IR 05000244/2019004
| ML20037A118 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/05/2020 |
| From: | Erin Carfang Division Reactor Projects I |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2019004 | |
| Download: ML20037A118 (15) | |
Text
February 5, 2020
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT, LLC - INTEGRATED INSPECTION REPORT 05000244/2019004
Dear Mr. Hanson:
On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at R.E. Ginna Nuclear Power Plant, LLC. On January 28, 2020, the NRC inspectors discussed the results of this inspection with Mr. Daren Blankenship, Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance 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,
/RA/
Erin E. Carfang, Chief Reactor Projects Branch 1 Division of Reactor Projects
Docket No. 05000244 License No. DPR-18
Enclosure:
As stated
Inspection Report
Docket Number:
05000244
License Number:
Report Number:
Enterprise Identifier: I-2019-004-0034
Licensee:
Exelon Generation Company, LLC
Facility:
R.E. Ginna Nuclear Power Plant, LLC
Location:
Ontario, NY
Inspection Dates:
October 01, 2019 to December 31, 2019
Inspectors:
J. Schussler, Senior Resident Inspector
M. Montecalvo, Acting Resident Inspector
H. Anagnostopoulos, Senior Health Physicist
E. Andrews, Health Physicist
P. Cataldo, Senior Resident Inspector
E. Dipaolo, Senior Reactor Inspector
P. Ott, Operations Engineer
S. Shaffer, Senior Health Physicist
Approved By:
Erin E. Carfang, Chief
Reactor Projects Branch 1
Division of Reactor Projects
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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions on December 18, 2019
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
'A' emergency diesel generator system during 'B' emergency diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance test run on October 28, 2019 (2)
'A' auxiliary feedwater following 'B' auxiliary feedwater surveillance test on November 26, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1)
'A' spent fuel pool cooling, following 'A' spent fuel pool pump testing on November 19, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (4 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
(1)
'B' battery room on October 2 and 3, 2019
- (2) Relay room on November 17, 2019
- (3) Air handling room on December 15, 2019
- (4) Turbine building basement on December 15, 2019
71111.07A - Heat Sink Performance
Annual Review (IP Section 02.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1) 'A' emergency diesel generator lube oil and jacket water heat exchangers on December 13, 2019
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on November 22, 2019
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 in the main control room during a planned load reduction in preparation for a scheduled turbine driven auxiliary feedwater pump surveillance test on October 10, 2019 and a scheduled 'B' emergency diesel generator 24-hour surveillance test on October 28, 2019.
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 examinations on November 13, 2019. The examination involved a scenario that contained, but was not limited to, a loss off all offsite power circuits, pressurizer pressure transmitter failure, component cooling water pump failing to run, main steam isolation valves failing to isolate, safety injection trains failing to actuate, and a residual heat removal pump failing to start.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Main steam system (System 81) on December 4, 2019
Quality Control (IP Section 02.02) (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:
- (1) Commercial grade dedication and receipt inspection of an emergency diesel generator fitting, electrical diode, half inch relief valve, and an orifice plate on December 17, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Planned maintenance, elevated risk (yellow), flow calibration of AOV-111, on October 18, 2019
- (2) Planned maintenance, elevated risk (green), 7T offsite power circuit system outage window, on October 21, 2019
- (3) Planned maintenance, elevated risk (yellow), alternate reactor cooling system injection pump out of service on November 4, 2019
- (4) Planned maintenance, elevated risk (yellow), 'A' emergency diesel generator system outage window on November 13, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (6 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Pressure relief tank transmitter spikes on November 1, 2019 (2)
'B' battery room water intrusion on November 7, 2019 (3)
'A' motor driven auxiliary feedwater coupling elevated vibrations on November 8, 2019 (4)
'A' and 'B' emergency diesel generator common cause fuel fitting failure on November 8, 2019
- (5) Turbine driven auxiliary feedwater, hand controller HVC-487B failure on November 18, 2019
- (6) Emergency diesel generator transfer pump elevated vibrations, re-baseline pump on December 16, 2019
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)
'A' reactor vessel level indication system temporary modification, ECP-19-000414 on November 20, 2019 (2)
'B' battery room modification, water intrusion, ECP-19-000559 on December 2, 2019 (3)
