IR 05000454/2008005: Difference between revisions

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{{Adams|number = ML090420213}}
{{Adams
| number = ML090510040
| issue date = 02/19/2009
| title = IR 05000454-08-005, 05000455-08-005 on 02/10/2009 for Errate, Byron, Units 1 and 2, Integrated Inspection
| author name = Skokowski R A
| author affiliation = NRC/RGN-III/DRP/B3
| addressee name = Pardee C G
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000454, 05000455
| license number = NPF-037, NPF-066
| contact person =
| document report number = IR-08-005
| document type = Inspection Report, Letter
| page count = 9
}}


{{IR-Nav| site = 05000454 | year = 2008 | report number = 005 }}
{{IR-Nav| site = 05000454 | year = 2008 | report number = 005 }}
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=Text=
=Text=
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[[Issue date::February 10, 2009]]
[[Issue date::February 19, 2009]]


Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555
Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555


SUBJECT: BYRON STATION, UNITS 1 AND 2 INTEGRATED INSPECTION REPORT 05000454/2008-005 05000455/2008-005
SUBJECT: ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2008-005; 5000455/2008-005


==Dear Mr. Pardee:==
==Dear Mr. Pardee:==
On December 31, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Byron Station, Units 1 and 2. The enclosed inspection report documents the inspection findings which were discussed on January 15, 2009, with Mr. D. Hoots 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.
On February 10, 2009, the U.S. Nuclear Regulatory Commission (NRC) issued Integrated Inspection Report 05000454/2008-005, 05000455/2008-005 for your Byron Station. An inspection sample for Post Maintenance Testing and an inspection sample for Emergency Preparedness Drill Observation were inadvertently omitted in the original report.


The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, two NRC-identified findings of very low safety significance were identified. The findings involved violations of NRC requirements. However, because of their very low safety significance, and because the issues were entered into your corrective action program, the NRC is treating the issues as Non-Cited Violations in accordance with Section VI.A.1 of the NRC Enforcement Policy. Furthermore, four licensee identified violations are listed in Section 4OA7 of this report. If you contest the subject or severity of a Non-Cited Violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the Byron Station. In accordance with 10 CFR 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 (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
The enclosed errata contain the omitted inspection samples. Please replace Page 12 of the enclosure, Page 5 and 7 of the Attachment to the enclosure, and insert Page 12(a)
and Page 18(a) of the enclosure where appropriate into the NRC Integrated Inspection Report 05000454/2008-005, 05000455/2008-005 with the enclosed revised pages. We regret any inconvenience this may have caused.


Sincerely,/RA/ Richard A. Skokowski, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


===Enclosure:===
Should you have any questions concerning these errata, we will be pleased to discuss them with you.
Inspection Report No. 05000454/2008-005 and 05000455/2008-005


===w/Attachment:===
Sincerely,/RA/
Supplemental Information cc w/encl: Site Vice President - Byron Station Plant Manager - Byron Station Manager Regulatory Assurance - Byron Station Senior Vice President - Midwest Operations Senior Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director - Licensing and Regulatory Affairs Manager Licensing - Braidwood, Byron, and LaSalle Associate General Counsel Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency J. Klinger, State Liaison Officer, Illinois Emergency Management Agency P. Schmidt, State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station
Richard A. Skokowski, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66


=SUMMARY OF FINDINGS=
February 19, 2009 Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555
-------------------------1


=REPORT DETAILS=
SUBJECT: ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2008-005; 05000455/2008-005
-------------------------.3 Summary of Plant Status -------------------------.3


==REACTOR SAFETY==
==Dear Mr. Pardee:==
....----------------------.3
On February 10, 2009, the U.S. Nuclear Regulatory Commission (NRC) issued Integrated Inspection Report 05000454/2008-005, 05000455/2008-005 for your Byron Station. An inspection sample for Post Maintenance Testing and an inspection sample for Emergency Preparedness Drill Observation were inadvertently omitted in the original report.
{{a|1R01}}
==1R01 Adverse Weather Protection==
{{IP sample|IP=IP 71111.01}}
.....................................................3
{{a|1R04}}
==1R04 Equipment Alignment==
{{IP sample|IP=IP 71111.04}}
................................................................4
{{a|1R05}}
==1R05 Fire Protection==
{{IP sample|IP=IP 71111.05}}
...........................................................................4
{{a|1R06}}
==1R06 Flooding==
{{IP sample|IP=IP 71111.06}}
....----------------------.6
{{a|1R07}}
==1R07 Annual Heat Sink Performance==
{{IP sample|IP=IP 71111.07}}
.................................................6
{{a|1R11}}
==1R11 Licensed Operator Requalification Program==
{{IP sample|IP=IP 71111.11}}
.............................7
{{a|1R12}}
==1R12 Maintenance Effectiveness==
{{IP sample|IP=IP 71111.12}}
.......................................................8
{{a|1R13}}
==1R13 Maintenance Risk Assessments and Emergent Work Control==
{{IP sample|IP=IP 71111.13}}
..9
{{a|1R15}}
==1R15 Operability Evaluations==
{{IP sample|IP=IP 71111.15}}
...........................................................10
{{a|1R18}}
==1R18 Plant Modifications==
{{IP sample|IP=IP 71111.18}}
..................................................................11
{{a|1R19}}
==1R19 Post-Maintenance Testing==
{{IP sample|IP=IP 71111.19}}
......................................................12
{{a|1R20}}
==1R20 Outage Activities==
{{IP sample|IP=IP 71111.20}}
.....................................................................13
{{a|1R22}}
==1R22 Surveillance Testing==
{{IP sample|IP=IP 71111.22}}
................................................................15
{{a|1EP6}}
==1EP6 Drill Evaluation==
{{IP sample|IP=IP 71114.06}}
........................................................................18 2. Radiation SAFETY......---------------------..19 2OS1 Access Control to Radiologically Significant Areas (71121.01).................19 2OS2 As-Low-As-Reasonably-Achievable Planning and Controls (71121.02)...22
{{a|4OA1}}
==4OA1 Performance Indicator Verification==
{{IP sample|IP=IP 71151}}
...............................................23
{{a|4OA2}}
==4OA2 Identification and Resolution of Problems==
{{IP sample|IP=IP 71152}}
....................................28
{{a|4OA5}}
==4OA5 Other Activities -------------------------30 4OA6==
Management Meetings---------------------..32 4OA7 Licensee-Identified Violations....................................................................33


=SUPPLEMENTAL INFORMATION=
The enclosed errata contain the omitted inspection samples. Please replace Page 12 of the enclosure, Page 5 and 7 of the Attachment to the enclosure, and insert Page 12(a) and Page 18(a) of the enclosure where appropriate into the NRC Integrated Inspection Report 05000454/2008-005, 05000455/2008-005 with the enclosed revised pages. We regret any inconvenience this may have caused.


