IR 05000400/2019001

Nuclear Regulatory Commission Integrated Inspection Report 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

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: NPF-63 Report Number: 05000400/2019001 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 Enclosure

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 71152.

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.

71111.04 - Equipment Alignment Partial Walkdown (IP Section 02.01)

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)

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.)

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)

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)

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)

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)

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)

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)

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)

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 Type Designation Description or Title Revision or

Procedure Date

71111.04 Procedures OP-107 Chemical and Volume Control Revision 117

OP-112 Containment Spray System Revision 46

OP-139 Service Water System Revision 136

71111.05Q Fire Plans CSD-HNP-PFP- Reactor Auxiliary Building Elevations 190 and 216 Pre-Fire Revision 1

RAB-190-216 Plan

CSD-HNP-PFP- Reactor Auxiliary Building Elevation 236 Pre-Fire Plan Revision 2

RAB-236

CSD-HNP-PFP- Out Building Pre-Fire Plan Revision 4

SEC

CSD-HNP-RAB- Reactor Auxiliary Building Elevation 286 Pre-Fire Plan Revision 1

286

Miscellaneous Fire Protection

Permit and

Impairment Log

Entries

Procedures AD-EG-ALL-1520 Transient Combustible Control Revision 11

FPP-001 Fire Protection Program Manual Revision 44

FPP-013 Fire Protection - Minimum Requirements, Mitigation Actions Revision 99

and Surveillance Requirements

71111.06 Calculations PRA-F-E-004 Reactor Auxiliary Building Unit 1 Elevation 190' & 216' Revision 8

Internal Flooding Analysis

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

AOP-025 Loss of One Emergency AC Bus (6.9kV) or One Emergency Revision 42

DC Bus (125V)

AP-002 Plant Conduct of Operations Revision 73

EOP-E-0 Reactor Trip or Safety Injection Revision 12

MST-I0001 Train A Solid State Protection System Actuation Logic & Revision 38

Master Relay Test

OMM-001 Operations Administrative Requirements Revision 114

OMM-014 Operation of the Work Coordination Center Revision 73

Inspection Type Designation Description or Title Revision or

Procedure Date

OP-104 Rod Control System Revision 43

Work Orders WO 20281152 Conduct SSPS Testing on 'A' Train

71111.12 Calculations HNP-F/PSA-0020 HNP PRA Evaluation of Risk Significant SSCs for Revision 1

Maintenance Rule

HNP-F/PSA-0065 HNP PRA - System Notebooks Revision 8

Corrective Action NCR 02241966 Containment ventilation isolation radiation monitor 3561C

Documents failed to alarm when tested

NCR 02250497 Loose fan belts on 'A' RHR/CS pump room air handler

system

Miscellaneous NUMARC 93-01 Industry Guideline for Monitoring the Effectiveness of Revision 4A

Maintenance at Nuclear Power Plants

Procedures AD-EG-ALL-1210 Maintenance Rule Program Revision 1

EOP-E-1 Reactor Trip Response Revision 5

OWP-RM Radiation, Effluent, and Explosive Gas Monitoring Revision 45

Work Orders WO 20287202 Perform MST-I0347 to determine cause of electronic spikes

on RM-01CR-3561ASA

WO 20303302 Repair loose belts on 'A' RHR/CS pump room air handler

71111.13 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- On-Line Work Management Revision 13

200

AD-WC-ALL- On-Line Risk Management Process Revision 1

240

AD-WC-ALL- Work Activity Integrated Risk Management Revision 7

0410

OMM-001 Conduct of Operations Revision 114

Work Orders WO 10622005 Lubrication of 'A' ESW booster pump coupling

WO 12296955 Tighten seal water piping connection on 'A' containment

spray pump

WO 20193828 AFW pump motor 1A-SA testing

WO 20237424 Preventive maintenance on 'A' ESW stuffing box and seal

water cooling system

Inspection Type Designation Description or Title Revision or

Procedure Date

WO 20266256 Replace actuator oil in 'A' AFW discharge control valve

WO 20311779 Repair emergent issue with N-41 upper detector reading

high

WOs 20181791, 'B' train sequencer relay calibrations and replacement

266115, and

266116

71111.15 Corrective Action NCR 01959624 Copper detected in CCW pump bearing oil sample

Documents NCR 02203899 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

DBD-103 Chemical and Volume Control System Revision 24

DBD-106 Containment Spray System Revision 17

DBD-131 Component Cooling Water System Revision 17

DBD-201 Emergency Diesel Generator System Revision 18

OST-1013 1A-SA Emergency Diesel Generator Operability Test Revision 43

Monthly Interval Modes 1-6

OST-1107 ECCS/Containment Spray Flow Path and Piping Filled Revision 36

Verification Monthly Interval Modes 1-6

PM-M0102 3/8 - 6 Inch Diaphragm Valve Nonmetallic Component Revision 6

Replacement

Work Orders WO 20179904 Evaluate gas voids

71111.18 Engineering EC 413085 Non-Controlled Plant Equipment Wireless Emitting Device Revision 1

Changes Installation

EC 414212 Electromagnetic Interference Proximity for Transceivers Revision 3

Miscellaneous NEI 96-07 Guidelines for 10 CFR 50.59 Evaluations Endorsed by Revision 1

Regulatory Guide 1.187

Regulatory Guide Guidance for Implementation of 10 CFR 50.59, dated

1.187 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 Revision 13

Changes

AD-EG-ALL-1137 Engineering Change Product Selection Revision 5

Inspection Type Designation Description or Title Revision or

Procedure Date

AD-LS-ALL-0008 10 CFR 50.59 Review Process Revision 0

Work Orders WO 20288719 Install wireless emitting device and hardware for main control

room

71111.19 Procedures PLP-400 Post Maintenance Testing Revision 64

Work Orders WO 10622005 Lubrication of 'A' ESW booster pump coupling

WO 12296955 Tighten seal water piping connection on 'A' containment

spray pump

WO 20191986 Obtain one set of inrush current data

WO 20193828 AFW pump motor 1A-SA testing

WO 20237424 Preventive maintenance on 'A' ESW stuffing box and seal

water cooling system

WO 20266256 Replace actuator oil in 'A' AFW discharge control valve

WO 20285410 VMS-2, Determine available adjustment for future

modification

WO 20307647 TDAFW pump tripped while starting during OST-1044

71111.22 Procedures CSD-EG-HNP- Flexible Response to Extended Loss of ALL AC Power Revision 0

8888

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

NEI 99-02 Regulatory Assessment Performance Indicator Guideline

Procedures AD-LS-ALL-0004 NRC Performance Indicators and Monthly Operating Report Revision 3

71152 Engineering 412571 HNP RFO-21 Thermal Sleeve Flange Upper Flange Wear Revision 0

Changes Inspection Results

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 Type Designation Description or Title Revision or

Procedure 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

DBD-136 Containment Ventilation & Cooling Systems Revision 12

OWP-RM Radiation, Effluent, and Explosive Gas Monitoring Revisions 44

and 45

Work Orders WO 20191928 Replace breaker to radiation monitor RM-3561A

WO 20191929 Replace breaker to radiation monitor RM-3561C

13