IR 05000277/2020001
| ML20127H944 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/06/2020 |
| From: | Jon Greives Reactor Projects Region 1 Branch 4 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Greives J | |
| References | |
| IR 2020001 | |
| Download: ML20127H944 (12) | |
Text
May 6, 2020
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 -
INTEGRATED INSPECTION REPORT 05000277/2020001 AND 05000278/2020001
Dear Mr. Hanson:
On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Peach Bottom Atomic Power Station, Units 2 and 3. On April 10, 2020, the NRC inspectors discussed the results of this inspection with Mr. Matthew Herr, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, X /RA/
Signed by: Jonathan E. Greives Jonathan E. Greives, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 05000277 and 05000278 License Nos. DPR-44 and DPR-56
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000277 and 05000278 License Numbers: DPR-44 and DPR-56 Report Numbers: 05000277/2020001 and 05000278/2020001 Enterprise Identifier: I-2020-001-0057 Licensee: Exelon Generation Company, LLC Facility: Peach Bottom Atomic Power Station, Units 2 and 3 Location: Delta, PA 17314 Inspection Dates: January 1, 2020 to March 31, 2020 Inspectors: J. Heinly, Senior Resident Inspector P. Boguszewski, Resident Inspector J. Schoppy, Senior Reactor Inspector Approved By: Jonathan E. Greives, 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 an integrated inspection at Peach Bottom Atomic Power Station,
Units 2 and 3, 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 2 began the inspection period at rated thermal power. On March 26, 2020, operators reduced power to 55 percent for a routine maintenance load drop. The unit was returned to rated thermal power on March 27, 2020 and remained there for the duration of the inspection period.
Unit 3 began the inspection period at rated thermal power. On March 6, 2020, operators reduced power to 73 percent for a routine maintenance load drop. The unit was returned to rated thermal power on March 9, 2020 and remained there for the duration 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/readingrm/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. From January 1 - March 19, 2020, 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; and observed risk significant activities when warranted. In addition, resident and regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In the cases where it was determined the objectives and requirements could not be performed remotely, management elected to postpone and reschedule the inspection to a later date.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated winter readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures, potential deepening extreme drought, and seasonal heavy rains on January 22 and 23, 2020
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 3 reactor core isolation cooling (RCIC) during Unit 3 high-pressure coolant injection (HPCI) system outage window (SOW) on January 21, 2020
- (2) Unit 2 standby liquid control system during Unit 2 and Unit 3 E-1 emergency diesel generator (EDG) SOW on February 4, 2020
- (3) Unit 3 'B' core spray (CS) on February 10, 2020
- (4) Unit 2 and Unit 3 E-3 EDG while Unit 2 and Unit 3 E-1 EDG was inoperable on February 27, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Inner screen area, PF-145, on January 9, 2020
- (2) Cable spreading room, PF-78H, on January 15, 2020
- (3) Unit 3 'A' CS instrument room, PF-13G, on January 23, 2020
- (4) Unit 3 'B' CS instrument room, PF-13F, on January 23, 2020
- (5) Switchgear rooms during E-1 SOW, PF 117, on January 31, 2020
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 2 'B' and 'D' CS rooms
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 2 'D' residual heat removal (RHR) heat exchanger on January 14, 2020
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 main control room on February 28, 2020
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated requalification training that involved multiple equipment failures that resulted in a reactor SCRAM and a steam leak on January 27, 2020
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 2 RHR during the week of March 22, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unit 2 startup electrical feed out of service on January 21, 2020
- (2) Unit 2 and Unit 3 E-1 SOW during the week of January 27, 2020
- (4) Unit 3 HPCI on February 26, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2 'D' RHR minimum flow slow stroke on January 3, 2020
- (2) Unit 2 'D' RHR heat exchanger degraded thermal performance on January 14, 2020
- (3) Unit 3 HPCI overspeed trip nonfunctional on January 15, 2020
- (4) Unit 2 and 3 EDG, E-2, and E-4 turbo inlet check valve on January 29, 2020
- (5) Unit 2 and Unit 3 E-1 coolant system voiding on February 29, 2020
- (6) Bussman KLM-3 fuse defects on March 10, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 3 HPCI pressure switch replacement on January 23, 2020
