ML060610443: Difference between revisions

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==Dear Mr. Crane:==
==Dear Mr. Crane:==
On February 9, 2006, the NRC staff completed its performance review of Byron Station, Units 1 and 2. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2005. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.
On February 9, 2006, the NRC staff completed its performance review of Byron Station, Units 1 and 2. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2005. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.
This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as Exempt from Public Disclosure in accordance with 10 CFR 2.390 will include the physical protection review and resultant inspection plan.
This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as Exempt from Public Disclosure in accordance with 10 CFR 2.390 will include the physical protection review and resultant inspection plan.
Overall, Byron Station Units 1 and 2 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter, as well as for the first three quarters of the assessment cycle, was within the Licensee Response column of the NRCs Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). Therefore, we plan to conduct reactor oversight process baseline inspections at your facility.
Overall, Byron Station Units 1 and 2 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter, as well as for the first three quarters of the assessment cycle, was within the Licensee Response column of the NRCs Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). Therefore, we plan to conduct reactor oversight process baseline inspections at your facility.
In our mid-cycle assessment letter dated August 30, 2005, (ML052420448), we advised you of a substantive cross-cutting issue in the cross-cutting area of human performance involving weaknesses in personnel performance regarding procedure adherence. Since the mid-cycle assessment, there has been one new Green finding/violation where personnel performance was not adequate. Over the course of the assessment period, there was a total of six findings of very low safety significance where personnel performance was not adequate. Four of these findings were in the reactor safety strategic performance area (SPA): one in the initiating events cornerstone, one in the mitigating system cornerstone, and two in the barrier integrity cornerstone. The other two findings were in the radiation safety SPA, both in the occupational radiation safety cornerstone. We recognize that you have initiated actions to understand the reasons for these human performance errors; however, several of the related corrective actions were yet to be implemented as of the end of the assessment period. Therefore, there continues to be a substantive cross-cutting issue in the area of human performance.
In our mid-cycle assessment {{letter dated|date=August 30, 2005|text=letter dated August 30, 2005}}, (ML052420448), we advised you of a substantive cross-cutting issue in the cross-cutting area of human performance involving weaknesses in personnel performance regarding procedure adherence. Since the mid-cycle assessment, there has been one new Green finding/violation where personnel performance was not adequate. Over the course of the assessment period, there was a total of six findings of very low safety significance where personnel performance was not adequate. Four of these findings were in the reactor safety strategic performance area (SPA): one in the initiating events cornerstone, one in the mitigating system cornerstone, and two in the barrier integrity cornerstone. The other two findings were in the radiation safety SPA, both in the occupational radiation safety cornerstone. We recognize that you have initiated actions to understand the reasons for these human performance errors; however, several of the related corrective actions were yet to be implemented as of the end of the assessment period. Therefore, there continues to be a substantive cross-cutting issue in the area of human performance.


