IR 05000327/2019003
| ML19301B352 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/28/2019 |
| From: | Omar Lopez-Santiago Division Reactor Projects II |
| To: | Jim Barstow Tennessee Valley Authority |
| Reeder D | |
| References | |
| IR 2019003 | |
| Download: ML19301B352 (17) | |
Text
October 28, 2019
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000327/2019003 AND 05000328/2019003
Dear Mr. Barstow:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah, Units 1 and 2. On October 9, 2019, the NRC inspectors discussed the results of this inspection with Mr. Matt Rasmussen and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or significance or severity of the violation documented in this inspection report, 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 Sequoyah.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Sequoyah 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/
Omar R. Lpez-Santiago, Chief Reactor Projects Branch 5 Division of Reactor Projects
Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000327 and 05000328
License Numbers:
Report Numbers:
05000327/2019003 and 05000328/2019003
Enterprise Identifier:
I-2019-003-0023
Licensee:
Tennessee Valley Authority
Facility:
Sequoyah, Units 1 and 2
Location:
Soddy Daisy, TN 37379
Inspection Dates:
July 01, 2019 to September 30, 2019
Inspectors:
N. Childs, Senior Resident Inspector
D. Hardage, Senior Resident Inspector
N. Morgan, Resident Inspector
A. Nielsen, Senior Health Physicist
W. Pursley, Health Physicist
Approved By:
Omar R. Lpez-Santiago, Chief
Reactor Projects Branch 5
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Sequoyah, 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.
List of Findings and Violations
Failure to Follow Procedures Cornerstone Significance Cross-Cutting Aspect Report Section Public Radiation Safety Green NCV 05000328,05000327/2019003-01 Open
[H.1] -
Resources 71124.06 A self-revealed Green finding and associated non-cited violation of Technical Specification 5.5 was identified when the licensee failed to follow a plant procedure to estimate flow rates when the Unit 1 (U1) and Unit 2 (U2) Shield Building Ventilation Flow Rate Monitoring Systems (SBVMS) were out of service.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000327/2019-002-00 LER 2019-002-00 for Sequoyah Nuclear Plant Unit 1 Regarding Steam Generator Pressure Transmitter Degraded Sensing Line Causes Condition Prohibited by Technical Specifications.
71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power (RTP). On August 27, 2019, the unit experienced an automatic reactor trip due to a dropped control rod. The unit was returned to 76 percent RTP on August 30, 2019 and remained at or near 76 percent RTP for the remainder of the inspection period due to end of life coastdown conditions.
Unit 2 operated at or near RTP 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
External Flooding Sample (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated readiness to cope with external flooding for the following areas:
- Essential Raw Cooling Water (ERCW) Building
- Emergency Diesel Generator (EDG) Building
71111.04Q - 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) Vital Battery V alignment to Battery Board II during Vital Battery II surveillance testing on July 16, 2019
- (2) Train B ERCW while the QA ERCW pump was out of service for emergent maintenance on July 25, 2019
- (3) Unit 2 train 'B' emergency core cooling system (ECCS) pumps while 2A-A safety injection pump (SIP) room cooler was out of service for planned cooling coil replacement on September 20, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 emergency diesel generators on July 11, 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) Unit 1 and Unit 2, Control Building - El. 685 (Auxiliary Instrument Rooms) on July 16, 2019
- (2) Unit 1 and Unit 2, Auxiliary Building - El. 714 on July 22, 2019
- (3) Unit 1 and Unit 2, Auxiliary Building - El. 690 on July 31, 2019
- (4) Unit 1 and Unit 2, Control Building - El. 732 on September 24, 2019
- (5) Unit 1 and Unit 2, Control Building - El. 706 on September 24, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (2 Samples)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Auxiliary Building A and B 6.9KV Shutdown Board Rooms elevation 734
- (2) Auxiliary Building 1A and 2A 480V Shutdown Board Rooms elevation 749
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 Control Room:
- Following a Unit 1 automatic reactor trip and subsequent U1 recovery activities August 27, 2019 through August 30, 2019.
