IR 05000400/2019001
| ML19130A153 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/10/2019 |
| From: | Lundy Pressley NRC/RGN-II/DRP/RPB4 |
| To: | Hamilton T Duke Energy Progress |
| References | |
| IR 2019001 | |
| Download: ML19130A153 (16) | |
Text
May 10, 2019
SUBJECT:
SHEARON HARRIS UNIT 1 - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000400/2019001
Dear Ms. Hamilton:
On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Shearon Harris Unit 1. On April 10, 2019, the NRC inspectors 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.
No NRC-identified or self-revealing findings were identified during this inspection.
However, inspectors documented a licensee-identified violation which was determined to be of very low safety significance in this report. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident inspector at the Shearon Harris Nuclear Power Plant. 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/
Lundy F. Pressley, Acting Chief Reactor Projects Branch 4 Division of Reactor Projects Docket No.: 05000400 License No.: NPF-63
Enclosure:
Inspection Report 05000400/2019001
Inspection Report
Docket Number:
05000400
License Number:
Report Number:
Enterprise Identifier: I-2019-001-0025
Licensee:
Duke Energy Progress, LLC
Facility:
Shearon Harris, Unit 1
Location:
New Hill, NC 27562
Inspection Dates:
January 01, 2019 to March 31, 2019
Inspectors:
J. Zeiler, Senior Resident Inspector
A. Patz, Resident Inspector
S. Downey, Senior Reactor Inspector (Section 71152.2)
Approved By:
Lundy F. Pressley, Acting Chief
Reactor Projects Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a quarterly inspection at Harris, Unit 1 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. Findings and violations being considered in the NRCs assessment are summarized in the table below. A licensee-identified non-cited violation is documented in report section 7115
List of Findings and Violations
No findings were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 operated at or near rated thermal power for the entire inspection period.
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 performed plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 02.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) A boric acid transfer system during B boric acid transfer pump unavailability on January 3, 2019 (2)
'B' emergency service water (ESW) pump and 'B' ESW booster pump while 'A' ESW pump and 'A' ESW booster pump was out-of-service for preventive maintenance on January 15, 2019 (3)
'A' containment spray (CS) pump while 'B' CS pump was out-of-service for preventive maintenance on February 5, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) ESW intake structure and yard area (fire zones 12-I-ESWPA, 12-I-ESWPA-BAL, 12-I-ESWPB, 12-I-ESWPB-BAL, and 12-I-ESW-BAL) on January 15, 2019
- (2) Reactor auxiliary building (RAB) 190' elevation 'A' residual heat removal (RHR)and CS pump room (fire zone 1-A-1-PA) on February 5, 2019
- (3) RAB 216' elevation mechanical penetration room, south corridor, and ESW pipe tunnel (fire zones 1-A-2-MP, 1-A-2-COR, and 1-A-2-PT) on February 6, 2019
- (4) RAB 286' elevation 'B' electrical switchgear and ventilation rooms (fire zones 1-A-SWGRB and 1-A-5-HVB) on February 13, 2019
- (5) RAB 236' elevation chemical and volume control system (CVCS) area (fire zone 1-A-3-COMB) on February 15, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the RAB 216' elevation on February 14, 2019.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
The inspectors observed and evaluated licensed operator performance in the control room during 'A' train reactor trip breaker and solid state protection system testing on March 18, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated a simulator scenario for operator requalification training involving a small-break loss-of-coolant accident on February 19, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Containment ventilation isolation radiation monitor 3561C failed to alarm when tested on November 7, 2018
- (2) Loose fan belts on 'A' RHR/CS pump room air handler system resulting in fan speed below minimum requirements on December 31, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Elevated (Green) risk during planned unavailability of the 'A' ESW pump and 'A' ESW booster pump for preventive maintenance on January 15, 2019
- (2) Elevated (Green) risk during planned unavailability of the 'B' CS pump for seal water piping inspections on February 5, 2019
- (3) Elevated (Green) risk during emergent repair of power range nuclear instrument channel NI-41 following inoperability due to anomalous upper detector high current on February 11, 2019
- (4) Elevated (Green) risk during planned unavailability of the 'B' emergency safeguards sequencer for relay calibration and replacement on February 13, 2019
- (5) Elevated (Green) risk during planned unavailability of the 'A' motor driven auxiliary feedwater (AFW) pump for preventive maintenance on February 19, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determinations and Functionality Assessments Sample (IP Section 02.01) (4 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Leakage of diaphragm valves in the emergency core cooling system (ECCS)recirculation flow path on January 15, 2019 (nuclear condition reports (NCRs) 02252508 and 02252515)
- (2) Increased levels of particulate found in oil of 'A' component cooling water (CCW)pump inboard bearing on January 31, 2019 (NCR 02255195)
