Letter Sequence Other |
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TAC:MD8950, Clarify Application of Setpoint Methodology for LSSS Functions (Open) |
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MONTHYEARNG-08-0366, Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value Affected Technical Specification: Section 3.3.8.12008-05-30030 May 2008 Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value Affected Technical Specification: Section 3.3.8.1 Project stage: Other ML0819101062008-07-11011 July 2008 Request for Supplemental Information Pertaining to a License Amendment Request to Revise the 4160 Volt Bus Undervoltage (Degraded Voltage) Maximum Allowed Value Project stage: Other ML0820503962008-07-17017 July 2008 Calculation CAL-E95-006, Revision 4, 4.16 Kv Essential Bus Degraded Voltage Setpoint Calculation. Project stage: Request NG-08-0551, Response to Request for Supplemental Information Regarding Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value, Affected Tech Spec: Section 3.3.8.12008-07-17017 July 2008 Response to Request for Supplemental Information Regarding Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value, Affected Tech Spec: Section 3.3.8.1 Project stage: Supplement ML0822106322008-08-0808 August 2008 E-mail to Transmit a Comment Found During Acceptance Review Re Supplementing LAR, Duane Arnold Project stage: Acceptance Review ML0822506372008-08-12012 August 2008 MD8950 - Request for Supplemental Information (Rsi) 2008-08-12 Project stage: Other NG-08-0709, Request to Withdraw Portions of the Information Submitted Regarding Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value.2008-09-10010 September 2008 Request to Withdraw Portions of the Information Submitted Regarding Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value. Project stage: Other ML0826204382008-10-0303 October 2008 Acceptance Ltr. 2008-09-18-1250, Acceptance of Request for License Amendment Pertaining to Revision of the 4160 Volt Bus Undervoltage (Degraded Voltage) Maximum Allowed Value Project stage: Acceptance Review ML0833301672008-11-28028 November 2008 Draft RAI on Proposed Amendment Regarding Degraded Voltage Maximum Allowable Value Project stage: Draft RAI ML0900904162009-01-12012 January 2009 Request for Additional Information Pertaining to a License Amendment Request to Revise the 4160 Volt Bus Undervoltage (Degraded Voltage) Maximum Allowed Value Project stage: RAI ML0902105742009-01-21021 January 2009 MD8950 RAI Response - Changed Response Data Project stage: RAI ML0902704312009-01-26026 January 2009 MD8950 - Record of Changing RAI Response Date from 1/26/2009 to 2/27/2009 Project stage: RAI NG-09-0054, Response to Request for Additional Information Pertaining to a License Amendment Request to Revise the 4160 Volt Bus Undervoltage (Degraded Voltage) Maximum Allowed Value2009-02-27027 February 2009 Response to Request for Additional Information Pertaining to a License Amendment Request to Revise the 4160 Volt Bus Undervoltage (Degraded Voltage) Maximum Allowed Value Project stage: Response to RAI ML0911903952009-04-29029 April 2009 Revision to e-mail: (1) MD8950 State Consultation; and (2) Changed Contact Person as State Liaison Officer (re-sent with Correct Iowa State Domain) Project stage: Other ML0912605512009-05-15015 May 2009 License Amendment, Revision of the 4160 Volt Bus Undervoltage (Degraded Voltage) Maximum Allowed Value Project stage: Other 2008-08-08
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Category:Letter
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) NG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update ML23137A1672023-05-11011 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22339A0012022-12-22022 December 2022 Acceptance of Requested Licensing Action Amendment Request for Common Emergency Plan IR 05000331/20220032022-12-13013 December 2022 NRC Inspection Report No. 05000331/2022003 (Drss) ML22285A0072022-10-13013 October 2022 NRC Analysis of NextEra Energy Duane Arnold'S Decommissioning Funding Status Report, Docket No. 50-331 IR 05000331/20220022022-07-13013 July 2022 NRC Inspection Report Nos. 05000331/2022002(DNMS) and 07200032/2022002(DNMS) ML22090A1922022-05-26026 May 2022 Letter to B. Coffey, FPL from M. Doell - Duane Arnold Post Shutdown Activities Report Review Letter ML22132A2872022-05-24024 May 2022 ISFSI DQAP Approval Letter ML22111A0332022-05-20020 May 2022 Operating License Page Correction Letter to B. Coffey, Florida Power and Light, from M. Doell NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan ML22089A0492022-05-12012 May 2022 Sfmp Review Letter NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative IR 05000331/20224012022-04-27027 April 2022 Decommissioning Security Inspection Report 05000331/2022401 NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 22022-04-25025 April 2022 NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2 ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22080A1822022-03-22022 March 2022 Letter to B. Coffey from M. 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July 11, 2008 Mr. Richard L. Anderson Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR SUPPLEMENTAL INFORMATION PERTAINING TO A LICENSE AMENDMENT REQUEST TO REVISE THE 4160 VOLT BUS UNDERVOLTAGE (DEGRADED VOLTAGE) MAXIMUM ALLOWED VALUE (TAC NO. MD8950)
