IR 05000269/2019001: Difference between revisions
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=PLANT STATUS= | =PLANT STATUS= | ||
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On January 24, 2019, the unit performed a planned power reduction to 24 percent RTP to repair to a heater drain system valve (1HD-30). The unit was returned to 100 percent RTP on January 25, 2019. | |||
On March 3, 2019, the 1A2 feedwater heater developed a minor steam leak and the unit performed an unplanned power reduction to 65 percent RTP to make repairs on March 5, 2019. | On March 3, 2019, the 1A2 feedwater heater developed a minor steam leak and the unit performed an unplanned power reduction to 65 percent RTP to make repairs on March 5, 2019. | ||
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The inspectors evaluated readiness for impending adverse weather conditions for extreme cold weather on January 24, 2019 through January 30, 2019. | The inspectors evaluated readiness for impending adverse weather conditions for extreme cold weather on January 24, 2019 through January 30, 2019. | ||
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)=== | ===Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)=== | ||
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the | The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems: standby shutdown facility (SSF); protected service water (PSW) building; auxiliary building heating and cooling; and turbine building heating and cooling on January 9, 2019, January 10, 2019, and January 17, 2019. | ||
==71111.04 - Equipment Alignment== | ==71111.04 - Equipment Alignment== | ||
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Unit 1 turbine building basement during preventive maintenance (PM) on the Unit 1 Presray watertight door on February 4, 2019. | Unit 1 turbine building basement during preventive maintenance (PM) on the Unit 1 Presray watertight door on February 4, 2019. | ||
Inspection Activities - Underground Cables (IP Section 02.02c.) (1 Sample) | Inspection Activities - Underground Cables (IP Section 02.02c.) (1 Sample) | ||
The inspectors evaluated cable submergence protection in: | The inspectors evaluated cable submergence protection in: | ||
CT-5 cable trench in the west laydown yard (elevation 793') on January 15, 2019 and the CT-5 cable trench west of the old radiation protection building (elevation 791') on January 16, 2019. | |||
===71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04) === | ===71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04) === | ||
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The inspectors observed and evaluated licensed operator performance in the control room during the start of 'A' chiller due to the unexpected stopping of the 'B' chiller which resulted in degraded control room area cooling on January 24, 2019. Additionally, the inspectors observed and evaluated licensed operator performance in the control room during a reduction in reactor power from 100 percent RTP to 25 percent RTP on January 24, 2019, in preparation for repair to the 1B first stage reheater drain tank dump valve 1HD-30. | The inspectors observed and evaluated licensed operator performance in the control room during the start of 'A' chiller due to the unexpected stopping of the 'B' chiller which resulted in degraded control room area cooling on January 24, 2019. Additionally, the inspectors observed and evaluated licensed operator performance in the control room during a reduction in reactor power from 100 percent RTP to 25 percent RTP on January 24, 2019, in preparation for repair to the 1B first stage reheater drain tank dump valve 1HD-30. | ||
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample) | Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample) | ||
The inspectors observed and evaluated operator training on SSF operation following a | The inspectors observed and evaluated operator training on SSF operation following a simulated loss of power and loss of all feedwater on January 15, 2019. | ||
==71111.13 - Maintenance Risk Assessments and Emergent Work Control== | ==71111.13 - Maintenance Risk Assessments and Emergent Work Control== | ||
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Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned power changes per 7000 critical hours. | Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned power changes per 7000 critical hours. | ||
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample) | IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample) | ||
Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance | Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned scrams with complications. | ||
==OTHER ACTIVITIES== | ==OTHER ACTIVITIES== | ||
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This inspection is a Part 72 inspection. The Inspection Number is 07200004/2019001 and this inspection closes Temporary Instruction 2690/011. | This inspection is a Part 72 inspection. The Inspection Number is 07200004/2019001 and this inspection closes Temporary Instruction 2690/011. | ||
Aging Mgmt at ISFSI (1 Sample)=== | ===Aging Mgmt at ISFSI (1 Sample)=== | ||
Temporary Instruction 2690/011 is an information-gathering activity whose results will be used to develop an inspection procedure to address the licensees performance of the AMP activities related to ISFSIs. From January 21 to January 22, 2019, the inspectors evaluated the licensees processes or procedures of the aging management program (AMP) for the ISFSI for adequacy. The inspectors conducted an in-office review of additional information following the inspection. Because Oconee is a pre-SRP (Standard Review Plan) plant, it did not specifically follow the ten elements defined in the AMP as identified in NUREG-1927, Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel, Revision 1. | Temporary Instruction 2690/011 is an information-gathering activity whose results will be used to develop an inspection procedure to address the licensees performance of the AMP activities related to ISFSIs. From January 21 to January 22, 2019, the inspectors evaluated the licensees processes or procedures of the aging management program (AMP) for the ISFSI for adequacy. The inspectors conducted an in-office review of additional information following the inspection. Because Oconee is a pre-SRP (Standard Review Plan) plant, it did not specifically follow the ten elements defined in the AMP as identified in NUREG-1927, Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel, Revision 1. | ||
Revision as of 05:00, 2 November 2019
ML19129A068 | |
Person / Time | |
---|---|
Site: | Oconee ![]() |
Issue date: | 05/09/2019 |
From: | Frank Ehrhardt NRC/RGN-II |
To: | Burchfield J Duke Energy Corp |
References | |
IR 2019001 | |
Download: ML19129A068 (23) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION May 8, 2019
SUBJECT:
OCONEE NUCLEAR STATION - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000269/2019001, 05000270/2019001, 05000287/2019001, AND 07200004/2019001
Dear Mr. Burchfield:
On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Oconee Nuclear Station Units 1, 2, and 3. On April 24, 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 finding or violation 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/
Frank Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos.: 50-269, 50-270, 50-287,72-004 License Nos.: DPR-38, DPR-47, DPR-55, SNM-2503
Enclosure:
IR 5000269/2019001, 5000270/2019001, 05000287/2019001, and 07200004/2019001
Inspection Report
Docket Numbers: 50-269, 50-270, 50-287,72-004 License Numbers: DPR-38, DPR-47, DPR-55, SNM-2503 Report Numbers: 05000269/2019001, 05000270/2019001, 05000287/2019001, 07200004/2019001 Enterprise Identifier: I-2019-001-0020 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Units 1, 2, and 3 Location: Seneca, SC Inspection Dates: January 1, 2019 to March 31, 2019 Inspectors: E. Crowe, Senior Resident Inspector J. Parent, Resident Inspector A. Ruh, Resident Inspector J. Bundy, Operations Engineer P. Capehart, Senior Operations Engineer R. Carrion, Senior Reactor Inspector M. Riley, Reactor Inspector Approved By: F. Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a quarterly baseline inspection at Oconee Units 1, 2, and 3 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 and self-revealed findings, violations, and additional items are summarized in the table below.