C. Crane                                       Based on this substantive cross-cutting issue, we plan on conducting an annual inspection sample using Inspection Procedure 71152, Identification and Resolution of Problems, to focus on human performance issues. The Inspection Procedure 71152 annual reviews will also be increased to the upper band to better assess personnel error reduction. In addition, the semiannual trend review of your corrective action program will assess your efforts to ensure effective reduction of personnel errors to avoid repeat events. These inspection samples will provide us with further assessment on plant performance in the area of human performance and enable us to determine whether the plant meets the criteria established in Inspection Manual Chapter 0305, Operating Reactor Assessment Program, Section 06.06i, for clearing this cross-cutting issue.
C. Crane Based on this substantive cross-cutting issue, we plan on conducting an annual inspection sample using Inspection Procedure 71152, Identification and Resolution of Problems, to focus on human performance issues. The Inspection Procedure 71152 annual reviews will also be increased to the upper band to better assess personnel error reduction. In addition, the semiannual trend review of your corrective action program will assess your efforts to ensure effective reduction of personnel errors to avoid repeat events. These inspection samples will provide us with further assessment on plant performance in the area of human performance and enable us to determine whether the plant meets the criteria established in Inspection Manual Chapter 0305, Operating Reactor Assessment Program, Section 06.06i, for clearing this cross-cutting issue.
Furthermore, as a result of this substantive cross-cutting issue, we request that you provide an update of the issue during the upcoming annual public meeting. In addition, we request that you provide us a written response to the substantive cross-cutting issue raised in this letter, including your focused areas of concern, the status of the associated corrective action, and a current assessment of personnel performance. This response should be sent to the NRC within 30 days of the receipt of this letter.
Furthermore, as a result of this substantive cross-cutting issue, we request that you provide an update of the issue during the upcoming annual public meeting. In addition, we request that you provide us a written response to the substantive cross-cutting issue raised in this letter, including your focused areas of concern, the status of the associated corrective action, and a current assessment of personnel performance. This response should be sent to the NRC within 30 days of the receipt of this letter.
Additionally, on October 27, 2005, the staff issued a Severity Level III Notice of Violation in accordance with the NRCs Enforcement Policy. The violation was associated with 27 ventilation/filtration-related technical specification surveillance tests that were falsified as complete by the system engineer. The failure to perform the Technical Specification-required surveillance tests and the falsification of these test records were determined to be a deliberate violation and were categorized collectively as a Severity Level III Violation (EA-05-0159).
Additionally, on October 27, 2005, the staff issued a Severity Level III Notice of Violation in accordance with the NRCs Enforcement Policy. The violation was associated with 27 ventilation/filtration-related technical specification surveillance tests that were falsified as complete by the system engineer. The failure to perform the Technical Specification-required surveillance tests and the falsification of these test records were determined to be a deliberate violation and were categorized collectively as a Severity Level III Violation (EA-05-0159).
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In accordance with 10 CFR 2.390 of the NRCs 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).
In accordance with 10 CFR 2.390 of the NRCs 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).


C. Crane                                     If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan.
C. Crane If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
Sincerely,
                                            /RA/
/RA/
Richard A. Skokowski, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Richard A. Skokowski, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66


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See next page
See next page


C. Crane                                                                 If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan.
C. Crane If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
Sincerely,
                                                                          /RA/
/RA/
Richard A. Skokowski, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
Richard A. Skokowski, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66


==Enclosure:==
==Enclosure:==
Byron Station Inspection/ Activity Plan DISTRIBUTION:
Byron Station Inspection/ Activity Plan DISTRIBUTION:
See next page DOCUMENT NAME:G:\Branch TSS\ALL EOC\EOC CY2005\EOC Letters For CY 2005\Byron.wpd G Publicly Available                       G Non-Publicly Available                 G Sensitive             G 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                           RIII                               RIII NAME               RSkokowski:sls DATE               03/01/2006 OFFICIAL RECORD COPY
See next page DOCUMENT NAME:G:\\Branch TSS\\ALL EOC\\EOC CY2005\\EOC Letters For CY 2005\\Byron.wpd G Publicly Available G Non-Publicly Available G Sensitive G 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 RIII RIII NAME RSkokowski:sls DATE 03/01/2006 OFFICIAL RECORD COPY


C. Crane                                 cc w/encl: Site Vice President - Byron Station Plant Manager - Byron Station Regulatory Assurance Manager - Byron Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer, State of Illinois State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station President, Village of Leaf River President, Village of Davis Junction President, Village of Stillman Valley Ogle County Board Chairman Ogle County Sheriff/EMA Coordinator EMA Coordinator, Winnebago County Winnebago County Board Chair Winnebago County Sheriff/ESDA Mayor of Oregon Mayor of Byron President, Village of Mt. Morris Mayor of Rochelle INPO
C. Crane cc w/encl:
Site Vice President - Byron Station Plant Manager - Byron Station Regulatory Assurance Manager - Byron Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer, State of Illinois State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station President, Village of Leaf River President, Village of Davis Junction President, Village of Stillman Valley Ogle County Board Chairman Ogle County Sheriff/EMA Coordinator EMA Coordinator, Winnebago County Winnebago County Board Chair Winnebago County Sheriff/ESDA Mayor of Oregon Mayor of Byron President, Village of Mt. Morris Mayor of Rochelle INPO


