IR 05000244/2020003

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R. E. Ginna Nuclear Power Plant, LLC: Reissued Integrated Inspection Report 05000244/2020003
ML21103A416
Person / Time
Site: Ginna 
Issue date: 04/15/2021
From: Erin Carfang
NRC Region 1
To: Rhoades D
Exelon Generation Co
References
IR 2020003
Download: ML21103A416 (18)


Text

April 15, 2021

SUBJECT:

R. E. GINNA NUCLEAR POWER PLANT, LLC - REISSUED INTEGRATED INSPECTION REPORT 05000244/2020003

Dear Mr. Rhoades:

The U.S. Nuclear Regulatory Commission (NRC) identified one factual error in NRC Integrated Inspection Report 05000244/2020003, dated November 10, 2020 (ADAMS Accession No.

ML20315A368). The Radiation Safety section did not document the completion of inspection procedures 71124.01 and 71124.03 including associated samples, which were performed by NRC inspectors during the inspection period. As a result, the NRC has reissued the report in its entirety to correct the error.

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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, X /RA/

Signed by: Erin E. Carfang

Erin E. Carfang, Chief Reactor Projects Branch 1 Division of Reactor Projects

Docket No. 05000244 License No. DPR-18

Enclosure:

As stated

cc w/ encl: Distribution via LISTSERV

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at R. E. Ginna Nuclear Power Plant, LLC, 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.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Ginna began the inspection period at 100 percent power. The unit remained at, or near, 100 percent 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 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted. As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (1 Sample)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1)

'B' service water system alignment following scheduled surveillance testing September 29, 2020

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Turbine building main feedwater pump room on July 23, 2020
(2) Control room air handling room on August 6, 2020
(3) Walkdown of fire piping systems S13, S24, S12, S24, and S38 on September 24, 2020
(4) Technical support center on September 25, 2020

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections of:

(1) Door gaskets to 'B' battery and 'B' emergency diesel generator rooms on July 22, 2020

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Residual heat recovery 'B' heat exchanger on August 21, 2020

===71111.07T - Heat Sink Performance

Triennial Review (IP Section 03.02)===

The inspectors evaluated heat exchanger/sink performance on the following on August 21, 2020:

(1)

'B' emergency diesel generator lube oil cooler heat exchanger, cooled by service water (2)

'B' emergency diesel generator jacket water heat exchanger, cooled by service water (3)

'B' spent fuel pool heat exchanger, cooled by service water (4)

'B' containment recirculating fan cooler heat exchanger, cooled by service water

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance and procedure use and adherence in the main control room following an eight inch fire water pipe fitting failure that caused water to partly fill the condenser pit on September 3, 2020 and observed reactor power reduction for a planned turbine driven auxiliary feedwater surveillance and test performance on September 22, 2020

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the simulator during licensed operator re-qualification training on September 3, 2020.

The training involved a scenario that contained, but was not limited to, a chemical volume control system leak in the reactor coolant letdown line, a loss of one offsite circuit, a steam generator tube leak, and safety injection pump failures.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

(1)

'D' standby auxiliary feedwater system on August 7, 2020

(2) Alternating current and direct current distribution system, breaker 52/MMC1G1 failure to transfer bus 18 480v loads to safety related equipment, maintenance rule action plan on August 14, 2020
(3) Service air compressor system 11/12, maintenance rule action plan on September 28, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (8 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Elevated risk, (yellow), during planned maintenance of 'B' emergency diesel generator air roll and replacement of 'B' battery room door gasket on July 1, 2020
(2) Elevated risk, (yellow), during planned maintenance of service air compressor, dryer, and relief valves on July 6, 2020
(3) Elevated risk, (yellow), during planned maintenance of 'C' standby auxiliary feedwater pump system on August 11, 2020
(4) Elevated risk, (yellow), during planned quarterly testing of 'A' residual heat removal pump on September 1, 2020
(5) Elevated risk, (green), during unplanned maintenance of 'B' motor driven auxiliary feedwater lube oil cooler service water system flush on September 14, 2020
(6) Elevated risk, (green), during unplanned maintenance of turbine driven auxiliary feedwater steam admission line visual inspection for pipe integrity on September 25, 2020
(7) Elevated risk, (green), during unplanned maintenance of fire system S04 pipe failure and associated replacement on September 25, 2020
(8) Elevated risk, (action green), during planned maintenance of the 'B' control room emergency air treatment system cooling system on September 28, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) OPEVAL-20-004 microprocessor rod position indication subsystem 1 DC power supply failure PS2 on August 20, 2020 (2)

