-144 3.3.1-114 A
Raw Water (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.C1.A-727 3.3.1-134 A,2 Copper Alloy
(>15% Zn)
Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VII.I.AP-66 3.3.1- 009 A
Condensation (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Raw Water (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.C1.A-727 3.3.1-134 A,2,3 Selective Leaching (B2.1.21)
VII.C1.A-47 3.3.1- 072 A
SLRA Table 3.3.2-24 (page 3-729) is revised as follows:
Plant Specific Notes:
- 1. The EWST is internally coated/lined
- 2. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 3. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-30 (page 3-795) is revised as follows:
Table 3.3.2-30 Auxiliary Systems - Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (emergency feedwater pump turbine oil cooler)
Tubes Heat Transfer Copper Alloy
(>15% Zn)
Lubricating Oil (External)
Reduction of Heat Transfer Lubricating Oil Analysis (B2.1.25)
VII.H2.A-791 3.3.1-257 A,4 One-Time Inspection (B2.1.20)
VII.H2.A-791 3.3.1-257 A,4
SLRA Table 3.3.2-30 (page 3-796) is revised as follows:
Table 3.3.2-30 Auxiliary Systems - Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (emergency feedwater pump turbine oil cooler)
Tubes Heat Transfer Copper Alloy
(>15% Zn)
Raw Water (Internal)
Reduction of Heat Transfer Open-Cycle Cooling Water System (B2.1.11)
VII.H2.AP-187 3.3.1- 042 B,4 Pressure Boundary Copper Alloy
(>15% Zn)
Lubricating Oil (External)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.H2.AP-133 3.3.1- 099 C,4 One-Time Inspection (B2.1.20)
VII.H2.AP-133 3.3.1- 099 C,4 Raw Water (Internal)
Cracking Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-473b 3.3.1-160 B
Loss of Material Selective Leaching (B2.1.21)
VII.C1.A-66 3.3.1- 072 A
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-179 3.3.1- 038 B,4 Heat Exchanger (emergency feedwater pump turbine oil cooler)
Tubesheet Pressure Boundary Copper Alloy
(>15% Zn)
Lubricating Oil (External)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.H2.AP-133 3.3.1- 099 C,4 One-Time Inspection (B2.1.20)
VII.H2.AP-133 3.3.1- 099 C,4 Raw Water (Internal)
Cracking Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-473b 3.3.1-160 B
Loss of Material Selective Leaching (B2.1.21)
VII.C1.A-66 3.3.1- 072 A
SLRA Table 3.3.2-30 (page 3-797) is revised as follows:
Table 3.3.2-30 Auxiliary Systems - Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (emergency feedwater pump turbine oil cooler)
Tubesheet Pressure Boundary Copper Alloy
(>15% Zn)
Raw Water (Internal)
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-179 3.3.1- 038 B,4
SLRA Table 3.3.2-30 (page 3-799) is revised as follows:
Table 3.3.2-30 Auxiliary Systems - Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Piping Pressure Boundary Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.E1.AP-127 3.3.1- 097 A
One-Time Inspection (B2.1.20)
VII.E1.AP-127 3.3.1- 097 A
Structural Integrity Copper Alloy Air - Indoor Uncontrolled (External)
None None VII.J.AP-144 3.3.1-114 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.H2.AP-133 3.3.1- 099 A
One-Time Inspection (B2.1.20)
VII.H2.AP-133 3.3.1- 099 A
Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.H2.AP-133 3.3.1- 099 A,4 One-Time Inspection (B2.1.20)
VII.H2.AP-133 3.3.1- 099 A,4
SLRA Table 3.3.2-30 (page 3-804) is revised as follows:
Table 3.3.2-30 Auxiliary Systems - Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Sight Glass Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.H2.AP-133 3.3.1- 099 A,4 One-Time Inspection (B2.1.20)
VII.H2.AP-133 3.3.1- 099 A,4 SLRA Table 3.3.2-30, (page 3-810) is revised as follows:
Plant Specific Notes:
- 1. MTOT cooler heads have a localized coating type repair that will be managed with the Open Cycle Cooling Water program.
