IR 05000456/2014008: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532
[[Issue date::March 27, 2014]]
-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


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 05000456/2014008; 05000457/2014008


SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000456/2014008; 05000457/2014008
==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.


==Dear:==
The NRC inspectors did not identify any findings or violations of more than minor significance.
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).
 
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  
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:===
===Enclosure:===
Inspection Report 05000456/2014008; 05000457/2014008  
Inspection Report 05000456/2014008; 05000457/2014008


===w/Attachment:===
===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: NPF-72; NPF-77 Report No: 05000456/2014008; 05000457/2014008 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  
Supplemental Information cc w/encl: Distribution via ListServŽ U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket No
: 50-456; 50-457 License No
: NPF-72; NPF-77 Report No:
05000456/2014008; 05000457/2014008 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=
=SUMMARY OF FINDINGS=
IR 05000456/2014008, 05000457/2014008; 01/21/2014 - 03/27/2014; 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.
IR 05000456/2014008, 05000457/2014008; 01/21/2014  
 
- 03/27/2014; 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. NRC-Identified===
===A. NRC-Identified===
and Self-Revealed Findings  
and Self-Revealed Findings  


===Cornerstone: Initiating Events No findings of significance were identified.
===Cornerstone: Initiating Events===
 
No findings of significance were identified.


===B. Licensee-Identified Violations===
===B. Licensee-Identified Violations===
No violations of significance were identified.===
 
No violations of significance were identified.


2
2
Line 54: Line 78:


===Cornerstone:===
===Cornerstone:===
Initiating Events, Mitigating Systems, and Barrier Integrity
Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluation s of Changes, Tests, and Experiments and Permanent Plant Modifications (71111.17)
{{a|1R17}}
 
==1R17 Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications==
===.1 Evaluation of Changes, Tests,===
{{IP sample|IP=IP 71111.17}}
 
===.1 Evaluation of Changes, Tests, and Experiments===
and Experiments


====a. Inspection Scope====
====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 and 13 samples of screenings as defined in IP 71111.17-04.
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====
====b. Findings====
Line 69: Line 98:


====a. Inspection Scope====
====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.
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====
====b. Findings====
No findings of significance were identified.
No findings of significance were identified.


==OTHER ACTIVITIES (OA)==
==OTHER ACTIVITIES==
(OA)
{{a|4OA2}}
{{a|4OA2}}
==4OA2 Problem Identification and Resolution==
==4OA2 Problem Identification and Resolution==
Line 81: Line 117:


====a. Inspection Scope====
====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 plant 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 incorporation 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.
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====
====b. Findings====
No findings of significance were identified.
No findings of significance were identified.
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Meetings==
==4OA6 Meetings==


===.1 Exit Meeting Summary===
===.1 Exit Meeting===
On March 27, 2014, the inspectors presented the inspection results to Mr. P. Raush and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented.
 
Summary  On March 27, 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===
===.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.
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 On February 7, 2014, the inspectors presented the inspection results to Mr. M. Kanavos, and other members of the licensee staff.===
===.3 Interim Exit Meeting===
The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. ATTACHMENT:   
 
On 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=
=SUPPLEMENTAL INFORMATION=


