IR 05000247/2020001
| ML20120A581 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/29/2020 |
| From: | Daniel Schroeder Reactor Projects Branch 2 |
| To: | Vitale A Entergy Nuclear Operations |
| Schroeder D | |
| References | |
| IR 2020001 | |
| Download: ML20120A581 (19) | |
Text
April 29, 2020
SUBJECT:
INDIAN POINT ENERGY CENTER, UNITS 2 AND 3 - INTEGRATED INSPECTION REPORT 05000247/2020001 AND 05000286/2020001
Dear Mr. Vitale:
On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Indian Point Energy Center, Units 2 and 3. On April 14, 2020, the NRC inspectors 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, X /RA/
Signed by: Daniel L. Schroeder
Daniel L. Schroeder, Chief Reactor Projects Branch 2 Division of Reactor Projects
Docket Nos. 05000247 and 05000286 License Nos. DPR-26 and DPR-64
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000247 and 05000286
License Numbers:
Report Numbers:
05000247/2020001 and 05000286/2020001
Enterprise Identifier: I-2020-001-0060
Licensee:
Entergy Nuclear Operations, Inc.
Facility:
Indian Point Energy Center, Units 2 and 3
Location:
450 Broadway, Generation Support Building
Buchanan, NY 10511-0249
Inspection Dates:
January 1, 2020, to March 31, 2020
Inspectors:
B. Haagensen, Senior Resident Inspector
S. Obadina, Resident Inspector
J. Vazquez, Resident Inspector
L. Dumont, Reactor Inspector
K. Warner, Senior Health Physicist
S. Wilson, Senior Health Physicist
Approved By:
Daniel L. Schroeder, Chief
Reactor Projects Branch 2
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Indian Point Energy Center, 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 18, 2020, Unit 2 began a coast down in preparation for the planned permanent cessation of operations and defueling. At the end of the inspection period, the plant was at 89 percent rated thermal power.
Unit 3 operated at or near rated thermal power for the entire 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 to 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
71111.04 - 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) Main and reheat steam due to steam leaks on several main steam non-return check valve vent valves at Unit 3 on January 22, 2020 (2)31, 32, and 33 emergency diesel generators (EDGs) due to 31 EDG prelube pump motor issues and 32 EDG 6-year inspection, maintenance, and testing at Unit 3 on February 11, 2020
- (3) Spent fuel pool cooling system after maintenance on AC-723 (spent fuel pool drain valve) at Unit 3 on February 13, 2020
- (4) Containment pressure relief system following pressure relief after the failure of PCV-1190 (containment pressure relief valve) at Unit 2 on February 24, 2020
- (5) Conformance with established charging system isolation and nitrogen supply ventilation requirements during charging pump recirculation line freeze seal implementation at Unit 2 on March 31, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (8 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) Primary auxiliary building, general floor plan, 35-foot elevation (pre-fire plan (PFP)-205), at Unit 2 on January 3, 2020
- (2) Cable spreading room and battery rooms (PFP-252, PFP 252A, and PFP-254) at Unit 2 on January 24, 2020
- (3) Auxiliary feedwater pump room and atmospheric steam dumps in auxiliary building (PFP-365 and PFP-367) at Unit 3 on February 11, 2020
- (4) Control room (PFP-253) at Unit 2 on February 18, 2020 (5)31, 32, and 33 EDGs (PFP-354) at Unit 3 on February 26, 2020 (6)480V switchgear room and air conditioning equipment room (PFP-351 and PFP-351A) at Unit 3 on March 11, 2020
- (7) Primary auxiliary building, safety injection pumps/main corridor (PFP-305), at Unit 3 on March 16, 2020
- (8) Charging pump cells during hot work on 32 charging pump recirculation line (PFP-307B) at Unit 3 on March 31, 2020
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated operator performance during an emergency planning drill at Unit 2 on January 29, 2020.