'A' steam generator level transmitter 461 instrument deviation on August 24, 2020

(3) Service water hanger SWU-164 loose turnbuckle on September 22, 2020

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from September 14 through September 18, 2020.

(1) A-2018-007, P-15.54, Diesel air compressor procedure to start, stop, ensure correct configuration control and monitor the compressors, dated February 1, 2018
(2) A-2018-049, Increase the residual heat removal pump motor bearing oil temperature operating temperature range, dated September 12, 2018
(3) A-2018-051, Raise spent fuel pool pump/motor temperature limits, dated September 19, 2018
(4) A-2018-069, Revise acceptance criteria of alternate reactor coolant system injection system flow test, dated December 14, 2018
(5) A-2019-048, Low screenhouse water level, dated July 29, 2019
(6) A-2019-064, Technical specification basis change to clarify allowed duration of emergency diesel generator operation while parallel to the grid, dated October 22,2019
(7) A-2020-074, Allow reactor coolant system loop fill with refueling water purification pump, dated April 17, 2020
(8) B-2017-049, NFPA 805 Modification to reduce likelihood of spurious actuation of standby auxiliary feedwater valves, dated March 23, 2018
(9) B-2018-002, Auxiliary building high energy line break requirements, dated January 23, 2018
(10) B-2018-005, Tornado missile protection structural barriers, dated February 14, 2018
(11) B-2018-020, Guidance for withdrawal rates after prolonged 'D' bank insertion in R.E. Ginna Cycle 40, dated April 20, 2018
(12) B-2018-052, Equivalent change to allow use of either element of dual element RTD TE-410A for reactor coolant loop 'B' leg temperature, dated October 17, 2018
(13) B-2018-053, Manipulator crane overload/underload setpoints increase to +/- 200lbs, dated October 22, 2018
(14) B-2018-055, Permanent scaffolds inside containment for temporary lead shielding, dated October 24, 2018
(15) B-2019-007, TSB change to revise B 3.8.9 and B 3.8.10 for minimum DC system voltage to be 129 VDC, dated February 26, 2019
(16) B-2019-009, MSSV setpoint tolerance change, dated March 11, 2020
(17) B-2019-014, Turbine driven auxiliary feedwater instrumentation upgrade, dated June 26, 2019
(18) B-2019-015, Newly identified SSCs in scope of license renewal, section 18.1.3 update, dated April 3, 2019
(19) B-2019-040, Permanently maintain the open phase in an alarm only configuration in accordance with Revision 3 of the NEI Voluntary Industry Initiative, dated December 12, 2019
(20) B-2020-007, Design change to resolve resonant condition on turbine driven auxiliary feedwater pump turbine, dated May 11, 2020
(21) B-2020-013, Disconnect pressurizer heater 28, dated May 10, 2020
(22) B-2020-0014, Swap F12 and H13 CET trains, dated May 10, 2020
(23) B-2020-0015, PCTCC to defeat the zirconium guide tube trip function in PT-34.0, dated May 8, 2020
(24) C-2017-004, Change valve 9080 from normal closed to normal open, dated December 1, 2017
(25) C-2018-001, Retire AVT area radiation monitors R-23, R-24, R-25, R27 and R-28, dated May 17, 2018
(26) C-2018-002, Remove all remaining intake heaters from the intake structure, dated June 21, 2018
(27) C-2018-004, AMSAC Actuation Logic (STP-O-R-21 Test interval Extension - Technical Requirements Manual change: TSR 3.4.3.6 change required frequency from 18 months to 36 months, dated October 19, 2018
(28) C-2019-001, Compensatory measure to tagout 738A switch and allow local operation only, dated March 18, 2019