- 2. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 3. In accordance with industry best practice, the internal coating of this tank is not maintained. Therefore, loss of material of the tank base metal will be managed by the Lubricating Oil Analysis program
- 4. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-31 (page 3-815) is revised as follows:
Table 3.3.2-31 Auxiliary Systems - Keowee Turbine Guide Bearing Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Strainer Body Pressure Boundary Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.C1.AP-133 3.3.1- 099 A,1 One-Time Inspection (B2.1.20)
VII.C1.AP-133 3.3.1- 099 A,1 Strainer Screen Filtration Copper Alloy
(>15% Zn)
Lubricating Oil (External)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.C1.AP-133 3.3.1- 099 A,1 One-Time Inspection (B2.1.20)
VII.C1.AP-133 3.3.1- 099 A,1 Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.C1.AP-133 3.3.1- 099 A,1 One-Time Inspection (B2.1.20)
VII.C1.AP-133 3.3.1- 099 A,1 SLRA Table 3.3.2-31 (page 3-817) is revised as follows:
Plant Specific Notes:
- 1. None. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-32 (page 3-821) is revised as follows:
Table 3.3.2-32 Auxiliary Systems - Keowee Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Pump Casing (purified oil discharge)
Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.C1.AP-133 3.3.1- 099 C,2 One-Time Inspection (B2.1.20)
VII.C1.AP-133 3.3.1- 099 C,2
SLRA Table 3.3.2-32 (page 3-822) is revised as follows:
Table 3.3.2-32 Auxiliary Systems - Keowee Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Pump Casing (unpurified oil feed)
Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.C1.AP-133 3.3.1- 099 C,2 One-Time Inspection (B2.1.20)
VII.C1.AP-133 3.3.1- 099 C,2 Sight Glass Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.C1.AP-133 3.3.1- 099 A,2 One-Time Inspection (B2.1.20)
VII.C1.AP-133 3.3.1- 099 A,2
SLRA Table 3.3.2-32 (page 3-824) is revised as Table 3.3.2-32 Auxiliary Systems - Keowee Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.C1.AP-133 3.3.1- 099 A,2 One-Time Inspection (B2.1.20)
VII.C1.AP-133 3.3.1- 099 A,2 Waste Water (Internal)
Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.E5.A-473c 3.3.1-160 A
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.E5.AP-272 3.3.1- 095 A,1,2 SLRA Table 3.3.2-32 (page 3-825) is revised as follows:
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-40 (page 3-861) is revised as follows:
Table 3.3.2-40 Auxiliary Systems - Keowee Turbine Sump Pump System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Piping Pressure Boundary Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Air - Outdoor (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Concrete (External)
None None VII.J.A-711 3.3.1-166 A,2 Waste Water (Internal)
Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.E5.A-473c 3.3.1-160 A
Loss of Material Selective Leaching (B2.1.21)
VII.E5.A-547 3.3.1- 072 A
SLRA Table 3.3.2-40 (page 3-866) is revised as follows:
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-46 (page 3-907) is revised as follows:
Table 3.3.2-46 Auxiliary Systems - Refueling System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Structural Integrity Copper Alloy
(>15% Zn)
Treated Water (Internal)
Loss of Material One-Time Inspection (B2.1.20)
VIII.F.SP-101 3.4.1- 016 A,1 Selective Leaching (B2.1.21)
VII.C2.AP-32 3.3.1- 072 A
Water Chemistry (B2.1.2)
VIII.F.SP-101 3.4.1- 016 A,1 Stainless Steel Air - Indoor Uncontrolled (External)
Cracking One-Time Inspection (B2.1.20)
VII.C1.AP-209a 3.3.1- 004 A
Loss of Material One-Time Inspection (B2.1.20)
VII.C1.AP-221a 3.3.1- 006 A
Air with Borated Water Leakage (External)
None None VII.J.AP-18 3.3.1-120 A
Treated Water (Internal)
Loss of Material One-Time Inspection (B2.1.20)
VIII.G.SP-87 3.4.1- 085 A
Water Chemistry (B2.1.2)
VIII.G.SP-87 3.4.1- 085 A
Plant Specific Notes:
- 1. None. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-49 (page 3-954) is revised as follows:
Table 3.3.2-49 Auxiliary Systems - Low Pressure Service Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Steel Raw Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VII.C1.A-532 3.3.1-193 A
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-194 3.3.1- 037 B
Structural Integrity Copper Alloy Air - Indoor Uncontrolled (External)
None None VII.J.AP-144 3.3.1-114 A
Air with Borated Water Leakage (External)
None None VII.J.AP-11 3.3.1-115 A
Raw Water (Internal)
Loss of Material Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-196 3.3.1- 034 B,1 Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Raw Water (Internal)
Cracking Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-473b 3.3.1-160 B
Loss of Material Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-196 3.3.1- 034 B,1,4 Selective Leaching VII.C1.A-47 3.3.1- 072 A
SLRA Table 3.3.2-49 (page 3-956) is revised as follows:
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 3. Stored equipment used for alternate Reactor Building Cooling is located in a hose trailer and in the yard. Those components stored within the hose trailer are evaluated with an air-indoor uncontrolled environment while those stored in the yard are evaluated with an air-outdoor environment.
