IR 05000341/2019012
| ML19211B289 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/29/2019 |
| From: | Karla Stoedter NRC/RGN-III/DRS/EB2 |
| To: | Fessler P DTE Energy |
| References | |
| IR 2019012 | |
| Download: ML19211B289 (25) | |
Text
July 29, 2019
SUBJECT:
FERMI POWER PLANT, UNIT 2DESIGN BASIS ASSURANCE INSPECTION (TEAMS); INSPECTION REPORT 05000341/2019012
Dear Mr. Fessler:
On July 10, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2, 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.
Two findings of very low safety significance (Green) are documented in this report. Two of these findings involved violations of NRC requirements. The 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 non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violations or significance or severity of the violations documented in this inspection report, 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 III; the Director, Office of Enforcement; and the NRC Resident Inspector at Fermi.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Fermi. 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, Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety
Docket No. 50-341 License No. NPF-43
Enclosure:
As stated
Inspection Report
Docket Number:
05000341
License Number:
Report Number:
Enterprise Identifier: I-2019-012-0005
Licensee:
DTE Electric Company
Facility:
Fermi Power Plant, Unit 2
Location:
Newport, MI
Inspection Dates:
May 06, 2019 to July 10, 2019
Inspectors:
A. Dahbur, Senior Reactor Inspector
N. Feliz-Adorno, Senior Reactor Inspector
W. Hopf, Contractor
M. Jones, Reactor Inspector
L. Rodriguez, Reactor Inspector
R. Waters, Contractor
Approved By:
Karla K. Stoedter, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Fermi Power Plant, Unit 2, 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.
Licensee-identified non-cited violations are documented in report sections: 71111.21M.
List of Findings and Violations
Failure to Incorporate Acceptance Limits Contained in High Pressure Coolant Injection Design Documents Into Test Procedure Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2019012-01 Open/Closed
[H.8] - Procedure Adherence 71111.21M The inspectors identified a finding of very low safety significance (Green) and an associated Non-Cited Violation (NCV) of Title 10 of the Code of Federal Regulations (CFR), Part 50,
Appendix B, Criterion XI, Test Control, for the licensee's failure to incorporate the minimum total developed head acceptance limits contained in Design Document DC-0501, HPCI Hydraulic Analysis, Revision F, into Test Procedure 24.202.01, HPCI Pump and Valve Operability Test at 1025 psi, Revision 118.
Non-Conservative Motor-Operated Valve Output Torque Capacity Methodology Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2019012-02 Open/Closed None (NPP)71111.21M The inspectors identified a finding of very low safety significance (Green) and associated NCV of 10 CFR Part 50, Appendix B, Criterion III, Design Control, for the licensee's failure to verify the adequacy of the output torque capacity of safety-related motor-operated valves (MOVs).
Specifically, the licensee evaluated MOV output torque capability, in part, by using the ComEd WP-125 method and the full motor nominal voltage (rather than using the calculated terminal voltage) when the calculated voltage was greater than 90 percent of the nominal voltage.
However, the use of full motor nominal voltage when calculating the output torque capacity using the ComEd WP-125 method was non-conservative and resulted in output torque values which were not reflective of the actual motor capacity limit needed to ensure safety-related MOVs would perform their safety function.
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 licensee 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 components and associated attributes, permanent modifications, and operating experience listed below. During this review, the inspectors noted degradation of containment coatings and became concerned that the coatings could peel off and interfere with the operation of safety systems in the unlikely event of an accident. The NRC determined this concern warranted additional inspection by a Special Inspection Team. The results of the Special Inspection will be documented in Inspection Report 05000341/2019050.
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===
- (1) Drywell Exhaust and Air Purge Isolation Valves (T4803-F602 & T4600-F411/F402)
- Licensing basis requirements
- Material condition and configuration
- Operating procedures
- System health, corrective maintenance, and corrective action history
- Maintenance effectiveness
- Consistency between station documentation (e.g., procedures) and vendor specifications
- Environmental qualification
- Valve capability calculations
- Air supply availability and capability
- Stroke timing
- Testing procedures, acceptance criteria, and recent results
- Thermal overload testing and sizing
- Response to degraded voltage
- Minimum voltage calculation
- Torque requirement calculation Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (5 Samples)
- (1) High Pressure Coolant Injection (HPCI) Pump (E4101C001A)
- Licensing basis requirements
- Material condition and configuration
- Operating procedures
- Modifications
- System health, corrective maintenance, and corrective action history
- Maintenance effectiveness
- Consistency between station documentation (e.g., procedures) and vendor specifications
- Turbine and pump performance and capability calculations
- Runout and minimum flow
- Submergence (i.e., net positive suction head (NPSH) and vortexing)
- Protection against flooding and seismic events
- Water supply availability
- Steam supply availability
- Suction strainer blockage
- Gas intrusion and hydraulic transients
- Room heat up and ventilation
- Component lubrication
- Surveillance and test procedures, acceptance criteria, and results
- Control logic for turbine trips and pump start
- Component control instrumentation
- Instrumentation set point calculations
