|
|
Line 23: |
Line 23: |
| Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.Respectfully, George H. Gellrich Site Vice President Document Control Desk September 19, 2014 Page 2 CERTIFICATION: | | Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.Respectfully, George H. Gellrich Site Vice President Document Control Desk September 19, 2014 Page 2 CERTIFICATION: |
| I, George H. Gellrich, certify that I am Vice President-Calvert Cliffs Nuclear Power Plant, LLC, and that the information contained in this submittal accurately presents changes made since the previous submittal, necessary to reflect information and analyses submitted to the Commission or prepared pursuant to Commission requirement. | | I, George H. Gellrich, certify that I am Vice President-Calvert Cliffs Nuclear Power Plant, LLC, and that the information contained in this submittal accurately presents changes made since the previous submittal, necessary to reflect information and analyses submitted to the Commission or prepared pursuant to Commission requirement. |
| GHG/BJD/bjd Attachments: | | GHG/BJD/bjd Attachments: |
| (1) Changes to Commitments Made to the Nuclear Regulatory Commission (2) Report Consistent with 10 CFR 54.37(b) on How Aging Effects for Newly-Identified Structures, Systems, or Components are Managed | | (1) Changes to Commitments Made to the Nuclear Regulatory Commission (2) Report Consistent with 10 CFR 54.37(b) on How Aging Effects for Newly-Identified Structures, Systems, or Components are Managed |
|
| |
|
|
---|
Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML21278A2832021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.18, Fuel Handling Incident ML21278A2602021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 13, Section 13.4, Post-Refueling Startup Event ML21278A2692021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.9, Loss-of-Coolant Flow Event ML21278A3042021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 16, Table 16.1, Aging Management Programs (Amp), Indexed by LRA Section and System ML22115A0432021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 02, Section 2.2, Population and Land Use_Redacted ML22115A0462021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 9, Figures 9.1 Through 9.30_Redacted ML21278A3022021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 16, Section 16.5, References ML21278A2932021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.22, Waste Gas Incident ML21278A2962021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 16, Section 16.4, 10 CFR 54.67(B) Update ML21278A3032021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 16, Section 16.3, Evaluation of Time-Limited Aging Analyses ML22115A0472021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 10, Appendix 10A Figure 10A.1-1, Main Steam System: Redacted ML21278A2852021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.21, Deleted ML21278A2872021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.15, Steam Generator Tube Rupture Event ML21278A2912021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.26, Feedline Break Event ML21278A2552021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.1, Organization and Methodology ML21278A2762021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations, Table of Contents ML21278A2802021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 15, Table of Contents ML21278A2842021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.16, Seized Rotor Event ML21278A2922021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.23, Waste Processing System Incident ML21278A2712021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.7, Excess Feedwater Heat Removal Event ML21278A2742021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.12, Asymmetric Steam Generator Event ML21278A2672021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.10, Loss-Of-Non-Emergency AC Power ML21278A2622021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 12, Figures, Deleted ML21278A2642021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.6, Loss of Feedwater Flow Event ML21278A2682021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.8, Reactor Coolant System Depressurization ML21278A2752021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.2, Control Element Assembly Withdrawal Event ML21278A2612021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.14, Steam Line Break Event ML21278A2772021-09-0707 September 2021 2 to Final Safety Analysis Report, Chapter 14, Safety Analysis, Table of Contents ML21278A2532021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.5, Loss of Load Event ML21278A2522021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 11, Section 11.3, Radiation Safety ML22115A0482021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 11, Figures: Redacted ML21278A2892021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.24, Maximum Hypothetical Accident ML21278A2572021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 13, Initial Tests and Operation, Table of Contents ML21278A2662021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 13, Section 13.0, Initial Tests and Operation ML21278A2992021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 16, Section 16.1, Introduction ML22115A0422021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 1, Figures: Redacted ML21278A2822021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14 Section 14.25, Excessive Charging Event ML21278A2862021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Figures 14.2.1 Through 14.26-10 ML21278A2702021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 12, Section 12.5, Review and Audit of Operations ML21278A2542021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.11, Control Element Assembly Drop Event ML21278A2562021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 12, Section 12.6, Emergency Planning ML21278A2722021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.13, Control Element Assembly Ejection ML22115A0442021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 2, Section 2.10, Other Design Considerations: Redacted ML21278A2942021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.19, Turbine-Generator Overspeed Incident ML21278A2982021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 16, Section 16.2, Aging Management Programs and Activities ML22115A0452021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 5, Section 5.6, Other Structures - Redacted ML21278A2882021-09-0707 September 2021 2 to Updated Safety Analysis Report, Chapter 14, Section 14.20, Containment Response ML21278A2782021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 14, Section 14.4, Excess Load Event ML21278A2812021-09-0707 September 2021 2 to Updated Final Safety Analysis Report, Chapter 15, Section 15.0, Technical Requirements Manual ML21278A2902021-09-0707 September 2021 2 to Final Safety Analysis Report, Chapter 14 ,Section 14.17, Loss-of-Coolant Accident 2021-09-07
[Table view] |
Text
-George Gellrich Exelon Generation Site Vice President Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5200 Office 717 497 3463 Mobile www.exeloncorp.com george.gellrich@exeloncorp.com 10 CFR 50.71 10 CFR 54.37(b)September 19, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318
Subject:
Updated Final Safety Analysis Report, Revision 47 Enclosed for your use is one copy (CD) of our Updated Final Safety Analysis Report (UFSAR), Revision 47. This revision is submitted within six months after the latest refueling outage in accordance with 10 CFR 50.71(e).The List of Effective pages are included.
