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The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments." | The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments." | ||
This inspection constituted seven samples of evaluations an d 13 samples of screenings as defined in IP 71111.17-04. | This inspection constituted seven samples of evaluations an d 13 samples of screenings as defined in IP | ||
==71111.17 - 04.== | |||
====b. Findings==== | ====b. Findings==== | ||
| Line 97: | Line 99: | ||
the supporting design and licensing basis documentation was updated; the changes were in accordance with the specified design requirements; the procedures and training plans affected by the modification have been adequately updated; the test documentation as required by the applicable test programs has been updated; and post-modification testing adequately verified system operability and/or functionality. The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an attachment to this report. | the supporting design and licensing basis documentation was updated; the changes were in accordance with the specified design requirements; the procedures and training plans affected by the modification have been adequately updated; the test documentation as required by the applicable test programs has been updated; and post-modification testing adequately verified system operability and/or functionality. The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an attachment to this report. | ||
This inspection constituted seven permanent plant modification samples as defined in IP 71111.17-04. | This inspection constituted seven permanent plant modification samples as defined in IP | ||
==71111.17 - 04.== | |||
====b. Findings==== | ====b. Findings==== | ||
Revision as of 10:48, 17 September 2018
| ML14087A444 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/27/2014 |
| From: | Daley R C Engineering Branch 3 |
| To: | Pacilio M J Exelon Generation Co, Exelon Nuclear |
| Dariusz Szwarc | |
| References | |
| IR-14-008 | |
| Download: ML14087A444 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532
-4352 March 27, 2014 Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Co., LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 EVALUATION S OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000 456/20 1 4008; 05000 457/20 14008
Dear:
Mr. Pacillio:
On March 27, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications inspection at your Braidwood Station, Units 1 and 2. The enclosed inspection report documents the inspection results which were discussed on March 27, 2014, with Mr. P. Raush and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
The NRC inspectors did not identify any findings or violations of more than minor significance.
In accordance with Title 10, Code of Federal Regulations (CFR), Section 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50
-456; 50-457 License Nos. NPF
-72; NPF-77
Enclosure:
Inspection Report 05000456/2014008; 05000457/2014008
w/Attachment:
Supplemental Information cc w/encl: Distribution via ListServŽ U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-456; 50-457 License No
05000 456/20 1 4008; 05000 457/20 1 4008 Licensee: Exelon Generating Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: January 21 through March 27, 2014 Inspectors:
D. Szwarc, Senior Reactor Inspector N. Féliz Adorno, Reactor Inspector I. Hafeez, Reactor Inspector Approved by:
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety 1 Enclosure
SUMMARY OF FINDINGS
IR 05000 456/20 1 4008, 05000 457/20 1 4008; 01/21/2014
- 0 3/2 7/2014; Braidwood Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
This report covers a two-week announced baseline inspection on evaluations of changes, tests, and experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors.
The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG
-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
A. N RC-Identified and Self-Revealed Findings
Cornerstone: Initiating Events
No findings of significance were identified.
B. Licensee-Identified Violations
No violations of significance were identified.
2
REPORT DETAILS
REACTOR SAFETY
Cornerstone:
Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluation s of Changes, Tests, and Experiments and Permanent Plant Modifications (71111.17)
.1 Evaluation of Changes, Tests, and Experiments
a. Inspection Scope
The inspectors reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 13 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
the changes, tests, and experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; the safety issue requiring the change, tests and experiment was resolved; the licensee conclusions for evaluations of changes, tests, and experiments were correct and consistent with 10 CFR 50.59; and the design and licensing basis documentation was updated to reflect the change.
The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments."
This inspection constituted seven samples of evaluations an d 13 samples of screenings as defined in IP
71111.17 - 04.
b. Findings
No findings of significance were idenfied.
.2 Permanent Plant Modifications
a. Inspection Scope
The inspectors reviewed seven permanent plant modifications that had been installed in the plant during the last three years. This review included in
-plant walkdowns for portions of the modified diesel generator governor booster; backup power supplies for the steam generator power operated relief valves; isolation valves in the safety injection system; temporary scaffolds; and electrical circuits related to high energy line break (HELB) in the diesel generator rooms, miscellaneous electric rooms, and engineered safety features switchgear rooms.
