IR 05000298/2019003
| ML19303A660 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/30/2019 |
| From: | Christopher Newport NRC/RGN-IV/DRP/RPB-C |
| To: | Dent J Nebraska Public Power District (NPPD) |
| References | |
| EPID I-2019-003-0003 IR 2019003 | |
| Preceding documents: |
|
| Download: ML19303A660 (40) | |
Text
October 30, 2019
SUBJECT:
COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2019003
Dear Mr. Dent:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On October 17, 2019, the NRC inspectors discussed the results of this inspection with Mr. J. Sullivan, General Manager Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
Two findings of very low safety significance (Green) are documented in this report. These findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or significance of the violations 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 IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Cooper Nuclear Station.
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 IV; and the NRC Resident Inspector at Cooper Nuclear Station.
J. Dent, Jr.
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/
Christopher W. Newport, Acting Chief Reactor Projects Branch C Division of Reactor Projects
Docket No. 05000298 License No. DPR-46
Enclosure:
As stated
Inspection Report
Docket Number:
05000298
License Number:
Report Number:
Enterprise Identifier: I-2019-003-0003
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
Brownville, NE
Inspection Dates:
July 1, 2019 to September 30, 2019
Inspectors:
B. Baca, Health Physicist
L. Carson, Senior Health Physicist
L. Flores, Project Engineer
N. Greene, Senior Health Physicist
J. O'Donnell, Health Physicist
N. Okonkwo, Reactor Inspector
D. Proulx, Senior Project Engineer
W. Sifre, Senior Reactor Inspector
M. Stafford, Senior Resident Inspector
C. Stott, Reactor Inspector
P. Vossmar, Senior Resident Inspector
Approved By:
Christopher W. Newport, Acting Chief
Reactor Projects Branch C
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Cooper Nuclear Station 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 Implement Fire Protection Program Surveillance Requirements for a Fire Barrier Seal Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000298/2019003-01 Open/Closed
[P.1] -
Identification 71111.05Q The inspectors identified a Green, non-cited violation of License Condition 2.C(4), Fire Protection, for the failure to implement all provisions of the approved fire protection program.
Specifically, prior to July 2, 2019, the licensee failed to implement Surveillance Procedure 6.FP.606, Fire Barrier/Penetration Seal Visual Examination, Revision 25, for visual inspection of the cable expansion room west wall fire barrier and its associated MN 46 penetration to ensure that an unsealed penetration opening was identified. As a result, the licensee failed to identify that the conduit seal was degraded until it was discovered by the inspectors on July 2, 2019, and subsequently declared nonfunctional by operations personnel.
Failure to Take Required Actions of Technical Specification 3.5.2 for Reactor Pressure Vessel Water Inventory Control During Secondary Containment Work Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000298/2019003-02 Open/Closed
[H.5] - Work Management 71153 The inspectors documented a self-revealed, Green, non-cited violation of Technical Specification 3.5.2, Reactor Pressure Vessel Water Inventory Control, for the licensees failure to take technical specification required actions during a reactor pressure vessel water inventory control activity. Specifically, on October 10, 2018, during a planned water inventory control activity, the licensee failed to meet Technical Specification 3.5.2, Condition C, when an unplanned and unrecognized breach of secondary containment occurred, and the licensee did not verify secondary containment could be closed as required until the breach was discovered several hours later. In particular, during residual heat removal service water piping work, the penetration of the same residual heat removal service water piping on both the control building and reactor building sides of the secondary containment boundary was not recognized, and as a result, a containment closure plan was not in place.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000298/2018-002-00 Lack of Procedural Guidance Results in Work Scheduling Error Causing Breach of Secondary Containment and Condition Prohibited by Technical Specifications 71153 Closed
PLANT STATUS
Cooper Nuclear Station began the inspection period at rated thermal power. On August 23, 2019, the unit was down powered to 70 percent for a control rod sequence exchange. The plant was returned to rated thermal power on August 24, 2019, and remained at or near rated thermal 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
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Standby liquid control B on July 8, 2019
- (2) Service water booster pump A subsystem on July 16, 2019
- (3) Reactor core isolation cooling on September 13, 2019
- (4) Core spray B on September 26, 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 hardened containment vent system installed in accordance with NRC Order EA-13-109 on August 27, 2019. [Completion of this sample was in accordance with the guidance in Temporary Instruction 2515/193, with credit taken in IP
71111.04 - further details are documented in Inspection Report 05000298/2019012, ADAMS
Accession No. ML19266A571.]
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Cable expansion room on July 3, 2019
- (2) Reactor building suppression pool 859 feet elevation on July 22, 2019
- (3) Southeast quad 859 feet and 881 feet elevations on August 21, 2019
- (4) Control cable spreading room on September 17, 2019
- (5) Critical switchgear rooms 1F and 1G on September 18, 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:
- (1) Reactor building 931 feet elevation on September 30, 2019
Inspection Activities - Underground Cables (IP Section 02.02c.) (1 Sample)
The inspectors evaluated cable submergence protection in:
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 during a planned quarterly downpower on August 24, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator training drill performed as a corrective action for a declining emergency response performance trend on July 30, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Reactor building essential ventilation units on September 30, 2019
Quality Control (IP Section 02.02) (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:
- (1) Reactor core isolation cooling commercially dedicated signal conditioner failure on September 24, 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) Standby liquid control A pump planned maintenance on July 8, 2019
- (2) Unplanned reactor core isolation cooling unavailability on July 24, 2019
- (3) Core spray B planned work window on August 13, 2019
- (4) Emergency station service transformer planned work window on August 21, 2019
- (5) Emergent RF-MO-29 valve packing injection on August 27, 2019
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:
- (1) Part 21 for reactor core isolation cooling positioner defect on July 3, 2019
- (2) Residual heat removal to radwaste primary containment isolation valve classification/operability on August 15, 2019
- (3) Service water check valve 37 past operability on August 19, 2019
- (4) Southeast quad fan coil unit failed to meet surveillance acceptance criteria on August 16, 2019
- (5) Questionable results during containment isolation valve local leak-rate test on September 19, 2019
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from September 20, 2013, to September 20, 2019:
- (1) Evaluation 2013-3, Revision 2, Remove heater bay steam leak detection temperature switches
- (2) Evaluation 2015-2, Revision 0, Startup transformer replacement
- (3) Evaluation 2015-4, Revision 1, Time critical operator action for suppression pool cooling
- (4) Evaluation 2015-5, Revision 1, Reactor containment isolation cooling turbine governor control system replacement
- (5) Evaluation 2018-1, Revision 0, Engineering Change (EC) 6038060, Open phase protection system
- (6) Evaluation 2018-2, Revision 0, Engineering Evaluation (EE)18-012, Extending inspection duration of underwater torus region
- (7) Evaluation 2019-2, Revision 0, Technical Requirements Manual 3.7.1, flooding forecast removed
- (8) Screen 71719, 161 kV low voltage limit
- (9) Screen 71720, CR-CNS-2016-02270, Standing Order 2016-005
- (10) Screen 81728, R3402, sudden pressure relay replacement
- (11) Screen 81739, Service water surveillance operation, Division 2
- (12) Screen 81731, Use of NSF fuel channels
- (13) Screen 81734, Control room air conditioning temporary compressor breaker
- (14) Screen 91748, Procedure 6.1EE.306, 4160 V, bus 1F, undervoltage relay channel functional test
- (15) Screen 91758, 4160 V, bus 1G, undervoltage relay channel functional test (Division 2)
- (16) Screen 91770, Reactor equipment cooling sequential load time delay relay relocation
- (17) Screen 91778, Code Case N-513-3 compensatory actions
- (18) Screen 91795, Operability Evaluation CR-CNS-2016-05558
- (19) Screen 91793, Reclassify MCC-L and MCC-T as nonessential motor control centers
- (20) Screen 101794, CR-CNS-2016-05628, CA-001
- (21) Screen 111827, High pressure core injection turbine overspeed functional test
- (22) Screen 121884, Asea Brown Bovari breaker 145PMB40 BLK limit switch upgrade (1602)
- (23) Screen 121895, Service water booster pump oil sight glasses and reservoir
- (24) Screen 121898, T2 transformer sudden pressure and seal-in relay replacement
- (25) Screen 121948, Replace high pressure core injection flow controller (analog to digital)
- (26) Screen 121953, Main generator underfrequency relay replacement
- (27) Screen 122011, Residual heat removal service water booster pump system
- (28) Screen 122025, Emergency diesel generator indicating light isolation
- (29) Screen 122038, Reclassify relays HV-REL-1CFX and HV-REL-1DFX to nonessential
- (30) Screen 122067, Various motor operated valve packing load adjustment calculation revisions
- (31) Screen 122093, High pressure core injection loss of coolant heat exchanger thermal performance and tube plugging margin
- (32) Screen 122143, Residual heat removal and high pressure core injection net positive suction head margins for an anticipated transient without SCRAM event
- (33) Screen 142229, Reactor equipment cooling heat exchanger allowable tube plugging increase
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) Hardened containment vent system installed in accordance with NRC Order EA-13-109 on August 29, 2019. [Completion of this permanent modification sample was in accordance with the guidance in Temporary Instruction 2515/193, with credit taken in Inspection Procedure
71111.18 - further details are documented in
Inspection Report 05000298/2019012, ADAMS Accession No. ML19266A571.]
