IR 05000269/2019011

NRC Evaluation of Changes, Tests, and Experiments Report Number 05000269/2019011 and 05000270/2019011 and 05000287/2019011

ML19186A018
Person / Time
Site:	Oconee
Issue date:	07/03/2019
From:	James Baptist Division of Reactor Safety I
To:	Burchfield J Duke Energy Carolinas
References
IR 2019011
Download: ML19186A018 (11)

Text

uly 3, 2019

SUBJECT:

OCONEE NUCLEAR STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS REPORT NUMBER 05000269/2019011 AND 05000270/2019011 AND 05000287/2019011

Dear Mr. Burchfield,

On June 14, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Oconee Nuclear Station and discussed the results of this inspection with you 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: Jonathan M. Montgomery for/

James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000269 and 05000270 and 05000287 License Nos.: DPR-38 and DPR-47 and DPR-55

Enclosure:

NRC IR 05000269/2019011, 270/2019011 and 287/2019011

Inspection Report

Docket Numbers: 05000269, 05000270 and 05000287 License Numbers: DPR-38, DPR-47 and DPR-55 Report Numbers: 05000269/2019011, 05000270/2019011 and 05000287/2019011 Enterprise Identifier: I-2019-011-0004 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station Location: Seneca, SC Inspection Dates: June 10, 2019 to June 14, 2019 Inspectors: N. Morgan, Reactor Inspector G. Ottenberg, Senior Reactor Inspector M. Schwieg, 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 NRC inspection at Oconee 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 were identified.

INSPECTION SCOPE

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 June 10, 2019, to June 14, 2019.

(1) 50.59 Evaluation- AR 2089921, 230KV Yellow Bus Differential Upgrade (EC 112284)

(2) 50.59 Evaluation- AR 1351688, Unit 3 Main Power System Protective Relaying Upgrade (EC 96549)

(3) Applicability Determination- AR 2021192, 5AD for TT/3/A/0500/003 Rev 001

(4) 50.59 Evaluation- AR 1995154, Unit 3 BWST Recirculate Isolation (EC 109548)

(5) Applicability Determination- AR 2038726, Additional pressurizer breaker operations

(6) Applicability Determination- AR 2070884, Open open breaker prior to manual valve operation

(7) 50.59 Screening- AR 1989410, KEOWEE I&C Cable Separation - PSW Cable Spreading Area (EC 400196)

(8) 50.59 Screening- AR 2218386, SSF Electrical and DG Design Bases Clarification and Corrections (EC 410953)

(9) 50.59 Evaluation- AR 1350547, Change from End-of-Cycle Hot Full Power Moderator Temperature Coefficient of -35.0 pcm/F to -38.0 pcm/F

(10) 50.59 Evaluation- AR 2050877, Modify the Unit 2 RCS Letdown Line to Support SSF Operability in All Modes (EC 403752)

(11) Applicability Determination- AR 2014500, Add Guidance to Operate 1HP-119 if Needed in New Enclosure of OP/1/A/1104/002 (HPI System)

(12) 50.59 Screening- AR 2214631, 5SCR for new AP/0/A/1700/048 (Loss of a Startup Transformer)

(13) 50.59 Screening- AR 1978046, Dedicated QA-1 Air Accumulators for 1FDW-32, 35, 41, 44 to Supply Control Air (EC 114334)

(14) 50.59 Screening- AR 1998265, Unit 1 Replace MSRV Discharge Elbows and Re-stagger MSRV Setpoints to Allow the Test Acceptance Criteria to Be Changed to

+3%/-3% (EC 114919)

(15) 50.59 Evaluation- AR 02177848, 10 CFR 50.59 Evaluation for EC 405339 Rev 1 -

Reroute the Keowee Turbine Sump Discharge Piping to the Keowee Station Sump to Prevent Oil Discharging to the Tailrace

(16) 50.59 Evaluation- AR 02246774, Revision to UFSAR Section 9.1.5

(17) 50.59 Screening- AR 01342323, EC109885 - 000 - Reduce Design Temp for CC on Units 1, 2, and 3

(18) 50.59 Screening- AR 01979852, EC113381 - 000 - RE-route Unit 1 LPSW Supply to the MDEFWPS

