ML20315A368
| ML20315A368 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/10/2020 |
| From: | Erin Carfang Reactor Projects Branch 1 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Carfang E | |
| References | |
| IR 2020003 | |
| Download: ML20315A368 (17) | |
See also: IR 05000244/2020003
Text
November 10, 2020
Mr. Bryan C. Hanson
Senior Vice President
Exelon Generation Company, LLC
President and Chief Nuclear Officer
Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT:
R. E. GINNA NUCLEAR POWER PLANT, LLC - INTEGRATED INSPECTION
REPORT 05000244/2020003
Dear Mr. Hanson:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an
inspection at R. E. Ginna Nuclear Power Plant, LLC. On October 16, 2020, the NRC inspectors
discussed the results of this inspection with Mr. Paul Swift, Site Vice President and other
members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
OFFICE R1/DRP
R1/DRP
R1/DRP
NAME
Jschussler/via email
CLally/via email
ECarfang/via email
DATE
11/09/2020
11/09/2020
11/10/2020
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000244
License Number:
Report Number:
Enterprise Identifier: I-2020-003-0041
Licensee:
Exelon Generation Company, LLC
Facility:
R. E. Ginna Nuclear Power Plant, LLC
Location:
Ontario, New York
Inspection Dates:
July 1, 2020 to September 30, 2020
Inspectors:
J. Schussler, Senior Resident Inspector
S. Monarque, Resident Inspector
J. DeBoer, Reactor Inspector
S. Elkhiamy, Operations Engineer
J. Rady, Emergency Preparedness Inspector
J. Schoppy, Senior Reactor Inspector
S. Shaffer, Senior Health Physicist
Approved By:
Erin E. Carfang, Chief
Reactor Projects Branch 1
Division of Reactor Projects
2
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.
3
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
4
(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) (4 Samples)
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
5
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
6
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) (28 Samples)
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
7
(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) (4 Samples)
(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
8
(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.: 19-65, EP-AA-1000, Exelon Nuclear Standardized
Radiological Emergency Plan, Revision 32
Evaluation No.: 19-84, EP-AA-1000, Exelon Nuclear Standardized
Radiological Emergency Plan, Revision 33
Evaluation No.: 19-89, EP-AA-1012, Exelon Nuclear Radiological Emergency
Plan Annex for Ginna Station, Revision 8
Evaluation No.: 19-90, EP-AA-1012, Addendum 1, Rev 1, R. E. Ginna Nuclear
Power Plant On-Shift Staffing Technical Basis, Revision 1
9
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, 2020
RADIATION SAFETY
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01) (2 Samples)
(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
10
(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, 2019
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 Sample)
(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
11
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, 2020
INSPECTION RESULTS
Observation: 'B' Control room emergency air treatment system filter failure
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
12
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.
13
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
STP-O-30.8
Service Water System Valve Position Verification
Revision 002
Corrective Action
Documents
Resulting from
Inspection
Corrosion at Threaded Fitting downstream of Diesel Generator
Preaction System S13 Isolation Valve V-5230
09/28/2020
Corrosion at Threaded Fitting Upstream of 5216K
09/28/2020
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
EDG "B" Jacket Water Heat Exchanger Inspection Report
11/26/2018
Corrective Action
Documents
AOV4270 and AOV 4272 did not close during testing
05/05/2020
SAC trip on Motor Overload
05/20/2020
Corrective Action
Documents
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
50.59 Self Assessment Screen not Performed within 90 days
07/24/2017
AD-AA-101-F-01 not filled correctly
09/27/2017
Follow up actions from 50.59 inspection
09/29/2017
'A' Auxiliary feed water pump motor high temp during test
01/10/2018
Entered ER-SC.3 due to screenhouse level lowering 6 inches
01/27/2019
NRC identified 50.59 screen/eval not performed for 738A OP
03/06/2019
Pipe blockage upstream of 4516
06/03/2020
Corrective Action
Documents
Resulting from
Inspection
NRC 50.59 Inspection non-conformance not entered into CAP
09/17/2020
NRC 50.59 Inspection lack design control for CETS
09/17/20
Procedures
Exelon 50.59 Resource Manual
Revision 14
Corrective Action
Documents
Resulting from
Inspection
WO C93690133 field copy data not transferred to Master
07/30/2020
NRC Identified - Fuel Oil Weepage found on KDG08
08/20/2020
14
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
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
Corrective Action
Documents
Siren 82 indicated a communication issue on evening poll
10/07/2018
Siren 18 indicated a no response during evening poll
02/13/2020
Miscellaneous
Design Report
R. E. Ginna Nuclear Power Station Site-Specific Offsite
February 26,
15
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiological Emergency Preparedness Alert and Notification
System Quality Assurance
1986
Miscellaneous
Exelon Nuclear Standardized Radiological Emergency Plan
Revision 33
Exelon Nuclear Radiological Emergency Plan Annex for Ginna
Station
Revision 8
Addendum 1
R. E. Ginna Nuclear Power Plant On-Shift Staffing Technical
Basis
Revision 1
Miscellaneous
10 CFR 50.54(q) Change Evaluation
Revision 10
Corrective Action
Documents
150 foot wind direction weather vane damaged
01/28/2019
OCCRP computer sign on = 12 minutes impact
05/14/2019
Corrective Action
Documents
Resulting from
Inspection
NRC EP program inspection - EP equipment removed from
either procedure
07/29/2020
Miscellaneous
EP-AA-121-F-12
Ginna Equipment Matrix
Revision 1