IR 05000254/2010006
| ML102590632 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/16/2010 |
| From: | Ring M A NRC/RGN-III/DRP/B1 |
| To: | Pacilio M J Exelon Generation Co, Exelon Nuclear |
| References | |
| IR-10-006 | |
| Download: ML102590632 (20) | |
Text
September 16, 2010
Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION
05000254/2010-006; 05000265/2010-006
Dear Mr. Pacilio:
On August 27, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed a routine biennial Problem Identification and Resolution (PI&R) inspection at your Quad Cities Nuclear Power Station, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on August 27 with Mr. Gideon and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified. The team concluded that problems were properly identified, evaluated, and resolved within the corrective action program (CAP). Assessments, the use of operating experience, and monitoring of the safety-conscious work environment were also adequate. There were some minor issues identified with CAP implementation such that continued attention to the program is appropriate.
Therefore, your staff should be attentive to the significance and difficulty certain issues represent so that the corrective actions are more appropriately aggressive. 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). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/ Mark A. Ring, Chief Branch 1 Division of Reactor Projects
Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30
Enclosure:
Inspection Report 05000254/2010-006; 05000265/2010-006
w/Attachment:
Supplemental Information
cc w/encl: Distribution via ListServe
Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 50-254, 50-265 License Nos: DPR-29, DPR-30 Report No: 05000254/2010-006 and 05000265/2010-006 Licensee: Exelon Nuclear Facility: Quad Cities Nuclear Power Station, Units 1 and 2 Location: Cordova, IL Dates: August 9, 2010, through August 27, 2010 Inspectors: C. Moore, Project Engineer, DRP D. Jones, Reactor Inspector, DRS B. Cushman, Quad Cities Resident Inspector, DRP A. Shaikh, Reactor Inspector, DRS C. Mathews, Illinois Emergency Management Agency (IEMA) Inspector
Approved by: M. Ring, Chief Branch 1 Division of Reactor Projects Enclosure
SUMMARY OF FINDINGS
IR 05000254/2010-006; 05000265/2010-006; 08/9/2010 - 08/27/2010; Quad Cities Nuclear Power Station, Units 1 & 2 routine biennial problem identification and resolution inspection (PI&R). This inspection was performed by three regional inspectors, the Quad Cities Resident Inspector, and the Illinois Emergency Management Agency Re sident Inspector. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
Problem Identification and Resolution On the basis of the sample selected for review, the team concluded that implementation of the Corrective Action Program (CAP) was generally good. The licensee had a low threshold for identifying problems and entering them into the CAP. Items entered into the CAP were screened and prioritized in a timely manner using established criteria; were properly evaluated commensurate with their safety significance; and corrective actions were generally implemented in a timely manner, commensurate with the safety significance. The team noted that the licensee reviewed operating experience for applicability to station activities. Audits and self-assessments were determined to be performed at an appropriate level to identify deficiencies. On the basis of licensee self-assessments and interviews conducted during the inspection, workers at the site expressed freedom to raise safety concerns. The team observed that some corrective actions were not fully implemented in a timely manner.
A. NRC-Identified
and Self-Revealed Findings No violations of significance were identified.
B. Licensee-Identified Violations
None.
REPORT DETAILS
OTHER ACTIVITIES
4OA2 Problem Identification and Resolution
Completion of sections
.1 through .4 constitutes one biennial sample of problem identification and resolution as defined in Inspection Procedure 71152. .1 Assessment of the CAP Effectiveness
a. Inspection Scope
The inspectors reviewed the licensee's Corrective Action (CA) program implementing procedures and attended CA program meetings to assess the implementation of the CA program by site personnel.
The inspectors reviewed risk and safety significant issues in the licensee's CA program since the last NRC Problem Identification and Resolution (PI&R) inspection in July -
August of 2008. The selection of issues ensured an adequate review of issues across NRC cornerstones. The inspectors used issues identified through NRC generic communications, department self-assessments, licensee audits, operating experience reports, and NRC documented findings as source s to select issues. Additionally, the inspectors reviewed issue reports generated as a result of facility personnel's performance in daily plant activities. In addition, the inspectors reviewed Issue Reports (IRs) and a selection of completed investigations from the licensee's various investigation methods, which included root cause, apparent cause, equipment apparent cause, and common cause investigations.
