IR 05000461/2012007: Difference between revisions

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| issue date = 08/01/2012
| issue date = 08/01/2012
| title = IR 05000461-12-007, 06/25/2012 - 07/12/2012, Clinton Power Station; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
| title = IR 05000461-12-007, 06/25/2012 - 07/12/2012, Clinton Power Station; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
| author name = Daley R C
| author name = Daley R
| author affiliation = NRC/RGN-III/DRS/EB3
| author affiliation = NRC/RGN-III/DRS/EB3
| addressee name = Pacilio M J
| addressee name = Pacilio M
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000461
| docket = 05000461
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:August 1, 2012
[[Issue date::August 1, 2012]]


Mr. Michael Senior Vice-President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555
==SUBJECT:==
CLINTON POWER STATION EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000461/2012007


SUBJECT: CLINTON POWER STATION EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000461/2012007
==Dear Mr. Pacilio:==
On July 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Clinton Power Station. The enclosed inspection report documents the inspection results, which were discussed on July 12, 2012, with you and other members of your staff.


==Dear Mr. Pacilio:==
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
On July 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Clinton Power Station. The enclosed inspection report documents the inspection results, which were discussed on July 12, 2012, with you 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. Based on the results of this inspection, no findings of significance were identified. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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).
 
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
 
Based on the results of this inspection, no findings of significance were identified.
 
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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/


Sincerely,/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-461 License Nos. NPF-62  
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-461 License Nos. NPF-62  


===Enclosure:===
===Enclosure:===
Inspection Report 05000461/2012007  
Inspection Report 05000461/2012007 w/Attachment: Supplemental Information
 
REGION III==
Docket No:
50-461 License No:
NPF-62 Report No:
05000461/2012007 Licensee:
Exelon Generation Facility:
Clinton Power Station Location:
Clinton, IL Dates:
June 25 - July 12, 2012 Inspectors:
M. Munir, Reactor Inspector (Lead)
 
J. Gilliam, Reactor Inspector
 
L. Jones, Reactor Inspector Approved by:
R. Daley, Chief Engineering Branch 3 Division of Reactor Safety


===w/Attachment:===
Enclosure  
Supplemental Information cc w/encl: Distribution via ListServŽ Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-461 License No: NPF-62 Report No: 05000461/2012007 Licensee: Exelon Generation Facility: Clinton Power Station Location: Clinton, IL Dates: June 25 - July 12, 2012 Inspectors: M. Munir, Reactor Inspector (Lead) J. Gilliam, Reactor Inspector L. Jones, Reactor Inspector Approved by: R. Daley, Chief Engineering Branch 3 Division of Reactor Safety 1 Enclosure  


=SUMMARY OF FINDINGS=
=SUMMARY OF FINDINGS=
IR 05000461/2012007; 06/25/2012 - 07/12/2012; Clinton Power Station; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications. This report covers a two-week announced baseline inspection on evaluations of changes, tests, or 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. No findings of significance were identified.
IR 05000461/2012007; 06/25/2012 - 07/12/2012; Clinton Power Station; Evaluations of  
 
Changes, Tests, or Experiments and Permanent Plant Modifications.
 
This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. The NRCs 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.
 
No findings of significance were identified.


===NRC-Identified===
===NRC-Identified===
and Self-Revealed Findings B. No violations of significance were identified.
and Self-Revealed Findings B.
 
No violations of significance were identified.


===Licensee-Identified Violations===
===Licensee-Identified Violations===
1.


1. REACTOR SAFETY
REACTOR SAFETY


=REPORT DETAILS=
=REPORT DETAILS=
Cornerstone:  Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications


===.1 ===
===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity===
{{a|1R17}}
 
==1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
 
==
===.1===
{{IP sample|IP=IP 71111.17}}
{{IP sample|IP=IP 71111.17}}
a. Evaluation of Changes, Tests, or Experiments From June 25, 2012 through July12, 2012, the inspectors reviewed 7 safety-evaluations performed pursuant to 10 CFR 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 22 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if: Inspection Scope the changes, tests, or 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 or experiment was resolved; the licensee conclusions for evaluations of changes, tests, or 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 7 samples of evaluations and 22 samples of changes as defined in IP 71111.17-04. b. No findings of significance were identified. Findings
a.
 
