ML22318A007
| ML22318A007 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/14/2022 |
| From: | Wesley Deschaine Division Reactor Projects II |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2022003 | |
| Download: ML22318A007 (16) | |
See also: IR 05000390/2022003
Text
November 14, 2022
Mr. Jim Barstow
Vice President Nuclear Regulatory
Affairs & Support Services
Tennessee Valley Authority
Chattanooga, TN 37402-2801
SUBJECT: WATTS BAR NUCLEAR PLANT - INTEGRATED INSPECTION REPORT
05000390/2022003 AND 05000391/2022003
Dear Jim Barstow:
On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an
inspection at Watts Bar Nuclear Plant. On October 24, 2022, the NRC inspectors discussed the
results of this inspection with Mr. Anthony Williams and other members of your staff. The results
of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
The Regional Administrator has authorized staff to use IP 50001, Steam Generator
Replacement Inspection, to inspect Watts Bar Unit 2 Steam Generator Replacement because
the steam generator replacement inspection is an infrequent inspection and outside of the
routine reactor oversight program (ROP) baseline inspections.
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 Title 10 of the Code of Federal Regulations 2.390, Public
Inspections, Exemptions, Requests for Withholding.
Sincerely,
Signed by Deschaine, Wesley
on 11/14/22
Wesley D. Deschaine, Chief
Reactor Projects Branch 5
Division of Reactor Projects
Docket Nos. 05000390 and 05000391
License Nos. NPF-90 and NPF-96
Enclosure:
As stated
cc w/ encl: Distribution via LISTSERV
X Non-Sensitive X Publicly Available
X SUNSI Review
Sensitive Non-Publicly Available
OFFICE RII/DRP
NAME W. Deschaine
DATE 11/14/22
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Numbers: 05000390 and 05000391
License Numbers: NPF-90 and NPF-96
Report Numbers: 05000390/2022003 and 05000391/2022003
Enterprise Identifier: I-2022-003-0020
Licensee: Tennessee Valley Authority
Facility: Watts Bar Nuclear Plant
Location: Spring City, TN 37381
Inspection Dates: July 01, 2022 to September 30, 2022
Inspectors: N. Childs, Senior Project Engineer
P. Cooper, Senior Reactor Inspector
N. Karlovich, Resident Inspector
K. Kirchbaum, Operations Engineer
M. Magyar, Reactor Inspector
N. Peterka, Fuel Facility Inspector
M. Riley, Senior Project Engineer
D. Simpkins, Sr. Tech Training Program Specialist
J. Steward, Senior Resident Inspector
D. Turpin, Resident Inspector
Approved By: Wesley D. Deschaine, Chief
Reactor Projects Branch 5
Division of Reactor Projects
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting an integrated inspection at Watts Bar Nuclear Plant, in accordance
with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for
overseeing the safe operation of commercial nuclear power reactors. Refer to
https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
2
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On July 21, Unit
1 was reduced to 98 percent power due to condenser vacuum and returned to 100 percent RTP
on July 28. On August 2, 2022, Unit 1 was briefly reduced to 70 RTP to repair D common
station service transformer (CSST) and returned to 100 RTP on the same day. The unit
remained at or near RTP for the entire inspection period.
Unit 2 began the inspection period at Mode 1 following the refueling outage and returned to 100
RTP on July 5, 2022. On August 2, 2022, Unit 1 was reduced to 70 RTP to repair D CSST and
returned to 100 RTP on the same day. The unit remained at or near RTP for the entire
inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors performed activities described in IMC 2515,
Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of
IPs. 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
71111.04 - 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) Emergency Diesel Generator (EDG) 2A on August 12, 2022.
(2) Unit 1 and 2 125V DC System Channel I, II, and IV on August 24, 2022
(3) Safety Injection Pump (SI) 1A on September 21, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1) The inspectors evaluated system configurations during a complete walkdown of the
Essential Raw Cooling System (ERCW) on August 17, 2022.
3
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a
walkdown and performing a review to verify program compliance, equipment functionality,
material condition, and operational readiness of the following fire areas:
(1) Diesel Generator Building (Elevation 742' and 760.5') on July 22, 2022.
