IR 05000498/2015003

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IR 05000498/2015003 and 05000499/2015003, July 5 Through October 3, 2015 South Texas Project Electric Generating Station - Integrated Inspection Report
ML15316A638
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 11/12/2015
From: Nick Taylor
NRC/RGN-IV/DRP/RPB-B
To: Koehl D
South Texas
Nicholas Taylor
References
IR 2015003
Download: ML15316A638 (29)


Text

mber 12, 2015

SUBJECT:

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000498/2015003 AND 05000499/2015003

Dear Mr. Koehl:

On October 3, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your South Texas Project Electric Generating Station, Units 1 and 2, facility.

On October 8, 2015, the NRC inspectors discussed the results of this inspection with Mr. A. Capristo, Executive Vice President and Chief Administrative Officer, and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.

The NRC inspectors did not identify any findings or violations of more than minor significance.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs 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/

Nicholas H. Taylor, Branch Chief Project Branch B Division of Reactor Projects Docket Nos.: 50-498 and 50-499 License Nos.: NPF-76 and NPF-80

Enclosure:

Inspection Report 05000498/2015003 and 05000499/2015003 w/Attachment 1: Supplemental Information w/Attachment 2: Document Request for O

REGION IV==

Docket: 05000498, 05000499 License: NPF-76, NPF-80 Report: 05000498/2015003 and 05000499/2015003 Licensee: STP Nuclear Operating Company Facility: South Texas Project Electric Generating Station, Units 1 and 2 Location: FM 521 - 8 miles west of Wadsworth Wadsworth, Texas 77483 Dates: July 5 through October 3, 2015 Inspectors: A. Sanchez, Senior Resident Inspector P. Nizov, Resident Inspector P. Hernandez, Health Physicist J. Melfi, Project Engineer M. Phalen, Senior Health Physicist Approved Nicholas H. Taylor By: Chief, Project Branch B Division of Reactor Projects-1- Enclosure

SUMMARY

IR 05000498/2015003, 05000499/2015003; 07/05/2015 - 10/03/2015; South Texas Project

Electric Generating Station, Units 1 and 2.

The inspection activities described in this report were performed between July 5 and October 3, 2015, by the resident inspectors at the South Texas Project and inspectors from the NRCs Region IV office. The significance of inspection findings is indicated by their color (Green, White, Yellow, or Red), which is determined using Inspection Manual Chapter 0609,

Significance Determination Process, Dated April 29, 2015. Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, Aspects within the Cross-Cutting Areas, dated December 4, 2014. Violations of NRC requirements are dispositioned in accordance with the NRC Enforcement Policy, dated February 4, 2015. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5.

No findings were identified.

PLANT STATUS

Unit 1 began the period at 100 percent power and remained at or near 100 percent power for the entire inspection period.

Unit 2 began the period at 100 percent power. On July 16, 2015, Unit 2 experienced an automatic main steam moisture separator reheater isolation, which resulted in a reactor power reduction to approximately 93.5 percent power. On July 16, 2015, reactor power was restored to 100 percent power following restoration of the main steam moisture separator reheaters. Unit 2 remained at or near 100 percent power for the remainder of the inspection period.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

Summer Readiness for Offsite and Alternate AC Power Systems

a. Inspection Scope

On August 10, 2015, the inspectors completed an inspection of the stations off-site and alternate-ac power systems. The inspectors inspected the material condition of these systems, including transformers and other switchyard equipment to verify that plant features and procedures were appropriate for operation and continued availability of off-site and alternate-ac power systems. The inspectors reviewed outstanding work orders and open condition reports for these systems. The inspectors walked down the switchyard to observe the material condition of equipment providing off-site power sources.

The inspectors verified that the licensees procedures included appropriate measures to monitor and maintain availability and reliability of the off-site and alternate-ac power systems.

These activities constituted one sample of summer readiness of off-site and alternate-ac power systems, as defined in Inspection Procedure 71111.01.

b. Findings

No findings were identified.

