IR 05000458/2018003
| ML18313A028 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/08/2018 |
| From: | Jason Kozal NRC/RGN-IV/DRP |
| To: | Maguire W Entergy Operations |
| References | |
| IR 2018003 | |
| Download: ML18313A028 (24) | |
Text
November 8, 2018
SUBJECT:
RIVER BEND STATION - NRC INTEGRATED INSPECTION REPORT 05000458/2018003
Dear Mr. Maguire:
On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your River Bend Station, Unit 1. On October 18, 2018, 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.
No NRC-identified or self-revealing findings were identified during this inspection. However, inspectors documented a licensee-identified violation which was determined to be of very low safety significance in this report. The NRC is treating this violation as a non-cited violation consistent with Section 2.3.2.a of the NRC Enforcement Policy.
If you contest the violation or significance of the non-cited violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC resident inspector at the River Bend Station. 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 David Proulx Acting for/
Jason W. Kozal, Chief Project Branch C Division of Reactor Projects
Docket No. 50-458 License No. NPF-47
Enclosure:
Inspection Report 05000458/2018003 w/ Attachment: Documents Reviewed
Enclosure U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number(s):
05000458
License Number(s):
Report Number(s):
Enterprise Identifier: I-2018-003-0009
Licensee:
Entergy Operations, Inc.
Facility:
River Bend Station
Location:
Saint Francisville, Louisiana
Inspection Dates:
July 1, 2018 to September 30, 2018
Inspectors:
J. Sowa, Senior Resident Inspector
C. Speer, Acting Senior Resident Inspector
B. Parks, Resident Inspector
P. Elkmann, Senior Emergency Preparedness Inspector
G. Pick, Senior Reactor Inspector
H. Freeman, Senior Reactor Inspector
R. Kopriva, Senior Reactor Inspector
C. Stott, Reactor Inspector
S. Makor, Reactor Inspector
C. Osterholtz, Senior Operations Engineer
N. Hernandez, Operations Engineer
M. Chambers, Security Specialist
Approved By:
J. Kozal, Chief,
Project Branch C
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at River Bend Station 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.
No findings or violations of more than minor significance were identified during the inspection.
Additional Tracking Items
Type Issue number Title Inspection Procedure Status LER 05000458/2017-004-01 Loss of High Pressure Core Spray Safety Function During Surveillance Due to Malfunction of Test Return Valve 71153 Closed LER 05000458/2018-001-00 Potential Loss of Safety Function of Control Building HVAC Due to Legacy Design Flaw 71153 Closed LER 05000458/2018-004-00 Unanalyzed Condition Due to Inappropriate Protection from Tornado Generated Missiles 71153 Closed VIO 05000458/2017009-01 Failure to Obtain Prior NRC Approval for a Change in Reactor Core Isolation Cooling Injection Point 92702 Closed
PLANT STATUS
River Bend Station began the inspection period at rated thermal power. On August 14, 2018, the unit was down powered to 70 percent in order to troubleshoot a failed pilot solenoid associated with a main steam isolation valve and to conduct power suppression testing. The unit was returned to rated thermal power on August 30, 2018. On September 21, 2018, the unit was down powered to 60 percent for a control rod sequence exchange and to suppress a suspected nuclear fuel leak. The unit was returned to rated thermal power on September 28, 2018, and remained at or near rated thermal power for the remainder of the 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 July 18, 2018.
71111.04Equipment Alignment Partial Walkdown
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Residual heat removal A system on July 5, 2018
- (2) Residual heat removal C system on July 18, 2018
- (3) Reactor core isolation cooling system on July 18, 2018
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the Division I and Division II standby liquid control systems on July 23, 2018.
71111.05AQFire Protection Annual/Quarterly Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Residual heat removal pump A room, fire area AB-5, on July 5, 2018
- (2) Residual heat removal pump C room, fire area AB-4/Z-1 and Z-2, on July 18, 2018
- (3) Reactor core isolation cooling pump room, fire area AB-4/Z-1 and Z-2, on July 18, 2018
- (4) Standby liquid control area, fire area RC-4/Z-4, on July 23, 2018
71111.06Flood Protection Measures Internal Flooding
The inspectors evaluated internal flooding mitigation protections in residual heat removal pump room B on September 4, 2018.
71111.07Heat Sink Performance Heat Sink
The inspectors evaluated residual heat removal B heat exchanger performance on September 26, 2018.
