IR 05000255/2020011
ML20112F494 | |
Person / Time | |
---|---|
Site: | Palisades |
Issue date: | 04/21/2020 |
From: | Karla Stoedter NRC/RGN-III |
To: | Corbin D Entergy Nuclear Operations |
References | |
IR 2020011 | |
Preceding documents: |
|
Download: ML20112F494 (12) | |
Text
April 21, 2020
SUBJECT:
PALISADES NUCLEAR PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000255/2020011
Dear Mr. Corbin:
On March 19, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant and 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 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,
/RA/
Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 05000255 License No. DPR-20
Enclosure:
As stated
Inspection Report
Docket Number: 05000255 License Number: DPR-20 Report Number: 05000255/2020011 Enterprise Identifier: I-2020-011-0025 Licensee: Entergy Nuclear Operations, Inc.
Facility: Palisades Nuclear Plant Location: Covert, Michigan Inspection Dates: March 02, 2020 to March 19, 2020 Inspectors: C. Baron, Contractor J. Benjamin, Senior Reactor Inspector I. Hafeez, Reactor Inspector B. Jose, Senior Reactor Inspector S. Kobylarz, Contractor E. Sanchez Santiago, Senior Reactor Inspector Approved By: Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Palisades Nuclear Plant, 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.
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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensees performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)
=
- (1) Safety-Related Service Water Pump P-7A
- Technical Specifications
- Protection Against External Events
- Protection Against Internal Events
- Maintenance Effectiveness
- Overall System Health
- Translation of Vendor Specifications
- Configuration Management
- Testing
- Pump and Check Valve In-service Testing (IST)
- Pump Flow Quarterly and Semi-Annual Flow Verification
- Calculations
- Service Water Outlet Submergence Back Pressure
- Service Water System Hydraulic Model
- Generation of Flow Rate Acceptance Criteria for Technical Specification Surveillance Test RO-216
- Emergency Diesel Generator Voltage and Frequency Variation Evaluation on Safety-Related Service Water Pumps
- (2) Safety-Related High Pressure Control Air Receiver T-9A
- Design Basis Documents
- Technical Specification Applicability
- Testing
- Small Break Loss of Coolant Accident and Concurrent Loss of Offsite Power Supply Capability
- Maintenance Effectiveness
- (3) 125 Vdc Distribution Panels ED-11/11A/21/21A
- Load Flow Calculations to determine whether panels were applied within required current ratings
- Voltage Drop Calculations
- Voltage Rating During Battery Equalizing
- Short Circuit and Protective Device Calculations to determine whether equipment was adequately protected and immune from spurious tripping
- Maintenance Schedules, Procedures, and Maintenance Records, including Circuit Breaker Test Requirements, to determine whether panels and associated circuit breakers were properly maintained
- Visual inspection of the 125 Vdc Distribution Panels to assess material condition and the presence of hazards
- (4) 125 Vdc Station Battery ED-01 and ED-02
- Short Circuit and Protective Device Calculations to determine whether the batteries were adequately protected and immune from spurious tripping
- Battery Surveillance Procedures and Completed Tests to determine whether the acceptance criteria and results were consistent with design basis calculations
