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Category:Letter type:W
MONTHYEARW3F1-2024-0049, Notification of Readiness for Supplemental Inspection2024-10-21021 October 2024 Notification of Readiness for Supplemental Inspection W3F1-2024-0042, License Amendment Request to Extend Allowable Outage Times for One or More Control Room Air Conditioning Units Inoperable2024-10-16016 October 2024 License Amendment Request to Extend Allowable Outage Times for One or More Control Room Air Conditioning Units Inoperable W3F1-2024-0038, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0039, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0041, Reply to a Notice of Violation, EA-24-0522024-09-19019 September 2024 Reply to a Notice of Violation, EA-24-052 W3F1-2024-0040, Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days2024-09-0303 September 2024 Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0019, (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 252024-07-22022 July 2024 (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0032, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-07-17017 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation W3F1-2024-0024, Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days2024-06-17017 June 2024 Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program2024-05-0808 May 2024 Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program W3F1-2024-0018, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 252024-05-0101 May 2024 Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0014, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20242024-04-29029 April 2024 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2024 W3F1-2024-0015, Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure2024-04-24024 April 2024 Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure W3F1-2024-0016, Annual Radiological Environmental Operating Report (AREOR) - 20232024-04-24024 April 2024 Annual Radiological Environmental Operating Report (AREOR) - 2023 W3F1-2024-0017, Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.22062024-04-23023 April 2024 Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.2206 W3F1-2024-0020, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20232024-04-11011 April 2024 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023 W3F1-2024-0008, Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0009, Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0012, Response to NRC Integrated Inspection Report 05000382/20230042024-03-11011 March 2024 Response to NRC Integrated Inspection Report 05000382/2023004 W3F1-2024-0006, Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days2024-02-28028 February 2024 Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0056, Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owners 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 2024-09-03
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Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093
-Entergy Tel 504-739-6715 Fax 504-739-6698 rmurill@entergy.com Robert J. Murillo Licensing Manager Waterford 3 W3F1-2006-0043 August 29, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC- 20555
SUBJECT:
Additional Information in Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used In Pressurizer Penetrations and Steam Space Piping Connections Waterford Steam Electric Station, Unit 3 Docket No. 50-382
REFERENCES:
1 NRC letter dated May 28, 2004, NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used In the Fabricationof Pressurizer Penetrationsand Steam Space Piping Connections at Pressurized-Water Reactors 2 Entergy letter dated July 27, 2004, Response to NRC Bulletin 2004-01 Regarding Inspection of Alloy 82/182/600 Materials Used In Pressurizer Penetrationsand Steam Space Piping Connections (W3F1-2004-0058)
Dear Sir or Madam:
On May 28, 2004, the Nuclear Regulatory Commission (NRC) issued NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used In the Fabricationof PressurizerPenetrations and Steam Space Piping Connections at Pressurized-WaterReactors (Reference 1). The NRC requested that all pressurized water reactor addressees provide description of their pressurizer heater and steam space penetrations and inspection plans for the forthcoming and subsequent refueling outages. On July 27, 2004 (Reference 2), Entergy provided the required response for the Waterford Steam Electric Station, Unit 3 (Waterford-3).
In the response, Entergy had noted that weld repairs/replacements were being planned during the spring 2005 refueling outage (RF-1 3) for the pressurizer heater and small bore Alloy 600 pressurizer nozzles and welds. The purpose of this letter is to confirm that associated repairs or replacements were performed. The attachment to this letter provides details on the repairs that were performed during the RF-13 outage.
W3F1-2006-0043 Page 2 There are no commitments associated with this letter. If you have any questions or require additional information, please contact Steve Bennett at 479-858-4626.
Sincerely, RJM/SAB/ssf
Attachment:
Repairs Performed on the Waterford-3 Pressurizer During the Spring 2005 Refueling Outage
W3F17-2006-0043 Page 3 cc: Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Mel Fields MS O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn Attn: N.S. Reynolds 1400 L Street, NW Washington, DC 20005-3502 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. O. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 29th S. Main Street West Hartford, CT 06107-2445
Attachment W3FI -2006-0043 Repairs Performed on the Waterford-3 Pressurizer During the Spring 2005 Refueling Outage
Attachment to W3F1 -2006-0043 Page 1 of I Re;pairs Performed on the Waterford-3 Pressurizer During the Spring 2005 Refueling Outage Heater Sleeves The Waterford-3 Pressuizer contains thirty (30) heater sleeves. Pressurizer Heater Sleeve F-4 was repaired during the fall 2000 refueling outage with an Alloy 690 plug. This plug was retained and no additional repairs or modifications were performed in the spring 2005 refueling outage (RF-13). The remaining twenty nine (29) nozzles were replaced using a half nozzle, mid-wall repair during RF-1 3. The half nozzle repair design relocates the reactor coolant pressure boundary from a partial penetration (J-groove) weld on the inside surface of the pressurizer to a partial penetration weld at the mid-wall of the pressurizer shell. The new pressure boundary for these sleeves is constructed with Alloy 690 materials.