==KEY POINTS OF CONTACT==
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Licensee
: [[contact::D. Hoots]], Site Vice President
: [[contact::W. Grundmann]], Regulatory Assurance Manager
: [[contact::Z. Cox]], Chemist
: [[contact::G. Contrady]], Programs Manager
: [[contact::H. Do]], Corporate ISI Engineer
: [[contact::S. Greenlee]], Engineering Director
: [[contact::D. Thompson]], Radiation Protection Manager
Nuclear Regulatory Commission 
: [[contact::R. Skokowski]], Branch Chief 
==LIST OF ITEMS==
OPENED, CLOSED AND DISCUSSED
===Opened===
: 05000454/2008005-01
: 05000455/2008005-01 NCV Failure to Remove or Evaluate Loose Debris Inside of Containment Prior to Applicable Mode
: 05000454/2008005-02
: 05000455/2008005-02  NCV Failure to Evaluate Radiological Hazards for Airborne Radioactivity 


===Closed===
Should you have any questions concerning these errata, we will be pleased to discuss them with you.
: 05000454/2008005-01
: [[Closes finding::05000455/FIN-2008005-01]] NCV Failure to Remove or Evaluate Loose Debris Inside of Containment Prior to Applicable Mode
: 05000454/2008005-02
: [[Closes finding::05000455/FIN-2008005-02]] NCV Failure to Evaluate Radiological Hazards for Airborne Radioactivity
: 05000454;
: 455/2008-003-06 URI Unit 1 and Unit 2 Auxiliary Feedwater Tunnel Hatch Margin to Safety
: 2
==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.


==Section 1R01: Adverse Weather Protection==
Sincerely,/RA/ Richard A. Skokowski, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
: WO 1020141 01; 89-13 Heat Exchanger Inspection for 2B Diesel Driven AF Pump Closed Cycle Cooler, October 16, 2008 Issue
: 846625; Procedure Enhancement, November 18, 2008 BOP
: SX-T2; SX Tower Operations Guidelines, Revision 12
 
==Section 1R04: Equipment Alignment (Quarterly) 2BOSR 7.8.1-1; Unit 2 Essential Service Water System Valve Position Monthly Surveillance, Revision 16==
: BOP
: DG-1; Diesel Generator Alignment to Standby Condition, Revision 11
: BOP
: VD-5; DG Room Ventilation System Operation, Revision 6
: BwOP
: VD-5; DG Room Ventilation System operation, Revision 12
: BwOS
: VD-1a; Diesel Ventilation Systems; Revision 4 10
: CFR 50.59 Screening, BOP Vd-5 DG Room Ventilation System Operation; January 06, 1986 
: Corrective Action Documents as a Result of NRC Inspection
: IR 852537; Compensatory Actions Not Procedurally Directed, December 4, 2008
 
==Section 1R05: Fire Protection (Quarterly) Corrective Action Documents as a Result of==
: NRC Inspection
: IR 842026; Fire Zone Walkdown Issues, November 07, 2008
: IR 850920; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
: IR 850922; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
: IR 850925; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
: IR 850926; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
: IR 850929; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
: IR 850931; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
: IR 850932; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
: IR 842026; Fire Zone Walkdown Issues, November 07, 2008
: IR 847572; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
 
==Section 1R05: Fire Protection (Annual)==
: BAP 1100-10; Response Procedure for Fire, Revision 7
: BAP 1100-10T1; 401' Fire Brigade Equipment Inventory, Revision 7
: Byron Emergency Self-Contained Breathing Apparatus Storage Locations Monthly Inventory, September 2008
: OP-AA-201-003; Fire Drill Performance, Revision 7 
: 3OP-AA-201-005; Fire Brigade Qualification, Revision 6
: OP-AA-201-008; Pre-Fire Plans, Revision 1
: RP-BY-1000; Maintenance Care and Inspection of the ISI Viking Self-Contained Breathing Apparatus (SCBA), Revision 9 Self-Contained Breathing Apparatus Monthly Inspection, September 2008
: Byron Station Fire Drill Critique Form, August 24, 2008
: Summary Report for Each Shift Reflecting Fire Brigade and HazMat Qualification Status, October 12, 2008
: IR 823253; Safe-Guards Information Slows Fire Response, September 27, 2008
 
==Section 1R07: Heat Sink Performance==
: WO 1036955; Perform As-Found/As-Left Inspections of 2C RCFC Issue
: 830146; Replace RCFC Channel Heads with stainless Steel in B2R15, October 13, 2008
: IR 830370; Restricted Tubes in 2C RCFC, Need to Plug, October 13, 2008
: IR 829315; 2C RCFC Channel Head Degradation, Divider Plates, October 10, 2008
 
==Section 1R08: Inservice Inspection Activities==
: IR 829647; Penetration 41 Not Examined During B2R13; October 11, 2008
: IR 831084; Foreign Objects Found In 2C SG Secondary Side - B2R14; October 15, 2008
: IR 829610; Acceptance Criteria Used On SX Pipe Was Not Appropriate; October 11, 2008
: IR 843635, Steam Generator Tube Sheet Inspection Results - B2R14, November 11, 2008
: IR 832181; Foreign Objects Found In 2A SG Secondary - B2R14; dated October 17, 2008
: IR 830452; B2R14 - Weld Defects Revealed During Radiography Of Repair;
: October 14, 2008
: IT00717275-02; Buildup of Deposits in Steam Generators, NRC
: IN 2007-37
: ER-AP-335-1012; Bare Metal Visual Examination of PWR Vessel Penetration and Nozzle Safe-Ends; Revision 3
: ER-AP-335-040; Evaluation of Eddy Current Data for Steam Generator Tubing; Revision 4
: EXE-ISI-11; Liquid Penetrant Examination, Revision 4
: EXE-UT-350; Procedure for Acquiring Material Thickness and Weld Contours; Revision 2
: EXE-PDI-UT-2; Ultrasonic Examination of Austenitic Piping Welds in Accordance with
: PDI-UT-2; Revision 5
: EXAE-ISI-8;
: VT-1 Direct; Revision 1
: ER-AP-335-039; Multi-Frequency Eddy Current Data Acquisition of Steam Generator Tubing;
: Revision 5
: ER-MW-335-1009; Site Specific Performance; Revision 4
: ER-AP-331; Boric Acid Corrosion Control (BACC) Program; Revision 3
: ER-AP-331-1001; Boric Acid Corrosion control (BACC) Inspection Locations, Implementation and Inspection Guidelines; Revision 3
: ER-AP-331-1002; Boric Acid Corrosion control Program Identification, Screening, and Evaluation; Revision 4
: ER-AP-331-1004; Boric Acid Corrosion Control (BACC) Training and Qualification, Revision 2
: ER-AP-420-002; Byron/Braidwood Unit 2:
: Steam Generator Eddy Current Activities; Revision 8


==Section 1R11: Licensed Operator Requalification Program==
DOCUMENT NAME: G:\Byron\BYR 2008-005 Errata.doc X Publicly Available G Non-Publicly Available G Sensitive X 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 RNg:dtp RSkokowski
: Six Reactor Operator Biennial Written Examinations for
: CY 2008; no dates Thirty Senior Reactor Operator Examination Questions for
: CY 2008 Exams; no dates Twelve Dynamic Simulator Scenarios; no dates
: 448 Job Performance Measures; no dates Licensed Operator Written Examination and Operating Test Results,
: CY 2008; no date


