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Category:Report
MONTHYEARML23354A2462023-12-20020 December 2023 Cracking Assessment for Framatome RSG Channel Head Assembly ML23215A1992023-08-31031 August 2023 ANP-4012NP, Callaway, Unit 1, Rod Ejection Accident Analysis Revision 2, August 2023 ML23299A1982023-06-16016 June 2023 Enclosure 2: Callaway RR Tech Report Containment Post-Tensioning System Inservice Inspection Technical Report Basis for Proposed Extension of Examination Interval, Revision 0 ML23156A6712023-06-0505 June 2023 Description and Justification for Changes ML23150A1832023-05-30030 May 2023 EIP-ZZ-00240 Addendum E, Revision 027, Health Physics Coordinator (Hpc) Checklist Administrative Correction ML23150A1842023-05-18018 May 2023 EIP-ZZ-00240 Addendum E, Revision 027, Health Physics Coordinator (Hpc) Checklist ML23150A1892023-05-18018 May 2023 EIP-ZZ-00245 Addendum H, Revision 004, Security Coordinator Checklist for the Alternate Tsc/Osa Assembly Area ML23131A3882023-04-26026 April 2023 EIP-ZZ-PRO2O Minor Revision 54, Activation and Operation of the Joint Information Center - Procedure Review Form and 50.54(q) Screening Form ML23110A0712023-04-0606 April 2023 Procedure Review Form (PRF) for EIP-ZZ-A0066, Revision 28, RERP Training Program ML23068A0992023-03-0909 March 2023 Special Report 2023-01 PAM Report ML23052A0492023-02-14014 February 2023 Enclosure 7 - Holtec International Report HI-2230125, Revision 0, Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station, Revision 0, Dated February 14, 2023 ML22349A6272022-12-15015 December 2022 Enclosure 3 - 2022 Proxy Statement of Ameren Corporation ML22349A6322022-12-15015 December 2022 Enclosure 8 - 10-K Filed 02/23/2022 ML22349A6342022-12-15015 December 2022 Enclosure 9 - 10-Q Filed 03/31/2022 ML22349A6352022-12-15015 December 2022 Enclosure 10 - 10-Q Filed 06/30/2022 ML22349A6362022-12-15015 December 2022 Enclosure 11 - 10-Q Filed 09/30/2022 ML22349A6402022-12-15015 December 2022 Enclosure 14 - Schedule 14C Information for Union Electric Company March 2022 ML22327A2242022-11-23023 November 2022 Enclosure 1: Callaway Plant - Report Period: 10 CFR 50.59 and 10 CFR 72.48 Summary Report June 16, 2021 to November 23, 2022 ML22335A5012022-11-16016 November 2022 Enclosure 3: ANP-4012NP, Revision 1, Callaway Rod Ejection Accident Analysis ML22318A1902022-11-14014 November 2022 Enclosure 2 - Pressurized Water Reactor Owners Group Letter, OG-22-187, Subject: PWR Owners Group Mode 4 LOCA Analysis for Westinghouse NSSS Plants ML22299A2352022-10-21021 October 2022 HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station ML22285A1252022-10-12012 October 2022 Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 2022 ML22285A1222022-10-12012 October 2022 Attachment 5 to Enclosure 1: ANP-3947NP, Callaway Unit 1 License Amendment Request Inputs for Use of Framatome Fuel, Revision 3, Dated October 2022 ML22285A1232022-10-12012 October 2022 Attachment 6 to Enclosure 1: ANP-3944NP, Callaway Realistic Large Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1242022-10-12012 October 2022 Attachment 7 to Enclosure 1: ANP-3943NP, Callaway Small Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22181B1362022-06-30030 June 2022 Attachment 6 - Replacement for Attachment 6, Description and Assessment Specific to TSTF-439, of ULNRC-06688 ML22181B1402022-06-30030 June 2022 Enclosure 1 - Replacement for Enclosure 1, List of Revised Required Actions to Corresponding PRA Functions, of ULNRC-06688 ML22181B1412022-06-30030 June 2022 Enclosure 4 - Replacement for Enclosure 4, Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models, of ULNRC-06688 ML22153A1822022-06-0202 June 2022 Attachment 6 - Non-Proprietary Version of Rlbloca Summary Report ML22153A1832022-06-0202 June 2022 Attachment 7 - Non-Proprietary Version