Rev 1 to Civil Engineering Branch Instruction CEB-CI 21.97, Operability Criteria for Pipe & Pipe Supports on TVA Class I Seismic Piping - Browns Ferry.| ML18033A188 |
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Browns Ferry  |
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| Issue date: |
03/31/1988 |
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TENNESSEE VALLEY AUTHORITY |
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| Shared Package |
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| ML18033A186 |
List: |
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| References |
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| CEB-CI-21.97, NUDOCS 8805040417 |
| Download: ML18033A188 (9) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18039A8811999-09-28028 September 1999
Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J
ML18039A8241999-07-28028 July 1999
Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys
ML18039A8001999-06-0303 June 1999
Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions
ML18039A6991999-02-22022 February 1999
Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation
ML18039A6601998-12-15015 December 1998
Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY
ML20206F8131998-12-0303 December 1998
Rev 12 to ODCM, for BFN
ML18039A5041998-09-0808 September 1998
Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys
ML18039A5001998-09-0404 September 1998
Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses
ML18039A4791998-08-14014 August 1998
Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months
ML18039A4611998-07-31031 July 1998
Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages
ML18039A4481998-07-17017 July 1998
Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions
ML18039A4091998-06-26026 June 1998
Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt
ML18039A4021998-06-19019 June 1998
Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS
ML18039A3921998-06-12012 June 1998
Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs
ML20249A5661998-06-10010 June 1998
Proposed Tech Specs Section 5.0,revising Administrative Controls
ML20248C5151998-05-27027 May 1998
Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating
ML18039A3181998-04-16016 April 1998
Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS
ML18039A2711998-03-16016 March 1998
Proposed Tech Specs Re Power Uprate Operation
ML18039A2671998-03-13013 March 1998
Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4).
ML18039A2641998-03-12012 March 1998
Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys.
ML18039A2611998-03-0303 March 1998
Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves
ML20199E8051998-01-23023 January 1998
Proposed Tech Specs Section 5.0 Re Administrative Controls
ML18039A2401998-01-15015 January 1998
Bfnp Unit 2 Cycle 10 Power Ascension Test Program Start-Up Rept, for Period 970929-1105
ML18039A2221997-12-30030 December 1997
Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown
ML18039A2151997-12-23023 December 1997
Proposed Tech Specs Section 3.7 Re Plant Sys
ML18039A2181997-12-22022 December 1997
Proposed Tech Specs Section 3.8 Re Electrical Power Sys
ML20217P5051997-12-0808 December 1997
Rev 10 to ODCM, Containing Markups to Rev 9 & 10
ML18039A2101997-12-0404 December 1997
Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys.
ML18039A2071997-12-0404 December 1997
Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5
ML18039A2011997-12-0303 December 1997
Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations.
ML18039A1981997-12-0303 December 1997
Improved Tech Specs Pages Re Section 5, Administrative Controls.
ML20199D5471997-11-14014 November 1997
Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes
ML20199E1361997-11-14014 November 1997
Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys
ML20198Q4521997-11-0505 November 1997
Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions
ML18038B9611997-10-0101 October 1997
Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt
ML18038B9361997-08-15015 August 1997
Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days
ML20210V1171997-07-29029 July 1997
Qualification Plan & Rept MIL-STD-462D,CS114,Conducted Susceptibility,Bulk Cable Injection Numac Reactor Bldg Vents Radiation Monitor TVA Bfn,Units 1,2 & 3
ML18038B9061997-06-19019 June 1997
Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities
ML20138J3781997-05-0101 May 1997
Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments
ML18038B8651997-04-24024 April 1997
Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3
ML20137U1691997-04-11011 April 1997
Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses
ML18038B8341997-03-12012 March 1997
Proposed Tech Specs Re Extended EDG Allowed Outage Time
ML20136F7851997-03-0606 March 1997
Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design
ML20134G5401997-02-0505 February 1997
Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber
ML18038B8281997-01-31031 January 1997
Rev 1 to GE-NE-B13-01805-22, Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3.