- During at power dilution activities on Unit 1 to maintain Tavg on program on September 25, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator training scenario on August 1, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Review of Sequoyah Nuclear Plant Maintenance Rule Fourteenth Periodic Assessment Report - Units 1, 2, and Common, September 1, 2016 thru March 31, 2018
- (2) Review of licensee response to recent engineered safety feature (ESF) room cooler coil leaks on September 25, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
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 13, including protected equipment status reviews for scheduled maintenance on 2A emergency diesel generator, 1A centrifugal charging pump and emergent maintenance on 2A 480V board room chiller
- (2) Unit 1 and Unit 2, week of July 21 - July 27, including protected equipment status reviews for scheduled maintenance on 2A motor driven auxiliary feedwater pump and emergent maintenance on QA essential raw cooling water pump
- (3) Unit 1 and Unit 2, week of September 16 - 20, during conservative operations alert including protected equipment status review for scheduled maintenance on 2A-A safety injection pump room cooler
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (5 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
===1528237)
- (2) N31 startup rate failed low (CR 1534200)
- (3) Missed surveillance for blackout start of 2A motor driven auxiliary feedwater pump (CR 1536523)
- (4) Wrong grease found in 1A pipe chase cooler fan motor (CR 1538643)
(5)1A 690 penetration room cooler leak (CR 1543865)
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) DCN 023085, Replace breaker handle, breaker operating mechanism and remove Kirk key interlock for ERCW MCC 1A-A, 1B-B, 2A-A, and 2B-B
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01)===
The inspectors evaluated the following post maintenance tests (PMTs):
- (1) WO 120561705, Through wall piping leak on ERCW supply to 2A EDG on July 9, 2019 (2)0-SI-EBT-250-100.2, 125VDC Battery Biannual Operability, after 36 month vital battery II charger performance test on July 19, 2019
- (3) WO 120612292, Replace the upper bearing cooling coil in QA ERCW pump motor on July 29, 2019
- (4) WO 120710728, 1-PT-1-23 slow to respond during Unit 1 reactor trip on August 27, 2019
- (5) WO 119866320, 2A SIP room cooler PMT after cooling coil replacement on September 20, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)2-SI-EDC-082-307.B, Undervoltage/Degraded Voltage, DG Start and Load Shedding Time Response Relay Test on July 15, 2019 (2)0-SI-EBT-250-104.2, Modified Performance Testing of 125VDC Vital Battery II and 125VDC Vital Battery Charger Test on July 19, 2019
Inservice Testing (IP Section 03.01) (1 Sample)
(1)2-SI-SXP-072-201.A, Containment Spray Pump 2A-A Performance Test on August 21, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Emergency preparedness drill conducted on July 24,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walk Downs and Observations (IP Section 02.01) (1 Sample)
The inspectors walked down the following gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design:
(1)
- 1-RE-90-400, Shield Building Vent Normal/Accident Range Noble Gas
- 0-RE-90-101B, Auxiliary Building Vent
- 0-RE-90-122, Waste Disposal System Discharge Monitor
Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02) (1 Sample)
The inspectors reviewed the following gaseous and liquid effluent monitor instrument calibrations and tests:
(1)
- Work Order 118702807, Calibration of Auxiliary Building Gaseous Radiation Monitor 0-90-101B and Exhaust Vent Flow Monitor 0-F-30-174, 03/01/2018
- Work Order 119266265, Functional Test of Auxiliary Building Gaseous Radiation Monitor 0-90-101B and Exhaust Vent Flow Monitor 0-F-30-174, 11/21/2018
- Work Order 119651155, Functional Test of Auxiliary Building Gaseous Radiation Monitor 0-90-101B and Exhaust Vent Flow Monitor 0-F-30-174, 05/20/2019
- Work Order 118552385, Channel Calibration of Waste Disposal System Liquid Effluent Radiation Monitor 0-R-90-122.0, 01/24/2018
- Work Order 119619088, Channel Calibration of Waste Disposal System Liquid Effluent Radiation Monitor 0-R-90-122.0, 05/10/2019
Sampling and Analysis (IP Section 02.03) (1 Sample)
The inspectors reviewed the following:
- (1) Radioactive Effluent Sampling and Analysis Activities
- Weekly Unit 2 Containment Vent sampling at 2RM-90-106
Effluent discharges
- None were available during this inspection.
