|
---|
Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML16155A3072016-05-23023 May 2016 Summary of Facility Changes, Tests, Experiments and Commitment Changes ML12264A5632012-09-18018 September 2012 Reactor Vessel Internals Inspection Plan Review Request Response to Request for Additional Information ML12215A0122012-07-24024 July 2012 2012 Inservice Inspection Summary Report ML12125A2792012-05-0303 May 2012 Inservice Inspection Program Fourth Ten-Year Interval 10 CFR 50.55a Request No. RR-2-4 ML12125A3002012-05-0303 May 2012 Inservice Inspection Program Fourth Ten-Year Interval Withdrawal of 10 CFR 50.55a Request No. RR-2-3 ML12123A2702012-05-0101 May 2012 Inservice Inspection Program Fourth Ten-Year Interval Supplement to 10 CFR 50.55a Request No. RR-2-3 ML12122A1372012-04-30030 April 2012 Inservice Inspection Program Fourth Ten-Year Interval, 10 CFR 50.55A Request No. RR-2-3, Response to Request for Additional Information ML12129A0362012-04-30030 April 2012 Inservice Inspection Program Fourth Ten-Year Interval 10 CFR 50.55a Request No. RR-2-3, Response to Request for Additional Information ML12120A0042012-04-29029 April 2012 Inservice Inspection Program Fourth Ten-Year Interval Relief Request RR-2-3 ML11355A1562011-12-12012 December 2011 Reactor Vessel Internals Inspection Plan Review Request ML11284A1932011-09-28028 September 2011 Inservice Inspection Program Fourth Ten-Year Interval Limitation to Examination Relief Request No. RR-G-5 ML11178A0332011-06-13013 June 2011 2011 Inservice Inspection Summary Report ML1025200782010-09-0707 September 2010 Inservice Inspection Program Fourth Ten-Year Interval 10 CFR 50.55a Request No. RR-2-2 ML1000705542010-01-0404 January 2010 2009 Inservice Inspection Summary Report ML0821806562008-07-29029 July 2008 Inservice Inspection Summary Report ML0701005242007-01-0808 January 2007 Inservice Inspection Summary Report ML0608102632006-03-17017 March 2006 Second 10-year Inservice Inspection Class Mc (ISI) Program ML0524402632005-06-23023 June 2005 Inservice Inspection Third 10-Year Interval June 16, 1994 - June 16, 2004 Limitation to Examination Relief Requests of the Kewaunee Nuclear Power Plant ML0506202422005-02-24024 February 2005 2004 Inservice Inspection (ISI) Summary Report ML0427203662004-09-17017 September 2004 Response to Request for Additional Information Related to Third and Fourth 10-Year In-Service Inspection Intervals Request for Relief for Nuclear Management Company, LLC ML0423901562004-08-16016 August 2004 Inservice Testing Program Fourth Ten-Year Interval Update ML0411805802004-04-16016 April 2004 In-Service Inspection (ISI) Program Relief Request No. RR-1-8 Rev.1, RR-1-9, RR-1-10, RR-1-11 and RR-G-6 for Third Ten-Year Interval. In-Service Inspection (ISI) Program Relief Request No. RR-1-7 Rev. 1 and RR-1-8 Rev. 1 for Fourth Ten-Year ML0402803772004-01-16016 January 2004 In-Service Inspection (ISI) Program Relief Request No. RR-MC-2 for Class Mc ML0335807352003-12-16016 December 2003 to Risk-Informed Inservice Inspection Program Plan, Kewaunee Nuclear Power Plant ML0335807342003-12-16016 December 2003 Inservice Inspection Program for Fourth Inspection Interval ML0323205222003-08-14014 August 2003 Inservice Testing Program Project ML0322501652003-08-0606 August 2003 2003 Inservice Inspection (ISI) Summary Report ML0207205472002-02-22022 February 2002 Part 2 of 2, Kewaunee Nuclear Power Plant, 2001 Inservice Inspection (ISI) Summary Report ML0207205592002-02-22022 February 2002 Part 1 of 2, Kewaunee Nuclear Power Plant, 2001 Inservice Inspection (ISI) Summary Report 2016-05-23
