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| | 17265 River Road Killona, LA 70057-3093 Tel 504 739 6685 Fax 504 739 6698 jjarrel@entergy.com John P. Jarrell III Manager, Regulatory Assurance Waterford 3 10 CFR 50.55a W3F1-2018-0044 September 12, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 |
| | |
| | ==SUBJECT:== |
| | Clarification to Waterford 3 Request for Alternative W3-ISI-023 Waterford Steam Electric Station, Unit 3 (Waterford 3) |
| | License No. NPF-38 Docket No. 50-382 |
| | |
| | ==REFERENCES:== |
| | : 1. W3F1-2013-0044, Waterford 3 Request for Alternative W3-ISI-023, ASME Code Case N-770-1 Successive Examinations, September 26, 2013 [NRC ADAMS Accession Number ML13270A041]. |
| | : 2. Waterford Steam Electric Station, Unit 3 - Request for Alternative W3-ISI-023, ASME Code Case N-770-1 Successive Examinations, Third 10-Year Inservice Inspection Interval (TAC No. MF2815), February 26, 2014 [NRC ADAMS Accession Number ML14070A008]. |
| | : 3. W3F1-2012-0102, Waterford 3 Supplemental Response to an NRC Request for Additional Information (RAI) Associated with W3-ISI-020, Request For Alternative to ASME Code Case N-770-1 Baseline Examination (TAC No. ME9801), December 16, 2012 [NRC ADAMS Accession Number ML12352A172]. |
| | : 4. 2CAN121201, Revised Request For Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination Arkansas Nuclear One, Unit 2, December 4, 2012 [NRC ADAMS Accession Number ML12340A449]. |
| | |
| | ==Dear Sir or Madam:== |
| | |
| | By letter dated September 26, 2013 (Reference 1), Entergy Operations, Inc. (EOI), submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for an alternative to the inspection coverage requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), Section XI, for seven full-penetration welds at the Waterford Steam Electric Station, Unit 3 (Waterford 3). This requested relief pursuant to 50.55a(a)(3)(ii) from the requirements of ASME Code Case N-770-1, as conditioned by 10 CFR 50.55a(g)(6)(ii)(F), pertaining to volumetric examination of the dissimilar metal welds associated with the suction and discharge piping of the Reactor Coolant Pumps (RCP) and the Safety Injection (SI) nozzle to safe-ends at Waterford 3. |
| | |
| | W3F 1-2018-0044 Page 2 of 3 By letter dated March 26, 2014 (Reference 2), the NRC approved the use of alternative W3-ISI-023 for 54 months following the Spring 2014 refueling outage examinations, with examinations to be performed during the Fall 2018 refueling outage. The outage schedule has since been revised and will now commence in early 2019. The Spring 2014 outage ended May 14, 2014; therefore, the 54 month alternative ends November 9, 2018. |
| | By this letter, Entergy requests clarification to the duration of the approved alternative to be 54 operating months following the Spring 2014 refueling outage. The basis for the alternative states that flaw growth in the subject welds would not exceed the ASME Code allowable flaw size during 54 months at operating temperatures of 525 °F or higher. Given the operating history since the Spring 2014 outage, 54 months at operating temperature would end January 31, 2019. The start date of the Spring 2019 refueling outage is before January 31, 2019, therefore, the alternative to inspection requirements will not exceed 54 operating months. The examinations will be performed prior to completion of the Spring 2019 refueling outage. Entergy previously provided the technical basis supporting the alternative inspection period in References 3 and 4. |
| | Relief was originally requested per 10 CFR 50.55a(a)(3)(ii). Since approval of the request, 10 CFR 50.55a has been revised and the corresponding regulation is 10 CFR 50.55a(z)(2). In addition, the subject code case N-770-1 has been replaced by N-770-2. Code case N-770-2 has been incorporated into the Waterford 3 Inservice Inspection program. |
| | This document contains a revision to a regulatory commitment that was made in Reference 1. |
| | This revision is provided in the Attachment. |
| | Entergy requests approval by November 8, 2018. |
| | Should you have questions regarding this report, please contact John P. Jarrell, Regulatory Assurance Manager, at (504) 739-6685. |
| | ly, JPJ/RRD |
| | |
| | ==Attachment:== |
| | Waterford 3 Steam Electric Station Regulatory Commitment |
| | |
| | W3F1-2018-0044 Page 3 of 3 cc: Mr. Kriss Kennedy, Regional Administrator U.S. NRC, Region IV RidsRgn4MailCenter@nrc.gov U.S. NRC Project Manager for Waterford 3 April.Pulvirenti@nrc.gov U.S. NRC Senior Resident Inspector for Waterford 3 Frances.Ramirez@nrc.gov Chris.Speer@nrc.gov |