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:

(1) Inservice test for residual heat removal suction valves, motor operated valve 851, following planned maintenance on July 7, 2020
(2) Operational testing of the service air compressor, dryer, and relief valves, following planned maintenance on July 16, 2020 (3)

'C' standby auxiliary feedwater pump, comprehensive test, valve and modification, following planned maintenance on July 16, 2020

(4) NFPA 805 diesel generator operational test, following planned maintenance on August 26, 2020
(5) Standby auxiliary feed water pump diesel generator operational test, following planned maintenance on August 27, 2020
(6) Operational testing of the instrument air compressor and relief valve, following planned maintenance on September 8, 2020

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) STP-O-36Q-D, 'D' standby auxiliary feedwater pump quarterly test on July 28, 2020
(2) STP-O-12.2, 'B' emergency diesel generator monthly test on August 28, 2020
(3) STP-O-R-20, 'B' emergency diesel generator auto start undervoltage logic test on September 30, 2020
(4) STP-O-16QT, auxiliary feedwater turbine driven pump quarterly test on September 30, 2020

Inservice Testing (IP Section 03.01) (1 Sample)

(1) STP-O-3-COMP-B, 'B' containment spray pump comprehensive test on September 15, 2020

FLEX Testing (IP Section 03.02) (1 Sample)

(1) STP-O-40.1C, beyond design basis flex pump PBD01C periodic test on September 10, 2020

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.01-02.04) (1 Sample)

(1) The inspectors evaluated Exelon's maintenance and testing of the Ginna alert and notification system on July 27-30, 2020, for the period of July 2018 through June 2020

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of Exelon's Emergency Preparedness Organization on July 27-30, 2020

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes onsite on July 27-30, 2020. The NRC notes that this evaluation does not constitute NRC approval.
  • Evaluation No.: 19-90, EP-AA-1012, Addendum 1, Revision 1, R. E. Ginna Nuclear Power Plant On-Shift Staffing Technical Basis, Revision 1

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program on July 27-30, 2020, for the period of July 2018 through June 2020

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated an emergency drill in the simulator control room and emergency offsite facility involving an Alert, Site Area Emergency, and General Emergency declaration due to a scenario which contained, but was not limited to, a loss of reactor vessel inventory affecting fuel clad with containment challenged on July 14, 2020

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated a simulator drill involving an Unusual Event, Alert, Site Area Emergency, and General Emergency declaration due to a scenario which contained, but as not limited to, a loss of coolant accident and a loss of reactor coolant system barrier with a potential containment barrier on August 25,

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated radiological protection-related instructions to plant workers

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

(1) The inspectors observed personnel monitoring and the monitoring of tools, materials, and equipment at the main access control point
(2) The inspectors observed contamination control practices for 'B' residual heat removal heat exchanger maintenance

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

(1) The inspectors observed auxiliary building ventilation high-efficiency particulate air filter testing
(2) The inspectors observed release surveys of equipment being removed from the radiological controlled area
(3) The inspectors observed the storage conditions and labeling of contaminated equipment stored in the contaminated storage building

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)

(1) The inspectors examined all accessible high radiation and locked high radiation areas in the auxiliary building
(2) The inspectors examined all accessible high radiation and locked high radiation areas in the intermediate building

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated the auxiliary building ventilation system and observed the filter efficiency testing for the auxiliary building ventilation system filters.

Temporary Ventilation Systems (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the temporary ventilation system installed for the independent spent fuel storage installation campaign.