- (2) Reactor Core Isolation Cooling (RCIC) Pump (E5101C001)
- Licensing basis requirements
- Material condition and configuration
- Operating procedures
- Protection against flooding, seismic events, and high energy line breaks
- Maintenance effectiveness
- Component health, corrective maintenance, and corrective action history
- Consistency between station documentation (e.g., procedures) and vendor specifications
- Turbine and pump performance and capability calculations
- Runout and minimum flow
- Submergence (e.g., NPSH and vortexing)
- Water supply availability
- Gas intrusion and hydraulic transients
- Room heat up and ventilation calculations
- Surveillance and test procedures, acceptance criteria, and results (3)260/130 Volt DC Main Distribution Panels 2PA-2 and 2PB-2 (R3200S026/7)
- Licensing basis requirements
- Operating procedures
- Component health, corrective maintenance, and corrective action history
- Maintenance effectiveness
- Flood and seismic protection
- Room heat up and ventilation
- Surveillance and test procedures, acceptance criteria, and results
- Load, short circuit, and coordination calculations
- Temperature effects and environmental qualification
- Inverter capacity and capability to supply adequate voltage
- Cable ampacity
- Protective breakers and trip set points
(4)130/260 Volt DC Battery 2PA and 2PB (R3200S003/4)
- Licensing basis requirements
- System health, corrective maintenance, and corrective action history
- Maintenance effectiveness
- Performance testing
- Technical Specification required surveillance testing
- Discharge testing
- Battery charger sizing
- Terminal corrosion resistance
- Battery sizing and loading
- Short circuit calculation
- Voltage drop calculation
- Protection against flooding and seismic events
- Room heat up and ventilation calculations
- (5) Safety Relief Valve (B2104F013A)
- Licensing basis requirements
- Operating procedures
- System health, corrective maintenance, and corrective action history
- Maintenance effectiveness
- Consistency between station documentation (e.g., procedures) and vendor specifications
- Environmental qualification
- Relief capacity
- Accumulator sizing calculations
- Pneumatic supply capability
- Lift settings
- Low-low set setpoint
- Surveillance and test procedures, acceptance criteria, and results
- Control logic
Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)
(1)
===37272.001, RCIC Pump Discharge High Point Vent Relocation
- (2) Calculation Change DC-0501 VOL I, HPCI Hydraulic Analysis
- (3) Calculation Change DC-6478 VOL I, 120 Volts Alternating Current Protective Device Coordination Calculation for Divisions 1 and 2
- (4) Calculation Change DC-5512 VOL I, Evaluation of 1E/Non-1E Separation Criteria
Review of Operating Experience Issues (IP Section 02.06)===
- (1) NRC Information Notice 2005-30, Safe Shutdown Potentially Challenged by Unanalyzed Internal Flooding Events and Inadequate Design
- (2) NRC Information Notice 2017-06, Battery and Battery Charger Short-Circuit Contribution to a Fault on DC System
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.21M 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 (NCV), consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix B, Criterion XVI, Corrective Action, requires, in part, that measures be established to assure conditions adverse to quality (CAQ), such as non-conformances, are promptly identified and corrected.
Contrary to the above, between June 28, 2007, and April 26, 2019, the licensee failed to establish measures to assure a CAQ was promptly corrected. Specifically, on June 28, 2007, the licensee identified the HPCI, RCIC, and core spray (CS) pumps, which are safety-related, were not protected from air-entraining vortices when their suctions were aligned to the condensate storage tank. This CAQ was captured in the Corrective Action Program as CARD 07-23630. However, on April 26, 2019, the licensee identified they had not corrected this CAQ because the implementation of the proposed corrective action (i.e., installation of a vortex suppressor) had been deferred multiple times without an appropriate justification.
Significance: Green. The finding was evaluated using the Significance Determination Process in accordance with Inspection Manual Chapter 0609 Appendix A, The Significance Determination Process for Findings At-Power, using Exhibit 2, Mitigating Systems Screening Questions. The finding screened as having very low safety significance (Green) because it did not result in the loss of operability or functionality of the HPCI, RCIC, or CS pumps.
Specifically, the licensee reasonably determined the HPCI and RCIC pump suctions would likely transfer to the torus before vortexing became a concern during a design basis event by crediting the torus high water level automatic suction transfer. In addition, the licensee reviewed historical condensate storage tank water levels and reasonably determined the condensate storage tank actual level was sufficient to enable CS to accomplish its function before vortexing became a concern.
Corrective Action References: CARD 07-23630, CARD 19-23227, CARD 19-23632, CARD 19-23797, and CARD 19-23966 Observation: Effectiveness Review of Corrective Actions Taken by the Licensee to Issues Identified during Previous Component Design Basis Inspection and Design Bases Assurance Inspections 71111.21M In accordance with IP 71111.21M, Section 02.05c, the inspectors reviewed the effectiveness of corrective actions taken by the licensee to address issues identified during previous Component Design Basis Inspections and Design Bases Assurance Inspections. No findings or violations were identified. The items reviewed were:
1. NCV 05000341/2007003-03, HPCI Pump In-Service Testing Acceptance Criterion
Was Not Conservative with Respect to the System Performance Requirements.
2. NCV 05000341/2016007-07, Failure to Ensure that Protective Devices for the Loads
Required at the Beginning of a Loss of Coolant Accident Would Not Trip Under Degraded Voltage Conditions.
