IR 05000254/2016007

NRC Problem Identification and Resolution Inspection Report 05000254/2016007; 05000265/2016007

ML16305A345
Person / Time
Site:	Quad Cities
Issue date:	10/31/2016
From:	Karla Stoedter NRC/RGN-III/DRP/B1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2016007
Download: ML16305A345 (33)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 October 31, 2016

Mr. Bryan Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road

Warrenville, IL 60555

SUBJECT: QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2-NRC PROBLEM IDENTIFICATION AND RESOLUTI ON INSPECTION REPORT 05000254/2016007; 05000265/2016007

Dear Mr. Hanson:

On September 30, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a Problem Identification and Resolution (PI&R) inspection at your Quad Cities Nuclear Power Station, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed at an exit meeting on September 30, 2016, with Mr. K. Ohr and other members

of your staff. The inspectors 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.

On the basis of the samples selected for review, the team concluded that the Corrective Action Program (CAP) at Quad Cities Nuclear Power Station, Units 1 and 2, was generally effective in identifying, evaluating and correcting issues. The licensee had a low threshold for identifying issues and entering them into the CAP. A risk based approach was used to determine the significance of the issues and priority for issue evaluation and resolution. Corrective actions were generally implemented in a timely manner, commensurate with their safety significance. Operating experience was entered into the CAP when appropriate and evaluated according to procedure. The use of operating experience was integrated into daily activities and found to be effective in preventing similar issues at the plant. In addition, self-assessments and audits were conducted at appropriate frequencies with sufficient depth for all departments based on the documents the team reviewed. The assessments were thorough and effective in identifying site performance deficiencies, programmatic concerns, and improvement opportunities. On the basis of the interviews conducted, the inspectors did not identify any impediment to the establishment of a safety conscious work environment at Quad Cities Nuclear Power Station. Licensee staff was aware of and generally familiar with the CAP and other station processes, including the Employee Concerns Program, through which concerns could be raised. The team determined that your station's performance in each of these areas supported nuclear safety. Based on the results of this inspection, no finding of significance was identified.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," 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's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/

Karla Stoedter, Chief Branch 1 Division of Reactor Projects Docket Nos. 50-254; 50-265 License Nos. DPR-29, DPR-30

Enclosure:

IR 05000254/2016007; 05000265/2016007 cc: Distribution via LISTSERV

Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 50-254; 50-265 License Nos: DPR-29; DPR-30 Report No: 05000254/2016007; 05000265/2016007 Licensee: Exelon Generation Company, LLC Facility: Quad Cities Nuclear Power Station, Units 1 and 2 Location: Cordova, IL Dates: September 12, 2016, through September 30, 2016 Team Leader: R. Ng, Project Engineer Inspectors: R. Murray, Senior Resident Inspector - Quad Cities J. Rutkowski, Project Engineer J. Mancuso, Reactor Engineer L. Rodriguez, Reactor Inspector C. Mathews, Resident Inspector, Illinois Emergency Management Agency (IEMA)

Approved by: K. Stoedter, Chief Branch 1 Division of Reactor Projects 2

SUMMARY OF FINDINGS

Inspection Report 05000254/2016007; 05000265/2016007; 09/12/2016-09/31/2016; Quad Cities Nuclear Power Station, Units 1 and 2; Identification and Resolution of Problems.

This inspection was performed by four region-based inspectors, the IEMA resident inspector and the Quad Cities Senior Resident Inspector. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process" Revision 6, dated February 2016. Identification and Resolution of Problems On the basis of the samples selected for review, the team concluded that the Corrective Action Program (CAP) at Quad Cities Nuclear Power Station, Units 1 and 2, was generally effective in identifying, evaluating and correcting issues. The licensee had a low threshold for identifying issues and entering them into the CAP. A risk based approach was used to determine the significance of the issues and priority for issue evaluation and resolution. Corrective actions were generally implemented in a timely manner, commensurate with their safety significance. Operating experience was entered into the CAP when appropriate and evaluated according to procedure. The use of operating experience was integrated into daily activities and found to be effective in preventing similar issues at the plant. In addition, self-assessments and audits were conducted at appropriate frequencies with sufficient depth for all departments based on the documents the team reviewed. The assessments were thorough and effective in identifying site performance deficiencies, programmatic concerns, and improvement opportunities. On the basis of the interviews conducted, the inspectors did not identify any impediment to the establishment of a safety conscious work environment at Quad Cities Nuclear Power Station.

Licensee staff was aware of and generally familiar with the CAP and other station processes, including the Employee Concerns Program, through which concerns could be raised. The team determined that the licensee's performance in each of these areas supported nuclear safety.

Although implementation of the CAP was determined to be effective overall, the inspectors identified several issues that represented potential weakness of the program.

3

REPORT DETAILS

4OA2 Problem Identification and Resolution

This inspection constituted one biennial sample of problem identification and resolution (PI&R) inspection as defined by Inspection Procedure 71152, "Problem Identification and Resolution." Documents reviewed are listed in the Attachment to this report.

.1 Assessment of the Corrective Action Program Effectiveness

a. Inspection Scope

The inspectors reviewed the procedures and processes that described the CAP at Quad Cities Nuclear Power Station to ensure, in part, that the requirements of 10 CFR 50, Appendix B, Criterion XVI, "Corrective Action," were met. The inspectors observed and

evaluated the effectiveness of meetings related to the CAP, such as the Management Review Committee meeting and the Station Ownership Committee meeting. Selected licensee personnel were interviewed to assess their understanding of and their involvement in the CAP. The inspectors reviewed selected issue reports (IRs) across all seven Reactor Oversight Process cornerstones to determine if problems were being properly identified and entered into the licensee's CAP. The majority of the risk-informed samples of IRs reviewed were issued since the last NRC biennial PI&R inspection completed in September of 2014. The inspectors also reviewed selected issues that were more than 5 years old. The inspectors assessed the licensee's characterization and evaluation of the issues and examined the assigned corrective actions. This review encompassed the full range of safety significance and evaluation classes, including root cause evaluations, apparent cause evaluations, and workgroup evaluations. The inspectors assessed the scope and depth of the licensee's evaluations. For issues that were characterized as significant conditions adverse to quality, the inspectors evaluated the licensee's corrective actions to prevent recurrence and for issues that were less significant, the inspectors reviewed the corrective actions to determine if they were implemented in a timely manner commensurate with their safety significance. The inspectors performed a 5-year evaluation of safety-related relay failures based on input from the resident staff. These safety-related relay failures encompassed multiple risk significant systems. The primary purpose of this review was to determine whether the licensee was monitoring and addressing performance issues of safety-related

relays. A 5-year review of the aging management program was also performed to assess the licensee's efforts in monitoring and correcting age-related performance issues. Specifically, the inspectors review ed implementing Aging Management Program procedures, attended CAP meetings to observe how aging management issues were being addressed, reviewed licensee CAP documents related to aging management issues, and performed a walkdown of the high pressure coolant injection rooms to assess the licensee's evaluation of some aging management related issues of the

system. The CAP documents selected for revi ew were chosen from a list of documents that were either screened by the licensee as being related to aging management, or because they contained aging related keywords such as "corrosion" and/or "aging" in their titles. The inspectors performed walkdowns, as needed, to verify the resolution of

issues. The inspectors examined the results of self-assessments of the CAP completed during the review period. The results of the self-assessments were compared to self-revealed and NRC-identified findings. The inspectors also reviewed the corrective actions associated with previously identified NCVs and findings to determine whether the station properly evaluated and resolved those issues. The inspectors also performed walkdowns, as necessary, to verify the resolution of the issues. b. Assessment

(1) Identification of Issues Based on the results of the inspection, the inspectors concluded that Quad Cities Nuclear Power Station was generally effective in identifying issues at a low threshold and entering them into the CAP. The inspectors determined that problems were normally identified and captured in a complete and accurate manner in the CAP. The station was appropriately screening issues from both NRC and industry operating experience at an appropriate level and entering them into the CAP when applicable to the station. The inspectors also noted that deficiencies were identified by external organizations (including the NRC) that had not been previously identified by licensee personnel. These deficiencies were subsequently entered into the CAP for resolution. The inspectors determined that the licensee was generally effective at trending low level issues to prevent larger issues from developing. The licensee used the CAP to document instances where previous correct ive actions were ineffective or were inappropriately closed.