| | |
| | Attachment to W3F1-2018-0044 Waterford 3 Steam Electric Station Regulatory Commitment (1 page) |
| | |
| | Attachment to W3F1-2018-0044 Page 1 of 1 Waterford 3 Steam Electric Station Regulatory Commitment This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRCs information and are not commitments. |
| | TYPE SCHEDULED (Check one) |
| | COMPLETION COMMITMENT ONE- DATE CONTINUING TIME (If Required) |
| | COMPLIANCE ACTION Perform N-770-2 examination of the 30 Prior to conclusion and 12 RCS nozzles within 54 operating of the Spring 2019 months with cold leg temperatures at or X Waterford 3 above 525 °F following the Spring 2014 Refueling refueling outage. Outage.}} |
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MONTHYEARW3F1-2018-0044, Clarification to Waterford 3 Request for Alternative W3-ISI-0232018-09-12012 September 2018 Clarification to Waterford 3 Request for Alternative W3-ISI-023 Project stage: Request W3F1-2018-0060, Request for NRC Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-0312018-10-19019 October 2018 Request for NRC Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-031 Project stage: Request ML18310A4352018-11-0606 November 2018 NRR E-mail Capture - Waterford 3 - Acceptance Review of Request for Alternative Regarding Alternative to ASME Code Case N0770-2 Weld Examinations Project stage: Acceptance Review ML18318A4352018-11-14014 November 2018 NRR E-mail Capture - Waterford 3 - Final Request for Additional Information Regarding Request for Alternative to ASME Code Case N-770-2 Project stage: RAI W3F1-2018-0067, Response to NRC Request for Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-0312018-11-19019 November 2018 Response to NRC Request for Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-031 Project stage: Request ML18345A0162018-12-10010 December 2018 NRR E-mail Capture - Verbal Authorization for Relief Request W3-ISI-0131, Proposed Alternative for ASME Code Case N-770-2 for Waterford Steam Electric Station, Unit 3 Project stage: Other ML19157A3162019-06-12012 June 2019 Authorization of Proposed Alternative to ASME Code Case N-770-2 Project stage: Other 2018-11-06
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Category:Letter type:W
MONTHYEARW3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 W3F1-2022-0028, Annual Radiological Environmental Operating Report - 20212022-04-26026 April 2022 Annual Radiological Environmental Operating Report - 2021 W3F1-2022-0029, Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.22062022-04-26026 April 2022 Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.2206 W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2022-0031, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-2842022-04-25025 April 2022 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-284 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2022-0019, WAT-2022-02 Post Exam Analysis2022-03-0909 March 2022 WAT-2022-02 Post Exam Analysis W3F1-2022-0011, Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-02-0808 February 2022 Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0008, SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days2022-02-0101 February 2022 SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days W3F1-2021-0074, Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-022021-12-16016 December 2021 Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-02 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0063, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery2021-10-12012 October 2021 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0057, (Waterford 3) - Emergency Plan Revision 0522021-08-18018 August 2021 (Waterford 3) - Emergency Plan Revision 052 W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator 2023-09-28
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Text
Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504 739 6685 Fax 504 739 6698 jjarrel@entergy.com John P. Jarrell III Manager, Regulatory Assurance Waterford 3 10 CFR 50.55a W3F1-2018-0044 September 12, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Clarification to Waterford 3 Request for Alternative W3-ISI-023 Waterford Steam Electric Station, Unit 3 (Waterford 3)
License No. NPF-38 Docket No. 50-382
REFERENCES:
- 1. W3F1-2013-0044, Waterford 3 Request for Alternative W3-ISI-023, ASME Code Case N-770-1 Successive Examinations, September 26, 2013 [NRC ADAMS Accession Number ML13270A041].