71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification
The inspectors observed and evaluated a portion of an annual requalification test for licensed operators on August 16, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated the operators performance during a period of heightened risk associated with reactor power maneuvering following a rod pattern adjustment on August 30, 2018.
Operator Exams (1 Sample)
The inspectors reviewed and evaluated requalification examination results on September 21, 2018.
Operator Requalification Program (1 Sample)
The inspectors evaluated the operator requalification program from August 27, 2018, to September 21, 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) Functional failure review of the residual heat removal system on September 19, 2018
Quality Control (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance issues:
- (1) Work order for emergency diesel generator relay (EGS-PNL3A-R2) replacement missing safety class and seismic qualification information on July 17, 2018
71111.13Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Yellow risk during extended maintenance outage on Division II diesel generator on July 2, 2018
- (2) Yellow shutdown risk condition with reactor core isolation cooling out of service for testing on July 10, 2018
- (3) Yellow risk during discharge check valve replacement on Division I standby service water system on July 30, 2018
71111.15Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Division II standby service water normal service water return valve SWP-MOV96B could not be opened remotely on July 11, 2018
- (2) Primary containment following alarm in annulus radiation detector on July 25, 2018
- (3) Main steam isolation valve B21-F022B following loss of electrical power to the B solenoid for B21-AOVF022B on August 27, 2018
71111.17TEvaluations of Changes, Tests and Experiments
The inspectors evaluated the following from September 10 to September 14, 2018:
10 CFR 50.59 Evaluations
- (1) EC No. 54958 - Install a modern digital turbine control system (Westinghouse Ovation) to replace the current analog C85 steam bypass and pressure control system and the Mark II turbine control system.
- (2) EN-2017-002 - While running the Division I emergency diesel generator for a scheduled test, a water leak was found on the jacket water system exhaust jacket behind the number 6 cylinder. The Process Applicability Determination (PAD)determined that the manual operator action to implement the compensatory measures should be evaluated under 10 CFR 50.59.
- (3) EN-2015-001 - Core operating limit report for updated fuel loading pattern for Cycles C19A, C19B, and C19C due to leaking fuel bundles.
- (4) EN-2015-003 - Updated methodology for calculating ultimate heat sink heat load to determine ultimate heat sink minimum technical specification level.
- (5) EN-2017-001 - Core operating limit report for updated fuel loading pattern for Cycle C20A due to leaking fuel bundles.
- (6) EN-2015-004 - The design Release Time of the affected Agastat relays, the main steam isolation valve closure/reactor protection system trip circuits could exceed their technical requirements manual response time values even if all relays in the circuit operated within their design specifications and this specific condition is limited to 4 of the 16 loops associated with the main steam isolation valve closure scram circuits.
The design and licensing basis proposed change provides an upper limit for the scram delay time to bind the design of the Agastat relays.
- (7) EN-2016-001 - EC 59951 implements a design to provide an alternate method of ensuring that the reactor feedwater pumps are tripped on increasing reactor pressure vessel level during a fire in the main control room that prevents the plant operators from securing the feedwater system in the normal manner.
10 CFR 50.59 Screening/Applicability Determinations
- (1) PAD EC-58840 - Condition Report CR-RBS-2014-02754 documents failures during the performance of Surveillance Test Procedures STP-508-4812 and STP-508-4813.
The response time in Step 7.5.11 was found to be 102 milliseconds for the A channel and 94 milliseconds for the B channel, which exceed the technical requirements manual limit of 90 milliseconds.
- (2) PAD EC-56521 - The temporary modification installed a gag on residual heat removal heat exchanger cooling water relief valve E12-RVF100B and credited locked open manual valve E12-VF014B to prevent a thermal overpressure condition in the piping between E12-VF014B and E12-MOVF068B.
- (4) PAD EC-16264 - Replace the existing General Electric supplied series 6823 heater controllers manufactured by Electronic Control Systems, with new digital controllers supplied by OMEGA model number CNI8DH44.
- (5) PAD EC-76398 - Provide acceptable replacement relays for existing safety-related Gould J11 Series, 120 VAC, permanent magnet latching relays with a relay assembly comprised of an Allen Bradley base relay 700-P400A1 with a latching attachment 700-PLL11A1 as a replacement.
