IR 05000482/2020011
| ML20135H324 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/21/2020 |
| From: | Vincent Gaddy NRC/RGN-IV/DRS/EB-2 |
| To: | Reasoner C Wolf Creek |
| References | |
| IR 2020011 | |
| Preceding documents: |
|
| Download: ML20135H324 (21) | |
Text
May 21, 2020
SUBJECT:
WOLF CREEK GENERATING STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000482/2020011
Dear Mr. Reasoner:
On April 24, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station and discussed the results of this inspection with Mr. S. Smith, Vice-President, Engineering, and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Wolf Creek Generating 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 Wolf Creek Generating Station. 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, Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 05000482 License No. NPF-42
Enclosure:
As stated
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
Enterprise Identifier: I-2020-011-0014
Licensee:
Wolf Creek Nuclear Operating Corp.
Facility:
Wolf Creek Generating Station
Location:
Burlington, KS
Inspection Dates:
April 6, 2020 to April 24, 2020
Inspectors:
D. Reinert, Reactor Inspector
W. Sifre, Senior Reactor Inspector
F. Thomas, Reactor Inspector
Approved By:
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at Wolf Creek Generating 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 Identify a Condition Adverse to Quality Involving an Overthrust of Valve ENHV0016 Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2020011-01 Open
[H.11] -
Challenge the Unknown 71111.21N.
The inspectors identified a Green finding and associated non-cited violation (NCV) of Title 10 of the Code of Federal Regulations Part 50, Appendix B, Criterion XVI, Corrective Action, for the licensees failure to identify a condition adverse to quality involving an overthrust event in excess of the maximum thrust rating of the Limitorque actuator for valve ENHV0016.
Additional Tracking Items
None.
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 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. Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), regional inspectors were directed to begin telework. The inspection documented below was determined that the objectives and requirements stated in the IP could be completed remotely.
REACTOR SAFETY
===71111.21N.02 - Design-Basis Capability of Power-Operated Valves (POVs) Under 10 CFR 50.55a Requirements
POV Review (IP Section 03)===
The inspectors:
a. Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases specific guidance b. Determined whether the sampled POVs are capable of performing their design-basis functions c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible)
Selected Samples:
- (1) BGHV8160, Letdown System Containment Isolation Valve
- (2) ABPV0001, Steam Generator A Atmospheric Relief Valve
- (3) ABHV0005, Main Steam Loop 2 to Turbine Driven Auxiliary Feedwater Pump
- (4) ABHV0006, Main Steam Loop 3 to Turbine Driven Auxiliary Feedwater Pump
- (5) BBHV8000A, Reactor Coolant System Pressurizer PORV Isolation (Block) Valve
- (6) EFHV0025, A Train Essential Service Water to Service Water Isolation Valve
- (7) EJHV8811A, Containment Recirculation Sump to Residual Heat Removal Pump A
- (8) FCHV0312, Auxiliary Feedwater Pump Trip and Throttle Valve
- (9) BNHV8812B, Refueling Water Storage Tank to Residual Heat Removal Pump Suction Isolation Valve
- (10) EJHV8804A, Residual Heat Removal A to Chemical and Volume Control System Component Cooling Pump Isolation.
INSPECTION RESULTS
Failure to Identify a Condition Adverse to Quality Involving an Overthrust of Valve ENHV0016 Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems
Green NCV 05000482/2020011-01 Open
[H.11] -
Challenge the Unknown 71111.21N.0 The inspectors identified a Green finding and associated non-cited violation (NCV) of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion XVI, Corrective Action, for the licensees failure to identify a condition adverse to quality involving an overthrust event in excess of the maximum thrust rating of the Limitorque actuator for valve ENHV0016.
Description:
Valve ENHV0016 is a 3 Anchor-Darling flexible wedge gate valve with a Limitorque SMB-00 motor actuator. ENHV0016 is normally closed and must open on a containment spray actuation signal to provide a flow path for sodium hydroxide from the containment spray additive tank to the suction of the containment spray pump. On September 29, 2019, following a scheduled actuator replacement during the fall 2019 refueling outage, the valve experienced an overthrust event due to an improperly installed actuator torque switch.
