IR 05000373/2009007

Download: ML093451499

Text

December 11, 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: LASALLE COUNTY STATION, UNITS 1 AND 2 PROBLEM IDENTIFICATION AND RESOLUTION (PI&R) INSPECTION 05000373/2009007; 05000374/2009007

Dear Mr. Pardee:

On November 23, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed a Problem Identification and Resolution (PI&R) inspection at the LaSalle County Station Units 1 and 2. The enclosed report documents the inspection results, which were discussed on November 23, 2009, with 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. The inspection concluded that your staff was effective at identifying problems and incorporating them into the corrective action program. In general, issues were appropriately prioritized, evaluated, and corrected, audits and self-assessments were thorough and probing, and operating experience was appropriately screened and disseminated. Your staff was aware of the importance of having a strong safety-conscious work environment and expressed a willingness to raise safety issues. No findings or violations were identified during this inspection. 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 the 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/

Kenneth Riemer, Chief Branch 2 Division of Reactor Projects Docket No. 50-373; 50-374 License No. NPF-11; NPF-18

Enclosure:

Inspection Report 05000373/2009007; 05000374/2009007

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 05000373; 05000374 License Nos: NPF-11; NPF-18 Report No: 05000373/2009007; 05000374/2009007 Licensee: Exelon Generation Company, LLC Facility: LaSalle County Station, Units 1 and 2 Location: Marseilles, IL Dates: November 2-20, 2009 Inspectors: N. Shah, Project Engineer - Team Lead F. Ramirez, Resident Inspector - LaSalle C. Scott, Reactor Engineer D. Swarzc, Reactor Engineer Observers: Jane Yesinowki, Illinois Emergency Management Agency

Approved by: Kenneth Riemer, Chief Branch 2 Enclosure

SUMMARY OF FINDINGS

...........................................................................................................1

REPORT DETAILS

.......................................................................................................................3

OTHER ACTIVITIES

......................................................................................................3

4OA2 Problem Identification and Resolution

..................................................3

4OA6 Management Meetings.......................................................................................

.9

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

.....................................................................................................1

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED.........................................................1

LIST OF DOCUMENTS REVIEWED

.........................................................................................2

LIST OF ACRONYMS

US [[]]

ED..................................................................................................19

Enclosure

SUMMAR Y

OF [[]]

FINDIN [[]]

GS [[]]

IR [[05000373/2009007; 05000374/2009007 (November 2, 2009 - November 20, 2009), LaSalle County Station Units 1 and 2; Biennial Baseline Inspection of the Identification and Resolution of Problems. This team inspection was performed by three regional inspectors and the site resident inspector. No findings or violations were identified. Identification and Resolution of Problems Overall, the corrective action program (]]

CAP) was being effectively implemented. Issues were identified at a low threshold, evaluated and corrected. Self-assessments and audits by Nuclear Oversight (NOS) were thorough and critical of the assessed areas. Operating experience was recognized as valuable and was effectively communicated. Interviews with

licensee staff and a review of the Employee Concerns Program (ECP) indicated that the

licensee had a positive safety culture environment that encouraged identification of issues in the CAP. However, the inspectors identified several areas of concern that may negatively impact the licensee's ability to identify and resolve issues. In some cases, these issues had been

recognized by the licensee, but effective corrective action had not been taken. Briefly, the

issues were: The current

CAP performance indicators were not always effectively used or sufficient to monitor the program. Although the licensee was aware of these issues,

CAP staff appeared willing to live with the shortcomings and had not formally taken corrective action. There were some examples of long-standing issues that were either not corrected or not evaluated. In some cases, the licensee had identified the issues, but had not evaluated why previous corrective actions were ineffective. There were several examples where the review of operating experience (OE) in cause evaluations were not documented in accordance with licensee procedures. Additionally, there was no formal requirement to evaluate whether the failure to use OE was a precursor during the evaluation of events. Although the licensee had identified these

issues in the

CAP , the corrective actions were somewhat limited. Issues that were reviewed by the

ECP, but not captured in a formal case file, were not always well documented. This resulted in some uncertainty regarding whether potentially significant issues were appropriately dispositioned.

Enclosure

A. [[]]

NRC-Identified and Self-Revealed Findings Cornerstone: Mitigating Systems None. B. Licensee-Identified Violations No violations of significance were identified.

Enclosure

REPORT [[]]

DETAIL S 4.

OTHER [[]]

ACTIVI TIES

4OA 2 Problem Identification and Resolution (71152B) The activities documented in Sections .1 through .4 constituted one biennial sample of Problem Identification and Resolution (

PI&R) as defined in Inspection Procedure

(IP) 71152. .1 Assessment of the Corrective Action Program Effectiveness a. Inspection Scope The inspectors reviewed the licensee's corrective action program (CAP) implementing procedures and attended

CAP program meetings to assess the implementation of the

CAP. The inspectors selectively reviewed risk and safety-significant issues entered in the

CAP since the last

NRC PI&R inspection in November 2007. The selection of issues ensured

an adequate review of issues across the

NRC cornerstones. The inspectors included issues identified through

NRC generic communications, department self-assessments, licensee audits, operating experience reports, and NRC documented findings as part of

this assessment. The inspectors also reviewed a selection of completed root, apparent

and common cause evaluations. The inspectors performed a more extensive review of the licensee's control of cabling located in underground vaults, and corrective actions and temporary modifications that had been open for greater than one year. The review of the cabling located inside

underground vaults consisted of a five year search of related issues identified in the CAP

and discussions with appropriate licensee staff to assess the licensee's efforts in

addressing identified concerns. During the reviews, the inspectors evaluated whether the licensee staff's actions were in compliance with the facility's

CAP and 10

CFR Part 50, Appendix B requirements. Specifically, the inspectors evaluated if licensee personnel were identifying plant issues

at the proper threshold, if these issues were entered into the CAP in a timely manner,

and if these issues were appropriately resolved. The inspectors also evaluated whether

root, apparent, and common cause evaluations were assigned and performed as appropriate. The inspectors also evaluated the timeliness and effectiveness of corrective actions for selected issue reports, completed investigations, and

NRC -identified issues. b. Assessment (1) Effectiveness of Problem Identification Overall, the

CAP program was effectively implemented in that issues were identified at a low threshold, evaluated and corrected. Workers were encouraged to identify issues and were familiar with the various avenues available (NRC,

ECP ,

CAP, etc.). This was

evident by the large number of CAP items generated annually, which were reasonably

Enclosure distributed across the various departments. A shared computerized database was used for creating individual reports and for subsequent management of the processes of issue

evaluation and response. This included determining the issue's significance, addressing such matters as regulatory compliance and reporting, and assigning any actions deemed necessary or appropriate. However, the inspectors noted that the licensee performance indicators for monitoring the CAP program were not being effectively utilized. The inspectors identified that there

was no requirement to investigate instances where indicators identified poor

performance. For example, the inspectors noted that no Action Requests (ARs) had been initiated for several indicators that were either in the yellow or red band (indicating poor performance) during the past year. During interviews, licensee CAP staff

commented that some of these indicators, because of how they were defined, may be

inaccurately reporting performance. However, the inspectors could not find any CAP

entries identifying these indicators so that they could be corrected. The inspectors questioned the efficacy of the indicators when no effort was made to evaluate instances when poor performance was identified or to revise those considered inaccurate. The

licensee issued

AR 993280 to evaluate this issue. The inspectors determined that the station was generally effective at trending low level issues to prevent larger issues from developing. The licensee also used the

CAP to document instances where previous corrective actions were ineffective or were inappropriately closed. Findings No findings of significance were identified. (2) Effectiveness of Prioritization and Evaluation of Issues The inspectors concluded that the station was generally effective at prioritizing and evaluating issues commensurate with the safety significance of the identified problem. The inspectors determined that CAP screening meetings were generally thorough and

maintained a high standard for approving actions.