- (6) PAD EC-68298 - To temporarily swap the storage locations for the steam dryer and the steam separator to expedite refueling activities.
- (7) PAD EC-49287 - Service water check valves SWP-V199 and SWP-V200 internals removal.
- (8) PAD EC-57658 - Raise ultimate heat sink level alarm setpoints to allow maximum inventory.
- (9) PAD EC-59110 - Upgrade and relocate positioners for reactor feedwater level control valves C33-LVF001A/B/C and reactor feedwater startup valve C33-LVF002.
- (10) PAD EC-67339 - Reactor water cleanup regenerative heat exchanger permanent shielding installation.
- (11) PAD EC-67341 - Reactor water cleanup non-regenerative heat exchanger permanent shielding installation.
- (12) PAD EC-72603 - Standby diesel generator exhaust pipe manifold modification to address exhaust piping flange bolt failures.
- (13) PAD LBDCR-2016-02 - Correction to Technical Requirement Manual 3.6.1.2 to delete requirement to test airlock before each restart.
- (14) PAD EC-55881 - Revises ultimate heat sink basin minimum technical specification level increase and ultimate heat sink heat load calculation.
- (15) PAD EC-60680 - Issues a new calculation G13.18.3.6*027, required to calculate the voltages for the subject motor operated valves during a high energy line break scenario analyzing at relay dropout rather than relay reset.
- (16) PAD EC-63133 - Proposes to modify six existing Masterpact circuit breakers associated with Class 1E switchgear EJS-SWG1A, EJS-SWG1B, EJS-SWG2A, and EJS-SWG2B by placing a normally closed contact in series with each breaker-closing coil.
- (17) PAD EC-64630 - The proposed activity provides a document change that revises River Bend Station Design Criterion 240.201A, Post-Fire Safe Shutdown
Analysis.
- (18) PAD EC-64657 - This engineering change replaces the voltage regulator and part of the control circuitry for reactor protection system motor generator set C71-S001A and C71-S001B.
- (19) PAD EC65450 - This modification updates the capacity factor calculation (G13.18.9.0-008 Estimate of River Bend Station Capacity Factor for Environmental Qualification Applications) and updates the cable environmental qualification assessment reports to reflect the changed normal dose impact on the environmental qualification replacement frequency.
71111.19Post Maintenance Testing
The inspectors evaluated the following post maintenance tests:
- (1) STP-309-0207, Revision 27, Division II Diesel Generator 184 Day Operability Test, following extended maintenance outage on Division II emergency diesel generator on July 3, 2018
- (2) STP-204-6302, Revision 33, Division II LPCI Pump and Valve Operability Test, post-maintenance test following maintenance on residual heat removal C line fill pump check valve E12-VF084C on July 28, 2018
- (3) EN-WM-105, Revision 21, Mechanical Maintenance Test: Valve, Glove or Gate, post-maintenance test following replacement of residual heat removal C pump suction vent valve E12-VF013C on August 2, 2018
- (4) STP-209-6310, Revision 40, RCIC Quarterly Pump and Valve Operability Test, following replacement of remote servo mechanism in reactor core isolation cooling system on August 14, 2018
===71111.22Surveillance Testing The inspectors evaluated the following surveillance tests:
Routine===
- (1) STP-207-4539, Revision 301, RCIC Isolation - RCIC Steam Supply Pressure - Low Channel Functional Test, on August 9, 2018
71114.01Exercise Evaluation
The inspectors evaluated the biennial emergency plan exercise conducted on June 27, 2018. The exercise scenario simulated the inability to secure a liquid radioactive release above discharge permit limits, a catastrophic jet pump failure in the reactor which created fragments which damaged reactor fuel, failure of the reactor protection system to shut down the reactor, failures of the reactor core isolation cooling and high pressure core spray systems, a leak in the reactor water cleanup system outside of containment, and a monitored release through turbine building ventilation. The inspectors discussed the exercise with staff at FEMA Region VI.
71114.04Emergency Action Level and Emergency Plan Changes
The inspectors evaluated submitted River Bend Station On-Shift Staffing Analysis Final Report, Revision 1, dated November 14, 2017, on July 3, 2018. This evaluation does not constitute NRC approval.
71114.06Drill Evaluation Drill/Training Evolution
The inspectors evaluated a site-wide emergency preparedness drill on September 25, 2018.