'A' and 'B' emergency diesel generator sump modification, ECP-19-000479 on December 16, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Service water flow to 'B' motor driven auxiliary feedwater pump lube oil cooler unplanned corrective maintenance and follow up of deficiencies on October 4, 2019
- (2) Turbine driven auxiliary feedwater main control board hand controller HCV-487B replacement, unplanned maintenance on October 9, 2019
- (3) Service water AOV-4651 valve stroke time testing following planned maintenance on October 11, 2019
- (4) Alternate reactor coolant system injection portable pump following planned maintenance on October 22, 2019 (5)
'B' Service water pump comprehensive surveillance test following planned maintenance on November 5, 2019 (6)
'A' emergency diesel generator system outage window on November 15, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) STP-O-16QA, 'A' motor driven auxiliary feedwater on October 9, 2019
- (2) STP-O-16QT, turbine driven auxiliary feedwater on October 11, 2019
- (3) STP-O-12.2-24, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 'B' emergency diesel generator run on October 31, 2019
- (4) STP-O-36QD, 'D' standby auxiliary feedwater on November 1, 2019
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) STP-O-40.4, standby auxiliary feedwater diesel generator run test (30 percent load) and STP-O-40.10, alternate reactor cooling system injection pump flow test on November 6, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) The inspectors evaluated a simulator drill involving an Unusual Event and Alert declaration due to a loss of both offsite circuits and main steam isolation valves failing to close coincident with a steam line break in the plant on November 7,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walk Downs and Observations (IP Section 02.01) (1 Sample)
- (1) The inspectors walked down the gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design.
Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02) (1 Sample)
- (1) The inspectors evaluated the gaseous and liquid effluent monitor instrument calibration and testing.
Sampling and Analysis (IP Section 02.03) (1 Sample)
- (1) The inspectors reviewed:
1. Radioactive effluent sampling activities
2. Representative sampling requirements
3. Compensatory measures taken during effluent discharges with inoperable
effluent radiation monitoring instrumentation
4. The use of compensatory radioactive effluent sampling
5. The results of the inter-laboratory and intra-laboratory comparison program,
including scaling of hard-to-detect isotopes
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
- (1) The inspectors reviewed radioactive effluent discharge system surveillance test results and reviewed the methodology used to determine the radioactive effluent stack and vent flow rates based on Technical Specifications/Off Site Dose Calculation Manual acceptance criteria.
Dose Calculations (IP Section 02.05) (1 Sample)
- (1) The inspectors reviewed several liquid and gaseous discharge permits to evaluate public dose calculations (monthly, quarterly, and annual) and the annual radiological effluent release reports for 2017 and
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15)===
- (1) The inspectors reviewed licensee submittals for the occupational radiological occurrences PI for the fourth quarter 2018 through the third quarter of 2019.
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 2018 through the third quarter of 2019.
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue on December 19, 2019.
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) A main steam isolation valve failed to close as expected by main control room switch or pushbutton, Action Request
INSPECTION RESULTS
Observation: A Main Steam Isolation Valve Failed to Close as Expected by Main Control Room Switch or Pushbutton 71152 The inspectors performed an in-depth review of Exelons actions following the failure of the A Main Steam Isolation Valve (MSIV) to close following attempts using the Main Control Room hand switch (1/3517) and pushbutton (PB/LAFA) during a plant shutdown on June 16, 2019. A third attempt to close the valve using the hand switch successfully closed the valve. The inspectors reviewed the cause analysis, troubleshooting records, the corrective actions taken and planned, and the extent of condition. 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 Exelons work group evaluation for the issue provided a detailed evaluation of the event and thorough review of the associated equipment issues. The cause of the failure was determined to be a mechanically bound and galled hand switch, 1/3517, that prevented makeup of the switch contacts on the first attempt. The second, more forceful attempt successfully closed the MSIV. The failure to close the valve using the pushbutton (PB/LAFA) was determined to be due to the MSIVs air-operated valve open solenoids being energized. This was because the mechanically bound hand switch inadvertently traveled to the open position and engaged the MSIV open contacts when the operator manually returned the switch to the Auto position following the first attempt to close the MSIV. The inspectors verified that Exelon properly evaluated the issue, performed a thorough review of operating experience, and performed or planned appropriate corrective actions.
