IR 05000498/2016004
| ML17045A224 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 02/08/2017 |
| From: | Taylor N H NRC/RGN-IV/DRP/RPB-B |
| To: | Powell G T South Texas |
| NICK TAYLOR | |
| References | |
| IR 2016004 | |
| Download: ML17045A224 (69) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD.
ARLINGTON, TX 76011-4511 February 13, 2017 Mr. G. Executive Vice President and Chief Nuclear Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483
SUBJECT: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION
- NRC INTEGRATED INSPECTION REPORT 05000498/2016004 AND 05000499/2016004
Dear Mr. Powell:
On December 31, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your South Texas Project Electric Generating Station, Units 1 and 2, facility
. On January 5, 2017
, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding s or violation s of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading
-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding.
"
Sincerely,/RA/
Nicholas H. Taylor, Branch Chief Project Branch B Division of Reactor Projects
Docket Nos.: 05000498, 05000499 License Nos.: NPF-76, NPF-80 G.
Enclosure:
Inspection Report 05000498/201 6004 and 05000499/201 6004 w/ Attachment 1: Supplemental Information w/ Attachment 2: Information Request for Inservice Inspection Activities w/ Attachment 3: Information Request for Occupational Radiation Safety Inspection w/ Attachment 4: Information Request for Public Radiation Safety Inspection SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - NRC INSPECTION REPORT 05000498/20 16004 AND 05000499/2016004 DATED FEBRUARY 13, 2017 DISTRIBUTION: Regional Administrator (Kriss.Kennedy@nrc.gov)
Deputy Regional Administrator (Scott.Morris@nrc.gov) DRP Director (Troy.Pruett@nrc.gov)
DRP Deputy Director (Ryan.Lantz@nrc.gov)
DRS Director (Anton.Vegel@nrc.gov) DRS Deputy Director (Jeff.Clark@nrc.gov) Acting Senior Resident Inspector (Chris.Smith@nrc.gov) Resident Inspector (Nicholas.Hernandez@nrc.gov) Branch Chief, DRP/B (Nick.Taylor@nrc.gov) Senior Project Engineer, DRP/B (David.Proulx@nrc.gov) Project Engineer, DRP/B (Steven.Janicki@nrc.gov) Project Engineer, DRP/B (Jim.Melfi@nrc.gov)
STP Administrative Assistant (Lynn.Wright@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov) Project Manager (Lisa.Regner@nrc.gov)
Team Leader, DRS/
IPAT (Thomas.Hipschman@nrc.gov) Project Engineer, DRS/IPAT (Eduardo.Uribe@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov)
Senior Congressional Affairs Officer (Jenny.Weil@nrc.gov)
RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov)
RIV/ETA: OEDO (Jeremy.Bowen@nrc.gov) ROPreports ADAMS ACCESSION NUMBER: SUNSI Review By: NHT/dll ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: NRC-002 OFFICE ASRI:DRP/B RI:DRP/B SRI:DRP/B C:DRS/EB1 C:DRS/EB2 C:DRS/OB NAME CSmith NHernandez ASanchez TFarnholtz GWerner VGaddy SIGNATURE
/RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 2/6/17 2/6/17 2/7/17 2/2/2017 02/01/2017 2/1/2017 OFFICE TL:DRS/IPAT C:DRS/PSB2 BC:DRP/B NAME THipschman HGepford NTaylor SIGNATURE
/RA/ /RA/ /RA/ DATE 2/1/2017 02/03/2017 2/13/17 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000498, 05000499 License: NPF-76, NPF-80 Report: 05000498/2016004, 05000499/20 16004 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: October 1 through December 31, 2016 Inspectors:
C. Smith, Acting Senior Resident Inspector A. Sanchez, Senior Resident Inspector N. Hernandez, Resident Inspector R. Azua, Senior Reactor Inspector L. Carson
, II, Senior Health Physicist K. Clayton, Senior Operations Engineer S. Graves, Senior Reactor Inspector N. Greene, PhD
, Health Physicist J. Melfi, Project Engineer M. Phalen, Senior Health Physicist D. Proulx, Senior Project Engineer Approved By: Nicholas H. Taylor Chief, Project Branch B Division of Reactor Projects
SUMMARY
IR 05000498/2016004, 05000499/2016004; 10/01/2016 - 12/31/2016; South Texas Project Electric Generating Station, Units 1 and 2,
Integrated Inspection Report. The inspection activities described in this report were performed between October 1 and December 31, 2016, by the resident inspectors at the South Texas Project and inspectors from the NRC's 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." Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, "Aspects within the Cross-Cutting Areas." Violations of NRC requirements are dispositioned in accordance with the NRC Enforcement Policy.
The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process."
No findings were identified.
PLANT STATUS
Unit 1 began the inspection period at full power and remained there for the remainder of the inspection period.
Unit 2 began the inspection period at full power. On October 1, 2016, the unit commenced coast down for a planned refueling outage. Refueling Outage 2RE18 began with a normal reactor shutdown on October 8, 2016. The unit remained in an outage until November 9, 2016, when the generator breaker was closed and the unit synchronized to the grid. Unit 2 returned to full power on November 14, 2016
, and remained at full power for the remainder of the inspection period.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
.1 Readiness for Seasonal Extreme Weather Conditions
a. Inspection Scope
On November 10, 2016
, the inspectors completed an inspection of the station's readiness for seasonal extreme weather conditions. The inspectors reviewed the licensee's adverse weather procedures for cold weather and evaluated the licensee's implementation of these procedures. The inspectors verified that prior to the onset of cold weather
, the licensee had corrected weather-related equipment deficiencies identified duri ng the previous winter season
. The inspectors selected two risk-significant systems that were required to be protected from cold weather
- Essential cooling water intake structure for Unit 1 and Unit 2 Boric acid storage tanks for Unit 1 and Unit 2
The inspectors reviewed the licensee's procedures and design information to ensure the systems would remain functional when challenged by cold weather. The inspectors verified that operator actions described in the licensee's procedures were adequate to maintain readiness of these systems. The inspectors walked down portions of these systems to verify the physical condition of the adverse weather protection features.
These activities constitute d one sample of readiness for seasonal adverse weather
, as defined in Inspection Procedure 71111.01.
b. Findings
No findings were identified.
.2 Readiness for Impending Adverse Weather Conditions
a. Inspection Scope
On November 17, 2016, the inspectors completed an inspection of the station's readiness for impending adverse weather conditions.
The inspectors reviewed plant design features
, the licensee's procedures to respond to tornadoes and high winds
, and the licensee's planned implementation of these procedures.
The inspectors evaluated operator staffing, and accessibility of controls and indications for those systems required to control the plant
.
These activities constitute d one sample of readiness for impending adverse weather condition s, as defined in Inspection Procedure 71111.01.
b. Findings
No findings were identified.
1R04 Equipment Alignment
.1 Partial Walk
-Down
a. Inspection Scope
The inspectors performed partial system walk
-downs of the following risk
-significant systems: November 8, 2016, Unit 2, train A centrifugal charging pump while the positive displacement charging pump was out of service for planned maintenance November 30, 2016, Unit 2, train C high head safety injection system while train B high head safety injection system was out of service for planned maintenance
The inspectors reviewed the licensee's procedures and system design information to determine the correct lineup for the systems. They visually verified that critical portions of the systems were correctly aligned for the existing plant configuration
. These activities constitute d two partial system walk
-down sample s, as defined i n Inspection Procedure 71111.04.
b. Findings
No findings were identified.
.2 Complete Walk
-Down
a. Inspection Scope
On December 12, 2016, the inspectors performed a complete system walk-down inspection of the Unit 1 component cooling water (CCW) system. The inspectors reviewed the licensee's procedures and system design information to determine the correct CCW system lineup for the existing plant configuration. The inspectors also reviewed outstanding work orders, open condition reports, and other open items tracked by the licensee's operations and engineering departments. The inspectors then visually verified that the system was correctly aligned for the existing plant configuration.
These activities constitute d one complete system walk
-down sample
, as defined in Inspection Procedure 71111.04.
b. Findings
No findings were identified.
1R05 Fire Protection
Quarterly Inspection
a. Inspection Scope
The inspectors evaluated the licensee's fire protection program for operational status and material condition. The inspectors focused their inspection on five plant areas important to safety
- October 18, 2016
, Unit 2, reactor containment building
, Fire Area 63, Fire Zone Z208 October 21, 2016, Unit 2, turbine generator building, Fire Area 90, Fire Zone Z708 November 8, 2016
, Unit 1, mechanical auxiliary building, Fire Area 29, Fire Zone Z140 November 8, 2016
, Unit 1, mechanical auxiliary building, Fire Area 2, Fire Zone Z128 November 22, 2016, Unit 1, electrical auxiliary building, Fire Area 2, Fire
Zone Z005 For each area, the inspectors evaluated the fire plan against defined hazards and defense-in-depth features in the licensee's 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 constitute d five quarterly inspection sample s, as defined in Inspection Procedure 71111.05.
b. Findings
No findings were identified.
1R06 Flood Protection Measures
a. Inspection Scope
On November 3, 2016, the inspectors completed an inspection of the station's ability to mitigate flooding due to internal causes. After reviewing the licensee's flooding analysis, the inspectors chose one plant area containing risk
-significant structures, systems, and components (SSCs) that were susceptible to flooding:
Unit 1, main control 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 d completion of one flood protection measures sample
, as defined in Inspection Procedure 71111.06.
b. Findings
No findings were identified.
1R07 Heat Sink Performance
a. Inspection Scope
On December 13, 2016, the inspectors completed an inspection of the readiness and availability of risk
-significant heat exchangers. The inspectors
- (1) observed performance tests for the Unit 2 train A, B, and C, component cooling water heat exchangers
- (2) reviewed the data from a performance test for the component cooling water heat exchangers
- and (3) verified the licensee used the industry standard periodic maintenance method outlined in EPRI NP-7552, "Heat Exchanger Performance Monitoring Guidelines,"
for the component cooling water heat exchangers
. Additionally, the inspectors walked down the heat exchanger s to observe its performance and material condition and verified that the heat exchangers were correctly categorized under the Maintenance Rule and were receiving the required maintenance.
These activities constitute d completion of one heat sink performance annual review sample, as defined in Inspection Procedure 71111.07.
b. Findings
No findings were identified.
1R08 Inservice Inspection Activities
The activities described in subsections 1 through 4 below constitute completion of one inservice inspection sample, as defined in Inspection Procedure 71111.08.
.1 Non-destructive Examination
Activities and Welding Activities
a. Inspection Scope
The inspectors directly observed the following nondestructive examinations:
SYSTEM WELD IDENTIFICATION EXAMINATION TYPE Reactor Coolant System 3-RC-2003-BB1-1 Ultrasonic Reactor Coolant System 4-RC-2126-BB1-3 Ultrasonic Reactor Coolant System 6-RC-2009-NSS-7 Ultrasonic Reactor Coolant System D2RCTE0420Y and Thermowell Penetrant Reactor Coolant System Reactor Coolant System Loop 2B Hot Leg Thermowell (E) Installation Detail Penetrant Reactor Coolant System Reactor Coolant System Loop 2B Hot Leg Thermowell (E) Installation Detail Visual 1 Auxiliary Feedwater System GUIDE/AF-2073-HL5002 Visual 3 Auxiliary Feedwater System RIGID RESTRAINT /
AF-2073-HL5004 Visual 3 Auxiliary Feedwater System 4-AF-2073-GA2-C (WA1-WA2) Visual 1 and Magnetic Particle Feedwater System FW2016 (FW
-20) Radiograph Feedwater System FW2016 (FW
-21) Radiograph
The inspectors reviewed records for the following nondestructive examinations:
SYSTEM WELD IDENTIFICATION EXAMINATION TYPE Main Steam System 30-MS-2001-GA2 (Weld 27)
Ultrasonic
During the review and observation of each examination, the inspectors observed whether activities were performed in accordance with the ASME Code requirements and applicable procedures. The inspectors also reviewed the qualifications of all nondestructive examination technicians performing the inspections to determine whether they were current.
The inspectors directly observed a portion of the following welding activities:
SYSTEM WELD IDENTIFICATION WELD TYPE Reactor Coolant System D2RCTE0420Y and Thermowell Gas Tungsten Arc Welding The inspectors reviewed whether the welding procedure specifications and the welders had been properly qualified in accordance with ASME Code Section IX requirements. The inspectors also determined whether that essential variables were identified, recorded in the procedure qualification record, and formed the bases for qualification of the welding procedure specifications.
b. Findings
No findings were identified.
.2 Vessel Upper Head Penetration Inspection Activities
No vessel upper head penetration inspection activities were scheduled for the South Texas Project, Unit 2, Outage 2RE18
.
.3 Boric Acid Corrosion Control
Inspection Activities
a. Inspection Scope
The inspectors reviewed the licensee's implementation of its boric acid corrosion control program for monitoring degradation of those systems that could be adversely affected by boric acid corrosion. The inspectors reviewed the documentation associated with the licensee's boric acid corrosion control walk
-down as specified in Procedure 0PGP03-ZE-0133, "Boric Acid Corrosion Control Program," Revision 10. The inspectors reviewed whether the visual inspections emphasized locations where boric acid leaks could cause degradation of safety significant components, and whether engineering evaluation used corrosion rates applicable to the affected components and properly assessed the effects of corrosion induced wastage on structural or pressure boundary integrity. The inspectors observed whether corrective actions taken were consistent with the ASME Code and 10 CFR Part 50, Appendix B requirements.
b. Findings
No findings were identified.