During the reviews, the inspectors determined whether the licensee staff's actions were in compliance with the facility's corrective action program and 10 CFR Part 50, Appendix B requirements. Specifically, the inspectors determined if licensee personnel were identifying plant issues at the proper threshold, entering the plant issues into the station's CA program in a timely manner, and assigning the appropriate prioritization for resolution of the issues. The inspectors also determined whether the licensee staff assigned the appropriate investigation method to ensure the proper determination of root, apparent, and contributing causes. The inspectors also evaluated the timeliness and effectiveness of corrective actions for selected issue reports, completed investigations, and NRC findings, including non-cited violations.
b. Assessment (1) Effectiveness of Problem Identification Overall, based on the number of IRs generated by all the plant departments, plant procedures that established a low threshold for reporting, and the types of issues in the program, the team concluded that the licensee was adequately identifying issues in the CAP. However, there was one instance during the course of a root cause investigation the licensee failed to identify an unmonitored release path to the environment. The root cause investigation performed following the explosion of the Floor Drain Surge Tank vestibule is the root cause evaluation in question. The root cause report failed to identify 3 Enclosure that an uncontrolled and unmonitored release of radioactivity had occurred on multiple occasions prior to the explosion of the Floor Drain Surge Tank vestibule when its ventilation fan and the Max Recycle ventilation fans were out-of-service and the Floor Drain Surge Tank was being filled. Since the licensee was able to show that the radiation released was less than one percent of the total annual gaseous effluent released, this violation of 10 CFR 20.1501, Radiological Surveys and Monitoring, is considered of minor significance. This NRC-identified issue was subsequently entered into the CAP.
Findings No findings of significance were identified.
(2) Effectiveness of Prioritization and Evaluation of Issues The team concluded that issue resolutions, established and monitored through the Ownership Review Committee and the Management Review Committee, were correctly assigned significance and priority in accordance with station procedures.
Findings No findings of significance were identified.
(3) Effectiveness of Corrective Actions Although corrective actions reviewed by the team were effective in most cases, several examples where results were less than desirable were also observed. While corrective actions were generally adequate, the team identified five issues that were not resolved in a timely manner. The team found that a lack of technical rigor resulted in repeat equipment issues with the Emergency Diesel Generator Cooling Water Pump and Containment Air Monitor operation and parts evaluations did not provide the intended solution. Two consecutive Personnel Contamination Events during Rad Waste Filter work and repeated problems associated with leaking Turbine Building Heating Coils were also noted. A lack of technical rigor also resulted in a problem with the Met tower not transferring information to the Plant Process Data System (PPDS), but this was not a repeat issue. In all of these cases, the licensee's response was not aggressive enough to be effective. At the time of the inspection, corrective actions were showing positive results.
Findings No findings of significance were identified.
.2 Assessment of the Use of Operating Experience (OE)
a. Inspection Scope
The inspectors reviewed the implementation of the OE program. Specifically, the inspectors reviewed implementing operating experience program procedures, attended CA program meetings to observe the use of OE information, completed evaluations of OE issues and events, and selected monthly assessments of the OE composite 4 Enclosure performance indicators. The inspectors' review was to determine whether the licensee was effectively integrating OE experience into the performance of daily activities, whether evaluations of issues were proper and conducted by qualified personnel, whether the licensee's program was sufficient to prevent future occurrences of previous industry events, and whether the licensee effectively used the information in developing departmental assessments and facility audits. The inspectors also assessed if corrective actions, as a result of OE experience, were identified and effectively and timely implemented.
b. Assessment The team observed that the licensee was effectively receiving and processing operating experience reports from all sources. Operating experience was being incorporated into pre-job briefings and the performance of daily activities was generally effective in preventing repeats of previous industry events.