- 2. Waterford Steam Electric Station, Unit 3 - Request for Alternative W3-ISI-023, ASME Code Case N-770-1 Successive Examinations, Third 10-Year Inservice Inspection Interval (TAC No. MF2815), February 26, 2014 [NRC ADAMS Accession Number ML14070A008].
- 3. W3F1-2012-0102, Waterford 3 Supplemental Response to an NRC Request for Additional Information (RAI) Associated with W3-ISI-020, Request For Alternative to ASME Code Case N-770-1 Baseline Examination (TAC No. ME9801), December 16, 2012 [NRC ADAMS Accession Number ML12352A172].
- 4. 2CAN121201, Revised Request For Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination Arkansas Nuclear One, Unit 2, December 4, 2012 [NRC ADAMS Accession Number ML12340A449].
Dear Sir or Madam:
By letter dated September 26, 2013 (Reference 1), Entergy Operations, Inc. (EOI), submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for an alternative to the inspection coverage requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, for seven full-penetration welds at the Waterford Steam Electric Station, Unit 3 (Waterford 3). This requested relief pursuant to 50.55a(a)(3)(ii) from the requirements of ASME Code Case N-770-1, as conditioned by 10 CFR 50.55a(g)(6)(ii)(F), pertaining to volumetric examination of the dissimilar metal welds associated with the suction and discharge piping of the Reactor Coolant Pumps (RCP) and the Safety Injection (SI) nozzle to safe-ends at Waterford 3.
W3F 1-2018-0044 Page 2 of 3 By letter dated March 26, 2014 (Reference 2), the NRC approved the use of alternative W3-ISI-023 for 54 months following the Spring 2014 refueling outage examinations, with examinations to be performed during the Fall 2018 refueling outage. The outage schedule has since been revised and will now commence in early 2019. The Spring 2014 outage ended May 14, 2014; therefore, the 54 month alternative ends November 9, 2018.
By this letter, Entergy requests clarification to the duration of the approved alternative to be 54 operating months following the Spring 2014 refueling outage. The basis for the alternative states that flaw growth in the subject welds would not exceed the ASME Code allowable flaw size during 54 months at operating temperatures of 525 °F or higher. Given the operating history since the Spring 2014 outage, 54 months at operating temperature would end January 31, 2019. The start date of the Spring 2019 refueling outage is before January 31, 2019, therefore, the alternative to inspection requirements will not exceed 54 operating months. The examinations will be performed prior to completion of the Spring 2019 refueling outage. Entergy previously provided the technical basis supporting the alternative inspection period in References 3 and 4.
Relief was originally requested per 10 CFR 50.55a(a)(3)(ii). Since approval of the request, 10 CFR 50.55a has been revised and the corresponding regulation is 10 CFR 50.55a(z)(2). In addition, the subject code case N-770-1 has been replaced by N-770-2. Code case N-770-2 has been incorporated into the Waterford 3 Inservice Inspection program.
This document contains a revision to a regulatory commitment that was made in Reference 1.
This revision is provided in the Attachment.
Entergy requests approval by November 8, 2018.
Should you have questions regarding this report, please contact John P. Jarrell, Regulatory Assurance Manager, at (504) 739-6685.
ly, JPJ/RRD
Attachment:
Waterford 3 Steam Electric Station Regulatory Commitment
W3F1-2018-0044 Page 3 of 3 cc: Mr. Kriss Kennedy, Regional Administrator U.S. NRC, Region IV RidsRgn4MailCenter@nrc.gov U.S. NRC Project Manager for Waterford 3 April.Pulvirenti@nrc.gov U.S. NRC Senior Resident Inspector for Waterford 3 Frances.Ramirez@nrc.gov Chris.Speer@nrc.gov
Attachment to W3F1-2018-0044 Waterford 3 Steam Electric Station Regulatory Commitment (1 page)
Attachment to W3F1-2018-0044 Page 1 of 1 Waterford 3 Steam Electric Station Regulatory Commitment This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRCs information and are not commitments.
TYPE SCHEDULED (Check one)
COMPLETION COMMITMENT ONE- DATE CONTINUING TIME (If Required)
COMPLIANCE ACTION Perform N-770-2 examination of the 30 Prior to conclusion and 12 RCS nozzles within 54 operating of the Spring 2019 months with cold leg temperatures at or X Waterford 3 above 525 °F following the Spring 2014 Refueling refueling outage. Outage.