IR 05000269/2019011
| 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
July 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:
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
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
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.17T Calculations
0079-0222-CALC-
011
Pressurizer Relief Valve Waterhammer Analysis
Rev. 1
KC-2003
Turbine Sump Pump Flow Calculation
Rev. 3
OSC -0995.01-
00-0013
S/R 2-54A-3-0-435B-R10
Rev. 5
OSC-10319
U1/2/3 NFPA 805 Circuit Breaker and Fuse Coordination
Study
Rev. 8
OSC-11087
Unit 3 Main Generator Relay Settings for SEL-300G and
Beckwith M-3425 Relays
Rev. 4
OSC-11796
SSF Letdown Line Release to Rx Building - Containment
Response
Rev. 0
OSC-494
The Discharge side of the Reactor Building Spray Pump line
"2A" System 54A
Piping Analysis Problem No. 2-54-01
Rev. 11
OSC-5501
Containment Response Following Loss of All A.C. Power
Rev. 11
OSC-7413
Post Accident Access Dose Assessment
Rev. 4
Corrective Action
Documents
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
Paper clip and ribbon in SSF Control Room
dated
06/12/2019
2019 50.59 Insp-Incorrect Stmnt in EC 405339 (KHU sump)
dated
06/12/2019
NRC-identified - 2019 50.59 -UFSAR Incorrectly Describe
dated
06/13/2019
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
Section)
Rev. 50
O FD-101A-01-02 Flow Diagram of High Pressure Injection System (Storage
Section)
Rev. 46
O FD-101A-01-03
Flow Diagram of High Pressure Injection System (Charging
Section)
Rev. 34
O FD-101A-01-04
Flow Diagram of High Pressure Injection System (Charging
Section)
Rev. 49
O FD-101A-01-05
Flow Diagram of High Pressure Injection System (SSF
Portion)
Rev. 27
O-0443-406521-
Isometric Piping Layout SF Pool Transfer Header 1SF-2
Replacement
Rev. A
OM 245.-
2583.001, Sht. 1
Velan Bolted Bonnet Gate Valve (Cast) c/w Vent Valves
(Forged)
Rev. G
OSFD-100A-3
Summary Flow Diagram of Emergency Core Cooling and RB
Spray Systems
Rev. 5I
OSFD-107A-1
Summary Flow Diagram of Coolant Storage System Quench
Tank Portion
Rev. 6A
Engineering
Changes
Unit 3 BWST Recirculation Pump Isolation Valve Installation
Rev. 0
Reduce Design Temp for CC [Component Cooling] on Units
1, 2, and 3
Rev. 0
230 KV Yellow Bus Differential Upgrades
Rev. 6
Re-route Unit 1 LPSW [Low Pressure Service Water] Supply
to the MDEFWPS [Motor-driven Feedwater Pumps]
Rev. 0
Dedicated QA-1 Air Accumulators for 1FDW-32, 35, 41, 44
Rev. 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
to Supply Control Air for 2 Hour Mission Time
Unit 1 Replace MSRV Discharge Elbows and Re-stagger
MSRV Setpoints to Allow the Test Acceptance Criteria to Be
Changed to +3%/-3%
Rev. 0
Keowee I&C Cable Separation - PSW Cable Spreading Area
Rev. 0
Modify U2 SSF Letdown Line to Support SSF Operability in
All Modes of Applicability
Rev. 2
Reroute the Keowee Turbine Sump Discharge Piping to the
Keowee Station Sump
Rev. 19
SSF Electrical and DG Design Bases Clarification and
Corrections
Rev. 0
Unit 3 Main Power Protective Relaying Upgrades
Rev. 0
Engineering
Evaluations
DPND-1553.63-
0733
Rev. 0
Miscellaneous
Safety Evaluation by the Office of Nuclear Reactor
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
10/01/1991
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 RE:
ISSUANCE OF AMENDMENTS (TAC NO
MA9597, AND MA9598)
dated
09/26/2001
ISSUANCE OF AMENDMENTS -OCONEE NUCLEAR
STATION, UNITS 1, 2, AND 3 (TAC NO
- S. M99297, M99298,
AND M99299)
dated
2/07/1998
Safety Evaluation by the Office of Nuclear Reactor
Regulation Duke Power Company McGuire Nuclear Station
Docket No. 50-369 and 50-370 Catawba Nuclear Station
Docket Nos. 50-413 and 50-414
dated
04/26/1996
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 -
SAFETY EVALUATION OF REVISIONS TO TOPICAL
REPORTS DPC-NE-3000, -3003, AND -3005 (TAC NOS.
MB5441, MB5442, AND MB5443)
dated
09/24/2003
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 RE:
dated
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SAFETY EVALUATION FOR REVISION 1 TO.TOPICAL
REPORT DPC-NE-3005-P, "UFSAR CHAPTER 15
TRANSIENT-AND ACCIDENT ANALYSIS
METHODOLOGY" (TAC NO
- S. MA4713, MA4714, AND
MA4715)
05/25/1999
REVIEW OF UPDATED FINAL SAFETY ANALYSIS
REPORT, CHAPTER 15, TRANSIENT ANALYSIS
METHODOLOGY SUBMITTAL - OCONEE NUCLEAR
STATION, UNITS 1, 2, AND 3 (TAC NO
- S. M99349, M99350,
AND M99351)
dated
10/01/1998
DPC-NE-3005-A
UFSAR Chapter 15 Transient Analysis Methodology
Rev. 2
Problem Investigation Process No. O-04-2808
Rev. 1
OSS-0027.00-00-
0001
Design Specification for Class A, B, C, D and F Pip Supports
and Restraints
Rev. 15
OSS-0254.00-00-
4005
Design Basis Specification for Design Basis Events
Rev. 34
PRR 02014486
OP/1/A/1104/002
dated
03/25/2016
UFSAR Change
Number 16-019
dated
2/20/2017
UFSAR Change
Number 17-010
AR 2135023-10
dated
11/06/2017
Procedures
AD-EG-All-1122
Failure Modes and Effects Analysis and Single Failure
Analysis
Rev. 1
AD-LS-ALL-0005
UFSAR Updates
Rev. 6
AD-LS-ALL-0007
Applicability Determination Process
Rev. 6
AD-LS-ALL-0008
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
Support Procedures
Rev. 13
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
20010422