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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24198A0442024-07-16016 July 2024 Inservice Inspection Report ML24177A1832024-06-25025 June 2024 Inservice Inspection Report ML24005A0232024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports, Refueling Outage 25 CC1R25 ML24005A0242024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports, Refueling Outage 23 CC2R23 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 ML23160A0032023-06-0909 June 2023 Inservice Inspection Report ML21169A0352021-06-18018 June 2021 Inservice Inspection Report ML20363A1562020-12-17017 December 2020 Inservice Inspection Report ML20182A1622020-06-30030 June 2020 Proposed Alternative to Supplemental Position Indication Testing Interval NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 ML19249B9942019-09-0606 September 2019 Submittal of the Update to the Fifth Ten-Year Interval Snubber Inservice Testing Program Plan ML19200A0292019-07-16016 July 2019 Spring 2019 - 180 Day Steam Generator Report ML19169A0602019-06-13013 June 2019 Lnservice Inspection Report NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants ML18354A4312018-12-19019 December 2018 Submittal of Relief Requests Associated with the Fifth Lnservice Inspection (ISI) Interval ML18192B9902018-07-0606 July 2018 Submittal of the Fifth Ten-Year Interval Inservice Testing Program for Safety Related Pumps and Valves ML18169A1492018-06-14014 June 2018 Inservice Inspection Report ML17159A5252017-06-0505 June 2017 Clavert Cliffs, Unit 1 - Inservice Inspection Report ML16243A4792016-08-29029 August 2016 CC1 R23 180-Day Steam Generator Tube Inspection Report ML16159A2982016-06-0606 June 2016 Inservice Inspection Report ML16012A4682016-01-0808 January 2016 Inservice Inspection Reports ML15314A0792015-11-0606 November 2015 Spring 2015 - 180 Day Steam Generator Report ML15239A2922015-08-25025 August 2015 Spring 2015 - 180 Day Steam Generator Report ML15160A3222015-06-0404 June 2015 Inservice Inspection Report, 2015 Owner'S Activity Report for RFO-20 Inservice Examinations ML14170A8922014-06-17017 June 2014 Inservice Inspection Report ML13168A3952013-06-13013 June 2013 Inservice Inspection Report ML12255A3902012-09-0707 September 2012 Inservice Inspection Report ML12178A4442012-06-25025 June 2012 Submittal of Inservice Inspection Report ML12032A2732012-01-31031 January 2012 Inservice Inspection Report Revision 01 (Unit 2) ML11147A0712011-05-25025 May 2011 Inservice Inspection Report, 2011 Owner'S Activity Report for RFO Inservice Examinations ML1017404372010-06-21021 June 2010 Inservice Inspection Report ML0916702682009-06-12012 June 2009 2009 Owner'S Activity Report for RFO-17 Inservice Examinations ML0900200972008-12-29029 December 2008 Submittal of Fourth Ten-Year Interval Inservice Inspection Program Plan and Request for Approval of Alternatives (Relief Requests) to American Society of Mechanical Engineers Code, Section XI ML0816503462008-06-11011 June 2008 Inservice Inspection Report ML0719701942007-07-0202 July 2007 Fourth Ten-Year Inservice Test Program for Safety-Related Pumps and Valves ML0719804932007-07-0202 July 2007 Attachment 2, Pump and Value Inservice Test Program for Calvert Cliffs Nuclear Power Plant Unit 2 Fourth Ten Year Interval ML0719901302007-07-0202 July 2007 Attachment (3), Pump and Value Inservice Test Program Relief Requests for Calvert Cliffs Nuclear Power Plant Units 1 and 2 - Fourth Ten Year Interval ML0718300692007-06-27027 June 2007 Inservice Inspection Report ML0717201712007-06-20020 June 2007 Notification of Extension of the Inservice Test Program Third Ten-Year Interval ML0619800682006-07-10010 July 2006 Inservice Inspection Report ML0517200442005-06-14014 June 2005 Inservice Inspection Report for Calvert Cliffs Nuclear Power Plant Unit 2 ML0506107142005-02-25025 February 2005 2004 Steam Generator Tube Inspection Results Report ML0423304862004-08-0404 August 2004 Inservice Inspection Report ML0320300182003-07-18018 July 2003 Inservice Inspection Report ML0231900892002-11-12012 November 2002 Third Interval Inservice Inspection Program Relief Request No. RR-RI-ISI-2; Risk Informed Inservice Inspection (ISI) Program ML0226302882002-09-17017 September 2002 Inservice Inspection Report ML0215503412002-05-29029 May 2002 Third Interval Inservice Inspection Program Relief, Risk-Informed Inservice Inspection (ISI) Program ML0037360122000-07-25025 July 2000 Inservice Inspection Report 2024-07-16