The modifications were selected based upon risk significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:
the supporting design and licensing basis documentation was updated; the changes were in accordance with the specified design requirements; the procedures and training plans affected by the modification have been adequately updated; the test documentation as required by the applicable test programs has been updated; and post-modification testing adequately verified system operability and/or functionality. The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an attachment to this report.
This inspection constituted seven permanent plant modification samples as defined in IP
71111.17 - 04.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
(OA)
4OA2 Problem Identification and Resolution
.1 Routine Review of Condition Reports
a. Inspection Scope
The inspectors reviewed several corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to permanent p lant modifications and evaluations of changes, tests, or experiments. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporatio n of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Meetin gs
.1 Exit Meeting
Summary O n March 2 7, 2014 , the inspector s presented the inspection results to Mr. P. Raush and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented.
.2 Interim Exit Meeting
On February 20, 2014, the inspectors presented the inspection results to Mr. J. Bashor and other members of the licensee staff.
.3 Interim Exit Meeting
O n February 7, 2014, the inspector s presented the inspection results to Mr. M. Kanavos , and other members of the licensee staff. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
Attachment
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC
T Licensee
- M. Kanavos, Plant Manager
- M. Marchionda, Plant Manager
- J. Bashor, Engineering
Director
- A. Ferko, Operations Manager
- R. Belair, Mechanical Design Engineering Manager
- P. Raush, Regulatory Assurance
Manager
- D. Riedinger, Engineering Training
- G. Wilhelmsen, Design Engineering Manager
- M. Abbas, NRC coordinator
Nuclear Regulatory Commission
- J. Benjamin, Senior Resident Inspector
- R. Daley, Chief, Reactor Safety, Engineering Branch 3
- E. Duncan, Chief, Reactor Projects, Branch 3
LIST OF ITEMS OPENED, CLOSED AND DISCUSS
ED Opened , Closed, and Discussed
None
LIST OF DOCUMENTS REVIEWED The following is a list of documents reviewed during the inspection.
Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort. Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
CFR 50.59 EVALUATIONS
Number Description or Title
Date or Revision
BRW-E-2011-122 Installation of Backup Power Supplies for the Steam Generator Power Operated Relief Valves October 21, 2011
BRW-E-2012-0 85 Change In-Core Decay Time for A1R16
April 13, 2012
BRW-E-2012-120 Eliminating Action 3.3.y.D from TRM 3.3.y
May 30, 2012
BRW-E-2012-126 Install Time Delayed Auto-Restart for U
-1 (U-2) VD Fans in Support of HELB Mitigation Strategy
August 12, 2013
BRW-E-2012-155 Lake Screen House Traveling Screen Level Control September 7, 2012
BRW-E-2012-156 Install Time Delay Auto
-Restart for U
-1 (U-2) VX Fans in Support of
HELB Mitigation Strategy January 31, 2013
BRW-E-2012-186 Abnormal Component Position Sheet for Closing the Isolation Valves to the MSIV
Hydraulic Accumulator Manifolds' Relief Valves September 11, 2012
CFR 50.59 SCREENINGS
Number Description or Title
Date or Revision BRW-S-2011-0 84 Retention of a Temporary Scaffold Installed in the 2A RHR Heat Exchanger Room Beyond 90 Days
June 9, 2011
BRW-S-2011-0 88 Revised NPSH Required Value for the CV Pumps
June 23, 2011
BRW-S-2011-097 Incorporate Time Delay Relay into 1