C. Crane                                   ADAMS Distribution:
C. Crane ADAMS Distribution:
GYS DWW JBH1 RidsNrrDirslpab JLC1 GEG KGO RML2 SRI Byron DRPIII DRSIII PLB1 JRK1 ROPreports@nrc.gov (inspection reports, final SDP letters, any letter with an IR number)
GYS DWW JBH1 RidsNrrDirslpab JLC1 GEG KGO RML2 SRI Byron DRPIII DRSIII PLB1 JRK1 ROPreports@nrc.gov (inspection reports, final SDP letters, any letter with an IR number)


Page 1 of 1                                                                                      Byron 03/01/2006    16:01:51                                                                Inspection / Activity Plan Report 22 03/01/2006 - 09/30/2007 Unit                                                                                                          No. of Staff   Planned Dates          Inspection Number      Inspection Activity                                                    Title                        on Site       Start    End            Type M50.59         - MOD 50.59 INSPECTION                                                                       2 1, 2           IP 7111102              Evaluation of Changes, Tests, or Experiments                                         03/06/2006 03/24/2006 Baseline Inspections 1, 2           IP 7111117B              Permanent Plant Modifications                                                         03/06/2006 03/24/2006 Baseline Inspections IP 71114       - EP NON-EXERCISE BASELINE INSP                                                             1 1, 2           IP 7111402              Alert and Notification System Testing                                                 03/13/2006 03/17/2006 Baseline Inspections 1, 2           IP 7111403              Emergency Response Organization Augmentation Testing                                 03/13/2006 03/17/2006 Baseline Inspections 1, 2           IP 7111405              Correction of Emergency Preparedness Weaknesses and Deficiencies                     03/13/2006 03/17/2006 Baseline Inspections 1, 2           IP 71151                Performance Indicator Verification                                                   03/13/2006 03/17/2006 Baseline Inspections FY 2006       - BYRON INIT PREP 05/2006                                                                   2 1                 W90122               OL - INITIAL EXAM - BYRON - MAY/JUN 2006                                             05/22/2006 05/26/2006 Not Applicable ME             - MAINTENANCE RULE INSPECTION                                                               1 1              IP 7111112B              Maintenance Effectiveness                                                            06/12/2006 06/16/2006 Baseline Inspections FY 2006       - BYRON INIT EXAM 06/2006                                                                   3 1                 W90122               OL - INITIAL EXAM - BYRON - MAY/JUN 2006                                             06/19/2006 06/30/2006 Not Applicable 71121.03      - RP INSTRUMENTATION                                                                        1 1, 2           IP 7112103              Radiation Monitoring Instrumentation and Protective Equipment                         07/17/2006 07/21/2006 Baseline Inspections IP 71122       - RAD WASTE PROCESSING AND TRANSPORTATION                                                   1 1, 2           IP 7112202              Radioactive Material Processing and Transportation                                   08/21/2006 08/25/2006 Baseline Inspections 1, 2           IP 71151                Performance Indicator Verification                                                   08/21/2006 08/25/2006 Baseline Inspections ISI           - BYRON UNIT 1 ISI INSPECTION                                                               1 1              IP 7111108P              Inservice Inspection Activities - PWR                                                09/11/2006 09/29/2006 Baseline Inspections 71121.02       - ALARA PLANNING (OUTAGE)                                                                   1 1              IP 7112102              ALARA Planning and Controls                                                          09/11/2006 09/15/2006 Baseline Inspections CDBI           - COMPONENT DESIGN BASES INSPECTION                                                         6 1              IP 7111121              Component Design Bases Inspection                                                    10/30/2006 12/01/2006 Baseline Inspections 71111.11       - LIC