IR 05000334/2019011

Design Basis Assurance Inspection (Programs) Inspection Report 05000334/2019011 and 05000412/2019011

ML19169A179
Person / Time
Site:	Beaver Valley
Issue date:	06/13/2019
From:	Glenn Dentel NRC Region 1
To:	Bologna R FirstEnergy Nuclear Operating Co
References
IR 2019011
Download: ML19169A179 (8)

Text

une 13, 2019

SUBJECT:

BEAVER VALLEY POWER STATION UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000334/2019011 AND 05000412/2019011

Dear Mr. Bologna:

On May 23, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Beaver Valley Units 1, 2 and discussed the results of this inspection with Mr. Rod Penfield, Plant Manager 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 Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Glenn T. Dentel, Chief Engineering Branch 2 Docket Nos.: 05000334 and 05000412 License Nos.: DPR-66 and NPF-73

Enclosure:

Inspection Report 05000334/2019011 and 05000412/2019011

Inspection Report

Docket Numbers: 05000334 and 05000412 License Numbers: DPR-66 and NPF-73 Report Numbers: 05000334/2019011 and 05000412/2019011 Enterprise Identifier: I-2019-011-0016 Licensee: FirstEnergy Nuclear Operating Co.

Facility: Beaver Valley, Units 1 and 2 Location: Shippingport, PA 15077-0004 Inspection Dates: April 29, 2019 to May 23, 2019 Inspectors: C. Hobbs, Reactor Inspector D. Kern, Senior Reactor Inspector K. Mangan, Senior Reactor Inspector Approved By: Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Design Basis Assurance Inspection (Programs) inspection at Beaver Valley Units 1 and 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.

List of Findings and Violations No findings 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.

REACTOR SAFETY

===71111.21N - Design Bases Assurance Inspection (Programs)

The inspectors evaluated Environmental Qualification program implementation through the sampling of the following components:

Select Sample Components to Review - Primary Containment (Inside Containment)

(IP Section 02.01) ===

Unit 2, Power Operated Relief Valve (2RCS-PCV-455C) [solenoid operated pilot valve, position indication switch, wire splice, containment penetration, power cable]

Select Sample Components to Review - Risk Significant/Low Design (Inside/Outside

Containment) (IP Section 02.01) (7 Samples)

(1) Unit 1, Turbine Driven Auxiliary Feedwater Pump Steam Supply Isolation Trip Valve (TV-1MS-105B) [solenoid valve, cable splice, limit switch]

(2) Unit 1, Fast Acting Feedwater Isolation Trip Valve (HYV-1FW-100A) [valve actuator, power cable, limit switch]

(3) Unit 1, Volume Control Tank Outlet to Charging Pumps Suction Valve (MOV-1CH-115E) [motor, valve operator]

(4) Unit 1, Outside Recirculation Spray Pump (1RS-P-2B) [motor, power cable]

(5) Unit 1, Containment High Range Area Monitor (RM-1RM-219B) [high range radiation monitor, containment penetration, instrument cable]

(6) Unit 2, Residual Heat Release Valve (2SVS-HCV104) [valve actuator, solenoid valve, limit switch, power cable]

(7) Unit 2, Main Steam Flow Transmitter (2MSS-FT485) [transmitter, instrument cable]

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On May 23, 2019, the inspector presented the Design Basis Assurance Inspection (Programs) Inspection results to Mr. Rod Penfield, Plant Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21N Calculations 8700-DQC-0024 Namco Limit Switch models EA 180 and EA740 with EC210 Revision 7-2

or EC290 Receptacle/Connector Qualified Life of 60 Year

License and Post Accident Operability Time for EPU

8700-DQC-0225 Siemens-Allis Outside Recirculation Spray Pump Motor Revision 0

Qualified Life for 60 Year License and Post Accident

Operability Time for EPU

Corrective Action CR-2018-07610

Documents CR-2018-08482

CR-2018-08656

CR-2018-08656

CR-2019-00243

Corrective Action ATA-2019-06673

Documents ATA-2019-06920

Resulting from CR-2019-04029

Inspection CR-2019-04083

CR-2019-04084

CR-2019-04589

CR-2019-04612

EER-601219932,

Continued

Temperature

Monitoring

Engineering 1BV-02-0183 FlowServe/Edward Vogt Valve Co. Valve Actuator Model Revision 5

Evaluations A-180

1BV-2008 ASCO Solenoid Valve Revision 14

1BV-2009 Outside Spray Pump Motors Revision 5

1BV-2015 Radiation Monitors and Cable Connectors Revision 6

1BV-2503 NAMCO EA180 Series Limit Switches with 1/2 EC210 Revision 9

Receptacle Connector/Cable Assembly

1BV-6 Electrical Penetrations Revision 6

2BV-209A Westinghouse Electro-Hydraulic Actuated Valve Revision 9

2BV-648A Pressure Transmitters Revision 8

Inspection Type Designation Description or Title Revision or

Procedure Date

2BV-651NAMCO NAMCO Limit Switches Revision 2

2BV-HE-09 Garret / Crosby PORV Solenoid Operated Pilot Valve and Revision 8

Position Indicating Devices

WCAP-14424 Duquesne Light company Equipment LIFETIME Monitor Revision 0

Radiation and Thermal Environment Report for Beaver

Valley Unit 1

WCAP-17717-P FENOC Equipment LIFETIME Monitor Radiation and Revision 1

Thermal Environment Report for Beaver Valley Units 1 and 2

Miscellaneous NRC Safety Evalulation Report for Final Resolution of 03/07/1985

Environmental Qualification of Electric Equipment Important

to Safety - Beaver Valley Unit 1

EGS-TR-902200- Test Report for NAMCO EA-180 and EA-740 Limit Switches 02/28/1995

for use in Cooper Nuclear Station,

NRC Information Age/Environment Induced Cable Failures 06/16/1986

Notice 86-49

NUREG-1057 Safety Evaluation Report Related to the Operation of Beaver Supplement

Valley Power Station Unit 2 5

Work Orders 200015627

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