IR 05000286/2021002
| ML21158A253 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/07/2021 |
| From: | Daniel Schroeder Division of Operating Reactors |
| To: | Burroni R Holtec Decommissioning International |
| Schroeder D | |
| References | |
| IR 2021002 | |
| Download: ML21158A253 (13) | |
Text
June 7, 2021
SUBJECT:
INDIAN POINT ENERGY CENTER, UNIT 3 - INTEGRATED INSPECTION REPORT 05000286/2021002
Dear Mr. Burroni:
On May 13, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Indian Point Energy Center, Unit 3. On May 19, 2021, the results of this inspection were discussed with Mr. Anthony J. Vitale, Site Vice President, Entergy Nuclear Operations, Inc., and other members of his 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, Daniel L. Schroeder, Chief Reactor Projects Branch 2 Division of Operating Reactor Safety
Docket No. 05000286 License No. DPR-64
Enclosure:
As stated
Inspection Report
Docket Number:
05000286
License Number:
Report Number:
Enterprise Identifier: I-2021-002-0029
Licensee:
Entergy Nuclear Operations, Inc.1
Facility:
Indian Point Energy Center, Unit 3
Location:
450 Broadway, Generation Support Building
Buchanan, NY 10511-0249
Inspection Dates:
April 1, 2021, to May 13, 2021
Inspectors:
G. George, Senior Resident Inspector
E. Allen, Resident Inspector
K. Warner, Senior Health Physicist
Approved By:
Daniel L. Schroeder, Chief
Reactor Projects Branch 2
Division of Operating Reactor Safety
1 License transferred to HOLTEC Decommissioning International, LLC on May 28, 2021.
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Indian Point Energy Center, Unit 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 3 began the inspection period at 92 percent rated thermal power. On April 30, 2021, the unit was shut down for defueling outage 3D21. All reactor fuel was removed from the reactor vessel and safely stored in the spent fuel pool on May 11, 2021. By letter dated May 11, 2021, Entergy Nuclear Operations, Inc. submitted a Certification of Permanent Cessation of Power Operations to the NRC certifying that Unit 3 had permanently ceased power operations and that all fuel had been permanently removed from Unit 3 (ADAMS Accession No. ML21131A157).
Effective May 13, 2021, the NRC notified Entergy Nuclear Operations, Inc. that oversight activities will no longer be conducted in accordance with the Operating Reactor Assessment Program and that oversight activities will be conducted in accordance with the Decommissioning Power Reactor Inspection Program (ADAMS Accession No. ML21132A069). On May 28, 2021, Entergy Nuclear Operations, Inc. informed the NRC of the successful purchase and sale transaction closing of the Indian Point facilities to Holtec Decommissioning International, LLC (ADAMS Accession No. ML21147A553). On May 28, 2021, the NRC issued license amendments transferring Indian Point Unit Nos. 1, 2, and 3 facility licenses from Entergy Nuclear Operations, Inc. to Holtec Indian Point 2, LLC; Holtec Indian Point 3, LLC; and Holtec Decommissioning International, LLC (ADAMS Accession No. ML21126A004).
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.
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 and regional 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, increasing the amount of time onsite as local COVID-19 conditions permitted. As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D, observed risk significant activities, and completed onsite portions of IPs. 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 some cases, portions of an IP were completed remotely and onsite. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Back-up spent fuel pool cooling system on April 27, 2021 (2)31 and 32 component cooling water heat exchangers and 31, 32, and 33 emergency diesel generator jacket water coolers in single service water header operation on May 10, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection (IP Section 03.01) (2 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) Circulating and Service Water Pumps Building (PFP-385) on April 28, 2021
- (2) Primary Auxiliary Building, general floor plan, 41-foot elevation (PFP-306), on April 28, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Residual heat removal pump rooms, Primary Auxiliary Building, 15-foot elevation, on April 21, 2021
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1)31 and 32 component cooling water heat exchangers and 31, 32, and 33 emergency diesel generator jacket water coolers for single service water header operation on May 10, 2021
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during the Unit 3 shutdown and cooldown to defueling outage from April 30 to May 1, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated operator classroom training for the final reactor shutdown prior to defueling on April 28, 2021.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management (IP Section 03.01) (2 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) High integrated risk due to emergency diesel generator 31 surveillance test failure and electric governor replacement, work order 560279, from April 5 to 7, 2021
- (2) Emergent leaking of reactor cavity segmented seal during yellow outage risk from May 8 to 11, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
(CR-IP3-2021-00868) Operability determination of emergency diesel generator service water cooling discharge valves due to bent instrument air supply tubing on April 9, 2021 (2)
(CR-IP3-2021-01051) Operability determination when the intermediate range detector NI-35 failed to automatically energize source range detectors on May 1, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Work Order 52884300, Temporary modification for erection of scaffolding to operate BF-7-1 near turbine driven auxiliary feedwater pump, P-32, exhaust piping on April 25, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test (IP Section 03.01) (1 Sample)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Emergency diesel generator number 31 following replacement of the electronic governor on April 7, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 3 defueling outage 3D21 activities from April 30 to May 13, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)3-PT-M079A, 31 diesel generator monthly load test on April 7, 2021 (2)3-PT-CS028, Power operated relief valve test on May 1,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas for the following:
- (1) Radiation Work Packages
===20213521, "3D21 Reactor Disassembly"
- 20213509, "Emergent Work"
- 20213501, "3D21 Radiation Protection Support" Electronic Alarming Dosimeter Alarms
- No unanticipated dose rate alarms during this inspection period
- Reviewed four anticipated dose rate alarms during this inspection period
Labeling of Containers
- Reviewed labeling of containers in radioactive material storage areas
Contamination and Radioactive Material Control (IP Section 03.03)===
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material for the following:
- (1) Observed workers exiting the radiation control area during defueling outage 3D21
- (2) Observed licensee surveys of potentially contaminated material leaving the radiation control area
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities for the following:
- (1) Monitored pre-job briefings and observed work associated with the blind flange removal in the vapor containment fuel transfer canal
- (2) Monitored pre-job briefings and observed work associated with emergent work in the fuel transfer canal on the spent fuel pool gate valve in the Fuel Storage Building
- (3) Evaluated site reviews of surveys in areas with potentials for dose gradients to determine if enhanced job controls were used as appropriate
- (4) Monitored the pre-job briefings and observed work with the core exit thermal couple nozzle assembly removal and bullet nose installation work activity
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas:
- (1) Primary Auxiliary Building, 73-foot elevation
- (2) Vapor containment lower cavity
- (3) Vapor containment regenerative heat exchanger cubicle
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours (IP Section 03.01)===
- (1) April 1, 2020, through March 31, 2021
IE03: Unplanned Power Changes per 7000 Critical Hours (IP Section 03.02) (1 Sample)
- (1) April 1, 2020, through March 31, 2021
IE04: Unplanned Scrams with Complications (IP Section 03.03) (1 Sample)
- (1) April 1, 2020, through March 31,
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 6, 2021, the inspectors presented the radiological hazard assessment and controls inspection results to Mr. Anthony J. Vitale, Site Vice President, Entergy Nuclear Operations, Inc., and other members of the licensee staff.