The inspectors performed a 5-year review of safety-related relay failures. As part of this review, the inspectors interviewed the system engineer and supervisor, reviewed a sample of equipment apparent cause evaluations for relay failures, IRs, operating experience, test calibration data, and Maintenance Rule status. The inspectors reviewed licensee's CAP and work management system procedures that provided guidance for trending. The inspectors concluded that safety-related relay concerns were identified and entered into the CAP at a low threshold, and concerns were resolved in a timely manner commensurate with their safety significance.

i) Observation CAP Classification Based on Plant Condition On February 6, 2014, the licensee initiated AR 1617892 for a through wall leak on a service water supply line to the 2B residual heat removal service water (RHRSW) cubicle cooler. The issue was assigned a significance level 3 in the CAP because it resulted in an unplanned Limiting Condition for Operation (LCO) entry which could lead to a unit shutdown. The issue was then assigned a "B" investigation class (Apparent Cause Evaluation) to be evaluated. These assignments were performed in accordance with CAP procedure PI-AA-120, "Issue Identification and Screening Process." On September 10, 2015, the licensee initiated AR 2553103 for a similar through wall leak on a similar line, the service water supply line to the 2A RHRSW cubicle cooler. However, that issue was assigned a significance level 4 and a "D" investigation class (no formal investigation required) because it was discovered during post maintenance testing when the RHRSW pump was already in a LCO due to planned maintenance. Since the leak in AR 2553103 did not cause an unplanned LCO entry due to the plant conditions at the time it was discovered, it was treated as a less significant issue than the leak in AR 1617892, even though both leaks were nearly identical. Therefore, the licensee's CAP process allows the significance level, and as a result, the investigation class of identified issues to be influenced by plant conditions at the time of discovery. This could lead to a significant issue being treated and reviewed as less significant simply because it was discovered during a plant condition where entry into an unplanned LCO was not warranted (i.e. during an outage). Although the licensee appropriately dispositioned the issue in AR 2553103, the inspectors identified this as a vulnerability in the licensee's CAP. It is important to correctly assign the significance level of an issue because it directly affects the level of review, and ultimately, the corrective actions assigned to address the issue. ii) Findings No findings were identified.

(2) Prioritization and Evaluation of Issues

Based on the results of the inspection, the inspectors concluded that the station was effective at prioritizing and evaluating issues commensurate with the safety significance of the identified issue, including an appropriate consideration of risk.

The inspectors determined that the Management Review Committee meetings and the Station Ownership Committee meetings were generally thorough and maintained a high standard for evaluation quality. Members of the Management Review Committee discussed selected issues in sufficient detail and challenged each other regarding their conclusions and recommendations.

The inspectors determined that the licensee usually evaluated equipment functionality requirements adequately after a degraded or non-conforming condition was identified.

In general, appropriate actions were assigned to correct the degraded or non-conforming

condition.

i) Observations Insufficient Documentation During the latest refueling outage, Q2R23, the licensee identified that 17 General Electric Type HFA relays were deficient and had not been repaired or replaced. The licensee documented in the CAP that the relays should be repaired or replaced prior to plant startup. These relay deficiencies were reviewed by the Outage Scope Panel for addition into the outage. However the outage panel decided that repair was not necessary and removed the work from the outage. No written justification was provided in the CAP and there was no Outage Scope Panel meeting notes to document why the repair was not necessary. Upon questioning by the inspectors, the licensee was able to provide an engineering evaluation that determined that the relays were not degraded enough to require repair/replacement during the refueling outage. This information was not contained in the IR when the IR was closed. Similarly, on August 20, 2014, the licensee initiated AR 1694580 due to elevated levels of contamination being discovered near the Unit 2 reactor water clean-up phase separator decant pump. The contamination was believed to be from a leak of the pump due to the discovery of dried resin near the pump. Since the pump had been recently run, the leak was not believed to be an "active" leak. The corrective action document specified that no work order was required because the pump would be decontaminated and then monitored for an "active" leak. If an "active" leak were to be discovered, a separate corrective action document would be generated. When reviewing the actions assigned for the issue, the inspectors noted that although there was an action to decontaminate the pump, there was no action to track the monitoring of the pump for "active" leakage. From discussions with the licensee, although the monitoring of the pump was not being tracked in the corrective action document, individuals involved were able to confirm that the monitoring had been accomplished and that an "active" leak had not been identified. The inspectors discussed with the licensee the importance of ensuring the CAP properly tracks and documents actions necessary to resolve identified issues. Even though the lack on documentation in the CAP was not wide spread, the inspectors did come across a number of these examples and therefore, considered the lack of complete information a weakness in the CAP. This weakness has the potential to lead to degraded or inoperable conditions not being recognized. Therefore, the licensee needs to be more vigilant to ensure that complete information is provided before a CAP item can be closed. ii) Findings No findings were identified.

(3) Effectiveness of Corrective Action Based on the results of the inspection, the inspectors concluded that the licensee was generally effective in addressing identified issues and the assigned corrective actions were generally appropriate. The licensee implemented corrective actions in a timely manner, commensurate with their safety significance, including an appropriate consideration of risk. Since 2013, outstanding corrective actions had been trending down. As of the beginning of the inspection, the licensee had 29 corrective actions open and only 2 of these were greater than 2 years-old. The inspectors sampled a number of these corrective actions in each significance level and determined that they were being tracked with appropriate level of attention to ensure their completion. The inspectors also sampled other action items and verified that the licensee did not systematically downplay the action items as non-corrective actions.

Problems identified using root or apparent cause methodologies were resolved in accordance with the CAP procedural and regulatory requirements. Corrective actions designed to prevent recurrence were generally comprehensive, thorough, and timely.

The inspectors sampled corrective action assignments for selected NRC documented violations and determined that actions assigned were generally effective and timely.

The inspectors also performed a 5-year extensive review of the licensee's implementation of their Aging Management Program. In general, the licensee was appropriately implementing their Aging Management Program at the station. The licensee was following their program and identifying aging related issues. Those issues were properly evaluated under the CAP and adequately dispositioned. Identified aging related issues were also being adequately monitored in order to identify further degradation. i) Observations Corrective Action Not Complete In NRC inspection report 2015004, the NRC issued a licensee-identified non-cited violation for the licensee's failure to have an adequate procedure for installing fuse blocks in safety-related breakers. The procedure did not provide the operators guidance to ensure the fuse blocks were fully seated. This resulted in the breaker closing springs not being charged following post-maintenance testing of the 1A residual heat removal pump breaker and the system being declared operable on August 21, 2015, when in fact, the system was inoperable. In the licensee's equipment apparent cause evaluation (EACE), the licensee stated that because not all fuse blocks were fully seated even when they were flush with the fuse block holder, some fuse blocks required additional pressure when being seated, and would actually be slightly recessed into the fuse block holder. Therefore, procedure QCOP 6500-07, "Racking in a 4160 Volt Horizontal Type AMHG or G26 Circuit Breaker," contained incomplete guidance for ensuring the fuse blocks were properly installed. The licensee's corrective actions were to revise the procedure to include discussion that the installed position for some fuse blocks would be slightly beyond flush and might require additional pressure to fully seat. Direction would also be added to pull on the fuse block after insertion to verify it was snug and fully seated. During this PI&R inspection, the inspectors reviewed the licensee's corrective actions associated with this violation. Although the licensee did add guidance in the discussion section of the procedure to provide direction on how to ensure the fuse blocks were fully inserted, Section F of the procedure that contained the execution steps for inserting fuse blocks still directed the fuse block to be "fully inserted and flush with the fuse block holder." The inspectors determined that the licensee failed to fully implement the corrective actions as stated in the EACE.

Given that the licensee had briefed all operations crews on the direction to properly insert fuse blocks into the holders and added this skill to their training curriculum for operations, the inspectors determined the likelihood of this event occurring again was minimal, and therefore determined the inadequate procedure change was a minor corrective action violation. The licensee entered this issue into the CAP as AR 2716518 and is evaluating actions for changing the procedure. ii) Findings No findings were identified.

