IR 05000247/2020001

Integrated Inspection Report 05000247/2020001 and 05000286/2020001

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: DPR-26 and DPR-64 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 Enclosure

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.

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:

(1) 32 EDG jacket water and lube oil heat exchanger performance at Unit 3 on February 11, 2020

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,

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 71152 Release/Open When De-Energized 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 71152 Sensitive Operator Actions (TSOAs)

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

• Align residual heat removal shutdown cooling

• 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 Type Designation Description or Title Revision or Date

Procedure

71111.04 Corrective Action CR-IP2-2010-03881, CR-IP2-2010-04395, CR-IP2-2010-

Documents 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 9321-F-27363 Flow Diagram, Chemical & Volume Control System, Sheet Revision 55

No. 1

Procedures 0-PIP-401-FRZ Piping Freeze Seal Procedure Revision 5

2-PT-R027C WCPPS Local Leak Rate Revision 11

2-PT-R027C- Containment Pressure Relief Valves PCV-1190 and Revision 12

DS001 PCV-1191

EN-DC-214 Freeze Seal Evaluations Revision 3

Work Orders 00541612

71111.05 Corrective Action CR-IP2-2020-00236

Documents

Corrective Action CR-IP2-2020-00274, CR-IP2-2020-00275, CR-IP2-2020-

Documents 00633

Resulting from

Inspection

Fire Plans PFP-205 Primary Auxiliary Building, 35-0 Elevation and 42-0 Revision 0

Elevation

PFP-206 Piping Bay and Tunnel, PAB 35-0, Primary Auxiliary Revision 0

Building

PFP-252 Cable Spreading Room, Control Building Revision 11

PFP-252A Battery Rooms, Control Building Revision 0

PFP-253 Control Room, Control Building Revision 13

PFP-254 Battery Room 23, Superheater Building Revision 16

PFP-307 General Floor Plan - Primary Auxiliary Building, 55-0 Revision 12

Elevation

PFP-307B Charging Pumps - Primary Auxiliary Building Revision 12

Inspection Type Designation Description or Title Revision or Date

Procedure

Miscellaneous TCE 20-046 Transient Combustible Evaluation for 32 Charging Pump Revision 1

Cell and Corridor

Procedures EN-MA-118 Foreign Material Exclusion Revision 16

71111.11Q Miscellaneous 13SX-LOR- PT-404 Fails High, Bus 6A Faults, ATWS, Faulted SG and Revision 4

SES024 MSIV Fails Open

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

71111.13 Corrective Action CR-IP2-2020-00476

Documents

Resulting from

Inspection

Miscellaneous EOOS T-2 Risk Schedule for the Work Week March 23 to 27, 2020 March 19, 2020

EOOS Unit 3 Operators On-Line Risk Report for January 9, 2020 January 9, 2020

EOOS Unit 3 Operators' On-Line Risk Report for March 30, 2020 March 30, 2020

EOOS Unit 3 Operators On-Line Risk Report for February 5, 2020 February 5, 2020

EOOS Unit 2 Operators On-Line Risk Report for March 23, 2020 March 23, 2020

EOOS Unit 2 Operators On-Line Risk Report for March 24, 2020 March 24, 2020

EOOS Unit 2 Operators On-Line Risk Report for March 25, 2020 March 25, 2020

EOOS Unit 2 Operators On-Line Risk Report for March 26, 2020 March 26, 2020

EOOS Unit 2 Operators On-Line Risk Report for March 27, 2020 March 27 ,2020

Procedures EN-MA-119-02 General Material Handling Revision 1

EN-WM-104 On Line Risk Assessment Revision 20

71111.15 Calculations IP-CALC-19- Leak Evaluation at 21 CCW HX Service Water Inlet Line Revision 2

00057 Downstream of Valve SWN-34

IP-CALC-20- Structural PAD Reinforcement for Service Water Line #411 Revision 0

00003 Elbow IAW ASME Code Case N-789-1

IP-CALC-20- Finite Element Analysis and Code Qualification of Leaking Revision 0

Inspection Type Designation Description or Title Revision or Date

Procedure

00005 Service Water Elbow

Corrective Action CR-IP2-2018-06412, CR-IP2-2019-04593, CR-IP2-2019-

Documents 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 CR-IP2-2020-00172, CR-IP2-2020-00410

Documents

Resulting from

Inspection

Miscellaneous IP2-CISS/WCPS Design Basis Document for Weld Channel Pressurization Revision 1

DBD System

Procedures 0-CON-403-ALK CBI Personal and Equipment Airlock Hatches Revision 0

2-PC-R9 RHR System Flow - CCR Revision 19

2-SOP-4.2.1 Residual Heat Removal System Operation Revision 68

EN-OP-104 Operability Determination Process Revision 16

EN-WM-100 Work Request Generation, Screening and Classification Revision 15

Work Orders 00538166

2453837

2579841

2731336

71111.18 Corrective Action CR-IP2-2019-04593, CR-IP2-2019-04787, CR-IP2-2020-

Documents 00014, CR-IP2-2020-00034, CR-IP2-2020-00098, CR-IP2-

20-00295

Drawings Drawing 9321-F- Flow Diagram of Auxiliary Cooling System in Primary Revision 34

