IR 05000289/2019002
| ML19224A092 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/09/2019 |
| From: | Matt Young NRC Region 1 |
| To: | Bryan Hanson Exelon Generation Co |
| References | |
| IR 2019002 | |
| Download: ML19224A092 (14) | |
Text
August 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:
Report Number:
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
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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
External Flooding Sample (IP Section 03.04) (1 Sample)
- (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) (4 Samples)
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 Sample)
- (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) (5 Samples)
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.) (1 Sample)
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 Sample)
- (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) (2 Samples)
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) (6 Samples)
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) (8 Samples)
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) (1 Sample)
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) (6 Samples)
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,
RADIATION SAFETY
71124.07 - Radiological Environmental Monitoring Program
Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)
- (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 Sample)
- (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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
01387409
Procedures
3301-SA1
Dike Inspection
Revision 17
Drawings
2-610
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
Corrective Action
Documents
260051
260056
Drawings
2-630
Spent Fuel Cooling System Flow Diagram
Revision 35
2-728
Spent Fuel Pool & Fuel Transfer Canal Leak Detection Flow
Diagram
Revision 1
71111.05Q Fire Plans
AB-FZ-2A, 2B
AND 2C
Auxiliary Building Elevation 281', Makeup Pump 1A, 1B, and
1C Cubicles
Revision 2
AB-FZ-7
Auxiliary Bldg. Elev. 305; Decay Heat Removal & Nuclear
Services Closed Cycle Cooling Pump Area
Revision 6
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
IN)
Fuel Handling Bldg. Elev. 338-6; Control Bldg. Patio Area
Revision 4
FH-FZ-5-
(355/365 FT)
CB Patio Area (FH-FZ-5-355/365 I & C Shop/Office Area)
Revision 5
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
Pumps
Revision 5
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
Procedures
Cable Condition Monitoring Program
Revision 5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
0486509201
71111.11Q Procedures
Operator Training Programs
Revision 18
Corrective Action
Documents
03972831
03979144
04021479
04055198
04073686
04075335
04075603
04181275
04199316
213052
234449
Miscellaneous
Three Mile Island Unit 1 Maintenance Rule Periodic
Assessment per 10 CFR 50.65(a)(3) January 2017 to
December 2018
Revision 0
Maintenance Rule System Basis Document, Instrument Air,
Unit 1 System 852
May 9, 2019
Procedures
Maintenance Rule - Periodic (a)(3) Assessment
Revision 5
Procedures
Protected Equipment Program
Revision 5
Work Orders
4766855
4865674
4895823
Calculations
C-1101-531-
E310-015
Calculation for an Acceptable Silt Accumulation in the Intake
Screen and Pump House
Revision 1
Corrective Action
Documents
208006
237660
237997
237999
245812
245826
248669
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Engineering
Changes
28061
Reroute the SD-P-3A/B and SD-P4A/B Discharge Header to
the Turbine Building
Revision 0
Corrective Action
Documents
252235
253158
251535
Drawings
208-169 Sh. 1
Electrical Elementary Diag. 4160V Switchgear E.S. Bus 1E
Undervoltage & Potential Circuits
Revision 27
208-169 Sh. 2
Electrical Elementary Diag. 4160V Switchgear E.S. Bus 1E
Undervoltage & Potential Circuits
Revision 5
209-581
Electrical Elementary Wiring Diagram Engineered
Safeguards E.S. Act. B H.P. INJ & Loading Seq Channel
RC1B
Revision 20
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
Procedure
Type
Designation
Description or Title
Revision or
Date
4716376
4895823
23932
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
Relay Calibration and Logic Test
Revision 19
1303-5.2A
"A" Emergency Loading Sequence and HPI Logic
Channel/Component Test
Revision 19
Dose Equivalent Iodine Determination
Revision 6
Reactor Coolant System Chemistry for Three Mile Island
Revision 20
Dose Equivalent Iodine Preparation for Reactor Coolant
Revision 1
N1807.1
Reactor Coolant & Pressurizer Sampling
Revision
20E
IST of BS-P-1B and Valves
Revision
16A
RCS Leak Rate Determination
Revision 14
Work Orders
4847623
4877135
4877805
4895823
71151
Procedures
Monthly Data Element for NRC Reactor Coolant System
(RCS) Specific Activity
Revision 4
Monthly Data Element for NRC Reactor Coolant System
(RCS) Leakage
Revision 5