Findings No findings of significance were identified.
.3 Assessment of Self-Assessments and Audits
a. Inspection Scope
The inspectors assessed the licensee staff's ability to identify and enter issues into the CA program, prioritize and evaluate issues, and implement effective corrective actions, through efforts from departmental assessments and audits.
b. Assessment The programs for self-assessments and audits were scheduled and included a broad cross-section of performance areas. Procedures for performing assessments were in place and implemented, providing guidance and consistency. For the audits and assessments reviewed, no deficiencies were identified. Overall, self-assessment was adequately performed.
Findings No findings of significance were identified.
.4 Assessment of Safety-Conscious Work Environment
a. Inspection Scope
The inspectors assessed the licensee's safety-conscious work environment through reviews of the facility's employee concerns program (ECP) implementing procedures, discussions with coordinators of the employee concern program, interviews with personnel from various departments, and reviews of issue reports.
5 Enclosure b. Assessment The inspection team interviewed 49 plant employees. The interviews were conducted with 19 First Line Supervisors and 30 bargaining unit employees. The individuals interviewed were from the Maintenance, Operations, Stores, Work Control, Radiation Protection, Chemistry, Security, and Engineering Departments. Through our interviews with selected staff members, we did not identify any concerns that would indicate an adverse safety-conscious work environment.
The team determined that employees are willing and able to raise safety concerns. However, once an issue is raised, its resolution is not always communicated to affected individuals. An example of this was when an individual reported what he thought was mold inside several Bullet Resistant Enclosures (BREs). The licensee investigated the issue and determined a course of action but did not adequately inform the entire security force, who had become aware of the issue, and were concerned for their health. This type of miscommunication can lead to safety-conscious work environment challenges. Security is evolving to correct this issue, and two new Action Tracking Items (ACITs) were generated for Issue Report (IR) 1099935 as a result of the teams' interviews.
Findings No findings of significance were identified.
4OA6 Management Meetings
Exit Meeting Summary
On August 27, 2010, the inspectors presented the inspection results to Mr. Gideon, and other members of the licensee staff. The licensee acknowledged the issues presented.
The inspectors confirmed that none of the potential report inputs discussed was
considered proprietary. ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Beck, W. Regulatory Affairs Manager
Neels, V. Chemistry
Summers, P. Maintenance Director
Darin, S. Engineering
O'Shea,
- J. Corrective Action Program Manager Peterson, T. Regulatory Assurance
Gideon, R. Site Vice President
Williams, A Radiation Protection
Illinois Emergency Management Agency (IEMA)
C. Mathews
Nuclear Regulatory Commission
- J. McGhee, Senior Resident Inspector
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
None.
Attachment
LIST OF DOCUMENTS REVIEWED
The following is a list of documents reviewed during the inspection.
- Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.
- Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
- PLANT PROCEDURES
- Number Description or Title Date or RevisionER-AA-600-1045 Assessment of Missed or Deficient Surveillances Rev. 3