.2 Assessment of the Use of Operating Experience

a. Inspection Scope

The inspectors reviewed the licensee's implementation of the facility's Operating Experience (OE) program. Specifically, the inspectors reviewed the OE program implementing procedures, attended CAP meetings to observe the use of OE information, and reviewed licensee evaluations of OE issues and events. The objective of the review was to determine whether the licensee was effectively integrating OE into the performance of daily activities, whether evaluations of issues were appropriate, 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, were identified and implemented in an effective and timely manner. b. Assessment In general, OE was appropriately used at the station. Industry OE was disseminated across the various plant departments. The inspectors also verified that the use of OE in formal CAP products such as root cause evaluations and equipment apparent cause evaluations was appropriate and adequately considered. Generally, OE that was applicable to Quad Cities Station was thoroughly evaluated and actions were implemented in a timely manner to address any issues that resulted from the evaluations. c. Observations Preventive Maintenance of Safety-Related Relays Since 2014, the inspectors identified at least three failures of safety-related relays that were attributed to age-related causes. In some of the failure examples, the licensee identified that there were no preventive maintenance tasks (i.e. visual inspection or contact resistance testing) performed on the failed relays. In each of these instances, the licensee corrected the issues and performed extent of condition reviews as appropriate. However, the inspectors questioned the licensee on their plan to perform a more comprehensive review of their safety-related relays, to include identification of

component age and associated preventive maintenance tasks. The licensee established the service life of their safety-related relays through their performance centered maintenance (PCM) template. The PCM template was based on Electric Power Research Institute (EPRI) Report 3002000541, "Relay Series - Specific Guidance:

Generic Service Life Analysis (GSLA)and Preventive Maintenance (PM) Templates,"

dated July 2013. The EPRI report states, in part, "The service lives in this evaluation assume that all recommended preventive maintenance, inspections, and surveillances are performed as intended." After discussing the service life of safety-related relays with the licensee, the inspectors determined the licensee had identified a list of relays to be reviewed. However, the licensee did not have a well-documented, specific, or systematic plan to identify gaps between the EPRI report and existing assigned preventive maintenance tasks for safety-related relays. The inspectors did not identify any specific instances where the licensee was not meeting their PCM template for service life. The inspectors considered this a gap in the preventive maintenance program that could potentially lead to failures.

d. Findings

No findings were identified.

.3 Assessment of Self-Assessments and Audits

a. Inspection Scope

The inspectors reviewed selected self-assessments and Nuclear Oversight audits, as well as the schedule of past and future assessments. The inspectors evaluated whether these audits and self-assessments were effectively managed, adequately covered the subject areas, and properly captured identified issues in the CAP. In addition, the

inspectors interviewed licensee personnel regarding the implementation of the audit and self-assessment programs. b. Assessment Based on the results of the inspection, the inspectors concluded that self-assessments and audits were typically accurate, thorough, and effective at identifying issues and enhancement opportunities at an appropriate threshold. The inspectors concluded that these audits and self-assessments were completed by personnel knowledgeable in the subject area. In many cases, these self-assessments and audits had identified numerous issues that were not previously recognized by the station. These issues were entered into IRs as required by the CAP procedures. The inspectors also determined that findings from the CAP self-assessment were consistent with the inspectors' assessment.

c. Findings

No findings were identified.

.4 Assessment of Safety Conscious Work Environment

a. Inspection Scope

The inspectors assessed the licensee's sa fety conscious work environment (SCWE) through the reviews of the facility's Employee Concerns Program (ECP) implementing procedures, discussions with the coordinator of the ECP, interviews with personnel from various departments, and reviews of issue reports. The inspectors also reviewed the results from a 2015 safety culture survey and meeting minutes of the Safety Culture

Monitoring Panel.

The inspectors held scheduled interviews with approximately 30 non-supervisory individuals and approximately 6 first-line supervisors in various group and individual settings, to assess their willingness to raise nuclear safety issues. Additionally, the inspectors interviewed other personnel info rmally during plant walkdown to ascertain their views on the effectiveness of the CA program and their willingness and freedom to raise issues.

The individuals in the scheduled interviews were randomly selected to provide a distribution across various departments at the site. In addition to assessing individuals' willingness to raise nuclear safety issues, the interviews also included discussion on any changes in the plant environment over the last 12 months. Items discussed included:

• knowledge and understanding of the CAP;

• effectiveness and efficiency of the CAP;

• willingness to use the CAP; and

• knowledge and understanding of ECP.

The inspectors also discussed the functioning of the ECP with the program coordinator; reviewed program logs from 2014 through 2016; and reviewed selected case files to identify any emergent issues or potential trends.

b. Assessment The inspectors did not identify any issues of concern regarding the licensee's SCWE.

Information obtained during the interviews indicated that an environment was established where licensee personnel felt free to raise nuclear safety issues without fear of retaliation. Licensee personnel were aware of and generally familiar with the CAP and other processes, including the ECP and the NRC's allegation process, through which concerns could be raised. In addition, a review of the types of issues in the ECP indicated that the licensee staff members were appropriately using the CAP and ECP to identify issues. The inspectors did not observe and were not provided any examples where there was retaliation for the raising of nuclear safety issues. Documents provided to the inspectors regarding surveys and monitoring of the safety culture and SCWE generally supported the conclusions from the interviews.

c. Findings

No findings were identified.

4OA6 Management Meetings

Exit Meeting On September 30, 2016, the inspectors presented the inspection results to Mr. K. Ohr and other members of the licensee staff. The licensee acknowledged the issues presented. One item had remained open pending licensee's evaluation. This open item was discussed and closed during a teleconference on October 6, 2016. The inspectors confirmed that none of the potential report input discussed was considered proprietary.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

K. Ohr, Plant Manager

W. Beck, Regulatory Assurance Manager

T. Bell, Engineering Director

R. Craddick, Organization Effectiveness Manager

D. Collins, Radiation Protection Manager

J. Cox, Operations Support Manager

R. Earley, Outage Manager

R. Hight, Maintenance Director

H. Dodd, Operations Manager

T. Wojcik, Engineering Program Manager

J. Wooldridge, Chemistry Manager

NRC

K. Stoedter, Branch Chief

R. Murray, Senior Resident Inspector

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Open None

Closed

None

Discussed

None

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 or 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.

Issue Reports

AR 1024260 1A RHRSW HP Pump Leak 02/01/2010

AR 1288784 CDBI - Technical Specification Limits for

EDG 11/10/2001

AR 1326102 Additional Actions from Byron RED NER

NC-12-005-R 02/13/2012

AR 1330499 Security Officer found Sub Door Open and Unable to Close It 02/22/2012

AR 1486872 Q1R22 PSU As Found Condition Bus 2201-32 Relay 2330-106 03/13/2013

AR 1500638 Auto-Blowdown Initiation Relay Failed to Actuate QCOS 203-08 04/11/2013

AR 1502238

NCV 12-005-01, Clsr Pkg, EDG Freq and Voltage TS Tolerance 04/15/2013

AR 1503634 Relay Has Harmonic Noise/Vibration 04/18/2013

AR 1508408 QCOS 1000-31, 1A LPCI LOOP Logic Test 04/30/2013

AR 1508524 1000-31, 1A LPCI LOOP Logic Test Time Delay 04/30/2013

AR 1513576 Overload Relays Not Passing Acceptance Criteria 05/14/2013

AR 1518664

2-0590-102A MSIV A Relay Occasionally Chattering 05/28/2013

AR 1539107 Relay

2-0595-121 Failed to Energize During QCOS 1600-44 07/24/2013

AR 1541630 PCI Relay Failure During Unit 2 Group 2 Logic Testing 07/31/2013

AR 1552033 Cyber Security Lessons Learned: Milestone 2 08/29/2013

AR 1552034 Cyber Security Lessons Learned: Milestone 3 08/29/2013

AR 1569267 IAM WO Needed To Replace TR Relay In

MCC 19-2 Cub D4 10/08/2013

AR 1569450 Bus 23-1 Degraded Voltage Relay Found Outside Tech Specs 10/08/2013

AR 1572952 Relay K4 On Averaging Card Z29 for APRM 4 Needs Replaced 10/16/2013

AR 1576023 Cyber Security Lessons Learned: Milestone 3 Data Diode Kvm 10/24/2013

AR 1577312 Relay

2-0590-101A Low Condenser Vacuum Very Loud 10/16/2013

AR 1578649 NRC Concern with Detail in Evacuation Time Estimates 10/30/2013

AR 1596033 Bus 23 Cub 9 A Phase Overcurrent Relay Needs Replaced 12/11/2013

AR 1596034 Bus 23 Cub 9 C Phase Overcurrent Relay Needs Replaced 12/11/2013

AR 1611255 U2 EDG Start Failure Relay Failure During Surveillance 01/23/2014

AR 1617892 Through Wall Leak Line

2-10116B-2"-D 2B RHRSW Cubicle Cooler 02/06/2014

AR 1626418 2B CRD Pump A Phase TOC Relay

OOT 02/26/2014

AR 1626424 2B CRD Pump C Phase TOC Relay

OOT 02/26/2014

AR 1638243 Relay 24A-K3X For The 2A CAM Making Loud Noise 03/25/2014

AR 1641010 Thru Wall Leak on CRD HCU Scram Isolation Valve Body 03/31/2014

AR 1643402 PSU RPS 1 SDV Hi Level Relays Deenergized 04/03/2014

AR 1644851 PSU Main Generator Backup Reverse Power Relay Found

OOT 04/08/2014

AR 1645005 Inspection Of HFA Relay Conflict In Reporting Discrepancies 04/09/2014