71114.08Exercise Evaluation - Scenario Review
The inspectors reviewed and evaluated the proposed scenario for biennial emergency plan exercise on May 22, 2018. This review does not constitute NRC approval. The inspectors discussed the proposed scenario with staff at FEMA Region VI.
OTHER ACTIVITIES - BASELINE
71151Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
- (1) MS08: Heat Removal Systems (07/01/2017-06/30/2018)
- (2) MS09: Residual Heat Removal Systems (07/01/2017-06/30/2018)
- (3) MS10: Cooling Water Support Systems (07/01/2017-06/30/2018)
- (4) EP01: Drill/Exercise Performance Sample (04/01/2017-03/31/2018)
- (5) EP02: Emergency Response Organization Drill Participation Sample (04/01/2017-03/31/2018)
- (6) EP03: Alert And Notification System Reliability Sample (04/01/2017-03/31/2018)
71153Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports
The inspectors evaluated the following licensee event reports (LERs) which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
- (1) LER 05000458/2017-004-01, Loss of High Pressure Core Spray Safety Function During Surveillance Due to Malfunction of Test Return Valve on March 23, 2017.
The inspectors reviewed the updated LER submittal and did not identify any additional performance deficiencies. The previous LER submittal was reviewed in Inspection Report 05000458/2017004.
- (2) LER 05000458/2018-001-00, Potential Loss of Safety Function of Control Building HVAC Due to Legacy Design Flaw on September 18, 2018.
The inspectors reviewed this LER and documented a licensee-identified violation.
- (3) LER 05000458/2018-004-00, Unanalyzed Condition Due to Inappropriate Protection from Tornado Generated Missiles on May 4, 2018
The inspectors reviewed this LER and did not identify any performance deficiencies.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 92702Follow-up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, and Alternative Dispute Resolution Confirmatory Orders The inspectors reviewed the licensees response to Notice of Violation 05000458/2017009-01 and determined that the reason, corrective actions taken and planned to address recurrence, and the date when full compliance will be achieved for this violation are adequately addressed and captured on the docket.
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71153 - Follow-up of Events and Notices of Enforcement Discretion This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2.a of the NRC Enforcement Policy.
Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, that measures shall be established to assure that the design basis for those structures, systems, and components to which Appendix B applies is correctly translated into specifications, drawings, procedures, and instructions. The design basis for the control building air conditioning system, as specified in the updated safety analysis report, requires that the system be capable of performing its safety function in the event of a single failure in any component.
Contrary to the above, the licensee failed to assure that the design basis was correctly translated into specifications for the control building air conditioning system. Specifically, while reviewing the control logic for the control building air conditioning system, the licensee discovered that the control logic was designed such that a single failure in a component in the control logic could have prevented the system from performing its specified safety function.
Significance/Severity Level: The inspectors determined that the finding was of very low safety significance (Green) because it did not represent an actual loss of function of at least a single train for greater than its technical specification outage time and it did not represent an actual loss of function of one or more non-technical specification trains of equipment designated as high safety significance in accordance with the licensees Maintenance Rule program for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Corrective Action Reference(s): CR-RBS-2018-02211
EXIT MEETINGS AND DEBRIEFS
On May 21, 2018, the inspectors discussed the proposed biennial exercise scenario with Ms. D. Bordelon, Branch Chief, Technological Hazards Branch, FEMA Region VI.
On May 22, 2018, the inspectors discussed the proposed biennial exercise scenario with Mr. R. Leasure, Manager, Emergency Preparedness, and other members of the licensee staff.
On May 28, 2018, the inspectors discussed the biennial emergency plan exercise conducted June 27, 2018, with Ms. D. Bordelon, Branch Chief, Technological Hazards Branch, FEMA Region VI.
On July 11, 2018, the inspectors presented the emergency preparedness exercise inspection results to W. Maguire, Site Vice President, and other members of the licensee staff.
On September 14, 2018, the inspectors presented the evaluations of changes, tests and experiments inspection results to Mr. J. Reynolds, Director, Regulatory and Performance Improvement and other members of the licensee staff.
On September 26, 2018, the inspectors presented the licensed operator requalification inspection results to Steve Vercelli, General Manager, Plant Operations.
On October 18, 2018, the inspectors presented the quarterly resident inspector inspection results to Mr. W. Maguire, Site Vice President, and other members of the licensee staff.