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Service water check valve 37 leakage post maintenance testing on July 23, 2019
- (2) Reactor building outer railroad airlock door seal post maintenance testing on July 25, 2019
- (3) Scram discharge volume check valve replacement on August 6, 2019
- (4) Core spray B planned work window on August 16, 2019
- (5) Southeast quad fan coil unit flow test following coil cleaning on September 5, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Emergency diesel generator 2 monthly operability test on July 15, 2019
- (2) Control room emergency filtration system flow test on July 19, 2019
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Reactor equipment cooling motor operated valve operability inservice test on July 31, 2019
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Spent fuel pool secondary level instrument functional testing on August 7,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walk Downs and Observations (IP Section 02.01) (1 Sample)
The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.
- (1) The inspectors reviewed the following:
Portable Survey Instruments
- RO-20 RP-11376
- AMS-4 RP-10762
- Model 3 RP-11438
- TelePole RP-11451
- REM 500 RP-11177
- Model 177 RP-11275
- H-809V RP-11469
Source Check Demonstration
- RO-20 RP-11419
- Model 3 RP-11438
- TelePole RP-11451 Area Radiation Monitors and Continuous Air Monitors
- CNS-0-RMA-RA-2
- CNS-0-RMA-RA-6
- CNS-0-RMA-RA-7
- CNS-0-RMA-RA-11
- CNS-0-RMA-RA-16
- CNS-0-RMA-RA-23
- CNS-0-RMA-RA-24
Personnel Contamination Monitors, Portal Monitors and Small Article Monitors
- PCM-2 RP-10571
- PM-12 RP-11178
- SAM-12 RP-11152
Calibration and Testing Program (IP Section 02.02) (1 Sample)
The inspectors evaluated the calibration and testing program implementation.
- (1) The inspectors reviewed the following:
Alarm Setpoint and Calibration Method Check of Personnel Contamination Monitors, Portal Monitors and Small Article Monitors
- PM-12 RP-11178
- SAM-12 RP-11152
Failure to Meet Calibration or Source Check Acceptance Criteria
- None Available
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)
- Liquid waste effluent system
- Elevated release point (ERP) system
- Radwaste ventilation
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)
- ERP
- Liquid radwaste
- Reactor building
Sampling and Analysis (IP Section 02.03) (1 Sample)
The inspectors reviewed the following:
- (1) Radioactive Effluent Sampling and Analysis Activities
- ERP
- Reactor building
- Radwaste
- Turbine building
Effluent Discharges The licensee did not perform a continuous or batch liquid effluent discharge during the inspection for observation. The inspectors reviewed selected discharge permits and the licensee's procedures for performing liquid and gaseous effluent discharges.
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
The inspectors reviewed the following radioactive effluent discharge system surveillance test results:
- (1) Air Cleaning System Surveillances
- Standby gas treatment
- Control room envelope filtration system [CREFS]
High-Range Effluent Monitoring Instrumentation Calibrations
- Reactor building
- Radwaste
- ERP
Dose Calculations (IP Section 02.05) (1 Sample)
The inspectors reviewed the following to asses public dose:
- (1) Liquid and Gaseous Discharge Permits The inspectors walked through the EFFECTS computer program, which documented the weekly continuous gaseous effluent discharge sample inputs, with a chemistry technician and the associated procedure for selected time periods during the inspection period. In addition, the inspectors reviewed the following liquid batch discharge releases:
- 18-15
- 18-33
- 18-42
- 19-10
- 19-13
- 19-43
Annual Radiological Effluent Release Reports
Abnormal Gaseous or Liquid Tank Discharges The licensee did not have an abnormal gaseous or liquid tank release during the inspection period. The inspectors reviewed release logs and discharge permits for abnormal discharges. The inspectors verified an infrequent tank discharge was performed according to licensee procedures.
71124.07 - Radiological Environmental Monitoring Program
Site Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the radiological environmental monitoring program implementation.
- Air sampling station No. 1
- Air sampling station No. 2
- Air sampling station No. 6 (aka solar station No. 1)
- Air sampling station No. 7
- Thermo-luminescent dosimeter (TLD) monitoring station No. 2
- TLD monitoring station No. 7
- TLD monitoring station No. 10
Environmental Sample Collections and Preparation Observation
1. Environmental samples: None were available for review and observation during this
inspection. The inspectors visited a milk cow collection point and observed the licensees delivery of a milk sampling container in preparation for the next milk sampling. The inspectors observed the collection and replacement of air sample cartridges at the following stations:
- Air sampling station No. 1
- Air sampling station No. 2
- Air sampling station No. 6 (aka solar station No. 1)
- Air sampling station No. 7
Licensee Actions in Response to Missed Sample, Inoperable Sampler, Lost TLD or Anomalous Measurement
1. CR-CNS-2019-03895: Sampling at positions Nos. 28 and 35 were not available due
to flooding July 19, 2019
July 1, 2019
3. CR-CNS-2018-06283: Air samplers Stations 03, 05, and 08 were inaccessible due
to excessive flooding October 10, 2018
4. CR-CNS-2018-08143: 100-meter A channel wind speed excessively high;
repair/replace November 30, 2018
5. CR-CNS-2018-02820: 100-meter B channel temperature sensor erroneous/incorrect
May 9, 2018
Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)
Sampling Program for the Potential of Licensed Material Entering Groundwater Groundwater Monitoring Well (GMW)
- CR-CNS-2019-01891, GMW-15 out of service due to excessive flooding, 03/26/19
- CR-CNS-2019-03553, GMW-12 out of service due to excessive flooding, 06/27/19
- CR-CNS-2019-00355, GMW-10 out of service due to excessive flooding, 06/27/19
- CR-CNS-2018-01877, GMW-06 & GMW out of service due to broken submersible pump, 03/29/19
For the 19 GMWs available for the inspection period, all wells measured less than 3,000 pCi/l H-3. The reporting level for H-3 in groundwater is 20,000 pCi/l.
- GMWs: 1D, 1S, 2, 3, 4D, 4S, 5, 6, 7D, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
and Transportation
Radioactive Material Storage (IP Section 02.01)
The inspectors evaluated radioactive material storage.
- (1) The inspectors toured the following areas:
- Low Level Radioactive Waste (LLRW) Storage Pad
- Radioactive Materials Storage Building - Blue Building
- East Warehouse Radioactive Material Storage
- Dry Fuel Storage Pad - ISFSI Horizontal Storage Module (HSM) Pad
- Multipurpose Facility (MPF)
- Spent Fuel Pool Area
The inspectors performed a container check (e.g., swelling, leakage and deformation)on the following various containers:
- LSA Boxes in Blue Building
- 55 Gallon Drums
- Sealands with Dry Active Waste
- Used Oil Drums
- Wooden Boxes
- Radioactive Trash Bags
Radioactive Waste System Walkdown (IP Section 02.02) (1 Sample)
The inspectors evaluated the following radioactive waste processing systems and processes during plant walkdowns:
- (1) Liquid or Solid Radioactive Waste Processing Systems
- Floor Drain Filter System
- Reactor Water Cleanup System
- Condensate Waste Storage System
- Low Level Radioactive Waste Processing
Radioactive Waste Resin and/or Sludge Discharges Processes
- NUPAC Resin Dewatering System
Waste Characterization and Classification (IP Section 02.03) (1 Sample)
The inspectors evaluated the radioactive waste characterization and classification for the following waste streams:
(1)
- CONDWST - WST RESIN/COND RESIN, March 4, 2019
- DAW - DRY ACTIVE WASTE, March 4, 2019
- SPENT - SPENT BEAD RESIN, March 4, 2019
- SCO - Surface Contaminated Equipment, March 4, 2019
- LAUNDRY - Contaminated Laundry, March 4, 2019
- DAW - Dry Active Waste, April 11, 2019
Shipment Preparation (IP Section 02.04) (1 Sample)
The inspectors evaluated and observed the following radioactive material shipment preparation processes:
(1)
- The inspectors were not able to evaluate and observe actual radioactive material shipment preparation processes as no shipments were in process.
