IR 05000498/2018004
| ML19032A079 | |
| Person / Time | |
|---|---|
| Site: | South Texas, 07201041  |
| Issue date: | 02/01/2019 |
| From: | Nick Taylor NRC/RGN-IV/DRP |
| To: | Gerry Powell South Texas |
| References | |
| IR 2018002, IR 2018004 | |
| Download: ML19032A079 (36) | |
Text
ary 1, 2019
SUBJECT:
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000498/2018004; 05000499/2018004, AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07201041/2018002
Dear Mr. Powell:
On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your South Texas Project Electric Generating Station, Units 1 and 2. On January 10, 2019, 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 findings or violations 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. 50-498; 50-499, and 07201041 License Nos. NPF-76 and NPF-80 Enclosure:
Inspection Report 05000498/2018004, 05000499/2018004 and 0720104/2018002 w/attachments:
1. Documents Reviewed 2. NRC Request for Information
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Numbers: 05000498, 05000499 and 07201041 License Numbers: NPF-76 and NPF-80 Report Numbers: 05000498/2018004; 05000499/2018004 and 07201041/2018002 Enterprise Identifier: I-2018-004-0004 and I-2018-002-0096 Licensee: STP Nuclear Operating Company Facility: South Texas Project Electric Generating Station, Units 1, 2, and ISFSI Location: Wadsworth, Texas Inspection Dates: October 1, 2018 to December 31, 2018 Inspectors: A. Sanchez, Senior Resident Inspector J. Choate, Resident Inspector R. Kopriva, Senior Reactor Inspector L. Brookhart, Senior ISFSI Inspection, FCDB E. Simpson, CHP, Health Physicist, FCDB O. Masnyk Bailey, Health Physicist, RI A. Bolger, Health Physicist, MLIB E. Love, Spent Fuel Transportation and Storage Inspector, DSFM J. Woodfield, Spent Fuel Transportation and Storage Inspector, DSFM N. Hernandez, Operations Engineer Approved By: Nicholas H. Taylor Chief, Project Branch B Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at South Texas Project, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC-identified and self-revealed findings, violations, and additional items are summarized in the table below.
Licensee-identified non-cited violations are documented in the Inspection Results at the end of this report.
List of Findings and Violations No findings or violations of more than minor significance were identified during the inspection.
PLANT STATUS
Unit 1 began the inspection period at 93 percent rated thermal power as part of coast down operations for refueling outage 1RE21, which began on October 5, 2018, and ended on November 11, 2018. The unit was returned to rated thermal power on November 14, 2018, and remained there for the rest of the inspection period.
Unit 2 operated at or near rated thermal power for the entire inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515 Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01Adverse Weather Protection External Flooding
The inspectors evaluated readiness to cope with external flooding on December 14, 2018.
71111.04Equipment Alignment Partial Walkdown
The inspectors evaluated system configuration during partial walkdown of the Unit 1, train B residual heat removal system during refueling outage on November 1, 2018.
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the Units 1 and 2 essential chilled water system on December 10, 2018.
71111.05AQFire Protection Annual/Quarterly Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit 1, containment building, Fire Area 63, Fire Zones 211 through 214, on October 9, 2018
- (2) Unit 1, train C safety related switchgear and battery rooms, Fire Area 4, Fire Zones 52 and 53, on October 16, 2018
- (3) Unit 2, train B emergency diesel generator room, Fire Area 37, Fire Zone 501, on November 1, 2018
- (4) Unit 2, train A, B, C, and D auxiliary feedwater pump rooms, Fire Areas 48 through 51, on December 26, 2018
71111.08Inservice Inspection Activities (Unit 1)
The inspectors evaluated nondestructive examination activities by observing the following activities:
- (1) Magnetic Particle Examinations a) Feedwater System: Pipe Lugs 18-FW-1032-AA2 / 1PL1-LPL8, Work Order 86000011, Work Authorization 526051, and Report MT-2018-116
- (2) Dye Penetrant Examinations a) Residual Heat Removal System: Welded Attachment RHAHRS-1A-SK Support Skirt, Work Order 86000011, and Report PT-2018-196 b) Chemical and Volume Control System: Seal Water Injection Filter 1B Outlet Valve, Weld HFW0120, Pipe-to-Valve CV-0250B, Work Order 96013951, Work Authorization 598944, and Report PT-2018-190
- (3) Ultrasonic Examinations a) Reactor Coolant System: Pipe-To-Elbow 4-RC-1422-BB1 Weld 4, Scanning Angle of 450, Work Order 86000011, and Report UT-2018-104 b) Reactor Coolant System: Pipe-To-Elbow 4-RC-1422-BB1 Weld 2, Scanning Angle of 450, Work Order 86000011, and Report UT-2018-102 c) Reactor Coolant System: Pipe-To-Elbow 4-RC-1422-BB1 Weld 3, Scanning Angle of 450, Work Order 86000011, and Report UT-2018-103 d) Reactor Coolant System: Pressurizer Surge Line Weld Overlay, Safe End-To-Bent Pipe (PRZ Surge Noz-N1) / Pressurizer Surge Nozzle-To-Safe End PRZ-1-N1-SE-WOL /1 - WOL (N1), Scanning Angle of 450, Work Order 86000011, and Report UT-2018-105 e) Reactor Coolant System: Pressurizer Surge Line, PRZ-1-Nl-IR/ Surge Nozzle Inner Radius, Work Order 86000011, and Report UT-2018-100 f) Replacement Steam Generator: Tube Plate to Lower Shell Barrel A / RSG-1A-T1, Work Order 86000011, and Report UT-2018-097
- (4) Visual Examinations a) Reactor Coolant System: Bottom Mounted Instrumentation Penetrations 1-58, Work Order 753, and Report VE-2018-008 b) Reactor Coolant System: Reactor Vessel Closure Head Bare Metal Visual Examination of Penetration Nozzles 1-9, 14-23, 25-27, 29-61, 66-68, 70, 72, 75-78 (including vent pipe and general head area), Work Order 753, and Report VE-2018-009 c) Containment: Snubber SI-1208-HL5005, Work Order 86000011, and Report VTC-2018-060 The inspectors evaluated welding activities by observing the following welding activity:
- (1) Gas Tungsten Arc Weld - Manual a) Chemical and Volume Control System: Seal Water Injection Filter 1B Outlet Valve Replacement CV-0250B, Pipe-to-Valve CV-0250B, Weld HFW0120, Work Order 96013951, and Work Authorization 598944 The inspectors evaluated the licensees boric acid control program performance.
