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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] 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