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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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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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George Vanderheyden 1650 Calvert Cliffs Parkway Vice President Lusby, Maryland 20657 Calvert Cliffs Nuclear Power Plant 410 495-4455 Constellation Generation Group, LLC 410 495-3500 Fax Constellation Energy Group November 3, 2003 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 1; DocketNos. 50-317 Response to Second 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) Letter from Mr. G. S. Vissing (NRC) to Mr. P. E. Katz (CCNPP), dated July 25 2003, "Request for Additional Information, Technical Specification Change to Increase Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit (TAC No. MB8896)"
(b) Letter from Mr. P. E. Katz (CCNPP) to NRC Document Control Desk, 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 affect the No Significant Hazards Consideration Determination or the Environmental Impact Review of Reference (b).
Requested Information:
- 1. In your letter of May 1, 2003, you proposedincreasingthe maximum enrichmentfor standardfuel assemblies to 5.0 weight percent, while te current Technical SpecifIcation of Calvert Cliffs Nuclear Power Plant (CCNPP) limits the maximum enrichment for standardfuel assemblies to 4.52 weight percent. Indicate wletler the weight of the fuel assenbliessupported by the spentfuel racks will increase as result of the enrichment. If the weight of the fuel assemblies is increased, what are the effects on the spent fuel racks and the spent fuel pool structure due to the increased weight?
CCNPP Response:
Increasing the maximum enrichment does not result in a weight increase of the fuel assemblies. The process that will be used to increase the enrichment will result in some of the heavier U-238 fuel being replaced with lighter U-235.
' OCI
Document Control Desk November 3, 2003 Page 2
- 2. In consideration of the possibilityfor increased loads from spent fuel racks, discuss your past operation, inspection and maintenance experience of the CCNPPspentfuel racks and spentfuel pool structures. As applicable, discuss any pool wall/bottom slab cracking, settlement and/orpool water leakages observed to date andrepairmeasurestaken to remedy then.
CCNPP Response:
Increasing the maximum enrichment will not result in increased loads.
- 3. What is tie maximum bulk pool temperature at afull core off-load during a refueling outage? If the temperature exceeds 150 "F, provide technicaIjustifcationsfor exceeding a gross temperature of 150 IF in accordance with the guidance in the American Concrete Institute Code 349 for long-term operation.
CCNPP Response:
As stated in the Updated Final Safety Analysis Report, Section 9.4.1, the maximum temperature with a full core off-load would be 130"F, assuming two loops of spent fuel pool cooling is in operation.
The increased enrichment does not result in the maximum temperature of the spent fuel pool exceeding the limit stated in the Updated Final Safety Analysis Report during a normal refueling outage. Assuming a more conservative bounding temperature of 155"F does not alter the design basis value of 1301F. The 155"F value denotes a worst-case short-term accident value that is not valid for long-term operation.
- 4. In Section 7.0, Technical Assumptions, of the license amendment request, the licensee cites that the Nuclear Regulatory Commission acknowledged commitment in Section 2.1.3.7 of the license renewal applicationfor CCNPP. In this commitment, the licensee stated it would perform an analysis on carborundum to demonstrate that it can perform its criticality controlfunction for 70years. According to Section 3.10.2.4, "Time-Limited Aging Analysis," of the Final Safetj' Evaluation Report regarding the license renewal of CCNPP Unit Nos. I and 2, the licensee's analysis was to be completed in 2000.
If the licensee proposes to credit this analysisfor its amendment request, CCNPPshould provide the analysis to support the amendment request.
CCNPP Response:
Section 2.1.3.7 of the CCNPP License Renewal Application indicates that CCNPP will perform an analysis to demonstrate that the carborundum can perform its criticality control function for a 70-year service life. The Nuclear Regulatory Commission acknowledged this commitment in NUREG-1705, Section 3.10.2.4. Therefore, it was necessary to account for the additional boron that could be lost between 40 and 70 years. In addition, previous criticality calculations have also considered a 10%
uncertainty in addition to using the worst-case B-10 loading. This uncertainty is to account for the experimental variation in boron loss rate measurement.
The original minimum loading was 0.024 gcm2 . A B-10 loading of 0.020 g/cm 2 was used in the design basis analysis to represent a 15% loss over 40 years. Linearly extrapolating this loss rate to 70 years yields (with the implicit assumption that the rate remains constant) a B-10 loading of 0.0177 g/cm 2 (0.024 - 70/40*0.15*0.024) and 0.01593 g/cm2 for the 10% uncertainty case. Note that the
Document Control Desk November 3, 2003 Page 3 carborundum test data indicates that the boron loss plateaus at gamma exposures in excess of 10"1 Rads. Thus, the use of a linear extrapolation in poison weight loss is very conservative. This effort constitutes the 70-year service life extension analysis.
S. In Attachment (1) under Background and Analysis in tie System Design section, the licensee states tat CCNPP has a coupon surveillanceprogram to test tle condition of the carborundum material. Also, the licensee indicates that as a result ofLicense Renewal, that the boron loss from the carborundum between 40 and 70 years has been analyzed. The staff requests the licensee explain how the coupon surveillanceprogram will be modified to accountfor boron depletion due to the added neutron fluence of fuel with a greater enrichment as well as the increasedplant operatinglifespan.
CCNPP Response:
Analysis has determined that the boron depletion due to the added neutron fluence of fuel with a greater enrichment will be negligible for the service life of the spent fuel pool racks (up to 70 years).
Therefore, it is not necessary to modify the coupon surveillance program to account for boron depletion. However, the coupon surveillance program was modified as follows to account for the possible degradation of the coupons during the 70 years of service in a boric acid environment.
The accelerated poison sample surveillance program initially had 12 coupons and extracted a coupon for analysis every two years. The duration was increased to eight years to account for plant-life extension, with a final withdrawal scheduled for 2037. The affected coupons are re-inserted for possible future examination.
The long-term poison sample surveillance program initially had 12 coupons and extracted a coupon for analysis every four years. The duration was increased to five years to account for plant-life extension, with a final withdrawal scheduled for 2040. The affected coupons are re-inserted for possible future examination.
Document Control Desk November 3, 2003 Page 4 Should you have questions regarding this matter, we will be pleased to discuss them with you.
Ve rUy urs, STATE OF MARYLAND
- TO WIT:
COUNTY OF CALVERT I, 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 o my personal knowledge, they are based upon information provided by other CCNPP employees nor consultants. Such information has been reviewed in accordance with company practice and I I te able.
7C Subscribed and sworn before me, a Notary Pub ic in apd for the State of Maryland and County of 5;. thisP-9P day of 0?'eI A.- ,2003.
/ {) , , - n-WITNESS my Hand and Notarial Seal:
Notary Pu
-My Cornissi n Expires:
Dhte GV/DJM/bjd .--
cc: J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R. I. McLean, DNR G. S. Vissing, NRC