ML20084N818
| ML20084N818 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/28/1983 |
| From: | Malandra L, John Marshall WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML18092A175 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR WCAP-10167, NUDOCS 8405170226 | |
| Download: ML20084N818 (107) | |
Text
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. -m - ! '% g WESTINGHOUSE CLASS 3 o
T Although infonnation contained in this report '
% is nonproprietary, no distribution shall 1 M be made outside Westinghouse or its licensees without the customer's approval.
EVALUATION OF THE ACCEPTABILITY OF THE REACTOR VESSEL HEAD LIFT RIG, REACTOR VESSEL INTERNALS , LIFT RIG, LOAD CELL, AND LOAD CELL LINKAGE ; TO THE REQUIREMENTS OF.NUREG 0612 for PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM GENERATING STATION UNITS 1 AND 2 FEBRUARY, 1983 L. J. MALANDRA', P. E. - App v : d n_E., IM ManagiFr J K Marshal 17. efueling Equipment Engineering WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems P.O. Box 355 Pittsburgh, PA 15230 'M b '8405170226 840511 PDR ADOCK 05000272 P PDR 61168:1/022583
w _ t ABSTRACT An evaluation of the Salem reactor vessel head and internal lift aigs, , load cell, and load cell linkage was perfonned to determine the . acceptability of these devices to meet the requirements of NUREG 0612. The evaluation consists of: (1) a comparison report of the ANSI N14.6 requirements and the requirements used in the design and manufacture of these devices; (2) a stress report in accordance with the design criteria of ANSI N14,6; and (3) a list of recomendations to enable these devices to demonstrate compliance with the intent of NUREG 0612 and ANSI N14.6. ! l l l l I I iii 6116B:1/020883
1 TABLE OF CONTENTS , t Section Title Page ABSTRACT 111
- 1. INTRODUCTION 1 -1 1.~1 Background 1-2
- 2. COMPONENT DESCRIPTION 2-1 -
2.1 Reactor Vessel Head Lift Rig 2-1 2.2 Reactor Yessel Internals Lift Rig 2-1 2.3 Load Cell and Load Cell Linkage 2-2 ,
- 3. SCOPE OF EVALUATION 3-1 !
3.1 Study of ANSI N14.6-1978 3-1 ! l I 3.2 Stress Report 3-1 3.3 Recomendations 3-2
- 4. DISCUSSION OF EVALUATIONS 4-1 4.1 Study of ANSI N14.6-1978 4-1 4.2 Stress Report 4-1
- 4.3 Recomendations - 4-2 l
- 5. CONCLUSIONS 5-1 l
6-1 l
- 6. RECOMENDATIONS 1
V 61168:1/020883 , l
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LIST OF ILLUSTRATIONS Figure Title Page 2-1 Reactor Vessel Head Lift Rig 2-3 2-2 Reactor Vessel Internals Lift Rig 2-4
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W e l q g ATTACHMENTS A. Comparison of ANSI N14.6-1978 Requirements for Special Lifting Devices and the Requirements for the Reactor Vessel Head Lift Rig, Reactor Vessel Internals Lift Rig, Load Cell, and Load Cell Linkage for Public Service Electric and Gas Company, Salem Generating Station, Units 1 and 2. i B. Stress Report - Reactor Yessel Head Lift Rig, Reactor Vessel Inter-nals Lift Rig, Load Cell, and Load Cell Linkage for Public Service Electric and Gas Company, Salem Generating Station, Units 1 and 2. t I I
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1 1 i j l ' IX 6116B:1/020883 t
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I O REFERENCES
- 1. George, H., Control of Heavy Loads at Nuclear Power Plants .
Resolution of Generic Technical Activity A-36, NUREG 0612, July, 1980.
- 2. ANSI N14.6-1978 Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear Material
- 3. ANSI B 30.9-1971. Slings, American National Standards Institute, New York, 1971.
- 4. Westinghouse Drawing 685J059 - 3 Loop Head Lifting Rig General Assembly
- 5. Westinghouse Drawing 113E480 - 4 Loop Plants Lifting Rig Internals -
General A'ssembly i l i t l xi 6116B:1/020983
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SECTION 1 INTRODUCTION The Nuclear Regulatory Comission (NRC) issued NUREG 0612 " Control of Heavy Load at Nuclear Power Plants"O in 1980 to address the control , of heavy loads to prevent and mitigate the consequences of postulated accidental load drops. NUREG 0612 imposes various training, design, i inspection and procedural requirements for assuring safe and reliable operation for the handling of heavy loads. In the containment building, NUREG 0612 Sectio'n 5.1.1(4) requires special lifting devices to meet the requirements of ANSI N14.6-1978 "Anerican National Standard for Special Lifting Devices for Shi ng Containers Weighing 10,000 Pounds or More , for Nuclear Materials". In general, ANSI N14.6 contains detailed requirements for the design, fabrication, testing, maintenance, and quality assurance of special lifting devices. In addition, ANSI N14.6 requims that when wire rope or chain is used in the design of a special lifting device, the wire rope or chain shall be in confomance with ANSI B30.9-1971 "American National Standard Safety Standard for Slings" .[3] ( l The Salect Generating Station lifting devices which can be categorized as special lifting devices and which are contained in the scope of this { report are: t
- 1. Reactor vessel head lift rig
- 2. Reactor vessel internals lift rig I
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- 3. Load cell 1
- 4. Load cell linkage This report contains the evaluation perfomed on these lifting devices i to detemine the acceptability of these devices to meet the above requirements.
l 9 61168:1/022583 1 -1 l
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y . > f i m Cs V 1.1 BACXGROUND The reactor vessel head lift rig, the reactor vessel internals lift rig, Joad cell, and load cell linkage were originally designed and built for the Salem Generating Station circa 1967-71. Subsequently, the Unit 2 internals lift rig was transferred to another plant site in 1975-76 and replaced in 1977 with an almost identical design. The actual design criteria is unknown for the lifting devices. It appears that Westing- ! house used the design criteria that the resulting stress in the load l carrying members, when subjected to the total combined lifting weight, f should not exceed cne fifth (1/5) of the ultimate strength of the j material. These items were not classified as nuclear safety components l and requirements for formal documentation of design requirements and l stress reports were not appifcable. Thus, stress reports and design specifications were not formally documented. Westinghouse defined the :
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design, fabrication and quality assurance requirements on detailed ! manufacturing drawings a'd n purchase order documents. Westinghouse also , issued field a'ssembly instructions for the reactor vessel head and
-internals lift rigs which included an initial load test followed by l
-non-destructive surface examination of critical load bearing areas. l
. Additionally, the new Unit 2 internais ifft rig was load test'ed at the
. manufacturers shop at 125 percent of the maximum weight. Subsequent -
modifications (presently in progress) to the internals lifting rig : include rotolock studs and. inserts designed, manufactured, and tested to l the requirements of ANSI N14.6. ! l-i i I i i i l O : f;
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6116B:1/020983 1-2 i i L
r m - CN SECTION 2 COMPONENT DESCRIPTION 2.1 REACTOR VESSEL HEAD LIFT RIG The reactor vessel head lift rig CI3 is a three-legged carbon steel structure, approximately 43 feet high and 14 feet in diameter, weighing approximately 28,000 pounds. It is used to handle the assembled reactor vessel head. The three vertical legs and Control Rod Drive Mechanism (CRDM) platfom assembly are pemanently attached to the reactor vessel head lifting lugs. The tripod sling assembly is attached to the three vertical legs and is used when installing and removing the reactor vessel head. Duving plant operations, the sling assembly is removed and the three van.fcal legs and platfom assembly remain attached to the reactor vessel head. l t
/, 7 2.2 REACTOR VESSEL INTERNALS LIFT RIG y.
The reactor vessel internals lift rig [2] is a three-legged carbon and stainless steel structure, approximately 25 feet high and 14 feet in diameter weighing approximately 14,500 pounds. It is used to handle the upper and lower reactor vessel internals packages. It is attached to the main crane hook for all lifting, lowering and traversing opera- ; tifons. A load cell linkage is connected between the main crane hook and the rig to monitor loads during all operations. When not in use, the rig is stored on the upper internals storage stand. ' The original rig design attaches to the internals packages by means of three engaging screws which are screwed into tapped holes in the inter-nals flanges. These screws are manually operated from the manipulator crane walkway using a handling tool which is essentially a long wrench. The screws are nomally spring retracted upward and are depmssed to engage the tapped holes by tha weight of the handling teol. Modifica-tions to these rigs, presently in progress, include installation of an p E I LJ 6116B:1/020883 2-1
_., . - . . ^~ s '1 operating pictform, integral tools and a change to the type of engage-ment with inte nals to a rotolock stud and insert type. These rotolock studs are manually operated from the new internals lift rig platform using a handling tool which is an integral part of the rig. The studs l are nonna11y spring retracted upward and are depressed to engage the
,j , inserts. Rotating the mechanism locks it in both positions. Since h these rotolock studs are in the process of being incorporated, both j types of Toad carrying items are included in this report.
2.3 LOAD CELL AND LOAD CELL LINKAGE
]! The load cell is used to monitor the load during lifting and Towering j the reactor vessel head or internals to ensure no excessive loadings are occurring. It is installed between the load cell linkage and the lift-ing device. The load cell is a strain gage (tension) type, rated at 400,000 pounds aid built by W. C. Dfilon and Co. The load cell linkage is an assembly af pins, plates and bolts which connect the polar crane C')
\J main hook to th? Toad cell.
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q _ x ._ - Om HOOK PIN S10E PLATE BOTTOM PIN f h LINK LUG UPPER CLEVIS 5" O ETER UPPER p , I
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SUPPORT LUG [ '
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8b i ! 's Figure 2-1. Reactor Vessel Head Lift Rig j I [G 6116B:l/020883 2-3
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i I /- x l, I WHERE PSE AND FNJ RIGS OlFFER,THE PSE ITEMS ARY DISTINGUISHED BY AN "A" SUFFIX.THE PNJ ITEMS BY A "B" SUFFIX 71/2 DIA HOOK PIN l SIDE PLATE l UPPER ADAPTOR ADAPTOR PIN LOAD CELL BOTTOM ADAPTOR A&B TOP LUG 6"DIA REMOVABLE PIN A&8 4"DIA CLEVIS PIN SUPPORT PLATE A&B A&B SIDE LUG SUPPORT PIPE A&B ! A&B UPPER CLEVIS { G LEG A&8 SPACER A&B LOWER CLEVIS ' 4" DIA CLEVIS
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s % END PLATE SPR EADER " MOLY , v BACKING # BLOCK i [ ! f fl' :*23B . PNJ M 2 8 LOAD NUT B TUBE HOUSING h i i PSE ., 25A l 278 h d B GUIDE SLEEVE - N ,1 27
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t _ BRACE PLATE o A&B LEG SUPPORT BLOCK f ADAPTOR A I RING GIRDER OUTER TUBE A GUIDE SLEEVE A
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ENGAGING SCREW A&B Figure 2-2. Reactor Vessel Internals Lift Rig 61168:1/020883 2-4 L
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i i SECTION 3 i I SCOPE OF EVALUATION I The evaluation of these lifting devices consists mainly of three parts:
- 1. A detailed review of the ANSI N14.6 requirements
- 2. . Preparation of a stress report
- 3. Recomendations to demonstrate compliance with NUREG 0612, i Section 5.1.1(4). .
l Discussion of these items follows. ! 3.1 REVIEW OF ANSI N14.t-1978 l l A detailed comparison was made of the infomation contained in i ANSI N14.6 with the infomation that was used to design, manufacture, ! inspect and test these special lifting devices. The detailed comparison is provided in three parts: i l 1. Overall item by item comparison of requirements i
- 2. Preparation of a critical item list per ANSI N14.6 Section 3.1.2, and P
i- 3. Preparation of a list of nonconfaming items. [ j This detailed analysis is contained in Attachment A to this report. ; 3.2 PREPARATION OF A STRESS REPORT l Section 3.1.3 of ANSI N14.6 and NUREG 0612 Section 5.1.1(4) require a f. stress report to be prepared. Special loads and allowable stress criteria are specified for this analysis. The stress report is Attach-ment B to this report. O d ; 61168:1/020883 3-1 l 1 l . . I l--- . . - _ . . . . . - , --.. . _ . . _ . . . . . . . . . . _ . . . . . , _ _ . . . , _ --,.