==KEY POINTS OF CONTACT==
Attachment
Licensee  
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC
: [[contact::M. Kanavos]], Plant Manager  
T Licensee  
: [[contact::M. Marchionda]], Plant Manager  
: [[contact::M. Kanavos]], Plant Manager
: [[contact::J. Bashor]], Engineering Director  
: [[contact::M. Marchionda]], Plant Manager
: [[contact::A. Ferko]], Operations Manager  
: [[contact::J. Bashor]], Engineering
: [[contact::R. Belair]], Mechanical Design Engineering Manager  
Director  
: [[contact::P. Raush]], Regulatory Assurance Manager  
: [[contact::A. Ferko]], Operations Manager
: [[contact::D. Riedinger]], Engineering Training  
: [[contact::R. Belair]], Mechanical Design Engineering Manager
: [[contact::G. Wilhelmsen]], Design Engineering Manager  
: [[contact::P. Raush]], Regulatory Assurance
: [[contact::M. Abbas]], NRC coordinator Nuclear Regulatory Commission  
Manager  
: [[contact::J. Benjamin]], Senior Resident Inspector  
: [[contact::D. Riedinger]], Engineering Training
: [[contact::R. Daley]], Chief, Reactor Safety, Engineering Branch 3  
: [[contact::G. Wilhelmsen]], Design Engineering Manager
: [[contact::E. Duncan]], Chief, Reactor Projects, Branch 3  
: [[contact::M. Abbas]], NRC coordinator
==LIST OF ITEMS==
Nuclear Regulatory Commission
OPENED, CLOSED AND DISCUSSED
: [[contact::J. Benjamin]], Senior Resident Inspector
===Opened, Closed, and Discussed===
: [[contact::R. Daley]], Chief, Reactor Safety, Engineering Branch 3
None   
: [[contact::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-2012-085 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-2011-084 Retention of a Temporary Scaffold Installed in the 2A RHR Heat Exchanger Room Beyond 90 Days
June 9, 2011
BRW-S-2011-088 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 0CF19T 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 Value 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
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
WO 10450738
Add Isolation Valves Upstream of 2SI8801A&B
October 29, 2012
WO 1314278
1LS-WF025 Essential Service Water Sump Level Switch June 21, 2013
WO 1538365
Thermal Performance Test at Start of Outage
October 8, 2013
WO 1566935
CE Perform MOD Testing per CC
-AA-107 ATT 1 EC
389506 March 15, 2013
WO 1566935
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
CS Core Spray
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
HELB High Energy Line Break
HVAC Heating, Ventilation, and Air Conditioning
HX Heat Exchanger
IMC Inspection Manual Chapter
IST Inservice Testing
LOCA Loss of Coolant Accident
LOOP Loss of Offsite Power
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
RHR Residual Heat Removal
SDP Significance Determination Process
SI Safety Injection
UFSAR Updated Final Safety Analysis Report
WO Work Order