The majority of issues were of low level and were either closed to trend or at a level appropriate for a condition evaluation. Some of these issues were closed to a work request or to another CAP report, but the inspectors noted that both the parent and

daughter documents had the necessary verbiage to document the interrelationship.

The inspectors also had no concerns with those assigned an apparent, root or common

cause evaluation. There were no items in the operations, engineering, or maintenance

backlogs that were risk significant, individually or collectively. Root, apparent and common cause evaluations were generally thorough; however, the inspectors did identify two examples where the level of review was less than appropriate: AR 882701882701was written to perform a common cause evaluation for an adverse trend regarding issues with work orders/packages. The evaluation identified that this issue had been recurring since 2003, but did not address why previous

corrective actions were ineffective.

Enclosure

AR 784631 was written after the

NRC resident inspectors had observed a high radiation barrier (fenced enclosure) that had been built adjacent to the Unit 1 safety-related Standby Gas Treatment System piping. The barrier was in contact

with the piping (potentially raising a concern regarding the seismic analysis), but

there was no licensee evaluation supporting this condition. Subsequently, the barrier was removed, but there was no documentation for its removal. The licensee captured the above issues in the

CAP as

AR Nos. 996319 and 995883.

The inspectors determined that the licensee was generally effective at evaluating equipment functionality requirements after a degraded or non-conforming issue was

identified. The inspectors reviewed Maintenance Rule action plans associated with

systems currently in (a)(1) and for those returning to a(2) status within the last two years. No issues were identified from this review.

The inspectors also concluded that the licensee had been effectively managing

underground cabling.

Findings

No findings of significance were identified.

(3) Effectiveness of Corrective Actions The inspectors concluded that corrective actions for identified deficiencies were generally timely and adequately implemented, commensurate with their safety significance. The inspectors also concluded that sampled corrective actions

assignments for selected

NRC documented violations were generally effective and timely. However the inspectors did notice some untimely corrective actions as described below.

AR 840401 was written after the

NRC identified a non-safety hanger attached to a safety related cable tray. In the evaluation, the licensee failed to note that the same issue had been previously identified about four years earlier (

AR 352075352075 and that corrective actions had not been taken. The inspectors noted that the licensee had not taken appropriate action to address potential preconditioning due to inappropriate work scheduling (for example, scheduling a post-maintenance test just prior to a surveillance test)

despite having two prior NRC-identified instances of such, associated with the

main steam isolation valves and reactor core isolation cooling systems.

AR 856961 was written to address oscillations observed on a Unit 1 control rod drive flow control valve. Although a work order was written to address this, it remained open for over two years. The inspectors did not identify any

CAP item evaluating why the work order was open for so long.

AR 736409 was written to address high dose rates associated with a radioactive waste sample sink. The

AR was closed to a work order, but there was no documentation that the work was actually performed.

Enclosure The inspectors noted that work orders associated with the removal of temporary modifications, did not contain the necessary cross-referencing as required by procedure (i.e., neither the work order nor the temporary modification paperwork

referenced the other). The licensee wrote ARs 989540, 995336, 995957 and 988746, respectively, to address the above issues. The inspectors also identified that numerous, recurring issues (since 2006) with the Units 1 and 2 gaseous and particulate radiation monitors used for reactor leak detection

had not been resolved. The issues were varied and potentially affected the reliability of

the monitors. Although these monitors were nonsafety-related, they were required by

Technical Specifications. The licensee had performed past cause evaluations that had recommended corrective actions, but these actions had not been implemented. Additionally, the licensee had not evaluated whether the issues significantly impacted the ability of the monitors to detect primary system leakage. The licensee subsequently

identified that the monitors would perform the Technical Specification function and wrote

AR 989527989527to address this issue. The licensee had 19 open corrective actions that were greater than one year old, with the oldest being 731 days old. The inspectors verified that the open actions were

appropriate, that work orders were in place (and scheduled) for final implementation of

the action, and that plant operation or risk was not adversely affected.

Findings

No findings of significance were identified. .2 Assessment of the Use of Operating Experience a. Inspection Scope The inspectors reviewed the licensee's implementation of the facility's

OE program. Specifically, the inspectors reviewed implementing

OE program procedures, observed daily station and pre-job briefings to observe the use of OE information, and selectively

reviewed completed evaluations of OE issues and events. The intent of the 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 implemented. b. Assessment The inspectors concluded that the station appropriately screened OE information for applicability, and used the information for corrective and preventative actions to identify

and prevent similar issues. The inspectors observed that OE was discussed as part of

the daily station and pre-job briefings and was effectively disseminated across the

Enclosure various plant departments. During interviews with the inspectors, licensee staff generally commented favorably on the use of

OE in their daily activities. Although

OE was considered as part of root, apparent and common cause evaluations, the inspectors identified that these reviews were not always documented in accordance with CAP procedures. The licensee had identified several examples during

self-assessments conducted in 2008 and 2009 and had taken corrective action.

A subsequent licensee review, conducted prior to the

NRC [[]]

PI&R inspection, had

identified no additional issues. However, the inspectors identified several examples

where OE potentially applicable to the station was either not reviewed or the review was not documented as required. These examples occurred after the licensee self-assessments were completed, and were not identified in the licensee's effectiveness

review. The licensee initiated

AR 995934 to evaluate this issue. The inspectors also noted that the licensee's staff was not required to evaluate whether the failure to use

OE was a contributing cause of an event. Instead, the staff was only required to identify OE related to an event and use any insights gained in developing the corrective actions. The inspectors noted that several of the licensee's root, apparent

and common cause evaluations had identified OE that may have prevented the event

had it been appropriately evaluated. The licensee initiated AR 995981995981to evaluate this

issue. Findings No findings of significance were identified. .3 Assessment of Self-Assessments and Audits a. Inspection Scope The inspectors reviewed selected focused area self-assessments, check-in self-assessments, root cause effectiveness reviews, and NOS audits. The inspectors evaluated whether these audits and self-assessments were being effectively managed, adequately covered the subject areas, and whether identified issues were appropriately

captured in the CAP. In addition, the inspectors also interviewed licensee personnel

regarding the implementation of the audit and self-assessment programs. b. Assessment The inspectors concluded that self-assessments and audits were typically accurate, thorough, and effective at identifying issues and enhancement opportunities at an

appropriate threshold level. The inspectors concluded that these audits and

self-assessments were completed by personnel knowledgeable in the subject area. The inspectors considered the quality of the NOS audits to be thorough and critical.

The self-assessments were acceptable but, as expected, they were not at the same level of quality as the audits. The inspectors observed that

CAP items had been initiated for issues identified through the

NOS audits and self-assessments. Findings No findings of significance were identified.