Failure to Incorporate Acceptance Limits Contained in High Pressure Coolant Injection Design Documents into Test Procedure Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2019012-01 Open/Closed
[H.8] - Procedure Adherence 71111.21M The inspectors identified a finding of very low safety significance (Green) and an associated NCV of 10 CFR Part 50, Appendix B, Criterion XI, Test Control, for the licensees failure to incorporate the minimum total developed head acceptance limits contained in Design Document DC-0501, HPCI Hydraulic Analysis, Revision F, into Test Procedure 24.202.01, HPCI Pump and Valve Operability Test at 1025 psi, Revision 118.
Description:
The HPCI pump is safety-related and is part of the emergency core cooling systems designed to provide core cooling during design basis events. To verify the pump develops the flow rate required by the applicable safety analyses, Technical Specifications Surveillance Requirement (SR) 3.5.1.9 requires periodic in-service testing in accordance with the ASME OM Code. This SR is implemented by Procedure 24.202.01, HPCI Pump and Valve Operability Test at 1025 psi, Revision 118, which is intended to evaluate test results against the acceptance criteria established by Calculation DC-0501, HPCI Hydraulic Analysis, Revision F.
However, the inspectors noted the HPCI pump minimum total developed head acceptance limits contained in Procedure 24.202.01 were less restrictive than the acceptance limits established in Calculation DC-0501. Therefore, the test procedure acceptance limits did not ensure the HPCI pump was capable of developing the flow rates required by the applicable safety analyses.
Further review determined the calculation was revised in January 2018, and the licensee failed to update the procedure with the revised acceptance limits. Through discussions with the licensee, the inspectors learned the test procedure was not updated because a procedure revision notice had not been issued. The licensee relies on procedure revision notices to identify and update procedures affected by calculation changes.
Corrective Actions: As an immediate corrective action, the licensee reviewed historical test data obtained since the issuance of Revision F of DC-0501 and reasonably determined the HPCI pump performance was acceptable. The licensees proposed corrective action is to revise Procedure 24.202.01 before the next scheduled test to incorporate the revised acceptance limits.
Corrective Action References: CARD 19-23989
Performance Assessment:
Performance Deficiency: The inspectors determined the licensees failure to incorporate the acceptance limits contained in Design Document DC-0501, Revision F, into Test Procedure 24.202.01, Revision 118, was contrary to 10 CFR Part 50, Appendix B, Criterion XI, Test Control, and was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the failure to incorporate the acceptance limits contained in the revised hydraulic analysis into the test procedure would have the potential to lead to the acceptance of a condition where the HPCI pump is incapable of performing its accident mitigating function.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The finding affected the Mitigating Systems cornerstone and screened as having very low safety significance (Green) because it did not result in the loss of operability or functionality of the HPCI pump.
Specifically, the licensee reviewed historical test data since the issuance of Revision F of DC-0501 and reasonably determined the HPCI pump performance was acceptable.
Cross-Cutting Aspect: H.8 - Procedure Adherence: Individuals follow processes, procedures, and work instructions. Specifically, the licensee did not identify and update procedures affected by the revision of Calculation DC-0501 in 2018, which was not in accordance with Procedure MES20, Implementation of Modifications, Revision 35B.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion XI, Test Control, requires, in part, that a test program be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents. The licensee established Procedure 24.202.01, HPCI Pump and Valve Operability Test at 1025 psi, Revision 118, as the implementing procedure for the HPCI in-service testing required by SR 3.5.1.9. Also, the licensee established Calculation DC-0501, HPCI Hydraulic Analysis, Revision F, as the design document for the applicable test acceptance limits.
Contrary to the above, since January 2018, the licensee failed to establish a test program to assure that testing required to demonstrate the safety related HPCI pump will perform satisfactorily in service was identified and performed in accordance with written test procedures which incorporated the requirements and acceptance limits contained in applicable design documents. Specifically, the licensee failed to incorporate the HPCI minimum total developed head acceptance limits contained in Revision F of DC-0501 into Revision 118 of Test Procedure 24.202.01.
Enforcement Action: This violation is being treated as an NCV, consistent with Section 2.3.2 of the Enforcement Policy.
Non-Conservative Motor-Operated Valve Output Torque Capacity Methodology Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2019012-02 Open/Closed None (NPP)71111.21M The inspectors identified a finding of very-low safety significance (Green) and associated NCV of 10 CFR Part 50, Appendix B, Criterion III, Design Control, for the licensee's failure to verify the adequacy of the output torque capacity of safety-related MOVs. Specifically, the licensee evaluated MOV output torque capability, in part, by using the ComEd WP-125 method and the full motor nominal voltage (rather than using the calculated terminal voltage) when the calculated voltage was greater than 90 percent of the nominal voltage. However, the use of full motor nominal voltage when calculating the output torque capacity using the ComEd WP-125 method was non-conservative and resulted in output torque values which were not reflective of the actual motor capacity limit needed to ensure safety-related MOVs would perform their safety function.