- 4. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-52 (page 3-973) is revised as follows:
Table 3.3.2-52 Auxiliary Systems - Keowee Turbine Generator Cooling Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Piping Pressure Boundary Copper Alloy Air - Indoor Uncontrolled (External)
None None VII.J.AP-144 3.3.1-114 A
Raw Water (Internal)
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-196 3.3.1- 034 B
Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Raw Water (Internal)
Cracking Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-473b 3.3.1-160 B
Loss of Material Selective Leaching (B2.1.21)
VII.C1.A-47 3.3.1- 072 A
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-196 3.3.1- 034 B,2
SLRA Table 3.3.2-52 (page 3-974) is revised as follows:
Table 3.3.2-52 Auxiliary Systems - Keowee Turbine Generator Cooling Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Piping Pressure Boundary Stainless Steel Raw Water (Internal)
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-54 3.3.1- 040 B
Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A
Concrete (External)
None None VII.J.AP-282 3.3.1-112 A
Raw Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VII.C1.A-532 3.3.1-193 A
Loss of Material Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-400a 3.3.1-127 B
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-194 3.3.1- 037 B
Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Raw Water (Internal)
Cracking Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-473b 3.3.1-160 B
Loss of Material Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-196 3.3.1- 034 B,1,2 Selective Leaching (B2.1.21)
VII.C1.A-47 3.3.1- 072 A
SLRA Table 3.3.2-52 (page 3-976) is revised as follows:
Table 3.3.2-52 Auxiliary Systems - Keowee Turbine Generator Cooling Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Copper Alloy Air - Indoor Uncontrolled (External)
None None VII.J.AP-144 3.3.1-114 A
Raw Water (Internal)
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-196 3.3.1- 034 B
Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Raw Water (Internal)
Cracking Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-473b 3.3.1-160 B
Loss of Material Selective Leaching (B2.1.21)
VII.C1.A-47 3.3.1- 072 A
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-196 3.3.1- 034 B,2 SLRA Table 3.3.2-52 (page 3-977) is revised as follows:
Table 3.3.2-52 Auxiliary Systems - Keowee Turbine Generator Cooling Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Copper Alloy
(>8% Al)
Raw Water (Internal)
Loss of Material Selective Leaching (B2.1.21)
VII.C1.A-47 3.3.1- 072 A
Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-196 3.3.1- 034 B,2
SLRA Table 3.3.2-52 (page 3-978) is revised as follows:
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-54 (page 3-985) is revised as follows:
Table 3.3.2-54 Auxiliary Systems - Standby Shutdown Facility Diesel Jacket Water Cooling System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (jacket water) Tubes Heat Transfer Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (External)
Reduction of Heat Transfer Closed Treated Water System (B2.1.12)
VII.C2.AP-205 3.3.1- 050 A,1,2 Raw Water (Internal)
Reduction of Heat Transfer Open-Cycle Cooling Water System (B2.1.11)
VII.H2.AP-187 3.3.1- 042 B,1,2 Pressure Boundary Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (External)
Cracking Closed Treated Water System (B2.1.12)
VII.C2.A-473a 3.3.1-160 A, 1 Loss of Material Closed Treated Water System (B2.1.12)
VII.E1.AP-203 3.3.1- 046 A,1,2 Raw Water (Internal)
Cracking Open-Cycle Cooling Water System (B2.1.11)
VII.C1.A-473b 3.3.1-160 B, 1 Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-179 3.3.1- 038 B,1,2
SLRA Table 3.3.2-54 (page 3-987) is revised as follows:
Plant Specific Notes:
- 1. Material of construction is inhibited Brass which is not susceptible to selective leaching.
- 2. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-55 (page 3-989) is revised as follows:
Table 3.3.2-54 Auxiliary Systems - Standby Shutdown Facility Diesel Jacket Water Cooling System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (lube oil) Tubes Heat Transfer Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (Internal)
Reduction of Heat Transfer Closed Treated Water System (B2.1.12)
VII.C2.AP-205 3.3.1- 050 A,1,3 Lubricating Oil (External)
Reduction of Heat Transfer Lubricating Oil Analysis (B2.1.25)
VII.H2.A-791 3.3.1-257 A,3 One-Time Inspection (B2.1.20)
VII.H2.A-791 3.3.1-257 A,3 Pressure Boundary Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (Internal)
Cracking Closed Treated Water System (B2.1.12)
VII.C2.A-473a 3.3.1-160 A, 1 Loss of Material Closed Treated Water System (B2.1.12)
VII.E1.AP-203 3.3.1- 046 A,1,3 Lubricating Oil (External)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VII.H2.AP-133 3.3.1- 099 A,3
SLRA Table 3.3.2-55 (page 3-990) is revised as follows:
Table 3.3.2-55 Auxiliary Systems - Standby Shutdown Facility Diesel Lube Oil System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (lube oil) Tubes Pressure Boundary Copper Alloy
(>15% Zn)
Lubricating Oil (External)
Loss of Material One-Time Inspection (B2.1.20)
VII.H2.AP-133 3.3.1- 099 A,3 SLRA Table 3.3.2-55 (page 3-995) is revised as follows:
Plant Specific Notes:
- 1. Material of construction is inhibited Brass which is not susceptible to selective leaching.
- 2. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 3. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match.
Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.3.2-57 (page 3-1011) is revised as follows:
3.3.2-57 Auxiliary Systems - Standby Shutdown Facility Starting Air System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Valve Body Pressure Boundary Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 A
Condensation (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.D.A-26 3.3.1- 055 A
Zinc Air - Indoor Uncontrolled (External)
None None VII.J.A-712 3.3.1-167 A
Condensation (Internal)
None None VII.J.A-712 3.3.1-167 A
Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-405a 3.3.1-132 A
Condensation (Internal)
None None VII.J.AP-144 3.3.1-114 A,1,3
SLRA Table 3.3.2-57 (page 3-1012) is revised as follows:
Plant Specific Notes:
- 1. Cracking of copper alloy (>15% Zn) in indoor air could result from ammonia-based compounds conveyed to external surfaces from bolted joint leakage through insulation. However, cracking of internal surfaces is not expected as these surfaces are not exposed to contamination from external leakage sources.
- 2. The compressor skid functions as an equivalent anchor for non-safety attached to safety piping.
- 3. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match.
Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.4.2-1 (page 3-1116) is revised as follows:
Table 3.4.2-1 Steam and Power Conversion Systems - Condensate System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (condensate booster pump oil cooler)
Head Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-454 3.4.1-106 C
Closed-Cycle Cooling Water (Internal)
Cracking Closed Treated Water System (B2.1.12)
VII.C2.A-473a 3.3.1-160 A
Loss of Material Closed Treated Water System (B2.1.12)
VIII.E.SP-8 3.4.1- 027 C,4
SLRA Table 3.4.2-1 (page 3-1134) is revised as follows:
Table 3.4.2-1 Steam and Power Conversion Systems - Condensate System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Sight Glass Pressure Boundary Stainless Steel Treated Water >60°C
(>140°F) (Internal)
Cracking One-Time Inspection (B2.1.20)
VIII.E.SP-88 3.4.1- 011 A
Water Chemistry (B2.1.2)
VIII.E.SP-88 3.4.1- 011 A
Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-454 3.4.1-106 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VIII.E.SP-92 3.4.1- 043 A,4 One-Time Inspection (B2.1.20)
VIII.E.SP-92 3.4.1- 043 A,4 Treated Water (Internal)
Loss of Material One-Time Inspection (B2.1.20)
VIII.F.SP-101 3.4.1- 016 A,4 Selective Leaching (B2.1.21)
VIII.E.SP-55 3.4.1- 033 A
Water Chemistry (B2.1.2)
VIII.F.SP-101 3.4.1- 016 A,4 Page
SLRA Table 3.4.2-1 (page 3-1144) is revised as follows:
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. Internal surfaces of the main condenser outlet waterboxes and tubesheets will be managed with the Open Cycle Cooling Water AMP.
- 3. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 4. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match.
Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.4.2-2 (page 3-1158) is revised as follows:
Table 3.4.2-2 Steam and Power Conversion Systems - Feedwater System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Sight Glass Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-454 3.4.1-106 A
Treated Water (Internal)
Loss of Material One-Time Inspection (B2.1.20)
VIII.F.SP-101 3.4.1- 016 A,3 Selective Leaching (B2.1.21)
VIII.E.SP-55 3.4.1- 033 A
Water Chemistry (B2.1.2)
VIII.F.SP-101 3.4.1- 016 A,3
SLRA Table 3.4.2-2 (page 3-1164) is revised as follows:
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 3. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match.
Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
SLRA Table 3.4.2-3 (page 3-1168) is revised as follows:
Table 3.4.2-3 Steam and Power Conversion Systems - Heater Drain System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Heat Exchanger (E heater drain pump oil cooler)
Head Structural Integrity Copper Alloy
(>15% Zn)
Closed-Cycle Cooling Water (Internal)
Loss of Material Closed Treated Water System (B2.1.12)
VIII.E.SP-8 3.4.1- 027 C,3 Selective Leaching (B2.1.21)
VIII.F.SP-29 3.4.1- 033 C
SLRA Table 3.4.2-3 (Page 3-1176) is revised as follows:
Table 3.4.2-3 Steam and Power Conversion Systems - Heater Drain System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item 2192 Table 1 Notes Sight Glass Structural Integrity Copper Alloy
(>15% Zn)
Air - Indoor Uncontrolled (External)
Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-454 3.4.1-106 A
Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VIII.E.SP-92 3.4.1- 043 A,3 One-Time Inspection (B2.1.20)
VIII.E.SP-92 3.4.1- 043 A,3 SLRA Table 3.4.2-3 (page 3-1183) is revised as follows:
Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 3. Components constructed of Copper Alloy and Copper Alloy >15% Zn share common aging effects. For Copper Alloy >15% Zn components, these common aging effects are managed by aligning to a GALL SLR item for Copper Alloy as a direct match. Unique aging effects applicable only to components constructed of Copper Alloy >15% Zn, are managed by aligning to a GALL SLR line item specific to Copper Alloy >15% Zn.
ATTACHMENT 19 OCONEE NUCLEAR STATION SUBSEQUENT LICENSE RENEWAL APPLICATION SLRA UPDATES UPDATE TO FLOW-ACCELERATED CORROSION AMP
Update to Flow-Accelerated Corrosion Aging Management Program (TRP-17)
Affected SLRA Sections:
Tables 3.1.2-4, 3.3.1, 3.3.2-48, 3.3.2-49, 3.4.2-1, 3.4.2-3, 3.4.2-7, 3.4.2-10 Sections 3.3.2.1.48, 3.3.2.1.49, A2.8, B2.1.8 SLRA Page Numbers:
3-201, 3-411, 3-413, 3-475, 3-928, 3-949, 3-1126, 3-1127, 3-1144, 3-1172, 3-1173, 3-1183, 3-1212, 3-1217, 3-1236, 3-1241, A-9, B-82 Description of Change:
- 1. Delete wall thinning due to FAC as an aging effect for the Steam Outlet Nozzle component in the Steam Generators Aging Management Review table (3.1.2-4).
- 2. Recognize wall thinning due to erosion as an aging effect requiring management via the FAC AMP for the LPS and CCW systems.
- 3. Clarify that component materials in FAC and erosion susceptible systems include gray cast iron components and copper alloy components. For Plant Heating System, add Stainless Steel Piping and Piping Components in Treated Water as susceptible to wall thinning due to erosion.