Enclosure .4 Assessment of Safety-Conscious Work Environment (SCWE) a. Inspection Scope The inspectors interviewed selected members of the licensee's staff to determine if there were any impediments of a

SCWE. In addition, the inspectors discussed the implementation of the

ECP with the

ECP coordinators, and reviewed 2007 - 2009

ECP activities to identify any emergent issues or potential trends. In addition, the inspectors reviewed the facility's

ECP implementing procedures, interviewed the licensee

ECP coordinators, and reviewed licensee safety culture surveys. The licensee's programs to publicize the

CAP and

ECP programs were also reviewed. b. Assessment The inspectors determined that the plant staff were aware of the importance of having a strong

SC [[]]

WE and expressed a willingness to raise safety issues. No one interviewed had experienced retaliation for safety issues raised, or knew of anyone who had failed to

raise issues. All persons interviewed had an adequate knowledge of the

CAP and

ECP process. These results were similar to the findings of the licensee's safety culture surveys. Based on these interviews, the inspectors concluded that there was no

evidence of an unacceptable

SCWE. The inspectors determined that the

ECP process was being effectively implemented. The review of the selected

ECP issues indicated that site personnel were appropriately using the

CAP and

ECP to identify concerns. However, during the interviews most station personnel did not know where the

ECP office was located, although they could

identify the ECP personnel. This did not appear to have a detrimental affect, based on

the number of

ECP issues currently in the system. However, the inspectors observed that

ECP issues not captured in a formal case file, were not always well documented. This resulted in some uncertainty regarding whether potentially significant issues were appropriately dispositioned. For example, there was one issue regarding a plant individual who exhibited signs of aberrant behavior while on

shift. Although this concern was documented by the ECP staff, a formal case record

was not opened. The inspectors could find no record of whether this concern was

reviewed by the security staff as required by the site Security plan. Subsequently, the inspectors verified that this had occurred; however, the lack of a written record made it somewhat difficult to confirm. The ECP staff acknowledged this issue and was

developing corrective actions. However, due to the potential to release confidential

information, this observation was not captured in the CAP. Findings No findings of significance were identified.

Enclosure

4OA [[6 Management Meetings .1 Exit Meeting Summary On November 23, 2009, the inspectors presented the inspection results to Mr. Wozniak and other members of the licensee staff. The licensee acknowledged the issues presented. The inspectors confirmed that none of the potential report input discussed was considered proprietary.]]

ATTACH MENT:

SUPPLE [[]]

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INFORM [[]]

ATION Attachment

SUPPLE [[]]

MENTAL [[]]

INFORM [[]]

ATION [[]]

KEY [[]]

POINTS [[]]

OF [[]]

CONTACT Licensee J. Bashor, Engineering Director L. Blunk, Operations Training Manager

A. Byers, Performance Improvement Specialist

K. Ihnen, Nuclear Oversight Manager

B. Rash, Maintenance Director

T. Simpkin, Regulatory Assurance Manager K. Taber, Operations Director J. Vergara, Senior Regulatory Specialist

H. Vinyard, Work Management Director

D. Wozniak, Site Vice President Nuclear Regulatory Commission K. Riemer, Chief, Branch 2, Division of Reactor Projects

LIST [[]]

OF [[]]

ITEMS [[]]

OPENED ,

CLOSED [[]]

AND [[]]

DISCUSSED Opened and Closed None.

Attachment

LIST [[]]

OF [[]]

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED 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 [[]]

PROCED URES Number Description or Title Date or Revision

LS -

AA -1012 Safety Culture Monitoring Revision

0 EI -

AA -101 Employee Concerns Program Revision

8 EI -

AA -1 Safety-Conscious Work Environment Revision

2 EI -

AA -101-1001 Employee Concerns Program Processes Revision

8 LS -

AA -1012 Safety Culture Monitoring Revision

0 CC -

AA -103 Configuration Control for Permanent Physical Plant Changes Revision

19 AD -

AA -2001 Management and Oversight of Supplemental Workforce Revision

6 LS -

AA -1001 Root Cause Analysis Manual Revision

7 LS -

AA -126-1007 Performance Improvement Toolbox Revision

1 CC -

AA -112 Temporary Configuration Changes Revision

14 LS -

AA -115-1004 Processing of

NER s And

NNOE 's Revision

0 LS -

AA -115 Operating Experience Procedure Revisions 3,4,5 and

10 LS -

AA -115-1003 Processing of Significance Level

3 OPEX Evaluations Revision 0

LS -AA-115-1002 Processing of Significance Level

2 OPEX Evaluations Revision 0

LS -AA-115-1001 Processing of Significance Level

1 OPEX Evaluations Revision 0

LS -AA-115 Operating Experience Program Revision

14 LOP -

HS -01 Hydrogen Seal Oil System Startup and Operation Revision

18 LOP -

HS -03 Hydrogen Seal Oil System Shutdown Revision

13 LOP -

WL -01 Filling and Venting the Lake Makeup Piping Revision

16 LOP -

WL -01 Filling and Venting the Lake Makeup Piping Revision

15 LOP -

WL -13 Filling the Makeup Line with the Makeup Pump(s) Revision

5 LIP -

RH -602B Unit

2 RHR Pump 2B/2C Flow Indication Calibration Revision 5

LS -AA-125-1002 Common Cause Analysis Manual Revision

6 LS -

AA-125-1003 Apparent Cause Evaluation Manual Revision 8

Attachment

CORREC [[]]

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ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED "Number Description or Title Date or Revision 871625 [[SSC" contains a listed "[" character as part of the property label and has therefore been classified as invalid. [Foreign Material] Accumulated Debris on Reactor Jet Pump 15 1/25/2009 732084 1A]]

DG [[[Diesel Generator] Room Vent Supply Filter High D/P 2/5/2008 727393 Unit 1 Control Rod 18-39 Inoperable 1/27/2008 727361 Unit 1 Control Rod 18-23 Inoperable 1/26/2008 721332 Unit 1]]

RR [[[Reactor Recirculation] Flow Change 1/11/2008]]

970547 NOS [[[Nuclear Oversight] Identifies]]

PI&R [[]]

FASA [[[Focused Area Self-Assessment] Plan and Report Issues 9/25/2009 954832]]

NOS [[]]

ID [[:]]

CAPR 872750-14 Closure Issues 8/18/2009

945993 LOA -

PWR -101 Reference Error 7/10/2009 919749 Insufficient

CA Closure Documentation 1/23/2009 901425

CCA Actions not Created by Department 11/26/2008

899233 IR 891213 and

IR 891204 Incorrectly Closed to One Another 3/29/2009 680941 Off Scale Control Room Reading 10/6/2007 710857 Worker Alarmed

MAF Portal Monitor 12/12/2007 694587 Low Level Issues

EP Drills 3rd/4th Quarter Facilities 9/26/2007 709901

6 MREM Emergent Dose was Received 12/10/2007 710836 Security-Weapons Cabinet at India Needs Anchored 12/12/2007 711281

LS -AA-115 Review Needed for

OE 25417 12/12/2007 742353 Multiple

TSI [[]]

OK [[]]

LED 's not Lit 2/28/2008 731386 Reactor Building High Rad Alarm 2/4/2008 721355 Unit

2 HWC [[[Hydrogen Water Chemistry] System Trip Due to High Hydrogen Pressure 1/12/2008 721319 Received Unexpected Unit 1]]

CRD [Control Rod Drive] HCU [Hydraulic Control Unit] Alarm for

Rod 42-51 1/12/2008 720249 Unexpected U1

CRD Accumulator 54-23 Alarm 1/10/2008 872502 Shaw-Pipefitter Received Dose Rate Alarm in Drywell 1/26/2009 953952 Security-Vehicle Discovered Operable Without Key 8/16/2009 933571 Security Explosive Detector #1 and #2 Not Working Properly 6/21/2009 876268 Security-Live Round of Ammunition Declared at Check Point 2/4/2009 678960 Through Fault on L0104 Line Between Braidwood and LaSalle 9/15/2009 881434

TLD Ran Through X-Ray 2/17/2009 914174 NOS Finding in Corrective Action Effectiveness 4/30/2009

Attachment

CORREC [[]]

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ACTION [[]]

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ED Number Description or Title Date or Revision

914632 NOS [[]]

ID [[:]]

RCR [[[Root Cause Report] Checklist Answered Improperly 5/1/2009 913283]]

NOS [[]]

ID No Evidence of Valve Inspection 11/30/2007 914165

NOS [[]]

ID [[:]]

CAP Investigations Do Not Meet Some Admin Requirements 4/30/2009 848279: assignment 30 Address Issues Raised During