& 2 VD Fans High Differential Pressure Trip Circuit Due to Turbine Building High Energy Line Break (HELB)
July 14, 2011
BRW-S-2011-138 Revision to UFSAR Section 9.2.2.5 "Test and Inspections" and Revision
of Related Procedures
August 31, 2011 BRW-S-2011-162 Retention of Three Non
-Permanent Scaffolds Installed in the U1 Auxiliary Building on the 426' Elevation Beyond 90 Days
October 13, 2011 BRW-S-2012-101 Receiving Bulk Loads of Sodium Bromide into 0CF19 T May 4, 2012
BRW-S-2012-124 UFSAR Change to Table 3
-2-1 for Aux Safeguard Relay Cabinet Indicating
Lights (1/2 EL
-LV002 & June 13, 2012
10 CFR 50.59 SCREENINGS
Number Description or Title
Date or Revision 003) BRW-S-2012-150 Revise EDG Fuel Calculations to Address Frequency and CDBI Identified Issues
July 31, 2012
BRW-S-2012-228 Revision of the <75 VDC DC Ground V alue for a Bus Cross Tie to a <103 VDC Action Value. October 27, 2012 BRW-S-2012-238 UFSAR Update for Generic Letter 2008
-01 Response November 9, 2012 BRW-S-2013-039 ESF Switchgear Room Fan 1(2)VX01C DP Switch Setpoint Change and Non
-ESF Switchgear Room Vent Fan 1(2)VX02C DP Switch Setpoint Change
April 9, 2013
BRW-S-2013-041 Transferring a 4160V or 6900V Bus from a Unit Auxiliary Transformer to a System Auxiliary Transformer April 10, 2013
BRW-S-2013-069 Retention of Temporary Scaffold S
-1543 Beyond 90 Days May 10, 2013
BRW-S-2013-348 Turbine Building Floor Drain Sump Level High High
February 14, 2013 CALCULATIONS
Number Description or Title
Date or Revision 19-T-6 Diesel Generator Loading During LOOP / LOCA
- Braidwood Unit 1
6F BRW-00-0010-M Byron/Braidwood Uprate Project
- Spent Fuel Pool Temperature Analysis
April 11, 2012
BRW-04-0005-M RHR, SI, CV and CS Pumps NPSH During ECCS Injection Mode
July 7, 2011 BRW-11-0115-M Evaluation of the Potential for CV Pump Gas Binding
November 10, 2011 BRW-96-362-I Diesel Oil Storage Tank Level Setpoints
October 5, 2012
BRW-97-0274 Containment Spray Additive Tank Level Switch LO
-2 Setpoint Analysis
2A PSA-B-98-08 Byron/Braidwood ECCS Flow Calculations for Safety Analysis 3E
CORRECTIVE ACTION PROGRAM DOCUMENTS INITIATED DURING INSPECTION
Number Description or Title
Date or Revision
1611719 NRC Poses Question on 50.59 Screening BRW
-S-2013-348 January 23, 2014
1611724 Old Calculation Needs to be Superseded
January 23, 2014
1613724 NRC 2014 50.59 Inspection, Error in Procedures BWAR 2-15-A11 ~ D11 January 28, 2014
1615733 Missing Records for Scaffold Installed in 2A RHR HX Room January 31, 2014
1616558 Deficiencies Noted During an NRC Walkdown
February 3, 2014
1617606 EDG Governor Booster Line Slopes Not In Accordance with EC
February 5, 2014
1617670 Permanent Scaffolds Missing Documentation
February 5, 2014
1617930 50.59 Document Not Aligned with Scaffold Procedure February 6, 2014
1618112 Lessons Learned: NRC MODS/50.59 Baseline Inspection
February 6, 2014
CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
Number Description or Title
Date or Revision
1142820 GL 08-01: Procedure Enhancement for 1/2BWOSR 3.5.2.2-2 November 19, 2010 1146838 NRC ID - Revise Calculation to Show Disposition of Vortex in CSAT
November 30, 2010 1234663 B4 Trend Code: 2LDS
-SW007 As Found OOT
June 28, 2011
237140 Non-Conservative Inputs to HELB Analysis
July 6, 2011
264955 SOER 7-02 Event Readiness
-CW Pump Trip Lifted
September 19, 2011 1269263 NRC MOD/50.59 Inspection
- Concrete Compressive Strength
September 27, 2011 1323285 GL 2008-01 Analyses and Evaluations Require an UFSAR Update
February 6, 2012
1353449 LR Revise UFSAR Table 3.2
-1 for LV Lights
April 13, 2012
1383554 PI&R Action to Address Previous Issue Not Adequate June 29, 2012