7 ... ... .. I f t i I 3.3 REC 0144 ENDED ACTIONS An obvious result from the previous evaluations is a list of items that can be perfonned to demonstrate to the NRC that these special lifting , 5 devices are in compliance with the guidelines of ANSI N14.6 and NUREG 0612 Section 5.1.l(4). These recomendations are identified in i Section 6. ! . r I l l i i i
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't ! 61168:l/020883 3-2 i !- _ . _ . _ . . . _ _ _ _ _ _ _ . . _ _ _ _ _ -
f k I l I SECTION 4 j DISCUSSION OF EVALUATIONS 4.1 STUDY OF ANSI N14.6-1978 A review of ANSI N14.6 identifies certain analyses to be perfomed and : certain identifications that are required to be made to demonstrate compliance with this document. These are a preparation of a stress
! report in accordance with Section 3.2 and a preparation of a critical items list in accordance with Section 3.1.2. The stress report is Attachment B to this report. The critical items list has been pre-pared per Section 3.1.2 and is contained in Appendix A to Attachment A.
This list identifies the critical load, path parts and welds, the materials of these items, and the applied non-destructive volumetric and surface inspections that were perfomed. (Details of these non-destruc-I tive processes and acceptance standards are available at Westinghouse should they be needed.) l l A detailed itEn by item comparison of all the requirements of ANSI N14.6 and those used for the design, manufacture and inspection of these lift-ing devices is contained as Table 2-1 of Attachmint A.' The comparison L shows that these devices meet the intent of the ANSI document for design, fabrication and quality control. However, they do not meet the requirements of ANSI N14.6 for periodic maintenance, proof and func-
- l j tional testing. Thus, a tabulation of those ANSI N14.6 requirements that are incompatible with these lifting devices was prepared and is Appendix B to Attachment' A. Included in Appendix B to Attachment A are i recommended actions that may be used to demonstrate acceptability to the
! NRC.
4.2 STRESS REPORT As p'a rt of the invoking of the ANSI N14.6 document, the NRC requested utilities to demonstrate their compliance with the stress criteria with
, some qualifying conditions. Attachment B is the stress report for these -
devices perfomed in accordance with the criteria of ANSI N14.6. A l I 6116B:l/020883 4-1 k g . 0..
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y , l O . g] - discussion is included which responds to the NRC qualifying conditions ; of NUREG 0612. All of the tensile and shear stresses meet the design j criteria of Section 3.2.1.1 of ANSI N14.6, requiring application of l stress design factors of three and five with the accompanying allowable ! stress limits of yield and ultimate stmngth, respectively. . 4.3 RECOR4ENDATIONS i i The recomendations identified in Section 6 require a review of plant : maintenance and operating instructions to ensure that they contain ' infomation relative to the identification, maintenance and periodic ; testing required by ANSI N14.6. The extent of the periodic testing is also addressed and the mcomendations identify procedures which are intended to fully meet the intent of NUREG 0612 and ANSI N14.6 with the ! least amount of perturbation to the refueling sequence. These recom- l mendations do not involve any equipment changes unless stricter com- ! pliance becomes necessary, and then a change to the sling blocks is [ recomended. !
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t t 61168:1/020883 4-2 . I
T , i l I SECTION 5 CONCLUSIONS The following conclusions are apparent as a result of this evaluation:
- 1. The ANSI N14.6 requirements for design, fabrication and qua11ty assurance are generally in agreement with those used for these i
special lift devices.
- 2. The ANSI N14.6 criteria for stress limits associated with certain stress design factors for tensfie and shear stresses are adequately satisfied.
i 3. These devices are not in strict compliance only with the i ANSI'N14.6 requirements for acceptance testing, maintenance and verification of continuing compliance. Recommendations are ine.luded to identify actions that should enable these devices to l I be considered in compliance with the intent of ANSI N14.6. i 4. The application of the ANSI N14.6 criteria for stress design fr.ctor of 3 and 5 are only for shear and tensile loading craditions. Other loading conditions are to be analyzed to k other appropriate criteria. i I I l l 1 L I k 5-1 l 6116B:1/020983 d
T i i i i SECTION 6 RECOMMENDATIONS i The following reconenendations address the areas of ANSI N14.6 which are incompatible with the pmsent lifting devices and which are considered most important in demonstrating the continued reliability of these devices. They consist of suggestions and proposed responses to identify compliance to the NRC and future considerations. 6.1 Review plant operating procedures to include consideration of ANSI N14.6 Sections 5.1.3 through 5.1.8. These sections include requirements for: scheduled periodic testing; special identifica-tion and marking; maintenance, repair, testing and use. Westing-
! house remarks on addressing these sections are, listed in Attachment
- ' A, Appendix B, Items 7, 8, and 9.
6.2 A proposed msponse to the requireme'it of ANSI N14.6 Section 5.2.1 requiring an initial acceptance load test prior to use equal to 150 l ) percent of the maximum load is as follows: J
' After site assembly these special lifting devices were subject to a 100 pen:ent load test followed by non-destructive testing of all critical areas. The Unit 2 internals lift rig was subject to a 125 percent load test followed by appropriate non-destructive testing of i
i, all critical areas. The new load path items will be tested to 150
' percent of the maximum load prior to shipment.
6.3 A proposed response to ANSI N14.6 Section 5.3 wh.ch requires.
- annually, either a 150 percent maximum load test or dimensional,
' visual and non-destructive testing of major load carrying welds and l
[ critical amas follows. (Since the 150 pen:ent load test is very ' ' impractical, the approach identified in the following reconsnendation is to perfonn a minimum of non-destructive testing.) : I l } ! 4- 6-1 Y 61168:1/022583 1 L- - - - - - - . - ___ _ _ _. .
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- a. Reactor Yessel Head Lift Nig !
l Prior to use and after reassembly of the spreader assembly, f lifting lug a.d upper lifting legs to the upper portion of the ! I lift rig, visually check all welds. Raise the vessel head .
.s11ghtly above its support and hold for 10 minutes. During this !
time, visually inspect the sling block top lug to top plate f weld, side lugs to support pipe welds, and spreader lug to j spreader arm weld. If no problems are apparent, continue to lift, monitoring the load cell readout at all times.
. b. Reactor Yessel Internals Lift Rig Prior to use, visually inspect the rig components and welds while on the storage stand for signs of cracks or deformation.
Check all bolted joints to ensure that they are tight and
; secure. After connection to the upper or lower internals, raise V( '
the assembly slightly off its support and hold for 10 minutes. During this time, visually inspect the sling block top lug to support plate weld, side lugs to support pipe welds, spacer to leg weld, and brace plate and leg support block to leg welds.
- i. If no problems are apparent, continue to lift, monitoring the load cell readout at all times.
The above actions do not include a non-destructive test of these welds because: 4
- a. Access to the welds for surface examination is difficult.
These rigs are in containment and some contamination is present.
- b. All tensile and shear stresses in the welds are well within the allowable stress.
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{ ) c. The items that are welded remain assembled and cannot be misused for any other lift other than their intended l function. i
- d. To perfonn non-destructive tests would require:
(1) Removal of paint around the area to be examined which is contaminated. l (2) Perfonnance of either magnetic particle inspection or liquid penetrant inspection and i' (3) Repainting after testing is completed. 2 (4) Cleanup of contaminated items.
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i Perfonning non-destructive tests on these welds every refueling would increase the critical path refueling time. f ! l } i i Dimensional checking is not included since these structures are 1arge (about 14 feet diameter by 30 feet high) and the results of dimensional checking would always be questionable. Other checks on
- critical load path parts such as pins, are also not included since i - an examination of these items would require disassembly of the
.e j special lift devices.
1 6.4 Reconsnend that a periodic non-destructive surface examination of ( critical welds and/or parts be perfonned once every ten years as f part of an inservice inspection outage.
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6.5 Recommend that the head and internals lift rig sling block be [, l changed to a forged block with welded side lugs to reduce the number ! i of welds and eliminate any concern, if any, of lamellar tearing, a should the NRC require yearly surface inspection of welds and plates. l I 6-3 j 6116B:1/020883 k . m um
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l l l 6.6 Recomend that nn changes be made to the reactor vessel internals i lift rig should the stresses, discussed in Attachment B, be o considered excessive by others because: . 4
- a. The design weight used in the stress calculations is based on I b
the weight of the lower internals. The lower internals are only removed when a periodic inservice inspection of the vessel is
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required (once/10 years). . l i i
- b. Prior to removal of the lower internals, all fuel is removed.
1 Thus the concern for handling over fuel is non-existent in this i particular case. l
- c. Nonnal use of the rig is for moving the upper internals which ,
weigh less than one-half of the lower internals. The design weight is based on lifting the lower internals. Thus all the stresses could be reduced by more than 50 percent and considered well within the ANSI N14.6 criteria for stress design factors. l l l l t I l-I l l' (~ ( N) 61168:1/020883 6-4 ,
7 WESTINGHOUSE CLASS 3 - Although information contained in this report ATTACHMENT A
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- is nonproprietary, no distribution shall to WCAP-10167 be made outside Westinghouse or its ,
licensees without the customer's approval . 4
\
Comparison of ANSI N14.6-1978 Requirements for Special Lifting Devices and the Requirements for the Reactor' Vessel Head Lift Rig, Reactor Vessel Internal s Lift Rig, Load Cell, and Load Cell Linirage for Public Service Electric and Ga s Company Salem Generating Station f Units 1 and 2 1 i February 1983 L. J. Mal a ndra , P.E. l 9 l l l'
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4 I 4 5 f Appr ved h -- + J. R. Mar shall , P.E. Mand Refueling Equipment Engineering l i
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[- 6122B:1/030283 , i g . v, w
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i l I ABSTRACT l The requirements used in the original design, fabrication, testing, maintenance and quality assurance were compared to the ANSI N14.6-1978 f i requirements for the Salem reactor vessel head and internals lift rig, load cell and load cell ifnkage. A critical items list per ANSI N14.6
; section 3.1.2.has been prepared and a tabulation of ANSI N14.6 requirements that are, at present, incompatible with the Salem lifting devices has been prepared.