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &

Transportation

Radioactive Material Storage (IP Section 03.01)

(1) Inspectors evaluated the licensees performance in controlling, labeling and securing radioactive materials in the radioactive waste yard east
(2) Inspectors evaluated the licensees performance in controlling, labelling and securing radioactive materials in the steam generator mausoleum

Radioactive Waste System Walkdown (IP Section 03.02 (2 Samples)

(1) Inspectors walked down accessible portions of the solid radioactive waste handling system and evaluated system configuration and functionality
(2) Inspectors walked down accessible portions of the liquid radioactive waste systems and evaluated system configuration and functionality

Waste Characterization and Classification (IP Section 03.03) (2 Samples)

(1) The inspectors evaluated the licensees characterization and classification of radioactive waste in spent resin sample identification number 2019-227SA analyzed on October 15, 2019
(2) The inspectors evaluated the licensees characterization and classification of radioactive waste in dry active waste sample identification number 2018-189SA analyzed on December 11, 2018

Shipment Preparation (IP Section 03.04) (1 Sample)

(1) The inspectors reviewed the records for shipment packaging, surveying, labeling, placarding, vehicle surveys, emergency instructions, manifests, and shipping papers provided to the driver

Shipping Records (IP Section 03.05) (4 Samples)

The inspectors evaluated the following non-excepted radioactive material shipments through a record review:

(1) The inspectors reviewed the shipping records for shipment 2018-054 shipped on August 23, 2018
(2) The inspectors reviewed the shipping records for shipment 2018-092 shipped on November 9, 2018
(3) The inspectors reviewed the shipping records for shipment 2019-020 shipped on March 25, 2019
(4) The inspectors reviewed the shipping records for shipment 2019-049 shipped on July 31,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

EP01: Drill/Exercise Performance (IP Section 02.12)===

(1) Submitted data from April 1, 2019 - March 31, 2020

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

(1) Submitted data from April 1, 2019 - March 31, 2020

EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) Submitted data from April 1, 2019 - March 31, 2020

MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)

(1) Submitted data from July 1, 2019 - June 30, 2020

MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)

(1) Submitted data from July 1, 2019 - June 30, 2020

MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)

(1) Submitted data from July 1, 2019 - June 30, 2020

MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)

(1) Submitted data from July 1, 2019 - June 30, 2020

MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)

(1) Submitted data from July 1, 2019 - June 30, 2020

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) The inspectors reviewed licensee submittals for the occupational radiological occurrences PI for the fourth quarter 2019 through the third quarter of 2020

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) The inspectors reviewed licensee submittals for the radiological effluent TS/ODCM radiological effluent occurrence PI for the fourth quarter 2019 through the third quarter of 2020

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Control room emergency air treatment system, IR 04351801, on September 10,

INSPECTION RESULTS

Observation: 'B' Control room emergency air treatment system filter failure 71152 The inspectors reviewed Exelons corrective action program evaluation, work orders, extent of condition reviews, and corrective actions associated with the B train of the control room emergency air treatment system charcoal filter efficiency failure. Exelon entered this issue into their corrective action program as IR 04351801, specifically the charcoal filter efficiency results for the B train of the control room emergency air treatment system were below the Technical Specification 3.7.9 surveillance requirements, detailed in section 5.5.10. The inspectors assessed Exelons problem identification threshold, causal analysis, prioritization, and timeliness of corrective actions to determine whether Exelon had taken timely and appropriate corrective actions.

The inspectors observed that Exelon performed a thorough review of the issue and determined the cause of the sample efficiency failure to meet the acceptance criteria was due to contamination of the sample. Exelons immediate corrective actions were to declare the system inoperable and enter the applicable technical specification action statement. Exelon completed evacuation of the existing charcoal and replaced the charcoal particulate with new material. Additional corrective actions are long term and appear to be appropriate and commensurate with the significance which include increased sample quantity and a review of the efficiency acceptance criteria.

