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Category:Letter
MONTHYEARML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000317/20240052024-08-29029 August 2024 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2024005 and 05000318/2024005) ML24240A1112024-08-27027 August 2024 Registration of Use of Casks to Store Spent Fuel ML24240A2462024-08-27027 August 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000317/20240022024-08-0606 August 2024 Integrated Inspection Report 05000317/2024002 and 05000318/2024002 IR 05000317/20240102024-07-31031 July 2024 Age-Related Degradation Inspection Report 05000317/2024010 and 05000318/2024010 ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24198A0442024-07-16016 July 2024 Inservice Inspection Report IR 05000317/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000317/2024401 and 05000318/2024401 05000317/LER-2024-001, Submittal of LER 2024-001-01 for Calvert Cliffs Nuclear Power Plant, Unit 1, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed2024-07-0202 July 2024 Submittal of LER 2024-001-01 for Calvert Cliffs Nuclear Power Plant, Unit 1, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed ML24177A1832024-06-25025 June 2024 Inservice Inspection Report RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24161A0012024-06-0909 June 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML24150A0522024-05-29029 May 2024 Operator Licensing Examination Approval ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24136A1962024-05-15015 May 2024 Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report IR 05000317/20240012024-05-0707 May 2024 Integrated Inspection Report 05000317/2024001 and 05000318/2024001 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24121A0022024-04-29029 April 2024 Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus ML24115A1832024-04-24024 April 2024 Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip ML24101A1942024-04-22022 April 2024 Closeout Letter for GL 2004-02 ML24114A0182024-04-18018 April 2024 Electronic Reporting of Occupational Exposure Reporting ML24107B0992024-04-12012 April 2024 Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000317/20240402024-04-11011 April 2024 95001 Supplemental Inspection Report 05000317/2024040 and Follow-Up Assessment Letter RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24082A0082024-03-22022 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24078A1152024-03-18018 March 2024 10 CFR 50.46 Annual Report ML24059A0632024-03-15015 March 2024 Authorization and Safety Evaluation for Alternative Request ISI-05-021 (EPID L-2023-LLR-0006) - Non-Proprietary IR 05000317/20230062024-02-28028 February 2024 Annual Assessment Letter for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, (Reports 05000317/2023006 and 05000318/2023006 ML24052A0072024-02-14014 February 2024 Core Operating Limits Report for Unit 1, Cycle 27, Revision 0 ML24040A0962024-02-0909 February 2024 Notification of Readiness for NRC 95001 Inspection ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 IR 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-2023-003, 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 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 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 2024-09-06
[Table view] Category:Safety Evaluation
MONTHYEARML24059A0632024-03-15015 March 2024 Authorization and Safety Evaluation for Alternative Request ISI-05-021 (EPID L-2023-LLR-0006) - Non-Proprietary ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications 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 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 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23086C0672023-04-24024 April 2023 Issuance of Amendment Nos. 345 and 323 Deletion of License Conditions Related to Decommissioning Trust ML22195A0252023-01-0303 January 2023 Authorization and Safety Evaluation for Alternative Request No. ISI-05-016 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22202A5142022-07-28028 July 2022 Authorization of Relief Request No. RR-ISI-05-20 Regarding Mitigation of Buried Saltwater System Piping Degradation ML22105A4052022-05-0202 May 2022 Authorization and Safety Evaluation for Proposed Alternative No. ISI-05-019 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML21347A8642022-01-13013 January 2022 Issuance of Amendment Nos. 342 and 320 Modifying the Licensing Basis to Allow for Full Core Offload with No Shutdown Cooling Loop Available During Certain Refueling Outages ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21299A0052021-12-14014 December 2021 Issuance of Amendments No. 340 and 318 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21190A0042021-09-0202 September 2021 Proposed Alternative to the Requirements of the ASME Section