IR 05000286/2020012
| ML20204A825 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/27/2020 |
| From: | Mel Gray Engineering Region 1 Branch 1 |
| To: | Vitale A Entergy Nuclear Operations |
| Gray M | |
| References | |
| IR 2020012 | |
| Download: ML20204A825 (8) | |
Text
July 27, 2020
SUBJECT:
INDIAN POINT ENERGY CENTER, UNIT 3 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000286/2020012
Dear Mr. Vitale:
On June 25, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Indian Point Energy Center, Unit 3 and discussed the results of this inspection with Mr. John Ferrick 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, X /RA/
Signed by: Melvin K. Gray
Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety
Docket No. 05000286 License No. DPR-64
Enclosure:
As stated
Inspection Report
Docket Number:
05000286
License Number:
Report Number:
Enterprise Identifier: I-2020-012-0009
Licensee:
Entergy Nuclear Operations, Inc.
Facility:
Indian Point Energy Center, Unit 3
Location:
450 Broadway, Generation Support Building
Buchanan, NY 10511-0249
Inspection Dates:
June 8, 2020 to June 25, 2020
Inspectors:
C. Bickett, Senior Reactor Inspector
A. Patel, Senior Reactor Inspector
J. Schoppy, Senior Reactor Inspector
Approved By:
Mel Gray, 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 Indian Point Energy Center, Unit 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 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 (assisted by the NRC senior resident inspector), 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), regional inspectors were directed to begin telework. The inspection documented below was determined that the objectives and requirements stated in the IP could be completed remotely.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
The inspectors:
a. Determined whether the sampled power-operated valves (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. Evaluate maintenance activities including a walkdown by the NRC senior resident inspector of the sampled POVs (if accessible).
- (1) MOV-536, Power Operated Relief Valve Blocking Valve
- (2) MOV-731, Residual Heat Removal Supply from the Reactor Coolant System
- (3) MOV-822A, #31 Residual Heat Removal Heat Exchanger Component Cooling Water Outlet Isolation Valve
- (4) MOV-885A, Containment Sump Residual Heat Removal Suction Isolation Valve
- (5) MOV-1802A, Recirculating Pump Discharge Isolation Valve
- (6) PCV-455C, Power Operated Relief Valve
- (7) PCV-1139, #32 Auxiliary Feed Pump Steam Control
- (8) FCV-1176, Emergency Diesel Generators Service Water System Flow Control
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 25, 2020, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. John Ferrick and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
00186-C-019
AOV Component Level Calculation for Rising Stem Valve
MS-PCV-1139 at Indian Point 3 Nuclear Power Plant
Revision 0
00186-C-020
AOV Component Level Calculation for Rising Stem Valves
RC-PCV-455C and 456
Revision 0
3-MCC-001-ELC
Westinghouse 480 Volt MCC Maintenance Inspection
Revision 48
93162-C-05
Valve Thrust Assessment 14" Copes Vulcan Gate Valve:
AC-MOV-730 & 731
Revision 2
93162-C-27
Valve Thrust Assessment 10" Anchor Darling Gate Valve:
SI-MOV-1802A & B
Revision 4
IP-CALC-20-
00016
Update of MOV Thrust and Torque Calculations AC-MOV-
745B, AC-MOV-822A, SI-MOV-856B, SI-MOV-889A, and
SI-HCV-638
Revision 0
IP3-CALC-ED-
01074
Evaluation of Thermal Overload Heater Sizing for MOV
Motors
Revision 1
IP3-CALC-RCS-
00978
Thrust and Torque Limits for RC-MOV-536
Revision 6
IP3-CALC-SWS-
03684
AOV Component Level Calculation for Diesel Generator
Cooler Flow Control Valves FCV-1176 and 1176A
Revision 0
IP3-CALC-SWS-
03685
AOV System Level Calculation for Diesel Generator
Cooler Flow Control Valves FCV-1176 and -1176A
Revision 0
IP3-RPT-MULT-
279
Evaluation of Coefficient of Friction for GL 89-10 MOVs
Revision 5
S1-01004
Thrust and Torque Calculation SI-MOV-1802A (IPEC-3)
AC Motor Operated GL96-05 Gate Valve
Revision 6
Corrective Action
Documents
Resulting from
Inspection
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
IP3-LO-2019-
00120
Power Operated Valve Focused Self-Assessment Report
01/21/2020
TSP-011
Environmental Qualification (EQ) Program Harsh Areas
and Service Conditions
Revision 11
Procedures
Air Operated Valve Program
Revision 8
MOV Thrust / Torque Setpoint Calculations
Revision 3
MOV Program
Revision 6
ENN-EE-S-002-
IP
Sizing of Thermal Overload Relays
Revision 0