IR 05000369/2019010
| ML19219A668 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/07/2019 |
| From: | James Baptist Division of Reactor Safety II, NRC/RGN-II/DRS/EB1 |
| To: | Teresa Ray Duke Energy Carolinas |
| Reeder D | |
| References | |
| IR 2019010 | |
| Download: ML19219A668 (12) | |
Text
August 7, 2019
SUBJECT:
WILLIAM B. MCGUIRE NUCLEAR STATION - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000369/2019010 AND 05000370/2019010
Dear Mr. Ray:
On July 18, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at William B. McGuire Nuclear Station and discussed the results of this inspection with Ed Pigott 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/
James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety
Docket Nos. 05000369 and 05000370 License Nos. NPF-17 and NPF-9
Enclosure:
As stated
cc w/ encl: Distribution via LISTSERV
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline inspection at William B McGuire 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
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from July 15-18, 2019.
(1)50.59 Evaluation - AR 02073877, Allow Use of Upgraded VIPRE Code for Analysis (2)50.59 Evaluation, AR 01983884, UFSAR Change in Support of Lifting Reactor Vessel Upper Internals Lift Rig (3)50.59 Screening - AR 1339299, Replace 1A EDG Voltage Regulators U1 (EC 104503)
(4)50.59 Screening - AR 2168938, ECCS and NS System Gas Void Acceptance Criteria (EC 410608)
(5)50.59 Screening - AR 1267495, RN Strainer Backwash Pump - 1A MOD (EC 102477)
- (6) Applicability Determination - AR 2162253, Replace Bussman BAF-3A Fuses For 125VDC Vital I&C Distribution Center Voltmeter CKTS & U1/U2 PNLBD Loss of Voltage (EC 409942)
- (7) Applicability Determination - AR 1338041, RN Suction Overpressure Protection "1A" (OBDN) - Unit 1 Exemption "40" List - 43-14 (EC 107089)
(8)50.59 Evaluation - AR 02014647, Allow Replacement of Digital Rod Position Indication (DRPI) Controller (EC 113220)
(9)50.59 Evaluation - AR 02050448, Tune Distributed Control System (CS) Controls Due to Hot Leg Streaming (EC 404368)
(10)50.59 Screening - AR 1228654, VC/YC Chiller Compressor Oil Pump (EC 101374)
(11)50.59 Screening - AR 1349726, 1C NCP Motor Stator Upgrade (EC 104254)
(12)50.59 Screening - AR 1286447, Replace Panelboard 2EKVB Mod (EC 105979)
- (13) Applicability Determination - AR 2052086, Revise Unit 1 CA Pump Motor Time Overcurrent Relay 51 Setting (EC 405274)
- (14) Applicability Determination - AR 1339802, Replace Solenoid Valves on 2NCSV0273AC and 2NCSV0275B With Different Model Target Rock Valve (EC 111336)
(15)50.59 Evaluation - AR 1955292, Assured CA Suction for Extended SBO Per NRC Order EA-12-049 & INPO IER L1-11-4 (Fukushima Dai-ichi Accident Response) Unit 2 (EC 109072)
(16)50.59 Evaluation - AR 2047562, Revision to Methodology Report DPC-NE-2009-P-A to Implement WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, Optimized ZIRLO, and Addendum 2-A, Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLO (17)50.59 Screening - AR 1336245, 0000103936 - 000 - Change Actuator On 2RN0279 from NA2 to NA1E (EC 103936)
(18)50.59 Screening - AR 2081907, 0000400132 - 000 CA Discharge Piping Design Pressure Increase Per NCR 01901450 (EC 400132)
(19)50.59 Screening - AR 1990687, The acceptable Valve Stroke Times (VST) for valves 1NM-22AC,1NM-25AC, 1NV-141A, 0RN-10AC, 0RN-147AC, 0RN-148AC, 1RN-64A, 2RN-70A, 1RN-253A, 1 RN-276A, 2RN-279B, 2RN-299A, 1VE-5A, and 2VI-362A are revised to restore margin to the MOV stroke time for these valves (EC 402504)
(20)50.59 Screening - AR 2051913, 0000101492 - 000 Unit 1 NI and NV Cold Leg Throttle Valve Seat Clearance Capital (EC 101492)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 18, 2019, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Ed Pigott and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.17T Calculations
DPC -1552.08-00-
0109
Safety Injection Flows For Safety Analysis
Rev. 25
MCC 1206.02-83-
0034
EC101494 - Addition of Valve 2NV-1077
Rev. 27
MCC 1223.02-00-
0001
Engineered Safety Feature Valves Response Time
Testing Response
Rev. 24
MCC 1223.02-00-
0002
Engineered Safety Feature Valves Response Time
Testing Response
Rev. 22
MCC-1201.05-00-
0006
Rerate Qualification Report for 3X4X9E MSD 9 Stage
Auxiliary Feedwater Pump
Rev. 1
MCC-1201.05-00-
0007
Rerate Qualification Report for 4X6X10B MSD-D 10
Stage Auxiliary Feedwater Pump
Rev. 1
MCC-1206.02-83-
0034
Piping Analysis Problem NV-353
Rev. 27
MCC-1223.42-00-
0004
CA System Parameter Design Parameter Verification
Rev. 5
MCC-1381.05-00-
0147
Maximum Allowable Cable Lengths for Size 1 and 2
Starters at McGuire
Rev. 9
Corrective Action
Documents
VC/YC Chiller Compressor Oil Pump
Rev.0
Replace Panelboard 2EKVB Modification
Rev.0
RN Strainer Backwash Pump - 1A MOD
dated
05/14/2012
CFR 50.59 Screen 0000108639 - 000 - Revise RN,
NM, NV, VE and VI System TAC Sheet Valve Stroke
Times.