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7 6 i TABLE OF CONTENTS Section Title Page ABSTRACT iii i PURPOSE 1-1 2 INTRODUCTION 2-1 2.1 Background 2-1 2.2 Component Description 2-2 2.2.1 Reactor Yessel Head Lift Rig 2-2 2.2.2 Reactor Vessel Internals Lift Rig 2-2 2.2.3 Load Cell and Load Cell Linkage 2-3 3 DISCUSSION 3-1 I 4 CONCLUSIONS 4-1 APPENDIX A - CRITICAL ITEMS LIST PER ANSI N14.6-1978 A-1 APPENDIX B - TABULATION OF ANSI N14.6-1978 REQUIREMENTS B-1 INCOMPATIBLE WITH THE SALEM SPECIAL LIFTING DEVICES y.- (d 61228:i/021483 y
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l I s s x-3 LISTOFILLUSTRATIONS
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Figsre Title , Page ; A-1 Reactor Vessel Head Lift Rig - A-5 l
. A-2 Reactor Yessel Internals Lift Rig A-10 ;
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- i s A-3 Rotolock Studs and Inserts Arrangement .
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b p i l ! LIST OF TABLES Table Title Page 2-1 Comparison of the Requirements of ANSI N14.6 2-4 and Salem Special Lifting Devices A-1 Reactor Vessel Head Lift Rig, Critical Items A-3 , List of Parts per ANSI N14.6-1978 A-2 Reactor Yessel Head Lift Rig, Critical Items A-4 List of Welds per ANSI N14.6-1978 Reactor Vessel Internals Lift Rig, Load Cell A-6 A-3 ' and Load Cell Linkage, Critical Itsus List of Parts per ANSI N14.6-1978 l Reactor Vessel Internals Lift Rig, Load Cell A-12 { ) A-4 l and Load Cell Linkage, Critical Items List , of Welds per ANSI N14.6-1978 i i 61228:1/022583 ix
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REFERENCES e ,
- 1. Westinghouse Dr' awing 685J059 - Head Li,fting Rig General Assembly
- 2. Westinghouse Drawing 113E480 - 4 Loop Plants L*fting Rig Internals ;
General Assembly ;
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I SECTION 1 PURPOSE The purpose of this report is to compare the requirements of the special lifting rigs used to lift the reactor vessel head, reactor vessel upper and lower internals with the requirements contained in ANSI N14.6 for ! special lifting devices. l P P i l i i i l l I I ! 6122B:1/021003 1-1 l l
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SECTION 2 INTRODUCTION ANSI N14.6-1978 "American hational Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear ' Materials" contains detailed requirements for tne design. fabrication, testing, maintuance and quality assurance of special lifting devices. . NUREG 0612 " Control of Heavy Load at Nuclear Power Plants", paragrapn 5.1.l(4), specifies tnat special lifting devices should satisfy the gu idelines of ANSI N14.6-1978. Subsequently the Nuclear Regulatory Commission (NRC) has requestea operating plants to demonstrate compiiance with NUREG 0612. To demonstrate compi f ance with this document, a detailed comparison of the original design, fabrication, testing, maintenance ana quality assurance requirements witn those of ANSI N14.6 is necessary. Thus, the ANSI N14.6 document has been reviewed in cetail ana comparea to the requirements used to cesign and manufacture the reactor vessel I k head lif t rig, tne reactor vessel inte?nals lift rig, load cell, load cell linkage and the reactor coolant pt;mp motor lif t sling. Th is comparison is listed in Table 2-1.
2.1 BACKGROUND
The reactor vessel head lift rig, the reactcr vessel internals lift rig, load cell, and load cell linkage were originally designed and ouilt for the the Salem Generating Station circa 1967-1971. Suosequently, the Unit 2 internals lif t rig was transferrea to another plant site in 1975-76 anc replaced in 1977 with an almost iaentical design. The actual design criteria is unknown for the 1ifting devices. It appears that Westinghouse used the design criteria tnat the resulting stress in the load carrying members, when subjected to the total comoined lif ting weif t, should not exceed one fifth (1/5) of the ultimate strengtn of the material. These items were not classified as nuclear safety com-ponents and requirements for formal documentation of design requirements and stress reports were not applicable. Thus, stress reports and design l I specifications were not formally documented. Westinghouse oefined the 61228:l/030183 2-1
'O design, fabrication and quality assurance requirements on detailed manufacturing drawings and purchase order documents. Westinghouse also issued field assembly instructions for the reactor vessel head and ,
t
- internais lift rigs which included an initial load test followed by g non-destructive surface examination of critical load bearing areas.
Additionally, the new Unit 2 internals lift rig was load tested at the 1 i manufacturers shop at 125 percent of the maximum weight. Subsequent j i. modifications (presently in progress) to the internals lifting rig g include rotolock studs and inserts designed, manufactured, and tested to { the requirements of ANSI N14.6. c' 2.2 COMPONENT DESCRIPTION 2.2.1 Reactor Yessel Head Lift Rig The reactor vessel head lift rigEU is a three-legged carbon steel b_
; structure, approximately 43 feet high and 14 feet in diameter, weighing
() approximately 28,000 pounds. It is used to handle the assembled reactor vessel head. 9 The three vert # cal legs and control rod drive mechanism (CRDM) platform assembly are pe manently attached to the reactor vessel head lifting I- lugs. The trfpod sling assembly is attached to the three vertical legs and is used when installing and removing the reactor vessel head. I Ducing plant operations, the sling assembly is removed and the three l vertical legs and platform assembly remain attached to the reactor l 7 vessel head. 1 (
) 2.2.2 Reactor Vessel Internals Lift Rig
.3
$ The reactor vessel internals lift rig [2] is a three-legged carbon and 1
stainless steel structure, approximately 25 feet high and 14 feet in , , ,(f diameter weighing approximately 14,500 pounds. It is used to handle the l l j upper and lower reactor vessel internais packages. It is attached to ! 6122B:1/021483 2-2 l
.[ the main crane hook for all lifting, lowering and traversing operations. A load cell linkage is connected between the main crane '
hook and the rig to monitor loads during all operations. khen not in use, the rig is stored on the upper internals storage stand. i The original rig design attaches to the internals packages by means of three engaging screws which are screwed into tapped holes in the internals flanges. These screws are manually operated from the manipulator crane walkway using a handling tool which is essentially a long wrench. The screws are normally spring retracted upward and are depressed to engage the tapped holes by the weight of the handling tool. Modifications to these rigs, presently in progress, include installation of an operating platform, integral tools and a change to the type of engagement with the internals to a rotolock stud and insert type. These rotolock studs are manua.11y operated from the new internals lift rig platform using a handling tool which is an integral part of the rig. The studs are normally spring retracted upward and are depressed l l to engage the inserts. Rotating the mechanism locks it in both positions. Since these rotolock studs are in the process of being incorporated, both types of load carrying items are included in this report. , 2.2.3 Load Cell and Load Cell Linkage The load cell is used to monitor the load during lifting and lowering the reactor vessel head or internals to ensure no excessive loadings are occurring. It is installed between the load cell ifnkage and the lifting device. The load cell is a strain gage (tensiun) type, rated at l ! 400,000 pounds, built by W. C. Dillon and Co. The load cell linkage is an assembly of pins, plates and bolts which connect the polar crane main hook to the load cell. , \ l l I 6122B:l/021483 2-3
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( (v) TABLE 2-1 COMPARISON OF THE REQUIREMENTS OF ANSI N14.6 AND { SALEM SPECIAL LIFT DEVICES y , C o Actual Special Lift Device Requirements M ANSI N14.6 Description of ANSI N14.6 Requirement - g Section These sections are definitive, and not 1 Sco e and Definitions - These sections requirements. 1.1 e ine the scope of the document and to include pertinent definitions of 1.3 specific items : 2 1' A. No original design specification was 3 Design written concerning these specific 3.1 ITisigner's Responsibilities - This section requirements. Subsequent modifications 3.1.1 contains requirements for preparing .to the internals lift. rig meet these to a design specification and its' contents, requirements. liowever, assembly and 3.1.4 stress reports; repair procedures; limi- detailed manufacturin'g drawings and tations on use with respect to environ-mental conditions; marking and nameplate purchasing documents contain the m information; and critical items list. following requirements: a (1) Material specification for most of the cri.tical load path items to ASTM, -l ASME specifications or special listed requirements. (2) All welding, weld procedures and welds to be in sccordance with ASME Boiler and Pressure Vessel Code - Section IX. (3) Special non-destructive testing for specific critical load path . items to be performed to written and approved procedures in accordance with ASTM or specified requirements
^ - - - - - - -
_, , , , ,, ...%.~>...m- . - . . . ~ , i3 [$ TABLE 2-1 (cont) C0HPARISON OF THE REQUIREMENT OF ANSI N14.6 AND , SALEM SPECIAL LIFT DEVICES , gg ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements ,, Section i (4) All coatings to be performed to strict compliance with specified requirements. (5) Letters of compliance for materials and specifications were required for verification with original specifications. i B. A stress report was not originally required but has been prepared and is
- Attachment B.
C. Repair procedures were not identified. D. No limitations were identified as to the use of these devices under adverse environments. E. Markings and nameplate information was not addressed. F. Critical item lists have been prepared for each device and are identified as Appendix A to this Attachment A. G
. . - . -. - - . ~ . - . - . . -
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TABL 2-1 (cont) COMPARISON OF THE NEQUIREMENT OF- ANSI _ N14.6 AND ' 6 SALEM SPECIAL LIFT DEVICES. a
; ANSI N14.6 Description of ANSI N14.6 Hequirement Actual Special Lift Device Nequirements j Section
! 3.2 Design Criteria 1. The actual design criteria is un . ! 3. 2.1 Stress Design factors - These sections known for the lif ting devices. It - j 3.2.6 contain requirements for the use of stress appears that for ~ the head lifting rig, j design factors of 3 and 5 for allowable internals lif t rig and load ' cell, that
- stresses of yield and ultimate respec- in most cases the design criteria used
., tively for maximum shear and tensile was that the resulting stress in stresses; high strength material stress the load carrying members, when sub-design factors; special pins; wire rope jected to the total combined lif ting i and slings to meet ANSI B30.9-1971; and weight, shoold not exceed one fiftn
! drop-weight tests and Charpy impact test (1/b) of the ultimate strength of i requirements the material. A stress report
, m ( Attachment 8) has been generated
- .& which addresses the capability of i these rigs to meet the ANSI design ;
l stress factors. i l 2. High strength materials are used in l some of these devices (mostly for l pins,loadcell). Although the i fracture toughness was not cetermined, the material was selected based on it's excellent fracture toughness j . characteristics. However, the stress ,
; design factors of ANSI hl4.6 Section l 3.2.1 of 3 and 5 were used in the j analysis and the resulting stresses j are acceptable.