The inspectors evaluated the results of the licensees bare metal visual inspection of the reactor vessel upper head penetrations. The inspectors reviewed whether the required inspection coverage was achieved and whether limitations were properly recorded. The inspectors also reviewed whether the personnel performing the inspection were certified examiners to their respective nondestructive examination method.
The steam generator tube inspections were not required to be performed in this outage.
The inspectors evaluated a sample of 26 condition reports associated with inservice inspection activities.
71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification
The inspectors observed and evaluated just-in-time training for Unit 1 shutdown and cool down activities on October 1-2, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated Unit 1 brief and operations during startup and heat up activities on November 6, 2018.
Operator Exams (1 sample)
The inspectors reviewed and evaluated requalification examination results on December 27, 2018.
71111.12Maintenance Effectiveness Routine Maintenance Effectiveness
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety-significant functions:
- (1) Units 1 and 2, residual heat removal systems on December 10, 2018
- (2) Unit 1, main steam generator power-operated relief valves due to functional failures on December 21, 2018
- (3) Units 1 and 2, electrical auxiliary building heating, ventilation, and air conditioning systems on December 21, 2018
Quality Control (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance issues:
- (1) Unit 1, train D steam generator power-operated relief valve cracked bonnet on October 23, 2018
71111.13Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit 1, elevated risk due to planned maintenance on train B 125 Vdc battery and inverter IV-1203, which required entry into the Configuration Risk Management Program on November 16, 2018
- (2) Unit 1, elevated risk due to emergent maintenance to tighten a reactor coolant system instrument tube fitting on the loop A flow transmitter (FT-0419) on November 17, 2018
- (3) Unit 1, elevated risk due to planned maintenance on train A 125 Vdc battery and inverter IV-1201 which required entry into the Configuration Risk Management Program on November 30, 2018
71111.15Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Unit 1, containment equipment hatch closure within required time limit on November 15, 2018
- (2) Unit 1, secondary containment normal level sump pump level transmitter level indication output on November 15, 2018
- (3) Unit 2, loop 3 reactor coolant system delta temperature channel spiking down to 87 percent then back to 100 percent on November 16, 2018
- (4) Unit 1, loop A flow transmitter (FT-0419) instrument line leak on November 19, 2018
- (5) Unit 1, train C emergency diesel generator jacket water leak on November 20, 2018
- (6) Unit 1, loop D flow transmitters (FT-0447, 0448, and 0449) following a bias shift during a leak repair on an instrument tubing union on November 24, 2018
- (7) Unit 2, train C emergency diesel generator following local voltage unbalance alarms received during a surveillance test which required shutting down the generator on November 26, 2018
71111.19Post Maintenance Testing
The inspectors evaluated the following post-maintenance tests:
- (1) Unit 1, train B residual heat removal pump following motor replacement on September 26, 2018
- (2) Unit 2, train A spent fuel pool cooling pump following a failure to run on October 4, 2018
- (3) Unit 1, extended range nuclear instrument NI-46 following power spiking on October 31, 2018
- (4) Unit 1, train C main steam isolation valve following overhaul maintenance on November 2, 2018
71111.20Refueling and Other Outage Activities
The inspectors evaluated refueling outage 1RE21 activities from October 1 to November 11, 2018.
71111.22Surveillance Testing The inspectors evaluated the following surveillance tests: Routine
- (1) Unit 1, train B emergency safeguards function actuation test during a simulated loss of offsite power on October 12, 2018
Inservice (1 Sample)
- (1) Unit 2, train A residual heat removal inservice test on November 16, 2018
Reactor Coolant System Leak Detection (1 Sample)
- (1) Unit 1, reactor coolant inventory on November 15,
OTHER ACTIVITIES - BASELINE
71151Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below for South Texas Project, Units 1 and 2:
- (1) MS09: Residual Heat Removal Systems (10/01/2017 through 09/30/18)
- (2) MS10: Cooling Water Support Systems (10/01/2017 through 09/30/18)
71152Problem Identification and Resolution Semiannual Trend Review
The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (4 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) The failure of a Unit 1 circuit board in the main steam pegging valve control circuitry on June 25, 2018. This caused an excessive steam demand transient and an increase in thermal reactor power to 103 percent before operators reduced power down to 48 percent.
- (2) The failure of Units 1 and 2 diesel driven fire pumps to meet acceptance criteria for discharge pressure between June 14 and September 25, 2018.
- (3) The failure of a Unit 2, train A electrical auxiliary building main air handling unit supply fan motor due to a fault inside the motor windings on June 5, 2017. This issues was documented in Condition Report (CR) 17-17075.
- (4) The discovery of Sago pond weed in the Units 1 and 2 essential cooling pond ultimate heat sink and the introduction of grass eating carp (triploids) to resolve the issue. This issue was documented in CR 17-21846.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60854 - Preoperational Testing of an Independent Spent Fuel Storage Inspection (ISFSI)60856 - Review of 10 CFR 72.212(b) Evaluations 60857 - Review of 10 CFR 72.48 Evaluations Inspections of dry cask storage operations were conducted at STP on September 24-27 and November 26-29, 2018, by inspectors from NRC Regions I, IV, and the NRC Division of Spent Fuel Management. The purpose of the inspections was to observe and evaluate the licensees pre-operational demonstrations required by the Holtec HI-STORM FW Certificate of Compliance (COC), which STP had selected to use under its general 10 CFR Part 72 license.
STP conducted the demonstrations in accordance with the conditions and requirements specified in the Holtec HI-STORM FW Storage System COC 1032 Amendment 2 and HI-STORM FW Final Safety Analysis Report (FSAR), Revision 5.
License Condition No. 9 of the COC lists the pre-operational testing and training exercises required to be completed by a general licensee. During the September through November 2018 inspection dates, NRC inspectors observed STP perform the following operations: transfer of the multi-purpose canister (MPC) from the transfer cask to the HI-STORM FW overpack, MPC unloading operations from the storage overpack back into the transfer cask, and movement of the loaded HI-STORM FW overpack onto the STP ISFSI pad. STP had successfully completed the above listed pre-operations activities and fully demonstrated that the procedures, programs, and training related to those dry cask storage operations had been successfully integrated into its site operations. In addition, NRC inspectors reviewed the licensee's programs for heavy loads, emergency planning, fire protection, quality assurance, radiation protection, and record retention for inclusion of the 10 CFR Part 72 requirements of their generally licensed ISFSI into existing 10 CFR Part 50 programs. The licensee still has a number of demonstrations that are required to be completed before utilization of the HI-STORM FW system. Those demonstrations are projected to be performed in early 2019.