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
DOCUMENTS REVIEWED
71111.01Adverse Weather Protection
Calculations/Specifications
Number
Title
Revision/Date
8.3.1.32
Design Basis Flood - River Bend Station (West
Creek and Grants Bayou)
8.3.1.34
PMP in Site Area (Assuming no Berm Around
Excavation)
8.3.1.37
Determination of Water Surface Elevations in
Grants Bayou and West Creek Near Plant Site for
CF8503290006
Peelle Design Calculation for Pressuretight and
Watertight Doors
March 15, 1985
CI8412200004
Calculations Design & Stress Analysis for
Watertight & Pressuretight Doors
December 17, 1984
Specification for Missile Protected Doors
Specification for Pressuretight Doors, Watertight
Doors, and Special Doors
Specification for Pressuretight and Watertight Doors 1
71111.04Equipment Alignment
Condition Reports (CR-RBS-)
2012-00092
2017-05633
2018-00108
2018-00402
2018-01330
2018-02069
2018-02927
2018-02956
2018-03099
2018-03687
Procedures
Number
Title
Revision
Corrective Action Program
SOP-0028
SOP-0031
Residual Heat Removal System
338
SOP-0035
Reactor Core Isolation Cooling System
055
71111.05Fire Protection
Calculation
Number
Title
Revision
G13.18.12.2-022
River Bend Station Combustible Loading
005
Procedures
Number
Title
Revision
AB-070-502
RHR Pump A Room Fire Area AB-5
AB-070-503
RCIC Pump Room Fire Area AB-4/Z-1 and Z-2
AB-070-504
RHR Pump C Room Fire Area AB-4/Z-1 and Z-2
RB-141-008
SLC Area Fire Area RC-4/Z-4
71111.06Flood Protection Measures
Calculations
Number
Title
Revision
PN-314
Moderate Energy Line Crack Flow Rates
PN-317
Max Flood Elevations for Moderate Energy Line
Cracks in Cat I Structures
71111.07Heat Sink Performance
Calculations
Number
Title
Revision
G13.18.2.0*031
Minimum RHR Heat Exchanger Performance
Evaluation
000
G13.18.14.0*164
Permissible Tube Blockage of RHR Heat Exchanger 000
Condition Reports (CR-RBS-)
2017-03099
2017-03109
2018-00106
2018-01330
2018-02927
Procedures
Number
Title
Revision
Heat Exchanger Performance and Condition
Monitoring
010
Procedures
Number
Title
Revision
SEP-HX-RBS-002
Performance Monitoring Program for the Residual
Heat Removal Heat Exchangers E12-EB001B and
E12-EB001D
006
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
Condition Reports (CR-RBS-)
2016-00111
2016-02615
2016-06433
2017-02896
2017-04305
2018-00928
2018-02336
2018-02337
Miscellaneous
Number
Title
Date
N/A
Individual Remediation Training/Evaluation
May 25, 2017
N/A
Crew Remediation Training/Evaluation
June 29, 2017
N/A
Individual Remediation Training/Evaluation
May 18, 2018
N/A
Individual Remediation Training/Evaluation
June 6, 2018
N/A
Individual Remediation Training/Evaluation
September 14, 2017
N/A
Individual Remediation Training/Evaluation
March 30, 2018
N/A
Individual Remediation Training/Evaluation
April 18, 2018
N/A
Individual Remediation Training/Evaluation
June 6, 2018
N/A
Individual Remediation Training/Evaluation
March 2, 2018
N/A
Individual Remediation Training/Evaluation
March 14, 2018
N/A
Individual Remediation Training/Evaluation
May 9, 2017
OLTS Report 9
Active Operators Count - RBS
August 28, 2018
OLTS Report 14
License Restrictions Report - RBS
August 28, 2018
N/A
2017 Annual Operating Tests
N/A
N/A
2016 Annual Operating Tests
N/A
N/A
2018 Biennial Written Examinations
N/A
Procedures
Number
Title
Revision
1063.008
Operations Training Sequence
Fitness for Duty Program
Procedures
Number
Title
Revision
Medical Program
Conduct of Operations
25
Medical Program
Licensed Operator Requalification Training Program
Description
Training Oversight Program