dated
09/05/2013
0000103936 - 000 - Change Actuator On 2RN0279 from
NA2 to NA1E
dated
03/14/2013
EC107089 & EC107090: RN Suction Supplemental Vent
Line 1A & 2A
dated
06/04/2013
0000104503 - 000 - Replace 1A EDG Voltage Regulators
U1
dated
08/08/2013
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Replace Solenoid Valves on 2NCSV0273AC AND
2NCSV0275B with Different Model Target Rock Valve
Rev.0
Rev.10
Assured CA Suction for Extended SBO Per NRC Order
EA-12-049 & INPO IER L1-11-4 (Fukushima Dai-ichi
Accident Response) Unit 2
dated
09/20/2015
Use of Containment Building Polar Crane for Lifts of
Reactor Vessel Upper Internal Lifts Rig
dated
2/19/2016
The acceptable Valve Stroke Times (VST) for valves
1NM-22AC, 1NM-25AC, 1NV-141A, 0RN-10AC, 0RN-
147AC, 0RN148AC, 1RN-64A, 2RN-70A, 1RN-253A, 1
RN-276A, 2RN-279B, 2RN-299A, 1VE-5A, and 2VI-362A
are revised to add
margin to the MOV stroke time for these valves. (10 CFR 50.59 Screen)
dated
2/01/2016
The acceptable Valve Stroke Times (VST) for valves
1NM-22AC,1NM-25AC, 1NV-141A, 0RN-10AC, 0RN-
147AC, 0RN-148AC, 1RN-64A, 2RN-70A, 1RN-253A, 1
RN-276A, 2RN-279B, 2RN-299A, 1VE-5A, and 2VI-362A
are revised to restore margin to the MOV stroke time for
these valves
dated
01/13/2016
PT/1/A/4200/009 A to Support EC-402504.
dated
2/06/2016
PT/2/A/4200/009 A to Support EC-402504 (Rev. 102)
dated
10/25/2016
PT/2/A/4200/009 B to Support EC-402504.
dated
05/10/2016
Revision to Methodology Report DPC-NE-2009-P-A to
Implement WCAP-12610-P-A and CENPD-404-P-A,
Addendum 1-A, Optimized ZIRLO, and Addendum 2-A,
Westinghouse Clad Corrosion Model for ZIRLO and
Optimized ZIRLO
dated
07/21/2016
0000101492 - 000 Unit 1 NI and NV Cold Leg Throttle
Valve Seat Clearance Capital
dated
08/08/2016
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Revise Unit 1 CA Pump Motor Time Overcurrent Relay
Setting
Rev.0
MNS 50.59 evaluation for VIPRE upgrade from mod 2r to
mod
dated
10/27/2016
0000400132 - 000 CA Discharge Piping Design Pressure
Increase Per NCR 01901450
dated
11/28/2016
Replace Bussmann BAF-3A Fuses For 125VDC
dated
11/01/2017
0000410608 - 000 ECCS and NS System Gas Void
Acceptance
dated
01/22/2018
NCR 1655939
Control circuit cable lengths for several motor operated
valves exceed the maximum allowable cable length per
the new revision of MCC 1381.05-00-0147 (Maximum
Allowable Cable Lengths for Size 1 and Size 2 starters at
McGuire)
dated
03/13/2014
NCR 1901864
Update calculation MCC-1381.05-00-0147 R07
(Maximum Allowable Cable Lengths For Size 1 AND 2
Starters at McGuire) for replacement of Starters with 65%
Coil Pickup
dated
2/10/2016
NCR 1903794
Calculation MCC-1381.05-00-0263 has been revised to
Rev. 7 and MNS engineering needs to evaluate the
results and take appropriate actions.
