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MONTHYEARML0201704952002-01-17017 January 2002 RAI - Application for Amendments to Facility Operating Licensees Project stage: RAI ML0215401562002-05-27027 May 2002 Request to Revise Technical Specifications, Reactor Trip System Instrumentation Over Temperature Delta Temperature (OTDT) Reactor Trip Function Request for Additional Information Project stage: Request ML0222700882002-08-0909 August 2002 Amendment Nos. 127 and 105, Revising the Current TSs for Vogtle to Place a Cooldown Clamp on the Overtemperature Delta Temperature Reactor Trip Function Project stage: Other ML0222500712002-08-0909 August 2002 Tech Spec Pages for Amendment Nos 127 and 105 Re Application Dated October 30, 2001, as Supplemented by Letters Dated February 11 and May 27, 2002 Project stage: Other ML0223201562002-08-20020 August 2002 Corrected Page 2 for Amendments 127 & 105 to Licenses NPF-68 & NPF-81, Respectively. for Vogtle Electric Generating Plant, Units 1 & 2 Project stage: Other 2002-05-27
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Category:Letter
MONTHYEARML24032A0252024-02-0505 February 2024 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026-2023009 ML24010A0712024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports and Recordkeeping and Suspicious Activity Reporting) ML24031A6102024-01-31031 January 2024 Cyber Security Inspection Report 05200026/2024401 - Public ML24029A0592024-01-30030 January 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report Enclosure 2, GAE-NRCD-RF-LR-000002 P-Attachment, Rev. 0 ML24016A1132024-01-30030 January 2024 Correction of Unit 1 Amendment Nos. 96 and 190 and Unit 2 Amendment Nos. 74 and 173 Adoption of Standard Technical Specifications Westinghouse Plants NL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 IR 05000424/20244032024-01-26026 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000424/2024403; 05000425/2024403 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report ML23347A2092024-01-17017 January 2024 Voluntary Requests for Data, Information, And/Or Observation ML23279A0042024-01-17017 January 2024 Amendment No. 194 to Remove Combined License Appendix C NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23345A1312024-01-0303 January 2024 Withholding Letter - 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Text
January 17, 2002 Mr. J. B. Beasley, Jr.
Vice President Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: APPLICATION FOR AMENDMENTS TO FACILITY OPERATING LICENSEES, VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (TAC NOS. MB3568 AND MB3569)
Dear Mr. Beasley:
The Nuclear Regulatory Commission is reviewing your amendment request dated October 17, 2001, in which you proposed changes to Vogtle Unit 1 and Unit 2 Technical Specification Table 3.3.1-1, Reactor Trip Instrumentation. These changes would clamp the over temperature T (OTT) function during cooldown events to a value 3- lower than the reference temperature for the associated loop. This clamp will limit the OTT trip setpoint increase during cooldown events, thereby increasing the clad stress margin. In addition, you proposed to use this increased clad stress margin to allow relaxation of the reduced relaxed axial offset control (RAOC) band to limits which do not account for cycle-to-cycle fuel management variations.
The staff has determined that, in order to complete its review, a detailed technical justification is needed to show that the proposed clamp will provide the required clad stress margin to allow relaxation of the RAOC band to the limits proposed in the licensing amendment request. In addition, the staff is requesting you to show that the effects of relaxation of the RAOC band have been considered for plant transients and accidents for which the axial flux difference (AFD) is an initial condition. Based on these considerations, the staff requests the following information in order to continue with its review:
- 1) Identify the clad stress criteria used as the basis for determining the allowable values of the AFD. Include a reference to the NRC approved methodologies used in performing the analyses that serve as the basis for justifying the proposed changes.
- 2) Submit a quantitative technical justification demonstrating that the proposed OTT clamp value will result in the required clad stress margin necessary to allow relaxation of the RAOC band to the proposed limits.
- 3) Demonstrate that with the proposed RAOC band the clad stress criteria identified in question number (1) continues to be met for all transients and accidents for which the AFD is an initial condition. In addition, identify any transients or accidents which will have a reduced safety margin resulting from the proposed changes.
- 4) Provide justification for the non-conservative change in the trip setpoint reduction value when AFD > +10 percent. Include a discussion of the effects of the change in this value from 2.7 percent rated thermal power (RTP) to the less conservative 1.95 percent RTP on transients and accidents which result in a top-skewed AFD.
- 5) Provide a discussion, including references to NRC approval, explaining the technical considerations which resulted in the current AFD limits for Vogtle.
I discussed these questions with Mr. Jim Bailey, Vogtle Licensing Manager, and he estimated that your answers will be submitted by January 31, 2002.
Sincerely,
/RA/
Ramin Assa, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425 cc: See next page
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