- (3) Gas voids found in piping upstream of 'B' CS pump discharge containment isolation valve 1CT-88 on February 20, 2019 (NCR 02258496)
(4)
'A' train emergency diesel generator auxiliary lube oil pump tripped after starting on March 21, 2019 (NCR 02264131)
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modification:
- (1) Installation of wireless electronic equipment in the nuclear plant power block including control room
71111.19 - Post Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Operations surveillance test (OST)-1214, ESW System Operability Train A Quarterly Interval Modes 1-2-3-4-5-Defueled, following scheduled preventive maintenance on the 'A' ESW pump and 'A' ESW booster pump on January 15, 2019
- (2) OST-1122, Train A 6.9 kV Emergency Bus Undervoltage Trip Actuating Device Operational Test and Contact Check, following corrective replacement of the turbine driven AFW pump governor positioner on January 19, 2019
- (3) Technical Procedure Testing (OPT)-1512, Train B Essential Chilled Water Turbopak Units Quarterly Inspection and Checks, following preventive maintenance on the B essential services chilled water (ESCW) chiller on January 29, 2019
- (4) OST-1119, Containment Spray Operability Train B Quarterly Interval Modes 1-4, following scheduled preventive maintenance on the 'B' CS pump on February 5, 2019
- (5) OST-1211, Auxiliary Feedwater Pump 1A-SA Operability Test Quarterly Interval Modes 1-4, and OST-1077, Auxiliary Feedwater Valves Operability Test Quarterly Interval Mode 4-5-6, following scheduled preventive maintenance on the 'A' motor driven AFW pump motor and discharge pressure control valve on February 19, 2019
- (6) Operating Procedure (OP)-145, Component Cooling Water, for operating the 'B' CCW pump following pump inrush current testing on March 4, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
FLEX Testing (IP Section 03.02)
Work orders (WO) 20281145-02 and 20281145-03, Perform quarterly functional tests of FLEX diesel generators 1FLX-E042 and 1FLX-E043, on March 6, 2019
In Service Testing (IST) (IP Section 03.01) (1 Sample)
OST-1093, CVCS/Safety Injection System Operability Train B Quarterly Interval Modes 1-4, on January 3, 2019
Reactor Coolant System (RCS) Leak Detection (IP Section 03.01) (1 Sample)
OST-1026, Reactor Coolant System Leakage Evaluation, Computer Calculation, Daily Interval, Modes 1-4, on March 22, 2019
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) OST-1076, Auxiliary Feedwater Pump 1B-SB Operability Test Quarterly Interval Modes 1-4, on January 7, 2019
- (2) OPT-1538, Emergency Safeguards Sequencer System Test - Train B Quarterly Interval Modes 1-6, on February 13,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
Unit 1 (January 1, 2018 - December 31, 2018)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
Unit 1 (January 1, 2018 - December 31, 2018)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
Unit 1 (January 1, 2018 - December 31, 2018)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) TS 3.0.3 entered for both trains of containment vacuum relief rendered inoperable during maintenance on containment ventilation isolation radiation monitors (NCR 02244746)
- (2) Operating experience smart sample (OpESS) 2018/01, 10 CFR Part 21 notification of the potential existence of defects related to control rod drive mechanism (CRDM)thermal sleeves (NCRs 02220429, 02208989)
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71152 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Technical Specification (TS) 3.6.5, Vacuum Relief System, requires two containment vacuum relief trains shall be operable in Modes 1, 2, 3, and 4. The associated action statement for TS 3.6.5 with one inoperable containment vacuum relief train requires the inoperable train to be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Since there is no TS action statement addressing inoperability of both containment vacuum relief trains, the limiting condition for operation associated with TS 3.0.3 applies. TS 3.0.3 requires, within one hour, action shall be initiated to place the unit in a mode in which (TS 3.6.5) does not apply and be in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and cold shutdown within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Contrary to the above, on November 20, 2018, while in Mode 1, the licensee failed to follow the action requirements of TS 3.0.3, in that, within one hour of entering TS 3.0.3, after both containment vacuum relief trains were rendered inoperable, actions were not initiated to place the unit in a mode in which TS 3.6.5 did not apply. TS 3.0.3 was exited 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 18 minutes from the time both containment vacuum relief valves were initially rendered inoperable. Both containment vacuum relief trains were rendered inoperable during planned maintenance to replace the electrical breakers to containment ventilation isolation radiation monitors 3561A and 3561C. When both radiation monitors were de-energized for this planned work, a containment ventilation isolation signal (CVIS) was generated as designed, which prevents opening containment ventilation systems, including both A and B train containment vacuum relief valves. While reviewing procedural guidance for returning the radiation monitors to service and resetting CVIS after the work was completed, the operators realized that the containment vacuum relief system had been impacted and TS 3.0.3 had been applicable.
