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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 |
| | }} |
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| {{IR-Nav| site = 05000454 | year = 2008 | report number = 005 }} | | {{IR-Nav| site = 05000454 | year = 2008 | report number = 005 }} |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter: |
| [[Issue date::February 10, 2009]] | | [[Issue date::February 19, 2009]] |
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| 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 |
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| 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 |
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| ==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. |
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| 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. |
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| 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). |
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| ===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
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| ===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 |
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| =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
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| =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
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| ==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}}
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| ==1R01 Adverse Weather Protection==
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| {{IP sample|IP=IP 71111.01}}
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| .....................................................3 | |
| {{a|1R04}}
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| ==1R04 Equipment Alignment==
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| {{IP sample|IP=IP 71111.04}}
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| ................................................................4
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| {{a|1R05}}
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| ==1R05 Fire Protection==
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| {{IP sample|IP=IP 71111.05}}
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| ...........................................................................4
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| {{a|1R06}}
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| ==1R06 Flooding==
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| {{IP sample|IP=IP 71111.06}}
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| ....----------------------.6
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| {{a|1R07}}
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| ==1R07 Annual Heat Sink Performance==
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| {{IP sample|IP=IP 71111.07}}
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| .................................................6
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| {{a|1R11}}
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| ==1R11 Licensed Operator Requalification Program==
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| {{IP sample|IP=IP 71111.11}}
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| .............................7
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| {{a|1R12}}
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| ==1R12 Maintenance Effectiveness==
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| {{IP sample|IP=IP 71111.12}}
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| .......................................................8
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| {{a|1R13}}
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| ==1R13 Maintenance Risk Assessments and Emergent Work Control==
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| {{IP sample|IP=IP 71111.13}}
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| ..9
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| {{a|1R15}}
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| ==1R15 Operability Evaluations==
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| {{IP sample|IP=IP 71111.15}}
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| ...........................................................10
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| {{a|1R18}}
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| ==1R18 Plant Modifications==
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| {{IP sample|IP=IP 71111.18}}
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| ..................................................................11
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| {{a|1R19}}
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| ==1R19 Post-Maintenance Testing==
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| {{IP sample|IP=IP 71111.19}}
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| ......................................................12
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| {{a|1R20}}
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| ==1R20 Outage Activities==
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| {{IP sample|IP=IP 71111.20}}
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| .....................................................................13
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| {{a|1R22}}
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| ==1R22 Surveillance Testing==
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| {{IP sample|IP=IP 71111.22}}
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| ................................................................15
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| {{a|1EP6}}
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| ==1EP6 Drill Evaluation==
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| {{IP sample|IP=IP 71114.06}}
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| ........................................................................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
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| {{a|4OA1}}
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| ==4OA1 Performance Indicator Verification==
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| {{IP sample|IP=IP 71151}}
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| ...............................................23
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| {{a|4OA2}}
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| ==4OA2 Identification and Resolution of Problems==
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| {{IP sample|IP=IP 71152}}
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| ....................................28
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| {{a|4OA5}}
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| ==4OA5 Other Activities -------------------------30 4OA6==
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| Management Meetings---------------------..32 4OA7 Licensee-Identified Violations....................................................................33
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| =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. |
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| ==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
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| : [[contact::D. Hoots]], Site Vice President
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| : [[contact::W. Grundmann]], Regulatory Assurance Manager
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| : [[contact::Z. Cox]], Chemist | |
| : [[contact::G. Contrady]], Programs Manager
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| : [[contact::H. Do]], Corporate ISI Engineer
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| : [[contact::S. Greenlee]], Engineering Director
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| : [[contact::D. Thompson]], Radiation Protection Manager
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| Nuclear Regulatory Commission
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| : [[contact::R. Skokowski]], Branch Chief
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| ==LIST OF ITEMS==
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| OPENED, CLOSED AND DISCUSSED
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| ===Opened===
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| : 05000454/2008005-01
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| : 05000455/2008005-01 NCV Failure to Remove or Evaluate Loose Debris Inside of Containment Prior to Applicable Mode
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| : 05000454/2008005-02
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| : 05000455/2008005-02 NCV Failure to Evaluate Radiological Hazards for Airborne Radioactivity
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| ===Closed===
| | Should you have any questions concerning these errata, we will be pleased to discuss them with you. |
| : 05000454/2008005-01
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| : [[Closes finding::05000455/FIN-2008005-01]] NCV Failure to Remove or Evaluate Loose Debris Inside of Containment Prior to Applicable Mode
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| : 05000454/2008005-02
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| : [[Closes finding::05000455/FIN-2008005-02]] NCV Failure to Evaluate Radiological Hazards for Airborne Radioactivity
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| : 05000454;
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| : 455/2008-003-06 URI Unit 1 and Unit 2 Auxiliary Feedwater Tunnel Hatch Margin to Safety
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| : 2
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| ==LIST OF DOCUMENTS REVIEWED==
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| The following is a list of documents reviewed during the inspection.
