IR 05000247/2019011
| 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
July 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:
Report Numbers:
05000247/2019011 and 05000286/2019011
Enterprise Identifier: I-2019-011-0017
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
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees 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 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 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)===
- (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.
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-
CR-IP2-2019-
2578, CR-IP2-
2019-02497, CR-
CR-IP3-2019-
2487, CR-IP3-
2019-02488, CR-
Engineering
Evaluations
PQE-8.1
Automatic Switch Company Solenoid Valve
5