IR 05000254/2019003
| ML19304B518 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/31/2019 |
| From: | Kenneth Riemer NRC/RGN-III |
| To: | Bryan Hanson Exelon Generation Co |
| References | |
| IR 2019003 | |
| Download: ML19304B518 (16) | |
Text
October 31, 2019
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000254/2019003 AND 05000265/2019003
Dear Mr. Hanson:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Quad Cities Nuclear Power Station, Units 1 and 2. On October 1, 2019, the NRC inspectors discussed the results of this inspection with Mr. P. Boyle, Acting Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)
consistent with Section 2.3.2 of the Enforcement Policy.
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/
Kenneth R. Riemer, Chief Branch 1 Division of Reactor Projects
Docket Nos. 05000254 and 05000265 License Nos. DPR-29 and DPR-30
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000254 and 05000265
License Numbers:
Report Numbers:
05000254/2019003 and 05000265/2019003
Enterprise Identifier: I-2019-003-0061
Licensee:
Exelon Generation Company, LLC
Facility:
Quad Cities Nuclear Power Station, Units 1 and 2
Location:
Cordova, IL
Inspection Dates:
July 01, 2019 to September 30, 2019
Inspectors:
J. Cassidy, Senior Health Physicist
M. Garza, Emergency Preparedness Inspector
C. Mathews, Illinois Emergency Management Agency
R. Murray, Senior Resident Inspector
C. Norton, Senior Resident Inspector
D. Tesar, Resident Inspector
Approved By:
Kenneth R. Riemer, Chief
Branch 1
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Quad Cities Nuclear Power Station,
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.
A licensee-identified non-cited violation is documented in report section: 71124.0
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 The unit began the inspection period at full rated thermal power, where it remained until August 25, 2019, with the exception of short term power reductions as requested by the transmission system operator. On August 25, 2019, the unit experienced an automatic SCRAM following the actuation of the Unit 1 main generator ground fault detection relay. The licensee entered Mode 2 on August 29, 2019, and commenced startup. The unit entered Mode 1 on August 30, 2019.
Following replacement of several insulators on the 'A' phase of the isophase bus duct leading to the unit auxiliary transformer, the licensee synchronized to the grid and achieved full power on September 1, 2019. The unit remained at or near full power for the remainder of the inspection period.
Unit 2 The unit began the inspection period at full rated thermal power, where it remained for the entire inspection period, with the exception of short term power reductions as requested by the transmission system operator.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated readiness for impending adverse weather conditions for extreme hot temperatures expected for the week of July 15, 2019.
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) Unit 2 emergency diesel generator during 1/2 emergency diesel generator surveillance test on July 22, 2019
- (2) Unit 1/2 and Unit 2 emergency diesel generator during extended maintenance on Unit 1 emergency diesel generator on September 9, 2019
- (3) Unit 2A, 'B', and 'D' residual heat removal service water loops during planned maintenance on Unit 2C residual heat removal service water loop on September 17, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1/2 emergency diesel generator and Unit 2 emergency diesel generator during residual heat removal outage on June 16, 2019.