XI, Subsection Iwl Concerning Unbound Post-Tensioning Systems ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21039A6362021-02-17017 February 2021 R. E. Ginna - Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20363A2422021-01-26026 January 2021 Issuance of Amendment Nos. 339 and 317 Regarding Accident Tolerant Fuel Lead Test Assemblies (EPID L-2019-LLA-0282) - (Non-Proprietary) ML20356A1212021-01-15015 January 2021 Relief from the Requirements of the ASME Code ML20273A0882020-11-0909 November 2020 Issuance of Amendment Nos. 338 and 316 Revise Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20275A1022020-11-0404 November 2020 Proposed Alternative I4r-07 to the Requirements of the American Society of Mechanical Engineers Code ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20182A1942020-08-13013 August 2020 Issuance of Amendment Nos. 336 and 314 Concerning Reactor Coolant Pump Flywheel Inspection Program ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19330D9092020-02-28028 February 2020 Issuance of Amendment Nos. 332 and 310 Risk-Informed Categorization and Treatment of Systems, Structures, and Components ML19337D0352020-02-28028 February 2020 Issuance of Amendment Nos. 333 and 311 Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19298C9722019-10-31031 October 2019 50.69 Apla SE Input L-2018-LLA-0482 ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19165A2472019-08-26026 August 2019 Issuance of Amendment Nos 330 and 308 Relocation and Consolidation the Emergency Operations Facility and Joint Information Center for the Calvert Cliffs Nuclear Power Plant ML19168A1172019-07-29029 July 2019 Issuance of Relief Request 15R-03 Use of ASME Code N-513-4 ML19196A1232019-07-19019 July 2019 Issuance of Relief Request 15R-04 Use of Encoded Phased Array Ultrasonic Examination Techniques ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19134A3732019-05-30030 May 2019 Issuance of Relief Request I5R-05 Relief from the Requirements of the ASME Code ML19136A2162019-05-30030 May 2019 Use of a Provision in a Later Edition of the ASME Code ML19053A5882019-04-19019 April 2019 Plants, Units 1 and 2 - Issuance of Amendment Nos. 329 and 307 Removal of an Exception to the Minimum Education Requirements for Shift Technical Advisors ML19046A0432019-02-25025 February 2019 Plants, Units 1 and 2 - Revision to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule ML18365A3732019-01-22022 January 2019 Issuance of Amendment Nos. 328 and 306 to Extend Completion Time of Required Action D.3 of Technical Specification 3.8.1 to 14 Days ML18318A0142018-11-30030 November 2018 Correction to Amendment Nos. 326 and 304 Add Risk-Informed Completion Time Program ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements 2024-03-15
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 27, 2011 Mr. George H. Gellrich, Vice President Calvert Cliffs Nuclear Power Plant, LLC Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO.2 -REVIEW OF THE 2011 STEAM GENERATOR TUBE,INSPECTIONS (TAC NO. ME6672)
Dear Mr. Gellrich:
By letter dated June 30, 2011, Calvert Cliffs Nuclear Power Plant, LLC, the licensee, submitted information summarizing the results of the 2011 steam generator (SG) tube inspections performed at the Calvert Cliffs Nuclear Power Plant Unit No.2. The Nuclear Regulatory Commission (NRC) staff has completed its review of this report. Based on its review, the staff concludes that the licensee provided the information required by the plant's technical specifications.
In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and that inspection results appear to be consistent with industry operating experience at similarly designed and operated units. The NRC staff's review of this report is enclosed.
Please feel free to contact me at 1364 if you have any questions.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-318
Enclosure:
As stated cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION CALVERT CLIFFS NUCLEAR POWER PLANT. LLC REVIEW OF THE 2011 STEAM GENERATOR TUBE INSPECTIONS CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO.2 DOCKET NUMBER 50-318 By letter dated June 30, 2011 (Agencywide Documents Access Management System Accession No. ML111822717), Calvert Cliffs Nuclear Power Plant, LLC, the licensee, submitted information summarizing the results of the 2011 steam generator (SG) tube inspections performed at Calvert Cliffs Nuclear Power Plant Unit No.2 (Calvert Cliffs Unit 2). Calvert Cliffs Unit 2 has two Babcock and Wilcox International SGs. Each SG contains 8471 thermally-treated Alloy 690 tubes. Each tube has a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.042 inches. The SGs have a triangular tube pitch arrangement with 1 inch spacing between tube centers. The tubes are hydraulically expanded the entire depth of the tubesheet.