- (4) Unit 2 and Unit 3 E-1 EDG following coolant vent replacement on March 5, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 2 and Unit 3 Standby Gas Treatment System 'B' Filter Functional test on January 7, 2020
- (2) Unit 2 'D' battery charger on February 17 and 18, 2020
- (3) Unit 2 RCIC Logic System Functional testing on March 3, 2020
- (4) Unit 3 RCIC on March 12, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
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) ===
- (1) Unit 2 unplanned scrams from January 2019 to December 2019
- (2) Unit 3 unplanned scrams from January 2019 to December 2019 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)
(2 Samples)
- (1) Unit 2 unplanned power changes from January 2019 to December 2019
- (2) Unit 3 unplanned power changes from January 2019 to December 2019
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 2 unplanned scrams with complications from January 2019 to December 2019
- (2) Unit 3 unplanned scrams with complications from January 2019 to December 2019
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program (CAP) related to the following issues:
- (1) Unit 3 Control Rod Drive Pressure Low After 220-08 Line Trip
INSPECTION RESULTS
Observation:
71152 - Problem Identification and Resolution (Annual Sample) 71152
The inspectors concluded that Exelon had taken timely and appropriate actions in accordance with Exelons operating and alarm response procedures; PI-AA-125, CAP Procedure; 10 CFR Part 50, Appendix B; and technical specification requirements. The inspectors determined that Exelons associated engineering evaluations and trending were sufficiently thorough and based on the best available information, sound judgment, and relevant operating experience. Exelons assigned corrective actions were aligned with engineering evaluations, adequately tracked, appropriately documented, and completed as scheduled. Based on the documents reviewed, plant walkdowns (including the Unit 2 and Unit 3 hydraulic control units, control rod drive systems, and common control room), and discussions with engineering personnel, the inspectors noted that Exelon personnel identified problems and entered them into the CAP at low threshold.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 10, 2020, the inspectors presented the integrated inspection results to Mr. Matthew Herr, Site Vice President, and other members of the licensee staff.
- On February 20, 2020, the inspectors presented the control rod drive system problem identification and resolution sample inspection results to Mr. Pat Navin, former Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.01 Procedures RT-O-040-630-2 Winterizing Procedure Revision 16
SO 48.4.A Draining ESW and HPSW Return Lines to Emergency Revision 4
Cooling Tower For Winter Freeze Protection
71111.06 Corrective Action 3224909
Documents
Drawings M-518 Sh 1 Plumbing, Drainage Reactor Building No. 2 Plan at EL. 91FT Revision 12
- 01N
Procedures AO 20A.1 Temporary Removal and Installation of Flood Barriers in the Revision 16
Reactor Drainage System
RT-W-020-930-2 Survey for Flood Barriers in Reactor Building Drainage Revision 6
System
71111.07A Procedures RT-O-010-660-3 RHR Heat Exchanger Performance Test Revision 16
71111.15 Corrective Action 4300003
Documents 4308870
Corrective Action 4316660
Documents
Resulting from
Inspection
Drawings M-377 Sh 1 Diesel Generator Auxiliary Systems Starting Air System Revision 44
M-377 Sh 2 Diesel Generator Auxiliary Systems Starting Air Systems Revision 47
Procedures COL 52E.3.A-1 E-1 EDG Jacket Coolant/Air Coolant System Revision 17
Work Orders 4816084
71111.19 Corrective Action 4316697
Documents ST-O-014-301-3 CS Loop A Pump, Valve, Flow and Cooler Functional and Revision 35
Inservice Test
Procedures SI3P-23-97-ABC2 Calibration Check of HPCI Pump and Turbine Pressure Revision 7
Switches
71111.22 Procedures ST-I-013-100-2 RCIC Logic System Functional Test Revision 23
ST-O-013-300-2 RCIC Pump, Valve, Flow and Unit Cooler Functional and In- Revision 13
Service Test Without Vibration Data Collection
71152 Corrective Action 2617713
Documents 4032065
Inspection Type Designation Description or Title Revision or
Procedure Date
4033536
25980
4145554
4145556
4145711
4181079
20504
20161
234301
234302
237862
245711
293799
293922
294473
294608
4306294
4307507
29471
29472
Corrective Action 4319685
Documents 4319696
Resulting from 4319708
Inspection 4319715
4319735
Drawings 6280-M-356 Unit 3 Control Rod Drive (CRD) Hydraulic System Part A Revision 76
Engineering 4220504 Unit 3 CRD Charging Header Pressure Indication Low Work dated
Evaluations Group Evaluation 3/18/19
PEA-3-2019-0181 Unit 3 Charging Header Depressurized dated
5/13/19
Miscellaneous CRD System Health Report dated 2/6/20
Peach Bottom Nuclear Power Station Unit 2 & Unit 3 CRD dated
System Check Valves (CV) 36 A/B Test Assessment Report 5/23/19
PMC-19-121889 Create a New PM to Open and Inspect CRD Pump dated
Inspection Type Designation Description or Title Revision or
Procedure Date
Discharge Valves 12/9/19
Procedures ON-107 Loss of CRD Regulating Function Revision 25
PI-AA-120 Issue Identification and Screening Process Revision 8
PI-AA-125 CAP Procedure Revision 7
Work Orders 4908357
10