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Category:Letter type:RS
MONTHYEARRS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 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-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-101, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-21-009, Proposed Relief Request Associated with Code Case N-9212022-01-18018 January 2022 Proposed Relief Request Associated with Code Case N-921 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-114, Request for Exemption from 10 CFR 2.109(b)2021-10-28028 October 2021 Request for Exemption from 10 CFR 2.109(b) RS-21-110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-19019 October 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-103, Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station2021-09-28028 September 2021 Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station RS-21-097, Withdrawal of Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3, and Previously Submitted Licensing Actions in Support of Decommissioning2021-09-15015 September 2021 Withdrawal of Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3, and Previously Submitted Licensing Actions in Support of Decommissioning RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-086, Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2021-08-23023 August 2021 Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel 2023-08-30
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Exelon Generation wwwexeloncorp corn Nuclear 4300 Winfield Road Warrenville, IL 60555 RS-02-1 97 November 11, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
Reply to Request for Comments on Draft Response to Task Interface Agreement Concerning the Reactor Building Crane and Heavy Loads Handling
Reference:
Letter from U. S. NRC to J. L. Skolds (Exelon Generation Company, LLC), "Dresden Nuclear Power Station, Units 2 and 3 - Draft Response to Task Interface Agreement 2001-13 Concerning the Reactor Building Crane and Heavy Loads Handling," dated September 11, 2002 In the referenced letter, the NRC provided a draft response to a Task Interface Agreement (TIA) to Exelon Generation Company, LLC (Exelon) and gave Exelon the opportunity to identify any technical errors or relevant information that was not considered in the draft TIA response. The attachment to this letter provides our comments on this draft TIA response.
In a teleconference between Mr. L. W. Rossbach of the NRC and Mr. A. R. Haeger of Exelon, it was agreed that our comments would be provided by November 11, 2002.
Should you have any questions concerning this letter, please contact Mr. Allan R.
Haeger at (630) 657-2807.
Respectfully, Patrick R. Simpson Manager - Licensing Mid-West Regional Operating Group Attachment cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station
Attachment Reply to Request for Comments on Draft Response to Task Interface Agreement Concerning the Reactor Building Crane and Heavy Loads Handling
Background
In a letter from the U. S. NRC to J. L. Skolds (Exelon Generation Company, LLC),
"Dresden Nuclear Power Station, Units 2 and 3 - Draft Response to Task Interface Agreement 2001-13 Concerning the Reactor Building Crane and Heavy Loads Handling," dated September 11, 2002, the NRC reached conclusions regarding the licensing basis for Dresden Nuclear Power Station (DNPS) concerning heavy loads handling. The letter provided Exelon with the opportunity to identify any technical errors or relevant information that was not considered in the draft response.
Response
Exelon has reviewed the draft task interface agreement (TIA) response and provides the following comment on the conclusions stated in the draft TIA response in the following sections.
Section 3.1 "In the SER, the staff stated that the reactor building crane met the intent of the requirements in BTP APCSB 9-1 for handling heavy loads weighing up to 100 tons ... "
Section 3.2.1 "Following restoration of the reactor building crane to conform to its original licensing basis, the licensee is prohibited from lifting loads exceeding 100 tons as a 'single failure-proof' crane."
Section 3.2.3 (F)
"As stated in Sections 3.1 and 3.2.1 above, the single-failure licensing basis for the Dresden reactor building crane requires that the loads be carried within the established controlled area (or a safe load path) and that they do not exceed 100 tons, which includes the weight of the lifting apparatus."
Additionally, a number of other sections refer to the single-failure-proof capacity of the crane as 100 tons.
In References 1 and 2, Commonwealth Edison (CoinEd) Company, now Exelon, requested approval for Dresden Nuclear Power Station (DNPS) to handle spent fuel shipping casks weighing nominally up to 100 tons with the handling system described in reports attached to References 1 and 2. The handling system described in the reports includes a description of the lifting rig for the casks, and evaluates acceptability of this lifting rig. The weight of the lifting rig was specified to be 10 tons. In Reference 3, the NRC Safety Evaluation (SE) stated, "...we conclude that the overhead crane handling system and proposed spent fuel cask handling Technical Specifications meet our requirements and are acceptable for handling spent fuel casks weighing up to 100 tons."
Exelon concludes from this SE that for handling spent fuel casks, the licensing basis recognizes that the total crane lifted load would be 110 tons (i.e., the weight of the cask and lifting apparatus).
Exelon considers the References 1 and 2 submittals and the Reference 3 NRC approval to have evaluated the reactor building crane as a 125-ton single failure proof crane and, separately, to have evaluated the cask handling devices and cask handling Technical Page 1 of 3
Attachment Reply to Request for Comments on Draft Response to Task Interface Agreement Concerning the Reactor Building Crane and Heavy Loads Handling Specifications. This understanding is consistent with the information in References 1 and 2, which demonstrated that the crane met the required factors of safety as specified in BTP 9-1 based on a 125-ton load. This is also consistent with statements in Reference 3, which concluded that the integrated design of the crane controls and cask lifting devices meets the intent of BTP 9-1.