The inspectors observed loads of sampled soil being removed from the site which was appropriately surveyed and analyzed. The inspectors also reviewed several shipment packages that included surveys and assessments in preparation for shipment.
Shipping Records (IP Section 02.05) (1 Sample)
The inspectors evaluated the following nonexcepted package shipment records:
(1)
- 17-24, Type A, October 17, 2017
- 17-25, Type A, December 6, 2017
- 17-26, Type A, December 15, 2017
- 18-05, Type A, August 9, 2018
- 18-10, Type A, September 11, 2018
- 18-11, Type A, October 11, 2018
- 18-14, Type A, December 11, 2018
- 19-01, Type B, March 4, 2019
- 19-03, Type B, April 2,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03)===
- (1) July 1, 2018 - June 30, 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
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in emergency preparedness drill classification that might be indicative of a more significant safety issue on August 2, 2019.
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000298/2018-002-00, Lack of Procedural Guidance Results in Work Scheduling Error Causing Breach of Secondary Containment and Condition Prohibited by Technical Specifications (ADAMS Accession No. ML18353A278). The circumstances surrounding this LER and an associated non-cited violation are documented in the Inspection Results section of this report.
INSPECTION RESULTS
Failure to Implement Fire Protection Program Surveillance Requirements for a Fire Barrier Seal Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems
Green NCV 05000298/2019003-01 Open/Closed
[P.1] -
Identification 71111.05Q The inspectors identified a Green, non-cited violation of License Condition 2.C(4), Fire Protection, for the failure to implement all provisions of the approved fire protection program.
Specifically, prior to July 2, 2019, the licensee failed to implement Surveillance Procedure 6.FP.606, Fire Barrier/Penetration Seal Visual Examination, Revision 25, for visual inspection of the cable expansion room west wall fire barrier and its associated MN 46 penetration to ensure that an unsealed penetration opening was identified. As a result, the licensee failed to identify that the conduit seal was degraded until it was discovered by the inspectors on July 2, 2019, and subsequently declared nonfunctional by operations personnel.
Description:
On July 2, 2019, the inspectors toured the cable expansion room, a risk-significant area where safety-related cables from both divisions are routed. The inspectors observed that a 3-inch cable conduit ran about 8 feet from the west wall of the room and opened near one of the cable trays. The west wall of the cable expansion room was an FP1 Technical Requirements Manual (TRM)-required fire barrier. The open end of the conduit had four cables in it, and the inspectors noted that the conduit seal material was missing from about half of the conduit opening. The inspectors reported the degraded seal, labeled MN 46, to the control room. In response, operations and fire protection personnel walked down the seal. After review of applicable procedures and plant drawings, the licensee determined that the required intact smoke and hot gas seal could not be proven to exist.
Because the deficiency represented an unsealed fire barrier penetration, operations personnel declared the FP1 fire barrier that the conduit penetrated nonfunctional under TRM 3.11.7 and implemented the required hourly fire watch.
The inspectors noted that the seal appeared to have been degrading for some period of time prior to discovery and the inspectors noted that the degraded seal should have been identified during inspections required by TRM 3.11.7, Fire Barrier and Fire Wall Penetration Fire Seals, Technical Surveillance Requirement (TSR) 3.11.7.1. TSR 3.11.7.1 states, visually inspect each side of each fire barrier and penetration fire seal (where possible) on a 24-month frequency. The inspectors reviewed the results of the licensees most recently performed TSR inspection, documented in Procedure 6.FP.606, Fire Barrier/Penetration Seal Visual Examination, Revision 25, and performed on August 27, 2018. The inspectors noted that Procedure 6.FP.606 directed plant personnel to inspect the adequacy of the fire barriers and penetration seals via plant drawings and a checklist of the walls in each room. Step 5.1 contained inspection for "all fire barriers" and required verification that there were "no unsealed openings" and "no unsealed penetrations." The inspectors also noted that Fire Protection Program Procedure 3.6.1, "Fire Barrier Control," Revision 21, stated that the internal sealing requirement for a conduit with a diameter of 2-4 inches is a "smoke and hot gas seal within 5 feet of barrier or nearest opening." In addition, Engineering Evaluation (EE)10-055, "Conduit Internal Seals," Revision 0, which was credited in the licensee's NFPA 805 licensing basis contained industry testing data and stated, in part, that larger sized conduits, 3 inches diameter and over, allowed quantities of smoke to pass through the barrier and escape the conduits such that an exposure to sensitive equipment on the non-fire side of the barrier could be postulated. The smoke, if released on the non-fire side, could be expected to affect exposed equipment. The inspectors concluded that the seal contained in conduit MN 46 was a required penetration seal, and the lack of an intact seal should have been identified during performance of Procedure 6.FP.606.
After discussion with fire protection personnel, the inspectors noted that although Surveillance Procedure 6.FP.606 required identification of any unsealed openings and penetrations in fire barriers, the licensee failed to implement the procedure in a manner that ensured unsealed conduit penetrations like MN 46 would be identified. Specifically, although conduit MN 46 penetrated the wall and partially extended out into a room where it opened, plant personnel stated that they only inspected the external seal surrounding the outside of the conduit located at the wall and had not inspected the seal at the opening of the conduit. Fire protection personnel stated that they had determined that this seal was inaccessible and inspection at this location was not possible. After review of Procedure 6.FP.606, the inspectors concluded that the seal in question was accessible. Specifically, Procedure 6.FP.606 defines inaccessible as penetration seals or sections of fire barriers/fire walls that cannot be visually examined due to field configurations, and directs consideration of factors like hazardous material exposures, potential for plant trip or damage to safety equipment, and the need to remove permanent plant equipment to access the seal. The inspectors determined that MN 46 met none of the criteria listed in that it was located in an open area approximately 7 feet from the floor and was easily accessed via normal traversing paths. As a result, the inspectors determined that the licensee had failed to inspect the cable expansion room west wall fire barrier and its associated MN 46 penetration in accordance with TSR 3.11.7.1 and Procedure 6.FP.606.
Corrective Actions: Corrective actions included declaring the fire barrier nonfunctional, implementing TRM requirements for an hourly fire watch, and resealing the degraded penetration seal.
Corrective Action References: Condition Report CR-CNS-2019-03631
Performance Assessment:
Performance Deficiency: The licensees failure to implement fire protection program inspection requirements for an FP1 fire barrier was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Protection Against External Factors attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the performance deficiency resulted in a nonfunctional fire barrier in the cable expansion room, which houses both Division 1 and Division 2 safety-related cabling.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Because the finding involved the ability to confine a fire, the inspectors applied Inspection Manual Chapter 0609, Appendix F, Fire Protection SDP, to determine the findings significance. The inspectors determined that there was an adequate automatic suppression system on either side of the fire confinement element, and therefore, they concluded that the performance deficiency was of very low safety significance (Green).
Cross-Cutting Aspect: P.1 - Identification: The organization implements a corrective action program with a low threshold for identifying issues. Individuals identify issues completely, accurately, and in a timely manner in accordance with the program. Specifically, fire protection personnel failed to identify the need to inspect the conduit seal at the opening of fire barrier penetration MN 46 during fire barrier surveillance inspections and failed to identify that the seal was degraded during walkdowns.
Enforcement:
Violation: License Condition 2.C(4) requires, in part, that, NPPD shall implement and maintain in effect all provisions of the approved fire protection program. TRM 3.11.7, Fire Barrier and Fire Wall Penetration Fire Seals, TSR 3.11.7.1 states, visually inspect each side of each fire barrier and penetration fire seal (where possible) on a 24-month frequency.
Surveillance Procedure 6.FP.606, Fire Barrier/Penetration Seal Visual Examination, Revision 25, implements this TSR and Step 5.1 states, in part, for all fire barriers, verify no unsealed openings and no unsealed penetrations.