FASA with

RCR 641194 Provide Guidance On Documenting

OPEX Use in

CAP Investigations 10/26/2009 848279: assignment 24/01 Address Issues Raised During

FASA with

RCR 641194 Provide Guidance On Documenting

OPEX Use in

CAP Investigations 10/26/2009

840401 NRC Identified Inspection Findings in Aux Building Ceiling 11/04/2008 352075 Mass Spectrometer Duct Attachment to Cable Tray Support 7/1/2005 344802 Design Changes Required Due to Re-Location of Equipment 6/15/2005 849004

NRC Potential Finding Undersized Spray Nozzles 11/21/2008

708358 PI&R Inspection-Untimely Corrective Actions for

CSCS [Component System Cooling Water] Valve

Replacements 12/6/2007

709749 NCV [[[Non-Cited Violation] Associated with Diesel Fuel Storage Not Fully Addressed 12/10/2007 703553]]

TS B3.8.3 Fuel Oil Capacity Required for Division 3 Inconsistent 11/21/2007

699901 TS Bases 3.8.3 Fuel Oil Capacity for 7 days Inconsistent 11/12/2007 955205

NRC 2nd Quarter Inspection Report 8/19/2009

699299 NRC [[]]

ID 'd Wrong Location for New

2DG 117 Valve in

LOP -DG-09M 11/12/2007

708359 PI&R Inspection-No Site Investigation for L1R11

JP [[[Jet Pump]]]

RB [[[Riser Brace] Delays 12/6/2007 729732]]

NRC -Identified Problem 1/31/2008

735802 NRC Identifies

GAP in

FME Barrier Curtain 2/13/2008 741419 During

NRC Walkdown, Whip Restraint was Identified Loose 2/26/2008

772740 NRC 1st Quarter Inspection Report-Green Findings with One

NCV 3/31/2008 786350 Security-Training Records With Administrative Errors 6/13/2008

841567 NRC Identified Appendix R

ELBP Light Indication Abnormalities 11/6/2008

846783 NRC Triennial: Smoke Detectors Affect Any Other Functions 11/12/2008

ACE 839916 Security Negligent Weapon Discharge 7/30/2009

Attachment

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ED Number Description or Title Date or Revision

ACE 731403 Unposted High Radiation Area Identified in Unit 1 Reactor Building B

RHR [Residual Heat Removal]

Pump Room 2/4/2007

ACE 728969 Workers Instructed to Log Off

ED [[[Electronic Dosimeter] Prior to Exceeding]]

X. 4 Mrem 1/30/2008

ACE [[]]

728710 CA s fro

CCA 325231 Are Ineffective 1/29/2008

ACE 723807 Broken Fuel Bundle Spacer 1/17/2008

ACE 907825 Contamination Discovered Outside a Posted

CA [[[Contaminated Area] 4/15/2009]]

ACE 687105 Security Posting Not Properly Documented 10/19/2007

ACE 696564 Cask Shoring Makes Contact With

HIC [[[high integrity container] During Loading 11/8/2007]]

ACE 758197 L1R12 Steam Affected Dose 8.579

REM Over Estimate 4/2/2008

RCE 696281

CCA Rolled Into Root Cause Following Management Challenge (Modifications Not Fully Incorporated due to Lack of Clear Standards) 11/8/2007

RCE 872750 Unit 2 Refuel Bridge Mast-Braided Wire Cable 1 of 2 Failed 1/27/2009

RCE [[]]

752478 EP Pre-Exercise

DEP Failure to Classify in Timely Manner 3/19/2008

RCE 924205

RR [[[Reactor Recirculation] Ganged Controller Malfunction 5/27/2009]]

RCE 868704 Elevated Dose Rates Identified During L2R12 1/19/2009 924999

MRC Directed

IR from

EACE Review: 1B

HD [[[Heater Drain] Bearing Failure 4/4/2009 927524]]

MRC Rejection of

ACE 908791

EHC Software Mod Not Performed 6/3/2009

940703 LAS [[]]

VE Root Cause Does not Address All Potential Causes 7/10/2009

963546 RA -

FRPT Deficiency-IR 848279-Issues with

RCR 641194 9/3/2009 916994 Ineffective

CAPR Associated With

LVDT Failure

RCR 5/7/2009

CCE 882701 Investigate Documentation Issues For Past 9 Months 2/19/2009

CCE 676417 Adverse Trend in Radiation Protection Performance Indicator 9/26/2007

CCE 914174

NOS Finding In Corrective Action Effectiveness 4/30/2009

CCE 901038 Online Dose Estimating Accuracy Needs Improvement 4/1/2009 899020 Declining Reliability of Radiation Monitors Across Fleet 3/28/2009 936524 System

IQ Assessment Report 6/29/2009 898613 Operations Identified Adverse Trend 1(2)PL15J and 1(2)PL75J 3/27/2009

Attachment

CORREC [[]]

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ED Number Description or Title Date or Revision

CCE 827168 2

PL 15J Trouble In Main Control Room 10/6/2008

CCE 693124 Rad Monitor Trend Pull

ID 's Need for Further Investigation 11/1/2007 894269

2PL 75J Particulate Channel Rad Hi Alarm 3/18/2009 844159

NOS [[]]

ID Enhancement for New Fuel Transfer Basket 11/12/2008 704754

NOS [[]]

ID [[]]

FPR [[[Fire Protection Report] Descriptions, Drawings, and Pre-Fire Plan Issues 11/28/2007 692354 U2]]

SFP [[[Spent Fuel Pool] Boraflex Panel Degradation Projections through 7/1/08 10/31/2007 880430 L2R12 Shaw Performance Common Cause Analysis (]]

AT 865420-02) 2/13/2009

798029 NOS [[]]

ID Finding Refrigerant Control Deficiencies 7/16/2008 892574 1C

CW [[[Circulating Water] Pump Failure to Start, Then Overcurrent Conditions 3/13/2009 859439 L2R12 Late Work Order Generated from]]

PM 12/22/2008

856855 EP [[]]

FASA 843943-Deficiency in Augmentation Drills Time/Day 12/16/2008 759725 Break In Lake Make Up Line Following System Pump Start 04/05/2008 799885 Perform Root Cause On Unit

1 MDRFP Work Window 07/24/2008 756083 Training

INPO [[]]

ATV Identified

OJT /TPE As Team Identified Finding 03/28/2008 916375 Technician Performed Task Without Qualification 05/06/2009 889582 Adverse Trend In

MMD Performance 03/06/2009 889584 Adverse Trend In

EMD Performance 03/06/2009 889592 Adverse Trend In

IMD Performance 03/06/2009 693812 Labeling Discrepancy During 1

VX 08C Troubleshooting 11/02/2007

735952 OSHA Recordable-

WELDTE C 02/14/2008 737285 Shaw- 3" Line Incorrectly Identified in Minor

WO Revision 02/16/2008 738459 Generator Seal Oil Ingress 02/19/2008 836359 Leak Work Off Curve Is Off Track 10/27/2008 852498

NOS [[]]

ID [[: Corrective Actions For Transient Combustible Issues 12/04/2008 874657 Shaw - Sea Van Slides Off Of Truck Backing Into Refuel Pad 02/01/2009 878589 Coordination Issue Between Turbine Roll and Switching 02/10/2009 911322 Vibration Analysis Identifies Wiped Bearing(s) On 0]]

VL 03C 04/24/2009

665602 OPEX - LaSalle County Station

SME Review of OE25373 08/28/2007

Attachment

CORREC [[]]

TIVE [[]]

ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Number Description or Title Date or Revision 633803 Wiring of

STS Controller 0

TIC -VC002 Does Not Match Drawing 05/25/2007 633816 Wiring for

STS Controller 0

TIC -VC045 Does Not Match Drawing 05/25/2007 633809 Wiring for

STS Controller 0

TIC -VC003 Does Not Match Drawing 05/25/2007 885736 Troubleshooting A Controller Issue 02/26/2009