OPERATOR REQUAL PROGRAM EVALUATION                                                     2 1, 2          IP 7111111B              Licensed Operator Requalification Program                                            10/30/2006 11/03/2006 Baseline Inspections 71121.01       - ACCESS CONTROL                                                                             1 1, 2           IP 7112101              Access Control to Radiologically Significant Areas                                   02/12/2007 02/16/2007 Baseline Inspections HEATSINK       - HEAT SINK INSPECTION                                                                       1 1, 2          IP 7111107B              Heat Sink Performance                                                                02/26/2007 03/02/2007 Baseline Inspections 71121.02       - ALARA - OUTAGE                                                                             1 1, 2          IP 7112102              ALARA Planning and Controls                                                          04/02/2007 04/13/2007 Baseline Inspections This report does not include INPO and OUTAGE activities.
Byron Inspection / Activity Plan 03/01/2006 - 09/30/2007 Inspection Type Inspection Activity Planned Dates Start End No. of Staff on Site Title Unit Number Page 1 of 1 03/01/2006 16:01:51 Report 22 2
M50.59
- MOD 50.59 INSPECTION Baseline Inspections 03/06/2006 03/24/2006 1, 2 7111102 IP Evaluation of Changes, Tests, or Experiments Baseline Inspections 03/06/2006 03/24/2006 1, 2 7111117B IP Permanent Plant Modifications 1
IP 71114
- EP NON-EXERCISE BASELINE INSP Baseline Inspections 03/13/2006 03/17/2006 1, 2 7111402 IP Alert and Notification System Testing Baseline Inspections 03/13/2006 03/17/2006 1, 2 7111403 IP Emergency Response Organization Augmentation Testing Baseline Inspections 03/13/2006 03/17/2006 1, 2 7111405 IP Correction of Emergency Preparedness Weaknesses and Deficiencies Baseline Inspections 03/13/2006 03/17/2006 1, 2 71151 IP Performance Indicator Verification 2
FY 2006
- BYRON INIT PREP 05/2006 Not Applicable 05/22/2006 05/26/2006 1
W90122 OL - INITIAL EXAM - BYRON - MAY/JUN 2006 1
ME
- MAINTENANCE RULE INSPECTION Baseline Inspections 06/12/2006 06/16/2006 1
7111112B IP Maintenance Effectiveness 3
FY 2006
- BYRON INIT EXAM 06/2006 Not Applicable 06/19/2006 06/30/2006 1
W90122 OL - INITIAL EXAM - BYRON - MAY/JUN 2006 1
71121.03
- RP INSTRUMENTATION Baseline Inspections 07/17/2006 07/21/2006 1, 2 7112103 IP Radiation Monitoring Instrumentation and Protective Equipment 1
IP 71122
- RAD WASTE PROCESSING AND TRANSPORTATION Baseline Inspections 08/21/2006 08/25/2006 1, 2 7112202 IP Radioactive Material Processing and Transportation Baseline Inspections 08/21/2006 08/25/2006 1, 2 71151 IP Performance Indicator Verification 1
ISI
- BYRON UNIT 1 ISI INSPECTION Baseline Inspections 09/11/2006 09/29/2006 1
7111108P IP Inservice Inspection Activities - PWR 1
71121.02
- ALARA PLANNING (OUTAGE)
Baseline Inspections 09/11/2006 09/15/2006 1
7112102 IP ALARA Planning and Controls 6
CDBI
- COMPONENT DESIGN BASES INSPECTION Baseline Inspections 10/30/2006 12/01/2006 1
7111121 IP Component Design Bases Inspection 2
71111.11
- LIC OPERATOR REQUAL PROGRAM EVALUATION Baseline Inspections 10/30/2006 11/03/2006 1, 2 7111111B IP Licensed Operator Requalification Program 1
71121.01
- ACCESS CONTROL Baseline Inspections 02/12/2007 02/16/2007 1, 2 7112101 IP Access Control to Radiologically Significant Areas 1
HEATSINK
- HEAT SINK INSPECTION Baseline Inspections 02/26/2007 03/02/2007 1, 2 7111107B IP Heat Sink Performance 1
71121.02
- ALARA - OUTAGE Baseline Inspections 04/02/2007 04/13/2007 1, 2 7112102 IP ALARA Planning and Controls This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.}}
This report shows only on-site and announced inspection procedures.}}

Latest revision as of 11:13, 15 January 2025

(EOC) Annual Assessment Letter (Report 05000454/455/2006-001)
ML060610443
Person / Time
Site: Byron  Constellation icon.png
Issue date: 03/02/2006
From: Richard Skokowski
NRC/RGN-III/DRP/RPB3
To: Crane C
Exelon Generation Co, Exelon Nuclear
References
IR-06-001
Download: ML060610443 (7)
v • d • e


Text

March 2, 2006 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

ANNUAL ASSESSMENT LETTER AND INSPECTION PLAN - BYRON STATION, UNITS 1 AND 2 (05000454/2006001; 05000455/2006001)

Dear Mr. Crane:

On February 9, 2006, the NRC staff completed its performance review of Byron Station, Units 1 and 2. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2005. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.