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- 3. Were necessary, the weight of pins .
was considered for handling. i l I m- 61228:1/022583
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4' M e $ O# "O'e ' +d( $* , b $ TABLE 2-1 (cont) . m . n O! COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND k O SALEM SPECIAL LIFT DEVICES C! Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements $ ANSI N14.6 Section
- 4. Drop weight and Charpy impact tests were not required nor performed.
Design Considerations - These sections Decontamination was not specifically 3.3 3.3.1 contain considerations for; materials of addressed. Lamellar tearing was construction, lamellar tearing; decontam- considgred in the desian of the reactor to ination effects; remote engagement provi- vessel and internals lift ria sTTng 3.3.8 blocks by requiring non-dsstructive-sfons; equal load distribution; lock tests (ultrasonic, magnetic particle devices; position indication of remote actuators; retrieval of device if disen- and radiograph) of the base material gaged; and nameplates, and as_sembly welds. Even distribution of the load is evident from these - designs. Locking plates, pins, etc. are m used throughout these special lifting 4 devices. Remote actuation is only used when engaging the internals lift rig with the internals, however, present modifications include positive position indication of engagement. All these items were considered and the designs reflect these requirements. Design Considerations to Minimize Decontam- Decontamination was not specifically 3.4 addressed. However, the design and 3.4.1 ination Efforts in Special Lifting Device Use - These sections contain fabrication, manufacture included many of these to items, i.e. lock devices, pins, etc. 3.4.6 Eding, finishes, joint and machining requirements to permit ease in .
. decontamination.
O O V I's U I S
'f S TABLE 2-1 (cont)
M ~l'
, COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND l E SALEM SPECIAL LIFT DEVICES ! -
8 1 ; , S i 8 ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section I 3.5 Coatings - These sections contain provi- The requirements for coating carbon
- 3.5.1 stons for ensuring proper methods are steel surfaces are contained in a j to used in coating carbon steel surfaces Westinghouse process specification j 3.5.10 and for ensuring non-contamination of referenced on the assembly and detail
' stainless steel items. drawings. This specification requires a proven procedure, proper cleaning, preparation, application and final i inspection of the coating. These j . requirements meet the intent of 3.5.1 through 3.5.8. No provisions were ! m included in these designs for
& consideration qf decontamination materials or the use of non-contaminating i, contact materials for use in stainless !
j steel parts. )j 3.6 3.6.1 Lubricants - These sections contain No specific lubrication requirements requirements for special lubricants to have been identified. However, neolube' i to minimize contamination and degradation of is recomunended for use with the engaging l 3.6.3 the lubricant and contacted surfaces screws in the internals lift device { or water pools which are under water and silicone i grease for the load cell pins which are out of water. , 4
. - _ - . _ . _ _ _ _ _ _ . _ . _ _ _ . ~ . . . _ . ~ . _ _ _ _ _ . _ _ . - _ . - _ . _ . _ . . . . . . _ . . _ _ . . , , . , - - - . _ _ . ~ _ . _ . _ . _ _ . . - , _ _ . - . . . ~ . - .
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hj TABLE 2-1.(cont) i*: COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND SALEM SPECIAL LIFT DEVICES- [3 8 w ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section 4 Fabrication A formal quality assurance program for the 4.1 Fabricators Responsibilitie -!5asa manufacturer was not specifically required. 4.1.1 sections contain specific requirements However, all the manufacturers welding pro-to for proper quality assurance, document cedures and non-destructive testing pro-4.1.12 control, deviation control, procedure cedures were reviewed by Westinghouse prior control, material identification to use. All critical load carrying members and certificate of compliance. require. letters of compliance for material requirements. Westinghouse performed certain checks and inspections during various steps of manufacturing. Final Westinghouse review includes visual, dimensional, procedural, cleanliness, personnel qualification, etc. and issuance 7' of a quality release to ensure conformance
"' with drawing requirements. ,
4.2 Inspectors Responsibilities -These Westinghouse Quality Assurance personnel 4.2.1 sections contain requirements for performed inprocess and final to a non-supplier inspector, inspections similar to those identified 4.2.5 in these sections. ( Also see comments to Section 4.1 above) 4.3 Fabrication Considerations -These General good manufacturing processes-4.3.1 sections contain special requirements were followed in the manufacture to for ease in decontamination or control of these devices. However, the 4.3.3 of corrosion. information defined in these sections was not speci fically addressed. . w ~ m , _, -,,
s TABLE 2-1 (cont) [ COMPARIS0N OF REQUIREMENT OF THE ANSI N14.6 AND {} SALEM SPECIAL LIFT DEVICES
.B.s (
.: o D! ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements
$1 Section i u
5 Acceptance Testing Maintenance, Both of these rigs were load tested after and Assurance of Continued initial assembly on site followed by non-Compliance Owner's Respontibilities - destructive testing of critical load 5.1 Sections 5.1.1 and 5.1.2 require the bearing areas. The new Unit 2 internals 5.1.1 owner to verify that the special lift rig was also load tested to 125% of to lifting devices meet the performance the design weight. However, the Westing-5.1.8 criteria of the design specification house Quality Release may be considered by reviewing records and witness an acceptable alternate to verify that of testing, the criteria for letters of compliance - for materials and specifications required by the Westinghouse drawings i' and purchasing documents was satisfied. E Maintenance and inspection procedures Section 5.1.3 requires periodic functional testing should be revised to include a visual check of critical welds and parts during lifting to comply with this requirement for functional testing. Section 5.1.4 requires operating procedure Operating instructions for the reactor vessel internals lift rig were furnished to the utility and operating procedures were prepared and are used.
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@! TABLE 2-1 (cont)
(( COMPARIS0N OF THE REQUIREMENT OF ANSI N14.6 AND h! SALEM SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section I - Sections 5.1.5, 5.1.5.1 and 5.1.5.2 require It is obvious from their designs special identification and marking to that these rigs are special lifting prevent misuse, devices and can only be used for their intended purpose. Specific identifi-
, cation of the rig can be made by mark-ing, with stencils, the rig name and rated capacity, preferably on the spreader assembly.
Sections 5.1.6, 5.1.7 and 5.1.8 require Operating instructions and maintenance the owner to provide written documenta- instructions should be reviewed to tion on the maintenance, repair, testing assure that they contain the require-and use of these rigs. ments to address maintenance logs, is repair and testing history, damage
- incidents etc.
e t ,_ _ _~ _ __
(% / .f% [ t TABLE 2-1 (cont) COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND P' SALEM SPECIAL LIFT DEVICES C 2
% ANSI N14.6 Description of ANSI Nf4.6 Requireiaent Actual Special Lift Device Requirements $ Section 5.2 Acceptance Testing and Testing to Verify and The head and internals lift rigs were load Continuir.g Compliance - These paragraphs tested after field assembly. In addition, 5.3 requira the rigs to be initially tested 5.2.1 the new Unit 2 internals lift rig was load at 150% maximum load followed by tested to 125% Toad at initial manufacture.
to non-destructive testing of critical load 5.2.3 The new load bearing modifications presently in bearing parts and welds and also annual progress will meet these requirements. It is and 150% load tests or annual non-destructive 5.3.1 suggested that a check of critical welds and tests and examinations; qualification of parts be included in the maintenance pro-to replacement parts. 5.3.8
- cedures. Preferably, a visual check during initial lift should be acceptable. Further note that with the use of the load cell for the head and internals, lifting and lowering m is monitored at all times. However, the load cell, cannot exceed the rated load by 20%
h without being inaccurate. This would preclude monitoring of a 150% load test with the present equipment. Replacement parts should be in accordance with the original or equivalent requirements. J e e W
,-- o ,,
_ k ' i TABLE 2-1 (cont) l h . COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND
@ SALEM SPECIAL LIFT DEVICES C
o y ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements g Section , 5.4 Maintenance and Repair - This section Maintenance and repair procedure should 5.4.1 requires any maintenance and repair to be contain, as much as possible, require-to performed in accordance with original ments that were used in the original 5.4.2 requirements and no repairs are permitted fabrication. The critical items list of , for bolts, studs and nuts. Appendix A contains the original type of ! non-destructive testing. The procedure - should also define bolts, studs and nuts as non-repairable items. 5.5 Non-destructive Testing Procedures, Liquid penetrant, magnetic particle, 5.5.1 Personnel Qualifications, and Acceptance ultrasonic and radiograph inspections to criteria - This section requires non- were performed on identified items. y 5.5.2 destructive testing to be performed in These were in accordance with Westing-house process specifications or as noted g accordance with the requirements of the ASME Boiler and Pressure Vessel Code on detailed drawings and provide similar results to the requirement of the ASME Code. 6 Special Lifting Devices for Critical It is assumed that compliance with 6.1 Loads - These sections contain special NUREG 0612, Section 5.1 has been 6.2 requirements for items handling critical demonstrated and therefore this se:: tion 6.3 loads. is not applicable to these devices. 9
l s 3 [ i SECTION 3
? DISCLISSION 7 '
t'
- j. The mactor vessel head and internals lift rigs, load cell and load cell j linkage generally meet the intent of the ANSI N14.6 mquirements for j design and manufactum. However, they are not in strict compliance with ,
s i the ANSI N14.6 mquirements for acceptance testing, maintenance and
'i verification of continuing compliance. ;
g
?$
3 Although no specific design specification was written, the assembly and j detailed manufacturing drawings and purchase order documents contain equivalent requirements. A stress report has been prepared for these [f I* devices and the design criteria is considered satisfied. These devices, j I were manufactured under Westinghouse surveillance with identified hold l
) points, procedure review and personnel qualification which adequately
~
meet these related ANSI mquirements. Acceptance testing as defined in j y ANSI N14.6 was not perfomed, but an initial 100 percent load test was i conducted on these special lift devices followed by non-destructive [J \ ( testing of critical areas. In addition, the Unit 2 internals lift rig was 125 percent load tested. The new modifications of load bearing
]) [.
j items will comply with ANSI N14.6. The load cell was calibrated in tension at its capacity of 400,000 pounds. l Q
- s It is anticipated that a 100 percent load test, perfomed on each f
- 4 3 device, followed by a visual check of critical welds would be sufficient j to demonstrate compliance. This may require modification of Salem operating and maintenance procedums.
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i SECTION 4 O CONCLUSIONS The review of the ANSI N14.6 requirements and comparison with the original Westinghouse requireme,nts has shown that these items are generally in agreement for the design, fabrication and quality assurance of the lifting devices. l.owever, the lifting devices are not in strict compliance with the ANSI N14.6 requirements for acceptance testing, maintenance and verification of continuing compliance. These specific requirements that are incompatible with the lifting devices are ; dis, cussed in Appendix B with suggested actions. Westinghouse's objective was to provide a quality product and this product was designed, fabricated, assembled and inspected in accordance with internal Westinghouse requirements. In general, Westinghouse requirements meet the intent of ANSI N14.6 but not all the specific detailed requirements. I I 1 l } 4-1 6122B:1/021083 B.