AR 1651656 PSU Relay

2-0595-127 Failed

PMT 04/25/2014

AR 1661302 CV#3 RPS

1-0590-121B Relay Alignment Issue 05/18/2014

AR 1667001 PI

OM.01, Unplanned Entries Into Shutdown LOCs, In Variance 06/02/2014

AR 1672301 NRC ID'D Angle Iron Support Against U2 Torus 06/17/2014

AR 1672301 NRC ID'd Angle Iron Support Against U2 Torus 06/17/2014

AR 1673507 EOC Walkdown Documenting Potential Torus Interferences 06/20/2014

AR 1677448 Unit 1/2 EDG Protective Relay Replacement 07/01/2014

AR 1678894 Incorrect ID of Fire Detect Sys Results in Missed Fire Watch 07/05/2014

AR 1685429 'A' Control Room HVAC 'A' Chiller Trip During Venting 07/24/2014

AR 1685738 Potential Adverse Trend in Drywell CAM Inoperability 07/25/2014

AR 1687895 Corrosion Pit Found During Visual Insp of Pump Disch Elbow 07/31/2014

AR 1688189 FASA Def - Acceptance Criteria Error is Non-Conservative 08/01/2014

AR 1691935 IST Trend: U1 HPCI High Differential Pressure 08/13/2014

AR 1692098 EC Due Date for Longstanding CO Extended 08/13/2014

AR 1693715 Need WO to Recalibrate U-1 HPCI PI

1-2340-2 08/18/2014

AR 1694388 W/O #

01618737-01, Cubicle Inspection Found Burnt Relays 08/20/2014

AR 1694388 WO#

01618737-01, Cubicle Inspection Found Burnt Relays 08/20/2014

AR 1694580 Elevated Contamination Levels in U2 RWCU Phase Sep. Pump Rm 08/20/2014

AR 1697974 LL - RHR HX Thermal Performance Testing 08/29/2014

AR 2059639 Unable to Adjust voltage on U2 125VDC Charger 09/08/2014

AR 2382388 Missed Performance Indicator Opportunity During PI Drill 09/17/2014

AR 2383029 ACE Required from SPC for 1A RHRSW HP Elbow Degradation 09/18/2014

AR 2383029 ACE Required from SPC for 1A RHRSW HP Elbow Degradation 09/18/2014

AR 2383051 RHRSW HP Elbow Extent of Condition Plan 09/18/2014

AR 2383344 TT

1-6620-166 Is Obsolete And A Replacement Is Requested 09/19/2014

AR 2391920 Pitting Identified in Deaerator Tank Piping 10/07/2014

AR 2392135 CAP Weaknesses - Adverse Trend Identified 10/07/2014

AR 2393113 IEAMA ID'd- Additional Support Requiring Walk Down 10/09/2014

AR 2396725 Safeguard Battery Part 21 Inspection 10/16/2014

AR 2397066 Potential Site-wide Trend in ERO Performance 10/17/2014

AR 2403922 DEP Classification Failure During 3rd Qtr Drill Cycle 10/30/2014

AR 2406984 IEMA U2 HPCI Flood Penetration Concern 11/05/2014

AR 2406984 IEMA U2 HPCI Flood Penetration Concern 11/05/2014

AR 2407265 CDBI. Pipe Support Base Plate Condition 11/05/2014

AR 2407735 3Q14 PI Drill Follow-up Issues. Procedure Quality Issues 11/06/2014

AR 2407755 3Q14 PI Drill Follow-up Issues: Program Admin and Maint 11/06/2014

AR 2407858 3Q14 PI Drill Follow-up Issues. TSC Facility Evacuation 11/06/2014

AR 2408090 U1 SBO Took Multiple Attempts to Start 11/06/2014

AR 2408256 590-101A MN CNDSR LO VACU SCRAM Buzzing Loudly 11/07/2014

AR 2412012 Unplanned ED Dose Rate Alarm 11/14/2014

AR 2416190 Unit 1 Control Vlv 3 Suicided Closed During Qtrly Turb Test 11/23/2014

AR 2417224 Procedurally Controlled Temporary Configuration Change Issue 11/25/2014

AR 2421519 ED Dose Rate Alarm 12/05/2014

AR 2424445

NCV 14-004-01, Clsr Pkg , Support Too Close to U2 Torus 12/12/2014

AR 2424445

NCV 14-004-01, Clsr Pkg. Support Too Close to U2 Torus 12/12/2014

AR 2425242 Control Room Door Will Not Close 12/15/2014

AR 2427286 2-100-C Control Switch (10A-S3C) Potentially Non-conforming 12/18/2014

AR 2428691 Structures Monitoring Discharge Bay 12/22/2014

AR 2432246 Loss of Power to Offsite EP Siren 01/04/2015

AR 2433389 1/2 EDG FOTP Unit 2 Breaker Found Tripped 01/06/2015

AR 2433389 1/2 EDG FOTP Unit 2 Breaker Found Tripped 01/02/2015

AR 2434983 Greater than 50% Zebra Mussel Coverage 01/09/2015

AR 2443171 1B Recirc Pump Tripped for Cause Yet Unknown 01/27/2015

AR 2443171 1B Recirc Pump Tripped For Cause Yet Unknown 01/27/2015

AR 2443171 1B Recirc Pump Tripped For Cause Yet Unknown 01/27/2015

AR 2443241 Entered QCOA 0300-04 Mis-positioned Control Rod 01/27/2015

AR 2446040 Relay 1-595-102A Buzzing Loudly 02/02/2015

AR 2450376 HPCI Interlock Doors Opened Simultaneously 02/10/2015

AR 2450782 INPO Walkdown Surface Corrosion on T82 Mod N2 Tanks Fittings 02/11/2015

AR 2450896 U1 HPCI Steam Supply Valve Open During Sys Repressurization

2/11/2015

AR 2450896 U1 HPCI Steam Supply Valve Open During Sys Repressurization February 25, 2015

