IR 05000369/2022010
| ML22047A184 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 02/16/2022 |
| From: | James Baptist, Paul Carman NRC/RGN-II/DRS/EB1 |
| To: | Teresa Ray Duke Energy Carolinas |
| References | |
| 05000369/2022010, 05000370/2022010, IR 2022010 | |
| Download: ML22047A184 (10) | |
Text
February 16, 2022
SUBJECT:
MCGUIRE NUCLEAR STATION - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000369/2022010 AND 05000370/2022010
Dear Mr. Ray:
On February 3, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station and discussed the results of this inspection with Mr. Ed Pigott 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,
/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
Inspection Report
Docket Numbers:
05000369 and 05000370
License Numbers:
Report Numbers:
05000369/2022010 and 05000370/2022010
Enterprise Identifier:
I-2022-010-0020
Licensee:
Duke Energy Carolinas, LLC
Facility:
McGuire Nuclear Station
Location:
Huntersville, North Carolina
Inspection Dates:
January 31, 2022 to February 03, 2022
Inspectors:
P. Carman, Senior Reactor Inspector
T. Fredette, Reactor Operations Engineer
T. Su, Reactor Inspector
Approved By:
James B. Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
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 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 January 31-February 3, 2022.
(1)50.59 Evaluation: EC 102728, Reanalysis of Steam Valve Enclosure (Doghouse)
HELB Pressure Loads Using GOTHIC Code, Rev. 2 (2)50.59 Screening: EC 95873, Replace All Three 125 VDC SSF Battery, Rev. 10 (3)50.59 Screening: EC 102728, Installation of Tornado Missile Barriers in Steam Valve (Doghouse), 09/11/2013 (4)50.59 Screening: EC 102971, Replacement of Dresser Relief Valve 1NI-161, Rev. 4 (5)50.59 Screening: EC 103924, Change Actuator on 2NI-150B from 16NA2-57 to 16NA1E-29, Rev. 1 (6)50.59 Screening: EC 106366, Replace Panelboard 1EKVC, Rev. 0 (7)50.59 Screening: EC 107430, RN (1B) Suction Piping - Supplemental Vent Line, Rev. 10 (8)50.59 Screening: EC 113795, Change the Actuator On 2KC0001A From a Rotork NA2 To a Limitorque SMB, Rev. 3 (9)50.59 Screening: EC 113885, Replace 1RN-19 and 1RN-237 and modify piping layout, Rev. 1 (10)50.59 Screening: EC 401581, Disable Temperature Control for EDG Intercoolers; Configure for Maximum Flow, Rev. 1 (11)50.59 Screening: EC 413913, Rescale 2D THOT - Average Signal Due to Loss Of 2NCRD8280, Rev. 0 (12)50.59 Screening: EC 415533, Replace Dresser Relief Valve 2ND-64, Rev. 2 (13)50.59 Screening: EC 415977, Install Thermal Overpressure Relief Line in RHR System, Rev. 3 (14)50.59 Screening: EC 416799, IMAC Phase II, Motor Current Signature Analysis (MCSA), Rev. 5 (15)50.59 Screening: EC 418961, Digital to Digital Replacement 2CFCR5000 & 5060, Rev. 1 (16)50.59 Screening: EC 420097, U2 D/G Sequencer Reset Contact Change, Rev. 3 (17)50.59 Applicability Determination: EC 101521, Steam Generator Primary Manway Nut Repl with Hydra-Nut U2 Mod, Rev. 2 (18)50.59 Applicability Determination: EC 112840, RHR Flow Transmitter Replacement, Rev. 1 (19)50.59 Applicability Determination: EC 