IR 05000220/2019011
| ML19336B928 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/29/2019 |
| From: | Glenn Dentel Engineering Region 1 Branch 2 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Dentel G | |
| References | |
| IR 2019011 | |
| Download: ML19336B928 (9) | |
Text
November 29, 2019
SUBJECT:
NINE MILE POINT NUCLEAR STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000220/2019011 AND 05000410/2019011
Dear Mr. Hanson:
On November 7, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station and discussed the results of this inspection with Mr. Peter Orphanos, Site Vice President 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. 05000220 and 05000410 License Nos. DPR-63 and NPF-69
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000220 and 05000410
License Numbers:
Report Numbers:
05000220/2019011 and 05000410/2019011
Enterprise Identifier: I-2019-011-0019
Licensee:
Exelon Generation Company, LLC
Facility:
Nine Mile Point Nuclear Station
Location:
Oswego, NY
Inspection Dates:
October 21, 2019 to November 7, 2019
Inspectors:
C. Bickett, Senior Reactor Inspector
D. Kern, Senior Reactor Inspector
J. Schoppy, Senior 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 of the environmental qualification program implementation at Nine Mile Point Nuclear 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.
REACTOR SAFETY
===71111.21N - Design Bases Assurance Inspection (Programs)
The inspectors evaluated environmental qualification program implementation through the sampling of the components listed below.
Select Sample Components to Review - Risk Significant/Low Design (Inside/Outside Containment) (IP Section 02.01)===
- (1) Unit 1, Reactor Pressure High/High Trip Pressure Transmitter - (PT-36-08C)
[transmitter, seal]
- (2) Unit 1, Motor Actuator - Core Spray Discharge Isolation Valve 11 (ACT-40-12)
[actuator, circuit breaker, torque switch, position switch, thermal relay]
- (3) Unit 1, Drywell Temperature Element (TE-201-64) [thermocouple, quick disconnect connectors]
- (4) Unit 2, Outboard Main Steam Isolation Valve (2MSS*AOV7B) [solenoid valve cluster assembly, limit switches]
- (5) Unit 2, Reactor Core Isolation Cooling Steam Supply Valve to Turbine (2ICS*MOV120) [actuator, motor, limit switch, lubricant]
- (6) Unit 2, Drywell Area High Range Radiation Monitor (2RMS*RE1B) [radiation monitoring system]
Select Sample Components to Review - Primary Containment (Inside Containment) (IP Section 02.01) (2 Samples)
- (1) Unit 1, Pressure Safety Valve - Automatic Depressurization System Electromatic Relief Valve 121 (PSV-01-102C) [solenoid operated valve, position switch, cables]
- (2) Unit 2, Containment Monitoring System from Drywell, Inside Automatic Isolation Valve (2CMS*SOV61A) [solenoid, limit switch, seal]
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On November 7, 2019, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Peter Orphanos, 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
1EQNORMTEMP.0001
Determination of Normal Ambient Temperatures Used
as Input to the Unit 1 Environmental Qualification
Program
Revision 0
1EQPBD
Nine Mile Point Unit 1 Environmental Qualification
Program Basis Document (Volumes 1, 2, and 3)
Revision 4
Unit 1 Environmental Qualification Master Equipment
List (EQML) Reconstitution
Revision 8
2EQNORMTEMP.0001
Determination of Normal Ambient Temperatures Used
as Input to the Unit 2 Environmental Qualification
Program
Revision 0
2EQNORMTEMP.2014
Temperature Monitoring Data Collected from 2012 to
2014 at Unit 2 for Use by the EQ Program
Revision 0
2EQPBD
Nine Mile Point Unit 2 Environmental Qualification
Program Basis Document (Volumes 1, 2, and 3)
Revision 4
Unit 2 Environmental Qualification Master List
(EQML) Reconstitution
Revision 3
ECP 17-000670
EQ Program Impact Evaluation
Revision 0
EQ1AGEPCMULTIP.0001 Qualified Life for EGS Quick Disconnects
Revision 0
EQ2AGEPCMSS04
Qualified Life Calculation for MSIV Solenoid Valve
Cluster Assembly (SVCA) with AVCO Solenoid
Valves
Revision 0
Corrective Action
Documents
Resulting from
Inspection
290078*
290145*
290625*
290633*
290635*
292360*
293204*
294393*
295049*
295065*
295227*
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
295712*
Engineering
Evaluations
Control and Low Voltage Power Cable Environmental
Qualification Document Package
Revision 1
Low Voltage Power, Control, Thermocouple, and
Instrumentation Cable Environmental Qualification
Document Package
Revision 2
MCC Electrical Replacement Components
Environmental Qualification Document Package
Revision 2
Motor Control Center (MCC) Environmental
Qualification Document Package
Revision 2
Components for use in Limitorque Valve Motor
Operator Environmental Qualification Document
Package
Revision 3
Valve Motor Operator Environmental Qualification
Document Package
Revision 2
Position Switch Environmental Qualification
Document Package
Revision 1
SAIC/EGS Quick Disconnect Connector Model
Numbers 880701 and 913601
Revision 3
Solenoid Operated Valve (Solenoid Actuator
Assembly) Environmental Qualification Document
Package
Revision 2
PYCO Corp. Models 102-3171-08-2.0-4, 102-3171-
08-1.8-4.0, 102-9039-08-6 Thermocouple
Temperature Detector
Revision 2
Rosemount 1152N Series Transmitters
Revision 1
Motor on Motor Operated Valve Environmental
Qualification Document Package
Revision 1
Namco Controls EA740 Series Limit Switch
Revision 4
High Range Radiation Monitor - Kaman
Instrumentation Corporation
Revision 1
Conax Electric Conductor Seal Assembly (SCSA) -
N-11XXX Series
Revision 7
Solenoid Valves Cluster Assembly - Ralph A. Hiller
Revision 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Company
Target Rock Solenoid Valve - 76P Series
Revision 2
Miscellaneous
NMP Environmental Qualification Program FASA
dated
10/18/19
ECN 2009-000280
Revision of SRV Acoustic Monitoring System for RG 1.97 Category 2 to Category 3
Revision 0
ECP 15-000422-CN-018
EQ Exemption Basis for ECP-15-000422 which
Downgraded the H2-O2 System from Safety Related
to Non-Safety Related
Revision 0
N2H19800VALVOP001
Maintenance and Instruction Manual for Main Steam
Isolation Valve Actuator Model SA-A087
Revision 1
N2T02000VALVE06
Project Technical Manual Target Rock Solenoid
Operated Valve
Revision 12
Procedures
Environmental Qualification Program
Revision 14
N1-IPM-TRS-001
EQ Area Temperature Data Logger Maintenance
Revision 2
N2-IPM-TRS-001
EQ Area Temperature Data Logger Maintenance
Revision 2
NMP-CM-7.01-2000
Environmental Qualification (EQ) Program
Administration
Revision 0
NMP-CM-7.01-2003
Preparation and Revision of an Environmental
Qualification Document Package
Revision 1