771796 STS Controller Mod Enhancements 05/05/2008 889586 Adverse Trend In

IMD Performance 03/06/2009

858932 FME Plug Left In

CRD 10-11

SSPV Exhaust Port 12/21/2008

CCA 889592-02 Adverse Trend In

MWP Performance 03/18/2009

RCE 756083 Improper Implementation of Electrical Maintenance

OJT /

TPE 04/25/2008

CCA 889582-02 Adverse Trend in

MMD Performance 04/01/2009

RCA 916375 Unqualified

IMD Technicians Performed

LIS -

WS-201, Unit 2 Service Water Effluent Monitor

Calibration. 05/05/09 RCA 799885-03 Motor Driven Reactor Feed Pump Work Window Scope Expansion due to Less than Optimal Pump

Internal Component Design Specifications 07/20/2007

CCA 889586-02 Low Level Performance Issues in

IMD Performance 04/03/2009

RCA 759725 Lake Makeup Line Leakage Due to Procedure Placekeeping Error 04/05/08

CCA 889584-02 Low Level Performance Issues in

EMD 03/27/2009

ACE 836359 Leak Work Curve is Off Track 10/27/2008

ACE 735952 Lost Time Accident- WeldTech Pipe Filter Struck by Tool 07/13/2008

ACE 693812 Unit 1 24/48

VDC System B Battery Room Exhaust Fan Running with Clearance 11/02/07

ACE [[]]

858932 FME Plug Left In

CRD 10-11

SSPV Exhaust Port 12/21/2008

ACE 911322 Vibration Analysis Identifies Wiped Bearings(s) on

0VL 03C 04/24/2009

ACE 878589-04 During Initial Turbine Roll Prior to Synchronization the Unit2 Turbine Tripped on Generator Lockout. 02/09/2009

ACE 874657-04 Cargo Container Slides Over the Side of a Flatbed Trailer 01/31/2009

ACE 852498-06 Inability to Arrest the Adverse Trend in the Transient Combustible Control 01/11/2009 ACE 737285 Condensate Booster System Line Incorrectly Identified and Removed 02/16/2008 492926 Assignment 2 Perform a Common Cause Analysis on Rod 26-35 double notch on withdraw. Validate latest revision

of

LS -

ASA-125-1002 for CCA format. 9/1/2006 496876 Control Room Indication Bands Differ 6/5/2006

Attachment

CORREC [[]]

TIVE [[]]

ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Number Description or Title Date or Revision 496876 Assignment 2 Operations Services to Evaluate Referenced Indicators and Document Appropriate Bands for

Incorporation in

T& [[]]

RM with Assistance from

Engineering as Required 9/21/2006 716812 Assignment 4 For Finding 2, verify all actions are complete and appropriate to prevent a future finding (IR 663732) 3/19/2008 764450 Assignment 2 Perform Common Cause Analysis on Reactivity management Performance Indicator Adverse

Trend. Validate latest revision of

LS -

AA-125-1002

for

CCA format. 5/23/2008 507829 Control Room Indicator Differences (Part 2) 7/10/2006 678869 1B

DG Cooling Strainer Stuck in

BW When System is in

STBY 10/2/2007 679684 U-2 Drywell Cooler Condensate Flow Rate Erratic Indication 10/4/2007

680151 RWLC Level Setpoint Set Down Ramping Out too Soon upon Reset 10/4/2007 681645 Trng: 2

ILT Students Fail Systems Final Exam 10/8/2007 681658 Trng:

INPO Identifies Gap to Excellence in

SIM [[Critiques 10/8/2007 681731 Possibility of New Fuel Failure on LaSalle Unit 1 10/8/2007 681885 Domestic Water Underground Valve Operator Box Full of Debris 10/9/2007 682781 1B Diesel Generator Load/Speed Drifts 10/10/2007 682796 1B Diesel Generator Voltage Regulator Adjustment Erratic 10/10/2007 683328 A]]

VC Refrigeration Compressor Inop Due to Short Circuit 10/11/2007 683695 Received

PPC Alarm for 'A'

RHR [[]]

INOP 10/12/2007 684937 2B

DG Fuel Oil Sample Results 10/15/2007 696832

NRC Preconditioning Question on 1-16-07 2E51-F019 Cycling 11/9/2007

698423 ERO Exam Security Issue During Annual Requal training 11/13/2007 707328 Check-in Opex 12/4/2007 716812

NRC Inspection Report 2007-004 - Green Findings and One Asso (NCV) 12/31/2007 727361 Unit 1 Control Rod 18-23 Inoperable 1/27/2008

729156 NRC Insp

RPT 2007-006 - Green Findings Associated

NCV s 1/30/2008 735550

NRC Insp

RPT 2007-005 - Green Finding and Associated

NCV 2/13/2008

741941 MSR Low Load

VLV 1B21-RSLLV2 Full Closed.

RSLLV 2 Full Open 2/28/2008 744606 Fluctuations Observed in Instantaneous Reactor Power 3/4/2008 748777

NOS ID: Porc Issues 3/12/2008

Attachment

CORREC [[]]

TIVE [[]]

ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Number Description or Title Date or Revision

759538 NRC -Identified:

MSIV Preconditioning 4/4/2008 764450 Reactivity Management Performance Indicator Adverse Trend 4/17/2008

784631 NRC Identified - Unit 1

SBGT Line Contact with Scaffold 6/9/2008 786762 U2 in Drywell Inlet Pressure Low Alarm 6/16/2008 795700 Roof Runoff Water Pooling on Top of

SEC /

TSC [[]]

DG Storage Tank 7/11/2008 803468 Request

CCA be Performed on Configuration Control Events 8/4/2008 808859 1C

RHR Suction Valve Tripped Thermal Overload 8/20/2008 812175

NRC -Identified - Air Leakage Past Watertight Door 17 8/28/2008

815803 NRC -Identified:

CRD Drive Water

PCV Bypass 9/9/2008 818563 Observed Increase in U2 Offgas Pre-Treat

XE -133 Activity 9/16/2008 819234 2B21-F016 & 2B21-F019 Not Tested 9/18/2008 823046 Failed

PMT For

WO # 384652, 2B Fuel Pool Cooling

PP 9/26/2008 823530 Exceeded Thermal Limit During L1M18 Shutdown 9/28/2008 827452 Perform Root Cause Investigation for L1C12 Fuel Failures 10/7/2008 828198

NOS [[]]

ID D Operations Declining Performance Trend 10/8/2008 833268

SBLC Solution Temperature Low 10/20/2008

837037 SBLC Solution Tank Temperature Low 10/28/2008 839821 Water in

TSC /IS

DG Storage Tank Sample 11/3/2008 843802

CRD 26-35 High Temp Alarm 11/12/2008 844283 Unexpected Group

1 MSIV Half-Isolation Signal 11/12/2008 846571 "A"

RR Pump Oil Level Alarm Causing Div 1 125V Ground Alarm 11/18/2008

847325 LOS -

DG -M2 Requires Procedure Change 11/19/2008

848993 NRC Potential Finding; Transient Combustibles 11/24/2008 855280 Transient Combustible Compliance Issues 12/11/2008 855678 Ice Buildup on Top of the

TSC /SEC

DG Fuel Oil Storage Tank 12/12/2008 856949 U-1

MSL Hi Rad Alarm Spike 12/16/2008 856961 1C11-R600 U1

CRD [[]]

FCV Oscillating in Auto 12/16/2008

857522 NRC -Id'D: Reported Unavailability for

RHR When Not Required 12/17/2008

861035 NRC -Identified - Water Identified on a

VC /VE Platform 12/29/2008 863045 Operations Crew 6 Clock Reset 1/6/2009 864514 2A