The ISFSI activities specifically reviewed during the on-site inspections and during in-office review included:
- (1) Evaluated and observed dry run operations, listed above, associated with License Condition No. 9 of the COC
- (2) Reviewed the licensees implementation of STPs Heavy Load Program to encompass dry cask storage operations
- (3) Reviewed analyses to determine maximum weights placed on the cask handling crane during loading operations and procedures for manual operation of the hoisting system and the bridge and trolley transfer mechanisms in emergent conditions
- (4) Reviewed evaluations that verify the cask handling crane meets the single-failure proof criteria as described in NUREG-0554
- (5) Reviewed load testing documentation for the cask handling crane for compliance with ASME B30.2 and ASME B30.10 criteria
- (6) Reviewed cask handling crane daily, periodic, and annual inspection procedures for compliance with ASME B30.2 criteria
- (7) Reviewed STPs wire and synthetic rope periodic and annual testing procedures for compliance with ASME B30.9 criteria
- (8) Reviewed design specifications, load testing documentation, and maintenance procedures for all special lifting devices, including the HI-TRAC VW Lift Blocks, HI-TRAC VW Lift Yoke, MPC Lift-Lock, and HI-STORM Lift Brackets for compliance with ANSI N14.6
- (9) Reviewed design specifications, purchase specifications, and load testing for the vertical cask transporter
- (10) Reviewed fuel selection procedures for compliance with license requirements with regard to cooling time, decay heat, burn-up, enrichment, etc.
- (11) Reviewed the licensees implementation of 10 CFR Part 72 emergency planning requirements into the existing 10 CFR Part 50 Emergency Plan
- (12) Reviewed the licensees fire and explosion hazards analysis for the ISFSI and conducted a walk-down of the heavy haul path and ISFSI to ensure all hazards had been identified and evaluated
- (13) Reviewed the licensees 10 CFR 72.212 report to verify all site-specific evaluations had been completed to ensure conformance with the terms, conditions, and specifications of the HI-STORM FW COC in accordance with Inspection Procedure 60856
- (14) Reviewed radiological dose calculations to verify that the annual levels from ISFSI operations would be less than the limits specified in 10 CFR 72.104
- (15) Reviewed licensees ISFSI maintenance and surveillance procedures to verify compliance with requirements from the FW FSAR and license Technical Specifications
- (16) Reviewed STPs quality assurance program, corrective action program, and implementing procedures for incorporation of ISFSI related activities
- (17) Reviewed STPs radiation protection program for implementation of ISFSI activities, which included ALARA planning, neutron dosimetry, radiation work plans, and calibration of radiological instrumentation
- (18) Verified the licensee had established procedures to ensure record retention requirements of 10 CFR 72.212 and verified the licensee had submitted its ISFSI Decommissioning Funding Plan per 10 CFR 72.30(b)
- (19) Reviewed the licensees program and procedures to implement changes in accordance with 10 CFR 72.48 requirements. Additionally, inspectors reviewed 10 CFR 72.48 safety evaluations/screenings performed by the licensee for ISFSI operations at STP in accordance with Inspection Procedure 60857
- (20) Evaluated and observed the licensees radiation protection implementation during the dry run observations
- (21) Evaluated and observed the licensees implementation of foreign material exclusion process during MPC transfer operations The inspectors did not identify any issues of concerns requiring documentation.
INSPECTION RESULTS
Observation
71152 - Semi-Annual
Trend Review The inspectors reviewed the licensees corrective action program entries, NRC generated condition reports, maintenance activities deferred from outage scope, maintenance re-work performance indicator, foreign material exclusion (FME) performance indicator and corrective action documents, and recent equipment issues discovered following refueling outages.
The inspectors noted and documented the following issues and trends:
- There have been several issues associated leaking reactor coolant system (RCS) loop flow transmitter tubing connections. One instance in Unit 2 on RCS loop B resulted in a temporary modification that installed an enclosure around the tubing connection and injected it with sealant. The leak was discovered on August 29, 2018, and documented in Condition Report (CR) 18-10183. There were two tubing leaks discovered in Unit 1. One leak on RCS loop A was discovered on November 14, 2018, and is being monitored with contingency actions if the leak increases in size and is also on the Unit 1 forced outage list for repair. This issue was documented in CR 18-13993. The second leak on RCS loop D was discovered during Mode 3 normal operating pressure and temperature walkdowns. During the repair, the three transmitters in loop D were over-ranged and experienced a zero-bias shift. The transmitter discrepancy was discovered during a channel check on November 24, 2018, and documented in CR 18-14266. Operations continues to monitor these channels for any changes. The licensee captured the trend and is performing a common cause evaluation under CR 18-14369.
The inspectors verified that all issues concerning the leaking RCS flow transmitter tubing connections were addressed within the scope of the corrective action program.
As of the date of this inspection report, the cause evaluation and corrective action development had not been completed and could not be assessed. The inspectors did not identify any trends or concerns that might be indicative of a more significant safety issue.
- The FME program performance has been placed on departmental elevation notice for continued poor performance despite the station having performed 10 cause evaluations for significant FME issues since 2011. This was concluded on July 23, 2018, and documented in CR 18-5434. The licensees root cause evaluation determined the root cause to be that the program oversight had not identified and corrected declines in behavioral performance. Part of the failure to recognize declines in performance was the incorrect categorization of more significant events as lower safety significant events and not associating FME events with human performance errors. The licensee is in the process of implementing corrective actions.
The inspectors verified that all issues concerning the FME program were addressed within the scope of the corrective action program and that the completed and planned corrective actions appeared to be appropriate to correct the identified causes. The inspectors did not identify any trends or concerns that might be indicative of a more significant safety issue as most issues were identified prior to closing up systems and being placed in service.
EXIT MEETINGS AND DEBRIEFS
On October 26, 2018, the inspectors presented the inservice inspection results to Mr. J. Connolly, Chief Nuclear Officer, and other members of the licensee staff.
On December 31, 2018, the inspector presented the annual requalification inspection results to Mr. A. Culver, Training Supervisor, and other members of the licensee staff.
On January 8, 2019, the inspectors presented the results from the pre-operational ISFSI inspections to Mr. G. T. Powell, President and Chief Executive Officer, and other members of the licensee staff during a telephonic exit conference. Licensee personnel acknowledged the information presented.
