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
uly 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 /RA/ /RA by Email/ /RA/
GGeorge Acting For/
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 /RA/ /RA/
KClayton Acting For/
DATE 07/25/19 07/24/19 07/30/19
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number: 05000382 License Number: NPF-38 Report Number: 05000382/2019002 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 Enclosure
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)
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)
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)
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)
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.)
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)
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)
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)
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)
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)
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)
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)
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)
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 Type Designation Description or Title Revision or
Procedure Date
71111.01 Corrective Action CR-WF3-YYYY- 2017-06756, 2019-03900, 2019-05201, 2019-05189
Documents NNNNN
Miscellaneous EN-FAP-WM-016 Waterford 3 Steam Electric Station Summer 2019 Seasonal 1
Reliability Plan
NUC-001: R2, Amended and Restated Nuclear Plant Operating Agreement 5
R5, R9.1.2 for Waterford III Nuclear Power Plant
Procedures EN-FAP-EP-010 Severe Weather Response 7
ENS-DC-201 ENS Transmission Grid Monitoring 6
OP-010-004 Power Operations 333
OP-901-314 Degraded Grid Conditions 5
OP-901-521 Severe Weather and Flooding 329
OP-901-521 Severe Weather and Flooding 324
OP-901-521 Severe Weather and Flooding 316
OP-901-521 Severe Weather and Flooding 315
71111.04 Drawings G-151 Sheet 4 Main & Extraction Steam 7
Procedures OP-002-004 Chilled Water System 317
OP-005-004 Main Steam 35
OP-009-003 Emergency Feedwater 309
OP-903-092 Main Steam Isolation Actuation Signal Test 301
71111.05Q Corrective Action CR-WF3-YYYY- 2019-05002, 2019-05003, 2019-05206, 2019-05222,
Documents NNNNN 2019-05243
Miscellaneous FWPH-001 Waterford-3 S.E.S Pre-Fire Strategy Fire Water Pump 3
House
NS-TB-005 Waterford-3 S.E.S Pre-Fire Strategy Turbine Building 1
Operating Floor +67.00
RAB 2-002 Waterford-3 S.E.S Pre-Fire Strategy Elev. +46.00' RAB Main 6
Steam Isolation Valve Passage
RAB 20-001 Waterford-3 S.E.S Pre-Fire Strategy Elev. +21.00' RAB 8
(RCA) Component Cooling Water Pump "A/B"
ROOF E-001 Waterford-3 S.E.S. Pre-Fire Strategy RAB +46 Roof E 5
(MSIV B)
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.06 Calculations ECM 15-004 Waterford 3 FLEX Internal Flooding Calculation 0
MNQ3-5 Flooding Analysis Calculation 5
PRA-W3-01-002 W3 Internal Flooding Analysis 3
Corrective Action CR-WF3-YYYY- 2014-04161, 2015-03826
Documents NNNNN
71111.11Q CR-WF3-YYYY- 2019-05055, 2019-05060, 2019-05184
NNNNN
Miscellaneous Reactor Startup and Power Ascension Following C23 Mid- 05/28/2019
Cycle Forced Outage 23-1
FAL19 W3-002 Startup with Elevated LP Exhaust Temperatures 05/29/2019
Procedures OP-003-033 Main Feedwater 324
OP-004-004 Control Element Drive 24
OP-004-019 Estimated Critical Configuration 16
OP-010-003 Plant Startup 348
71111.12 Corrective Action CR-WF3-YYYY- 2017-04461, 2019-02295, 2019-02123, 2016-04193,
Documents NNNNN 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 4
270-ICE-6002 Control Element Drive Mechanism Control System 1
PO 10582083 Purchase Order
TD-C490.0205 CE Control Element Drive Mechanism Control System 4
Technical Manual
Procedures EN-DC-203 Maintenance Rule Program 4
EN-DC-204 Maintenance Rule Scope and Basis 4
EN-DC-205 Maintenance Rule Monitoring 6
EN-DC-206 Maintenance Rule (A)(1) Process 3
STA-001-005 Leakage Testing of Air and Nitrogen Accumulators for Safety 320
Related Valves
Work Orders 52806256, 476966, 461082, 73486, 515588, 52789254,
2788273, 52475493
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.13 Corrective Action CR-WF3-YYYY- 2019-04037
Documents NNNNN
Miscellaneous 2019-0063- Tagout 0
ACCW Train A
Procedures EN-OP-119 Protected Equipment Postings 10
EN-WM-104 On Line Risk Assessment 18