RR [[]]

FCV Drifting While Locked-Up and Pumps Off 1/9/2009

Attachment

CORREC [[]]

TIVE [[]]

ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Number Description or Title Date or Revision 865886 Div 2 Visual Annunciator Power Supply Failure 1/13/2009

866819 CA Management Review Completed Late 1/14/2009 868063

NRC -Identified - Standing Order Not Screened

IAW 50:59 10/17/2007 868501 Control Rod 34-59 Took 20 Minutes to Insert 1/19/2009 872750 U2

RFB Mast - Braided Wire Load cable 1 of 2 Failed 1/28/2009 876016 A

OB [[]]

MSIV Accumulator Fails Drop Test 2/4/2009

881009 EHC System

HYD Fault Setting Incorrect 2/16/2009 883503 Untimely

IR Resolution 9/21/2009 889586 Adverse Trend in

IMD Performance 3/6/2009 898146 Additional Discrepancies with

ISI Documentation 3/26/2009 900378 Hi-Rad Area around cask well drain needs to be disassembled and removed 3/31/2009 902423 Operator Work Around Board Meeting Results 4/3/2009 910096

NRC -Identified Dry Sight Glass for

VG Loop Seal 4/21/2009 919000 Perform a

CCA for Level 5 Rm Events - 2008 5/13/2009

919624 ACE Requested for

IR 908769,

RO - Mode Switch Issue 5/14/2009 921752 2A

RR [[]]

FCV Actuator Seal Leakage 5/19/2009 923160 Unit 1 Scram Due to 1W

MPT Lightning Arrestor Failure 5/22/2009

924545 CH Identifies Possible Trends in Recent

HU Performance 5/27/2009 925331 Adverse Trend in Even Free Clock Resets at LaSalle 5/29/2009 926304 Color Banding between Units does not Match 6/1/2009 926589 1B

RR Pump Outer Seal Degrading 6/2/2009 930540 Request

CCA on LaSalle Configuration Control Events 6/12/2009 934253 Observed Increase in U1 Offgas Pre-Treat Activities 6/23/2009

955588 NRC Question on

ARI Initiation During U2 Scram 8/20/2009 956315 Unit 1 and

2 DEHC Surveillances Not Performed 8/21/2009 990437 Proc. Comp. Not Capturing Rod Moves During U-2

CRD Cycling 11/8/2009

993280 NRC [[]]

IDD - Effectiveness of Performance Indicators Questioned 11/13/2009

995883 NRC [[]]

ID [[:]]

WO Not found for High Radiation Barrier Removal 11/19/2009 995957 Contingency Package Left Open for Extended Period 11/19/2009 683820

CDBI Lessons Learned

LOCA Block Start Calculation 10/12/2007 691865 2B

RHR Seal Cooler Has a Low Flow Rate of 10.2 GPM 10/30/2007

Attachment

CORREC [[]]

TIVE [[]]

ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Number Description or Title Date or Revision 692247 Conflicting Procedures Need Revision 10/31/2009 702329 Wrong Transducer Used for Test Results in Bad Data 11/21/2007

705226 PI&R Insp -

NRC Identified the Need for Better Documentation 11/29/2007 706551 Applicability of Dresden

MOV Concern to LaSalle 12/3/2007 707882 Plant Walkdown with

NRC 12/6/2007 710706 1B

DG Oil Cooler Outlet Temp Gauge 1E22-R531 Reads Low 12/12/2007 711140 System Trending Identifies Margin Issue 12/13/2007 714115 Revise Procedures

LIS -PC-121(221) 12/20/2007 716242 Design Eng

ID s Non-Conservative Step in

CC -AA-112 Rev 12 12/28/2007 728597 1B21-F513B Moderate Packing Leak 1/29/2008 728626

1ES 002 Severe Packing Leak 1/29/2008 737253 Engineering Not Following Procedure

ER -AA-340-2000 as Written 2/16/2008 770555 Hydrogen Found in Bearing 10 Casing 5/1/2008 791008 1E12-F042B Examine

MOV Motor for Magnesium Rotor Degradation 6/27/2008 796221 1

FP 125

RB Ring Header Stop Valve Minor Leak 7/14/2008 836452 U1 Small

RCIC Turbine Steam Leak Previously Identified 10/27/2008 852332 Triennial

EH&S Audit 2008 Findings and Recommendations 12/4/2008 864964 Extent of Condition Review for Unit 2 Spent Fuel Pool 1/9/2009 888535 Calibrate 2

FI -FC038 Before Performing

LOS -

FC -Q1 on 5/25/2009 3/4/2009 912034 Replace the 1E12-F064C Valve in L1R15 4/27/2009

926938 OE on Jet Pump Slip Joint Clamps Applicable to

LSCS 6/2/2009

948170 NRC -Identified: No Emergency Restoration Att for Los-

SC -Q1 7/31/2009

953484 NRC Question:

SBLC Availability During Surveillance 8/14/2009 955487 Boroscope

MOV Motor for 2E12-F024B in L2R13 8/20/2009 968594 Active Oil Seepage from Thrust Bearing Oil Return Box Cover 9/22/2009 986109

RM - Suspended U-1

RR [[]]

HPU Subloop Swap

PMID 's 10/29/2009 987190 B1

RR [[]]

HPU Subloop Discharge Pressure Found High 11/1/2009 988238

CAPR Unable to be Complied with, Needs Revision 11/03/2009

Attachment

CORREC [[]]

TIVE [[]]

ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Number Description or Title Date or Revision

ACE 736609 Water Issues from Valve Bonnet Due to Insufficient Draining 2/14/2008

ACE [[]]

737220 IVVI (In-Vessel Visual Inspection) Examinations Performed with Expired Visual Acuity 2/7/2008

ACE 737253 System Engineering Failed to Use Empirical Data When Determining Tube-Plugging Limits 2/16/2008

ACE 757852 Spurious Technical Support Center Emergency Makeup Unit Start 4/1/2008

ACE 775338 2B Diesel Engine Trip Up with Lockout Reset 5/14/2008

ACE 851075 Late Identification of Degrading Trend on Control Valve #3

LVDT 12/1/2008

ACE 869141 Unit-2

RPV Head Lift Stopped Due to High Indicated Weight 1/20/2009

ACE 870845 Replacement of 0

VE 04CA Compressor Due to Anomalous Head Temperatures 11/19/2008

ACE 909987

NOS Identified Numerous Deficiencies in the Implementation of SystemIQ 2/20/2009

CCA 890184 E-5 to E-1 Stability Due to Negative Trend 4/8/2009

CCA 905332 Historical

EHC Pump Performance 4/30/2009

CCA 914651 Human Performance Issues Identified in

NOS Review 5/21/2009

RCR 742287 Failure of Turbine Speed Detection System While Synching the Generator to the Grid 4/28/2008

RCR 825873 Excessive Hydrogen Leakage on Unit 1 Main Generator Hydrogen Seal 10/30/2008

RCR 881009 Electro-Hydraulic Control (EHC) System Hydraulic Transmitter Fault Setting Incorrect Due to

Ineffective Review of Software File Changes 2/5/2009

RCR 920759 Abnormal Knocking Noise and High Vibrations on 0

VE 04CA Refrigeration Compressor 7/9/2009

RCR 923335 Untimely Recognition that No Steam Packing Exhauster Blower was Running 7/2/2009 886819 2C

CD /CB Min Flow Failed Open,

MCR Unexpected Alarm 2/28/2009 824848 Rod 34-31 Withdraw Speed is Too Fast 10/1/2008 683288 Thermography Identifies Minor Hotspot in 1W