- - . . _ . ~ . ..
[] V APPENDIX A CRITICAL ITEMS LIST PER ANSI N14.6-1978
- 1. GENERAL j
Section 3.1.2 of ANSI N14.6-1978 specifies that the design specification
' shall include a critical items list, which identifies critical components and defines their critical characteristics for material, fabrication, non-destructive testing and quality assurance.
" Critical items list" is further defined in ANSI N14.6, Section 2 as:
" critical items list. A list that specifies the items of a special lifting device and their essential characteristics for which specified quality requirements shall apply in the design, fabrication, utilization, and maintenance of the device."
! 4 U Load carrying members and welds of these special lifting devices are l considered to be the critical items. 1 Tables A-1, A-2, A-3, and A-4, are the critical items list of par ts and welds for the reactor vessel head lift rig, the reactor vessel k.cernals lift rig, load cell and load cell linkage, respectively. These tables include the material identification, and the applicable volumetric and surface inspections that were performed in the fabrication of these special lifting devices. In some instances, non-destructive testing was not specified since the material selection and strength result in very low' tensile stresses and thus, non-destructive testing was not justified.
The material selection for most critical load path items was made to ASTM, ASME or special material requirements. The material requirements
; were supplemented by Westinghouse imposed non-destructive testing, and/or special heat treating requirements for all of the critical items. Westinghouse required all welding, welders, and weld proccdures l
{~~) Q' 6122B:1/021083 A-1 j
$1
_l '
to be in accordance with ASME Boiler and Pressure Yessel Code Section IX for carbon steel welds. Westinghouse required certificates, or letters ;
- of compliance that the materials and processes used by the manufacturer !
were in accordance with the purchase order and drawing requirements. l Westinghouse also performed final inspections on these devices and I issuedquaiityreleases. The new modifications to the internals lift ! rig pertinent to critical items are also included. f i O .t O A-2 6122B:1/021083 . mmae. -a e
?
ll' TABLE A-1 REACTOR VESSEL HEAD LIFT RIG CRITICAL ITEMS LIST OF PARTS _ I PER ANSI N14.6-1978 i
) Item (a) Description Material Non-destructive Testing Haterial Finished 1,3,6,10, Pins ASTM A434 Ultrasonic Magnetic 15 Class BD Particle 2 Side Plate ASTM A514 Ultrasonic Magnetic or USS-Tl Particle 4,5 Sling Assembly ASTM A237 Ultrasonic Magnetic Link and Lug Class A Particle
' 7,9 Clevis ASTM A237 Ultrasonic Magnetic
; Class BD Particle i
8 Arm ASTM A306 Ultrasonic Magnetic f Grade 70 Particle km Support Lug ASTM A515 Ultrasonic , ( ) 11 1 Grade 70 Magnetic Particle 12 Ring Girder ASTM A285 Grade C i j 13 Leg ASTM A36 s i 14 Clevis Plate ASTM A515 Ultrasonic
! Grade 70 Magnetic j - Particle i
(a)See figure A-1 f i l l
; 61228:1/021083 A-3 k..
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i l s I
\j. TABLE A-2 REACTOR VESSEL HEAD LIFT RIG l CRITICAL ITEAS LIST OF WELOS f PER ANSI N14.6-1978 )
l Item (a) Weld Non-destructive Testing i Description- Root Pass Final
)
4,5 Link Lugs to Link Radiograph (full penetration) Magnetic Particle !
' 11,12 Ring Girder to Support Lug (fillet) Magnetic Particle ;
13,14 Clevis Plate to Leg Visual Magnetic (fillet) Particle t t i i (a)See figure A-1. !O i c
., j i
n ;
)
i
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I I-l- 61228:1/021083 A-4 I e
.N k_)_ HOOK PIN @
SIDE PLATE @ g p sorTouPiN @ s otAuETER uPPE
@ CLEVIS PIN O ARMh Clevis @
5"D8AMETER PIN h o h SUPPORT LUG s RING GIRDER h
//
N T d s N ~/ LEG @
' 4 CLEVISPLATE h I q s~ oiAutrER pin @
a L
.i Of N_ ,/ Figure A-1. Reactor Yessel Head lift Rig 61228:1/021483 A-5 j ,
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O b TABLE A-3 REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF PARTS PER ANSI N14.6-1978 Item (l) Description Material Non-destructive Testing Material Finished 1,3,7, 7-1/2" Dia. ASTM A434 Ultrasonic Magnetic 12 Hook Pin Class BD Particle 6" Dia. Adaptor AISI 4340 Pin 6" Dia. Removable Pin 4" Dia. Clevis, Pin 2 Load Cell ASTM A515 Ultrasonic Linkage Grade 7Q Side Plates - h (9 4,6 Adaptors AISI 4340 Ultrasonic Magnetic l \/ Particle r 5 Load Cell 17-4 pH Stain- Ultrasonic Liquid , less Steel, Particle Condition H-1100 Top Lug ASTM A515 Magnetic 8a,(2) Support Plate Grade 70 Particle l 10a ! Ultrasonic l ab,10b(2) Top u g ASTM 533 Magnetic Support Plate Grade B Particle Class 1 Ultrasonic 11a(2) Side Lug ASTM A515 Magnetic Grade 70 Particle Ultrasonic 11b(2) Side Lug ASTM A588 Ultrasonic Grade A Magnetic L Class 1 Particle I III ee S figure A-2 (2) Subscript (a) refers to Unit 1 only, while subscript (b) refers to Unit 2; no subscript means identical to both units. l b ' l 61228:1/030783 A-6 .
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~
("]! TABLE A-3 (cont) REACTOR VESSEL INTERNALS LIFT RIG LOAD CELL AND LOAD CELL LINKAGE h CRITICAL ITEMS LIST OF PARTS PER ANSI H14.6-1978 Item (l) Description Material Non-destructive Testing Material Finished 13a,15a(2) Clevis SA508 Ultrasonic Magnetic Class 2 Particle -
,13b ,15b(2) Clevis ASTM A668 Ul trasonic - Magnetic AISI 4340 Particle Class M 14a(2) Sling Leg AISI 1117 Hot Rolled AISI 1020 Cold Rolled 14b(2) Sling Leg ASTM A434 Ul trasonic Magnetic 2h)
( Class BC Particle AISI 4340 16 4" Dia. Clevis A!!M A434 Ultrasonic Bolt Class BD AtSI 4340
't:
20 Spacer ASTM A588 Grade A or B a 21,22 Leg Channel ASTM A36 Brace Plate 23 Leg Support AISI 8620 Ultrasonic Block Magnetic Particle n III ee figure A-2 . i I2}SSubscript (a) refers to Unit 1 only, while subscript (b) refers to
+ Unit 2; no subscript means identical to both units.
61228:1/030783 A-7 '
l i R. TABLE A-3 (cont) REACTOR VESSEL INTERNALS LIFT RIG [ LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITENS LIST OF PARTS PER ANSI N14.6-1978 [ Item (l) Description Material Non-destructive Testing l Material Finished 24a , Adaptor ASTM A276 26a Guide Sleeve Type 304 Condition A 25aI3) Outer Tube ASTM A312 Type 304 Seamless 27(3) ' Engaging ASTM A56'4 Ultrasonic Liquid Screw Grade 630, Penetrant Cond.1100 t] V-21b(2). Load Nut ASTM A276. Type 304 Cond. A 29b(3) Tube ASTM A276 Housing Type 304 . Cond. A 3(b(3) Guide ASTM A276 Sleeve Type 304 Cond. A III I2)See figure A-2 Subscript (a) refers to Unit 1 only, while subscript (b) refers to Unit 2; no subscript means identical to both units. (3)These items will be replaced in the forthcoming modifications. O 61228:1/030783 A-8 , t
9 in i f ( ,) TABLE A-3 (cont) REACTOR VESSEL INTERNALS LIFT RIG LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF PARTS j PER ANSI N14.6-1978 i ItemIII Description Material Non-destructive Testing Material Finished 31aI4) Load Nut ASTM A276, Ul trasonic
, Type 304 SS Condition,A 32I4) Rod Housing ASTM A276 Ultrasonic Type 304 SS Condition A 33I4) Guide Sleeve ASTM A276 Ul trasonic Liquid Type 304 SS Penetrant Condition A Y
b) .\ 34I4) Rotolock Stud ASTM A564, Type 630, 17-4 pH, H1100 Ul trasonic Liquid Penetrant 35I4), Upper and Lower ASTM A637 Ultrasonic Liquid
; 36I4) Internals Grade 688 Penetrant i Inserts Type 2 ;j Inconel X-750 N IIISee figure A-2, A-3 (4)These items are the new items to be installed.
o i l l i i 61228:1/030783 A-9
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. i WHERE PSC AND PNJ P.G101FFER.THE PSE ITEMS '
ARE DISTINGUNNED JY AN "A" SUFFIX.THE PNJ ' g ITEMS 8Y A "8'A3L'/FIX p
; , s
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SiOE PLATE @ UP*ER ADAPTOR ADAPTOR PIN h LOAD CELL
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=\. A& h TOP LUG s ( 6" DIA REMOVA8LE PIN @
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\ .\ 448 h 4"DIA CLEVIS PIN l -- SUPPORT PLATE h A&B
\ 'i s, *7x A&S h SIDE LUG .
; SUPPORT PIPE h A&B .
w T
,, A&R h UPPER CLEVIS ING LEG h A&8 f
\ ,
SPACER @ l
' UA&S h LOWER * ;
CLEVIS d 4" DI A CLEVIS @
' BOLT. -
) d END PLATE h s h yREADER b$ ' l
[ f* ; M8LY s ( b '? " '- h SACKING # l , (
-s
' BLOCK' s , '. 1 u '
[Y I, y ..,,,2ss l} ,i c 23e . PNJ = O
@B LOAD NUT , (2
@s Tune HOUSING !h i - pl k#8 2n '
l J PSE .h - 25A i
@5 GUIDE SLEEVE l
l
~
'3 g, j\ >
, j ghll',
E , N. .;' J y y w - i
;. , \ ! I i
@ sRACE PLATE
\
A&s @ LEG SUPPORT BLOCK ' ADAPTOR @ A RING GIRDER ,
' OURh TUBE s
@A
-~
. t- GulDE sleeve @ A s ..
sw , ENGAGING SCREW @ AaB s, ,
~
,Y\ '
Aj _ Figure A-2 Reactor Vessel Internals Lift Rig A-10 . 61228:1/02{483 rs . , b i
c O x r
' LOAD NUTh A 3
5' I[rLEG SUPPORT "'
*@ k l
> /Ah hs ._.
t f h RODHOUSINGh _ i .#f2 s :,_1 j' ! ![ S$SSE @ !, !,
; ;r ROTrLOcx 1 l' I "
9; ; L i. p v sTuo@ i .. .. 7,. [ d (r -d l, - l1
$ LOWER INTERNALS / I I
f ~
' LOWER k
$ ' UPPER INTERNALS r- !