The licensee determined that the valve had been subject to a thrust force as high as 37,100 lbs. The licensee assessed the impact of the overthrust event to the Limitorque actuator in Condition Report 136328 using the characteristics for a SMB-0 Limitorque actuator, which was the incorrect actuator size. The basis for the operability conclusion regarding the actuator was a vendor document, Limitorque Maintenance Update 92-1, that allows a one-time overthrust of up to 250 percent of nominal actuator thrust rating. By considering the incorrect model SMB-0 actuator, which has a maximum thrust overload rating of 60,000 lbs., the licensee erroneously concluded that the valve remained operable.
The inspectors identified that the actuator is a smaller SMB-00 actuator. Evaluating the correct actuator model, the licensee determined that the maximum load of 37,100 lbs.
exceeded the actuators 35,000 lbs. maximum thrust overload rating. Limitorque states that exceeding the maximum thrust rating can damage the actuator qualification and that an overthrust has the potential to cause damage to thrust related components, such as the housing cover and housing cover bolting area. The vendor document that was the basis for operability determination in September 2019, Limitorque Maintenance Update 92-1, prescribes additional actions including visual inspections, component replacements, or evaluations to be performed if the maximum thrust rating is exceeded.
Because the licensee did not identify in September 2019 that they had exceeded the maximum thrust overload rating of the installed SMB-00 actuator, the licensee did not perform either those additional actions or any equivalent evaluations to ensure the operability of the actuator until it was identified by the team during the inspection.
Corrective Actions: After the inspectors identified that the maximum thrust overload rating of the actuator for ENHV0016 had been exceeded, the licensee declared the valve inoperable and removed it from service. The licensee performed visual inspections and bolt tightness checks as prescribed in Limitorque Maintenance Update 92-1 and observed no signs of damage or cracks in the actuator housing. Additionally, the licensee obtained Limitorque SMB-00 overthrust test data performed by Kalsi Engineering that demonstrated the actuator could remain functional even after being subject to an overthrust force as high as 47,781 lbs. The licensee also generated a work order to replace and overhaul the actuator during the next refueling outage.
Corrective Action References: Condition Report 142119
Performance Assessment:
Performance Deficiency: The licensees failure to identify that the September 29, 2019, overthrust event had exceeded the maximum allowable one-time thrust overload of the SMB-00 Limitorque actuator was a performance deficiency. By evaluating the incorrect actuator model, the licensee erroneously concluded that valve ENHV0016 remained operable and that no further corrective actions were necessary. If the licensee had appropriately evaluated the SMB-00 actuator, the licensee would have recognized that visual inspections, component replacements, or evaluations were necessary during the refueling outage to ensure that the valve would remain capable of performing its safety function.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the equipment performance 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, by failing to identify that the maximum thrust overload of the actuator had been exceeded they did not take corrective actions during the outage while the system was already unavailable. Consequently, the licensee had to remove the valve from service and incur additional unplanned system unavailability time to ensure the operability of the system after the condition was identified by the inspectors during the inspection.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, "Mitigating Systems Screening Questions," the finding screened as having very low safety significance (Green) because the finding did not represent a loss of operability or functionality; did not represent an actual loss of safety function of the system or train; did not result in the loss of one or more trains of non-technical specification equipment; and did not screen as potentially risk-significant due to seismic, flooding, or severe weather.
Cross-Cutting Aspect: H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. Contrary to the above, from September 29, 2019, until April 22, 2020, the licensee failed to establish measures to assure that a condition adverse to quality was promptly identified and corrected. Specifically, the licensee failed to identify that the SMB-00 Limitorque actuator for valve ENHV0016 had been subject to an overthrust event that exceeded its maximum thrust overload rating.