List of Findings and Violations No findings were identified.
Additional Tracking Items Type Issue number Title Report Section Status Unresolved 05000269,05000270, Degraded Voltage 71111.21M Closed Item (URI) 05000287/2014007- Relay Scheme
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On January 24, 2019, the unit performed a planned power reduction to 24 percent RTP to repair to a heater drain system valve (1HD-30). The unit was returned to 100 percent RTP on January 25, 2019.
On March 3, 2019, the 1A2 feedwater heater developed a minor steam leak and the unit performed an unplanned power reduction to 65 percent RTP to make repairs on March 5, 2019.
The unit was returned to 100 percent RTP on March 6, 2019 and remained at this power level for the remainder of the inspection period.
Unit 2 began the inspection period at 100 percent RTP and remained at this power level for the entire inspection period.
Unit 3 began the inspection period at 100 percent RTP and remained at this power level 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
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.03)
The inspectors evaluated readiness for impending adverse weather conditions for extreme cold weather on January 24, 2019 through January 30, 2019.
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems: standby shutdown facility (SSF); protected service water (PSW) building; auxiliary building heating and cooling; and turbine building heating and cooling on January 9, 2019, January 10, 2019, and January 17, 2019.
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 02.01)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) PSW; 4160 volt safety related electrical distribution system; emergency feedwater system (EFW); SSF; and Lee combustion turbines and associated CT-5 transformer during dual Keowee hydro outage on January 15 - 17, 2019 (installation of anti-rotational device during Keowee hydro Unit 1 stator replacement)
- (2) SSF on January 19, 2019
- (3) Lee combustion turbines and dedicated AC power path to CT-5 on January 31, 2019
- (4) PSW; 4160 volt safety related electrical distribution system, EFW; SSF; and Lee combustion turbines and associated CT-5 transformer during dual Keowee hydro outage on February 6 - 7, 2019 (removal of anti-rotational device during Keowee hydro Unit 1 stator replacement)
- (5) 'B' chiller and operating temporary chiller during planned maintenance of the 'A' chiller on March 12 - 14, 2019
- (6) Unit 2 low pressure injection (LPI) trains 'A' and 'B' during planned maintenance on the 2C LPI pump on March 13 - 14, 2019
71111.04S - Equipment Alignment Complete Walkdown (IP Section 02.02)
The inspectors evaluated system configurations during a complete walkdown of the PSW system on February 6 and 7, 2019.
71111.05A - Fire Protection (Annual)
Annual Inspection (IP Section 03.02)
The inspectors evaluated fire brigade performance on January 22, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit 2 auxiliary building elevation 771', fire zone 66 on March 13, 2019
- (2) Unit 2 auxiliary building elevation 783', fire zone 83 on March 13, 2019
- (3) Unit 1 turbine building elevation 775', fire zone 24 on March 14, 2019
- (4) Unit 3 auxiliary building elevation 771', fire zone 60 on March 29, 2019
- (5) Unit 3 auxiliary building elevation 783', fire zone 79 on March 29, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.)
The inspectors evaluated internal flooding mitigation protections in the:
Unit 1 turbine building basement during preventive maintenance (PM) on the Unit 1 Presray watertight door on February 4, 2019.
Inspection Activities - Underground Cables (IP Section 02.02c.) (1 Sample)
The inspectors evaluated cable submergence protection in:
CT-5 cable trench in the west laydown yard (elevation 793') on January 15, 2019 and the CT-5 cable trench west of the old radiation protection building (elevation 791') on January 16, 2019.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04)
The inspectors reviewed the facility operating history and associated documents in preparation for this inspection. During the week of March 11 - 15, 2019, the inspectors reviewed documentation, interviewed licensee personnel, and observed the administration of operating tests associated with the licensees operator requalification program. Each of the activities performed by the inspectors was done to assess the effectiveness of the facility licensee in implementing requalification requirements identified in 10 CFR Part 55, Operators Licenses. The evaluations were also performed to determine if the licensee effectively implemented operator requalification guidelines established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, and IP 71111.11, Licensed Operator Requalification Program. The inspectors also evaluated the licensees simulation facility for adequacy for use in operator licensing examinations using ANSI/ANS-3.5-2009, American National Standard for Nuclear Power Plant Simulators for use in Operator Training and Examination. The inspectors observed two crews during the performance of the operating tests. Documentation reviewed included written examinations, job performance measures (JPMs), simulator scenarios, licensee procedures, on-shift records, simulator modification request records, simulator performance test records, operator feedback records, licensed operator qualification records, remediation plans, watchstanding records, license reactivation packages, and medical records. The records were inspected using the criteria listed in IP 71111.11.
Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on March 11, 2019.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
The inspectors observed and evaluated licensed operator performance in the control room during the start of 'A' chiller due to the unexpected stopping of the 'B' chiller which resulted in degraded control room area cooling on January 24, 2019. Additionally, the inspectors observed and evaluated licensed operator performance in the control room during a reduction in reactor power from 100 percent RTP to 25 percent RTP on January 24, 2019, in preparation for repair to the 1B first stage reheater drain tank dump valve 1HD-30.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated operator training on SSF operation following a simulated loss of power and loss of all feedwater on January 15, 2019.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Oconee Nuclear Site elevated green risk during Keowee hydro dewater activities for installation of Keowee hydro Unit 1 anti-rotation device to support stator replacement on January 15 - 17, 2019
- (2) Unit 1 elevated green risk associated with emergent work activities associated with valve controller failure for 1-HD-30 on January 24, 2019
- (3) Oconee Nuclear Site elevated green risk during Keowee hydro dewater activities for removal of Keowee hydro Unit 1 anti-rotation device to support stator replacement on February 6 - 7, 2019
- (4) Oconee Nuclear Site elevated yellow risk during PM activities to 3B circulating water system pump discharge valve 3CCW-11 on February 13, 2019
- (5) Oconee Nuclear Site elevated yellow risk during PM activities to 1A circulating water system pump discharge valve 1CCW-10 on March 4, 2019
- (6) Emergent work activities associated with 1A2 feedwater heater steam leak on March 4 -
6, 2019
71111.15 - Operability Determinations and Functionality Assessments
===Operability Determinations and Functionality Assessments Sample (IP Section 02.01) (7 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Unit 1 essential siphon system tank minimum flow valve 1ESV-29 failed to cycle during stroke testing of February 13, 2019. (Nuclear Condition Report (NCR) 02257474)
- (2) Missing flow restrictor cartridge element in valve 3-LPSW-849 (NCR 2253656)
- (3) External grid trouble protection system 230kV red bus Y-phase underfrequency relay failure (NCR 2261061)
- (4) Vendor identified failure mode for PSW flow control valves (NCR 2259431)
- (5) 1-HP-4 failed to operate from SSF power (NCR 2241697)
- (6) Incorrectly configured pipe support on Unit 1 B main steam line (NCR 2238294)
- (7) 2A high pressure injection pump motor cooler test failed acceptance criteria (NCR
===2265364)
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following permanent modifications:
- (1) Engineering Change (EC)110240, Alternate Chilled Water System And Procedure Changes Associated With Unanalyzed Effects In Unit 3 Cable Room
71111.19 - Post Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01)===
The inspectors evaluated the following post maintenance tests:
- (1) PT/0/A/0400/005, SSF auxiliary service water pump test following planned mechanical and electrical maintenance on January 10, 2019
- (2) PT/0/A/0620/009, operability test of Keowee hydro Unit 2 following restoration from dewatering activity on January 16, 2019
- (3) OP/3/A/1104/010, Low Pressure Service Water; Enclosure 4.34, Shutdown and Return to Service of 3B LPSW pump following planned mechanical and electrical maintenance on February 4, 2019
- (4) PT/1/A/0203/006A, Low Pressure Injection Pump Test - Recirculation following PM to the 1B LPI pump on February 5, 2019
- (5) 3B CCW pump discharge valve (3CCW-11) stroke test following planned electrical and mechanical maintenance on February 8, 2019 (Work Order (WO) 20276508)
- (6) PT/1/A/0600/027, PAM Instrument Channel Checks following repairs to 1RIA-58 on March 15, 2019 (WO # 20301820)
- (7) MP/0/B/3009/020 C, Motor - Non-QA - Electric - Removal, Replacement, and Post Maintenance Testing following the replacement of the B spent fuel pool pump's motor on March 18, 2019 (WO # 20289815)71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors reviewed URI 05000269, 270, 287/2014007-04, Degraded Voltage Relay Scheme, for closure.
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (1 Partial)
- (1) URI 05000269, 270, 287/2014007-04, Degraded Voltage Relay Scheme
71111.22 - Surveillance Testing
===The inspectors evaluated the following surveillance tests:
In Service Testing (IST) (IP Section 03.01)===
- (1) PT/2/A/0600/013, Test of the 2B Motor Driven Emergency Feedwater Pump, on January 11, 2019
- (2) PT/0/A/0500/001, PSW Primary and Booster Pump Test on February 26, 2019 Surveillance Testing (IP Section 03.01) ===
- (1) OP/0/A/1600/010, Operation of the SSF Diesel-Generator, on February 19, 2019.
- (2) PT/2/A/0152/002, Building Spray System Valve Stroke Test of 2BS-2, on February 26, 2019
71114.06 - Drill Evaluation
Drill and/or Simulator-Based Licensed Operator Requalification Training (IP Section 02.01)
Inspectors observed a simulator-based licensed operator requalification training evolution on March 19, 2019, that involved a small RCS leak that developed into a larger leak, fuel damage and a leak through the containment equipment hatch.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===
Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned scrams.
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned power changes per 7000 critical hours.
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
Unit 1, 2, 3 (March, 2018 - March, 2019) the inspectors verified licensee performance indicator and submittal for unplanned scrams with complications.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL Temporary Instruction 2690/011 - Review of Aging Management Programs at Independent Spent Fuel Storage Installations (ISFSIs)
This inspection is a Part 72 inspection. The Inspection Number is 07200004/2019001 and this inspection closes Temporary Instruction 2690/011.
Aging Mgmt at ISFSI (1 Sample)
Temporary Instruction 2690/011 is an information-gathering activity whose results will be used to develop an inspection procedure to address the licensees performance of the AMP activities related to ISFSIs. From January 21 to January 22, 2019, the inspectors evaluated the licensees processes or procedures of the aging management program (AMP) for the ISFSI for adequacy. The inspectors conducted an in-office review of additional information following the inspection. Because Oconee is a pre-SRP (Standard Review Plan) plant, it did not specifically follow the ten elements defined in the AMP as identified in NUREG-1927, Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel, Revision 1.
60855.1 - Operation of an Independent Spent Fuel Storage Installation (ISFSI) at Operating Plants Operation of an ISFSI at Operating Plant
The inspectors evaluated the licensee's independent spent fuel storage installation cask loading of DSC 154 and DSC 155 on January 27 - 31, 2019, and February 19 - 21, 2019, respectively.
INSPECTION RESULTS
Unresolved Item Degraded Voltage Relay Scheme 71111.21M (Closed) 05000269,05000270,05000287/2014007-04
Description:
This URI was opened on June 27, 2014, in NRC Design Bases Assurance Inspection Report 05000269/2014007, 05000270/20140007, and 05000287/2014007 (ADAMS Accession Number: ML14178A535) to determine if a performance deficiency existed with respect to the degraded voltage relay (DVR) protection scheme at Oconee Nuclear Station. During the inspection, the team questioned the DVR protection scheme on the 4.16kv safety buses during normal operation, the licensees use of manual actions during mitigation of degraded voltage conditions, and the setpoints of the loss of power relays not being included in the technical specifications. The team determined that consultation with the Office of Nuclear Reactor Regulation was warranted, and task interface agreement (TIA)2014-04, Request for Technical Assistance Regarding the Adequacy of the Oconee Station Design and Licensing Bases for the Degraded Voltage Relay Protection Design, (ADAMS Accession Number: ML18226A215) was issued to determine if these issues were within the plants current licensing basis. TIA 2014-04 concluded that Oconee Nuclear Stations DVR protection scheme, including the issues described above, was consistent with the plants licensing basis. Therefore, based on the conclusions in the TIA, the team determined that no performance deficiency was identified.
