Letter Sequence Response to RAI |
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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 Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owners 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 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 W3F1-2009-0020 June 1, 2009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to NRC Request for Additional Information Re: The 2007 and 2008 (Refueling Outage 15) Steam Generator Tube Inspections (TAC No. ME0164)
Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
REFERENCES:
1 Entergy letter dated November 25, 2008 "180-Day Steam Generator Tube Inspection Report for the 1 5 th Refueling Outage" (W3F1-2008-0074) 2 NRC letter dated April 17, 2009 "Waterford Steam Electric Station, Unit 3 - Request for Additional Information Re: The 2007 and 2008 (Refueling Outage 15) Steam Generator Tube Inspections (TAC No.
ME0164)" (ILN09-0044)
Dear Sir or Madam:
On April 17, 2009, Entergy received communication (Reference 2) from members of the NRC Staff requesting additional information associated with Entergy's submittal of Waterford 3's "180-Day Steam Generator Tube Inspection Report for the 1 5 th Refueling Outage" (Reference 1).
Attachment 1 contains Entergy's response to the NRC questions. Attachment 2 contains a legible copy of Table E-1.
There are no new commitments contained in this letter.
.40oy
W3F1-2009-0020 Page 2 If you have any questions or require additional information, please contact me at 504-739-6715.
Sincerely, RJM/RJP Attachments:
- 1. Entergy's response to the NRC questions
- 2. Legible copy of Table E-1
W3F1-2009-0020 Page 2 cc: Mr. Elmo E. Collins, Jr.
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library 95 Glastonbury Blvd.
Suite 300 Glastonbury, CT 06033-4443
Attachment 1 To W3F1 -2009-0020 Response to NRC Request for Additional Information Re: The 2007 and 2008 (Refueling Outage 15)
Steam Generator Tube Inspections
(
to W3F1-2009-0020 Page 1 of 3 Response to Request for Additional Information Question 1:
The information in Table E-1 is not legible; please provide another copy of Table E-1.
Response 1:"
A legible copy of Table E-1 is provided as Attachment 2.
Question 2:
In Table E-1, SG-31 appears to have 8474 tubes inservice prior to RFO15 and 1176 tubes that were previously removed from service. These numbers do not agree with the total number of SG tubes (i.e., 9350 tubes). Please clarify the actual number of tubes in service and removed from service.
Response 2:
A corrected copy of Table E-1 is provided as Attachment 2.
The original submittal includes the correct number of tubes in-service in paragraph 2.0.
Question 3:
In Table F-1, the total number of plugs listed for SG-32 is 1217; however, the numbers associated with the separate outages from the column "SG32 Plugs" sum to 1218, not 1217.
The asterisk associated with the number 460 (for 2006) was not shown in your outage summary report for RFO 14 (fall 2006). Please verify the number of tubes plugged in SG-32.
Also, please discuss the tube that is plugged in just one end (i.e., the tube referenced by the asterisk).
Response 3:
During RF14 tube SG32 R1 C1l15 was selected to be plugged preventatively as part of the response to failed batwings. The tube was plugged on one end only. The inability to plug this tube on one end was entered into the W3 Corrective Action program in Condition Report CR-WF3-2006-04601. Entergy determined that it was acceptable to operate with the tube plugged on one end prior to start-up from RF14.
The number of tubes "in-service" has duplicity because one is treated as "plugged' with respect to plugging limits [reduces RCS flow] and is "open" for tube integrity [RCS pressure boundary].
During RF15 the tube was re-examined and found to be without flaws. The plug was planned to be removed to allow full examination. The plug was not removed due to technical, difficulties. This condition was also entered into the W3 Corrective Action program in
P to W3F1-2009-0020 Page 2 of 3 Condition Report CR-WF3-2008-02203. The open end of the tube was plugged during RF1 5, and the tube was removed from service. The number of tubes plugged in SG32 is 1217.
Question 4:
In Section G of your November 25, 2008, letter, you discuss condition monitoring, but the discussion on structural integrity limits only references the three times the normal operating differential pressure criterion. Please confirm that this criterion is the most limiting of the structural integrity performance criteria. If this is not the most limiting criterion, please discuss whether the tubes satisfied all the structural integrity performance criteria.