- (2) The inspectors observed and evaluated operator performance during a licensed operator requalification examination at Unit 3 on March 3, 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 remain capable of performing their intended function:
- (1) Instrument air system at Unit 3 on March 23, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (7 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) Yellow risk during 23 charging pump maintenance at Unit 2 on January 9, 2020
- (2) Yellow risk due to 35 circulating water pump out of service at Unit 3 on January 21, 2020
- (3) Yellow risk due to replacement of time delay relay 62-2/6A after 480V undervoltage/degraded grid protection system testing at Unit 3 on January 27, 2020
- (4) Yellow risk during concurrent 22 auxiliary boiler feedwater pump and 23 charging pump maintenance at Unit 2 on February 4, 2020
- (5) Elevated risk due to bonnet replacement of AC-723 (spent fuel pool primary water isolation valve) with freeze seal and transfer cask movement at Unit 3 on February 21, 2020
- (6) Comprehensive risk review for Unit 2 work week March 23 to 27, 2020
- (7) Emergent work for 32 charging pump recirc line repairs and freeze seal at Unit 3 on March 30, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (10 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
(CR-IP2-2020-00135) 21 service water pump vacuum breaker fastener degradation and leakage at Unit 2 on January 14, 2020 (2)
(CR-IP3-2020-00020) 31 screen wash basket strainer not rotating at Unit 3 on January 14, 2020 (3)
(CR-IP2-2020-00142) Containment equipment hatch air lock leakage at Unit 2 on January 15, 2020 (4)
(CR-IP2-2020-00020) 21 component cooling water heat exchanger service water line 411 wall thickness approaching minimum allowable for structural integrity under code case N513-4 at Unit 2 on January 27, 2020 (5)
(CR-IP2-2020-00410) Residual heat removal pump flow indicators reading non-zero value with pumps not in service at Unit 2 on January 31, 2020 (6)
(CR-IP2-2020-00331) 21 component cooling water heat exchanger service water line weld plate non-conformance with Code Case at Unit 2 on February 2, 2020 (7)
(CR-IP3-2020-00282) 32 EDG jacket water cooler crevice/pitting corrosion on gasket seating surface of the jacket water cooler reversing cover at Unit 3 on February 11, 2020 (8)
(CR-IP2-2020-00034) 21 component cooling water heat exchanger service water line wall-thinning, finite element analysis to justify structural integrity at Unit 2 on March 3, 2020 (9)
(CR-IP2-2020-00741) 32 charging pump recirculation line leak impacts reactor coolant system unidentified leak rate determination at Unit 3 on March 25, 2020 (10)
(CR-IP2-2020-00741) Leak on the common charging pump recirculation line to the volume control tank impacts 32 and 33 charging pump functionality at Unit 3 on March 31, 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 2 EC-85530, permanent modification to weld plate onto 21 component cooling water heat exchanger service water line per Code Case N-789, Revision 1
- (2) Unit 3 EC-85154, temporary modification to establish freeze seal for repairs to AC-723, spent fuel pool fill line
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
(1)23 EDG test following 2-year inspection and protective relay calibration at Unit 2 on January 13, 2020 (2)21 service water pump Zurn' strainer test following replacement at Unit 2 on January 27, 2020 (3)31 auxiliary feedwater pump maintenance and testing of BFD-FCV-1121 (recirculation control valve) at Unit 3 on February 26, 2020 (4)33 EDG 6-year maintenance, inspection, and testing at Unit 3 on March 5, 2020 (5)32 charging pump recirculation line following installation of temporary patch on March 27, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)3-PT-2Y001C, 33 EDG overspeed trip test at Unit 3 on January 10, 2020 (2)2-PT-Q027A, 21 auxiliary feedwater pump test at Unit 2 on January 21, 2020 (3)3-PT-Q117B, 32 containment spray pump functional test at Unit 3 on January 29, 2020 (4)2-PT-Q027B, 23 auxiliary feedwater pump test at Unit 2 on March 3, 2020 (5)3-PT-OL3B1, 31 auxiliary boiler feed pump load sequencer calibration at Unit 3 on March 5, 2020 (6)3-PT-M024, low pressure steam dump surveillance test frequency change at Unit 3 on March 11, 2020 (7)2-PT-Q28A, 21 residual heat removal pump at Unit 2 on March 13, 2020 (8)3-PT-Q085, safety injection system valve operability test at Unit 3 on March 13, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) 2-PT-2Y045A, 21 service water pump full flow test at Unit 2 on January 27, 2020
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
(1)0-SOP-LEAKRATE-001, reactor coolant system operational leakage assessment at Unit 2 on January 8, 2020
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) FLEX-P-3B, diesel driven pump performance/operational test at Unit 3 on March 31, 2020
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Conduct of a routine emergency preparedness drill at Unit 2 on January 29,
RADIATION SAFETY
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Unit 3 primary auxiliary building Unit 3 fuel storage building
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Unit 2 fuel storage building skid Unit 3 reactor coolant filter cell Unit 3 fuel storage building truck bay
