IR 05000237/2018011

NRC Triennial Inspection of Evaluation of Changes, Tests and Experiments Inspection Report 05000237/2018011; 05000249/2018011

ML18053A071
Person / Time
Site:	Dresden
Issue date:	02/21/2018
From:	Robert Daley NRC/RGN-III/DRS/EB1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2018011
Download: ML18053A071 (6)

Text

UNITED STATES uary 21, 2018

SUBJECT:

DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3NRC TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS INSPECTION REPORT 05000237/2018011 and 05000249/2018011

Dear Mr. Hanson:

On February 2, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluation of Changes, Tests and Experiments inspection at your Dresden Nuclear Power Station, Units 2 and 3. The NRC inspectors discussed the results of this inspection with Pete Karaba and other members of your staff. The results of this inspection are documented in the enclosed report.

Base on the results of this inspection, no violations or findings of significance were identified.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Robert C. Daley, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-237; 50-249;72-037 License Nos. DPR-19; DPR-25

Enclosure:

IR 05000237/2018011; 05000249/2018011

REGION III==

Docket Nos: 05000237; 05000249; 07200037 License Nos: DPR-19; DPR-25 Report No: 05000237/2018011; 05000249/2018011 Enterprise Identifier: I-2018-00011-0006 Licensee: Exelon Generation Company, LLC Facility: Dresden Nuclear Power Station, Units 2 and 3 Location: Morris, IL Dates: January 29 through February 2, 2018 Inspectors: A. Shaikh, Senior Reactor Inspector J. Gilliam, Reactor Inspector J. Park, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting an Evaluations of Changes, Tests and Experiments inspection at Dresden Generating 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 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

===71111.17TEvaluations of Changes, Tests and Experiments The inspectors evaluated the following from January 29 to February 2, 2018:

10 CFR 50.59 Evaluations71111.17T ===

(1) 2016-05-001; Revise References Within UFSAR Section 9.6.4.1.5; Revision 0;

(2) 2016-10-001; Reactor Building Flood Barriers; Revision 0;

(3) 2016-04-001; Essential Service Bus UFSAR and Technical Specification Bases Update; Revision 0; and

(4) 2016-03-001; On-line Noble Metals Chemical (OLNC) Injection for Unit 2 and Unit 3; Revision 0 and 1.

10 CFR 50.59 Screening/Applicability Determinations71111.17T (20 Samples)

(1) 2015-116; FW Check Valve Test Taps A Loop - U2; Revision 0;

(2) 2015-161; Isolation Condenser Level Hi/Lo; Revision 0;

(3) 2015-289; Hardened Containment Vent System Modification - U3 Online; Revision 0;

(4) 2016-005; Unit 2(3) SBO Ventilation; Revision 0;

(5) 2016-033; Seismic Event Retrieval/Evaluation; Revision 0;

(6) 2016-080; Revision to UFSAR 5.4.6.3; Revision 0;

(7) 2016-083; MOV 2-3906 to be Changed to Manually Operated Valve; Revision 0;

(8) 2017-187; Declassification or RWCU Isolation Panel Power Supply to Non- EQ;

(9) 2015-356; Revise TRM Sections 3.3.e, Fire Detection Instrumentation and 3.7.K, Gaseous Suppression System; Revision 0;

(10) 2016-316; Bypass ESS UPS- U2; Revision 2;

(11) 2017-212; Failure of Unit 2 125 VDC Power Supply; Revision 0;

(12) 2016-051; Jumper Cell 3 and Cell 110 on 250 VDC Station Battery; Revision 0;

(13) 2017-160; Zinc Injection System Operation; Revision 27;

(14) 2017-147; Loss of Offsite Power; Revision 76;

(15) 2017-125; SDC Cold Shutdown Method; Revision 17;

(16) 2017-023; Largest Single Load for Emergency Diesel Generators; Revision 00;

(17) 2016-46; Nuclear Fuel Transition To AREVA ATRIUM 10XM; Revision 000;

(18) 2015-169; Fuel Moves and Refueling; Revision 32;

(19) 2015-093; Reactor Building Ventilation; Revision 44; and

(20) 2015-135; RPV Head Cooling; Revision

INSPECTION RESULTS

No findings or violations were identified

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

On February 2, 2018 the inspector presented the Evaluations of Changes, Tests and Experiments inspection results to Mr. Pete Karaba and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.17TEvaluations of Changes, Tests and Experiments

- DAN 902(3)-3 D-4; ISOL CONDR LVL HI/LO; Revision 13

- DMP 5800-18; Load Handling of Heavy Loads and Lifting Devices; Revision 28

- DOP 0010-13; Seismic Event Retrieval/Evaluation; Revision 7

- DOP 6620-21; Unit 2(3) SBO Ventilation; Revision 8

- DRE12-0079; Evaluation of Plant Structures for Probable Maximum Flood Loads; Revision 2

- DSSP 0100-A; Hot Shutdown Procedure - Path A; Revision 29

- DSSP 0100-A2/B2; Hot Shutdown Procedure - Path A2/B2; Revision 41

- EC 399633; FW Check Valve Test Taps A - U2; Revision 0

- EC 400578; Hardened Containment Vent System Modification - U3 Online; Revision 0

- EC 404969; MOV 2-3906 to be Changed to Manually Operated Valve; Revision 0

- MA-AA-716-021; Rigging and Lifting Program; Revision 28

- AR 02740507; U3 250VDC Battery Cell #3 Needs to be Replaced; 11/13/2016

- AR 02740508; U3 250VDC Battery Cell #110 Needs to be Replaced; 11/13/2016

- 12E-3325; 120/240V AC Distribution Essential Service Bus and Instrument Bus; Revision AK

- DRE15-0045; Thermal Lag Calculation for RWCU Leak Detection Power Supply; Revision 00

- EC 405600; Classification of ESS UPS; Revision 0

- EC 405313; Essential Service Bus UFSAR and Technical Specification Bases Update;

Revision 00

- EC 407161; Jumper Cell 3 and Cell 110 on 250 VDC Station Battery; Revision 0

- AR 04099977; Deficient 50.59 Screening Documentation; 02/01/2018

- Drawing M-269; Diagram of Reactor Building Ventilation; Revision K

- AR 03949647; TRM 3.7.J, Water Suppression System Enhancement; 12/05/2016

- AR 02536377; Unauthorized T-MOD Not Corrected as Recommended; 08/02/2015

- AR 02506029; U2 Galleries North of RBCCW HT EX Missing Nuts; 05/27/2015

- AR 04098862; NRC Question Concerning Operation with Reduced RBV Fans; 01/30/2018

- DOS 6600-03; Bus Undervoltage and ECCS Integrated Functional Test for Unit 2/3 Diesel

Generator to Unit 3; Revision 43

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