==LIST OF DOCUMENTS REVIEWED==
Mr. Michael J. Pacilio
The following is a list of documents reviewed during the inspection.
Senior Vice President, Exelon Generation Co., LLC
: 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.
President and Chief Nuclear Officer, Exelon Nuclear
: 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.
4300 Winfield Road
: 10
Warrenville, IL 60555
: CFR 50.59 EVALUATIONS Number Description or Title Date or Revision
SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000456/2014008; 05000457/201400
: BRW-E-2011-122 Installation of Backup Power Supplies for the Steam Generator Power Operated Relief Valves October 21, 2011
Dear:  Mr. Pacillio
: BRW-E-2012-085 Change In-Core Decay Time for A1R16 April 13, 2012
: On February 7, 2014, the  
: BRW-E-2012-120 Eliminating Action 3.3.y.D from TRM 3.3.y May 30, 2012
: [[contact::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
: 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
the inspection results which were discussed on March 27, 2014, with Mr.  
: BRW-E-2012-155 Lake Screen House Traveling Screen Level Control September 7, 2012
: [[contact::P. Raush]], and other members of your staff.
: 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
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.
: BRW-E-2012-186 Abnormal Component Position Sheet for Closing the Isolation Valves to the MSIV
The NRC inspectors did not identify any findings or violations of more than minor significance.
: Hydraulic Accumulator Manifolds' Relief Valves September 11, 2012
In accordance with Title 10, Code of Federal Regulations
: 10
(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
: CFR 50.59 SCREENINGS Number Description or Title Date or Revision
-rm/adams.html
: BRW-S-2011-084 Retention of a Temporary Scaffold Installed in the 2A RHR Heat Exchanger Room Beyond 90 Days June 9, 2011
(the Public Electronic Reading Room).
: BRW-S-2011-088 Revised NPSH Required Value for the CV Pumps June 23, 2011
Sincerely,
: 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
  /RA/
: BRW-S-2011-138 Revision to UFSAR Section 9.2.2.5 "Test and Inspections" and Revision of Related Procedures August 31, 2011
Robert  
: 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
: [[contact::C. Daley]], Chief
: BRW-S-2012-101 Receiving Bulk Loads of Sodium Bromide into 0CF19T May 4, 2012
Engineering Branch 3
: BRW-S-2012-124 UFSAR Change to Table 3-2-1 for Aux Safeguard Relay Cabinet Indicating Lights (1/2
Division of Reactor Safety
: EL-LV002 & June 13, 2012 
Docket Nos. 50
: 10
-456; 50-457 License Nos. NPF
: CFR 50.59 SCREENINGS Number Description or Title Date or Revision 003)
-72; NPF-77 Enclosure:
: BRW-S-2012-150 Revise EDG Fuel Calculations to Address Frequency and CDBI Identified Issues July 31, 2012
Inspection Report 05000456/2014008; 05000457/2014008
: BRW-S-2012-228 Revision of the <75 VDC DC Ground Value for a Bus Cross Tie to a <103 VDC Action Value. October 27, 2012
w/Attachment:  Supplemental Information
: BRW-S-2012-238 UFSAR Update for Generic Letter 2008-01 Response November 9, 2012
cc w/encl:  Distribution via ListServ&#x17d;
: 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
DOCUMENT NAME:
: BRW-S-2013-041 Transferring a 4160V or 6900V Bus from a Unit Auxiliary Transformer to a System Auxiliary Transformer April 10, 2013
G:\DRS\Work in Progress
: BRW-S-2013-069 Retention of Temporary Scaffold S-1543 Beyond 90 Days May 10, 2013
\Misc Boilers
: BRW-S-2013-348 Turbine Building Floor Drain Sump Level High High February 14, 2013
\con 5.doc
: CALCULATIONS Number Description or Title Date or Revision 19-T-6 Diesel Generator Loading During LOOP / LOCA - Braidwood Unit 1 6F
  -Publicly Available
: BRW-00-0010-M Byron/Braidwood Uprate Project - Spent Fuel Pool Temperature Analysis April 11, 2012
  -Sensitive
: BRW-04-0005-M RHR, SI, CV and CS Pumps NPSH During ECCS Injection Mode July 7, 2011
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
: BRW-11-0115-M Evaluation of the Potential for CV Pump Gas Binding November 10, 2011
OFFICE RIII RIII       NAME DSzwarc:ls
: BRW-96-362-I Diesel Oil Storage Tank Level Setpoints October 5, 2012
RCDaley   DATE 03/27/14 03/27/14     OFFICIAL RECORD COPY
: BRW-97-0274 Containment Spray Additive Tank Level Switch
Letter to Michael J. Pacilio
: LO-2 Setpoint Analysis 2A
from Robert C. Daley
: PSA-B-98-08 Byron/Braidwood ECCS Flow Calculations for Safety Analysis 3E   
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
: CORRECTIVE ACTION PROGRAM DOCUMENTS INITIATED DURING INSPECTION Number Description or Title Date or Revision
DISTRIBUTION
: 1611719 NRC Poses Question on 50.59 Screening
: Ernesto Quinones
: BRW-S-2013-348 January 23, 2014