1R04 Equipment Alignment

Partial Walkdown

a. Inspection Scope

The inspectors performed partial system walk-downs of the following risk-significant systems:

  • September 22, 2015, Unit 1, train A electrical auxiliary building heating, ventilation, and air conditioning while train B electrical auxiliary building heating, ventilation, and air conditioning was out of service for planned maintenance
  • September 28, 2015, Unit 2, train A essential cooling water while train B essential cooling water was out of service for planned maintenance
  • September 28, 2015, Unit 1, train B auxiliary feedwater while train C was out of service for planned maintenance The inspectors reviewed the licensees procedures and system design information to determine the correct lineup for the systems. They visually verified that critical portions of the trains were correctly aligned for the existing plant configuration.

These activities constituted three partial system walk-down samples, as defined in Inspection Procedure 71111.04.

b. Findings

No findings were identified.

1R05 Fire Protection

.1 Quarterly Inspection

a. Inspection Scope

The inspectors evaluated the licensees fire protection program for operational status and material condition. The inspectors focused their inspection on four plant areas important to safety:

  • September 22, 2015, Unit 1, train A control room heating, ventilation, and air conditioning, Fire Zone Z005
  • September 22, 2015, Unit 1, train A emergency switchgear room, Fire Zone Z004
  • September 28, 2015, Unit 2, train A essential cooling water pump room, Fire Zone Z605
  • September 28, 2015, Unit 1, train B auxiliary feedwater pump room, Fire Zone Z407 For each area, the inspectors evaluated the fire plan against defined hazards and defense-in-depth features in the licensees fire protection program. The inspectors evaluated control of transient combustibles and ignition sources, fire detection and suppression systems, manual firefighting equipment and capability, passive fire protection features, and compensatory measures for degraded conditions.

These activities constituted four quarterly inspection samples, as defined in Inspection Procedure 71111.05.

b. Findings

No findings were identified.

.2 Annual Inspection

a. Inspection Scope

This evaluation included observation of an unannounced and an announced fire drill on February 11, 2015, and September 25, 2015.

During this drill, the inspectors evaluated the capability of the fire brigade members, the leadership ability of the brigade leader, the brigades use of turnout gear and fire-fighting equipment, and the effectiveness of the fire brigades team operation. The inspectors also reviewed whether the licensees fire brigade met NRC requirements for training, dedicated size and membership, and equipment.

These activities constituted one annual inspection sample, as defined in Inspection Procedure 71111.05.

b. Findings

No findings were identified.

1R06 Flood Protection Measures

a. Inspection Scope

On October 2, 2015, the inspectors completed an inspection of the stations ability to mitigate flooding due to internal causes. After reviewing the licensees flooding analysis, the inspectors chose one plant area containing risk-significant structures, systems, and components that were susceptible to flooding:

  • Unit 1, train C emergency switchgear room The inspectors reviewed plant design features and licensee procedures for coping with internal flooding. The inspectors walked down the selected areas to inspect the design features, including the material condition of seals, drains, and flood barriers. The inspectors evaluated whether operator actions credited for flood mitigation could be successfully accomplished.

These activities constitute completion of one flood protection measures sample, as defined in Inspection Procedure 71111.06.

b. Findings

No findings were identified.

1R11 Licensed Operator Requalification Program and Licensed Operator Performance

.1 Review of Licensed Operator Requalification

a. Inspection Scope

On July 30, 2015, the inspectors observed simulator training for an operating crew. The inspectors assessed the performance of the operators and the evaluators critique of their performance. The inspectors also assessed the modeling and performance of the simulator during the simulator training.

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 Review of Licensed Operator Performance

a. Inspection Scope

On September 22, 2015, the inspectors observed the performance of on-shift licensed operators in the Unit 1 main control room. At the time of the observations, Unit 1 was in a period of heightened risk due to a large number of train B safety-related equipment out of service for maintenance. The inspectors observed the operators performance of the following activities:

  • Control of work activities and distractions while in the increased risk configuration
  • Response to an unexpected high radiation monitor alarm in the mechanical auxiliary building, including crew updates and off-normal procedure adherence In addition, the inspectors assessed the operators adherence to plant procedures, including conduct of operations manual and other operations department policies.

These activities constitute completion of one quarterly licensed operator performance sample, as defined in Inspection Procedure 71111.11.

b. Findings

No findings were identified.

