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TAC:MB6062, Administratively Control Containment Penetrations (Approved, Closed) TAC:MC6063, Administratively Control Containment Penetrations (Approved, Closed) TAC:MC6062, Administratively Control Containment Penetrations (Approved, Closed) |
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MONTHYEARML0227402062002-09-26026 September 2002 Proposed Amendments Re 2 TSTFs Project stage: Other ML0406406372004-03-0101 March 2004 Response to Request for Additional Information Concerning the License Amendment Request to Revise the Refueling Operations Section of the Technical Specifications Project stage: Response to RAI ML0414505032004-05-20020 May 2004 Additional Information Concerning the License Amendment Request to Revise the Refueling Operations Section of the Technical Specifications Project stage: Request ML0422902382004-08-11011 August 2004 Withdrawal of Change 1 to License Amendment Request Regarding Revisions to the Refueling Operations Section of the Technical Specifications Project stage: Withdrawal ML0425304362004-09-13013 September 2004 Issuance of License Amendments Revision to the Refueling Operations Section of the Technical Specifications Project stage: Approval ML0425802462004-09-13013 September 2004 Tech. Spec. Pages for Amendments 268 and 244 Revision to the Refueling Operations Section of the Technical Specifications Project stage: Other ML0430001872004-10-21021 October 2004 Technical Specification Page for Corrected Amendment Nos. 268 and 244 Project stage: Other ML0429500162004-10-21021 October 2004 Correction to Amendment No. 268 and 244 Project stage: Other 2004-03-01
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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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Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Constellation Generation Group, LLC Lusby, Maryland 20657 Constellation Energy Group May 20, 2004 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 Additional Information Concerning the License Amendment Request to Revise the Refueling Operations Section of the Technical Specifications
REFERENCES:
(a) Letter from Mr. G. Vanderheyden (CCNPP) to Document Control Desk (NRC), dated March 1, 2004, Response to Request for Additional Information Concerning the License Amendment Request to Revise the Refueling Operations Section of the Technical Specifications (b) Letter from Mr. P. E. Katz (CCNPP) to Document Control Desk (NRC),
dated August 6, 2002, License Amendment Request: Revisions to the Refueling Operations Section of the Technical Specifications This letter provides clarifying information to the information that was provided 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).
Reference (a) provided information concerning the current analysis for Control Room doses. It has been determined that additional information would provide some clarification to the current Control Room dose analysis. This clarifying information is provided below.
In the mid-1990's Calvert Cliffs performed in-leakage testing of the Control Room and identified excessive in-leakage. Major modifications were implemented to reduce the amount of in-leakage.
Subsequent testing performed over the years has demonstrated significant reduction in in-leakage.
The most limiting unfiltered in-leakage into the Calvert Cliffs Nuclear Power Plant (CCNPP) Control Room is 3000+/-250 cubic feet per minute (CFM), which is less than the in-leakage value of 3500 CFM assumed in the CCNPP design basis radiological analyses.
Document Control Desk May 20, 2004 Page 2 The latest CCNPP Control Room tracer gas testing that resulted in the 3000+/-250 CFM unfiltered in-leakage was performed in January 2000. The test was performed by Nucon International, Inc. who is a 10 CFR Part 50, Appendix B vendor. The test determined the overall in-leakage into the Control Room via a Sulfur Hexaflouride (SF6) decay test per American Society for Testing and Materials E-741 guidance. The Control Room test configuration was 100% continuous recirculation mode, which is the accident lineup. Subsequent informal tests have shown in-leakage values that are consistent with the January 2000 test.
The CCNPP design basis radiological analysis that is currently credited in our Updated Final Safety Analysis Report (UFSAR) was completed in September 2000. The design basis analysis is based on a Maximum Hypothetical Accident (MHA) and a Fuel Handling Accident (FHA) in Containment with the following assumptions:
- a. The atmospheric dispersion coefficient from the Containment to the Control Room was assumed to be 7.7E-4 (0-8 hours), 4.5E-4 (8-24 hours), 2.5E-4 (1-4 days), and 6.3E-5 (4-30 days). These values are based on three years of onsite data.
- b. The Control Room volume is assumed to be 166,000 ft3 in accordance with the design value.
- c. The Control Room is in continuous recirculation (accident) mode with 3500 CFM of unfiltered leakage.
- d. The Control Room recirculation filter flow starts at 2.1 seconds on a high radiation signal. The portion of the recirculation flow which passes through the 90% efficient post-loss-of-coolant accident filters is 2,000+/-10% CFM.
- e. The Control Room occupancy factors are assumed to be 1.0 (0-1 day), 0.6 (1-4 days), and 0.4 (4-30 days), per Standard Review Plan 6.4-19, Revision 2.
- f. The self-contained breathing apparatus (SCBA) was assumed to have a Protection Factor of 10,000.
The proposed change (Reference b) would allow containment penetrations to be opened under administrative control during movement of irradiated fuel assemblies within Containment. The majority of the containment penetrations that would be allowed open under administrative control would open into the Auxiliary Building penetration room, which has a filtered release. Since the Control Room atmospheric dispersion coefficient assumes uniform containment leakage over the containment surface and no filtration is assumed prior to reaching the Control Room ventilation system, this analysis bounds both filtered and unfiltered release paths. The filters in the Auxiliary Building penetration room provide an additional conservatism beyond the calculated results. Therefore, any release of radioactivity from containment penetrations following a FHA would be bounded by our current analysis.
The radiological analyses concluded that the Control Room post-loss-of-coolant accident thyroid dose will be maintained below the [General Design Criterion (GDC) 19] 30-day limit of 30 rem, if planned protective measures (i.e., SCBAs) are implemented within 32 minutes for a MHA and 82 minutes for a FHA in Containment. The use of SCBAs and Potassium Iodide (KI) tablets by the Control Room operators following an accident is consistent with Calvert Cliffs' Emergency Response Plan. There are sufficient SCBAs staged in the Control Room to provide protection to all Control Room operators following an accident and that additional SCBAs are staged elsewhere onsite for operators coming on-shift. The methodology employed for these analyses is contained in UFSAR, Chapters 9 and 14. The calculated
Document Control Desk May 20, 2004 Page 3 Control Room operator doses for the FHA in Containment is provided below in Table 1. Detailed results are provided only for the FHA in Containment because it is the incident of concern for this proposed amendment.
Table 1 FHA in Containment Regulatory Limit Design Basis(Rm FIA Dose (Rem) (Rem)
Control Room In-leakage (CFM) 3500 Control Room Thyroid Dose 29.8 30 Whole Body Dose 2.60 5 Beta Skin Dose 1.15 30 Time to Don SCBAs (Minutes) 82 The current analysis for the FHA in Containment assumes the radioactive release is unfiltered and the proposed change (Reference b) will not result in higher in-leakage into the Control Room. Therefore, the current FHA analysis bounds the Containment configuration when containment penetrations are opened under administrative control.
Document Control Desk MayQ0, 2004 Page 4 Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, Bruce S. ontgo /
Manage, CCNPP-Engineer$ Services STATE OF MARYLAND
- TO WIT:
COUNTY OF CALVERT I, Bruce S. Montgomery, being duly sworn, state that I am Manager, Engineering Services - 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 my personal knowledge, they are based upon information provided by other CCNPP employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.
Sut bed an sworn before me,_,p Notary Public in an the State of M and County of
____ ____ ,this is day ofM 4,2004.
WITNESS my Hand and Notarial Seal:
-I0 - Nottry Publo9 Iy§J 1190l My Commission Expires:
Date BSMIGV/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