of SBLOCA Summary Report ML22153A1852022-06-0202 June 2022 Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report ULNRC-06715, Enclosure 3: Attachment a to the NPDES Permit Modification Application2022-03-0101 March 2022 Enclosure 3: Attachment a to the NPDES Permit Modification Application ML22027A8092022-01-27027 January 2022 Enclosure 4: Callaway, Unit 1, Acronyms and Definitions ML22027A8082022-01-27027 January 2022 Enclosure 3: Callaway, Unit 1, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ML22027A8062022-01-27027 January 2022 Enclosure 1: Request for Exemptions for Risk-Informed Approach to Resolution for Generic Letter 2004-02 ML21356B5072021-12-22022 December 2021 Enclosure 1: Mark-up of Operating License (OL) ML21356B5082021-12-22022 December 2021 Enclosure 2: Clean Copy of Affected OL Pages (Reflecting Proposed Change) ML21343A0952021-12-0909 December 2021 Attachment 1: Description and Assessment ML21335A1602021-12-0101 December 2021 Special Report 2021-02: Accident Monitoring Instrumentation Non-Functional for Greater than 7 Days ML21280A3802021-10-0707 October 2021 Cumulative Summary of Changes to Enclosure 2, License Amendment Request, and Enclosure 3, Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02, of ULNRC-06526 ML21280A3812021-10-0707 October 2021 License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02 ML21272A1702021-09-28028 September 2021 Enclosure 2 - Full Scope Implementation of Alternative Source Term Evaluation of Proposed Changes (Redacted) ML21237A1372021-08-23023 August 2021 Enclosure 1: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - Baseline Weld Input ML21237A1382021-08-23023 August 2021 Enclosure 2: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Critical Breaks) ULNRC-06683, Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks)2021-08-23023 August 2021 Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks) ULNRC-06526, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-022021-07-22022 July 2021 Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ULNRC-06660, Cycle 24 Commitment Change Summary Report2021-06-22022 June 2021 Cycle 24 Commitment Change Summary Report ML21173A3412021-06-22022 June 2021 CFR 50.59 and 10 CFR 72.48 Summary Report - May 16, 2019 to June 15, 2021 ML21090A2502021-03-31031 March 2021 Attachment 1 - Changes to the Westinghouse ECCS Evaluation Model and PCT Penalty Assessments ML21090A1882021-03-31031 March 2021 Enclosure 3 - Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 2023-08-31
[Table view] Category:Technical
MONTHYEARML23354A2462023-12-20020 December 2023 Cracking Assessment for Framatome RSG Channel Head Assembly ML23215A1992023-08-31031 August 2023 ANP-4012NP, Callaway, Unit 1, Rod Ejection Accident Analysis Revision 2, August 2023 ML23299A1982023-06-16016 June 2023 Enclosure 2: Callaway RR Tech Report Containment Post-Tensioning System Inservice Inspection Technical Report Basis for Proposed Extension of Examination Interval, Revision 0 ML23150A1892023-05-18018 May 2023 EIP-ZZ-00245 Addendum H, Revision 004, Security Coordinator Checklist for the Alternate Tsc/Osa Assembly Area ML23110A0712023-04-0606 April 2023 Procedure Review Form (PRF) for EIP-ZZ-A0066, Revision 28, RERP Training Program ML23052A0492023-02-14014 February 2023 Enclosure 7 - Holtec International Report HI-2230125, Revision 0, Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station, Revision 0, Dated February 14, 2023 ML22349A6402022-12-15015 December 2022 Enclosure 14 - Schedule 14C Information for Union Electric Company March 2022 ML22349A6272022-12-15015 December 2022 Enclosure 3 - 2022 Proxy Statement of Ameren Corporation ML22349A6352022-12-15015 December 2022 Enclosure 10 - 10-Q Filed 06/30/2022 ML22349A6322022-12-15015 December 2022 Enclosure 8 - 10-K Filed 02/23/2022 