IR 05000250/2021010

From kanterella
Jump to navigation Jump to search
Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000250/2021010 and 05000251/2021010
ML21057A220
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 02/26/2021
From: James Baptist
NRC/RGN-II
To: Moul D
Florida Power & Light Co
References
IR 2021010
Download: ML21057A220 (10)


Text

February 26, 2021

SUBJECT:

TURKEY POINT UNITS 3 & 4 - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000250/2021010 AND 05000251/2021010

Dear Mr. Moul:

On February 5, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Turkey Point Units 3 & 4 and discussed the results of this inspection with Mr. Michael Pearce, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000250 and 05000251 License Nos. DPR-31 and DPR-41

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000250 and 05000251 License Numbers: DPR-31 and DPR-41 Report Numbers: 05000250/2021010 and 05000251/2021010 Enterprise Identifier: I-2021-010-0033 Licensee: Florida Power & Light Company Facility: Turkey Point Units 3 & 4 Location: Homestead, FL33035 Inspection Dates: February 01, 2021 to February 05, 2021 Inspectors: G. Ottenberg, Senior Reactor Inspector R. Patterson, Senior Reactor Inspector T. Su, Reactor Inspector Approved By: James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline inspection at Turkey Point Units 3 & 4, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from November 2017 to December 2020.

(1) 10 CFR 50.59 Evaluation - MSP-290605, Alternative Source Term Dose
Analysis:

Error in Concurrent Iodine Spike Cases, Revision 0

(2) 10 CFR 50.59 Evaluation - EC 290775, Wireless Infrastructure Project, Revision 3
(3) 10 CFR 50.59 Evaluation - EC 292163, Lap Patch and Nozzle Repair for N2 Nozzle on 3T201 (U3 PRT), Revision 1
(4) 10 CFR 50.59 Evaluation - EC 293042, Core Power Distribution Testing at 50% and 80 % Power, Revision 0
(5) 10 CFR 50.59 Evaluation - EC 294694, Add Code Boundary Change Designator "C" to "SR" Downstream of ICW Valves 3-50-406 and 3-50-407, Revision 0
(6) 10 CFR 50.59 Evaluation - EC 290017, Metal Shavings Collected from the CCW System, Revision 0
(7) 10 CFR 50.59 Screening - EC 241972, Revise MOV Open Torque Switch Bypass From 25% to 75%, Revision 2
(8) 10 CFR 50.59 Screening - EC 242266, ICW Pumps Discharge Check Valves Modification, Revision 0
(9) 10 CFR 50.59 Screening - EC 276212, Unit 3 Load Center 3B K-Line Breaker Replacement, Revision13
(10) 10 CFR 50.59 Screening - EC 283459, Protection of MCC 3B / 4B Power Cables in Fire Areas X and V with Thermo-Lag (NFPA 805), Revision 6
(11) 10 CFR 50.59 Screening - EC 285438, MOV-4-744B motor replacement, Revision 0
(12) 10 CFR 50.59 Screening - EC 287381, Unit 4 Sequencer Loop Test Switch, Revision
(13) 10 CFR 50.59 Screening - EC 292338, Reactor Coolant Pump Seal Faces Upgrade, Revision 2
(14) 10 CFR 50.59 Screening - PCR 2249587, 3/4-EOP-E-3, Steam Generator Tube Rupture, dated 2/22/2018
(15) 10 CFR 50.59 Screening - EC 285556, Modification of Inlet Pipe to RV-4-747A/B PTN-12-0005, Revision 1
(16) 10 CFR 50.59 Screening - EC 287848, Snubber Replacement in PT3-30 Fall 2018 Outage, Revision 20
(17) 10 CFR 50.59 Screening - EC 293317, SLR EQ DOC PAC Updated Part 3, Revision
(18) 10 CFR 50.59 Screening - EC 293978, Unit 3 Pressurizer Backup Heaters 3A & 3B Trip Blocks Removal, Revision 1
(19) 10 CFR 50.59 Screening - PCR 2231997, 0-ONOP-011.1 Intake Canal Low Level or High Temperature, Revision 13
(20) 10 CFR 50.59 Screening - PCR 2207808, 3/4-ONOP-075, Auxiliary feedwater System Malfunction, dated 3/13/2018

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On February 5, 2021, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Michael Pearce and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Corrective Action AR 1677185

Documents

71111.17T Corrective Action AR 2113436

Documents

71111.17T Corrective Action AR 2218430

Documents

71111.17T Corrective Action AR 2218437

Documents

71111.17T Corrective Action AR 2236913

Documents

71111.17T Corrective Action AR 2245071

Documents

71111.17T Corrective Action AR 2303446

Documents

71111.17T Corrective Action AR 2303447

Documents

71111.17T Corrective Action AR 2303452

Documents

71111.17T Corrective Action AR 404103

Documents

71111.17T Corrective Action AR 538249

Documents

71111.17T Corrective Action NAI NCR 2017-09 Errors Identified in Turkey Point AST Dose Analysis dated

Documents Calculations 01/15/2018

71111.17T Corrective Action AR 02383043 Prevention of CCW Hx Tube Cuttings/Shavings in System dated

Documents 02/04/2021

Resulting from

Inspection

71111.17T Corrective Action AR 02383083 ICW Code Classification Discrepancy dated

Documents 02/04/2021

Resulting from

Inspection

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Corrective Action AR 02383086 EC 276212 K-Line Breaker Replacement Project, New dated

Documents Breaker Response Time Issue 02/04/2021

Resulting from

Inspection

71111.17T Drawings 5610-M-65A-3- "Duo-Check" Check Valve General Assy. w/ 70-72 Deg. Rev. 0

