IR 05000250/2021012

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Biennial Problem Identification and Resolution Inspection Report 05000250/2021012 and 05000251/2021012
ML21125A227
Person / Time
Site: Turkey Point  
Issue date: 05/05/2021
From: David Dumbacher
NRC/RGN-II/DRP/RPB3
To: Moul D
Florida Power & Light Co
References
IR 2021012
Download: ML21125A227 (20)


Text

May 5, 2021

SUBJECT:

TURKEY POINT UNITS 3 & 4 - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000250/2021012 AND 05000251/2021012

Dear Mr. Moul:

On March 26, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Turkey Point Units 3 & 4 and discussed the results of this inspection with Mr. Michael Pearce and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.

Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.

Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

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/

David E. Dumbacher, Acting Chief Reactor Projects Branch 3 Division of Reactor Projects

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:

05000250/2021012 and 05000251/2021012

Enterprise Identifier: I-2021-012-0003

Licensee:

Florida Power & Light Company

Facility:

Turkey Point Units 3 & 4

Location:

Homestead, FL 33035

Inspection Dates:

March 08, 2021 to March 26, 2021

Inspectors:

A. Beasten PhD, Resident Inspector

A. Goldau, Operations Engineer

N. Pitoniak, Sr. Fuel Facility Project Inspector

R. Reyes, Resident Inspector

Approved By:

David E. Dumbacher, Chief

Reactor Projects Branch 3

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution 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.

OTHER ACTIVITIES - BASELINE

71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)

(1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.
  • Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a five-year review of the high head safety injection system and instrument air systems.
  • Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.
  • Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.

INSPECTION RESULTS

Assessment 71152B Corrective Action Program Assessment: Based on the samples reviewed, the team determined that the licensees corrective action program (CAP) complied with regulatory requirements and self-imposed standards. The licensees implementation of the CAP adequately supported nuclear safety.

Effectiveness of Problem Identification: The inspectors determined that the licensee was effective in identifying problems and entering them into the CAP at the appropriate threshold. This conclusion was based on a review of the requirements for initiating action requests (ARs) as described in licensee procedure PI-AA-104-1000, "Condition Reporting,"

and the site's management expectation that employees were encouraged to initiate condition reports. Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues. The inspectors reviewed ARs system health trending for Component Cooling Water Systems, High Head Safety Injection, Emergency Diesel Generators, and the Instrument Air System, and performed walkdowns of accessible portions of select systems. Based on the inspectors' reviews and walk downs, the inspectors determined that deficiencies were being identified and placed in the CAP.

Effectiveness of Problem Prioritization and Evaluation: Based on the review of ARs sampled by the inspection team during the onsite period, the inspectors concluded that problems were generally prioritized and evaluated in accordance with the AR significance determination guidance in procedure PI-AA-104-1000. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that plant personnel had generally conducted cause evaluations in compliance with the licensees CAP procedures, including appropriate cause determinations, and performed adequate levels of analysis based on the significance of the issues being evaluated.

Effectiveness of Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the inspectors determined that corrective actions were effective, timely, and commensurate with the safety significance of the issues. For significant conditions adverse to quality, the corrective actions directly addressed the cause and effectively prevented recurrence. The inspectors reviewed performance indicators, CRs, and effectiveness reviews, as applicable, to verify that the significant conditions adverse to quality had not recurred. Effectiveness reviews for corrective actions to preclude repetition (CAPRs) were sufficient to ensure corrective actions were properly implemented and were effective.

Assessment 71152B Operating Experience, Self-Assessments, and Audits: The inspectors examined the licensee's program for obtaining and using industry operating experience. This included a review of procedure PI-AA-102, "Operating Experience Program," selected corrective action program action requests, and the licensees operating experience (OE) database to assess the effectiveness of how external and internal OE data was evaluated at the plant. Additionally, the inspectors selected OE documents such as NRC generic communications, licensee event reports, vendor notifications, and plant internal OE items which had been issued since March 2019 to verify that the licensee had appropriately evaluated each notification for applicability to the station, and whether issues identified through these reviews were entered into the CAP.