ML18038B8111997-01-22022 January 1997
Rev 0 to Browns Ferry Nuclear Plant,Surveillance Instruction,Inservice Insp Program,Unit 3.
ML20132B7401996-12-11011 December 1996
Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity
ML20117P3341996-09-15015 September 1996
Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations
ML18038B7541996-09-0606 September 1996
Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1
ML20117G7121996-08-30030 August 1996
Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds
1999-09-28
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206F8131998-12-0303 December 1998
Rev 12 to ODCM, for BFN
ML20217P5051997-12-0808 December 1997
Rev 10 to ODCM, Containing Markups to Rev 9 & 10
ML18038B8281997-01-31031 January 1997
Rev 1 to GE-NE-B13-01805-22, Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3.
ML18038B8111997-01-22022 January 1997
Rev 0 to Browns Ferry Nuclear Plant,Surveillance Instruction,Inservice Insp Program,Unit 3.
ML20137H3251996-08-23023 August 1996
Rev 8 to ODCM for Bfn
ML18038B8851996-08-14014 August 1996
Rev 8 to Surveillance Instruction 2-SI-4.6.G, ISI Program Unit 2.
ML18038B7811996-04-26026 April 1996
Rev 7 to Surveillance Instruction 2-SI-4.6.G, ISI Program Unit 2.
ML18038B6541995-08-12012 August 1995
Rev 7 to Odcm.
ML18038B6531995-05-25025 May 1995
Rev 6 to Odcm.
ML18037A8151993-11-19019 November 1993
Rev 3 to Odcm.
ML18037A7681993-10-21021 October 1993
Rev 3 to Surveillance Instruction 1/3-SI-4.6.G, ISI Program Units 1 & 3.
ML18037A7661993-10-21021 October 1993
Rev 2 to Surveillance Instruction 2-SI-4.6.G, ISI Program Unit 2.
ML18037A8161993-10-0101 October 1993
Rev 14 to RETS Manual.
ML20062L9321993-09-30030 September 1993
Test Plan GE102, Electromagnetic Interference & Susceptibility Test Plan for Rbvprm Part Number: 304A3718G001
ML18037A4471993-04-16016 April 1993
Emd Owners Group Procedure EMD9314, Recommended Maint Program.
ML18036B1631993-02-16016 February 1993
Rev 1 to Surveillance Instruction 2-SI-4.6.G, ISI Program, Unit 2.
ML18036B1521993-01-29029 January 1993
Rev 1 to Odcm.
ML18036B1961993-01-27027 January 1993
Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training.
ML20114D7161992-08-31031 August 1992
Inservice Testing Program for Pumps & Valves for Second 10-Yr Interval. Relief Requests Encl
ML18036A8441992-06-30030 June 1992
Revised Odcm.
ML18036A5911992-03-25025 March 1992
Rev 0 to Odcm.
ML20086D5561991-11-14014 November 1991
Rev 6 to General Design Criteria BFN-50-C-7104, Design of Structural Supports
ML20079C3431991-06-12012 June 1991
Design Criteria BFN-50-C-7100,Attachment F, Browns Ferry Nuclear Plant Detailed Design Criteria for Structrual & Miscellaneous Steel/Components for Class I & II Structures
ML18033B6431991-02-28028 February 1991
Revised Browns Ferry Nuclear Plant Offsite Dose Calculation Manual,Jul-Dec 1990.
ML18033B6121990-06-22022 June 1990
Rev 8 to Radiological Effluent Tech Spec Manual.
ML18033A9191989-06-30030 June 1989
Changes to ODCM for Jan-June 1989.
ML18033A6621989-03-0202 March 1989
Radioactive Effluent Release Rept Browns Ferry Nuclear Plant Rev of Process Control Program.