Evaluation of Changes, Tests, or Experiments From June 25, 2012 through July12, 2012, the inspectors reviewed 7 safety-evaluations performed pursuant to 10 CFR 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 22 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
Inspection Scope
* the changes, tests, or 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 or experiment was resolved;
* the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
* the design and licensing basis documentation was updated to reflect the change.


===.2 a. Permanent Plant Modifications From June 25, 2012 through July 12, 2012, the inspectors reviewed 12 permanent plant modifications that had been installed in the plant during the last three years.===
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 review Inspection Scope 3 Enclosure included in-plant walkdown for a portion of the installed Division 1, 2 and 3 emergency diesel exhaust system and the newly installed Nuclear Steam Supply Protection System inverters 1C71-S001A & 1C71-3001B. 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 twelve permanent plant modification samples as defined in IP 71111.17-04. b. No findings of significance were identified. Findings
 
This inspection constituted 7 samples of evaluations and 22 samples of changes as defined in IP 71111.17-04.
 
b.
 
No findings of significance were identified.
 
Findings
 
===.2 a.===
Permanent Plant Modifications From June 25, 2012 through July 12, 2012, the inspectors reviewed 12 permanent plant modifications that had been installed in the plant during the last three years. This review Inspection Scope included in-plant walkdown for a portion of the installed Division 1, 2 and 3 emergency diesel exhaust system and the newly installed Nuclear Steam Supply Protection System inverters 1C71-S001A & 1C71-3001B. 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 twelve permanent plant modification samples as defined in IP 71111.17-04.
 
b.
 
No findings of significance were identified.
 
Findings


==OTHER ACTIVITIES (OA)==
==OTHER ACTIVITIES (OA)==
{{a|4OA2}}
4OA2
==4OA2 ==
 
===.1 Identification and Resolution of Problems===
===.1 Identification and Resolution of Problems===
a. Routine Review of Condition Reports From June 25, 2012 through July 12 2012, the inspectors reviewed 21 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 pant modifications and evaluations for changes, tests, or experiments issues. 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.
a.
 
Routine Review of Condition Reports From June 25, 2012 through July 12 2012, the inspectors reviewed 21 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 pant modifications and evaluations for changes, tests, or experiments issues. 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.
 
Inspection Scope b.
 
No findings of significance were identified.
 
Findings 4OA6


Inspection Scope b. No findings of significance were identified. Findings 4 Enclosure
===.1 Meetings===
{{a|4OA6}}
On July 12, 2012, the inspectors presented the inspection results to Mr. Noll and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
==4OA6 ==
===.1 Meetings On July 12, 2012, the inspectors presented the inspection results to Mr. Noll and other members of the licensee staff.===
The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.  


=====Exit Meeting Summary=====
===Exit Meeting Summary===
ATTACHMENT:
ATTACHMENT:  


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=


==KEY POINTS OF CONTACT==
==KEY POINTS OF CONTACT==
: [[contact::W. Noll]], Site Vice President Licensee  
: [[contact::W. Noll]], Site Vice President
Licensee  
: [[contact::B. Taber]], Plant Manager  
: [[contact::B. Taber]], Plant Manager  
: [[contact::D. Kemper]], Site Engineering Director  
: [[contact::D. Kemper]], Site Engineering Director  
Line 80: Line 159:
: [[contact::J. Smith]], Sr. Manager Plant Engineering  
: [[contact::J. Smith]], Sr. Manager Plant Engineering  
: [[contact::K. Baker]], Regulatory Assurance Manager  
: [[contact::K. Baker]], Regulatory Assurance Manager  
: [[contact::R. Daley]], Chief, DRS Nuclear Regulatory Commission  
: [[contact::R. Daley]], Chief, DRS
Nuclear Regulatory Commission  
: [[contact::B. Kemker]], Senior Resident Inspector  
: [[contact::B. Kemker]], Senior Resident Inspector  
==LIST OF ITEMS==
==LIST OF ITEMS==
===OPENED, CLOSED AND DISCUSSED===
===OPENED, CLOSED AND DISCUSSED===
NoneOpened, Closed, and
None
===Discussed===