ML22349A6362022-12-15015 December 2022 Enclosure 11 - 10-Q Filed 09/30/2022 ML22349A6342022-12-15015 December 2022 Enclosure 9 - 10-Q Filed 03/31/2022 ML22327A2242022-11-23023 November 2022 Enclosure 1: Callaway Plant - Report Period: 10 CFR 50.59 and 10 CFR 72.48 Summary Report June 16, 2021 to November 23, 2022 ML22335A5012022-11-16016 November 2022 Enclosure 3: ANP-4012NP, Revision 1, Callaway Rod Ejection Accident Analysis ML22318A1902022-11-14014 November 2022 Enclosure 2 - Pressurized Water Reactor Owners Group Letter, OG-22-187, Subject: PWR Owners Group Mode 4 LOCA Analysis for Westinghouse NSSS Plants ML22299A2352022-10-21021 October 2022 HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station ML22285A1242022-10-12012 October 2022 Attachment 7 to Enclosure 1: ANP-3943NP, Callaway Small Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1232022-10-12012 October 2022 Attachment 6 to Enclosure 1: ANP-3944NP, Callaway Realistic Large Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1222022-10-12012 October 2022 Attachment 5 to Enclosure 1: ANP-3947NP, Callaway Unit 1 License Amendment Request Inputs for Use of Framatome Fuel, Revision 3, Dated October 2022 ML22285A1252022-10-12012 October 2022 Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 2022 ML22181B1412022-06-30030 June 2022 Enclosure 4 - Replacement for Enclosure 4, Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models, of ULNRC-06688 ML22181B1402022-06-30030 June 2022 Enclosure 1 - Replacement for Enclosure 1, List of Revised Required Actions to Corresponding PRA Functions, of ULNRC-06688 ML22181B1362022-06-30030 June 2022 Attachment 6 - Replacement for Attachment 6, Description and Assessment Specific to TSTF-439, of ULNRC-06688 ML22153A1852022-06-0202 June 2022 Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report ML22153A1832022-06-0202 June 2022 Attachment 7 - Non-Proprietary Version of SBLOCA Summary Report ML22153A1822022-06-0202 June 2022 Attachment 6 - Non-Proprietary Version of Rlbloca Summary Report ML22027A8082022-01-27027 January 2022 Enclosure 3: Callaway, Unit 1, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ML21272A1702021-09-28028 September 2021 Enclosure 2 - Full Scope Implementation of Alternative Source Term Evaluation of Proposed Changes (Redacted) ULNRC-06683, Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks)2021-08-23023 August 2021 Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks) ML21237A1382021-08-23023 August 2021 Enclosure 2: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Critical Breaks) ML21237A1372021-08-23023 August 2021 Enclosure 1: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - Baseline Weld Input ULNRC-06526, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-022021-07-22022 July 2021 Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ULNRC-06660, Cycle 24 Commitment Change Summary Report2021-06-22022 June 2021 Cycle 24 Commitment Change Summary Report ML21090A1882021-03-31031 March 2021 Enclosure 3 - Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ML21090A2502021-03-31031 March 2021 Attachment 1 - Changes to the Westinghouse ECCS Evaluation Model and PCT Penalty Assessments ML20178A6732020-06-26026 June 2020 Attachment 3 - Callaway Unit 1, Steam Generator Operational Assessment to Support Deferral of Planned Inspections from 1R24 to 1R25, Revision 1 (Redacted) ML20178A6712020-06-26026 June 2020 Attachment 1 - Discussion of Change ULNRC-06571, 10 CFR 50.46 Annual Report, ECCS Evaluation Model Revisions2020-03-31031 March 2020 10 CFR 50.46 Annual Report, ECCS Evaluation Model Revisions ML20070R1212020-03-10010 March 2020 Technical Specification Page Markup ML20070R1142020-03-10010 March 2020 Description and Assessment of the Proposed Change ULNRC-06534, RERP Appendix J, Revision 005 Callaway Plant On-Shift