Significance: Green. The inspectors assessed the significance of the finding using IMC 0609, Appendix A, Significance Determination Process for Findings At-Power, dated June 19, 2012. The finding was screened using Exhibit 3, Barrier Integrity Screening Questions, since it was associated with a degraded containment pressure control system. The finding was determined to be of very low safety significance (Green) because it did not represent an actual open pathway in the physical integrity of containment or partial failure of containment isolation systems or containment heat removal components; and Harris does not have hydrogen igniters.
Corrective Action Reference: NCR
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 10, 2019, the inspectors presented the quarterly resident inspector inspection results to Ms. Tanya Hamilton, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Chemical and Volume Control
Revision 117
Containment Spray System
Revision 46
Service Water System
Revision 136
71111.05Q Fire Plans
CSD-HNP-PFP-
RAB-190-216
Reactor Auxiliary Building Elevations 190 and 216 Pre-Fire
Plan
Revision 1
CSD-HNP-PFP-
RAB-236
Reactor Auxiliary Building Elevation 236 Pre-Fire Plan
Revision 2
CSD-HNP-PFP-
SEC
Out Building Pre-Fire Plan
Revision 4
CSD-HNP-RAB-
286
Reactor Auxiliary Building Elevation 286 Pre-Fire Plan
Revision 1
Miscellaneous
Fire Protection
Permit and
Impairment Log
Entries
Procedures
AD-EG-ALL-1520
Transient Combustible Control
Revision 11
Fire Protection Program Manual
Revision 44
Fire Protection - Minimum Requirements, Mitigation Actions
and Surveillance Requirements
Revision 99
Calculations
PRA-F-E-004
Reactor Auxiliary Building Unit 1 Elevation 190' & 216'
Internal Flooding Analysis
Revision 8
71111.11Q Procedures
AD-OP-All-0106
Conduct of Infrequently Performed Test or Evolution
Revision 4
AD-OP-ALL-1000
Conduct of Operations
Revision 15
AD-TQ-ALL-0420
Conduct of Simulator Training and Evaluation
Revision 14
Loss of One Emergency AC Bus (6.9kV) or One Emergency
DC Bus (125V)
Revision 42
AP-002
Plant Conduct of Operations
Revision 73
Reactor Trip or Safety Injection
Revision 12
Train A Solid State Protection System Actuation Logic &
Master Relay Test
Revision 38
OMM-001
Operations Administrative Requirements
Revision 114
OMM-014
Operation of the Work Coordination Center
Revision 73
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Rod Control System
Revision 43
Work Orders
Conduct SSPS Testing on 'A' Train
Calculations
HNP-F/PSA-0020
HNP PRA Evaluation of Risk Significant SSCs for
Maintenance Rule
Revision 1
HNP-F/PSA-0065
Revision 8
Corrective Action
Documents
Containment ventilation isolation radiation monitor 3561C
failed to alarm when tested
Loose fan belts on 'A' RHR/CS pump room air handler
system
Miscellaneous
Industry Guideline for Monitoring the Effectiveness of
Maintenance at Nuclear Power Plants
Revision 4A
Procedures
AD-EG-ALL-1210
Revision 1
Reactor Trip Response
Revision 5
OWP-RM
Radiation, Effluent, and Explosive Gas Monitoring
Revision 45
Work Orders
Perform MST-I0347 to determine cause of electronic spikes
on RM-01CR-3561ASA
Repair loose belts on 'A' RHR/CS pump room air handler
Procedures
AD-NF-ALL-0501
Electronic Risk Assessment Tool (ERAT)
Revision 3
AD-OP-ALL-0201
Protected Equipment
Revision 5
AD-OP-ALL-1000
Conduct of Operations
Revision 15
AD-WC-ALL-
200
On-Line Work Management
Revision 13
AD-WC-ALL-
240
On-Line Risk Management Process
Revision 1
AD-WC-ALL-
0410
Work Activity Integrated Risk Management
Revision 7
OMM-001
Conduct of Operations
Revision 114
Work Orders
Lubrication of 'A' ESW booster pump coupling
