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MONTHYEARML14050A3742014-02-13013 February 2014 License Amendment Request Re Pressurizer Safety Valve Technical Specification Revision Project stage: Request ML14168A0002014-06-16016 June 2014 NRR E-mail Capture - Acceptance Review Results Regarding Calvert Cliffs 1 & 2 - As-found Lift Tolerance Modification in the Pressurizer Safety Valve Surveillance Requirement Amd Project stage: Acceptance Review ML15112A3742015-05-0606 May 2015 Request for Additional Information Regarding the As-Found Lift Tolerances for the Pressurizer Safety Valves License Amendment Request (Tac Nos. MF3541 and MF3542) Project stage: RAI ML15083A0182015-05-26026 May 2015 Regulatory Audit Regarding the Pressurizer Safety Valves License Amendment Request (Tac No. MF3541) Project stage: Other ML15177A1152015-06-22022 June 2015 Request for Additional Information Regarding the As-found Lift Tolerances for the Pressurizer Safety Valves License Amendment Request Project stage: Request ML15187A0092015-08-11011 August 2015 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML15279A1912015-12-30030 December 2015 Issuance of Amendment Revision to Pressurizer Safety Valve Technical Specifications Project stage: Approval 2015-05-26
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Category:Audit Plan
MONTHYEARML22214A0042022-08-0202 August 2022 Audit Plan to Support the Review of Amendments to Revise Criticality Safety Analysis Methodologies (Epids L-2022-LLA-0085, L-2021-LLA-0124, and L-2021-LLA-0159) ML21200A0742021-07-20020 July 2021 Audit Plan in Support of Review of License Amendment Request Regarding Change Spent Fuel Pool Cooling Design Basis ML20174A0592020-06-30030 June 2020 Regulatory Audit Summary Regarding License Amendment Request for Revision to Technical Specification Surveillance Requirements Relating to Emergency Diesel Generator ML20098G9652020-05-18018 May 2020 Audit Plan in Support of Review of License Amendment Request Regarding Accident Tolerant Fuel Lead Test Assemblies ML20052E9852020-02-28028 February 2020 Audit Plan in Support of Review of License Amendment Request to Revise Technical Specification Surveillance Requirements Relating to Emergency Diesel Generator ML19065A0442019-03-20020 March 2019 Audit Plan in Support of Review of License Amendment Request to Allow Use of Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML18345A1942018-12-21021 December 2018 Plants, Units 1 and 2 - Regulatory Audit Risk-Informed Approach to License Amendment Request for Closure of Generic Safety Issue-191 ML18143A3102018-05-24024 May 2018 Plants, Units 1 and 2 - Audit Plan in Support of the Review of the License Amendment Request to Allow the Use of Risk-Informed Completion Times (CAC Nos. MF7415 and MF7416; EPID L-2016-LLA-001) ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16249A0032016-09-15015 September 2016 Regulatory Audit Plan for September 19-21, 2016, Audit at Kennett Square, PA in Support of the License Amendment Request to Implement Risk-Informed TS Initiative 4B ML15083A0182015-05-26026 May 2015 Regulatory Audit Regarding the Pressurizer Safety Valves License Amendment Request (Tac No. MF3541) ML14356A0032015-02-10010 February 2015 Audit of Licensee Responses to the Expedited Seismic Evaluation Process to Support Implementation of Near-Term Task Force Recommendation 2.1, Seismic ML14336A2562014-12-0404 December 2014 Regulatory Audit Plan Regarding the National Fire Protection Association Standard 805 Transition License Amendment Request (Tac Nos. MF2993 and MF2994) ML14210A4492014-08-0505 August 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 2022-08-02
[Table view] 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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 26, 2015 Mr. George H. Gellrich Site Vice President Exelon Generation Company, LLC Calvert Cliffs Nuclear Power Plant, LLC 1650 Calvert Cliffs Parkway Lusby, MD 20657
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -
REGULATORY AUDIT REGARDING THE PRESSURIZER SAFETY VALVES LICENSE AMENDMENT REQUEST (TAC NO. MF3541)
Dear Mr. Gellrich:
By letter dated February 13, 2014, Calvert Cliffs Nuclear Power Plant, LLC, submitted a license amendment request to revise Technical Specification 3.4.10, "Pressurizer Safety Valves," for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (Calvert Cliffs). The proposed amendment increases the as-found lift tolerances in the Surveillance Requirement for the pressurizer safety valves and decreases the nominal set pressure for valve RC-201.
The U.S. Nuclear Regulatory Commission (NRC) staff is currently reviewing the submission and has determined that additional information is needed to support its review. Therefore, the NRC staff has conducted a regulatory audit with the intent to gain understanding, to verify information, and/or to identify information that will require docketing to support the basis of the licensing or regulatory decision.
The regulatory audit was conducted in accordance with the Office of Nuclear Reactor Regulation Instruction LIC-11.1 at Calvert Cliffs from March 25 - 26, 2015. The regulatory audit plan is enclosed.
G. Gellrich If you have any questions regarding this matter, please contact me at (301) 415-2549.
Sincerely,
~ ,,,_-
Alexander N. Chereskin, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
As stated cc w/encl: Distribution via Listserv
REGULATORY AUDIT PLAN REGARDING PRESSURIZER SAFETY VALVES LICENSE AMENDMENT REQUEST CALVERT CLIFFS NUCLEAR POWER PLANT, LLC.