410765, Replace 1NC-141 and -142 Diaphragm Valves - OBDN Issue, Rev 2 (20)50.59 Applicability Determination: EC 412266, Unit 1 NI-60 (Safety Injection Check Valve) Like-for-Like Replacement, Rev. 2 (21)50.59 Applicability Determination: EC 412340, Replace CS Pipe with SS Adjacent to 2RN-277B, Rev. 1 (22)50.59 Applicability Determination: EC 417707, Unit 1 EDG Cooling Water Pipe Hanger/Support - Resolve Installation vs. Design, Rev. 0 (23)50.59 Applicability Determination: EC 419324, Unit 2 RCS Replace Flow Transmitter w/ Rosemount 3154 Series, Rev.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On February 3, 2022, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Ed Pigott and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DPC-1552.08-00-
260
McGuire/Catawba Main Steam/Main Feedwater Isolation and
Relief Valve Enclosure (Doghouse) Pressurization and
Environmental Response Analysis Due to Pipe Rupture
Rev. 1
MCC 1223.02-00-
0002
Engineered Safety Features Valve Response Time Testing
Requirements
Rev. 22
MCC-1206.02-70-
0004
NCA
Rev. 15
MCC-1206.02-74-
28
Rigorous Stress Analysis of Piping Math Model CA-351
Rev. 49
MCC-1206.02-84-
2056
1A & 1B ND Heat Exchanger Drain Line Piping - Problem RND
Rev. 1
MCC-1381.05-
0194-ICC-0037
Seismic Evaluation for EC 106366
Rev. 0
MCC-2201.37-00-
0006
Replacement Steam Generators, Structural Integrity
Qualification Report for Primary Manway Studs with Hydranuts
Rev. 1
MCM 1205.00-
0737.001
Seismic Report-Owners Review for Walworth 4H-3
Rev. 2
Calculations
MCM-1205.10-
268.001
Design Report for Crosby Relief Valve Model MRV-365
Rev. 0
PART 21 ITT ENG VLVS DIAPHRAGM RAD DOSE TESTING
08/05/2014
Inside Containment Isolation Diaphragm Valves Not Qualified
07/19/2016
2CFCR5060 CHART RECORDER DARK
04/03/2019
Corrective Action
Documents
Replacement Chart Recorders for QA Applications
01/28/2020
Corrective Action
Documents
Resulting from
Inspection
22 NRC 50.59 Insp. - EC Screen Q3 Answer Box Not
Checked
2/01/2022
MCEE-214-00.12
McGuire Nuclear Station Unit 2, Elementary Diagram, DG 2B
Load Sequencer
Rev. 8
MCEE-214.00.12
McGuire Nuclear Station Unit 2, Elementary Diagram, DG 2B
Load Sequencer
Rev. 9
Drawings
MCFD-1574-
Flow Diagram of Nuclear Service Water System (RN)
Rev. 14
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
03.01
MCFD-2562-
03.00
Flow Diagram of Safety Injection System (NI)
Rev. 21
MCFD-2574-
04.00
Flow Diagram of Nuclear Service Water System (RN)
Rev. 31
MCM 1205.10-
0016.001
O/L MRV-001, 003, 010, 029, 033, 039, 050, 051
Rev. 20
MCM 1205.10-
263.001
Crosby Relief Valve, ASME Section II Class 2
Rev. 0B
MCM 1205.10-
266.001
Pressure Relief Valve
Rev. B
MCM 1205.28-
25.001
O/L for 02D-2001, 3/4 CS Ball Valve; Manual Operator; 300
ANSI Class BNL Industries
Rev. 2
Replace All Three 125 VDC SSF Battery Charger Mod
Rev. 10
EC 00001066366
Replace Panelboard 1EKVC
Rev. 0
Change the Actuator on 2KC0001A From a Rotork NA2 TO a
Limitorque SMB
Rev. 3
Replace 1NC-141 and -142 Diaphragm Valves - OBDN Issue
Rev. 2
Rescale 2D THOT - Average Signal Due to Loss of
2NCRD8280
Rev. 0
ISSUE ITT GRADE M1 QUALIFICATION FOR INSIDE-CIV
