IR 05000335/2020011

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000335/2020011 and 05000389/2020011

ML20351A316
Person / Time
Site:	Saint Lucie
Issue date:	12/16/2020
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Moul D Florida Power & Light Co
References
IR 2020011
Download: ML20351A316 (10)

Text

December 16, 2020

SUBJECT:

ST. LUCIE UNITS 1 & 2 - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000335/2020011 AND 05000389/2020011

Dear Mr. Moul:

On November 20, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at St. Lucie Units 1 & 2 and discussed the results of this inspection with Mr. Dan DeBoer 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 Paul Carmen acting for/

James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000335 and 05000389 License Nos. DPR-67 and NPF-16

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000335 and 05000389 License Numbers: DPR-67 and NPF-16 Report Numbers: 05000335/2020011 and 05000389/2020011 Enterprise Identifier: I-2020-011-0020 Licensee: Florida Power & Light Company Facility: St. Lucie Units 1 & 2 Location: Jensen Beach, FL 34957 Inspection Dates: November 16, 2020 to November 20, 2020 Inspectors: M. Greenleaf, Reactor Inspector A. Lerch, Reactor Inspector N. Morgan, Reactor Inspector G. Ottenberg, Senior 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 St. Lucie Units 1 & 2, 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 October 2020.

(1) 10 CFR 50.59 Screening - EC284322, PSL U1 ECCS A & B Radiation Monitor Replacement, Rev. 0

(2) 10 CFR 50.59 Evaluation - EC289683, Rev 0 PSL-ENG-SENS-15-001, St. Lucie Unit 1 Hot Leg Injection Implementation Documentation, Rev. 1

(3) 10 CFR 50.59 Evaluation - EC290539, Unit 2 UFSAR Changes for Section 15.6 due to Vendor Error, Rev. 0

(4) 10 CFR 50.59 Evaluation - EC291265, St. Lucie Unit 2 SFP Improved Offload Timing, Rev. 0

(5) 10 CFR 50.59 Evaluation - EC292529, St. Lucie Unit 1 Cycle 29 Reload EC, Rev. 0

(6) 10 CFR 50.59 Evaluation - EC292636, PSL Unit 2, Fuel Transition Non-LOCA Events UFSAR Changes, Rev. 0

(7) 10 CFR 50.59 Evaluation - EC292761, St. Lucie Unit 1 UFSAR Changes due to the non-conservatism associated with the Modified Barnett CHF Correlation in the MSLB analysis, Rev. 0

(8) 10 CFR50.59 Screening - EC276197, Charging Pump Recirculation Line Removal, Rev. 0

(9) 10 CFR 50.59 Screening - EC281755, U1 Install Mesh Liners and Restriction Orifices for RAB Floor Drain Lines to ECCS Pump Rooms AR 01954945-07, Rev. 0

(10) 10 CFR 50.59 Screening - EC284073, U1 Intake Coarse Screen Rake, Rev. 1

(11) 10 CFR 50.59 Screening - EC285232, Revise the Charging Pump 2B Control Circuitry Associated with SIAS, Rev. 1

(12) 10 CFR 50.59 Screening - EC288327, Replace Unit 2 Neutron Detector #8, Rev. 0

(13) 10 CFR 50.59 Screening - EC288458, PSL1 EDG Load Calc (Calc PSL-1-F-J-E-90-0013) Full Revision to Update & Change to EDG Steady-State Loading Profile Analysis Only, Rev. 0

(14) 10 CFR 50.59 Screening - EC293411, U2 Pressurizer Code Safety Valve Blowdown Change to 10%, Rev. 0

(15) 10 CFR 50.59 Applicability Determination - EC235891, PCM-08058 Unit 1 CROAI Radiation Monitor Channels 46 & 47 Replacement for AST, Rev. 1

(16) 10 CFR 50.59 Applicability Determination - EC290638, St. Lucie Unit 1 EDG Dynamic Transient Analysis, Rev. 0

(17) 10 CFR 50.59 Applicability Determination - EC292581, Action Plans for Failed Closed Generator Connected Circuit Breakers, Rev. 0