/5 . b UPPER INTERNALS I
l
,- INTERNALS
,, INSERTh INSERTh
' .//; A-UPPER INTERNALS LOWER INTERNALS L
ARRANGEMENT ARRANGEMENT i 'NEWITEMS LETTER "A" SUFFIX IS FOR UNIT 1 ONLY (PSE)
~.
4 i Figure A-3. Rotolock Studs and Inserts Arrangement l l 61228:1/022583 A-11
' i.
Ow. _
l t .
*s i
l- i ; 1
/k TABLE' A'-4 i; ,
REACTOR VESSEL INTERNALS LIFT RIG 4 LOAD CELL AND LOAD CELL LINKAGE 4 CRITICAL ITEC LIST OF WELDS i l J PER ANSI N14.6-1978
,y ;
\ t Item Weld Description Non-destructiva Testing ;
'b Root Pass Final 8,10 Sling Block .s4agnetic Particle Ultrasonic ,
Top Lugs to Support Magnetic Particle / Plate (full penetration)
'I . 9.11
, Side Lugs to Magnetic Particle Radiograph
/ Support Pipe Magnetic Particle '
(full penetration) ,
'! / 20 Spacer Magnetic Particle Visual to Leg Weld Magnetic Particle O, . (Top and Bottom) .
V (full penetration) 24aIII, Torque Tube Liquid Penetrant Liquid Penetrant : 25a Adapter to Outer l
, i Tube (full pene-tration) .
f 21,22,23 2 Brace Plate and Magnetic Particle Visual , Leg Support Block , Magnetic Particle 7
]
to Leg Weld (fillet) l Ill ubscript S (a) refers only to Unit 1.
?
.I i ..
t t 61228:1/022583 A-12
, . , _ , . . . , , , . . , ,-.--_,n.,-~.,.-.,,,...n n. - ,--., ,
x = u m t APPENDIX B TABULATION OF ANSI .414.6-1978 REQUIREMENTS INCOMPATIBLE WITH THI SALEM LIFTING DEVICES
- 1. GENERAL The comparison of the various ANSI N14.6 requirements and those of these '
lifting devices has shown that these devices are not in strict compliance with all the ANSI N14.6 requirements. Listed below is a tabulation of those sections of ANSI N14.6 considered most important in demonstrating the continued load handling reifabfif ty of these special lifting devices. Associated Westinghouse remarks are also ifsted and could be used as suggested actions and/or responses to demonstrate compliance to f the NRC. i i la. Requirement: f Para. 3.1.4 - requires the designer to indicate f permissible repair procedures and acceptance criteria for
~ - the repair.
lb. Remarks:
!' Any repair to these special lifting devices is considered ;[.
to be in the form of welding. Should pins, bolts or other
' fasteners need repair, they should be replaced, in lieu of
- repair, in accordance with the, original or equivalent requirements for material and non-destructive testing.
[ Weld repairs should be performed in accordance with the requirements icentified in NF-4000 and NF-5000 I (Fabrication and Examination) of the ASME Boiler and Pressure Vessel Code, Section III, Division 1 Subsection NF. 2a. Requirement: Para. 3.2.1.1 - requires the design, when using materials with yield strengths above 80 percent of their ultimate l I
- 61228
- 1/021483 B-1 W
g , a g;
a
- t. . .. 3 I
strengths, to be based on the material's fracture i toughness and not the listed design factors. f 2b. Remarks: ' High strength materials are used in these devices. j l Although the fracture toughness was not determined, the material was selected based on it's excellent fracture l toughness characteristics. However, in lieu of a { different. stress design factor, the stress design factors listed in 3.2.1 of 3 and 5 were used in tne analysis and l the resulting stresses are considered acceptable. 3a. Requirement: , Para. 3.2.6 requires material for load-bearing members to l be subjected to drop-weight or Charpy impact tests. i 3b. Remarks: f. Fracture toughness requirements were not identified for the material used in these special lifting devices except j l l for the u'pper and lower clevises of the internals lift rig. The applicable specification for these items is an l ASME specification which requires Charpy tests. However, . all material selection.was based on its excellent fracture toughness characteristics. 4a. Requirement. Para. 3.3.6 requires an indication that an actuating [ mechanism is engaged. , i 4b. Remarks:
~
The original reactor-vessel internals lift rig design employs a long handled toof to engage the rig and the [
. internals. The tool depresses a spring loaded tube and turns the engaging screw into the internals. No specific j position indication is identified, except for scribe marks on the tool, and the visual difference in the top of the B-2 i 61228:1/021483
-. 7 a %
e- > 4 - ~ - , , - - - , r
- v. e = .
- spring loaded tube is considered sufficient indication
; that the internals am engaged. However, the new modifications, presently in progress, include an integral tool with indication of engagement.
Sa. Requirement: Para. 4.1.6 requires a fomal quality assurance program for the manufacturer and para. 4.1.7 requires . certification and identification of materials. Sb. Remarks: A fomal quality assurance program for the manufacturer was not required for all items. However, the
, manufacturers welding procedures and non-destructive testing procedures were reviewed by Westinghouse prior to j use. All of the critical load carrying members require letters of comp!iance for material requirements.
Westinghouse perfomed certain checks and inspections g g ( -c during various steps of manufacturing. Final Westinghouse review includes visual, dimensional, procedural, I cleanliness, personnel qualification, etc. and issuance of
$ a quality release to ensure confomance with drawing $ requimments.
2 3 f 6a. Requirement: Para. 5.1 lists Owner Responsibilities and 5.1.2 requires h the owner to verify that the special lifting devices meet f3 the perfomance criteria of the desigr, specification by records and witness of ~ testing. \ 6b. Remarks:
,4 Them wasn't any design specification for these rigs.
I Load testing was perfomed on these lifting devices after
' field assembly. These were 100 percent load tested and non-destructive testing was conducted on critical welds i following the test. In addition, the new Unit 2 internals l l l 6'.22B :1/022583 B-3 I
b l 9 1
r . 3 1 x . I lift rig was load tested at assembly to 125 percent of the design weight. However, the Westinghouse Quality Release may be considered an acceptable alternate to verify that the criteria for letters of compliance for materials and specifications required by the Westinghouse drawings and purchasing document were satisfied. 7a. Requirement: Para. 5.1.3 requires periodic functional testing and a system to indicate continued reliable performance. 7b. Remarks: Maintenance and inspection procedures should include a visual check of critical welds and parts during lifting to comply with this requirement for functional testing. i 8a. Requirement: Para. 5.1.5, 5.1.5.1 and 5.1.5.2 require special identification and marking to prevent misuse. 8b. Remarks: It is obvious, from their designs, that these rigs are specific lifting devices and can only be used for their intended purpose and parts are not interchangeable. Specific identification of the rig can be made by marking with stencils, the rig name and rated capacity, preferably on the spreader assembly. l
- 93. Requirement:
Para. 5.1.6, 5.1.7 and 5.1.8 require the owner to provide written documentation on the maintenance, repair, testing and use of.these rigs. I 9b. Remarks: Operating instructions and maintenance instructions should [ be reviewed to assure that they contain the requirements [~' l V} ) I 61228:1/021483 8-4 ,
- v--- r ,, s - --v-, - -- w -- - --
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l I to address maintenance logs, repair and testing history, 1 danage incidents and other items mentioned in these paragraphs. ;
.' 10a. Requirement:
Para 5.2.1 requires the rigs to be initially tested at 150 percent maximum load followed by non-destructive testing of critical load bearing parts and welds. 10b. Remarks The head lift rig and internals lift rig were all load tested at assembly to 100 percent of the load followed by N; non-destructive testing of critical welds. In addition, 5 the new Unit 2 internals Ifft rig was 125 percent load 3 tested at assembly.
$l l $ 11a. Requirement:
Para 5.2.2 requires replacement parts to be individually qualified and tested. H l J . l ^i lib. Remarks Replacement parts, should they be required, should be made of identical (or equivalent) material and d fj inspections as originally required. Only pins, bolt and > Q nuts are considered replacement parts for the reactor vessel head and internal lift rigs. Q S . f4
!] 12a. Requirement:
Para 5.3 requires testing to verify continuing compliance and annual 150 percent load tests or annual non-destructive tests and examinations to be performed. t 12b. Remarks These special'11fting devices are used during plant refueling which is approximately once per year. During plant operation these special lifting devices are l 4 6122B:1/021483 B-5 3 l 9 , -- . .
ff
. .t =
l
\ f inaccessable since they are permanently installed and/or remain in the containment. They cannot be removed from the containment unless they are disassembled and no known
~
purposes exist for disassembly. Lead testing to 150 j 4 percent of the total weight before each use would require ! I special fixtures and is impractical to perform. It is suggested that a check (visual) of critical welds and i parts be conducted at initial lift prior to moving to f full lift and movement for these devices. Preferably, a visual check during initial lift should be acceptable. f Further note that with the use of the load cell for the head and internals lift rigs, all lifting and lowering is } monitored at all times. ;
- 2. SIMMARY .
The requirements for periodic checking and functional load testing appear f to be the ANSI N14.6 requirements that are most difficult to demonstrate (^ compliance. It is almost impractical to perform the 150 percent load ( l test prior to each use. It is suggested that the proposal to the NRC include a 100 percent load test to be performed with a minimum of [ non-de'structive testing, (visual-only) in the critical parts and welds. t i t i l 1 i i fy ! V- !
.6122B:1/021483 B-6 ,
i s . - , - , - . - . . . , _ - , .
--.-,,,-.,'-,,,,,r , , , . - . . , , . , , , . -
.- .--. -. . . ~
T . _ . . ._ l WESTINGHOUSE CLASS 3
- h. ' ATTACHMENT B to
( 5 b % WCAP-10167 t t
- Although information contained in this report ;
is nonproprietary, no ai stribution shall be made outside Westinghouse or its Ifcensees without the customer's approval . i 7 i STRESS REPORT I REACTOR VESSEL HEAD LIFT RIG,
. REACTOR YESSEL INTERNALS LIFT RIG, l
d . LOAD CELL AND LOAD CELL LINKAGE
~ ! . FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM GENERATING STATION t UNITS 1 AND 2 ,
[ , t I (g. ,, February 1983 ._.
; i 5 -N' L. J. klandra, P.E. i r i
\,
l l , s, i ( 'N
. Appro d: O 3/fA
! . R. Marball , P. E., Anager ; Refueling Equipment Engineering i l 61268:1/030283
** m. a. - 9 l
h
I I
. ABSTRACT h' I A stress analysis of the Salem reactor vessel head and internal lift k rigs, load cell and load cell linkage was perfomed to determin; the acceptability of these devices to meet the design requirements of ANSI ,
f N14.6.~ ,
> i P l 4 .\
S, -
?-
f I I E 4 E -
't 5-E e
L 3 t g r b i a 3; l I
. iii 4 6126B:1/021083 .
i~ l .l t ACKNOWLEDGMENT I j Acknowledgment is hereby made to the following individuals who contrib- t uted to the structural analysis presented in this report. l t - t J. W. Richard, P.E. l J. S. Urban 4 F. Peduzzi i l i i t [ r r t i
)
.. i i
I I fv i 61268:1/022883 . [
?