(2) Auxiliary Building Rooms (Elevation 692' - Charging Pump Rooms and Pipe Chases)
on Aug 5, 2022.
(3) Auxiliary Building Corridor (Elevation 692) on August 5, 2022.
(4) Transformer Yard (Elevation 729') on August 15, 2022.
(5) Control Building (Elevation 692', 708', 729', and 755') on August 12, 2022.
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
(1) The inspectors evaluated the onsite fire brigade training and performance during two
unannounced fire drills one on July 13 in the Control Building Cable Spreading Room
and on August 9 in the Unit 1 Turbine Driven Auxiliary Feedwater Pump area.
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (2 Samples)
The inspectors evaluated internal flooding mitigation protections in the:
(1) Intake Pump Station (IPS) A train rooms
(2) 480V / Motor Control Center (MCC) board rooms
71111.08P - Inservice Inspection Activities (PWR)
PWR Inservice Inspection Activities Sample (IP Section 03.01) (1 Sample)
(1) The inspectors evaluated pressurized water reactor non-destructive testing by
reviewing the following examinations from March 7 - July 25, 2022:
1. Ultrasonic Testing (UT)
a. RSG-3-H-SE, Primary Nozzle to Safe End, Class 1 (reviewed)
b. RSG-3-C-SE, Primary Nozzle to Safe End, Class 1 (reviewed)
c. 3065 FW-1, RCS Hot Leg Elbow to RSG Nozzle Safe End, Class 1
(reviewed)
d. 3065 FW-2, RCS Crossover Leg Elbow to RSG Nozzle Safe End,
Class 1 (reviewed)
2. Radiographic Testing (RT)
a. 3065 FW-1, RCS Hot Leg Elbow to RSG Nozzle Safe End, Class 1
(reviewed)
b. 3065 FW-2, RCS Crossover Leg Elbow to RSG Nozzle Safe End,
Class 1 (reviewed)
3. Penetrant Testing (PT)
a. 3065 FW-1, RCS Hot Leg Elbow to RSG Nozzle Safe End, Class 1
(reviewed)
4
b. 3065 FW-2, RCS Crossover Leg Elbow to RSG Nozzle Safe End,
Class 1 (reviewed)
4. Visual Testing (VT)
a. R-033, Reactor Vessel Closure Head, Code Case N-729-6 (reviewed)
The Inspectors evaluated the licensees boric acid corrosion control program
performance.
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 Main
Control Room during a dual unit downpower to 70% power, swap of electrical buses
and return to 100% power on August 2, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1) The inspectors observed and evaluated the following licensed operator requalification
simulator scenarios: crew A on July 20, 2022, and crew A on August 17, 2022. Both
observations make up one sample.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the
following planned and emergent work activities to ensure configuration changes and
appropriate work controls were addressed:
(1) Risk assessment for (week of) August 1, 2022, with the D CSST failure on 7/31 and
swaps to A CSST.
(2) Risk assessment for (week of) July 11, 2022, with the B MCR Chiller out of service for
maintenance.
(3) Risk assessment for maintenance feed to D CSST swap on the 6.9KV shutdown
Boards, on September 15, 2022.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensee's justifications and actions associated with the
following operability determinations and functionality assessments:
(1) CR 1793858 - Shutdown Board 1B-B secondary block maintenance, on
August 3, 2022.
5
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) Temporary modification WBN-2-2022-068-001, Removal of Unit 2 Loop 1 T Cold 2
RTD from scan in Eagle 21 on July 19, 2022.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system
operability and/or functionality:
(1) 1-SI-62-901-A, 1A-A Centrifugal Charging Pump (CCP) Quarterly Performance Test,
following preventative maintenance, on July 5, 2022, (WO 122055915).
(2) 2-SI-63-901-B, Safety Injection Pump 2B-B Quarterly Performance Test, after
preventative maintenance was performed under WOs 122517428 and 122517424.