Description:
The licensee verified MOV output torque capacity in Calculation DC-5719, Minimum Required Target Thrust (MRTT) for Generic Letter 89-10 Gate, Globe and Quarter-Turn Valves, Revision V. This calculation determined output torque values using the following two methods:
- (1) the Limitorque Torque Capability method and
- (2) the ComEd WP-125 method. Regardless of the calculational method used, the licensee utilized full nominal voltage values as an input even when expecting degraded voltage values. The licensee selected the higher of the resulting two output torque values as the motor capability limit during MOV diagnostic testing, which was intended to demonstrate the MOVs can perform their accident mitigating functions.
The inspectors noted the use of full nominal voltage in place of the degraded terminal voltage was only allowed by the Limitorque Torque Capability method. Specifically, Limitorque Technical Update 98-01 allowed for the use of full nominal voltage in place of the calculated terminal voltage when the calculated value was greater than 90 percent of the nominal value.
However, the application of this voltage allowance when calculating output torque values using the ComEd WP-125 method was not allowed because it resulted in non-conservative output torque values and could result in multiple safety-related valves being unable to perform their mitigating functions.
Corrective Actions: As an immediate corrective action, the licensee preliminarily revised their calculation with the correct version of the ComEd WP-125 method using the calculated terminal voltage and determined eight MOVs had negative analytical torque margin. As a result, the licensee performed further analysis for these MOVs using different analytical strategies and reasonably determined they remained operable. These MOVs were the reactor recirculation pump A discharge isolation valve (B3105F031A), residual heat removal (RHR)
Division 1, pump C, suppression pool suction isolation valve (E1150F004C), RHR Division 2 drywell spray inboard isolation valve (E1150F021B), RHR Division 1 suppression pool containment spray test isolation valve (E1150F028A), RHR Division 2 suppression pool containment spray test isolation valve (E1150F028B), CS Division 2 torus suction isolation valve (E2150F036B), reactor building close cooling water Division 1 supply isolation valve (P4400F603A), and emergency equipment cooling water Division 1 drywell return outboard isolation valve (P4400F607A).
Corrective Action References: CARD 19-23915, CARD 19-23640, CARD 19-23636, CARD 19-23865, and CARD 19-23863.
Performance Assessment:
Performance Deficiency: The inspectors determined the licensees failure to verify the adequacy of the output torque capacity for safety-related MOVs was contrary to the requirements of 10 CFR Part 50, Appendix B, Criterion III, Design Control, and was a performance deficiency. Specifically, the licensee evaluated MOV output torque capability, in part, by using the ComEd WP-125 method and the full motor nominal voltage in place of the calculated terminal voltage when the calculated value was greater than 90 percent of nominal. However, the use of full nominal voltage in place of the calculated terminal voltage for calculating the output torque capacity using the ComEd WP-125 method was non-conservative.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone. The performance deficiency adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of mitigating systems to respond to initiating events to prevent undesirable consequences. Specifically, the failure to verify the adequacy of safety-related MOV output torque capacity did not ensure the MOVs were capable of performing their accident mitigating functions.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The finding screened as of very low safety significance (Green) because it did not result in the loss of operability or functionality of mitigating systems. Specifically, the licensee performed an operability evaluation and reasonably determined that all impacted MOVs remained operable.
Cross-Cutting Aspect: Not Present Performance. No cross cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, states, in part, that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.
Contrary to the above, as of May 21, 2019, the licensee failed to verify or check the adequacy of design of safety-related MOVs by the performance of design reviews, the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.
Specifically, the licensee evaluated MOV output torque capability, in part, by using the ComEd WP-125 calculational method and the full motor nominal voltage when the calculated terminal voltage was greater than 90 percent of the nominal voltage. However, the use of full nominal voltage in place of the calculated terminal voltage for calculating the output torque capacity using the ComEd WP-125 method was non-conservative and resulted in output torque capabilities which were not reflective of the those needed during accident conditions.
