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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) 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) ML24240A2462024-08-27027 August 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML24240A1112024-08-27027 August 2024 Registration of Use of Casks to Store Spent Fuel 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 ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 ML24040A0962024-02-0909 February 2024 Notification of Readiness for NRC 95001 Inspection 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 IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 2024-09-06
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARML19045A2422019-02-13013 February 2019 Reactor Vessel Level Monitoring System Special Report ML14114A5462014-04-23023 April 2014 CFR 50.46 30-day Report for Changes to the Emergency Core Cooling System Performance Analysis ML14080A3072014-03-20020 March 2014 10 CFR 50.46 30-day Report and Annual Report for Changes to the Emergency Core Cooling System Performance Analysis ML13115A2792013-04-22022 April 2013 10 CFR 50.46 30-day Report and Annual Report for Changes to the Emergency Core Cooling System Performance Analysis ML1212203062012-04-30030 April 2012 CFR 50.46 30-day Report and Annual Report for Changes to the Emergency Core Cooling System Performance Analysis ML12094A1002012-03-29029 March 2012 Submittal of Containment Water Level Indication Special Report ML12024A3912012-01-19019 January 2012 CFR 50.46 30-day Report for Changes to the Emergency Core Cooling System Performance Analysis ML1006105262010-02-22022 February 2010 LER Calvert Cliffs, Special Report: Noncompliance with Effluent Limitations ML0818206982008-06-30030 June 2008 Containment Tendon Surveillance - 30 Day Report ML0510200112005-04-0606 April 2005 10 CFR 50.46 30-Day Report for Changes to the Plant Emergency Core Cooling System Performance Analysis ML0424501002004-08-25025 August 2004 Units I & 2 - Special Report: National Pollutant Discharge Elimination System Discharge Permit 02-DP-01 87 2019-02-13
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Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 0 :*
- nstellation En rgy Nuclear Generation Group June 30, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. I; Docket No. 50-317 Containment Tendon Surveillance Day Report In accordance with Technical Specification 5.6.8, Calvert Cliffs Nuclear Power Plant (CCNPP) is submitting a report of abnormal degradation of the containment structure detected during performance of the periodic tendon surveillance. This report is required within 30 days of discovery of the degradation .
The tendon surveillance for Unit 1 post-tensioning containment structure, required by Technical Specification 5.5.6, is currently ongoing. This report documents abnormal degradations detected to date during performance of the tendon surveillance. The first reportable abnormal degradation of the surveillance was detected on May 30, 2008.
BACKGROUND The CCNPP post-tensioning system consists of:
I. Three groups of 68 dome tendons oriented at 60 degrees to each other for a total of 204 tendons anchored at the vertica l face of the dome ring girder.
- 2. Two-hundred-four vertical tendons anchored at the top surface of the ring girder and at the bottom of the base slab.
- 3. Six groups of 78 hoop tendons, each enclosing 120 degrees of arc, for a total of 468 hoop tendons anchored at the 6 vertical buttresses.
Each tendon consists of 90 high-strength steel wires 1/4-inch in diameter with stressing washers and buttonheads on each end of the wires.
INSPECTION PROCEDURE In accordance with Technical Specification 5.5.6 the tendon surveillance program for the containment post-tensioning system consists of the following :
- a. Determining that for a representative sample of at least nine tendons (three dome, three vertical, and three hoop), each tendon has a normalized lift-off force equaling or exceeding its lower limit expected range for the time of the test. If the normalized lift-off force of anyone tendon in a
Document Control Desk June 30, 2008 Page 2 group lies between the lower limit expected range and the lower bound individual, an adjacent tendon on each side shall be checked for lift-off force . If both of these tendons are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable. If either of the adjacent tendons is found unacceptable, it shall be considered as evidence of possible abnormal degradation of the containment structure . In addition, more than one unacceptable tendon out of those selected for surveillance (from all three tendon groups) shall be considered as evidence of possible abnormal degradation of the containment structure.