- (2) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 standby liquid control system following air sparge for chemistry sample on August 1, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Fire Zone 8.2.6.E; Unit 2 turbine building, elevation 595'-0", hallway on June 25, 2019
- (2) Fire Zones 8.2.7.A, 6.1.A, 6.1.B, and 7.1; Unit 2 turbine building, elevation 615' and 628', battery charger rooms, hydrogen seal oil areas, and battery room on September 17, 2019
- (3) Fire Zones 8.2.7.E, 6.2.A, 6.2.B, and 7.2; Unit 1 turbine building, elevation 615' and 628', battery charger rooms, hydrogen seal oil areas, and battery room on September 18, 2019
- (4) Fire Zone 11.2.1; Unit 1 reactor building, elevation 554'-0", southwest corner room, 1B core spray on September 19, 2019
- (5) Fire Zone 11.2.3; Unit 1 reactor building, elevation 554'-0", northwest corner room, 1A core spray on September 19, 2019
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during the Unit 1 startup from Forced Outage Q1F67 on August 29, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated cycle 5 training on September 23, 2019.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
(1)work week risk and impending extreme hot temperatures for week of July 15, 2019 (2)emergent work and operational risk activity for the failure of the Unit 2 250 Vdc battery charger on July 30, 2019 (3)emergent work and work week risk following Unit 1 SCRAM and ground on Unit 1 main generator on August 26, 2019 (4)work week risk during week of September 9, 2019 (Unit 1 emergency diesel generator work risk)
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (3 Samples 2 Partials)
The inspectors evaluated the following operability determinations and functionality assessments:
(1)
(Partial)
Issue Report 4254547, Unit 1 HPCI [high pressure coolant injection] Did Not Trip Locally During QCOS 2300-13 on June 5, 2019
- (2) Issue Report 4263259, Unit 2 DWEDS [drywell equipment drain sump pump] Level Switch Issues Prevent Accurate Trending on July 9, 2019
- (3) Issue Report 4267234, Failure of [Unit]1B 24/48 Volt Battery Charger on July 11, 2019
- (4) Issue Report 4267593, Received 902-10 A10, [Unit 2] 250V Battery Charger 2 Trip, on July 29, 2019 (5)
(Partial)
Issue Report 4278317, [Unit] 2A RHRSW [residual heat removal service water] Vault Door Found Not Dogged Closed with Unit 1 EDG [emergency diesel generator] OOS
[out-of-service] for Maintenance on September 12, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) QCOS 1000-4, Unit 1 Residual Heat Removal Service Water Pump Operability Test on July 25, 2019
- (2) Work Order 4945512, Unit 2 250 Vdc Battery Charger #2 Trip Alarm 902-8 A10 (2-8350) on July 30, 2019 (3)testing and synchronization to the grid following repairs to the Unit 1A phase of the isophase bus on August 31, 2019
- (4) Unit 2C residual heat removal service water post-maintenance testing following discharge elbow replacement on September 16, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Forced Outage Q1F67 from Unit 1 reactor SCRAM due to generator ground fault on August 28, 2019.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) QCOS 6620-01, [Unit 1] SBO [station blackout] DG [diesel generator] Quarterly Load Test on July 29, 2019
- (2) QCOS 1100-07, [Unit 1A] SBLC [standby liquid control] Pump Flow Rate Test on July 22, 2019
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) QCOS 1000-31, [Unit 1A] RHR [residual heat removal] Logic Test on May 22, 2019
- (2) QCOS 2300-06, [Unit 2] HPCI System Air Operated Valve Test on July 30, 2019
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes:
- Evaluation 18-45, Exelon Nuclear Standardized Radiological Emergency Plan, Revision 30
This evaluation does not constitute NRC approval.
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
- RO20 - 0014095
- RO20 - 0020433
- RO20 - 0018385
- RO20 - 0014093
- RO20 - 0012237
- RAMGAM - 0010619
- Model 3 - 0020028
- Model 3 - 0021709
- Telepole - 00141189
Source Check Demonstration
- RO20 - 0014095
- RO20 - 0020433
- Model 3 - 0021709
- Telepole - 00141189
Area Radiation Monitors and Continuous Air Monitors
- Area Radiation Monitor, Low Range, Unit 1 Refuel Floor, 690'
- Area Radiation Monitor, High Range, Unit 1 Refuel Floor, 690'
- Area Radiation Monitor, Low Range, Unit 2 Refuel Floor, 690'
- Area Radiation Monitor, High Range, Unit 2 Refuel Floor, 690'
- Area Radiation Monitor, Low Range, Unit 1 Spent Fuel Pool, 690'
- Area Radiation Monitor, High Range, Unit 1 Spent Fuel Pool, 690'
- Area Radiation Monitor, Low Range, Unit 2 Spent Fuel Pool, 690'
- Area Radiation Monitor, High Range, Unit 2 Spent Fuel Pool, 690'
- Area Radiation Monitor, Outside Unit TIP Room, 595'
- Continuous Air Monitor, Unit 1 Refuel Floor, 690
- Continuous Air Monitor, Unit 1 13-Line, 595'
Personnel Contamination Monitors, Portal Monitors and Small Article Monitors
- IPM 9, Instrument Number I350
- SAM 12, Instrument Number 12205
- PM 12, Instrument Number 12047
- SAM 11, Instrument Number LAM1
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 9, Instrument Number I350
- SAM 12, Instrument Number 12205
- PM 12, Instrument Number 12047
Failure to Meet Calibration or Source Check Acceptance Criteria
- RO20 - 0018385
- RO20 - 0014093
- RO20 -
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 (07/01/2018 - 06/30/2019)
- (2) Unit 2 (07/01/2018 - 06/30/2019)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 (07/01/2018 - 06/30/2019)
- (2) Unit 2 (07/01/2018 - 06/30/2019)
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) Issue Report (IR) 4238831, [Unit] 1C RHRSW High Pressure Outboard Seal Leak During Run
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01)
- (1) Unit 1 reactor SCRAM event follow-up activities on August 25,
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71124.05 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Technical Specification 5.5.1 states, in part, that the Offsite Dose Calculation Manual shall be established, implemented, and maintained.
