IR 05000456/2014008
| 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
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 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. 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 Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
.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 and 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 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.
b. Findings
No findings of significance were identified.
4OA6 Meetings
.1 Exit Meeting Summary
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.
.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.
The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
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 DISCUSSED
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.
- 10
- 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
- 10
- 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-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
- 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
- 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
- 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
- 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 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
LIST OF ACRONYMS
- USED [[]]
- NRC [[]]
UFSAR Updated Final Safety Analysis Report WO Work Order
Mr. Michael
- OF [[]]
- AND [[]]
- AND [[]]
- PLANT [[]]
- 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]]
- 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 [[]]
- RECORD [[]]
- OF [[]]
- AND [[]]
- AND [[]]
- PLANT [[]]