Letter Sequence Approval |
---|
|
|
MONTHYEARML0414800492004-06-10010 June 2004 Issuance of Amendment Elimination of Requirements for Hydrogen and Oxygen Montiors Project stage: Approval ML0713006482007-05-23023 May 2007 Supplement to Safety Evaluation for Amendment No. 254 Regarding Relocation of Requirements for Hydrogen and Oxygen Monitors Project stage: Approval 2004-06-10
[Table View] |
|
---|
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. Doell - Duane Arnold ISFSI QAPD RAI Letter L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022 Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22059A7462022-03-10010 March 2022 ISFSI-Only Physical Security Plan License Amendment Approval NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks IR 05000331/20220012022-03-0404 March 2022 Subject: NRC Inspection Report Nos. 05000331/2022001(DNMS) and 07200032/2022001(DNMS) NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22007A2722022-02-11011 February 2022 Cover Letter - NRC Duane Arnold Exemption Issuance NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22028A2822022-02-0303 February 2022 Defueled Physical Security Plan License Amendment Approval ML22033A0802022-02-0202 February 2022 Supplement to License Amendment Request (TSCR-188): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition IR 05000331/20210012022-01-25025 January 2022 NRC Inspection Report Nos. 05000331/2021001(DNMS); 07200032/2021001(DNMS); and 07200032/2021002(DNMS) - Duane Arnold Energy Center ML21172A2172022-01-21021 January 2022 Issuance of License Amendment to Adopt ISFSI-Only Technical Specifications NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021 Registration of Independent Spent Fuel Installation Storage Casks NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister 2024-01-25
[Table view] |
Text
May 23, 2007 Mr. Gary Van Middlesworth Site Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - SUPPLEMENT TO SAFETY EVALUATION FOR AMENDMENT NO. 254 REGARDING RELOCATION OF REQUIREMENTS FOR HYDROGEN AND OXYGEN MONITORS (TAC NO. MC1900)
Dear Mr. Van Middlesworth:
In your letter of July 17, 2006 (ADAMS Accession No. ML062080521), you requested that the safety evaluation for Amendment No. 254 be corrected to include, in the commitment for oxygen monitoring equipment, the following language, (for post-accident monitoring function).
This letter responds to that request.
On June 10, 2004, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No.
254 to Facility Operating License DPR-49 for Duane Arnold Energy Center (DAEC). The Amendment consisted of changes to the DAEC Technical Specifications in response to an application letter from Nuclear Management Company, LLC (NMC) dated January 30, 2004 (ML040420424). Amendment No. 260, issued on January 27, 2006, transferred the DAEC license from NMC to FPL Energy Duane Arnold, LLC (FPL Energy).
In the application dated January 30, 2004, two new commitments were made; the second of which addressed the Oxygen Monitoring System. The application included site-specific information within Enclosure 1, Table 1, which contained a footnote (a) that applied to Monticello Nuclear Generating Plant (MNGP) and to DAEC. Footnote (a) clarified for both MNGP and DAEC, in part, that [o]nly the post-accident monitoring function will meet Regulatory Guide 1.97 and will be included in the Technical Requirements Manual [for DAEC]
or the Commitment Tracking Program [for MNGP]. DAEC implemented the change to its Technical Requirements Manual by modifying Table T3.3.3-1 on page 3.3-11.
The clarifying phrase (for post-accident monitoring function) should have been included in the safety evaluation (SE) Section 4.2 for DAEC Amendment No. 254, as it was in the SE Section 4.2 for MNGP Amendment No. 138 contained in the NRC letter dated May 21, 2004 (ML041180612), since both the DAEC and MNGP amendments were based on the same application dated January 30, 2004, and footnote (a) applied to the oxygen monitoring functions of both facilities. The NRC staff considers the omission to be an administrative error.
G. Van Middlesworth The enclosure provides a revised page 5 for the SE included in the NRC letter dated June 10, 2004. Please replace the current page 5 with the revised page 5.