Small Bore Pressurizer Penetrations The Waterford-3 Pressurizer contains six (6) small bore instrument nozzles and 1 (one) temperature nozzle localed both in the steam and water space of the pressurizer. Two upper steam space nozzles were repaired in the spring of 1999 using Alloy 600 weld filler and two were repaired using Alloy 690 materials in the fall 2000 refueling outages. The 2 previously repaired nozzles using Alloy 600 weld filler, the temperature nozzle and the remaining two instrument nozzles, were replaced during RF-13 utilizing a new half-nozzle welded to a pad on the outside of the pressurizer shell using Alloy 690 half-nozzles and weld filler.
Note: There are 5 remaining large bore pressurizer welds and nozzles consisting of two 6-inch pressurizer relief valve nozzles, a spare 6-inch nozzle, the 4-inch pressurizer spray line, and 12-inch surge line. No repairs have been performed on these welds or nozzles to date.
Text
Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093
-Entergy Tel 504-739-6715 Fax 504-739-6698 rmurill@entergy.com Robert J. Murillo Licensing Manager Waterford 3 W3F1-2006-0043 August 29, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC- 20555
SUBJECT:
Additional Information in Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used In Pressurizer Penetrations and Steam Space Piping Connections Waterford Steam Electric Station, Unit 3 Docket No. 50-382
REFERENCES:
1 NRC letter dated May 28, 2004, NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used In the Fabricationof Pressurizer Penetrationsand Steam Space Piping Connections at Pressurized-Water Reactors 2 Entergy letter dated July 27, 2004, Response to NRC Bulletin 2004-01 Regarding Inspection of Alloy 82/182/600 Materials Used In Pressurizer Penetrationsand Steam Space Piping Connections (W3F1-2004-0058)
Dear Sir or Madam:
On May 28, 2004, the Nuclear Regulatory Commission (NRC) issued NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used In the Fabricationof PressurizerPenetrations and Steam Space Piping Connections at Pressurized-WaterReactors (Reference 1). The NRC requested that all pressurized water reactor addressees provide description of their pressurizer heater and steam space penetrations and inspection plans for the forthcoming and subsequent refueling outages. On July 27, 2004 (Reference 2), Entergy provided the required response for the Waterford Steam Electric Station, Unit 3 (Waterford-3).
In the response, Entergy had noted that weld repairs/replacements were being planned during the spring 2005 refueling outage (RF-1 3) for the pressurizer heater and small bore Alloy 600 pressurizer nozzles and welds. The purpose of this letter is to confirm that associated repairs or replacements were performed. The attachment to this letter provides details on the repairs that were performed during the RF-13 outage.
W3F1-2006-0043 Page 2 There are no commitments associated with this letter. If you have any questions or require additional information, please contact Steve Bennett at 479-858-4626.
Sincerely, RJM/SAB/ssf
Attachment:
Repairs Performed on the Waterford-3 Pressurizer During the Spring 2005 Refueling Outage
W3F17-2006-0043 Page 3 cc: Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Mel Fields MS O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn Attn: N.S. Reynolds 1400 L Street, NW Washington, DC 20005-3502 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. O. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 29th S. Main Street West Hartford, CT 06107-2445
Attachment W3FI -2006-0043 Repairs Performed on the Waterford-3 Pressurizer During the Spring 2005 Refueling Outage
Attachment to W3F1 -2006-0043 Page 1 of I Re;pairs Performed on the Waterford-3 Pressurizer During the Spring 2005 Refueling Outage Heater Sleeves The Waterford-3 Pressuizer contains thirty (30) heater sleeves. Pressurizer Heater Sleeve F-4 was repaired during the fall 2000 refueling outage with an Alloy 690 plug. This plug was retained and no additional repairs or modifications were performed in the spring 2005 refueling outage (RF-13). The remaining twenty nine (29) nozzles were replaced using a half nozzle, mid-wall repair during RF-1 3. The half nozzle repair design relocates the reactor coolant pressure boundary from a partial penetration (J-groove) weld on the inside surface of the pressurizer to a partial penetration weld at the mid-wall of the pressurizer shell. The new pressure boundary for these sleeves is constructed with Alloy 690 materials.
Small Bore Pressurizer Penetrations The Waterford-3 Pressurizer contains six (6) small bore instrument nozzles and 1 (one) temperature nozzle localed both in the steam and water space of the pressurizer. Two upper steam space nozzles were repaired in the spring of 1999 using Alloy 600 weld filler and two were repaired using Alloy 690 materials in the fall 2000 refueling outages. The 2 previously repaired nozzles using Alloy 600 weld filler, the temperature nozzle and the remaining two instrument nozzles, were replaced during RF-13 utilizing a new half-nozzle welded to a pad on the outside of the pressurizer shell using Alloy 690 half-nozzles and weld filler.
Note: There are 5 remaining large bore pressurizer welds and nozzles consisting of two 6-inch pressurizer relief valve nozzles, a spare 6-inch nozzle, the 4-inch pressurizer spray line, and 12-inch surge line. No repairs have been performed on these welds or nozzles to date.