ML20246P8801989-02-22022 February 1989
Rev 1 to Design Criteria BFN-50-C-7302, Operation Criteria for Evaluation of Lower Drywell Access Platforms
ML20246H3521989-02-0101 February 1989
Maint Improvement Program, Books 1 & 2
ML18033A4391988-08-31031 August 1988
Rev 0 to Partially Deleted TVA-BCD-906N, Summary Rept for Browns Ferry Nuclear Plant,Unit 2,Cycle 6,Insp & Reconstitution Program.
ML20151G7131988-07-20020 July 1988
Emergency Operating Instruction Procedures Generation Package
ML18033A6611988-07-20020 July 1988
Semiannual Radioactive Effluent Release Rept Browns Ferry Nuclear Plant,Changes to Odcm.
ML20153B3531988-07-0707 July 1988
Rev 1 to Ampacity Evaluation Program Plan
ML18033A2701988-06-13013 June 1988
Rev 0 to Site Director Std Practice SDSP-12.7, Sys Preoperability Checklist (Spoc).
ML20151B2871988-06-10010 June 1988
Safety Sys Functional Insp Plan
ML18033A2801988-05-24024 May 1988
Operability Criteria for Miscellaneous Steel.
ML18033A2771988-05-23023 May 1988
Operability Criteria for Evaluation of Lower Drywell Access Platforms - Browns Ferry.
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Rev 0 to Special Test ST-88-16, Diesel Generator a Emergency Load Acceptance Test
ML20151L4711988-04-27027 April 1988
Rev 0 to Special Test ST-88-17, Diesel Generator B Emergency Load Acceptance Test
ML18033A2691988-04-18018 April 1988
Rev 2 to Site Director Std Practice SDSP-12.4, Return to Svc & Closure of Mods.
ML20151L5051988-04-14014 April 1988
Rev 1 to Restart Test Program Test Instruction 2-BFN-RTP-082, Standby Diesel Generators
ML18033A1961988-03-31031 March 1988
Rev 1 to Civil Engineering Branch Instruction CEB-CI 21.100, Brown Ferry Nuclear Class I HVAC Duct & Duct Support Seismic Qualification Interim Operability Acceptance Criteria.
ML18033A1911988-03-31031 March 1988
Rev 1 to Civil Engineering Branch Instruction CEB-C1.102, Operability Criteria for Miscellaneous Steel.
ML18033A1881988-03-31031 March 1988
Rev 1 to Civil Engineering Branch Instruction CEB-CI 21.97, Operability Criteria for Pipe & Pipe Supports on TVA Class I Seismic Piping - Browns Ferry.
ML20148G6141988-03-25025 March 1988
ASME Section XI, Revised Pump & Valve Test Program
ML18032A7391988-03-10010 March 1988
Procedure BFN 50 C 7100, Detailed Design Criteria for Structural Acceptance of Drywell Access Platforms.
ML18033A1631988-03-0303 March 1988
Rev 0 to Civil Engineering Branch Instruction CEB-C1.102, Operability Criteria for Miscellaneous Steel.
ML18033A1601988-02-25025 February 1988
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Rev 4 to Design Baseline & Verification Program
ML20151L4811988-01-28028 January 1988
Rev 1 to Restart Test Program Test Instruction 2-BFN-RTP-065, Secondary Containment
1998-12-03
[Table view] |
Text
ENCLOSURE 2
+ecor~ RIMS /J B4J. 880401 001 TV see TENNESSEE VALLEY AUTHORlTY Val Division of Nuclear Engineering Aut ority CIVIL ENGINEERING BRANCH INSTRUCTION CEB-CI 21.97 YIYI.Eg OPERABILITY CRITERIA FOR PIPE AND PIPE SUPPORTS ON TVA CLASS I SEISMIC PIPING - BROh'NS FERRY ISSUE DAYK REVlSlON RO Dec. 10, 1987 S. E. Azzazy p/z./&'P'4 PREPARED REVIEWED D. R. Dencon APPROVED V. E. Penneil .sf+'.
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OPERABILITY CRITERIA FOR PIPE AND PIPE SUPPORTS ON REVISION LOG Title .'
