IR 05000327/2018003
| ML18306A927 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/29/2018 |
| From: | Masters A NRC/RGN-II/DRP/RPB5 |
| To: | James Shea Tennessee Valley Authority |
| References | |
| IR 2018003 | |
| Download: ML18306A927 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ber 29, 2018
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC INTEGRATED INSPECTION REPORT 05000327/2018003 AND 05000328/2018003
Dear Mr. Shea:
On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant, Units 1 and 2. On October 11, 2018, the NRC inspectors discussed the results of this inspection with Mr. Tony Williams and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection. However, inspectors documented a licensee-identified violation which was determined to be of very low safety significance in this report. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident inspector at the Sequoyah Nuclear Plant. 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/
Anthony D. Masters, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos.: 05000327, 05000328 License Nos.: DPR-77, DPR-79
Enclosure:
IR 05000327/2018003 and 05000328/2018003
Inspection Report
Docket Number(s): 50-327, 50-328 License Number(s): DPR-77, DPR-79 Report Number(s): 05000327/2018003 and 05000328/2018003 Enterprise Identifier: I-2018-003-0034 Licensee: Tennessee Valley Authority (TVA)
Facility: Sequoyah Nuclear Plant Location: Soddy-Daisy, TN 37379 Inspection Dates: July 1, 2018 to September 30, 2018 Inspectors: D. Hardage, Senior Resident Inspector N. Childs, Resident Inspector W. Deschaine, Resident Inspector B. Collins, Reactor Inspector (Triennial Heat Sink Inspection)
Approved By: A. Masters, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a quarterly integrated inspection at Sequoyah Nuclear Plant, Units 1 and 2 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. No NRC-identified or self-revealing findings were identified during this inspection. A licensee-identified non-cited violation is documented in report Section 71111.15.
List of Findings and Violations None
PLANT STATUS
Unit 1 began the inspection period at rated thermal power and remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On July 27, 2018, the unit was down powered to 65 percent to replace the 2A generator terminal bushing fan motor. The unit was returned to rated thermal power on July 28, 2018. On September 11, 2018, the unit was down powered to 65 percent to replace the 2B and 2C generator terminal bushing fan motors. The unit was returned to rated thermal power on September 12, 2018. Unit 2 operated at or near rated thermal power for the rest 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
The inspectors evaluated readiness for impending adverse weather conditions for a tornado watch on July 20 - 21, 2018.
External Flooding (1 Sample)
The inspectors evaluated readiness to cope with external flooding on September 14, 2018.
71111.04 - Equipment Alignment Partial Walkdown
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) A train essential raw cooling water (ERCW) while J-A and K-A were out of service for maintenance on July 25, 2018
- (2) Unit 1 and 2 offsite power while A common station service transformer was out of service for corrective maintenance on September 7, 2018
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the Unit 2 safety injection (SI) system on September 14, 2018.
71111.05AQ - Fire Protection Annual/Quarterly Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit 1 and 2, control building - elevation 732 on July 11, 2018
- (2) Unit 1 and 2, control building - elevation 669 on August 22, 2018
- (3) Unit 1 and 2, control building - elevation 685 on August 24, 2018
- (4) Unit 1 and 2, residual heat removal (RHR) pump rooms - elevation 653 on September 14, 2018
Annual Inspection (1 Sample)
The inspectors evaluated fire brigade performance during an unannounced fire drill in the control building 24V/48V battery board and charger room on September 19, 2018.
71111.06 - Flood Protection Measures Internal Flooding
The inspectors evaluated internal flooding mitigation protections in the Unit 1 RHR pump rooms and the Unit 2 SI pump rooms on September 14, 2018.
71111.07 - Heat Sink Performance Heat Sink (Triennial)
The inspectors evaluated heat exchanger/sink performance on the following components from August 6 - 10, 2018:
- (1) component cooling system (CCS) 1A1 heat exchanger (SQN-1-HEX-070-0008A)
- (2) emergency diesel generator 1A2 oil cooler (SQN-1-CLR-082-0280/2)
- (3) main control room B-B chiller (SQN-0-CLR-311-0141-B)
- (4) ERCW intake structure & Chickamauga Lake, specifically Sections 02.02d.4, 02.02d.5, 02.02d.6 and 02.02d.7 were completed.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification
The inspectors observed and evaluated main feedwater pump trip with turbine runback, rod control system failure, and LOOP with faulted steam generator on August 13, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated Unit 2 downpower to 67 percent on September 11, 2018.