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.05 - Radiation Monitoring Instrumentation
Walk Downs and Observations (IP Section 02.01) (1 Sample)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Portable Survey Instruments
- Unit 3
- (3) telepole serial numbers 228317-063, 228317-077, 228317-100,
===228317-102
- Unit 3
- (6) RO-20 serial numbers 12709, 13073, 13071
- Unit 3 neutron detector model ASP-2 serial numbers 264 and 290
Source Check Demonstration
- Unit 3 telepole (geiger-muller detector)
- Unit 3 RO-20 (ion chamber detector)
- Unit 3 radiation protection sample count room SAC-4 (scintillation detector)
- Chemistry laboratory detector 34 (high-purity germanium detector w/gamma spectroscopy)
- Chemistry laboratory tri-carb beta analyzer number alpha H-3 (scintillation detector)
- Unit 3 J.L. Shepherd and Associates model 89 calibrator serial number 8154-20043 (cesium-137 sealed sources)
- Unit 3 model 81-12B beam irradiator serial number 11461 (cesium-137 sealed sources)
Area Radiation Monitors and Continuous Air Monitors
- Unit 2 control room monitor R-1
- Unit 2 fuel storage building monitor R-5
- Unit 3 control room monitor R-1
- Unit 3 fuel storage building monitor R-5
- Unit 2 portable continuous air monitor serial number 411630
- Unit 3 portable continuous air monitor serial number 413081
Personnel Contamination Monitors, Portal Monitors, and Small Article Monitors
- Unit 3 dosimetry area Fastscan whole-body counter
- Unit 3 small article monitor
- Unit 3 personnel contamination monitor
- Security building exit personnel contamination monitor Calibration and Testing Program (IP Section 02.02)===
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Alarm Setpoint and Calibration Method Check of Personnel Contamination Monitors, Portal Monitors, and Small Article Monitors
- Unit 3 small article monitor
- Unit 3 personnel contamination monitor
- Security building exit personnel contamination monitor
Failure to Meet Calibration or Source Check Acceptance Criteria
- Telepole number 11698
- RO-2 number
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 2 (January 1, 2019, to December 31, 2019)
- (2) Unit 3 (January 1, 2019, to December 31, 2019)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 3 (January 1, 2019, to December 31, 2019)
- (2) Unit 2 (January 1, 2019, to December 31, 2019)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Part 21 report associated with A220 480V contactors failing to release/open when de-energized at Units 2 and 3
- (2) The time critical operator action program to validate that operator manual actions credited in the updated final safety analysis report, chapter 14, events are appropriately tracking actual operator response times
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000247/2018-003-01, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap (ADAMS Accession No.
ML20050C993). The inspectors reviewed the updated LER submittal. The previous LER submittal was reviewed in Inspection Report 05000247/2019-001 (ADAMS Accession No. ML19134A080). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensees ability to foresee or correct and, therefore, was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified.
INSPECTION RESULTS
Observation: Part 21 Report Associated with A220 480V Contactors Failing to Release/Open When De-Energized 71152 The inspectors interviewed the licensee and assessed the licensee's evaluation and corrective actions for Westinghouse Nuclear Safety Advisory Letter (NSAL-19-2), Contactors Failing to Release Open When Deenergized. NSAL-19-2 described a problem with 480 volts contactors, used in a full voltage non-reversing application, which failed to open when de-energized. Although the operability evaluation and corrective actions performed by the licensee were satisfactory, the Part 21 evaluation was not completed as required by the licensee procedure. The inspectors determined that this issue was minor because the Part 21 evaluation would have concluded that the discovery was not a reportable defect or failure.
Observation: Validation of Time Critical Operator Actions (TCOAs) and Time Sensitive Operator Actions (TSOAs)71152 EN-OP-123, Time Critical Action/Time Sensitive Action Program Standard, Revision 2, provides direction for establishing and maintaining the TCOA program at Indian Point. This program ensures that plant staff can accomplish operator manual actions within the scope defined by the updated final safety analysis report (UFSAR) and the Indian Point probabilistic risk assessment (PRA) model for TCOAs and TSOAs, respectively. The inspectors reviewed the program guidance, interviewed personnel, and verified that the program was being adequately maintained and administered. The inspection reviewed the program for TCOAs on both units but concentrated on Unit 3 for TSOAs.
The inspectors determined that, in general, 17 Units 2 and 3 TCOAs had been properly identified from the UFSAR, tracked, and time-verified in the simulator and/or in plant walkthroughs. Past observations made during 71111.11Q licensed operator requalification training inspections were consistent with this inspection.
