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Design Basis Assurance Inspection (Programs) Inspection Report 05000528/2021014, 05000529/2021014 and 05000530/2021014
	ML21194A067
Person / Time
Site:	Palo Verde
Issue date:	07/14/2021
From:	David Proulx; Division of Reactor Safety IV
To:	Lacal M; Arizona Public Service Co
References
	IR 2021014
	Download: ML21194A067 (14)
	v • d • e

July 14, 2021

SUBJECT:

PALO VERDE NUCLEAR GENERATING STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000528/2021014 AND 05000529/2021014 AND 05000530/2021014

Dear Ms. M. Lacal:

On June 9, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station and 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.

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, David Proulx, Acting Branch Chief Engineering Branch 1 Division of Reactor Safety

Docket Nos. 05000528 and 05000529 and 05000530 License Nos. NPF-41 and NPF-51 and NPF-74

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000528, 05000529 and 05000530

License Numbers:

NPF-41, NPF-51 and NPF-74

Report Numbers:

05000528/2021014, 05000529/2021014 and 05000530/2021014

Enterprise Identifier: I-2021-014-0000

Licensee:

Arizona Public Service Company

Facility:

Palo Verde Nuclear Generating Station

Location:

Tonopah, AZ

Inspection Dates:

May 10, 2021 to May 28, 2021

Inspectors:

J. Braisted, Reactor Inspector

W. Cullum, Reactor Inspector

R. Kopriva, Senior Reactor Inspector

Approved By:

David Proulx, Acting Branch Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at Palo Verde Nuclear Generating Station, 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 a 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

71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)

Main article: IP 71111.21

The inspectors:

a. Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

b. Determined whether the sampled POVs are capable of performing their design-basis functions.

c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.

d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).

(1) Unit 1 Motor-Driven Auxiliary Feedwater Pump to Steam Generator 1 Flow Control Valve 1JAFBHV0030

(2) Unit 1 Nuclear Cooling Water Supply to Reactor Coolant Pump Cooler Outboard Containment Isolation Valve 1JNCAUV0402

(3) Unit 1 Steam Generator 1 Steam Supply to Auxiliary Feed Pump Turbine Isolation Valve (Penetration 2) 1JSGAUV0134

(4) Unit 2 Chemical Volume and Control System Letdown from Regenerative Heat Exchanger Outboard Containment Isolation Valve (Penetration 40) 2JCHBUV0523

(5) Unit 2 Refueling Water Tank Outlet Isolation Valve 2JCHBHV0530

(6) Unit 2 Safety Injection System Containment Sump to Safety Injection Pump Suction Inboard Containment Isolation Valve (Penetration 24) 2JSIBUV0675

(7) Unit 3 Auxiliary Feedwater Turbine Driven Auxiliary Feedwater Pump to Steam Generator 1 Isolation Valve (Penetration 75) 3JAFCUV0036

(8) Unit 3 Motor-Driven Auxiliary Feedwater Pump to Steam Generator 2 Isolation Valve 3JAFBUV0035

(9) Unit 1 Main Steam, Steam Generator 2, Economizer Feedwater Downstream Isolation Valve (Penetration 10) 1JSGBUV0137

(10) Unit 2 Chemical Volume and Control System Auxiliary Pressurizer Spray Valve 2JCHAHV0205

(11) Unit 2 Auxiliary Feedwater Steam Generator 2 Steam Supply to Auxiliary Feed Pump Turbine Isolation Valve (Penetration 3) 2JSGAUV0138

(12) Unit 3 Safety Injection Containment Spray Control Valve and Outboard Containment Isolation Valve (Penetration 21) 3JSIAUV0672

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

On June 9, 2021, the inspectors presented the Exit Meeting inspection results to Ms. M.

Lacal, Vice President / Chief Nuclear Officer and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.02 Calculations

01-EC-MA-0221

AC Distribution

01-EC-PK-0207

DC Battery Sizing and Minimum Voltage

01-J-ZZI-0004

Controlled Motor Operator Database

2-EC-MA-0221

AC Distribution

2-J-ZZI-0006

Controlled - Air Operated Valve Setpoint Database

03-EC-MA-0221

AC Distribution

03-EC-PK-0207

DC Battery Sizing and Minimum Voltage

03-J-ZZI-0004

Controlled Motor Operator Data Base

13-JC-CH-0102

Air Operated Valve (AOV) Setting Calculation for Letdown

to Regen HX Isolation Valves and Regenerative

Heat Exchanger Outlet Isolation Valves

000

13-JC-ZZ-0300