- QC-SURV-01 Missed Surveillance Risk Assessment For the Unit 2 125 VDC Battery Rev. 1 QCOS 1400-01 Quarterly Core Spray Pump Flow Rate Test Rev. 39
Operating Experience
- Program Issue Identification and Screening Process Rev. 15 Rev. 12
- QCOP 1000-18
- QCOP 1600-16 QCOP 2010-34
- QCOP 2010-37
- QCOP 2099-18
- QCOP 2000-37
- QCOP 2000-39
- QCOP 2010-40
- QCOP 5750-03 Corrective Action Program Procedure Self-Assessment Program Performance Improvement Program Description Design Input and Configuration Change Impact Screening Torus Water Transfer to the Waste Collector Tank, Floor Drain Collector Tank, or Floor
- Drain Surge Tank Floor Drain Surge Tank Transfer to Torus Draining the CCSTs to the Floor Drain Surge Tank Processing the Floor Drain Collector Tank with the Floor Drain Collector pump Through
the Spare Filter to the Floor Drain Surge Tank During Unit Outages Transfer of Decontamination Water to the
- River Discharge or the Floor Drain Surge
- Tank Pumping the Waste Collector Tank to the
- Floor Drain Surge Tank Using the Floor Drain Collector pump Pumping the Waste Collector Tank to the Floor Drain Surge Tank Using the Waste Collector pump Pumping the Floor Drain Collector Tank to the Floor Drain Surge Tank Radwaste Ventilation System Rev. 14 Rev. 6
- Rev. 0
- Rev. 14
- Rev. 20
- Rev. 9 Rev. 9
- Rev. 8
- Rev. 2
- Rev. 3
- Rev. 5
- Rev. 4
- Rev. 12
- Attachment PLANT PROCEDURES
- Number Description or Title Date or Revision
- QCMM 1515-08 Inspection of Safety and Non Safety Related Check Valves During Disassembly, Repair and Reassembly of Valves Rev. 13 QCMM 1515-07 General Valve Packing Procedure Rev. 21
- MA-QC-736-100 Quad Cities Station Lubrication Guide Rev. 22
- QCOS 0010-04 Operations Master Lubrication List Rev. 42
- QCOS 0202-22 Online Testing of Unit 2 Division ii ATWS Recirculation Pump Terip and Alternate Rod Insertion Logic Rev. 4 QCOS 1000-04 RHR Service Water Pump Operability Test Rev. 49 QCOS 0010-19
- Security Event Support Equipment Surveillance Rev. 7 QCOS 0020-02 Safety System Monthly Manual Valve Position Verification Rev. 12
- Control Of Portable Measurement and Test Equipment Program Rev. 7 MA-AA-716-010-
- 1005 Operating Experience User Guide Rev. 0
- MA-AA-716-010-
- 1104 Mechanical Seal Leakage Evaluation and Reporting Rev. 0
- MA-AA-716-010 Maintenance Planning Rev. 16
- AUDITS, ASSESSMENTS AND
- SELF-ASSESSMENTS
- Number Description or Title Date or Revision
- NOSA-QDC-10-04 (IR# 998214)
- NOS 2010 Chemistry Audit
- 06/23/2010
- NOSA-QDC-09-06 (IR# 853531)
- NOS 2009 Radiation Protection Audit 08/19/2009
- NOSA-QDC-10-03 (IR# 998213)
- NOSA-QDC-10-05
(IR#998215)
- NOSA-QDC-10-02 (IR#998212)
- NOSA-QDC-10-01
(IR#998209) NOS Emergency Preparedness Audit Engineering Programs and Station Blackout Audit Security Programs Audit
- Maintenance Audit
- 05/05/2010
- 04/26/2010
- 2/01/2010
- 2/15/2010
- 862703 Annual CCA on Chemistry Fundamentals 01/05/2009
- 995712 Annual CCA on Chemistry Fundamentals 11/19/2009
- Attachment MISCELLANEOUS
- Number Description or Title Date or Revision
- Regulatory Guide
- 1.21 Radiochemistry Evaluation of Quad Cities Unit 1 Cycle 21
- Electrical Installation Plan Surge Tank Sections and Details Max Recycle Radwaste Bldg Wiring Diagram - Radwaste Building 480V
- System Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste
- 05/25/2010
- J
- S
- WO 01236098 Repair /Replace 1 B CS
stop check valve
- 1-1402-65B
- 08/12/2010
- WO 1138588-01 EDGCW pump impeller wear rings (Boroscope inspection)
- 09/05/2008