On January 10, 2019, the inspector presented the quarterly resident inspection results to Mr. G. T. Powell, President and CEO, and other members of the licensee staff.
The inspectors verified no proprietary information was retained or documented in this report.
DOCUMENTS REVIEWED
71111.01 - Adverse Weather
Condition Reports
18-1565 18-2147 18-6407 18-10622 18-9383
18-9384
Procedures
Number Title Revision
0PGP03-ZV-0001 Severe Weather Plan 21
0PEP07-ZG-0024 Exterior Flood Barrier Penetration Seal Visual Examination 0
0PEP01-ZE-0001 Structures Monitoring 5
0PSP11-ZE-0001 Check Valve Inspection 11
71111.04 - Partial Equipment Alignment
Condition Reports (CRs)
18-11066 18-11194 18-12135 18-11792 18-15228
Procedures
Number Title Revision
0POP02-CH-0001 Essential Chilled Water System 57
Drawings
Number Title Revision
5R209F05018#1 Piping and Instrumentation Diagram Component Cooling Water 18
System
5R169F20000#1 Piping and Instrumentation Diagram Residual Heat Removal 27
System
5V119V10001#2 Piping and Instrumentation Diagram HVAC Essential Chilled 33
Water System
3V119V10002#2 Piping and Instrumentation Diagram HVAC Essential Chilled 13
Water System
3V119V10003#2 Piping and Instrumentation Diagram HVAC Essential Chilled 16
Water System
71111.05AQ - Fire Protection Annual/Quarterly
Procedures
Number Title Revision
0RCB63-FP-0211 Fire Preplan Reactor Containment Building SW Peripheral Area 3
0RCB63-FP-0212 Fire Preplan Reactor Containment Building NW Peripheral Area 3
0RCB63-FP-0213 Fire Preplan Reactor Containment Building NE Peripheral Area 3
0RCB63-FP-0214 Fire Preplan Reactor Containment Building SE Peripheral Area 3
0EAB04-FP-0052 Fire Preplan Electrical Auxiliary Building ESF Switchgear Room, 4
Train C
0EAB04-FP-0053 Fire Preplan Electrical Auxiliary Building, Channel IV Battery and 3
Distribution Room
0DGB37-FP-0501 Fire Preplan Diesel Generator Building, Train B 3
0DGB37-FP-0513 Fire Preplan Diesel Air Intake/Exhaust, Train B 3
0IVC50-FP-0401 Fire Preplan Isolation Valve Cubicle, Pump Room Train A 2
0IVC49-FP-0402 Fire Preplan Isolation Valve Cubicle, Pump Room Train B 3
0IVC48-FP-0403 Fire Preplan Isolation Valve Cubicle, Pump Room Train C 3
0IVC51-FP-0400 Fire Preplan Isolation Valve Cubicle, Pump Room Train D 2
71111.08 - Inservice Inspection Activities
Condition Reports
17-12995 17-15763 17-17970 18-1146 17-12997
17-15859 17-18419 18-3055 17-13007 17-16094
17-19487 18-4215 17-13011 17-16125 17-19831
18-4536 17-13083 17-16270 17-19835 18-12050
17-13360 17-16285 17-20667 18-12531 17-14067
17-16604 17-20673 18-12532 17-15032 17-16990
Work Authorization Numbers (WAN)
24603 96013951
Procedures
Number Title Revision
0PEP01-ZA-0305 Testing/Programs Engineering Program Requirements 4
0PEP10-ZA-0001 Nondestructive Examination Written Practice 10
0PEP10-ZA-0002 Inservice Inspection Ultrasonic Nondestructive Examination 6
Written Practice
0PEP10-ZA-0004 General Ultrasonic Examination 7
0PEP10-ZA-0009 Recording Data from Direct Visual, Liquid Penetrant, and 2
Magnetic Particle Examinations
0PEP10-ZA-0010 Liquid Penetrant Examination (Color Contrast Solvent 5
Removable)
0PEP10-ZA-0017 Magnetic Particle Examination (Dry Powder Yoke Method) 5
0PEP10-ZA-0023 Visual Examination of Component Supports for American 7
Society of Mechanical Engineers (ASME)Section XI Inservice
Inspection
0PEP10-ZA-0024 ASME XI Examination for VT-1 and VT-3 4
0PEP10-ZA-0025 ASME Section XI Visual Examination for Containment Metal 5
Liner Inspections
0PEP10-ZA-0032 Visual VT-2 Examinations 4
0PEP10-ZA-0054 ASME Section XI VE Visual Examinations 2
0PGP03-ZE-0033 RCS Pressure Boundary Inspection for Boric Acid Leaks 13
0PGP03-ZE-0133 Boric Acid Corrosion Control Program 11
0PGP04-ZE-0304 Inservice Inspection Program for Welds and Component 13
Supports
0PSP11-RC-0015 ASME Section XI Inservice Inspection 17
OPSP11-SN-0004 Hydraulic Snubbers Functional Test 8
PDI-UT-1 Performance Demonstration Initiative (PDI) Generic Procedure G
for the Ultrasonic Examination of Ferritic Pipe Welds
PDI-UT-2 PDI Generic Procedure for the Ultrasonic Examination of H
Austenitic Pipe Welds
PDI-UT-5 PDI Generic Procedure for the Straight Beam Ultrasonic F
Examination of Bolts and Studs
PDI-UT-8 PDI Generic Procedure for the Ultrasonic Examination of Weld H
Overlaid Similar and Dissimilar Metal Welds
Procedures
Number Title Revision
PQR-003 Procedure Qualification Record for Welding Procedure 0
Specification (WPS) No. P1-T.
PQR-0126 Procedure Qualification Record for WPS No. P1-T (CVN). 0
PQR-0127 Procedure Qualification Record for WPS No. P1-T (CVN). 0
PQR-016 Procedure Qualification Record for WPS No. P8-T-Ag-1. 0
PQR-0197 Procedure Qualification Record for WPS No. P8-T-Ag. 0
PQR-0199 Procedure Qualification Record for WPS No. P1-A-Lh. 0
PQR-0205 Procedure Qualification Record for WPS No. P1-A-Lh. 0
PQR-035 Procedure Qualification Record for WPS No. P8-T-Ag. 2
PQR-037 Procedure Qualification Record for WPS No. P8-T-Ag, P8-A 0
and P8-AT-Ag.
PQR-040 Procedure Qualification Record for WPS No. P1-A/P1-A- 0
Lh/P1AT-Lh.