Contrary to the above, prior to July 2, 2019, the licensee failed to verify there were no unsealed openings and no unsealed penetrations for all fire barriers. Specifically, the licensee failed to implement Surveillance Procedure 6.FP.606 for visual inspection of the cable expansion room west wall fire barrier and its associated MN 46 penetration to ensure that an unsealed penetration opening was identified. As a result, the licensee failed to identify that the conduit seal was degraded and nonfunctional until it was discovered by the inspectors on July 2, 2019.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Failure to Take Required Actions of Technical Specification 3.5.2 for Reactor Pressure Vessel Water Inventory Control During Secondary Containment Work Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity
Green NCV 05000298/2019003-02 Open/Closed
[H.5] - Work Management 71153 The inspectors documented a self-revealed, Green, non-cited violation of Technical Specification 3.5.2, Reactor Pressure Vessel Water Inventory Control, for the licensees failure to take technical specification required actions during a reactor pressure vessel water inventory control activity. Specifically, on October 10, 2018, during a planned water inventory control activity, the licensee failed to meet Technical Specification 3.5.2, Condition C, when an unplanned and unrecognized breach of secondary containment occurred, and the licensee did not verify secondary containment could be closed as required until the breach was discovered several hours later. In particular, during residual heat removal service water piping work, the penetration of the same residual heat removal service water piping on both the control building and reactor building sides of the secondary containment boundary was not recognized, and as a result, a containment closure plan was not in place.
Description:
During the licensees refueling outage, on September 30, 2018, work orders for residual heat removal service water (RHRSW) piping, located in the control building, were added to an originally approved scope on the same line of RHRSW piping located in the reactor building. When the work was added to the original scope, the licensee did not plan for the repairs to be ongoing simultaneously and, therefore, did not identify the need for a contingency plan to be established for a breach of a secondary containment boundary. On October 10, 2018, Day 11 of the refueling outage, control rod drive mechanism (CRDM)maintenance was ongoing during the RHRSW piping repairs. The CRDM maintenance involved some leakage of reactor pressure vessel (RPV) water during the maintenance activity and was considered a planned water inventory control activity (WICA). Technical Specification (TS) 3.5.2, Reactor Pressure Vessel Water Inventory Control, requires that the drain time of the RPV water inventory to the top of active fuel must be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The licensee calculated the drain time to be 21.62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br /> for the CRDM maintenance. As such, entry into TS Limiting Condition for Operation (LCO) 3.5.2, Condition C, was required. One of the requirements of TS 3.5.2, Condition C, is that the licensee must verify that each secondary containment penetration flow path will be capable of being isolated in less than the drain time within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of LCO entry. Upon entry into the LCO for the CRDM work, at 12:10 a.m. on October 10, 2018, the licensee took action to verify containment closure plans were in place for all secondary containment breaches that plant personnel were aware of.
Containment closure contingency planning is contained in the licensees procedures.
Administrative Procedure 0-CNS-OU-108, Cooper Shutdown Safety Management Program, Revision 6, Section 6.17, contains containment defense in depth considerations that include, in part, maintaining containment closure capability during reduced water inventory operations.
Within that section, Step 6.17.4 references Administrative Procedure 0.50.5, Outage Shutdown Safety, Revision 40, for containment control requirements. Administrative Procedure 0.50.5 states, in part, that during Modes 4 and 5 when containment closure is required, simultaneously breaching both sides of a secondary containment piping penetration requires preplanned means to block off the breach.
On October 10, 2018, at 11:15 a.m., the licensee discovered that both the control building side and the reactor building side of the RHRSW piping were open simultaneously without a preplanned containment closure document (contingency plan) in place and failed to meet the technical specification LCO requirement that was entered for CRDM maintenance. This configuration existed for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> before the breach was secured. The licensee was able to re-establish the boundary in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery and established a containment closure plan for the RHRSW piping work. Had the licensee recognized that the RHRSW piping work was ongoing in both the control building and the reactor building simultaneously during the RPV water inventory control activity, the containment closure plan would have contained these secondary containment penetrations and included them for the verification of flow path isolation capability within the 4-hour time requirement, and the TS violation would not have occurred. However, during the approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> that the condition existed, the licensee was unaware of the breach until discovery at 11:15 a.m., and if containment closure was required during that time, sealing of this breach would not have occurred. This issue was identified through an event reported to the NRC as a condition prohibited by TS in LER 05000298/2018-002-00, Lack of Procedural Guidance Results in Work Scheduling Error Causing Breach of Secondary Containment and Condition Prohibited by Technical Specifications. It was self-revealed in that workers in the vicinity were unable to weld due to the sustained high volume of air flow through the secondary containment breach.
Corrective Actions: The licensee immediately stopped work, re-established the secondary containment boundary within an hour, and established a contingency closure plan for the RHRSW piping repairs.
Corrective Action References: Condition Report CR-CNS-2018-06295
Performance Assessment:
Performance Deficiency: The licensees failure to take actions required by Technical Specification 3.5.2 for reactor pressure vessel water inventory control is a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Configuration Control attribute of the Barrier Integrity Cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the licensee was unaware that there was ongoing work on RHRSW piping in both the control building and reactor building that breached secondary containment. These piping penetrations were not contained in a contingency closure plan and thus not verified to be capable of being isolated within the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> required by TS LCO 3.5.2, Condition C, when performing a reactor pressure vessel water inventory control activity.
Significance: The inspectors assessed the significance of the finding using Appendix G, Shutdown Safety SDP. The inspectors determined that the performance deficiency degraded the ability to close or isolate the containment, and as a result, Appendix G, 1, Exhibit 4, directed entry into Inspection Manual Chapter 0609, Appendix H, Containment Integrity Significance Determination Process. The inspectors applied Appendix H, Section 07.02, Approach for Assessing Type B Findings at Shutdown, Step 2.1, to the finding. At the time of the event, the plant operating status (POS) was POS 3, which represents the Mode 5 shutdown condition when the RPV water level is the minimum level required for movement of irradiated fuel assemblies within the RPV. The inspectors determined that the finding was of very low safety significance (Green) because it:
- (1) did not occur in POS 1 or POS 2;
- (2) did not occur in TW-E (Early Time Window); and
- (3) it did not occur within 8 days of the start of the outage.
Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities. Specifically, the licensee failed to implement a process of planning, controlling, and executing work, resulting in a breach of secondary containment that was not recognized as a secondary containment penetration that needed to be verified to be capable of isolation by TS 3.5.2, Condition C, for the RPV water inventory control activity.
Enforcement:
Violation: Technical Specification (TS) 3.5.2, RPV Water Inventory Control, requires, in part, that in Modes 4 and 5, drain time of RPV water inventory to the top of active fuel (TAF)shall be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The TS action statement requires that, with Drain time < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, verify each secondary containment penetration flow path is capable of being isolated in less than the drain time within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or initiate action to restore drain time to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> immediately.
Contrary to the above, on October 10, 2018, for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, while in Mode 5, the licensee failed to ensure the drain time of RPV water inventory to the TAF was 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or take the required actions. Specifically, with the drain time of < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the licensee failed to verify each secondary containment penetration flow path was capable of being isolated in less than the drain time within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or initiate action to restore drain time to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> immediately. In particular, improperly sequenced RHRSW work created an unplanned and unrecognized breach of secondary containment, which resulted in the licensee failing to identify the need to take the TS required actions.
Enforcement Action: This violation is being treated as a 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 August 22, 2019, the inspectors presented the Public Radiation Safety Cornerstone inspection results to Mr. J. Sullivan, General Manager Plant Operations, and other members of the licensee staff.
- On September 19, 2019, the inspectors presented the Evaluations of Changes, Tests, and Experiments inspection results to Mr. J. Sullivan, General Manager of Plant Operations, and other members of the licensee staff.