MPT Cabinet 10/11/2007 687932 A

VE Oil Temperature Has Approached 155 Degrees F 10/22/2007 688935 Part 21 for 2B

DG Air Start Solenoid Valve Never Installed 10/24/2007 696350 Bolted Bus Connections May Need Replacement 11/08/2007 699827 Emergent Work Impacts Work Planning Daily Planning 11/15/2007 709276

0VE 09

YB Damper Failure 12/09/2007

713811 FT -

VR026 Loop May be OOT 12/19/2007

Attachment

CORREC [[]]

TIVE [[]]

ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Number Description or Title Date or Revision 713225 Potential Thread Engagement Issue on 2B D/G Emergency Stop 12/18/2007 723586 Unknown High Conductivity Input in

RW Floor Drain 1/17/2008 729396

NOS [[]]

ID Issues Regarding the 1A 24

VDC Battery Charger 1/31/2008 736409

0PL 31J High Rad Area is Contaminated 2/14/2008 740511 Apparent Seat Leakage by 1E12-F064B 2/25/2008 741586 No

EPN [[]]

FW Process

SPL Valve Isolation Valve Doesn't Isolate 2/27/2008 754492 Nesting on B Radwaste Crane Intermittent Issues 3/25/2008

763535 ECP Probe for Unit 1 is Degrading 4/15/2008 778769 Did Not Receive

ERO Page 5/23/2008 785154

2VD 05C Tripped 6/11/2008 861648 Temporary Catch Basin Used As A Permanent Solution 12/31/2008 863162

OPEX Review of Susquehanna

OE 28038 1/06/2009 866492 Did Not Receive

ERO Page on 1/12/2009 1/14/2009

868523 SRM A Signal to Noise Ratio 1/19/2009 873905 Particulate Slightly Elevated in

RCIC Turbine Oil 1/30/2009 934253 Observed Increase in U1 Offgas Pre-Treat Activities 6/23/2009 934958 A Train

VE Inleakage Into

CRE is Greater Than Allowed 6/24/2009 964856 Inaccurate Does Estimation on Work Task 9/14/2009 965049

1PA 06J Westinghouse 7300 Panel 9/15/2009 969345 Classification of

MS Branch Piping & Components 9/23/2009 990192 U-1 Turb Bldg

CAM Alarm 11/7/2009 991337 Miscellaneous Automatic Control System Power Failure 11/10/2009

ACE 681645

2ILT Students Fail Systems Final Exam 12/07/2007

ACE 696564 Cask Shoring Makes Contact With

HIC During Loading 12/14/2007

ACE 695614 Drywell Floor Drain Sump Fill-Up Rate/Pump Discharge Flow Recorder Failed 12/28/2007

ACE 748777

NOD [[]]

ID 'd Concerns With the Implementation of

LS-AA-106, Plant Operations Review Committee

(PORC) 4/30/2008

ACE 769736 The 2A

DG Room Exhaust Damper

2VD 11

YA /B Did Not Open As Expected 7/10/2008

ACE 869141 Unit-2

RPV Head Lift Stopped Due to High Indicated Weight 2/26/2009 ACE 890180 New Disc Installed in 2B21-F032A With Potential Weight Difference 4/16/2009

Attachment

CORREC [[]]

TIVE [[]]

ACTION [[]]

PROGRA M

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Number Description or Title Date or Revision

ACE 900673 Low Service Water Pressure and Shutdown of 1A Service Water Pump Due to

FME (Foreign

Material Exclusion) Concerns From Dive Activity

in the Service Water Tunnel 5/05/2009

ACE 908791

EHC Software Modification Not Performed 6/09/2009

ACE 954664 1

ES 065 Stem Disc Separation 10/01/2009

ACE 969479

IMD Technician Exceeded the

GL 82-12 Overtime Guideline as Specified in

LS -AA-119 10/29/2009

RCE 827452 L1C12 Nuclear Fuel Failures 11/06/2008

OPERAT ING

EXPERI [[]]

ENCE Number Description or Title Date or Revision

521373 OE 23020 Potential for

RCIC Water Hammer- Nine Mile Point 2 08/18/2006

578711 MOV [[]]

OPEX [[]]

OE 23797- Corporate Engineering Action Plan 01/12/2007 665602

OPEX - LaSalle County Station

SME Review of

OE 25373 08/28/2007

669975 OPEX - LaSalle County Station Review of Green

NER - 07-057 09/11/2007

674693 IN 2007-24 Summary of 2006

FFD Performance Reports 09/24/2007 678868

IN 2007-29 Operability Effects of Temp Scaffolding 10/02/2007 684958 Fleet Review of Operating Experience Report 24759 10/15/2007 719685

NER [[]]

NC 07-044 Rev 1 Red- Essential Service Water Piping 01/09/2008 736805

NER [[]]

NC -08-007 Yellow Fleet Actions-

TMI High Rad Area Event 02/15/2008

737688 NER [[]]

NC -08-009 Yellow- Security Force Members Lapsed Quals 02/18/2008

904247 IN 2009-04 Age-Related Constant Support Degradation 04/07/2009 830408

RIS 2008-23

GTRI for High Risk Radiological Material 10/13/2008

OE07-001 Operability Evaluation, Reactor Vessel Jet Pump 19 Instrumentation Line (IR 581231) Revision 2 OE07-002 Operability Evaluation, Emergency Diesel Generators, Diesel Fuel Storage Tanks, Diesel Fuel Day Tanks: Use of Ultra-Low-Sulfur Diesel

will Require Increased Fuel Storage Volume

(IR 612524) Revision 5

Attachment

OPERAT [[]]

ING [[]]

EXPERI [[]]

ENCE Number Description or Title Date or Revision

OE 08-003 Operability Evaluation, Unit 1 and 2 Division 3 Batteries 1

DC 18E and 2DC18E, Unit 1 and 2

HPCS Pump Breakers 1

AP 07E (S35) and

2AP 07E-004 (S35) Alternate Breaker Sequence Possible during a

LOOP -LOCA (IR 792505) Revision

1 OE 08-005 Operability Evaluation, 0

VE04CB, Refrigerant Compressor subject to internal damage due to

liquid refrigerant slugging during startup Revision

5 OEE 08-02 Operability Evaluation, Unit 1 and 2 Diesel Generators Air Inlet Temperature Rating Issues (

IR 744660,

IR 746204) Revision 0

AUDITS ,

ASSESS [[]]

MENTS [[]]

AND [[]]

SELF -ASSESSMENTS Number Description or Title Date or Revision

NOSA -

LAS -09-03 Security Plan,

FFD , Access Authorization, and

PADS (AR 858488858488 Revision

2 NOSA -

LAS -09-01 Corrective Action Program (AR 859231859231 Revision

2 NOSA -

LAS -09-06 LaSalle Radiation Protection Program (AR 862840862840 Revision 0 848279-03 Preparation for

NRC [[]]

PI&R Inspection 11/2-20/2009 848253-03 Security 848244-02

SOER [[[Significant Operational Event Report] 01-1 Implementation Assessment 878991-02 Employee Concerns Program Check-In Assessment 10/2009 917330-02 Safety Culture Monitoring 6/5/09 Executive Review of Exelon Nuclear's Learning Programs August 2009 707328-04 Operating Experience Results Measurement Review 08/27/09 707328-04 Operating Experience Check-In Assessment 12/17/08 713021 Maintenance Functional Area Audit 2/6/2008 848238 Maintenance Rigging and Lifting Program Check-In Assessment 3/31/2009 912557-01 Mechanical Maintenance Document of Work Issues Check-In Assessment 12/15/2009 912590-01 Check-In Assessment to Review Documentation of Work Issues 12/29/09 908683-01 Low Level Performance Issues in]]

IMD 12/31/2009 907966 Management Directed Assessment Plan Maintenance Red Rating 09/15/09

