IR 05000289/2019002

Integrated Inspection Report 05000289/2019002

ML19224A092
Person / Time
Site:	Three Mile Island
Issue date:	08/09/2019
From:	Matt Young NRC Region 1
To:	Bryan Hanson Exelon Generation Co
References
IR 2019002
Download: ML19224A092 (14)

Text

ust 9, 2019

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - INTEGRATED INSPECTION REPORT 05000289/2019002

Dear Mr. Hanson:

On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Three Mile Island Nuclear Station, Unit 1. On July 19, 2019, the NRC inspectors discussed the results of this inspection with Joe Dullinger, Plant Manager, 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/

Matthew R. Young, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket No. 05000289 License No. DPR-50

Enclosure:

As stated

Inspection Report

Docket Number: 05000289 License Number: DPR-50 Report Number: 05000289/2019002 Enterprise Identifier: I-2019-002-0033 Licensee: Exelon Generation Company, LLC Facility: Three Mile Island Nuclear Station, Unit 1 Location: Middletown, PA 17057 Inspection Dates: April 1, 2019 to June 30, 2019 Inspectors: Z. Hollcraft, Senior Resident Inspector S. Horvitz, Resident Inspector B. Lin, Nuclear Systems Engineer N. Floyd, Senior Reactor Inspector J. Furia, Senior Health Physicist Approved By: Matthew R. Young, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Three Mile Island Nuclear Station, 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.

List of Findings and Violations No findings or violations of more than minor significance were identified.

Additional Tracking Items None.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power. On May 29, 2019, the unit was down powered to 77 percent as requested by Transmission for load following. The unit was returned to rated thermal power on May 29, 2019, and remained at or near rated thermal power for the remainder of the inspection period.

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 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.

71111.01 - Adverse Weather Protection External Flooding Sample (IP Section 03.04)

(1) The inspectors evaluated readiness to cope with external flooding for the following areas:

• Flood dike on April 9, 2019, Operating Experience Smart Sample 2007/02, Revision 3

Impending Severe Weather Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated readiness for impending adverse weather conditions for a tornado watch on May 29, 2019.

Summer Readiness Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated summer readiness of offsite and alternate alternating current power systems on June 29, 2019.

71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Protected system lineup during the B emergency diesel generator system outage window on April 8, 2019

(2) B reactor building spray pump following maintenance and quarterly pump testing on April 18, 2019

(3) B and C nuclear services closed cycle cooling pump systems during A pump maintenance on May 1, 2019

(4) Fire service pump FS-P-1 system restoration following maintenance on June 27, 2019

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

(1) The inspectors evaluated system configurations during a complete walkdown of the spent fuel cooling system on May 23, 2019.

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Auxiliary building elevation 281', makeup pump 1A, 1B, and 1C cubicles, AB-FZ-2A, AB-FZ-2B, and AB-FZ-22C on April 23, 2019

(2) Turbine building elevation 322', TB-FA-1(3), TB-FA-1(9), and TB-FA-1(10), on April 30, 2019

(3) Auxiliary building elevation 305', AB-FZ-7 and AB-FZ-8, on May 1, 2019

(4) Control building elevation 322', CB-FA-2D and CB-FA-2E, on May 2, 2019

(5) Control building elevation 380' and patio area all levels, CB-FZ-5A, CB-FZ-5B, and FH-FZ-5, on June 3, 2019

71111.06 - Flood Protection Measures Inspection Activities - Underground Cables (IP Section 02.02c.)

The inspectors evaluated cable submergence protection in:

(1) Manhole E-8 on May 29, 2019

71111.07T - Heat Sink Performance Triennial Review (IP Section 02.02)

The inspectors evaluated heat exchanger/sink performance on the following:

(1) A/B/C/D Nuclear Services Heat Exchangers, Cooled by River Water, Section 02.02b

(2) A and B Spent Fuel Pool Heat Exchangers, Closed Loop, Section 02.02c

(3) Ultimate Heat Sink - Nuclear Services River Water System, Section 02.02d, Specifically Sections 02.02d4, 02.02d5, 02.02d6 and 02.02d7 were completed.