Corrective Action Reference(s): PIP O-14-2034
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 24, 2019, the inspector presented the inspection results to Mr. J. Ed Burchfield, and other members of the licensee staff.
DOCUMENTS REVIEWED
71111.01: Adverse Weather Protection
Procedures
OMP 2-16, Shift Turnover, Rev. 037
OP/0/A/1104/037, Plant Heating, Rev. 005
OP/0/A/1104/041, Auxiliary Building Ventilation, Rev. 042
OP/0/A/1106/041, Turbine Building Ventilation, Rev. 009
OP/0/A/1600/002, Standby Shutdown Facility Heating, Ventilation and Air Conditioning System
Operation (HVAC), Rev. 037
OP/0/B/1104/050, Weather Related Activities, Rev. 005
OP/1/A/1104/051, ESV System, Rev. 028
OP/2/A/1102/020 D, SSF and Outside Rounds, Rev. 089
OP/2/A/1104/051, ESV System, Rev. 040
OP/3/A/1104/051, ESV System, Rev. 028
PT/0/A/0110/017, Cold Weather Protection, Rev. 015
RP/0/A/1000/035, Severe Weather Preparations, Rev. 004
Nuclear Condition Report
229621; 02240341; 02242590; 02247787; 02251763; 02251764; 02253556
Other
Clearance: OPS-1 -18-AS -EARLY TAGS -2329
Clearance: PSC-0 -18-PH -PH 251 SPINS-0314
Operators Logs on eSOMS
Work Orders/Requests
20118741; 20119309; 20122195; 20124638; 20125908; 20130858; 20130863; 20143662;
243947; 20289421
71111.04: Equipment Alignment
Documents
OMP 5-05, 100 KV Backup/Emergency Power System, Rev. 002
OSS-0254.00-00-1000, Design Basis Document for Emergency Feedwater and Auxiliary
Service Water Systems, Rev. 55
OSS-0254.00-00-1021, Design Basis Document for the Control Room Ventilation System, Rev.
OSS-0254.00-00-1053, Design Basis Document for Protected Service Water System, Rev. 2
OSS-0254.00-00-2000, Design Basis Document for 4KV Essential Auxiliary Power System,
Rev. 22
OSS-0254.00-00-2004, Design Basis Document for 230KV Switchyard System, Rev. 22
OSS-0254.00-00-2011, Design Basis Document for 100KV Alternate Power System. Rev. 17
OSS-0254.00-00-2014, Design Basis Document for 4160/600/120V SSF Essential AC Power
System, Rev. 15
Drawings
O-702, One Line Diagram 6900V and 4160V Station Auxiliary System, Rev. 36
O-702-A, One Line Diagram 6900V and 4160V Auxiliary System, Rev. 35
O-702-A2, One Line Diagram 6900V and 4160V Station Auxiliary System, Rev. 18
OFD-102A-2.1, Flow Diagram of Low Pressure Injection System (Borated Water Supply and LPI
Pump Suction), Rev. 59
OFD-102A-2.2, Flow Diagram of Low Pressure Injection System (LPI Pump Discharge), Rev. 52
OFD-116J-1.2, Flow Diagram of Control Room Air Condition System, Rev. 15
OFD-116J-1.5, Flow Diagram of Chilled Water System Pumps and Chillers, Rev. 26
OFD-116J-1.6, Flow Diagram of Chilled Water System Chilled Water Supply and Return,
Rev. 21
OFD-121D-1.1, Flow Diagram of Emergency Feedwater System, Rev. 38
OFD-121D-2.1, Flow Diagram of Emergency Feedwater System, Rev. 40
OFD-121D-3.1, Flow Diagram of Emergency Feedwater System, Rev. 46
OFD-131A-1.1, Flow Diagram of Protected Service Water System, Rev. 2
OFD-131A-1.2, Flow Diagram of Protected Service Water System, Rev. 1
OFD-131A-2.2, Flow Diagram of Protected Service Water System, Rev. 1
OFD-131A-3.2, Flow Diagram of Protected Service Water System, Rev. 2
OFD-133A-1.1, Flow Diagram of Condenser Cooling Water System (CCW Intake Pump
Discharge), Rev. 32
OFD-133A-1.2, Flow Diagram of Normal Intake and Discharge (CCW System), Rev. 25
OFD-133A-2.5, Flow Diagram of Condenser Circulating Water System (SSF Aux. Service), Rev.