[Table view] Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000305/20240022024-08-22022 August 2024 NRC Inspection Report 05000305/2024002 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24136A1952024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24130A0022024-05-0909 May 2024 Summary of Facility Changes, Tests and Experiments and Commitment Changes IR 05000305/20240012024-05-0202 May 2024 NRC Inspection Report No. 05000305/2024001 ML24121A2472024-04-29029 April 2024 and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24101A0422024-04-22022 April 2024 Solutions Inc. – Exemption from Select Requirements of 10 CFR Part 73 ((Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24106A0492024-04-15015 April 2024 2023 Annual Radioactive Effluent Release Report ML24080A0702024-03-20020 March 2024 Decommissioning Trust Fund Annual Report ML24079A0162024-03-19019 March 2024 Annual Property Insurance Status Report ML24073A2312024-03-13013 March 2024 and Three Mile Island Nuclear Station, Unit 2 - Management Change ML24061A0202024-02-15015 February 2024 (Ksp) ISFSI, Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 6 ML23339A1332024-01-26026 January 2024 Exemption from the Req of 10 CFR Part 50.82(a)(8)(i)(A) to Use the Kewaunee Decommissioning Trust Fund for the Management of Site Restoration Activities IR 05000305/20230022023-12-27027 December 2023 NRC Inspection Report 05000305/2023002 (Drss); 07200064/2023001 (Drss) ML23332A1922023-11-28028 November 2023 Solutions, Inc., Request for Exemptions from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23278A1002023-10-0505 October 2023 Response to Request for Additional Information (RAI) Application for Kewaunee Solutions (Ks) Site Restoration Activities ML23222A1522023-08-29029 August 2023 Letter RAI KPS Exemption Site Restoration Final Repaired IR 05000305/20230012023-08-17017 August 2023 NRC Inspection Report No. 05000305/2023001-Kewaunee Power Station ML23171B0822023-07-0505 July 2023 Letter - Kewaunee Power Station - Issuance of Exemption from Certain Requirements from 10 CFR Part 20, Appendix G, Section Iii.E ML23132A0012023-05-11011 May 2023 2022 Annual Radiological Environmental Operating Report ML23116A2182023-04-26026 April 2023 2022 Annual Radioactive Effluent Release Report ML23089A3042023-03-30030 March 2023 Decommissioning Fund Status Report ML23093A0312023-03-29029 March 2023 Solutions, Inc., Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv) for Site Restoration Activities ML23088A2752023-03-29029 March 2023 Solutions, Inc., Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23087A0402023-03-27027 March 2023 Annual Property Insurance Status Report ML23087A0292023-03-27027 March 2023 2022 Annual Report of Occupational Radiation Exposure ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23024A0122023-01-26026 January 2023 Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring IR 05000305/20220022023-01-0303 January 2023 NRC Inspection Report Nos. 05000305/2022002(DRSS) Kewaunee Power Station ML22292A2302022-11-25025 November 2022 U.S. Nuclear Regulatory Commissions Analysis of Dominion Energy Kewaunees Decommissioning Funding Status Report for Kewaunee Power Station, Docket No. 50-305 ML22290A0052022-10-13013 October 2022 Resubmittal of Kewaunee Power Station Independent Spent Fuel Storage Installation (ISFSI) Only Emergency Plan (Ioep) and IOEP- Emergency Action Level (EAL) Basis Document, Revision 0KS ML22241A0302022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 5 ML24061A0182022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Pla11, Training and Qualification Plan and Safeguards Contingency Plan Revision 5 IR 05000305/20220012022-08-0101 August 2022 NRC Inspection Report Nos. 05000305/2022001(DNMS) - Kewaunee Power Station ML22215A1512022-07-27027 July 2022 Executed Financial Assurance Instruments for the Kewaunee License Transfer License No. DPR-43 (Docket Nos. 50-305, 72-64) ML22209A1252022-07-26026 July 2022 Amendment No. 11 to Indemnity Agreement No. B-53 for Kewaunee