.4 Steam Generator Tube Inspection Activities
No steam generator tube inspection activities were scheduled for the South Texas Project, Unit 2, Outage 2RE18.
.5 Identification and Resolution of Problems
a. Inspection scope
The inspectors reviewed 34 condition reports which dealt with inservice inspection activities and found the corrective actions were appropriate. From this review, the inspectors concluded that the licensee had an appropriate threshold for entering issues into the corrective action program and had procedures that directed a root cause evaluation when necessary. The inspectors also determined the licensee had an effective program for applying industry operating experience. Specific documents reviewed during this inspection are listed in the report attachment.
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 October 26, 2016, the inspectors observed just-in-time simulator training of an operations crew preparing for Unit 2 reactor start
-up following 2RE18. 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 training event
.
These activities constitute d 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
The inspectors observed the performance of on
-shift licensed operators in the plant's main control room. At the time of the observations, the plant was in a period of heightened activity due to the following
- October 8, 2016, Unit 2, plant shutdown for Refueling Outage 2RE18 October 11, 2016, Unit 2, reduced inventory operations for planned maintenance October 17, 2016, Unit 2, core off-load activities for Refueling Outage 2RE18 In addition, the inspectors assessed the operators' adherence to plant procedures, including the conduct of operations procedure and other operations department policies.
These activities constitute d completion of one quarterly licensed operator performance sample, as defined in Inspection Procedure 71111.11
b. Findings
No findings were identified.
.3 Annual Inspection
(Units 1 and 2)
The licensed operator requalification program involves two training cycles that are conducted over a two year period. In the first cycle, the annual cycle, the operators are administered an operating test consisting of job performance measures and simulator scenarios. In the second part of the training cycle, the biennial cycle, operators are administered an operating test and a comprehensive written examination. For this annual inspection requirement, the licensee was in the first part of the training cycle.
a. Inspection Scope
The inspector reviewed the results of the operating tests for both units to satisfy the annual inspection requirements.
On November 17, 2016, the licensee informed the lead inspector of the following Unit 1 and 2 operating test results: A total of 87 operators took the tests (60 senior reactor operators, 27 reactor operators)
Fifteen of fifteen crews passed the simulator portion of the operating test Eighty-seven of eighty
-seven licensed operators passed the simulator portion of the operating test Eighty-six of eighty
-seven licensed operators passed the job performance measure portion of the examination There are currently four licensed reactor operators in the current initial training class and are administratively restricted from standing watch until receipt of a senior reactor operator license or successful completion of all requirements to go back on shift as a reactor operator. The individual that failed the job performance measure portion of the operating test was remediated, retested, and passed a retake operating test prior to returning to shift.
The inspector completed one inspection sample of the annual licensed operator requalification program.
b. Findings
No findings were identified.
1R12 Maintenance Effectiveness
.1 Routine Maintenance Effectiveness
a. Inspection Scope
The inspectors reviewed two instances of degraded performance or condition of safety-related SSCs: December 14, 2016, Unit 2, power range nuclear instrument 42 declared inoperable due to power supply failure December 20, 2016, Unit 2, train A spent fuel pool heat exchanger CCW return pressure relief valve socket weld failure In addition, the inspectors performed a complete system review (a vertical slice inspection
) of: December 13, 2016, Unit 1, train A, B, and C component cooling water system The inspectors reviewed the extent of condition of possible common cause SSC failures and evaluated the adequacy of the licensee's corrective actions. The inspectors reviewed the licensee's work practices to evaluate whether these may have played a role in the degradation of the SSCs. The inspectors assessed the licensee's 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.
For the vertical slice inspection, the inspectors reviewed all of the above and corrective maintenance performed on the component cooling water system during the past year.
These activities constituted completion of three maintenance effectiveness sample s, as defined in Inspection Procedure 71111.12.
.2 Quality Control
a. Inspection Scope
On December 19, 2016, the inspectors reviewed the licensee's quality control activities through a review of parts installed in the Unit 1, train A emergency diesel generator fire damper. These parts were purchased commercial
-grade but were dedicated prior to installation in a quality-grade application
. The inspectors reviewed the licensee's control of quality parts during maintenance associated with the fire damper replacement.
These activities constituted completion of one quality control 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
On October 16, 2016, the inspectors reviewed the licensee's implementation of the Configuration Risk Management Program, the associated risk assessment, and risk management actions. Specifically, for a transformer replacement activity that affected the Unit 1, 4.16 kV emergency safeguards bus E1 A, channel 3 and channel 4 undervoltage and degraded voltage relays the inspectors reviewed the licensee's actions prior to changes in plant configuration that elevated risk
.
The inspectors verified that this risk assessment was 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 licensee's risk assessment and verified that the licensee implemented appropriate risk management actions based on the result of the assessment.
Additionally, the inspectors also observed portions of one emergent work activity that had the potential to cause an initiating event, to affect the functional capability of mitigating systems, or to impact barrier integrity
. Specifically, on February 18, 2016, the inspectors observed Unit 2, steam generator feed pump 23 repairs following a failed overspeed test.
The inspectors verified that the licensee appropriately developed and followed a work plan for these activities. The inspectors verified that the licensee took precautions to minimize the impact of the work activities on unaffected SSCs.
These activities constitute d completion of two maintenance risk assessments and emergent work control inspection sample s, as defined in Inspection Procedure 71111.13.
b. Findings
No findings were identified.
1R15 Operability Determinations
and Functionality Assessments (71111.15)
a. Inspection Scope
The inspectors reviewed four operability determinations and functionality assessments that the licensee performed for degraded or nonconforming SSCs:
October 19, 2016, operability determination for the Unit 2 equipment hatch in a configuration that was not fully bolted in Mode 4 November 2, 2016
, operability determination of Unit 2, train C essential chilled water electrical auxiliary building main supply air handling unit 11C bypas s temperature control valve due to corrosion November 12, 2016, operator workaround for Unit 1 volume control tank hydrogen makeup regulator leakage.
November 30, 2016
, operability determination of the reactor coolant pressure boundary following identification of loose or missing bolts on the Unit 2 reactor vessel water level system heated junction thermocouple Grayloc connectors The inspectors reviewed the timeliness and technical adequacy of the licensee's evaluations. Where the licensee determined the degraded SSC to be operable or functional, the inspectors verified that the licensee's compensatory measures were appropriate to provide reasonable assurance of operability or functionality. The inspectors verified that the licensee had considered the effect of other degraded conditions on the operability or functionality of the degraded SSC. The inspectors reviewed operator actions taken or planned to compensate for degraded or nonconforming conditions.
The inspectors verified that the licensee effectively managed these operator workarounds to prevent adverse effects on the function of mitigating systems and to minimize their impact on the operator s' ability to implement abnormal and emergency operating procedures.
These activities constitute d completion of four operability and functionality review samples, which included one operator work
-around sample, as defined in Inspection Procedure 71111.15.
b. Findings
No findings were identified.
1R18 Plant Modifications
a. Inspection Scope
The inspectors reviewed two permanent plant modifications that affected risk
-significant SSCs: October 12, 2016
, installation of test connections at Unit 2 emergency diesel generator train C control panel to facilitate surveillance testing December 22, 2016, Unit 1 and Unit 2, trains A, B, and C, installation of a flow orifice in the essential cooling water return line to reduce cavitation and erosion in the piping The inspectors reviewed the design and implementation of the modification s. The inspectors verified that work activities involved in implementing the modification s did not adversely impact operator actions that may be required in response to an emergency or other unplanned event. The inspectors verified that post
-modification testing was adequate to establish the operability or functionality of the SSC s as modified.
These activities constitute d completion of two samples of permanent modifications
, as defined in Inspection Procedure 71111.18.
b. Findings
No findings were identifi ed.
1R19 Post-Maintenance
Testing (71111.19)
a. Inspection Scope
The inspectors reviewed seven post-maintenance testing activities that affected risk-significant SSCs:
October 6, 2016
, Unit 2, train C emergency diesel generator circulating water pump discharge check valve replacement October 16, 2016, Unit 1, train A, 4.16kV degraded and undervoltage potential transformer replacement following an emergent failure November 23, 2016, Unit 2, train A spent fuel pool heat exchanger CCW return pressure relief valve following a weld repair to a through-wall leak December 1 2, 2016, Unit 1, train B, CCW pump common header suction isolation motor operated valve 132 inspection and lubrication December 13, 2016, Unit 1, train B steam generator power
-operated relief valve 7421 following a drain line repair December 15, 2016, Unit 2, reactor coolant system loop 2B hot leg narrow range temperature element following replacement of loop B reactor coolant system thermowell and resistance temperature detector 420Y December 22, 2016, Unit 2
, train B emergency diesel generator diesel electrical relay testing after blown fuse and dropped start signal 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 d completion of seven post-maintenance testing inspection samples, as defined in Inspection Procedure 71111.19.
b. Findings
No findings were identified.
1R20 Refueling and Other Outage Activities
a. Inspection Scope
During the station's Refueling Outage 2RE18 that concluded on November 9, 2016, the inspectors evaluated the licensee's outage activities. The inspectors verified that the licensee considered risk in developing and implementing the outage plan, appropriately managed personnel fatigue, and developed mitigation strategies for losses of key safety functions. This verification included the following:
Review of the licensee's outage plan prior to the outage Review and verification of the licensee's fatigue management activities Monitoring of shut
-down and cool
-down activities Verification that the licensee maintained defense
-in-depth during outage activities Observation and review of reduced
-inventory and mid
-loop activities Observation and review of fuel handling activities Monitoring of heat
-up and start
-up activities These activities constitute d completion of one refueling outage sample
, as defined in Inspection Procedure 71111.20.
b. Findings
No findings were identified.
1R22 Surveillance Testing
a. Inspection Scope
The inspectors observed six 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 test s: November 16, 2016, Unit 1, component cooling water pump train B in-service test Containment isolation valve surveillance tests: October 19, 2016, Unit 2
, local leak rate test of the reactor containment building equipment hatch in a fully bolted configuration and in a four
-bolt configuration November 23, 2016, Unit 2, feedwater isolation actuation and response time test Other surveillance tests:
October 4, 2016, Unit 2
, technical support center diesel generator undervoltage test October 31, 2016, Unit 2, train A emergency diesel generator 21 loss-of-offsite power test November 9, 2016, Unit 2, main turbine overspeed 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 d completion of six surveillance testing inspection sample s, as defined in Inspection Procedure 71111.22.
b. Findings
No findings were identified.
RADIATION SAFETY
Cornerstones:
Public Radiation Safety and Occupational Radiation Safety
2RS1 Radiological Hazard Assessment and Exposure Controls
a. Inspection Scope
The inspectors evaluated the licensee's performance in assessing the radiological hazards in the workplace associated with licensed activities. The inspectors assessed the licensee's implementation of appropriate radiation monitoring and exposure control measures for both individual and collective exposures. During the inspection, the inspectors interviewed licensee personnel, walked down various areas in the plant, performed independent radiation dose rate measurements, and observed postings and physical controls. The inspectors reviewed licensee performance in the following areas:
Radiological hazard assessment, including a review of the plant's radiological source terms and associated radiological hazards
. The inspectors also reviewed the licensee's radiological survey program to determine whether radiological hazards were properly identified for routine and non
-routine activities and assessed for changes in plant operations
. Instructions to workers including radiation work permit requirements and restrictions, actions for electronic dosimeter alarms
, changing radiological condition, and radioactive material container labeling. Contamination and radioactive material control
, including release of potentially contaminated material from the radiologically controlled area, radiological survey performance, radiation instrument sensitivities, material control and release criteria, and control and accountability of sealed radioactive sources
. Radiological hazards control and work coverage
. During walk-downs of the facility and job performance observations, the inspectors evaluated ambient radiological conditions, radiological postings, adequacy of radiological controls, radiation protection job coverage, and contamination controls. The inspectors also evaluated dosimetry selection and placement as well as the use of dosimetry in areas with significant dose rate gradients. The inspectors examined the licensee's controls for items stored in the spent fuel pool and evaluated airborne radioactivity controls and monitoring
. High radiation area and very high radiation area controls. During plant walk-downs, the inspectors verified the adequacy of posting and physical controls, including areas of the plant with the potential to become risk
-significant high radiation areas.
Radiation worker performance and radiation protection technician proficiency with respect to radiation protection work requirements. The inspectors determined if workers were aware of significant radiological conditions in their workplace, radiation work permit controls/limits in place, and electronic dosimeter dose and dose rate set points. The inspectors observed radiation protection technician job performance, including the performance of radiation surveys.
Problem identification and resolution for radiological hazard assessment and exposure controls. The inspectors reviewed audits, self
-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.
These activities constitute completion of the seven required samples of radiological hazard assessment and exposure control program, as defined in Inspection Procedure 71124.01.
b. Findings
No findings were identified.