Attachment
===Opened, Closed, and Discussed===
==LIST OF DOCUMENTS REVIEWED==
==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.
: CALCULATIONS Number Description or Title 2011-043 Date or Revision Application of TRACG04P Version 4.2.600.3 for OPM Setpoint Determination at Clinton December 10, 2011 2009-057 Application of TRACG04P for OPRM Setpoint Determination at Clinton Power Station January 8, 2010 01FP14 Effects of Initiation of Fire Suppression Systems on Safe Shutdown Equipment at CPS Revision 1-C
: IP-C-0069 Setpoint Calculation for Turbine Control Valve Fast Closure Scram 1C71-N005 A, B, C, D Revision 02 19-AN-30 ERAT Protective Relay Settings
: Revision 0
: CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED Number Description or Title
: AR 01255411 Date or Revision CPS Review of OE340092- Vital Battery Loss of Capacity August 25, 2011
: AR 01119021 Full Down Limit Switches for F15 and F11 are Unreliable September 28, 2010
: AR 01020200 F 15 Full Down Limit Switch Requires Frequent Adjustment
: January 23, 2010
: AR 00837146 1C71S001C:
: Received MCR Annunciator 5002-5N NSPS INV Trouble
: October 29, 2008
: AR 01010271 Revise 3509.01 and C003 to Remove Fuse Blown Light December 29, 2009
: AR 01128037 Actions for EC379450 (D2) and 381281(D1) Inv. Replacement October 19, 2010
: AR 01283729 Potential Design Problem with NSPS P/S MOD
: EC 383951 October 31, 2011
: AR 01301072 Div 2 NSPS Inverter Test Results did not Meet Acceptance Criteria December 11, 2011
: AR 00837140 1C71S001C:
: Received MCR Annunciator 5002-5N NSPS INV Trouble October 29, 2008
: AR 00936869 Common Configuration Issue with Divisional Inverters June 29, 2009
: AR 01364492 NRC Inspection Identified Loose Lagging DIV 3 DG Exhaust May 8, 2012
: AR00694902 CDBI EDG Exhaust Pressure Calculation Inadequacies November 5, 2007
: AR 00879750 NRC MOD and 50.59 Insp Identified USAR Issue with EDG Exhaust February 12, 2009
: AR 01343910 FASA Review Identified Weakness in 10CFR50.59 Screening Doc March 21, 2012
: AR 01074788 CDBI NRC Inspector Challenges Information in
: IR 1037486 March 28, 2012 
: Attachment CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED Number Description or Title
: AR 01032794 Date or Revision 1DG01KA: 2010 CDBI FASA - DG Fuel Oil Consumption Rate February 19, 2010
: AR 01008883 Possible Problem with C1-R12 IA Mod December 22, 2009
: AR 00122958 Containment Isolation for Instrument Air September 13, 2002
: AR 00970557 Issue with Auto Start of Div 3 Diesel Following Manual Stop September 25, 2009
: AR 01312881
: ENS 47510 Retraction Evaluation
: January 12, 2012
: AR 01299460 DC Ammeter Circuit Deficiency Appendix R Issue December 8, 2011
: CORRECTIVE ACTION PROGRAM DOCUMENTS GENERATED Number Description or Title
: AR 01387682 Date or Revision
: NRC 50.59 Insp:
: USAR Enhancement for EQ Harsh Environment July 11, 2012
: AR 01387980
: NRC 50.59 Insp:
: Observation 50.59 Screening not Stand-Alone
: July 12, 2012
: AR 01382499 NRC ID
: MOD 50.59 No Tracking Mech. In-Place for CALC Update June 27, 2012
: AR 01387197
: NRC 50.59 Insp:
: Coating Loss on External DG Exhaust July 10, 2012
: AR 01387217 Door 1DR1-781 is Missing Some Components July 10, 2012
: AR 01387232 Incorrect Marking On Danger/Caution Sign on Door July 10, 2012
: DRAWINGS Number Description or Title 20-112392 Date or Revision Schematic 7.5 KVA Inverter Alarms 125VDC, Sht. 1 Revision C 20-112391 Schematic 7.5 KVA Inverter 125 Vdc, 120 Vac, Sht. 1 Revision A
: MO6-1035 P&ID Diesel Generator System Piping Clinton Power Station Unit 1 Revision
: Z M0-1056 P&ID Plant Service Water (WS) Revision AR M-1DG06017S DG Shock Assy - Sheet 1 of 2 Revision D M05-1035 Diesel Gen Aux System (DG) Starting Air Exhaust & Combustion Sys; Sheet 1 Revision
: AE M05-1035 Diesel Gen Aux System (DG) Starting Air Exhaust & Combustion Sys; Sheet 2 Revision AB M05-1035 P&ID Diesel Gen Aux Sys (DG) (Starting Air Exhaust & Combustion Sys); Sheet 3
: Revision AB A30-10000-01C Control Building; Intermediate Floor Plan - Area 1 Revision F M05-1054 P&ID Control Building Floor Drain System (TF) Revision E 40075 SX Strainer April 22, 1977 40097 SX Strainer March 11, 1977 38922 SX Strainer December 9, 1976 E02-1IA99 Instrument Air System (IA) Containment IA HDR ISOL Valves
: Revision 0 
: Attachment DRAWINGS Number Description or Title M05-1040, Sheet 5 Date or Revision P&ID Instrument Air Containment Building (IA) Revision S E02-1HP99, Sheet 202 High Pressure Core Spray (HP) Div 3 Diesel Generator
: Revision M E02-1AP12 Relaying and Metering Diagram Emergency Reserve Aux Transformer
: Revision V E02-1RI99 Reactor Core Isolation Cooling System Revision L E02-1RH99 Residual Heat removal Sys RHR/SSW Cross Tie Valves 1E12-F094 and 1E12-F096 Revision H
: 10
: CFR 50.59 EVALUATIONS Number Description or Title
: CL-2011-E-043 Date or Revision Application of TRACG04P Version 4.2.600.3 for OPM Setpoint Determination at Clinton December10, 2011
: CL-2009-E-057 Application of TRACG04P for OPRM Setpoint Determination at Clinton Power Station January 8, 2010
: CL-2009-E-013 Deferral of Division 3 DG Fuel Oil Storage Tank Cleaning to September 2009 and a 25 percent Interval Extension to Reg Guide 1.137 10-Year FOST Cleaning Frequency for All 3 Divisions. Revision 0
: CL-2011-E-002 Defeat Turbine Thrust Bearing Wear Detection Trip Revision 0
: CL-2009-E-030 Defeat Turbine Thrust Bearing Wear Detection Trip Revision 0
: CL-2012-E-002 Open Breaker and Defeat OOS Alarm for 1E12F094-MSO Revision 0
: CL-2010-E-001 CPS Operations with the Potential to Drain the Reactor Vessel (OPDRV) Revision 1
: 10
: CFR 50.59 SCREENINGS Number Description or Title
: CL-2010-S-008 Date or Revision MR90 Type Temp Power Feed Due Date Extension March 8, 2010
: CL-2010-S-037 Revise O.R.M Section 2.6.3 to Delete Testing Requirement 4.6.3.d November 7, 2011
: CL-2011-S-034 TMOD to Bypass Full Down Limit switch in the Refueling Platform November 14,2011
: CL-2010-S-028 Replacement of Safety-Related NSPS Inverters 1C71-S001A and 1C71-S001B November 10, 2010 CL- 2011-S-048 Remote Monitoring System (RMS) January 4, 2012 CL- 2011-S-004 Remove X12 Relay From Division IV Inverter 1C71S001D March 30, 2011 