Enforcement Action: This violation is being treated as an non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
On April 24, 2020, the inspectors presented the Design-Basis Capability of Power-Operated Valves inspection results to Mr. S. Smith, Vice-President, Engineering,and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
AB-M-016
KVAP Analysis for 4 Air-Operated Pilot Balanced Globe
Valves ABHV0005 and ABHV0006 to determine required
stem thrust for the valves operation,
AB-M-020
Determination of the Limiting Line Pressure and Maximum
Expected Differential Pressure (MEDP) for 4 Air-
Operated Pilot Balanced Globe Valves ABHV0005 and
ABHV0006
AB-M-020
Determination of the Limiting Line Pressure and Maximum
Expected Differential Pressure (MEDP) for 4 Air-
Operated Pilot Balanced Globe Valves ABHV0005 and
ABHV0006
AB-M-023
Determination of the Limiting Line Pressure and Maximum
Expected Differential Pressure (MEDP) for 8 Air-
Operated Globe Valves ABPV0001 thru 4
BB-M-004
BBHV8000A/B MOV Bounding Pressure Conditions
Determination
BB-M-006
Thrust/Torque Calculation for BBHV8000A and
BBHV8000B
BG-M-026
KVAP Valve Thrust Analysis for 3 Air-Operated Globe
Valves (AOV) BGHV8152 and BGHV8160
BG-M-041
Determination of the Limiting Line Pressure and Maximum
Expected Differential Pressure (MEDP) for 3 Air-
Operated Globe Valves BGHV8152 and BGHV8160
BN-M-011
Thrust/Torque Calculation for BNHV8812A and
BNHV8812B
BN-M-012
BNHV8812A/B MOV Bounding Pressure Conditions
Determination
EF-M-020
Torque Calculation for EFHV0037 and EFHV0038
EF-M-025-000-
CNOOl
CCP 07416 REPLACES the existing JAMESBURY 30"
Butterfly Valves with CRANE Butterfly Valves. This
calculation evaluates the suitability o{ the CRANE
2/13/2005
EJ-M-007
EJHV8804A/B MOV Bounding Pressure Conditions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EJ-M-009
EJHV8811A/B MOV Bounding Pressure Conditions
Determination
EJ-M-013
Thrust/ Torque C lculation for EJHV88 I IA and EJHV88 I
IB
EJ-M-015
Thrust/Torque Calculation For EJHV8804A and
EJHV8804B.
EJ-M-015-CN001
Enhance Actuator Output Capacity Via a Gear
Modification for MOV EJHV9904B
01/30/2018
FC-HV-0312 Motor Operated Valve Bounding Conditions
Determination
KA-03-W
KA System Back-Up Nitrogen Accumulators Capacity
Calculation
Corrective Action
Documents
CR 00100188,
CR 00102932,
CR 00108858,
CR 00109603,
CR 00113061,
CR 00118719,
CR 00118720,
CR 00121822,
CR 00134071,
CR 00139894,
CR 00140707,
CR 00028059,
CR 00056643,
CR 00116489,
CR 00116786,
CR 00121846,
CR 00129536,
CR 00136203,
CR 00092412,
CR 00121915,
CR 00093264,
CR 00140834,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 00118615,
CR 00119845,
CR 00124924,
CR 00129219,
CR 00131467,
CR 00131500,
CR 00093413,
CR 00101570,
CR 00124921,
CR 00131578,
CR 00132933,
CR 00132934,
CR 00135085,
CR 00135321,
CR 00137012,
CR 00137074,
CR 00137187,
CR 00137426,
CR 00092506,
CR 00098261,
CR 00116357,
CR 00112876,
CR 00093143,
CR 00094183,
CR 00110041 CR
00122562, CR
00125053, CR
00131418, CR
00136707, CR
00136708, CR
00077667, CR
00099535, CR
00108088, CR
00112083, CR
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
00117699, CR
00123450, CR
00123689, CR
00124586, CR
00136341, CR
00100941, CR
00101570, CR
00113201, CR
00093562. CR
00094801, CR
00100941, CR
00112248, CR
00124709, CR
00132041, CR
00132042, CR
00096738, CR
00140834, CR
00075821, CR
00103147, CR
00140936, CR
00066911, CR
00088527, CR
00130424, CR
00078201, CR
00070646, CR
00078201, CR
00112597, CR
00112597, CR
00117159, CR
00128977,CR