2RS2 Occupational ALARA Planning and Controls
a. Inspection Scope
The inspectors assessed licensee performance with respect to maintaining individual and collective radiation exposures as low as is reasonably achievable (ALARA)
. The inspectors performed this portion of the attachment during the refueling outage in order to directly observe the licensee's ALARA process activities
, including planning, implementation of radiological work controls, execution of work activities, and ALARA review of work
-in-progress. During the inspection, the inspectors interviewed licensee personnel, reviewed licensee documents, and evaluated licensee performance in the following areas:
Implementation of ALARA and radiological work controls. The inspectors observed pre
-job briefings, reviewed planned radiological administrative, operational, and engineering controls, and compared the planned controls to field activities.
Radiation worker and radiation protection technician performance during work activities performed in radiation areas, airborne radioactivity areas, or high radiation areas
. Problem identification and resolution for ALARA and radiological work controls. The inspectors reviewed audits, self
-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.
These activities constitute completion of two of the five required samples of occupational ALARA planning and controls program, as defined in Inspection Procedure 71124.02.
b. Findings
No findings were identified.
2RS5 Radiation Monitoring Instrumentation
a. Inspection Scope
The inspectors evaluated the accuracy and operability of the radiation monitoring equipment used by the licensee to monitor areas, materials, and workers to ensure a radiologically safe work environment. This evaluation included equipment used to monitor radiological conditions related to normal plant operations, anticipated operational occurrences, and conditions resulting from postulated accidents
. The inspectors interviewed licensee personnel, walked down various portions of the plant, and reviewed licensee performance associated with radiation monitoring instrumentation, as described below: The inspectors performed walk
-downs and observations of selected plant radiation monitoring equipment and instrumentation, including portable survey instruments, area radiation monitors, continuous air monitors, personnel contamination monitors, portal monitors, and small article monitors. The inspectors assessed material condition and operability, evaluated positioning of instruments relative to the radiation sources or areas they were intended to monitor, and verified performance of source checks and calibrations
.
The inspectors evaluated the calibration and testing program, including laboratory instrumentation
, whole body counters
, post-accident monitoring instrumentation, portal monitors, personnel contamination monitors, small article monitors, portable survey instruments, area radiation monitors
, electronic dosimetry
, air samplers, and continuous air monitors
.
The inspectors assessed problem identification and resolution for radiation monitoring instrumentation. The inspectors reviewed audits, self
-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.
These activities constitute completion of the three required samples of radiation monitoring instrumentation, as defined in Inspection Procedure 71124.05.
b. Findings
No findings were identified.
2RS6 Radioactive Gaseous and Liquid Effluent Treatment
a. Inspection Scope
The inspectors evaluated whether the licensee maintained gaseous and liquid effluent processing systems and properly mitigated, monitored, and evaluated radiological discharges with respect to public exposure. The inspectors verified that abnormal radioactive gaseous or liquid discharges and conditions, when effluent radiation monitors are out of service, were controlled in accordance with the applicable regulatory requirements and licensee procedures. The inspectors verified that the licensee's quality control program ensured radioactive effluent sampling and analysis adequately quantified and evaluated discharges of radioactive materials. The inspectors verified the adequacy of public dose projections resulting from radioactive effluent discharges. The inspectors interviewed licensee personnel and reviewed licensee performance in the following areas:
During walk-downs and observations of selected portions of the radioactive gaseous and liquid effluent equipment, the inspectors evaluated routine processing and discharge of effluents, including sample collection and analysis
. The inspectors observed equipment configuration and flow paths of selected gaseous and liquid discharge system components
, effluent monitoring systems, filtered ventilation system material condition, and significant changes to effluent release points.
Calibration and testing program for process and effluent monitors, including National Institute of Standards and Technology (NIST) traceability of sources
, primary and secondary calibration data, channel calibrations, set-point determination bases, and surveillance test results
.
Sampling and analysis controls used to ensure representative sampling and appropriate compensatory sampling. Reviews included results of the inter-laboratory comparison program and effluent releases made with inoperable radiation monitors.
Instrumentation and equipment, including effluent flow measuring instruments, air cleaning systems, and post
-accident effluent monitoring instruments
.
Dose calculations for effluent releases. The inspectors reviewed a selection of radioactive liquid and gaseous waste discharge permits and abnormal gaseous or liquid tank discharges, and verified the projected doses were accurate. The inspectors also reviewed 10 CFR Part 61 analyses and methods used to determine which isotopes were included in the source term. The inspectors reviewed land use census results, off-site dose calculation manual changes, and significant changes in reported dose values from previous years.
Problem identification and resolution for radioactive gaseous and liquid effluent treatment. The inspectors reviewed audits, self
-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.
These activities constitute completion of the six required samples of radioactive gaseous and liquid effluent treatment program, as defined in Inspection Procedure 71124.06.
b. Findings
No findings were identified.
2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation
a. Inspection Scope
The inspectors evaluated the effectiveness of the licensee
's programs for processing, handling, storage, and transportation of radioactive material.
The inspectors interviewed licensee personnel and reviewed the following items:
Radioactive material storage, including waste storage areas including container labeling/marking and monitoring containers for deformation or signs of waste decomposition
.
Radioactive waste system
, including walk
-downs of the accessible portions of the radioactive waste processing systems and handling equipment. The inspectors also reviewed or observed changes made to the radioactive waste processing systems, methods for dewatering and waste stabilization, waste stream mixing methodology, and waste processing equipment that was not operational or abandoned in place
.
Waste characterization and classification
, including radio-chemical sample analysis results for radioactive waste streams and use of scaling factors and calculations to account for difficult
-to-measure radionuclides, and processes for waste classification including use of scaling factors and 10 CFR Part 61 analyses.
Shipment preparation, including packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and preparation of the disposal manifests.
Shipping records for LSA I, II, III, SCOI, II, Type A, or Type B radioactive material or radioactive waste shipments.
Problem identification and resolution for radioactive solid waste processing and radioactive material handling, storage, and transportation. The inspectors reviewed audits, self
-assessments, and corrective action program documents to verify problems were being identified and properly addressed for resolution.
These activities constitute completion of the six required samples of radioactive solid waste processing, and radioactive material handling, storage, and transportation program, as defined in Inspection Procedure 71124.08.
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
- Residual Heat Removal System s (MS09)
a. Inspection Scope
The inspectors reviewed the licensee's mitigating system performance index data for the period of April 1, 2015
, through September 30, 2016
, 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 residual heat removal systems for Units 1 and 2, as defined in Inspection Procedure 71151.
b. Findings
No findings were identified.
.2 Mitigating Systems Performance Index
- Cooling Water Support Systems (MS10)
a. Inspection Scope
The inspectors reviewed the licensee's mitigating system performance index data for the period of April 1, 2015
, through September 30, 2016
, 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 cooling water support systems for Units 1 and 2, as defined in Inspection Procedure 71151.
b. Findings
No findings were identified.
.3 Occupational Exposure Control Effectiveness (OR01)
a. Inspection Scope
The inspectors verified that there were no unplanned exposures or losses of radiological control over locked high radiation areas and very high radiation areas during the period of April 1, 2015, to September 30, 2016. The inspectors reviewed a sample of radiologically controlled area exit transactions showing exposures greater than 100 mrem. 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 occupational exposure control effectiveness performance indicator, as defined in Inspection Procedure 71151.
b. Findings
No findings were identified.
.4 Radiological Effluent Technical Specifications (RETS)/Offsite Dose Calculation Manual (ODCM) Radiological Effluent Occurrences (PR01)
a. Inspection Scope
The inspectors reviewed corrective action program records for liquid or gaseous effluent releases that occurred between April 1, 2015
, and September 30, 2016, and were reported to the NRC to verify the performance indicator 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 radiological effluent technical specifications (RETS)/offsite dose calculation manual (ODCM) radiological effluent occurrences performance indicator, as defined in Inspection Procedure 71151.
b. Findings
No findings were identified.
4OA2 Problem Identification and Resolution
(71152)
.1 Routine Review
a. Inspection Scope
Throughout the inspection period, the inspectors performed daily reviews of items entered into the licensee's corrective action program and periodically attended the licensee's 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 licensee's problem identification and resolution activities during the performance of the other inspection activities documented in this report.
b. Findings
No findings were identified.
.2 Semiannual Trend Review
a. Inspection Scope
The inspectors reviewed the licensee's corrective action program, performance indicators, system health reports
, and other documentation to identify trends that might indicate the existence of a more significant safety issue. The inspectors verified that the licensee was taking corrective actions to address identified adverse trends.
Inspectors reviewed five electrical breaker failures that occurred from March 2016 to October 2016 for a potential trend Inspectors reviewed a licensee identified trend in equipment clearance order issues that occurred from July 2016 to December 2016 These activities constitute d completion of one semiannual trend review sample, as defined in Inspection Procedure 71152. b. Observations and Assessments The inspectors' review of the potential trend and trend identified above produced the following observations and assessments:
For the potential trend involving electrical breaker malfunctions that occurred from March 2016 to October 2016, the inspectors reviewed the licensee's investigations and causal analysis of each failure. The licensee experienced one instance of a Westinghouse type DS
-206 breaker failure to open, two instances of a Siemens HKR breaker failure to close, one instance of a Westinghouse type DS-206 breaker failure to close, and one instance of a Cutler Hammer molded case circuit breaker failed in the tripped open condition.
After reviewing these five instances of breaker failures, the licensee concluded that while different types and sizes of breakers had failed for various reasons in various states, no common cause or trend in a particular type of breaker or maintenance practice existed. The licensee did take action to improve maintenance procedures for overhauling Westinghouse type DS-206 breakers and to include additional site acceptance testing for Siemens HKR medium voltage breakers. The inspectors concluded that in response to these breaker failures
, the licensee had completed an appropriate evaluation and had developed appropriate planned corrective actions. For a negative trend involving equipment clearance orders, the licensee identified five equipment clearance order performance issues that occurred between July 2016 and December 2016
. The licensee is conducting a common cause investigation and conducting corrective actions under Condition Report 16-13975. The licensee has intiated action to re-establish the focus on equipment clearance order procedural compliance and strengthening worker engagement
. At the end of the inspection period, these actions were ongoing. Specifically, the licensee performed a safety stand down, briefed crews on safety expectations, and are working on a common cause analysis. The inspectors concluded that in response to this trend
, the licensee had developed and planned appropriate corrective actions
.
c. Findings
No findings were identified.
.3 Annual Follow
-up of Selected Issues
a. Inspection Scope
The inspectors selected two issues for an in
-depth follow
-up: On November 14, 2016
, inspectors completed an in
-depth review of the failure of Unit 1, control rod D
-6, to fully insert into the core during control rod drop testing activities on Novem ber 18, 2015.
The inspectors assessed the licensee's problem identification threshold, cause analyses, extent of condition reviews and compensatory actions. The inspectors verified that the licensee appropriately prioritized the planned and completed corrective actions and that these actions were adequate to correct the condition.
The licensee entered the issue into the corrective action program as Condition Report 15
-25420. The licensee submitted and received a one
-time license amendment to operate Unit 1 without control rod D
-6 on December 11, 2015.
The associated safety evaluation report for this issue is available in ADAMS wit h Accession No. ML15343A128.
The licensee removed the control rod, installed a flow restrictor, and modified the digital rod position indicator input and output.
Since reaching full power, Unit 1 has not experienced any issues with the modification. The licensee submitted a license amendment request dated April 7, 2016, to make the change permanent as the licensee has decided to forgo the rapid refuel function, the function in which the control rod drive mechanism was damaged and led to the control failure to operate properly.
The licensee received the license amendment on December 21, 2016 to operate Unit 1 with 56 full
-length control rods, with no full
-length control rod in core location D
-6. The associated safety evaluation report for this issue is available in ADAMS with Accession No. ML16319A010
.
During an in
-office inspection from November 28 through November 30, 2016, the inspector reviewed the three cyber security
-related findings documented in Inspection Report 05000498/2014406 and 05000 499/2014406, "INSPECTION OF IMPLEMENTATION OF INTERIM CYBER SECURITY MILESTONES 1
-7," (ML15033A104) for in
-depth follow
-up review. The inspector s reviewed a sample of updated program documents and procedures, updated critical digital asset listings, causal evaluations, training documents, and corrective action documents.
The inspectors assessed the licensee's extent of condition reviews, causal evaluations, compensatory actions, and pending and completed corrective actions. The inspector s verified that the licensee appropriately prioritized the corrective actions and that these actions were appropriate.
These activities constitute d completion of two annual follow
-up samples, as defined i n Inspection Procedure 71152.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On October 27, 2016, the inspectors presented the in-service inspection results to Mr. G. Powell, Executive Vice President and Chief Nuclear 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
.
On October 28, 2016, the inspectors presented the radiation safety inspection results to Mr. G. Powell, Executive Vice President and Chief Nuclear 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.
On November 30, 2016, the inspector presented the annual follow
-up of selected issues inspection results to Mr. W. Bankston, General Manager, Corporate Services, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspector did not review any proprietary information.
On December 1, 2016, the inspectors presented the radiation safety inspection results to Mr. B. Jefferson, Operations Director and Acting Plant Manager, 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.