: Attachment 10
: CFR 50.59 SCREENINGS Number Description or Title
: CL-2010-S-026 Date or Revision Temporary 5VDC Power Supply to Division II Self Test in MCR NSPS Panel 1H13-P662 September
: 8, 2010
: CL-2011-S-038 Revise O.R.M Section 2.6.3 to Delete Testing Requirement 4.6.3.d November 10, 2011
: EC 3771228 Permanent Removal of EDG Outside Exhaust Piping Insulation and Application of High Temperature Coating Revision 0
: EC 3775534 GE14 Fuel Changes Beginning With C1C13 Revision 0
: CL-2010-S-005 Add MCR Air Intake Radiation Indicators to RG 1.97 Table 7.1-13 April 7, 2010
: CL-2009-S-042 RHR Flow Calculation Revision and Tech Spec Bases Change Revision 3
: CL-2010-S-010 Isolate Floor Drain Line in LPCS Pump Room and Revise Flood Plan Accordingly Revision 3
: CL-2009-S-010 Camera Installed in ABST with Power/Feed Cable Running through Containment Shaker Space Revision 2
: CL-2009-S-032 Change to ORM Attachment 2 Table 7 Section 4d page 13 Revision 3
: CL-2010-S-038 Raise Setpoint for 1C71NOOSA-D to Accommodate Drift Revision 3
: CL-2009-S-054 Div 3 DG Auto Start Immediately Following LOOP After Manual Stop Revision 0
: CL-2008-S-022 Add Time Delay Relays and Replace Control Switches to IA System Containment Isolation Valves Logic to Prevent Inadvertent Scram on Momentary Loss of Power to Valve Solenoids Revision 3
: CL-2012-S-004 Installation of Fuses in DC MCC 1A (1DC13E) for the Protection of Circuit for Ammeter 1
: II-DC006 in MCR Panel 1 H13-P877-14B Revision 0
: CL-2011-S-032 Revise Calculation 19-AN-30 and E02-9AP99 to Change the Trip Time Setting for the ERAT Ground Fault Relay that Interfaces with the 138 kV Transmission System Revision 0
: CL-2011-S-042 Add Shorting Switch to Prevent Spurious Opening of 1E51F059-MSO Revision 0
: CL-2009-S-049 Alternate Negative Sequence Time Overcurrent (SGC Model) Relay for Main Generator Revision 0
: MODIFICATIONS Number Description or Title
: EC 373058 Date or Revision Remove Relay X12 from Division III Inverter 1C71S001C Revision 0 
: Attachment MODIFICATIONS Number Description or Title
: EC 379450 Date or Revision Replacement of Safety-Related NSPS Inverter 1C71-3001B Revision 0 2009-018 USAR Update to Clarify Description of Exposed EDG Exhaust Pipe July 20, 2009
: ECN 6674 Delete Rupture Disc Per. Sargent and Lundy Letters
: SLMI-18029 November 13, 1985
: EC 377321 Isolate Floor Drain Line in LPCS Pump Room and Revise the Flood Plan for
: RHR-A Pump Room and the Radwaste Pipe Tunnel Revision 0
: EC 381130 RHR A, B, C System Flow Calculations Revision 0
: EC 373775 Raise Setpoint for 1C71N005A-D to Accommodate Drift Revision 3
: EC 386361 Calculation and Setpoint Change in Support of License Amendment No.196 for DG Fuel Oil Consumption Revision 0
: EC 331623 Add Time Delay Relays and Replace Control Switches to IA System Containment Isolation Valves Logic to Prevent Inadvertent Scram on Momentary Loss of Power to Valve Solenoids Revision 7
: EC 377658 Div 3 DG Auto Start Immediately Following LOOP After Manual Stop Revision 0