00078202, CR
00090385, CR
00112598, CR
00120102, CR
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
00129306, CR
00140707, CR
00136328
Corrective Action
Documents
Resulting from
Inspection
CR 00140707,
CR 00141886,
CR 00141888,
CR 00142119,
CR 00142156
Drawings
E-138839
Schematic Diagram Pressurizer Relief Isolation Valves
E-13BN03A
Schematic Diagram Refueling Water Storage Tank TO
E-13EF02
Schematic Diagram ESW to SW System Isolation Valves
E-13EF06A
Schematic Diagram - ESW to Ultimate Heat Sink Isolation
Valves
E-13EG07A
Schematic Diagram Component Cooling Water Supply to
Residual Heat Removal Heat Exchanger
(CEGHV_0,1=02)
E-13EJ06A
SCHEMATIC DIAGRAM SUMP TO NO. 1 RESIDUAL
HEAT REMOVAL PUMP
E-13FC23
Auxiliary Feedwater Pump Turbine Trip & Throttle Valve
Valve Regulator for ABHV006 Replaced per CCP Without
Guage
W13
M-12AB01
P&ID - Main Steam System
M-12AB02
P&ID Main Steam System
M-12BB02
P&ID-Reactor Coolant System
M-12BG01
P&ID Chemical and Volume Control System
M-12EF01
P&ID Essential Service Water System
M-12eJ01
P&ID Residual Heat Removal System
M-12EJ01
P&ID Residual Heat Removal System
M-13BG22
Piping Isometric, CVCS-Letdown Reactor Building
M72402011
Internal Wiring Diagram Westinghouse Motor Operated
Valve Limit Close With Positive Close Indication
Engineering
011337
Relocate Instrumentation Package from the Atmospheric
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
Relief Valves ABPV0001 thru 0004
011924
EJHV8811A AND EJHV8811B MOV Margin Evaluation
BN-M-011-008-
CN001
Enhances actuator output capacity via a gearing
modification for MOVs BNHV8812A and BNHV8812B.
01/30/2018
Miscellaneous
EQSD-II Environmental Qualification Program Master List
(Table 1) Plus Mild Environment SR Electrical Equipment
List (Table 2)
BWROG-TP-09-
005
Inspection of Motor Operated Valve Limitorque AC Motors
with Magnesium Rotors
E-025-00003
Limitorque Design Information
W13
E-02s=00025
IM Butterfly Application Guide
W01
ER-5.0
Equipment Inaccuracy Summary for Motor Operated
Valves
ET 00-0022
Docket No. 50-482: Clarification to Closeout Response to
Generic Letter 96-05 -Wolf Creek Generating Station
08/18/2000
ET 96-0093
Docket No. 50-482: Sixty Day Response to Generic Letter 96-05, "Periodic Verification of Design-Basis
Capability of Safety-Related Motor-Operated Valves"
11/13/1996
ET 97-0024
Docket No. 50-482: 180 Day Response to Generic Letter 96-05, "Periodic Verification of Design-Basis Capability of
Safety-Related Motor-Operated Valves"
03/17/1997
ET 98-0036
Docket No. 50-482: Additional Response to GL 96-05,
Periodic Verification of Design-Basis Capability of
Safety-Related Motor-Operated Valves
04/29/1998
J-601A
Technical Specification for Nuclear Service Control Valves
- Wolf Creek Nuclear Operation Corporation
M-724-00236-
W04
Globe Valves, Westinghouse Electric Corporation
1W
Joint Owners' Group (JOG) Motor Operated Valve
Periodic Verification Program Summary
November
2006
PQE-E-035-P01
Plant Qualification Evaluation of Electrical Equipment
SA-2020-0153
Self Assessment - Power Operated Valves (POVs)
April 1, 2020
Wolf Creek Generating Station Valve Factors for Valve
10/28/2005
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Location 8811A and 8811B
TSA 20698-000
Wolf Creek Generating Station Motor Operated Valve
Thrust Information
08/26/1991
WCAP 13097
System Operating Basis for Motor-Operated Valves
Docket No. 50-482: Response to Request for Additional
Information Regarding Generic Letter 96-05, "Periodic
Verification of Design-Basis Capability of Safety-Related
