AEP-NRC-2025-36, Updated Final Safety Analysis Report (Ufsar), Revision 33, 10 CFR 54.37(b) Review for the Renewed License, November 2023 to May 2025: Difference between revisions
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{{Adams | |||
| number = ML25307A105 | |||
| issue date = 10/30/2025 | |||
| title = Updated Final Safety Analysis Report (Ufsar), Revision 33, 10 CFR 54.37(b) Review for the Renewed License, November 2023 to May 2025 | |||
| author name = | |||
| author affiliation = Indiana Michigan Power Co | |||
| addressee name = | |||
| addressee affiliation = NRC/NRR | |||
| docket = 05000315, 05000316 | |||
| license number = | |||
| contact person = | |||
| case reference number = AEP-NRC-2025-36 | |||
| package number = ML25307A008 | |||
| document type = Updated Final Safety Analysis Report (UFSAR) | |||
| page count = 1 | |||
}} | |||
=Text= | |||
{{#Wiki_filter:Donald C. Cook Nuclear Plant 10 CFR 54.37(b) Review for the Renewed License November 2023 to May 2025 For holders of a renewed license, 10 CFR 54.37(b) requires that newly identified Systems, Structures or Components (SSCs) be included in the FSAR update required by 10 CFR 50.71(e). | |||
This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in 10 CFR 54.4(b) will be effectively maintained during the period of extended operation. Renewal licensees are obligated to comply with 10 CFR 54.37(b) as a condition of license renewal. | |||
Newly identified SSCs are SSCs that were installed in the plant prior to receiving the renewed license but were not identified during the License Renewal (LR) process as meeting the scoping criteria of 10 CFR 54.4. | |||
An Engineering Change (EC) was developed to provide emergency make-up water to the Component Cooling Water (CCW) system using existing nonsafety-related components in the Primary Water System (PWS). Since the failure of the PWS to supply make-up water could prevent satisfactory accomplishment of a safety function, these PWS components meet the scoping criteria of 10 CFR 54.4(a)(2). In addition, these components must maintain their pressure boundary to perform their intended function and were installed prior to receiving the renewed license. Based on these factors, these components in the PWS are newly identified. | |||
Table 1 Primary Water System-Summary of Aging Management Review lists the newly identified components and provides information as to how the effects of aging are managed such that the intended function(s) will be effectively maintained during the period of extended operation. Table 1 provides the material/environment combination, aging effect, and Aging Management Program (AMP) for the newly identified components. | |||
The method used to perform the Aging Management Review for these newly identified components is the same method described in the D. C. Cook Nuclear Power Plant License Renewal Application (LRA) that was submitted in Attachment 2 to AEP:NRC:3034 dated October 31, 2003. In addition, the definitions of intended functions, the description of environments, and description of the program used in Attachment 2 are the same as those in the LRA. No changes to the AMPs are necessary since the Water Chemistry Control Program already manages the aging effects. | |||
10 CFR 54.37(b) Review for the Renewed License November 2023 to May 2025 Page 2 of 2 Table 1: Primary Water System - Summary of Aging Management Review Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs Bolting Pressure boundary Stainless Steel Air (external) | |||
None None Fitting Pressure boundary Stainless Steel Air (external) | |||
None None Treated water (internal) | |||
Loss of material Water Chemistry Control Piping Pressure boundary Stainless Steel Air (external) | |||
None None Treated water (internal) | |||
Loss of material Water Chemistry Control Pump Casing Pressure boundary Stainless Steel Air (external) | |||
None None Treated water (internal) | |||
Loss of material Water Chemistry Control Tank Pressure boundary Stainless Steel Air (external) | |||
None None Treated water (internal) | |||
Loss of material Water Chemistry Control Thermowell Pressure boundary Stainless Steel Air (external) | |||
None None Treated water (internal) | |||
Loss of material Water Chemistry Control Tubing Pressure boundary Stainless Steel Air (external) | |||
None None Treated water (internal) | |||
Loss of material Water Chemistry Control Valve Pressure boundary Stainless Steel Air (external) | |||
None None Treated water (internal) | |||
Loss of material Water Chemistry Control}} | |||
Latest revision as of 01:44, 21 February 2026
Text
Donald C. Cook Nuclear Plant 10 CFR 54.37(b) Review for the Renewed License November 2023 to May 2025 For holders of a renewed license, 10 CFR 54.37(b) requires that newly identified Systems, Structures or Components (SSCs) be included in the FSAR update required by 10 CFR 50.71(e).
This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in 10 CFR 54.4(b) will be effectively maintained during the period of extended operation. Renewal licensees are obligated to comply with 10 CFR 54.37(b) as a condition of license renewal.
Newly identified SSCs are SSCs that were installed in the plant prior to receiving the renewed license but were not identified during the License Renewal (LR) process as meeting the scoping criteria of 10 CFR 54.4.
An Engineering Change (EC) was developed to provide emergency make-up water to the Component Cooling Water (CCW) system using existing nonsafety-related components in the Primary Water System (PWS). Since the failure of the PWS to supply make-up water could prevent satisfactory accomplishment of a safety function, these PWS components meet the scoping criteria of 10 CFR 54.4(a)(2). In addition, these components must maintain their pressure boundary to perform their intended function and were installed prior to receiving the renewed license. Based on these factors, these components in the PWS are newly identified.
Table 1 Primary Water System-Summary of Aging Management Review lists the newly identified components and provides information as to how the effects of aging are managed such that the intended function(s) will be effectively maintained during the period of extended operation. Table 1 provides the material/environment combination, aging effect, and Aging Management Program (AMP) for the newly identified components.
The method used to perform the Aging Management Review for these newly identified components is the same method described in the D. C. Cook Nuclear Power Plant License Renewal Application (LRA) that was submitted in Attachment 2 to AEP:NRC:3034 dated October 31, 2003. In addition, the definitions of intended functions, the description of environments, and description of the program used in Attachment 2 are the same as those in the LRA. No changes to the AMPs are necessary since the Water Chemistry Control Program already manages the aging effects.
10 CFR 54.37(b) Review for the Renewed License November 2023 to May 2025 Page 2 of 2 Table 1: Primary Water System - Summary of Aging Management Review Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs Bolting Pressure boundary Stainless Steel Air (external)
None None Fitting Pressure boundary Stainless Steel Air (external)
None None Treated water (internal)
Loss of material Water Chemistry Control Piping Pressure boundary Stainless Steel Air (external)
None None Treated water (internal)
Loss of material Water Chemistry Control Pump Casing Pressure boundary Stainless Steel Air (external)
None None Treated water (internal)
Loss of material Water Chemistry Control Tank Pressure boundary Stainless Steel Air (external)
None None Treated water (internal)
Loss of material Water Chemistry Control Thermowell Pressure boundary Stainless Steel Air (external)
None None Treated water (internal)
Loss of material Water Chemistry Control Tubing Pressure boundary Stainless Steel Air (external)
None None Treated water (internal)
Loss of material Water Chemistry Control Valve Pressure boundary Stainless Steel Air (external)
None None Treated water (internal)
Loss of material Water Chemistry Control