PQR-046 Procedure Qualification Record for WPS No. P8-T-Ag and 0
P8-AT-Ag.
PQR-087A Procedure Qualification Record for WPS No. P1-AT-Lh (CVN). 0
PQR-087B Procedure Qualification Record for WPS No. P1-AT-Lh (CVN). 0
UTI-004 Ultrasonic Technical Instruction 6
UTI-016 Ultrasonic Technical Instruction 3
UTI-065 Ultrasonic Technical Instruction 0
WPS No. P1-A-Lh QW-482 ASME WPS 8
WPS No. P1-T QW-482 ASME WPS 9
WPS No. R8-T-Ag QW-482 ASME WPS 10
Drawings
Number Title Revision
10025E58 South Texas Project Electric Generating Station, Units 1 and 2, 4
Closure Head General Assembly Interface Inf. for RRVCH
2M369PCV0217 Chemical and Volume Control "CV" 7
5R179F05007#1 Piping and Instrumentation Diagram Chemical and Volume 52
Control System
Figure: B-RHX-1 South Texas Project Electric Generating Station, Units 1 and 2, 3
Residual Heat Removal Hxs 1A, 1B, 1C
W9324055 Anchor/Darling Valve Company, 2"-1888 Socket Ends Stainless A
Steel Double Disc Gate Valve with Non-Cobalt Trim and 10" Tee
Handle
Miscellaneous
Documents Revision
Number Title or Date
Boric Acid Corrosion Control Program Health January 25,
Scorecard, 4th Quarter 2017 2018
Examination Plan for 1RE21, ASME Section XI October 3, 2018
Inservice Inspection Programs of South Texas
Project Electric Generating Station, Unit 1
Letter - Markley to South Texas Project Electric Generating Station, April 5, 2011
Halpin Units 1 and 2 - Request for Relief RR-ENG-3-02
from ASME Code Requirements for Reactor
Pressure Vessel Flange Insert Nondestructive
Examination (TAC Nos. ME4764 and ME4765)
Letter - Markley to South Texas Project Electric Generating Station, September 10,
Richards Units 1 and 2 - Request for Relief RR-ENG-3-04 to 2012
Apply Alternative to the ASME Boiler and Pressure
Vessel Code Section XI Requirements for
Examination of Class 1 and Class 2 Piping Welds
(TAC Nos. ME70SS and ME70S6)
Letter - Pascarelli to South Texas Project Electric Generating Station, June 30, 2016
Powell Unit 2 - Request for Relief No. RR-ENG-3-20 for
Extension of the Inspection Frequency of the
Reactor Vessel Cold-Leg Nozzle to Safe-End Welds
with Flaw Analysis (CAC NO. MF7428)
Letter - Pascarelli to South Texas Project Electric Generating Station, July 24, 2018
Powell Units 1 and 2 - Relief Request RR-ENG-3-22 for the
use of Encoded Phased Array Ultrasonic
Examination Techniques In Lieu of Radiography
(EPID L-2017-LLR-0154}
Miscellaneous
Documents Revision
Number Title or Date
Model No: South Texas Project Nuclear Operating Company August 4, 2016
16-1000001 Assmnt Assessment Report. (Snapshot Assessment)
No: 73 Cnd Seq No: Leakage trending associated with the 12 Boric Acid
16-9146 Corrosion Control Program PM's.
PM MM-2-90002098 BACC Preventative Maintenance. Reactor April 11, 2018
Containment Fan Cooler Cooling Coil (10 Coils).
Cleaning/Inspection.
PM MM-2-90002097 BACC Preventative Maintenance. RCFC Fan 22B April 11, 2018
RCFC Cooling Coil (10 Coils). Cleaning/Inspection.
PM MM-2-90002096 BACC Preventative Maintenance. RCFC Fan 22A April 11, 2018
RCFC Cooling Coil (10 Coils). Cleaning/Inspection.
PM MM-2-90002095 BACC Preventative Maintenance. Reactor October 14,
Containment Fan Cooler Cooling Coil (10 Coils). 2016
Cleaning/Inspection.
PM MM-2-90002094 BACC Preventative Maintenance. RCFC Fan 21B October 14,
RCFC Cooling Coil (10 Coils). Cleaning/Inspection. 2016
PM MM-2-90002093 BACC Preventative Maintenance. Reactor October 14,
Containment Fan Cooler Cooling Coil (10 Coils). 2016
Cleaning/Inspection.
PM MM-1-90002092 BACC Preventative Maintenance. RCFC Fan 11B October 29,
RCFC Cooling Coil (10 Coils). Cleaning/Inspection. 2015
PM MM-1-90002091 BACC Preventative Maintenance. RCFC 11C October 29,
Cooling Coil (10 Coils). Cleaning/Inspection. 2015
PM MM-1-90002090 BACC Preventative Maintenance. Reactor October 29,
Containment Fan Cooler Cooling Coil (10 Coils). 2015
Cleaning/Inspection.
PM MM-1-90002089 BACC Preventative Maintenance. Reactor March 30, 2017
Containment Fan Cooler Cooling Coil (10 Coils).
Cleaning/Inspection.
PM MM-1-90002088 BACC Preventative Maintenance. RCFC 12B March 30, 2017
Cooling Coil (10 Coils). Cleaning/Inspection.
PM MM-1-90002087 BACC Preventative Maintenance. RCFC 12A March 30, 2017
Cooling Coil (10 Coils). Cleaning/Inspection.
Miscellaneous
Documents Revision
Number Title or Date
NOC-AE-17003532 South Texas Project Electric Generating Station, December 12,
Units 1 and 2, Docket No. STN 50-498, STN 50-499, 2017
Proposed Alternative for the use of Encoded Phased
Array Ultrasonic Examination Techniques in Lieu of
Radiography (Relief Request RR-ENG-3-22)
STP8053 (7/13) Station Self-Assessment Program, Snapshot Self- June 24, 2014
Assessment Plan. Risk-Informed ISI Periodic
Evaluation for South Texas Project Electric
Generating Station, Units 1 and 2, in Conjunction
with End of the Third Interval, First Period. Condition
Report CR-14-10410
1000975 Electric Power Research Institute (EPRI) Boric Acid 1
Corrosion Guidebook. Managing Boric Acid
Corrosion Issues at PWR Power Stations
PM 05000175 Pressurizer Power Operated Relief Valves. Monitor September 19,
WAN 560570 Reactor Coolant System Trends and Develop 2018
Corrective Actions, as Necessary.