However, the Unit 3 TSOA program appeared to be missing many risk-significant operator actions. None of the 20 operator manual actions credited in the PRA with Birnbaum importance ratings greater than 1E-6 core damage frequency and/or 1E-7 large early release frequency had been screened for time criticality using the criteria in EN-OP-123, Section 5.1. Seven of these potential TSOAs were similar to corresponding TCOAs and may have been functionally credited/time-validated under the TCOA program. However, the time criteria credited under PRA may also have been different than the time credited in the UFSAR and should have been reviewed. Moreover, during interviews, Entergy personnel appeared to be unfamiliar with the TSOA requirements and screening criteria. A list of operator manual actions with sufficient risk importance to require screening was provided to Operations.
This issue of concern was documented in CR-HQN-2020-00729 and assigned for follow-up. Identification of TSOAs are not explicitly required by NRC regulations (but are required by Entergy procedure EN-OP-123), therefore, this is not a violation of NRC requirements.
Risk-significant operator actions that have a Birnbaum risk importance that exceed 1E-6 core damage frequency or 1E-7 large early release frequency (as specified in EN-SA-G-001) that are not similar to TCOAs include:
- Trip reactor coolant pumps following loss of component cooling water (CCW)
- Reset motor control centers following a loss of offsite power or safety injection signal
- Establish alternate 480V switchgear room ventilation
- Align backup city water cooling to charging pumps after a loss of CCW
- Rapidly depressurize reactor coolant system to minimize reactor coolant pump seal leakage during station blackout
- Perform post-loss-of-coolant accident cooldown and depressurization
- Align backup city water cooling to residual heat removal pump 31
- Align alternative safe shutdown system loads to motor control center 312A following a 480V switchgear room flood event
- Start a charging pump in maximum speed following a loss of CCW
- Align primary bleed-and-feed cooling on loss of secondary heat sink
- Isolate a stuck-open pressurizer power-operated relief valve
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 14, 2020, the inspectors presented the integrated inspection results to Anthony J. Vitale, Site Vice President, and other members of the licensee staff.
- On March 5, 2020, the inspectors presented the radiation protection inspection debrief for in-plant airborne radioactivity and radiation monitoring instrumentation (inspection procedures 71124.03 and 71124.05) inspection results to Anthony Vitale, Site Vice President, and other members of the licensee staff.
- On February 13, 2020, the inspectors presented the Part 21 report associated with A220 480V contractors failing to release/open when de-energized at Units 2 and 3 inspection results to Mahvash Mirzai, Regulatory Assurance Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
Corrective Action
Documents
CR-IP2-2010-03881, CR-IP2-2010-04395, CR-IP2-2010-
04830, CR-IP2-2014-01364, CR-IP2-2014-01767, CR-IP2-
2014-01983, CR-IP2-2015-01072, CR-IP2-2016-01973, CR-
IP2-2016-02152, CR-IP2-2016-02383, CR-IP2-2018-01335,
CR-IP2-2018-02008, CR-IP2-2018-02475, CR-IP2-2018-
2541, CR-IP2-2018-02588, CR-IP2-2019-04736, CR-IP2-
2019-04766, CR-IP2-2019- 04916
Drawings
21-F-27363
Flow Diagram, Chemical & Volume Control System, Sheet
No. 1
Revision 55
Procedures
0-PIP-401-FRZ
Piping Freeze Seal Procedure
Revision 5
2-PT-R027C
WCPPS Local Leak Rate
Revision 11
2-PT-R027C-
DS001
Containment Pressure Relief Valves PCV-1190 and
PCV-1191
Revision 12
Freeze Seal Evaluations
Revision 3
Work Orders
00541612
Corrective Action
Documents
Corrective Action
Documents