(3) 2-SI-3-907-B, Valve Position Indication Verification (Train B) Auxiliary Feedwater
(AFW) System, after replacement of 2-FSV-003-0359-B, Auxiliary Feedwater Pump
2B-B recirculation flow solenoid valve, under WO 122419369.
(4) N-VT-4, In-service Visual Examination after replacement of the High Pressure Fire
Water (HPFW) strainer outlet isolation valves (WBN-0-ISV-026-0553, WBN-0-ISV-
026-0549, WBN-0-ISV-026-0575, and WBN-0-ISV-026-0582), under WOs
113642168, 120411298, 120716471, and 120919948.
(5) 1-SI-61-901-A, Valve Full Stroke Exercising During Plant Operation Ice Condenser
System (Train A), WO 122610129 on August 23, 2022.
(6) 0-TI-50.045, 2B-B Diesel Starting Air System Quarterly Check Valve Test, WO 122610225 on August 23, 2022.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability
and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (4 Samples)
(1) Surveillance Instruction 1-SI-63-51, 18-Month Channel Calibration RWST Level,
Channel II Loop 1-LPL-63-51, on July 13, 2022 (WO 122561234)
(2) Surveillance Instruction 0-SI-82-11-B, Monthly Diesel Generator Start and Load Test
DG 1B-B, on August 11, 2022 (WO 122609865)
(3) Surveillance Instruction 1-SI-61-6, Weekly Ice Condenser Intermediate Deck Doors
Visual Inspection, on September 13, 2022 (WO 122658134).
(4) Surveillance Instruction 1-SI-74-901-B, Residual Heat Removal Pump 1B-B Quarterly
Performance Test, on August 24, 2022 (WO 122610132)
6
Inservice Testing (IP Section 03.01) (1 Sample)
(1) Surveillance Instruction 2-SI-63-901-A, Safety Injection Pump 2A-A Quarterly
Performance Test, on August 31,2022, (WO 122610433)
OTHER ACTIVITIES - BASELINE
71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1) Corrective actions and referenced calculations associated with the as-left open
running loads for the Unit 2 RCS loop 4 to RHR inlet bypass isolation valve, 2-MVOP-
074-0009-B, not meeting acceptance criteria on September 28 and 29, 2022.
71153 - Follow Up of Events and Notices of Enforcement Discretion
Personnel Performance (IP Section 03.03) (1 Sample)
(1) The inspectors evaluated a dual unit downpower to 70%, swap of electrical buses
and return to 100% power and licensees performance on August 2, 2022.
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
50001 - Steam Generator Replacement Inspection
During the Watts Bar Unit 2 Spring 2022 refueling outage, all four of the Westinghouse model
D3 (Alloy 600) original steam generators (OSGs) were replaced with Westinghouse Model
68AXP (Alloy 690) replacement steam generators (RSGs). This inspection report documents
inspection activities required by inspection procedure (IP) 50001, Steam Generator
Replacement Inspection, that were completed during the third quarter of 2022 and provides an
overall summary of inspection activities completed during the first, second, and third quarters of
2022. The table below identifies and correlates specific IP 50001 inspection requirements
examined over the first, second, and third quarters of 2022, with the corresponding quarterly
reports in which the inspection activities were completed.
IP 50001 Requirement Quarterly Integrated
Section Report(s)
02.02.a.1 Verify that selected design changes and modifications to 2022-001
systems, structures, and components (SSCs) described in 2022-002
the updated final safety analysis report (UFSAR) reviewed 2022-003
for compliance with 10 CFR 50.59.
02.02.a.2 Review key design aspects and modifications for the 2022-001
RSGs and other modifications associated with steam 2022-002
generator (SG) replacement. Include design reviews for 2022-003
7
temporary containment opening.
02.02.b Review engineering design, modification, testing, and 2022-001
analysis associated with SG lifting and rigging.
02.02.c Review radiation protection program controls, planning, 2022-002
and preparation.
02.02.d Review security considerations associated with vital and 2022-001
protected area barriers and plans to minimize any adverse
impact on the operating unit and common systems.