- On October 17, 2019, the inspectors presented the integrated inspection results to Mr. J. Sullivan, General Manager Plant Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.04Q Drawings
2006, Sheet 4
Flow Diagram Control Building Service Water System
71111.04Q Drawings
2036, Sheet 1
Flow Diagram Reactor Building Service Water System
A6
71111.04Q Drawings
2043
Flow Diagram Reactor Core Isolation Coolant and Reactor
Feed Systems
71111.04Q Drawings
2045, Sheet 1
Flow Diagram Core Spray System
N58
71111.04Q Procedures
2.2.67
Reactor Core Isolation Cooling System
71111.04Q Procedures
2.2.67.1
Reactor Core Isolation Cooling System Operations
71111.04Q Procedures
2.2.67A
Reactor Core Isolation Cooling System Component Checklist
71111.04Q Procedures
2.2.67B
Reactor Core Isolation Cooling System Instrument Valve
Checklist
71111.04Q Procedures
2.2.74A
Standby Liquid Control System Component Checklist
71111.04Q Procedures
2.2.74B
Standby Liquid Control System Instrument Valve Checklist
71111.04Q Procedures
2.2.9
Core Spray System
71111.04Q Procedures
2.2A.CS.DIV2
Core Spray Component Checklist (DIV 2)
71111.04Q Procedures
2.2A.RHRSW.DIV1 RHR Service Water Booster Pump System Component
Checklist
71111.04Q Procedures
2.2B.CS.DIV2
Core Spray System Instrument Valve Checklist (DIV 2)
71111.04Q Procedures
2.2B.RHRSW.DIV1 RHR Service Water Booster Pump System Instrument Valve
Checklist
71111.04Q Work Orders
71111.05Q Corrective Action
Documents
CR-CNS-
2019-03631
71111.05Q Engineering
Evaluations
EE 10-055
Conduit Internal Seals
71111.05Q Fire Plans
CNS-FP-136
Fire Area Boundary Drawing
71111.05Q Fire Plans
CNS-FP-212
Reactor SE Quad, Elevations 881 and 859
71111.05Q Fire Plans
CNS-FP-285
Fire Barrier Penetration Seal Details
71111.05Q Miscellaneous
CNS-FP-234
Office Building Cable Expansion Room Elevation 918 6
71111.05Q Miscellaneous
CNS-FP-39
Reactor Building Suppression Pool Elevation 859-9
71111.05Q Miscellaneous
NEDC 10-080
Fundamental Fire Protection Program and Design Elements
Review
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05Q Procedures
0-BARRIER-MAPS
Barrier Maps
71111.05Q Procedures
0-BARRIER-MAPS
Barrier Maps
71111.05Q Procedures
0-BARRIER-
REACTOR
71111.05Q Procedures
0.7.1
Control of Combustibles
71111.05Q Procedures
3.6.1
Fire Barrier Control
71111.05Q Procedures
6.FP.606
Fire Barrier/Penetration Seal Visual Examination
Corrective Action
Documents
CR-CNS-
2017-00229, 2019-02931, 2019-04268, 2019-05066, 2019-
271, 2019-05283
Procedures
0-BARRIER
Barrier Control Process
Procedures
0-BARRIER-
REACTOR
71111.11Q Miscellaneous
RMP 31-013
Quarterly Downpower, 10-EN-RE-215/6CO, Att 2
71111.11Q Procedures
10.13
Control Rod Sequence and Movement Control
71111.11Q Procedures
10.9
Control Rod Scram Time Evaluation
71111.11Q Procedures
2.0.3
Conduct of Operations
2
Corrective Action
Documents
CR-CNS-
2018-07835, 2019-02127, 2019-02581, 2019-03265, 2019-
03488, 2019-03501, 2019-03934, 2019-03936, 2019-04317,
2019-04336, 2017-04701
Engineering
Evaluations
EE-PF02F
Maintenance Rule Function EE-PF02F Performance Criteria
Basis
Miscellaneous
Maintenance Rule (a)(1) Evaluation RCIC-PF01 - RCIC
System
0, 1
Miscellaneous
8001553-1
Turbine Control Schematic
Miscellaneous
RCIC-PF01
Maintenance Rule Function RCIC-PF01 Performance Criteria
Basis
Procedures
3-EN-DC-206
Maintenance Rule (a)(1) Process
3C3
Procedures
6.2HV.601
Air Flow Test of Fan Coil Unit FC-R-1E (DIV 2)
Work Orders
Corrective Action
Documents
CR-CNS-
2019-03936, 2019-03947, 2019-03964, 2019-04218, 2019-
04347
Drawings
18-900# Gate Valve - R.S.-Press Seal Cast STL WCB -
Stellite Trim - B.W. Ends SMB-2 (60#) Motor Operator
760-3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Critical Evolutions Meeting Presentation - RF-MOV-29MV
Reactor Feed Pump A Discharge Valve, Packing Gland
Leak Injection
Miscellaneous
Risk Management Plan - RF-MOV-29MV Reactor Feed
Pump A Discharge Valve, Packing Gland Leak Injection
Miscellaneous
Protected Equipment Tracking Form - ESST Planned Work
Window
08/21/2019
Miscellaneous
Protected Equipment Tracking Form - SLC A LCO
07/08/2019
Miscellaneous
Protected Equipment Tracking Form - Core Spray B 1933
Maintenance Window
08/13/2019
Miscellaneous
Protected Equipment Tracking Form - RCIC inoperable
07/24/2019
Miscellaneous
284609-03
Work Plan, RF-MOV-29MV
Miscellaneous
284609-05
Work Plan, RF-MOV-29MV
Procedures
0-CNS-WM-104
Online Schedule Risk Assessment
Procedures
0-CNS-WM-104
1, Risk Characterization, for WO 5284609-5
Procedures
0-PROTECT-EQP
Protected Equipment Program
Work Orders
WO 201509, 5209480, 5211242, 5211244, 5211377, 5211509,
284609-Rev. 3, 5284609-Rev. 5, 5309711
Corrective Action
Documents
CR-CNS-
2017-04701, 2019-02127, 2019-03189, 2019-03478, 2019-
03860, 2019-03889, 2019-03934, 2019-03936, 2019-04317,
2019-04336
Drawings
2040, Sheet 2
Flow Diagram - Residual Heat Removal Sys Loop B
Engineering
Evaluations
EE 10-073
Deletion of Type C Testing of One Barrier due to Closed Loop
Analysis for 9 Pens
Miscellaneous
CNS Original Custom Technical Specifications
Miscellaneous
LO 2019-0045
Part 21 Issue
06/07/2019
Miscellaneous
USQE-1999
Combine Table V-2-7 and Table VII-3-1
Procedures
6.2HV.601
Air Flow Test of Fan Coil Unit FC-R-1E (DIV 2)
Procedures
6.2SW.401
Diesel Generator Service Water Check Valve and Sump Test
(IST) (DIV 2)
Work Orders
WO 5166780, 5196337, 5312924
Calculations
NEDC 92-064
Transient Temperature Rise in SWBP Room After Loss of
Cooling
Calculations
NEDC 94-034B
CNS Containment System Response for NPSH Analysis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
NEDC 97-044A
NPSH Margins for the RHR and CS Pumps
Calculations
NEDC 97-044D
RHR and HPCI NPSH Margins for ATWS Event
Corrective Action
Documents
CR-CNS-
2019-02345, 2019-02364, 2019-03587, 2019-03790, 2019-
03880, 2019-04668
Corrective Action
Documents
Resulting from
Inspection
CR-CNS-
2019-04959
Drawings
CNS-EE-319
SSST OPP Cabinets #1 and #2 Connection Diagram
Drawings
3001
Main One Line Diagram
Drawings
3006, Sh. 5
Auxiliary One Line Diagram MCC Z, SWGR Bus 1A, 1B, 1E,
& Critical SWGR Bus 1F 1G
Drawings
3006, Sh. 5
Auxiliary One Line Diagram Starter Racks LZ and TZ MCCs
K, L, LX, RA, RX, S, T, TX, X
Drawings
3017, Sh. 1
4160V Switchgear Elementary Diagrams
Drawings
20, Sh. 4
4160V Switchgear Elementary Diagrams
Drawings
3031, Sh. 3
Control Elementary Diagrams Switch Developments
Drawings
3040, Sh. 9
Control Elementary Diagram
Drawings
253, Sh. DT4
460V Motor Control Centers Wiring Details, Connection
Wiring Diagram
Drawings
3700, Sh. 19
Annunciator Elementary Ladder Diagram
N09
Drawings
791E271, Sh. 6
HPCI System Elementary Diagram
Drawings
CNS-EE-320
ESST OPP Cabinets #1 and #2 Connection Diagram
Drawings
IL-E-70-3, Sh.
107B
Area Temp. Monitoring System for Nuclear Boiler Systems
Leak Detection
Drawings
IL-E-70-3, Sh.