Tighten seal water piping connection on 'A' containment
spray pump
Preventive maintenance on 'A' ESW stuffing box and seal
water cooling system
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Replace actuator oil in 'A' AFW discharge control valve
Repair emergent issue with N-41 upper detector reading
high
WOs 20181791,
266115, and
266116
'B' train sequencer relay calibrations and replacement
Corrective Action
Documents
Copper detected in CCW pump bearing oil sample
Oil sample particulate results for the 'A' CCW pump
Procedures
AD-OP-ALL-0105
Operability Determinations and Functionality Assessments
Revision 4
AD-OP-ALL-0202
Aggregate Operator Impact Assessment
Revision 2
Chemical and Volume Control System
Revision 24
Containment Spray System
Revision 17
Component Cooling Water System
Revision 17
Emergency Diesel Generator System
Revision 18
OST-1013
1A-SA Emergency Diesel Generator Operability Test
Monthly Interval Modes 1-6
Revision 43
OST-1107
ECCS/Containment Spray Flow Path and Piping Filled
Verification Monthly Interval Modes 1-6
Revision 36
PM-M0102
3/8 - 6 Inch Diaphragm Valve Nonmetallic Component
Replacement
Revision 6
Work Orders
Evaluate gas voids
Engineering
Changes
Non-Controlled Plant Equipment Wireless Emitting Device
Installation
Revision 1
Electromagnetic Interference Proximity for Transceivers
Revision 3
Miscellaneous
Guidelines for 10 CFR 50.59 Evaluations Endorsed by
Revision 1
Guidance for Implementation of 10 CFR 50.59, dated
November 2000
Procedures
AD-EG-ALL-1110
Design Review Requirements
Revision 6
AD-EG-ALL-1130
Activation of Engineering Changes
Revision 2
AD-EG-ALL-1132
Preparation and Control of Design Change Engineering
Changes
Revision 13
AD-EG-ALL-1137
Engineering Change Product Selection
Revision 5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AD-LS-ALL-0008
CFR 50.59 Review Process
Revision 0
Work Orders
Install wireless emitting device and hardware for main control
room
Procedures
PLP-400
Post Maintenance Testing
Revision 64
Work Orders
Lubrication of 'A' ESW booster pump coupling
Tighten seal water piping connection on 'A' containment
spray pump
Obtain one set of inrush current data
Preventive maintenance on 'A' ESW stuffing box and seal
water cooling system
Replace actuator oil in 'A' AFW discharge control valve
VMS-2, Determine available adjustment for future
modification
TDAFW pump tripped while starting during OST-1044
Procedures
CSD-EG-HNP-
8888
Flexible Response to Extended Loss of ALL AC Power
Revision 0
ISI-800
Inservice Testing of Pumps
Revision 30
OST-1093
Completed procedures on January 14, 2015, and January
2, 2017
PD-OP-ALL-0500
Diverse and Flexile Coping Strategies FLEX Program
Revision 1
71151
Miscellaneous
2018 Licensee
Event Reports
2018 Operator
Log Entries
Regulatory Assessment Performance Indicator Guideline
Procedures
AD-LS-ALL-0004
NRC Performance Indicators and Monthly Operating Report
Revision 3
Engineering
Changes
2571
HNP RFO-21 Thermal Sleeve Flange Upper Flange Wear
Inspection Results
Revision 0
Procedures
AD-LS-ALL-0006
Notification/Reportability Evaluation
Revision 1
AD-PI-ALL-0100
Corrective Action Program
Revision 20
AD-PI-ALL-0102
Apparent Cause Evaluation
Revision 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AD-PI-ALL-0104
Prompt Investigation Response Team
Revision 4
AD-PI-ALL-0106
Cause Investigation Checklists
Revisions 2
and 3
AD-PI-ALL-0108
Performance Analysis
Revision 0
Containment Ventilation & Cooling Systems
Revision 12
OWP-RM
Radiation, Effluent, and Explosive Gas Monitoring
Revisions 44
and 45
Work Orders
Replace breaker to radiation monitor RM-3561A
Replace breaker to radiation monitor RM-3561C