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MONTHYEARNL-08-096, Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses2008-07-0808 July 2008 Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses Project stage: Request ML0820307962008-07-21021 July 2008 License Amendment Request for License Condition to Support Implementation of Extended In-Service Inspection Interval Project stage: Request ML0827603842008-10-0101 October 2008 Attachment 2, Marked Up Tech Spec Pages for License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel.. Project stage: Request ML0827603832008-10-0101 October 2008 Attachment 1, Evaluation of the Proposed Change to License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel.. Project stage: Request CP-200900009, Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses2009-03-0404 March 2009 Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses Project stage: Request ML0918907412009-07-0808 July 2009 Withdrawal of License Amendment Request: Reporting of Reactor Vessel Inservice Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel In-Service Inspection Interval Project stage: Withdrawal 2CAN100902, Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations2009-10-29029 October 2009 Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: Request TMI-09-142, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-022009-10-29029 October 2009 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-02 Project stage: Request RC-11-0117, Request to Use Alternatives to ASME Code Requirements in VCSNS 3rd Ten Year Inservice Inspection Interval (RR-III-07) Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval2011-08-16016 August 2011 Request to Use Alternatives to ASME Code Requirements in VCSNS 3rd Ten Year Inservice Inspection Interval (RR-III-07) Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval Project stage: Other 2CAN041303, Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations2013-04-24024 April 2013 Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: Request 2CAN111305, Unit 2, Response to Request for Additional Information Related to Relief Request ANO2-ISI-0042013-11-11011 November 2013 Unit 2, Response to Request for Additional Information Related to Relief Request ANO2-ISI-004 Project stage: Response to RAI AEP-NRC-2018-51, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-4-082018-08-0101 August 2018 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-4-08 Project stage: Request 2009-03-04
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Category:Letter
MONTHYEARML24222A6772024-08-0909 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 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 ML24114A0182024-04-18018 April 2024 Electronic Reporting of Occupational Exposure Reporting 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 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information 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 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 2024-08-09
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ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE TABLE OF CONTENTS 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 Significant Hazards Consideration 4.4 Conclusions
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
Calvert Cliffs Nuclear Power Plant, Inc.
October 1, 2008
ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE 1.0
SUMMARY
DESCRIPTION This letter requests an amendment to Renewed Operating Licenses DPR-53 and DPR-69 for Calvert Cliffs Nuclear Power Plant (Calvert Cliffs), Unit Nos. 1 and 2. The proposed change will insert into the respective operating licenses a requirement involving the reporting of specified Reactor Vessel (RV) In-Service Inspection (ISI) information and analyses as specified in Reference (1). This amendment request is a required element of a code relief request (Reference 2) to extend the RV ISI 10-year inspection interval. The code relief request is based on the analysis contained within Reference (3). The methodology in Reference (3) was evaluated by the Nuclear Regulatory Commission (NRC), in Reference (4), as being acceptable for referencing in license amendment requests. Reference (4) requires that licensees desiring to extend the frequency of the RV ISI interval, which do not implement 10 CFR 50.61a, must amend their licenses to require the submittal of information and analyses requested in paragraph (e) of the final 10 CFR 50.61a [or the proposed 10 CFR 50.61a, as listed in Reference (1) prior to the issuance of the final 10 CFR 50.61a]. Currently, Calvert Cliffs has not implemented 10 CFR 50.61a because the final rule has not yet been approved. Therefore, in accordance with Reference (4), we are requesting to amend our licenses as described below.
Acceptance of this amendment request would allow the RV ISI interval to be extended such that Unit 1's third interval ISI would be completed during the 2018 refueling outage and its fourth interval inspection would be completed during the 2038 refueling outage. Likewise Unit 2's third interval ISI interval would be completed during the 2019 refueling outage and its fourth interval inspection would be completed during its 2039 refueling outage. This is consistent with the proposed inspection schedule in Reference (5).
2.0 DETAILED DESCRIPTION Calvert Cliffs proposed change will add, as item (6) to Section 2.C of Unit 1's license and item (8) to Section 2.C of Unit 2's license the following requirement:
Reactor Vessel In-Service Inspection Interval Extension As part of Calvert Cliffs Nuclear Power Plants relief request to extend the reactor vessel In-Service Inspection interval (if approved), Calvert Cliffs shall submit to the NRC the information and analyses specified in paragraph (e) of the proposed 10 CFR 50.61a, given in 72 FR 56275 following completion of each American Society of Mechanical Engineers (ASME) Code,Section XI, Category B-A and B-D reactor vessel weld inspection. The information and analyses shall be submitted within one year of the completion of each inspection. Once the final 10 CFR 50.61a is effective, the required information and analyses specified in paragraph (e) of the final 10 CFR 50.61a shall be the information submitted to the NRC.
This proposed change implements the requirement to submit a license amendment request at the time of submitting a relief request as specified in Reference (4).
3.0 TECHNICAL EVALUATION
The proposed change is administrative in nature because it adds a reporting requirement to the operating licenses. The justification for the information requested, and the scope and frequency of the ISI examinations is given in Reference (2). This proposed amendment only addresses the reporting of results following the described ISI examination.
