ML21042B969

Notification of NRC Design Bases Assurance Inspection and Initial Request for Information

ML21042B969
Person / Time
Site:	Palo Verde
Issue date:	02/18/2021
From:	Vincent Gaddy Division of Reactor Safety IV
To:	Lacal M Arizona Public Service Co
Scott L
References
IR 2021014
Download: ML21042B969 (10)

Text

February 18, 2021 Mrs. Maria L. Lacal Executive Vice President/

Chief Nuclear Officer Arizona Public Service Company P.O. Box 52034, MS 7602 Phoenix, AZ 85072-2034

SUBJECT:

PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 -

NOTIFICATION OF NUCLEAR REGULATORY COMMISSION DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) (05000528/2021014, 05000529/2021014, AND 05000530/2021014) AND INITIAL REQUEST FOR INFORMATION

Dear Mrs. Lacal:

On May 10, 2021, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite inspection at the Palo Verde Nuclear Generating Station Units 1, 2, and 3. A three-person team will perform this inspection using NRC Inspection Procedure 71111, Attachment 21N.02, Design Bases Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements.

This inspection will evaluate the reliability, functional capability, and design basis of risk-important power-operated valves as required by 10 CFR 50.55a and applicable 10 CFR Part 50, Appendix A and Appendix B, requirements, and as required by the Palo Verde Nuclear Generating Station Units 1, 2, and 3 Operating Licenses. Additionally, the team will perform an inspection of the documentation files to verify that the plant activities associated with safety-related motor-operated valves meet your commitments to Generic Letter (GL) 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance, and GL 96-05, "Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves." In conducting this inspection, the team will select power-operated valves used to prevent and mitigate the consequences of a design basis accident.

The inspection will include an information gathering site visit by the team leader and two weeks of onsite inspection by the team. The inspection will consist of three NRC inspectors. The current inspection schedule is as follows:

Onsite Information Gathering Visit: March 22-26, 2021 Preparation Weeks: May 3-7, 2021, and May 17-21, 2021 Onsite Weeks: May 10-14, 2021 and May 24-28, 2021

M. Lacal The purpose of the information gathering visit is to meet with members of your staff to become familiar with the power-operated valve activities at the Palo Verde Nuclear Generating Station.

The lead inspector will request a meeting with your personnel to discuss the site power-operated valve procedures. Additionally, the lead inspector will request a discussion with your staff to become familiar with the regulations and standards applicable to power-operated valves at the site. Additional information and documentation needed to support the inspection will be identified during the inspection, including interviews with engineering managers and engineers.

In order to minimize the inspection impact on the site and to ensure a productive inspection, we have enclosed a request for information needed for the inspection. This information should be made available to the lead inspector during the week of March 15-19, 2021. Since the inspection will be concentrated on safety-related and risk significant power-operated valves, a list of such power-operated valves should be available to review during and following the information gathering visit to assist in our selection of appropriate power-operated valves to review.

Additional requests by inspectors will be made during the onsite weeks for specific documents needed to complete the review of specific power-operated valves and associated activities. It is important that all these documents are up-to-date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection. To facilitate the inspection, we request that a contact individual be assigned to each inspector to ensure information requests, questions, and concerns are addressed in a timely manner.

The lead inspector for this inspection is Mr. Ronald A. Kopriva. We understand that our licensing engineer contact for this inspection is Mr. Mohamed Diane. If there are any questions about the inspection or the requested materials, please contact the lead inspector by telephone at 817-200-1104 or by email at Ron.Kopriva@nrc.gov.

This letter contains mandatory information collections that are subject to the Paperwork Reduction Act of 1995 86& HWVHT  The Office of Management and Budget (OMB) approved these information collections (approval number 31500011). Send comments regarding this information collection to the Information Services Branch, Office of the Chief

,QIRUPDWLRQ2IILFHU0DLO6WRS7$0861XFOHDU5HJXODWRU\&RPPLVVLRQ:DVKLQJWRQ DC 20555-0001, or by email to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (31500011) Office of Management and Budget, Washington, DC 20503.

The NRC may not conduct nor sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.

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M. Lacal 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 5RRPLQDFFRUGDQFHZLWK&)5³3XEOLF,QVSHFWLRQV([HPSWLRQV5HTXHVWVIRU Withholding.

