IR 05000382/2019002
| ML19214A227 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/31/2019 |
| From: | John Dixon NRC Region 4 |
| To: | Dinelli J Entergy Operations |
| References | |
| IR 2019002 | |
| Download: ML19214A227 (16) | |
Text
July 31, 2019
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - INTEGRATED INSPECTION REPORT 05000382/2019002
Dear Mr. Dinelli:
On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Waterford Steam Electric Station, Unit 3. On July 11, 2019, the NRC inspectors discussed the results of this inspection with Mr. Sergio Vazquez, General Manager of Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
John L. Dixon, JR, Chief Reactor Projects Branch D
Docket No.: 05000382 License No.: NPF-38
Enclosure:
As stated
ML19214A227 X SUNSI Review ADAMS:
Non-Publicly Available X Non-Sensitive Keyword:
By: BKC X Yes No X Publicly Available Sensitive NRC-002 OFFICE SRI:DRP/D RI:DRP/D C:DRS/EB1 C:DRS:EB2:
C:DRS/RCB C:DNMS/RIB NAME CSpeer JVera GGeorge NTaylor MHaire GWarnick SIGNATURE
/RA/
/RA/
/RA by GGeorge Acting For/
/RA/
/RA by Email/
/RA/
DATE 07/26/19 07/29/19 07/24/19 07/24/19 07/28/19 07/24/19 OFFICE C:DRS/OB TL:DRS/IPAT C:DRP/D
NAME GWerner RKellar JDixon
SIGNATURE
/RA by KClayton Acting For/
/RA/
/RA/
DATE 07/25/19 07/24/19 07/30/19
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000382
License Number:
Report Number:
Enterprise Identifier: I-2019-002-0002
Licensee:
Entergy Operations, Inc.
Facility:
Waterford Steam Electric Station, Unit 3
Location:
17265 River Road
Killona, LA
Inspection Dates:
April 1, 2019 to June 30, 2019
Inspectors:
F. Ramirez Munoz, Senior Resident Inspector
C. Speer, Senior Resident Inspector
J. Vera, Resident Inspector
T. DeBey, Resident Inspector, Arkansas Nuclear One
Approved By:
John L. Dixon, JR, Chief
Reactor Projects Branch D
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Waterford Steam Electric Station, Unit 3 in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
The Waterford Steam Electric Station, Unit 3, began the inspection period at 100 percent power.
On May 16, 2019, the main turbine automatically tripped with a subsequent automatic reactor trip due to an electrical fault in the main generator exciter. Following repairs to the main generator exciter, the plant was restarted on May 28, 2019, and achieved full power on June 1, 2019. On June 26, 2019, power lowered to approximately 95 percent after the main steam re-heater temperature control valves unexpectedly closed. Following repairs of the associated electrical supplies, power was raised to 100 percent on June 29, 2019. The unit remained at 100 percent 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
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.03) (1 Sample)
The inspectors evaluated readiness for impending adverse weather conditions for severe thunderstorms and flooding on April 4, 2019.
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of hurricane season for the following systems:
- Offsite electrical power
Summer Readiness Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems on June 4, 2019.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Emergency feedwater train A with train B unavailable for maintenance on April 2, 2019
- (3) Essential chilled water train AB following realignment for maintenance on June 22, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the main steam system on May 6, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Fire area ROOF E-001, main steam isolation valve B area on April 10, 2019
- (2) Fire area NS-TB-005, turbine building operating floor on May 21, 2019
- (3) Fire area RAB 2-002, main steam isolation valve passage on June 11, 2019
- (4) Fire area FWPH-001, fire water pump house on June 11, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
Flood zones 20 and 39, switchgear room B, on June 5, 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)
The inspectors observed and evaluated licensed operator performance in the control room during an unplanned automatic reactor trip due to main generator exciter issues on May 16, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated reactor startup just-in-time training on May 23, 2019.