: EC 385716 Revise Calculation 19-AN-30 and E02-9AP99 to Change the Trip Time Setting for the ERAT Ground Fault Relay that Interfaces with the 138 kV Transmission System Revision 0
: EC 387302 Installation of Fuses in DC MCC 1A (1DC13E) for the Protection of Circuit for Ammeter 1
: II-DC006  in MCR Panel 1 H13-P877-14B Revision 0
: PROCEDURES Number Description or Title
: CC-AA-112 Date or Revision Temporary Configuration Changes Revision 18
: CC-AA-103 Configuration Change Control for Permanent Physical Plant Changes Revision 23 GD (RS) - 20.00 Design Basis Hierarchy Revision 5
: OTHER DOCUMENTS Number Description or Title
: EC 382424 Date or Revision Clinton Unit 1 Cycle 14 Core Reload Design 1
: Letter from J. Michael Downs, GNF Customer Project Manager, to A. Wlezien, Exelon Nuclear Fuel Services, Subject: 10
: CFR 50.59 Error Correction Revision for TRACG04P and Evaluation Basis for Implementation of
: TRACG04P DIVOM.
: 06/15/2010
: Evaluation Report from GE Hitachi, Subject: TRACGO4P (Version 4.2.60.3) DIVOM 10
: CFR 50.59 Evaluation Basis April 2012 
: Attachment OTHER DOCUMENTS Number Description or Title
: RS-08-103 Date or Revision License Amendment Request to Adopt
: TSTF-2 "Relocate the 10-Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control" September 2, 2008
: BE 417N Basic Engineers "Mechanical Shock Arrestor Extended Unit Assy" September 27, 1976 U-0110 Letter:
: From Clinton Power Station to NRC Harold Denton; Licensing December 1, 1979 U-600595 Letter: From Clinton Power Station to NRC Harold Denton - FSAR Amendment No. 38 May 29, 1986 U-601279 Letter: From Clinton Power Station to NRC - Submittal of the Updated Safety Analysis Report October 6, 1988 U-601144 Letter:
: From Clinton Power Station to NRC RIII RA Bert Davis - Annual Operating Report February 29, 1988
: DC-DG-01-CP Diesel Generator Design Criteria - Clinton Power Station Unit 1 Revision 08
: U-600436 Letter:
: From Clinton Power Station to NRC Harold Denton - FSAR Amendment No. 36 January 27, 1986
: CI-01.00 Instrument Setpoint Calculation Methodology Revision 04
: Group 17 Drift Update r3.xls (Demonstrates As-Found and As-Left) July 10, 2012 K-2878 Proposal Spec 70293-A; Plant Service Water Strainers October 24, 1975 U-602062 Station Blackout (SBO) Safety Evaluation for Clinton Power Station (CPS), Response to the Station Blackout Rule 10CFR50.63, "Loss of All Alternating Current Power" - (Supplemental Response)
: October 30, 1992 U-602081 Clinton Power Station (CPS) - Response to Supplemental Safety Evaluation for the Station Blackout (SBO) Rule,
: 10CFR50.63 December 22, 1992 U-601663 CPS Supplemental Response to the Station Blackout Rule May 11, 1990 U-601427 Clinton Power Station April 16, 1989 Response to the Station Blackout Rule
: 01032794-02 Operability Evaluation - Review of Administrative Controls as Compensatory Actions for EDG Fuel level
: Revision 3
: LER 2011-007-00 Unfused DC Ammeter Circuits Result in Unanalyzed Condition
: December 8, 2011 EC Eval
: 387053 CPS
: ENS 47510 Retraction Evaluation
: Revision 1 
: Attachment
==LIST OF ACRONYMS==