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| : 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.
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| : 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.
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| ==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
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| : 846625; Procedure Enhancement, November 18, 2008 BOP
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| : SX-T2; SX Tower Operations Guidelines, Revision 12
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| ==Section 1R04: Equipment Alignment (Quarterly) 2BOSR 7.8.1-1; Unit 2 Essential Service Water System Valve Position Monthly Surveillance, Revision 16==
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| : BOP
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| : DG-1; Diesel Generator Alignment to Standby Condition, Revision 11
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| : BOP
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| : VD-5; DG Room Ventilation System Operation, Revision 6
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| : BwOP
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| : VD-5; DG Room Ventilation System operation, Revision 12
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| : BwOS
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| : VD-1a; Diesel Ventilation Systems; Revision 4 10
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| : CFR 50.59 Screening, BOP Vd-5 DG Room Ventilation System Operation; January 06, 1986
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| : Corrective Action Documents as a Result of NRC Inspection
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| : IR 852537; Compensatory Actions Not Procedurally Directed, December 4, 2008
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| ==Section 1R05: Fire Protection (Quarterly) Corrective Action Documents as a Result of==
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| : NRC Inspection
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| : IR 842026; Fire Zone Walkdown Issues, November 07, 2008
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| : IR 850920; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
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| : IR 850922; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
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| : IR 850925; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
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| : IR 850926; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
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| : IR 850929; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
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| : IR 850931; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
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| : IR 850932; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
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| : IR 842026; Fire Zone Walkdown Issues, November 07, 2008
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| : IR 847572; Interim NRC Inspector Fire Zone Walkdown Findings, November 20, 2008
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| ==Section 1R05: Fire Protection (Annual)==
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| : BAP 1100-10; Response Procedure for Fire, Revision 7
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| : BAP 1100-10T1; 401' Fire Brigade Equipment Inventory, Revision 7
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| : Byron Emergency Self-Contained Breathing Apparatus Storage Locations Monthly Inventory, September 2008
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| : OP-AA-201-003; Fire Drill Performance, Revision 7
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| : 3OP-AA-201-005; Fire Brigade Qualification, Revision 6
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| : OP-AA-201-008; Pre-Fire Plans, Revision 1
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| : 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
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| : Byron Station Fire Drill Critique Form, August 24, 2008
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| : Summary Report for Each Shift Reflecting Fire Brigade and HazMat Qualification Status, October 12, 2008
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| : IR 823253; Safe-Guards Information Slows Fire Response, September 27, 2008
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| ==Section 1R07: Heat Sink Performance==
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| : WO 1036955; Perform As-Found/As-Left Inspections of 2C RCFC Issue
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| : 830146; Replace RCFC Channel Heads with stainless Steel in B2R15, October 13, 2008
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| : IR 830370; Restricted Tubes in 2C RCFC, Need to Plug, October 13, 2008
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| : IR 829315; 2C RCFC Channel Head Degradation, Divider Plates, October 10, 2008
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| ==Section 1R08: Inservice Inspection Activities==
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| : IR 829647; Penetration 41 Not Examined During B2R13; October 11, 2008
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| : IR 831084; Foreign Objects Found In 2C SG Secondary Side - B2R14; October 15, 2008
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| : IR 829610; Acceptance Criteria Used On SX Pipe Was Not Appropriate; October 11, 2008
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| : IR 843635, Steam Generator Tube Sheet Inspection Results - B2R14, November 11, 2008
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| : IR 832181; Foreign Objects Found In 2A SG Secondary - B2R14; dated October 17, 2008
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| : IR 830452; B2R14 - Weld Defects Revealed During Radiography Of Repair;
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| : October 14, 2008