- 4. Provide consistent wording in Appendices A (Section A2.8) and B (Section B2.1.8) for the FAC program description (e) evaluating and trending
- 5. Revise the applicable environments identified in Appendix B, Section B2.1.8 for components susceptible to wall thinning due to FAC.
SLRA Table 3.1.2-4 (page 3-201) is revised as follows:
Table 3.1.2-4 Reactor Vessel, Reactor Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Steam Outlet Nozzle Pressure Steel Steam (Internal)
Loss of Material One-Time Inspection (B2.1.20)
IV.D2.RP-153 3.1.1- 083 Water Chemistry (B2.1.2)
IV.D2.RP-153 3.1.1- 083 Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
IV.D2.R-38 3.1.1- 061 Tube Plugs Pressure Nickel Alloy Reactor Coolant (External)
Cracking Steam Generators (B2.1.10)
IV.D2.R-40 3.1.1- 070 Water Chemistry (B2.1.2)
IV.D2.R-40 3.1.1- 070 Cumulative Fatigue Damage TLAA IV.D2.R-46 3.1.1- 002 Loss of Material Water Chemistry (B2.1.2)
IV.C2.RP-23 3.1.1- 088 Tube Support Plate Assembly (spacers, nuts, keys, and wedges)
Structural Support Steel Secondary Feedwater (External)
Cumulative Fatigue Damage TLAA IV.D2.R-33 3.1.1- 005 Loss of Material Steam Generators (B2.1.10)
IV.D2.RP-162 3.1.1- 072 Water Chemistry (B2.1.2)
IV.D2.RP-162 3.1.1- 072 Tube Support Plate Assembly (support rods)
Structural Support Stainless Steel Secondary Feedwater (External)
Cracking Steam Generators (B2.1.10)
SLRA Section 3.3.2.1.48 (page 3-411) is revised as follows:
Cracking Cumulative Fatigue Damage Flow Blockage Hardening or Loss of Strength Long-Term Loss of Material Loss of Coating or Lining Integrity Loss of Material Loss of Preload Reduction of Heat Transfer Wall Thinning Aging Management Programs The aging effects for components in the Condenser Circulating Water System are managed by the following AMPs:
- Bolting Integrity (B2.1.9)
- Boric Acid Corrosion (B2.1.4)
- Buried and Underground Piping and Tanks (B2.1.26)
- External Surfaces Monitoring of Mechanical Components (B2.1.23)
Flow-Accelerated Corrosion (B2.1.8)
Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.27)
- One-Time Inspection (B2.1.20)
- Open-Cycle Cooling Water System (B2.1.11)
Selective Leaching (B2.1.21)
SLRA Section 3.3.2.1.499 (page 3-413) is revised as follows:
Aging Effects Requiring Management Components in the Low Pressure Service Water System require aging management to address the following aging effects:
Cracking Cumulative Fatigue Damage Flow Blockage Hardening or Loss of Strength Long-Term Loss of Material Loss of Coating or Lining Integrity Loss of Material Loss of Preload Wall Thinning Aging Management Programs The aging effects for components in the Low Pressure Service Water System are managed by the following AMPs:
- Bolting Integrity (B2.1.9)
- Boric Acid Corrosion (B2.1.4)
- Compressed Air Monitoring (B2.1.14)
- External Surfaces Monitoring of Mechanical Components (B2.1.23)
Flow-Accelerated Corrosion (B2.1.8)
Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
- Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.27)
- One-Time Inspection (B2.1.20)
- Open-Cycle Cooling Water System (B2.1.11)
- Selective Leaching (B2.1.21)
SLRA Table 3.3.1 (page 3-475) is revised as follows:
Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL-SLR Report Item Number Component Aging Effect/
Mechanism Aging Management Program Further Evaluation Recommended Discussion 3.3.1-126 Metallic piping, piping components exposed to treated water, treated borated water, raw water Wall thinning due to erosion AMP XI.M17, Flow-Accelerated Corrosion No Not applicable. Wall thinning due to erosion has not been identified as an applicable aging effect in ONS metallic piping, piping components exposed to treated water, treated borated water, or raw water in the scope of SLR in auxiliary systems. The associated NUREG-2191 aging items are not used. Consistent with NUREG-2191.