Submittal of the data required by 10 CFR 50.61a is necessary to demonstrate the RV maintains its ability to meet code fracture toughness requirements and is used to justify continued use of the approved code relief request for an extended RV ISI interval. Since the proposed change involves only a requirement for 1
ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE the submittal of information, it clearly does not have any impact on the operation of the plant or any design basis accident, and is not related to a margin of safety.
The relief request to extend the RV ISI interval is separate from this license change and is reviewed separately.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria This amendment request is a required part of a code relief request submitted to extend Calvert Cliffs RV ISI 10-year inspection interval. Reference (4) provides the requirements a station must meet in order for the NRC to approve such an alternative to Section XI of the ASME code. This amendment request meets the requirement, listed in Section 3.4 of Reference (4), that the licensee will submit identified information and analyses to the NRC.
The proposed change, to report results from RV examinations required by Section XI of the ASME code, is being submitted in support of demonstrating Calvert Cliffs ability to justify extending its RV ISI interval frequency.
4.2 Precedent While there is no existing approved precedent for this proposed change, Indian Point Units 2 and 3 and Palisades Nuclear Plant, have recently submitted license amendment requests for this proposed change that are similar in content and approach. Submittal of this proposed change is consistent with the requirements stated in Reference (4).
4.3 Significant Hazards Consideration Calvert Cliffs is submitting a code relief request from American Society of Mechanical Engineers (ASME) code,Section XI that will allow Calvert Cliffs to extend the frequency of the reactor vessel In-Service Inspection (ISI) beyond the required 10-year interval. The code relief request is based on the analysis of Topical Report WCAP-16168-NP, Revision 2 which was found to be an acceptable approach by a Nuclear Regulatory Commission (NRC) Safety Evaluation. The Safety Evaluation required that utilities not implementing 10 CFR 50.61a (Calvert Cliffs is not implementing 10 CFR 50.61a at this time) must submit a license amendment request that requires the submittal of information and analyses specified in Section (e) of 10 CFR 50.61(a) (or the proposed 10 CFR 50.61a, given in 72 FR 56275, for the time period prior to the issuance of the final 10 CFR 50.61a). This proposed change adds a statement in Calvert Cliffs licenses to provide the required information and analyses.
Calvert Cliffs has evaluated whether or not a significant hazards consideration is involved with the proposed change by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment" as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change, which adds a requirement within Calvert Cliffs licenses to provide required information and analyses as a supporting condition for extending the allowed reactor vessel ISI interval, only involves the commitment to provide data obtained from the reactor vessel ISI. This proposed change involves only the submittal of generated data that will be used to verify the reactor vessel has more than sufficient margin to prevent any pressurized thermal shock event from occurring. This proposed change does not involve any change to the design basis of the plant or of 2
ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE any structure, system, or component. Therefore, the proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change, which adds a requirement within Calvert Cliffs licenses to provide required information and analyses as a supporting condition for extending the reactor vessel ISI interval, only involves the commitment to provide data and analyses obtained from the reactor vessel ISI. As such this proposed change does not result in physical alteration to the plant configuration or make any change to plant operation. As a result no new accident scenarios, failure mechanisms, or single-failures are introduced. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
The proposed change, which adds a requirement within Calvert Cliffs licenses, to provide required information and analyses as a supporting condition for extending the allowed reactor vessel ISI interval, only involves the commitment to provide data and analyses obtained from the reactor vessel ISI. The submitted data may be used to verify the condition of the reactor vessel meets all required standards to ensure sufficient safety margin is maintained against the occurrence of a pressurized thermal shock event during the expanded time interval between reactor vessel ISIs. The proposed change is administrative in nature and is not related to any margin to safety. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based upon the above evaluation, Calvert Cliffs has concluded that the proposed change does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified.
4.4 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
The proposed amendment is confined to (i) changes to surety, insurance and/or indemnity requirements, or (ii) changes to recordkeeping, reporting or administrative procedures, or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in conjunction with the proposed amendment.
6.0 REFERENCES
(1) Federal Register Notice (72 FR 56275), dated October 3, 2007, Alternative Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events (2) Letter from Mr. M. D. Flaherty (CCNPP) to Document Control Desk (NRC), dated October 1, 2008, Revised Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examinations - Relief Requests (ISI-020 and ISI-021) 3
ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE (3) WCAP-16168-NP, Revision 2, dated June 2008, Risk-Informed Extension of the Reactor Vessel In-Service Inspection Interval (4) Letter from H. K. Nieh (NRC) to G. Bischoff (PWROG), dated May 8, 2008, Final Safety Evaluation for Pressurized Water Reactor Owners Group (PWROG) Topical Report (TR)
WCAP-16168-NP, Revision 2, Risk-Informed Extension of the Reactor Vessel In-Service Inspection Interval (TAC No. MC9768)
(5) PWR Owners Group letter OG-06-356, "Plan for Plant Specific Implementation of Extended Inservice Inspection Interval per WCAP 16168-NP, Revision 1," Risk Informed Extension of the Reactor Vessel In-Service Inspection Interval" MUHP 5097-99, Task 2059," dated October 31, 2006 4