107BB
Area Temperature Monitoring System for Nuclear Boiler
Systems Leak Detection
Drawings
NC 02161
One-line Switching Diagram 345KV/161KV/4160V
Drawings
NC 43456
Cooper 161kV Substation One-line Switching Diagram
Drawings
NC 66688
Cooper 345kV Substation One-line Switching Diagram
Drawings
OPP-ELE-B101,
Pg. 1 of 18
Open Phase Detection and Protection System
Drawings
OPP-ELE-B101,
Pg. 2 of 18
Open Phase Detection and Protection System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
OPP-ELE-B101,
Sh. 3 of 18
Open Phase Detection and Protection System
Drawings
OPP-ELE-B101,
Sh. 4 of 18
Open Phase Detection and Protection System
Drawings
OPP-ELE-B101,
Sh. 5
Open Phase Detection and Protection System
Drawings
OPP-ELE-B101,
Sh. 6
Open Phase Detection and Protection System
Drawings
OPP-ELE-B101,
Sh. 7
Open Phase Detection and Protection System
Drawings
OPP-ELE-B101,
Sh. 8 of 18
Open Phase Detection and Protection System
Drawings
SKE-EC-
6016502-3
HPCI Flow Control Wiring Diagram
Engineering
Changes
DEC 5243039
Emergency Diesel Generator Indicating Light Isolation
Engineering
Changes
HPCI Flow Control
Engineering
Changes
Main Generator Under Frequency Relay Replacement
Engineering
Changes
SWBP Oil Sight Glasses and Reservoir
Engineering
Evaluations
EE 16-021
Engineering Evaluation for 161KV Low Voltage Limit
Engineering
Evaluations
EE 16-048
Engineering Evaluation MCC-L and MCC-T to Non-Essential
Engineering
Evaluations
EE 18-012
Re-Evaluation of Torus Inspection Frequency During Period
of Extended Operation
Engineering
Evaluations
EE 18-028
Various MOV Packing Load Adjustment Calculation
Revisions
Engineering
Evaluations
EE 18-045
HPCI LOC HX Thermal Performance and Tube Plugging
Margin
Engineering
Evaluations
EE 18-046
RHR and HPCI NPSH Margins for ATWS Event
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Evaluations
EE 19-018
REC HX Allowable Tube Plugging Increase
Engineering
Evaluations
EE-18-021
Engineering Evaluation for Reclassifying Relays
HV-REL-1CFX and HV-REL-1DFX to Non-Essential
15C11
Engineering
Evaluations
MDE-270-1285
Evaluation of ATWS Performance at Cooper Nuclear Station
December
1985
Miscellaneous
CDA-EE-001-C1
Control Group Assessment - Open Phase Protection System
Controller (CRIO-9068)
Miscellaneous
CDA-EE-001-ES
Control Group Assessment - Open Phase Protection System
Injection Source
Miscellaneous
CDA-EE-001-ES1
Control Group Assessment - Open Phase Protection System
DC Power Supply
Miscellaneous
CDA-EE-001-KP
Control Group Assessment - Open Phase Protection System
Keypad
Miscellaneous
CDA-EE-001-R
Control Group Assessment - Open Phase Protection System
Recorder
Miscellaneous
CDA-EE-001-REL
Control Group Assessment - Open Phase Protection System
Current Switch
Miscellaneous
CDA-EE-001-UPS
Control Group Assessment - Open Phase Protection System
Miscellaneous
CDA-EE-0013
Functional Description and Consequence Analysis
Miscellaneous
IEGR-MN-699
Vendor Manual Open Phase Protection (OPP) System
Operating and Maintenance Manual
1.03
Miscellaneous
NLS2018053
l0 CFR 50.59(dX2) and 10 CFR 72.48(dX2) Summary Report
Cooper Nuclear Station, Docket No. 50-298, License
No. DPR-46
10/08/2018
Miscellaneous
RCE 2017-07513
Both EDGs Declared Inoperable Due to Test Failure of Spare
Indicating Light
Procedures
0-CNS-LI-100
Process Applicability Determination
Procedures
0-CNS-LI-101
CFR 50.59 Evaluations
Procedures
0-CNS-LI-112
CFR 72.48 Evaluations
Procedures
0-EN-HU-106
Procedure and Work Instruction Use and Adherence
3C2
Procedures
2.0.1.3
Time Critical Operator Action Control and Maintenance
Procedures
2.1.11.1
Turbine Building Data
178
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
2.2.70
RHR Service Water Booster Pump System
Procedures
2.3_R-1
Alarm Procedure for Panel R - Annunciator R-1
Procedures
2.4HVAC
Computer Room Ventilation Failure/Temperature High
Procedures
3-ED-DC-167
Classification of Structure, Systems, and Component
4C2
Procedures
3-EN-DC-115
Engineering Change Process
15C14
Procedures
6.1EE.302
4160V Bus 1F Undervoltage Relay and Relay Timer
Functional Test (DIV 1)
Procedures
6.1EE.306
4160V Bus 1F Undervoltage Relay Channel Functional Test
(DIV 1)
Procedures
7.2.14
RHR SWBP Overhaul and Replacement
Procedures
7.3.41
Examination, Repair, High Pot Testing of Non-Segregated
Buses and Associated Equipment
Procedures
IP-ENG-001
Standard Design Process
0C0
Self-Assessments 2019-0098
50.59 Pre-Inspection Focused Self-Assessment
Self-Assessments QAD 2018-008
QA Audit 18-02, "Engineering"
03/27/2018
Corrective Action
Documents
CR-CNS-
2017-04701, 2019-03889, 2019-04141, 2019-04142, 2019-
209, 2019-04222, 2019-04317, 2019-04336
Miscellaneous
SW-CV-37 Leakage Troubleshooting Plan
Miscellaneous
11628207
Notification
Procedures
2.2.8
Control Rod Drive System
106
Procedures
6.2CS.101
Core Spray Test Mode Surveillance Operation (IST) (DIV 2)
Procedures
6.2CS.201
CS Motor Operated Valve Operability Test (IST) (DIV 2)
Procedures
6.2HV.601
Air Flow Test of Fan Coil Unit FC-R-1E (DIV 2)
Procedures
6.2SW.401
Diesel Generator Service Water Check Valve and Sump Test
(IST) (DIV 2)
Procedures
6.CRD.201
North and South SDV Vent and Drain Valve Cycling, Open
Verification, and Timing Test
Procedures
6.SC.501
Secondary Containment Leak Test
Procedures
6.SC.502
Secondary Containment Penetration Examination
Procedures
7.0.10
Railroad Airlock Door Operations
Procedures
7.0.5
Post-Maintenance Testing
Work Orders
WO 201509, 5209480, 5210423, 5211242, 5211244, 5211377,
265105, 5309143, 5312924
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-CNS-
2019-23824
Miscellaneous
2174
Vendor Manual - Mohr SFP-1 Level Prove Assembly
Technical Manual
2/13/2015
Procedures
14.41.1.2
FPC-LIT-2 Testing
Procedures
2.2.32
Fuel Pool Cooling and Demineralizer System
105
Procedures
2.2.84
HVAC Main Control Room and Cable Spreading Room
Procedures
6.2DG.101
Diesel Generator 31 Day Operability Test (IST) (DIV 2)
Procedures
6.HV.105
Control Room Envelope Pressurization and CREFS Flow
Test
Procedures
6.REC.201
REC Motor Operated Valve Operability Test (IST)
Work Orders
WO 5195163, 5234083
Miscellaneous
Drill Scenario Guide
07/30/2019
Calibration
Records
5149599
Area Radiation Monitors Calibration and Functional Test
09/20/2018
Calibration
Records
5156820
SW Radiation Monitor - B Calibration Check and Instrument
Channel Test - RMP-RM-332B
05/16/2018
Calibration
Records
5166729
High Range Containment Monitor Victoreen Model 875
Source Calibration Check
10/03/2018
Calibration
Records
5166732
Containment High Range Monitors A/R/H Determination
10/03/2018
Calibration
Records
5166734
Main Steam Line Process Radiation Monitor Channel
Calibration, Source Test, and Setpoint Determination
RMP-RM-251A/B/C/D Data Sheets
10/04/2018
Calibration
Records
5167782
Containment High Range Area Monitor Channel Calibration
RMA-RM-40 A/B
08/29/2018
Calibration
Records
5167787
Main Steam Line Process Radiation Monitor Channel
Calibration, Source Test, and Setpoint Determination
RMP-RM-251A/B/C/D Data Sheets
09/11/2018
Calibration
Records
5186806
REC Radiation Monitor Calibration Check and Instrument
Channel Test
05/01/2019
Calibration
Records
Detector 1
Inch Particulate Filter at 5 cm