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) The inspectors observed and evaluated licensed operator performance in the control room during the A train emergency load sequence and high-pressure injection logic testing on April 25, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator requalification classroom training on May 22, 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) Title 10 of the Code of Federal Regulations (CFR) 50.65 (a)(3) maintenance rule periodic assessment for the period of January 1, 2017, through December 31, 2018

(2) Instrument air system on June 5, 2019

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 risk during performance of D 4kV bus loss of voltage/degraded grid timing relay calibration and logic test on April 4, 2019

(2) Scheduled system outage window for the B emergency diesel generator on April 7-11, 2019

(3) Elevated risk due to 'A' train reactor building containment isolation logic and component engineered safeguards actuation system testing on May 23, 2019

(4) Elevated risk due to 1E 4160V bus undervoltage 27-4 relay replacement post maintenance testing on May 29, 2019

(5) Elevated risk due to inservice testing of the power operated relief valve (PORV)isolation valve and its setpoint check on June 13, 2019

(6) Emergent work to replace a reactor coolant pressure bistable trip module for the channel 2 engineered safeguards actuation system on June 18, 2019

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Operability evaluation of decay closed cooling shell bypass control valve (DC-V-65B)on April 4, 2019

(2) Operability evaluation of electrical penetration (PP-FI-98) flow exceeding procedural acceptable limit on April 9, 2019

(3) Operability evaluation of electrical penetration (PP-FI-130) flow exceeding procedural acceptable limit on April 9, 2019

(4) B steam generator level transmitter (FW-LT-1052) indication drifted on April 9, 2019

(5) Operability evaluation of the A nuclear service closed cooling pump (NS-P-1A) for a seal and flange leak following replacement on May 2, 2019

(6) High silt levels at the intake screen house on May 9, 2019

(7) Reactor coolant system heat balance evaluation results were unsatisfactory on May 27, 2019

(8) A spent fuel pool active leakage on June 3, 2019

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 modifications:

(1) Alternate flow path for SD-P-3A/B and SD-P-4A/B to the Turbine building on June 15, 2019

71111.19 - Post-Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance tests:

(1) Retest of the B emergency diesel generator on April 11, 2019, at the conclusion of a scheduled system outage window

(2) Retest of the B decay closed heat exchanger shell bypass control valve (DC-V-65B)on March 15, 2019

(3) 1E 4160V bus undervoltage 27-4 relay replacement post maintenance testing on May 29, 2019

(4) Retest of control rod drive power supply (CRD-SRPS-22B) on May 30, 2019

(5) Channel 2 engineered safeguards bistable replacement on June 18, 2019

(6) Fire service pump FS-P-1 following packing replacement on June 27, 2019

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Inservice Testing (IP Section 03.01)

(1) OP-TM-214-202, in-service testing of the B reactor building spray pump on April 18, 2019 Reactor Coolant System (RCS) Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) OP-TM-220-251, reactor coolant system leak rate determination on May 2, 2019

Surveillance Tests (other) (IP Section 03.01) (5 Samples)

(1) 1302-5.31C, 4kV D bus loss of voltage/degraded grid timing relay calibration and logic test on April 4, 2019

(2) 1303-11.37B, heat sink protection system steam generator level and pressure channel II test on April 16, 2019

(3) 1304-5.2A, A emergency load sequence and high-pressure injection logic testing on April 25, 2019

(4) 1301-3, reactor coolant system chemistry and activity sampling on May 15, 2019

(5) 1303-4.11, engineered safeguards relay testing on June 18,

71124.07 - Radiological Environmental Monitoring Program Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02)

(1) The inspectors reviewed: groundwater monitoring results; changes to the Groundwater Protection Initiative (GPI) program since the last inspection; anomalous results or missed groundwater samples; leakage or spill events including entries made into the decommissioning files (10 CFR 50.75(g)); evaluations of surface water discharges; and evaluation of any positive groundwater sample results including appropriate stakeholder notifications and effluent reporting requirements.

Site Inspection (IP Section 02.01) (1 Sample)

The inspectors evaluated the radiological environmental monitoring program implementation.