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| : IT00717275-02; Buildup of Deposits in Steam Generators, NRC
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| : IN 2007-37
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| : ER-AP-335-1012; Bare Metal Visual Examination of PWR Vessel Penetration and Nozzle Safe-Ends; Revision 3
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| : ER-AP-335-040; Evaluation of Eddy Current Data for Steam Generator Tubing; Revision 4
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| : EXE-ISI-11; Liquid Penetrant Examination, Revision 4
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| : EXE-UT-350; Procedure for Acquiring Material Thickness and Weld Contours; Revision 2
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| : EXE-PDI-UT-2; Ultrasonic Examination of Austenitic Piping Welds in Accordance with
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| : PDI-UT-2; Revision 5
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| : EXAE-ISI-8;
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| : VT-1 Direct; Revision 1
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| : ER-AP-335-039; Multi-Frequency Eddy Current Data Acquisition of Steam Generator Tubing;
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| : Revision 5
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| : ER-MW-335-1009; Site Specific Performance; Revision 4
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| : ER-AP-331; Boric Acid Corrosion Control (BACC) Program; Revision 3
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| : ER-AP-331-1001; Boric Acid Corrosion control (BACC) Inspection Locations, Implementation and Inspection Guidelines; Revision 3
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| : ER-AP-331-1002; Boric Acid Corrosion control Program Identification, Screening, and Evaluation; Revision 4
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| : ER-AP-331-1004; Boric Acid Corrosion Control (BACC) Training and Qualification, Revision 2
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| : ER-AP-420-002; Byron/Braidwood Unit 2:
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| : Steam Generator Eddy Current Activities; Revision 8
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| ==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
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| : 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,
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| : CY 2008; no date | |
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| ==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
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| : IR 460411; VA Supply/Exhaust Fan Vibration Alarm Setpoint Basis Concern
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| : IR 717005;
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| : VA-Tolerance for Equipment Degradation, January 1, 2008
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| : IR 726481; High Vibrations on 0C VA Fan (Supply Fan), January 24, 2008
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| : IR 727128; VA Issues, January 26, 2008
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| : IR 735812; VA Concerns, February 13, 2001
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| : IR 748406; Need (A)(1) Determination: VA Unacceptable Performance Trend, March 12, 2008
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| : IR 850742; Control Damper Problems for 1A DG Ventilation, December 01, 2008
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| : IR 869580; MM Expanded Scope Replace Linear Converter, January 23, 2007
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| : IR 999934; Replace Linear Converter, November 07, 2008
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| : 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
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| ==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
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| : Protected Equipment Log for 2B DG Outage, October 11, 2008
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| : Protected Equipment Log for Line 0622/Bus 12 Outage, October 12, 2008
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| : 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
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| : B2R14 Shutdown Risk Evaluation; October 15, 2008
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| : 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
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|
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|
| ==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
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| : IR 810867; Expansion Tank Overflow When Started and Running, August 26, 2008
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| : IR 814019; Low JW Level in the 1B AF Pump, September 04, 2008
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| : IR 846398; Need Work Order Created to Replace Grease, November 18, 2008
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| : 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
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| : EC 371879; Operations Evaluation 08-007, Gas Void at 2CS009A, November 20, 2008
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| : EC 371965; Operations Evaluation 08-008, 2B AF Pump Jacket Water Overflow, Revision 000
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| : 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
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|
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| ==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
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| : TCP 373002 are Incorrect, November 18, 2008
| |
| : EC 373002; Installation of Temporary Line to Connect the Drain Lines of RCP Standpipes 2A
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| and 2D, Revision 0
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| : 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
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|