Sincerely, Digitally signed by Vincent G. Vincent G. Gaddy Date: 2021.02.18 Gaddy 05:04:12 -06'00' Vincent G. Gaddy, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000528, 05000529, and 05000530 License Nos. NPF-41, NPF-51, and NPF-74 Enclosure(s):

Design Bases Assurance Inspection (Programs) Power-Operated Valve Request for Information Valves of Interest List cc w/ encl: Distribution via LISTSERV 3

ML21042B969 SUNSI Review Non-Sensitive Publicly Available Initials: RAK Sensitive Non-Publicly Available SRI:EB1 C:PBD C:EB1 RKopriva JDixon VGaddy RAK JLDJ VGG 02/11/2021 02/11/2021 02/12/2021 M. Lacal Initial Request for Information Design Bases Capability of Power-Operated Valves PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 Inspection Report(s): 05000528/2021014, 05000529/2021014, and 05000530/2021014 Information Gathering Dates: March 22-26, 2021 Inspection Dates: May 10-14, 2021 and May 24-28, 2021 Inspection Procedure: IP 71111, Attachment 21N.02, Design Bases Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements Lead Inspector: Ronald A. Kopriva, Senior Reactor Inspector I. Information Requested for Information Gathering Visit (March 22, 2021)

The following information should be provided to the lead inspector in hard copy or electronic format, to the attention of Ronald A. Kopriva by March 15, 2021 to facilitate the reduction in the items to be selected for a final list of components. The inspection team will finalize the selected list during the prep week using the documents requested in this enclosure. The specific items selected from the lists shall be available and ready for review on the day indicated in this request. *Please provide requested documentation electronically in pdf files, Excel, or other searchable formats, if possible.

The information should contain descriptive names and be indexed and hyperlinked to facilitate ease of use. Information in "lists" should contain enough information to be easily understood by someone who has knowledge of pressurized water reactor technology. If requested documents are large and only hard copy formats are available, please inform the inspectors, and provide subject documentation during the first day of the onsite inspection.

1. Provide the valve characteristics for the valves listed in the attached list as described in Appendix C of NRC Inspection Procedure 71111, Attachment 21N.02, Design Bases Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements.

2. List of power-operated valves (POVs) important to safety for the Palo Verde Nuclear Generating Station. The list should include (a) component identification number; (b) applicable plant system; (c) ASME Boiler and Pressure Vessel Code (BPV Code)

Class; (d) safety-related or nonsafety-related classification; (e) valve type, size and manufacturer; and (f) actuator type, size, and manufacturer. If the NRC has granted a license amendment to categorize structures, systems, and component in accordance with 10 CFR 50.69, please provide the risk-informed safety category of the component.

3. Listing of POVs sorted by risk importance, including external risk considerations.

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4. Word searchable updated final safety analysis report UFSAR), license conditions, technical specifications, and most recent in-service testing (IST) program plan (and bases document), including any standards that have been committed to with respect to POV capability and testing. Also, identify which UFSAR sections address environmental, seismic, and functional qualification of POVs.

5. Provide copies of the latest POV program level procedures or manuals.

6. NRC Safety Evaluation Report(s) associated with the Palo Verde Nuclear Generating Station IST program and relief and alternative requests submitted in accordance with 10 CFR 50.55a for POVs.

7. Provide the most recently completed audit, self-assessment, or benchmark of POV programs at Palo Verde Nuclear Generating Station.

8. List of systems, system numbers/designators and corresponding names.

9. List of site contacts that will be associated with the inspection.

II. Discussions Requested

1. Interview with a Palo Verde Nuclear Generating Station representative to discuss site POV capability analyses, including plant drawings and assumptions. This includes analysis for accident conditions.

2. Interview with a Palo Verde Nuclear Generating Station representative to discuss POV maintenance elements as integrated into plant programs and procedures.

3. Interview with a Palo Verde Nuclear Generating Station representative to discuss maintaining the design basis capability of POVs if they have entered a period of extended operation, if applicable.

III. Information Requested for Inspection Preparation (May 3, 2021)

1. Calculations and/or evaluations associated with the selected POVs, as applicable.

For example, these may include those related to motor-operated valve (MOV) torque switch setpoint, MOV terminal (degraded) voltage, maximum expected differential and pressure, torque switch bypass settings, rate of loading, environmental and process conditions during normal/accident operation, seismic and weak-link analysis, and pressure locking and thermal binding, etc. (Eight to Twelve specific valves will be identified and communicated to you prior to April 19, 2021.)