Staffing Analysis Report2019-09-26026 September 2019 RERP Appendix J, Revision 005 Callaway Plant On-Shift Staffing Analysis Report ML19024A4742019-01-23023 January 2019 Attachment 4 - FSAR Technical Requirements I 6.7.13 ML18208A1682018-06-19019 June 2018 Revised Site Addendum Item - Chapter 10, Steam and Power Conversion System ML18208A1672018-06-19019 June 2018 Revised Site Addendum Item - Chapter 9.0, Auxiliary Systems ML18208A1662018-06-19019 June 2018 Revised Site Addendum Item - Chapter 9.0, Figures ML18208A1652018-06-19019 June 2018 Revised Site Addendum Item - Chapter 8.0, Electric Power ML18208A1642018-06-19019 June 2018 Revised Site Addendum Item - Chapter 8.0, Figures ML18208A1632018-06-19019 June 2018 Revised Site Addendum Item - Chapter 4.0, Reactor ML18208A1622018-06-19019 June 2018 Revised Site Addendum Item - Chapter 3.0, Design of Structures, Components, Equipment and Systems ML18208A1612018-06-19019 June 2018 Revised Site Addendum Item - Chapter 3.0, Figures 2023-08-31
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ULNRC-05963 February 28, 2013 Enclosure 1 CALLAWAY PLANT UNIT 1 LICENSE RENEWAL APPLICATION Page 1 of 6 REQUEST FOR ADDITIONAL INFORMATION (RAI) SET #22 RESPONSES ULNRC-05963 February 28, 2013 Enclosure 1 Page 2 of 6 RAI A4-1
Background:
By letter dated December 15, 2011, Union Electric Company (Ameren Missouri) (the applicant) applied to the U.S. Nuclear Regulatory Commission (NRC) for renewal of the Ce.llaway Plant, Unit 1 (Callaway), Operating License No. NPF-30 tor an additional 20 years beyond the current expiration date, October 18, 2024. Included in the license renewal application (LRA) Section A4, Table A4-1, "License Renewal Commitments," are commitments for license renewal and an associated schedule for when Ameren Missouri plans to implement or complete the commitments.
- The staff is reviewing the Callaway's LRA for compliance with the requirements of Title 10 of the Code of Federal Regulations (CFR) Part 54, "Requirements for Renewal of Operating Licenses for NLJclear Power Plants," and will document its preliminary findings in its "Safety Evaluation Report with Open Items Related to the License Renewal of Callaway Plant Unit 1." Upon the issuance of a renewed license, the NRC will impose a generic condition on the license. Specifically, the license condition will state that the applicant's final safety analysis report (FSAR) supplement describes certain programs to be implemented and activities to be completed prior to the period of extended operation and that Ameren Missouri shall implement those new programs and enhancements to existing programs no later than 6 months prior to the period of extended operation.
The license condition will also state that Ameren Missouri shall complete those inspection or testing activities as noted in certain commitments either before the end of the last refueling outage prior to the period of extended operation or 6 months prior to the . period of extended operation, whichever occurs later. The purpose of requiring the completion of implementation, inspection, and testing either before the end of the last refueling outage or prior to the 6-month time frame is to ensure that the implementation of programs and completion of specific activities can be verified by the NRC's oversight process before the plant enters the period of extended operation.
The license condition will state: The licensee's FSAR supplement submitted pursuant to 10 CFR 54.21 (d), as revised during the license renewal application review process, and as supplemented by Appendix A of NUREG-[XXXX], "Safety Evaluation Report Related to the License Renewal of Callaway Plant Unit 1" dated [Month Year], describes certain programs to be implemented and activities to be completed prior to the period of extended operation.