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| ==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]]
| |
| }} | | }} |
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05000455/2023402 IR 05000454/20230012023-05-0505 May 2023 Integrated Inspection Report 05000454/2023001 and 05000455/2023001 IR 05000454/20230102023-04-19019 April 2023 License Phase 1 Report 05000454/2023010 IR 05000454/20234012023-03-30030 March 2023 Baseline Security Inspection 05000454/2023401; and 05000455/2023401 IR 05000454/20223012023-03-0707 March 2023 NRC Initial License Examination Report 05000454/2022301 and 05000455/2022301 IR 05000454/20220062023-03-0101 March 2023 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000455/2022006 and 05000454/2022006) IR 05000454/20220042023-02-0101 February 2023 Integrated Inspection Report 05000454/2022004 and 05000455/2022004 IR 05000454/20220102023-01-17017 January 2023 Design Basis Assurance Inspection (Programs) Inspection Report Report 05000454/2022010 and 05000455/2022010 IR 05000454/20224032022-12-28028 December 2022 Cyber Security Inspection Report 05000454/2022403 and 05000455/2022403 IR 05000454/20224052022-12-0909 December 2022 Material Control and Accounting Program Inspection Report 05000454/2022405 and 05000455/2022405 IR 05000454/20220032022-11-0707 November 2022 Integrated Inspection Report 05000454/2022003 and 05000455/2022003 BYRON 2022-0072, Steam Generator Tube Inspection Report for Refueling Outage 232022-10-27027 October 2022 Steam Generator Tube Inspection Report for Refueling Outage 23 IR 05000454/20220052022-08-24024 August 2022 Updated Inspection Plan for Byron Station Units 1 and 2 (Report 05000454/2022005; 05000455/2022005) IR 05000454/20224022022-08-0909 August 2022 Security Baseline Inspection Report 05000454/2022402 and 05000455/2022402 IR 05000454/20220022022-08-0808 August 2022 Integrated Inspection Report 05000454/2022002 and 05000455/2022002 IR 05000454/20220012022-05-0303 May 2022 Integrated Inspection Report 05000454/2022001 and 05000455/2022001 IR 05000454/20224012022-04-0404 April 2022 Security Baseline Inspection Report 05000454/2022401 and 05000455/2022401 IR 05000454/20210062022-03-0202 March 2022 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2021006 and 05000455/2021006) IR 05000454/20210042022-02-11011 February 2022 Integrated Inspection Report 05000454/2021004 and 05000455/2021004 IR 05000454/20210122022-01-0606 January 2022 Biennial Problem Identification and Resolution Inpsection Report 05000454/2021012 and 05000455/2021012 IR 05000454/20213012021-12-17017 December 2021 NRC Initial License Examination Report 05000454/2021301; 05000455/2021301 IR 05000454/20214032021-11-22022 November 2021 Security Baseline Inspection Report 05000454/2021403 and 05000455/2021403 IR 05000454/20210032021-10-29029 October 2021 Integrated Inspection Report 05000454/2021003 and 05000455/2021003 and Exercise of Enforcement Discretion IR 05000454/20214022021-09-28028 September 2021 Security Baseline Inspection Report 05000454/2021402 and 05000455/2021402 IR 05000454/20210052021-09-0101 September 2021 Updated Inspection Plan for Byron Station Units 1 and 2 (05000454/2021005 and 05000455/2021005) IR 05000454/20210022021-08-0404 August 2021 Integrated Inspection Report 05000454/2021002; 05000455/2021002; and 07200068/2021001 IR 05000454/20210112021-05-14014 May 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000454/2021011 and 05000455/2021011 IR 05000454/20215012021-04-21021 April 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2021501 and 05000455/2021501 IR 05000454/20210012021-04-20020 April 2021 Integrated Inspection Report 05000454/2021001 and 05000455/2021001 IR 05000454/20214012021-03-24024 March 2021 Security Baseline Inspection Report 05000454/2021401 and 05000455/2021401 IR 05000454/20180102021-03-19019 March 2021 Closure of Auxiliary Feedwater System Unresolved Item 05000454/2018010-04 and 05000455/2018010-04 IR 05000454/20200062021-03-0404 March 2021 Annual Assessment Letter for Byron Station (Report 05000454/2020006 and 05000455/2020006) IR 05000454/20210102021-02-0909 February 2021 Triennial Fire Protection Inspection Report 05000454/2021010 and 05000455/2021010 IR 05000454/20200042021-01-27027 January 2021 Integrated Inspection Report 05000454/2020004 and 05000455/2020004 IR 05000454/20204032020-12-16016 December 2020 Security Baseline Inspection Report 05000454/2020403 and 05000455/2020403 IR 05000454/20200032020-11-10010 November 2020 Integrated Inspection Report 05000454/2020003 and 05000455/2020003 IR 05000454/20200112020-09-29029 September 2020 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000454/2020011 and 05000455/2020011 IR 05000454/20204022020-09-18018 September 2020 Security Baseline Inspection Report 05000454/2020402 and 05000455/2020402 IR 05000454/20200052020-09-0101 September 2020 Updated Inspection Plan for Byron Station Units 1 and 2 (Report 05000454/2020005 and 05000455/2020005) IR 05000454/20200022020-07-27027 July 2020 Integrated Inspection Report 05000454/2020002 and 05000455/2020002 IR 05000454/20200012020-04-24024 April 2020 Integrated Inspection Report 05000454/2020001 and 05000455/2020001 IR 05000454/20204012020-03-30030 March 2020 Security Baseline Inspection Report 05000454/2020401 and 05000455/2020401 IR 05000454/20190062020-03-0303 March 2020 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2019006 and 05000455/2019006) 2024-02-02
[Table view] Category:Letter
MONTHYEARIR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23192A0362023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 IR 05000454/20234022023-07-18018 July 2023 Baseline Security Inspection Document; 05000454/2023402; 05000455/2023402 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) ML23159A1542023-06-0808 June 2023 2022 Regulatory Commitment Change Summary Report RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23003A7882023-05-11011 May 2023 Report for December 12-16, 2022, Regulatory Audit Regarding Reinsertion of a High Burnup Accident Tolerant Fuel Lead Test Assembly 2024-02-02
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Inspection Report - Byron - 2008005 |
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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