IR 05000483/2013002
| ML13123A252 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/02/2013 |
| From: | O'Keefe N NRC/RGN-IV/DRP/RPB-B |
| To: | Heflin A Union Electric Co |
| O'Keefe N | |
| References | |
| IR-13-002 | |
| Download: ML13123A252 (30) | |
Text
U N IT E D S TA TE S N U C LE AR R E GU LA TOR Y C OM MI S S I ON May 2, 2013
SUBJECT:
CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2013002
Dear Mr. Heflin,
On March 27, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Callaway Plant. The enclosed inspection report documents the inspection results which were discussed on April 3, 2013, with Mr. C. Reasoner, Vice President Engineering, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
No findings 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 NRC's Agencywide Document 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/
Neil O'Keefe, Chief Project Branch B Division of Reactor Projects Docket No.: 50-483 License No.: NPF-30 Enclosure: Inspection Report 05000483/2013002 w/ Attachment: Supplemental Information cc w/ encl: Electronic Distribution
SUMMARY OF FINDINGS
IR 05000483/2013002, 01/01 - 03/27/2013; Callaway Plant, Integrated Resident and Regional
Report The report covered a 3-month period of inspection by resident inspectors and an in-office review by region-based inspectors. No findings were identified. The significance of most findings is indicated by their color (Green, White, Yellow, or Red) using Inspection Manual Chapter 0609,
Significance Determination Process. The cross-cutting aspect is determined using Inspection Manual Chapter 0310, Components Within the Cross-Cutting Areas. Findings for which the significance determination process does not apply may be Green or be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process,
Revision 4, dated December 2006.
NRC-Identified Findings and Self-Revealing Findings
None
Licensee-Identified Violations
None
REPORT DETAILS
Summary of Plant Status
Callaway began the inspection period at 100 percent power. With the exception of planned power reductions for routine surveillance testing, the plant remained at full power until March 15, 2013. On that date, the plant began an end of cycle coastdown with power slowly lowering as available fuel reactivity decreased near the end of the designed core life. The plant ended the inspection period at 93.5 percent power.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
Readiness for Impending Adverse Weather Conditions
a. Inspection Scope
Since thunderstorms with potential tornados and high winds were forecast in the vicinity of the facility for January 29, 2013, the inspectors reviewed the plant personnels overall preparations/protection for the expected weather conditions. The inspectors evaluated the adequacy of the plant staffs preparations against the sites procedures. During the inspection, the inspectors focused on plant-specific design features and the licensees procedures used to respond to specified adverse weather conditions. The inspectors toured the plant grounds to look for any loose debris that could become missiles during a tornado. The inspectors also reviewed a sample of corrective action program (CAP)items to verify that the licensee-identified adverse weather issues at an appropriate threshold and dispositioned them through the corrective action program in accordance with station corrective action procedures. Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of one readiness for impending adverse weather condition sample as defined in Inspection Procedure 71111.01-05.
b. Findings
No findings were identified.
1R04 Equipment Alignment
Partial Walkdown
a. Inspection Scope
The inspectors performed partial system walkdowns of the following risk-significant systems:
January 4, 2013, vital ac switchgear air conditioning unit train A with train B out of service February 7, 2013, control room air conditioning system train A with train B out of service February 14, 2013, essential service water train A during replacement of essential service water train B pump motor February 25, 2013, non-safety auxiliary feedwater pump The inspectors selected these systems based on their risk significance relative to the reactor safety cornerstones at the time they were inspected. The inspectors attempted to identify any discrepancies that could affect the function of the system, and, therefore, potentially increase risk. The inspectors reviewed applicable operating procedures, system diagrams, Final Safety Analysis Report, technical specification requirements, administrative technical specifications, outstanding work orders, condition reports, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have rendered the systems incapable of performing their intended functions. The inspectors also inspected accessible portions of the systems to verify system components and support equipment were aligned correctly and operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no obvious deficiencies. The inspectors also verified that the licensee had properly identified and resolved equipment alignment problems that could cause initiating events or impact the capability of mitigating systems or barriers and entered them into the corrective action program with the appropriate significance characterization. Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of four partial system walkdown samples as defined in Inspection Procedure 71111.04-05.
b. Findings
No findings were identified.
