IR 05000237/2022012
| ML22244A231 | |
| Person / Time | |
|---|---|
| Site: | Dresden |
| Issue date: | 09/06/2022 |
| From: | Richard Skokowski Engineering Branch 3 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2022012 | |
| Download: ML22244A231 (7) | |
Text
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000237/2022012 AND 05000249/2022012
Dear Mr. Rhoades:
On August 18, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3 and discussed the results of this inspection with Ms. C. Joseph, Plant Manager 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, Richard A. Skokowski, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000237 and 05000249 License Nos. DPR-19 and DPR-25
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000237 and 05000249
License Numbers:
Report Numbers:
05000237/2022012 and 05000249/2022012
Enterprise Identifier:
I-2022-012-0019
Licensee:
Constellation Energy Generation, LLC
Facility:
Dresden Nuclear Power Station, Units 2 and 3
Location:
Morris, IL
Inspection Dates:
July 11, 2022 to August 18, 2022
Inspectors:
J. Benjamin, Senior Resident Inspector
A. Shaikh, Senior Reactor Inspector
M. Siddiqui, Reactor Inspector
Approved By:
Richard A. Skokowski, Chief
Engineering Branch 3
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline inspection at Dresden Nuclear Power Station, 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.
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
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from February 2018.
- (1) Screen 13137, Temporarily Gag the U3 Reactor Feed Pump Recirculation Damper 3-5772-46 in Open Position
- (2) Screen 13148, High Pressure Coolant Injection (HPCI) Room Cooler Tube Plugging /
Issue Minor Revision DRE-98-0077 Rev.001C
- (3) Screen 13264, Updated Final Safety Analysis Report (UFSAR) Change - HPCI Room Exemption from Harsh Environment
- (4) Screen 13362, Disable 2-3001-A / 2A steam jet air ejector (SJAE) Steam Isolation Valve in Closed Direction
- (5) Screen 13134, Hot Shutdown Procedure Path A1
- (6) Screen 13141, Trash Rake Operation
- (7) Screen 13177, Ventilation System (RB) Failure
- (8) Screen 13221, Temporary Configuration Change for Alternate Fire Pump
- (9) Screen 13217, Surveillance Frequency Change for Diesel Fire Pump Test
- (10) Screen 13453, Secondary Containment Leak Rate Test
- (11) Evaluation 2020-05-001, Unit 3 Installation of a Reactor Feed Pump (RFP) Suction Strainer 3-3404-A, 3-3404-B, 3-3404-C
- (12) Evaluation 2020-08-001, Install Switches to Bypass Fuel Pool Cooling Pump Low Suction Pressure Trips
- (13) Evaluation 2019-09-002, Unit 2 Installation of RFP Suction Strainer 2-3404-A, 2-3404-B, 2-3404-C
- (14) Screen 13130, Main Steam Isolation Valve Lo-Lo Level Keylock Switch Logic Change
- (15) Screen 13132, Defeat Alarm 2-0902 E-4 and E-6
- (16) Screen 13133, Add Clarifying Information Related to Acceptable Reactor Building Ventilation Lineup and Technical Specification Applicability
- (17) Screen 13140, TSFS-562-T Bases Clarification for Technical Specification (TS) 3.8.1, Required Action B.3.1 and B.3.2
- (18) Screen 13143, Change HPCI Injection Motor Operated Valve (MOV) 3-2301-8 Logic from Torque Switch Close to Limit Switch Close
- (19) Screen 13194, Change HPCI Injection MOV 2-2301-8 Logic from Torque Switch Close to Limit Switch Close
- (20) Screen 13219, Clarify Actions to Bypass HPCI Initiation Signal to Support Alternate Emergency Depressurization
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On August 18, 2022, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Ms. C. Joseph, Plant Manager and other members of the licensee staff.
On July 15, 2022, the inspectors presented the Technical Debrief inspection results to Mr. P. Boyle, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
DRE98-0077
Dresden HPCI Room Thermal Response with Reduced
Room Cooler Capability
001C
Corrective Action
Documents
03984974
Unit 3 HPCI Room Cooler Eddy Current Results
03/14/2017
Corrective Action
Documents
Resulting from
Inspection
04510809
50.59 Inspection EC 625940 Record Submittal Needed
07/13/2022
0000623029
Reactor Feed Pump Recirculation Damper 3-5772-46 Master
Actuator Damper Pin Disconnected Resulting in Damper
Gagged Open WO 04743349
0000625940
Basis and Justification for Considering HPCI Room as Mild
Environment in an Event of LOCA
11/28/2018
0000628004
Disable the 2-3001-A / 2A SJAE Steam Supply Valve in
Closed Position with Sealant Injection
28890
Installation of Reactor Feed Pump (RFP) Suction
Strainer 3-3404-A, 3-3404-B, 3-3404-C
630570
Installation of Reactor Feed Pump (RFP) Suction
Strainer 2-3404-A, 2-3404-B, 2-3404-C
Engineering
Changes
631971
Install Switches to Bypass Fuel Pool Cooling Pump Low
Suction Pressure Trips
Screening 13134
Hot Shutdown Procedure Path A1
Screening 13141
Trash Rack Operation
Screening 13177
Ventilation System (RB) Failure
Screening 13217
Surveillance Frequency Change for Diesel Fire Pump Test
Screening 13221
TCCP for Alternate Fire Pump
Screening 13453
Secondary Containment Leak Rate Rest
Miscellaneous
Training LT SEG
21-09E
Dresden Operations Training - Injecting with Standby
Coolant
DEOP 500-3
Alternate Water Injection Systems
Procedures
50.59 Resource Manual
14