Enforcement Action: This violation is being treated as an NCV, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
- On July 10, 2019, the inspectors presented the Design Basis Assurance Inspection (Teams) inspection results to Paul Fessler and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
2-00058
Summary Report for the GE Component Seismic Evaluation
RCIC System
BE
DBD-E51-00
Reactor Core Isolation Cooling
F
DC-0369 Volume
I
RCIC System Design Computations
F
DC-0469 Volume
I
Essential Accumulators for Class I Valves (MSIVs,
ADS-SRVs, LLS-SRVs)
04/17/1997
DC-0501
HPCI Hydraulic Analysis
F
DC-0502 Volume
I
RCIC Hydraulic Analysis
G
DC-0885
ECCS Suction Line Air Ingestion
E
DC-0885 Volume
I
ECCS Suction Line Air Ingestion
E
DC-3078
Reactor Water Level Transmitters: Zero Elevation and Span
C
DC-4255 Volume
II
Sizing of the Primary Containment Pneumatic Supply
Back-Up Nitrogen Bottles
08/25/2008
DC-4523
Reactor Wide Range Water Level Surveillance Procedure
Validation
J
DC-4523 Volume
I
Reactor Wide Range Water Level Surveillance Procedure
Validation
J
DC-4528
Reactor Narrow Range Water Level Surveillance Procedure
Validation
G
DC-5147 Volume
I
DBTF Concerns With Battery Room/Charger Area HVAC
DC-5426 Volume
I
PBOC - High and Moderate Energy Line Break Evaluation
D
DC-5487
Maximum Expected Differential Pressure (MEDP) for Valves
T4803F601, F602, T4804F601A/B, F602A/B, F603A/B,
F604A/B, F605A/B, F606A/B, F001A/B, F002A/B, F003A/B
C
DC-5589 Volume
I
Reactor Building Environmental Response for HELB and
LOCA Conditions
C
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DC-5719 VOL I
Minimum Required Target Thrust (MRTT) for Generic letter
89-10 Gate, Globe and Quarter-Turn Valves (Torque)
V
DC-5954 Volume
I
Anchorage Qualification of Div. II 260/130V Battery Racks
DC-5979
Estimation of Debris Sources for ECCS Suction Strainers
DC-6212 Volume
I
Environmental Response Profiles for Areas Containing
Safety Related Equipment
A
DC-6372 Volume
I
Assessment of Channel Instrument Error (CIE) for RCIC
Flow and Speed Loops
DC-6397 Volume
I
Calculation of Safety Related GL 89-10/96-05 and non
GL 89-10/96-05 AC MOV Motor Terminal Voltages
C
DC-6478 Volume
I
20 VAC Protective Device Coordination Calculation for
Division 1 and 2
C
DC-6480 Volume
I
130/260 DC System Analysis
C
DC-6480 Volume
I
130/260 V DC System Analysis
C
DC-6482
260/130V and 48/24V DC Protective Devices Coordination
C
DC-6482 Volume
I
260/130V and 48/24V Protective Device Coordination
Calculation
C
EDP-37272
RCIC Pump Discharge High Point Vent Relocation
M4A
SBFW Pump NPSHA
2/10/2008
QR-284030-01
Environmental and Seismic Qualification Report
TSR-35639
Revision of Design Calculation DC-2680
A
TSR-36510
Issue New/Revised AOV Torque Calculations (2206C,
2399C, 2402C, 2414C, DC-5989 Vol. I), update CECO, and
Relevant BCDDs for Re-Analysis Using Lower Air Pressure
TSR-37565
Revise CECO & Post Changes Against BCDDs Such as
DC-5719 and DC-6083 (Both Vol. I)
Corrective Action
Documents
05-25383
SEN Internal Flood Design Deficiencies
05/20/2009
07-23630
CDBI: UFSAR Anti-Vortex Methodology Non-Conservative
06/28/2007
07-23851
NRC CDBI Inspection Item 073: HPCI IST Test Acceptance
Criteria Inadequate
07/11/2007
09-20540
WGI(URS) Review of the Design Calculation DC-0215
01/27/2009
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10-298000
Degraded Torus Earthquake Tie Attached to Bay 9
10/30/2010
2-24503
Potential Non-Conservative Application of TS SR 3.5.1.4
05/16/2012
13-20872
HPCI Booster Pump Outboard Bearing Level Indication
2/05/2013
14-21750
Stroke Time Limits for T4600F402 do not Match in
24.404.03 Between Sections 5.1 and 5.2
2/27/2014
14-23884
Conflicting Design Basis MEDP Capability for T4803F601
and T4803F602
05/05/2014
15-20116
Revise 23.205 for LPCI Inoperability in SDC
01/06/2015
15-28410
Degraded Coatings Identified Inside the Torus
10/29/2015
16-26533
2016 CDBI Issue - Non-Conformance to License Bases for
Evaluation of Degraded Voltage
08/17/2016
16-26800
CDBI: Inappropriate Disposition of Penetration Min-K Debris
Generation
08/26/2016
17-22973
Extensive Coating Defects Identified during Torus
Underwater Inspection
04/02/2017
17-23743
RCIC Turbine Oil Filter Inlet Pressure Indication Reading
Low OOS
04/19/2017
17-25515
Drains Backed up Causing Overflow on to Floor
06/22/2017
18-24343
Procedure and Required M&TE Inconsistency
05/31/2018
18-24957
Floor Drains Overflowed From Pumping Down Sump DO-74