- I t
?
6 I TABLE OF CONTENTS Section Titie Page ABSTRACT 111 INTRODUCTION 1 -1 1 1.1 Background 1 -1 COMP 0NENT DESCRIPTION 2-1 2
, 2.1 Reactor Vessel Head Lift Rig 2-1 2.2 Reactor Vessel Internal s Lift Rig 2-1 2.3 Load Cell and Load Cell Linkage 2-2 3 DESIGN BASIS 3-1 3.1 Design Criteria 3-1 3.2 Design Weights 3-2 jI 4 MATERIALS 4-1 4.1 Material Description 4-1.
5 5-1 SINMARY OF RESULTS_ Di scu ssion of Resul ts 5-1 i 5.1 5.2 Conclu sion 5-4 i APPENDIX A DETAILED STRESS ANALYSIS - REACTOR VESSEL HEAD LIFT RIG A-1 APPENDIX B DETAILED STRESS ANALYSIS - REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LINKAGE B-1 I I v j 6126B:1/030283 I l J
y r; . s x 8
?l!Ill LIST OF ILLUSTRATIONS h !
Figure Titl e Page [ 5-1 Reactor Vessel Head Lift Rig 5-12 l 5-2 Reactor Vessel Internal s Lift
.j ,
' Rig, Load Cell and Linkage 5-35 n ,
5-3 Rotolock Studs and Inserts Arrangement 5-36 i ! t i
.?
E t
- I I i t lI } l i
E i ; b ! 5
, i .I'.
i
? !
L - 1 ' I 2 k i 1 E i I l I i vii l 61268:1/030283 , l
T. o . s. -. A > LIST OF TABLES Table Titl e Page 4-1 Reactor Vessel Head Lift Rig Material and sterial Properties 4-2 l 4-2 Reactor Yessel Interral s Lift Rig, Load Cell and Load Cell Linkage Material and %terial Properties 4-3 5-1 Sumary of Resul ts - Reactor Vessel Head Lift Rig L-5-2 Sucrnary of Resul ts - Reactor Vessel Internal s Lift Rig, Load Cell and I Load Cell Linkage 5-13 . l I 1 } i l l fx 5 61268:1/030283 7 E
ar. -
- a 1
REFERENCES
?. t. i Vj 1.. George, H., Control of Heavy Loads at Nuclear' Power Plants 3 Resolution of Gs.gric Technical Activity A-36, NUREG 0612. July, 4
y 1980. i,
- 2. ANSI N14.6-1978, "Special Lifting Devices for Shipping Containers Weighing.10,000 Pounds (4500kg) or More for Nuclear Material,"
- Anerican National Standards Institute, New York,1978.
- 3. ANSI B-30.9-1971, " Slings," Anerican National Standards Institute, New York,1971.
J.
- 4. Westinghouse Drawing 113E775 - 3 Loop Head Lifting Rig General N Assembly G -
dj
- 5. Westinghouse Drawing 1099E84 - General Assembly - Lifting Rig Internals j g ts, id 6. Lin, C. W., " Approximate Evaluation of Dynamic Load Factors for in 3d Certain Types of Load Factors for Certain Types of Loading," ASME
- o
- aii Paper 70-WA/NE-2.
6 L kj, 7. Biggs, J. M., Introduction to Structural Dynamics, McGraw-Hill, New M York,1964.
.M
- 8. Gwinn, Jr. , J. T., "Stop Over-Designing for Impact Loads," Machine l
{ff. Design, 33, pp.105-113 (1961). ('
- 9. Timoshenko, S., Strength of Materials, Part 1, Elementary Theory and j S Problems, D. Van Nostrand Company, Inc. Third Edition April 1985, t e pp. 263-279.
, 14
-3 ,
_a a e b O f oJi xj [ 9: y 61268:1/022883 t f( .
,l t - -
b T - _ ... w_ 15 m ! l O 10.- ASME Boiler and Pressure Yessel Code, Section III, Division 1 i
" Nuclear Power Plant Components," American Society of Hechanical
~
Engineers, New York,1980. f 7
- 11. Manual of Steel Construction, Seventh Edition, American Institute of l
Steel Construction, New York,1973. l O ( Xii
- 6126B:1/022883 f
e r._ .__ .. o .. i I SECTION 1 i.j INTRODUCTION i The Nuclear Regulatory Comission (NRC) issued NUREG 0612 " Control of I Heavy Load at Nuclear Power Plants" in 1980 to address the control of heavy loads to prevent and mitigate the consequences of postulated accidental load drops. NUREG 0612 imposes various training, design, inspection and procedural requirements for assuring safe and reliable operation for the handling of heavy loads. In the containment building, NUREG 0612 requires special lifting devices to meet the requirements of ANSI N14.6-1978 "American National Standard for Special Lifting Devices
$ for Shippin Containers Weighing 10,000 Pounds or More fo- Nuclear 9 Materials". In general, ANSI N14.6 contains detailed requirements for the design, fabrication, testing, maintenance and quality assurance st of special lifting devices. In addition, ANSI N14.6 requires that when
$ wire rope or chain is used in the design of a lifting device, the wire
$ rope or chain shall be in conformance with ANSI B30.9-1971 "American National Standard Safety Standard for Slings".E 3 The NRC has l
y requested operating plants to demonstrate compliance with these
.i requirements.
9 p This report contains the stress analysis performed on the Salem reactor f vessel head lift rig, reactor vessel internals lift rig, load cell and
-$ load cell linkage to determine the acceptability of these devices to meet k these requirements.
(I.
1.1 BACKGROUND
i J The reactor vessel head lift rig, the reactor vessel internals lift rig, p, load cell, and load cell linkage were originally designed and built for j the Salem Generating Station circa 1967-1971. Subsequently, the Unit 2 internals lift rig was transferred to another plant site in 1975-76 and
' ~
h. replaced in 1977 with an almost identical design. The actual design 6 criteria is unknown for the lifting devices. It appears that Westinghouse used the design criteria that the resulting stress in the load carrying members, when subjected to the total combined lifting 6126B:1/021083 l-l a ~
- x. _ _. . =
l k)- E weight, should not exceed one fifth (1/5) of the ultimate strength of the material. These items were not classified as nuclear safety components and requirements for formal documentation of design requirements and stress reports were not applicable. Thus, stress reports and design specifications were not formally documented. Westinghouse defined the design, fabrication and quality assurance requirements on detailed manufacturing drawings and purchase order documents. Westinghouse also issued field assembly instructions for the reactor vessel head and internals lift rigs which included an initial load test followed by non-destructive surface examination of critical load bearing areas. Additionally, the new Unit 2 intenals lift rig was load tested at the manufacturers shop at 125 percent of the maximum weight. Subsequent ; modification (presently in progress) to the internals lifting rig include rotolock studs and inserts designed, manufactured and tested to the requirement of ANSI NT4.6. t f I' C rs ! L l > I 6126B:1/021083 1-2 l.
F . x .x x
- l jtf i 2.1 REACTOR VESSEL HEAD LIFT RIG SECTION 2 COMPONENT DESCRIPTION 3
The reactor vessel head lift rig E43 is a three-legged carbon steel
$ structure, approximately 43 feet high and 14 feet in diameter, weighing k approximately 28,000 pounds. It is used to handle the assembled reactor y vessel head.
f M The three vertical legs and control rod drive mechanism (CRDM)' platform : k assembly are permanently attached to the reactor vessel head lifting lugs. The tripod sling assembly is attached to the three vertical legs
~
and is'used when installing and removing the reactor vessel head. During plant operations, the sling assembly is renioved and the three
~
vertical legs and platfcrm assembly remain attached to the reacter vessel head. t 2.2 REACTOR VESSEL INTERNALS LIFT RIG The reactor vessel internals lift rig [5] is a three-legged carbon and stainless steel structure, approximately 25 feet high and 14 feet in diameter weighing approximately 14,500 pounds. It is used to handle the upper and lower reactor vessel internals packages. It is attached to I the main crane hook for all lifting, lowering and traversing opera-tions. A load cell linkage is connected between the main crane hook and the rig to monitor loads during all operations. When not in use, the rig is stored on the upper internals storage stand. l l
!l The original rig design attaches to the internals packages by means of
[ three engaging screws which are screwed into tapped holes in the , internals flanges. These screws are manually opefated from the g manipulator crane walkway using a handling tool which is essentially a { long wrench. The screws are normally spring retracted upward and are i+ depressed to erlage the tapped holes by the weight of the handling tool. Modifications to these rigs, presently in progress, include . 6126B:1/021083 2-1
~~ -
f
-w- - ~ . . . . . _ . _
l CAi ~ installation of an operat1ng platform, integral tools and a change to j the type of engagement with the internals to a rotolock stud and insert type. These rotolock studs are manually operated from the new internals l lift rig platfom using a handling tool which is an integral part of the l
, ri g. The studs are nomally spring retracted upward and are depressed l to engage the inserts. Rotating the mechanism locks it in both
! positions. Since these rotolock studs are in the process of being I
incomorated, both types of load carrying items are included in this ; i report. . 2.3 LOAD CELL AND LOAD CELL LINKAGE The load cell is used to monitor the load during lifting and lowering l
~' I the reactor vessel head or internals to ensure no excessive loadings are occurring. It is installed between the load cell linkage and the lifting device. The load cell is a strain gage (tension) type, Eated at i 400,000 pounds, built by W. C. Dillon and Co. The load cell linkage is
) an assembly of pins, plates and bolts which connect the polar crane main i hook to the load cell.
~
i
~
i l ! 6
,. 1 i
(.e l l ! 61268:1/022883 2-2 .
,G, .- . - , == ut --
k SECTION 3 d b u
'N DESIGN BASIS M i s S 3.1 DESIGN CRITERIL I M >
f- Y3 N!.' REG 0612, paragraph S.1.1(4) states that special lifting devices If; should satisfy the guidelines of ANSI N14.6. Further, NUREG 0612, 3 5.1.1(4) states: "In addition, the stress design factor stated in
.4 Section 3.2.1.1 of ANSI N14.6 should be based on the combined maximum
.w ,
.;: static and dynamic loads that could be imparted on the handling device
;f based on charecteristics of the crane which will be used. This is in
.Q lieu of the guideline in Section 3.2.1.1 of ANSI N14.6 which bases the h stress design' factor on only the weight (static load) of the load and of
$ the intervening components of the special handling device".
h It can be inferred from this paragraph that the stress design factors specified in Section 3.2.1.1 of ANSI N14.6 (3 and 5) are not all.inclu-, l l ;- sive. Also, it can be inferred that the specified ANSI N14.6 stress ; i design factors should be increased by an amount based on the crane dy-pg namic characteristics. The dynamic characteristics of the crane would be based on the main hook and associated wire ropes holding the hook. f (d Mo'st main containment' cranes use sixteen (16) or more wire ropes to _p S handle the load. Should the crane hook suddenly stop during the lifting >
.E or lowering of a load, a shock load could be transmitted to the con- :
nected sievice. Because of the elasticity of the sixteen or more wire i f ropos, tre dynamic factor for a typical containment crane is'not much larger thao 1.0. The maximum design factor that is recomended by most h design ' texts [6,7,8] is a factor of 2 for loads that are suddenly M
~
l applied. The stress design factors required in Section 3.2.1.1 of ANSI k$ N14.6 are: 1 y h 3 (weight) < Yield Strength' L 5 (weight) < Ultimate Strength l ffj The factor of 3 specified, certainly, includes consideration of suddenly l 4% applied loads for cases where the dynamic impact factor may be as high l l 5h 7 61268:1/022883 3-1 lk - l
- s. ~
- x. - . .a ..
l l O ),as 2.0. Thus, we feel that the use of the design criteria in ANSI N14.6
\
satisf(es the NUREG requirement. 1 ET o provide flexibility on stress design factor, the sumary table list Thus, any stress the stresses with stress design factors of 1, 3 and 5. design factor ma'y be easily applied to satisy any concerns.