AR 2456214 IEMA ID 2A RHR Subdoor not Dogged 02/20/2015

AR 2457686 U2 EDG Failed to Stop Following Monthly Run, QCOS 6600-42 02/23/2015

AR 2462520 PSU Relay

1-0590-108E Has High Resistance on PT 3-4 03/03/2015

AR 2462525 PSU Relay

1-0590-109A Has High Resistance on PT 3-4 03/03/2015

AR 2462576 2015-01, Level 2

PCE 03/03/2015

AR 2462834 2015-03, Level 1

PCE 03/03/2015

AR 2463154 HEPA Malfunction 03/04/2015

AR 2463479 NRC Observation 1B Core Spray Room Door Open 03/04/2015

AR 2463774 Rapid Trending Of RB Basement Watertight Doors 03/05/2015

AR 2464065 IEMA ID U1 HPCI Watertight Door Found Open 03/05/2015

AR 2464065 IEMA ID U1 HPCI Watertight Door Found Open 03/05/2015

AR 2466337 2015-04, Level 1

PCE 03/10/2015

AR 2467182 PSU Relay Screw For The Trem Spot Sheered Off 03/11/2015

AR 2468191 RHRSW HP Elbow Engineering Recommendation Explanation 03/13/2015

AR 2468396 Bus 16 UV Relay

OOT 03/13/2015

AR 2468409 Effectiveness Review on HPCI Interlocks 03/13/2015

AR 2471609 1A ASD Latch Fault Relay Failure 03/20/2015

AR 2471912 Received 901-3 G3, Rx Bldg. Vent Rad Monitor Channel Hi 03/20/2015

AR 2471966 T11 To Bus 14 Relay Found

OOT 03/08/2015

AR 2472107 U1 ADS Relays Need Contacts Burnished 03/21/2015

AR 2472416 RCIC MO

1-1301-61 Motor Degraded 03/22/2015

AR 2476532 Perform ACE to Address 2015 WANO AFI -

ER.3-3 Deficient Parts 03/30/2015

AR 2476557

NCV 14-005-01, Clsr Pkg. 4Q14 HPCI Flood Barrier 03/30/2015

AR 2479120 U1 Manual Scram Due to Steam Leak on D-Ring Header 04/03/2015

AR 2483896 NRC Observations During 1st Quarter 2015 04/12/2015

AR 2484017 QCOS 6600-54, EDG

TD-5 Time Delay Relay Proc Enhancement

04/13/2015

AR 2484419 1AP09EC Sync Check Relay Stuck in Operate Position 04/10/2015

AR 2485051 EACE Requested of Failure Of Unit 1 ADS Logic For

IR 2472107 05/12/2015

AR 2485212 Inconsistent Test Results For U1 EDG TD5 Relay, QCOS 6600-

04/15/2015

AR 2488359 U1 EDG TD5 Relay Tested With Inconsistent Results 04/20/2015

AR 2494731 Div 1 2nd level Undervoltage Relay As Found OOT

PSU 05/02/2015

AR 2496135 Check Of DC Input Power To U1 EDG Time Relay TD2 05/05/2015

AR 2496550 MO

1-1001-7C and MO

1-1001-7D Not Replaced During Q1R23 05/06/2015

AR 2497234 Spurious U1 RBCCW Rad Alarm During QCIS 1700-10 SJAE

Cal and 05/07/2015

AR 2497455 New

2-2330-134 TD Relay Failed AS Left Surveillance 05/07/2015

AR 2498267 1AP09EA 227-201B1 PH BC Relay As Found Time Unsat 05/09/2015

AR 2498275 1AP09EH 227X2-21B1-2

TD-5 Relay target Amps As Found

OOS 05/09/2015

AR 2499179 Installed Relay Has The Wrong Coil Voltage Rating 05/11/2015

AR 2500934 Obsolescence Procedure Adherence Issue 05/14/2015

AR 2503101 Protected Equipment Program Not Capturing All Components 05/19/2015

AR 2506630

NCV 15-001-01 Closure Package EDG FOTP Relay Failure Lacked PM

05/25/2015

AR 2506644

NCV 15-001-02, Clsr Pkg. HPCI Not in Standby Lineup 05/28/2015

AR 2507084 Replace 32G2 and 92G2 Reverse Power Relays 05/29/2015

AR 2511669 Multiple/Potential Part 21, Allen Bradley Relay Model 700RTC 06/08/2015

AR 2511855 Relays Failed Bench Testing 06/08/2015

AR 2513060 RHR Min Flow Valves

1-1001-18A & B Found Out of Position 06/10/2015

AR 2516196 FASA

2423383-02 Methodology #3 Walk Down 06/18/2015

AR 2520071 Operational Focus and Fundamental Assessments Results 06/26/2015

AR 2521136 EACE Requested Of Failure Of U2 Edg Vent Tt For

IR 2507805 06/09/2015

AR 2522030 WR For Additional Troubleshoot Testing On U1 EDG TDS Relay 06/30/2015

AR 2523303 Hose End was Not Covered on a HEPA Vacuum in a

CA 07/02/2015

AR 2524574 SPC Assignment for Q1R23 Core Spray Pipe Flaw Issue (IVVI) 07/07/2015

AR 2524699 NRC ID'D: Preconditioning Concern in QCOS 7500-08 07/07/2015

AR 2524699 NRC ID'D Preconditioning Concern in QCOS 7500-08 07/07/2015

AR 2528431 ERVR- No Procedure CRD Drive Water Pressure Bypass Valve 07/15/2015

AR 2528616

NCV 15-201-01, Closure Package Post Exercise Critique Issue 07/15/2015

AR 2530897 OLL Followup Action: HCU DCV on Unit 1 and 2 07/21/2015

AR 2533523 Damper 1/2-5741-329 Failed Part Open 07/27/2015

AR 2533523 Damper 1/2-5741-329 Failed Part Open 07/27/2015

AR 2535898 1AP04EG 551/550-AT1H PH B Relay As Found Out of Spec 07/31/2015

AR 2543911 Spurious Chattering of Relay

2-2043-156 03/22/2016

AR 2545024 1A RHR Pump Breaker Closing Springs Not Charged 08/22/2015

AR 2545579 CDE Panel Requires WR to Replace Timing Relay 08/24/2015

AR 2546812 Primary Containment O2 Found Above TS Limit during Surveillance

08/26/2015

AR 2547236 Material Storage for Cond Demin Work >90 Days 08/27/2015

AR 2549095

NCV 15-002-01 Clsr Pkg PMT not Performed on

RCIC-61 Valve 08/31/2015

AR 2549525 Possibility of Old Capacitors in need of Testing in U2

SBO 09/01/2015

AR 2550801 WGE Needed for Issue in

IR 2545024 09/03/2015

AR 2553103 Leak Identified on 2A RHRSW Piping 09/10/2015

AR 2554939 U2

RHR 21 Valve Did Not Close During Logic Surveillance 10/22/2015

AR 2557373 Security - Potential Issue Identified Procedure Adherence 09/18/2015

AR 2557417 1B CAM Continues to Read High for O2 09/18/2015

AR 2558274 NOS ID: Gap in RWP Dose Rate Setpoint 09/21/2015

AR 2559869 NOS ID: Ops Pre-job Briefing Issue 09/27/2015

AR 2560327 ERVR Review Identified Significant Errors in IQREVIEW Data

09/25/2015

AR 2560576 Review HPCI Door Hardware for Safety Classification 03/11/2016

AR 2560585 ERVR. QDC RPS/NI/TIP IQREVIEW Gaps 09/25/2015

AR 2561408

WO 01729356-01 Pre LCO Testing of TDR1 Relay @Panel

251-100A

09/28/2015

AR 2564632 1/2 250 VDC Batt charger Indication Less Than Rounds Minimum 10/02/2016

AR 2571409 ERVR- Feedwater and CD/CB Pump FLEX Hose Vulnerability 10/15/2015

AR 2572506 Accumulated Dose Alarm Received in U2 Clean Up HX Room 10/17/2015

AR 2575404 Received Unexpected CRD Accumulator Alarm

HCU 30-31 10/22/2015

AR 2576334 2-590-102F MSIV 203-1B 2B Closure Scram Relay Chatter 10/25/2015

AR 2577396 TSC Ventilation Emergency Mode Flow Rate Found High 10/27/2015

AR 2578071 Calculation 004-E031 Requires Update (REF

EC 374641) 10/28/2015

AR 2578245 NRC ID: SBGTS Preconditioning Issues

10/28/2015

AR 2581210 OPS: OIO - Dresden Thermal Limit Violation Procedure 11/03/2015

AR 2582802 MMD Individual Offsite Greater Than 90 Days 11/05/2015

AR 2584548 EP- NARS Phone Issues 11/09/2015

AR 2586432 Possible Trend with Supplemental Workers Performance 11/12/2015

AR 2587065 Outdated UFSAR Description of Penetration Seal Material 11/13/2015

AR 2588615 ERVR Important Check Valve Classified as "Non-Critical" 11/17/2015

AR 2588868 ODM Action Item Closed With Out a Copy of ODM Attached 11/18/2015

AR 2594316 Safe Shutdown Report Missing Alternate Feed to RCIC Valves 12/01/2015

AR 2595999 MRule Panel Recommendations For Sub Door Human Performance

2/04/2015

AR 2596725 912-1 G-12, Control Room Standby HVAC Sys Major Trbl 12/07/2015

AR 2596725 912-1 G12, Control Room Standby HVAC Sys Major Trbl 12/12/2015

AR 2600254 Installation of FLEX Lip Barriers Damaging Equipment 12/15/2015

AR 2600539 Results of 2015 Self-Assessment Check-In Critical Ctrl Docs 12/15/2015

AR 2605112 U0 EDG Syncrocheck Relay Found

OOT 12/28/2015

AR 2609716 Gap in Supplemental Workforce Oversight 01/08/2016

AR 2612022 CIAR DEF 1: Three IRs Classified as NCAP that should be

CAP 01/13/2016

AR 2612380 Tracking Of Actions For Licensee Identified Violations-Opex 01/14/2016

AR 2612380 Tracking of Actions for Licensee Identified violations - OPEX 01/14/2016