71111.12 - Maintenance Effectiveness
Quality Control (IP Section 02.02) (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:
Control element drive system failure due to degraded components and the procurement of replacement optical isolator boards on May 28, 2019
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:
Main steam system on April 18, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Emergent work review associated with a degraded control room envelope boundary door on April 11, 2019
- (2) Risk assessment associated with planned auxiliary component cooling water train A maintenance on April 16, 2019
- (3) Risk assessment associated with planned yellow risk due to maintenance on nitrogen accumulator 5, affecting steam generator atmospheric dump valve 1 and emergency feedwater train A on April 17, 2019
- (4) Risk assessment associated with planned yellow risk due to switchyard maintenance on April 24, 2019
- (5) Emergent work review associated with disassembling the main generator exciter on May 20, 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) Operability determination associated with the emergency diesel generator train B jacket water circulation pump on April 9, 2019
- (2) Operability determination associated with wet cooling tower fans train B after identifying thermal overload relays were improperly set on May 3, 2019
- (3) Operability determination associated with the control element assembly 41 following abnormal voltages on May 9, 2019
- (4) Operability determination associated with the plant protection system with reactor power cutback taken out of service on May 23, 2019
- (5) Functionality assessment associated with the non-safety related control element drive motor control system following optical isolator card degradation potentially affecting the movability of multiple control element assemblies on May 28, 2019
- (6) Operability determination associated with reactor components following radial peaking factor testing on June 6, 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) Reactor trip circuit breaker 4 on April 10, 2019
- (2) Control element assembly 41 following the replacement of a current sensor on April 30, 2019
- (3) Wet cooling tower fan 2B thermal overload replacement on May 1, 2019
- (4) Static uninterruptable power supply 3014AB on June 5, 2019
- (5) Main steam isolation valve 1 upstream drip pot normal drain valve following maintenance on its associated steam trap on June 12, 2019
- (6) Broad range gas monitors train A following maintenance on June 26, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
Emergency feedwater pump AB steam supply normal drain isolation valve MS-408 on May 7, 2019
FLEX Testing (IP Section 03.02) (1 Sample)
FLEX diesel driven water transfer pump 3-year performance test on May 14, 2019
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
Reactor coolant system leak detection for elevated values during forced outage on May 31, 2019
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
- (1) Auxiliary component cooling water pump B on May 23, 2019
- (2) Emergency diesel generator B on June 24, 2019
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
Emergency Preparedness training exercise on April 3,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
April 1, 2018 through March 30, 2019
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
April 1, 2018 through March 30, 2019
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
April 1, 2018 through March 30, 2019
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Suspected defective process analog control cards that could cause spurious operations or failures to operate potentially affecting the controlled ventilation area system, component cooling water, and auxiliary component cooling water on April 1, 2019
- (2) Nuclear plant island structure penetration missing from licensee Procedure OP-901-521, Severe Weather and Flooding, on May 10, 2019
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
The inspectors evaluated the following licensee event and degraded conditions for plant status and mitigating actions, and provided input to determine whether a supplemental inspection was warranted:
On May 16, 2019, Waterford 3 received an automatic trip of the main turbine generator. As expected, the main turbine generator trip caused a reactor power cutback actuation.
Following the reactor power cutback actuation, an unexpected level deviation occurred between the two level-measurement channels on each steam generator. In response to the level deviation, the feedwater control system transitioned to manual as designed. With the feedwater controllers in manual, the system could not lower feedwater flow in time to respond to the rising steam generator levels, resulting in a reactor trip due to high steam generator level.
The licensee determined that the initial main turbine generator trip was due to a fault on the main generator exciter caused by blown fuses on each phase of the exciter. The licensee completed repairs to the generator exciter and disabled the non-safety related reactor power cutback system pending further investigation. The reactor was restarted on May 28, 2019, and full power was reached on June 1, 2019.