Exelon also performed additional testing of the removed charcoal to aid in determining the failure cause. These samples were determined to meet acceptance criteria. Through the corrective action program evaluation document, Exelon concluded the removed charcoal would have met the efficiency requirements and the error was either contamination during testing or sample retrieval. Furthermore, Exelon notes specific conclusion of cause is unlikely because the samples are destroyed during the testing process.

The inspectors independently reviewed the testing data, requirements, and methodology. At the time of Exelons immediate correction actions, the inspectors observed the in-field activities to replace the charcoal particulate. During this time, the inspectors also observed how Exelon accomplished the sample retrieval process. Additionally, the inspectors reviewed work orders and efficiency trends dating back to 2007 to identify adverse trends. Lastly, the inspectors independently reviewed Exelons conclusion and technical basis that the efficiency of the removed charcoal would have met performance requirements outlined in the plants technical specification. The inspectors determined that Exelons actions in identifying and resolving the issue was appropriate and timely and commensurate with the safety significance. The inspectors independently evaluated the deficiencies noted above for significance in accordance with the guidance in IMC 0612, Appendix B, Issue Screening, and Appendix E, Examples of Minor Issues. The inspectors determined that none of the conditions were deficiencies of greater than minor significance and, therefore, are not subject to enforcement action in accordance with the NRCs Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On July 30, 2020, the inspectors presented the Emergency Preparedness Program inspection results to Mr. Paul Swift, Site Vice President and other members of the licensee staff.
  • On August 21, 2020, the inspectors presented the Triennial Heat Sink inspection results to Mr. Paul Swift, Site Vice President and other members of the licensee staff.
  • On September 18, 2020, the inspectors presented the Triennial 50.59 Team inspection results to Mr. Paul Swift, Site Vice President and other members of the licensee staff.
  • On October 16, 2020, the inspectors presented the integrated inspection results to Mr. Paul Swift, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Procedures

STP-O-30.8

Service Water System Valve Position Verification

Revision 002

71111.05

Corrective Action

Documents

Resulting from

Inspection

AR 04372590

Corrosion at Threaded Fitting downstream of Diesel Generator

Preaction System S13 Isolation Valve V-5230

09/28/2020

AR 04372603

Corrosion at Threaded Fitting Upstream of 5216K

09/28/2020

71111.06

Work Orders

C93709104

Perform Visual Inspection/Replacement - Door Neoprene

Gaskets (B Train)