Rows 1-18 of the U-bend received stress relief treatment after bending. The licensee provided the scope, extent, methods, and results of their SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging, taken in response to the inspection findings. The tubes in SGs 21 and 22 were inspected this outage. After reviewing the information provided by the licensee, the staff has the following comments or observations: The licensee reported that all plugs were visually inspected and confirmed to be in the proper location with no evidence of deformation or leakage. The licensee reported that the 1 st lattice support was visually inspected with views looking upward at the bottom of the 1 st lattice support showing mostly clean conditions, with an occasional flake wedged between the tubes and the lattice bars. The tube surfaces had a fairly uniform thin film of deposit but looked clean. The licensee reported that all lattice support and shroud support components appeared structurally sound and in good condition.
In addition, the shroud support bracket weldments and lattice ring backing bars were observed and found to be in good condition.
It was also reported that the annular region of the 1 st lattice support was viewed and all structural components such as shroud support lugs were found to be sound and intact. The horizontal surfaces Enclosure
-2 in the annular region were characterized as being uniformly coated with a thin, dark gray colored film deposit. The licensee also reported that the materials for the lattice, lattice assembly, bolts, and the support structures appeared as manufactured with no degradation. The licensee reported 343 Potential Loose Part (PLP) indications in SG 21, and 203 were recorded in SG 22. Of the 343 PLP indications in SG 21, 92 of them were classified as inner bundle single (IBS) indications.
In addition, of the 203 PLP indications detected in SG 22, 69 of them were classified as IBS indications.
The licensee stated that I BS indications are defined as PLP indications located in a single tube without a PLP indication in an adjacent bounding tube. The licensee indicated that most of the PLPs were caused by sludge rocks and/or scale. The licensee indicated that during the 2011 refueling outage, the only metallic objects identified and remaining in the Calvert Cliffs Unit 2 SGs are three pieces of wire plus a small shear pin (1/32" diameter by 1/16" length) in SG 22 and two other smaller metallic objects in SG 21 (machining curl and a piece of wire). The licensee also identified non-metallic objects (primarily sludge rocks, flakes, gasket material, etc.) that remain in the SGs. It was reported that historical metallic objects continue to remain in the SGs from previous outages. These objects were addressed and dispositioned at the time. The disposition either allowed the object to remain in-place or required associated tubes to be plugged and/or stabilized. The licensee confirmed that a bounding analysis was performed on the objects newly identified during the Unit 22011 refueling outage. The licensee stated that the results of this analysis concluded that a complete through-wall wear scar or indication in the tube outer diameter is not probable over the next two fuel cycles or four effective full power years. Furthermore, it was indicated that the analysis previously performed in support of historical metallic objects continues to remain in effect, where applicable.
Based on a review of the information provided, the staff concludes that the licensee provided the information required by the technical specifications.
In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and that inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Principal Contributor:
A. Obodoako, NRR Date: October 27, 2011 October 27, 2011 Mr. George H. Gellrich, Vice President Calvert Cliffs Nuclear Power Plant, LLC Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO.2 -REVIEW OF THE 2011 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. ME6672)
Dear Mr. Gellrich:
By letter dated June 30, 2011, Calvert Cliffs Nuclear Power Plant, LLC, the licensee, submitted information summarizing the results of the 2011 steam generator (SG) tube inspections performed at the Calvert Cliffs Nuclear Power Plant Unit No.2. The Nuclear Regulatory Commission (NRC) staff has completed its review of this report. Based on its review, the staff concludes that the licensee provided the information required by the plant's technical specifications.
In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and that inspection results appear to be consistent with industry operating experience at similarly designed and operated units. The NRC staff's review of this report is enclosed.
Please feel free to contact me at 1364 if you have any questions.
Sincerely, Ira! Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-318
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL 1-1 r/f RidsNrrDorlLpL 1-1 RidsNrrPMCalvertCliffs RidsOgcMailCenter RidsAcrsAcnwMailCenter RidsNrrDeEsgb AOgodoako, NRR RidsRegion1 MailCenter KKarwoski, NRR VCusumano, NRR RidsN rrLAS Little GDentel, R1 ADAMS Accession No.: ML112930436 OFFICE LPL 1-1/PM LPL 1-1/LA ESGB/BC LPL1-1/BC NAME DPickett ABaxter for SLittle VCusumano(A) by memo dated NSalgado DATE 101 I 11 10/25 111 10/11/11 101 111 OFFICIAL RECORD COpy