05/03/2017
Calibration
Detector 1
2000 ml Marinelli with 1.5 Density
05/17/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Records
Calibration
Records
Detector 1
500 cc Charcoal Marinelli
10/05/2018
Calibration
Records
Detector 1
Charcoal Cartridge at 5 cm
05/05/2017
Calibration
Records
DG11095729
Tri-Carb 2910TR Efficiency Calibration
2/28/2019
Calibration
Records
RP-10571
Instrument Calibration Sheet (PCM-2) S/N 401
07/03/2019
Calibration
Records
RP-10588
RMV-CAM-20 Particulate & Iodine Calibration Sheets
03/27/2019
Calibration
Records
RP-10765/11497
Instrument Calibration Data Sheet - AMS-4
01/19/2019
Calibration
Records
RP-10848
XLB Calibration Data Sheet - Unit 1
01/23/2019
Calibration
Records
RP-11152
Instrument Calibration Sheet Thermo Eberline SAM
Contamination Monitor
05/22/2019
Calibration
Records
RP-11178
PM-12 Calibration Data Sheet S/N 0902PM1207
06/11/2018
Calibration
Records
RP-11241
Instrument Calibration Data Sheet - DRM-1 or DRM-2
06/25/2019
Calibration
Records
RP-11376
Instrument Calibration Data Sheet - RO-20
2/14/2019
Calibration
Records
RP-11724
Instrument Calibration Data Sheet - H-809V1
06/10/2019
Corrective Action
Documents
CR-CNS-
2017-06407, 2017-06689, 2018-03723, 2018-05687, 2018-
06543, 2018-08139, 2019-00818, 2019-00866, 2019-00880,
2019-01310, 2019-01442, 2019-02130, 2019-02362, 2019-
2669
Miscellaneous
PCM-2 Weekly Source Checks
08/18/2019
Miscellaneous
PM-7/PM-12 Daily/Weekly Source Checks
08/20/2019
Miscellaneous
SAM-11 / SAM-12 Weekly Functional Checks
08/18/2019
Miscellaneous
06/2019
Miscellaneous
Results of Radiochemistry Cross Check Program (Quarterly
2/13/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Results)
through
06/05/2019
Miscellaneous
878-10
Source Calibration Certificate (S/N 135)
06/26/2003
Miscellaneous
878-10A
Source Calibration Certificate (S/N 126)
09/24/2003
Miscellaneous
878-10B
Source Calibration Certificate (S/N 121)
09/18/2003
Procedures
15.ARM.302
Area Radiation Monitors Calibration and Functional Test
Procedures
6.PRM.322
Containment High Range Area Monitor Channel Calibration
Procedures
6.PRM.323
High Range Containment Monitor Victoreen Model 875
Source Calibration Check
Procedures
6.PRM.324
Main Steam Line Process Radiation Monitor Channel
Calibration, Source Test and Setpoint Determination
Procedures
6.PRM.326
Drywell Air Sampling System Known Source Calibration and
Functional Test
Procedures
6.PRM.329
Containment High Range Monitors A/R/H Determination
Procedures
6.PRM.331
SW Radiation Monitor A Calibration Check and Instrument
Channel Test
Procedures
8-CNS-CY-102
Laboratory Analytical Quality Control
Procedures
8-CNS-CY-110
Canberra APEX Gamma Spectroscopy System Operation
Procedures
8.5.2.4
Tri-Carb 2910TR Liquid Scintillation System
Procedures
9.INST.15
Rem 500 Neutron Survey Meter
Procedures
9.INST.53
Ion Chamber Survey Instrument Eberline Model RO-20
Procedures
9.INST.57
Friskers
Procedures
9.INST.64
Thermo Electron Corporation Small Articles Monitor (SAM)
Procedures
9.INST.68
WR Telepole GM Survey Instrument
Self-Assessments LO 2018-0186-04
Radiological Monitoring Instrumentation and Radioactive
Solid Waste Processing and Radioactive Material Handling,
Storage, and Transport
05/17/2019
Self-Assessments QAD 2018-019
QA Audit 18-05, "Radiological Controls"
08/23/2018
Corrective Action
Documents
CR-CNS-
2017-04647, 2017-05654, 2017-05888, 2017-06574, 2018-
00199, 2018-02613, 2018-03046, 2018-03588, 2018-04125,
2018-04354, 2018-04569, 2018-04936, 2018-05167, 2018-
07906, 2018-07922, 2019-01916, 2019-02850, 2019-02904,
2019-03082, 2019-03460, 2019-03497, 2019-03946
Miscellaneous
Teledyne Brown Engineering Environmental Services
07/20/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Laboratory Quality Control Program: 2nd Quarter 2019
Quality Assurance Report
Miscellaneous
Teledyne Brown Engineering Environmental Services
Laboratory Quality Control Program: 4th Quarter 2018 Quality
Assurance Report
2/04/2019
Miscellaneous
20-AUG-19-
210006
Gama Spectrum Analysis: ERP Particulate
08/20/2019
Miscellaneous
Liquid Radioactive
Waste Discharge
Form
Liquid Radioactive Waste Discharge Form: Floor Drain
Sample Tank (FDST)
08/17/2018
Miscellaneous
Liquid Radioactive
Waste Discharge
Form
Liquid Radioactive Waste Discharge Form: Floor Drain
Sample Tank (FDST)
11/17/2018
Miscellaneous
Liquid Radioactive
Waste Discharge
Form
Liquid Radioactive Waste Discharge Form: Floor Drain
Sample Tank (FDST)
2/31/2018
Miscellaneous
Liquid Radioactive
Waste Discharge
Form
Liquid Radioactive Waste Discharge Form: Floor Drain
Sample Tank (FDST)
03/27/2019
Miscellaneous
Liquid Radioactive
Waste Discharge
Form
Liquid Radioactive Waste Discharge Form: Floor Drain
Sample Tank (FDST)
04/02/2019
Miscellaneous
Liquid Radioactive
Waste Discharge
Form
Liquid Radioactive Waste Discharge Form: Floor Drain
Sample Tank (FDST)
05/25/2019
Miscellaneous
Liquid Radioactive
Waste Discharge
Form
Liquid Radioactive Waste Discharge Form: Floor Drain
Sample Tank (FDST)
07/03/2019
Miscellaneous
LO-2018-0186-008
Liquid and Gaseous Effluents Focused Self-Assessment
Report
06/05/2019
Miscellaneous
NUPIC Audit
24791
NUPIC Audit/Survey: Teledyne Brown Engineering-
Environmental Services
05/09/2019
Miscellaneous
NUPIC Audit:
24391
NUPIC Audit/Survey: NCS Corporation
03/30/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Cooper Nuclear Station Offsite Dose Assessment Manual for
Gaseous and Liquid Effluents
10/03/2018
Miscellaneous
2018 Annual Land Use Census
07/16/2018
Miscellaneous
QAD 2017-0031
Quality Assurance (QA) Audit 17-07: "Chemistry and
Radiological Effluent and Environmental Monitoring Program"
10/11/2017
Procedures
6.1SGT.501
SGT A Carbon Sample, Carbon Absorber and HEPA Filter In-
Place Leak Test, and Components Leak Test (DIV 1)
Procedures
6.2SGT.501
SGT B Carbon Sample, Carbon Absorber and HEPA Filter In-
Place Leak Test, and Components Leak Test (DIV 2)
Procedures
6.HV.104
Control Room Emergency Filter System Flow Test, Charcoal
and HEPA Filter Leak Test, Filter DP Test, and Charcoal
Sample Analysis
Procedures
6.PRM.306
Liquid Radwaste Effluent Flow Monitor Channel Calibration
Procedures
6.PRM.308
Liquid Radwaste Effluent System Channel Calibration
Procedures
6.PRM.310
ERP Kaman Monitor Channel Calibration
Procedures
6.PRM.313
Reactor Building Kaman Monitor Channel Calibration
Procedures
6.PRM.320
Radwaste Building Kaman Monitor Channel Calibration
Procedures
6.PRM.328
Kaman Sample Flow System Channel Calibration
Procedures
8-CNS-CY-102
Laboratory Analytical Quality Control
Procedures
8.11.1
EFFECTS Program
Procedures
8.8.1.19
Effluent Composite Sample Preparation and Analysis
Procedures
8.8.11
Liquid Radioactive Waste Discharge Authorization
Procedures
8.8.ERP
Particulate and Iodine Sample Collection for ERP Effluent
Procedures
8.8.RW
Particulate and Iodine Sample Collection for Radwaste
Building Effluent
Procedures
8.8.RX
Particulate and Iodine Sample Collection for Reactor Building
Effluent
Procedures
8.8.TB
Particulate and Iodine Sample Collection for Turbine Building
Effluent
Work Orders
WO 28538, 5034888, 5043642, 5078036, 5078037, 5080852,
5094262, 5114291, 5119827, 5123375, 5132845, 5147008,