Section 12.2.1, Radioactive Liquid Effluent Monitoring Instrumentation, of the Offsite Dose Calculation Manual (Revision 13) includes Radiological Effluent Surveillance Requirement 12.2.1.3, which requires channel functional tests of the Unit 1 and Unit 2 service water effluent gross activity monitors to be performed on a 92 day frequency.
Contrary to the above, between December 19, 2018 and August 6, 2019, the licensee failed to implement radiological effluent surveillance requirements contained within the Offsite Dose Calculation Manual. Specifically, the licensee did not perform channel functional tests on Unit 1 or Unit 2 service water effluent gross activity monitors.
Significance/Severity: Green. The finding was determined to be of very low safety significance (Green) because the issue involved a radioactive effluent release, but did not: (1)represent a substantial failure to implement the radioactive effluent release program; or (2)result in public exposure that exceeded the dose values in Appendix I to 10 CFR Part 50 and/or 10 CFR 20.1301(e) limits.
Corrective Action References: Issue Report 4268906
Observation: 1C Residual Heat Removal Service Water Outboard Seal Leak 71152 The inspectors reviewed Issue Report 4238831, 1C RHRSW High Pressure Outboard Seal Leak During Run, dated April 12, 2019. The condition report documented a large amount of water leaking and spraying from the outboard seal of the 1C residual heat removal service water pump shortly after pump start in support of a surveillance test. Once the report was received in the control room, operators secured the pump. The licensee declared the pump inoperable and entered the appropriate Technical Specification. After the pump was secured, operators reported that the seal was continuing to leak approximately 3 gallons per minute.
The licensee had been tracking the leaking seal on this pump since it was first reported on March 18, 2019, which was documented in Issue Report 4230672, 1C RHRSW HP [high pressure] O/B [outboard] Seal Leaking. Following the seal leak identified in Issue Report 4230672, the licensee determined that seal replacement would be required, and planned the repair for a future residual heat removal work window. The licensee completed all necessary repairs on April 15, 2019, and the pump was restored to an operable status. The inspectors determined that the licensee's corrective action for this issue was appropriate and in accordance with the significance of the issue. The licensee identified that the cause of the seal failure was inadequate pump seal cooling water flow due to a small pebble getting stuck in a flow-restricting orifice, which blocked flow in the seal cooling line. The inspectors reviewed the licensees responses to Issue Reports 4230672 and 4238831, the design of the RHRSW system, prior RHRSW bay inspections, and internal operating experience. The inspectors determined that the cause of the pump failure and seal leak was not within the licensee's ability to foresee and correct, and no performance deficiency was identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 1, 2019, the inspectors presented the integrated inspection results to Mr. P. Boyle, Acting Plant Manager, and other members of the licensee staff.
- On September 20, 2019, the inspectors presented the radiation protection inspection results inspection results to Mr. K. Ohr, Site Vice President, and other members of the licensee staff.