Rev. 0
IMAC Phase II, Motor Current Signature Analysis (MCSA)
Rev. 5
Digital to Digital Replacement 2CFCR5000 & 5060
Rev. 1
Engineering
Changes
U2 D/G Sequencer Reset Contact Change
Rev. 3
0000101521 - 000 - Steam Generator Primary Manway Nut
Repl with Hydra-Nut U2 Mod
03/15/2012
0000102728 - 002 Installation of Tornado Missile Barriers in
Steam Valve Enclosure (Doghouse)
09/11/2013
0000401581 - 001 Disable Temperature Control for EDG
Intercoolers; Configure for Maximum Flow
2/22/2021
EC107430 & EC107431: Adding RN 1B &2B Supplemental
Vent
11/12/2014
Engineering
Evaluations
0000113885 - 000 - Replace 1RN-0019 and 1RN-0237 and
5/20/2015
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Modify Piping Layout
0000103924 - 000 Change Actuator on 2NI-150B from Rotork
NA2
2/04/2018
0000102971 - 002 Replace Dresser Relief Valve 1NI-161
2/12/2019
0000415533 - 002 Replace Dresser Relief Valve 2ND-64
01/29/2020
0000415977 - 003 Install Thermal Overpressure Relief Line in
RHR System
07/28/2021
MCR-1205.10-00-
0009
Technical Requirements for Procurement of ASME Section III
Relief Valves for IST Applications
Rev. 0
MCS-1240.03-00-
0001
McGuire Nuclear Station Plant Environmental Qualification and
Parameters
Rev. 15
MCS-1562.NI-00-
0001
Design Basis Specification for the NI System
Rev. 31
MCTC-1562-
NI.V015-01
McGuire Nuclear Station, Units 1 & 2 Design Criteria,
Operability Requirements and Compensatory Measures,
Testing and Acceptance Criteria Isolation Valves 1/2NI-118A
and -150B
Rev. 1
PCD 2000.00-00-
0030
Parts Classification for BNL Industries Ball Valves
Rev. 3
McGuire Nuclear
Station Selected
License Condition
16.8.3
Diesel Generator Supplemental Testing
McGuire Nuclear
Station Selected
License Condition
16.9.16
Area Temperature Monitoring
MCM-1205.04-
277.001
Diaphragm Life Testing for Duke Power
08/22/1987
MCS-1205.04-1
Diaphragm-Type Valves to ASME Boiler & Pressure Vessel
Cole Section III
2/14/1972
NAI 8907-09
GOTHIC Containment Analysis Package Qualification Report
Version 7.2a(QA)
Rev. 9
Miscellaneous
PRR 02414484
22 NRC 50.59 Insp. - Procedure Review for AD-EG-ALL-
2/02/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1133, Table 1 (50.59/72.48 Exclusion Criteria) Documentation
Requirements
AD-EG-ALL-1132
AD-EG-ALL-1132, Preparation and Control of Design Change
Engineering Changes
Rev. 19
AD-EG-ALL-1133
Preparation and Control of Design Equivalent Change
Engineering Changes
Rev. 15
AD-EG-ALL-1134
Preparation and Control of Evaluation Engineering Changes
Rev. 6
AD-EG-ALL-1135
Preparation and Control of Configuration Management
Engineering Changes
Rev. 1
AD-EG-ALL-1136
Preparation and Control of Commercial Change Engineering
Changes
Rev. 10
AD-EG-ALL-1137
Engineering Change Product Selection
Rev. 10
AD-EG-ALL-1157
Engineering of Plant Digital Systems and Components
Rev. 6
AD-LS-ALL-0005
UFSAR Updates
Rev. 9
AD-LS-ALL-0007
Applicability Determination Process
Rev. 8
AD-LS-ALL-0008
CFR 50.59 Review Process
Rev. 3
AD-PI-ALL-0100
Corrective Action Program
Rev. 26
NSD 209
CFR 50.59 Process
Rev. 14
Procedures
PT/1/A/4200/001C
Isolation Valve Leak Rate Test
Rev. 134