- Corrective Action Documents and Maintenance Records to determine whether there were any adverse operating trends
- Visual Inspection of the 125 Vdc Batteries to assess material condition and the presence of hazards due to battery cover cracks
- (5) 125 Vdc Battery Charger ED-15
- Material Condition and Configuration (e.g., Visual Inspection during a Walkdown)
- Operating Environment
- Consistency Between Station Documentation (e.g., Procedures) and Vendor Specifications
- Maintenance Effectiveness
- Corrective Maintenance Records and Corrective Action History
- Charger Short Circuit Contribution
- Surveillance Testing
- Float and Equalize Voltage and Coordination
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)
- (1) Motor Operated Valve (MOV) 3015: Shutdown Cooling Return from Reactor Coolant System
- Technical Specifications
- Protection Against External Events
- Protection Against Internal Events
- Maintenance Effectiveness
- Overall System Health
- Translation of Vendor Specifications
- In-service and Generic Letter 89-10 Testing
- Calculations
- Weak Link Analysis
- Pressure Lock/Thermal Binding Evaluation
- Generic Letter 89-10 MOV Thrust Window
- Torque Reduction at Elevated Temperatures
- Design Basis Flows and Delta Pressures
- Generic Letter 89-10 Valve Factor
- Generic Letter 89-10 Stem Nut Friction
Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)
- (1) Engineering Change (EC) 74105 - SPTS-1474; Replace Speed Switch for Emergency Diesel Generator 1-1
- (2) EC 54503 - 250/251-205: Replace Obsolete Overcurrent Relay for Pump P-2B
- (3) EC 55409 - Child EC to Replace Motor Control Center Breaker
- (4) EC 55441 - Install High Head Auxiliary Feedwater Pump P-8D & Shed and Cross Connect Tanks T-2 to T-939 - NFPA 805 Project
Review of Operating Experience Issues (IP Section 02.06) (2 Samples)
- (1) NRC Information Notice (IN) 2017-06, Battery and Battery Charger Short Circuit Current Contributions to a Fault on the Direct Current Distribution System
- (2) NRC IN 2002-29 Recent Design Problems in Safety Functions of Pneumatic Systems
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 19, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. D. Corbin, Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.21M Calculations 1/4RB System Protection Calculation Sheet 5
1/6C Primary Loop Shut Down Cooling Valve MO-3015 12/20/2012
1B-205-250-251 Protective Device Calculation for Relay 205/250-251 2
1D-204-150-151 Update Breaker Setting for Breaker 152-204 of Pump P-7A 1
EA-A-PAL-94- Seismic Analysis and Weak Link Calculation for 12" 1500 03/20/1995
279-009 Forges Stainless Motor Operated Bolted Bonnet Gate Valve
EA-C-PAL-00- High Pressure Air Single Failure Evaluation 0
258-01
EA-C-PAL-97- Evaluation of the Effect of Submerged Service Water 06/27/1997
0853 System (SWS) Outlets on the Minimum Predicted SWS Rate
Using Pipe - Flo
EA-C-PAL-99- Generation of Flow Rate Acceptance Criteria for Technical 3
209B-01 Specifications Surveillance Test RO-216
EA-CPCP-PAL- GL 89-10 Program Worst Case Pressures and Flows 04/13/1995
DSS-94-01
EA-EC-235-1 Assessment of the High Pressure Air System's Capacity to 0
Cycle Valves in the West Engineering Safeguards
EA-EC64020-01 NFPA 805 Related 125 Vdc Electrical Coordination Analysis 0
EA-ELEC-EDSA- Palisades System Level Under Voltage Relay Setpoint 0
004 Determination
EA-ELEC-EDSA- Palisades AC Power System Short Circuit Analysis 2
006
EA-ELEC-EDSA- DC System Battery D02 Short Circuit Analysis 1