==Section 1R12: Maintenance Effectiveness==
DATE 02/19/09 02/19/09 OFFICIAL RECORD COPY Letter to from R. Skokowski dated February 19, 2009
: IR 417274; Hydramotor Indication Shows Open but Damper Blades are Closed, March 11, 2002
: IR 460411; VA Supply/Exhaust Fan Vibration Alarm Setpoint Basis Concern
: IR 717005;
: VA-Tolerance for Equipment Degradation, January 1, 2008
: IR 726481; High Vibrations on 0C VA Fan (Supply Fan), January 24, 2008
: IR 727128; VA Issues, January 26, 2008
: IR 735812; VA Concerns, February 13, 2001
: IR 748406; Need (A)(1) Determination: VA Unacceptable Performance Trend, March 12, 2008
: IR 850742; Control Damper Problems for 1A DG Ventilation, December 01, 2008
: IR 869580; MM Expanded Scope Replace Linear Converter, January 23, 2007
: IR 999934; Replace Linear Converter, November 07, 2008
: WO 99270872; 1A DG Vent Outside Damp Not Fully Closed, September 13, 2008 VA Degradation/Status Presentations to the Plant Health Committee, December 10, 2007, February 4, 2008, and May 5, 2008


==Section 1R13: Maintenance Risk Assessments and Emergent Work Control==
SUBJECT: ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2008-005; 05000455/2008-005 cc w/encl: Site Vice President - Byron Station Plant Manager - Byron Station Manager Regulatory Assurance - Byron Station Senior Vice President - Midwest Operations Senior Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director - Licensing and Regulatory Affairs Manager Licensing - Braidwood, Byron, and LaSalle Associate General Counsel Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency J. Klinger, State Liaison Officer, Illinois Emergency Management Agency P. Schmidt, State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station
: Unit 1 Risk Configurations; Week of October 13, 2008, Revision 3 Unit 2 Risk Configurations; Week of November 17, 2008
: Protected Equipment Log for 2B DG Outage, October 11, 2008
: Protected Equipment Log for Line 0622/Bus 12 Outage, October 12, 2008  
: Protected Equipment Log for Unit 0 Component Cooling Water Heat Exchanger, October 11, 2008 Protected Equipment Log for Unit 2 CC Heat Exchanger, November 16, 2008 Protected Equipment Log for 2RA RH Pump Suction OOS, November 17, 2008
: B2R14 Shutdown Risk Evaluation; October 15, 2008  
: B2R14 Outage Status, October 16, 2008
: Byron Operations Log; October 15, 2008, to October 16, 2008
: OU-AP-104; Shutdown Safety Management Program Byron/Braidwood Annex, Revision 11
: IR 832167; NOS Identified OPS Lacks Sensitivity to OLR/SDR, October 17, 2008
: Unit 0/1/2 Standing Order; Operator Ownership During IMD Surveillances, October 17, 2008
: IR 829481; NOS ID Shutdown Risk Vulnerability, October 10, 2008


==Section 1R15: Operability Evaluations==
Letter to from R. Skokowski dated February 19, 2009
: IR 810117; Unit 1 LM Indicates Potential Source of Noise as Near 1RC8002D, August 22, 2008
: IR 810867; Expansion Tank Overflow When Started and Running, August 26, 2008
: IR 814019; Low JW Level in the 1B AF Pump, September 04, 2008
: IR 846398; Need Work Order Created to Replace Grease, November 18, 2008
: IR 846420; 2SI8811A; Motor Found Degraded Per Inspection Criteria, November 18, 2008
: EC 366163; Operations Evaluation 07-005, Unventable Gas Voids in Containment Recirculation Sump Piping, November 20, 2008
: EC 371879; Operations Evaluation 08-007, Gas Void at 2CS009A, November 20, 2008
: EC 371965; Operations Evaluation 08-008, 2B AF Pump Jacket Water Overflow, Revision 000
: EC 373393; Operations Evaluation 08-010, 1B DG Cylinder and Head Indications, December 18, 2008 Fluid Analysis Report; Unit 2 AF Cooler, September 24, 2008 
: 5Operational and Technical Decision Making 2008 - 2009; Suspect 1RC8002D Valve guide(s) Not Properly Retained in Valve Body Adverse Condition Monitoring and Contingency Plan; Unit 1 Loose Parts Monitoring System (LPMS) Noise, August 26, 2008
: CAE-02-31 Westinghouse Letter; LSIV Loose Parts 50.59 Screen
: EVAL-02-062, Revision 1, March 21, 2002
: WO 1072112 02; MOV PM, Actuator Inspection, Diagnostic testing, November 18, 2008


==Section 1R18: Plant Modifications==
SUBJECT: ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2008-005; 05000455/2008-005 DISTRIBUTION:
: IR 842362; 2CV181 "2A RCP Standpipe PW Supply Valve" Failed to Close, November 08, 2008
Tamara Bloomer RidsNrrDorlLpl3-2 RidsNrrPMByron Resource RidsNrrDirsIrib Resource Mark Satorius Kenneth OBrien Jared Heck Allan Barker Carole Ariano Linda Linn Cynthia Pederson DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports@nrc.gov
: IR 843783; Unexpected Alarm, November 12, 2008
: IR 846404; Revised Bars for
: TCP 373002 are Incorrect, November 18, 2008
: EC 373002; Installation of Temporary Line to Connect the Drain Lines of RCP Standpipes 2A
and 2D, Revision 0
: EC 371360; Install Vent Valve on 2SI05CA-8, Revision 2
: EC 373224; Provide Temporary Fans for 1A DG Room, Revision 0
: WO 01149077; Install Vent Valve on 2SI05CA-8, October 18, 2008
: WO 01149077 13; SEP PMT:
: VT-2 of 2SI130, October 15, 2008
: WO 01149077 14; OP PMT: Verify No Seat leakage on 2SI130, October 15, 2008
: WO 01149077 15; SEP PMT: Record Vibe Data 2SI130 at Full Flow Conditions, October 15, 2008