Dear Mr. Anderson:
By letter dated May 30, 2008, Agencywide Documents Access and Management System (ADAMS) Accession No. ML081630205, the FPL Energy Duane Arnold, LLC, requested for a license amendment (LAR) to revise the upper limit of the allowable value for Function 2.a, 4.16 kV Emergency Bus Voltage (Degraded Voltage), Bus Undervoltage, in technical specifications (TS) Table 3.3.8.1-1, Loss of Power Instrumentation, from less than or equal to 3899 volts to less than or equal to 3822 volts.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff=s acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR),
an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that FPL Energy Duane Arnold, LLC, supplement the application to address the information requested in the enclosure by July 17, 2008. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff=s request is not received
R. Anderson by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff=s detailed technical review by separate correspondence.
The information requested and associated time frame in this letter were discussed with Tony Browning of your staff on July 2, 2008.
If you have any questions, please contact me at (301) 415-3079.
Sincerely,
/RA/
Karl D. Feintuch, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
As stated cc w/encl: See next page
ML081910106 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/EICB/BC NRR/LPL3-1/BC NAME KFeintuch THarris WKemper LJames DATE 7/10/08 7/9/08 7/10/08 7/11/08 REQUEST FOR SUPPLEMENTAL INFORMATION DUANE ARNOLD ENERGY CENTER LICENSE AMENDMENT REQUEST REVISION OF TECHNICAL SPECIFICATION (TS) TABLE 3.3.8.1-1, 4160 V BUS UNDERVOLTAGE By letter dated May 30, 2008, the FPL Energy Duane Arnold, LLC, requested a license amendment (LAR) to revise the upper limit of the allowable value for Function 2.a, 4.16 kV Emergency Bus Voltage (Degraded Voltage), Bus Undervoltage, in TS Table 3.3.8.1-1, Loss of Power Instrumentation, from less than or equal to 3899 volts to less than or equal to 3822 volts.
The staff has determined that in order to complete its review of the LAR acceptability, the staff needs the following supplemental information:
- 1. Setpoint Calculation Methodology: Provide documentation (including sample calculations) of the methodology used for establishing the limiting setpoint (or NSP) and the limiting acceptable values for the As-Found and As-Left setpoints as measured in periodic surveillance testing described below. Indicate the related analytical limits and other limiting design values (and the sources of these values) for the setpoint.
- 2. Safety Limit (SL)-Related Determination: Provide a statement as to whether or not the setpoint is a limiting safety system setting for a variable on which a SL has been placed as discussed in 10 CFR 50.36(d)(1)(ii)(A). Such setpoints are described as ASL-Related@ in the discussions that follow. In accordance with 10 CFR 50.36(d)(1)(ii)(A), the following guidance is provided for identifying a list of functions to be included in the subset of limiting safety system settings (LSSSs) specified for variables on which SLs have been placed as defined in Standard Technical Specifications Sections 2.1.1, reactor core SLs and 2.1.2, reactor coolant system pressure SLs. This subset includes automatic protective devices in TSs for specified variables on which SLs have been placed that: (1) initiate a reactor trip; or (2) actuate safety systems. As such these variables provide protection against violating reactor core safety limits, or reactor coolant system pressure boundary safety limits.
Examples of instrument functions that might have LSSSs included in this subset in accordance with the plant-specific licensing basis, are pressurizer pressure reactor trip (pressurized-water reactors), rod block monitor withdrawal blocks (boiling-water reactors), feedwater and main turbine high water level trip (boiling-water reactors), and end of cycle recirculation pump trip (boiling-water reactors).
