IR 05000440/2019002

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Integrated Inspection Report 5000440/2019002
ML19210D576
Person / Time
Site: Perry 
Issue date: 07/26/2019
From: Chuck Norton
NRC/RGN-III/DRP/B2
To: Payne F
FirstEnergy Nuclear Operating Co
References
IR 2019002
Download: ML19210D576 (12)


Text

July 26, 2019

SUBJECT:

PERRY NUCLEAR POWER PLANTINTEGRATED INSPECTION REPORT 05000440/2019002

Dear Mr. Payne:

On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Perry Nuclear Power Plant. On July 17, 2019, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Charles H. Norton, Acting Chief Branch 2 Division of Reactor Projects

Docket No. 05000440 License No. NPF-58

Enclosure:

As stated

Inspection Report

Docket Number:

05000440

License Number:

NPF-58

Report Number:

05000440/2019002

Enterprise Identifier: I-2019-002-0056

Licensee:

FirstEnergy Nuclear Operating Company

Facility:

Perry Nuclear Power Plant

Location:

Perry, OH

Inspection Dates:

April 01, 2019 to June 30, 2019

Inspectors:

T. Briley, Senior Resident Inspector

J. Nance, Resident Inspector

J. Rutkowski, Project Engineer

J. Steffes, Senior Resident Inspector

Approved By:

Charles H. Norton, Acting Chief

Branch 2

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Perry Nuclear Power Plant 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.

PLANT STATUS

The plant began the inspection period shutdown for refueling outage (RFO) 1R17. On April 5, 2019, at 5:16 a.m., the plant was placed in startup mode and achieved criticality at 7:25 a.m. that same day. On April 6, 2019, at 11:59 p.m., the main generator was synchronized to the grid. On April 7, 2019, at 2:44 a.m., the main generator was removed from the grid due to hydraulic oil intrusion into the generator casing. On April 7, 2019, at 5:44 p.m., after correcting the cause of the oil intrusion to the generator casing, the main generator was synchronized to the grid. The plant reached 100 percent power on April 11, 2019. On April 27, 2019, the licensee reduced reactor power to 60 percent in order to correct balance of plant steam leaks.

The licensee resumed 100 percent power operations that same day. On May 31, 2019, the licensee commenced power reduction to 13 percent reactor power and removed the main generator from the grid on June 1, 2019. On June 2, 2019, following repairs to the number four turbine stop valve, the licensee synchronized the main generator to the grid at 1:43 a.m. and commenced power ascension. The licensee returned the plant to 100 percent power on June 4, 2019. The reactor remained at approximately 100 percent power for the remainder of the inspection period except for rod sequence exchanges and required testing.

On April 25, 2018, FirstEnergy Solutions (FES) / FirstEnergy Nuclear Operating Company (FENOC) notified the U.S. Nuclear Regulatory Commission (NRC) that they intend to shut down all four of their operating nuclear power plants (ADAMS Accession Number ML18115A007).

Perry Nuclear Power Plant, Unit 1, is scheduled to be shut down May 31, 2021. On March 21, 2018, FES, FirstEnergy Nuclear Generation (FENGEN), and FENOC filed for bankruptcy. The NRC continues to maintain focus on public health and safety and the protection of the environment. This will include a continuous evaluation by inspectors to determine whether the licensee's financial condition is impacting safe operation of the plant.

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 performed plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Summer Readiness Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated summer readiness of offsite and alternate alternating current power systems on June 5 and 24, 2019

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 1 division 1 direct current system while the high pressure core spray system was unavailable on May 9, 2019
(2) Reactor core isolation cooling system May 25-30, 2019
(3) Unit 2 start-up transformer electrical lineup on June 24-25, 2019

71111.04S - Equipment Alignment

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

Low pressure core spray complete system walkdown

(1) The inspectors evaluated system configurations during a complete walkdown of the low pressure core spray system on April 3-4, 2019

71111.05Q - Fire Protection

Quarterly Inspection (IP Section 03.01) (5 Samples)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Auxiliary building 574 foot elevation fire zone (FZ) 1AB-1g, on May 28-30, 2019
(2) Control complex division 1 switchgear FZ 3c on May 28-30, 2019
(3) Control complex 638 foot elevation FZ 4a, e, l, g, h, c and d on May 28-30 2019
(4) Intermediate building 599 foot elevation OIB-2, FHB 0FH-1,2 on May 28-30, 2019
(5) Diesel generator division 2, FZ 1DG-1a on May 28-30, 2019

71111.06 - Flood Protection Measures

Inspection Activities - Underground Cables (IP Section 02.02c.) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Underground cable inspection and condition review for safety-related manholes 1 and 2 on May 8 and 22, 2019

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during plant startup from 1R17 refueling outage on April 5-9, 2019