==Section 1R19: Post Maintenance Testing==
12 Enclosure This inspection constituted one permanent plant modification sample as defined in IP 71111.18-05. a. Findings No findings of significance were identified. 1R19 Post-Maintenance Testing (71111.19) a. Inspection Scope The inspectors reviewed the following post-maintenance (PM) activities to verify that procedures and test activities were adequate to ensure system operability and functional capability:
: 1BOSR 3.2.8-610B; Unit 1 ESFAS Instrumentation Slave Relay Surveillance and Automatic Actuation Test (Train B Automatic Safety Injection - K610), Revision 2 2BOSR 7.5.5-2; Unit 2 Train B Auxiliary Feedwater Valve Emergency Actuation Signal Verification Test, Revision 4
* Unit 2 Safety Injection System Accumulator Injection Check Valve 2SI8818C Repair; * Unit 2 Charging/Safety Injection System Flow Balance following Outage Maintenance;  
: WO 999110; 1AP12E-A Relay #1-RCF2 for 1VP01CB Operations PMT Partial 1BOSR 3.2.8-
* Unit 1 Train B Charging Pump Return to Service Following Maintenance;  
: 610B, November 25, 2008 2BOSR 3.2.8-632A; ESFAS Instrumentation Slave Relay Surveillance (Train A Auxiliary Feedwater Actuation - Relays k632, K639, Revision 2
* Unit 2 Train B Auxiliary Feedwater Valve Emergency Actuation Signal Verification Test;
: WO 1165207 01;
* Work Order (WO) 1171264, Operate Diesel Generator 2A in Local Following Switch Repair;  
: MM-Repair of 2SI8818C During B2R14
* Barring Over of Unit 1 Train B Diesel Generator to Look for Moisture in the Cylinders Following the Identification of an Indication in Two Cylinders;
: WO 1165207 04; EP - Perform Visual Examination of Disassembled Check Valve
* WO 00999110, Unit 1 Train B RCFC Following Breaker Maintenance; and
: WO 1165207 06; Operations PMT - 2SI8818C SLT Per 2BOSR 4.14.1-1
* Relay Actuation Surveillance 2BOSR 3.2.8-632A to Test Valve 2AF004A. These activities were selected based upon the structure, system, or component's ability to impact risk. The inspectors evaluated these activities for the following (as applicable): the effect of testing on the plant had been adequately addressed; testing was adequate for the maintenance performed; acceptance criteria were clear and demonstrated operational readiness; test instrumentation was appropriate; tests were performed as written in accordance with properly reviewed and approved procedures; equipment was returned to its operational status following testing (temporary modifications or jumpers required for test performance were properly removed after test completion), and test documentation was properly evaluated. The inspectors evaluated the activities against TS, the UFSAR, 10 CFR Part 50 requirements, licensee procedures, and various NRC generic communications to ensure that the test results adequately ensured that the equipment met the licensing basis and design requirements. In addition, the inspectors reviewed corrective action documents associated with post-maintenance tests to determine whether the licensee was identifying problems and entering them in the CAP and that the problems were being corrected commensurate with their importance to safety. Documents reviewed are listed in the Attachment to this report. This inspection constituted seven post-maintenance testing samples as defined in IP 71111.19-05.
: WO 1165207 07; Operations PMT - 2SI8818C CO Per 2BOSR 5.5.8RH.2-2
: WO 1020023 01; 2RH25
: VT-2 Exam, October 15, 2008 ASME Section XI Repair/Replacement Plan; 2SI8818C (Loop 3 Cold Leg Accumulation Injection Check Valve, September 29, 2008
: BOP
: CV-19; Switching Charging Pumps, Revision 14
: 1BOSR 5.5.1-1; Unit 1 RCS Seal Injection Flow Verification Monthly Surveillance, Revision 4 2BVSR 5.c.2-1; Unit 2 Charging/Safety Injection System Flow Balance, Revision 4


==Section 1R20: Refueling and Outage Activities Ultrasonic Thickness Calibration Data Sheet; Report Number 2008-707==
12(a) Enclosure b. Findings No findings of significance were identified.
: IR 826879; Calibrate/Repair 2FI-0928A, October 05, 2008
: IR 834405; Need B2R15 W/O to Retrieve Rag and Wire From Upender Pit B2R14 Work Orders Added to Date, October 15, 2008 
: 6List of Work Orders Removed from B2R14 via SCARF Process as of 7:00 am on October 16, 2008
: 1BGP 100-2; Plant Startup, Revision 37 1BGP 100-2A1; Reactor Startup, Revision 26 1BGP 100-2TI; Plant Startup Flowchart, Revision 10
: 1BGP 100-2T3; Reactor Startup Flowchart, Revision 5
: 1BGP 100-4; Power Descension, Revision 36
: 1BGP 100-4T1; Power Descension Flowchart, Revision 11
: 1BGP 100-5; Plant Shutdown and Cooldown, Revision 53 1BGP 100-5TI; Plant Shutdown and Cooldown Flowchart, Revision 26 BOP
: RH-6; Operation of the RH System in Shutdown Cooling, Revision 36
: BOP
: RH-8; Filling the Refueling Cavity for Refueling, Revision 18
: BOP
: RH-9; Pump Down of the Refueling Cavity to the RWST, Revision 24
: ALM Corporation Material Handling Platform Lift Manual
: BAP 1450-1; Access to Containment, Revision 37 2BOSR Z.5.B.1-1; Containment Loose Debris Inspection, Revision 0
: Issue
: 834555; B2R14 Reactor Cavity Hoist Cable Ties, October 22, 2008
: LS-AA-125; Corrective Action Program Procedure, Revision 12
: IR 833539; White Plastic Cable Tie Not Immediately Retrievable, October 20, 2008
: IR 834002; Foreign Material in 2B ECCS Recirculation Sump, October 21,2008
: IR 834087; Loose Debris Walkdown Items Requiring Disposition, October 21, 2008
: IR 835427; B2R14 LL - Weakness in Control of Material Left in Containment, October 23, 2008
: EC 372856; Evaluation of Foreign Material in Unit 2 Containment Building, November 12, 2008
: Corrective Action Documents as a Result of NRC Inspection
: IR 833612; Inactive Boric Acid Leak on 2SI8822C, October 20, 2008
: IR 833613; Inactive Boric Acid Leak on 2SI8810C, October 20, 2008
: IR 833881; Inactive Boric Acid Leak, System Not Verified At This Time, October 21, 2008
: IR 834410; B2R14 NRC Mode 3 Containment Walkdown Identified Items, October 22, 2008
: IR 856813; Operator Missing a Cover During Mode 4 Walkdown, December 16, 2008
: IR 856819; 2LL091E Trickle Charge Light Is Out, December 16, 2008
: IR 834410; B2R14 NRC Mode 3 Containment Walkdown Identified Items, October 22, 2008


