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MONTHYEARML0318805582003-07-0909 July 2003 Request for Additional Information, Technical Specification Change to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit Project stage: RAI ML0319806092003-07-25025 July 2003 Second Request for Additional Information, Technical Specification Change to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit (Tac No. MB8896) Project stage: RAI ML0327401222003-09-25025 September 2003 Response to RAI Concerning the License Amendment Request to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit Project stage: Response to RAI ML0331400752003-11-0303 November 2003 Response to Second RAI Concerning the License Amendment Request to Increase the Spent Fuel Maximum Enrichment Limit with Soluble Boron Credit Project stage: Request ML0406106792004-02-25025 February 2004 Response to Third RAI Concerning the License Amendment to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit Project stage: Other ML0406505312004-04-0202 April 2004 Environmental Assessment, Finding of No Significant Impact Related to a Proposed Amendment to Increase Maximum Enrichment of Fuel Assemblies in Spent Fuel Pool Project stage: Other ML0410401292004-06-0303 June 2004 License Amendment Re Amendment to Increase the Spent Fuel Pool Maximum Enrichment Limit Project stage: Acceptance Review ML0418202322004-06-23023 June 2004 Correction to Technical Specifications for Amendment No. 267 (TAC MB8896). Table of Contents, Page III & Page 4 of Appendix C Updated to Correct Errors Project stage: Other ML0417402582004-06-23023 June 2004 Ltr, Correction to Amendment No. 267 (TAC MB8896). Table of Contents, Page III & Page 4 of Appendix C Updated to Correct Errors Project stage: Other 2003-09-25
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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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!Z Kevin J. Nietmann 1650 Calvert Cliffs Parkway Plant General Manager Lusby, Maryland 20657 Calvert Cliffs Nuclear Power Plant 410 495-4101 Constellation Generation Group, LLC 410 495-4787 Fax Constellation Energy Group February 25, 2004 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket Nos. 50-317 Response to Third Request for Additional Information Concerning the License Amendment Request to Increase Unit I Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit
REFERENCES:
(a) Telephone Conference between Ms. D. J. Mitchell, et.al. (CCNPP) and Mr. G. S. Vissing, et.al. (NRC), on January 29, 2004, same subject (b) Letter from Mr. P. E. Katz (CCNPP) to Document Control Desk (NRC),
dated May 1, 2003, "License Amendment Request: Increase to the Unit I Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit" This letter provides the information requested in Reference (a). This information supports and/or clarifies the information provided in Reference (b). This information does not change the conclusions of the No Significant Hazards Consideration Determination or the Environmental Impact Review of Reference (b).
Attachment (1) contains the proposed words for the License Condition.
During the review of Reference (b), the Nuclear Regulatory Commission (NRC) staff determined that the current available data did not conclusively predict the maximum boron weight loss and that we would need to provide more data to accurately depict the boron loss trend. The NRC staff is concerned that, combined with this lack of data, key boron loss data may be overlooked during the longer intervals between coupon removal. During the conference call (Reference a), it was agreed to add a License Condition in Appendix C of the Technical Specifications that will require us to develop a coupon surveillance program for the Carborundum samples that wvill demonstrate the assumptions of conservative boron loss measurement. This proposed coupon surveillance program will be submitted to the NRC for the staff's approval no later than three years after the approval of our License Amendment Request to increase the Unit I Spent Fuel Pool maximum enrichment limit (Reference b). The three year period includes sufficient time to determine the modifications needed to the coupon surveillance program for the Carborundum samples to demonstrate the assumptions of a conservative boron loss measurement for 70 years. Since a possible modification to the coupon surveillance program includes using the Long-Term Surveillance Assembly (LTSA) samples as Accelerated Surveillance Assembly (ASA) samples, it is
Document Control Desk February 25, 2004 Page 2 requested that the LTSA coupon surveillance program be discontinued at this time so that sufficient coupons remain for possible extended ASA program.