[Table view] Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 IR 05000318/20240072024-11-0606 November 2024 Assessment Follow-Up Letter for Calvert Cliffs Nuclear Power Plant, Unit 2 (Report 05000318/2024007) ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000317/20240032024-10-22022 October 2024 Integrated Inspection Report 05000317/2024003, 05000318/2024003, and Independent Spent Fuel Storage Installation Report 07200008/2024001 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 ML24283A0012024-10-0909 October 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000317/20245012024-10-0707 October 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000317/2024501 and 05000318/2024501 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24255A8642024-09-0606 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 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 05000317/LER-2024-002, Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus2024-04-29029 April 2024 Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus 05000318/LER-2024-001, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip2024-04-24024 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 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 05000318/LER-2023-004-01, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-04-12012 April 2024 Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 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)) 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 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 2024-09-06
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Larry D. Smith Manager-Regulatory Assurance Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5219 Office www.exeloncorp.com larry.smith2@exeloncorp.com June 13, 2019 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit No. 1 Renewed Facility Operating License No. DPR-69 NRC Docket No. 50-318
Subject:
lnservice Inspection Report
Reference:
- 1. American Society of Mechanical Engineers, Boiler & Pressure Vessel Code,Section XI, Article IWA-6000 Pursuant to Reference 1, please find enclosed the lnservice Inspection Report for the Calvert Cliffs Nuclear Power Plant Unit 2.
There are no regulatory commitments contained in this letter.
Should you have questions regarding this matter, please contact Mr. Larry D. Smith at (410) 495-5219.
Respectf u Ily,
~~~
~arry rJ. Smith Manager - Regulatory Assurance LDS/KLG/lmd
Enclosure:
(1) 2019 Owner's Activity Report for 2-RF0-22 lnservice Examinations cc: (Without Enclosure)
NRC Project Manager, Calvert Cliffs NRC Resident Inspector, Calvert Cliffs NRC Regional Administrator, Region I D. A. Tancabel, MD-DNA
ENCLOSURE (1) 2019 OWNER 1S ACTIVITY REPORT FOR 2-RF0-22 INSERVICE EXAMINATIONS Calvert Cliffs Nuclear Power Plant June 13, 2019
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number CC2R23 Plant Calvert Cliffs Nuclear Power Plant Unit No. 2 Commercial Service April 1, 1977 Refueling Outage CC2R23 Date Number (if applicable)
ISi and Pressure Testing (PT) Fourth lnservice Inspection Interval -October 10, 2009 to June 30, 2019; Current Inspection Interval Containment lnservice Inspection Interval - September 9, 2009 to June 30, 2019 (1, 2nd, 3rd, 4th, other)
ISi and Pressure Testing Third lnservice Inspection Period - October 10, 2016 to June 30, 2019; Containment (GISI)
Current Inspection Period Third lnservice Inspection Period September 9, 2016 to June 30, 2019 (1", 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plans 2004 Edition, No addenda ISi- Rev. 00200 Dated August 19, 2015 and Rev. 00300 Dated January 28, 2019; PT - Rev. 00200 Dated Date I Revision of Inspection Plans October 23, 2014 and Rev. 00300 Dated January 28, 2019; GISI - Rev. 00100 Dated February 6, 2014 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-460, N-504-4, N-513-3, N-513-4, N-526, N-532-4, N-552, N-552-1, N-561-2, N-562-2, N-566-2, N-586-1, N-593, N-593-2, N-613-1, N-616, N-619, N-624, N-638-6, N-639, N-641, N-643-2, N-648-1, N-653-1, N-664, N-686-1, N-705, N-716, N-722-1, N-729-1, N-729-4, N-739, N-731, N-733, N-747, N-751, N-753, N-762, N-770-1, N-770-2, N-773, N-786, N-786-1, N-789, N-798, N-800, N-805, N-823, N-825, N-845 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests, meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of CC2R23 conform to the requirements of Section XI (refueling outage number)
- - - - - ~ - - Signec1-zemenu*DemeKe=-*/~~~--~ ~ - ~ - - - - Date -GT\,;}fa,-~-~ .