The inspectors concluded that a supplemental inspection was not warranted.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 11, 2019, the inspectors presented the integrated inspection results to Mr. S. Vazquez, General Manager of Plant Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2017-06756, 2019-03900, 2019-05201, 2019-05189
Miscellaneous
EN-FAP-WM-016
Waterford 3 Steam Electric Station Summer 2019 Seasonal
Reliability Plan
NUC-001: R2,
R5, R9.1.2
Amended and Restated Nuclear Plant Operating Agreement
for Waterford III Nuclear Power Plant
Procedures
EN-FAP-EP-010
Severe Weather Response
ENS-DC-201
ENS Transmission Grid Monitoring
OP-010-004
Power Operations
333
OP-901-314
Degraded Grid Conditions
OP-901-521
Severe Weather and Flooding
29
OP-901-521
Severe Weather and Flooding
24
OP-901-521
Severe Weather and Flooding
316
OP-901-521
Severe Weather and Flooding
315
Drawings
G-151 Sheet 4
Main & Extraction Steam
Procedures
OP-002-004
Chilled Water System
317
OP-005-004
OP-009-003
Emergency Feedwater
309
OP-903-092
Main Steam Isolation Actuation Signal Test
301
71111.05Q Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2019-05002, 2019-05003, 2019-05206, 2019-05222,
2019-05243
Miscellaneous
FWPH-001
Waterford-3 S.E.S Pre-Fire Strategy Fire Water Pump
House
NS-TB-005
Waterford-3 S.E.S Pre-Fire Strategy Turbine Building
Operating Floor +67.00
RAB 2-002
Waterford-3 S.E.S Pre-Fire Strategy Elev. +46.00' RAB Main
Steam Isolation Valve Passage
RAB 20-001
Waterford-3 S.E.S Pre-Fire Strategy Elev. +21.00' RAB
(RCA) Component Cooling Water Pump "A/B"
ROOF E-001
Waterford-3 S.E.S. Pre-Fire Strategy RAB +46 Roof E
(MSIV B)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
ECM 15-004
Waterford 3 FLEX Internal Flooding Calculation
MNQ3-5
Flooding Analysis Calculation
PRA-W3-01-002
W3 Internal Flooding Analysis
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2014-04161, 2015-03826
CR-WF3-YYYY-
NNNNN
2019-05055, 2019-05060, 2019-05184
Miscellaneous
Reactor Startup and Power Ascension Following C23 Mid-
Cycle Forced Outage 23-1
05/28/2019
FAL19 W3-002
Startup with Elevated LP Exhaust Temperatures
05/29/2019
Procedures
OP-003-033
Main Feedwater
24
OP-004-004
Control Element Drive
OP-004-019
Estimated Critical Configuration
OP-010-003
Plant Startup
348
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2017-04461, 2019-02295, 2019-02123, 2016-04193,
2019-02295, 2019-02429, 2010-07065, 2019-03481,
2019-03140, 2019-03139, 2019-00225, 2019-00234,
2019-02662, 2014-01612, 2015-07032, 2015-07047,
2017-07409, 2019-02173, 2019-02364, 2016-06714,
2015-09353, 2019-04410, 2019-04654, 2019-04655,
2019-05014
Miscellaneous
00000-ICE-6002
Control Element Drive Mechanism Control System
270-ICE-6002
Control Element Drive Mechanism Control System
PO 10582083
Purchase Order
TD-C490.0205
CE Control Element Drive Mechanism Control System
Technical Manual
Procedures
Maintenance Rule Scope and Basis
Maintenance Rule Monitoring
Maintenance Rule (A)(1) Process
STA-001-005
Leakage Testing of Air and Nitrogen Accumulators for Safety
Related Valves
20
Work Orders
2806256, 476966, 461082, 73486, 515588, 52789254,
2788273, 52475493
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2019-04037
Miscellaneous
2019-0063-
ACCW Train A
Tagout
Procedures
Protected Equipment Postings
On Line Risk Assessment
Fire Protection System Impairments
21
ME-004-002
Main Generator
OI-037-000
Operations Risk Assessment Guideline
313
Work Orders
00525041, 504093, 52772446, 258200
Calculations
Wet Cooling Tower Fan Breaker Cubicle Installed
Inconsistent with Vendor Recommendations
Basis for Continued Operation on Auxiliary Component
Cooling Water Wet Cooling Tower Fans Train B
Operability Input for CR-WF3-2019-5014 - Optical Isolator
Cards for CEAs
05/26/2019