06/26/2018
18-26749
RCIC Lube Oil Pump Discharge Pressure Trend
09/07/2018
18-27527
Foreign Material Found in SRV T-Quencher in Bay 16
09/29/2018
19-23227
Recommend Review of Site Response to Open CARD 07-
23630
04/26/2019
19-23383
Oil Drops on HPCI Turbine Stop Valve Actuator
05/02/2019
91-0840
Seismic Adequacy of CST Water Source
10/31/1991
OE 2017-0529
IN-17-06, Battery and Battery Charger Short-Circuit Current
Contributions to a Fault on the Direct Current Distribution
11/03/2017
Corrective Action
Documents
Resulting from
Inspection
19-23216
PSA Main Control Room Abandonment Modeling
Discrepancy
04/26/2019
19-23490
2019 DBAI: DC-4523 Vol 1, Rev. J, Missing and Not
Updated References for NTSPs Moved From Tech Specs to
TRM (Legacy Issue)
05/06/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
19-23493
2019 DBAI: Discrepancy Between UFSAR and Tech Spec
Bases
05/06/2019
19-23495
2019 DBAI: Drawing I-2225-05 has the Incorrect PIS for
HPCI Turbine Speed Indicator
05/06/2019
19-23534
2019 DBAI: I-2201-15 Reference Drawing Listed for
Testability Trip Unit Relay B31K202A is Incorrect (Legacy
Issue)
05/07/2019
19-23571
2019 DBAI: DC-6480 Vol. I, Rev. C Issued Without Updating
Impacted MOV Outputs
05/08/2019
19-23574
2019 DBAI: Ambient Temperature Rating for DC Distribution
Cabinets R3200S026 and R3200S027
05/15/2019
19-23579
CARD 18-21882, Inadequate Evaluation of IN-1706
05/09/2019
19-23582
2019 DBAI: Use of Non-Conservative Values During
2.309.05
05/09/2019
19-23592
2019 DBAI: Two SRV Accumulator Check Valve Test
Procedures Exist
05/09/2019
19-23615
Unnecessary Evaluation of a Fault in DC Control Circuit for
480 Switchgear Breaker Feeding Non-1E Load from 1E
480V 1E Bus in Calculation DC-5512
05/09/2019
19-23616
2019 DBAI, SRV Set-Point out of Tolerance not Evaluated
for LLS/ADS SRVs
05/09/2019
19-23631
2019 DBAI: CST Valve Pit not Included on Confined Space
List
05/10/2019
19-23632
2019 DBAI: Update to 23.107.01 Section 3.5 to Correct
Inconsistency With Last Update
05/10/2019
19-23636
2019 DBAI: E4150F003 CECO Design Basis Open Stroke
Time Does not Match TRM 3.6-5 Open Stroke Time Note
05/10/2019
19-23637
2019 DBAI: HPCI/RCIC Procedures 24.202.03 and
24.206.03
05/10/2019
19-23640
DC-6447 Issued without Updating Impacted MOV Outputs
05/10/2019
19-23651
Information Notice IN-1706 - Battery Charger (Ametek) May
Contribute up to 10 Times their Rating for a Short Period
05/10/2019
19-23689
Calculation DC-6397 not Updated for Change to Thermal
Overload Resistance for Valve T4803F602
05/13/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
19-23754
2019 DBAI: Ambient Temperature Rating for DC Distribution
Cabinets R3200S026 and R3200S027
05/15/2019
19-23764
2019 DBAI: Typographical Errors Found in DC-3078 Vol. I
05/15/2019
19-23780
2019 DBAI: SRV Coatings/Corrosion When Shifting to a 24-
Month Cycle
05/16/2019
19-23797
2019 DBAI - Revisions to Procedures Related to CST Level
for Modes 4 and 5
05/16/2019
19-23850
2019 DBAI: Potential Trend in Missed Impacted Calculations 05/20/2019
19-23863
2019 DBAI: Margin Issues With AC Motor Operated Valves
05/20/2019
19-23865
2019 DBAI: Margin Issues With 250VDC Motor Operated
Valves Investigation
05/20/2019
19-23867
2019 DBAI: Past Operability Review not Documented for
CARD 17-23452
05/20/2019
19-23915
Methodology Error Found in MOV Torque Calculation
05/21/2019
19-23933
Revise HPCI/RCIC Surveillances to Clarify Tech Spec
Acceptance Criteria
05/22/2019
19-23939
2019 DBAI: MRFF Action Needed for Previously Closed
CARD 17-23452
05/22/2019
19-23961
2019 DBAI Related (Untimely Corrective Action for Coating
Restoration on 180 Torus Earthquake Tie)
05/23/2019
19-23966
2019 DBAI: Additional Procedure Guidance Needed for Use
of Core Spray Aligned to Condensate Storage Tank in
Modes 4 and 5
05/23/2019
19-23975
2019 DBAI Related - Consider Revision of 43.000.004
(Reference DBAI Item 19-398)
05/23/2019
19-23989
2019 DBAI - DC-0501 Vol. I, was Updated in January 2018
to Revision F Without Required PPRN Reviews
05/23/2019
19-24218
2019 DBAI: NRC Concern Blistered Torus Coating
06/03/2019
CARD 19-24605
2019 DBAI: Recommended Clarifications to Procedure
43.000.019 Primary Containment Inspection
06/18/2019
Drawings
61721-2095-30
Schematic Diagram Nuclear BLR PRCS INSTR A & B
Circuits Testability Modification
L
61721-2155-01
Schematic Diagram Reactor Protection System Power
Distribution Notes & References