SLRA Table 3.3.2-48 (page 3-928) is revised as follows:
Table 3.3.2-48 Auxiliary Systems - Condenser Circulating Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping Integrity Steel with Internal Raw Water (Internal)
Loss of Material Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.27)
VII.C1.A-414 3.3.1-139 Piping and Piping Components Pressure Steel Raw Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VII.C1.A-409 3.3.1-126 Integrity Steel Raw Water (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-34 3.3.1- 002 A,3 Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VII.C1.A-409 3.3.1-126 Pump Casing (chiller service water)
Structural Integrity Gray Cast Iron Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 Raw Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VII.C1.A-532 3.3.1-193 Loss of Material Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-194 3.3.1- 037 B,1 Selective Leaching (B2.1.21)
VII.C1.A-51 3.3.1- 072
SLRA Table 3.3.2-49 (page 3-949) is revised as follows:
Table 3.3.2-49 Auxiliary Systems - Low Pressure Service Water System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping (stored equipment)
Pressure Steel Air - Outdoor (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.F3.A-722 3.3.1-157 A,3 Piping and Piping Components Pressure Stainless Steel Raw Water (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-57 3.3.1- 002 A,2 Steel Raw Water (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-34 3.3.1- 002 A,2 Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VII.C1.A-409 3.3.1-126 Structural Integrity Steel Raw Water (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-34 3.3.1- 002 A,2 Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VII.C1.A-409 3.3.1-126 Pump Casing (chiller condenser service water)
Pressure Gray Cast Iron Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VII.I.A-77 3.3.1- 078 Raw Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VII.C1.A-532 3.3.1-193 Loss of Material Selective Leaching (B2.1.21)
VII.C1.A-51 3.3.1- 072 Loss of Material, Flow Blockage Open-Cycle Cooling Water System (B2.1.11)
VII.C1.AP-194 3.3.1- 037
SLRA Table 3.4.2-1 (page 3-1126) is revised as follows:
Table 3.4.2-1 Steam and Power Conversion Systems - Condensate System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping Structural Integrity Steel Air (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VIII.E.SP-60 3.4.1- 037 Treated Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VIII.E.S-432 3.4.1- 081 Loss of Material One-Time Inspection (B2.1.20)
VIII.E.SP-73 3.4.1- 014 Water Chemistry (B2.1.2)
VIII.E.SP-73 3.4.1- 014 Waste Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VII.E5.A-785 3.3.1-193 Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.E5.AP-281 3.3.1- 091 A,1 Piping and Piping Components Pressure Stainless Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-408 3.4.1- 060 A,3 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-57 3.3.1- 002 A,3 Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-16 3.4.1- 005 A,3,4 VIII.D1.S-408 3.4.1- 060 A,3,4
SLRA Table 3.4.2-1 (page 3-1127) is revised as follows:
Table 3.4.2-1 Steam and Power Conversion Systems - Condensate System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping and Piping Components Pressure Steel Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VIII.D1.S-11 3.4.1- 001 A,3 Structural Integrity Stainless Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-408 3.4.1- 060 A,3 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-57 3.3.1- 002 A,3 Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-16 3.4.1- 005 A,3,4 VIII.D1.S-408 3.4.1- 060 A,3,4 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VIII.D1.S-11 3.4.1- 001 A,3 Pump Casing (auxiliary boiler feed)
Structural Integrity Gray Cast Iron Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034 Treated Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VIII.E.S-432 3.4.1- 081 Loss of Material One-Time Inspection (B2.1.20)
VIII.E.SP-73 3.4.1- 014 Selective Leaching (B2.1.21)
VIII.E.SP-27 3.4.1- 033 Water Chemistry (B2.1.2)
VIII.E.SP-73 3.4.1- 014
SLRA Table 3.4.2-1 (page 3-1144) is revised as follows Table 3.4.2-1 Steam and Power Conversion Systems - Condensate System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Valve Body Structural Integrity Steel Waste Water (Internal)
Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.24)
VII.E5.AP-281 3.3.1- 091 A,1 Steel w. Nickel Plating Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034 Treated Water (Internal)
Loss of Material One-Time Inspection (B2.1.20)
VIII.E.SP-87 3.4.1- 085 Water Chemistry (B2.1.2)
VIII.E.SP-87 3.4.1- 085 Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. Internal surfaces of the main condenser outlet waterboxes and tubesheets will be managed with the Open Cycle Cooling Water AMP.
- 3. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 4. Steel Piping and Piping Components that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) includes components constructed of carbon steel and gray cast iron.
SLRA Table 3.4.2-3 (Page 1172) is revised as follows:
Table 3.4.2-3 Steam and Power Conversion Systems - Heater Drain System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping Structural Integrity Stainless Steel Treated Water >60°C
(>140°F) (Internal)
Cracking Water Chemistry (B2.1.2)
VIII.E.SP-88 3.4.1- 011 Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034 Treated Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VIII.E.S-432 3.4.1- 081 Loss of Material One-Time Inspection (B2.1.20)
VIII.E.SP-73 3.4.1- 014 Water Chemistry (B2.1.2)
VIII.E.SP-73 3.4.1- 014 Piping and Piping Components Pressure Stainless Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-408 3.4.1- 060 A,2 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-57 3.3.1- 002 A,2 Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-16 3.4.1- 005 A,2,3 VIII.D1.S-408 3.4.1- 060 A,2,3 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VIII.D1.S-11 3.4.1- 001 A,2 Structural Integrity Stainless Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-408 3.4.1- 060 A,2 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-57 3.3.1- 002 A,2
SLRA Table 3.4.2-3 (page 3-1173) is revised as follows:
Table 3.4.2-3 Steam and Power Conversion Systems - Heater Drain System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping and Piping Components Structural Integrity Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-16 3.4.1- 005 A,2,3 VIII.D1.S-408 3.4.1- 060 A,2,3 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VIII.D1.S-11 3.4.1- 001 A,2 Pump Casing (E heater drain pump auxiliary oil)
Structural Integrity Gray Cast Iron Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034 Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VIII.E.SP-91 3.4.1- 040 One-Time Inspection (B2.1.20)
VIII.E.SP-91 3.4.1- 040 Pump Casing (E heater drain shaft driven main oil)
Structural Integrity Gray Cast Iron Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034 Lubricating Oil (Internal)
Loss of Material Lubricating Oil Analysis (B2.1.25)
VIII.E.SP-91 3.4.1- 040 One-Time Inspection (B2.1.20)
VIII.E.SP-91 3.4.1- 040 Pump Casing (E heater drain)
Structural Integrity Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034
SLRA Table 3.4.2-3 (Page 3-1183) is revised as follows Table 3.4.2-3 Steam and Power Conversion Systems - Heater Drain System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Valve Body Structural Integrity Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034 Treated Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VIII.E.S-432 3.4.1- 081 Loss of Material One-Time Inspection (B2.1.20)
VIII.E.SP-73 3.4.1- 014 Water Chemistry (B2.1.2)
VIII.E.SP-73 3.4.1- 014 Plant Specific Notes:
- 1. Flow blockage due to fouling is not a concern for components that perform a structural integrity function.