Simulator Configuration Control
Conduct of Simulator Training and Evaluations
Conduct of Simulator Training
Examination Security
Emergency Operating Procedure - RPV
28
Emergency Operating Procedure - Primary
Containment
017
Emergency Operating Procedure - Secondary
Containment and Radioactive Release Control
018
TQF-201-IM05
Remedial Training Plan
71111.12Maintenance Effectiveness
Condition Reports (CR-RBS-)
2017-01980
2017-02107
2017-02470
2017-03761
2017-03976
2017-05002
2017-05033
2017-05214
2018-00398
2018-00402
2018-01022
2018-02927
2018-03099
2018-03109
Procedures
Number
Title
Revision
Equipment Database (EDB) Process and Controls
Maintenance Rule Scope and Basis
Maintenance Rule Monitoring
Maintenance Rule (A)(1) Process
Planning
Procedures
Number
Title
Revision
SOP-0031
Residual Heat Removal System (Sys #204)
338
71111.13Maintenance Risk Assessments and Emergent Work Control
Condition Reports (CR-RBS-)
2018-03715
2018-04124
Procedures
Number
Title
Revision
ADM-0096
Risk Management Program Implementation and
On-Line Maintenance Risk Assessment
27
On Line Risk Assessment
016
71111.15Operability Determinations and Functionality Assessments
Condition Reports (CR-RBS-)
2018-02828
2018-04024
2018-04458
Procedures
Number
Title
Revision
Operability Determination Process
SOP-0059
Containment HVAC System
STP-109-6802
MSIV Cold Shutdown Full Stroke Operability Test
71111.17TEvaluations of Changes, Tests and Experiments
Calculations
Number
Title
Revision
G13.18.10.1-020
Evaluation of Reactor Water Cleanup Regenerative
Heat Exchangers for the Addition of Permanent
Shielding
Calculations
Number
Title
Revision
G13.18.10.1-021
Evaluation of Reactor Water Cleanup Non-
Regenerative Heat Exchangers for the Addition of
Permanent Shielding
IA-SWP*9
Setpoint Calculation for Bistables Standby Service
Water ESX164, ESY164, ESX167, and ESY167
Standby Cooling Tower Hi-Low Level Alarm &
Minimum Water
004
Standby Cooling Tower Performance and
Evaporation Losses Without Drywell Unit Coolers
Condition Reports (CR-RBS-)
2013-00457
2014-03977
2014-06284
2015-02190
2015-03951
2015-08410
2016-02888
2016-04095
2016-04391
2016-05997
2016-06165
2016-06393
2017-00836
2017-01253
2017-01807
2017-02330
2017-03505
2017-05572
2017-06417
2017-06428
2017-06466
2017-07080
2017-07497
2018-00613
2018-00633
2018-02207
2018-03515
2018-03621
Miscellaneous
Number
Title
Revision/Date
Nineteenth Fuel Cycle Core Operating Limits
Report
River Bend Station Core Operating Limits Report
Cycle 19
River Bend Station Core Operating Limits Report
Cycle 19
Twentieth Fuel Cycle Core Operating Limits Report
(COLR)
River Bend Station Core Operating Limits Report
Cycle 20
River Bend Station Core Operating Limits Report
Cycle 20
Task Qualification Matrix - F-ADM-5059 Evaluator
50.59 Evaluator Qualification
August 2, 2018
Miscellaneous
Number
Title
Revision/Date
Task Qualification Matrix - F-ADM-Screener PAD
Screener
August 2, 2018
Task Qualification Matrix - F-ADM-5059 Evaluator
50.59 Evaluator Qualification
August 9, 2018
Task Qualification Matrix - F-ADM-Screener PAD
Screener
August 9, 2018
RLO-2017-00072
Self-Assessment for Upcoming 50.59 Changes,
Test, Experiments Inspection
July 10, 2018
RBG-47776
RBF1-17-0089
Revision 25 to the Updated Safety Analysis Report
River Bend Station - Unit 1, Docket No. 50-458, 72-
049, License No. NPF-47
July 28, 2017
Procedures
Number
Title
Revision
Process Applicability Determination
CFR 50.59 Evaluations
71111.19Post-Maintenance Testing
Condition Reports (CR-RBS-)
2017-03761
2018-01022
2018-03712
2018-03715
2018-03739
2018-03748