5149663, 5166229, 5166230, 5180017, 5183064, 5189063,
5191559, 5202504, 5226340, 5285586
Calibration
7318
Sample Station No. 7 Pump
04/10/19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Records
Calibration
Records
7319
Sample Station No. 2 Pump
04/23/19
Calibration
Records
21
Sample Station No. 111
04/10/19
Calibration
Records
7453
Sample Station No. 8
Calibration
Records
7454
Sample Station No. 10
04/10/19
Calibration
Records
7455
Sample Station No. 1 Pump
04/10/19
Calibration
Records
7539
Sample Station No. 9
04/10/19
Corrective Action
Documents
CR-CNS-
2017-06303, 2017-06091, 2017-06726, 2018-00145, 2018-
00508, 2018-00643, 2018-01230, 2018-01646, 2018-02826,
2018-03600, 2018-04300, 2018-07515, 2019-01684, 2019-
2054, 2019-02653, 2019-02693, 2019-02772, 2019-02966,
2019-03245
Miscellaneous
2018 Land Use Census
07/11/18
Miscellaneous
2018 Cooper Nuclear Station Radioactive Effluent Release
Report
2018
Miscellaneous
2017 Cooper Nuclear Station Radioactive Effluent Release
Report
2017
Miscellaneous
Cooper Radiological Environmental Monitoring Program
2017 Annual Report
2/31/17
Miscellaneous
Cooper Radiological Environmental Monitoring Program
2017 Annual Report
2/31/18
Miscellaneous
2019 Land Use Census
07/15/19
Procedures
8.ENV.1
CNS Radiological Environmental Monitoring Program
Administration
Procedures
8.ENV.4
CNS Environmental Air Pump Calibration and Maintenance
Procedures
8.ENV.5
Annual Review of Broadleaf Vegetation Sample Locations
Procedure
Procedures
8.ENV.8
Administering the CNS Meteorological Program (CNS MET)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
8.ENV.9
Ground Water Monitoring Program Sampling, Monitoring, and
Administrative Requirements
Procedures
14.MET.304
Meteorological Maintenance Procedure for New 100-Meter
Tower - System A
Procedures
14.MET.305
Meteorological Maintenance Procedure for New 100-Meter
Tower - System B
Procedures
8.ENV.2
REMP Sampling
Procedures
8.ENV.3
Action Levels for Environmental Samples
Self-Assessments
CNS Environmental Program Self-Assessment Support in
Advance of NRC Inspection
07/24/19
Self-Assessments
Cooper Nuclear Station 2018 Environmental Assessment
07/26/18
Self-Assessments LO Number: 2018-
0186-008 -
Assessment
Report
Radiological Environmental Monitoring Program Focused
Self-Assessment Report
06/06/19
Self-Assessments NUPIC
Audit/Survey
Number: 24229
Duke Energy / NUPIC QA Audit of GEL Laboratories -
October 2016
11/01/16
Self-Assessments NUPIC
Audit/Survey
Number: 24791
Radioanalytical Laboratory Audit Report: Teledyne Brown
Engineering-Environmental Services
04/19/19
Self-Assessments SS17-009
4500187675 "2016-2018 Environmental TLD Service"
11/06/17
Corrective Action
Documents
CR-CNS-
2017-02377; 2017-06224; 2017-06352; 2018-00572; 2019-
01039; 2019-02631
Corrective Action
Documents
Resulting from
Inspection
CR-CNS-
2019-04451; 2019-04462
Miscellaneous
Gamma Spectrum Analysis of ERP Tower Silt
07/31/2019
Miscellaneous
2017 Cooper Nuclear Station Radioactive Effluent Release
Report
2017
Miscellaneous
2018 Cooper Nuclear Station Radioactive Effluent Release
Report
2018
Miscellaneous
Onsite Radioactive Material Storage Areas
08/05/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Offsite Radioactive Material Storage Inventory
05/20/2019
Miscellaneous
Radioactive Material Storage Building Inventory
08/06/2019
Miscellaneous
Top Ten Equipment Reliability Action Plan - Radwaste
System Reliability
08/05/2019
Miscellaneous
469062001
Waste Stream Analysis for Dry Active Waste
11/14/2018
Miscellaneous
CNS-RP-602
CNS Radioactive Material Shipment Log - 2017
2017
Miscellaneous
CNS-RP-602
CNS Radioactive Material Shipment Log - 2018
2018
Miscellaneous
CNS-RP-602
CNS Radioactive Material Shipment Log - 2019
2019
Procedures
0.PCP.1
Procedures
2.5.4.4
NUPAC Dewatering System
Procedures
59.RW.10
Physical Protection of Category I Quantities of Radioactive
Material in Transit
Procedures
9.ENN-RP-106-1
Radiation and Contamination Surveys
Procedures
9.RADOP.10
Radioactive Source Control and Accountability
Procedures
9.RADOP.14
Off-Site Radioactive Material Storage
Procedures
9.RW.1
Radioactive Shipments
Procedures
9.RW.3
Dry Radioactive Waste Classification/Listing and Radioactive
Material Shipments
Procedures
9.RW.5
Control of On-Site Storage of RWCU and Condensate Resins
and Wastes (Transfer Out of Storage)
Procedures
9.RW.6
Control of On-Site Dry Active Waste Storage
Procedures
9.RW.7
Waste Stream Sampling
Procedures
9.RW.9
Filling Containers with Waste/Radioactive Material
Radiation
Surveys
Underwater Survey of Spent Fuel Pool
04/11/2019
Radiation
Surveys
OCA 903' - Rad Material Storage Building
06/04/2019
Radiation
Surveys
Multipurpose Facility (MPF) 903'
06/25/2019
Radiation
Surveys
Horizontal Storage Module (HSM) ISFSI Pad
07/08/2019
Radiation
Surveys
Horizontal Storage Module (HSM) ISFSI Pad Top View
07/08/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
CNS-RP-138
Alpha/Beta Smear Count Quarterly Survey of Offsite RAM
Storage
05/08/2019
Radiation
Surveys
CNS-RP-508
Low Level Radwaste Storage Building
03/20/2019
Self-Assessments
Annual Review of 10 CFR Part 37 Transportation Security
Plan, Hittman Transport, 2018
07/23/2018
Self-Assessments LO-2018-0186-04
Self-Assessment: Radiological Monitoring Instrumentation
and Radioactive Solid Waste Processing and Radioactive
Material Handling, Storage, and Transport
04/17/2019
Self-Assessments QA 18-05
Radiological Controls Quality Assurance Audit
08/23/2018
Shipping Records 17-24
UN3321 RAM - LSA II, Fissile-Excepted, 7, RQ, Spent Resin
10/17/2017
Shipping Records 17-25
UN3321 RAM - LSA II, Fissile-Excepted, 7, Dry Active Waste
2/06/2017
Shipping Records 17-26
UN2912 RAM - LSA I, Fissile-Excepted, 7, RQ, Dry Active
Waste
2/15/2017
Shipping Records 18-05
UN2912 RAM - LSA I, Fissile-Excepted, 7, RQ, Dry Active
Waste
08/09/2018
Shipping Records 18-10
UN3321 RAM - LSA II, Fissile-Excepted, 7, Spent Resin
09/11/2018
Shipping Records 18-11
UN3321 RAM - LSA II, Fissile-Excepted, 7, Dry Active Waste
10/11/2018
Shipping Records 18-14
UN3321 RAM - LSA II, Fissile-Excepted, 7, Dry Active Waste
2/11/2018
Shipping Records 19-01
UN2916 RAM - Type B(U), Fissile-Excepted, 7, RQ, Spent
Resin
03/04/2019
Shipping Records 19-03
UN2916 RAM - Type B(U), Fissile-Excepted, 7, RQ, Spent
Resin
04/02/2019
71151
Miscellaneous
3Q18 thru 4Q19 PI Verification Package - Complicated
Corrective Action
Documents
CR-CNS-
2018-08615, 2019-00171, 2019-01287, 2019-02281, 2019-
2371, 2019-02739, 2019-02791, 2019-02798, 2019-02842,
2019-02875, 2019-04219
Corrective Action
Documents
CR-CNS-
2018-06295
Miscellaneous
CNS Operations Log
10/09/2018
Miscellaneous
CNS Operations Log
10/10/2018
Miscellaneous
LER 2018-002-00
Lack of Procedural Guidance Results in Work Scheduling
Error Causing Breach of Secondary Containment and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Condition Prohibited by Technical Specifications
Procedures
0-CNS-OU-108
Cooper Shutdown Safety Management Program
Procedures
0-CNS-WM-102
Work Implementation and Closeout
10, 11
Procedures
0.50.5
Outage Shutdown Safety
Procedures
0.Barrier
Barrier Control Process
Work Orders
WO 267091, 5267093