(1) The inspectors walked down various thermoluminescent dosimeter and air and water sampling locations and reviewed associated calibration and maintenance records. The inspectors observed the sampling of various environmental media as specified in the Offsite Dose Calculation Manual (ODCM). The inspectors reviewed the groundwater monitoring program as it applies to selected potential leaking structures, systems, and components (SSCs), and 10 CFR 50.75(g) records of leaks, spills, and remediation since the previous inspection.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

BI01: RCS Specific Activity Sample (IP Section 02.10) ===

(1) January 1, 2018, through March 31, 2019

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) January 1, 2018, through March 31, 2019

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in maintenance and incident report (IR) generation that might be indicative of a more significant safety issue.

INSPECTION RESULTS

Observation: Semiannual Trend Review 71152 In light of anticipated permanent cessation of operations in September 2019, inspectors reviewed trends within the maintenance program related to backlog and the corrective action program related to IR generation. The licensee's maintenance backlog has seen no appreciable change since the beginning of 2019 and is generally kept low. IR generation is slightly lower than the previous year both overall, and on a per capita basis. However given the reduced amount of work being performed due to deferred maintenance, inspectors are unable to draw specific conclusions on this. The inspectors do not see any indication of decline in performance in either of these areas. The inspectors also have noted that the licensee is closely monitoring IR generation rates along with other metrics in order to self assess any declining performance.

EXIT MEETINGS AND DEBRIEFS

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

• On July 19, 2019, the inspectors presented the integrated inspection results to Joe Dullinger, Plant Manager, and other members of the licensee staff.

• On June 20, 2019, the inspectors presented the triennial heat sink inspection results to Edward Callan, Site Vice President, and other members of the licensee staff.

• On June 14, 2019, the inspectors presented the radiological environmental monitoring program (REMP) inspection results to Joe Dullinger, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 01387409

Documents

Procedures 3301-SA1 Dike Inspection Revision 17

71111.04 Drawings 302-610 Nuclear Services Closed Cycle Cooling Water Flow Diagram Revision 82

2-645 Decay Heat Flow Diagram Closed Cycle Cooling Water Revision 39

2-712 Reactor Building Spray Flow Diagram Revision 49

71111.04S Corrective Action 04260051

Documents 04260056

Drawings 302-630 Spent Fuel Cooling System Flow Diagram Revision 35

2-728 Spent Fuel Pool & Fuel Transfer Canal Leak Detection Flow Revision 1

Diagram

71111.05Q Fire Plans AB-FZ-2A, 2B Auxiliary Building Elevation 281', Makeup Pump 1A, 1B, and Revision 2

AND 2C 1C Cubicles

AB-FZ-7 Auxiliary Bldg. Elev. 305; Decay Heat Removal & Nuclear Revision 6

Services Closed Cycle Cooling Pump Area

AB-FZ-8 Auxiliary Bldg. Elev. 305; Waste Gas Decay Tanks Area Revision 3

CB-FA-2D Control Bldg. Elev. 322; A Inverter Room Revision 7

CB-FA-2E Control Bldg. Elev. 322; B Inverter Room Revision 7

CB-FZ-5A Control Bldg. Elev. 380; North H&V Equipment Room Revision 3

CB-FZ-5B Control Bldg. Elev. 380; South H&V Equipment Room Revision 3

FH-FZ-5-(322 FT) Fuel Handling Bldg. Elev. 322; Control Bldg. Patio Area Revision 7

FH-FZ-5-(338 FT Fuel Handling Bldg. Elev. 338-6; Control Bldg. Patio Area Revision 4

IN)

FH-FZ-5- CB Patio Area (FH-FZ-5-355/365 I & C Shop/Office Area) Revision 5

(355/365 FT)

FH-FZ-5-(380 FT) Fuel Handling Bldg. Elev. 380; Control Bldg. Patio Area Revision 3