The inspectors determined that the scopes of assessments and audits were adequate. Self-assessments were generally detailed and critical. The inspectors verified that ARs were created to document areas for improvement and findings resulting from self-assessments and verified that actions had been completed consistent with those recommendations. Audits of the quality assurance program appropriately assessed performance and identified areas for improvement. Generally, the licensee performed evaluations that were technically accurate.

The inspectors determined that the station's processes for the use of industry and NRC operating experience information and for the performance of audits and self-assessments were effective and complied with all regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The inspectors concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented to address lessons learned as needed. The inspectors determined that the licensee was effective at performing self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance.

Assessment 71152B Safety Conscious Work Environment: Based on a sample of at least 20 individuals interviewed from a cross-section of plant employees, the inspectors found no evidence of challenges to the safety conscious work environment. Employees interviewed appeared knowledgeable of avenues to raise safety concerns and appeared willing to raise nuclear safety concerns through at least one of the several means available.

EXIT MEETINGS AND DEBRIEFS

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

  • On March 26, 2021, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Michael Pearce and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Corrective Action

Documents

AR 2117406

AR 2200628

AR 2203822

AR 2213896

AR 2222114

AR 2237081

AR 2239727

AR 2264848

AR 2270832

AR 2272412

AR 2272881

AR 2272889

AR 2274559

AR 2276438

AR 2276852

AR 2280053

AR 2280239

AR 2280735

AR 2280767

AR 2281268

AR 2281271

AR 2282120

AR 2282440

AR 2284896

AR 2286774

AR 2289523

AR 2290554

AR 2291542

AR 2292076

AR 2292350

AR 2295122

AR 2295754

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AR 2296055

AR 2296056

AR 2296512

AR 2298655

AR 2298859

AR 2299807

AR 2300895

AR 2301281

AR 2303538

AR 2303820

AR 2303963

AR 2304807

AR 2304913

AR 2305193

AR 2305366

AR 2305543

AR 2305563

AR 2306492

AR 2306735

AR 2307666

AR 2307736

AR 2307809

AR 2307812

AR 2307812

AR 2308030

AR 2308244

AR 2310259

AR 2310652

AR 2311879

AR 2312024

AR 2312143

AR 2312394

AR 2312396

AR 2312778

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AR 2313132

AR 2313135

AR 2313778

AR 2315197

AR 2315745

AR 2316085

AR 2316914

AR 2316933

AR 2316960

AR 2317068

AR 2318579

AR 2319017

AR 2319908

AR 2319909

AR 2320056

AR 2320784

AR 2321107

AR 2321909

AR 2323634

AR 2323721

AR 2324077

AR 2324645

AR 2324645

AR 2326181

AR 2326781

AR 2327236

AR 2327449

AR 2327837

AR 2328013

AR 2328386

AR 2328799

AR 2329403

AR 2329979

AR 2330086

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AR 2330097