==Section 1R22: Surveillance Testing 1BOSR 6.1.1-11; Primary Containment Type C Local Leakage Rate Tests and==
18(a) Enclosure
: IST Tests of Pressurizer Relief System "Partial for 1RY8028", Revision 7 2BOSR 7.5.4-2; Unit 2 Diesel Driven Auxiliary Feedwater Pump Monthly Surveillance, Revision 16
.2 Emergency Preparedness Medical/Health Physics Drill Observation a. Inspection Scope The inspectors evaluated the conduct of a routine licensee emergency drill on June 3, 2008, to identify any weaknesses and deficiencies in classification, notification, and protective action recommendation development activities. The inspectors observed emergency response operations during the Annual Medical/Health Physics Drill to determine whether the event classification, notifications, and protective action recommendations were performed in accordance with procedures. The inspectors also attended the licensee drill critique to compare any inspector-observed weakness with those identified by the licensee staff in order to evaluate the critique and to verify whether the licensee staff was properly identifying weaknesses and entering them into the corrective action program. As part of the inspection, the inspectors reviewed the drill package and other documents listed in the Attachment to this report. This emergency preparedness drill inspection constituted one sample as defined in IP 71114.06-05. b. Findings No findings of significance were identified.
: 2BOSR 7.5.5-2; Unit 2 Train B Auxiliary Feedwater Valve Verification Test, Revision 4
: 2BOSR 8.1.2-1; Unit 2 A Diesel Generator Operability Surveillance, Revision 21
: 2BVSR 5.c.2-1; Unit 2 Charging/Safety Injection System Flow Balance, Revision 4
: WO 1024422 01; 2B Diesel Generator SI Signal Override Test, October 14, 2008
: WO 1028733 01; Reactor Coolant System CheckValve Leakage Surveillance, October 21, 2008
: WO 1157684 01; 1CV01PB Group A IST Requirement for CV Pump, November 06, 2008
: Byron Inservice Testing Bases Document; Valve EPN 2SI8818A-D, Loop A-D Cold Leg Accumulator Injection Check Valve Byron Inservice Testing Bases Document; Valve EPN 2SI8948A, Accumulator Outlet to RC Loop Second Check Valve 
: 7BOP
: DG-11; Diesel Generator Startup, Revision 20 BOP
: DG-12; Diesel Generator Shutdown, Revision 19
: Corrective Action Documents as a Result of NRC Inspection
: IR 841953; IST Basis Documents for 1/2SI8818A-D Need Updating, November 06, 2008
: IR 841953; IST Basis Documents for 1/2SI8818A-D Need Updating, November 07, 2008


==Section 2OS1: Access Control to Radiologically Significant Areas==
5 Attachment Operational and Technical Decision Making 2008 - 2009; Suspect 1RC8002D Valve guide(s) Not Properly Retained in Valve Body Adverse Condition Monitoring and Contingency Plan; Unit 1 Loose Parts Monitoring System (LPMS) Noise, August 26, 2008 CAE-02-31 Westinghouse Letter; LSIV Loose Parts 50.59 Screen EVAL-02-062, Revision 1, March 21, 2002 WO 1072112 02; MOV PM, Actuator Inspection, Diagnostic testing, November 18, 2008 Section 1R18: Plant Modifications IR 842362; 2CV181 "2A RCP Standpipe PW Supply Valve" Failed to Close, November 08, 2008 IR 843783; Unexpected Alarm, November 12, 2008 IR 846404; Revised Bars for TCP 373002 are Incorrect, November 18, 2008 EC 373002; Installation of Temporary Line to Connect the Drain Lines of RCP Standpipes 2A and 2D, Revision 0 EC 371360; Install Vent Valve on 2SI05CA-8, Revision 2 EC 373224; Provide Temporary Fans for 1A DG Room, Revision 0 WO 01149077; Install Vent Valve on 2SI05CA-8, October 18, 2008 WO 01149077 13; SEP PMT: VT-2 of 2SI130, October 15, 2008 WO 01149077 14; OP PMT: Verify No Seat leakage on 2SI130, October 15, 2008 WO 01149077 15; SEP PMT: Record Vibe Data 2SI130 at Full Flow Conditions, October 15, 2008  
: RP-AA-460; Controls for High Radiation and Locked High Radiation Areas; Revision 17
: RP-AA-460-001; Controls for Very High Radiation Areas; Revision 1
: RP-AA-460; Access to Reactor Incore Sump Area; Revision 2
: RP-
: BY-500-1003; Radiological Controls for Handling Items and Hanging Activated Parts in the Spent Fuel Pool Radiation Work Permit and Associated ALARA Reviews;
: RWP 10008926; B2R14 Seal Table - Rack Disconnect/Maintenance/Eddy Current/Restoration Radiation Work Permit and Associated ALARA Reviews;
: RWP 10009830; P-68 Penetrant Test and Vent Line Inspection
: IR 795311; RWP Violations (PC Requirements); dated July 10, 2008
: IR 761294; Level 1 Personal Contamination Event; dated 9, 2008
: IR 756342; Worker Entered A/D Platform without Electronic Dosimeter; dated March 29, 2008
: IR 754696; Worker Locked Out of RCA - Rad Worker Behavior; dated March 26, 2008
: IR 756136; PCE: B1R15 Personal Contamination Event; dated March 28, 2008
: IR 673712; RP Not Effectively Using Corrective Action Program; dated September 20, 2007
: IR 755986; Alpha Survey Documentation Gaps; dated March 27, 2008
: IR 756296;
: RP-AA-460-1001; Not Completed in Timely Manner; dated March 28, 2008
: IR 812338; Ni-63 Source Leak Tests Exceed 6-Month Surveillance Frequency; dated August 22, 2008


==Section 1EP6: Drill Evaluation==
Section 1R19: Post Maintenance Testing
: IR 844467; OSC Minimum Staffing Not Met for Crew D in Drill, November 13, 2008 Byron 2008 Drive-In Drill; Scenario Information Nuclear Accident Reporting System (NARS) Form; Utility Message No. 2, November 12, 2008
: Issue
: 844467; OSC Minimum Staffing Not Met for During Drill, November 12, 2008