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
The inspectors reviewed the following radioactive effluent discharge system surveillance test results:
(1)
- Work Order 117228061, Unit One Train A Containment Purge Air Exhaust System Filter Test, 02/07/2018
- Work Order 117228061, Unit One Train B Containment Purge Air Exhaust System Filter Test, 09/25/2018
Dose Calculations (IP Section 02.05) (1 Sample)
The inspectors reviewed the following to asses public dose:
- (1) Liquid and Gaseous Discharge Permits
- Permit Number 2019375.059.035.G, U2 Shield Bldg Vent Ng, 02/17/2019
- Permit Number 2019419.070.002.G, U2 Shld Bldg Exh H-3, 05/20/2019
- Permit Number 2019441.031.143.G, U2 Containment Vent, 07/16/2019
- Permit Number 2019459.008.087.L, Cask Decon Collector Tank, 06/28/2019
- Permit Number 2019458.007.306.L, Monitor Tank, 06/27/2019 Annual Radiological Effluent Release Reports
- Sequoyah Nuclear Plant Annual Radioactive Effluent Release Report, 2017 and 2018
Abnormal Gaseous or Liquid Tank Discharges
- CR 1457703 Large hole in Unit 2 General Exhaust Duct on Aux Bldg Roof
71124.07 - Radiological Environmental Monitoring Program
Site Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the radiological environmental monitoring program implementation.
- (1) The inspectors observed the collection of environmental samples and evaluated the location, physical condition, and maintenance records (as applicable) for the following sample equipment:
- 5 Particulate and Iodine Air Samplers
- 1 Surface Water Sampler
- 5 Environmental Dosimeters
The inspectors also observed the condition of the meteorological tower and reviewed instrument calibration records.
Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)
- (1) The inspectors evaluated the licensee's continued implementation of the Groundwater Protection Initiative as described in NEI 07-07 and reviewed recent groundwater monitoring well results.
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)===
- (1) Unit 1 (July 2018 - June 2019)
- (2) Unit 2 (July 2018 - June 2019)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 (July 2018 - June 2019)
- (2) Unit 2 (July 2018 - June 2019)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (July 2018 - June 2019)
- (2) Unit 2 (July 2018 - June 2019)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 2018 - June 2019)
- (2) Unit 2 (July 2018 - June 2019)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 2018 - June 2019)
- (2) Unit 2 (July 2018 - June 2019)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 2018 - June 2019)
- (2) Unit 2 (July 2018 - June 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) October 1, 2018 - June 30, 2019
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) Test issues during Section 6.10 of 0-SI-SFT-065-001.A, EGTS Decay Cooldown Leakby Test (CR 1538863)
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated the Unit 1 automatic reactor trip due to dropped control rod H-8 and the licensees response for the period of August 27 - 30, 2019.
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000327/2019-002-00, Steam Generator Pressure Transmitter Degraded Sensing Line Causes Condition Prohibited by Technical Specifications (ADAMS Accession No.: ML19207A069).
The circumstances surrounding this LER are documented in Inspection Report 05000327/2019002 and 05000328/2019002 in the Inspection Results section (NCV 05000327/2019002-01).
INSPECTION RESULTS
Failure to Follow Procedures Cornerstone Significance Cross-Cutting Aspect Report Section Public Radiation Safety
Green NCV 05000328,05000327/2019003-01 Open
[H.1] -
Resources 71124.06 A self-revealed Green finding and associated non-cited violation of Technical Specification 5.5 was identified when the licensee failed to follow a plant procedure to estimate flow rates when the Unit 1 (U1) and Unit 2 (U2) Shield Building Ventilation Flow Rate Monitoring Systems (SBVMS) were out of service.
Description:
In the third quarter of 2016, the licensee replaced flow elements in the U1 and U2 SBVMS as part of a design change to address system aging issues. During post-installation testing on U1, it was discovered that the new flow sensors could not meet system accuracy requirements during periods of low flow and the SBVMS was never returned to service. Based on the U1 test results, the U2 SBVMS was also declared inoperable.