EXELON GENERATION COMPANY, LLC CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1AND2 DOCKET NOS. 50-317 AND 50-318
1.0 BACKGROUND
By letter dated February 13, 2014 (Agencywide Documents Access and Management System (ADAMS) ML14050A374), Calvert Cliffs Nuclear Power Plant, LLC (the licensee), submitted a license amendment request to revise Technical Specification 3.4.10, "Pressurizer Safety Valves," for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (Calvert Cliffs). The proposed amendment increases the as-found lift tolerances in the Surveillance Requirement for the pressurizer safety valves (PSVs) and decreases the nominal set pressure for valve RC-201.
2.0 REGULATORY AUDIT SCOPE The U.S. Nuclear Regulatory Commission (NRC) staff focused on the following areas during this audit:
- Operating experience. Discuss the events related to PSV setpoints outside the allowable range. In particular, review the root cause evaluation for Licensee Event Report (LER) 317/2014-003, which involved a specific lot of "inadequate lift spring assemblies." Also review the root cause evaluation for related LERs referenced in 317/2014-003, which involved normal drift, excessive drift, and inadequate margin.
- Determination of an adequate margin for PSV operability. Discuss the determination that the surveillance requirement is "unnecessarily restrictive." Discuss the implications of "inoperable" PSVs on performance measures. Review the decision process that led to a determination that different off-set as-found PSV relief pressure for the two PSVs.
- Feedback from the PSV manufacturer, Dresser. Since the PSVs are set by Dresser, discuss the procedures for transporting and handling the PSVs, as well as the quality control procedures when the valves are returned. In particular, discuss Dresser's recommendations related to an appropriate tolerance for PSV operability.
Enclosure
- Feedback from other plants and industry groups. Discuss whether operating experience from other plants and/or industry groups contributed to the changes in tolerance and nominal pressure setpoints.
- Design basis accidents and transients. Discuss the events listed on Table 4-1 in the attachments to the proposed amendment. Discuss whether there are any differences in the input conditions or user-specified fuel thermal properties for the events determined to be bounded by the analysis of record (AOR) or bounded by one of the four reanalyzed events.
- Review details of the four reanalyzed events: loss of electrical load, loss of feedwater flow, feed line break, and control element assembly ejection accident. Discuss how the initial conditions and user-specified fuel thermal properties for the reanalyzed events compare to the AOR.
- Discuss the status of the Core Operating Limits Report, the "ongoing discussions" between AREVA and the NRC staff, and the potential for any changes to the analysis methods that could impact the PSV setpoints and tolerances.
- The proposed amendment notes that Appendix C to the license includes the following restriction regarding the use of the S-RELAP5 analysis methods, and requests NRC approval of the methodology used in support of the requested amendment:
Approval of the use of S-RELAP5 (Technical Specification 5.6.5.b.8) is restricted only to those safety analyses that confirm acceptable transient performance relative to the specified acceptable fuel design limits. Prior transient specific NRC approval is required to analyze transient performance relative to reactor coolant pressure boundary integrity until NRC approval is obtained for a generic or Calvert Cliffs-specific basis for the use of the methodology in Technical Specification 5.6.5.b.8 to demonstrate reactor coolant pressure boundary integrity.
Discuss the extent of the NRC approval being requested by the proposed amendment.
- Review the decision to reduce the nominal setpoint for RC-200 (referred to as 1RV200 or 2RV200 in the LERs) from 2565 pounds per squaure inch atmospheric (psia) to 2525 psia. Discuss the pros and cons of the nominal setpoint reduction, and how the operating experience and/or event reanalysis results contributed to the decision to reduce the nominal setpoint.
- Discuss how the following limitation placed on applications of S-RELAP5 in the safety evaluation for EMF-2310(P)(A), Rev. 1, is addressed for the Calvert Cliffs analyses of the four events:
As is the case in reviewing all generic topical report applications, submittals for specific plants and events must include justification of the nodalization used, input parameters, options selected, and all of the parameters that influence the progression of the event and its mitigation.
- Discuss how the licensee has exercised its responsibility to ensure that AREVA adheres to the conditions in the safety evaluations and the limitations stated in the Topical Reports for the codes and methodologies used in analyses of the four events, and that the methodologies are applicable to the Calvert Cliffs design basis.
3.0 TEAM ASSIGNMENTS Nadiyah Morgan, NRC - Project Manager Fred M. Forsaty, NRC - Lead Reviewer Dan Prelewicz - Information Systems Laboratories, Inc. (ISL, NRC contractor)
Diane Mlynarczyk - ISL 4.0 LOGISTICS Regulatory Audit Dates: March 25 - 26, 2015 Location: Calvert Cliffs 5.0 DELIVERABLES A summary of the regulatory audit will be provided within 30 days of completing the audit.
ML15083A018 *See dated memo OFFICE DORL/LPLl-1 /PM DORL/LPLl-1 /LA DSS/SRXB/BC DORL/LPLl-1 /BC(A)
NAME AChereskin KGoldstein CJackson* MDudek DATE 5/26/2015 3/26/2015 3/18/2015 5/26/2015