FP-001-015 Fire Protection System Impairments 321
ME-004-002 Main Generator 12
OI-037-000 Operations Risk Assessment Guideline 313
Work Orders 00525041, 504093, 52772446, 258200
71111.15 Calculations EC 81023 Wet Cooling Tower Fan Breaker Cubicle Installed 0
Inconsistent with Vendor Recommendations
EC 82775 Basis for Continued Operation on Auxiliary Component 0
Cooling Water Wet Cooling Tower Fans Train B
EC 83104 Operability Input for CR-WF3-2019-5014 - Optical Isolator 05/26/2019
Cards for CEAs
Corrective Action CR-WF3-YYYY- 2019-03820, 2019-04628, 2019-04410, 2019-04654,
Documents NNNNN 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 EN-OP-104 Operability Determination Process 16
Work Orders 523968, 523801, 524021
71111.18 Miscellaneous Data Sheet 50- Freedom C306 Class 20 OL Min/Max Trip Curves From Cold 001
40011 Start
71111.19 Corrective Action CR-WF3-YYYY- 2019-04018, 2019-05101, 2019-05357, 2019-05576
Documents NNNNN
Procedures MI-003-504 Broad Range Gas Detection System Channel Function Test 313
and Calibration HVCIA5510 A or HVCIA5510 B
OP-903-127 Reactor Trip Circuit Breaker Post-Maintenance Retest 8
Inspection Type Designation Description or Title Revision or
Procedure Date
Work Orders 52784435, 525792, 52738914, 523968
71111.22 Calculations EC-M94-040 Waterford 3 SES EFPT Steam Line Drain Valves 3
ECM14-003 FLEX Water Pump Sizing 1
Corrective Action CR-WF3-YYYY- 2019-04574, 2019-04960, 2019-04962
Documents NNNNN
Drawings G-165 Sheet 3 Flow Diagram Turbine Building Miscellaneous Systems 36
Miscellaneous Flex PM Task Report 06/05/2019
Goodwin 4049 HL100M JD4045T285 New GP3052 Trailer 0
W3F1-2016-0031 Notification of Full Compliance with EA-12-049, Order 07/21/2016
Modifying Licenses with Regard to Requirements for
Mitigating Strategies for Beyond-Design-Basis External
Events
Procedures CEP-IST-4 Standard on Inservice Testing 309
FSG-005 Initial Assessment and FLEX Equipment Staging 10
ME-007-008 Motor Operated Valves 18
ME-007-047 VOTES Testing of MOVs 5
OP-903-050 Component Cooling Water and Auxiliary Component Cooling 41
Water Pump and Valve Operability Test
OP-903-068 Emergency Diesel Generator and Subgroup Relay 323
Operability Verification
SEP-WF3-IST-1 WF3 Inservice Testing Basis Document 7
Work Orders 52815592, 52849799, 52849798, 52858644
71114.06 Procedures EP-001-001 Recognition & Classification of Emergency Conditions 33
EP-002-052 Protective Action Guidelines 25
EP-002-102 Emergency Operations Facility (EOF) Activation, Operation, 310
and Deactivation
OP-901-522 Seismic Event 309
OP-902-001 Reactor Trip Recovery 16
OP-902-004 Excess Steam Demand Recovery Procedure 17
OP-902-008 Functional Recovery 30
OP-902-009 Standard Appendices 319
71151 Corrective Action CR-WF3-YYYY- 2018-07285
Documents NNNNN
Inspection Type Designation Description or Title Revision or
Procedure Date
Miscellaneous W3F1-2018-0030 NRC Performance Indicator (PI) Data - 1st Quarter ROP 04/11/2019
Data
W3F1-2018-0042 NRC Performance Indicator (PI) Data - 2nd Quarter 2018 07/13/2018
ROP Data
W3F1-2018-0066 NRC Performance Indicator (PI) Data - 3rd Quarter 2018 10/21/2018
ROP Data
W3F1-2019-0003 NRC Performance Indicator (PI) Data - 4th Quarter 2018 01/10/2019
ROP Data
71152 Corrective Action CR-WF3-YYYY- 2018-05712, 2018-01994, 2018-04408, 2018-05482
Documents NNNNN
Engineering EC 79914 Nuclear Island Penetration - Flood Barriers 0
Evaluations
Procedures EN-LI-108 Event Notification and Reporting 17
EN-LI-108 Event Notification and Reporting 16
EN-OP-104 Operability Determination Process 15
EN-OP-104 Operability Determination Process 16
EN-OP-119 Protected Equipment Postings 8
OP-901-521 Severe Weather and Flooding 329
UNT-006-010 Event Notification & Reporting 307
71153 Calculations EC 82996 Steam Generator Level Deviation Resulting in Feedwater 05/23/2019
Control System Shifting to Manual
EC 83022 Actions for Feedwater Control in Manual 05/20/2019
Corrective Action CR-WF3-YYYY- 2019-04788, 2019-04774, 2019-04779, 2019-04848,
Documents NNNNN 2019-04887, 2019-04889, 2019-04946, 2019-04792
Procedures EN-FAP-OU-101 Force/Planned Outage Planning and Preparation 6
EN-OP-104 Operability Determination Process 11
OP-902-000 Standard Post Trip Actions 16
OP-902-001 Reactor Trip Recovery Procedure 16
TG- OP-902-000 Technical Guidance for OP-902-000 Standard Post Trip 304
Actions
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