(19) 50.59 Screening- AR 02102666, 50.59 Screen for EC 115310

(20) 50.59 Screening- AR 02174461, EC407469, EC407470, EC407471, EC408304, EC408556, EC408922, and EC408924 - Replace 6", Class C, Buried SSF ASW Piping for UNITS 1, 2, and 3. 10 CFR 50.59 Screening Rev. 4 addresses replacing the Unit 3 SSF ASW Piping and installing heat trace on the Unit 3 SSF ASW Piping

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On June 14, 2019, the inspectors presented the NRC inspection results to J. Ed Burchfield, Jr. and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations 0079-0222-CALC- Pressurizer Relief Valve Waterhammer Analysis Rev. 1

011

KC-2003 Turbine Sump Pump Flow Calculation Rev. 3

OSC -0995.01- S/R 2-54A-3-0-435B-R10 Rev. 5

00-0013

OSC-10319 U1/2/3 NFPA 805 Circuit Breaker and Fuse Coordination Rev. 8

Study

OSC-11087 Unit 3 Main Generator Relay Settings for SEL-300G and Rev. 4

Beckwith M-3425 Relays

OSC-11796 SSF Letdown Line Release to Rx Building - Containment Rev. 0

Response

OSC-494 The Discharge side of the Reactor Building Spray Pump line Rev. 11

"2A" System 54A

Piping Analysis Problem No. 2-54-01

OSC-5501 Containment Response Following Loss of All A.C. Power Rev. 11

OSC-7413 Post Accident Access Dose Assessment Rev. 4

Corrective Action AR 01351688

Documents AR 01816298

AR 01989410

AR 01995154

AR 02021192

AR 02021192

AR 02038726

AR 02070884

AR 02218386

AR 02246773

NCR 01792806

NCR 01905100

NCR 01905214

NCR 01906479

Inspection Type Designation Description or Title Revision or

Procedure Date

Corrective Action NCR 02277117 Paper clip and ribbon in SSF Control Room dated

Documents 06/12/2019

Resulting from NCR 02277126 2019 50.59 Insp-Incorrect Stmnt in EC 405339 (KHU sump) dated

Inspection 06/12/2019

NCR 02277256 NRC-identified - 2019 50.59 -UFSAR Incorrectly Describe dated

AFIS 06/13/2019

NCR 02277421 2019 50.59: EC Analysis Documentation dated

06/13/2019

Drawings KFD-102A-01-01 Flow Diagram of Turbine Sump Pump System Rev. 8C

O FD-101A-01-01 Flow Diagram of High Pressure Injection System (Letdown Rev. 50

Section)

O FD-101A-01-02 Flow Diagram of High Pressure Injection System (Storage Rev. 46

Section)

O FD-101A-01-03 Flow Diagram of High Pressure Injection System (Charging Rev. 34

Section)

O FD-101A-01-04 Flow Diagram of High Pressure Injection System (Charging Rev. 49

Section)

O FD-101A-01-05 Flow Diagram of High Pressure Injection System (SSF Rev. 27

Portion)

O-0443-406521- Isometric Piping Layout SF Pool Transfer Header 1SF-2 Rev. A

Replacement

OM 245.- Velan Bolted Bonnet Gate Valve (Cast) c/w Vent Valves Rev. G

2583.001, Sht. 1 (Forged)

OSFD-100A-3 Summary Flow Diagram of Emergency Core Cooling and RB Rev. 5I

Spray Systems

OSFD-107A-1 Summary Flow Diagram of Coolant Storage System Quench Rev. 6A

Tank Portion

Engineering EC 109548 Unit 3 BWST Recirculation Pump Isolation Valve Installation Rev. 0

Changes EC 109885 Reduce Design Temp for CC [Component Cooling] on Units Rev. 0

1, 2, and 3

EC 112284 230 KV Yellow Bus Differential Upgrades Rev. 6

EC 113381 Re-route Unit 1 LPSW [Low Pressure Service Water] Supply Rev. 0

to the MDEFWPS [Motor-driven Feedwater Pumps]