06/29/2020

71111.07A Work Orders

C93690133

EAC02B Clean, Inspect, and Eddy Current Tube Side of Heat

Exchanger

03/25/2020

71111.07T Miscellaneous

ER-AA-340-1002

EDG "B" Jacket Water Heat Exchanger Inspection Report

11/26/2018

71111.12

Corrective Action

Documents

AR 04341255

AOV4270 and AOV 4272 did not close during testing

05/05/2020

AR 04344709

SAC trip on Motor Overload

05/20/2020

71111.15

Corrective Action

Documents

AR 04358711

A Steam Generator level Transmitter LT-461 deviation

07/24/2020

Work Orders

C93451228

Contingency Repair/Replace Steam Generator Level

Transmitter

07/24/2020

71111.17T Corrective Action

Documents

AR 04034735

50.59 Self Assessment Screen not Performed within 90 days

07/24/2017

AR 04056448

AD-AA-101-F-01 not filled correctly

09/27/2017

AR 04057261

Follow up actions from 50.59 inspection

09/29/2017

AR 04092244

'A' Auxiliary feed water pump motor high temp during test

01/10/2018

AR 04214360

Entered ER-SC.3 due to screenhouse level lowering 6 inches

01/27/2019

AR 04226929

NRC identified 50.59 screen/eval not performed for 738A OP

03/06/2019

AR 04347695

Pipe blockage upstream of 4516

06/03/2020

Corrective Action

Documents

Resulting from

Inspection

AR 04370151

NRC 50.59 Inspection non-conformance not entered into CAP

09/17/2020

IR 04370150

NRC 50.59 Inspection lack design control for CETS

09/17/20

Procedures

LS-AA-104-1000

Exelon 50.59 Resource Manual

Revision 14

71111.19

Corrective Action

Documents

Resulting from

Inspection

AR 0435999

WO C93690133 field copy data not transferred to Master

07/30/2020

AR 04364457

NRC Identified - Fuel Oil Weepage found on KDG08

08/20/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedures

STP-O-2.3.3

Inservice Test of RHR Suction Valves

Revision

00001

STP-O-36-

COMP-C

Standby Auxiliary Feedwater Pump C - Comprehensive Test

Revision 021

STP-O-40.4

SAFW Diesel Generator (KDG08) Run Test

Revision 012

STP-O-40.5

NFPA Diesel Generator (KDG09) Run Test

Revision 011

Work Orders

699555

Replace service air filter to demineralizer mixed bed resin

vessels (FSA02)

07/06/2020

C93665383

Stroke the following Valves 7001D, 7001I, 7001J, 7001P,

7001T, 7000D, 7000E, 7000F, 7000G

07/06/2020

C93686385

Replace Motor for 851B RHR Pump Suction Valve from

Containment Sump B

04/08/2020

C93708985

Perform Instrument Air Compressor CIA02C Maintenance

07/23/2020

C93710361

Service Air Compressor Receiver Relief Valves

7/6/2020

C93711063

Annual Preventive Maintenance for Service Air Compressor

Dryer (TSA01A and TSA01B)

07/06/2020

C93711915

Perform Service Air Dryer Annual or 4 Year Preventive

Maintenance

07/06/2020

C93714754

Annual Maintenance on Diesel Generator KDG09 650 Kw

Load Run

8/18/2020

C93714763

Annual Maintenance on SAFW DG KDG08 and 650 kw Load

Run

08/17/2020

C93747333

Perform Corrective Maintenance on SMB-00 Motor Operator

for OP/851B Pump Suction

4/8/2020

C93749868

Perform Repairs o OP/851B RHR Pump Suction Valve

Actuator and Control Circuitry

5/3/2020

C93750631

RV-8302 Swap Out with Pre-Tested Spare and Test Removed

Valve

07/24/2020

71111.22

Procedures

STP-O-36Q-D

Standby Auxiliary Feedwater Pump D - Quarterly

Revision 020

STP-O-R-20

Diesel Generator B - Auto Start Undervoltage Logic Test

Revision 007

71114.02

Corrective Action

Documents

AR 04180998

Siren 82 indicated a communication issue on evening poll

10/07/2018

AR 04317551

Siren 18 indicated a no response during evening poll

2/13/2020

Miscellaneous

Design Report

R. E. Ginna Nuclear Power Station Site-Specific Offsite

February 26,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Radiological Emergency Preparedness Alert and Notification

System Quality Assurance

1986

71114.03

Miscellaneous

EP-AA-1000

Exelon Nuclear Standardized Radiological Emergency Plan

Revision 33

EP-AA-1012

Exelon Nuclear Radiological Emergency Plan Annex for Ginna

Station

Revision 8

EP-AA-1012

Addendum 1

R. E. Ginna Nuclear Power Plant On-Shift Staffing Technical

Basis

Revision 1

71114.04

Miscellaneous

EP-AA-120-1001

CFR 50.54(q) Change Evaluation

Revision 10

71114.05

Corrective Action

Documents

AR 04214466

150 foot wind direction weather vane damaged

01/28/2019

AR 04248782

OCCRP computer sign on = 12 minutes impact

05/14/2019

Corrective Action

Documents

Resulting from

Inspection

AR 04359748

NRC EP program inspection - EP equipment removed from

either procedure

07/29/2020

Miscellaneous

EP-AA-121-F-12

Ginna Equipment Matrix

Revision 1