T
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
61721-2225-03
Schematic Diagram HPCI Logic Circuit PT 1
61721-2522-01
Tank Mounted Cabinet for Miscellaneous Instruments
O
61721-2654-14
Schematic Diagram - Nitrogen Inerating Inboard Isolation
Valve
Q
System Diagram Nuclear Boiler System
BN
System Diagram Nuclear Boiler System
AN
One Line Diagram; 260/130V ESS Dual Battery 2PA
Distribution-Division 1
One Line Diagram 260/130V ESS Dual Battery 2PB
Distribution - Division II
AQ
Engineering
Evaluations
16-0246
High Pressure Coolant Injection (HPCI) Hydraulic Analysis
DECO-12-2191
Evaluation of Containment Coatings
June 1985
EQ1-EF2-155
EEQ Qualification Evaluation Report - Target Rock Valves
2/25/2009
ERE 32092
MOV Lubrication Change
C
NUC2016135.00
Evaluation of Fermi 2 Blister Torus Wetted (Immersion)
Region Substrate Coatings
03/10/2017
Miscellaneous
System Health Report Associated With RCIC
2018 Q3 &
Q4
2A2918AB
Nuclear Boiler Design Specification Data Sheet
EF2-57987
Letter Subject: Errors in BWR Water Level Indication
07/15/1982
EF2-60002
Letter Subject: Errors in BWR Water Level Indication
10/11/1982
EFA-R32-19-005
Engineering Functional Analysis - Information Notice IN -
1706 - Battery Chargers Contribution Fault Conditions
EQ0-EF2-018
Summary of Environmental Parameters Used for Fermi 2
EQ Program
N
EQ1-EF2-044
Qualification Evaluation Report
G
Instrument Setpoint Methodology
A
NUC2017123
Reactor Torus Desludge, ASME XI IWE VT Exams,
Coatings, Inspection & Coating Repair - Immersion Area
05/30/2017
NUC2018130
Reactor Torus Desludge, ASME XI IWE VT Exams,
Coatings Inspection & Coating Repair - Immersion Area
11/12/2018
TSR-36108
Increases in ECCS Suction Strainer Debris Loads
VMR1-45.2
Vertical Induction Triclad Motors
F
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
VMR4-14.1
RCIC Turbine
G
VMR4-4.0
RCIC Pump
B
VMR4-4.1
RCIC Pump
A
NDE Reports
VT-S12-021
Torus Earthquake Ties (4 Locations)
04/14/2012
Operability
Evaluations
TE-B21-19-021
Past Operability Review for CARDs 19-23867 and 17-
23452
05/30/2019
TE-E11-18-081
Past Operability Evaluation of Foreign Material Impact to
ECCS Suction Strainers
Procedures
20.000.18
Control of the Plant from the Dedicated Shutdown Panel
20.000.18
Control of the Plant from the Dedicated Shutdown Panel
20.000.19
Shutdown from Outside the Control Room
20.300.Offsite
2A
23.104
Condensate Storage and Transfer System
23.107.01
Standby Feedwater System
23.201
Safety Relief Valves and Automatic Depressurization
System
23.206
Reactor Core Isolation Cooling Syste
103
23.309
260/130 DC Electrical System (ESF and BOP)
23.601
Instrument Trip Sheets
24.107.03
SBFW Pump and Valve Operability and Lineup Verification
Test
24.137.02
MSIV/ADS and LLS SERV Accumulator Check Valve Test
24.201.01
SRV Vacuum Breaker Valve Operability Test
24.202.01
HPCI Pump and Valve Operability Test at 1025 PSI
118
24.202.03
HPCI System Piping Filled and Valve Position Verification
24.206.01
RCIC System Pump and Valve Operability Test
24.206.03
RCIC Discharge Piping Venting and Valve Verification Test
24.206.04
RCIC System Automatic Actuation and Flow Test
24.404.03
Standby Gas Treatment System Valve Operability Test
24.406.02
Nitrogen Inerting System Valve Position Indication Test
27.000.09
Time Critical Actions Validations and Verification
29.100.01 Sheet
RPV Control
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
29.ESP-06
Primary Containment Venting and Purge for Hydrogen and
Oxygen Control
29.ESP.07
Primary Containment Venting
3017-128-EZ-04
Electrical Design Instruction for Control and Power Cable
Ampacities
C
43.137.001
Main Steam Safety/Relief Valve Setpoint Testing
43.137.002
SRV Accumulator Check Valve Test
26A
44.210.059
D1 MS SRV Solenoid Functional Test
ARP 1D24
RCIC System Actuated
ARP 1D69
SBFW Sys Suction Pressure Low
ARP 1D79
RCIC Turbine Shutdown RPV H2) Level L8
ARP 1D81
RCIC Pump Discharge Flow Low
ARP 2D48
HPCI/RCIC Suction Trans CST Level Low
ARP 8D40
Cable Tray Cooling Fan Tripped
QCP-10-1
Underwater Coating Inspection
QCP-10-2
Underwater Coating Repair
TE-ANL-12-069
Risk Significant PSA Credited Operator Actions
C
Self-Assessments TMPE-18-0180
Quick Hit Self-Assessment: Preparation for the 2019 NRC
Design Basis Assessment Inspection Self-Assessment
09/22/2018
Work Orders
1162000318
Perform 43.137.002 Division 1 SRV Accumulator Check
Valve Test
05/10/2000
116201093
Perform 43.137.002 Division 1 SRV Accumulator Check