: [[ADAMS]] [[Agencywide Documents Access and Management System]]
: [[CFR]] [[Code of Federal Regulations]]
: [[CNO]] [[Chief Nuclear Officer]]
: [[DRS]] [[Division of Reactor Safety]]
: [[IP]] [[Inspection Procedure]]
: [[IR]] [[Inspection Report]]
: [[MCC]] [[Motor Control Center]]
: [[NEI]] [[Nuclear Energy Institute]]
: [[NRC]] [[U.S. Nuclear Regulatory Commission]]
: [[NUREG]] [[Nuclear Regulation]]
: [[PARS]] [[Public Available Records System]]
: [[ERAT]] [[Emergency Reserve Auxiliary Transformer]]
: [[CPS]] [[Clinton Power Station]]
: [[NSPS]] [[Nuclear Steam Supply Protection System]]
: [[EC]] [[Engineering Change]]
: [[CDBI]] [[Component Design Basis Inspection]]
: [[FASA]] [[Focused Area Self Assessment]]
: [[EDG]] [[Emergency Diesel Generator]]
: [[USAR]] [[Updated Safety Analysis Report]]
: [[EQ]] [[Environmental Qualification]]
: [[ENS]] [[Emergency Notification System]]
: [[DC]] [[Direct Current]]
: [[P&ID]] [[Piping & Instrumentation Diagram]]
: [[CALC]] [[Calculation]]
: [[MOD]] [[Modification]]
: [[SX]] [[Service Water]]
: [[MCR]] [[Main Control Room]]
: [[LOOP]] [[Loss of Offsite Power]]
: [[ORM]] [[Operations Requirement Manual]]
LPCS Low Pressure Core Spray
Mr. Michael
: [[J.]] [[Pacilio Senior Vice-President, Exelon Generation Company,]]
: [[LLC]] [[President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville]]
: [[IL]] [[60555]]
: [[SUBJEC]] [[T: CLINTON]]
: [[POWER]] [[]]
: [[STATIO]] [[N EVALUATIONS]]
: [[OF]] [[]]
: [[CHANGE]] [[S, TESTS,]]
: [[OR]] [[]]
: [[EXPERI]] [[MENTS]]
: [[AND]] [[]]
: [[PERMAN]] [[ENT]]
: [[PLANT]] [[]]
: [[MODIFI]] [[CATIONS BASELINE INSPECTION]]
: [[REPORT]] [[05000461/2012007 Dear Mr. Pacilio: On July 12, 2012, the U.S. Nuclear Regulatory Commission (]]
NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Clinton Power Station. The enclosed inspection report documents the inspection results, which were discussed on July 12, 2012, with you 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. Based on the results of this inspection, no findings of significance were identified. In accordance with
: [[10 CFR]] [[2.390 of the]]
NRC's "Rules of Practice," a copy of this letter and its enclosure 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. 50-461 License Nos.]]
: [[NPF]] [[-62 Enclosure: Inspection Report 05000461/2012007  w/Attachment:  Supplemental Information cc w/encl: Distribution via ListServŽ DISTRIBUTIONSee next page : DOCUMENT NAME:  R:\INSPRPTS\POWERS\CLI\CLIN 2012\CLI 2012]]
: [[007 MOD]] [[50 59]]
: [[MMM.]] [[docx  -Publicly Available  Non-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]] [[MMunir:ls RDaley]]
: [[DATE]] [[08/01/12 08/01/12]]
: [[OFFICI]] [[AL]]
: [[RECORD]] [[]]
: [[COPY]] [[Letter to Mr. Michael Pacilio from Mr. Robert Daley dated August 1, 2012. SUBJECT: CLINTON]]
: [[POWER]] [[]]
: [[STATIO]] [[N EVALUATIONS]]
: [[OF]] [[]]
: [[CHANGE]] [[S, TESTS,]]
: [[OR]] [[]]
: [[EXPERI]] [[MENTS]]
: [[AND]] [[]]
: [[PERMAN]] [[ENT]]
: [[PLANT]] [[]]
: [[MODIFI]] [[CATIONS BASELINE INSPECTION REPORT 05000461/2012007]]
}}
}}

