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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 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 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 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
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Office 410-470-613,3 f ý; Chief E(2'ct iv Offier Fax 44~3-213-6739
..nWia: Marja.Korsnick@cengj~c~com CENG..
a joint venture of Aft onaeltaion 4 OE.tkr -eDF March 7, 2014 U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant, Units I and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 Docket Nos. 50-317 and 50-318 Additional Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.1, Flooding - Flood Hazard Reevaluation
REFERENCES:
(a) Email from M. Thadani (NRC) to E. Tyler (CENG), "Calvert Cliffs R2.1 flooding reevaluations: RAIs," dated January 9, 2014 (ML14010A015)
(b) Letter from J. A. Spina (CENG) to Document Control Desk (NRC), Calvert Cliffs Nuclear Power Plant, Units I and 2, Flood Hazard Reevaluation Report, dated March 12, 2013 (ML13078A010)
(c) Letter from M. G. Korsnick (CENG) to Document Control Desk (NRC),
Calvert Cliffs Nuclear Power Plant, Units I and 2, Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.1, Flooding - Flood Hazard Reevaluation, dated February 10, 2014 On January 9, 2014 (Reference a), the Nuclear Regulatory Commission (NRC) issued a Request for Additional Information (RAI) to Constellation Energy Nuclear Group, LLC (CENG) regarding the Calvert Cliffs Nuclear Power Plant, LLC (CCNPP) Flood Hazard Reevaluation Report submitted on March 12, 2013 (Reference b). Reference (c) provided partial responses to Reference (a) and an explanation for the delay in submitting the CENG response to the NRC's RAI 3. The response to RAI 3 has now been prepared and is provided in Attachment (1).
This letter contains no new regulatory commitments.
If there are any questions regarding this submittal, please contact Bruce Montgomery, Manager-Nuclear Safety and Security, at 443-532-6533.
Constellation Energy Nuclear Group, LLC 100 Constellation Way, Suite 200C, Baltimore, MD 21202 AD0o
Document Control Desk March 7, 2014 Page 2 1declare under penalty of perjury that the foregoing is true and correct. Executed on March 7, 2014.
Sincerely, or snický MGK/GGM/EMT
Attachment:
(1) Calvert Cliffs Nuclear Power Plant Response to Request for Additional Information (RA! 3) cc: NRC Project Manager, Calvert Cliffs Resident Inspector, Calvert Cliffs NRC Project Manager, Ginna Resident Inspector, Ginna NRC Project Manager, Nine Mile Point Resident Inspector, Nine Mile Point Regional Administrator, NRC Regioný I S. Gray, DNR
ATTACHMENT (1)
CALVERT CLIFFS NUCLEAR POWER PLANT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI 3)
Constellation Energy Nuclear Group, LLC March 7, 2014
ATTACHMENT (1)
CALVERT CLIFFS NUCLEAR POWER PLANT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI 3)
NRC RAI 3 - Local Intense Precipitation Flooding The licensee is requested to provide a description of the methods used to incorporate elevation measurements in the flood analysis and the likely magnitude of the errors associated with these elevations. Elevation measurement and conversion is crucial in defining flow parameters such as slope and flowpaths. Staff are also requesting a discussion of the methods used to incorporate elevation measurements in the flood analyses performed using HEC-RAS and HEC-HMS.
CCNPP Response Ground elevations within the Calvert Cliffs Nuclear Power Plant (CCNPP) property boundary were obtained from an aerial photogrammetric survey conducted in 2007. The survey specification requires that at least 90 percent of all elevations on the I-foot contours are accurate within one-half the contour interval (0.5 foot), and the remaining 10 percent are accurate within one contour interval (1.0 foot). For spot elevations, the specification requires that at least 90 percent of the elevations shown on the maps are accurate within one-fourth of the contour interval (0.25 foot), and the remaining 10 percent are accurate within one-half of the contour interval (0.5 foot). The local intense precipitation flood evaluation in the Flooding Hazard Reevaluation Report (FHRR) used ground elevation data only within the CCNPP property boundary as the contributing sub-basins and schematized flow channels are entirely located within the property. The topographic data, as obtained from the aerial survey, were used to develop the HEC-RAS cross-sections as shown in Figures 2. 1-7a, 2.1-7b, and 2.1-8 of the FHRR. The cross-sections include the effects of structures that are blocking flows in the overbanks and were represented in HEC-RAS as an obstruction. Also, the cross-section areas where there is no flow conveyance were modeled as ineffective flow areas in HEC-RAS.
In addition to using the recent surveyed ground elevation data to develop the local intense precipitation flood model, the HEC-HMS and HEC-RAS models incorporated highly conservative assumptions, including conservative Manning's roughness coefficients and reduced time of concentration values. In addition, the entire site was considered impervious and modeled with a curve number of 98, and all storm drains were considered to be non-operational.
The combined effect of these conservative assumptions is expected to adequately compensate for any small uncertainty in the ground elevation measurements. Therefore, the estimated flood levels can be considered as the maximum possible flood levels due to the local intense precipitation over the site.
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