During normal operation, the SBVMS provides U1 and U2 Shield Building ventilation flow rates to the plant computer system (ICS). Chemistry personnel use this data point to calculate the quantity of radioactive effluents released from the plant for determining doses to the public. Although the SBVMS was out of service, the flow sensors were still providing erroneous data to ICS and the computer data point was still available. The inspectors noted that licensee procedure 0-SI-CEM-030-415.0, Gaseous Effluent Requirements (Noble Gas and Tritium), Rev 48, provided several methods to estimate Shield Building Vent Flow, including methods that did not rely on the SBVMS (e.g. using system design flows). However, erroneous flow data continued to be used until June 10, 2019, when, following a software upgrade to ICS, Chemistry personnel noticed significant errors in the data and the licensee realized that information from an inoperable system was being used.
The inspectors reviewed a licensee analysis that determined flow rates from the inoperable SBVMS were inaccurate, and therefore, from December 2016 - June 2019, effluent release calculations and resulting public dose estimates were also inaccurate. The inaccuracy overestimated the magnitude of effluents released. The inspectors noted that no effluent release limits were exceeded.
Corrective Actions: The licensee took immediate corrective actions including use of an alternative method to estimate Shield Building Vent flow as prescribed by procedure. Long term corrective actions include potential corrections to the 2016, 2017 and 2018 Annual Radiological Effluent Reports.
Corrective Action References: Condition Reports: 1524521 and 1246672
Performance Assessment:
Performance Deficiency: The inspectors determined the licensees failure to use an alternate method to estimate vent flow rates, as described in procedure 0-SI-CEM-030-415.0, when the Unit 1 and 2 SBVMS had been declared inoperable was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Plant Facilities/Equipment and Instrumentation attribute of the Public Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure adequate protection of public health and safety from exposure to radioactive materials released into the public domain as a result of routine civilian nuclear reactor operation.
Specifically, the use of flow data from equipment declared inoperable could impact the accuracy of doses to the public from plant effluents.
Significance: The inspectors assessed the significance of the finding using Appendix D, Public Radiation Safety SDP. The issue was a finding in the effluent release program, but it was not a substantial failure to implement the effluent release program and doses to the public did not exceed 10 CFR 50 Appendix I or 10 CFR 20.1301 limits. Therefore, the finding was determined to be of very low safety significance (Green).
Cross-Cutting Aspect: H.1 - Resources: Leaders ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety. Plant procedure 0-SI-CEM-030-415.0 did not provide clear guidance on when to use each of the available flow estimation methods.
Enforcement:
Violation: Technical Specification 5.5 requires the licensee to implement the procedures recommended by RG 1.33, which includes procedures for monitoring radioactive effluents. Specifically, licensee procedure 0-SI-CEM-030-415.0 provided multiple valid methods for estimating Shield Building vent flow rates. Contrary to this, from December of 2016 until June 10, 2019, the licensee failed to implement this procedure by using a valid method to estimate Shield Building vent flow rates when the SBVMS was out of service.
Enforcement Action: This violation is being treated as an non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 9, 2019, the inspectors presented the integrated inspection results to Mr.
Matt Rasmussen and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
SQN-DC-V-12.1
Sequoyah Design Criteria Document - Flood Protection
Provisions
Revision 21
Procedures
0-PI-OPS-510-
001.0
Operations Flood Preparation Equipment Inventory
Revision 20
0-TI-DXX-000-
2.0
EFPP Bases Document
Revision 3
0-TI-DXX-000-
2.1