Resulting from
Inspection
CR-IP2-2020-00274, CR-IP2-2020-00275, CR-IP2-2020-
00633
Fire Plans
Primary Auxiliary Building, 35-0 Elevation and 42-0
Elevation
Revision 0
Piping Bay and Tunnel, PAB 35-0, Primary Auxiliary
Building
Revision 0
Cable Spreading Room, Control Building
Revision 11
Battery Rooms, Control Building
Revision 0
Control Room, Control Building
Revision 13
Battery Room 23, Superheater Building
Revision 16
General Floor Plan - Primary Auxiliary Building, 55-0
Elevation
Revision 12
Charging Pumps - Primary Auxiliary Building
Revision 12
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
Miscellaneous
TCE 20-046
Transient Combustible Evaluation for 32 Charging Pump
Cell and Corridor
Revision 1
Procedures
Revision 16
Miscellaneous
SES024
PT-404 Fails High, Bus 6A Faults, ATWS, Faulted SG and
MSIV Fails Open
Revision 4
Procedures
2-POP-2.1
Operation at Greater Than 45% Power
Revision 66
3-AOP-480V-1
Loss of Normal Power to Any Safeguards Bus
Revision 7
3-AOP-INST-1
Instrument/Controller Failures
Revision 14
3-E-0
Reactor Trip or Safety Injection
Revision 6
3-E-1
Loss of Reactor or Secondary Coolant
Revision 4
3-E-2
Faulted Steam Generator Isolation
Revision 2
3-ES-1.1
SI Termination
Revision 4
3-FR-S.1
Response to Nuclear Power Generation/ATWS
Revision 3
Corrective Action
Documents
Resulting from
Inspection
Miscellaneous
T-2 Risk Schedule for the Work Week March 23 to 27, 2020
March 19, 2020
Unit 3 Operators On-Line Risk Report for January 9, 2020
January 9, 2020
Unit 3 Operators' On-Line Risk Report for March 30, 2020
March 30, 2020
Unit 3 Operators On-Line Risk Report for February 5, 2020
February 5, 2020
Unit 2 Operators On-Line Risk Report for March 23, 2020
March 23, 2020
Unit 2 Operators On-Line Risk Report for March 24, 2020
March 24, 2020
Unit 2 Operators On-Line Risk Report for March 25, 2020
March 25, 2020
Unit 2 Operators On-Line Risk Report for March 26, 2020
March 26, 2020
Unit 2 Operators On-Line Risk Report for March 27, 2020
March 27,2020
Procedures
General Material Handling
Revision 1
On Line Risk Assessment
Revision 20
Calculations
IP-CALC-19-
00057
Leak Evaluation at 21 CCW HX Service Water Inlet Line
Downstream of Valve SWN-34
Revision 2
IP-CALC-20-
00003
Structural PAD Reinforcement for Service Water Line #411
Elbow IAW ASME Code Case N-789-1
Revision 0
IP-CALC-20-
Finite Element Analysis and Code Qualification of Leaking
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
00005
Service Water Elbow
Corrective Action
Documents
CR-IP2-2018-06412, CR-IP2-2019-04593, CR-IP2-2019-
04787, CR-IP2-2020-00014, CR-IP2-2020-00034, CR-IP2-
20-00098, CR-IP2-2020-00135, CR-IP2-2020-00142, CR-
IP2-2020-00295, CR-IP3-2020-00741
Corrective Action
Documents
Resulting from
Inspection
CR-IP2-2020-00172, CR-IP2-2020-00410
Miscellaneous
IP2-CISS/WCPS
Design Basis Document for Weld Channel Pressurization
System
Revision 1
Procedures
0-CON-403-ALK
CBI Personal and Equipment Airlock Hatches
Revision 0
2-PC-R9
Revision 19
2-SOP-4.2.1
Residual Heat Removal System Operation
Revision 68
Operability Determination Process
Revision 16
Work Request Generation, Screening and Classification
Revision 15
Work Orders
00538166
2453837
2579841
2731336
Corrective Action
Documents
CR-IP2-2019-04593, CR-IP2-2019-04787, CR-IP2-2020-
00014, CR-IP2-2020-00034, CR-IP2-2020-00098, CR-IP2-
20-00295
Drawings
Drawing 9321-F-
27513, Sheet 1
Flow Diagram of Auxiliary Cooling System in Primary
Building and Fuel Storage Building
Revision 34
Engineering
Changes
Install Freeze Seal for AC-723 Work
February 13,
20
Structural Pad Reinforcement for Service Water Line #411
Elbow IAW ASME Code Case N-789-1
Revision 0
Miscellaneous
NRC Safety
Evaluation by
Proposed Alternative to Utilize ASME Code Case N-789-1
Relief Request RR-EN-15-1
Revision 1
Procedures
