IR 05000369/2022010

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000369/2022010 and 05000370/2022010

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: NPF-9 and NPF-17 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations DPC-1552.08-00- McGuire/Catawba Main Steam/Main Feedwater Isolation and Rev. 1

260 Relief Valve Enclosure (Doghouse) Pressurization and

Environmental Response Analysis Due to Pipe Rupture

MCC 1223.02-00- Engineered Safety Features Valve Response Time Testing Rev. 22

0002 Requirements

MCC-1206.02-70- NCA Rev. 15

0004

MCC-1206.02-74- Rigorous Stress Analysis of Piping Math Model CA-351 Rev. 49

28

MCC-1206.02-84- 1A & 1B ND Heat Exchanger Drain Line Piping - Problem RND Rev. 1

2056

MCC-1381.05- Seismic Evaluation for EC 106366 Rev. 0

0194-ICC-0037

MCC-2201.37-00- Replacement Steam Generators, Structural Integrity Rev. 1

0006 Qualification Report for Primary Manway Studs with Hydranuts

MCM 1205.00- Seismic Report-Owners Review for Walworth 4H-3 Rev. 2

0737.001

MCM-1205.10- Design Report for Crosby Relief Valve Model MRV-365 Rev. 0

268.001

Corrective Action AR 00701581 PART 21 ITT ENG VLVS DIAPHRAGM RAD DOSE TESTING 08/05/2014

Documents AR 02047023 Inside Containment Isolation Diaphragm Valves Not Qualified 07/19/2016

AR 02266597 2CFCR5060 CHART RECORDER DARK 04/03/2019

AR 02312924 Replacement Chart Recorders for QA Applications 01/28/2020

Corrective Action NCR 02414285 2022 NRC 50.59 Insp. - EC Screen Q3 Answer Box Not 02/01/2022

Documents Checked

Resulting from

Inspection

Drawings MCEE-214-00.12 McGuire Nuclear Station Unit 2, Elementary Diagram, DG 2B Rev. 8

Load Sequencer

MCEE-214.00.12 McGuire Nuclear Station Unit 2, Elementary Diagram, DG 2B Rev. 9

Load Sequencer

MCFD-1574- Flow Diagram of Nuclear Service Water System (RN) Rev. 14

Inspection Type Designation Description or Title Revision or

Procedure Date

03.01

MCFD-2562- Flow Diagram of Safety Injection System (NI) Rev. 21

03.00

MCFD-2574- Flow Diagram of Nuclear Service Water System (RN) Rev. 31

04.00

MCM 1205.10- O/L MRV-001, 003, 010, 029, 033, 039, 050, 051 Rev. 20

0016.001

MCM 1205.10- Crosby Relief Valve, ASME Section II Class 2 Rev. 0B

263.001

MCM 1205.10- Pressure Relief Valve Rev. B

266.001

MCM 1205.28- O/L for 02D-2001, 3/4 CS Ball Valve; Manual Operator; 300 Rev. 2

25.001 ANSI Class BNL Industries

Engineering EC 0000095873 Replace All Three 125 VDC SSF Battery Charger Mod Rev. 10

Changes EC 00001066366 Replace Panelboard 1EKVC Rev. 0

EC 0000113795 Change the Actuator on 2KC0001A From a Rotork NA2 TO a Rev. 3

Limitorque SMB

EC 0000410765 Replace 1NC-141 and -142 Diaphragm Valves - OBDN Issue Rev. 2

EC 0000413913 Rescale 2D THOT - Average Signal Due to Loss of Rev. 0

2NCRD8280

EC 0000414015 ISSUE ITT GRADE M1 QUALIFICATION FOR INSIDE-CIV Rev. 0

DIAPHRAGMS

EC 0000416799 IMAC Phase II, Motor Current Signature Analysis (MCSA) Rev. 5

EC 0000418961 Digital to Digital Replacement 2CFCR5000 & 5060 Rev. 1

EC 0000420097 U2 D/G Sequencer Reset Contact Change Rev. 3

Engineering AR 01295705 0000101521 - 000 - Steam Generator Primary Manway Nut 03/15/2012

Evaluations Repl with Hydra-Nut U2 Mod

AR 01325096 0000102728 - 002 Installation of Tornado Missile Barriers in 09/11/2013

Steam Valve Enclosure (Doghouse)

AR 01339778 0000401581 - 001 Disable Temperature Control for EDG 02/22/2021

Intercoolers; Configure for Maximum Flow

AR 01347755 EC107430 & EC107431: Adding RN 1B &2B Supplemental 11/12/2014

Vent

AR 01351646 0000113885 - 000 - Replace 1RN-0019 and 1RN-0237 and 5/20/2015

Inspection Type Designation Description or Title Revision or

Procedure Date

Modify Piping Layout

AR 02230818 0000103924 - 000 Change Actuator on 2NI-150B from Rotork 12/04/2018

NA2

AR 02301022 0000102971 - 002 Replace Dresser Relief Valve 1NI-161 12/12/2019

AR 02313145 0000415533 - 002 Replace Dresser Relief Valve 2ND-64 01/29/2020

AR 02388458 0000415977 - 003 Install Thermal Overpressure Relief Line in 07/28/2021

RHR System

MCR-1205.10-00- Technical Requirements for Procurement of ASME Section III Rev. 0

0009 Relief Valves for IST Applications

MCS-1240.03-00- McGuire Nuclear Station Plant Environmental Qualification and Rev. 15

0001 Parameters

MCS-1562.NI-00- Design Basis Specification for the NI System Rev. 31

0001

MCTC-1562- McGuire Nuclear Station, Units 1 & 2 Design Criteria, Rev. 1

NI.V015-01 Operability Requirements and Compensatory Measures,

Testing and Acceptance Criteria Isolation Valves 1/2NI-118A

and -150B

PCD 2000.00-00- Parts Classification for BNL Industries Ball Valves Rev. 3

0030

Miscellaneous McGuire Nuclear Diesel Generator Supplemental Testing

Station Selected

License Condition

16.8.3

McGuire Nuclear Area Temperature Monitoring

Station Selected

License Condition

16.9.16

MCM-1205.04- Diaphragm Life Testing for Duke Power 08/22/1987

277.001

MCS-1205.04-1 Diaphragm-Type Valves to ASME Boiler & Pressure Vessel 12/14/1972

Cole Section III

NAI 8907-09 GOTHIC Containment Analysis Package Qualification Report Rev. 9

Version 7.2a(QA)

PRR 02414484 2022 NRC 50.59 Insp. - Procedure Review for AD-EG-ALL- 02/02/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

1133, Table 1 (50.59/72.48 Exclusion Criteria) Documentation

Requirements

Procedures AD-EG-ALL-1132 AD-EG-ALL-1132, Preparation and Control of Design Change Rev. 19

Engineering Changes

AD-EG-ALL-1133 Preparation and Control of Design Equivalent Change Rev. 15

Engineering Changes

AD-EG-ALL-1134 Preparation and Control of Evaluation Engineering Changes Rev. 6

AD-EG-ALL-1135 Preparation and Control of Configuration Management Rev. 1

Engineering Changes

AD-EG-ALL-1136 Preparation and Control of Commercial Change Engineering Rev. 10

Changes

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 10 CFR 50.59 Review Process Rev. 3

AD-PI-ALL-0100 Corrective Action Program Rev. 26

NSD 209 10 CFR 50.59 Process Rev. 14

PT/1/A/4200/001C Isolation Valve Leak Rate Test Rev. 134

8