1409900 Potential Unidentified Condition with MSIV Accumulator
September 6, 2012 1433324 Label Request for EC 389506
November 29, 2012 1452606 2B DG Governor Booster
- Improve Oil Inlet Line Arrangement
December 15, 2012 1460488 CCP: Need Labels Made For New VD Temperature Switches February 8, 2013
1463427 EC 389506 Revision 001 Label Request
February 15, 2013
1466005 Scheduling Conflict with HELB Mods and DOST Sprinkler Mods
February 22, 2013
CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
Number Description or Title
Date or Revision
1468255 1HS-VD040 As Found Wiring did not Match Design Drawing CCP
February 28, 2013
1473152 1WF040A - Essential Service WTR Sump PMP 1A Discharge Check
February 9, 2013 1493072 CCP :Unit 1 Drawing is Referred in Unit 2
April 26, 2013
1543966 Retesting of 1TS
-VD002A Required Due to OOT M&TE September 5, 2013 1543967 Retesting of 1TS
-VD002B Required Due to OOT M&TE September 5, 2013 1589107 2013 FASA for Pre
-NRC MOD/50.59 Inspection Deficiency
- 50.59 Screen
November 22, 2013 DRAWINGS Number Description or Title
Date or Revision
20E-0-3600 Braidwood Unit 1& 2 Electrical Floor
and Wall 1 20E-1-4030VD01 Schematic Diagram Diesel Generator Room 1A HVAC System Ventilation Fan 1A 1VD01CA
M 20E-1-4030VD03 Schematic Diagram Diesel Generator Room 1A HVAC System Ventilation
and Exhaust Fans Auxiliary Relays, Switches
and Alarms -Part I O 20E-1-4030VD04 Schematic Diagram Diesel Generator Room 1A HVAC System Ventilation and Exhaust Fans Aux. Relays, Switches and Alarms Part II
L 20E-1-4030VD05 Schematic Diagram Diesel Generator 1A HVAC Sys. Diesel Oil Storage Room Exhaust Fans 1A
and 1B 1VD02CA and 1VD02CB L 20E-1-4030VD06 Schematic Diagram Diesel Generator 1B HVAC Sys. Diesel Oil Storage Room Exhaust Fans 1C
and 1D 1VD02CC and 1VD02CD L 20E-1-4030VD09 Schematic Diagram Diesel Generator Room 1B HVAC System Ventilation & Exhaust Fans Aux. Relays, Switches
and Alarms Part II
L 20E-1-4030VD11 Schematic Diagram Diesel Generator 1A
and Day Tank Room CO2 Fire Protection System Fire Damper Control
J 20E-1-4030VD12 Schematic Diagram Diesel Generator 1B & Day Tank Room CO2 Fire Protection System Fire Damper Control
J 20E-1-4507A Internal and External Wiring Diagram Diesel Generator HVAC Local Control Stations HIS
-VDO42 E 20E-1-4511B Internal Wiring Diagram Diesel Generator Room 1A Vent System Local Control Panel 1VD01JA PT.2
G 20E-1-4511E Internal-External Wiring
Diagram Diesel Generator
T
DRAWINGS Number Description or Title
Date or Revision
From 1A Vent. System Local Control Panel 1VD01JA Part
-5 D-10239 Schematic for A/DV Self Contained Hydraulic Actuator H M-136, Sheet 2
Diagram of Safety Injection
AF M-152, Sheet 20
Control Diagram Starting System and Alarms
G M-2097 HVAC/C&I Diagram Diesel Generator Room Ventilation System
-VD, sheet number 6
E M-4097-1VD05 Control Logic Diagram Diesel Oil Storage Room Vent Fan Control
C M-61, Sheet 2
Diagram of Safety Injection
AJ M-97 Diagram of Diesel Generator Rooms
1A & 1B Ventilation System
W MODIFICATIONS
Number Description or Title
Date or Revision
EC 374070 Diesel Generator Governor Booster
EC 385013 Add Redundant Isolation Valves in Series with 2SI8801 A/B
EC 388473 Install Time Delayed Auto
-Restart for U-1 VE Fans in Support of HELB Mitigation Strategy
EC 388475 Install Time Delayed Auto
-Restart For U
-1 VD Fans in Support of HELB Mitigation
EC 389506 Install High Temperature Trip for DOST Ventilation
Fans 3 EC377536 2A CV Pump Impeller Replacement
EC383595 Incorporate NPSH Required for Replacement Impeller for the 2A CV Pump into the NPSH Analysis from the RWST
PROCEDURES
Number Description or Title
Date or Revision
1BwEP-1 Loss of Reactor or Secondary Coolant Unit 1