However, Exelon understands that the licensing basis regarding this issue is subject to interpretation. In order to provide a long-term resolution of this matter, we plan to submit a license amendment request to clarify the licensing basis regarding the single-failure proof rating of the reactor building crane. Until this planned license amendment request is approved, Exelon has concluded that the licensing basis clearly supports lifting loads of up to 110 tons with the reactor building crane as a single-failure-proof crane. This conclusion was discussed in a teleconference between members of the NRC and members of Exelon on September 13, 2002.
Exelon provides the following additional comments regarding the draft TIA response.
These comments do not affect the general conclusions of the draft TIA response, but are provided to clarify or make minor corrections.
" The TIA and draft response imply that three modifications described in Reference 3 (i.e., the redundant mechanical limit switch in the main hoist power circuit, the electrical interlock system, and the capability for slow speed hoisting) may not have been installed or remained functional. Section 3.2.4 of the TIA response states, "This circumstance [i.e., failure to complete or maintain the modifications] should be corrected, and the licensee should be required to complete the modifications prior to moving casks. Accordingly, the licensee should be required to implement and maintain the overhead handling system modifications and re-evaluate its NUREG 0612 commitments to operate the crane within its design and licensing basis."
DNPS personnel have verified that the three modifications discussed are installed and functional, with the understanding that in Reference 3 the NRC approved an alternative modification that provided equivalent capability for slow speed hoisting.
In addition, a CoinEd submittal in 1991 (Reference 4) stated that these modifications had been installed. Exelon suggests that the TIA response clarify that the modifications are currently installed and functional.
Additionally the statement regarding re-evaluation of NUREG-0612 commitments is unclear in this context. Exelon suggests that this portion of the section be clarified.
" In Section 3.1, the second paragraph of the draft TIA response states that the November 8, 1974, letter (Reference 1) proposed certain modifications to the handling system to make it "single-failure-proof' for handling loads up to 100 tons.
The Reference 1 letter stated the following:
"Your approval is requested to handle spent fuel shipping casks weighing up to nominally 100 tons with the handling system described in the attached special reports."
Page 2 of 3
Attachment Reply to Request for Comments on Draft Response to Task Interface Agreement Concerning the Reactor Building Crane and Heavy Loads Handling Exelon suggests that this paragraph of the TIA response be clarified.
In Section 3.1, the last paragraph of the draft TIA response discusses ComEd's response to NRC Bulletin 96-02 and states, "the licensee stated that, in the future, prior to moving heavy loads [emphasis added] with the reactor in power operation, the licensee would demonstrate the capability of performing actions necessary to achieve safe shutdown following a dropped load inside the facility."
The CornEd response to Bulletin 96-02 stated that this capability would be demonstrated prior to moving dry storagie casks over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power. The draft TIA response appears to broaden the intent of the CoinEd NRC Bulletin 96-02 response.
Additionally, in 2001 (Reference 5), Exelon notified the NRC of a commitment change to clarify its response to Bulletin 96-02. This commitment change was based on Exelon's understanding that the reactor building crane was single-failure-proof, and that load drop analyses would therefore not be required for spent fuel cask handling. Exelon suggests that this paragraph of the draft TIA response be clarified.
- In Section 3.2.1, the TIA response states, "Any loads lifted above 100 tons should be analyzed following the guidelines of NUREG-0612, Section 5.1.1(2).
The reference to NUREG-0612 should be to Section 5.1.4(2).
References
- 1. Letter from J. S. Abel (Commonwealth Edison Company) to U. S. NRC, "Dresden Station Units 2 and 3, Quad Cities Station Units 1 and 2, Dresden Special Report No.
41,.Quad Cities Special Report No. 16, 'Reactor Building Crane and Cask Yoke Assembly Modifications,' AEC Dckt. 50-237, 50-249, 50-254 and 50-265," dated November 8, 1974
- 2. Letter from J. S. Abel (Commonwealth Edison Company) to U. S. NRC, "Dresden Station Units 2 and 3, Quad Cities Station Units 1 and 2, Dresden Special Report No.
41, Supplement A, Quad Cities Special Report No. 16 - Supplement A, 'Reactor Building Crane and Cask Yoke Assembly Modifications,' NRC Dckts. 50-237, 50 249, 50-254 and 50-265," dated June 3, 1975
- 3. Letter from U. S. NRC to R. L. Bolger (Commonwealth Edison Company), dated June 3, 1976
- 4. Letter from M. H. Richter (Commonwealth Edison Company) to U. S. NRC, "Dresden Nuclear Power Station Units 2 and 3; Application for Amendment to Facility Operating Licenses DPR-19 and DPR-25, Appendix A, Technical Specifications,"
dated August 9, 1991
- 5. Letter from P. Swafford (Exelon Generation Company, LLC) to U. S. NRC, "2001 Regulatory Commitment Change Summary Report," dated March 21, 2002 Page 3 of 3