IR 05000247/2019011

Design Basis Assurance Inspection (Programs) Inspection Report 05000247/2019011 and 05000286/2019011

ML19191A047
Person / Time
Site:	Indian Point
Issue date:	07/09/2019
From:	Glenn Dentel Engineering Region 1 Branch 2
To:	Vitale A Entergy Nuclear Operations
Dentel G
References
IR 2019011
Download: ML19191A047 (7)

Text

uly 9, 2019

SUBJECT:

INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND 3 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000247/2019011 AND 05000286/2019011

Dear Mr. Vitale:

On June 27, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Indian Point Nuclear Generating, Units 2 and 3 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.

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/

Glenn T. Dentel, Chief Engineering Branch 2

Division of Reactor Safety

Docket Nos. 05000247 and 05000286 License Nos. DPR-26 and DPR-64

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000247 and 05000286

License Numbers: DPR-26 and DPR-64

Report Numbers: 05000247/2019011 and 05000286/2019011

Licensee: Entergy Nuclear Operations, Inc.

Facility: Indian Point Nuclear Generating, Units 2 and 3

Location: Buchanan, NY 10511-0249

Inspection Dates: June 10, 2019 to June 27, 2019

Inspectors: A. Patel, Senior Reactor Inspector J. Brand, Reactor Inspector C. Hobbs, Reactor Inspector

Approved By: Glenn T. Dentel, Chief Engineering Branch 2

Division of Reactor Safety

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SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensee's performance by conducting a design basis assurance inspection (programs) inspection at Indian Point Nuclear Generating, Units 2 and 3 in accordance with the Reactor Oversight Process.

The Reactor Oversight Process is the NRC's pr ogram 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 were identified.

Additional Tracking Items None.

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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) ===

(1) Unit 3, Power Operated Relief Valve (RC-SOV-455C) [solenoid operated pilot valve, position indication switch, wire splice, containment penetration, power cable]

(2) Unit 3, Reactor Coolant System Hot Leg Residual Heat Removal Pressure Transmitter (PT-403) [transmitter, instrument cable]

Select Sample Components to Review - Risk Significant/Low Design (Inside/Outside Containment) (IP Section 02.01) (7 Samples)===

(1) Unit 2, Auxillary Feedwater Pump 21 Flow Control Valve (FCV-1121) [limit switch, terminal block, power cable]

(2) Unit 2, Refueling Water Storage Tank to Safety Injection Pumps Suction Valve (SI-1810 MOV) [motor operated valve, limit switch, terminal block, wire splice, power cable]

(3) Unit 2, Suction to Auxillary Feedwater from Condensate Storage Tank Solenoid Operated Valve (CST-SOV-1258) [solenoid operated valve, wire splice, power cable]

(4) Unit 2, Electrical Penetration (EP-H30) [containment penetration]

(5) Unit 3, 31 Residual Heat Removal Pump (31 RHR) [pump motor, wire splice, power cable]

(6) Unit 3, 32 Turbine Driven Auxillary Feedwater Pump Isolation Valve (PCV-1310B) [temperature switch, instrument cable]

(7) Unit 3, Current to Pressure Converter for 31 Auxillary Feedwater Pump to 31 Steam Generator Auxillary Feedwater Regulating Valve FCV-406A (AFW-PM-406E)

[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 June 27, 2019, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Anthony J. Vitale, Site Vice President, and other members of the licensee staff.

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DOCUMENTS REVIEWED

Inspection

Procedure Type Designation Description or Title Revision or

Date 71111.21N Calculations IP-CALC-07-

213 Pressure and Temperature Response from High Energy Line Break in the Auxiliary Feedwater Pump Room

Corrective Action Documents

Resulting from Inspection CR-IP2-2019-

2695, CR-IP2-

2019-02710, CR-

IP2-2019-02509, CR-IP2-2019-

2578, CR-IP2-

2019-02497, CR-

IP3-2019-02516, CR-IP3-2019-

2487, CR-IP3-

2019-02488, CR-

IP3-2019-02660

Engineering

Evaluations PQE-8.1 Automatic Switch Company Solenoid Valve 5