IR 05000277/2009004
| ML093160608 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/12/2009 |
| From: | Paul Krohn Reactor Projects Region 1 Branch 4 |
| To: | Pardee C Exelon Generation Co, Exelon Nuclear |
| References | |
| IR-09-004 | |
| Download: ML093160608 (54) | |
Text
UNITED NUCLEAR REGULATORY REGION 475 AI.LENDALE KING OF PRUSSIA. PENNSYLVANIA November 12, 2009 Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 PEACH BOTTOM ATOMIC POWER STATION -NRC INSPECTION REPORT 05000277/2009004 AND
Dear Mr. Pardee:
On September 30, 2009, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The enclosed . integrated inspection report documents the inspection results, which were discussed on October 23, 2009, with Mr. William Maguire and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection.
one self-revealing finding of very low safety significance (Green) and one Severity level IV inspector-identified violation were identified.
These findings were determined to involve violations of NRC requirements.
Additionally, a licensee-identified violation which was determined to be of very low safety significance is listed in this report. However, because of the very low safety significance and because the findings were entered into your corrective action program (CAP), the NRC is treating the findings as non-cited violations (NCVs), consistent with Section VI.A.1 of the NRC Enforcement Policy. If you contest any of the NCVs in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 w 0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, U. S. NRC, Washington, DC 20555-0001; and the NRC Senior Resident Inspector at the PBAPS. In addition, if you disagree with the characterization of the cross-cutting aspect of any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement.
to the Regional Administrator, Region 1 and the NRC Senior Resident Inspector at PBAPS. The information you provide will be considered in accordance with Inspection Manual Chapter (IMC) 0305.
C. 2 In accordance with Title 10 of the Code of Federal Regulations (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 the NRC's document system (ADAMS). " ADAMS is accessible from the NRC Website at httg:llwww.nrc.gov/reading-rm/adams.html
{the Public Electronic Reading Room}.
Sincerely, Paul G. Krohn, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos.:
License Nos.: DPR-44, Inspection Report 05000277/2009004 and
w/Attachment:
Supplemental
REGION I==
50-278 DPR-44, DPR-56 05000277/2009004 and 05000278/2009004 Exelon Generation Company, LLC Peach Bottom Atomic Power Station, Units 2 and 3 Delta, Pennsylvania July 1, 2009 through September 3D, 2009 F. Bower, Senior Resident Inspector M. Brown, Resident Inspector S. Barr, Senior. Emergency Preparedness Inspector J. Commiskey, Health Physicist P. Finney, Susquehanna Resident Inspector R. Nimitz, Senior. Health Physicist T. O'Hara, Reactor Inspector A. Ziedonis, Reactor Inspector Paul G. Krohn, Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure TABLE OF
SUMMARY OF FINDINGS
..........................................................................................................
REPORT DETAILS
.....................................................................................................................1.REACTOR SAFETY ................................................................................................................
1 R04 Equipment Alignment
..............................................................................................
1R05 Fire Protection
........................................................................................................
1R07 Heat Sink Performance
...........................................................................................
1R08 Inservice
Inspection (lSI) Activities
.........................................................................1 R11 Licensed Operator Requalification Program ...........................................................1 R12 Maintenance Effectiveness
.....................................................................................1 R 13 Maintenance Risk Assessments and Emergent Work Control .................................*1 R15 Operability Evaluations
..........................................................................................1 R 18 Plant Modifications ............................................................................................... 1
1R19 Post-Maintenance
Testing ....................................................................................1 R20 Refueling and Other Outage Activities
...................................................................1 R22 Surveillance Testing ... ; ......................................................................................... 1 EP2 Alert and Notification System (ANS) Evaluation
....................................................1 EP3 Emergency Response Organization (ERO) Staffing and Augmentation System ... 1 EP4 Emergency Action Level (EAL) and Emergency Plan Changes ............................1 EPS Correction of EP Weaknesses ) .............................................................................2.RADIATION SAFETY ............................................................................................................20S1 Access Controls ...................................................................................................20S2 ALARA Planning and Controls ..............................................................................20S3 Radiation Monitoring Instrumentation and Protective Equipment
..........................2PS1 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems .....2PS3 Radiological Environmental Monitoring Program (REMP) and Radioactive (RAM) Control ......................................................................................................................4.0THER ACTIVITIES (OA) .....................................................................................................40A1 Performance Indicator (PI) Verification
..................................................................40A2 Identification and Resolution of Problems (PI&R) ..................................................40A3 Follow-up of Events and Notices of Enforcement
.................................40A5 Other Activities
......................................................................................................40A6 Meetings, Including Exit.. ....................................................................................... 40A7 Licensee-Identified Violations
................................................................................ATTACHMENT:
=SUPPLEMENTAL
INFORMATION=
KEY POINTS OF CONTACT
..................................................................................................
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
.......................................................