2. Vendor manuals and technical sheets associated with the selected POVs.

3. Provide results (i.e., completed work orders) from the last three performances of diagnostic (static and/or dynamic) testing and in-service testing (stroke time, leak rate, etc.) of the selected POVs.

4. Provide performance (or failure) trending data for the selected POVs.

5. List of modifications related to the selected POVs.

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6. List of corrective action program documents, with a brief description, related to the selected POVs over the past five years.

7. List of preventive maintenance activities for the selected POVs (valve and actuator).

Include the identification number, title and/or description, and frequency.

8. System training manuals and/or design basis documents associated with the selected POVs.

9. Piping and instrument diagrams for systems related to the selected POVs.

10. Tours of the rooms in which the selected POVs are installed. If the inspection will be performed remotely, multiple pictures of selected valve and valve location can be provided. The pictures must have an orientation reference, a size reference, pictures of the surrounding environment, and pictures of the nameplates of both valve and valve operator.

IV. Discussions Requested During the First Inspection Week (May 10, 2021)

1. Brief presentation of POV programs at Palo Verde Nuclear Generating Station.

2. Interviews with representatives to discuss the design basis capability of POVs based upon the teams review of gathered information.

• Please sort the Section III responses by each selected POV.

Inspector Contact Information:

Ronald Kopriva Jonathan Braisted Wes Cullum Senior Reactor Inspector Reactor Inspector Reactor Inspector 817-200-1104 817-200-1469 817-200-1563 Ron.Kopriva@nrc.gov Jonathan.Braisted@nrc.gov Wes.Cullum@nrc.gov Mailing Address:

U.S. NRC, Region IV Attn: Ronald Kopriva 1600 East Lamar Blvd.

Arlington, TX 76011-45 7

Palo Verde Nuclear Generating Station Valves of Interest Number PLANT DKT SYS ID POV SAFETY VLV Type Size 1 Palo Verde 1 528 Auxiliary Feedwater - MOTOR-DRIVEN AFW 1JAFBHV0030 MOV Open/Close Globe 6 PUMP TO SG #1 FLOW CONTROL VALVE 2 Palo Verde 1 528 Chemical Volume & Control System - NORMAL 1JCHEPDV0240 AOV Open/Close Globe 2 CHARGING FLOWPATH ISOLATION VALVE 3 Palo Verde 1 528 Nuclear Cooling Water - NUCLEAR COOLING 1JNCAUV0402 MOV Close Butterfly 10 WATER SUPPLY TO RCP COOLER OUTBOARD CIV (PEN. 34) 4 Palo Verde 1 528 Main Steam - SG 1 STEAM SUPPLY TO AUX 1JSGAUV0134 MOV Open/Close Gate 6 FEED PUMP TURBINE ISOLATION VALVE (PEN.

2) 5 Palo Verde 1 528 Main Steam - SG 1 DOWNCOMER FEEDWATER 1JSGAUV0172 AOV Close Gate 8 UPSTREAM ISOLATION VALVE 6 Palo Verde 1 528 Main Steam - SG 2 DOWNCOMER FEEDWATER 1JSGAUV0175 AOV Close Gate 8 UPSTREAM ISOLATION VALVE 7 Palo Verde 1 528 Main Steam - SG 2 ECONOMIZER FEEDWATER 1JSGBUV0137 HOV Close Gate 24 DOWNSTREAM ISOLATION VALVE (PEN. 10) 8 Palo Verde 1 528 Safety Injection - SHUTDOWN COOLING 1JSIAUV0651 MOV Open/Close Gate 16 SUCTION ISOLATION VALVE 9 Palo Verde 1 528 Safety Injection - CONTAINMENT SPRAY 1JSIBHV0693 MOV Open/Close Gate 10 BYPASS VALVE 10 Palo Verde 1 528 Safety Injection - LPSI DISCHARGE HEADER 1JSIBUV0625 MOV Open Globe 12 OUTBOARD CIV (PEN. 18) 11 Palo Verde 2 529 Auxiliary Feedwater - TURBINE-DRIVEN AFW 2JAFAHV0054 MOV Open Globe 4 PUMP TRIP/THROTTLE VALVE 12 Palo Verde 2 529 Chemical Volume & Control System - AUXILIARY 2JCHAHV0205 SOV Open/Close Globe 2 PRESSURIZER SPRAY VALVE 13 Palo Verde 2 529 Chemical Volume & Control System - REFUELING 2JCHBHV0530 MOV Open/Close Gate 20 WATER TANK OUTLET ISOLATION VALVE

