|
---|
Category:Letter
MONTHYEARIR 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 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 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 ML24107B0992024-04-12012 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)) 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 2024-09-06
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding ML22320A0432022-11-15015 November 2022 Response to NRC Inspection Report and Preliminary White Finding ML0633503532006-11-27027 November 2006 Reply to a Notice of Violation, Inspection Report 05000317-06-012, 05000318-06-012 ML0534101222005-12-0101 December 2005 Independent Spent Fuel Storage Installation, Reply to a Notice of Violation - NRC Inspection Report No. 072-00008/2005-001 ML0415503052004-05-27027 May 2004 Reply to Non-Cited Violation 2004002-03 - NRC Integrated Inspection Report 50-317(318)/2004002 ML0228904922002-10-0909 October 2002 Calver Cliffs Units 1 & 2 Response to a Notice of Violation - NRC IR 05000317-02-010; 05000318-02-010 ML0226301232002-09-17017 September 2002 Reply to Notice of Violation - NRC Inspection Report 50-317/02-04; 50-318/02-04 2023-10-06
[Table view] |
Text
James A. Spina Calvert Cliffs Nuclear Power Plant, Inc.
Vice President 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.4455 410.495.3500 Fax (Donstellation Energy" Generation Group November 27, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Reply to a Notice of Violation; EA-06-198 - NRC Inspection Report Nos.
50-317/06-012: 50-318/06-012
REFERENCES:
(a) Letter from Mr. B. E. Holian (NRC) to Mr. J. A. Spina (CCNPP), dated September 8, 2006, Calvert Cliffs Nuclear Power Plant - NRC Inspection Report 50-317/06-012; 50-318/06-012; Preliminary White Finding (b) Letter from Mr. S. J. Collins (NRC) to Mr. J. A. Spina (CCNPP), dated October 27, 2006, Final Significance Determination for a White Finding and Notice of Violation (NRC Inspection Report 50-317/06-012; 50-318/06-012-Calvert Cliffs Nuclear Power Plant)
This letter provides Calvert Cliffs Nuclear Power Plant's response to References (a) and (b), which identified a Notice of Violation associated with a white finding. This Notice of Violation involved a failure to establish and ensure an adequate trip setpoint for the electrical circuit breaker that supplies the IA Emergency Diesel Generator essential support loads. The response to this Notice of Violation is provided in Attachment (1).
Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-4922.
Very truly yours, K?
JAS/ALS/bjd
Attachment:
(1) Reply to a Notice c6K Violation; EA-06-198 NRC Inspection Report 50-317(318)/06-012; Violation 06-012-01 cc: P. D. Milano, NRC R. I. McLean, DNR S. J. Collins, NRC T. R. Quay, NRC Resident Inspector, NRC R. J. Conte, NRC I/I
ATTACHMENT, (1)
REPLY TO A NOTICE OF VIOLATION; EA-06-198 NRC INSPECTION REPORT 50-317(318)/06-012; VIOLATION 06-012-01 Calvert Cliffs Nuclear Power Plant, Inc.
November 27, 2006
ATTACHMENT (11 REPLY TO A NOTICE OF VIOLATION; EA-06-198 NRC INSPECTION REPORT 50-317(318)/06-012; VIOLATION 06-012-01 10 CFR Part 50, Appendix B, Criterion III, "Design Control," requires, in part, that design control measures shall providefor verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculationalmethods, or by the performance of a suitable testingprogram.
Contrary to the above, since 1996 when Calvert Cliffs modified the on-site electrical distribution design by installing a new ]A emergency diesel generator (EDG), the licensee failed to ensure that design control measuresprovidedfor verifying or checking the adequacy of the design. Specifically, calculation D-E-94-O01, dated August 26, 1994, did not accountfor all the loads that can simultaneously start after an undervoltage event when establishing the short-term over-current trip setting for [the] electrical circuit breaker [feeding] 1MCC123, the electrical supply for the EDG support systems. In addition, neither adequate design reviews, alternate calculations,nor suitable testing was done to identify that the over-currenttrip setting was incorrect.
REASON FOR THE VIOLATION As stated above, the subject violation was issued because Calvert Cliffs (CCNPP) failed to ensure that design control measures provided for verifying or checking the adequacy of the design associated with the 1996 installation of the IA EDG. The root cause investigation performed to address this issue concluded that the root cause was a lack of questioning attitude by an Appendix B supplier (vendor) in August, 1994 which was not discovered in CCNPP's Owner Acceptance process, which was also performed in August, 1994. In particular, the vendor's assumption for the protective relay setpoint did not encompass all conditions which the protective relay would experience. This permitted some design conditions to exceed the setpoint assumption and result in the breaker tripping.
A contributing cause was a lack of questioning attitude when CCNPP reviewed the vendor's calculation.
Although the vendor listed their assumption in the calculation, CCNPP's review did not question the adequacy of the assumption.
Another contributing cause was a lack of questioning attitude regarding the scope of post-modification testing. During post-modification testing, the IA EDG electrical distribution system was not tested to its highest possible currents. In particular, IA EDG load sequencing tests did not require loading all loads onto the 1A EDG. If all loads had been started, this issue would have been detected during system testing in 1996.
CORRECTIVE STEPS THAT HAVE BEEN TAKEN AND RESULTS ACHIEVED The following actions have been taken to address the cause of this violation and prevent future occurrences.
- 1. All affected plant components' (Societe Alsacienne De Constructions Mecaniques De Mulhouse
[SACM] diesel generators) short-time overcurrent trip setpoints, have been corrected.
- 2. The vendor has been notified to ensure this issue is included in their corrective action program.
CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATIONS
- 1. Training will be provided to engineers on owner acceptance review expectations regarding Vendor Design Bases/Assumption Verification.
1
i .
ATTACHMENT (11 REPLY TO A NOTICE OF VIOLATION; EA-06-198 NRC INSPECTION REPORT 50-317(318)/06-012; VIOLATION 06-012-01
- 2. Training will be provided to identify when Engineering Test Procedures are required for post-modification testing. The training will include guidance for preparation and criteria of Engineering Test Procedures.
- 3. Calvert Cliffs will evaluate the safety-related 480V bus feeder breakers and safety-related MCC feeder breakers to ensure adequate margin exists between the feeder breaker overcurrent trip setpoint and the maximum design bases inrush current.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Calvert Cliffs is currently in compliance with 10 CFR Part 50, Appendix B Criterion III, "Design Control" with regard to ensuring that design control measures provide for verifying or checking the adequacy of design. The root cause of the subject issue is considered to be a latent design error due to the lack of questioning attitude associated with the design assumption in the calculation. Although a lack of questioning attitude by a vendor resulted in an inadequate protective relay setpoint, this is considered to be a special case. The SACM MCCs are significantly different than the other plant MCCs. The SACM MCCs have a large load capability, have multiple large loads that start simultaneously, and have high efficiency motors which require additional inrush current above other plant motors. The assumption used by the vendor is valid for other situations. Therefore, the vendor did not fully comprehend the special case in the SACM MCC design. Therefore, this is not considered symptomatic of a likely potential to affect other systems, structures, components, or processes.
Corrective steps have been taken as indicated above. The corrective steps indicated above that have not been taken will be completed in a timely manner, commensurate with the safety significance of the issue.
An effectiveness review is planned to verify that the corrective steps were effective.
2