EA-GL-89-10-01 Generic Letter 89-10 Motor Operated Valve (MOV) Thrust 11
Window Calculations
EA-GL-89-10-05 Design Valve Factors for Palisades GL - 89-10 MOVs 02/03/1999
EA-GL-89-10-10 Periodic Verification of GL-89-10 MOV Operating Margins 3
Using Static Diagnostic Test Results
EA-GL-8910-02 Torque Loss Calculation for MOVs at Elevated 3
Temperatures
EA-GL-8910-04 Replacement of MOV Stem Lubricant 0
Inspection Type Designation Description or Title Revision or
Procedure Date
EA-GL-8910-DP- Consolidated MOV 89-10 Analysis of the Worst Case 2
Operating Scenarios
EA-MOV-KALSI- Fatigue Life Prediction of Limitorque Type SBM/SB/SBD 05/11/1995
Actuator Torsional Components
EA-PIPEFLO- Service Water Hydraulic Model Using Pipe - Flo 2
SWS-01
EA-PLTB-02 Pressure Locking Evaluation for MOV 3015 and 3016 0
Corrective Action CR-PLP-2020- 2020 Design Bases Assurance Inspection, the NRC 03/03/2020
Documents 00712 Identified a Small Amount of Green Corrosion on Station
Resulting from Battery ED-01 Cell #43 Positive Post
Inspection CR-PLP-2020- During DBA Inspection Walkdown of High Pressure Air 03/04/2020
00737 Compressor T-9A in East Safeguards, Temporary Lighting
with no Work Tags and Unplugged was Found Around T-9A
CR-PLP-2020- Work Order (WO) 52790738 was Found to Be Missing Page 03/05/2020
00743 16 of the Completed RE-133 Procedure
CR-PLP-2020- During the 2020 Design Bases Assurance Inspection, the 03/05/2020
00753 NRC Questioned why the Dial Setting on One of the
Adjustable Trips on Battery Charger ED-15 Output Breaker
2-15A is Set at a Different Position than the Other
Adjustable Trip Settings
CR-PLP-2020- 2020 Design Bases Assurance Inspection, the NRC 03/05/2020
00754 Identified, During an ED-01 Walkdown, a Lid Crack Between
the Positive Posts of Cell #23
CR-PLP-2020- During the 2020 Design Bases Assurance Inspection, the 03/18/2020
00882 NRC Questioned the Technical Specification Impact from
Non-Functional High Pressure Air Compressors C-6A/B
CR-PLP-2020- During the 2020 Design Bases Assurance Inspection, It was 03/18/2020
00888 Identified that Section 9.5.2.5 Implies There is a Mitigating
Function for High Pressure Air Compressors
Drawings E-1, Sheet 1 Single Line Meter & Relay Diagram, 480 Volt Motor Control 90
Center
E-1, Sheet A Single Line Meter & Relay Diagram 15
E-5, Sheet 1 Single Line Meter & Relay Diagram, 480 Volt Motor Control 59
Centers
Inspection Type Designation Description or Title Revision or
Procedure Date
E-625 Wiring Diagram Battery D02, Fuse Box JL259 9
E-8 Single Line Meter & Relay Diagram, 125 Vdc, 120 V 61
Instrument & Preferred AC System
E-8, Sheet 1 Single Line Meter & Relay Diagram 125 Vdc, 120 V 58
Instrument & Preferred AC System
E-8, Sheet 2P 125 Vdc Distribution Panel No 2 ED21-1 Breaker Schematic 4
Diagrams
M-207, Sheet 2 P&ID Auxiliary Feedwater System 45
M-207, Sheet 3 P&ID P-8D/K-17 Diesel Driven Auxiliary Feedwater System 2
M-213 P&ID Service Water, Screen Structure and Chlorinator 97
Engineering 0000060795 125 Vdc Panel ED-21-1 Replacement 0
Changes EC#0000054503 250/251-205: Replace Obsolete O/C Relay For Pump P-2B 09/10/2015
Engineering PLP-RPT-12- Engineering Report System Protection Engineering 0
Evaluations 0014 Protective Device Calculation Review (EGAD-ELEC-22)
Miscellaneous 00520027 QO-14A-P-7A IST Service Water Pump 10/25/2019
5608 LCR 25: Foreign Material Inside Jar 05/08/2019
7S007.0 Seismic Test Report for C&D Batteries P/N: LCUN-33 1