If the proposed setpoint is determined not to be SL-related, explain the basis for this determination.
- 3. For setpoints that is determined to be SL-related: The Nuclear Regulatory Commission (NRC) letter to the Nuclear Energy Institute SMTF dated September 7, 2005 (Agencywide Documents Access and Management System Accession No. ML052500004), describes setpoint-related TS (SRTS) that are acceptable to the NRC for instrument settings associated with SL-related setpoints. Specifically: Part AA@ of the Enclosure to the letter provides limiting condition for operation notes to be added to the TS, and Part AB@ includes a check list of the information to be provided in the TS Bases related to the proposed TS changes.
- a. Describe whether and how you plan to implement the SRTS suggested in the September 7, 2005, letter. If you do not plan to adopt the suggested SRTS, then explain how you will ensure compliance with 10 CFR 50.36 by addressing items 3b and 3c, below.
- b. As-Found Setpoint evaluation: Describe how surveillance test results and associated TS limits are used to establish operability of the safety system.
Show that this evaluation is consistent with the assumptions and results of the setpoint calculation methodology. Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be Ainoperable@ or Aoperable but degraded.@ If the criteria for determining operability of the instrument being tested are located in a document other than the TS (e.g.
plant test procedure) explain how the requirements of 10 CFR 50.36 are met.
- c. As-Left Setpoint control: Describe the controls employed to ensure that the instrument setpoint is, upon completion of surveillance testing, consistent with the assumptions of the associated analyses. If the controls are located in a document other than the TS (e.g. plant test procedure) explain how the requirements of 10 CFR 50.36 are met.
- 4. For setpoints that are not determined to be SL-related: Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion information on the controls you employ to ensure that the as-left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. Also, discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be Ainoperable@ or Aoperable but degraded.@ If the controls are located in a document other than the TS (e.g., plant test procedure), describe how it is ensured that the controls will be implemented.
- 5. The LAR in Exhibit A, Section 3.2, DAEC Licensing Basis, states, The maximum allowable voltage for the 4160 volt Emergency Bus Undervoltage relays does not constitute a Limiting Safety System Setting (LSSS) Provide justifications for this statement, specifically considering the requirements for LSSS specified in 10 CFR 50.36(d)(1)(ii)(A).
Duane Arnold Energy Center cc:
Mr. J. A. Stall Mr. D. A. Curtland Executive Vice President, Nuclear and Plant Manager Chief Duane Arnold Energy Center Nuclear Officer 3277 DAEC Rd.
Florida Power & Light Company Palo, IA 52324-9785 P. O. Box 14000 Juno Beach, FL 33408-0420 Abdy Khanpour Vice President, Engineering Support Mr. M. S. Ross Florida Power & Light Company Managing Attorney P. O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408 P. O. Box 14000 Juno Beach, FL 33408-0420 Daniel K. McGhee Iowa Department of Public Health Ms. Marjan Mashhadi Bureau of Radiological Health Senior Attorney 321 East 12th Street Florida Power & Light Company Lucas State Office Building, 5th Floor 801 Pennsylvania Avenue, NW Des Moines, IA 50319-0075 Suite 220 Washington, DC 20004 Chairman, Linn County Board of Supervisors T. O. Jones 930 1st Street SW Vice President, Nuclear Operations Cedar Rapids, IA 52404 Mid-West Region Florida Power & Light Company Peter Wells, Acting Vice President, P. O. Box 14000 Nuclear Juno Beach, FL 33408 Training and Performance Improvement Florida Power & Light Company Steven R. Catron P. O. Box 14000 Manager, Regulatory Affairs Juno Beach, FL 33408-0420 Duane Arnold Energy Center 3277 DAEC Road Mark E. Warner Palo, IA 52324 Vice President, Nuclear Plant Support Florida Power & Light Company U. S. Nuclear Regulatory Commission P. O. Box 14000 Resident Inspector=s Office Juno Beach, FL 33408-0420 Rural Route #1 Palo, IA 52324 Mr. Mano Nazar Senior Vice President and Nuclear Chief Operating Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408 Last revised July 2, 2008