SH3-EC242266, Open

Sht. 3

71111.17T Drawings 5613-E-25 Sh. 8A Reactor Auxiliaries Pressurizer Heater Backup Group Rev. 8

3ABreaker 30109

71111.17T Drawings 5613-M-3019, Intake Cooling Water System Rev. 41

Sht. 1

71111.17T Drawings 5613-M-3019, Intake Cooling Water System Rev. 32

Sht. 2

71111.17T Engineering EC 241972 Revise MOV Open Torque Switch Bypass From 25% to 75% Rev. 2

Changes

71111.17T Engineering EC 242266 ICW Pumps Discharge Check Valves Modification Rev. 4

Changes

71111.17T Engineering EC 276212 Unit 3 Load Center 3B K-Line Breaker Replacement Rev. 13

Changes

71111.17T Engineering EC 283459 Protection of MCC 3B / 4B Power Cables in Fire Areas X and Rev. 6

Changes V with Thermo-Lag (NFPA 805)

71111.17T Engineering EC 285438 MOV-4-744B motor replacement Rev. 2

Changes

71111.17T Engineering EC 287381 Unit 4 Sequencer Loop Test Switch Rev. 2

Changes

71111.17T Engineering EC 290775 Wireless Infrastructure Project Rev. 3

Changes

71111.17T Engineering EC 292163 LAP Patch and Nozzle Repair for N2 Nozzle On 3T201 (U3 Rev. 1

Changes PRT)

71111.17T Engineering EC 292338 Reactor Coolant Pump Flowserve Seal Face Upgrades Rev. 2

Changes

71111.17T Engineering EC 293042 Core Power Distribution Testing at 50% and 80% Power Rev. 0

Changes

71111.17T Engineering EC 293317 SLR EQ DOC PAC Updates Part 3 Rev. 2

Inspection Type Designation Description or Title Revision or

Procedure Date

Changes

71111.17T Engineering EC 293978 Unit 3 Pressurizer Backup Heaters 3A & 3B Trip Blocks Rev. 1

Changes Removal

71111.17T Engineering MSP-290605 Alternative Source Term Dose Analysis: Error in Concurrent Rev. 0

Changes Iodine Spike Cases

71111.17T Engineering PC/M 89-542 Drawing Update- ISI Quality Group Classifications / dated

Changes Boundaries 08/02/1994

71111.17T Engineering 475241 PE Characteristic Identification dated

Evaluations 05/10/18

71111.17T Engineering EC 276212 Evaluation of Proposed Micrologic 5.0A Trip Unit Settings Rev. 1

Evaluations Attachment 4

71111.17T Engineering JPE-LR-87-45 JCO of PTP Unit 3 for ICW System Design Rev. 3

Evaluations

71111.17T Engineering PSL-ENG-SEIJ- Verification and Validation of NLI Qualification Report QR- Rev. 0

Evaluations08-069 14010646-1 Appendix "F"

71111.17T Miscellaneous Letter to Mr.

G. Lear (AEC) from Mr. R. Uhrig (FPL), 'Failure dated

of Non-Seismic Equipment' 01/07/1975

71111.17T Miscellaneous Letter, to Mr. R. DeYoung (AEC) from Mr. R. Uhrig (FPL) dated

11/06/1972

71111.17T Miscellaneous 5610-019-DB-002 Intake Cooling Water System dated

04/20/2018

71111.17T Miscellaneous 5610-060-DB-001 Design Basis Document, Auxiliary Building Ventilation dated

System 06/10/2020

71111.17T Miscellaneous ML19064A903 TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 dated

AND 4 - ISSUANCE OF AMENDMENTS REGARDING 03/27/2019

TRANSITION LICENSE CONDITIONS FOR REACTOR

COOLANT PUMP SEALS (EPID L-2018-LLA-0280)

71111.17T Miscellaneous PCR 2207808 3/4-ONOP-075 - Auxiliary Feedwater System Malfunction dated

03/13/2018

71111.17T Miscellaneous PRS P074- NextEra Energy Plant Turkey Point 2017 Predictive Wireless Rev 1.2

111317 Survey and Design Document

71111.17T Miscellaneous SPEC-IC-104 Engineering Maintenance Specification for Business Rev. 2

Wireless Infrastructure

71111.17T Miscellaneous Specification No. Specifications for Cast Iron Pipe dated

Inspection Type Designation Description or Title Revision or

Procedure Date

5610-M-79 09/11/1967

71111.17T Miscellaneous WCAP-10217-A Relaxation of Constant Axial Offset Control- FQ Surveillance Rev. 1A

Technical Specification

71111.17T Procedures 0-ADM-561 Structures Monitoring Program Rev. 10

71111.17T Procedures 0-ADM-564 Systems / Programs Monitoring Rev. 7

71111.17T Procedures 3-EOP-E-3 Steam Generator Tube Rupture Rev. 11

71111.17T Procedures EN-AA-203-1102 Safety Classification Determination Rev. 7

71111.17T Procedures EN-AA-203-1201 10 CFR Applicability and 10 CFR 50.59 Screening Reviews Rev. 20

71111.17T Procedures EN-AA-205-1100 Design Change Packages Rev. 31

71111.17T Procedures EN-AA-205-1104 Standard Design Process Rev. 1

71111.17T Procedures ER-AA-118 ASME Section XI Inservice Inspection Program Rev. 6

71111.17T Procedures RP-AA-103-1008 Remote Monitoring Rev. 4

8