PM 05000175 Pressurizer Power Operated Relief Valves. Monitor September 5,
WAN 559644 Reactor Coolant System Trends and Develop 2018
Corrective Actions, as Necessary.
PM 05000175 Pressurizer Power Operated Relief Valves. Monitor August 22, 2018
WAN 558683 Reactor Coolant System Trends and Develop
Corrective Actions, as Necessary.
PM 06000556 Chemical and Volume Control System. Perform October 22,
System Walkdowns in Valve Pits and Areas not 2018
Routinely Accessed to Properly Identify Outage
Scope.
PM 06000556 Chemical and Volume Control System, Inspect Valve October 22,
Pits and other Difficult to Access Areas 2018
Evaluations
Number Title Date
16-06764-5 N1CVFCV0111A, Reactor Make-Up to Chemical and October 2,2017
Volume Control System Blending Tee Flow Control Valve
17-15948 2N121NPA102C, Low Head Safety Injection Pump 1C June 7, 2017
17-16232-2 Residual Heat Removal System Heat Exchanger 1B November 16,
2017
Evaluations
Number Title Date
17-16255-1 7R171TCV0505, CVCS Blended Flow to Reactor Water June 7, 2017
Storage Tank Vent Valve
17-17970-2 Residual Heat Removal System Heat Exchanger 1A September 20,
2017
17-18058-2 2N121TSI0206B, High Head Safety Injection Pump 1B July 17, 2017
Discharge Valve
17-18419-2 B1RCFT0419, Active Leakage on RC-FT-0419 High November 2,
Pressure T to Drain Valve Outlet Fitting 2017
17-20067 2N121TSI0132, Low Head Safety Injection Pump 1A September 13,
Discharge Test/Vent Valve 2017
17-20624-3 2N121TSI0126 High Head Safety Injection Pump 1A September 14,
Discharge Sample Valve, Downstream Isolation Valve 2017
18-00390-3 Residual Heat Removal (RHR) System Heat March 14, 2018
Exchanger (HX) 1C
18-01250 2N121NPA102B, Low Head Safety Injection Pump 1B February 26,
Boric Acid Deposits 2018
71111.11Q - Licensed Operator Requalification Training
Procedures Revision
Number Title or Date
0POP03-ZG-0007 Plant Cooldown 86
Miscellaneous
Documents
Number Title Date
Annual Requalification Results Summary December 21, 2018
71111.12 - Maintenance Effectiveness
Condition Reports (CRs)
18-12135 18-1737 18-11194 18-11066 17-17075
17-15261 17-14667 18-12169
Purchase Order Number
29803
Work Authorization Numbers (WAN)
2819 562860 562104 565616 586343
Procedures
Number Title Revision
SEG-0009 Maintenance Rule Basis Document 6
SEG-0014 Maintenance Rule Program Users Guideline 1
0PGP04-ZE-0313 Maintenance Rule Program 9
Drawings
Number Title Date
16-11379-21 Life Cycle Management Plan for the Residual Heat November 2017
Removal System
Miscellaneous
Documents
Number Title Date
Maintenance Rule Expert Panel Meeting Package January 2018
Maintenance Rule Expert Panel Meeting Package June 2018
Maintenance Rule Expert Panel Meeting Package November 2018
71111.13 - Maintenance Risk Assessment and Emergent Work Control
Procedures
Number Title Revision
0POP11-DJ-0002 Online Class 1E125V DC Battery and Inverter Removal from 15
Service and Restoration
0POP01-ZO-0006 Risk Management Actions (RMAs)
0PGP03-ZG-RMTS Risk-Managed Technical Specifications Program
0PGP03-ZA-0091 Configuration Risk Management Program
0POP04-DJ-0001 Loss of Class 1E 125 VDC Power
0PGP03-ZO-0055 Protected Components
Condition Reports (CR)
18-13993 18-14534 17-18164
Work Authorization Numbers (WAN)
601368
Work Activity Risk (WAR)
2796
RICTCAL Sequence Number
269 3278
71111.15 - Operability Determinations and Functionality Assessments
Condition Reports (CRs)
18-12152 18-13993 06-3315 03-10610 11-4249
18-14343 18-14621 18-14266 18-14091 18-14038
18-2471 18-2395
Work Authorization Numbers (WAN)
601974 601591
Procedures
Number Title Revision
0PMP04-ZG-0012 Equipment Hatch Removal and Installation 31
0PGP03-ZO-0052 Containment Management 12
0POP03-RC-0100 RCS Vacuum Fill 44
0PGP03-ZO-0046 RCS Leakage Monitoring 11
0PSP03-RC-0006 Reactor Coolant Inventory 34
0PSP03-DG-0026 Standby Diesel Generator Common Mode Failure Test 2
0PSP03-ZQ-0028 Operator Logs 148
0PGP04-ZA-0002 Condition Report Engineering Evaluation 25
Drawings Revision
Number Title or Date
5R149F05001#1 RCS Primary Coolant Loop 42
5Q159F22540#1 Piping and Instrumentation Diagram Standby Diesel Jacket 21
Water
G5-253-202 Control Schematic (Generator) Protective Relaying and September
Metering 29, 1977
G5-253-202 Control Schematic (Generator) High Voltage and Regulator) June 4,
2001
Calculations Revision
Number Title or Date
11-RC-006 RCS Heatup Analysis for Units 1 and 2 Refueling Outages 1
09-RCS-004 RCS Time to Boil with Water in Reactor Cavity 1
MC-6477 Added Commodities Inside The RCB 5
AC05002#1 Quantification of Unqualified Coatings Inside The Reactor May 21,
Containment Building (RCB) For Unit 1 2018
71111.19 - Post Maintenance Test
Condition Reports (CRs)
16-10971 17-23347 18-11496 18-11855
Work Authorization Numbers (WAN)
543666 569573 598473 598800
Procedures
Number Title Revisions
0PSP05-NI-0046 Extended Range Neutron Flux Channel IV Calibration 18
0PGP03-ZM-0021 Control of Configuration Changes 21
0PSP03-SP-0024 Steam Line Isolation Actuation and Response Time Test 15
0PSP03-MS-0002 Main Steam System Cold Shutdown Valve Operability 23
0PSP03-RH-0002 Residual Heat Removal Pump 1B(2B) Inservice Test 18
0PMP05-RH-0001 Residual Heat Removal Pump Motor Inspection 11, 12,