AR 2331221

AR 2331262

AR 2331477

AR 2331477

AR 2331776

AR 2333328

AR 2333615

AR 2333910

AR 2334407

AR 2334979

AR 2335236

AR 2335890

AR 2336036

AR 2336764

AR 2336802

AR 2339663

AR 2341929

AR 2342597

AR 2342702

AR 2343968

AR 2343970

AR 2343974

AR 2344584

AR 2344597

AR 2344617

AR 2344653

AR 2344656

AR 2344659

AR 2344692

AR 2345097

AR 2345574

AR 2346157

AR 2347144

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AR 2347374

AR 2347886

AR 2348216

AR 2349189

AR 2349247

AR 2352363

AR 2354304

AR 2354585

AR 2354610

AR 2354721

AR 2354721

AR 2354725

AR 2354733

AR 2354737

AR 2355161

AR 2355529

AR 2355762

AR 2355849

AR 2355926

AR 2356436

AR 2356436

AR 2356439

AR 2356750

AR 2356982

AR 2358488

AR 2359498

AR 2361794

AR 2361794

AR 2364641

AR 2364676

AR 2365288

AR 2365425

AR 2365707

AR 2365708

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AR 2365714

AR 2365716

AR 2365717

AR 2365722

AR 2365723

AR 2365970

AR 2366002

AR 2366093

AR 2366158

AR 2367875

AR 2367969

AR 2368902

AR 2369762

AR 2370137

AR 2370145

AR 2371379

AR 2373465

AR 2373717

AR 2376289

AR 2379516

AR 2379814

AR 2379864

AR 2379865

AR 2379866

AR 2379868

AR 2379869

AR 2379870

AR 2380481

AR 2380482

AR 2380655

AR 2380781

AR 2383376

AR 2384687

AR 2385185

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AR 2388109

71152B

Corrective Action

Documents

Resulting from

Inspection

AR 2388052

AR 2387275

71152B

Drawings

5613-M-3047

Chemical and Volume Control System

71152B

Miscellaneous

5610-019-DB-002

PTN Unit 3 and 4 Intake Cooling Water System Design

Requirements

71152B

Miscellaneous

LER 2020-001-00

Technical Specification Action Not Taken for Unrecognized

Inoperable Reactor Protection System (RPS) and

Engineered Safety Feature Actuation System (ESFAS)

Instrument Channel.

6/24/2020

71152B

Miscellaneous

LER 2020-002-00

Manual Reactor Trip in Response to High Steam Generator

Level following Inadvertent Opening of Feedwater Heater

Bypass Valve

9/23/2020

71152B

Miscellaneous

LER 2020-003-00

Automatic Reactor Trip due to High Source Range Flux

during Reactor Startup

9/29/2020

71152B

Miscellaneous

LER 2020-004-00

Manual Reactor Trip from 34% Power in Response to

Automatic Trip of the 3B Steam Generator Feedwater Pump

71152B

Miscellaneous

LER 2020-005-00

POR determined N-3-32 inoperable since 4/1/2020 (PT3-31

shutdown)

71152B

Miscellaneous

PTN Unit 3 and 4

Equipment

Qualification

Documentation

Package 1001

Treatment of Issues

71152B

Miscellaneous

PTN Unit 3 and 4

Equipment

Qualification

Documentation

Package 14.1

Nutherm Starters

71152B

Procedures

0-ADM-016

Fire Protection Program

71152B

Procedures

0-ADM-032

NRC Performance Indicators Turkey Point

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Procedures

0-ADM-051

Outage Risk Assessment and Control

71152B

Procedures

0-ADM-211

Emergency And Off-Normal Operating Procedure Usage

71152B

Procedures

0-ADM-225

On Line Risk Assessment and Management

71152B

Procedures

0-ADM-511

Post Trip Review (PTR)