This electronic copy is a complete revision.Attachment (1) provides a description of changes to commitments made to the Nuclear Regulatory Commission.
Attachment (2) contains the report describing how newly identified items are managed for aging effects.There are no new regulatory commitments contained in this correspondence.
Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.Respectfully, George H. Gellrich Site Vice President Document Control Desk September 19, 2014 Page 2 CERTIFICATION:
I, George H. Gellrich, certify that I am Vice President-Calvert Cliffs Nuclear Power Plant, LLC, and that the information contained in this submittal accurately presents changes made since the previous submittal, necessary to reflect information and analyses submitted to the Commission or prepared pursuant to Commission requirement.
GHG/BJD/bjd Attachments:
(1) Changes to Commitments Made to the Nuclear Regulatory Commission (2) Report Consistent with 10 CFR 54.37(b) on How Aging Effects for Newly-Identified Structures, Systems, or Components are Managed
Enclosure:
Updated Final Safety Analysis Report, Revision 47 (CD)cc: NRC Project Manager, Calvert Cliffs (Without Enclosure)
NRC Regional Administrator, Region I NRC Resident Inspector, Calvert Cliffs S. Gray, MD-DNR ATTACHMENT (1)CHANGES TO COMMITMENTS MADE TO THE NUCLEAR REGULATORY COMMISSION Calvert Cliffs Nuclear Power Plant September 19, 2014 ATTACHMENT (1)CHANGES TO COMMITMENTS MADE TO THE NUCLEAR REGULATORY COMMISSION Calvert Cliffs has changed the following commitments made to the Nuclear Regulatory Commission (NRC): Commitment:
Change: Justification:
Commitment:
Change: Justification:
UFSAR Chapter 16 Table 16-2 line item #18 directs inspection of the containment emergency sump for corrosion.
Delete line item #18 inspection of the containment emergency sump cover and debris screen for general corrosion.
The original emergency containment sump cover was constructed of steel that was subject to general corrosion.
Inspecting the containment emergency sump cover and debris screen for general corrosion was credited with managing this degradation mechanism.
The emergency containment sump cover and debris screens were replaced with stainless steel -by ES199502396, Work Orders C1 19971659 & C21219963827.
As a result, general corrosion is no longer a credible aging mechanism.
See SE00138 (50.59 evaluation).
An aging management program relied on several Operations, for discovery of conditions that could allow general corrosion to progress for the instrument line supports by performance of visual inspections of plant operating areas during plant operator rounds. The purpose of this program is to provide requirements and guidance on personnel accountability for the correction of housekeeping, material and radiological deficiencies.
These Operations procedures are deleted from UFSAR Table 16-2 Lines 7 and 156.Several procedures were credited to assess the condition of component supports, specifically looking for general corrosion.
However, these procedures never looked for corrosion or any other aging degradation mechanism.
The purpose of these procedures is to look for deficiencies or plant abnormalities such as pooled water, leak, loose brackets, irregular temperatures, etc., to document the deficiency found, and to hold the spa e owner accountable for correcting the housekeeping issue. Instead, the licensee will credit the Structures and Systems Walkdown Program (AMBD-0052), which actually inspects for the applicable, plausible aging mechanisms for the same component supports.
Under AMBD-0052, the walkdowns will not be as frequent as the daily OPS walkdowns; however, with the intent of aging management to monitor for plausible ARDMs prior to degrading the SSC function, these less frequent inspections will not negatively affect the safety of the plant.Since all of the component supports discussed above are already inspected/monitored under other aging management programs, there is no need to rely on the Operations Procedures.
All of these AMPs now being credited are sufficient by themselves to detect ARDMs in time to take corrective action.1 ATTACHMENT (2)REPORT CONSISTENT WITH 10 CFR 54.37(b) ON HOW AGING EFFECTS FOR NEWLY-IDENTIFIED STRUCTURES, SYSTEMS, OR COMPONENTS ARE MANAGED Calvert Cliffs Nuclear Power Plant September 19, 2014 ATTACHMENT (2)REPORT CONSISTENT WITH 10 CFR 54.37(b) ON HOW AGING EFFECTS FOR NEWLY-IDENTIFIED STRUCTURES, SYSTEMS, OR COMPONENTS ARE MANAGED This report is in lieu of adding a level of detail to the Calvert Cliffs Nuclear Power Plant (CCNPP) Updated Final Safety Analysis Report (UFSAR) that is greater than in the remainder of the UFSAR, including the License Renewal Supplement.