This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as Exempt from Public Disclosure in accordance with 10 CFR 2.390 will include the physical protection review and resultant inspection plan.

Overall, Byron Station Units 1 and 2 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter, as well as for the first three quarters of the assessment cycle, was within the Licensee Response column of the NRCs Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). Therefore, we plan to conduct reactor oversight process baseline inspections at your facility.

In our mid-cycle assessment letter dated August 30, 2005, (ML052420448), we advised you of a substantive cross-cutting issue in the cross-cutting area of human performance involving weaknesses in personnel performance regarding procedure adherence. Since the mid-cycle assessment, there has been one new Green finding/violation where personnel performance was not adequate. Over the course of the assessment period, there was a total of six findings of very low safety significance where personnel performance was not adequate. Four of these findings were in the reactor safety strategic performance area (SPA): one in the initiating events cornerstone, one in the mitigating system cornerstone, and two in the barrier integrity cornerstone. The other two findings were in the radiation safety SPA, both in the occupational radiation safety cornerstone. We recognize that you have initiated actions to understand the reasons for these human performance errors; however, several of the related corrective actions were yet to be implemented as of the end of the assessment period. Therefore, there continues to be a substantive cross-cutting issue in the area of human performance.

C. Crane Based on this substantive cross-cutting issue, we plan on conducting an annual inspection sample using Inspection Procedure 71152, Identification and Resolution of Problems, to focus on human performance issues. The Inspection Procedure 71152 annual reviews will also be increased to the upper band to better assess personnel error reduction. In addition, the semiannual trend review of your corrective action program will assess your efforts to ensure effective reduction of personnel errors to avoid repeat events. These inspection samples will provide us with further assessment on plant performance in the area of human performance and enable us to determine whether the plant meets the criteria established in Inspection Manual Chapter 0305, Operating Reactor Assessment Program, Section 06.06i, for clearing this cross-cutting issue.

Furthermore, as a result of this substantive cross-cutting issue, we request that you provide an update of the issue during the upcoming annual public meeting. In addition, we request that you provide us a written response to the substantive cross-cutting issue raised in this letter, including your focused areas of concern, the status of the associated corrective action, and a current assessment of personnel performance. This response should be sent to the NRC within 30 days of the receipt of this letter.

Additionally, on October 27, 2005, the staff issued a Severity Level III Notice of Violation in accordance with the NRCs Enforcement Policy. The violation was associated with 27 ventilation/filtration-related technical specification surveillance tests that were falsified as complete by the system engineer. The failure to perform the Technical Specification-required surveillance tests and the falsification of these test records were determined to be a deliberate violation and were categorized collectively as a Severity Level III Violation (EA-05-0159).

The enclosed inspection plan details the inspections, less those related to physical protection scheduled through September 30, 2007. Significant inspections planned for this year include a Modifications/50.59 inspection in March 2006, and a Component Design Bases inspection in October 2006. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last nine months of the inspection plan are tentative and may be revised at the mid-cycle review.

In accordance with 10 CFR 2.390 of the NRCs 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).

C. Crane If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

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

Enclosure:

Byron Station Inspection/ Activity Plan DISTRIBUTION:

See next page

C. Crane If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

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

Enclosure:

Byron Station Inspection/ Activity Plan DISTRIBUTION:

See next page DOCUMENT NAME:G:\\Branch TSS\\ALL EOC\\EOC CY2005\\EOC Letters For CY 2005\\Byron.wpd G Publicly Available G Non-Publicly Available G Sensitive G 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 RIII RIII NAME RSkokowski:sls DATE 03/01/2006 OFFICIAL RECORD COPY