2018-03758
2018-03772
2018-03789
2018-04419
Procedures
Number
Title
Revision
Planning
MCP-4195
Calibration of the RCIC Turbine Speed Controls
STP-309-0202
Division II Diesel Generator Operability Test
331
Work Orders
00388750
00473240
00474866
00489058
00499410
00505226
2729764
71111.22Surveillance Testing
Procedures
Number
Title
Revision
STP-000-6617
Check Valves Tested per ASME XI Inservice Testing
by Disassembly
STP-204-6303
Div I RHR Quarterly Valve Operability Test
STP-207-4537
RCIC Isolation - RCIC Steam Line Flow High
Channel Functional Test
2
Work Orders
2817537
2817540
2824009
2824164
2825270
71114.01Exercise Evaluation
Condition Reports (CR-RBS-)
2018-03659
2018-03665
2018-03669
2018-03670
2018-03791
2018-03793
Miscellaneous
Number
Title
Date
Evaluation Report for the Exercise conducted
October 25, 2016
November 23, 2016
Evaluation Report for the Exercise conducted
November 14, 2017
November 14, 2017
Evaluation Report for the Exercise conducted
March 13, 2018
April 12, 2018
Evaluation Report for the Exercise conducted
April 24, 2018
May 24, 2018
Procedures
Number
Title
Revision
River Bend Station Emergency Plan
EIP-2-001
Classification of Emergencies
26, 27
EIP-2-002
Classification Actions
EIP-2-006
Notifications
43, 44
EIP-2-007
Protective Action Recommendation Guidelines
Procedures
Number
Title
Revision
EIP-2-016
Operations Support Center
29, 30
EIP-2-018
36, 37, 38
EIP-2-020
38, 39
Technical Support Center Operations
Operations Support Center Operations
Work Orders
2018-142-47
2018-142-48
2018-142-50
2018-142-51
2018-142-53
2018-142-54
2018-142-58
2018-142-60
2018-142-63
2018-142-66
2018-142-85
71114.04Emergency Plan and Emergency Action Level Changes
No additional documents were reviewed.
71114.06Drill Evaluation
Condition Reports (CR-RBS-)
2018-03659
2018-03660
2018-03666
2018-03683
2018-03791
2018-03870
2018-05221
71114.08Exercise Evaluation, Scenario Review
No additional documents were reviewed.
71151Performance Indicator Verification
Condition Reports (CR-RBS-)
2017-06728
2018-03659
2018-03666
2018-03683
Procedures
Number
Title
Revision
Regulatory Performance Indicator Process
& 12
EPP-2-701
Prompt Notification System Maintenance and
Testing
Regulatory Assessment Performance Indicator
Guideline
Work Orders
2757383 01
2809147 01
71153Follow-up of Events and Notices of Enforcement Discretion
Condition Reports(CR-RBS-)
2017-02790
2018-02687
2018-02768
2018-02775
2702Follow-up on Traditional Enforcement Actions Including Violations, Deviations,
Confirmatory Action Letters, Confirmatory Orders, and Alternative Dispute Resolution
Confirmatory Orders
Miscellaneous
Number
Title
Date
RBG-47771
RBF1-17-0080
Reply to Notice of Violation 05000458/2017-009-01;
River Bend Station - Unit 1
Docket No. 50-458
License No. NPF-47
July 6, 2017
RBG-47823
Request for Review and Approval of Relocation of
the Reactor Core Isolation Cooling (RCIC) Injection
Point from the Reactor Vessel Head Spray Nozzle
to the A Feedwater Line via the A Residual Heat
Removal (RHR) Shutdown Cooling Return Line
River Bend Station - Unit 1
Docket No. 50-458
License No. NPF-47
January 29, 2018
SUNSI Review:
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By: DLP
Yes No
Publicly Available
Sensitive
OFFICE
ASRI:DRP/C
RI:DRP/C
SPE:DRP/C
C:DRS/EB1
C:DRS/EB2
C:DRS/OB
NAME
CSpeer
BParks
DProulx
TFarnholtz
GWerner
VGaddy
SIGNATURE
BP
DLP
TRF
GEW
Vgg
DATE
10/31/18
10/31/18
10/29/18
10/29/2018
10/29/2018
10/30/18
OFFICE
C:DRS/PSB2
TL:IPAT
BC:DRP/C
NAME
HGepford
GMiller
JKozal
SIGNATURE
hjg
gbm
DLP
DATE
10/29/18
10/31/18
11/8/18