The lead inspector obtained the final annual examination results for licensed operator requalification and telephonically exited with Mr. G. Janak, Operations Training Manager, on December 12, 2016
. The inspector did not review any proprietary information during this inspection.
On January 5, 2017, the inspectors presented the inspection results to Mr. G. Powell, Executive Vice President and Chief Nuclear 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.
1
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- D. Aguilar, Radiation Protection
- R. Aguilera, Manager, Health Physics
- J. Atkins, Manager, Systems Engineering
- M. Berg, Manager, Design Engineering
- J. Berrio, Manager, Operations, Production Support & Programs
- C. Bowman, Manager, Nuclear Support
- W. Brost, Engineer III
- A. Capristo, Executive Vice President and Chief Administrative Officer
- C. Clinton, Supervisor, Chemistry
- J. Connolly, Site Vice President
- I. Duncanson, Chemist, Chemistry
- R. Dunn Jr., Manager, Nuclear Fuel and Analysis
- G. Ferrigno, General Supervisor, Radiation Protection
- T. Frawley, Manager, Plant Protection/Emergency Response
- C. Gann, Manager, Employee Concerns Program
- T. Gardner, Technician, Chemistry
- R. Gibbs, Manager, Operations
Division, Unit Operations
- R. Gonzales, Senior Licensing Engineer
- M. Hellman, Supervisor, Cyber Security Program
G. Hildebran
dt, Manager, Operations
- K. Hilscher, Manager, Training
- G. Janak, Operations Training Manager
- B. Jefferson, Director, Operations, and Acting Plant Manager
L. Kauffman
, ALARA Supervisor, Radiation Protection
- K. Kawabata, Technician, Health Physics
- C. Kinman, Radiation Protection
- M. Kistler, Inspection Lead
- B. Lane, Manager, Operations Division, Integrated Work Management & Outage
- J. Lovejoy, Manager, I&C Maintenance
- E. Matejceck, Manager, Mechanical Maintenance
- J. McLeod, Analyst, Internet Technology Security
- R. McNeil, Manager, Maintenance Engineering
- B. Migl, Supervisor, Testing and Programs
- J. Milliff, Manager, Security
- P. Murphy, Operations
- M. Murray, Manager,
Regulatory Affairs
- K. Nigmatullina, Effluent Primary Chemist, Chemistry
- A. Otto, Radiation Protection
- M. Page, General Manager, Engineering
- C. Pence, Manager, Chemistry
- L. Peter, General Manager, Projects
- M. Pilgreen, Technical Supervisor, Radiation Protection
- G. Powell, Executive Vice President and Chief Nuclear Officer
- D. Rencurrel, Senior Vice President, Operations
Licensee Personnel
- R. Richardson, Welding Engineer
- P. Rodriquez, Radiation Protection
- M. Ruvalcaba, Manager, Strategic Projects
- R. Savage, Engineer, Licensing Consult Specialist
- R. Scarborough, Manager, Quality Assurance
- M. Schaefer, Plant General Manager
- L. Spiess, Supervisor, Engineering Testing/Programs
- R. Stastny, Maintenance Manager
- L. Sterling, Supervisor, Licensing
- L. Stoicescu, Health
Physicist, Radiation Protection
- C. Stone, RMC Supervisor, Health Physicist
- J. Von Suskil, Owner Rep
- J. Williams, Spec Engineering Consultant Testing/Programs (SE)
- P. Williams, Spec Engineering Consultant Testing/Programs (SE)
- D. Zink, Supervising Engineering Specialist
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
None
LIST OF DOCUMENTS REVIEWED
Section 1R01: Adverse Weather Protection
Condition Reports
(CRs)
- 15-17727 16-4787
Procedures
- Number Title Revision
- WCG-0013 Winter Peak Period Readiness
Work Orders
- Number Title Revision
- RO-1-91000555 Cold Weather Pre parations 10
- RO-2-91000556 Cold Weather Pre parations 10
- Section 1R04
- Equipment Alignment
Condition Reports
(CRs)
- 07-17718 14-02704 14-03724 14-04953 14-05559
- 14-05683 14-06251 14-07917 14-08917 14-10584 14-11071 14-17022 14-21867 14-21968 14-22640 14-22987 15-01103 15-23181 15-23393 15-24271 15-24274 15-24277 15-24278 15-24325 15-25462 15-26575 16-01483 16-05824 16-07179 16-07803 16-08007 16-10480 16-15574 16-15575 16-15576
Drawings
- Number Title Revision 5R209F05017
- Component Cooling Water System
- 5R209F05018
- Component Cooling Water System
- 5R209F05019
- Component Cooling Water System
- 5R209F05020
- Component Cooling Water System
- 5R209F05021
- Component Cooling Water System
- 5R209Z42040
- Component Cooling Water Pumps Logic Diagram
Miscellaneous
- Title Revision Design Basis Document 5R209MB1018, Component Cooling Water System 3 Calculation NC
-9703, MAB Flooding Analysis
- CCW System 3
rd quarter 2016 System Health Report
Procedures
- Number Title Revision 0POP02-CC-0001 Component Cooling Water
- 0POP02-SI-0002 Safety Injection System Initial Lineup
- 0PSP03-CV-0014 CVCS Equipment Verification Section 1R05
- Fire Protection
Procedures
- Number Title Revision 0MAB02-FP-0128 Fire Preplan Mechanical Auxiliary Building CCW Pump and Chiller, Train A
Procedures
- Number Title Revision 0MAB29-FP-0140 Fire Preplan Mechanical Auxiliary Building CCW Pump and Chiller, Train B
- 0RCB63-FP-0208 Fire Preplan Reactor Containment Building NW Peripheral Area 3 0TGB90-FP-0702 Fire Preplan Turbine Generator Building 4.16kV and Electrical Equipment Rooms
- 0EAB02-FP-0005 Fire Preplan Electrical Auxiliary Building Control Room HVAC Equipment Room, Train A
- Section 1R06
- Flood Protection Measures
Procedures
- Number Title Revision
- NC 9701 Flooding Analysis Electrical Auxiliary Building
- Section 1R07
- Heat Sink Performance Calculation
s Number Title Revision
- MC-6219 NRC Generic Letter 89
-013 2
Condition Reports
(CRs)
- 08-7910 10-15780
Miscellaneous
- Number Title Date
- ST-P2-HS-583 Response to IEN 86
-096 June, 25, 1987
- ST-P2-HS-605 Response to SOER 84
-001, Revision 1
- July 20, 1987
- ST-HL-AE-3341 Response to NRC Generic Letter 89
-13, Service Water System Problems Affecting Safety
-Related Equipment January 29, 1990
Procedures
- Number Title Revision 0PEP07-EW-0001 Performance Test for Essential Cooling Water Heat Exchangers
- 0PGP03-ZE-0080 Essential Cooling Water System Reliability Program Work Authorization Number (WAN)
- 508549
Section 1R08: Inservice Inspection Activities
Condition Reports
(CRs)
- 15-12024 15-12691 15-17763 15-17764 15-20733 15-21002 15-22714 15-26312 16-05990 16-07377 16-07766 16-08367 16-08728 16-10995 16-11576 16-13170 16-11677 16-11682 16-12236 16-12237 16-12239 16-12241 16-12242 16-12246 16-12428 16-12429 16-12430 16-12431 16-12432 16-12434 16-12448 16-12450 16-12451 16-12452 16-13342
Drawings
- Number Title Revision/Date Westinghouse
- 218E54 (R/3)
- Reactor Coolant System Loop 2
- July 10, 1978
- Westinghouse
- 2D33357 Reactor Coolant System Fast Response Thermowell Installation Detail
- Hot Leg 1 Westinghouse
- 1847E84 Reactor Coolant System Fast Response RTD Thermowell Detail - Hot Leg 2
Procedures
- Number Title Revision 0PEP10-ZA-0001 Non-Destructive Examination Written Practice
- 0PEP10-ZA-0002 Inservice Inspection Ultrasonic Non
-Destructive Examination Written Practice
- 0PEP10-ZA-0004 General Ultrasonic Examination
Procedures
- Number Title Revision 0PEP10-ZA-0009 Recording Data from Direct Visual, Liquid Penetrant, and Magnetic Particle Examinations
- 0PEP10-ZA-0010 Liquid Penetrant Examination (Color Contrast Solvent Removable
) 6 0PEP10-ZA-0017 Magnetic Particle Examination (Dry Powder Yoke Method)
- 0PEP10-ZA-0023 Visual Examination of Component Supports for ASME Section XI Inservice Inspection
- 0PEP10-ZA-0024 ASME XI Examination for VT
-1 and
- VT-3 4 0PEP10-ZA-0054 ASME Section XI VE Visual Examination
- 0PGP03-ZA-0014 Foreign Material Exclusion Program, Implementing Procedure
- 0PGP03-ZA-0014A Foreign Material Exclusion Program, Administrative Procedure
- 0PGP03-ZE-0133 Boric Acid Corrosion Control Program
- 0PGP03-ZX-0002A CAQ [Condition Adverse to Quality] Resolution Process
- 0PGP04-ZE-0304 Inservice Inspection Program for Welds and Component Supports 13 0PSP11-RC-0015 ASME Section XI Inservice Inspection
Work Orders
- 486958
- 508156
- 508303
- 513622
- 520246 523346
Section 1R11: Licensed Operator Requalification Program
and Licensed Operator Performance
Miscellaneous
- Title Date Operating Test Results November 17, 2016
- Section 1R12
- Maintenance Effectiveness
Condition Reports
(CRs)
- 16-8007 16-7803 16-7684 16-7179 16-5824 16-2121 16-1483 15-26575 15-25462 15-24278 15-24941 15-23747 15-23393 15-1103 14-21867 14-12769 15-13166 16-14555 16-14777
Miscellaneous
- Number Title Date
- N-666 Cases of ASME Boiler and Pressure Vessel Code Case N-666 April 18, 2006
Procedures
- Number Title Revision
- SEG-0009 Maintenance Rule Basis Document Guideline
- CFR 50.59 Evaluations Work Authorization Number (WAN)
- 516182
- 552285
- Section 1R13
- Maintenance Risk Assessments and Emergent Work Control
Condition Reports
(CRs)
- 16-12732 16-14257 16-14258 16-14259
Procedures
- Number Title Revision 0PGP03-ZA-0091 Configuration Risk Management Program
- 0PGP03-ZG-RMTS Risk-Managed Technical Specifications Program
- 0PSP03-CC-0001 Component Cooling water Pump 1A(2A) Inservice Test
- Work Activity Risk (WAR
)
- 2673
- Work Authorization Number (WAN)
- 508525
- Section 1R15
Condition Report
- Engineering Evaluation (CREE
)
- 16-12260-24 16-13368 16-12244-9 16-14462 16-15688
Condition Reports
(CRs)
- 16-12260 16-12244
Miscellaneous
- Number Title Revision
- WCAP-10857 Stress Report for RVLMS Head Adapter
- 5R179MB1017
Design Basis Document
- Chemical Volume and Control
Procedures
- Number Title Revision 0PEP10-ZA-0005 Ultrasonic Thickness Examination
- 0PGP03-ZE-0023 System Pressure Testing Program
- 0PGP03-ZO-9900 Operability Determinations and Functionality Assessments Program 7 0PGP04-ZA-0002 Condition Report Engineering Evaluation
- 0PMP04-ZG-0012 Equipment Hatch Removal and Installation
- 0POP01-ZA-0049 Condition Report Operations Evaluation Program 7 0POP01-ZO-0011 Operability, Functionality, and Reportability Guidance
- SEG-0001 System Engineering Administrative Guideline Work Authorization Number (WAN)
- 550153
- 488047
- Section 1R18
- Plant Modifications
Condition Reports
(CRs)
- 05-11049 05-8601 13-11301 16-5320 16-3502 13-0079
Design Basis Document
(DBD)
- Number Title Revision 5R289MB1006
- Essential Cooling Water System
Drawings
- Number Title Revision 5R289F05038
- 2 Essential Cooling Water System Train 2C 20 5R289F05039#1
- Essential Cooling Water System
- 5R289F05039#2
- Essential Cooling Water System
- 5R289F05038#2
- Essential Cooling Water System Train 2B
- 5R289F05038#1
- Essential Cooling Water System Train 1C
- 5R289F05039#1
- Essential Cooling Water System 16 5R289F05039#2
- Essential Cooling Water System
Procedures
- Number Title Revision/Date 0PGP04-ZE-0309/R15 Design Change Package Install Test Connections at Emergency Standby Diesel Generator Control Panels to Facilitate Surveillance Testing November 16,
- 2006 0PGP04-ZE-0309/R15 Design Change Package Install Test Connections at Emergency Standby Diesel Generator Control Panels to Facilitate Surveillance Testing December 19,
- 2007 0PGP04-ZE-0309/R15 Design Change Package Install Test Connections at Emergency Standby Diesel Generator Control Panels to Facilitate Surveillance Testing April 13,
- 2009 0PGP04-ZE-0309/R15 Design Change Package Install Test Connections at Emergency Standby Diesel Generator Control Panels to Facilitate Surveillance Testing March 30, 2011 0PGP04-ZE-0309/R15 Design Change Package Install Test Connections at Emergency Standby Diesel Generator Control Panels to Facilitate Surveillance Testing July 18, 2011