205 1BwOS XLE-R1 Unit One Locked Equipment Surveillance
1BwOSR 3.8.1.2-1 1A Diesel Generator Operability Surveillance
2BwEP-1 Loss of Reactor or Secondary Coolant Unit 2
205 2BwOS XLE-R1 Unit Two Locked Equipment Surveillance
BwAR 1-17-B13 Alarm Response Procedure for CW Pump dP Low
BwAR 1-17-D13 Alarm Response Procedure for Intake Bay Level
BwAR 1-17-E13 Alarm Response Procedure for Traveling Screen Trouble 8 BwOP MS-5 MSIV Accumulator Operability Check
BwOP SI-M1 Operating Mechanical Lineup Unit 1
BwOP SI-M2 Operating Mechanical Lineup Unit 1
2 MA-AA-716-025 Scaffold Installation, Modification, and Removal Request Process
MA-AA-716-040 Measurement and Test Equipment Evaluation
OTHER DOCUMENTS
Number Description
or Title Date or Revision
PP-CV-5 IST Evaluation CV Pump New Ref Values
July 28, 2010
Add Isolation Valves Upstream of 2SI8801A&B
October 29, 2012
1LS-WF025 Essential Service Water Sump Level Switch June 21, 2013
Thermal Performance Test at Start of Outage
October 8, 2013
-AA-107 ATT 1 EC 389506 March 15, 2013
IM Bench Cal Temp Switches per EC 389506
OAP (HAMMOCK) Testing per CC
-AA-107 ATT 1 EC 389506 December 8, 2012 WO 1566937
IM - 1TS - VD002B Calibrate per EC 289506
August 29, 2013
WO 384197 SEP Pump Curve/Full Flow Test
October 26, 2009
LIST OF ACRONYMS USE
D ADAMS Agencywide Documents Access and Management System
CDBI Component Design Basis Inspection
CFR Code of Federal Regulations
CSAT Containment Spray Additive Tank
DG Diesel Generator
DOST Diesel Oil Storage Tank
EC Engineering Change
ECCS Emergency Core Cooling System
EDG Emergency Diesel Generator
FASA Focused Area Self-Assessment
FIN Finding GL Generic Letter
HVAC Heating, Ventilation, and Air Conditioning
HX Heat Exchanger
IMC Inspection Manual Chapter
IST Inservice Testing
LOCA Loss of Coolant Accident
MSIV Main Steam isolation Valve
NCV Non-Cited Violation
NEI Nuclear Energy Institute
NPSH Net Positive Suction Head
NRC U.S. Nuclear Regulatory Commission
PARS Public Available Records System
SDP Significance Determination Process
SI Safety Injection
UFSAR Updated Final Safety Analysis Report
WO Work Order
Mr. Michael J. Pacilio
Senior Vice President, Exelon Generation Co., LLC
President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road
Warrenville, IL 60555
SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000456/2014008; 05000457/201400
Dear: Mr. Pacillio
- On February 7, 2014, the
- U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications inspection at your Braidwood Station, Units 1 and 2. The enclosed inspection report documents
the inspection results which were discussed on March 27, 2014, with Mr.
- P. Raush, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
The NRC inspectors did not identify any findings or violations of more than minor significance.
In accordance with Title 10, Code of Federal Regulations
(CFR), Section 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html
(the Public Electronic Reading Room).
Sincerely, /RA/
Robert
- C. Daley, Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50
-456; 50-457 License Nos. NPF
-72; NPF-77 Enclosure:
Inspection Report 05000456/2014008; 05000457/2014008
w/Attachment: Supplemental Information
cc w/encl: Distribution via ListServŽ
DOCUMENT NAME:
G:\DRS\Work in Progress
\Misc Boilers
\con 5.doc -Publicly Available
-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
OFFICE RIII RIII NAME DSzwarc:ls
RCDaley DATE 0 3/27/14 0 3/27/14 OFFICIAL RECORD COPY
Letter to Michael J. Pacilio
from Robert C. Daley
dated March 27, 2014. SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000456/2014008; 05000457/201400
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