- On May 19, 2021, the inspectors presented the integrated inspection results to Mr. Anthony J. Vitale, Site Vice President, Entergy Nuclear Operations, Inc., and other members of the licensee staff.
THIRD PARTY REVIEWS
The inspectors reviewed Institute on Nuclear Power Operations reports that were issued during the inspection period.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
21-F-20276
Piping and Instrumentation Diagram Back-Up Spent Fuel
Pool Cooling System
Revision 5
21-F-20333
Flow Diagram Service Water System
Revision 61
21-F-27223
Flow Diagram Service Water System Nuclear Steam Supply
Plant
Revision 45
Procedures
3-OSP-RW-005
Service Water System Alignment for Single Service Water
Header Operation
Revision 8
3-SOP-RW-005
Service Water System Operation
Revision 42
3-SOP-SFP-003
Operation of the Back-Up Spent Fuel Pool Cooling System
Revision 24
Calculations
IP3-CALC-FP-02795 Combustible Loading Calculation for IP3 Fire Hazards
Revision 2
Fire Plans
Unit 3 Primary Aux. Bldg. - General Floor Plan, Elev. 41'-0"
Revision 15
Unit 3 Circulating and Service Water Pumps Bldg., Elev. 15'-
0"
Revision 0
Calculations
IP-CALC-08-00031
Misc. Structural Evaluation for IP2 & IP3 RHR Pump Motor
Flood Protection
Revision 0
IP-CALC-08-00061
Sizing Calculation for RHR Pump Flooding Line
Revision 0
Corrective Action
Documents
Resulting from
Inspection
Engineering
Changes
Installation of RHR Pump Motor Flood Protection
Revision 0
Calculations
IP-CALC-06-00017
Service Water System PROTO-FLO Model Expansion
Revision 2
Engineering
Changes
Indian Point 3 Containment Temperature After Loss of RHR
Cooling During 3R15 Engineering Report IP-RPT-09-00021
Revision 0
71111.11Q Miscellaneous
3-Graph-RCS-4
Minimum Shutdown Boron Concentration
Revision 41
Procedures
3-POP-2.1
Operation at Greater Than 45% Power
Revision 72
3-POP-3.1
Plant Shutdown from 45% Power
Revision 55
3-POP-3.3
Plant Cooldown - Hot to Cold Shutdown
Revision 57
Infrequently Performed Tests or Evolutions
Revision 16
Corrective Action
Documents
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
On Line Risk Assessment
Revision 22
Corrective Action
Documents
05/01/2021
Corrective Action
Documents
Resulting from
Inspection
04/06/2021
Corrective Action
Documents
Resulting from
Inspection
CR-IP3-2021- 01014
04/25/2021
Procedures
Control of Scaffolding
Revision 22
Work Orders
2884300
Corrective Action
Documents
Resulting from
Inspection
CR-IP3-2021-00870
04/05/2021
Work Orders
00560279
Frequency of the 31 Diesel Was Fluctuating
04/07/2021
Corrective Action
Documents
Resulting from
Inspection
CR-IP3-2021- 01023
04/27/2021
Procedures
0-NF-203
Internal Transfer of Fuel Assemblies and Inserts
Revision 27
3-AOP-RHR-1
Loss of RHR
Revision 13
3-POP-3.3
Plant Cooldown - Hot to Cold Shutdown
Revision 57
3-POP-4.1
Operation at Cold Shutdown
Revision 41
3-REF-003-GEN,
Section 2.2
Indian Point Unit 3 Refueling Procedure
Revision 10
3-SOP-CVCS-003
Reactor Coolant System Boron Concentration Control
Revision 45
3-SOP-RCS-007
Pressurizer Relief Tank Operations
Revision 20
3-SOP-RHR-001
Residual Heat Removal System
Revision 53
Procedures
3-PT-CS028
Pressurizer PORV and Block Valve Test RC-PCV-455C and
456 RC-MOV-535 and 536
Revision 14
ALARA Plans
3D21 Disassembly of Reactor and Resetting of RX Head
04/30/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
3-REF-001-GEN
Fuel Transfer Tube Blind Flange Removal
Revision 5
3-REF-002-GEN
CETNA/Instrument Port Conoseal Disassembly
Revision 5
Radiation Work
Permits
213521
3D21 Reactor Disassembly
Revision 2