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| {{#Wiki_filter:July 15, 2021 Mr. Bob Coffey Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd. | | {{#Wiki_filter:}} |
| Juno Beach, FL 33408
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| ==SUBJECT:==
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| TURKEY POINT NUCLEAR GENERATING STATION - NOTIFICATION OF SUPPLEMENTAL INSPECTION (95001) AND REQUEST FOR INFORMATION
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| ==Dear Mr. Coffey:==
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| By {{letter dated|date=May 7, 2021|text=letter dated May 7, 2021}}, (ADAMS Accession No. ML21127A186), the U.S. Nuclear Regulatory Commission (NRC) communicated to you that our review identified that the Unplanned Scrams per 7000 Critical Hours performance indicator had crossed the green-to-white threshold. This was due to four unplanned scrams that occurred on August 17, 2020, August 19, 2020, August 20, 2020, and March 1, 2021.
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| On May 20, 2021, we were notified by your staff that you were ready for the NRC to conduct our supplemental inspection to review the actions taken to address the White performance indicator.
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| Accordingly, we plan to conduct a supplemental inspection, beginning on August 16, 2021, at the Turkey Point Nuclear Generating Station using Inspection Procedure 95001, Supplemental Inspection Response To Action Matrix Column 2 (Regulatory Response) Inputs (ADAMS Accession No. ML19179A011). This on-site inspection is scheduled to be performed August 16 through August 20, 2021.
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| In order to minimize the impact to your on-site resources and to ensure a productive inspection for both organizations, we have enclosed a request for documents needed for this inspection.
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| The documents identified are those that the inspectors will need prior to and upon arrival at the site. It is important that all of these documents are up-to-date and complete in order to minimize the number of additional documents requested during the on-site portion of the inspection.
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| We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. Bob Murrell of your organization. If there are any questions about this inspection or the material requested, please call or email Mr.
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| Wilson at 404-997-4574 or adam.wilson@nrc.gov.
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| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
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| B. Coffey 2 Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Mr. Wilson at (404) 997-4574 or the resident inspectors.
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| Sincerely,
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| /RA/
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| David Dumbacher, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 05000250 and 05000251 License Nos. DPR-31 and DPR-41
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| ==Enclosure:==
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| Information Request for Turkey Point 95001 Inspection cc: Distribution via ListServ PAPERWORK REDUCTION ACT STATEMENT This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011.
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| PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
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| ML21196A104 x Non-Sensitive x Publicly Available x SUNSI Review Sensitive Non-Publicly Available OFFICE RII/DRP RII/DRP NAME A. Wilson D. Dumbacher DATE 7/7/2021 7/15/2021 4
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| INFORMATION REQUEST FOR TUREKY POINT 95001 INSPECTION (AUGUST 16-20, 2021)
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| Please assemble the following documents and provide them to the inspector on or before August 2, 2021. Please provide the requested documents in electronic format. If the information is not available in electronic format, please contact the inspection team leader to coordinate other available methods to provide the information. Information provided onsite should be the latest approved documentation. Proprietary information and security related information should be clearly marked. Draft documentation should not be provided as part of this information request.
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| : 1. Administrative procedures governing the sites corrective action program, including:
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| a) The identification and resolution of problems; b) Root cause, apparent cause and other types of causal evaluations; and c) Common cause assessments, effectiveness reviews, and self-assessments.
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| : 2. The causal evaluation report(s) and associated documents for the white performance issue.
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| : 3. All corrective actions implemented for the white performance issue:
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| a) Documentation supporting completion of any corrective actions; and b) Current schedule and resource commitments for open corrective actions.
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| : 4. The evaluation of the extent of condition and extent of cause of the white performance issue.
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| : 5. Ongoing, planned, or completed effectiveness reviews associated with the implemented corrective actions.
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| : 6. Results of any effectiveness reviews, audits, self-assessments, mock inspections, etc. used to validate preparation for the inspection.
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| : 7. If applicable, any evaluations of the effectiveness of previous corrective actions to prevent recurrence.
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| : 8. Corrective action documents generated as a result of the NRC Special Inspection associated with the August 2020 reactor trips (Inspection Report 05000250/2020050 and 05000251/2020050).
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| Enclosure
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| 5
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| : 9. Corrective action documents generated as a result of the March 1, 2021 reactor trip.
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| : 10. Copies of Licensee Event Reports (LERs) issued as a result of the white performance issue.
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| : 11. Drawings, System Description, and Plant Procedures associated with the Turbine Control System and Feedwater Control System.
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| : 12. Plant Procedures:
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| * 3-ARP-097.CR.C, Annunciator Response Procedure Control Room Response - Panel C
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| * 3-ARP-097.CR.D, Annunciator Response Procedure Control Room Response - Panel D
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| * 3-EOP-E-0, Reactor Trip or Safety Injection
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| * 3-EOP-ES-0.1, Reactor Trip Response
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| * 3-GOP-103, Power Operation to Hot Standby
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| * 3-GOP-301, Hot Standby to Power Operations, completed for 8-19-20 startup
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| * 3-ONOP-089, Turbine Runback
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| * EN-AA-205-1100, Design Change Packages
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| * ENG-QI-1.5, Calculations
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| * LI-AA-1000, On-Site Review Group
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| * OP-AA-1000, Conduct of Infrequently Performed Tests or Evolutions
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| * OP-AA-100-1000, Conduct of Operations
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| * OP-AA-103-1000, Reactivity Management
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| : 13. Engineering Change Documents:
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| * EC-246849, Turbine Digital Control System
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| * EC-246870, Design Change Package
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| == Description:==
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| Feedwater Regulating Valve Upgrade
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| * EC-246935, Main Feedwater Pump Rotating Assembly Replacement - Extended Power Uprate
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| * EC-295196, Temporary Modification Change: Disable Unit 3 Medium Runback on CV 2011}}
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