71152B

Procedures

0-ADM-561

Structures Monitoring Program

71152B

Procedures

3-EOP-FR-H.1

Response To Loss Of Secondary Heat Sink

71152B

Procedures

3-GOP-100

Fast Load Reduction

71152B

Procedures

3-GOP-103

Power Operation to Hot Standby

71152B

Procedures

3-NOP-040.02

Refueling Core Shuffle

71152B

Procedures

3-NOP-040.03

Fuel Handling And Insert Shuffle In The Spent Fuel Pit

71152B

Procedures

3-NOP-075

Auxiliary Feedwater System Malfunction

71152B

Procedures

3-OSP-023.1

Diesel Generator Operability Test

71152B

Procedures

3-OSP-047.2

3-312A, 3-312B, and 3-312C Inservice Test

71152B

Procedures

3-OSP-206.2

Quarterly Inservice Valve Testing

71152B

Procedures

3-PMI-059.36

PRNI Protection set II channel N-42 Installation of new

current and streaming constant at shutdown

71152B

Procedures

4-ONOP-004.2

Loss of 4A 4KV Bus

71152B

Procedures

4-ONOP-067

Radioactive Effluent Release

71152B

Procedures

AD-AA-100-1004

Preparation, Revision, Review / Approval of Procedures

71152B

Procedures

AD-AA-100-1004

71152B

Procedures

BO-AA-103-1001-

10003

Long Term Asset Management Entries

71152B

Procedures

BO-AA-103-1002

Nuclear Fleet Long Range Planning

71152B

Procedures

EN-AA-203-1001

Operability Determinations/Functionality Assessments

71152B

Procedures

EP-AA-1001

Nuclear Division Pandemic Influenza Procedure

71152B

Procedures

ER-AA-100-1002

Maintenance Rule Program Administration

71152B

Procedures

ER-AA-101

Equipment Reliability

71152B

Procedures

ER-AA-113

Inservice Testing (IST) Program

71152B

Procedures

ER-AA-113-1001-

10000

Evaluation Guidelines for Relief Valve Failures

71152B

Procedures

ER-AA-201-2001

System and Program Health Reporting

71152B

Procedures

ER-AA-201-2002

System Performance Monitoring

71152B

Procedures

EVT-050-2020-

Maintenance Rule Functional Failure Assessment

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

39591

71152B

Procedures

MA-AA-100

Conduct of Maintenance

71152B

Procedures

MA-AA-100-1002

Scaffold Installation, Modification, Fleet Scaffold

71152B

Procedures

MA-AA-204-1000

Preventative Maintenance and Surveillance Procedure

71152B

Procedures

MTG-PTN-2020-

263

Maintenance Rule Meeting Minutes

71152B

Procedures

OP-AA-100-1000

Conduct of Operations

71152B

Procedures

PI-AA-100-1000

Level 2 Independent Assessment Planning, Conduct, and

Reporting

71152B

Procedures

PI-AA-100-1005

Root Cause Analysis

71152B

Procedures

PI-AA-100-1006

Common Cause Evaluation

71152B

Procedures

PI-AA-100-1007

Issue Investigation

71152B

Procedures

PI-AA-101

Assessment and Improvement Programs

71152B

Procedures

PI-AA-101-1001

Level 1 Core Business Assessments

71152B

Procedures

PI-AA-102

Operating Experience Program

71152B

Procedures

PI-AA-102-1001

Operating Experience Program Screening and Responding

to Incoming Operating Experience

71152B

Procedures

PI-AA-104-1000

Condition Reporting

71152B

Self-Assessments 2345097-01 HU

Investigation

SDTC Runback

HU Error

Human Performance Investigation checklist

rev 042929

71152B

Self-Assessments AR 2356982

Escalation

Closure Package

PTN Organizational Effectiveness Fleet Escalation Closure

Report

71152B

Self-Assessments CR 2356982

Organizational

Effectiveness

Investigation

Checklist

Fleet Level Escalation (OP - ER station overall performance)

05/18/20

71152B

Self-Assessments Effectiveness

Review

Effectiveness Review - PTN escalation of OPS human

performance

final

71152B

Self-Assessments L1A 2282508

Level 1 Core Business Assessment - Review of NRC NCV

with Cross Cutting Aspect P.1

6/23/18 -

6/25/18

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Self-Assessments L1A 2338196

Level 1 Core Business Assessment - 4Q2020 Trend Review

Operations

10/1/20 -

2/31/20

71152B

Self-Assessments L1A 2338196

Level 1 Core Business Assessment - 4Q20 Operations Trend 10/1/20 -

2/31/20

71152B

Self-Assessments L1A 2364676

Level 1 Core Business Assessment - PTN H.12 Cross-cutting

Aspect

undated

71152B

Self-Assessments L2A 02374396

Nuclear Safety Culture Assessment

05/18/20 -

05/30/20 and

10/27/20 -

11/3/20

71152B

Self-Assessments Operations

Improvement

GADR Gaps 1-2

status report

Operations Improvement GADR Gaps 1-2 status report

updated

3/12/21

71152B

Self-Assessments PI-AA-100-1005-

F04

Effectiveness Review of DLAs

71152B

Self-Assessments PTN-17-008

Nuclear

Assurance Report

Turkey Point Nuclear Assurance Report - Audit, Performance

Improvement

01/17/18

71152B

Self-Assessments PTN-19-002

Nuclear

Assurance Report

Turkey Point Nuclear Assurance Report - Audit, QA

Programs and Records Management

3/30/19

71152B

Self-Assessments PTN-20-005

Nuclear

Assurance Report

Turkey Point Nuclear Assurance Report - Audit, Operations

07/13/20

71152B

Work Orders

WO 40199508

WO 40201076

WO 40570266

WO 40583625

WO 40624125

WO 40649312

WO 40654613

WO 40656961

WO 40660975

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

WO 40660975

WO 40665245

WO 40666137

WO 40683334

WO 40690186

WO 40699342