Power Station (KPS) - Signed by Kewaunee Solutions, Inc ML22175A1132022-06-30030 June 2022 Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure ML22160A5272022-06-28028 June 2022 Enclosure 1 - Amendment No. 221 to Renewed Facility Operating License No. DPR-43 ML22160A5262022-06-28028 June 2022 Letter - KPS - Issuance of Conforming License Amendment Regarding Indirect Transfer of License from DEK, Inc. to Kewaunee Solutions, Inc ML22160A5282022-06-28028 June 2022 Enclosure 2 - Amendment No. 11 to Indemnity Agreement B-53 ML22188A0812022-06-23023 June 2022 ISFSI, Virgil C. Summer Nuclear Station, Unit 1 & ISFSI, North Anna Power Station, Units 1 & 2 & ISFSI, Surry Power Station, Units 1 & 2 & ISFSI - Submission of Revision 32 of the Quality Assurance Topical Report ML22172A2452022-06-22022 June 2022 Notification of Planned Closing Date and Required Regulatory Approvals for the Kewaunee License Transfer Transaction ML22175A0662022-06-17017 June 2022 Designation of Additional Reviewing Official for ISFSI and 10 CFR Part 37 Program Security Background Investigations ML22166A3392022-06-13013 June 2022 Notification of Nuclear Insurance ML22138A2552022-05-10010 May 2022 Submittal of 2021 Annual Radiological Environmental Operating Report ML22158A2112022-05-10010 May 2022 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML22091A1892022-04-0101 April 2022 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML22108A0352022-04-0101 April 2022 License Transfer to Kewaunee Solutions, Inc ML22089A2432022-03-30030 March 2022 Decommissioning Funding Status Report, Financial Test and Independent Public Accountants' Letter of Attestation 2024-09-18
[Table view] |
Text
Dominion Energy Kewaunee, Inc.
N490 Hwy 42, Kewaunee, W1 54216 ,[
Web Address: www.dom.com April 30, 2012 ATTN: Document Control Desk Serial No. 12-319A U. S. Nuclear Regulatory Commission LIC/JG/RO 11555 Rockville Pike Docket No.: 50-305 Rockville, MD 20852-2738 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION INSERVICE INSPECTION PROGRAM FOURTH TEN-YEAR INTERVAL 10 CFR 50.55a REQUEST NO. RR-2-3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION By application dated April 29, 2012 (Reference 1), Dominion Energy Kewaunee, Inc.
(DEK), requested approval of 10 CFR 50.55a Request RR-2-3 for the Fourth Ten-year Interval of the Inservice Inspection (ISI) Program for Kewaunee Power Station (KPS).
10 CFR 50.55a Request RR-2-3 proposed a temporary deviation from the requirements of ASME Section XI, Appendix IX, Article IX-1000, Paragraph (c)(2), which prohibits the use of clamping devices on "... portions of a piping system that forms the containment boundary" and ASME Section XI, Appendix IX, Article IX-6000(a), which states that the area immediately adjacent to the clamping device shall be examined using a volumetric method.
During a telephone conference call with DEK personnel on April 29, 2012, the Nuclear Regulatory Commission (NRC) staff requested additional information (RAI) regarding 10 CFR 50.55a Request RR-2-3. The RAI questions and associated DEK responses are provided in Attachment 1 to this letter.
If you have questions or require additional information, please feel free to contact Mr.
Craig Sly at 804-273-2784.
Very truly yours, Site Vic resident - Kewaunee Power Station 01g
Serial No. 12-319A RAI Response RR-2-3 Page 2 of 2
Attachment:
- 1. Response to Request for Additional Information, 10 CFR 50.55a Request RR-2-3
References:
- 1. Letter from A. J. Jordan (DEK) to Document Control Desk (NRC), "Inservice Inspection Program Fourth Ten-Year Interval 10 CFR 50.55a Request No. RR-2-3",
,dated April 29, 2012.
Commitments made by this letter: None cc:
Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. Karl D. Feintuch Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station.