Sincerely
/RA/
Karl Feintuch, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
Revised page 5 of Safety Evaluation for Amendment No. 254 cc w/encl: See next page
ML071300648 OFFICE LPL3-1/PM LPL3-1/LA OGC LPL3-1/BC NAME KFeintuch THarris BKlukan LRaghavan DATE 05/11/07 5/11/07 5/22/07 5/23/07 degradation of the reactor coolant pressure boundary. Oxygen monitors have not been shown by a probabilistic risk assessment to be risk-significant. Therefore, the staff finds that oxygen monitoring equipment requirements no longer meet any of the four criteria in 10 CFR 50.36(c)(2)(ii) for retention in TS and, therefore, may be relocated to other licensee-controlled documents.
However, for plant designs with an inerted containment, each licensee should verify that it has, and make a regulatory commitment to maintain, an oxygen monitoring system capable of verifying the status of the inert containment. In addition, separate requirements for primary containment oxygen concentration will be retained in TS for plant designs with an inerted containment. The basis for retention of this requirement in TS is that it meets Criterion 2 of 10 CFR 50.36(c)(2)(ii) in that it is a process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. This is based on the fact that calculations typically included in Chapter 6 of Updated Final Safety Analysis Reports assume that the primary containment is inerted, that is, oxygen concentration < 4.0 volume percent, when a design-basis LOCA occurs.
4.0 VERIFICATIONS AND COMMITMENTS As requested by the staff in the notice of availability for this TS improvement, the licensee has addressed the following plant-specific verifications and commitments.
4.1 Each licensee should verify that it has, and make a regulatory commitment to maintain, a hydrogen monitoring system capable of diagnosing beyond design-basis accidents.
The licensee has verified that it has a hydrogen monitoring system capable of diagnosing beyond design-basis accidents. The licensee has committed to maintain the hydrogen monitors within its Technical Requirements Manual. The licensee will implement this commitment as part of the implementation of the amendment.
4.2 For plant designs with an inerted containment, each licensee should verify that it has, and make a regulatory commitment to maintain, an oxygen monitoring system capable of verifying the status of the inert containment (for applicable plants).
The licensee has verified that it has an oxygen monitoring system capable of verifying the status of the inert containment (for post-accident monitoring function). The licensee l has committed to maintain the oxygen monitors within its Technical Requirements Manual. The licensee will implement this commitment as part of the implementation of the amendment.
The NRC staff finds that reasonable controls for the implementation and for subsequent evaluation of proposed changes pertaining to the above regulatory commitments are provided by the licensees administrative processes, including its commitment management program.
Should the licensee choose to incorporate a regulatory commitment into the emergency plan, final safety analysis report, or other documents with established regulatory controls, the associated regulations would define the appropriate change-control and reporting requirements.
Revised by NRC letter dated May 23, 2007
Duane Arnold Energy Center cc:
Mr. J. A. Stall U.S. Nuclear Regulatory Commission Senior Vice President, Nuclear and Chief Suite 210 Nuclear Officer 2443 Warrenville Road Florida Power & Light Company Lisle, IL 60532-4351 P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. Warner Vice President, Nuclear Operations, Mr. M. S. Ross North Region Managing Attorney Florida Power & Light Company Florida Power & Light Company P. O. Box 14000 P. O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Mr. D. A. Curtland Marjan Mashhadi Plant Manager Senior Attorney Duane Arnold Energy Center Florida Power & Light Company 3277 DAEC Rd.
801 Pennsylvania Avenue, NW Palo, IA 52324-9785 Suite 220 Washington, DC 20004 Mr. R. S. Kundalkar Vice President, Technical Services Mr. W. E. Webster Florida Power & Light Company Vice President, Nuclear Operations P. O. Box 14000 South Region Juno Beach, FL 33408-0420 Florida Power & Light Company P. O. Box 14000 Daniel K. McGhee Juno Beach, FL 33408-0420 Iowa Department of Public Health Bureau of Radiological Health John Bjorseth 321 East 12th Street Site Director Lucas State Office Building, 5th Floor Duane Arnold Energy Center Des Moines, IA 50319-0075 3277 DAEC Road Palo, IA 52324 Chairman, Linn County Board of Supervisors Steven R. Catron 930 1st Street SW Manager, Regulatory Affairs Cedar Rapids, IA 52404 Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 May 4, 2007 Palo, IA 52324 Regional Administrator, Region III