If the normalized lift-off force of any single tendon lies below the lower bound individual, the occurrence should be considered as evidence of possible abnormal degradation of the containment structure.
In addition, determining that the average of the normalized lift-off forces for each sample population (hoop, vertical, dome) is equal to or greater than the required average prestress level; 536 kips for hoop tendons , 622 kips for vertical tendons, and 555 kips for dome tendons. If the average is below the required average prestress force, it shall be considered as evidence of possible abnormal degradation of the containment structure.
- b. Removing one wire from each of a dome, vertical, and hoop tendon checked for lift-off force, and determining over the entire length of the wire:
I. The extent of corrosion , cracks, or other damage. The presence of abnormal corrosion, cracks, or other damage shall be considered evidence of possib le abnormal degradation of the contain ment structure .
- 2. A minimum tensile strength value of 240 ksi (guaranteed ultimate strength of the tendon material) for at least three wire samples (one from each end and one at mid-length) cut from each removed wire. Failure of anyone of the wire samples to meet the minimum tensile strength test is evidence of possible abnormal degradation of the containment structure.
- c. Perform a chemical analysis to detect changes in the chemical properties of the sheath filler grease. Report any unusual changes in physical appearance or chemical properties that could adversely affect the ability of the filler grease to adhere to the tendon wires or otherwise inhibit corrosion .
- d. The structural integrity of the end anchorages and adjacent concrete surfaces is demonstrated by determining through inspection of a representative sample of tendons that no apparent changes have occurred in the visual appearance of the end anchorages or their adjacent concrete exterior surfaces.
REPORTABLE ABNORMAL DEGRADATIONS During the performance of the tendon surveillance, conditions which may represent abnorma l degradation of the containment structure were found for two hoop tendons . These tendons were found to have lift-offforces lower than the lower limit expected lift-off range at the time of the test .
Hoop Tendon 24H67 exhibited a lift-off force of 590.24 kips as opposed to its lower limit expected value of 605.1 kips. Adjacent tendons 24H66 and 24H68 were tested and were also found to be below the acceptable lift-off measurements of 605.1 kips. Adjacent tendon testing continued and acceptable lift-off values were found on tendons 24H63 and 24H69. After 24H63 and 241-169 were found acceptable, all
Document Control Desk June 30, 2008 Page 3 intermediate tendons were re-tensioned to acceptable values above the predicted (100%) value at the time of the test.
Additionally, hoop tendon 24H30 also exhibited a lift-off force of 560.29 kips as opposed to the lower limit expected value of 605 .1 kips. Adjacent tendon 24H29 was tested and found acceptable. Due to interference, hoop tendon 24H31 was visually inspected and tendons 24H32 and 24H33 were inaccessible. Tendon 24H34 was tested and found to be below 605.1 kips as was 24H35. Tendon 24H36 was found to be above 605 .1 kips (actually 678 .9 kips) and acceptable. After acceptable adjacent lift-offs were found, all accessible intermediate tendons were re-tensioned to acceptable values above the predicted (100%) value at the time of the test.
No signs of abnormal degradation of the end anchorage or adjacent concrete surface of the Containment have been found in any of these areas. No water was found, nor broken/missing wires that had not been previously noted.
CORRECTIVE ACTIONS All corrective actions have been completed by restoring lift-off forces to a level above the predicted value at the time of the test. Acceptable lift-off force levels have been found in tendons beyond the low-force tendons and these instances arc considered isolated. Despite the lift-off force levels being lower than expected they have all been above the design basis accident load for each tendon, therefore, the Containment remains Operable.
Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.
Very truly yours, f-~ Z~ "}Qo.k~
Mark D. Flaherty Manager - Engineering Services MDF/PSF/bjd cc: D. V. Pickett, NRC Resident Inspector, NRC S. J. Collins, NRC S. Gray, DNR