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Review of Function 030-K, Shutdown Board Room Chillers on September 5, 2018
Quality Control (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance issues:
- (1) Work Order (WO) 119655843, Repair of through wall leak downstream of 2-FCV-67-65, ERCW header 2A supply to 2B diesel generator on August 3, 2018.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit 1 and Unit 2, week of July 7 - July 14, 2018, including protected equipment status reviews for scheduled maintenance on J-A ERCW pump diesel generator and emergent maintenance on R-A ERCW pump
- (2) Unit 1 and Unit 2, week of July 21 - July 28, 2018, including protected equipment status reviews for scheduled maintenance on J-A and K-A ERCW and emergent inoperability of A ERCW to support 1A1, 1A2, 2A1 and 2A2 CCS heat exchanger flushing
- (3) Unit 1 and Unit 2, week of August 4 - August 11, 2018, including protected equipment status reviews for scheduled replacement of 1A-A shutdown board transformer and scheduled maintenance on K-A ERCW pump
71111.15 - Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Void identified in Unit 2 emergency boration line, Condition Report (CR) 1430796 on July 20, 2018
- (2) Fouling factor for 1A1/1A2 CCS heat exchanger exceeded acceptance criteria during testing, CR 1434213 on July 31, 2018
- (3) Unisolable through wall leak upstream of A1A-A ERCW strainer backwash isolation valve, CR 1436447 on August 6, 2018
- (4) Appendix R Control Building Issue for RHR Pumps, CR 1440822 on September 11, 2018
71111.18 - Plant Modifications
The inspectors evaluated the following temporary or permanent modifications:
- (1) DCN-22778, Installation of relief valve for the turbine driven auxiliary feedwater (TDAFW) mini-flow line on September 13.
71111.19 - Post Maintenance Testing
The inspectors evaluated the following post maintenance tests:
- (1) WO 119126956, Adjust impeller clearance to improve R-A ERCW pump performance on August 3
- (2) WO 119283073, Electric board room chiller temperature control valve maintenance on September 4
- (3) WO 119793667, Perform permanent repair of through wall leak on ERCW strainer A1A-A backflush valve on September 9
- (4) WO 119362989, 669 penetration room cooler 2B-B belt replacement on September 12
- (5) WO 119283426, Replace fuel oil flex hoses on diesel driven fire pump on September 12
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine
- (1) 2-SI-SXP-003-201.S, Turbine Driven Auxiliary Feedwater Pump 2A-S Performance Test on September 17, 2018
In-service (1 Sample)
- (1) 0-SI-SXP-067-201.J, Essential Raw Cooling Water Pump J-A Performance Test on August 3, 2018
71114.06 - Drill Evaluation Emergency Planning Drill
The inspectors evaluated the emergency preparedness drill on August 8, 2018. The drill included:
- A fire in the 2A-A charging pump and a contaminated injury responder
- A turbine trip on generator differential and anticipated transient without scram (ATWS)
- A fuel failure, 500 gpm loss of coolant accident (LOCA) and loss of containment due to failure of containment ventilation isolation valves
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below for the period from July 2017 through June 2018.
- (1) emergency AC power systems (Unit 1 and Unit 2)
- (2) heat removal systems (Unit 1 and Unit 2)
- (3) safety systems functional failures (Unit 1 and Unit 2)
- (4) high pressure injection systems (Unit 1 and Unit 2)
- (5) residual heat removal systems (Unit 1 and Unit 2)
- (6) cooling water support systems (Unit 1 and Unit 2)
INSPECTION RESULTS
Licensee Identified Non-Cited Violation
71111.15 - Operability Determinations and
Functionality Assessments This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Sequoyah Unit 1 Operating License Condition 2.C(16) and Sequoyah Unit 2 Operating License Condition 2.C(13) require in part that TVA shall implement and maintain in effect all provisions of the approved fire protection program. The Sequoyah fire protection report describes how the licensee complies with applicable sections of 10 CFR 50, Appendix R, including Section III.L.1 which states in part that alternative or dedicated shutdown capability provided for a specific fire area shall be able to achieve cold shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and maintain cold shutdown conditions thereafter.
Contrary to the above, since implementation of the Sequoyah Fire Protection Program, the licensee failed to maintain all aspects of the approved program. Specifically, in August 2018, the licensee discovered that the sites ability to achieve cold shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> would be challenged due to an inadequate evaluation of the RHR pumps functionality during certain Appendix R fire scenarios.