1R12 Maintenance Effectiveness

a. Inspection Scope

The inspectors reviewed one instance of degraded performance or condition of safety-related structures, systems, and components (SSCs):

  • October 2, 2015, Unit 1, train A and Unit 2, train A and C essential cooling water continued a(1) status due to corrective and preventative maintenance activities The inspectors reviewed the extent of condition of possible common cause SSC failures and evaluated the adequacy of the licensees corrective actions. The inspectors reviewed the licensees work practices to evaluate whether these may have played a role in the degradation of the SSCs. The inspectors assessed the licensees characterization of the degradation in accordance with 10 CFR 50.65 (the Maintenance Rule), and verified that the licensee was appropriately tracking degraded performance and conditions in accordance with the Maintenance Rule.

These activities constituted completion of one maintenance effectiveness sample, as defined in Inspection Procedure 71111.12.

b. Findings

No findings were identified.

1R13 Maintenance Risk Assessments and Emergent Work Control

a. Inspection Scope

The inspectors reviewed three risk assessments performed by the licensee prior to changes in plant configuration and the risk management actions taken by the licensee in response to elevated risk:

  • Week of September 7, 2015, Unit 1, train D, 125 volts direct current battery and inverter 1202, 10-year preventative maintenance that required entry into the stations Configuration Risk Management Program
  • Week of September 21, 2015, Unit 1, train C work week that resulted in an elevated incremental core damage probability for the week (yellow)
  • Week of September 28, 2015, Unit 1, planned removal and corrective maintenance of the full flow condensate polishing system for the majority of the week The inspectors verified that these risk assessments were performed timely and in accordance with the requirements of 10 CFR 50.65 (the Maintenance Rule) and plant procedures. The inspectors reviewed the accuracy and completeness of the licensees risk assessments and verified that the licensee implemented appropriate risk management actions based on the result of the assessments.

These activities constitute completion of three maintenance risk assessments inspection samples, as defined in Inspection Procedure 71111.13.

b. Findings

No findings were identified.

1R15 Operability Determinations and Functionality Assessments

a. Inspection Scope

The inspectors reviewed four operability determinations that the licensee performed for degraded or nonconforming SSCs:

  • September 23, 2015, operability determination of the Unit 2 source range nuclear instrumentation following a failure in the solid state protection systems that energized these detectors while the reactor was at 100 percent power
  • September 29, 2015, operability determination of the Unit 2, train B essential cooling water upon discovery of degraded room inlet damper The inspectors reviewed the timeliness and technical adequacy of the licensees evaluations. Where the licensee determined the degraded SSC to be operable, the inspectors verified that the licensees compensatory measures were appropriate to provide reasonable assurance of operability. The inspectors verified that the licensee had considered the effect of other degraded conditions on the operability of the degraded SSC.

These activities constitute completion of four operability review samples, as defined in Inspection Procedure 71111.15.

b. Findings

No findings were identified.

1R19 Post-Maintenance Testing

a. Inspection Scope

The inspectors reviewed four post-maintenance testing activities that affected risk-significant SSCs:

  • August 12, 2015, Unit 2, train C emergency diesel generator following repairs of starting air leaks and other planned maintenance activities
  • September 9, 2015, Unit 2, train C control room heating, ventilation, and air conditioning following repair of the supply fan motor fan
  • September 29, 2015, Unit 2, emergency diesel generator 22 following replacement of several agastat plug-in relays in the diesel generator control circuits The inspectors reviewed licensing and design basis documents for the SSCs and the maintenance and post-maintenance test procedures. The inspectors observed the performance of the post-maintenance tests to verify that the licensee performed the tests in accordance with approved procedures, satisfied the established acceptance criteria, and restored the operability of the affected SSCs.

These activities constitute completion of four post-maintenance testing inspection samples, as defined in Inspection Procedure 71111.19.

b. Findings

No findings were identified.