==Section 4OA1: Performance Indicator Verification==
1BOSR 3.2.8-610B; Unit 1 ESFAS Instrumentation Slave Relay Surveillance and Automatic Actuation Test (Train B Automatic Safety Injection - K610), Revision 2 2BOSR 7.5.5-2; Unit 2 Train B Auxiliary Feedwater Valve Emergency Actuation Signal Verification Test, Revision 4 WO 999110; 1AP12E-A Relay #1-RCF2 for 1VP01CB Operations PMT Partial 1BOSR 3.2.8-610B, November 25, 2008 2BOSR 3.2.8-632A; ESFAS Instrumentation Slave Relay Surveillance (Train A Auxiliary Feedwater Actuation - Relays k632, K639, Revision 2 WO 1165207 01; MM-Repair of 2SI8818C During B2R14 WO 1165207 04; EP - Perform Visual Examination of Disassembled Check Valve WO 1165207 06; Operations PMT - 2SI8818C SLT Per 2BOSR 4.14.1-1 WO 1165207 07; Operations PMT - 2SI8818C CO Per 2BOSR 5.5.8RH.2-2 WO 1020023 01; 2RH25 VT-2 Exam, October 15, 2008 WO 1192590; Bar Over Diesel Generator to check for Moisture ASME Section XI Repair/Replacement Plan; 2SI8818C (Loop 3 Cold Leg Accumulation Injection Check Valve, September 29, 2008 BOP CV-19; Switching Charging Pumps, Revision 14 1BOSR 5.5.1-1; Unit 1 RCS Seal Injection Flow Verification Monthly Surveillance, Revision 4 2BVSR 5.c.2-1; Unit 2 Charging/Safety Injection System Flow Balance, Revision 4 Section 1R20: Refueling and Outage Activities Ultrasonic Thickness Calibration Data Sheet; Report Number 2008-707 IR 826879; Calibrate/Repair 2FI-0928A, October 05, 2008 IR 834405; Need B2R15 W/O to Retrieve Rag and Wire From Upender Pit B2R14 Work Orders Added to Date, October 15, 2008 7 Attachment BOP DG-11; Diesel Generator Startup, Revision 20 BOP DG-12; Diesel Generator Shutdown, Revision 19 Corrective Action Documents as a Result of NRC Inspection IR 841953; IST Basis Documents for 1/2SI8818A-D Need Updating, November 06, 2008 IR 841953; IST Basis Documents for 1/2SI8818A-D Need Updating, November 07, 2008  
: LS-AA-2090; Monthly Data Elements for NRC Reactor Coolant System (RCS) Specific Activity; dated July 3, 2007 through September 2, 2008
: LS-AA-2100; Monthly Data Elements for NRC Reactor Coolant System Leakage, Revision 5
: LS-AA-2150; Monthly Data Elements for RETS/ODCM Radiological Effluent Occurrences; dated July 10, 2007 through September 10, 2008  
: MSPI Derivation Report; Unit 1 and Unit 2 High Pressure Injection System Unavailability and Unreliability Index, February 2008 Operations Log; February 01, 2008 - February 29, 2008
: MSPI Derivation Report; Unit 1 and Unit 2 Cooling Water System Unavailability and Unreliability Index, March 2008
: IR 854124; Inconsequential Error identified in March 2008 MSPI Data for SX, December 09, 2008
: 8Operations Log; March 01, 2008 - March 31, 2008 MSPI Derivation Report; Unit 1 and Unit 2 Residual Heat Removal System Unavailability and Unreliability Index, July 2008 Operations Log; July 01, 2008 - July 31, 2008 MSPI Derivation Report; Unit 1 and Heat Removal System Unavailability and Unreliability Index, October 2007
: Operations Log; October 01, 2007 - October 31, 2007
: MSPI Derivation Report; Unit 1 and Unit 2 Heat Removal System Unavailability and Unreliability Index, April 2008 Operations Log; March 01, 2008 - March 31, 2008 Operations Log; October 01, 2007 - October 31, 2007
: MSPI Derivation Report; Unit 1 and Unit 2 Emergency AC Power System Unavailability and Unreliability Index, June 2008
: Operations Log, June 01, 2008 - June 30, 2008


==Section 4OA2: Identification and Resolution of Problems==
Section 2OS1: Access Control to Radiologically Significant Areas RP-AA-460; Controls for High Radiation and Locked High Radiation Areas; Revision 17 RP-AA-460-001; Controls for Very High Radiation Areas; Revision 1 RP-AA-460; Access to Reactor Incore Sump Area; Revision 2 RP- BY-500-1003; Radiological Controls for Handling Items and Hanging Activated Parts in the Spent Fuel Pool Radiation Work Permit and Associated ALARA Reviews; RWP 10008926; B2R14 Seal Table - Rack Disconnect/Maintenance/Eddy Current/Restoration Radiation Work Permit and Associated ALARA Reviews; RWP 10009830; P-68 Penetrant Test and Vent Line Inspection IR 795311; RWP Violations (PC Requirements); dated July 10, 2008 IR 761294; Level 1 Personal Contamination Event; dated 9, 2008 IR 756342; Worker Entered A/D Platform without Electronic Dosimeter; dated March 29, 2008 IR 754696; Worker Locked Out of RCA - Rad Worker Behavior; dated March 26, 2008 IR 756136; PCE: B1R15 Personal Contamination Event; dated March 28, 2008 IR 673712; RP Not Effectively Using Corrective Action Program; dated September 20, 2007 IR 755986; Alpha Survey Documentation Gaps; dated March 27, 2008 IR 756296; RP-AA-460-1001; Not Completed in Timely Manner; dated March 28, 2008 IR 812338; Ni-63 Source Leak Tests Exceed 6-Month Surveillance Frequency; dated August 22, 2008 Section 1EP6: Drill Evaluation IR 844467; OSC Minimum Staffing Not Met for Crew D in Drill, November 13, 2008 Byron 2008 Drive-In Drill; Scenario Information Nuclear Accident Reporting System (NARS) Form; Utility Message No. 2, November 12, 2008 IR 844467; OSC Minimum Staffing Not Met for During Drill, November 12, 2008 Cycle 08-4 Out of the Box Evaluation, 08-4-1, Revision 0.
: IR 642107; IST Program Implementation, June 19, 2007
: IR 678543; Possible Pre-Conditioning Issue - IST Testing, October 1, 2007
: IR 686518; Byron Review of Braidwood Potential Pre-Conditioning Issue, October 18, 2007
: ER-AA-302-1006; Generic Letter 96-05 Program Motor-Operated Valve Maintenance and Testing Guidelines, Revision 7


==Section 4OA5: Other Activities 1BOSR 8.1.14-1; Unit 1A Diesel Generator 24 Hour Endurance Run, Revision 10 1BOSR 8.1.14-2; Unit 1B Diesel Generator 24 Hour Endurance Run, Revision 8 2BOSR 8.1.14-1; Unit 2A Diesel Generator 24 Hour Endurance Run, Revision 10 2BOSR 8.1.14-2; Unit 2B Diesel Generator 24 Hour Endurance Run, Revision 10==
Section 4OA1: Performance Indicator Verification LS-AA-2090; Monthly Data Elements for NRC Reactor Coolant System (RCS) Specific Activity; dated July 3, 2007 through September 2, 2008 LS-AA-2100; Monthly Data Elements for NRC Reactor Coolant System Leakage, Revision 5 LS-AA-2150; Monthly Data Elements for RETS/ODCM Radiological Effluent Occurrences; dated July 10, 2007 through September 10, 2008 MSPI Derivation Report; Unit 1 and Unit 2 High Pressure Injection System Unavailability and Unreliability Index, February 2008 Operations Log; February 1, 2008 - February 29, 2008 MSPI Derivation Report; Unit 1 and Unit 2 Cooling Water System Unavailability and Unreliability Index, March 2008 IR 854124; Inconsequential Error identified in March 2008 MSPI Data for SX, December 9, 2008
: Calculation 19-T-5; Diesel Generator Loading During LOOP/LOCA, Revision 6
==LIST OF ACRONYMS==
: [[US]] [[]]
: [[ED]] [[]]
: [[AFW]] [[Auxiliary Feedwater System]]
ALARA As Low As Reasonably Achievable
CAP Corrective Action Program
CFR Code of Federal Regulations
: [[JPM]] [[Job Performance Measure]]
: [[IMC]] [[Inspection Manual Chapter]]
IP Inspection Procedure IR Inspection Report
IR Issue Report
: [[IST]] [[Inservice Testing]]
: [[LORT]] [[Licensed Operator Requalification Training]]
MSPI Mitigating Systems Performance Index NCV Non-Cited Violation
NEI Nuclear Energy Institute
: [[NRC]] [[U.S. Nuclear Regulatory Commission]]
: [[OOS]] [[Out of Service]]
ODCM Offsite Dose Calculation Manual OSP Outage Safety Plan
: [[PI]] [[Performance Indicator]]
: [[RC]] [[]]
FC Reactor Containment Fan Cooler
: [[RCS]] [[Reactor Coolant System]]
: [[RETS]] [[Radiological Effluent Technical Specifications]]
RWP Radiation Work Permit SDP Significance Determination Process
TI Temporary Instructions
: [[TS]] [[Technical Specification]]
: [[UFSAR]] [[Updated Final Safety Analysis Report]]
: [[URI]] [[Unresolved Item WO Work Order]]
}}
}}