02.03.a Review special procedures for welding and non- 2022-002
destructive examination (NDE); training and qualifications 2022-003
for welding and NDE personnel; NDE results and work
packages for selected welds; completion of pre-service
NDE requirements for welds; and completion of baseline
eddy current examination of new SG tubes.
02.03.b Review activities associated with lifting and rigging. 2022-001
2022-002
02.03.c Observe portions of old and new SG cutting, movement, 2022-001
and reconnection inside and outside containment. 2022-002
02.03.d Major structural modifications to facilitate SG replacement 2022-002
and review condition of old SG hold down bolts for 2022-003
degradation.
02.03.e Inspect activities associated with containment access and 2022-002
restoration of temporary containment opening and 2022-003
containment leakage testing.
02.03.f Inspect establishment of operating conditions including 2022-001
defueling, RCS drain down, system isolation and safety 2022-002
tagging; implementation of radiation protection controls;
foreign material exclusion (FME) controls associated with
the primary and secondary side of the SGs and in related
RCS openings; and installation, use, and removal of
temporary services.
02.03.g Review radiological safety plans for temporary storage or 2022-002
disposal of retired SGs and components.
02.04 Conduct SG post-installation inspections and verifications 2022-003
in accordance with the inspection plan including,
containment leak testing, RCS leakage testing, and SG
secondary side leakage testing.
Steam Generator Replacement Inspection (6 Samples)
8
(1) Design Changes and Modifications to Systems, Structures, and Components - 10
CFR 50.59 Review (Sections 02.02.a.1 and 02.02.a.2)
The inspectors reviewed design documentation for restoration of the shield building
dome after replacement of the Unit 2 steam generators to verify that the acceptance
criteria for the restoration, as specified in the design documentation, were met.
(2) Welding and Non-Destructive Examination (NDE) Activities (Section 02.03.a)
In accordance with the guidance of IP 71111.08, the inspectors reviewed the
following nondestructive examination (NDE) documentation associated with the
fabrication and preservice examinations of the steam generator (SG) replacement
project.
ASME Section III radiography, magnetic particle, and ultrasonic examination
of the tubesheet and primary head weld
ASME Section XI ultrasonic examinations of the tubesheet and primary head
weld
Eddy Current examination for the SG tubes
The inspectors also reviewed welding and NDE associated with the reconnection of
the steam generator (SG) to the reactor coolant system. These items are
documented in section 71111.08P of this report.
(3) Old and New SG Cutting, Movement, and Reconnection Inside and Outside
Containment (Section 02.03.c)
Observations of reconnection activities were completed in the second quarter of
2022. During this inspection period, the inspectors reviewed welding and NDE
associated with the reconnection of the steam generator (SG) to the reactor coolant
system. These items are documented in section 71111.08P of this report.
(4) Major Structural Modifications to Facilitate SG Replacement (Section 02.03.d)
As required by IP 50001, Section 02.03.d, the inspectors reviewed documentation
associated with the inspection of the SG hold down bolts to verify that any
degradation identified was appropriately addressed.
(5) Containment Access and Restoration of Temporary Containment Opening and
Containment Leakage Testing (Section 02.03.e.)
The inspectors reviewed results of quality control acceptance testing performed on
materials (cement, fine and coarse aggregate, water, and admixtures) selected for
batching of the concrete. The inspectors also reviewed the concrete mix data to
ensure that selected trial mix met concrete design strength requirements, and that
Quality Control (QC) acceptance criteria specified in the procedures for the concrete
were based on the trial mixes.
The inspectors reviewed related concrete testing and sampling activities to assure
compliance with American Concrete Institute (ACI) and American Society for the
Testing of Materials (ASTM) codes.
(6) SG Post-Installation Verification and Testing (Section 02.04)
As required by IP 50001, Section 02.04, the inspectors performed selective
documentation reviews, consistent with the safety significance, of the following
9
areas: snubber pre-service testing; containment leak testing; RCS leakage testing;
SG secondary side leakage testing; and calibration and testing of instrumentation for
both the primary (RCS) and secondary side (feedwater and main steam) systems
affected by the SG replacement.
