IR 05000461/2018011

From kanterella
Jump to navigation Jump to search
NRC Design Basis Assurance Inspection (Programs) Inspection Report 05000461/2018011 (DRS-B.Jose)
ML18332A326
Person / Time
Site: Clinton Constellation icon.png
Issue date: 11/27/2018
From: Karla Stoedter
NRC/RGN-III/DRS/EB2
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2018011
Download: ML18332A326 (7)


Text

ber 27, 2018

SUBJECT:

CLINTON POWER STATIONNRC DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000461/2018011

Dear Mr. Hanson:

On November 8, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an NRC Design Basis Assurance inspection (Programs) at your Clinton Power Station.

On November 8, 2018, the NRC inspectors discussed the results of this inspection with Mr. B. Kapellas, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any findings or violations 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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Karla Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 50-461 License No. NPF-62 Enclosure:

Inspection Report 05000461/2018011 cc: Distribution via LISTSERV

Letter to Bryan

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a Design Bases Assurance (Programs) Inspection at Clinton Power 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. The NRC and self-revealed findings, violations, and additional items are summarized in the table below.

List of Findings and Violations No findings or violations 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 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

===71111.21NDesign Bases Assurance Inspection (Programs)

The inspectors evaluated Environmental Qualification Program implementation through the sampling of the following components:

Risk Significant/Low Design Margin Components ===

(1) 1E12C002A, Residual Heat Removal (RHR) Pump 1A;
(2) 1E12F014A, RHR Heat Exchanger 1A Safety-Related Service Water Inlet Valve;
(3) 1E22N056, High Pressure Core Spray Pump Discharge Minimum Flow Differential Pressure Transmitter;
(4) 1VY08CA, High Pressure Core Spray Pump Room Supply Fan; and
(5) 1E12F053B, RHR Shutdown Cooling Injection Valve.

Primary Containment Components (4 Samples)

(1) 1C41C001A, Standby Liquid Control Pump 1A;
(2) 1C41F004A, Standby Liquid Control Pump 1A Squib Valve;
(3) 1FC007, Fuel Pool Cooling Return Isolation Valve; and
(4) 1B21F041B, Main Steam Safety Relief Valve.

INSPECTION RESULTS

71111.21NDesign Bases Assurance Inspection (Programs) No findings or violations were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure. No proprietary information was documented in this report.

  • On November 8, 2018, the inspectors presented the Design Bases Assurance Program Inspection results to Mr. B. Kapellas, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.21NDesign Bases Assurance Inspection (Programs)

-EQ-CL021, EQ Binder for Rosemount Pressure Transmitters, Revision 39

-EQ-CL027, EQ Binder for Limtorque Model SMB Motor Operated Valves, Revision 38

-EQ-CL004, EQ Binder for Westinghouse Fan Motors, Revision 24

-M05-1075, P&ID Residual Heat Removal System, Revision AO

-AR 02597979-04; Revise EQ Binders EQ-CL105, EQ-CL027 and MS-02.00 Standard to

Incorporate Changes Due To EC 400205; 12/09/2015

-AR 02604131-01; Revise EQ Binder EQ-CL006 to Incorporate (EOL#117); 12/23/2015

-AR 04048899-01; Complete EQ Annual Health Report (Model AR 1143818, M4); 09/05/2017

-AR 04096292-07; 2018 EQ Self-Assessment Strength #1; 01/23/2018

-AR 04096292-09; Recommended Enhancement to EQ Binder EQ-CL027; 01/23/2018

-AR 04170013-01; Complete EQ Annual Health Report; 09/05/2018

-Calculation IP-Q-0428; Environmental Qualification of Okonite-FMR [Flame and Moisture

Retardant] Insulated Low Voltage Power Cables (3 Conductor #6 AWG [American wire gauge]

& 3 Conductor #8 AWG); Revision 00

-EC 334889 - 0; Extended Power Uprate - Evaluation of 30 EQ Binders Which Envelope the

New EPU Environmental Conditions [Ref: CPS CALC.EPU-T1004]; 05/10/2002

-EQ-CL006; Environmental Qualification of the Okonite Company Low Voltage Power and

Control Cables; Revision 20

-EQ-CL009; Environmental Qualification of Limitorque Motor Operators Models SMB, SMB/HBC

& SB (Inside Containment); Revision 53

-EQ-CL065; Environmental Qualification of Seitz Solenoid Valve Model #6A39 (Seal Welded);

Revision 8

-MEQ-CL022; Environmental Qualification of Anchor/Darling 21/2& Larger Globe Gate & Check

Valves; Revision 43

-MEQ-CL073; Environmental Qualification of Dikkers Safety Relief Valves; Revision 19

-Commercial Grade Dedication (CGD) 57211; PDID Ring Tongue Terminal Lug, 22-16 AWG

(Red Stripe), #10 Stud; 06/29/2007

-EPRI [Electric Power Research Institute, Inc.] STD CGIEL01; EPRI CGI [Commercial Grade

Item] Joint Utility Task Group Commercial Grade Item Evaluation for Lugs, Compression,