dated
2/06/2018
Corrective Action
Documents
Resulting from
Inspection
NCR 2282169
2019 NRC 50.59 Inspection - 5AD question improper
response
dated
07/16/2019
Drawings
MCFD-1553-01.00
Flow Diagram of Reactor Coolant System (NC)
Rev. 12
MCFD-1554-03.01
Flow Diagram of Chemical & Volume Control
System (NV)
Rev. 25
MCFD-1562-01.00
Flow Diagram of Safety Injection System (NI)
Rev. 12
MCFD-1562-03.00
Flow Diagram of Safety Injection System (NI)
Rev. 18
MCFD-1562-03.01
Flow Diagram of Safety Injection System (NI)
Rev. 15
MCM 1205.00-
0073.001
Swing Check Valve
Rev. A
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
UNIT 1 NI and NV Cold Leg Throttle Valve Seat
Clearance Capital
Rev. 8
RN Strainer Backwash Pump - 1A Mod
Rev. 21
Change Actuator on 2RN-279B From NA2 To NA1E
Rev. 4
Replace 1A EDG Voltage Regulators U1 (MOD)
Rev. 3
RN Suction Overpressure Protection "1A" (OBDN) - Unit
Rev. 8
Revise RN, NM, NV, VE and VI System TAC Sheet Valve
Rev. 0
Equivalency For Joslyn Clark Coil Replacement
Rev. 0
Assured CA Suction For Extended SBO Per NRC
ORDER EA-12-049 & INPO IER L1-11-4
Rev. 9
Allow Replacement of Digital Rod Position Indication
(DRPI) Controller
Rev.0
CA Discharge Piping Design Pressure Increase Per NCR
01901450
Rev. 0
Update Valve Stroke Times For Low Voltage Coil
Installation
Rev. 0
Tune Distributed Control System (DCS) Controls Due to
Hot Leg Streaming
Rev.1
Replace Bussmann BAF-3A Fuses For 125VDC Vital I&C
Distribution Center
Rev. 1
ECCS and NS System Gas Void Acceptance Criteria
Rev. 0
Miscellaneous
DPC-NE-2009-PA
Duke Power Company Westinghouse Fuel Transition
Report
Rev. 3b
MCM-1399.05-
206.01
Vendor Manual-Digital Rod Position Indicator
REv D03
MCM-1399.05-
207.001
Vendor Manual-Digital Rod Position Indicator System
D03
MCS-1206.00-02-
0002
Specification PS 900.2
Rev. 202
MDSS-
0806.EDA.00001
EDA System-Digital Rod Position Indication ( DRPI)
Digital System Specification
Rev. 1
MDSS-
Digital Rod Position Indication System Software and Data Rev. 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0806.EDA.00001
Quality Assurance Plan
Memo To File EC 108775
Coil Comparison for EC108775, Joslyn Clark Coil
Replacement
Rev. 0
Acceptance For Referencing Of Licensing Topical Report
, EPRT NP-2511-CCM, "VIPRE-01: A Thermal -
Hydraulic Analysis Code FOQ Reactor Cores", Volumes
1, 2, 3 and 4
dated
05/01/1986
UFSAR Change
Number 15-51
dated
11/05/2015
UFSAR Change
Number 16-13
dated
01/10/2017
CENPD-404-P-A,
Addendum 1A
Optimized Zirlo
dated July
2006
CENPD-404-P-A,
Addendum 2-A
Westinghouse Clad Corrosion Model for Zirlo and
Optimized Zirlo
dated
October
2013
Procedures
AD-EG-ALL-1155
Post Modification Testing
Rev. 4
AD-EG-ALL-1206
Equipment Reliability Classification
Rev. 4
EDM-601
Engineering Change Manual
Rev. 18
EDM-601
Engineering Directives Manual
Rev. 29
PT/1/A/4200/009A
Engineered Safety Features Actuation Periodic Test
Train A
Rev. 148
PT/1/A/4200/009B
Engineered Safety Features Actuation Periodic Test
Train B
Rev. 17
PT/1/A/4200/017 A
NV To Cold Legs Flow Balance
Rev. 15
PT/1/A/4206/001A
1A NI Pump Performance Test
Rev. 57
PT/2/A/4200/009A
Engineered Safety Features Actuation Periodic Test
Train A
Rev. 107
PT/2/A/4200/009B
Engineered Safety Features Actuation Periodic Test
Train B
Rev. 19
TT/1/A/EC104503/000 Post Modification Testing for EC104503 - EDG 1A
Voltage Regulator Replacement
Rev. 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
20069641-01
DRPI Modification/Validation Test Plan
03/28/16