AR 2617163 IEMA ID 2B RHR Sub Door Not Dogged 01/26/2016

AR 2617619 Check-In Self Assessment: Supplemental Workforce Oversight 01/27/2016

AR 2618189 Benchmark Supplemental Workforce Oversight 01/28/2016

AR 2618890

NCV 15-003-02, Clsr Pkg. - Preconditioning of SBGTs 01/29/2016

AR 2621037 EO ID: 1A RHR. 1A CA Sub Door Not Dogged 02/03/2016

AR 2621037 EO ID 1A RHR AND 1A CS Sub Doors Not Dogged 02/03/2016

AR 2621530 NOS ID: Ground Water Corroding HPCI Equipment 02/03/2016

AR 2622401 Potential Trend in Security Human Performance 02/05/2016

AR 2626589

1764667-01 OL Heater Fail Testing, Replace Relay 02/16/2016

AR 2627722 Recommendation For Control Of Rx Bldg Sub Doors 02/17/2016

AR 2633471 FASA Identified - RCIC Pressure Indication 02/29/2016

AR 2634889 Preconditioning Concern During QCOS 0202-22 03/02/2016

AR 2637140 ADS Relay

1-0287-106A Needs Replaced in Q1R24 03/07/2016

AR 2637141 ADS Relay

1-0287-106B Needs Replaced in Q1R24 03/07/2016

AR 2637188 DPIS

1-0261-34d Did Not Respond As Expected 03/07/2016

AR 2637359 Adjustment Needed To B28/29-5 Time Delay Relay 03/08/2016

AR 2638315 2-590-100D Relay Contact Intermittent 03/10/2016

AR 2640007 NOS ID: Out of Spec ELBP, Omissions on ELBP Datasheets 03/14/2016

AR 2642943 PSU# Main Generator Over frequency Relay Found Failed 03/21/2016

AR 2643477 2A RFP Relay

2-6701-1-151A Found OOT During Q2R23 03/21/2016

AR 2644143 Mod Corrosion/Leakage Found on RWCU Valve

2-1279-68 03/23/2016

AR 2645027 IEMA ID Previous IR Did Not Disposition Past Reportability 03/24/2016

AR 2646178 PSU# Relay 590-116B Found Deficient During Inspection 03/23/2016

AR 2646581 PSU Relay 590-125A Found Deficient During Inspection 03/28/2016

AR 2646599 PSU# Relay 590-110D Found Deficient During Inspection 03/28/2016

AR 2646602 PSU# Relay 590-115B Found Deficient During Inspection 03/28/2016

AR 2646603 PSU# Relay 590-114B Found Deficient During Inspection 03/28/2016

AR 2646605 PSU# Relay 590-114D Found Deficient During Inspection 03/28/2016

AR 2646606 PSU# Relay 590-121D Found Deficient During Inspection 03/28/2016

AR 2646610 PSU# Relay 590-123B Found Deficient During Inspection 03/28/2016

AR 2646611 PSU# EM Relay 590-111D Found Deficient During Inspection 03/28/2016

AR 2646615 PSU# Relay 590-100D Found Deficient During Inspection 03/28/2016

AR 2646622 PSU# Relay 590-101D Found Deficient During Inspection 03/28/2016

AR 2646626 PSU# Relay 590-107H Found Deficient During Inspection 03/28/2016

AR 2646628 PSU# Relay 590-106D Found Deficient During Inspection 03/28/2016

AR 2646636 Relay 902-52B Found Deficient During Inspection 03/28/2016

AR 2646876 Workers Performing Work While Not Under a Clearance Order 03/28/2016

AR 2647397 NRC ID - Insufficient Alpha Smears Obtained 03/29/2016

AR 2647412 IEMA ID: U1 HPCI Subdoor found 1 Turn from Full Closed 03/29/2016

AR 2647412 IEMA ID U1 HPCI Subdoor Found 1 Turn From Full Closed 03/29/2016

AR 2647437 Dose Alarm and

PCE 2016-04 03/29/2016

AR 2647830 PSU Q2R23 Replace Relay

2-0590-116B 03/30/2016

AR 2647982 PSU# Q2R23 Replace Relay

2-0590-123B 03/30/2016

AR 2648058 PSU Q2R23 Bent Relay Contact Arms On Relay

2-0590-125A 03/22/2016

AR 2648075 Q2R23 Bent Relay Contact Arms on Relay

2-0902-52B Aux Relay 03/30/2016

AR 2651057 PSU# Investigate Air Leak/Replace Solenoid For Target Rock 04/05/2016

AR 2652197 Near Miss With Secure High Rad Area Access Control 04/07/2016

AR 2653905 Overload Relays Failed 04/11/2016

AR 2654566 Replace Engine Protective Relays on 1

EDG 04/12/2016

AR 2654571 Replace Engine Protective Relays on 2

EDG 04/12/2016

AR 2654576 Replace Engine Protective Relays on 1/2

EDG 04/12/2016

AR 2655056 Replace Field Flash Cutout Relay on Unit 1

EDG 04/13/2016

AR 2655063 Replace Field Flash Cutout Relay on Unit 1/2

EDG 04/13/2016

AR 2655219 AC Relay Had Discoloration 04/13/2016

AR 2655551 Main Chimney Radioactive Effluent Monitoring Vulnerability 04/14/2016

AR 2655599 Operations is Not Adhering to

OP-AA-101-111-1001 and the

CBA

04/14/2016

AR 2658866 Level 2

PCE 2016-10 04/21/2016

AR 2660181 Relay

1-0595-141A Abnormal Noise/Vibration 04/24/2016

AR 2665927 NOS ID: Unacceptable Inspection Items Not Doc in

CAP 05/05/2016

AR 2668750 74 Relay Coil Looks Burnt and Cracked 05/12/2016

AR 2669120 Replacement Of LPCI Swing Bus Relay

1-7200-19-2A-TDOD 05/12/2016

AR 2669123 Replacement Of LPCI Swing Bus Relay

2-7200-19-2A-TDOD 05/12/2016

AR 2672605 Procedure Improvement / Process Improve for EO ERO Actions 05/23/2016

AR 2672739 01-0595-141A Relay Appears To Have Degraded Coil 05/23/2016

AR 2673498 2C RFP Tripped Immediately on Start Attempt From Bus 21 05/25/2016

AR 2674281 HFA Relay Replacement Required

2-3241-52D 05/26/2016

AR 2675883 Fire Extinguisher is Not on a PM Inspection List 05/31/2016

AR 2675979 NOS ID: Elevation to EMD for Not Resolving ELBP Issues 05/31/2016

AR 2677621 NRC Concerns on Compliance with DW/Torus DO and O2 Conc

TS 06/03/2016

AR 2679804

NCV 16-001-02, Clsr Pkg. CREVS DPS Classification 06/09/2016

AR 2682985 QDC EP 2Q16 PI Drill TSC DC Failure 06/17/2016

AR 2682987 QDC EP 2Q16 PI Drill SIM DC Failure 06/17/2016

AR 2682988 QDC EP 2Q16 PI Drill Other Issues 06/17/2016

AR 2684130 2A RHR Sub Door Found Not Secured By Security 06/21/2016

AR 2684197 Cognitive Trend in IR Initiation for June 2016 06/21/2016

AR 2687691 ERVR Quad Cities FW Reg Valve Subcomponent Classifications 06/30/2016

AR 2691484 EP- Ops Status and Director's Hotline Failures 07/11/2016

AR 2691486 EP- Satellite Phone Issues 07/11/2016

AR 2694084 Everbridge ERO Notification System Failure 07/18/2016

AR 2696484 EP: EAL Language is Inconsistent with

EOP 07/25/2016

AR 2698621 U2 Control Rod Drive 30-35 High Temp 07/30/2016

AR 2702862 2B CRD Charging Header Pressure Trend Change 08/10/2016

AR 2703233 Foreign Material Found In Autopsied Tr Srv Solenoid 2-203-3a 08/11/2016

AR 2704078 Failed CR Relay 0-9908-1-A1 MCC Bucket 08/13/2016

AR 2704988 Relay Found Out of Tolerance 08/16/2016

AR 2706084 Rec Alarm 902-5 G2, 'CRD Accum Press Lo/Level Hi'. HCU 18-

08/19/2016

AR 2708935 Potential Cognitive Trend in Security PR&A 08/26/2016

AR 2716699 Long Term Storage Area on the

TB 611' Elev 09/16/2016

Apparent Cause Evaluation

ACE 1024260 Through Wall Leak on 1A RHRSW Pump Caused by Inadequate Fusion in Weld