TVA CLASS I SEISMIC PIPING BROWNS FERRY CEB-CI 21.97 Revision Dote No. DESCRIPTION OF REVISION Approved Revise to require documentation on a case-by-case basis for exception to the criteria in sections 3.0, 4.2.6 and 4.2.9 to reflect US-NRC comments in a meeting on March 17, 1988.
Revise allowable stress limits for bolting material to reflect US-NRC comments in a meeting on March 17, 1988 in Rockville, Maryland.
TVA 10554 {eN DEM 1st
.OPERABILITY CRITERIA FOR~PE AND PIPE SUPPORTS CEB-CI 21.97 ON TVA CLASS I SEISMIC P~NG BROWNS FERRY TABLE OF CONTENTS PAGE 1 0
~ PURPOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 2 0
~ SCOPE ~ ~ ~ ~ ~ ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 3.0 PIPE STRESS EVALUATION CRITERIA ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 4.0 PIPE SUPPORT EVALUATION CRITERIA -.....
5.0 DOCUMENTATION ~ ~ ~ ~ ~ ~ 3 6.0 REFERENCE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 DNE4 3141M
~
'OPERABILITY CRITERIA F0~PE AND PIPE SUPPORTS CEB-CI 21.97
, ON TVA CLASS I SEISMIC PMING BROWNS FERRY 1.0 PURPOSE The purpose of this instruction is to provide engineering guidelines for implementing Browns Ferry operability criteria as applicable to non-torus attached pipe and pipe support modifications for TVA Class I seismic piping.
2.0 SCOPE These guidelines shall apply to all piping and supports on TVA Class I seismic piping, for which pipe or pipe support modifications are required; i.e., any physical modification of pipe or pipe support required as a result of the inability to qualify according to Design Criteria BFN-50-C-7103 and BFN-50-C-7104 (Reference 1 & 2).
Modifications will be prioritized into two groups; those that require implementation for operability and those that require implementation for design criteria. Operability modifications are those piping and pipe support modifications that do not comply with the criteria in this document. Design criteria modifications are those piping and pipe supports modifications that comply with the requirements of this document but are necessary for design criteria compliance.
3.0 PIPE STRESS EVALUATION CRITERIA For piping systems that do not meet the design criteria BFN-50-C-7103 a case by case piping system operability review maybe performed as follows.
For the emergency loading combinations and stress intensification factors as defined in BFN-50-C-7103, evaluate the piping to ensure that the primary stress in the piping is less than 2 Sy and the secondary stress meets ASME Section III Equation 10 and ll allowables of Reference 5.
In cases where piping secondary exceeds the secondary stress allowables of reference 5 they may be shown to meet an augmented Class '2 and 3 fatigue evaluation (Reference 7). This approach shall be used only on a case-specific basis, and specifically documented and filed for inspection and audit.
The adjacent pipe supports shall meet allowables given in this criteria document.
4.0 PIPE SUPPORT EVALUATION CRITERIA 4.1 Load Combinations and Pi in Movements For prioritization the proposed pipe support modifications shall be evaluated only for the emergency loading condition in accordance with BFN-50-C-7103.
DNE4 3141M
lt OPERABILI=Y CRITERIA F~IPE AND PIPE SUPPORTS CEB-CI 21.97 ON TVA CLASS I SEISMIC PIPING BROWNS FERRY 4.2 Allowable Limits The following limits shall be used to establish priorities for pipe support modifications.
4.2.1 Linear Su orts:
The support member stresses shall not exceed the lessor of 1.2 Sy and 0.7 Su for tensile and flexural stresses, and 90 percent of the critical buckling stress as defined in AISC specification (Reference 3) for compressive loads. Shear-stresses shall not exceed 60 percent of allowable stress for tensile and flexure stresses.
4.2.2 Standard Su ort Com onents:
These shall meet the emergency allowables of BFN-SO-C-7103.
4.2.3 B~nltin The allowable stress for bolting shall be the minimum specified yield stress of the bolt material. When the yield stress of the bolt material is not specified, the allowable stress shall be 70 percent of the minimum specified ultimate strength.