Vendor
Documents
Number Title Revision
VTD-G077-0001 Ex-core Neutron Flux Monitoring 2
Engineering
Reports Number Title Date
DCP 18-11855-12 Update design documents per vendor recommendation October 26,
2018
71111.20 - Refueling and Other Outage Activities
Condition Reports (CRs)
18-1523 18-1804 18-2176
Work Authorization Number (WAN)
534670 564060 600430
Procedures
Number Title Revision
0POP03-ZG-0005 Plant Startup to100% 19
0POP03-ZG-0010 Refueling Operations 78
0PSP03-XC-0001 Refueling Containment Penetration Status 30
0POP03-ZG-0001 Plant Heatup 73
0POP03ZG-0007 Plant Cooldown 86
0POP03-ZG-0014 Mode Change Checklist 3
0POP03ZG-0004 Reactor Startup 49
71111.22 - Surveillance Testing
Condition Reports (CRs)
18-13993
Procedures
Number Title Revision
0PSP03-DG-0008 Standby Diesel 12(22) LOOP Test 39
0PSP03-DG-0014 Standby Diesel 12(22) LOOP - ESF Actuation Test 41
0PSP03-RH-0001 Residual Heat Removal Pump 1A(2A) Inservice Test 14
0POP02-RH-0001 Residual Heat Removal System Operation 74
0PGP03-ZO-0046 RCS Leakage Monitoring 11
0PSP03-RC-0006 Reactor Coolant Inventory 34
Drawings
Number Title Revision
5R169F20000#2 Residual Heat Removal System 28
5N129F05013#2 Safety Injection System 35
71152 - Problem Identification and Resolution
Condition Reports
18-7676 18-8940 18-9294 18-8098 18-11165
Condition Reports
18-9443 18-7925 14-16486 16-6495 18-5434
18-13113 18-11066 18-12213 18-12232
Procedures
Number Title Revision
0PGP03-ZF-0018 Fire Protection System Functionality Requirements 20
0PGP03-FP-0106 Fire Protection Water System Functional Test 19
SEG-0008 Printed Circuit Board Maintenance and Replacement Guideline 2
0PGP03-ZF-0001 Fire Protection Program 33
0PGP03-ZA-0014A Foreign Material Exclusion Program, Administrative Procedure 4
0PGP03-ZA-0014 Foreign Material Exclusion Program, Implementing Procedure 35
MG-0008 Station Rework Reduction Program 5
Drawings
Number Title Revision
7Q270F00006 Fire Protection Storage and Pumps 22
Engineering
Reports Number Title Date
SM-03566 Nonconformance Report, Fire Water Pump No 1 December 16, 1986
SM-03567 Nonconformance Report, Fire Water Pump No 2 December 16, 1986
SM-03568 Nonconformance Report, Fire Water Pump No 3 December 16, 1986
4OA5.1 Other Activities (IP 60854, IP 60856, IP 60857)
Condition Reports (CRs)
18-1458 18-2283 18-2440 18-3341 18-3394
18-6595 18-7248 18-7519 18-7780 18-7975
18-8173 18-8234 18-8236 18-8387 18-8710
18-9258 18-9284 18-9306 18-9350 18-9398
18-9582
Procedures
Number Title Revision
0PEP02-ZM-0012 Fuel Selection for Dry Cask Storage 0
0PEP02-ZM-0004 Physical Inventory of Fuel Assemblies 18
Procedures
Number Title Revision
STP Reporting Manual 17
0PEP02-ZM-0001 Special Nuclear Material Item Control Areas 12
0ERP01-ZV-IN01 Emergency Classification 10
0DCS03-ZO-0008 DCS Abnormal Response 0
ZV-0006 Letters of Agreement 21
0ESB99-FP-0906 Fire Preplan for ESB and ISFSI Pad 0
0PGP04-ZA-0328 Engineering and Vendor Document Processing 18
0DCS03-ZO-0001 HI-STORM Transport Operations 0
NOC-AE-17003456 STP Fire Hazards Analysis Report 24
HI-2146056 ISFSI Dose Rate and HI-STORM FW CoC Radiation 15
Protection Program Dose Rate Limits
0PGP04-ZA-0307 Assessment of External Flooding Effects for STP 1 & 2 6
HI-21566473 Safety Analysis Summary of the Tornado Generated Missile 0
Analysis for HI-STORM FW Version XL
0PGP04-ZA-0328 Specification for Total Plant Numbering System 13
0DCS03-ZO-0002 HI-STORM and MPC Pre-Use Inspections 0
0PSP03-ZQ-0028 Operator Logs 146
0PGP03-ZX-0002 Condition Reporting Process 52
0PQP01-ZA-0003 Vendor Overview Activities (numerous) 9
0PRP07-ZR-0036 Radiological Controls or Dry Cask Storage 0
STP-005 Proposal for Neutron Dosimetry Evaluation for STP 0
N/A ALARA Review Package 0
0DCS01-ZA-0001 Dry Cask Storage Program Implementation 0
0DCS02-ZN-0002 10CFR72.48 Screening and Evaluations 0
0DCS03-ZO-0003 MPC Loading Operations 0
0DCS03-ZO-0005 MPC Transfer Operations 0
0DCS03-ZO-0007 MPC Unloading Operations 0
Design Basis Documents
Number Title Revision
HI-2114830 Final Safety Analysis Report on the HI-STORM FW MPC 5
Storage System
N/A Certificate of Compliance No. 1032 2
Miscellaneous Revision
Documents Number Title or Date
N/A HI-STORM Belly Band Certifications August 24,
2018
TP-HOL-010 Dry Fuel Storage Training for Vertical Cask Transporter N/A
N/A Individual Training Certifications (numerous) N/A
HI-2135940 HI-STORM FW Cask Handling Weights 5
0PGP03-ZI-0026 Lifting, Rigging, and Material Handling 23
PS-3107 Purchase Specification for the HI-STORM FW Lift Bracket 1
PS-3701 Purchase Specification for the HI-TRAC VW Lift Links 2
PS-3702 Purchase Specification for the HI-TRAV VW Lift Yoke 5
PS-3723 Purchase Specification for the HI-TRAV VW Lift Lugs 4
DOC-104-107-063R0 HI-STORM FW Lift Brackets for South Texas Project 0
Nuclear Plant
PS-1120 Purchase Specification for the Vertical Cask Transporter 7
PS-3734 Purchase Specification for FW Lift Lock 1
G. Powell 3
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 31500011. The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget control
number.
This letter and its enclosure 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.