1R22 Surveillance Testing

a. Inspection Scope

The inspectors observed four risk-significant surveillance tests and reviewed test results to verify that these tests adequately demonstrated that the SSCs were capable of performing their safety functions:

In-service tests:

  • September 30, 2015, Unit 2, train B component cooling water pump in-service test Other surveillance tests:
  • August 22, 2015, Unit 2, train A essential cooling water system surveillance test The inspectors verified that these tests met technical specification requirements, that the licensee performed the tests in accordance with their procedures, and that the results of the test satisfied appropriate acceptance criteria. The inspectors verified that the licensee restored the operability of the affected SSCs following testing.

These activities constitute completion of four surveillance testing inspection samples, as defined in Inspection Procedure 71111.22.

b. Findings

No findings were identified.

Cornerstone: Emergency Preparedness

1EP6 Drill Evaluation

Emergency Preparedness Drill Observation

a. Inspection Scope

The inspectors observed emergency preparedness drills on July 22, 2015, and September 16, 2015, to verify the adequacy and capability of the licensees assessment of drill performance. The inspectors reviewed the drill scenarios, observed the drills from the simulator, and attended the post-drill critiques. The inspectors verified that the licensees emergency classifications, off-site notifications, and protective action recommendations were appropriate and timely. The inspectors verified that any emergency preparedness weaknesses were appropriately identified by the licensee in the post-drill critique and entered into the corrective action program for resolution.

These activities constitute completion of two emergency preparedness drill observation samples, as defined in Inspection Procedure 71114.06.

b. Findings

No findings were identified.

RADIATION SAFETY

Cornerstones: Public Radiation Safety and Occupational Radiation Safety

2RS2 Occupational ALARA Planning and Controls

a. Inspection Scope

The inspectors assessed licensee performance with respect to maintaining occupational individual and collective radiation exposures as low as is reasonably achievable (ALARA). During the inspection, the inspectors interviewed licensee personnel and reviewed licensee performance in the following areas:

  • Site-specific ALARA procedures and collective exposure history, including the current 3-year rolling average, site-specific trends in collective exposures, and source-term measurements
  • ALARA work activity evaluations/post-job reviews, exposure estimates, and exposure mitigation requirements
  • The methodology for estimating work activity exposures, the intended dose outcome, the accuracy of dose rate and man-hour estimates, and intended versus actual work activity doses and the reasons for any inconsistencies
  • Records detailing the historical trends and current status of tracked plant source terms and contingency plans for expected changes in the source term due to changes in plant fuel performance issues or changes in plant primary chemistry
  • Radiation worker and radiation protection technician performance during work activities in radiation areas, airborne radioactivity areas, or high radiation areas
  • Audits, self-assessments, and corrective action documents related to ALARA planning and controls since the last inspection These activities constitute completion of one sample of occupational ALARA planning and controls, as defined in Inspection Procedure 71124.02.

b. Findings

No findings were identified.

2RS4 Occupational Dose Assessment

a. Inspection Scope

The inspectors evaluated the accuracy and operability of the licensees personnel monitoring equipment, verified the accuracy and effectiveness of the licensees methods for determining total effective dose equivalent, and verified that the licensee was appropriately monitoring occupational dose. The inspectors interviewed licensee personnel, walked down various portions of the plant, and reviewed licensee performance in the following areas:

  • External dosimetry accreditation, storage, issue, use, and processing of active and passive dosimeters
  • The technical competency and adequacy of the licensees internal dosimetry program
  • Adequacy of the dosimetry program for special dosimetry situations such as declared pregnant workers, multiple dosimetry placement, and neutron dose assessment
  • Audits, self-assessments, and corrective action documents related to dose assessment since the last inspection These activities constitute completion of one sample of occupational dose assessment, as defined in Inspection Procedure 71124.04.

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 Mitigating Systems Performance Index: Emergency AC Power Systems (MS06)

a. Inspection Scope

The inspectors reviewed the licensees mitigating system performance index data for the period of April 2014 through June 2015 to verify the accuracy and completeness of the reported data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, to determine the accuracy of the reported data.

These activities constituted verification of the mitigating system performance index for emergency ac power systems for Units 1 and 2, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

.2 Mitigating Systems Performance Index: High Pressure Injection Systems (MS07)

a. Inspection Scope

The inspectors reviewed the licensees mitigating system performance index data for the period of April 2014 through June 2015 to verify the accuracy and completeness of the reported data. The inspectors used definitions and guidance contained in Nuclear Energy Institute Document 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, to determine the accuracy of the reported data.