1R05 Fire Protection
.1 Quarterly Fire Inspection Tours
a. Inspection Scope
The inspectors conducted fire protection walkdowns that were focused on availability, accessibility, and the condition of firefighting equipment in the following risk-significant plant areas:
January 31, 2013, residual heat removal pump room train A, containment spray pump room train A, safety injection pump room train A, and centrifugal charging pump room train A; fire areas A-2A and A-2B February 22, 2013, control building, room 3101, fire area C-1 February 22, 2013, lower cable spreading room; fire area C-21 February 22, 2013, upper cable spreading room; fire area C-22 March 8, 2013, load center and motor-generator sets room; fire area A-27 The inspectors reviewed areas to assess if licensee personnel had implemented a fire protection program that adequately controlled combustibles and ignition sources within the plant; effectively maintained fire detection and suppression capability; maintained passive fire protection features in good material condition; and had implemented adequate compensatory measures for out of service, degraded or inoperable fire protection equipment, systems, or features, in accordance with the licensees fire plan.
The inspectors selected fire areas based on their overall contribution to internal fire risk as documented in the plants Individual Plant Examination of External Events with later additional insights, their potential to affect equipment that could initiate or mitigate a plant transient, or their impact on the plants ability to respond to a security event. Using the documents listed in the attachment, the inspectors verified that fire hoses and extinguishers were in their designated locations and available for immediate use; that fire detectors and sprinklers were unobstructed; that transient material loading was within the analyzed limits; and fire doors, dampers, and penetration seals appeared to be in satisfactory condition. The inspectors also verified that minor issues identified during the inspection were entered into the licensees corrective action program.
Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of five quarterly fire-protection inspection samples as defined in Inspection Procedure 71111.05-05.
b. Findings
No findings were identified.
.2 Annual Fire Protection Drill Observation
a. Inspection Scope
On February 17, 2013, the inspectors observed the fire brigade activation for a fire drill in the laundry decontamination general area. The observation evaluated the readiness of the plant fire brigade to fight fires. The inspectors verified that the licensee staff identified deficiencies, openly discussed them in a self-critical manner at the drill debrief, and took appropriate corrective actions. Specific attributes evaluated were
- (1) proper wearing of turnout gear and self-contained breathing apparatus;
- (2) proper use and layout of fire hoses;
- (3) employment of appropriate fire fighting techniques;
- (4) sufficient
firefighting equipment brought to the scene;
- (5) effectiveness of fire brigade leader communications, command, and control;
- (6) search for victims and propagation of the fire into other plant areas;
- (7) smoke removal operations;
- (8) utilization of preplanned strategies;
- (9) adherence to the preplanned drill scenario; and
- (10) drill objectives.
These activities constitute completion of one annual fire-protection inspection sample as defined in Inspection Procedure 71111.05-05.
b. Findings
No findings were identified.
1R11 Licensed Operator Requalification Program and Licensed Operator
Performance (71111.11)
.1 Quarterly Review of Licensed Operator Requalification Program
a. Inspection Scope
On February 5, 2013, the inspectors observed a crew of licensed operators in the plants simulator during requalification testing. The inspectors assessed the following areas:
Licensed operator performance The ability of the licensee to administer the evaluations and the quality of the evaluation The modeling and performance of the control room simulator The quality of post-scenario critiques Follow-up actions taken by the licensee for identified discrepancies and for operators who failed the evaluation Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of one quarterly licensed operator requalification program sample as defined in Inspection Procedure 71111.11.
b. Findings
No findings were identified.
.2 Quarterly Observation of Licensed Operator Performance
a. Inspection Scope
On the dates listed below, the inspectors observed the performance of on-shift licensed operators in the plants main control room. The inspectors observed the operators performance of the following activities:
March 18, 2013, shifting trains of the component cooling water system March 25, 2013, routine control room activities including shift turnover during plant coastdown In addition, the inspectors assessed the operators adherence to plant procedures, including Procedure ODP-ZZ-00001, "Operations Department - Code of Conduct," and other operations department policies.
Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of two quarterly licensed-operator performance samples as defined in Inspection Procedure 71111.11.
b. Findings
No findings were identified.