RidsNrrDorlLpl3
: 1611724 Old Calculation Needs to be Superseded January 23, 2014
-2 Resource
: 1613724
RidsNrrPMBraidwood Resource
: NRC 2014 50.59 Inspection, Error in Procedures BWAR 2-15-A11 ~ D11 January 28, 2014
RidsNrrDirsIrib Resource
: 1615733 Missing Records for Scaffold Installed in 2A RHR HX Room January 31, 2014
Cynthia Pederson
: 1616558 Deficiencies Noted During an NRC Walkdown February 3, 2014
Darrell Roberts
: 1617606 EDG Governor Booster Line Slopes Not In Accordance with EC February 5, 2014
Steven Orth
: 1617670 Permanent Scaffolds Missing Documentation February 5, 2014
Allan Barker
: 1617930 50.59 Document Not Aligned with Scaffold Procedure February 6, 2014
DRPIII DRSIII Carole Ariano
: 1618112 Lessons Learned: NRC MODS/50.59 Baseline Inspection February 6, 2014
Linda Linn
: CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED Number Description or Title Date or Revision
Patricia Buckley
: 1142820
ROPreports.Resource@nrc.gov
: 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
: 1237140 Non-Conservative Inputs to HELB Analysis July 6, 2011
: 1264955 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 1
: EC 385013 Add Redundant Isolation Valves in Series with 2SI8801 A/B 0
: EC 388473 Install Time Delayed Auto-Restart for U-1 VE Fans in Support of HELB Mitigation Strategy 1
: EC 388475 Install Time Delayed Auto-Restart For U-1 VD Fans in Support of HELB Mitigation 2
: EC 389506 Install High Temperature Trip for DOST Ventilation Fans 3 EC377536 2A CV Pump Impeller Replacement 0 EC383595 Incorporate NPSH Required for Replacement Impeller for the 2A CV Pump into the NPSH Analysis from the RWST 0   
: 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 26 1BwOSR 3.8.1.2-1 1A Diesel Generator Operability Surveillance 35 2BwEP-1 Loss of Reactor or Secondary Coolant Unit 2 205 2BwOS
: XLE-R1 Unit Two Locked Equipment Surveillance 22 BwAR 1-17-B13 Alarm Response Procedure for CW Pump dP Low 13 BwAR 1-17-D13 Alarm Response Procedure for Intake Bay Level 10 BwAR 1-17-E13 Alarm Response Procedure for Traveling Screen Trouble 8 BwOP
: MS-5 MSIV Accumulator Operability Check 29 BwOP
: SI-M1 Operating Mechanical Lineup Unit 1 23 BwOP
: SI-M2 Operating Mechanical Lineup Unit 1 22
: MA-AA-716-025 Scaffold Installation, Modification, and Removal Request Process 9
: MA-AA-716-040 Measurement and Test Equipment Evaluation 8
: OTHER DOCUMENTS Number Description or Title Date or Revision
: PP-CV-5 IST Evaluation CV Pump New Ref Values July 28, 2010
: WO 10450738 14 Add Isolation Valves Upstream of 2SI8801A&B October 29, 2012
: WO 1314278 1LS-WF025 Essential Service Water Sump Level Switch June 21, 2013
: WO 1538365 Thermal Performance Test at Start of Outage October 8, 2013
: WO 1566935 10 CE Perform MOD Testing per
: CC-AA-107 ATT 1
: EC 389506 March 15, 2013
: WO 1566935 11 IM Bench Cal Temp Switches per
: EC 389506 OAP (HAMMOCK) Testing per
: CC-AA-107 ATT 1
: EC 389506 December 8, 2012
: WO 1566937 24 IM - 1TS - VD002B Calibrate per
: EC 289506 August 29, 2013
: WO 384197 SEP Pump Curve/Full Flow Test October 26, 2009
==LIST OF ACRONYMS==
: [[USED]] [[]]
: [[ADAMS]] [[Agencywide Documents Access and Management System]]
: [[CDBI]] [[Component Design Basis Inspection]]
: [[CFR]] [[Code of Federal Regulations]]
: [[CS]] [[Core Spray]]
: [[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]]
: [[HELB]] [[High Energy Line Break]]
: [[HVAC]] [[Heating, Ventilation, and Air Conditioning]]
: [[HX]] [[Heat Exchanger]]
: [[IMC]] [[Inspection Manual Chapter]]
: [[IST]] [[Inservice Testing]]
: [[LOCA]] [[Loss of Coolant Accident]]
: [[LOOP]] [[Loss of Offsite Power]]
: [[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]]
: [[RHR]] [[Residual Heat Removal]]
: [[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]]
: [[SUBJEC]] [[T: BRAIDWOOD STATION,]]
: [[UNITS]] [[1]]
: [[AND]] [[2 EVALUATIONS]]
: [[OF]] [[]]
: [[CHANGE]] [[S, TESTS,]]
: [[AND]] [[]]
: [[EXPERI]] [[MENTS]]
: [[AND]] [[]]
: [[PERMAN]] [[ENT]]
: [[PLANT]] [[]]
: [[MODIFI]] [[CATIONS BASELINE INSPECTION]]
: [[REPORT]] [[05000456/2014008; 05000457/2014008 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 ListServ&#x17d;   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]] [[03/27/14 03/27/14]]
: [[OFFICI]] [[AL]]
: [[RECORD]] [[]]
: [[COPY]] [[Letter to Michael]]
: [[J.]] [[Pacilio from Robert C. Daley dated March 27, 2014.]]
: [[SUBJEC]] [[T: BRAIDWOOD STATION,]]
: [[UNITS]] [[1]]
: [[AND]] [[2 EVALUATIONS]]
: [[OF]] [[]]
: [[CHANGE]] [[S, TESTS,]]
: [[AND]] [[]]
: [[EXPERI]] [[MENTS]]
: [[AND]] [[]]
: [[PERMAN]] [[ENT]]
: [[PLANT]] [[]]
: [[MODIFI]] [[CATIONS BASELINE INSPECTION REPORT 05000456/2014008; 05000457/2014008]]
}}
}}