Motor-Operated Valves"
07/14/1999
Procedures
AI 20E-004
Processing and Maintaining Incoming Operating
Experience
AI 23D-002
Motor Operated Valve Calculation Program
AI 23D-003
MOV Trending and Periodic Verification Program
AI 23D-004
Valve Maximum Expected Differential Pressure
Determination
AI 23N-001
Air Operated Valve Categorization
AI 23N-004
AOV Setpoint Conrtrol
AI 28A-010
Screening Condition Reports
Industry Operating Experience Program
Motor Operated Valve Program
Reportable Events - Evaluation and Documentation
Corrective Action Program
INC S-0020
Air Operated Valve (AOV) Diagnostic Testing
MGE EOOP-05
Insulation Resistance Testing
MGE LT-008
Routine Electrical Limitorque Operator Maintenance
8A
MGE LT-099
MOV Diagnostic Testing
MGE TL-001
Wiring Termination and Lug/Connector Installation
MPM LT-001
Limitorque Operator Minor Maintenance, Lubrication, and
Inspection
STN PE-068
Periodic Testing of Air Operated Valves
STS PE-007
Periodic Verification of Motor Operated Valves
5A
Work Orders
08-310207-009,
08-310207-010,
11-345972-000,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
11-345972-001,
11-345972-005,
11-345972-008,
2-359243-000,
15-406198-000,
15-406198-001,
16-411560-000,
17-428007-001,
18-438625-000,
04-259633-000,
2-359487-000,
15-406377-000,
18-441533-000,
18-441835-000,
07-291772-000,
11-344250-000,
13-376705-000,
13-376705-002,
15-406426-000,
15-406427-000,
18-441480-000,
08-313066-000,
14-392809-000,
16-412226-000,
16-417309-000,
18-436916-000,
18-441116-000,
18-441116-001,
14-385818-000,
14-395403-000,
14-395403-000,
16-413949-000,
17-433581-000,
19-451139-000,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
18-441449-000,
18-441121-018,
1'3-441121-000,
19-455526-000,
11-343497-000,
2-359637-000,
13-376741-000,
15-406545-000,
18-441509-000,
13-376745-000,
09-322159-001,
15-401832-043,
15.:.406549-000,
16-420882-000,
18-441531-000,
04-260056-000,
11-341816-000,
2-360692-000,
2-360692-002,
4-387530-000,
15-408729-000,
17-427448-000,
18-444853-000,
15-406571-000,
16-410863-000,
15-406571-001,
17-426105-003,
19-448747-000,
18-445367-011,
18-445367-001,
18-445367-000,
14-383865-000,
15-407954-000,
16-416704-000,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
18-438164-000,
18-442044-000,
15-407954-000,
16-416704-000,
18-438164-000,
18-442044-000,
09-322378-003,
09-322907-006,
15-398253-002,
13-365790-002,
15-403884-003,
18-444873-002,
09-322159-006,
13-376745-002,
15-401832-039,
15-406549-001,
16-420882-005,
18-441531-001,
15-406571-005,
16-410863-001,
7-426105-005,
18-445367-005,
19-448747-001,
11-346379-030,
14-389217-000,
15-403052-000,
17-429433-000,
18-441457-000,
07-294624-000,
05-272026-000,
07-294386-000,
06-291397-002,
06-291397-000.
08-305414-000,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
08-308675-000,
11-343296-000,
11-338112-000,
2-356099-000,
14-383600-000,
14-388921-000,
15-405072-000,
18-444284-000,
18-442056-000,
11-346686-000,
13-365790-000,
14-392810-000,
5-403884-000,
17-424277-000,
18-444873-000,
09-322907-000,
10-323794-000,
13-366745-000,
15-398253-000,
10-333138-001,
10-335908-000,
11-337505-000.
3-366743-000,
13-366744-000,
19-449238-000,
05-275912-000,
05-275913-000,
06-290435-000,
07-301283-001,
11-344916-000,
2-356709-000,
15-400731-000,
17-427382-000,
18-438185-000.
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
18-447586-000,
05-275912-000,
07-301279-001,
11-337987-001,
1-345510-000,
2-356710-000,
14-396150-000, l
7-427381-000,
17-433434-002,
96-109965-001,
20-462446-001