- 2. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 3. Steel Piping and Piping Components that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) includes components constructed of carbon steel and gray cast iron.
SLRA Table 3.4.2-7 (Page 3-1212) is revised as Follows:
Table 3.4.2-7 Steam and Power Conversion Systems - Auxiliary Steam System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping and Piping Components Pressure Stainless Steel Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-57 3.3.1- 002 A,1 Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-16 3.4.1- 005 A,1,2 VIII.D1.S-408 3.4.1- 060 A,1,2 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VIII.B1.S-08 3.4.1- 001 A,1 Structural Integrity Stainless Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-408 3.4.1- 060 A,1 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VII.E1.A-57 3.3.1- 002 A,1 Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-16 3.4.1- 005 A,1,2 VIII.D1.S-408 3.4.1- 060 A,1,2 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VIII.B1.S-08 3.4.1- 001 A,1 Sight Glass Structural Integrity Glass Air - Indoor Uncontrolled (External)
None None VIII.I.SP-33 3.4.1- 055 Treated Water (Internal)
None None VIII.I.SP-35 3.4.1- 055 Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034
SLRA Table 3.4.2-7 (page 3-1217) is revised as follows:
Table 3.4.2-7 Steam and Power Conversion Systems - Auxiliary Steam System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Plant Specific Notes:
- 1. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 2. Steel Piping and Piping Components that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) includes components constructed of carbon steel and gray cast iron.
SLRA Table 3.4.2-10 (page 3-1236) is revised as follows:
Table 3.4.2-10 Steam and Power Conversion Systems - Plant Heating System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Piping Structural Integrity Steel Treated Water (Internal)
Loss of Material One-Time Inspection (B2.1.20)
VIII.B1.SP-74 3.4.1- 014 Water Chemistry (B2.1.2)
VIII.B1.SP-74 3.4.1- 014 Piping and Piping Components Pressure Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-16 3.4.1- 005 A,1,2 VIII.D1.S-408 3.4.1- 060 A,1,2 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VIII.B1.S-08 3.4.1- 001 A,1 Stainless Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-408 3.4.1- 060 A,1 Structural Integrity Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-16 3.4.1- 005 A,1,2 VIII.D1.S-408 3.4.1- 060 A,1,2 Treated Water >60°C
(>140°F) (Internal)
Cumulative Fatigue Damage TLAA VIII.B1.S-08 3.4.1- 001 A,1 Stainless Steel Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-408 3.4.1- 060 A,1 Copper Alloy Treated Water (Internal)
Wall Thinning Flow-Accelerated Corrosion (B2.1.8)
VIII.D1.S-408 3.4.1- 060 A,1 Strainer Body Structural Integrity Gray Cast Iron Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034 Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VIII.H.S-30 3.4.1- 004 Treated Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VIII.A.S-432 3.4.1- 081 Loss of Material One-Time Inspection (B2.1.20)
VIII.B1.SP-74 3.4.1- 014
SLRA Table 3.4.2-10 (page 3-1241) is revised as follows:
Table 3.4.2-10 Steam and Power Conversion Systems - Plant Heating System - Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Aging Management Program NUREG-2191 Item NUREG-2192 Table 1 Notes Valve Body Structural Integrity Stainless Steel Treated Water >60°C
(>140°F) (Internal)
Cracking One-Time Inspection (B2.1.20)
VIII.B1.SP-88 3.4.1- 011 Water Chemistry (B2.1.2)
VIII.B1.SP-88 3.4.1- 011 Steel Air - Indoor Uncontrolled (External)
Loss of Material External Surfaces Monitoring of Mechanical Components (B2.1.23)
VIII.H.S-29 3.4.1- 034 Air with Borated Water Leakage (External)
Loss of Material Boric Acid Corrosion (B2.1.4)
VIII.H.S-30 3.4.1- 004 Treated Water (Internal)
Long-Term Loss of Material One-Time Inspection (B2.1.20)
VIII.A.S-432 3.4.1- 081 Loss of Material One-Time Inspection (B2.1.20)
VIII.B1.SP-74 3.4.1- 014 Water Chemistry (B2.1.2)
VIII.B1.SP-74 3.4.1- 014 Plant Specific Notes:
- 1. The terminology Piping and Piping Components represents pipes, pipe fittings (reducers, elbows, tees, etc), and in-line piping components (e.g. valves, traps, strainers, orifices, flow elements, etc.) and is used to identify components with the system that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) or cumulative fatigue damage. Component susceptibility to these aging effects is determined by susceptibility analyses, operating experience, or system design.