Revision as of 13:00, 27 August 2018

IR 05000454-08-005, 05000455-08-005 on 02/10/2009 for Errate, Byron, Units 1 and 2, Integrated Inspection
ML090510040
Person / Time
Site: Byron  Constellation icon.png
Issue date: 02/19/2009
From: Skokowski R A
Region 3 Branch 3
To: Pardee C G
Exelon Generation Co, Exelon Nuclear
References
IR-08-005
Download: ML090510040 (9)
v • d • e


Text

February 19, 2009

Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555

SUBJECT: ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2008-005; 5000455/2008-005

Dear Mr. Pardee:

On February 10, 2009, the U.S. Nuclear Regulatory Commission (NRC) issued Integrated Inspection Report 05000454/2008-005, 05000455/2008-005 for your Byron Station. An inspection sample for Post Maintenance Testing and an inspection sample for Emergency Preparedness Drill Observation were inadvertently omitted in the original report.

The enclosed errata contain the omitted inspection samples. Please replace Page 12 of the enclosure, Page 5 and 7 of the Attachment to the enclosure, and insert Page 12(a)

and Page 18(a) of the enclosure where appropriate into the NRC Integrated Inspection Report 05000454/2008-005, 05000455/2008-005 with the enclosed revised pages. We regret any inconvenience this may have caused.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning these errata, we will be pleased to discuss them with you.

Sincerely,/RA/

Richard A. Skokowski, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66

February 19, 2009 Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555

SUBJECT: ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2008-005; 05000455/2008-005

Dear Mr. Pardee:

On February 10, 2009, the U.S. Nuclear Regulatory Commission (NRC) issued Integrated Inspection Report 05000454/2008-005, 05000455/2008-005 for your Byron Station. An inspection sample for Post Maintenance Testing and an inspection sample for Emergency Preparedness Drill Observation were inadvertently omitted in the original report.

The enclosed errata contain the omitted inspection samples. Please replace Page 12 of the enclosure, Page 5 and 7 of the Attachment to the enclosure, and insert Page 12(a) and Page 18(a) of the enclosure where appropriate into the NRC Integrated Inspection Report 05000454/2008-005, 05000455/2008-005 with the enclosed revised pages. We regret any inconvenience this may have caused.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning these errata, we will be pleased to discuss them with you.

Sincerely,/RA/ Richard A. Skokowski, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66

DOCUMENT NAME: G:\Byron\BYR 2008-005 Errata.doc X Publicly Available G Non-Publicly Available G Sensitive X 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 RNg:dtp RSkokowski

DATE 02/19/09 02/19/09 OFFICIAL RECORD COPY Letter to from R. Skokowski dated February 19, 2009

SUBJECT: ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2008-005; 05000455/2008-005 cc w/encl: Site Vice President - Byron Station Plant Manager - Byron Station Manager Regulatory Assurance - Byron Station Senior Vice President - Midwest Operations Senior Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director - Licensing and Regulatory Affairs Manager Licensing - Braidwood, Byron, and LaSalle Associate General Counsel Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency J. Klinger, State Liaison Officer, Illinois Emergency Management Agency P. Schmidt, State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station

Letter to from R. Skokowski dated February 19, 2009

SUBJECT: ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2008-005; 05000455/2008-005 DISTRIBUTION:

Tamara Bloomer RidsNrrDorlLpl3-2 RidsNrrPMByron Resource RidsNrrDirsIrib Resource Mark Satorius Kenneth OBrien Jared Heck Allan Barker Carole Ariano Linda Linn Cynthia Pederson DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports@nrc.gov

12 Enclosure This inspection constituted one permanent plant modification sample as defined in IP 71111.18-05. a. Findings No findings of significance were identified. 1R19 Post-Maintenance Testing (71111.19) a. Inspection Scope The inspectors reviewed the following post-maintenance (PM) activities to verify that procedures and test activities were adequate to ensure system operability and functional capability:

  • Unit 2 Safety Injection System Accumulator Injection Check Valve 2SI8818C Repair; * Unit 2 Charging/Safety Injection System Flow Balance following Outage Maintenance;
  • Unit 1 Train B Charging Pump Return to Service Following Maintenance;
  • Work Order (WO) 1171264, Operate Diesel Generator 2A in Local Following Switch Repair;
  • Barring Over of Unit 1 Train B Diesel Generator to Look for Moisture in the Cylinders Following the Identification of an Indication in Two Cylinders;
  • Relay Actuation Surveillance 2BOSR 3.2.8-632A to Test Valve 2AF004A. These activities were selected based upon the structure, system, or component's ability to impact risk. The inspectors evaluated these activities for the following (as applicable): the effect of testing on the plant had been adequately addressed; testing was adequate for the maintenance performed; acceptance criteria were clear and demonstrated operational readiness; test instrumentation was appropriate; tests were performed as written in accordance with properly reviewed and approved procedures; equipment was returned to its operational status following testing (temporary modifications or jumpers required for test performance were properly removed after test completion), and test documentation was properly evaluated. The inspectors evaluated the activities against TS, the UFSAR, 10 CFR Part 50 requirements, licensee procedures, and various NRC generic communications to ensure that the test results adequately ensured that the equipment met the licensing basis and design requirements. In addition, the inspectors reviewed corrective action documents associated with post-maintenance tests to determine whether the licensee was identifying problems and entering them in the CAP and that the problems were being corrected commensurate with their importance to safety. Documents reviewed are listed in the Attachment to this report. This inspection constituted seven post-maintenance testing samples as defined in IP 71111.19-05.

12(a) Enclosure b. Findings No findings of significance were identified.

18(a) Enclosure

.2 Emergency Preparedness Medical/Health Physics Drill Observation a. Inspection Scope The inspectors evaluated the conduct of a routine licensee emergency drill on June 3, 2008, to identify any weaknesses and deficiencies in classification, notification, and protective action recommendation development activities. The inspectors observed emergency response operations during the Annual Medical/Health Physics Drill to determine whether the event classification, notifications, and protective action recommendations were performed in accordance with procedures. The inspectors also attended the licensee drill critique to compare any inspector-observed weakness with those identified by the licensee staff in order to evaluate the critique and to verify whether the licensee staff was properly identifying weaknesses and entering them into the corrective action program. As part of the inspection, the inspectors reviewed the drill package and other documents listed in the Attachment to this report. This emergency preparedness drill inspection constituted one sample as defined in IP 71114.06-05. b. Findings No findings of significance were identified.