Completed Test: Service Water Flow Verification 1R26 11/12/2018
9.20
DBD-1.02 Design Basis Document (DBD) Service Water System 10
DBD-1.05 Design Basis Document for Compressed Air Systems 6
DBD-2.01 DBD Low Pressure Safety Injection System 12
DBD-2.04 Design Basis Document for Primary Coolant System 8
DBD-4.02 DBD for 125 Vdc System (Safety-Related) 10
DPR-20 Palisades Plant - Facility Operating License 02/21/1991
E11B Specification for Inverter ED-06, ED-07, ED-08, and ED-09 0
and Battery Charger D15, D16, D17 and D18 Replacement
E11B-1 Solidstate Controls, Inc. Instruction/Technical Manual 200 0
Ampere Charger - Palisades
EA-SC-96-033-01 Replace Existing Chargers/Inverters 1
ESI-SR-17-199 Seismic Qualification of Speed Switch, 125 Vdc Input ESI 0
P/N: ESI50269B (DYNALCO P/N: SST2400A-424)
LER - 98-006-01 Licensee Event Report - Manual Operator Actions Not 1
Inspection Type Designation Description or Title Revision or
Procedure Date
Adequately Addressed in Operating Procedures
NB-PSA-SY-CIS Palisades Probabilistic Risk Analysis (PRA) System 0
Notebook Containment Isolation and Penetrations
NB-PSA-SY-HPA Palisades PRA Notebook High Pressure Air System 0
NB-PSA-SY-PZR Palisades PRA Notebook Pressurizer Pressure and Level 0
Control System and Power Operated Relief Valves
NB-PSA-SY-SWS Palisades PRA Notebook Service Water System 1
OE-NOE-2017- NRC-IN-2017-06 - Battery & Battery Charger Short-Circuit 10/04/2017
00346 Contributions to a Fault on the Direct Current Distribution
System
PLLP-ESPO- Training: Palisades Basis System Orientation - Service 5
PBSO-SWS Water System
QO-14B 0120 Completed Test: Inservice Test Procedure - Service Water 01/14/2020
Pumps
RO-144 1R26 Completed Test: Comprehensive Pump Test Procedure, 11/12/2018
Service Water Pumps P-7A, P-7B, P-7C 1R26
SC 96-033 Replace Safety Related Battery Chargers ED-15,16, 17& 18 0
& Inverters ED-06, 07, 08 & 09
Specification No: Specification for Service Water Pumps Palisades Plant 08/25/1967
5935-M-11 Consumers Power Company
T-SC-96-033-01 Post Installation Test for Battery Charger 1 (ED-15) 2
Procedures AOP-23 Primary Coolant Leak 2
AOP-23 Primary Coolant Leak 2
AOP-23 Primary Coolant Leak 2
ARP-3 Electrical Electrical Auxiliaries and Diesel Generator Scheme EK-05 82
Auxiliaries and (EC-11)
Diesel Generator
Scheme Rev. 82
EK-05 (EC-11)
EN-DC-167 Classification of Structures, Systems, and Components 11
EOP-4.0 Loss of Coolant Accident Recovery 24
EOP-9 MVAA-CA Maintenance of Vital Auxiliaries - Air 20
EPS-I-10 Diesel Generator 1-1 Electronic Speed Switch Calibration 7
and Interlock Check
Inspection Type Designation Description or Title Revision or
Procedure Date
Procedure No Material Condition Standards and Housekeeping 31
1.01 Responsibilities
RT-41 Pressurizer Safety Valves RV-1039, RV-1040, RV-1041 6
SOP-12 Feedwater System 81
SOP-20 High Pressure Control Air System 38
Work Orders 00515984-01 C-6A, Replace HP & LP Heads 08/19/2019
51660162-01 ED-15; Overhaul Battery Charger 05/06/2010
2436095 VOP 315 Static Test 03/30/2017
2646112-02 Design Engineering System Protection - Settings Station 05/02/2017
Battery Charger #1 ED-15
2687593-01 ED-15 Battery Charger #1 PM 11/09/2017
2693245-01 RE-133 -ED-15, Battery Charger No 1 Performance Test 11/09/2017
2713165-01 SPTS-1474; Replace Speed Switch (EC 75105) 02/06/2018
2722763-02 1-1 Diesel Tach Pak Calibration 02/08/2018
2764439 Inspect Electrical Panel Water Seals 01
2847642 QO- 4 Shutdown Cooling Valves IST 07/31/2019
10