2007 AFI [[]]

CM.4-2 Fuel Failures Check-In Self-Assessment Report (861374) Performance Gap Resolution in L2R12 outage 12/30/2008

Attachment

AUDITS ,

ASSESS MENTS

AND [[]]

SELF -ASSESSMENTS Number Description or Title Date or Revision

ACE 681645-02 2

ILT Students Fail Systems Final Exam 9/28/2007

ACE 744606

ACE - Investigation Fluctuations Observed in Instantaneous Reactor Power 3/4/2008

ACE 919624 Three Reactor Operators Fail to take Mode Switch to Shutdown during a Training Scenario 5/14/2009

CCA 919000-02 Level 5 Reactivity Management Issue Trends 6/4/2009 CCA 924545-02 Common Cause Analysis : Data Review of Items that Contain a Human Performance Element in

LaSalle Chemistry in 2009 6/18/2009

CCA 925331-02 Common Cause Analysis: Adverse Trend in LaSalle Event Free Clock Resets 1/1/- 6/1/2009

CCA 930540-02 Common Cause Analysis of LaSalle Configuration Control Events 9/2007 - 6/2009

NOSA -

LAS -07-07 Operations Functional Area (AR 576590576590 11/12 - 11/30/2007

RCE -727361-03 Unit 1 Channel Distortion Root Cause Report 2/23/2008

RCE 823530 Root Cause Investigation: Unplanned Thermal Limit

LCO Entry During L1M18 Shutdown 11/11/2008

RCE 827452-02 Root Cause Investigation: L1C12 Nuclear Fuel Failures 11/6/2008

RCE 923160 Root Cause Investigation: Ground Across the Unit 1 West Main Power Transformer Surger (Lightning) Arrester resulting in a Scram 7/8/2009 707328

OPEX Check-In Assessment 12/17/2008 828627-03

2008 CREHP Program Assessment 1/21/2009 862824 Engineering Design Control Audit

NOSA -LAS-09-05 8/20/2009 713027 Engineering Programs and Station Blackout Audit Report

NOSA -

LAS -08-05 7/2/2008 861376-01 Plant Systems - Performance Monitoring Check-In 6/30/2009 848177-02

ISI Program Preparedness for L2R12

NRC Inspection 1/29/2009

CONDIT [[]]

ION [[]]

REPORT S

GENERA TED

DURING [[]]

INSPEC TION Number Description or Title Date or Revision

993280 NRC -

IDD -Effectiveness of Performance Indicators Questioned 11/13/2009

996319 NRC [[]]

ID Review of Maintenance Documentation

CCA #882701 11/20/2009 995883

NRC [[]]

ID [[:]]

WO [[[Work Order] Not Found for High Radiation Barrier Removal 11/19/2009]]

996372 NRC [[]]

ID: WO 605660 Closed with No Work Performed 11/20/2009

Attachment

CONDIT [[]]

ION [[]]

REPORT S

GENERA TED

DURING [[]]

INSPEC TION Number Description or Title Date or Revision 995957 Contingency Package Left Open for Extended Period 11/18/2009

989540 NRC [[]]

ID 'D: Previously Identified Issue Waiting Resolution 11/5/2009

989527 NRC [[]]

PI&R 1(2)PL15J and 1(2)PL75J Reliability 11/4/2009

988746 NRC [[]]

ID [[:]]

CC -

AA -112 Note Not Included in T-MOD Work Packages 11/4/2009 995934 Documentation Issues With Regard to

CAP /

OPE x Investigations 11/19/2009

995581 NRC Recommendation Regarding

OPE x Use In

CAP Investigations 11/19/2009

MISCEL LANEOUS Number Description or Title Date or Revision 816066 (A)(1) Action Plan Development

RR -02 (Subloops) Revision 0 930416 (A)(1) Action Plan Development

AN -01 (Unit 2) Revision 0 891409 (A)(1) Action Plan Development

RE -03 Revision 0

NES -MS-04.1 Seismic Prequalified Scaffolds Rev.

5 IR 995336 Exelon Nuclear Issue - Statement of Confirmation:

NRC Id;

IR Actions Not Smarter 11/18/2009 List of OpEvals, Associated

IR and Status 2003 - 2009 Plan of the Day 11/4/2009

SOC Package 11/13/2009 Summary of Open Work Arounds and Challenges 11/2007 - 11/2009 Work Orders Number Description or Title Date or Revision

WO 01240425 2A

OTBD [[]]

MSIV 'Slow Test'

P.B. Sticks 10/28/2009

WO 1071579 1B Diesel generator Load/Speed Drifts: Adjust Friction Drive, Replace Lid 7/2/2008

WO 1186297 1A

RR [[]]

FCV Movement with No Operator Input 1/14/2008

WO 844595 Fleet Work Package Documentation Continuation 806424 11/13/2008 Temporary and/or Permanent Plant Modifications Number Description or Title Date or Revision

EC 369811 Remove Internals from

EFCV 1G33-F389E Revision

0 EC 369496 Install Vibration Monitoring for Main Turbine Control Valves

CV2 and CV4 Revision 0

Attachment Temporary and/or Permanent Plant Modifications Number Description or Title Date or Revision EC 367757 Hook Up Instrumentation to Gather Data to See if an Offset is a More Viable Option for Main

Turbine Back Pressure Indicators 1/10/2008

EC 371362 Bypassing the Reactor Recirc Flow Control Valve

LVDT to

RVDT Mismatch Alarm. The

RVDDT Signal has Degraded. 7/10/2008

EC 373691 Correct Various P&

ID Drawing Errors Revision

0 EC 376196 Reduce

OPS Burdens by Modifying

RHR Interlocks 7/8/2009

EC 362940 Install Caldon Non-Intrusive Flow Measuring Instrument in Support of

MWE Recovery Plan Revision 0

EC 369498 Replace Double Block Drain Valves 1B21-F032A/B/C & 1B21-F303A/B/C With Equivalent Two (2) Single Valve Assemblies in Series Using Drawing

IT -7000-M-

PP -32 Installation Details Revision

1 EC 376996 1(2)

PA 06J Westinghouse 7300 Panel-Power Supplies Revision

0 EC 348186

DWFDS Flow Tube Modification Revision 1

Attachment

LIST [[]]

OF [[]]

ACRONY [[]]

MS [[]]

USED [[]]

AR Action Request

CAP Corrective Action Program

CFR Code of Federal Regulations DRP Division of Reactor Projects

ECP Employee Concerns Program

IN Information Notices

IP Inspection Procedure

MRC Management Review Committee

NCV Non-Cited Violation NOS Nuclear Oversight

NRC U.S. Nuclear Regulatory Commission

OE Operating Experience

PARS Publicly Available Records

PI&R Problem Identification and Resolution

SC [[]]

WE Safety-Conscious Work Environment

WO Work Order

C. Pardee -2-

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 the

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/

Kenneth Riemer, Chief

Branch 2

Division of Reactor Projects Docket No. 50-373; 50-374

License No.

NPF -11;

NPF-18

Enclosure: Inspection Report 05000373/2009007; 05000374/2009007 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ

DOCUME [[]]

NT [[]]

NAME G:\1-

SECY \1-WORK

IN [[]]

PROGRE SS\LAS 2009

007 PIR.DO C 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 N

RIII E

RIII [[]]

RIII [[]]

NAME [[]]

NS hah:cms KRiemer

DATE 12/03/09 12/11/09

OFFICI AL

RECORD [[]]

COPY Letter to C. Pardee from K. Riemer dated December 11, 2009

SUBJEC T:

LASALL E

COUNTY [[]]

STATIO N,

UNITS 1

AND [[]]

2 PROBLE M

IDENTI FICATION

AND [[]]

RESOLU TION (PI&R)

INSPEC [[]]

TION 05000373/2009007; 05000374/2009007