(18) 10 CFR 50.59 Applicability Determination - EC294419, St. Lucie Unit 2 Control Element Assembly (CEA) Lifetime Determination, Rev.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On November 20, 2020, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Dan DeBoer and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations 32-9165570-002 St. Lucie 1 EPU - CVCS Malfunction Analysis Rev. 21

HI-2094395 Bulk Thermal Analyses for St. Lucie Unit 2 Spent Fuel Pool Rev. 8

with Extended Reactor Power Uprate (EPU)

NAI-1421-204 St. Lucie Unit 2 EPU Steam Generator Tube Rupture AST Rev. 2

Radiological Analysis

NAI-1421-211 St. Lucie Unit 2 EPU Letdown Line Break Outside Rev. 2

Containment AST Radiological Analysis

PSL-1-F-J-E-90- St. Lucie Unit 1 Emergency Diesel Generator 1A and 1B Rev. 9

0013 Electrical Loads

PSL-1FJF-19-074 St. Lucie Cycle 29 Reload EC - Groundrules Rev. 0

PSL-1OHC-16- Qualification of Unit 1 Intake Structure FlexRake Support Rev. 1

001 Frame

PSL-BFSM-15- Hydraulic Analysis for RAB Floor Drains - Orifice Sizing Rev. 0

2

SPL-1FSE-18- St. Lucie Unit 1 EDG Dynamic Transient Analysis Rev. 0

001

Corrective Action AR 02285892

Documents AR 02290545

CR-2018-10210

CR-2019-955

Corrective Action AR 2376210 2020 5059 Audit NRC Obs- Tubing in Unit 1 Chg Pp dated

Documents Cubicles 11/19/2020

Resulting from AR 2376227 2020 50.59 Audit Actions Related to Biasi DNB Correlation dated

Inspection LI NRC ID'ed 11/19/2020

Drawings 2770-B-231 Sht. Instrument Installation Details Rev. 2

21-12

2998-9312- RTG Board 205 Wiring Diagram Rev. 1

EC285232, Sht. 7

2998-9315- RTG Board 205 Wiring Diagram Rev. 1

EC285232, Sht.

2998-B-327- Charging Pump 2B Bypass Valve V-2554 Rev. 1

Inspection Type Designation Description or Title Revision or

Procedure Date

SH.197-

EC285232, Sht.

197

2998-G-272 Main One Line Wiring Diagram Rev. 33

2998-G-274 Auxiliary One Line Diagram, Sht. 1 Rev. 19

2998-G-274, Sht. Auxiliary One Line Diagram Rev. 19

2998-G-274, Sht. Auxiliary One Line Diagram Rev. 10

2998-G-275, Sht. 6.9kV Switchgear No. 2A1 and No. 2B1 One Line Diagrams Rev. 15

2998-G-275, Sht. 4.16kV Switchgear No. 2A2 and No. 2B2 One Line Diagrams Rev. 5

2998-G-275, Sht. 4.16kV Switchgear No. 2A3 and 2B3 One Line Diagrams Rev. 9

2998-G-275, Sht. Index Symbols, Abbreviations One Line Wiring Diagrams & Rev. 8

A Reference Drawings

8770-B-231 Sht. Instrument Installation Details Rev. 3

21-12

8770-B-231 Sht. Instrument Installation Details Rev. 0

21-12A

8770-B-327 Sht. Misc. Annunciators - RTGB-102 Revs. 10 &

1007 11

8770-B-327 Sht. Chemical and Volume Control Annunciator- M SH.2 RTGB- Revs. 17 &

149 105 18

8770-B-327 Sht. Circulating Intake & Cooling Water Annunciator- E SH. 1 Revs. 20 &