- 2. Steel Piping and Piping Components that are susceptible to wall thinning (due to erosion or flow accelerated corrosion) includes components constructed of carbon steel and gray cast iron.
SLRA Section A2.8 (page A-9) is revised as follows:
components will continue to be fulfilled for all licensing basis loads and events. Engineering evaluations used to disposition an examination result that does not meet the examination acceptance criteria will be conducted in accordance with NRC approved evaluation methods.
Enhancements The following enhancement(s) will be implemented:
- 1. The PWR Vessel Internals AMP will be updated as necessary to provide guidance for implementing the changes to primary and expansion items in MRP-227, Rev 1-A, Tables 4-1, 4-4 (and Table 5-1 for Element 6 only), as modified by the ONS gap analysis reported in Appendix B2.1.7. (Elements 4 and 6)
A2.8 Flow-Accelerated Corrosion Program Description The Flow-Accelerated Corrosion AMP is an existing condition monitoring program that manages wall thinning caused by flow-accelerated corrosion. The program is based on commitments made in response to NRC GL 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning, and relies on implementation of the EPRI guidelines in the Nuclear Safety Analysis Center (NSAC)-
202L, Revision 4 for an effective flow-accelerated corrosion program.
CHECWORKSTM is used to predict component wear rates and remaining service life in the systems susceptible to flow-accelerated corrosion which provides reasonable assurance that structural integrity will be maintained between inspections. The CHECWORKSTM model is evaluated and updated as required to reflect any significant changes in plant operating parameters such as power uprates to ensure continued accurate modeling and wear rate prediction. This improves the predictive capability of the model to ensure that intended functions are maintained.
The program also manages wall thinning caused by mechanisms other than flow-accelerated corrosion in situations where periodic monitoring is used in lieu of eliminating the cause of various erosion mechanisms.
The program includes: (a) identifying all susceptible piping systems and components; (b) developing flow-accelerated corrosion predictive models to reflect component geometries, materials, and operating parameters; (c) performing analysis of flow-accelerated corrosion models and, with consideration of OE, selecting a sample of components for inspections; (d) inspecting components; (e) evaluating and trending inspection data against acceptance criteria to determine the need for corrective actions including inspection sample expansion, repairs, or replacements, and to schedule future inspections; and (f) incorporating inspection data to refine flow-accelerated corrosion models.
SLRA Section B2.1.8 (page B-82) is revised as follows:
B2.1.8 FLOW-ACCELERATED CORROSION Program Description The Flow-Accelerated Corrosion AMP is an existing condition monitoring program that manages wall thinning caused by flow-accelerated corrosion in carbon steel piping and piping components exposed to reactor coolant, steam, secondary feedwater and treated water environments. The program is based on commitments made in response to NRC GL 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning, and relies on implementation of the Electric Power Research Institute (EPRI) guidelines in the Nuclear Safety Analysis Center (NSAC)-
202L, Revision 4 for an effective flow-accelerated corrosion program.
CHECWORKS' is used to predict component wear rates and remaining service life in the systems susceptible to flow-accelerated corrosion which provides reasonable assurance that structural integrity will be maintained between inspections. The model is revised if any changes in operating conditions or other factors that affect flow-accelerated corrosion (e.g.,
plant chemistry, power uprate) have occurred since the model was last updated. Changes may also result from plant modifications that effect flow-accelerated corrosion behavior such as material changes, the addition of piping systems, piping system configuration changes, and the addition or replacement of in-line components. The CHECWORKS' model is also refined by importing actual volumetric inspection data thickness measurements and re-running wear rate analyses. This improves the predictive capability of the model to ensure that intended functions are maintained.
The program also manages wall thinning caused by mechanisms other than flow-accelerated corrosion in carbon copper alloy, steel and stainless steel piping and piping components exposed to raw water, treated water and treated borated water environments in situations where periodic monitoring is used in lieu of eliminating the cause of various erosion mechanisms.
The program includes: (a) identifying all susceptible piping systems and components; (b) developing flow-accelerated corrosion predictive models to reflect component geometries, materials, and operating parameters; (c) performing analysis of flow-accelerated corrosion models and, with consideration of OE, selecting a sample of components for inspections; (d) inspecting components; (e) evaluating and trending inspection data against acceptance criteria to determine the need for corrective actions including for inspection sample expansion, repairs, or replacements, and to schedule future inspections; and (f) incorporating inspection data to refine flow-accelerated corrosion models.
Flow-accelerated corrosion inspections and inspections performed for wall thinning caused by mechanisms other than flow-accelerated corrosion that do not meet acceptance criteria are evaluated in accordance with the corrective action program.
NUREG-2191 Consistency The Flow-Accelerated Corrosion AMP is an existing program that will be consistent with the ten elements of AMP XI.M17, Flow Accelerated Corrosion specified in NUREG-2191 with the enhancement described below.