Latest revision as of 23:17, 11 January 2025

IR 05000461-12-007, 06/25/2012 - 07/12/2012, Clinton Power Station; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
ML12214A348
Person / Time
Site: Clinton Constellation icon.png
Issue date: 08/01/2012
From: Robert Daley
Engineering Branch 3
To: Pacilio M
Exelon Generation Co, Exelon Nuclear
Mohammad Munir
References
IR-12-007
Download: ML12214A348 (16)
v • d • e


Text

August 1, 2012

SUBJECT:

CLINTON POWER STATION EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000461/2012007

Dear Mr. Pacilio:

On July 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Clinton Power Station. The enclosed inspection report documents the inspection results, which were discussed on July 12, 2012, with you and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Based on the results of this inspection, no findings of significance were identified.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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. 50-461 License Nos. NPF-62

Enclosure:

Inspection Report 05000461/2012007 w/Attachment: Supplemental Information

REGION III==

Docket No:

50-461 License No:

NPF-62 Report No:

05000461/2012007 Licensee:

Exelon Generation Facility:

Clinton Power Station Location:

Clinton, IL Dates:

June 25 - July 12, 2012 Inspectors:

M. Munir, Reactor Inspector (Lead)

J. Gilliam, Reactor Inspector

L. Jones, Reactor Inspector Approved by:

R. Daley, Chief Engineering Branch 3 Division of Reactor Safety

Enclosure

SUMMARY OF FINDINGS

IR 05000461/2012007; 06/25/2012 - 07/12/2012; Clinton Power Station; Evaluations of

Changes, Tests, or Experiments and Permanent Plant Modifications.

This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. The NRCs 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.

No findings of significance were identified.

NRC-Identified

and Self-Revealed Findings B.

No violations of significance were identified.

Licensee-Identified Violations

1.

REACTOR SAFETY

REPORT DETAILS

Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity

==1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications

==

.1

Main article: IP 71111.17

a.

Evaluation of Changes, Tests, or Experiments From June 25, 2012 through July12, 2012, the inspectors reviewed 7 safety-evaluations performed pursuant to 10 CFR 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 22 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:

Inspection Scope

  • the changes, tests, or 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 or experiment was resolved;
  • the licensee conclusions for evaluations of changes, tests, or 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 7 samples of evaluations and 22 samples of changes as defined in IP 71111.17-04.

b.

No findings of significance were identified.

Findings

.2 a.

Permanent Plant Modifications From June 25, 2012 through July 12, 2012, the inspectors reviewed 12 permanent plant modifications that had been installed in the plant during the last three years. This review Inspection Scope included in-plant walkdown for a portion of the installed Division 1, 2 and 3 emergency diesel exhaust system and the newly installed Nuclear Steam Supply Protection System inverters 1C71-S001A & 1C71-3001B. 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 twelve permanent plant modification samples as defined in IP 71111.17-04.

b.

No findings of significance were identified.

Findings

OTHER ACTIVITIES (OA)

4OA2

.1 Identification and Resolution of Problems

a.

Routine Review of Condition Reports From June 25, 2012 through July 12 2012, the inspectors reviewed 21 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 pant modifications and evaluations for changes, tests, or experiments issues. 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.

Inspection Scope b.

No findings of significance were identified.

Findings 4OA6

.1 Meetings

On July 12, 2012, the inspectors presented the inspection results to Mr. Noll and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.

Exit Meeting Summary

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

W. Noll, Site Vice President

Licensee

B. Taber, Plant Manager
D. Kemper, Site Engineering Director
S. Kowalski, Sr. Manager Design Engineering Manager
J. Smith, Sr. Manager Plant Engineering
K. Baker, Regulatory Assurance Manager
R. Daley, Chief, DRS

Nuclear Regulatory Commission

B. Kemker, Senior Resident Inspector

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

None

Opened, Closed, and Discussed

LIST OF DOCUMENTS REVIEWED

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