5 Attachment Operational and Technical Decision Making 2008 - 2009; Suspect 1RC8002D Valve guide(s) Not Properly Retained in Valve Body Adverse Condition Monitoring and Contingency Plan; Unit 1 Loose Parts Monitoring System (LPMS) Noise, August 26, 2008 CAE-02-31 Westinghouse Letter; LSIV Loose Parts 50.59 Screen EVAL-02-062, Revision 1, March 21, 2002 WO 1072112 02; MOV PM, Actuator Inspection, Diagnostic testing, November 18, 2008 Section 1R18: Plant Modifications IR 842362; 2CV181 "2A RCP Standpipe PW Supply Valve" Failed to Close, November 08, 2008 IR 843783; Unexpected Alarm, November 12, 2008 IR 846404; Revised Bars for TCP 373002 are Incorrect, November 18, 2008 EC 373002; Installation of Temporary Line to Connect the Drain Lines of RCP Standpipes 2A and 2D, Revision 0 EC 371360; Install Vent Valve on 2SI05CA-8, Revision 2 EC 373224; Provide Temporary Fans for 1A DG Room, Revision 0 WO 01149077; Install Vent Valve on 2SI05CA-8, October 18, 2008 WO 01149077 13; SEP PMT: VT-2 of 2SI130, October 15, 2008 WO 01149077 14; OP PMT: Verify No Seat leakage on 2SI130, October 15, 2008 WO 01149077 15; SEP PMT: Record Vibe Data 2SI130 at Full Flow Conditions, October 15, 2008

Section 1R19: Post Maintenance Testing

1BOSR 3.2.8-610B; Unit 1 ESFAS Instrumentation Slave Relay Surveillance and Automatic Actuation Test (Train B Automatic Safety Injection - K610), Revision 2 2BOSR 7.5.5-2; Unit 2 Train B Auxiliary Feedwater Valve Emergency Actuation Signal Verification Test, Revision 4 WO 999110; 1AP12E-A Relay #1-RCF2 for 1VP01CB Operations PMT Partial 1BOSR 3.2.8-610B, November 25, 2008 2BOSR 3.2.8-632A; ESFAS Instrumentation Slave Relay Surveillance (Train A Auxiliary Feedwater Actuation - Relays k632, K639, Revision 2 WO 1165207 01; MM-Repair of 2SI8818C During B2R14 WO 1165207 04; EP - Perform Visual Examination of Disassembled Check Valve WO 1165207 06; Operations PMT - 2SI8818C SLT Per 2BOSR 4.14.1-1 WO 1165207 07; Operations PMT - 2SI8818C CO Per 2BOSR 5.5.8RH.2-2 WO 1020023 01; 2RH25 VT-2 Exam, October 15, 2008 WO 1192590; Bar Over Diesel Generator to check for Moisture ASME Section XI Repair/Replacement Plan; 2SI8818C (Loop 3 Cold Leg Accumulation Injection Check Valve, September 29, 2008 BOP CV-19; Switching Charging Pumps, Revision 14 1BOSR 5.5.1-1; Unit 1 RCS Seal Injection Flow Verification Monthly Surveillance, Revision 4 2BVSR 5.c.2-1; Unit 2 Charging/Safety Injection System Flow Balance, Revision 4 Section 1R20: Refueling and Outage Activities Ultrasonic Thickness Calibration Data Sheet; Report Number 2008-707 IR 826879; Calibrate/Repair 2FI-0928A, October 05, 2008 IR 834405; Need B2R15 W/O to Retrieve Rag and Wire From Upender Pit B2R14 Work Orders Added to Date, October 15, 2008 7 Attachment BOP DG-11; Diesel Generator Startup, Revision 20 BOP DG-12; Diesel Generator Shutdown, Revision 19 Corrective Action Documents as a Result of NRC Inspection IR 841953; IST Basis Documents for 1/2SI8818A-D Need Updating, November 06, 2008 IR 841953; IST Basis Documents for 1/2SI8818A-D Need Updating, November 07, 2008

Section 2OS1: Access Control to Radiologically Significant Areas RP-AA-460; Controls for High Radiation and Locked High Radiation Areas; Revision 17 RP-AA-460-001; Controls for Very High Radiation Areas; Revision 1 RP-AA-460; Access to Reactor Incore Sump Area; Revision 2 RP- BY-500-1003; Radiological Controls for Handling Items and Hanging Activated Parts in the Spent Fuel Pool Radiation Work Permit and Associated ALARA Reviews; RWP 10008926; B2R14 Seal Table - Rack Disconnect/Maintenance/Eddy Current/Restoration Radiation Work Permit and Associated ALARA Reviews; RWP 10009830; P-68 Penetrant Test and Vent Line Inspection IR 795311; RWP Violations (PC Requirements); dated July 10, 2008 IR 761294; Level 1 Personal Contamination Event; dated 9, 2008 IR 756342; Worker Entered A/D Platform without Electronic Dosimeter; dated March 29, 2008 IR 754696; Worker Locked Out of RCA - Rad Worker Behavior; dated March 26, 2008 IR 756136; PCE: B1R15 Personal Contamination Event; dated March 28, 2008 IR 673712; RP Not Effectively Using Corrective Action Program; dated September 20, 2007 IR 755986; Alpha Survey Documentation Gaps; dated March 27, 2008 IR 756296; RP-AA-460-1001; Not Completed in Timely Manner; dated March 28, 2008 IR 812338; Ni-63 Source Leak Tests Exceed 6-Month Surveillance Frequency; dated August 22, 2008 Section 1EP6: Drill Evaluation IR 844467; OSC Minimum Staffing Not Met for Crew D in Drill, November 13, 2008 Byron 2008 Drive-In Drill; Scenario Information Nuclear Accident Reporting System (NARS) Form; Utility Message No. 2, November 12, 2008 IR 844467; OSC Minimum Staffing Not Met for During Drill, November 12, 2008 Cycle 08-4 Out of the Box Evaluation, 08-4-1, Revision 0.

Section 4OA1: Performance Indicator Verification LS-AA-2090; Monthly Data Elements for NRC Reactor Coolant System (RCS) Specific Activity; dated July 3, 2007 through September 2, 2008 LS-AA-2100; Monthly Data Elements for NRC Reactor Coolant System Leakage, Revision 5 LS-AA-2150; Monthly Data Elements for RETS/ODCM Radiological Effluent Occurrences; dated July 10, 2007 through September 10, 2008 MSPI Derivation Report; Unit 1 and Unit 2 High Pressure Injection System Unavailability and Unreliability Index, February 2008 Operations Log; February 1, 2008 - February 29, 2008 MSPI Derivation Report; Unit 1 and Unit 2 Cooling Water System Unavailability and Unreliability Index, March 2008 IR 854124; Inconsequential Error identified in March 2008 MSPI Data for SX, December 9, 2008

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