93100 - Safety-Conscious Work Environment Issue of Concern Followup
Safety-Conscious Work Environment Issue of Concern Followup (1 Sample)
(1) NRC qualified safety culture assessors performed a limited assessment of the safety
conscious work environment (SCWE) in the Chemistry Department at Watts Bar in
accordance with IP 93100, Safety Conscious Work Environment Issue of Concern
Follow-up. The objectives of the assessment were to: (1) determine whether actions
taken by Tennessee Valley Authority improved the work environment in the Chemistry
Department; (2) determine if employees are currently reluctant to raise safety or
regulatory issues; and (3) determine if employees are currently being discouraged
from raising safety or regulatory issues.
The team interviewed all available employees (25) from the Chemistry and Radiation
Protection Departments, which consisted of technicians, chemists, supervisors,
managers, and the employee concern program (ECP) manager. In general, at the
time of the inspection, the team determined that many employees in the chemistry
department are hesitant to raise safety concerns through multiple avenues out of fear
of retaliation or have the perceptions that nothing will be done with their concerns if
they do raise them. The team noted that some will not use the ECP; some are
hesitant to talk to the NRC; and while they are sometimes willing to write condition
reports (CRs), they have an overall perception that nothing will be done with the CRs
once they write them. The team heard that the amount of turnover and churn among
the staff and supervisors is causing tremendous strain on the organization. The team
also reviewed TVAs responses to the GLINT assessment, the USA Alliance nuclear
safety culture assessment and responses to NRC Requests for Information, which all
identified the Chemistry Department as an area of concern and have determined that
corrective actions are new and have not yet been effective at fixing the previously
identified work environment issues within the Chemistry Department. In addition, the
team determined that the corrective actions are not comprehensive enough to
address the work environment issues within the department.
The NRC determined that there is a chilled work environment in the Chemistry
Department, meaning individuals are hesitant to raise nuclear safety concerns for fear
of retaliation and perceive that Chemistry supervision is retaliating against chemistry
employees for bringing up concerns. The NRC reviewed the NRC allegation manual
guidance, Section 5.2.i.6(a)(2), to determine if a chilling effect letter (CEL) is
warranted at this time. The NRC concluded that the CEL is not appropriate at this
time because the licensee had recently implemented corrective actions and is still
evaluating the effectiveness of corrective actions. The NRC has requested the
licensee respond to the NRCs assessment results and implement appropriate
corrective actions.
INSPECTION RESULTS
10
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 24, 2022, the inspectors presented the integrated inspection results to Mr.
Anthony Williams and other members of the licensee staff.
On October 31, 2022, the inspector presented the SGRP inspection results to Mr.
Anthony Williams and other members of the licensee staff.
11
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
50001 Miscellaneous 2-PI-CEM-15.0 Watts Bar Chemistry Primary to Secondary Leak Rate (data) 07/11/2022 -
07/17/2022
31814-116-PO Purchase Order - WP3730 Ready Mix Concrete for Dome 03/03/2022
Reinstall
31814-CGDP-001 SGT commercial grade dedication plan for concrete for Revision 1
reinstallation of WBN2 shield building dome following
replacement of SGs
31814-SPEC-C- SGT Specification - Bar Nuclear Plant Unit 2 - Concrete and Revision 5