- a. The licensee shall implement those new programs and enhancements to existing programs no later than 6 months prior to PEO. b. The licensee shall complete those inspection and testing activities before the end of the last refueling outage prior to the PEO or 6-months prior to PEO, whichever occurs later. The licensee shall notify the NRC in writing within 30 days after having accomplished item (a) above and include the status of those activities that have been or remain to be completed in item (b) above.
ULNRC-05963 February 28, 2013 Enclosure 1 Issue: Page 3 of 6 As proposed in Callaway's LRA Section A4, Table A4-1, the implementation schedule for some commitments may conflict with the implementation schedule intended by the generic license condition.
Request: 1. Identify those commitments to implement new programs and enhancements to existing programs.
Indicate when the implementation of these programs will be completed.
- 2. Identify those commitments to complete inspection or testing activities.
Indicate when the completion of these inspection and testing activities will occur. Callaway Response 1. LRA Appendix A Introduction, LRA Table A4-1, and LRA Appendix 81.2 have been revised as shown in LRA Amendment 22 to indicate when the commitments to implement new programs and enhancements to existing programs will be completed.
Specifically, Ameren Missouri will complete implementation of new programs and enhancements to existing programs no later than 6 months prior to period of extended operation (PEO). 2. LRA Appendix A Introduction, LRA Table A4-1, and LRA Appendix 81.2 have been revised as shown in LRA Amendment 22 to indicate when the inspection and testing activities will be completed.
Specifically, Ameren Missouri will complete inspection and testing activities by the 6-month date prior to PEO or the end of the last refueling outage prior to the PEO, whichever occurs later. Corresponding Amendment Changes Refer to the Enclosure 2 Summary Table "Amendment 22, LRA Changes from RAI Responses and Typographical Corrections," for a description of LRA changes with this response.
ULNRC-05963 February 28, 2013 Enclosure 1 RAI 82.1.1 0-3b
Background:
Page 4 of 6 The response dated November 20, 2012, to RAI 82.1.1 0-3a states that Callaway does not rely on estimated service life to manage internal coatings, and performs visual inspections as the primary method of monitoring coating conditions.
The response cites statements from Electric Power Research Institute (EPRI) TR 1019157, "Guideline on Nuclear Safety-Related Coatings," to support its use of visual inspections.
The response also states that corrective actions, extent of condition reviews, and evaluations for continued service are performed consistent with American Society for Testing and Materials (ASTM) 07167, "Standard Guide for Establishing Procedures to Monitor the Performance of Safety-Related Coating Service Level Ill Lining Systems in an Operating Nuclear Power Plant." The response notes that this standard addresses performance of physical tests, such as dry film thickness or pull-off adhesion testing, and that physical testing is at the discretion of the evaluator.
The staff notes that Callaway's Open-Cycle Cooling Water System aging management program (AMP) implements coatings inspections through procedures EDP-ZZ-01112, "Heat Exchanger Predictive Performance Manual," and EDP-ZZ-3001, GL 89-13; Heat Exchanger Inspection." Neither procedure refers to ASTM 07167, nor discusses the need to assess the integrity of degraded coatings through physical testing. The staff also notes that the signs of coating degradation, given in EDP-ZZ-3001 for as-found inspection criteria, only include "chips, iron deposits on the surface (indicative of holidays in the coating surface), scrapes, and any other sign of surface abrasion." The staff further notes that, although it addresses macrofouling, EDP-ZZ-01112 does not include loss of coating integrity in macrofouling.
In addition, the staff notes that coatings in applicable heat exchangers and strainers are inspected every 5 years and 6 years, respectively.
Issue: Callaway's current imple'menting procedures do not appear to include inspection criteria for coating delamination and do not address the need to assess the integrity of degraded coatings through physical tests, such as pull-off adhesion testing. It is not clear to the staff that coating delamination is considered and that the extent of delamination can be bounded through visual inspections.
In addition, since Callaway does not account for the service life of coatings, the staff needs additional assurance that the current inspection frequencies of 5 years and 6 years are adequate.
