IR 05000335/2020011

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Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000335/2020011 and 05000389/2020011
ML20351A316
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
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

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

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.17T Calculations

2-9165570-002

St. Lucie 1 EPU - CVCS Malfunction Analysis

Rev. 21

HI-2094395

Bulk Thermal Analyses for St. Lucie Unit 2 Spent Fuel Pool

with Extended Reactor Power Uprate (EPU)

Rev. 8

NAI-1421-204

St. Lucie Unit 2 EPU Steam Generator Tube Rupture AST

Radiological Analysis

Rev. 2

NAI-1421-211

St. Lucie Unit 2 EPU Letdown Line Break Outside

Containment AST Radiological Analysis

Rev. 2

PSL-1-F-J-E-90-

0013

St. Lucie Unit 1 Emergency Diesel Generator 1A and 1B

Electrical Loads

Rev. 9

PSL-1FJF-19-074

St. Lucie Cycle 29 Reload EC - Groundrules

Rev. 0

PSL-1OHC-16-

001

Qualification of Unit 1 Intake Structure FlexRake Support

Frame

Rev. 1

PSL-BFSM-15-

2

Hydraulic Analysis for RAB Floor Drains - Orifice Sizing

Rev. 0

SPL-1FSE-18-

001

St. Lucie Unit 1 EDG Dynamic Transient Analysis

Rev. 0

Corrective Action

Documents

AR 02285892

AR 02290545

CR-2018-10210

CR-2019-955

Corrective Action

Documents

Resulting from

Inspection

AR 2376210

20 5059 Audit NRC Obs-Tubing in Unit 1 Chg Pp

Cubicles

dated

11/19/2020

AR 2376227

20 50.59 Audit Actions Related to Biasi DNB Correlation

LI NRC ID'ed

dated

11/19/2020

Drawings

2770-B-231 Sht.

21-12

Instrument Installation Details

Rev. 2

2998-9312-

EC285232, Sht. 7

RTG Board 205 Wiring Diagram

Rev. 1

2998-9315-

EC285232, Sht.

RTG Board 205 Wiring Diagram

Rev. 1

2998-B-327-

Charging Pump 2B Bypass Valve V-2554

Rev. 1

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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.

A

Index Symbols, Abbreviations One Line Wiring Diagrams &

Reference Drawings

Rev. 8

8770-B-231 Sht.

21-12

Instrument Installation Details

Rev. 3

8770-B-231 Sht.21-12A

Instrument Installation Details

Rev. 0

8770-B-327 Sht.

1007

Misc. Annunciators - RTGB-102

Revs. 10 &

8770-B-327 Sht.

149

Chemical and Volume Control Annunciator-M SH.2 RTGB-

105

Revs. 17 &

8770-B-327 Sht.

841

Circulating Intake & Cooling Water Annunciator-E SH. 1

RTGB-102

Revs. 20 &

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

Drainage

Rev. 11

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Engineering

Changes

EC-285232

Revise U2 Charging Pump 2B SIAS Circuit

Rev. 2

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

Breakers

Rev. 0

EC276197

Design Change Package Description

Rev. 3

EC284322

Design Change Package Form PSL U1 ECCS A & B

Radiation Monitor Replacement

Rev. 4

EC288327

Replace Unit 2 Neutron Detector # 8

Rev. 0

EC289683

St. Lucie Unit 1 Hot Leg Injection Implementation

Documentation

Rev. 3

Engineering

Evaluations

2998-20831

Seismic Qualification Report for U.I.C. Excore Detector

Rev. 0

EC 284073

SW Coarse Screen Trough Pipe orifice Sizing Evaluation

dated

06/27/2016

EC 284073

14

Intake Bay Level Sensor Evaluation

dated

06/27/2016

EC284073

28

Evaluation of Rake System Impact to Coarse Screen Head

Loss

dated

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-

2-006

St. Lucie Unit 2 Control Element Assembly (CEA) Lifetime

Determination

Rev. 4

PSL-ENG-SEIS-

01-046

Emergency Operating Procedure Setpoint Basis Document

Rev. 8

PSL-ENG-SEMS-

2-006

Operator Action Times in the UFSAR PSL-ENG-SEMS-12-

006

Rev. 5

Miscellaneous

ADAMS

ML101160223, L-

2010-078

License Amendment Request Extended Power

Uprate Licensing Report Florida Power & Light St. Lucie

Nuclear Plant, Unit 1

dated

04/16/2010

ADAMS

ML12058A276

Safety Evaluation for License Amendment Request for

Extended Power Uprate St. Lucie Plant Unit 1, Facility

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

dated

03/15/2012

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

No. ME5091)

ADAMS

ML12156A208

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

Extended Power Uprate (TAC No, ME5091)

dated

07/09/2012

ANP-3000(P)

St. Lucie Unit 1 EPU - Information to Support License

Amendment Request

Rev. 0

EMF-2310(P)(A)

SRP Chapter 15 Non-LOCA Methodology for Pressurized

Water Reactors

Rev. 1

PSL-ENG-SENS-

00-108

EC 280623 Safety Evaluation 2000 FSAR Review Findings

Requiring Changes or Clarifications to the FSARs in

accordance with 10 CFR 50.59

Rev. 1

St. Lucie Unit 2

Updated Final

Safety Analysis

Report

Chapters 10 and 15

Rev. 26

XN-NF-82-21

(P)(A)

Application OF Exxon Nuclear Company PWR Thermal

Margin Methodology to Mixed Core Configurations

Rev. 1

Procedures

1-ADM-09.23

Time Critical Operator Actions and Time Sensitive Actions

Program

Rev. 19

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

Program

Rev. 19

Work Orders

40468251