Observation: Semi-Annual Trend Review 71152 The inspectors reviewed Exelons corrective action program (CAP) for trends that might be indicative of a more significant safety issue on December 19, 2019. The inspectors evaluated a sample of issues and events that occurred over the course of the third and fourth quarters of 2019 to determine whether issues were appropriately considered as emerging or adverse trends. The inspectors verified that these issues were addressed within the scope of the CAP or through department review.
The evaluation did not reveal any new trends that could indicate a more significant safety issue. The inspectors determined that Exelon personnel were identifying trend issues at a low threshold, entered them into the CAP for resolution and had appropriately prioritized investigation reviews. The inspectors noted minor adverse trends identified by Exelon staff in the areas of the frequency of non-reportable spills, less than adequate use of human performance tools by workers, less than adequate preventative maintenance reviews in engineering, and increased frequency of spurious main control board alarms on the vital battery monitoring system.
Based on the overall results of the semi-annual trend review, the inspectors determined that Exelon had properly identified adverse trends at Ginna before they became more significant safety problems. 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 October 4, 2019, the inspectors presented the radioactive gaseous and liquid effluent treatment inspection results to E. John Fischer and other members of the licensee staff.
- On November 21, 2019, the inspectors presented the 'A' main steam isolation valve failed to close as expected by main control room switch or pushbutton inspection results to E. John Fischer and other members of the licensee staff.
- On January 28, 2020, the inspectors presented the integrated inspection results to Mr. Daren Blankenship, Plant Manager, and other members of the licensee staff.
THIRD PARTY REVIEWS
Inspectors reviewed the Institute on Nuclear Power Operations report that were issued during the inspection period.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.04Q Corrective Action
Documents
Resulting from
Inspection
04300096
71111.05Q Corrective Action
Documents
Resulting from
Inspection
284753
Procedures
STP-O-13.4.33
Station Halon System Bottle Weighing and S08 (Relay
Room and Computer Room) Air Flow Test
Revision 006
Corrective Action
Documents
4068566
4190080
207454
21143
Corrective Action
Documents
Resulting from
Inspection
284419
04301459
Miscellaneous
Main Steam (System 81) Maintenance Rule System Basis
Document
19-09
Maintenance Rule Expert Panel Meeting
07/15/2019
19-10
Maintenance Rule Expert Panel Meeting Minutes
07/22/2019
Corrective Action
Documents
281616
282792
Corrective Action
Documents
Resulting from
Inspection
286955
Engineering
Evaluations
ECP-16-000669,
Technical
Evaluation
Revision
0000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
relating to 'B'
Battery Room
ESR-19-0196,
Technical
Evaluation
relating to 'B'
Battery Room
ESR-19-0220, 'A'
EDG common
cause failure
evaluation based
on 'B' EDG
cracked nipple
Corrective Action
Documents
263604
Corrective Action
Documents
Resulting from
Inspection
286032
286704
Corrective Action
Documents
257220
Corrective Action
Documents
Resulting from
Inspection
04301741
284066
284067
284072
284273
284068
284731
292129
284786
286472
Drawings
10905-0732
Main Steam Isolation Valve A (AOV-3517) Elementary
Wiring Diagram
21946-0732
Main Steam Isolation Valve A (AOV-3517) Control
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Schematic
33013-0663
Safeguard System SI Racks Safety Injection Sequence and
Main Steamline Isolation
Miscellaneous
VTD-W120-4189
Westinghouse Oil-Tite Pushbuttons Flush and Extended
Operators Vendor Technical Manual
Procedures
Critical Component Failure Clock
Maintenance Rule-Performance Criteria Selection
Issue Identification and Screening Process
Corrective Action Program Procedure
Work Orders
C93712470
C93712474