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2019-03820, 2019-04628, 2019-04410, 2019-04654,
2019-04655, 2015-00027, 2015-00627, 2015-01181,
2015-01857, 2015-02575, 2015-03342, 2016-03437,
2016-04027, 2016-04593, 2016-05185, 2016-05748,
2016-06406, 2018-00741, 2018-01278, 2019-04404,
2019-05144, 2019-04628, 2019-04436, 2019-04448,
2019-04449, 2019-04450, 2019-04577, 2019-04478,
2018-05014
Drawings
B289 Sh. 2D
Power Distribution and Motor Data MCC Overload Settings
DH
Procedures
Operability Determination Process
Work Orders
23968, 523801, 524021
Miscellaneous
Data Sheet 50-
40011
Freedom C306 Class 20 OL Min/Max Trip Curves From Cold
Start
001
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2019-04018, 2019-05101, 2019-05357, 2019-05576
Procedures
MI-003-504
Broad Range Gas Detection System Channel Function Test
and Calibration HVCIA5510 A or HVCIA5510 B
313
OP-903-127
Reactor Trip Circuit Breaker Post-Maintenance Retest
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
2784435, 525792, 52738914, 523968
Calculations
EC-M94-040
Waterford 3 SES EFPT Steam Line Drain Valves
ECM14-003
FLEX Water Pump Sizing
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2019-04574, 2019-04960, 2019-04962
Drawings
G-165 Sheet 3
Flow Diagram Turbine Building Miscellaneous Systems
Miscellaneous
Flex PM Task Report
06/05/2019
Goodwin 4049
HL100M JD4045T285 New GP3052 Trailer
Notification of Full Compliance with EA-12-049, Order
Modifying Licenses with Regard to Requirements for
Mitigating Strategies for Beyond-Design-Basis External
Events
07/21/2016
Procedures
CEP-IST-4
Standard on Inservice Testing
309
FSG-005
Initial Assessment and FLEX Equipment Staging
ME-007-008
Motor Operated Valves
ME-007-047
VOTES Testing of MOVs
OP-903-050
Component Cooling Water and Auxiliary Component Cooling
Water Pump and Valve Operability Test
OP-903-068
Emergency Diesel Generator and Subgroup Relay
Operability Verification
23
SEP-WF3-IST-1
WF3 Inservice Testing Basis Document
Work Orders
2815592, 52849799, 52849798, 52858644
Procedures
Recognition & Classification of Emergency Conditions
Protective Action Guidelines
Emergency Operations Facility (EOF) Activation, Operation,
and Deactivation
310
OP-901-522
Seismic Event
309
OP-902-001
Reactor Trip Recovery
OP-902-004
Excess Steam Demand Recovery Procedure
OP-902-008
Functional Recovery
OP-902-009
Standard Appendices
319
71151
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2018-07285
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
NRC Performance Indicator (PI) Data - 1st Quarter ROP
Data
04/11/2019
NRC Performance Indicator (PI) Data - 2nd Quarter 2018
ROP Data
07/13/2018
NRC Performance Indicator (PI) Data - 3rd Quarter 2018
ROP Data
10/21/2018
NRC Performance Indicator (PI) Data - 4th Quarter 2018
ROP Data
01/10/2019
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2018-05712, 2018-01994, 2018-04408, 2018-05482
Engineering
Evaluations
Nuclear Island Penetration - Flood Barriers
Procedures
Event Notification and Reporting
Event Notification and Reporting
Operability Determination Process
Operability Determination Process
Protected Equipment Postings
OP-901-521
Severe Weather and Flooding
29
UNT-006-010
Event Notification & Reporting
307
Calculations
Steam Generator Level Deviation Resulting in Feedwater
Control System Shifting to Manual
05/23/2019
Actions for Feedwater Control in Manual
05/20/2019
Corrective Action
Documents
CR-WF3-YYYY-
NNNNN
2019-04788, 2019-04774, 2019-04779, 2019-04848,
2019-04887, 2019-04889, 2019-04946, 2019-04792
Procedures
EN-FAP-OU-101
Force/Planned Outage Planning and Preparation
Operability Determination Process
OP-902-000
Standard Post Trip Actions
OP-902-001
Reactor Trip Recovery Procedure
TG-OP-902-000
Technical Guidance for OP-902-000 Standard Post Trip
Actions
304