- On October 3, 2019, the inspectors presented the Exit Meeting for EP Inspection per IP 71114, Attachment inspection results to Mr. L. Baker, EP Fleet Programs Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.04Q Procedures
QCOP 1000-04
RHR Service Water System Operation
QCOP 6600-04
Diesel Generator 1/2 Preparation for Standby Operation
QCOP 6600-24
Unit 2 Diesel Generator Preparation for Standby Operation
Corrective Action
Documents
Replace Unit 1 SBLC Heat Trace and Insulation
06/26/2017
Procedures
M-40
Diagram of Standby Liquid Control Piping
QOM 1-1100-01
Unit 1 Standby Liquid Control Valve Checklist
Work Orders
EM Replace/Upgrade 1-1101 U1 SBLC Heat Trace &
Insulation
09/06/2018
71111.05Q Fire Plans
FZ 11.2.1
Unit 1 RB 554'-0 Elev. SW Corner Room - 1B Core Spray
July 2009
FZ 11.2.3
Unit 1 RB 554'-0 Elev. NW Corner Room - 1A Core Spray
November
2011
FZ 6.1.A
Unit 1 TB 615'-6 Elev. 'A' Battery Charger Room U-1
October
2013
FZ 6.1.B
Unit 1 TB 615'-6 Elev. 'B' Battery Charger Room U-1
October
2013
FZ 6.2.A
Unit 2 TB 615'-6 Elev. 'A' Battery Charger Room U-2
July 2009
FZ 6.2.B
Unit 2 TB 615'-6 Elev. 'B' Battery Charger Room U-2
October
2013
FZ 7.1
Unit 1 TB 628'-6 Elev. 250V Battery Room
October
2013
FZ 7.2
Unit 2 TB 628'-6 Elev. 250V Battery Room
July 2009
FZ 8.2.6.E
Unit 2 TB 595'-0 Elev. Hallway
November
2018
FZ 8.2.7.A
Unit 1 TB 615'-6 Elev. Hydrogen Seal Oil Area and MCC's
October
2015
FZ 8.2.7.E
Unit 2 TB 615'-6 Elev. North Mezzanine Floor
November
2018
Miscellaneous
Unavailability
Report
July 2018 -
June 2019
Corrective Action
Documents
Received 902-10 A10, 250V Battery Charger 2 Trip
07/28/2019
250 Vdc Drawing Enhancement
07/30/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
250 Vdc Charger Require Updates
07/30/2019
Corrective Action
Documents
7/6/19 DWEDS Pumping had Step Change in Total Gallons
Pumped
07/06/2019
U2 DWED Sump Level Switch Fails to Stop 2A Pump at Low
Level
07/07/2019
U2 DWEDS Level Switch Issues Prevent Accurate Trending
07/11/2019
EO ID: Water Leak from 0-2007-22 AOV FDF Backwash
Inlet
07/11/2019
NRC ID: U2 DWFDS Leakage Increase Above NRC
Threshold
07/17/2019
Received 902-10 A10, 250V Battery Charger 2 Trip
07/28/2019
Drawings
Drawing 4E-1319
Key Diagram and Elevations 48-24 Vdc Distribution Centers
N
Miscellaneous
Alarm 902-8 A10
250V Battery Charger 2 Trip
Adverse Condition Monitoring and Contingency Plan
(ACMP) U2 Drywell Equipment Drain Sump (DWEDS) Pump
Degraded Flow (Rev. 1)
07/18/2019
Procedures
QOM 1-6300-T01
48/24 Vdc Distribution Panel + 1A Bus 4E-1319
QOM 1-6300-T02
48/24 Vdc Distribution Panel + 1B Bus 4E-1319
UFSAR Table
11.1-4
Drywell Equipment Drain Sump Sources for Radioactive
Material
Procedures
QCOS 1000-04
RHR Service Water Pump Operability Test
Work Orders
QCOS 1000-4 'A' RHR Serv Wtr Pump Flow Group 'A' Test
(IST)
07/23/2019
QCOS 1000-6 'A' RHR Pump Flow Rate Group 'A' Test (IST) 07/23/2019
QCOS 1000-6 'B' RHR Pump Flow Rate Group 'A' Test (IST) 07/23/2019
QCOS 1000-4 'B' RHR Serv Wtr Pump Flow Group 'A' Test
(IST)
07/23/2019
QCOS 1000-06 'A' Loop LPCI Mode RHR Flow Rate
07/23/2019
250 Vdc Battery Charger 2 Trip Alarm 902-8 A10 (2-8350)
07/30/2019
Corrective Action
Documents
U-1 Reactor Scram Gen Trip from Ground Relay (GIX 104)
08/25/2019
Procedures
Maintenance Rule
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
QCOS 1100-07
SBLC Pump Flow Rate Test
QCOS 2300-06
HPCI System Air Operated Valve Test
QCOS 6620-01
SBO DG 1(2) Quarterly Load Test
On-line Work Control Process