Significance/Severity Level: Using Inspection Manual Chapter 0609, Appendix F, Fire Protection Significance Determination Process, dated May 2, 2018, the inspectors determined that this finding was of very low safety significance (Green) because the finding did not affect the ability to reach and maintain hot shutdown/hot standby or safe and stable conditions.
Corrective Action Reference: CR
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 11, 2018, the inspector presented the quarterly resident inspector inspection results to Mr. Tony Williams, and other members of the licensee staff.
DOCUMENTS REVIEWED
Procedures
AOP-N.02, Tornado Watch/Warning, Revision 38
Procedures
0-SO-67-1, Essential Raw Cooling Water, Revision 110
0-SI-OPS-082-007.W, AC Electrical Power Source Operability Verification, Revision 45
Procedures
Sequoyah Fire Protection Report, Part II - Fire Protection Plan, Revision 36
PFP NO: CON-0-669-00, Fire Protection Pre-Fire Plans Auxiliary Building El. 653, Revision 9
PFP NO: CON-0-669-00, Fire Protection Pre-Fire Plans Control Building El. 669, Revision 5
PFP NO: CON-0-685-00, Fire Protection Pre-Fire Plans Control Building El. 685, Revision 7
Condition Reports
903960, 653 Fire Door A9 Weather Strip Needs Repaired
Work Orders
111466277, Replace the door seal around the 2B RHR pump room door
Other
Fire Drill Evaluation Report #76630, Electrical short in the 48V DC Plant Battery Board
Procedures
PFP NO: CON-0-669-00, Fire Protection Pre-Fire Plans Auxiliary Building El. 653, Revision 9
Calculations
MDN-000-000-2010-0203, SQN Probabilistic Risk Assessment - Internal Flooding Analysis,
Revision 4
Procedures
0-TI-SXX-000-146.0, Program for Implementing NRC Generic Letter 89-13, Rev. 0004
CHEM-004, Sequoyah Nuclear - Raw Water Chemistry Strategic Plan, Rev. 0002
NPG-SPP-09.14, Generic Letter (GL) 89-13 Implementation, Rev. 0004
SQN-0-MNWY-317-HH3, PM #052053000 Attachment A (Check Standing Water in A Train
Manholes/Handholes), Rev. 40
Completed Tests
WO118709012, Main Control Room A/C TCV Oil Cooler B-B Inspection, dated December 25,
2017
WO116794000, Main Control Room A/C Oil Cooler B-B TCV Inspection, dated December 28,
2015
WO118612358, Inspect, Lube and Test Shear Pin on ERCW Traveling Water Screens C-B,
dated October 30, 2017
WO117719469, Inspect, Lube and Test Shear Pin on ERCW Traveling Water Screens C-B,
dated January 30, 2017
WO118567200, Inspect, Lube and Test Shear Pin on ERCW Traveling Water Screen B-B,
dated October 16, 2017
WO118004823, Inspect and Lube ERCW Traveling Water Screen A-A, dated May 8, 2017
WO118818031, Inspect and Lube ERCW Traveling Water Screen A-A, dated February 2, 2018
WO118047422, Inspect, Lube and Test Shear Pin on ERCW Traveling Water Screens D-A,
dated May 22, 2017
WO118840573, Inspect, Lube and Test Shear Pin on ERCW Traveling Water Screens D-A,
dated February 19, 2018
WO117690785, Inspect, Lube and Test Shear Pin on ERCW Traveling Water Screen B-B,
dated January 16, 2017
WO118977651, S-PI-SFT-070-001-0 CCS Heat Exchangers Performance Test - 2A1 & 2A2,
dated August 8, 2018
WO118977655, S-PI-SFT-070-001-0 CCS Heat Exchangers Performance Test - 1A1 & 1A2,
dated August 7, 2018
WO115948317, Inspect D/G 1A-2 Heat Exchanger, dated January 26, 2015
WO117618925, Inspect D/G 1A-2 Heat Exchanger, dated January 23, 2017
Calculations
EWR-13-ENG-317-152, Engineering Work Request: Water Level at Which Safety-Related
Cable Conduits Would Be in Contact for Specific Manholes/Handholes, Revision 4
SQN-DC-V-7.4, Design Criteria Document: Essential Raw Cooling Water System (67), Revision
Drawings
1,2-47W845-1, Mechanical Flow Diagram - Essential Raw Cooling Water System (Flow
Markup), Revision 32