Revision as of 00:31, 2 July 2018

IR 05000456-14-008 & 05000457-14-008; 01/21/2014 - 03/27/2014; Braidwood Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
ML14087A444
Person / Time
Site: Braidwood  Constellation icon.png
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)
v • d • e


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 05000456/2014008; 05000457/2014008

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
NPF-72; NPF-77 Report No:

05000456/2014008; 05000457/2014008 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 05000456/2014008, 05000457/2014008; 01/21/2014

- 03/27/2014; 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. NRC-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 Meetings

.1 Exit Meeting

Summary On March 27, 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

On 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-2012-085 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-2011-084 Retention of a Temporary Scaffold Installed in the 2A RHR Heat Exchanger Room Beyond 90 Days

June 9, 2011

BRW-S-2011-088 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 0CF19T 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 Value 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

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

WO 10450738

Add Isolation Valves Upstream of 2SI8801A&B

October 29, 2012

WO 1314278

1LS-WF025 Essential Service Water Sump Level Switch June 21, 2013

WO 1538365

Thermal Performance Test at Start of Outage

October 8, 2013

WO 1566935

CE Perform MOD Testing per CC

-AA-107 ATT 1 EC 389506 March 15, 2013

WO 1566935

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

CS Core Spray

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

HELB High Energy Line Break

HVAC Heating, Ventilation, and Air Conditioning

HX Heat Exchanger

IMC Inspection Manual Chapter

IST Inservice Testing

LOCA Loss of Coolant Accident

LOOP Loss of Offsite Power

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

RHR Residual Heat Removal

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 03/27/14 03/27/14 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

DISTRIBUTION

Ernesto Quinones

RidsNrrDorlLpl3

-2 Resource

RidsNrrPMBraidwood Resource

RidsNrrDirsIrib Resource

Cynthia Pederson

Darrell Roberts

Steven Orth

Allan Barker

DRPIII DRSIII Carole Ariano

Linda Linn

Patricia Buckley

ROPreports.Resource@nrc.gov

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