EC 114334 Dedicated QA-1 Air Accumulators for 1FDW-32, 35, 41, 44 Rev. 1

Inspection Type Designation Description or Title Revision or

Procedure Date

to Supply Control Air for 2 Hour Mission Time

EC 114919 Unit 1 Replace MSRV Discharge Elbows and Re-stagger Rev. 0

MSRV Setpoints to Allow the Test Acceptance Criteria to Be

Changed to +3%/-3%

EC 400196 Keowee I&C Cable Separation - PSW Cable Spreading Area Rev. 0

EC 403752 Modify U2 SSF Letdown Line to Support SSF Operability in Rev. 2

All Modes of Applicability

EC 405339 Reroute the Keowee Turbine Sump Discharge Piping to the Rev. 19

Keowee Station Sump

EC 410953 SSF Electrical and DG Design Bases Clarification and Rev. 0

Corrections

EC 96549 Unit 3 Main Power Protective Relaying Upgrades Rev. 0

Engineering DPND-1553.63- ONS MSSV Setpoint Re-Stagger Rev. 0

Evaluations 0733

Miscellaneous Safety Evaluation by the Office of Nuclear Reactor 10/01/1991

Regulation, Alternative Testing for Reactor Vessel Head and

Internal Lifting Rigs, Tennessee Valley Authority, Sequoyah

Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-

28

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 RE: dated

ISSUANCE OF AMENDMENTS (TAC NO

S. MA9596, 09/26/2001

MA9597, AND MA9598)

ISSUANCE OF AMENDMENTS -OCONEE NUCLEAR dated

STATION, UNITS 1, 2, AND 3 (TAC NO

S. M99297, M99298, 12/07/1998

AND M99299)

Safety Evaluation by the Office of Nuclear Reactor dated

Regulation Duke Power Company McGuire Nuclear Station 04/26/1996

Docket No. 50-369 and 50-370 Catawba Nuclear Station

Docket Nos. 50-413 and 50-414

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 - dated

SAFETY EVALUATION OF REVISIONS TO TOPICAL 09/24/2003

REPORTS DPC-NE-3000, -3003, AND -3005 (TAC NO

S.

MB5441, MB5442, AND MB5443)

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 RE: dated

Inspection Type Designation Description or Title Revision or

Procedure Date

SAFETY EVALUATION FOR REVISION 1 TO.TOPICAL 05/25/1999

REPORT DPC-NE-3005-P, "UFSAR CHAPTER 15

TRANSIENT-AND ACCIDENT ANALYSIS

METHODOLOGY" (TAC NO

S. MA4713, MA4714, AND

MA4715)

REVIEW OF UPDATED FINAL SAFETY ANALYSIS dated

REPORT, CHAPTER 15, TRANSIENT ANALYSIS 10/01/1998

METHODOLOGY SUBMITTAL - OCONEE NUCLEAR

STATION, UNITS 1, 2, AND 3 (TAC NO

S. M99349, M99350,

AND M99351)

DPC-NE-3005-A UFSAR Chapter 15 Transient Analysis Methodology Rev. 2

LER 269/2004-02 Problem Investigation Process No. O-04-2808 Rev. 1

OSS-0027.00-00- Design Specification for Class A, B, C, D and F Pip Supports Rev. 15

0001 and Restraints

OSS-0254.00-00- Design Basis Specification for Design Basis Events Rev. 34

4005

PRR 02014486 OP/1/A/1104/002 dated

03/25/2016

UFSAR Change AR 02094629 dated

Number 16-019 02/20/2017

UFSAR Change AR 2135023-10 dated

Number 17-010 11/06/2017

Procedures AD-EG-All-1122 Failure Modes and Effects Analysis and Single Failure Rev. 1

Analysis

AD-LS-ALL-0005 UFSAR Updates Rev. 6

AD-LS-ALL-0007 Applicability Determination Process Rev. 6

AD-LS-ALL-0008 10 CFR 50.59 Review Process Revs. 0 and

AP/0/A/2000/002 Keowee Hydro Station - Emergency Start Rev. 20

OMP 4-02 Verification and Validation Process for APs, EOP, and Rev. 13

Support Procedures

OP/2/A/1103/005 Pressurizer Operation Rev. 47

OP/2/A/1104/004 Low Pressure Injection System Rev. 166

TT/3/A/0500/003 Protected Service Water Injection to SG 3A & 3B Rev. 1

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 20010422

9