C. Crane cc w/encl:

Site Vice President - Byron Station Plant Manager - Byron Station Regulatory Assurance Manager - Byron Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer, State of Illinois State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station President, Village of Leaf River President, Village of Davis Junction President, Village of Stillman Valley Ogle County Board Chairman Ogle County Sheriff/EMA Coordinator EMA Coordinator, Winnebago County Winnebago County Board Chair Winnebago County Sheriff/ESDA Mayor of Oregon Mayor of Byron President, Village of Mt. Morris Mayor of Rochelle INPO

C. Crane ADAMS Distribution:

GYS DWW JBH1 RidsNrrDirslpab JLC1 GEG KGO RML2 SRI Byron DRPIII DRSIII PLB1 JRK1 ROPreports@nrc.gov (inspection reports, final SDP letters, any letter with an IR number)

Byron Inspection / Activity Plan 03/01/2006 - 09/30/2007 Inspection Type Inspection Activity Planned Dates Start End No. of Staff on Site Title Unit Number Page 1 of 1 03/01/2006 16:01:51 Report 22 2

M50.59

- MOD 50.59 INSPECTION Baseline Inspections 03/06/2006 03/24/2006 1, 2 7111102 IP Evaluation of Changes, Tests, or Experiments Baseline Inspections 03/06/2006 03/24/2006 1, 2 7111117B IP Permanent Plant Modifications 1

IP 71114

- EP NON-EXERCISE BASELINE INSP Baseline Inspections 03/13/2006 03/17/2006 1, 2 7111402 IP Alert and Notification System Testing Baseline Inspections 03/13/2006 03/17/2006 1, 2 7111403 IP Emergency Response Organization Augmentation Testing Baseline Inspections 03/13/2006 03/17/2006 1, 2 7111405 IP Correction of Emergency Preparedness Weaknesses and Deficiencies Baseline Inspections 03/13/2006 03/17/2006 1, 2 71151 IP Performance Indicator Verification 2

FY 2006

- BYRON INIT PREP 05/2006 Not Applicable 05/22/2006 05/26/2006 1

W90122 OL - INITIAL EXAM - BYRON - MAY/JUN 2006 1

ME

- MAINTENANCE RULE INSPECTION Baseline Inspections 06/12/2006 06/16/2006 1

7111112B IP Maintenance Effectiveness 3

FY 2006

- BYRON INIT EXAM 06/2006 Not Applicable 06/19/2006 06/30/2006 1

W90122 OL - INITIAL EXAM - BYRON - MAY/JUN 2006 1

71121.03

- RP INSTRUMENTATION Baseline Inspections 07/17/2006 07/21/2006 1, 2 7112103 IP Radiation Monitoring Instrumentation and Protective Equipment 1

IP 71122

- RAD WASTE PROCESSING AND TRANSPORTATION Baseline Inspections 08/21/2006 08/25/2006 1, 2 7112202 IP Radioactive Material Processing and Transportation Baseline Inspections 08/21/2006 08/25/2006 1, 2 71151 IP Performance Indicator Verification 1

ISI

- BYRON UNIT 1 ISI INSPECTION Baseline Inspections 09/11/2006 09/29/2006 1

7111108P IP Inservice Inspection Activities - PWR 1

71121.02

- ALARA PLANNING (OUTAGE)

Baseline Inspections 09/11/2006 09/15/2006 1

7112102 IP ALARA Planning and Controls 6

CDBI

- COMPONENT DESIGN BASES INSPECTION Baseline Inspections 10/30/2006 12/01/2006 1

7111121 IP Component Design Bases Inspection 2

71111.11

- LIC OPERATOR REQUAL PROGRAM EVALUATION Baseline Inspections 10/30/2006 11/03/2006 1, 2 7111111B IP Licensed Operator Requalification Program 1

71121.01

- ACCESS CONTROL Baseline Inspections 02/12/2007 02/16/2007 1, 2 7112101 IP Access Control to Radiologically Significant Areas 1

HEATSINK

- HEAT SINK INSPECTION Baseline Inspections 02/26/2007 03/02/2007 1, 2 7111107B IP Heat Sink Performance 1

71121.02

- ALARA - OUTAGE Baseline Inspections 04/02/2007 04/13/2007 1, 2 7112102 IP ALARA Planning and Controls This report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures.

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