These activities constituted verification of the mitigating system performance index for high pressure injection systems for Units 1 and 2, as defined in Inspection Procedure 71151.

b. Findings

No findings were identified.

4OA2 Problem Identification and Resolution

.1 Routine Review

a. Inspection Scope

Throughout the inspection period, the inspectors performed daily reviews of items entered into the licensees corrective action program and periodically attended the licensees condition report screening meetings. The inspectors verified that licensee personnel were identifying problems at an appropriate threshold and entering these problems into the corrective action program for resolution. The inspectors verified that the licensee developed and implemented corrective actions commensurate with the significance of the problems identified. The inspectors also reviewed the licensees problem identification and resolution activities during the performance of the other inspection activities documented in this report.

b. Findings

No findings were identified.

.2 Annual Follow-up of Selected Issues

a. Inspection Scope

The inspectors selected two issues for an in-depth follow-up:

  • During Unit 2 Refueling Outage 2RE17, spring 2015, a negative trend in the rework and repeat maintenance activities for mechanical, electrical, instrumentation and controls, and the motor-operated and air-operated work groups.

The inspectors assessed the licensees problem identification threshold, cause analyses, extent of condition reviews, and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to arrest the negative trend in rework.

  • On July 16, 2015, Unit 2 experienced a complete main steam moisture separator reheater isolation, which resulted in an automatic control rod insertion and power reduction to approximately 93.5 percent.

The inspectors assessed the licensees problem identification threshold, cause analyses, extent of condition reviews and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned corrective actions and that these actions were adequate to correct the condition.

These activities constitute completion of two annual follow-up samples, as defined in Inspection Procedure 71152.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

Exit Meeting Summary

On July 30, 2015, the inspectors presented the radiation safety inspection results to Mr. D. Rencurrel, Senior Vice President, Operations, and other members of the licensee staff.

The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.

On October 8, 2015, the inspectors presented the inspection results to Mr. A. Capristo, Executive Vice President and Chief Administrative Officer, and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

R. Aguilera, Manager, Health Physics
J. Atkins, Manager, Systems Engineering
M. Berg, Manager, Design Engineering/Testing and Programs
C. Bowman, Manager, Nuclear Oversight
W. Brost, Engineer III
A. Capristo, Executive Vice President and Chief Administrative Officer
J. Connolly, General Manager, Engineering
R. Dunn Jr., Manager, Nuclear Fuel and Analysis
R. Engen, Manager, Engineering Projects
J. Enoch, Supervisor, Emergency Response
T. Farrand, Supervisor, RP ALARA
T. Frawley, Manager, Plant Protection/Emergency Response
C. Gann, Manager, Employee Concerns Program
R. Gibbs, Manager, Operations, Production Support
R. Gonzales, Senior Licensing Engineer
J. Hartley, Manager, Mechanical Maintenance
G. Hildebrandt, Manager, Operations
K. Hilscher, Manager, Training
G. Janak, Operations Training Manager
K. Kawabata, Health Physicist
D. Koehl, President and CEO
B. Lane, Shift Manager
J. Lovejoy, Manager, I&C Maintenance
A. McGalliard, Manager, Corporate Staff Support and Owner Liaison
R. McNeil, Manager, Maintenance Engineering
J. Milliff, Manager, Security
M. Murray, Manager, Regulatory Affairs
C. Pence, Manager, Chemistry
L. Peter, General Manager, Projects
J. Pierce, Manager, Unit 1 Operations
G. Powell, Site Vice President
D. Rencurrel, Senior Vice President, Operations
M. Ruvalcaba, Manager, Strategic Projects
R. Savage, Engineer, Licensing Consult Specialist
R. Scarborough, Manager, Quality Assurance
M. Schaefer, Plant General Manager
D. Shook, Fire Marshal
R. Stastny, Maintenance Manager
L. Sterling, Supervisor, Licensing
L. Stoicescu, Health Physicist
J. Von Suskil, Owner Rep - NRG South Texas LP
D. Zink, Supervising Engineering Specialist

Attachment 1

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

None

LIST OF DOCUMENTS REVIEWED