- 813347 Emerson Part 21, Fin 1997-01, Suppl 1, Actuator Diaphragms
- 09/02/2009
- CONDITION REPORTS GENERATED DURING INSPECTION
- Number Description or Title Date or Revision
- 1105169 FLR Drain Surge TK Ventil Design Basis Documentation
- 08/24/2010
- 1105713 Enhancements Identified for RW Vent
Procedure
- 08/25/2010
- CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
- Number Description or Title Date or Revision
- 00723954 U1 EDG CW pump failure
- 01/18/2008
- 08/11/2008
- 00923518 Unable to Obtain H2 Seal Oil System Parameters
- 05/24/2009
- 11/12/2008
- 00962562 Pinhole Leak Identified in Piping Downstream of
- 1-1402-38B
- 09/08/2009
- 00883127 RWCU Valve
- 1-1201-5 Failed to Close From Control Room
- 2/20/2009
- 04/27/2009
- Attachment CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
- Number Description or Title Date or Revision
- 00913457 PSU - Q1R20 ADD - B Bay Main Condenser Hole in Lagging
- 04/29/2009
- 00914117 PSU - MSIV 1-203-1A 2A Switch Out Of Tolerance
- 04/30/2009
- 00920012 PSU - Failed To Open Following Pump Run 05/15/2009
- 00931150 2A Jacket Water Booster Pump Breaker Thermals Found Tripped
- 06/15/2009
- 00946407 U2 EDG Vent Fan Tripped
- 07/27/2009
- 00955548
- Properly 08/20/2009
- 09/20/2009
- 00991442
- 11/10/2009
- 00991992 TSC Building Failed Pressure Test
- 11/11/2009
- 01006080 Bulb Separated From Base Base Still in Socket
- 2/16/2009
- 01023608 U2 Instrument Air Compressor Trip
- 01/30/2010
- 01028569 U2 HPCI Trip During QCOS 2300-05
- Surveillance
- 2/10/2010
- 01036563
- MCC 65-1 Feed Breaker Tripped
- 2/28/2010
- 01037275 Received U1 Digital EHC Alarms 03/01/2010
- 01040878 U2 SBO 'B' Diesel Jacket Water Booster Pump BKR Tripped
- 03/10/2010
- 01041377 MRULE:
- Adverse Trend for RB Ventilation
- 03/11/2010
- 01052746 2B RFP Vent Fan Motor Breaker Will Not Reset
- 04/05/2010
- 01066555 Received Alarm 912-5 C1, Reactor Bldg 1
- Low
- DP 05/07/2010
- 1073740 FDST High Silica
- 05/26/2010
- 1082186 Offgas and Effluent trending
- 06/18/2010
- 1085962
- 836178 Chimney Gas Activity Step Increase FDSgT explosion from RadWaste High Organics 06/30/2010
- 10/27/2008
- 1045112
- 910737
- 2582
- 811106
- 844466
- 876925
- NOS ID Adverse trend in Site Rad Worker
- Online Emergent Dose at Quad Cities
- Station Perform CCA on Rad Worker Issues at
- Quad Cities Station
- 03/19/2010
- 04/23/2009
- 07/16/2009
- 08/26/2010
- 11/13/2010
- 2/05/2009
- Attachment CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
- Number Description or Title Date or Revision
- 941800
- 947009
- 2022
- 1018768
- 1063644
- 1063645
- 866242
- 1091681
- 1061175
- 1055818
- 29882
- 719988
- 749355
- 937777
- 959168
- 993180
- 1030415
- 1105713
- 1105169
- 841251
- 1016122
- 1102273
- 1056375
- 918439
- 986413
- 994823
- 969849
- Perform CCA for 2009 online dose overages Perform CCA on Radiation Worker Practices CCA required for RP Dept Communication
- Perform CCA for Q2R20 PCEs Worker received ED Alarm Deficient Speakers found in Reactor Building BSMNT
- Failure of Public Address System Speaker
- SPING Rx Vent SPING pump was found tripped off Rx Vent SPING was found tripped off Rx Vent SPING pump stopped running Control room SPING terminal external fail light lit Control room SPING terminal external fail light Hi range detector - RV SPING not
functioning properly Enhancements Identified for RW Vent
Procedure
- PIR-FLR Drain Surge Tk Ventil Design Basis Documentation Insignificant Abnormal Radiological Effluent
- Release Steam Coils Freezing and Leaking on ECCS
- Bus
- LEL Above 10% in FDSGT but not a
- Potential Explosive Conc.