OFD-133A-2.5, Flow Diagram of Condenser Cooling Water System SSF Auxiliary Service
Water, Rev. 66
OM 245-2698.001, NPS 6 (DN 150) Bolted Bonnet Globe Valve (Forged) c/w Gear Operator,
Rev. D
Other
Procedures
LECOP/00/TBD/0007, Lee CT, Rev. 004
OMP 5-05, 100 kV Backup/Emergency Power System, Rev. 2
OP/0/A/1107/003, 100 KV Power Supply, Rev. 097
OP/0/A/1107/003, B, Procedure for Furnishing Power to Oconee, Rev. 15
OP/0/A/1650/001, PSW System, Rev. 4
OP/0/A/1650/002, PSW Ventilation, Rev. 4
OP/0/A/1650/005, PSW AC Power. Rev. 18
OP/0/A/1650/006, PSW DC Power, Rev. 9
OSS-0254.00-00-1053, Design Basis Document for Protected Service Water System, Rev. 2
PT/2/A/0203/006 A, Low Pressure Injection Pump Test - Recirculation, Rev. 087
Work Orders/Requests
261363; 20262803
Condition Report
256635; 2195609; 2259431; 2194263; 2108086; 2229649
71111.05: Fire Protection
Calculations
OSC-9375, Oconee Fire PRA, Fire Scenario Report, Rev. 007
OSC-9588, Oconee Fire Hazard Ignition Source Tabulation, Rev. 006
Documents
AD-EG-ALL-1522, Duties of a Fire Watch, Rev. 8
AD-HU-ALL-0003, Conduct of Pre-Job Briefs and Post-Job Critiques, Rev. 7
AD-OP-ALL-0111, Operations, Communications, Rev. 1
AD-OP-ALL-0207, Fire Brigade Administrative Controls, Rev. 1
AD-PI-ALL-0106, Cause Investigation Checklists, Rev. 3
AD-RP-ALL-6002, Inspections of Self-Contained Breathing Apparatus (SCBA) and Associated
Equipment, Rev. 1
AD-TQ-ALL-0086, Fire Brigade and Hazmat Training, Rev. 5
AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System
(NLMS), Rev. 9
O-FS-0-PA-9000-001, PA Unit 2 Transformers T2, 2T and CT2, Rev. 01
O-FS-1-TB-9775-001, Unit 1 - Turbine Building Elevation 775, Rev. 002
O-FS-2-AB-9771-001, Unit 2 - Auxiliary Building Elevation 771, Rev. 002
O-FS-2-AB-9783-001, Unit 2 - Auxiliary Building Elevation 783, Rev. 002
O-FS-2-TB-9775-001, Unit 2 Turbine Building Elevation 775, 796, 822, & 838, Rev. 001
O-FS-3-AB-9771-001, Unit 3 - Auxiliary Building Elevation 771, Rev. 002
O-FS-3-AB-9783-001, Unit 3 - Auxiliary Building Elevation 783, Rev. 002
OSS-0254.00-00-4008, Design Specification for Fire Protection, Rev. 043
Renewed License No. DPR-47, Renewed Facility Operating License, Amendment No. 363
Selected Licensee Commitments, Revised 11/28/2018
Nuclear Condition Report
251618; 02253705; 02254223; 02254847; 02255541; 02259084; 02261330; 02261333
263477
Other
Fire Drill Designator: MCC 2 X-C
HS0113-N Initial / HS0116-N Requalification, MSA-SCBA, Advanced Basic Respirator Initial,
Rev. 01
Impairment Status Sheet
Procedures
MP/0/A/1705/032, Fire Hose Stations - Common Areas - SLC Related - Inspections, Rev. 043
MP/0/A/1705/032 F, Fire Extinguisher Carts - Inspection, Rev. 002
PT/0/A/0250/010 A, Fire Protection Systems Monthly Check, Rev. 081
PT/0/B/2000/050, Fire Drill - Performance and Evaluation, Rev. 003
Work Orders/Requests
20300068; 20312030; 20312031
71111.06: Internal Flood Protection
Documents
AD-HS-ALL-0110, Electrical Safety, Rev. 11
OSS-0274.00-00-0006, Oconee Electric Component Aging Management Review for License
Renewal, Rev. 002
OSS-0274.00-00-0008, Time-Limited Aging Analyses of Electrical Components for License
Renewal, Rev. 001
Drawings
OM 111.-0223.001, PRSD3BHW Watertight Door, Rev. DI
OM 111.-0223.002, Sections A-A & C-C, Rev. DI
OM 111.-0223.003, Details 1 & 2, Rev. H
OM 111.-0223.004, Details 1A-D, 2A-D & 39, Rev. DI
OM 111.-0223.005, Details 12, 13, & 35, Rev. DI
OM 111.-0223.006, Details: 3, 4, 24 & 27, Rev. H
OM 111.-0223.007, Details 32, 50, 53, 56 & View Z, Rev. DI
OM 111.-0223 008, Detail 21, Rev. A
OM 111.-0223 009, Jamb Stop, Rev. 0
OM 111.-0223 010, Heavy Duty Hinge Blade, Rev. J
OM 111.-0223 012, Cam Plate, Rev. DD
Nuclear Condition Report
255726
Procedures
MP/0/A/1400/031, Door - Presray Watertight - Preventive Maintenance and Repair, Rev. 016
TE-MN-ALL-0002, Foreign Material Exclusion Level and Controls Screening, Rev. 1
Work Orders/Requests
20133147; 20267448 01; 20302072 01; 20302072 03
71111.11: Licensed Operator Requalification
Documents
AD-HU-ALL-0003, Conduct of Pre-Job Briefs and Post-Job Critiques, Rev. 5
AD-OP-ALL-0203, Reactivity Management, Rev. 11
AD-OP-ALL-1000, Conduct of Operations, Rev. 13
AD-TQ-ALL-0068, Licensed Operator Continuing Training Program, Rev. 9
AD-TQ-ALL-0230, Licensed Operator Requalification Annual and Biennial Exam Development,
Rev. 7
AD-TQ-ALL-0320, Development of Simulator Training and Evaluation Guides, Rev. 4
AD-TQ-ALL-0410, Remediation and Reevaluation, Rev. 5
AD-TQ-ALL-0420, Conduct of Simulator Training and Evaluation, Rev. 14
AD-TQ-ALL-0420, Development and Administration of Job Performance Measures, Rev 1
AD-TQ-ALL-0425, Simulator Scenario Based Testing, Rev. 3
AD-TQ-ALL-0450, Conduct of On-The-Job Training and Task Performance Evaluation, Rev. 4
OP-OC-PSF-091, Simulator Exercise Guide (PSF-091), Rev. 05a
Procedures
AP/0/A/1700/025, Standby Shutdown Facility Emergency Operating Procedure, Rev. 063
AP/1-2/A/1700/036, Degraded Control Room Area Cooling, Rev. 019
AP/3/A/1700/036, Degraded Control Room Area Cooling, Rev. 009
OP/1/A/1102/004, Operation At Power, Rev. 156
OP/1/A/1106/002 B, FDWPT Operation, Rev. 040