External Flood Protection Program
Revision 5
0-TI-SXX-000-
017.0
Hazard Barriers
Revision 1
NPG-SPP-09.22
External Flood Protection Program
Revision 2
71111.04Q Miscellaneous
0-PE-2019 / 2-63-
0012
Protected equipment for 2A-A SIP room cooler replacement
09/20/2019
Procedures
0-GO-16,
18
System Operability Checklists - U2 ECCS/ESF
Revision 24
0-SO-250-1
25 Volt DC Vital Power System
Revision 78
0-SO-67-1,
Essential Raw Cooling Water Valve Checklist
Revision 39
Procedures
0-SO-82-1
Diesel Generator 1A-A
Revision 60
0-SO-82-2
Diesel Generator 1B-B
Revision 59
71111.05Q Fire Plans
AUX-0-690-01
Fire Protection Pre-Fire Plans - Auxiliary Building - El. 690
(unit 1 side)
Revision 9
AUX-0-690-02
Fire Protection Pre-Fire Plans - Auxiliary Building - El. 690
(unit 2 side)
Revision 9
AUX-0-714-00
Fire Protection Pre-Fire Plans - Auxiliary Building El. 714
Revision 4
AUX-0-714-01
Fire Protection Pre-Fire Plans - Auxiliary Building El. 714
(Col. A1-15, Q-U)
Revision 8
AUX-0-714-02
Fire Protection Pre-Fire Plans - Auxiliary Building El. 714
(Col. U-X)
Revision 9
CON-0-685-00
Fire Protection Pre-Fire Plans - Control Building El. 685
Revision 6
CON-0-706-00
Fire Protection Pre-Fire Plans - Control Building El. 706
Revision 6
CON-0-732-00
Fire Protection Pre-Fire Plans - Control Building El. 732
Revision 8
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
DCN 23311
Install sensaphone on el. 734 and 749 to detect internal
flooding
Revision A
Procedures
1-AR-M15-B
Miscellaneous 1-XA-55-15B
Revision 45
Revision 5
71111.11Q Miscellaneous
SEG
OPL27351913
Simulator Training Guide - AOP-T.01, Security Event
Revision 0
Procedures
0-SO-62-7,
Section 6.1
Boron Concentration Control - At Power Routine Dilution
09/25/2019
Corrective Action
Documents
Condition Reports
(CRs)
387936; 1469779; 1546222
Miscellaneous
Table of Sequoyah room cooler coil replacement schedule
09/05/2019
Procedures
TI-4
Maintenance Rule Performance Indicator Monitoring,
Trending, and Reporting - 10CFR50.65
Revision 33
Corrective Action
Documents
Condition Reports
(CRs)
739500;
Miscellaneous
SQN-2-19-082
PRA evaluation response for missed surveillance
Revision 0
Operability
Evaluations
Prompt Determination of Operability (PDO) for PER 729802
and PER 739500
Revision 2
Work Orders
20656913; 120663698
Procedures
0-SI-SXI-000-
201.0
ASME Section XI Inservice Pressure Test
Revision 25
0-SI-SXP-067-
201.Q
Essential Raw Cooling Water Pump Q-A Performance Test
Revision 25
Work Orders
20593897
Perform Air Flow Balance IAW 0-PI-SFT-030-755.0
09/20/2019
Corrective Action
Documents
CR 1532597
Degraded Voltage Relay Failure
Work Orders
119772131;
20600783
Miscellaneous
SQN July Training Drill Package
July 24,
2019
Miscellaneous
Standing Order REP/EAL Guidance for Inoperable/Non-
Conforming Rad Monitors
7/07/2019
Procedures
0-TI-CEM-090-
016.1
Sampling Methods-Operable Containment Radiation
Monitors
Revision
21
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1-SI-OPS-000-
2.0
Shift Logs
Revision
27
Sequoyah Nuclear Plant, Offsite Dose Calculation Manual
Revision 63
Calibration
Records
Meteorological Monitoring Instrumentation Report of
Calibration, Ultrasonic Wind Sensor S/N B3720001
11/5/18
Miscellaneous
2018 Annual Radiological Environmental Operating Report,
Sequoyah Nuclear Plant Units 1 and 2
5/9/19
Procedures
0-TI-CEM-999-
000
Collection of Radiological Environmental Monitoring
Samples
Rev. 0
71151
Miscellaneous
Sequoyah Mitigating System Performance Index Basis
Document
Revision 10
Unit 1 and Unit 2 MSPI Derivation Reports - Cooling Water
System
June 2019
Unit 1 and Unit 2 MSPI Derivation Reports - High Pressure
Injection System
June 2019
Unit 1 and Unit 2 MSPI Derivation Reports - Heat Removal
System
June 2019
Unit 1 and Unit 2 MSPI Derivation Reports - Residual Heat
Removal System
June 2019
Unit 1 and Unit 2 MSPI Derivation Reports - Emergency AC
Power System
June 2019
Corrective Action
Documents
Condition Reports
(CRs)
24784; 1524125
Miscellaneous
Prompt
Investigation
Report
0-FCV-65-28A Gross Leakage
06/14/2019
Miscellaneous
Sequoyah Nuclear Power Plant - Unit 1 Reactor Trip Report
08/27/2019
Standing Order
SO-19-025
ODMI - Restart Following U1 H8 Dropped Rod
08/28/2019