Valve Test
11/13/2001
1162201117
SRV Accumulator Check Valve Test
11/17/2001
25975596
Desludge, Inspect, Repair - Torus Coatings Below Water
Level
05/21/2009
25975596
Desludge, Inspect, Repair - Torus Coatings Below Water
Level
04/01/2009
25980121
Perform HPCI Turbine Internal Inspection
06/08/2009
26766225
Perform 43.000.019 Inside Torus / Inside DW / Outside DW
(Offline) (VT-3) Inspection
04/15/2017
303100100
Perform Internal Inspection of RCIC Turbine per NUE NE-
PJ-90-0373
04/20/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
34379073
Perform 43.000.019 Inside Torus / Inside Drywell / Outside
DW (Offline) Inspection
03/14/2014
34567763
Perform 43.137.001 Main Steam Safety Relief Valves
Setpoint Test
03/27/2014
37491496
Inspection of Div. 2 Torus Suction Strainer (RHR, CS, HPCI)
2/09/2015
37545467
Perform 24.137.02
11/09/2015
37545495
Perform 24.137.02
11/12/2015
37734090
Perform 43.137.001 Main Steam Safety Relief Valves
Setpoint Test
2/04/2015
38115948
Perform 44.210.059 ECCS/ADS/MDS D1 SRV Solenoid
Functional Test
11/06/2015
38442118
Desludge, Inspect, Repair - Torus Coatings Below Water
Level
04/28/2017
38574156
Perform 24.206.01 RCIC System Pump Operability and
Valve Test @ 1000 PSIG
2/09/2016
281891
Perform 43.401.510 LLRT Purge and Vent Test 1:
T4803F602, T4600F402, T4600F411
01/14/2016
282032
Perform 24.404.03 Sec-5.1 SGTS Valve Operability Test
04/13/2016
43040731
Lube, Clean Cooling Coils, Replace Belts
09/22/2016
43168864
Perform 44.030.400 ECCS HPCI/RCIC CST Level,
E41N061B, Calibration/Functional
10/28/2016
43579247
EDP-37272 R18 Installation RCIC High Point Vent
04/20/2017
43648553
Perform 24.404.03 SEC-5.2 SGTS Valve Operability &
Position Indication Verif.
01/08/2017
44066355
Perform 24.201.01 SRV Vacuum Breaker Operability
03/21/2017
44151810
Perform 24.137.02
04/13/2017
44153720
Perform 44.210.059 ECCS/ADS/MDS D1 SRV Solenoid
Functional Test
04/10/2017
268548
Perform 24.406.01 Sec-5.2 N2 Inerting Cold S/D Valve
Operability/Timing Test
04/02/2017
44417440
Perform 43.137.001 Main Steam Safety Relief Valves
Setpoint Test
06/22/2017
44883915
Check P1100 Cabinet Space Heaters & Thermostats for
Proper Operation
08/09/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
45151430
Inspection of Div. 2 Torus Suction Strainers (RHR, CS,
HPCI)
06/23/2017
275955
Perform 24.404.03 Sec-5.1 SGTS Valve Operability Test
10/09/2017
46582800
Perform 44.030.401 ECCS HPCI/RCIC CST Level,
E41N061D, Calibration/Functional
06/21/2018
46748956
Perform 24.202.01 HPCI Pump/Flow Test & Valve Stroke at
25 PSIG
06/03/2018
203637
Check Listed Cabinet Space Heaters & Thermostats for
Proper Operation
08/07/2018
47345713
Perform 24.201.01 SRV Vacuum Breaker Operability
09/26/2018
47435850
Penetration X-25 Exceeds it Leakage Limit - Failed LLRT
06/08/2017
47460525
Perform 44.210.059 ECCS/ADS/MDS D1 SRV Solenoid
Functional Test
10/15/2018
47490205
Perform 24.406.01 Sec-5.2 N2 Inerting Cold S/D Valve
Operability/Timing Test
10/05/2018
47490879
Perform 24.137.02 for T4901-F040 Only
04/16/2017
47500501
Perform 24.137.02
10/19/2018
47510304
Perform 24.202.04 HPCI Offline Auto Initiation and Time
Response Test
10/22/2018
47525996
Perform 24.202.02 HPCI Flow Rate Test at 165 PSIG
10/21/2018
47526001
Perform 24.206.04 Sec. 5.2 RCIC System Automatic
Actuation Test
10/26/2018
47642989
Perform Mini Periodic MOV Inspection (T4803-F602)
10/03/2018
47654752
Perform 24.404.03 Sec-5.1 SGTS Valve Operability Test
09/18/2018
48399139
Perform 43.401.510 LLRT Purge and Vent Test 1:
T4803F602, T4600F402, T4600F411
09/20/2018
48555968
Perform 24.202.08 Sec-5.2 (DW Press) HPCI LSFT & Pump
Operability at 1025 PSIG
08/23/2018
48693770
Extensive Coating Defects Identified During Torus
Underwater Inspection
01/04/2019
48693770
Extensive Coating Defects Identified During Torus
Underwater Inspection
09/22/2018
48693800
Inspect and Repair Torus Coating, Above Water
01/24/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
49309090
Perform 44.060.002 RCIC System Logic Functional Test -
Online
05/06/2019
50350374
Perform 24.206.01 RCIC System Pump Operability and
Valve Test @ 1000 PSIG
10/26/2018
D167030100
Perform MOV Thermal O/L Test - T4803F602 @ MCC 72B-
3A POS-5C-R
05/01/2009
E016150100
Disassemble Motor, Inspect and Clean in Accordance With
NE-6/6-EQMS.036
06/14/2006
T577090200
Replace Valve Seat per EQ Requirement Contained in LTR
NE-6.6-EQMS.118
01/07/2016