OP/1/A/1106/002 D, HDP Operation, Rev. 015
OP/1/A/1106/014, Moisture Separator Reheater, Rev. 067
OP/1/A/6101/006, Alarm Response Guide 1SA-06, Rev. 045
PT/0/A/0120/033, Time Critical Action Verification, Rev. 077
PT/0/A/1103/020, Power Maneuvering Predictions, Rev. 026
Records
License Reactivation Packages (1 Record Reviewed)
LORP Training Attendance records (4 Records Reviewed)
Medical Files (15 Reviewed)
Remedial Training Records (4 Records Reviewed)
Remedial Training Examinations (4 Records Reviewed)
Written Examinations
LOR RO Biennial Week 3 3/15/2019
LOR SRO Biennial Week 3 3/15/2019
Simulator Scenario Based Tests
ASE-13, 246, 38, 48, 22, 42
Scenario Packages
ASE-02A; ASE-13; ASE-18; ASE-22; ASE-38; ASE-41; ASE-42; ASE-44; ASE-48; ASE-246
JPM Packages
ADM-CO-003
ADM-SO-023
AO-500
CO-502A
CO-P402B
AO-S402
CO-S400A
CO-S411A
Corrective Action Program Documents
Action Request 02259786
Action Request 02259986
Action Request 02259032
Action Request 02259027
71111.13: Risk Assessments
Documents
AD-EG-ALL-1004, Conduct of Probabilistic Risk Analysis Engineering, Rev. 3
AD-NF-ALL-0501, Electronic Risk Assessment Tool (ERAT), Rev. 3
AD-NF-NGO-0502, Probabilistic Assessment (PRA) Model Technical Adequacy, Rev. 3
OSS-0254.00-00-1000, Design Basis Document for Emergency Feedwater and Auxiliary
Service Water Systems, Rev. 55
OSS-0254.00-00-1053, Design Basis Document for Protected Service Water System, Rev. 2
OSS-0254.00-00-2000, Design Basis Document for 4KV Essential Auxiliary Power System,
Rev. 22
OSS-0254.00-00-2004, Design Basis Document for 230KV Switchyard System, Rev. 22
OSS-0254.00-00-2011, Design Basis Document for 100KV Alternate Power System. Rev. 17
OSS-0254.00-00-2014, Design Basis Document for 4160/600/120V SSF Essential AC Power
System, Rev. 15
Drawings
O-702, One Line Diagram 6900V and 4160V Station Auxiliary System, Rev. 36
O-702-A, One Line Diagram 6900V and 4160V Auxiliary System, Rev. 35
O-702-A2, One Line Diagram 6900V and 4160V Station Auxiliary System, Rev. 18
OFD-116J-1.5. Flow Diagram of Chilled Water System Pumps and Chillers, Rev. 26
OFD-121D-1.1, Flow Diagram of Emergency Feedwater System, Rev. 38
OFD-121D-2.1, Flow Diagram of Emergency Feedwater System, Rev. 40
OFD-121D-3.1, Flow Diagram of Emergency Feedwater System, Rev. 46
OFD-131A-1.1, Flow Diagram of Protected Service Water System, Rev. 2
OFD-131A-1.2, Flow Diagram of Protected Service Water System, Rev. 1
OFD-131A-2.2, Flow Diagram of Protected Service Water System, Rev. 1
OFD-131A-3.2, Flow Diagram of Protected Service Water System, Rev. 2
OFD-133A-1.1, Flow Diagram of Condenser Cooling Water System (CCW Intake Pump
Discharge), Rev. 32
OFD-133A-1.2, Flow Diagram of Normal Intake and Discharge (CCW System), Rev. 25
OFD-133A-2.5, Flow Diagram of Condenser Cooling Water System SSF Auxiliary Service
Water, Rev. 66
Nuclear Condition Report
253284; 2260482
Other
Projected ERAT Risk Profile
Procedures
AD-MN-ALL-0006, Fluid Leak Management, Rev. 1
AD-OP-ALL-0102, Operational Decision Making, Rev. 2
AD-WC-ALL-0390, Unit Threat, Forced Outage, and Downpower Management, Rev. 4
AD-WC-ALL-0410, Work Activity Integrated Risk Management, Rev. 7
AD-WC-ALL-0210, Work Request Initiation, Screening, Prioritization and Classification, Rev. 9
OP/1/A/1106/023, High and Low Pressure Extraction, Rev. 20
OP/1/A/1102/004, Operation At Power, Rev. 156
Work Orders/Requests
262803
71111.15: Operability Evaluations
Calculations
OSC-8671, Auxiliary Building Flood Design Values, Rev. 7
Documents
OSS-0254.00-00-1049, Design Basis Document for Essential Siphon Vacuum System, Rev. 13
Reportability Evaluation, AR 02238294 Piping Analysis Problem 1-01-01, dated 11/27/18
Reportability Evaluation, AR 02238294 Piping Analysis Problem 1-01-02, dated 11/21/18
Reportability Evaluation, AR 02238294 Supports affected by Stress analysis OSC-320, OSC-
21 and OSC-2221, dated 11/27/18
Reportability Evaluation, AR 02238294 Piping Analysis Problem 1-01-15, dated 11/26/18
Vendor Letter, Positioner Failure RMA C-18Z027, dated 2/22/19
Vendor Letter, 10 CFR Part 21 Report: Notification of a Defect with Target Rock Modulating
Valve Positioner; Model 810000-X, dated 3/6/19
Drawings
OFD-130A-1.1, Flow Diagram of Essential Siphon and Vacuum System, Rev. 8
OM 245.2415.001, Griswold, Automatic Flow Control Valves, Rev. 0
OM 253.0116.001, PSW - Modulating SOV System Calibration Procedure for DMV-1463, Rev.
DJ
OSS-0251.00-00-0007, Modulating Solenoid Operated Throttle Valves (DMV-1463) for the
Protected Service Water System, Rev. 4
OFD-124B-3.6, Flow Diagram of Low Pressure Service Water System (LPSW) Auxiliary
Building Air Handling Units, Rev. 26
O-2510B, Piping Layout Miscellaneous Piping Turbine Room Mezzanine Plan, Rev. 22
OEE-265-02, Elementary Diagram Protected Service Water Steam Generator 2A Flow Control
OLD-2004-04, 230kV Switchyard External Grid Trouble Protection System and Switchyard
Isolated Logic Diagram Channel #2, Rev. 2
OEE-76-2, External Grid Trouble Protection Channel No. 2 Logic Diagram, Rev. 1
OEE-76-8, Elementary Diagram External Grid Trouble Protective System Voltage Channel No.