1R12 Maintenance Effectiveness
a. Inspection Scope
The inspectors evaluated degraded performance issues involving the following risk significant system:
January 14, 2013, ultimate heat sink train A cooling tower sump heater The inspectors reviewed events such as where ineffective equipment maintenance has resulted in the unplanned inoperability of engineered safeguards systems and independently verified the licensee's actions to address system performance or condition problems in terms of the following:
Implementing appropriate work practices Identifying and addressing common cause failures Scoping of systems in accordance with 10 CFR 50.65(b)
Characterizing system reliability issues for performance monitoring
Charging unavailability for performance monitoring Trending key parameters for condition monitoring Ensuring proper classification in accordance with 10 CFR 50.65(a)(1) or -(a)(2)
Verifying appropriate performance criteria for structures, systems, and components classified as having an adequate demonstration of performance through preventive maintenance, as described in 10 CFR 50.65(a)(2), or as requiring the establishment of appropriate and adequate goals and corrective actions for systems classified as not having adequate performance, as described in 10 CFR 50.65(a)(1)
The inspectors assessed performance issues with respect to the reliability, availability, and condition monitoring of the system. In addition, the inspectors verified maintenance effectiveness issues were entered into the CAP with the appropriate significance characterization. Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of one quarterly maintenance effectiveness sample as defined in Inspection Procedure 71111.12-05.
b. Findings
No findings were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control
a. Inspection Scope
The inspectors reviewed licensee personnel's evaluation and management of plant risk for the maintenance and emergent work activities affecting risk-significant and safety-related equipment listed below to verify that the appropriate risk assessments were performed prior to removing equipment for work:
February 14, 2013, emergent emergency service water train B pump motor replacement, Job 13000796 March 7, 2013, failure of the in-core flux map console, Job 13001069 March 18, 2013, emergent control room air conditioning system train B chiller freon leak, Job 13001278 The inspectors selected these activities based on potential risk significance relative to the reactor safety cornerstones. As applicable for each activity, the inspectors verified that licensee personnel performed risk assessments as required by 10 CFR 50.65(a)(4)and that the assessments were accurate and complete. When licensee personnel performed emergent work, the inspectors verified that the licensee personnel promptly
assessed and managed plant risk. The inspectors reviewed the scope of maintenance work, and verified plant conditions were consistent with the risk assessment. The inspectors also reviewed the technical specification requirements and inspected portions of redundant safety systems, when applicable, to verify risk analysis assumptions were valid and applicable requirements were met. Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of three maintenance risk assessments and emergent work control inspection samples as defined in Inspection Procedure 71111.13-05.
b. Findings
No findings were identified.
1R15 Operability Evaluations and Functionality Assessments
a. Inspection Scope
The inspectors reviewed the following assessments:
January 14, 2013, ultimate heat sink cooling tower train A sump frozen over, Callaway Action Request 201300301 February 5, 2013, undocumented modification on control room chillers and class 1E electrical bus chillers, Callaway Action Request 201300905 March 4, 2013, containment isolation valves de-energized for maintenance, Callaway Action Request 201301650 March 26, 2013, turbine-driven auxiliary feedwater pump operability during end of cycle coastdown, Callaway Action Request 201301816 The inspectors selected these operability and functionality assessments based on the risk significance of the associated components and systems. The inspectors evaluated the technical adequacy of the evaluations to ensure technical specification operability was properly justified and to verify the subject component or system remained available such that no unrecognized increase in risk occurred. The inspectors compared the operability and design criteria in the appropriate sections of the technical specifications and Final Safety Analysis Report to the licensees evaluations to determine whether the components or systems were operable. Where compensatory measures were required to maintain operability, the inspectors determined whether the measures in place would function as intended and were properly controlled. Additionally, the inspectors reviewed a sampling of corrective action documents to verify that the licensee was identifying and correcting any deficiencies associated with operability evaluations. Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of four operability evaluations inspection samples as defined in Inspection Procedure 71111.15-05.
b. Findings
No findings were identified.
1R18 Plant Modifications
a. Inspection Scope
To verify that the safety functions of important safety systems were not degraded, the inspectors reviewed the following temporary modification:
Temporary Modification 12-0005, train A class 1E electrical equipment air conditioning unit (SGK05A) sensing line modification The inspectors reviewed the temporary modification and the associated safety evaluation screening against the system design bases documentation, including the Final Safety Analysis Report and the technical specifications, and verified that the modification did not adversely affect the system operability/availability. The inspectors also verified that the installation and restoration were consistent with the modification documents and that configuration control was adequate. Additionally, the inspectors verified that the temporary modification was identified on control room drawings, appropriate tags were placed on the affected equipment, and licensee personnel evaluated the combined effects on mitigating systems and the integrity of radiological barriers.
Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of one sample for temporary plant modifications as defined in Inspection Procedure 71111.18-05.
b. Findings
No findings were identified.
1R19 Post-Maintenance Testing
a. Inspection Scope
The inspectors reviewed the following post-maintenance activities to verify that procedures and test activities were adequate to ensure system operability and functional capability:
January 8, 2013, control room air conditioning train B functional test following compressor replacement, Job 11005024 February 16, 2013, essential service water train B pump post-maintenance testing following pump motor replacement, Job 13000796 March 6, 2013, containment spray train B pump and valve post-maintenance testing following system maintenance outage, Job 13500597 March 13, 2013, residual heat removal train B mini-flow valve post-maintenance testing following valve packing adjustment, Job 12001954 March 21, 2013, control room air conditioning train B functional test following freon leak repair, Job 13001278 March 26, 2013, control room filter fan train B testing following contactor replacement, Job 13001438 The inspectors selected these activities based upon the structure, system, or component's ability to affect risk. The inspectors evaluated these activities for the following:
The effect of testing on the plant had been adequately addressed; testing was adequate for the maintenance performed Acceptance criteria were clear and demonstrated operational readiness; test instrumentation was appropriate The inspectors evaluated the activities against the technical specifications, the Final Safety Analysis Report, 10 CFR Part 50 requirements, licensee procedures, and various NRC generic communications to ensure that the test results adequately ensured that the equipment met the licensing basis and design requirements. In addition, the inspectors reviewed corrective action documents associated with post-maintenance tests to determine whether the licensee was identifying problems and entering them in the corrective action program and that the problems were being corrected commensurate with their importance to safety. Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of six post-maintenance testing inspection samples as defined in Inspection Procedure 71111.19-05.
b. Findings
No findings were identified.
1R20 Refueling and Other Outage Activities
a. Inspection Scope
The inspectors reviewed the Callaway outage schedule, staffing plans, and contingency plans for the refueling outage, scheduled to commence April 8, 2013, to confirm that the licensee had appropriately considered risk, industry experience, and previous site-specific problems in developing and implementing a plan that assured maintenance of defense-in-depth. In addition, the inspectors reviewed the new fuel receipt process for the upcoming outage.
Specific documents reviewed during this inspection are listed in the attachment.
These inspection efforts constituted elements of a refueling outage sample as defined in Inspection Procedure 71111.20-05 which will be counted at the conclusion of Refueling Outage 19.
b. Findings
No findings were identified.
1R22 Surveillance Testing
a. Inspection Scope
The inspectors reviewed the Final Safety Analysis Report, procedure requirements, and technical specifications to ensure that the surveillance activities listed below demonstrated that the systems, structures, and/or components tested were capable of performing their intended safety functions. The inspectors either witnessed or reviewed test data to verify that the significant surveillance test attributes were adequate to address the following:
Evaluation of testing impact on the plant Acceptance criteria Test equipment Procedures Test data Testing frequency and method demonstrated technical specification operability Test equipment removal Restoration of plant systems Fulfillment of ASME Code requirements The inspectors also verified that licensee personnel identified and implemented any needed corrective actions associated with the surveillance testing.
January 9, 2013, infrequent at-power measurement of moderator temperature coefficient routine surveillance, Job 11508863
January 23, 2013, centrifugal charging pump train A inservice test, Job 12511736 January 31, 2013, safety injection system - containment spray actuation system train A slave relay routine testing, Job 12512150 March 8, 2013, reactor coolant system dose equivalent iodine-131 routine surveillance testing March 14, emergency diesel generator train B slow start routine testing, Job 13502063 Specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of four routine and one inservice surveillance testing inspection samples as defined in Inspection Procedure 71111.22-05.
b. Findings
No findings were identified.
Cornerstone: Emergency Preparedness
1EP4 Emergency Action Level and Emergency Plan Changes
a. Inspection Scope
The Nuclear Security and Incident Response headquarters staff performed an in-office review of the latest revisions of various emergency plan implementing procedures and the emergency plan located under ADAMS accession numbers ML130670147 and ML122000092.