0-PIP-401-FRZ
Piping Freeze Seal Procedure
Revision 5
Freeze Seal Evaluation Summary
Revision 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
9.3
Protective and Caution Tagging
Revision 24
Work Orders
00528976
Corrective Action
Documents
CR-IP2-2020-00289, CR-IP2-2020-00319
Miscellaneous
PICS
Unit 2 Plant Integrated Computer Readout for RCS Leak
Rate (Point U6003)
March 27, 2019
Procedures
0-EDG-407-ELC
Emergency and Appendix R Diesel Generator Engine
Analysis/Inspection
Revision 8
2-PT-M021C
Emergency Diesel Generator 23 Load Test
Revision 31
Work Orders
00541612
51504824
2693170
2787951
2910898
2910904
Corrective Action
Documents
FCV-1207
CR-IP3-2018-00901, CR-IP3-2018-01137, CR-IP3-2018-
2067, CR-IP3-2019-03183
FCV-1210
CR-IP3-2015-02273, CR-IP3-2016-04166, CR-IP3-2019-
00191, CR-IP3-2019-04175, CR-IP3-2020-00147, CR-IP3-
20-00429
Turbine
Overspeed CRs
CR-IP3-2017-02848, CR-IP3-2017-05149, CR-IP3-2018-
00054, CR-IP3-2019-01910
Engineering
Evaluations
Evaluation 20-
3001-00
Revise the IP3 TRM to Reduce the Test Frequency of the
Low-Pressure Steam Dump Valves from Monthly to
Quarterly
Revision 0
Procedures
0-SOP-
LEAKRATE-001
RCS Leakrate Surveillance, Evaluation, and Leak
Identification
Revision 6
2-PT-2Y045A
SWP Full Flow Test
Revision 5
2-PT-Q013-
DS082
Valve FCV-1123 IST Data Sheet
Revision 22
2-PT-Q013-
DS092A
Valve FTC-406C IST Data Sheet
Revision 30
2-PT-Q013-
Valve FTC-406D IST Data Sheet
Revision 28
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
DS092B
2-PT-Q027A
Auxiliary Feed Pump
Revision 18
2-PT-Q027B
Auxiliary Feed Pump
Revision 21
2-PT-Q028A
Revision 26
3-PT-M024
Low Pressure Steam Dump Functional Test
Revision 20
9.1
PAD for Evaluation 20-3001-00, Revise the IP3 TRM to
Reduce the Test Frequency of the Low-Pressure Steam
Dump Valves from Monthly to Quarterly
Revision 0
Work Orders
2807596
2810025
2865607
2865613
2904589
2904590
2904591
2909565
2912537
Procedures
Respiratory Protection Program
Revision 6
PortaCount Respirator Fit Testing
Revision 7
Miscellaneous
Instrument Response Check Failure Review, Telepole
Number 11698, Attachment 4, dated February 23, 2019
Revision 12
Instrument Response Check Failure Review, RO-2
Number 05473, Attachment 4, dated February 20, 2019
Revision 12
Self-Assessments Indian Point
Energy Center
Radiation Monitor
EAL Review
Indian Point Energy Center Emergency Action Levels
Review
October 10, 2019
71151
Miscellaneous
Email from T.R.
Jones
Subject: Unit 2 & 3 RCS Activity for Jan - Dec 2019
March 18, 2020
Unit 2 Chemistry
Log
January 1 to
December 31,
2019
Unit 2 eSOMs
Operator Rounds Log, RCS Identified Leak Rate
January 1 to
December 31,
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
2019
Unit 3 Chemistry
Log
Dose Equivalent Iodine
January 1 to
December 31,
2019
Unit 3 Chemistry
Log
January 1 to
December 31,
2019
Unit 3 eSOMs
Operator Rounds Log, RCS Identified Leak Rate
January 1 to
December 31,
2019
Corrective Action
Documents
CR-IP2-2011-05166, CR-IP2-2015-03699, CR-IP3LO-2015-
0032, CR-IP3-2018-03335, CR-IP3-2020-00256, CR-HQN-
20-00195
CR-HQN-2020-00134, CR-HQN-2020-00195, CR-IP2-2011-
05166, CR-IP2-2015-03699, CR-IP2-2019-03907, CR-IP2-
20-00578, CR-IP3-LO-2015-00032, CR-IP3-2018-03335,
CR-IP3-2019-03370, CR-IP3-2020-00256
Corrective Action
Documents
Resulting from
Inspection
CR-HQN-2020-00729*
Procedures
Corrective Action Program
Revision 39
EN-LI-108-01
CFR 21 Evaluations and Reporting
Revision 10
Time Critical Action/Time Sensitive Action Program Standard Revision 2
Time Critical Action/Time Sensitive Action Program Standard Revisions 001
and 002
EN-SA-G-001
Identification and Documentation of Time Critical Actions
Revision 1
EN-SA-G-001
Identification and Documentation of Time Critical Actions
Revision 1
OAP-115
Operations Commitments and Policy Details
Revision 34