Information Request
August 27, 2018
Notification of Inspection and Request for Information
South Texas Project Electric Generating Station Unit 1
NRC Inspection Report 05000498/2018004; 05000499/2018004
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October 12-26, 2018
Inspector: Ronald A. Kopriva
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 Ron Kopriva, by October 1, 2018, 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.
On October 12, 2018, a reactor inspector from the Nuclear Regulatory Commissions (NRC)
Region IV office will perform the baseline inservice inspection at South Texas Project
Electric Generating Station, Unit 1, using NRC Inspection Procedure 71111.08, "Inservice
Inspection Activities. Experience has shown that this inspection is a resource intensive
inspection both for the NRC inspector and your staff. The date of this inspection may
change dependent on the outage schedule you provide. 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 inspector is adequately prepared. The second
G. Powell 3
group (Section B of the enclosure) identifies the information the inspector 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 Ms. Robyn Savage of your
licensing organization. The tentative inspection schedule is as follows:
Preparation week: October 8-11, 2018
Onsite dates: October 12-26, 2018
Our inspection dates are subject to change based on your updated schedule of outage
activities. If there are any questions about this inspection or the material requested, please
contact the lead inspector Ronald A. Kopriva at (817) 200-1104.
(e-mail to: ron.kopriva@nrc.gov).
A.1 ISI/Welding Programs and Schedule Information
1. A detailed schedule (including preliminary dates) of:
1.1. Nondestructive examinations planned for ASME Code Class Components
performed as part of your ASME Section XI, risk informed (if applicable), and
augmented inservice inspection programs during the upcoming outage.
1.2. Examinations planned for Alloy 82/182/600 components that are not included in
the Section XI scope (If applicable)
1.3. Examinations planned as part of your boric acid corrosion control program
(Mode 3 walkdowns, bolted connection walkdowns, etc.)
1.4. Welding activities that are scheduled to be completed during the upcoming
outage (ASME Class 1, 2, or 3 structures, systems, or components)
2. A copy of ASME Section XI Code Relief Requests and associated NRC safety
evaluations applicable to the examinations identified above.
2.1. A list of ASME Code Cases currently being used to include the system and/or
component the Code Case is being applied to.
3. A list of nondestructive examination reports which have identified recordable or
rejectable indications on any ASME Code Class components since the beginning of
the last refueling outage. This should include the previousSection XI pressure
test(s) conducted during start up and any evaluations associated with the results of
the pressure tests.
G. Powell 3
4. A list including a brief description (e.g., system, code class, weld category,
nondestructive examination performed) associated with the repair/replacement
activities of any ASME Code Class component since the beginning of the last outage
and/or planned this refueling outage.
5. 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.
6. 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.
7. A list of any temporary non-code repairs in service (e.g., pinhole leaks).
8. Please provide copies of the most recent self-assessments for the inservice
inspection, welding, and Alloy 600 programs.
9. Copy of the procedures for welding and NDE that will be used during the outage.
A.2 Reactor Pressure Vessel Head
1. 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.
1.1. 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).
1.2. Provide records that demonstrate that a volumetric or surface leakage path
examination assessment was performed.
2. 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
1. 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.
G. Powell 3
2. 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 shutdown, please provide
documentation of containment walkdown inspections performed as part of the boric
acid corrosion control program.
A.4 Additional Information Related to all Inservice Inspection Activities
1. A list with a brief description of inservice inspection, and boric acid corrosion control
program 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 such as: inservice
inspection, ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust,
corrosion, boric acid, or errors in piping examinations.
2. Provide training (e.g. Scaffolding, Fall Protection, FME, Confined Space) if they are
required for the activities described in A.1 through A.3.
3. 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
B. Information to be Provided Onsite to the Inspector(s) at the Entrance Meeting
(October 12, 2018):
B.1 Inservice Inspection / Welding Programs and Schedule Information
1. Updated schedules for inservice inspection/nondestructive examination activities,
including planned welding activities, and schedule showing contingency repair
plans, if available.
2. 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:
- Weld data sheet (traveler).
- Weld configuration and system location.
- Applicable Code Edition and Addenda for weldment.
- Applicable Code Edition and Addenda for welding procedures.
G. Powell 3
- Applicable welding procedures used to fabricate the welds.
- Copies of procedure qualification records (PQRs) supporting the weld
procedures from B.1.b.v.
- Copies of welders performance qualification records (WPQ).
- Copies of the nonconformance reports for the selected welds (If
applicable).
- Radiographs of the selected welds and access to equipment to allow
viewing radiographs (if radiographic testing was performed).
- Copies of the preservice examination records for the selected welds.
- Readily accessible copies of nondestructive examination personnel
qualifications records for reviewing.
3. For the inservice inspection related corrective action issues selected by the inspector
from section A of this enclosure, provide a copy of the corrective actions and
supporting documentation.
4. For the nondestructive examination reports with relevant conditions on an ASME Code
Class components selected by the inspector from Section A above, provide a copy of
the examination records, examiner qualification records, and associated corrective
action documents.
5. A copy of (or ready access to) most current revision of the inservice inspection
program manual and plan for the current interval.
6. For the nondestructive examinations selected by the inspector 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
1. Provide the nondestructive personnel qualification records for the examiners who will
perform examinations of the reactor pressure vessel head replacement (If applicable).
G. Powell 3
2. Provide drawings showing the following:
- Reactor pressure vessel head and control rod drive mechanism nozzle
configurations
- Reactor pressure vessel head insulation configuration
Note: The drawings listed above should include fabrication drawings for the nozzle
attachment welds as applicable.
B.3 Boric Acid Corrosion Control Program
1. 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.
2. 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 Codes and Standards
1. 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):
- Applicable Editions of the ASME Code (Sections V, IX, and XI) for the
inservice inspection program and the repair/replacement program.
2. 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.).
3. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975.
SUNSI Review ADAMS: Non-Publicly Available Non-Sensitive Keyword:
By: NTaylor Yes No Publicly Available Sensitive NRC-002
OFFICE SRI:DRP/B RI:DRP/B C:DRS/PSB2 C:DRS/OB C:DRS/IPAT C:DRS/EB1
NAME ASanchez JChoate HGepford GWerner RKellar VGaddy
SIGNATURE AAS JMC HJG GEW RLK Vgg
DATE 1/29/19 01/25/19 01/19/19 01/20/19 01/17/19 1/17/19
OFFICE C:DRS/EB2 C:DNMS/CHP BC:DRP/B
NAME JDrake JKatanic NTaylor
SIGNATURE JFD JFK NHT
DATE 1/22/19 1/22/19 2/1/19