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated an operations crew-evaluation scenario in the plant training simulator on May 13, 2019

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Reactor recirculation system flow control valves on June 2-5, 2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Plant risk assessment while the low pressure core spray system was unavailable for maintenance on April 18, 2019
(2) Plant risk assessment while the "A" train of control room heating, ventilation and air conditioning and emergency recirculation system was unavailable due to maintenance on May 22-23, 2019
(3) Plant risk assessment associated with the main turbine electro-hydraulic control system emergent leak repair, May 28-June 1, 2019

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 02.02) (3 Samples)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Emergency service water "A" control power fuses operability determination on May 29-31, 2019
(2) Low pressure core spray operability determination on May 29-June 3, 2019
(3) Average power range monitors A, C, and E failed channel check acceptance criteria operability determination on June 1-4, 2019

71111.19 - Post-Maintenance Testing

Post Maintenance Test Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the following post maintenance tests:

(1) Division 3 diesel generator following maintenance on May 24, 2019
(2) Reactor recirculation pump A slow speed breaker 2A 52LCS mechanical switch contacts following repair on June 1, 2019
(3) Positive assist non-return check valves relay following repair on June 1, 2019
(4) Main turbine electro-hydraulic control leak following repair on June 3, 2019
(5) Remote shutdown panel following power supply replacement on June 26, 2019

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors continued evaluation of refueling outage 1R17 activities from April 1-6, 2019. Activities evaluated by the inspectors included, but were not limited to, refueling operations, containment closure, plant heatup, startup and fatigue management

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Inservice Testing (IP Section 03.01)

(1) SVI-E12-T2001, RHR 'A' Pump and Valve Operability Test, on June 25-26, 2019

Surveillance Tests (other) (IP Section 03.01) (3 Samples)

(1) SVI-B13-T0001, Shutdown Margin Calculation, on April 5-8, 2019
(2) SVI-B21-T0373-A, Safety Relief Valve and Low-Low Set Pressure Actuation Channel Calibration, for 1B21-N668A on April 25-26, 2019
(3) SVI-R43-T1317, Diesel Generator Start and Load Division 1, on June 27, 2019

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated an emergency response organization drill on May 15,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) Unit 1 (April 1, 2018 - March 31, 2019)

MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)

(1) Unit 1 (April 1, 2018 - March 31, 2019)

MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)

(1) Unit 1 (April 1, 2018 - March 31, 2019)

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in the flow-accelerated corrosion impacts and programmatic requirements that might be indicative of a more significant safety issue on June 28-29, 2019

71153 - Follow-Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)

(1) On April 7, 2019, at 1:23 a.m., following main generator synchronization to the grid after completion of the 1R17 refueling outage, operators tripped the main turbine in response to hydrogen seal oil detraining section level high and generator casing liquid level high alarms. The inspectors evaluated this unplanned event and licensees performance.

INSPECTION RESULTS

Observation: Flow-Accelerated Corrosion Program 71152 The inspectors reviewed condition reports associated with leaks in system piping induced by flow-accelerated corrosion. The inspectors considered the inputs, evaluations, planned and completed actions for each flow-accelerated corrosion induced leak. The inspectors further reviewed the licensee's programmatic and trend analysis and additionally performed their own search of the corrective action program to validate appropriate inputs were considered during the self-assessment. The inspectors compared the licensee's evaluations, actions, and trend analysis to the programmatic requirements and controls.

The inspectors did not identify any concerns with the licensee's characterization or corrective actions and determined that the scope of each evaluation was appropriate for the circumstances.

EXIT MEETINGS AND DEBRIEFS

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

  • On July 17, 2019, the inspectors presented the integrated inspection results to Mr. F Payne and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Miscellaneous