4.2.4 Concrete E ansion Anchors:
The minimum factors of safety for concrete expansion anchors (wedge 6 shell types) shail be 2.0. (Reference 6).
4.2.5 Pi e to Pi e Su ort Ga Supports with pipe to pipe support total gap which exceeds 1/2" shall be modified unless acceptable in accordance with the evaluation in 4.2.6. In addition, the first support adjacent to equipment nozzles, anchors, penetrations, and active valves and body or stem supported valves shall be modified if the total gap exceeds the installation requirement of 5/32 inch maximum total gap. (Reference 4) 4.2.6 Load Sharin Between Su orts:
For supports that do not meet the interim allowable stress criteria presented herein and are not adjacent to an equipment nozzle, an anchor, a penetration, an active valve, or a body/stem-supported valve, a case-by-case evaluation may be performed that considers redistribution of load to adjacent supports. This case-by-case evaluation must be specifically documented and filed for inspection and audit.
The effect of load redistribution on piping stress shall be considered in accordance with section 3.0.
DNE4 3141M
.- ~ OPEPABILITY CRITERIA FO~IPE AND PIPE SUPPORTS CEB-CI 21.97 ON TVA CLASS I SEISMIC PIPING BROGANS FERRY The adjacent pipe supports shall meet the allowables contained in this criteria document.
4.2.7 Constant and Variable S r in Su orts:
Shall be evaluated to accommodate the "maximum pipe movement" without bottoming out.
4.2.8 Subs stem Evaluations Portions of a stress analysis math model may be decoupled and a local analysis may be performed, to assess the need for the modification, provided appropriate overlap on model boundaries is considered. Hand calculations, new subsystem models, and scaling techniques may be utilized in addition to computer calculations.
The following section provide guidance for the evaluation of modifications required due to thermal loading.
4.2.8.1 Modifications Due to Thermal Loadin Support flexibility for specific supports may be utilized in the subsystem evaluations in lieu of conservative computer code default values to more realistically predict thermal loading.
The effects of gaps may be considered where large thermal loads result from the. constraint of small thermal growths due to opposing supports.
4.2.9 Thermal Monitorin Modifications identified due to exceeding the swing angle, binding, or other potential thermal interferences on snubber, strut, and spring supports need not be a design constraint and may be deferred, if visual monitoring shows no thermal
'inding or restraint in the support assembly. Additionally, supports requiring modification due to unrealistic thermal loads will be monitored with instrumentation to determine the actual thermal loads and the impact to other supports in the system should be assessed. This approach shall be used only on a case-specific basis, and specifically documented and filed for inspection and audit.
5.0 DOCUMENTATION Engineering evaluations performed to determine the priority of modifications shall be documented in calculations performed in accordance with the applicable QA requirements.
DNE4 3141M
ly OPERABILITY CRITERIA F~IPE AND PIPE SUPPORTS CEB-CI 21.97 ON TVA CLASS I SEISMIC MPING BROGANS FERRY
6.0 REFERENCES
6.1 Design Criteria for Structural Analysis and Qualification of Mechanical and Electrical Equipment BFN-50-C-7103.
6.2 Design Criteria for Design of Supports BFN-50-C-7104.
6.3 Specification for the Design, Fabrication, and Erection of Structural Steel Buildings, AISC 7TH and 8TH Editions.
6.4 Letter from R. L. Cloud Associates to TYA "Position Paper on Pipe to Support Gap Limit, "Letter No. P154-3 L-020, August 25, 1987.
6.5 ASME Section III, Subsection NC, 1983.
6.6 IE Bulletin No. 79-02, Revision 1, Supplement 1 dated August 20, 1079, Pipe Support Base Plate Designs Using Concrete Anchor Bolts.
6.7 NUREG/CR-2343, DATED June 1983, Comparisons of ASME Code Fatigue Evaluation Methods for Nuclear Class 1. Piping with Class 2 or 3 Piping.
DNE4 3141M
0