The licensee determined that in accordance with 10 CFR 50.54(q), the changes made in the revisions resulted in no reduction in the effectiveness of the plan, and that the revised plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The NRC review was not documented in a safety evaluation report and did not constitute approval of licensee-generated changes; therefore, this revision is subject to future inspection. The specific documents reviewed during this inspection are listed in the attachment.
These activities constitute completion of two samples as defined in Inspection Procedure 71114.04-05.
b. Findings
No findings were identified.
1EP6 Drill Evaluation
Emergency Preparedness Drill Observation
a. Inspection Scope
The inspectors evaluated the conduct of a routine licensee emergency drill on March 5, 2013, to identify any weaknesses and deficiencies in classification, notification, and protective action recommendation development activities. The inspectors observed emergency response operations in the team 1 and 2 turnover drill to determine whether the event classification, notifications, and protective action recommendations were performed in accordance with procedures. The inspectors also attended the licensee drill critique to compare any inspector-observed weakness with those identified by the licensee staff in order to evaluate the critique and to verify whether the licensee staff was properly identifying weaknesses and entering them into the corrective action program.
As part of the inspection, the inspectors reviewed the drill package and other documents listed in the attachment.
These activities constitute completion of one sample as defined in Inspection Procedure 71114.06-05.
b. Findings
No findings were identified.
OTHER ACTIVITIES
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness, Public Radiation Safety, Occupational Radiation Safety, and Security
4OA1 Performance Indicator Verification
.1 Data Submission Issue
a. Inspection Scope
The inspectors performed a review of the performance indicator data submitted by the licensee for the fourth quarter 2012 performance indicators for any obvious inconsistencies prior to its public release in accordance with Inspection Manual Chapter 0608, Performance Indicator Program.
This review was performed as part of the inspectors normal plant status activities and, as such, did not constitute a separate inspection sample.
b. Findings
No findings were identified.
.2 Mitigating Systems Performance Index - Emergency ac Power System (MS06)
a. Inspection Scope
The inspectors sampled licensee submittals for the mitigating systems performance index - emergency ac power system performance indicator for the period from the first quarter 2012 through the fourth quarter 2012. To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6. The inspectors reviewed the licensees operator narrative logs, mitigating systems performance index derivation reports, issue reports, event reports, and NRC integrated inspection reports for the period of January 2012 through December 2012 to validate the accuracy of the submittals. The inspectors reviewed the mitigating systems performance index component risk coefficient to determine if it had changed by more than 25 percent in value since the previous inspection, and if so, that the change was in accordance with applicable NEI guidance.
The inspectors also reviewed the licensees issue report database to determine if any problems had been identified with the performance indicator data collected or transmitted for this indicator and none were identified. Specific documents reviewed are described in the attachment to this report.
These activities constitute completion of one mitigating systems performance index -
emergency ac power system sample as defined in Inspection Procedure 71151-05.
b. Findings
No findings were identified.
.3 Mitigating Systems Performance Index - Cooling Water Systems (MS10)
a. Inspection Scope
The inspectors sampled licensee submittals for the mitigating systems performance index - cooling water systems performance indicator for the period from the first quarter 2012 through the fourth quarter 2012. To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6. The inspectors reviewed the licensees operator narrative logs, issue reports, mitigating systems performance index derivation reports, event reports, and NRC integrated inspection reports for the period of January 2012 through December 2012 to validate the accuracy of the submittals. The inspectors reviewed the mitigating systems performance index component risk coefficient to determine if it had changed by more than 25 percent in value since the previous inspection, and if so, that the change was in accordance with applicable NEI guidance.
The inspectors also reviewed the licensees issue report database to determine if any problems had been identified with the performance indicator data collected or transmitted for this indicator and none were identified. Specific documents reviewed are described in the attachment to this report.
These activities constitute completion of one mitigating systems performance index -
cooling water system sample as defined in Inspection Procedure 71151-05.
b. Findings
No findings were identified.
.4 Reactor Coolant System Specific Activity (BI01)
a. Inspection Scope
The inspectors sampled licensee submittals for the reactor coolant system specific activity performance indicator for the period from the first quarter 2012 through the fourth quarter 2012. To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6.
The inspectors reviewed the licensees reactor coolant system chemistry samples, technical specification requirements, issue reports, event reports, and NRC integrated inspection reports for the period of January 2012 through December 2012 to validate the accuracy of the submittals. The inspectors also reviewed the licensees issue report database to determine if any problems had been identified with the performance indicator data collected or transmitted for this indicator and none were identified. In addition to record reviews, the inspectors observed a chemistry technician obtain and analyze a reactor coolant system sample. Specific documents reviewed are described in the attachment to this report.