Number PLANT DKT SYS ID POV SAFETY VLV Type Size 14 Palo Verde 2 529 Chemical Volume & Control System - LETDOWN 2JCHBUV0523 AOV Close Globe 2 FROM REGENERATIVE HEAT EXCHANGER 15 Palo Verde 2 529 Nuclear Cooling Water - NUCLEAR COOLING 2JNCBUV0403 MOV Close Butterfly 10 WATER SUPPLY TO RCP COOLER INBOARD CIV (PEN. 34) 16 Palo Verde 2 529 Radioactive Drains - CONTAINMENT RADWASTE 2JRDBUV0024 AOV Close Gate 3 SUMP OUTLET OUTBOARD CIV (PEN. 9) 17 Palo Verde 2 529 Main Steam - STEAM GENERATOR 2JSGAHV0184 AOV Open/Close Globe 12 ATMOSPHERIC DUMP VALVE (ADV) (PEN. 1) 18 Palo Verde 2 529 Auxiliary Feedwater - SG 2 STEAM SUPPLY TO 2JSGAUV0138 MOV Open/Close Gate 6 AUX FEED PUMP TURBINE ISOLATION VALVE (PEN. 3) 19 Palo Verde 2 529 Safety Injection - CONTAINMENT SUMP TO SI 2JSIBUV0675 MOV Open/Close Butterfly 24 PUMP SUCTION INBOARD CIV (PEN. 24) 20 Palo Verde 2 529 Safety Injection - SHUTDOWN COOLING 2JSICUV0653 MOV Open/Close Gate 16 SUCTION INBOARD CIV (PEN. 27) 21 Palo Verde 3 530 Auxiliary Feedwater - MOTOR-DRIVEN AFW 3JAFBUV0035 MOV Open/Close Gate 6 PUMP TO SG #2 ISOLATION VALVE (PEN. 76) 22 Palo Verde 3 530 Auxiliary Feedwater - TURBINE-DRIVEN AFW 3JAFCUV0036 MOV Open/Close Gate 6 PUMP TO SG #1 ISOLATION VALVE (PEN. 75) 23 Palo Verde 3 530 Condensate Transfer - AFN-P01 SUCTION 3JCTAHV0001 MOV Close Butterfly 10 ISOLATION VALVE FROM CONDENSATE STORAGE TANK 24 Palo Verde 3 530 Reactor Coolant - REACTOR VESSEL HEAD 3JRCAHV0101 SOV Open/Close Globe 1 VENT VALVE 25 Palo Verde 3 530 Radioactive Drains - CONTAINMENT RADWASTE 3JRDBUV0024 AOV Close Gate 3 SUMP OUTLET OUTBOARD CIV (PEN. 9) 26 Palo Verde 3 Main Steam - STEAM GENERATOR 3JSGBHV0178 AOV Open/Close Globe 12 ATMOSPHERIC DUMP VALVE (ADV) (PEN. 2) 27 Palo Verde 3 530 Main Steam - MAIN STEAM ISOLATION VALVE 3JSGEUV0171 HOV Close Gate 28

Number PLANT DKT SYS ID POV SAFETY VLV Type Size (PEN. 3) 28 Palo Verde 3 530 Safety Injection - SHUTDOWN COOLING HEAT 3JSIAHV0657 MOV Open/Close Butterfly 16 EXCHANGER OUTLET THROTTLE VALVE 29 Palo Verde 3 530 Safety Injection - CONTAINMENT SPRAY 3JSIAUV0672 MOV Open/Close Gate 8 CONTROL VALVE AND OUTBOARD CIV (PEN.

21) 30 Palo Verde 3 530 Safety Injection - SHUTDOWN COOLING 3JSIDUV0654 MOV Open/Close Gate 16 SUCTION INBOARD CIV (PEN. 26)