Letter Sequence Other |
---|
|
|
MONTHYEARML17053D4942017-02-27027 February 2017 Closeout Letter Concerning Dissimilar Metal Butt Weld Flaw in Pressurizer Safety Relief Nozzle-to-Safe-End Weld Project stage: Other 2017-02-27
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 27, 2017 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 - CLOSEOUT LETTER CONCERNING DISSIMILAR METAL BUTT WELD FLAW IN PRESSURIZER SAFETY RELIEF NOZZLE-TO-SAFE-END WELD (CAC NO. MF7409)
Dear Mr. Hanson:
By letter dated February 25, 2016 (Agencywide Documents Access and Management System Accession No. ML16057A002), Exelon Generation Company, LLC (the licensee) submitted a report in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(ii)(F)(6) for the Calvert Cliffs Nuclear Power Plant, Unit 1 (CCNPP1 ). The report summarized the evaluation, along with inputs, methodologies, assumptions, and the preliminary causes for the identification of a change in size of a previous axial flaw in the pressurizer safety relief nozzle-to-safe-end dissimilar metal butt weld (ISi Weld 4-SR-1006-1) that was mitigated by the Mechanical Stress Improvement Process (MSIP) in 2006.
Under 10 CFR 50.55a(g)(6)(ii)(F)(6), for any mitigated weld whose volumetric examination detects growth of existing flaws in the required examination volume that exceeds the previous IWB-3600 flaw evaluations or new flaws, a report summarizing the evaluation, along with inputs, methodologies, assumptions, and causes of the new flaw or flaw growth is required to be provided to the U.S. Nuclear Regulatory Commission (NRC) prior to the weld being placed in service other than modes 5 or 6.
The NRC staff has completed its assessment of the subject report and finds that it meets the regulatory requirements of 10 CFR 50.55a(g)(6)(ii)(F)(6), and no additional followup regulatory action is required at this time.
As stated in the report, during the February 2016 refueling outage (CC1 R23), the licensee performed a full structural weld overlay of ISi Weld 4-SR-1006-1 to ensure future structural integrity of the weld for the remaining life of the plant. The licensee also examined all 27 dissimilar metal butt welds within the scope of the American Society of Mechanical Engineers (ASME) Code Case N-770-1 during the refueling outage. No other new flaws or changes in existing flaws were found. The NRC staff finds that the licensee's actions address any uncertainties concerning the leak-tightness or structural integrity of ISi Weld 4-SR-1006-1, and there are no immediate safety concerns regarding the subject weld or any other dissimilar metal butt welds under the scope of ASME Code Case N-770-1 at CCNPP1.
The NRC staff also reviewed the licensee's report for the generic impact of potential growth of an existing flaw in an MSIP mitigated weld. The NRC staff evaluated both the stress effect of the applied MSIP and the non-destructive examinations performed by the licensee in 2006,
B. Hanson 2010, and 2016. Based on the non-destructive examination information provided to the NRC, the staff was unable to reach an independent conclusion regarding the change in the reported axial flaw through-wall extent from the licensee's data between 2006 and 2016. Additionally, the NRC identified an issue of generic interest regarding the modeling of post-MSIP stresses; the NRC staff's continued assessment of this generic issue will be coordinated via the Electric Power Research lnstitute's Materials Reliability Program.
Based on the above, the NRC staff concludes that the regulatory requirements of 10 CFR 50.55a(g)(6)(ii)(F)(6) are satisfied, and no further action is requested from the licensee at this time. The NRC staff activities on the subject report have been concluded, and the associated Cost Activity Code MF7409 has been closed.
If you have any questions regarding this matter, please contact me at 301-415-1030 or Richard.Guzman@nrc.gov.
Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-317 cc: Distribution via Listserv
B. Hanson
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 - CLOSEOUT LETTER CONCERNING DISSIMILAR METAL BUTT WELD FLAW IN PRESSURIZER SAFETY RELIEF NOZZLE-TO-SAFE-END WELD (CAC NO. MF7409) DATED FEBRUARY 27, 2017 DISTRIBUTION:
Public RidsNrrDorlLpl1 Resource LPL 1 R/F RidsACRS_MailCTR Resource RidsNrrDeEpnb Resource JCollins, NRR RidsNrrPMMillstone Resource RidsNrrLALRonewicz Resource RidsRgn1 MailCenter Resource ADAMS A ccess1on N um ber: ML17053D494 *b>Y e-ma1 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DE/EPNB/BC* DORL/LPL 1/BC(A) DORL/LPL 1/PM NAME RGuzman LRonewicz DAiiey SKoenick RGuzman DATE 02/24/2017 02/24/2017 02/22/2017 02/27/2017 02/27/2017 OFFICIAL RECORD COPY