These activities constitute completion of one reactor coolant system specific activity sample as defined in Inspection Procedure 71151-05.
b. Findings
No findings were identified.
4OA2 Problem Identification and Resolution
.1 Routine Review of Identification and Resolution of Problems
a. Inspection Scope
As part of the various baseline inspection procedures discussed in previous sections of this report, the inspectors routinely reviewed issues during baseline inspection activities and plant status reviews to verify that they were being entered into the licensees corrective action program at an appropriate threshold, that adequate attention was being given to timely corrective actions, and that adverse trends were identified and addressed. The inspectors reviewed attributes that included the complete and accurate identification of the problem; the timely correction, commensurate with the safety significance; the evaluation and disposition of performance issues, generic implications,
common causes, contributing factors, root causes, extent of condition reviews, and previous occurrences reviews; and the classification, prioritization, focus, and timeliness of corrective actions. Minor issues entered into the licensees corrective action program because of the inspectors observations are included in the attached list of documents reviewed.
These routine reviews for the identification and resolution of problems did not constitute any additional inspection samples. Instead, by procedure, they were considered an integral part of the inspections performed during the quarter and documented in Section 1 of this report.
b. Findings
No findings were identified.
.2 Daily Corrective Action Program Reviews
a. Inspection Scope
In order to assist with the identification of repetitive equipment failures and specific human performance issues for follow-up, the inspectors performed a daily screening of items entered into the licensees CAP. The inspectors accomplished this through review of the stations daily corrective action documents.
The inspectors performed these daily reviews as part of their daily plant status monitoring activities and, as such, did not constitute any separate inspection samples.
b. Findings
No findings were identified.
4OA5 Other Activities
(Closed) Temporary Instruction 2515/187 - Inspection of Near-Term Task Force Recommendation 2.3 Flooding Walkdowns
a. Inspection Scope
The inspectors verified that the following walkdown packages contained the elements as specified in NEI 12-07, "Walkdown Guidance," document:
Job 12003510-530, Post Fukushima Flooding Walkdown Room 3101 Job 12003510-535, Post Fukushima Flooding Non-Radiologically Controlled Areas Job 12003510-540, Post Fukushima Flooding Walkdown Radwaste Tunnel 1974
On October 2, 2012, the inspectors accompanied the licensee on their walkdown of Job 12003510-540, Post Fukushima Flooding Walkdown Radwaste Tunnel 1974 location and verified that the licensee confirmed the following flood protection features:
Building internal surfaces were examined for cracks, water staining, and spalling Critical structures, systems, and components dimensions were measured Available physical margin, where applicable, was determined Labeled wall penetrations were compared with architectural drawings by the licensee walkdown teams Passive ground water stops for pipes, conduit, cables, and building seismic gaps, were inspected for leakage On February 22, 2013, the inspectors independently performed their walkdown and verified that the following flood protection features were in place for Job 12003510-530, Post Fukushima Flooding Walkdown Room 3101 location:
Passive ground water stops for pipes, conduit, cables, and building seismic gaps, were inspected for leakage Building internal surfaces were examined for cracks, water staining, and spalling The inspectors verified that noncompliances with the current licensing requirements, and issues identified in accordance with the 10 CFR 50.54(f) letter, Item 2.g of Enclosure 4, were entered into the licensees corrective action program. No issues were identified.
Specific documents reviewed during this inspection are listed in the attachment.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On April 3, 2013, the inspectors presented the inspection results to Mr. C. Reasoner, Vice President Engineering, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- M. Covey, Assistant Operations Manager
- B. Cox, Senior Director, Nuclear Operations
- F. Diya, Vice President, Nuclear Operations
- T. Elwood, Supervising Engineer, Regulatory Affairs and Licensing
- L. Graessle, Senior Director, Operations Support
- L. Kanuckel, Director, Engineering Design
- J. Little, Supervising Engineer, Reactor/Safety Analysis
- S. Maglio, Regulatory Affairs Manager
- S. Petzel, Engineer, Regulatory Affairs
- C. Reasoner, Vice President, Engineering
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed
None
Discussed
None