Procedures
- Number Title Revision/Date 0PGP04-ZE-0309/R15 Design Change Package Install Test Connections at Emergency Standby Diesel Generator Control Panels to Facilitate Surveillance Testing January 17, 2013 0PGP04-ZE-0309/R15 Design Change Package Install Test Connections at Emergency Standby Diesel Generator Control Panels to Facilitate Surveillance Testing December 1,
- 2015 0POP02-DG-0003 Emergency Diesel Generator 13(23)
- 0POP02-EW-0001 Essential Cooling Water Operations
- 0PSP03-EW-0019 Essential Cooling Water System Train C Testing
- 0PGP03-ZE-0022 Inservice Testing Program for Pumps
- 0PGP04-ZE-0311 Post Modification Acceptance Tests
- 0PGP04-ZE-0309 Design Change Package
- 0PSP03-EW-0012 Essential Cooling Water Pump 1C(2C) Reference Values Measurement
- 0PMP07-DG-0001 Standby Diesel Recording M&TE Installation Work Authorization Number (WAN)
- 549219
- 467920
- 475940
- 475863
- 475864
- 475941
- 474650
- 474716
- Section 1R19
- Post-Maintenance Testing
Condition Reports
(CRs)
- 16-12076 16-12732 16-14555 16-15651 16-15846
Drawings
- Number Title Revision 05S109F00016#1
- Piping and Instrumentation Diagram Main Steam
Procedures
- Number Title Revision 0PMP04-ZG-0058 Mission Split Disc/Clow Dual Plate Check Valve Maintenance
- 0PMP05-ZE-0206 Potential Transformer Test
Procedures
- Number Title Revision PMT Matrix 4.11
- Electrical Miscellaneous
- 0PSP03-MS-0001 Main Steam System Valve Operability Test
- 0PSP11-ZE-0001 Check Valve Inspection
- Work Authorization Number (WAN)
- 540664
- 550283
- 552285
- 517224
- 487060
- 554394
- Section 1R20
- Refueling and Other Outage Activities
Condition Reports
(CRs)
- 16-12244 16-12593 15-24053
Miscellaneous
- Title Date Shutdown Risk Assessment Report August 31, 2016
Procedures
- Number Title Revision 0PGP03-ZA-0101 Shutdown Risk Assessment
- 0PGP03-ZA-0114 Fatigue Rule Management
- 0PMP04-RX-0018A Non-Rapid Refueling Mechanical Support
- 0POP03-ZG-0007 Plant Cooldown
- 0POP03-ZG-0008 Power Operations
- 0POP03-ZG-0010 Refueling Operations
- 0POP08-FH-0001 Refueling Machine Operation Instruction
- 0POP08-FH-0009 Core Refueling
- 0PSP03-XC-0002A Containment Entry and Partial Inspection (Containment Integrity Established)
- Section 1R22
- Surveillance Testing
Condition Report
- Engineering Evaluation (CREE
)
- 16-12260-24
Condition Reports
(CRs)
- 16-12026 16-12023 16-11925 16-12032 16-12035 16-12025 16-12260
Procedures
- Number Title Revision 0PEP02-ZX-0010 Reload Initial Start Up Testing
- 0PEP07-TM-0007 Main Turbine Generator Startup Following Major Outage
- 0PGP03-ZA-0010 Performing and Verifying Station Activities
- 0PGP07-DB-0005 TSC Diesel Generator Performance Test
- 0PMP04-ZG-0012 Equipment Hatch Removal and Installation
- 0POP03-ZG-0001 Plant Heatup
- 0POP03-ZG-0005 Plant Startup to 100%
- 101 OPSP03-CC-0002 Component Cooling Water Pump 1B(2B) Inservice Test
- 0PSP11-XC-0001 LLRT: M-92 Equipment Hatch
- 2TEP07-XC-0001 Leak Rate Test: M
-92 Equipment Hatch
- 0PSP03-DG-0007 Standby Diesel 11(21) LOOP Test
- 0PSP03-SP-0023 Feedwater Isolation Actuation and Response Time Test Work Authorization Number (WAN
)
- 550153 486498
Section 2RS1: Radiological Hazard Assessment and Exposure Controls
- ALARA Work Packages Number Title WAN 504894
- Proportional Counter Detector
- Source Range
- 16-4031-7 Non-Rapid Refuel 2RE18 Reactor Disassembly
- Audits and Self
-Assessments Number Title Date 16-02 Radiological Control Quality Audit Report April 12, 2016
- 16-679 Self-Assessment
- STP Radiation Worker Training Program June 16, 2016
- 15-13617 Self-Assessment
- Contamination Control December 17, 2017
- 15-1253 Self-Assessment
-
- IP 71124.01 Radiological Hazards &
- IP 71124.03 In
-Plant Airborne Mitigation April 1, 2015
Condition Reports
(CRs)
- 15-23681 15-23921 15-24455 16-13284 16-03202
Miscellaneous
- 1RE19 Refueling Outage ALARA Report June 1, 2016
- 2RE18 ALARA Update Report October 26, 2016
- STPNOC Daily Operational Focus Meeting Package October 24
- 28, 2016 STPNOC ALARA Strategic Planning Guide 2016
-2020 July 24, 2016
- Chapter 12, "Radiation Protection"
- SFP Storage & Work Inventory 2016
- October 2016
- STP Radioactive Source Surveillance July 2016
- STP Tech Spec Source Inventory July 28, 2016
Procedures
- Number Title Revision STI 34206291
- Conduct of Operations Radiation Protection
- 0PGP03-ZR-0048 Personnel Dosimetry Program
- 0PGP03-ZR-0050 Radiation Protection Program 13 0PGP03-ZR-0051 Radiological Access Controls/Standards
- 0PRP03-ZR--0004 Inventory and Leak Testing of Radioactive Sources
- 0PRP04-ZR-0004 Release of Materials from Radiologically Controlled Areas
- 0PRP04-ZR-0011 Radiation Protection Key Control 31 0PRP04-ZR-0013 Radiological Survey Program
Procedures
- Number Title Revision 0PRP04-ZR-0015 Radiological Posting and Warning Devices
- 0PRP07-ZR-0033 Radiological Briefings
- 0PRP07-ZR-0016 Lockdown and Posting of Transfer of Spent Fuel Irradiated Material through Transfer Tube Radiation Work Permits Number Title Revision 2016-2-0078 2RE18-Radiation Protection Maintenance and Support
- 2016-2-0079 2RE18 Radiation Protection Support (HRA)
- 2016-2-0080 2RE18 Radiation Protection Support (LHRA)
- 2016-2-0091 2RE18-Major Decon of Reactor Cavity 2
- 2016-2-0131 RE18-O-Ring Groove Cleaning
- 2016-2-0130 2RE18- Reactor Head Lift
- 2016-2-0109 2RE18-Maintenance and Support Work
- 2016-2-0120 2RE18-Radiography Activities Inside the RCA (HRA)
- 2016-2-0129 2RE18-Refuel Perform Fuel Movement in RCB
Section 2RS2: Occupational
- ALARA Planning and Controls
- ALARA Work Packages Number Title 15-2020-9 2RE17 Non
-Rapid Refuel
- 15-17755-3 1RE19 Room 001 Activities
- 15-17755-5 1RE19 Non
-Rapid Refuel
- 15-17755-6 1RE19 Reactor Coolant Pump Maintenance
- 15-17755-7 1RE19 Room 003 Activities
- 15-17755-8 1RE19 Snubber Inspections
- 15-17755-9 1RE19 Steam Generator Inspections
- 15-17755-10 1RE19 D-6 Reactor Head Dis
-Assembly and Re
-Assembly 16-4031-7 2RE18 Non
-Rapid Refuel Audits, Self
-Assessments, and Surveillances Number Title Date 15-212 STPNOC Self
-Assessment of the Respiratory Protection Program October 12, 2015
- 16-002 STPNOC Radiological Controls Quality Audit Report April 13, 2016
- 16-771 STPNOC Snapshot Self-Assessment of Access to Radiologically Significant Areas August 23, 2016
Condition Reports
(CRs)
- 15-15896 15-18425 15-18787 15-21218 15-21254 15-23436 15-23900 15-24082 15-24195 15-24369 15-24953 15-24990 16-04859 16-04968 16-07321 16-09821 16-10241 16-10562 16-10566
Miscellaneous
- Title Revision/Date 1RE19 Refueling Outage ALARA Report June 1, 2016
- 2RE18 ALARA Update Report October 26, 2016
- STPNOC Daily Operational Focus Meeting Package October 24
- 28, 2016 STPNOC ALARA Strategic Planning Guide 2016
-2020 July 24, 2016
- Chapter 12, "Radiation Protection"
Procedures
- Number Title Revision 0PGP03-ZR-0050 Radiation Protection Program
- 0PGP03-ZR-0051 Radiological Access Controls/ Standards
- 0PGP03-ZR-0052 ALARA Program
- 0PRP07-ZR-0001 ALARA Engineering and Procedure Review
- 0PRP07-ZR-0004 Shielding
- 0PRP07-ZR-0010 Radiation Work Permits
/ Radiological Work ALARA Reviews 37 0PRP07-ZR-0023 Radiography Activities
- 0PRP08-ZR-0020 Installation and Operation of Underwater Filtration Equipment
- Radiation Work Permits Number Title Revision 2015-1-0176 1RE19 Radiation Protection Support (HRA)
- 2015-1-0238 1RE19 Retract/Re
-Insert Thimble Tubes Radiological Surveys Number Title Date 83857 S/G 1D Platform at Elev. +027' November 2, 2015
- 204 Solid Waste Process Aisle November 10, 2015
- 89337 Inside Secondary Shield Wall October 20, 2016
- 89424 Inside Secondary Shield Wall October 22, 2016
- Temporary Shielding Requests Number Title Date 2016-2-005 'A' 4" PZR Sprayline Vertical October 16, 2016
- 2016-2-009 Room 002 Rolling Shield October 12, 2016
- 2016-2-013 Room 307, Multiple RC Letdown Lines October 14, 2016
Section 2RS5: Radiation Monitoring Instrumentation
- Audits and Self-Assessments Number Title Date 14-02 Radiological Controls Quality Audit Report March 31, 2014
- 16-02 Radiological Controls Quality Audit Report April 13, 2016
- 23474 NUPIC Audit November 21, 2013
- MN-14-1-103131 QA Monitor Report:
- Radiological Instruments April 2, 2014
- MN-15-0-103859 QA Monitor Report:
- Radwaste & Radiological February 19, 2015
- MN-15-2-104056 QA Monitor Report:
- Radiological Instruments April 13, 2015
- First Quarter Sample Results March 2016
Condition Reports
(CRs)
- 16-15042 16-08717 16-08610 16-08096 16-08717 16-7276 16-7450 15-21708 15-15486
- Effluent Instrument Calibration Number Title Date
- RT-8010B Unit 2 Vent Wide Range Gas Monitor January 28, 2014
- RT-8010B Unit 2 Vent Wide Range Gas Monitor July 15, 2015
- RT-8038 Unit 1 Liquid Waste Processing Discharge Monitor May 16, 2016
- RT-8038 Unit 2 Liquid Waste Processing Discharge Monitor March 1, 2016
- RT-8038 Unit 1 Liquid Waste Processing Discharge Monitor November 5, 2014
- RT-8040 Unit-2 Component Cooling Water Radiation Transmitter November 9, 2016
- RT-8040 Unit-1 Component Cooling Water Radiation Transmitter June 15, 2016
- RT-8041 Unit-1 Turbine Generator Building Drain Monitor August 26, 2014
- RT-8041 Unit-1 Turbine Generator Building Drain Monitor October 10, 2013
Miscellaneous
- Title Date National Source Tracking Transaction Report January 27, 2009
- Post-Accident Monitor Calibration Number Title Date
- RT 8050 Unit 2 Reactor Containment Building High Range Monitor January 6, 2016
- RT 8050 Unit 1 Reactor Containment Building High Range Monitor January 21, 2016
- RT 8050 Unit 1 Reactor Containment Building High Range Monitor November 17, 2015
Procedures
- Number Title Revision 0PCP01-ZQ-0007 Quality Assurance for Radioanalysis Instrumentation
- 0PGP03-ZC-0001 Radiological Instrumentation Control Program
- 0PSP05-RA-8038 Liquid Waste Processing System No. 1 Monitor Calibration (RT
-8038) 15 0PSP05-RA-8010A MAB Unit Vent Wide Range Gas Monitor Calibration
- 0PSP05-RA-8010B MAB Unit Vent Wide Range Gas Monitor Calibration
- 0PSP05-WL-4078 Plant Liquid Waste Discharge Flow Calibration
- 0PSP05-RA-8050 RCB High Range Area Monitor Calibration
- 0PTP04-ZC-0036 Calibration of the Eberline AMS
-4 Air Monitoring System
Procedures
- Number Title Revision 0PTP04-ZC-0044 Calibration of Counting Instruments
- 0PTP04-ZC-0053 Calibration of Handheld Survey Meters/Ion Chambers
- 0PTP04-ZC-0054 Calibration of Area Monitors and Underwater Meters
- 0PTP04-ZC-0057 Maintenance Calibration of Eberline PCM
-1C Personnel Contamination Monitors
- 0PTP04-ZC-0058 Maintenance Calibration of Eberline PM
- 0PTP04-ZC-0062 Maintenance Calibration of SAM Series Small Article Monitors 1 0PTP04-ZC-0064 Calibration of Canberra Argos
-5AB Whole Body Monitor
- 0PTP04-ZC-0065 Calibration of Canberra GEM
-5 Gamma Exit Monitor
- 0PRP10-ZL-0015 RL Preparation of Radioactive Standard Solutions and Calibration Sources
- 0PRP03-ZR-0004 Inventory and Leak Testing of Radioactive Sources
- 0PSP03-ZQ-0028 Operator Logs
- 2 0PGP03-ZV-0005 Equipment Important to Emergency Response
- PMI-IC-RA-8040 Component Cooling Water System Monitor
- PMI-IC-RA-8039 Failed Fuel Liquid Monitor Radiation Protection Instrument Calibrations Number Title Date 1306-145 Canberra Argos 5AB Whole Body Monitor December 2, 2013
- 1306-146 Canberra GEM
-5 Gamma Exit Monitor July 15, 2016
- 97-015 Eberline RO