Serial No. 12-319A ATTACHMENT I RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 10 CFR 50.55a REQUEST NO. RR-2-3 FOURTH TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
Serial No. 12-319A RAI Response RR-2-3 Page 1 of 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 10 CFR 50.55a REQUEST NO. RR-2-3 During a telephone conference call with DEK personnel on April 29, 2012, the Nuclear Regulatory Commission (NRC) staff requested additional information (RAI) regarding 10 CFR 50.55a Request RR-2-3 (Reference 1).
The RAI questions are provided below, followed by the DEK response.
NRC Question 1 On page 3 of 7 in the reason for the request, the licensee stated that approximately 8 Rem of radiation dose is required for the first option. What is the radiological dose for the second option?
Response
The second option described in 10 CFR 50.55a Request RR-2-3 (Reference 1) is to perform a temporary repair of the RHR piping by installing a leak-limiting strong-back clamp to ensure structural integrity prior to making a MODE change from MODE 5 to MODE 4. The radiological dose estimate associated with installation and removal of the leak-limiting strong-back clamp is 350 mRem.
NRC Question 2 The licensee stated on page 7 of 11 of the temporary modification that during sealant injection, the RHR heat exchanger outlet temperature will be maintained between 1500 and 200 0 F. It appears that an RHR temperature of 200' would cause the plant to violate the 195°F maximum RCS temperature administrative limit for MODE 5 stated in Reference 7 of the Enclosure (temporary modification) to RR-2-3.
Please clarify what the temperature operating band is during sealant injection.
Response
On page 7 of 11 of the temporary modification, the statement that discussed RHR heat exchanger outlet temperature being maintained between 1500 and 2000 F, will be revised to state that during sealant injection, the maximum reactor coolant system
Serial No. 12-319A RAI Response RR-2-3 Page 2 of 3 temperature will not exceed 195 0 F as indicated by the hottest core exit thermocouple (CET) reading. Sealant injection will be performed in MODE 5. This process is controlled in accordance with plant procedures.
NRC Question 3 The licensee stated on page 9 of 11 in the temporary modification, in the constraining effects section, that the clamp will not constrain the pipe significantly during thermal expansion. Please provide in more detail your overall assessment of the thermal expansion effects, from the time of installation to the time of maximum system temperature. Please provide approximate maximum system temperature with the device installed.
Response
Constrainingeffects: The clamp holding the leak sealant enclosure is a single clamp band with a 3/16" fillet weld at the 3/4" pipe interface. The temperature increase experienced by the clamp from the point of installation until its removal will be no more than 95'F (From 150'F min to 245°F max). This temperature increase will result in a radial expansion of the 10" diameter pipe by no more than 0.005". The effect of this radial expansion on the strong-back bolts will be an increase in tensile stress of approximately 20%. The initial torque on the strong-back bolts is approximately 40% of the material yield. Therefore, the additional tensile stress on these bolts will remain within the yield point of the material.
There will also be a constraining effect on the 3/4" pipe due to the addition of the weld to the leak seal enclosure. If unrestrained, the thermal expansion from the center of the 10" pipe to the location of the new weld on the 3/4" pipe is approximately 0.007". Since the clamp materials have the same thermal expansion properties as the pipe materials it would also grow at the same rate. However, the clamp will be slightly cooler than the pipe due to the insulating effect of the sealant material around the 3/4" pipe. This minor difference in material temperatures will result in relatively small compressive loads on the 3/4" pipe shared with an increase in tensile loads on the strong-back bolts discussed above. The loads on the new weld are considered insignificant compared to the capacity of the weld (approximately 7400 Ibs).
In summary, the constraining effect of the leak sealant enclosure and strong-back will not significantly impact the piping stresses or the strong-back bolting.
Serial No. 12-319A RAI Response RR-2-3 Page 3 of 3 REFERENCE
- 1. Letter from A. J. Jordan (DEK) to Document Control Desk (NRC), "Inservice Inspection Program Fourth Ten-Year Interval 10 CFR 50.55a Request No. RR-2-3",
dated April 29, 2012.