Response 4:
Structural Integrity Performance Criteria evaluation concludes 3dP is most limiting.
Question 5:
Please confirm that no crack-like indications were found in the U-bend region of Rows 1 and 2 and that no crack-like indications were found during your dent and ding examinations. If indications were identified, please discuss the nature of the indications and the size of the dent/ding (if applicable) and the basis for not expanding the inspection.
Response 5:
The results of the examination of the Row 1 and 2 tubes identified no U-bend cracks and no dent/ding cracks.
Question 6:
Other than the free span indication in SG 31 in row 109 column 99, please discuss (and identify) whether any other free span indications (other than those near the top of the tubesheet) were detected.
Response 6:
A free span axial Outside Diameter Stress Corrosion Cracking (ODSCC) was also reported on R49 C59 at 04H +14.9" in SG32. Plus Point amplitude was 0.37V; length from profiling was 0.35 inch.
to W3F1-2009-0020 Page 3 of 3 Question 7:
During a conference call in May 2008, preliminary results indicated that one tube had a 42 percent through wall (TW) wear indication. Please identify this tube and confirm it was plugged. Also, please confirm that all other wear indications greater than or equal to 40 percent TW were plugged.
Response 7:
All tubes with greater than or equal to 40 percent TW were plugged. The tube with the 42%
TW is listed.
SG31 had no indications greater to or equal to 40 percent TW.
SG32: R74 C48 at BW5, 42%TW SG32: R1 10 C32 at BW9, 47%TW, both plugged Question 8:
Please discuss whether any crack-like indications were found at or near locations with wear indications (e.g., at the same eggcrate location).
Response 8:
There were no crack wear indications found at the same location.
In SG31, tube R26 C58 at 03H, both axial ODSCC and wear reported at same structure, wear and ODSCC are not coincident (Different bars of eggcrate structure).
Attachment 2 To
) W3F1 -2009-0020 Table E-1 to W3F1-2009-0020 Page 1 of 1 Table E-1 Waterford 3 RFO 15 Repair Summary May 2008 Tube Status SG - 31 SG - 32 Tubes in service prior to RF 8174 8184 Total Number of tubes previously removed from service 1176 1166 Repair Candidates from RFO15:
Hot Leg Top of Tubesheet Axial Indications (Above TTS) '0 0 Hot Leg Top of Tubesheet Circ: Indications (Above TTS) 0 1 Hot Leg Tube Sheet Axial Indications (Within Tubesheet) 23 9 Hot Leg Tube Sheet Circ. Indications (Within Tubesheet) 32 8 Tubesheet with Axial and Circumferential Indications 2 0 Tubesheet and Support Plate with Axial Indications 1 0 Tubesheet Circumferential and Support Plate Axial Indications 0 0 Egg-Crate With Axial Indications 73 15 Batwings With Axial Indication 6 4 Batwings With Axial Indication and Support Plate Axial Indication 0 0 Batwings With Volumetric Indication .0 0 Hot Leg Volumetric Indications 1 0 Cold Leg Volumetric Indications 0 0 Row 1 - Row 2 U-Bend Indications 0 0 Bobbin Percents => 40% 0 2 Customer Decision Preventative (Box In) 0 6 Customer Decision Preventative (Row 1/Row 2) 5 6 Hot Leg Total Tubes Deplugged and Replugged - Post RFO15 0 0 Cold Leg Total Tubes beplugged and Replugged - Post RFO15 3 21 Total Candidate Tubes to be Repaired 146 72 Hot Leg 54" Stabilizers Installed During RFO15* 11 7 Hot Leg 268" Stabilizers Installed During RFO15* 0 4 Hot Leg 384" Stabilizers Installed During RFO15* 0 0 Cold Leg 54" Stabilizers Installed During RFO15* 0 0 Cold Leg 268" Stabilizers Installed During RFO15* 0 5 Cold Leg 384" Stabilizers Installed During RFO15* 0 12 Total Stabilizers Installed - RFO15 11 28 Total Tubes Plugged - Post RFO15 1319 1217 Note: Above Tubesheet is all calls => .01" above.
Note: Within Tubesheet is all calls =<.00".
Note:
- Denotes Includes Deplugged tubes