Request: 1) Verify that the Open-Cycle Cooling Water System AMP includes inspections for signs of coating detachment (e.g., blistering, flaking/peeling/delamination) and provide the acceptance criteria for these inspections.
Otherwise, provide the bases for not including signs of coating detachment in the inspections of coatings where degradation may adversely affect downstream components.
- 2) Describe the Open-Cycle Cooling Water System AMP activities that verify coating integrity when visual indications of coating detachment are identified during periodic inspections.
Include industry standards as appropriate.
If these activities do not include physical testing ULNRC-05963 February 28, 2013 Enclosure 1 Page 5 of 6 such as adhesion testing, provide the technical bases to demonstrate that downstream components will not be adversely affected by coating degradation.
- 3) Describe the timing of coatings inspections for the related heat exchangers and strainers in redundant trains. Specifically, discuss whether these inspections are staggered between redundant trains during subsequent outages and if applicable provide the time span between these alternating inspections.
Include information to verify that the identical coating materials were installed with the same installation requirements in the redundant trains with the same operating conditions.
Callaway Response 1) The Open-Cycle Cooling Water System program implementing procedures will be enhanced to specify that coatings inspections will look for signs of coating detachment (e.g. blistering, flaking/peeling/delamination).
The Open-Cycle Cooling Water System program implementing procedures will also be enhanced to include the following acceptance criteria for signs of detachment which could affect downstream components:
- Peeling, flaking, or delamination are not allowed.
- Blisters are acceptable if limited to intact blister that is completely surrounded by sound coating bonded to the surface.
- Cracking is not considered a failure unless it is accompanied by detachment or loss of adhesion.
LRA Appendix 82.1.1 0 and LRA Table A4-1 item 6 have been revised as shown on Amendment 22 in Enclosure 2 to identify an enhancement for inspection of coating detachment and identification of acceptance criteria for those inspections.
- 2) The Open-Cycle Cooling Water System program implementing procedures will be enhanced to inspect for coating detachment, include inspection acceptance criteria, and require coating evaluation/testing as noted below. Coating detachments that are not repaired or removed to leave sound coating bonded to the surface will be evaluated to confirm downstream components are not adversely affected by coating detachment.
The evaluation will include confirmation that the coating manufacturer installation requirements have been met. Physical testing such as those identified in ASTM-07167 (e.g. dry film thickness test or adhesion test) will be required to determine if the coating is bonded to the surface. Coating detachments that are not repaired or removed to leave sound coating bonded to the surface will be trended. LRA Appendix 82.1 .1 0 and LRA Table A4-1 item 6 have been revised as shown on Amendment 22 in Enclosure 2 to identify an enhancement for coating evaluation and testing. 3) The following Open-Cycle Cooling Water System program components have coated internal surfaces:
- Component cooling water heat exchangers (one each in A and B trains)
- Control room air conditioners (one each in A and B trains)
- Class 1 E electrical equipment air conditioners (one each in A and B trains)
ULNRC-05963 February 28, 2013 Enclosure 1 Page 6 of 6 The coated Open-Cycle Cooling Water System program components are routinely inspected on a staggered outage basis between redundant trains. Therefore, there would be approximately 18 months between alternate train inspections, and 36 months between specific component inspections.
This is the normal practice at Callaway.
There may be times when the same train may be out of service 2 outages in a row. In this rather than put both trains out of service during the same refueling outage, the equipment in the same train may be inspected during 2 outages in a row. In no case would any of the coated surfaces of the Open-Cycle Cooling Water System program heat exchangers and strainers go more than 5 years between inspections as required by NRCGL 89-13. The Open-Cycle Cooling Water System program components with coatings are constructed of carbon steel and experience the same operating conditions.
All of the heat exchangers noted above are coated with Chesterton 855 coating. The ESW strainers are coated with Carboline 891. Therefore, for the same components in redundant trains, the same material/environment conditions are being inspected every refueling outage. Corresponding Amendment Changes Refer to the Enclosure 2 Summary Table "Amendment 22, LRA Changes from RAI Responses and Typographical Corrections," for a description of LRA changes with this response.