An entry on the Nuclear Regulatory Commission (NRC) website, "Frequently Asked Questions (FAQs) About License Renewal Inspection Procedure (IP) 71003, 'Post-Approval Site Inspection for License Renewal"'
relates to the amount of detail required per 10 CFR 54.37(b).
It states, "The NRC staff will consider it acceptable if the summary information included in the FSAR update is consistent with the requirements of 10 CFR 54.21(d), and the guidance provided in Revision 1 of NUREG-1800,'Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants'(SRP-LR), provided that the licensee has supplied the technical details (as described in RIS 2007-16) in another documented submittal to the NRC." The information in this report is consistent with the technical information previously submitted to the NRC with the License Renewal Application (LRA).On April 8, 1998 CCNPP submitted a LRA to the NRC to renew the operating licenses for CCNPP Units 1 and 2 for an additional 20 years beyond the original expiration dates of July 31, 2014 (Unit 1) and August 13, 2016 (Unit 2). Within the LRA, information was provided to define the component types, functions, and the Aging Management Programs that applied. Lists of individual components within the scope of license renewal were not required to be provided.Subsequent to the completion of the necessary reviews, audits, responses to Requests for Additional Information, and resolutions of other questions, the NRC published NUREG-1705, Safety Evaluation Report Related to the License Renewal of Calvert Cliffs Nuclear Power Plant, Units 1 and 2 in December of 1999, which documented the NRC staffs review of the information submitted to them through July 16, 1999. The renewed operating licenses for CCNPP 1 and CCNPP 2 were issued on March 23, 2000, extending the license for CCNPP 1 to July 31, 2034 and CCNPP 2 to August 13, 2036.For holders of a renewed operating license, 10 CFR 54.37(b) requires that newly-identified structures, systems, or components (SSCs) be included in the Final Safety Analysis Report (FSAR) update required by 10 CFR 50.71(e) describing how the effects of aging will be managed. Newly-identified SSCs are those SSCs that were installed in the plant at the time of License Renewal of CCNPP 1 and CCNPP 2, but were not evaluated as part of the LRA (as discussed in Regulatory Issue Summary 2007-16).During the period of April 2013 to April 2014, a review of the site component database identified approximately 7000 components installed before April 2, 1999 that may not have previously been screened for license renewal applicability.
Of the components that were identified as in-scope and subject to aging management review, 239 components were found to have not been addressed by the LRA and are, therefore, "newly identified" and subject to 10 CFR 54.37(b) reporting requirements.
The 239 components can be broken down into two groups. The first group of 237 is already addressed within the groups of device types submitted with the LRA. The second group consists of 2 components that would not have been addressed under any of the groups of device types in the LRA.The 239 "newly-identified" components have been evaluated for aging effects requiring management and those with such aging have been assigned to existing Aging Management Programs and appropriate aging management strategies have been invoked to adequately 1
ATTACHMENT (2)REPORT CONSISTENT WITH 10 CFR 54.37(b) ON HOW AGING EFFECTS FOR NEWLY-IDENTIFIED STRUCTURES, SYSTEMS, OR COMPONENTS ARE MANAGED detect and manage the applicable aging effects throughout the period of extended operation.
This can be verified by NRC inspection.
The CCNPP LRA was the first submitted to the NRC and the guidance currently available to applicants in the GALL Report (NUREG-1801) and the SRP (NUREG-1800) did not exist.Hence, the format of the CCNPP LRA does not align with what later applicants submitted.
Although the tables and discussion provided in the CCNPP LRA are not actually being revised, the attached tables show, in a format similar to what current LRAs would contain, how aging of the 2 newly-identified components would have been addressed, had these components been included in the LRA.Time-Limited Agina Analysis One new Time-Limited Aging Analysis was identified for CCNPP in association with aligning the CCNPP AMP for reactor vessel internals with industry guidance and GALL XI.M16A. The Time-Limited Aging Analysis addresses fatigue of reactor vessel internals in accordance with the guidance of MRP-227A.
Details of these analyses were reviewed at CCNPP by NRC Region 1 Inspectors during the Phase 2, IP71003, Post-Approval Inspection performed during the weeks of May 1 9 th, June 2 nd, and July 7 th 2014.2 ATTACHMENT (2)REPORT CONSISTENT WITH 10 CFR 54.37(b) ON HOW AGING EFFECTS FOR NEWLY-IDENTIFIED STRUCTURES, SYSTEMS, OR COMPONENTS ARE MANAGED CCNPP Control Room HVAC System -LRA Section 5.1 IC (2 Components)
Component Intended Aging Effect Requiring Aging NUREG-1801 Table 1 Type Function Material Environment Management Management Vol 2 Item Item Program Solenoid PB Copper Dry Air None N/A VII.J.AP-8 Valve Alloy I I I I I I 1