2, Rev. 9
OEE-76-10, External Grid Trouble Protective System Frequency Channel No. 2, Rev. 7
OEE-48F, Elementary Diagram 230kV Switchyard Control PCB No. 18 Control and Degraded
Grid, Rev. 4
OEE-151-1, Elementary Diagram Letdown Cooler 1B Outlet Vlv FS/1/15/4 1HP4 1HP VA0004,
Rev. 13
OEE-151-01-0A, Elementary Diagram Letdown Cooler 1B Outlet Vlv 1HP4 (FS/1/15/4) 1HP
VA0004, Rev. 4
OEE-163-16, Elementary Diagram Standby Shutdown Facility SSF Control Transfer, Rev. 2
OEE-163-16A, Elementary Diagram Standby Shutdown Facility Ctrl. Trans., Rev. 2
OEE-163-16B, Elementary Diagram Standby Shutdown Facility Control Transfer, Rev. 4
Nuclear Condition Report
238294; 02241697; 02253656; 02257474; 02259431; 02261061; 02265364; 2258827;
1893113
Procedures
MP/0/A/1200/189 B, Valve - Target Rock - Modulating Solenoid Operated Globe - Model 09L-
001 - Disassembly, Cleaning, Inspection, and Reassembly, Rev. 9
PT/1/A/0600/024, SSF Comprehensive Control Transfer Verification dated 11/9/18, Rev. 20
PT/1/A/0600/024, SSF Valve Control Transfer Verification dated 11/21/16, Rev. 18
PT/2/A/0230/015, High Pressure Injection Motor Cooler Performance Test, Rev. 42
Work Orders/Requests
20134135
71111.18: Plant Modifications
Calculations
KC-2005, Pipe Supports on Turbine Generator Cooling Water Discharge Piping. Math Model 1-
WL-03 (Civil), Rev. 7
KC-2268, Keowee Stator Project - Main and Neutral Lead Support & Barrier, Rev. 002
OSC-9659, Oconee Nuclear Safety Capability Assessment for Units 1, 2, And 3, Rev. 11
OSC-10969, Mechanical Design input Calculation for the Alternate Chilled Water (AWC)
System, Rev. 4
OSC-8671, Auxiliary Building Flood Design Values, Rev. 7
OSC-10790, Oconee Nuclear Station Internal Flooding Analysis, Rev. 3
Documents
AD-EG-ALL-1501, Fire Protection Change Process, Rev. 2
Drawings
K-0708-A, Interconnection Diagram Generator #1 Supervisory Equipment, Rev. 026
KM 300.--0323.001, Main and Neutral Leads Assembly, Rev. 001
OFD-116Q-1.2, Flow Diagram of Alternate Chilled Water System Auxiliary Building Chiller No. 1
Main Headers, Rev. 14
O-2510L, Piping Layout Miscellaneous Piping Elev. 809+3 - Auxiliary Building - Plan, Rev. 23
Engineering Change 101838, Replace Keowee Unit #1 Generator Stator, Rev. 028
110240, Install Chillers, Auxiliary Skid, and Piping for the Alternate Chilled Water System, Rev.
Nuclear Condition Report
254365; 02254442; 02254451; 02254469; 02254702; 02254711; 02254734; 02254911;
254985; 02255290; 02255471; 02255506; 02255513; 02262219; 2261444
Procedures
AP/1-2/A/1700/036, Degraded Control Room Area Cooling, Rev. 20
OP/0/A/1106/029C, Alternate Chilled Water System, Rev. 16
TT/0/A/EC101838/001, Keowee Stator Unit 1 Functional Testing, Rev. 004
Work Orders/Requests
227339; 2261518; 2261440; 2261234
71111.19: Post-Maintenance Testing
Documents
NIPM-QAF-18, Nuclear Inspection Program Manual - QAF-18 Mechanical Inspections, Rev.
005
OSS-0254.00-00-1028, Design Basis Document for Low Pressure Injection and Core Flood,
Rev. 55
OSS-0254.00-00-1039, Design Basis Document for Low Pressure Service Water System, Rev.
Drawings
OFD-102A-1.1, Flow Diagram for Lower Pressure Injection System, Rev. 71
OFD-102A-1.2, Flow Diagram of Low Pressure Injection System, Rev. 61
OFD-124A-3.1, Flow Diagram of Low Pressure Service Water Turbine Building (LPSW Pumps),
Rev. 39
Nuclear Condition Report
249362; 02254893
Procedures
IP/0/A/3001/001, Limitorque Preventive Maintenance, Rev. 96
MP/0/A/1300/019, Pump - Ingersoll Rand - Type 4X13LP - Spent Fuel Pool Coolant Pump -
Disassembly and Reassembly, Rev. 029
MP/0/A/1300/040, Generic - Alignment, Rev. 031
MP/0/B/3009/020 C, Motor - Non-QA - Electric - Removal, Replacement, and Post
Maintenance Testing, Rev. 009
OP/3/A/1104/010, Low Pressure Service Water, Rev. 114
PT/0/A/0400/004, SSF Auxiliary Service Water Pump Test, Rev. 69
PT/0/A/0620/009, Keowee Hydro Operation, Rev. 054
PT/1/A/0203/006A, Low Pressure Injection Pump Test - Recirculation, Rev. 92
PT/1/A/0600/027, PAM Instrument Channel Checks, Rev. 038
PT/3/A/0152/006, Condenser Circulating Water System Valve Stroke Test, Rev. 19
Work Orders/Requests
20129619; 2025238201; 20276508; 20301820
71111.22: Surveillance Testing
Calculations
OSC-9595, Protected Service Water System Hydraulic Model, Rev. 8
OSC-9596, Mechanical Design Input Calculation and System Calculation for the Protected
Service Water System, Rev. 11
OSC-9847, Protected Service Water (PSW) Primary Pump and Booster Pump Head Curves,
Rev. 3
OSC-9901, PSW Primary Pump Discharge Flow Instrument Uncertainty Calculation, Rev. 3
OSC-9536, Electrical Design Input Calculation for EC91878, Rev. 8
Documents
CSD-CP-ALL-0003, Fleet Closed Cooling Water Systems Chemistry Strategic Plan, Rev. 0
Drawings
OSS-0254.00-00-1053, Protected Service Water System, Rev. 2
ONTC-0-131A-0003-001, Protected Service Water Booster Pump Test Acceptance Criteria,
Rev. 0
ONTC-0-131A-0003-002, Protected Service Water Booster Pump Test Acceptance Criteria,
Rev. 0
