IR 05000237/2022012

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000237/2022012 and 05000249/2022012

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:

DPR-19 and DPR-25

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

71111.17T

Procedures

LS-AA-104-1000

50.59 Resource Manual

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