004 Grout
Work Orders WO 120927614 visual examination record for initial preservice exam of rigid 05/29/2022
supports - SG#3
WO 120931694 visual examination record for initial preservice exam of rigid 05/29/2022
supports - SG#1
WO 120931715 visual examination record for initial preservice exam of rigid 05/28/2022
supports - SG#2
WO 120931760 visual examination record for initial preservice exam of rigid 05/28/2022
supports - SG#4
WO 121321481 Reinstall Hydraulic Tubing and Hoses to SG 2-1 Snubbers 06/08/2022
WO 121879786 0-SI-0-914 Snubber Functional Testing - Unit 2 06/09/2022
WO 122343467 pressure testing of SCV liner after replacement/repairs per 06/24/2022
TI-88.01
WO 122498103 2-SI-68-32 Reactor Coolant System Water Inventory 07/07/2022
Balance
71111.04 Corrective Action CR 1803952 NRC Identified: Error in system 63 Power Checklists 9/21/2022
Documents
Drawings 0-45W700-1 120VAC and 125VDC Vital Plant Control Power System 85
1-47W811-1-ISI Flow Diagram Safety Injection System 85
Procedures 0-SI-0-3 Weekly Log 72
1-SOI-63.01 Safety Injection System 20
1-SOI-63.01 ATT- Safety Injection System Handswitch 0
1H
1-SOI-63.01 ATT- Safety Injection System Power Checklist 9
12
Inspection Type Designation Description or Title Revision or
Procedure Date
1P
1-SOI-63.01 ATT- Safety Injection System Valve Checklist 16
1V
71111.05 Fire Plans Fire Plans WBN-PREFIREPLAN-AUX-0-692-01, Rev. 4/Rev. 3, AUX-0-
692-02, Rev. 3/Rev. 3, AUX-0-692-03, Rev. 8/Rev. 2, AUX-
0-692-04, Rev. 1/Rev. 2
Miscellaneous WBN FHAR, Part Introduction, Table I-1 Summary Compliance Fire Protection 60
1
71111.06 Calculations MDN-000-999- WBN PRA Internal Flooding Analysis Notebook 2
2008-0146
WBN-OSG-4099 Moderate Energy Line Break Flooding Study 16
Drawings 37W201-1 Intake Pumping Station, Mechanical Drawing 9
WBN-46W401-8- Architectural Plan EL 772.0, 782.0, & 786.0 7
Miscellaneous WB-DC-40-31 Evaluating the Effect of Flooding due to Moderate Energy 5
Pipe Failures Inside and Outside Containment
WBN-DC-40-29 Flood Protection Provisions 19
71111.11Q Procedures 1-GO-4 Normal Power Operations 33
71111.13 Miscellaneous eSOMS
Daily risk status sheets
71111.15 Corrective Action Condition Report WBN-1-BD-211-B-B, 6.9KV Shutdown Board 1B-B
Documents 1793858
Miscellaneous 0-15E500-1 Key Diagram Station Aux Power System 85
71111.18 Engineering WBN-2-2022-068- Removal of Unit 2 Loop 1 Tcold2 RTD from scan in Eagle 06/29/2022
Changes 001 21
71111.19 Procedures 2-SI-63-901-B Safety Injection Pump 2 B-B Quarterly Performance Test 9
Work Orders 122517424 Testing of Large 2 Pole Motors-Safety Injection Pump 2B-B 09/06/2022
122517428 Safety Injection Pump 2 B-B, Inspect, Clean, 09/06/2022
Sample/Change Oil
122658395 Safety Injection Pump 2 B-B Quarterly Performance Test 09/06/2022
71111.22 Drawings WBN-2-47W811- Unit 2 Safety Injection System Flow Diagram 85
1-ISI-ISI
Procedures 2-SI-63-901-A Procedure, Safety Injection Pump 2A-A Quarterly 8
Performance Test
13
Inspection Type Designation Description or Title Revision or
Procedure Date
2-SOI-63.01 Safety Injection System 23
Work Orders WO 122610433 Safety Injection Pump 2A-A Quarterly Performance Test 08/31/2022
71152A Calculations MDQ0020742008- Documentation of Design Basis Review, Required 7
0302 Thrust/Torque Calculations and Valve and Actuator
Capability Assessment for Valve 2-FCV-74-009
Corrective Action CR 1763323
Documents
Miscellaneous DS-M18.2.21 Motor Operated Valve Thrust and Torque Calculations 28
S1001032800 Decommitment Package 17-2 3/21/2001
Procedures NPG-SPP-22.300 Corrective Action Program Rev 24
Work Orders 122176385
71153 Procedures 0-SOI-211.02 6.9KV Shutdown Board 1B-B 6
1-GO-4 Normal Power Operation 33
1-SOI-201.03 6.9 KV Unit Board 1C 5
14