841 RTGB-102 21

8770-C-453 Emergency Diesel Generator 1A/1B Load List Rev. 11

8770-G-093 Flow Diagram Miscellaneous Systems Revs. 42 &

8770-G-385 Intake Structure Conduit and Lighting Revs. 27 &

8770-G899 Turbine Building Riser Diagram and Details Plumbing and Rev. 11

Drainage

Inspection Type Designation Description or Title Revision or

Procedure Date

Engineering EC-285232 Revise U2 Charging Pump 2B SIAS Circuit Rev. 2

Changes EC-288458 Full Revision of Unit 1 EDG Load Calculation Rev. 0

EC-290638 St. Lucie Unit 1 EDG Dynamic Transient Analysis Rev. 0

EC-291265 St. Lucie Unit 2 SFP Improved Offload Timing Rev. 0

EC-292529 St. Lucie Unit 1 Cycle 29 Reload EC Rev. 2

EC-292581 Action Plans for Failed Closed Generator Connected Circuit Rev. 0

Breakers

EC276197 Design Change Package Description Rev. 3

EC284322 Design Change Package Form PSL U1 ECCS A & B Rev. 4

Radiation Monitor Replacement

EC288327 Replace Unit 2 Neutron Detector # 8 Rev. 0

EC289683 St. Lucie Unit 1 Hot Leg Injection Implementation Rev. 3

Documentation

Engineering 2998-20831 Seismic Qualification Report for U.I.C. Excore Detector Rev. 0

Evaluations EC 284073 SW Coarse Screen Trough Pipe orifice Sizing Evaluation dated

06/27/2016

EC 284073 Intake Bay Level Sensor Evaluation dated

14 06/27/2016

EC284073 Evaluation of Rake System Impact to Coarse Screen Head dated

28 Loss 07/27/2016

EC293944 St. Lucie Unit 2 Cycle 25 Reload EC Rev. 1

FS1-0041392 St. Lucie Unit 2 CEA Compatibility Evaluation Rev. 1

PSL-ENG-SEFJ- St. Lucie Unit 2 Control Element Assembly (CEA) Lifetime Rev. 4

2-006 Determination

PSL-ENG-SEIS- Emergency Operating Procedure Setpoint Basis Document Rev. 8

01-046

PSL-ENG-SEMS- Operator Action Times in the UFSAR PSL-ENG-SEMS-12- Rev. 5

2-006 006

Miscellaneous ADAMS Attachment 5 License Amendment Request Extended Power dated

ML101160223, L- Uprate Licensing Report Florida Power & Light St. Lucie 04/16/2010

2010-078 Nuclear Plant, Unit 1

ADAMS Safety Evaluation for License Amendment Request for dated

ML12058A276 Extended Power Uprate St. Lucie Plant Unit 1, Facility 03/15/2012

Operating License No. DPR-67, Docket No. 50-335 (TAC

Inspection Type Designation Description or Title Revision or

Procedure Date

No. ME5091)

ADAMS St. Lucie Plant, Unit 1 - Issuance of Amendment Regarding dated

ML12156A208 Extended Power Uprate (TAC No, ME5091) 07/09/2012

ANP-3000(P) St. Lucie Unit 1 EPU - Information to Support License Rev. 0

Amendment Request

EMF-2310(P)(A) SRP Chapter 15 Non-LOCA Methodology for Pressurized Rev. 1

Water Reactors

PSL-ENG-SENS- EC 280623 Safety Evaluation 2000 FSAR Review Findings Rev. 1

00-108 Requiring Changes or Clarifications to the FSARs in

accordance with 10 CFR 50.59

St. Lucie Unit 2 Chapters 10 and 15 Rev. 26

Updated Final

Safety Analysis

Report

XN-NF-82-21 Application OF Exxon Nuclear Company PWR Thermal Rev. 1

(P)(A) Margin Methodology to Mixed Core Configurations

Procedures 1-ADM-09.23 Time Critical Operator Actions and Time Sensitive Actions Rev. 19

Program

1-ARP-01-E00 Control Room Panel E RTGB-102 Rev. 46

1-ARP-01-M00 Control Room Panel M RTGB-105 Rev. 42

1-NOP-21.15 Intake Intrusion Monitoring and Mitigation Rev. 15

2-ADM-09.23 Time Critical Operator Actions and Time Sensitive Actions Rev. 19

Program

Work Orders 40468251

8