-20 Ion Chamber January 5, 2016
- 97-021 Eberline RO
-20 Ion Chamber January 5, 2016
- 31-018 Ludlum 3 Survey Meter April 18, 2016
- 17-015 Ludlum 1000 Decade Scaler March 16, 2016
- SAM12128 Thermo Electronic Corporation Small Article Monitor February 25, 2016
- S5E5196 Tennelec Alpha
-Beta Proportional Counter Calibrations November 11, 2016
- S5E16546 Tennelec Alpha
-Beta Proportional Counter Calibrations October 31, 2016
Section 2RS6: Radioactive Gaseous and Liquid Effluent Treatment
- Audits and Self
-Assessments Number Title Date 14-02 STPNOC Radiological Controls Quality Audit Report March 31, 2014
- MN-15-0-104304 Quality Monitoring Report May 6, 2015
- 14-47 STPNOC Assessment Report of Chemistry Effluent Report July 13, 2015
- 16-02 STPNOC Radiological Controls Quality Audit Report April 13, 2016
- MN-16-0-105225 Quality Monitoring Report May 4, 2016
Condition Reports
(CRs)
- 14-04529 14-17935 14-22739 15-02576 15-05805 15-05991 15-07953 15-11681 15-13698 15-14826 15-14827 15-16645 15-19120 15-22392 16-04256 16-05312 16-10431
- Gaseous and Liquid Release Permits Number Title Date 438 Unit 2 - Unit Vent and RCB (Gaseous)
- June 1, 2014
- 469 Unit 1 - Unit Vent and RCB (Gaseous)
- September 1, 2015
- 2175 Unit 1 - Waste Monitor Tank 1E (Liquid)
- February 16, 2014
- 287 Unit 2 - Waste Monitor Tank 2F (Liquid) January 2, 2015
- 289 Unit 2 - Waste Monitor Tank 2D (Liquid)
- January 8, 2015
- 2497 Unit 1 - Waste Monitor Tank 1F (Liquid)
- December 29, 2015
Miscellaneous
- Number Title Revision/Date 2014 Radioactive Effluent Release Report April 2015
- 2015 Radioactive Effluent Release Report April 2016
- 2014 Annual Radiological Environmental Operating Report April 2015
- 2015 Annual Radiological Environmental Operating Report April 2016
- STP 2nd Quarter 2016 System Health Report June 30, 2016
Miscellaneous
- Number Title Revision/Date
- 10
- CFR 50.75(g) Entries
- CAP Query Report November 9, 2016
Procedures
- Number Title Revision 0PCP07-ZS-0010 Waste Monitor Tank Sampling
- 0PCP07-ZS-0016 Continuous Atmospheric Monitors
- 0PCP09-ZO-0002 Liquid Scintillation Counting System
- Analysis, Operation and Calibration
- 0PCP09-ZR-0016 Off-Normal and Abnormal Radiological Effluent Monitoring
- 0PGP03-ZO-0053 Radiological Groundwater Protection Program
- 0PGP03-ZX-0007 Preparation of the Radioactive Effluent Release Report
- 0POP02-WG-0001 Gaseous Waste Processing System Operations
- 0POP02-WL-0100 Liquid Waste Release
- 0PRP10-ZL-0030 Interlaboratory Radioassay Measurement Assurance Program 3 0PSP07-VE-0002 Gaseous Effluent Particulate and Iodine Sampling and Analysis 17 0PSP07-WL-LDP1 Liquid Effluent Permit
- 0PSP07-WL-LDP2 Liquid Effluent Permit with RT
-8038 Inoperable
- 0PSP07-ZR-0004 Total Dose
- 0PSP11-ZH-0008 CRE and FHB HVAC In
-Place HEPA Filter Leak Test 20 0PSP11-ZH-0009 EAB and FHB HVAC In
-Place Adsorber Leak Test
Section 2RS8: Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation
- Audits and Self
-Assessments Number Title Revision/Date
- 16-002 Radiological Controls Quality Audit Report April 13, 2016
- 14-002 Radiological Controls Quality Audit Report March 31, 2014
- 14-072 Quality Department Audit Report, Low Level Radioactive Waste Disposal May 20, 2014
- 215 NUPIC Joint Audit of WMG Inc., Peekskill, NY
- March 18, 2016
- Audits and Self
-Assessments Number Title Revision/Date
- 23931 NUPIC Joint Audit of Energy Solutions, Columbia, SC
- 00, 01, 02
- 14-02 Radiological Controls Quality Audit Report March 31, 2014
Condition Reports
(CRs)
- 14-03474 14-24763 15-11263 15-21774 16-06459
Miscellaneous
- Number Title Date 2014 Annual Radioactive Effluent Release Report April 29, 2015
- 2015 Annual Radioactive Effluent Release Report April 12, 2016
Procedures
- Number Title Revision 0PGP03-ZA-0090 Work Process Program
- 0PGP03-ZA-0115 Hazardous Material Transportation Incident Response
- 0PGP03-ZO-0017 Radioactive Waste Process Control Program
- 0PGP03-ZR-0053 Radioactive Material Control Program
- 0POP02-WS-0002 High Integrity Container (HIC) Dewatering for Shipment and Burial
- 0POP02-WS-0003 Waste Transfer to the Portable Solidification System
- OPRP03-ZR-0001 Determination of Radioactive Material Curie Content, Reportability, DOT Sub
-Type, and Waste Classification
- OPRP03-ZR-0002 Radioactive Waste Shipments
- OPRP03-ZR-0004 Inventory and Leak Testing of Radioactive Sources
- OPRP03-ZR-0009 10
- CFR 61 Sampling and Analysis Program
- OPRP03-ZR-0010 Sorting and Processing of Radioactive Material
- OPRP03-ZR-0011 Shipment of Radioactive Material
- OPRP03-ZR-0012 Processing, Tracking, and Loading of Spent Radioactive Filters 08 OPRP03-ZR-0013 Receipt of Radioactive Material
- OPRP03-ZR-0014 On-Site Staging Facilities Operations
Procedures
- Number Title Revision OPRP03-ZR-0016 Receipt Inspection of Polyethylene Reusable Waste Containers
- OPRP04-ZR-0010 Radiological Monitoring for New Fuel
- OPRP04-ZR-0015 Radiological Posting and Warning Devices
- OPRP07-ZR-0013 Filter Replacement (Filters Stored in Room 218
-J) 07 OPRP07-ZR-0014 Filter Replacement (Alternate Storage Locations)
- OPRP07-ZR-0025 Preparation and Shipment of High Integrity Containers and Polyethylene Reusable Waste Containers
- OPRP11-ZR-0003 Radioactive Material Transportation Accidents
- SEG-0001 System Engineering Administrative Guideline
- WCG-0001 Work Screening and Processing
- WGC-0002 Work Management Scheduling Radioactive Material Shipments Number Title Date
- STP-0-16-038 N-16 Detector / MGP Instruments; Smyrna, GA
- October 18, 2016
- STP-1-16-007 Cask Resin / WCS; Andrews
, Texas February 17,
- 2016
- STP-1-16-022 Cask Resin / WCS; Andrews
, Texas June 8, 2016
- STP-2-16-014 Cask Class B Resin / WCS; Andrews
, Texas April 27,
- 2016
- STP-2-16-015 Cask Class B Resin / WCS; Andrews
, Texas May 4, 2016
- STP-2-16-051 40' Overpack / UniTech, Oak Ridge, Tennessee October 26,2016
- Section 4OA1
- Performance Indicator Verification
Miscellaneous
- Title Revision/Date Mitigating System Performance Index [MSPI] Bases Document
- MSPI Data Report (Raw Data) April 2015
- September 2016
- September 2016
- MSPI Derivation Report URI and UAI for Unit 1 & 2 Residual Heat Removal System September 2016
Procedures
- Number Title Revision 0PGP05-ZV-0013 Performance Indicator Tracking Guide
- SEG-0007 Mitigating System Performance Indicator Collection, Processing and Maintenance of Data Section 4OA2
- Problem Identification and Resolution
Condition Reports
(CRs)
- 11-23150 12-28460 12-30720 13-0102 15-25420 14-5140 14-17941 14-19256A 14-19590 14-19972 16-2648 16-11751 16-12538 16-13975 16-3503 16-10169 16-11357 16-10971 16-14557
Miscellaneous
- Number Title Revision/Date STI 34246503
- South Texas Project Unit 1:
- Issuance of Amendment
- RE:
- Revision to Technical Specifications for One Operating Cycle Operation with 56 Control Rods (Emergency Circumstances)
- December 11, 2015
- Integrity Check Training Presentation
- NTD521 Systems Cyber Security Training Presentation
- STI:
- 34048616 STP Cyber Security Plan For Units 1 & 2
- STP Cyber Security Network Overview
- NA
- Updated Critical Digital Asset Listing Spreadsheet Cyber Security Program Changes
- NA
Procedures
- Number Title Revision
- WCG-0008 Preventing Recurring Equipment Problems (PREP)
- 0PSP10-DM-0003 Automatic Multiple Rod Drop Measurement
- 0PMP06-ZS-0002 Portable Device Management
- 0PGP03-ZS-0012 Cyber Security Program
Procedures
- Number Title Revision 0PGP03-ZS-0013 Cyber Security Assessment of Digital Assets
(Partial Review) 14 0PGP03-ZS-0017 Control of Portable Devices for Cyber Security
- 0PGP03-ZS-0023 Cyber Security Assessment Team (CSAT)
- CS-007 Cyber Security System and Information Integrity
- STP-0721 Cyber Security Program
- 0PGP03-ZO-ECO1A Equipment Clearance Order Instructions
- 0PGP03-ZO-ECO1 Equipment Clearance Order Program
- PAPERWORK
- REDUCTION
- ACT STATEMENT
- This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
- Existing information collection requirements were approved by the Office of Management and Budget, control number 3150
- 0011. Information Request September 8,
- 2016 Notification of Inspection and Request for Information South Texas Project, Unit 2
- On October 11, 2016, reactor inspectors from the Nuclear Regulatory Commission's (NRC) Region IV office will perform the baseline in-service inspection at South Texas Project, Unit 2, using NRC Inspection
Procedure
- 71111.08, "Inservice Inspection Activities." Experience has shown that this inspection is a resource intensive inspection both for the NRC inspectors and your staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection.
- These documents have been divided into two groups. The first group
(Section A of the enclosure)
identified information to be provided prior to the inspection to ensure that the inspectors are adequately prepared.
- The second group (Section B of the enclosure) identifies the information the inspectors will need upon arrival at the site.
- It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
- We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Wendy Brost of your licensing organization.
- The tentative inspection schedule is as follows: Preparation week: October 3, 2016
- Onsite weeks: October 11
, 2016 - October 21,
- 2016 Our inspection dates are subject to change based on your updated schedule of outage activities.
- If there have any questions about this inspection or the material requested, please contact the lead inspector, Ray Azua at 817-200-1445, or Ray.Azua@nrc.gov.
- A. Information Requested for the In-Office Preparation Week
- The following information should be sent to the Region IV office in hard copy or electronic format (ims.certrec.com preferred), in care of Ray Azua, by September
- 26, 2016, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The inspector will select specific items from the information requested below and then request from your staff additional documents needed during the onsite inspection week (Section B of this enclosure).
- We ask that the specific items selected from the lists be available and ready for review on the first day of inspection.
- Please provide requested documentation electronically if possible.
- If requested documents are large and only hard copy formats are available, please inform the inspector(s), and provide subject documentation during the first day of the onsite inspection
.
- If you have any questions regarding this information request, please call the inspector as soon as possible.
- A.1 ISI/Welding Programs and Schedule Information
a) A detailed schedule (including preliminary dates) of: i. Nondestructive examinations planned for ASME Code Class Components including containment, performed as part of your ASME Section XI, risk informed (if applicable), and augmented in-service inspection programs during the upcoming outage. ii. Reactor pressure vessel head examinations required by 10CFR50.55a(g)(6)(ii)(D)
and Code Case N-729-1. iii. Examinations planned for Alloy 82/182/600
components that are not included in the Section XI scope (if applicable).
iv. Examinations planned as part of your boric acid corrosion control program (mode 3 walk downs, bolted connection walk downs, etc.). v. Welding activities that are scheduled to be completed during the upcoming outage (ASME Class 1, 2, or 3 structures, systems, or components).