Insulated; Revision 0

-Item Equivalency Evaluation (IEE) 84746; Flowserve Mechanical Seal Model UO-3375,

CID 1465335 as a Replacement for the Model UK-3375, CID 1148209

-M-94-0300-02 (OMM-713); Parts Classification Manual; Revision 2

-Procurement Engineering Evaluation 70657; Pre-Insulated Diamond Grip (PIDG) Ring Lug

Terminal; 11/23/2010

-Procurement Engineering Evaluation 70733; PIDG Ring Lug Terminal, Amp Part

Number 53418-1, Cat ID 1100581-2; 01/04/2011

-NEI [Nuclear Energy Institute] Efficiency Bulletin: 16-34; Streamline Program Health Reporting;

2/02/2016

-NSED [Nuclear Station Engineering Department] 88115; Engineering Review of Requisition

No. RO579130; Revision 3

-Qualification Test Report 110-11004; AMP [Aircraft Marine Products] Insulated Terminals and

Splices for Class 1E, Inside Containment Service in Nuclear Power Generating Stations;

2/02/1982

-CC-AA-203; Environmental Qualification Program; Revision 13

-CC-AA-320-1002; Dynamic (Seismic) Qualification for Alternate Replacement Items and

Commercial Grade Dedication Items; Revision 3

-ER-AA-1100; Implementing and Managing Engineering Programs; Revision 11

-ER-AA-1100; Implementing and Managing Engineering Programs; Revision 18

-NISP-EN [Nuclear Industry Standard Process - Engineering]-02; Standard Item Equivalency

Process (EB-18-XX), Revision B; 08/23/2017

-NSED [Nuclear Station Engineering Department] Instruction DE-15; Control of the Maintenance

of Equipment Qualification Program Manual, Engineering Standard MS-02.00; Revision 8

-NSED Procedure E.6; Environmental Qualification Packages; Revision 12

-PES-S-002; Exelon Nuclear Engineering Standards - Shelf Life; Revision 6

-PES-S-003; Exelon Nuclear Engineering Standards - In-Storage Maintenance of Nuclear

Material; Revision 7

-PES-S-004; Exelon Nuclear Generation Group Procurement Engineering Standards -

Sampling Plan; Revision 2

-PI-AA-127; Passport Action Tracking Management Procedure; Revision 2

-SM-AA-300; Procurement Engineering Support Activities; Revision 8

-PO 00026982; Main Steam Safety Relief Valve Inspection/Test/Repair; 08/01/2001

-PO 00042778; Main Steam Safety Relief Valve Inspection/Test/Repair; 12/01/2003

-PO 00069686; Main Steam Safety Relief Valve Inspection/Test/Repair; 11/17/2005

-PO 00074880; Main Steam Safety Relief Valve Inspection/Test/Repair; 11/17/2005

-PO 00408229; Main Steam Safety Relief Valve Inspection/Test/Repair; 01/02/2008

-PO 00430797; Main Steam Safety Relief Valve Inspection/Test/Repair; 11/30/2009

-PO 00456045; Main Steam Safety Relief Valve Inspection/Test/Repair; 09/11/2013

-PO 00483502; Main Steam Safety Relief Valve Inspection/Test/Repair; 04/29/2017

-WO 01217208-01; Perform Thrust Verification and MOV Clean & Inspect 1FC007; 06/29/2012

-WO 01730806-01; 1E12-F014A Indicated Intermediate When Shut; 06/04/2014

-WO 01730806-03; 1E12-F014A Indicated Intermediate When Shut; 12/19/2014

-WO 01760605-01; 9069.01A20 OP SX Pump OPER Test (SX Pump A); 09/24/2014

-EQ-CL004, EQ Binder for Westinghouse Fan Motors, Revision 24

-EQ-CL001, EQ Binder for General Electric RHR Pump Motors, Revision 24

-EQ-CL061B, EQ Binder for Standby Liquid Control System Pump Motor, Revision 12

-EQ-CL064, EQ Binder for Standby Liquid Control (Explosive) Valve and Replacement Kit,

Revision 5

-W0 01859548-01; EQ-CL064 Replace Parts after Firing per 9015.02; 05/14/2017

-WO 04660657-01; 1C41F004B Replace Parts after Firing per 9015.02; 05/18/2018

-WO 01876039-01; Lube and Inspect Motor 1C41C001A; 11/27/2017

-WO 01338786-01; Lube and Inspect Motor 1C41C001B; 10/30/2014

-M05-1077; P&ID for Standby Liquid Control; Revision AC

-GE PRC 87-01; ECCS Pump Motor Bracket and Felt Blocking; 04/09/1987

-DC-ME-090CP; Equipment Environmental Design Conditions; Revision 12

Corrective Actions Documents Generated as a Result of the Inspection

-AR 04187384, PMT Work Order Closure Timespan September to December, 1E12-F014A,

10/24/2018

-AR 04191083, Procedure Discrepancy between ER-AA-1100 and CC-AA-203-1001,

11/02/2018

-AR 04192152, Discrepancy between Station Procedure and Active Actions, 11/05/2018

5