ONTC-0-131A-0004-001, Protected Service Water Primary Pump Test Acceptance Criteria,
Rev. 0
ONTC-0-131A-0004-002, Protected Service Water Primary Pump Test Acceptance Criteria,
Rev. 0
Nuclear Condition Report
2173686
Other
SSF Diesel Jacket Water Chemistry Sample Results & Trends Sheets
SSF Engine Vent Exh. & SSF Online Vent Supply Fan Vibration Data Sheets
Procedures
CP/0/A/4002/032, Sampling the Closed Cooling Systems, Rev. 013
OP/0/A/1600/010, Operation of the SSF Diesel-Generator, Rev. 095
OP/2/A/1106/006, Emergency FDW System, Rev. 116
PT/0/A/0500/001, Protected Service Water Primary and Booster Pump Test dated February 26,
2019, Rev. 3
PT/0/A/0600/020, Standby Shutdown Facility Instrument Surveillance, Rev. 024
PT/0/A/0600/021, Standby Shutdown Facility Diesel-Generator Operation, Rev. 016
PT/0/A/0600/023, Standby Shutdown Facility Fuel Oil Inventory, Rev. 007
PT/2/A/0152/002, Building Spray System Valve Stroke Test, Rev. 036
PT/2/A/0600/013, Motor Driven Emergency Feedwater Pump Test, Rev. 074
Work Orders/Requests
20134795; 20222213
71114.06: Drill Evaluation
Documents
Critique Report, Oconee 2017-02 Quarterly Drill, dated 2 May 2017
Critique Report, Oconee 2017-03 Quarterly Drill, dated 22 June 2017
Critique Report, Oconee 2017-Augmentation Drill, dated 24 July, 2017
Critique Report, Oconee 4 February 2019 TSC Table Top Drill, WebEOC Critique Report
Critique Report, Oconee 21 January 2019 TSC Table Top Drill, WebEOC Critique Report
Critique Report, Oconee 11 February 2019 TSC Table Top Drill, WebEOC Critique Report
Critique Report, EPDR-ONS 18TT-1 Critique Report for 12 February 2018 Table Top Drill, dated
March, 2018
Critique Report, Oconee 18 February 2019 Drill, WebEOC Critique Report
ASE6, Simulator Exercise Guide, Rev. 2
71151: Performance Identification Verification
Documents
Unit 1 Station Operating Logs covering the period of March 1, 2018 through March 20, 2019
Unit 3 Station Operating Logs covering the period of March 1, 2018 through March 20, 2019
Procedures
AD-EG-ONS-1214, Condition Monitoring of Structures, Rev. 001
AD-LS-ALL-0006, Notification/Reportability Evaluation, Rev. 1
AD-LS-ALL-0007, Applicability Determination Process, Rev. 5
AD-NF-ALL-0602, Spent Fuel Management and ISFSI, Rev. 2
AD-PI-ALL-0100, Corrective Action Program, Rev. 20
AD-PI-ALL-0400, Operating Experience Program, Rev. 7
CSD-CP-ONS-0001, Oconee Primary Chemistry Strategic Plan, Rev. 004
HP/0/B/1000/054, Radiation Protection Routines, Rev. 049
MP/0/A/1700/010 A, Cask - Spent Fuel - Lifting Equipment (NUTECH) - Inspection and Load
Test, Rev. 009
MP/0/A/1700/014, Cask - NUTECH 24P Spent Fuel Transfer - Annual Maintenance, Rev. 006
OP/2/A/1102/020 D, SSF and Outside Rounds, Rev. 089
Corrective Action Documents
Action Request (AR) 02249489, Move ISFSI Inspection WO Task from Existing MWO
Other Documents Reviewed
Duke Energy Carolinas, LLC, Oconee, Independent Spent Fuel Storage Installation Technical
Specifications for Materials License SNM-2503, Appendix A, Amendment 9
Duke Energy Carolinas, LLC, Oconee, Independent Spent Fuel Storage Installation Technical
Specifications for Environmental Protection, Materials License SNM-2503, Appendix C,
Amendment 9
Duke Energy Company, Independent Spent Fuel Storage Facility, Oconee Nuclear Site,
Updated Final Safety Analysis Report, Rev. 27
OSC -11057, Independent Spent Fuel Storage Installation 5-yr Civil Inspection, Rev. 001
Work Order Package 20194321 01, U0, Mech PM SF NUTECH 24P Transf Cask
Work Order Package 20199663 01, U0 PM All Spent Fuel Yokes and Lifting Adapter
60855.1: Operation of an Independent Spent Fuel Storage Installation at Operating Plants
Documents
AD-RP-ALL-9001, ALARA Planning, Rev. 4
Amendment Number 13 to COC 1004, Technical Specifications for the Standardized NUHOMS
Horizontal Modular Storage System, Rev. 1
Docket No. 72-1004, Final Safety Evaluation Report - Transnuclear, Inc. Standardized
NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Amendment No. 13
NUH-003, Updated Final Safety Analysis Report for the Standardized NUHOMS Horizontal
Modular Storage System for Irradiated Nuclear Fuel, Rev. 14
Procedures
HP/0/B/1000/097, Radiological Protection Requirements for Independent Spent Fuel Storage
Installation, Rev. 018
MP/0/A/1500/024, Independent Spent Fuel Storage Installation Phase VIII DSC Loading and
Storage, Rev. 001
MP/0/A/1500/028, Spent Fuel Pool Bridge Operation, Rev. 009
MP/0/A/1500/031, Fuel Assembly/Component Tool Operation, Rev. 008
MP/0/A/1810/019, Cask - Nuhoms 24PTH-S-LC Dry Storage Canister - Welding, Rev. 032
NDE-NE-ALL-2101, Helium Mass Spectrometer Leak Test for Dry Fuel Storage ISFSI, Rev. 1
PT/0/A/0750/003, Physical Inventory of Reportable Special Nuclear Materials, Rev. 024
PT/0/A/1500/001, Independent Spent Fuel Storage Installation Horizontal Storage Module
Temperature Rise Verification, Rev. 010
Other
Completed Learning Activity Report
My Quals
VSDS Standard Map Survey Report Oconee Nuclear Station
Work Orders/Requests
201571
21