2/01/2010

ACE 1617892 Through Wall Leak Line

2-10116B-2"-D. 2B RHRSW Cubicle Cooler 02/06/2014

ACE 1660714 2C Condenser Backpressure Response is Slow 06/23/2014

ACE 1663403 HPCI Interlock Door Opened Simultaneously 05/22/2014

ACE 1689371

IR 1680216 on 0-7507-B Valve Identified as Maintenance Rule Functional Failure and CCF

10/03/2014

ACE 2059639 Unable to Adjust Voltage on U2 125VDC Charger 11/10/2014

ACE 2383029 ACE Required from SPC for 1A RHRSW HP Elbow Degradation 10/13/2014

ACE 2383029 ACE Required From SPC For 1A RHRSW HP Elbow Degradation

07/31/2014

ACE 2392135 CAP Weakness- Adverse Trend Identified 10/07/2014

ACE 2425242 South Main Control Room Door (0-0075-89) Will Not Close 01/21/2015

ACE 2432457 Perform Apparent Cause Evaluation for CCF and Downpower Events 04/06/2015

ACE 2433389 Power Supply Breakers to Unit 0 fuel Oil Transfer Pump Found Tripped 02/05/2015

ACE 2436224 Incorrect Breaker Tagged Out of Service 02/06/2015

ACE 2450376 Unit 1 HPCI Interlock Door Failure 02/10/2015

ACE 2471912 Unexpected U1 Reactor Building Vent Radiation Monitor Channel (1-1705-8A) A High

05/05/2015

ACE 2476532 2015 WANO AFI -

ER.3-3 Deficient Parts 04/24/2015

ACE 2479117 U1 3B ADS Valve - Unexpected Drywell Pressure Rise Following Manual Actuation of

1-0203-3B ERV Upon Entering

Q1F65 04/03/2015

ACE 2485051 Unit 1 ADS 'A' Trip Logic Failed for ERVs

1-0203-3B and 3D and 'B' Trip Logic As-Found Data was Lost

05/12/2015

ACE 2513060 Residual Heat Removal Minimum Flow Valves Discovered Out of Position 07/10/2015

ACE 2513060 Residual Heat Removal Minimum Flow Valves Discovered Out of Position

07/10/2015

ACE 2533523 Damper 0-5741-329 Failed Part Open 07/27/2015

ACE 2557223 Accumulated Dose Alarm 09/17/2015

ACE 2559343

1A RHR Pump Breaker Closing Springs Not Charged 10/19/2015

ACE 2572506 Accumulated Dose Alarm in the RWCU Heat Exchanger Room 10/17/2015

ACE 2572506 Accumulated Dose Alarm Received in U2 Clean Up HX Room 10/17/2015

ACE 2578409 Received Unexpected U1 Fuel Pool Channel A Downscale 10/29/2015

ACE 2596725 B Train of Control Room HVAC Failed to Start 01/22/2016

ACE 2646827 Contracted Workers Not Signed Onto Clearance Order 04/29/2016

ACE 2648253 Assembly to Assembly Contact during Q2R23 Fuel Moves 04/01/2016

ACE 2673498 2C Reactor Feed Pump Breaker Closure Failure 06/30/2016

Audit, Assessment and Self-Assessments

AR 1610901 Assessment of Control Room Habitability Program 10/31/2014

AR 2386126 FASA Deficiency: No Open WO For Control Rod 26-07 Rod Position Indication System (RPIS) Issue

09/25/2014 CIAR

1610922 Mechanical Damage Mechanism 10/31/2014 CIAR

1653903 Evaluate Completed Temporary Shielding Packages and Logs 07/23/2014 CIAR

2422519 Off-Year NRC PI&R Assessment of the Corrective Action Program Review

09/30/2015 CIAR

2426795 Radworker Performance 07/02/2015 CIAR

2556582 Corrective Action Program (NCAP) Compliance Review 01/14/2016 FASA

1598600 Quad Cities Station EQ Program 5-Year FASA 09/30/2014 FASA

2620212 Preparation for NRC Problem Identification and Resolution (PI&R) Inspection per Inspection Procedure 71152

07/12/2016 FRPT

1610903 MOV - Motor Operated Valves 11/14/2014

NOSA-QDC-15-04 Corrective Action Program Audit Report 04/15/2015

Miscellaneous

2Q2016 SCMP Snapshot Undated 2Q2016 SCMP Snapshot Undated ARs Relevant to Safety Culture (OR7); 01/01/2015 through 05/18/2016 Undated ARs Relevant to Safety Culture (OR7); 01/01/2015 through 05/18/2016 Undated EPRI Report

3002000541, Relay Series Specific Guidance Generic Service Life Analyses (GSLA) and Preventive Maintenance (PM) Templates July 2013 Evaluation of Pits in the Quad Cities 2C RHRSW High Pressure Discharge Elbow 08/20/2015 Long Term Safety Culture Trending, Third Quarter 2013 through Second Quarter 2016

Undated Long Term Safety Culture Trending, Third Quarter 2013 through Second Quarter 2016

Undated Management Review Committee Agenda Various Dates Organizational Effectiveness Survey Results 9/21/2015 - 11/9/2015 2015 Organizational Effectiveness Survey Results 9/21/2015 - 11/9/2015 2015 Safety Culture Summary for Quad 3Q12 - Number of Inputs, Average Trait Scores, and Examples Undated Safety Culture Summary for Quad 3Q12 - Number of Inputs, Average Trait Scores, and Examples Undated SCMP Handout for September 28, 2016, Meeting Undated SCMP Handout for September 28, 2016, Meeting Undated SCMP Presentation: SVP FFD Follow Up Question Undated SCMP Presentation: SVP FFD Follow Up Question Undated Station Ownership Committee Agenda Various Dates Calc. 004-E-031 Thermal Overload Reviews Revision 7

Calc.

QDC-2900-M-0472 Determination of Pressure Required for Safe Shutdown Makeup Pump System Injection Under Safe Shutdown

Conditions Revision 0B

Calc. QDC-5700-

E-0808 General Electric Thermal Overload Sizing for Continuous Duty Motors Revision 3

EC 342788 Classification of Secondary Containment Doors Revision 0

EC 374641 Evaluate replacement Motors for the U1 and U2 RHR Heat Exchanger MOV Motors at 1(2)-1001-16A/B and 1(2)-1001-

36A/B Revision 3

EC 398520 Support L Bracket May Come In Contact With U2 Torus During a Design Basis Event

11/19/2014

EC 398663 Address Supports That are Deemed too Close to the Unit 1 Torus - Issues Identified During Extent of Condition Walkdowns - OP Eval

EC 398520 CA

10/29/2014

EC 400144 Evaluation of Lateral and Vertical Restraints of the HCU and the Scram Inlet 126 Valve Revision 0

EC 401502 RHRSW Pump Discharge Elbow Possibly Degraded Operability Evaluation Revision 0

EC 403442 Initiation Time of the Standby Gas Treatment System (SBGTS) 10/01/2015

EC 406729 HPCI Interlock Doors Latch Evaluation Technical Evaluation Revision 0

EC 406756 Safety Classification Review of HPCI Interlock Door Latches Revision 0 Part Evaluation

91914 Damper, Isolation, 12 in, Less Actuator, Less Limit Switches Undated PMID

193042 Replace Hydraulic Closer on South Main Control Room Door Undated PMID 35876 SBO Battery Charger Inspection Undated PMID 35877 SBO Battery Charger

2-8330 Inspection Undated PMID 38193 Control Valve Junction Box and Upper Joint Inspection Undated

RWP 10016632 Reactor Water Clean Up (RWCU) Activities (Yes HRA/LHRA Access)

Revision 0 SESR 4-2713 The

2-1001-16A and

2-1001-16B Valve Motors are Being Replaced.