We believe that a three year timeframe is acceptable for developing a surveillance program because any rack degradation over that period will not challenge the criticality calculation for the racks. Our criticality calculation provided in Reference (b) assumed a 26.25 percent boron loss. To determine if we will remain within this assumption for the next three years, we reviewed the coupon surveillance results (see table below). Based on these results we believe the projected weight loss over the three years needed to develop the revised coupon surveillance program for the Carborundum will be well with in the limit of operation. The next sample is scheduled to be withdrawn by October 2005 and the results from this sample will be used to verify the assumptions for the projected boron loss. If the results from this sample indicate that the 26.25 percent boron loss is approached, actions will be taken to ensure we remain in compliance.
Sample Packet Number Sample Type Time in Spent Fuel Weight Loss (%)
Pool 25 LTSA 4YR 4MO 1.67 26 LTSA lOYR 2MO 3.19 32 LTSA 17YR 2 MO 4.10 2 ASA 4YR 4M0 2.25 7 ASA 6YR 6MO 2.87 8+9* ASA 10YR 2MO 5.90 15 ASA 14 YR I MO 5.70
- - Sample Packet 8 consisted of four samples, IU, IL, 2U, and 2L. The percent change in weight of the four samples are 18.34, 3.85, 5.15, and 2.74. The average change in weight for the four samples is 7.52 percent; however, if IU is disregarded, the change is 3.91 percent, which is less than the Sample 9 results taken at the same time. It is believed that sample IU of Sample Packet 8 is an anomaly due to poor handling. Sample Packet 9 pulled at the same time had an average degradation of 4.28 percent. The average Sample 8 and 9 weight loss was 5.90 percent, as indicated above.
Employing a very conservative linear extrapolation based on the worst slope of degradation over time from the above results predicts that the ASA weight loss will be approximately 12.3 percent at the next ASA coupon extraction and 14 percent in three years.
12.31% = (5.90 - 2.87)/(44 months) * (96 months) + 5.70%
13.96% = (5.90 - 2.87)/(44 months) * (120 months) + 5.70%
Both are substantially less than the 26.25 percent boron loss assumed in the criticality calculation.
Therefore, we believe three years in an appropriate time frame to revise the coupon surveillance program.
Document Control Desk February 25, 2004 Page 3 Should you have questions regarding this matter, we will be pleased to iscuss them with you.
Ve y STATE OF MARYLAND
- TO WIT:
COUNTY OF CALVERT 1,George Vanderheyden, being duly sworn, state that I am Vice President - Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP), and that I am duly authorized to execute and file this License Amendment Request on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on y personal knowledge, they are based upon information provided by other CCNPP employees an I nsultants. Such information has been reviewed in accordance with company practice and I belie it o e reliable.
Subscribed and sworn before me, a Notary Pubic in and for the State of Maryland and County of 5 this o29'y day of .y , 2004.
WITNESS my Hand and Notarial Seal: /,
~
Notary Publi My Cornnission Expires: ,vcz 62S* 2oODa 7 Dat6 GV/DJM/bjd
Attachment:
(1) Additional License Condition cc: J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC R. J. Laufer, NRC R. 1.McLean, DNR G. S. Vissing, NRC
ATTACHMENT (1)
ADDITIONAL LICENSE CONDITION Calvert Cliffs Nuclear Power Plant, Inc.
February 25,2004
ATTACHMENT (1)
ADDITIONAL LICENSE CONDITION Amendment No. Additional Conditions Implementation Date This amendment requires the licensee 3 years after approval of this develop a long-term coupon surveillance amendment program for the Carborundum samples. This program must verify that the Carborundum degradation rates assumed in the licensee's analyses to prove subcriticality, as required by 10 CFR 50.68, remain valid over the seventy-year life span of the Unit I spent fuel pool. The licensee must submit this modified coupon surveillance program to the NRC under the 10 CFR 50.90 requirements for its review and approval.
I