27513, Sheet 1 Building and Fuel Storage Building

Engineering EC-85154 Install Freeze Seal for AC-723 Work February 13,

Changes 2020

EC-85530 Structural Pad Reinforcement for Service Water Line #411 Revision 0

Elbow IAW ASME Code Case N-789-1

Miscellaneous NRC Safety Proposed Alternative to Utilize ASME Code Case N-789-1 Revision 1

Evaluation by Relief Request RR-EN-15-1

NRR

Procedures 0-PIP-401-FRZ Piping Freeze Seal Procedure Revision 5

EN-DC-214, Freeze Seal Evaluation Summary Revision 3

Inspection Type Designation Description or Title Revision or Date

Procedure

9.3

EN-OP-102 Protective and Caution Tagging Revision 24

Work Orders 00528976

71111.19 Corrective Action CR-IP2-2020-00289, CR-IP2-2020-00319

Documents

Miscellaneous PICS Unit 2 Plant Integrated Computer Readout for RCS Leak March 27, 2019

Rate (Point U6003)

Procedures 0-EDG-407-ELC Emergency and Appendix R Diesel Generator Engine Revision 8

Analysis/Inspection

2-PT-M021C Emergency Diesel Generator 23 Load Test Revision 31

Work Orders 00541612

51504824

2693170

2787951

2910898

2910904

71111.22 Corrective Action FCV-1207 CR-IP3-2018-00901, CR-IP3-2018-01137, CR-IP3-2018-

Documents 02067, 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 CR-IP3-2017-02848, CR-IP3-2017-05149, CR-IP3-2018-

Overspeed CRs 00054, CR-IP3-2019-01910

Engineering Evaluation 20- Revise the IP3 TRM to Reduce the Test Frequency of the Revision 0

Evaluations 3001-00 Low-Pressure Steam Dump Valves from Monthly to

Quarterly

Procedures 0-SOP- RCS Leakrate Surveillance, Evaluation, and Leak Revision 6

LEAKRATE-001 Identification

2-PT-2Y045A 21 SWP Full Flow Test Revision 5

2-PT-Q013- Valve FCV-1123 IST Data Sheet Revision 22

DS082

2-PT-Q013- Valve FTC-406C IST Data Sheet Revision 30

DS092A

2-PT-Q013- Valve FTC-406D IST Data Sheet Revision 28

Inspection Type Designation Description or Title Revision or Date

Procedure

DS092B

2-PT-Q027A 21 Auxiliary Feed Pump Revision 18

2-PT-Q027B 23 Auxiliary Feed Pump Revision 21

2-PT-Q028A 21 Residual Heat Removal Pump Revision 26

3-PT-M024 Low Pressure Steam Dump Functional Test Revision 20

EN-LI-100 PAD for Evaluation 20-3001-00, Revise the IP3 TRM to Revision 0

9.1 Reduce the Test Frequency of the Low-Pressure Steam

Dump Valves from Monthly to Quarterly

Work Orders 52807596

2810025

2865607

2865613

2904589

2904590

2904591

2909565

2912537

71124.03 Procedures EN-RP-501 Respiratory Protection Program Revision 6

EN-RP-505 PortaCount Respirator Fit Testing Revision 7

71124.05 Miscellaneous EN-RP-301 Instrument Response Check Failure Review, Telepole Revision 12

Number 11698, Attachment 4, dated February 23, 2019

EN-RP-301 Instrument Response Check Failure Review, RO-2 Revision 12

Number 05473, Attachment 4, dated February 20, 2019

Self-Assessments Indian Point Indian Point Energy Center Emergency Action Levels October 10, 2019

Energy Center Review

Radiation Monitor

EAL Review

71151 Miscellaneous Email from

T.R. Subject: Unit 2 & 3 RCS Activity for Jan - Dec 2019 March 18, 2020

Jones

Unit 2 Chemistry January 1 to

Log December 31,

2019

Unit 2 eSOMs Operator Rounds Log, RCS Identified Leak Rate January 1 to

December 31,

Inspection Type Designation Description or Title Revision or Date

Procedure

2019

Unit 3 Chemistry Dose Equivalent Iodine January 1 to

Log December 31,

2019

Unit 3 Chemistry RCS Dose Equivalent Iodine January 1 to

Log December 31,

2019

Unit 3 eSOMs Operator Rounds Log, RCS Identified Leak Rate January 1 to

December 31,

2019

71152 Corrective Action CR-IP2-2011-05166, CR-IP2-2015-03699, CR-IP3LO-2015-

Documents 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 CR-HQN-2020-00729*

Documents

Resulting from

Inspection

Procedures EN-LI-102 Corrective Action Program Revision 39

EN-LI-108-01 10 CFR 21 Evaluations and Reporting Revision 10

EN-OP-123 Time Critical Action/Time Sensitive Action Program Standard Revision 2

EN-OP-123 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

17