On-line Risk Management and Assessment
Work Orders
SBO Load Test
Miscellaneous
Evaluation 18-45
Exelon Nuclear Standardized Radiological Emergency Plan,
Revision 30
2/14/2019
Calibration
Records
Certificate
- 0011135270
Certificate of Calibration RO20AA
2/14/2019
Certificate
- 0011138654
Certificate of Calibration Model 3
11/29/2018
Certificate
- 0011150060
Certificate of Calibration Model 3
2/01/2019
Certificate
- 0011173293
Certificate of Calibration RAM GAM 1
05/28/2019
Certificate
- 0011173354
Certificate of Calibration BAK-2270
08/19/2019
Certificate
- 001153485
Certificate of Calibration RO-20AA
2/26/2019
ACCUSCAN II Calibration Acceptance Criteria
07/25/2018
Calibration Acceptance Criteria FASTSCAN
07/24/2018
IPM Calibration Data Sheet #I350
10/24/2018
PM-12 Calibration Data Sheet #12047
08/30/2019
SAM-12 Calibration Data Sheet #12205
2/18/2018
Corrective Action
Documents
Out of Tolerance Instrumentation During Calibration
07/20/2018
Out of Tolerance Instrumentation During Calibration
01/03/2019
Instruments Not Marked Information Only As Required
07/15/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Request Re-establish SWRM Channel Functional Test
Frequency to 92 Days
08/01/2019
Corrective Action
Documents
Resulting from
Inspection
Portable Instrument Source Check Acceptance Criteria
Exceeds Range of Scale
09/19/2019
Portable Instrument Source Check Acceptance Criteria
Significant Figure Issue
09/19/2019
Miscellaneous
C&C Irradiator Service LLC; Dose vs. Distance Curves
07/17/2019
Ref No S125722
Radcal Corporation Service Report
04/15/2019
Procedures
Radiochemistry Quality Control
Calibration Verification of Whole Body Counting Systems
Using APEX In-Vivo
Irradiator Reference Data Sheet
07/17/2019
Operation and Calibration of IPM Whole Body Frisking
Monitor
Operation and Calibration of the PM-12 Gamma Portal
Monitor
Operation and Calibration of the Model SAM-12 Small
Articles Monitor
Self-Assessments AR 4207564
NRC: Rad Protection - Rad Monitoring Instrumentation
Inspection
07/16/2019
Work Orders
01949080-01
QCIS 2400-05 Division II Rad Monitor Calibration/Functional
Test
04/19/2018
Corrective Action
Documents
1C Residual Heat Removal Service Water (RHRSW) High
Pressure Pump Outboard (OB) Seal Failure
1C RHRSW HP Pump O/B Seal Has Increased
08/02/2018
EO ID: 1C RHRSW HP O/B Seal Leaking
03/18/2019
EO ID: 1C RHRSW HP O/B Seal Leaking (Leak Template
IR)
03/18/2019
EOID: 1C RHRSW High Pressure Pump Outboard Seal
Leak Increase
03/31/2019
1C RHRSW High Pressure Pump OB Seal Leak During Run
04/12/2019
Pump Failed to Start During QCOS 1000-04
06/03/2019
Eold - 1C RHRSW High Pressure Pump Inboard Seal Leak
08/15/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1C RHRSW HP Pump 1B Seal Leak Follow-up to IR
272141
08/15/2019
IR 490375
PSU Q1M19 1C RHRSW Pump Seal Leak
05/16/2006
IR 580419
Gap Below RHRSW Separation Screen
01/18/2007
Drawings
Drawing B-35
Crib House Plan El. 595'-0 South Area
P
Drawing B-36
Crib House Plan El. 595'-0 North Area
N
Drawing B-37
Crib House Plan El. 559'-8
F
Drawing M-11
General Arrangement Crib House
E
Drawing M-79,
Sheet 1
Diagram of RHR Service Water Piping
BJ
Miscellaneous
UCC Job #02-14-
233.296 Letter
RHR Service Water Bay Inspection Report
2/07/2018
UCC Job #02-14-
233.327 Letter
RHR Service Water Bay Inspection Report
08/07/2018
UCC Job #02-14-
233.367
RHR Service Water Bay Inspection Report
2/07/2019
Corrective Action
Documents
U-1 Reactor Scram Gen Trip from Ground Relay (GIX 104)
08/25/2019