- Include the weld identification number, description of weld, category, class, type of exam and procedure number, and date of examination.
b) A copy of ASME Section XI, Code Relief Requests and associated
- NRC safety evaluations applicable to the examinations identified above. i. A list of ASME Code Cases currently being used to include the system and/or component the Code Case is being applied to. c) A list of nondestructive examination reports which have identified relevant indications on any ASME Code Class components since the beginning of the last refueling outage. d) A list including
a brief of repair/replacement activities of any ASME Code Class components since the beginning of the last outage and/or planned this refueling outage. e) If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined and the extent of the planned examination.
- Please also provide reference numbers for applicable procedures that will be used to conduct these examinations.
f) Copy of any 10 CFR Part 21 reports applicable to structures, systems, or components within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage. g) A list of any temporary non-code repairs in service (e.g., pinhole leaks). h) Please provide copies of the most recent self-assessments for the inservice
inspection, welding, and Alloy 600 programs.
i) Copies of the following procedures:
a. All NDE procedures required to be followed for the examinations scheduled
b. The site general welding procedure
c. The site inservice inspection program procedure
- A.2 Reactor Pressure Vessel Head (If Applicable)
a) Provide a detailed scope of the planned bare metal visual examinations
(e.g., volume coverage, limitations, etc.) of the vessel upper head penetrations and/or any nonvisual nondestructive examination of the reactor vessel head including the examination procedures to be used. i. Provide the records recording the extent of inspection for each penetration nozzle including documents which resolved interference or masking issues that confirm that the extent of examination meets 10 CFR 50.55a(g)(6)(ii)(D).
ii. Provide records that demonstrate that a volumetric or surface leakage path examination assessment was performed.
b) Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1 that establish the volumetric and visual inspection frequency for the reactor vessel head and J-groove welds.
- A.3 Boric Acid Corrosion Control Program a) Copy of the procedures that govern the scope, equipment and implementation of the inspections required to identify boric acid leakage and the procedures for boric acid leakage/corrosion evaluation.
b) Please provide a list of leaks (including code class of the components) that have been identified since the last refueling outage and associated corrective action documentation.
- If during the last cycle, the unit was shut down, please provide documentation of containment walk down inspections performed as part of the boric acid corrosion control program.
- A.4 Steam Generator Tube Inspections (If Applicable)
a) A detailed schedule of: i. Steam generator tube inspection, data analyses, and repair activities for the upcoming outage (if occurring).
ii. Steam generator secondary side inspection activities for the upcoming outage (if occurring).
b) Copy of SG history documentation given to vendors performing eddy current (ET)
testing of the SGs during the upcoming outage.
c) Copy of procedure containing screening criteria used for selecting tubes for in-situ pressure testing and the procedure to be used for in-situ pressure testing. d) Copy of previous outage SG tube operational assessment completed following
- Also include a copy of the following documents as they become available:
i.
- Degradation assessment ii. Condition monitoring assessment
e) Copy of the document defining the planned SG ET scope (e.g., 100 percent of unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion transition regions with rotating probe) and identify the scope expansion criteria, which will be applied.
- Also identify and describe any deviations in this scope or expansion criteria from the EPRI Guidelines.
f) Copy of the document describing the ET acquisition equipment to be applied including
- ET probe types.
- Also identify the extent of planned tube examination coverage with each probe type (e.g. rotating probe -0.080 inches, 0.115 inches pancake coils and mid-range +point coil applied at the top-of-tube-sheet plus 3 inches to minus 12 inches). g) Identify and quantify any SG tube leakage experienced during the previous operating cycle.
- Also provide documentation identifying which SG was leaking and corrective actions completed and planned for this condition.
h) Copy of steam generator eddy current data analyst guidelines and site validated eddy current technique specification sheets.
- Additionally, please provide a copy of EPRI Appendix H, "Examination Technique Specification Sheets," qualification records. i) Provide past history of the condition and issues pertaining to the secondary side of the steam generators
(including items such as loose parts, fouling, top of tube sheet condition, crud removal amounts, etc.). j) Indicate where the primary, secondary, and resolution analyses are scheduled to take place. A.5 Additional Information Related to all Inservice Inspection Activities
a) A list with a brief description of inservice inspection, boric acid corrosion control program, and steam generator tube inspection related issues (e.g., condition reports) entered into your corrective action program since the beginning of the last refueling outage.
- For example, a list based upon data base searches using key words related to piping or steam generator tube degradation such as: inservice inspection,
- ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping/steam generator tube examinations.
b) Provide training (e.g. Scaffolding, Fall Protection, FME, Confined Space) if they are required for the activities described in A.1 through A.4. c) Please provide names and phone numbers for the following program leads:
- Inservice inspection
(examination, planning)
- Containment exams Reactor pressure vessel head exams
- Snubbers and supports Repair and replacement program Licensing Site welding engineer Boric acid corrosion control program Steam generator inspection activities
(site lead and vendor contact)
- B. Informatio
n to be Provided Onsite to the Inspector(s)
at the Entrance Meeting (September
- 26, 2016)
- B.1 Inservice Inspection
/ Welding Programs and Schedule Information
a) Updated schedules for inservice inspection/nondestructive examination activities, including steam generator tube inspections, planned welding activities, and schedule showing contingency repair plans, if available.
b) For ASME Code Class welds selected by the inspector from the lists provided from section A of this enclosure, please provide copies of the following documentation for each subject weld: i. Weld data sheet (traveler).
ii. Weld configuration and system location.
iii. Applicable Code Edition and Addenda for weldment.
iv. Applicable Code Edition and Addenda for welding procedures.
v. Applicable welding procedures used to fabricate the welds. vi. Copies of procedure qualification records (PQRs) supporting the weld procedures from B.1.b.v. vii. Copies of welder's performance qualification records (WPQ). viii. Copies of the nonconformance reports for the selected welds (If applicable).
ix. Radiographs of the selected welds and access to equipment to allow viewing radiographs
(if radiographic testing was performed).
x. Copies of the preservice examination records for the selected welds. xi. Readily accessible copies of nondestructive examination personnel
qualifications records for reviewing.
c) For the inservice inspection related corrective action issues selected by the inspectors from section A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d) For the nondestructive examination reports with relevant conditions on ASME Code Class components selected by the inspectors from Section A above, provide a copy of the examination records, examiner qualification records, and associated corrective action documents.
e) A copy of (or ready access to) most current revision of the inservice inspection program manual and plan for the current interval.
f) For the nondestructive examinations selected by the inspectors from section A of this enclosure, provide a copy of the nondestructive examination procedures used to perform the examinations
(including calibration and flaw characterization/sizing procedures).
- For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, provide documentation supporting the procedure qualification
(e.g. the EPRI performance demonstration qualification summary sheets).
- Also, include qualification documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and nondestructive examination personnel qualification records. B.2 Reactor Pressure Vessel Head (RPVH) a) Provide drawings showing the following
(if performing any RPVH inspection activities):
i. RPVH and control rod drive mechanism nozzle configurations.
ii. RPVH insulation configuration.
- Note: The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.
b) Copy of the documents which demonstrate that the procedures to be used for volumetric examination of the reactor vessel head penetration
- J-groove welds were qualified by a blind demonstration test in accordance with 10 CFR 50.55a(g)(6)(ii)(D).
c) Copy of volumetric, surface and visual examination records for the prior inspection of the reactor vessel head and head penetration
- J-groove welds.
- B.3 Boric Acid Corrosion Control Program a) Please provide boric acid walk down inspection results, an updated list of boric acid leaks identified so far this outage, associated corrective action documentation, and overall status of planned boric acid inspections.
b) Please provide any engineering evaluations completed for boric acid leaks identified since the end of the last refueling outage.
- Please include a status of corrective actions to repair and/or clean these boric acid leaks.
- Please identify specifically which known leaks, if any, have remained in service or will remain in service as active leaks.
- B.4 Steam Generator Tube Inspections
a) Copies of the Examination Technique Specification Sheets and associated justification for any revisions.
b) Please provide a copy of the eddy current testing procedures used to perform the steam generator tube inspections
(specifically calibration and flaw characterization/sizing procedures, etc.).
c) Copy of the guidance to be followed if a loose part or foreign material is identified in the steam generators.
d) Identify the types of SG tube repair processes which will be implemented for defective
- SG tubes (including any NRC reviews/evaluations/approvals of this repair process).
e) Copy of documents describing actions to be taken if a new SG tube degradation mechanism is identified.
f) Provide procedures with guidance/instructions for identifying
(e.g. physically locating the tubes that require plugging) and plugging SG tubes. g) List of corrective action documents generated by the vendor and/or site with respect to steam generator inspection activities.
- B.5 Codes and Standards
a) Ready access to (i.e., copies provided to the inspector(s)
for use during the inspection at the onsite inspection location, or room number and location where available):
i. Applicable Editions of the ASME Code (Sections
- V, IX, and XI) for the inservice inspection program and the repair/replacement program. ii. EPRI and industry standards referenced in the procedures used to perform the steam generator tube eddy current examination.
b) Copy of the performance demonstration initiative
(PDI) generic procedures with the latest applicable revisions that support site qualified ultrasonic examinations of piping welds and components
(e.g.,
- PDI-UT-1,
- PDI-UT-2,
- PDI-UT-3,
- PDI-UT-10, etc.).
c) EPRI and industry standard references in the site procedures used to perform the SG tube eddy current examination, which includes EPRI documents: TR
-107621-R1, "Steam Generator Integrity Assessment Guidelines,"
- TR-107620-R1, "Steam Generator In
-Situ Pressure Test Guidelines," Steam Generator Management Program: Steam Generator Integrity Assessment Guidelines, Part 10, and
- 1003138, "Pressurized Water Reactor Steam Generator Examination Guidelines." Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975.
- The following items are requested for the Occupational Radiation Safety Inspection at South Texas Project Electric Generating Station October 24
- 28, 2016 Integrated Report 2016004
- Inspection areas are listed in the attachments below.
- Please provide the requested information on or before October 7, 2016.
- Please submit this information using the same lettering system as below.
- For example, all contacts and phone numbers for Inspection Procedure 71124.0
should be in a file/folder titled
"1- A," applicable organization charts in file/folder "
- 1- B," etc.
- If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at least 30 days later than t he on-site inspection dates, so the inspectors will have access to the information while writing the report.
- In addition to the corrective action document lists provided for each inspection procedure listed below, please provide updated lists of corrective action documents at the entrance meeting.
- The dates for these lists should range from the end dates of the original lists to the day of the entrance meeting.
- If more than one inspection procedure is to be conducted and the information requests appear to be redundant, there is no need to provide duplicate copies.
- Enter a note explaining in which file the information can be found.
- If you have any questions or comments, please contact the lead inspector, Louis Carson at (817) 200
-1221 or louis.carson@nrc.gov.
- Or, you may reach out to Natasha Greene at (817) 200-1154 or natasha.greene@nrc.gov
.
- PAPERWORK REDUCTION ACT STATEMENT
- This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
- Existing information collection requirements were approved by the Office of Management and Budget, control number 3150
-0011.
- 1. Radiological Hazard Assessment and Exposure Controls (71124.01) and Performance Indicator Verification (71151) Date of Last Inspection:
- April 13, 2015
- A. List of contacts and telephone numbers for the Radiation Protection Organization Staff and Technicians
- B. Applicable organization charts
- C. Audits, self
-assessments, and LERs written since date of last inspection
, related to this inspection area
- D. Procedure indexes for the radiation protection procedures
- E. Please provide specific procedures related to the following areas noted below
.
- Additional Specific Procedures may be requested by number after the inspector reviews the procedure indexes.
- 1. Radiation Protection Program Description
- 2. Radiation Protection Conduct of Operations
- 3. Personnel Dosimetry Program
- 4. Posting of Radiological Areas
- 5. High Radiation Area Controls
- 6. RCA Access Controls and Radworker Instructions
- 7. Conduct of Radiological Surveys
- 8. Radioactive Source Inventory and Control
- 9. Declared Pregnant Worker Program
- F. List of corrective action documents/condition reports
(including corporate and subtiered systems) since date of last inspection
a. Initiated by the radiation protection organization
b. Assigned to the radiation protection organization
- NOTE: The lists should indicate the significance level of each issue and the search criteria used.
- Please provide in document formats which are "searchable" so that the inspector can perform word searches.
- If not covered above, a summary of corrective action documents since date of last inspection involving unmonitored releases, unplanned releases, or releases in which any dose limit or administrative dose limit was exceeded (for Public Radiation Safety Performance Indicator verification in accordance with IP 71151)
- G. List of radiologically significant work activities scheduled to be conducted during the inspection period (If the inspection is scheduled during an outage, please also include a list of work activities greater than 1 rem, scheduled during the outage with the dose estimate for the work activity.)
- H. List of active radiation work permits
- I. Radioactive source inventory list
a.