Certification of Summer Readiness

06/28/2019

71111.04

Procedures

Drawing 302-

0632-00000

Reactor Core Isolation Cooling System

LL

ELI-R11

Station Interbus Transformers

ELI-R22

15KV and 5KV Metal Clad Switchgear

ELI-R42

DC Systems: Batteries Chargers Switchboards

05/09/19

ELI-S11

Power Transformer

SOI-E51

Reactor Core Isolation Cooling System

VLI-E51

Reactor Core Isolation Cooling System

71111.04S

VLI-E21

Low Pressure Core Spray System

71111.05Q

FPI-01B

Intermediate Building

FPI-0CC

Control Complex

FPI-0FH

Fuel Handling Building

FPI-1AB

Auxiliary Building Unit 1

FPI-1DG

Diesel Generator Building

PTI-P54-P0041

Semiannual Fire Door Inspection

71111.06

Work Orders

200701882

Manhole 1 and 2/ Division 3 Inspections

05/20/2019

200712140

Inspect and Dewater Manholes

06/17/2019

71111.11Q Miscellaneous

Evolution Specific

Reactivity Plan

Beginning of Cycle 18 Startup 129

OTLC-

3058201902_PY-

SGC1-Evaluated

Simulator

Scenario

OTLC-3058201902_PY-SGC1-Evaluated Simulator

Scenario

71111.12

Perry Nuclear

Power Plant Plant

Health Report

2018-2

Perry Nuclear Power Plant Plant Health Report 2018-2

01/28/2019

71111.13

eSOMS Plant

Narrative Logs

Plant Narrative Logs

05/28/2019

Procedures

NOP-OP-1007

Risk Management

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Work Orders

200595679

Replace Guide Vane Actuator OE

05/21/2019

200785158

Low Pressure Core Spray Water Leg Pump Water Leak 15

Drop Per Minute

04/18/2019

71111.15

Miscellaneous

eSOMS Plant

Narrative Logs

Plant Narrative Logs

05/24/2019

eSOMS Plant

Narrative Logs

Plant Narrative Logs

05/24/2019

Operability

Evaluations

ATL-2019-0251-

ATA-26

APRM Channel Checks

06/02/2019

71111.19

Procedures

PTI-E22-P0011

HPCS Diesel Generator Slow Speed Start for Post-

Maintenance Inspections

05/24/2019

Work Orders

200753986

Accident Monitoring and Remote Shutdown Channel Checks 06/26/2019

200759929

Perform Engine Maintenance

05/17/2019

20078821

'B' PAC (Positive Assist Check) Valves are not Opening/CR

06/02/2019

200788564

N32 - Turbine EHC (Electro Hydraulic Control) Fluid

Leak/CR

06/02/2019

200788818

Recirculation Pump 'A' Failed to Downshift. Single Loop

Operation on Reactor Recirculation Pump 'B' at this Time.

Simple Troubleshooting Order.

06/01/2019

71111.20

Corrective Action

Documents

2019-03242

Flow Control Valve A Movement During Hydraulic Power

Unit Startup

04/06/2019

2019-03270

Hotwell Pump Motor "A" and Surrounding Area Oil Spilled

04/07/2019

2019-03273

High Main Generator Casing Liquid Level Requires Manual Trip of Main Turbine

04/07/2019

Corrective Action

Documents

Resulting from

Inspection

2019-03184

NRC ID: Resident Inspector Identified an HRA Posting

Improvement

04/04/2019

Procedures

ARI-H51-P176-

0002-C2

Seal Drain Enlargement Liquid Detector Full

IOI-3

Power Changes

NOP-OP-1002

Conduct of Operations

SOI-N42

Hydrogen Seal Oil System

71111.22

SVI-B13_T0001

Shutdown Margin Calculation

04/05/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Work Orders

200714859

SVI-B21-T0373A

04/22/2019

200729176

SVI-E12-T2001, RHR A Pump and Valve Operability Test

06/25/2019

200754234

SVI-R43-T1317 Diesel Generator Start and Load Division 1

06/27/2019

71114.06

Miscellaneous

Perry ERO Integrated Drill Scenario Guide 5/15/2019 Rev 0

05/15/2019

71151

NOBP-LP-4012-

Mitigating Systems Performance Index (MSPI) Unavailability

Index (UAI) & Unreliability Index (URI) for Emergency AC

Power Systems

04/01/2018 -

03/31/2019

NOBP-LP-4012-

Mitigating Systems Performance Index (MSPI) Unavailability

Index (UAI) & Unreliability Index (URI) for High Pressure

Injection System (HPCS) & High Pressure Emergency

Diesel Generator (EDG)

04/01/2018 -

03/31/2019

NOBP-LP-4012-

Safety System Functional Failures

04/01/2018 -

03/31/2019

71152

Corrective Action

Documents

2019-00392

Two Through-Wall Leaks Identified in Low Pressure Drain

Piping

01/15/2019

2019-00935

Potential Negative Trend of Through-Wall Steam Leaks and

Piping Flange Steam Leaks

01/30/2019

2019-02268

1R17 FAC Location 49 on Heater Drain Inlet Nozzle to

1N21B0001C (Low Pressure Feedwater Heater 1C)

03/13/2019

2019-02332

1R17 FAC Examination Results on RWCU Spool Piece

Between 1C and 2A Heat Exchangers

03/14/2019

2019-02427

A Through Wall Hole Found on N36 Feed Water Heating 24

inch Extraction Steam Pipe

03/17/2019

2019-04170

Additional Pitting Discovered in Piping Downstream of

Emergency Service Water

05/07/2019

Procedures

NOP-ER-2005

Flow-Accelerated Corrosion Program

71153

Corrective Action

Documents

CR 2019-03273

High Main Generator Casing Liquid Level Requires Manual Trip of the Main Turbine

04/07/2019