TB-FA-1 (10) Turbine Bldg. Elev. 322; Turbine Driven Main Feedwater Revision 5

Pumps

TB-FA-1 (3) Electrical Equipment Room; Turbine Bldg. Elev. 322 Revision 5

TB-FA-1 (9) Turbine Bldg. Elev. 322; Main Turbine Oil Reservoir Revision 5

71111.06 Procedures ER-AA-300-150 Cable Condition Monitoring Program Revision 5

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 0486509201

71111.11Q Procedures TQ-AA-150 Operator Training Programs Revision 18

71111.12 Corrective Action 03972831

Documents 03979144

04021479

04055198

04073686

04075335

04075603

04181275

04199316

213052

234449

Miscellaneous Three Mile Island Unit 1 Maintenance Rule Periodic Revision 0

Assessment per 10 CFR 50.65(a)(3) January 2017 to

December 2018

Maintenance Rule System Basis Document, Instrument Air, May 9, 2019

Unit 1 System 852

Procedures ER-AA-310-1007 Maintenance Rule - Periodic (a)(3) Assessment Revision 5

71111.13 Procedures OP-AA-108-117 Protected Equipment Program Revision 5

Work Orders 4766855

4865674

4895823

71111.15 Calculations C-1101-531- Calculation for an Acceptable Silt Accumulation in the Intake Revision 1

E310-015 Screen and Pump House

Corrective Action 04208006

Documents 04237660

237997

237999

245812

245826

248669

Inspection Type Designation Description or Title Revision or

Procedure Date

248671

249014

250896

251968

251976

247814

248155

Procedures 1102-4 Power Operation Revision 137

1301-6.7 Monitoring of Silt Buildup in River Water Screen House Revision 23

1301-9.7 Intake Pump House Floor, Silt Accumulation and Inspections Revision 31

OP-TM-AOP-035 Loss of Spent Fuel Cooling Revision 9

Work Orders 4894086

71111.18 Engineering 628061 Reroute the SD-P-3A/B and SD-P4A/B Discharge Header to Revision 0

Changes the Turbine Building

71111.19 Corrective Action 04252235

Documents 04253158

251535

Drawings 208-169 Sh. 1 Electrical Elementary Diag. 4160V Switchgear E.S. Bus 1E Revision 27

Undervoltage & Potential Circuits

208-169 Sh. 2 Electrical Elementary Diag. 4160V Switchgear E.S. Bus 1E Revision 5

Undervoltage & Potential Circuits

209-581 Electrical Elementary Wiring Diagram Engineered Revision 20

Safeguards E.S. Act. B H.P. INJ & Loading Seq Channel

RC1B

Procedures 1107-3 Diesel Generator Revision 153

1301-8.2 Diesel Generator Major Inspection (Mechanical) Revision 101

1303-4.11 HPI/LPI Logic and Analog Channel Test Revision 60

1303-4.16 Emergency Power Systems Revision

1446

20-EG-2 Diesel Generator Troubleshooting Revision 11

Work Orders 4352004 DC-V-65B: Rebuild Actuator/Replace Accessories Revision 1

4693222

4715586

Inspection Type Designation Description or Title Revision or

Procedure Date

4716376

4895823

23932

71111.22 Procedures 1301-3 Reactor Coolant System Chemistry and Activity Revision 31

1303-11.37B HSPS - OTSG Level and Pressure Channel II Tests Revision 36

1303-2-5.31C 4160 V 1D Bus Loss of Voltage / Degraded Grid Timing Revision 19

Relay Calibration and Logic Test

1303-5.2A "A" Emergency Loading Sequence and HPI Logic Revision 19

Channel/Component Test

CY-AA-130-3010 Dose Equivalent Iodine Determination Revision 6

CY-AP-120-105 Reactor Coolant System Chemistry for Three Mile Island Revision 20

CY-TM-130-9032 Dose Equivalent Iodine Preparation for Reactor Coolant Revision 1

N1807.1 Reactor Coolant & Pressurizer Sampling Revision

20E

OP-TM-214-202 IST of BS-P-1B and Valves Revision

16A

OP-TM-220-251 RCS Leak Rate Determination Revision 14

Work Orders 4847623

4877135

4877805

4895823

71151 Procedures LS-AA-2090 Monthly Data Element for NRC Reactor Coolant System Revision 4

(RCS) Specific Activity

LS-AA-2100 Monthly Data Element for NRC Reactor Coolant System Revision 5

(RCS) Leakage

2