- All radioactive sources that are required to be leak tested
b.
- All radioactive sources that meet the 10 CFR Part 20, Appendix E, Category 2 and above threshold.
- Please indicate the radioisotope, initial and current activity (w/assay date), and storage location for each applicable source.
- J.
- The last two leak test results for the radioactive sources inventoried and required to be leak tested.
- If applicable, specifically provide a list of all radioactive source(s) that have failed its leak test within the last two years
- K. A current listing of any non
-fuel items stored within your pools, and if available, their appropriate dose rates (Contact / @ 30cm)
- L. Computer printout of radiological controlled area entries greater than 100 millirems since the previous inspection to the current inspection entrance date.
- The printout should include the date of entry, some form of worker identification, the radiation work permit used by the worker, dose accrued by the worker, and the electronic dosimeter dose alarm setpoint used during the entry (for Occupational Radiation Safety Performance Indicator verification in accordance with IP 71151)
.
- Date of Last Inspection:
- June 27, 2015
- A. List of contacts and telephone numbers for ALARA program personnel
- B. Applicable organization charts
- C. Copies of audits, self
-assessments, and LERs, written since date of last inspection, focusing on ALARA
- D. Procedure index for ALARA Program
- E. Please provide specific procedures related to the following areas noted below
.
- Additional specific procedures may be requested by number after the inspector reviews the procedure indexes.
- 1. ALARA Program
- 2. ALARA Committee
- 3. Radiation Work Permit Preparation
- F. A summary list of corrective action documents (including corporate and subtiered systems) written since date of last inspection
, related to the ALARA program.
- In addition to ALARA, the summary should also address Radiation Work Permit violations, Electronic Dosimeter Alarms, and RWP Dose Estimates
- NOTE: The lists should indicate the significance level of each issue and the search criteria used.
- Please provide in document formats which are "searchable" so that the inspector can perform word searches.
- G.
- List of work activities greater than 1 rem, since date of last inspection Include original dose estimate and actual dose.
- H. Site dose totals and 3
-year rolling averages for the past 3 years (based on dose of record) I. Outline of source term reduction strategy
- J. If available, provide
a copy of the ALARA outage report for the most recently completed outages for each unit
- K. Please provide your most recent Annual ALARA Report.
- The following items are requested for the Public Radiation Safety Inspection at South Texas Project November 28
- December 2, 2016 Integrated Report 2016004
- Inspection areas are listed in the attachments below.
- Please provide the requested information on or before November 14, 2016.
- Please submit this information using the same lettering system as below.
- For example, all contacts and phone numbers for Inspection Procedure 71124.0
should be in a file/folder titled
"1- A," applicable organization charts in file/folder "
- 1- B," etc.
- If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at least 30 days later than the on
-site inspection dates, so the inspectors will have access to the information while writing the report.
- In addition to the corrective action document lists provided for each inspection procedure listed below, please provide updated lists of corrective action documents at the entrance meeting.
- The dates for these lists should range from the end dates of the original lists to the day of the entrance meeting.
- If more than one inspection procedure is to be conducted and the information requests appear to be redundant, there is no need to provide duplicate copies.
- Enter a note explaining in which file the information can be found.
- If you have any questions or comments, please contact Louis Carson at (817) 817-200-1221 or Louis.Carson@nrc.gov.
- PAPERWORK REDUCTION ACT STATEMENT
- This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
- Existing information collection requirements were approved by the Office of Management and Budget, control number 3150
-0011.
- 5. Radiation Monitoring Instrumentation (71124.05)
- Date of Last Inspection:
- February 7, 2014
- A. List of contacts and telephone numbers for the following areas:
- 1. Effluent monitor calibration
- 2. Radiation protection instrument calibration
- 3. Installed instrument calibrations
- 4. Count room and laboratory instrument calibrations
- B. Applicable organization charts
- C. Copies of audits, self
-assessments, vendor or NUPIC audits for contractor support and LERs, written since date of last inspection
, related to:
- 1. Area radiation monitors, continuous air monitors, criticality monitors, portable survey instruments, electronic dosimeters, teledosimetry, personnel contamination monitors, or whole body counters
- 2. Installed radiation monitors
- D. Procedure index for:
- 1. Calibration, use, and operation of continuous air monitors, criticality monitors, portable survey instruments, temporary area radiation monitors, electronic dosimeters, teledosimetry, personnel contamination monitors, and whole body counters.
- 2. Calibration of installed radiation monitors
- E. Please provide specific procedures related to the following areas noted below
.
- Additional specific procedures will be requested by number after the inspector reviews the procedure indexes.
- 1. Calibration of portable radiation detection instruments (for portable ion chambers)
- 2. Whole body counter calibration
- 3. Laboratory instrumentation quality control
- F. A summary list of corrective action documents (including corporate and sub
-tiered systems) written since date of last inspection, related to the following programs:
- 1. Area radiation monitors, continuous air monitors, criticality monitors, portable survey instruments, electronic dosimeters, teledosimetry, personnel contamination monitors, whole body counters
- 2. Installed radiation monitors
- 3. Effluent radiation monitors
- 4. Count room radiation instruments
- NOTE: The lists should indicate the significance level of each issue and the search criteria used.
- Please provide in document formats which are "searchable" so that the inspector can perform word searches.
- G. Offsite dose calculation manual, technical requirements manual, or licensee
-controlled specifications which lists the effluent monitors and calibration requirements.
- H. Current calibration data for the whole body counter
s.
- I. Primary to secondary source calibration correlation for effluent monitors.
- J. A list of the point of discharge effluent monitors with the two most recent calibration dates and the work order numbers associated with the calibrations.
- K. Radiation Monitoring System health report for the previous 12 months
- 6. Radioactive Gaseous and Liquid Effluent Treatment (71124.06)
- Date of Last Inspection:
- February 7, 2014
- A. List of contacts and telephone numbers for the following areas:
- 1. Radiological effluent control
- 2. Engineered safety feature air cleaning systems
- B. Applicable organization charts
- C. Audits, self
-assessments, vendor or NUPIC audits of contractor support, and LERs written since date of last inspection, related to:
- 1.
- Radioactive effluents
- 2.
- Engineered safety feature air cleaning systems
- D. Procedure indexes for the following areas
- 1.
- Radioactive effluents
- 2.
- Engineered safety feature air cleaning systems
- E. Please provide specific procedures related to the following areas noted below
.
- Additional specific procedures will be requested by number after the inspector reviews the procedure indexes.
- 1. Sampling of radioactive effluents
- 2. Sample analysis
- 3. Generating radioactive effluent release permits
- 4. Laboratory instrumentation quality control
- 5. In-place testing of HEPA filters and charcoal adsorbers
- 6. New or applicable procedures for effluent programs (e.g., including ground water monitoring programs)
- F. List of corrective action documents (including corporate and sub
-tiered systems) written since date of last inspection, associated with:
- 1.
- Radioactive effluents
- 2.
- Effluent radiation monitors
- 3.
- Engineered safety feature air cleaning systems
- NOTE: The lists should indicate the significance level of each issue and the search criteria used.
- Please provide in document formats which are "searchable" so that the inspector can perform word searches.
- G. 2014 and 2015 Annual Radioactive Effluent Release Report or the two most recent reports. H. Current copy of the Offsite Dose Calculation Manual
- I. Copy of the 2014 and 2015
inter-laboratory comparison results for laboratory quality control performance of effluent sample analysis or the two most recent results.
- J. Effluent sampling schedule for the week of the inspection
- K. New entries into 10
- CFR 50.75(g) files since date of last inspection
- L. Operations department
(or other responsible dept.) log records for effluent monitors removed from service or out of service
- M. Listing or log of liquid and gaseous release permits since date of last inspection
- N. A list of the technical specification
-required air cleaning systems with the two most recent surveillance test dates of in
-place filter testing (of HEPA filters and charcoal adsorbers) and laboratory testing (of charcoal efficiency) and the work order numbers associated with the surveillances
- O. System health report for radiation monitoring instrumentation.
- Also, please provide a specific list of all effluent radiation monitors that were considered inoperable for 7 days or more since November 2011.
- If applicable, please provide the relative Special Report and condition report(s).
- P. A list of all radiation monitors that are considered §
- 50.65/Maintenance Rule equipment.
- Q. A list of all significant changes made to the gaseous and liquid effluent process monitoring system since the last inspection.
- If applicable, please provide the corresponding UFSAR section in which this change was documented.
- R.
- A list of any occurrences in which a non
-radioactive system was contaminated by a radioactive system.
- Please include any relative condition report(s).
- 7. Radiological Environmental Monitoring Program (71124.07)
- Date of Last Inspection:
- February 7, 2014
- A. List of contacts and telephone numbers for the following areas:
- 1. Radiological environmental monitoring
- 2. Meteorological monitoring
- B. Applicable organization charts
- C. Audits, self
-assessments, vendor or NUPIC audits of contractor support, and LERs written since date of last inspection, related to:
- 1. Radiological environmental monitoring program (including contractor environmental laboratory audits, if used to perform environmental program functions)
- 2. Environmental TLD processing facility
- 3. Meteorological monitoring program
- D. Procedure index for the following areas:
- 1. Radiological environmental monitoring program
- 2. Meteorological monitoring program
- E. Please provide specific procedures related to the following areas noted below
.
- Additional specific procedures will be requested by number after the inspector reviews the procedure indexes.
- 1. Environmental program description
- 2. Sampling, collection and preparation of environmental samples 3. Sample analysis (if applicable)
- 4. Laboratory instrumentation quality control
- 5. Procedures associated with the Offsite Dose Calculation Manual
- 6. Appropriate QA audit and program procedures, and/or sections of the station's QA manual (which pertain to the REMP) F. A summary list of corrective action documents (including corporate and sub
-tiered systems) written since date of last inspection, related to the following programs:
- 1. Radiological environmental monitoring
- 2. Meteorological monitoring
- NOTE:
- The lists should indicate the significance level of each issue and the search criteria used.
- Please provide in document formats which are "searchable" so that the inspector can perform word searches.
- G. Wind rose data and evaluations used for establishing environmental sampling locations
- H. Copies of the two most recent calibration packages for the meteorological tower instruments
- I. Copy of the 2014 and 2015
- Annual Radiological Environmental Operating Report and Land Use Census, and current revision of the Offsite Dose Calculation Manual, or the two most recent reports.
- J. Copy of the environmental laboratory's inter
-laboratory comparison program results for
- 2014 and 2015, or the two most recent results, if not included in the annual radiological environmental operating report
- K. Data from the environmental laboratory documenting the analytical detection sensitivities for the various environmental sample media
(i.e., air, water, soil, vegetation, and milk)
- L. Quality assurance audits (e.g.
, NUPIC) for contracted services
- M. Current NEI Groundwater Initiative Plan and status
- N.
- Technical requirements manual or licensee controlled specifications which lists the meteorological instruments calibration requirements
- O. A list of regulatory guides and/or NUREGs that you are currently committed to relative to the Radiological Environmental Monitoring Program.
- Please include the revision and/or date for the committed item and where this can be located in your current licensing basis/UFSAR.
- P. If applicable, per NEI 07
-07, provide any reports that document any spills/leaks to groundwater since the last inspection
- 8. Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage, and Transportation (71124.08)
- Date of Last Inspection:
- February 7, 2014
- A. List of contacts and telephone numbers for the following areas:
- 1. Solid Radioactive waste processing
- 2. Transportation of radioactive material/waste
- B. Applicable organization charts (and list of personnel involved in solid radwaste processing, transferring, and transportation of radioactive waste/materials)
- C. Copies of audits, department self
-assessments, and LERs written since date of last inspection related to:
- 1. Solid radioactive waste management
- 2. Radioactive material/waste transportation program
- D. Procedure index for the following areas:
- 1. Solid radioactive waste management
- 2. Radioactive material/waste transportation
- E. Please provide specific procedures related to the following areas noted below
.
- Additional Specific Procedures will be requested by number after the inspector reviews the procedure indexes.
- 2. Solid and liquid radioactive waste processing
- 3. Radioactive material/waste shipping
- 4. Methodology used for waste concentration averaging, if applicable
- 5. Waste stream sampling and analysis
- F. A summary list of corrective action documents (including corporate and sub
-tiered systems) written since date of last inspection related to:
- 1. Solid radioactive waste
- 2. Transportation of radioactive material/waste
- NOTE: The lists should indicate the significance level of each issue and the search criteria used.
- Please provide in document formats which are "searchable" so that the inspector can perform word searches.
- G. Copies of training lesson plans for 49
- CFR 172, Subpart H, for radwaste processing, packaging, and shipping.
- H. A summary of radioactive material and radioactive waste shipments made from date of last inspection to present
- I. Waste stream sample analyses results and resulting scaling factors for 2014 and 2015
, or the two most recent results.
- J. Waste classification reports if performed by vendors (such as for irradiated hardware)
- K. A listing of all on
-site radwaste storage facilities.
- Please include a summary or listing of the items stored in each facility, including the total amount of radioactivity and the highest general area dose rate.
- Although it is not necessary to compile the following information, the inspector will also review:
- L. Training, and qualifications records of personnel responsible for the conduct of radioactive waste processing, package preparation, and shipping