Manager, CCNPP Nuclear Engineering Programs ~
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Maryland The Hartford Steam Boiler of Hartford, Connecticut and employed by Inspection and Insurance Co.
have inspected the items described in this Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI By signing this certificate neither the Inspector nor his employer makes any warranty expressed or implied concerning the repair/
replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection
~ CJ " Comm;ss;oas NB 15304ANI, MD 1'!2B National Board, State, Province, and Endorsements
'spector's Signature)
Date b/JsJ/'\
FORM OAR-1 OWNER'S ACTIVITY REPORT Table 1 Items with Flaws or Relevant Condition that Require Evaluation for Continued Service
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Evaluated through-wall leaks and thinned areas in accordance with Salt Water Cooling Piping Code Case N-513-4 (reference Operability Evaluation 18-001 (issue 0-A, 02.10 reports 04138657 and 04139053)).
Chemical and Volume Boric acid deposits on and adjacent to the valve bolting were evaluated Control Valve 2-CV-517 8-P, 815.10 as acceptable per Code Case N-566-2 (reference ECP-19-000120).
Bolting Boric acid deposits at penetrations 72 and 73 were evaluated to be acceptable as required by Code Case N-729-4, -3142 (reference issue report 04224776). The source of the deposits was determined to be a Reactor Vessel Closure Code Case misaligned flange at valve 2HVRC-104 that leaked prior to restart from Head 2SYS064 N-729-4, 84.30 the 2017 refueling outage based on radiochemistry analysis and boric acid deposit observations. There was no wastage or ferritic steel wall reduction observed.
Boric Acid was identified on the 21 B RCP Studs, Nuts, and Seal Bolting.
Reactor Coolant Pump Evaluation ECP-19-000297, performed per Code Case N-566-2, RCP-21 B Main Flange concluded that the BACC deposits identified on the 21 B RCP Studs, 8-P, 815.10 Studs and Nuts and Seal Nuts, and Seal Bolting do not present any plant equipment operability Housing Bolts issues and no corrosion or degradation was identified to warrant further investigation.
Reactor Vessel (RV)120-degree Core Stabilizing Lug Shim Lockpin was discovered protruding and bent from its installed location. Approximately Core Support Barrel 9/16" of the length of the pin is hollowed and has broken off. ECP B-N-3, 813.70 Snubbers 000129 conclu.9~cj_ tb.?t the snubb.eLlugwilLbe_ableJo_per:form-its--. - -*
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intended safety function in the event of shim bolt/shim pin failures.
The 180-degree Core Support barrel (CSB) Alignment Key and key retaining pin was discovered to be slightly backed out. The result of this condition is that this one alignment key is no longer tight against the Upper Guide Structure keyway face in the CSB flange. ECP-19-000134 concluded that the gap Support Plate - (Top) & of the Core Barrel Alignment Keys in the Core Support Barrel Flange is B-N-3, 813.70 Keyways acceptable and that with the reactor internals assembled, there will be no potential for the key or retaining key pin to come loose.
FORM OAR-1 OWNER'S ACTIVITY REPORT Table 2 Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service
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Performed full structural weld overlay Cold Leg Charging Inlet repair. Reference February 11, 2019 Dissimilar Metal Weld Letter from Exelon Generation 03/14/2019 2019-2-009 2-CV-2005-30 (Accession Number ML 19072AA096}
for Additional Information).
Removed dye penetrant indications by Shutdown Cooling Heat grinding. No welding was required and 2 Exchanger 21 SDCHX 03/01/2019 2019-2-008 the indications were determined to be Outlet Nozzle due to fabrication or handling damage.
Salt Water Cooling Replaced 8" nominal pipe size pipe Piping Spool Pieces 2- spool segments with stainless steel 2018-2-006 and 3 06/18/2018 MC6-2004 and 2-MC6- piping due to wall thinning and through- 2018-2-007 2018 wall leak.
Component Cooling 3 Heat Exchanger Replaced defective tubing. 03/05/2019 2018-2-063 2HXCC21 Salt Water Pump Replaced valve with spare due to 2017-2-043 and 3 Discharge Check Valve through-wall leak. Repaired/rebuilt 05/23/2018 2017-2-046 2CKVSW-103 removed valve.