- 2C Condenser Backpressure Reads Higher
- Than Expected
- U2 Fuel Pool Pumps Tripped Due to Refueling Activities Operations Removed 1B RWCU Demin Instead of 1A
- TS SR 3.8.4.8 Frequency Not Met
- 07/14/2010
- 07/29/2010
- 08/11/2009
- 01/20/2010
- 04/30/2010
- 04/30/2010
- 01/13/2009
- 07/17/2010
- 04/25/2010
- 04/13/2010
- 01/31/2008
- 01/09/2008
- 03/13/2008
- 06/30/2009
- 08/29/2009
- 11/13/2009
- 2/12/2010
- 08/25/2010
- 08/24/2010
- 11/06/2008
- 01/13/2010
- 08/16/2010
- 04/14/2010
- 05/11/2010
- 10/30/2009
- 11/17/2009
- 09/24/2009
- 06/09/2010
- 1082207 Various Issues Identified During Inspection 06/18/2010
- 1080663 LR Inspection
- 2-1001-142A Minor Corrosion Identified
- 06/15/2010
- Attachment CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
- Number Description or Title Date or Revision
- 1063300 Evaluation of Decision Making Related to RHRSW Elbow Failure
- 04/29/2010
- 1065404 Fire Protection Guided Wave Ultrasonic Testing Results
- 05/04/2010
- 1073322 LL
- 05/26/2010
- 1086791 Nonconformance of Installed RHR/CS Pump Seal Repair Kits
- 07/01/2010
- 1066484 MPT 1 Serveron Leakage Following Repairs 05/06/2010
- 1073736 Non Safety Related Seal Repair Kit Installed On RHR/CS Pumps
- 05/26/2010
- 318520 U-2 EDG - Interior Surfaces Corrosion On Starting Air Piping
- 10/27/2009
- 03/19/2010
- 962562 Pinhole Leak Identified In Piping Downstream of
- 1-1402-38B
- 09/08/2009
- 997163 FASA - Buried pipe / Raw Water Corrosion 11/23/2009
- 1018379 NOS ID'D:
- Incorrect Torque Sequence Given In Work package
- 01/19/2010
- 1103641 NOS ID 2B ASD Troubleshooting Preparation Deficiencies
- 08/19/2010
- 05/24/2010
- 987905 1A RHR Room Cooler Heat Exchanger Tube Sheet Has Pitting
- 11/02/2009
- 849245 1B RHR Room Cooler Heat Exchanger Has Tube Sheet Pitting
- 11/25/2008
- 1069983 Unit 1 Drywell Pneumatic Compressor Seal Leak 05/17/2010
- 972234 Drywell Pneumatic Compressor Leak Detected 09/29/2009
- 952027 901-4 G-14 Drywell Air Compressor Trouble 08/11/2009
- 946473 Drywell Pneumatic Air Hi Lvl Switch Inoperable
- 07/28/2009
- 09/27/2008
- 828820 Received Unexpected Alarm 902-3, H10 10/09/2008
- Attachment OPERATING EXPERIENCE
- Number Description or Title Date or Revision
- 1088576 NRC Inspection Issue At Limerick/OE/OPEX 07/07/2010
- 1076063 (Vogtle)
- OE 31054-Dead Blow Hammer Failure 06/02/2010
- 797451 Operating Experience / Counterfeit or Fraudulent Parts
- 07/17/2008
- 658996 X-Ray Machine At TMI Missing Ground Pins 08/09/2007
- Attachment
LIST OF ACRONYMS
- USED [[]]
TS Technical Specification
M. Pacilio -2-
In accordance with
- NRC 's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the
NRC Website
at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA/ Mark A. Ring, Chief Branch 1
Division of Reactor Projects
Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30
Enclosure: Inspection Report 05000254/2010-006; 05000265/2010-006
w/Attachment: Supplemental Information
cc w/encl: Distribution via ListServe
- 006 PIR [[]]
IR 2010.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in th
e concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
- OFFICE [[]]
- RECORD [[]]
- QUAD [[]]
- POWER [[]]
- AND [[]]
RESOLUTION INSPECTION