LRA-1,2-47W845-2, Mechanical Flow Diagram - Essential Raw Cooling Water System (Flow
Markup), Revision 0
FSAR Figure 9.2.1-1, Component Cooling System, Amendment 17
Corrective Action Documents
CR1437443, Housekeeping Patch Used on A1A Backwash Line - Non-compliant with N-513-3,
dated August 7, 2018
CR1437446, White Stalactites Protruding from Ceiling in ERCW Intake Pumping Station, dated
August 7, 2018
CR1437452, Reach Rod in ERCW Intake Pumping Station, dated August 7, 2018
CR1437455, Internal Flooding Analysis/Temporary Sump Pump Usage for ERCW Intake
Pumping Station, dated August 7, 2018
PMCR1310958, Revise Section 5.1.3(c) to Require Manhole/Handhole Cover Removal, dated
August 9, 2018
Other Documents
TVA065-REPT-067, Service Water Integrity Aging Management Program - Identification of
Stagnant/Dead Legs for Fulfillment of Commitment 38(G) Tennessee Valley Authority
Sequoyah Nuclear Plant, Revision 1
Other
Simulator Exercise Guide (SEG) S-2A, Revision 2
Procedures
N-MT-6, Magnetic Particle Examination for ASME and ANSI Code Components and Welds,
Revision 6
N-VT-3, Visual Examination of Weld Ends, Fit-ups, and Dimensional Examination of Weld
Joints, Revision 31
TI-4, Maintenance Rule Performance Indicator Monitoring, Trending, and Reporting -
10CFR50.65, Revision 30
Other
MMDP-10, Category I/II weld data sheet for weld number 0-ER-1453A, work order 119655843
SQN-0-18-046, PRA risk significance for the A-A and B-B 6.9kV Shutdown Board Room Chillers
Procedures
NPG-SPP-07.3, Work Activity Risk Management Process, Revision 25
Procedures
NEDP-22, Operability Determinations and Functional Evaluations, Revision 18
2-PI-SFT-070-001.0, Performance Testing of Component Cooling Heat Exchangers 2A1, 2A2,
Revision 22
Calculations
MDQ00006320100240, Calculation of Effects of Gas Accumulation in ECCS Piping
Condition Reports
1434213, 1A1/1A2 CCS Hx Fouling Factor Exceeded
1433922, 2A CCS Hx Pair Indicate Increase in Fouling
1440822, Appendix R Control Building Issue for RHR Pumps
Other
Design Criteria SQN-DC-V-13.9.9, Component Cooling Water System (70), Revision 28
SQN Fire Protection Report, Revision 36
Procedures
NPG-SPP-09.3, Plant Modifications and Engineering Change Control, Revision 30
NPG-SPP-09.4, 10 CFR 50.59 Evaluations of Changes, Tests, and Experiments, Revision 12
NPG-SPP-09.5, Temporary Modifications Temporary Configuration Changes, Revision 14
Procedures
0-SI-SXP-067-201.R, Essential Raw Cooling Water Pump R-A Performance Test, Revision 21
0-SI-SXI-000-201.0, ASME Section XI Inservice Pressure Test, Revision 25
Condition Reports
1443773, Diesel Fire Pump B Engine Speed is greater than limits per 0-SI-FPU-026-193.M
Work Orders
WO 119126956, Adjust Impeller Clearance to improve ERCW pump performance
WO 119283073, Electric Board Room A/C Condenser B Temperature Control Valve
WO 119283165, Electric Board Room Chiller Package B-B
WO 119283426, Replace fuel oil flex hoses
WO 119793667, Perform permanent repair of through wall leak
Work Orders
119127825, 2-SI-SXP-003-201.S, TDAFW Pump 2A-S XI Test, September 17, 2018
performance
Procedures
NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7
NPG-SPP-02.2, Performance Indicator Program, Revision 10
Other
Sequoyah Mitigating System Performance Index Basis Document, Revision 10
Unit 1 and 2 MSPI Derivation Reports Emergency AC Power Systems July 2017-Jun 2018
Unit 1 and 2 MSPI Derivation Reports Heat Removal Systems July 2017-Jun 2018
Unit 1 and 2 MSPI Derivation Reports Cooling Water Systems July 2017-Jun 2018
Unit 1 and 2 MSPI Derivation Reports High Pressure Injection Systems July 2017-Jun 2018
Unit 1 and 2 MSPI Derivation Reports Residual Heat Removal Systems July 2017-Jun 2018
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