Evaluate Circuit Breakers O.L. Heaters and Cable Sizing for the New Motors

03/23/1995

SR 90670 Predefine Change - 17213, 17214, 17215, 17216, 22391, 2, 3, 4 -01 11/18/2015

SR 91113 Predefine Change - PMID 35876-01 and 35877-01 01/13/2016

Standing Order

11-11 Clarification on Guidance for Emergency Diesel Generator (EDG) Operating Frequency

11/15/2011

WO 1472106 PCI Group 2 Partial Isol Test At Power 07/24/2013

WO 1618393-01 EM Replacement of PCM Template Recommended Circuit Cards 11/14/2015

WO 1623553 Q1R22 PSU - As Found Condition Bus 2201-32 Relay 287-

107B 03/14/2013

WO 1646354

2-0590-102A MSIV A Relay Occasionally Chattering 05/28/2013

WO 1717548 (LR) Piping UT Wall Thickness Inspections 1117/2014

WO 1748175-03 EMS Trim Conduit Support in Torus Basement 10/17/2014

WO 1763245 Recalibrate U1 HPCI PI

1-2340-2 Due to Suspected

OOT 09/18/2014

WO 1767480-01 EM Troubleshoot Unable to Adjust Voltage on U2 125VDC

Charger 12/17/2014

WO 1792134-01 MM Inspect / Repair Main Control Room South Door 07/10/2015

WO 1827660 Rebuild

1-1301-61 Actuator

02/21/2016

WO 1849049-05 MMD Overhaul Actuator / Stroke Damper Manually 01/10/2016

WO 1854134-01 MMD EWP Replace Damper 0-5741-329 07/19/2016

WO 1872173-01 EM EWP Group 2, 15, 17 Eight Hour ELP Inspection 01/25/2016

WR 427400 Q1R22 PSU - As Found Condition Bus 2201-32 Relay 287-

107B 03/14/2013

WR 431129 Relay

1-0595-103D Has Harmonic Noise/Vibration 04/22/2013

WR 483719 Repair Concrete East Wall at Discharge Bay 12/29/2014

WR 524146 MM Mod Corrosion/Leakage Found on RWCU Valve 2-

279-68 03/24/2016

Operating Experience

AR 2423336 OPEX Eval for IER L3-14-53, Corrosion of Unlined Carbon Steel 12/10/2014

AR 2472635 OPEX - GE

SIL 675, R0, HCU Bracket Installation Error 03/23/2015

AR 2534289 OPEX Eval IER L3-15-27, Gas Binding Results in Loss of All Charging Flow

07/29/2015

AR 2577821 OPEX Eval IER L3-15-35, Loss of Shutdown Cooling Occurs During Plant Cooldown

10/28/2015

AR 2593375 GEH

SIL 678 R0, Susceptibility of Original Directional Control Valve Cap Screw

11/30/2015

AR 2597335 Quad Actions from OPEX Review

IR 2577821 12/08/2015

AR 2624986

SIL 678 Quad Cities Applicability DCV CAP Screws 02/11/2016

AR 2686774 OPEX Eval GEH

SIL 678, R1 Susceptibility of Original Directional Control Valve Cap Screws

06/28/2016

Procedures

EI-AA-101 Employee Concerns Program Revision 11

EI-AA-101-1001 Employee Concerns Program Process Revision 14

ER-AA-335-1005 Standard Approach on How to Evaluate and Inspect Outside Diameter (OD) Corrosion on Piping Revision 4

ER-AA-450 Structures Monitoring Revision 5

ER-AA-700-1003 Screening and Evaluation of Potential Aging Issues Revision 3

MA-AA-716-012 Post Maintenance Testing Revision 20

MA-AA-716-026 Station Housekeeping / Material Condition Program Revision 14

MA-AA-723-350 Emergency Lighting Battery Pack Quarterly Inspection Revision 14 MA-QC-716-026-

1001 Seismic Housekeeping Revision 3

OP-AA-103-105 Limitorque Motor Operated and Chainwheel Operated Valve Operations Revision 5

PI-AA-115 Operating Experience Program Revision 1

PI-AA-115-1003 Processing of Level 3 OPEX Evaluations Revision 2

PI-AA-120 Issue identification and Screening Process Revision 6

PI-AA-125 Corrective Action Program (CAP) Procedure Revision 4

PI-AA-125-1001 Root Cause Analysis Manual Revision 2

PI-AA-125-1003 Apparent Cause Evaluation Manual Revision 3

PI-AA-125-1004 Effectiveness Review Manual Revision 1

PI-AA-125-1004 Effectiveness Review Manual Revision 1

PI-AA-127 Passport Action Tracking Management Procedure Revision 2 QCAN 901(2)-5 G-2 CRD Accumulator N2 Side Low Pressure or High Water Level Revision 13 QCIS 1700-07 Reactor Building Ventilation and Fuel Pool Radiation Monitoring Calibration and Functional Test Revision 24 QCMPM 0220-01 Relief Valve Downcomer to Drywell Vacuum Breaker Preventive Maintenance Revision 13 QCOP 6500-07 Racking in a 4160 Volt Horizontal Type AMHG or G26

Circuit Breaker Revision 33 QCOP 6600-27 Unit 1 Diesel Generator Shut Down Revision 4 QCOS 1600-55 Secondary Containment Preventative Maintenance Program Revision 10 QCOS 2900-01 Safe Shutdown Makeup Pump Flow Rate Test Revision 37 QCOS 7500-04 Unit 1 Standby Gas Treatment Initiation and Reactor Building Ventilation Isolation Test Revision 35 QCOS 7500-08 Unit 2 Standby Gas Treatment Initiation and Reactor Building Ventilation Isolation Test Revision 24

RP-AA-400-1004 Emergent Dose Control and Authorization Revision 8a

RP-AA-403 Administration of the Radiation Work Permit Program Revision 8

Root Cause Evaluations

RCE 2443241 Operations Aggregate Performance Root Cause 04/10/2015

RCE 2468511 Individual Working on Bus 12 contacted Energized Equipment 05/11/2015

RCR 1641010 Forced Unit 2 Shutdown Due to Reactor Coolant Pressure Boundary Leakage

03/31/2014

RCR 2479120 U1 Manual Scram Due to Steam Leak on D-Ring Header 04/02/2015

Condition Reports

Generated for this Inspection

AR 2716239 PIR: Issue Resolution Closure Documentation Correction 09/15/2016

AR 2716518 PIR: QCOP 6500-07, Racking in Horizontal 4KV Breakers 09/16/2016

AR 2716521 PIR -

RCR 2479120 - NRC Observation 09/16/2016

AR 2716533 PIR - Effectiveness Review Criteria 09/16/2016

AR 2716581 PIR -

ACE 2557223 - NRC Observation 09/16/2016

AR 2716618

PIR 2016: Inadequate Documentation of Preconditioning Eval 09/16/2016

AR 2716692

PIR 2016: Preconditioning EC has Inaccurate Conclusion 09/16/2016

AR 2720738 PIR: EC Eval

342788 Requires Revision for HPCI Interlock

09/27/2016

AR 2721194 PIR: Revise Procedure QCEPM 0700-03 09/28/2016

AR 2721304 PIR:

IR 2578071 to Include SESR 4-2713 in Op. Disc. 09/28/2016

AR 2721644 PIR Platform Ladder in T.B. Did Not Have Wheels Chocked 09/29/2016

AR 2721809 PIR: Classification of

IR 2578071 as NCAP IRs 09/29/2016

AR 2721942 PIR:

AT 1617892-18 Contains Incorrect Trend Data 09/29/2016

AR 2721948 PIR Debrief Observation on

ACE 2513060 Actions 09/29/2016

AR 2721951 PIR Debrief Observation on IRs

1497588 and

IR 1630449 09/29/2016

AR 2722259 PIR NRC ID Documentation Issue in

IR 2646622 09/30/2016

AR 2722349 PIR - EACE

1617892 &

IR 2553103 - NRC Observation 09/30/2016

LIST OF ACRONYMS

ADAMS Agencywide Documents Access and Management System

CAP Corrective Action Program

CAPR Corrective Action to Prevent Recurrence

CFR Code of Federal Regulations

EACE Equipment Apparent Cause Evaluation

EPRI Electric Power Research Institute

IR Issue Report

ECP Employee Concern Program

IMC Inspection Manual Chapter

LCO Limiting Condition for Operation

NCV Non-Cited Violation

NRC Nuclear Regulatory Commission

PARS Publicly Available Records

PCM Performance Centered Maintenance

PI&R Problem Identification and Resolution

RHRSW Residual Heat Removal Service Water

SCWE Safety Conscious Work Environment

TS Technical Specification

B. Hanson -2-

Based on the results of this inspection, no finding of significance was identified.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," 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 's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS).

ADAMS is accessible from the

NRC Web site at http://www.nrc.gov/reading-rm/adams.html

(the Public Electronic Reading Room).

Sincerely,

/RA/

Karla Stoedter, Chief

Branch 1 Division of Reactor Projects Docket Nos. 50-254; 50-265 License Nos. DPR-29, DPR-30

Enclosure:

IR 05000254/2016007; 05000265/2016007 cc: Distribution via

LISTSE RV