. I i
l
' 3.2 DESIGN WEIGHTS J The following design weights were used in the analysis of the lifting l' l devices:
l l 3.2.1 Reactor Yessel Head lift Rig The design weight is 345,000 pounds which is the total' weight of the I reac. tor vessel head, its attachment and the lift rig. j 3.2.2 Reactor Vessel Internals Lift Rig, load Cell, and Load Cell
~
Linkage (a) The design weight for the internals lift rig is 285,000 pounds which is the total weight of the lifting device and the lower internals.
*l (b) The design weight is 285,000 pounds for the load cell and load cell linkage.
I i r ( i 3-2 j 61268:1/022883 b
= -
. . . ._ o . ._
. i SECTION 4
., h MATERIALS
'.i*
.4 4.1 MATERIAL DESCRIPTION '
.i -
;'.g The materials and material properties for the reactor vessel head lift 2 rig, the reactor vessel internals lift rig, load cell and load cell qi linkage are listed in Tables 4-1 and 4-2. -
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TABLE 4-1 Q REACTOR COOLANT HEAD LIFT RIG MATERIAL AND MATERIAL PROPERTIES S I Yield Ultimate I Strength Strength i Item (a) Description Materials Sy (ksi) Sult (Ksi) i ASTM A434 100 130 1 71/2" Diameter Pin 140 15 3.9" Dia. Bottom Clevis Pin Class BD 110 , 105 135 : 6,10 5" Dia. Clevis Pins l 8" Dia. Pin 100 130 f-, 3 5: ASTM A515 or 38 70 -W: 11 Support Lug Gr. 70 l jy
. -N 90 100 2 Side Plate ASTM A514 or USS-T1
. _p 50 80 k I)
'V 4,5 Sling Assembly Link, Lug ASTM A237 Class A !.ki M41 13 Leg ASTM A36 38 70 ld
- Q 12 Ring Girder AS1M A285 30 55 .(fr
' ti GR. C D$:
AS1M A237 50 80 by v 7,9 Upper Clevis Clevis C1. A .@
\r' Am ASTM A306 35 70 a
.b .
-t 8 Gr. 70 1.x ASTM A515 38 70 !.4g Clevis Plate I
14 Gr. 70 Gd .G i i l
-k; iM la)See figure 5-1 i
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6 61268:1/022883 ;;g
,i TABLE 4-2 3 REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND h j LOAD CELL LINKAGE MATERIAL AND MATERIAL PROPERTIES ,
e n [ Yiel d U1 tima te h Strength Strength [ Item III De scription Material S S y (ksi) ul t (k si) 1,3,7, 71/2" Dia. Hook Pin, ASTM A434 120 135 12 6" Dia. Adaptor Pin, AISI 4340
, 6" Dia. Removable Pin Class BD
-{ 4" Dia. Clevis Pin
;f. 2 Side Plate ASTM A515 38 70 Grade 70 ;
I
~
4,6 Load Cell AISI 4340 1 20 135 Adaptors 5 Load Cell 17-4 pH s/s 115 140 Cond. H1100
- i 8a(2) Top Lug, ASIN A515 38 70 Support Plate Grade 70 10a((2) 11a 2) Sidt Lug 8b(2) To', Lug ASTM 533 50 80
[ 10b(2) St.oport Plate Grade B Cla ss 1 9 9;pport Pipe ASTM A106 30 1 48 l i 11b(2) Side Lug ASTM A588
- 50 '
. 70 L Grade A '
l dass 1 - i y Upper Clevis, ASE SA 508 50 80 g 13a((2) 15a 2) Lower Clevis Class 2 i 1R!!! 1 2 8:d! MM " '5 l Class M k i i it (1) See figures 5-2 and 5-3 l (2) Subscript (a) refers to Unit 1 only, while subscript (b) refers to Unit 2; i no subscript means identical to both units i e l 6126B:1/030283 4-3
c p , -
-"- nos . ~ . - .- . -
l I TABLE 4-2 (cont) REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE MATERIAL AND MATERIAL PROPERTIES Yield Ultimate Strength Strength Item Il Description Material S y (ksi) S ult (ksi) 27(3) Engaging Screw ASTM A564 115 ' 140 Grade 630 Cond.1100 Load ' Nut ASTM A276 30 75 28b(2) Type 304
,} Cond. A
- 29b (2,3) Tube Housing ASTM .5276 30 75 i Type 304 j Cond. A 30b(2,3) Guide Sleeve ASTM A276 30 75 l l Type 304 Cond. A
.y l .h .
31a(2,4l Load Nut ASTM A276 30 75
? Type 304 SS j Condition A d 32(4) Rod Housing ASTM A276 Type 304 SS 30 75 Cond. A
_]l~{9 33(4) Guide Sleeve ASTM A276 30 75 D Type 304 SS
? *-
Cond. A
~f 34(4) Rotolock Stud ASTM A564, 115 140
- Type 630, 17-4 Ph, H1100
}s Upper and Lower ASTM A637 115 140 35((4) ,
'. 36 4) Internals Grade 688
/ Inserts Type 2 s Inconel X-750 ,
1 y. (1) See figure 5-2 and 5-3. j l (2) Subscript (a) refers to Unit 1 only, while subscript (b) refers to Unit 2; i
.. no subscript means identical to both units.
9 (3) These items will be replaced in the forthcoming modifications. Tc (4) These items are the new items to be installed.
- si '
61268:1/022883 4-5 N _ _ .
SECTION 5 SINMARY OF RESULTS Tables 5-1 and 5-2, suranarize the stresses on each of the parts which make up the reactor vessel head and internals lift rig, load cell, and load cell linkage respectively. All of the tensile and shear stresses meet the design criteria of section 3.2.1.1 of ANSI N14.6, requiring application of stress design factors of three and five with~ the accompanying allowable stress limits of yield and ultimate strength, respectively. Application of the ANSI N14.6 criteria to structural members subject to compression, bearing, or combined loads result in some stresses exceeding this criteria. However, when using more appropriate criteria, the resulting stresses are considered acceptable.
.f. 5.1 91SCUSSION OF RESULTS 1
N 5.1.1 Application of ANSI N14.6 Criteria . y The design criteria of section 3.2.1.1 of ANSI N14.6, requiring application of I I stress design factors of three and five with the accompanying allowable 3 stresses, are to be used for evaluating load bearing members of a special lifting device when subjected to loading conditions resulting in shear or
" - tensile stmsses. Application of these design load factors to other. loading
- conditions is not addressed in ANSI N14.6. However, these two stress design N factors have been used to detemine the stresses of the load carrying members j when subject to other loading conditions, viz. bearing, bending, buckling.
[f This is an extremely conservative approach and in some cases the resulting j stresses exceed the accompanying allowable stress limit.
~,
Structural elements loaded in compression are analyzed by the empirical
; equations of the ASME and/or AISC rules. Allowable stresses for compression members are base.d on the estimate that the upper limit of elastic buckling failure is defined by an average column stress equ,al to one-half of the yield stmss. These equations do not detemine the limiting stresses of members in buckling but indicate'whether or not the calculated stress is or is not within the allowable values. Instead, the ultimate load carrying capability of the member is the detemining factor in the structural member's acceptability.
l
.j, 61268:1/022883 5-1 j
M 1.w
v (m) TimoshenkoE93 n otes that the ultimate, load for short struts is equal to the materials yfeld point. Calculation a(the ultimate load results in this load being larger than the nominal design load and thus, these members are considered acceptable. s N_ 5.1.l2 BeinringStresses
~
f For 'he internals lifting rig, several of the parts do not meet this criteria. s However, since they are localized stresses, they can, if necessary, be considertd under sectIon 3.2.1.2, which states that the stress design factors of 3.2.1.1 are not intended to apply to situations where high local stresses are relieved by slight yielding. None of the bearing stresses reach the yield stress, and in . fact, alldof the bearing stresses meet the design criter la of the AISC Ull code of 0.9 yield. 5.1. 3 Combined Stresses The combined tensile stress from bending and tension, in the lower sling rod h) clevis (item 15), of the internals lift- rig exceed the section 3.2.1.1 criteria. Bending is not a unifom stress, but is'at a maximum at the l outemost fiber. Bending contributes to the major portion of the stress shown in the table, and, as a result, the tensile stress without the bending is extremely low and well within the section 3.2.1.1 criteria. The combined stresses also meet the AISC code criteria. 5.1.4 Fillet Weld Stresses The fillet weld stress at the les support block to leg weld on the internals lift rig meets the ASME criteria for weld stresses based on base material proparties. However, when applying the ANSI N14.6 SW criteria to the nominal i stress value, the ASME allowable stress value is exceeded. However, the ANSI N14.6 criteria is satisfied for this weld and thus it is considered acceptable. O 61268:1/030783 5-2 -
//
-9
- 2'
kk 5.1.s Structures Loaded in Compression $ The streader assembly of the reac. tor vessel internals lift rig, wnen analyzed $ for axial compression loadings, does not meet the allowable stresses of the However, it does meet the 3W and SW criteria of the ANSI N14.6 FY AISC code. It is well known that care should be taken when addressing members ' ).} c ri teri a. 5 in compression to ensure elastic stability. Thus, structures loaded in compression are analyzed by the empirical equations of the D0] AS14E Boiler-OI3 Part 5 ,; and Pressure Yessel Code Section III, Appendix XVII or the AISC
,; rule s.
Il.
;; If we were designing a new structure, the material and member size would be N changed to ensure these allowable stresses would De satisfied for all loading conditions. However, these calculations are being applied to an existing
'h structure and since these conditions am not satisfied then the ultimate load kj carrying capability must be detemined. a The column under consideration is relatively short (k = 33.7). L Timoshenko states that experiments show that sho columns buckle ist when the compressive strength reaches the material yield point. (The 94 $$ horizontal line on the figure below). M M $g y YlELD POINT I6W l EULER CURVE I E = 30 X 106 ps h,u I iS 12 1
% E l % t; 1 2 _,
n li 5 I 1 l 2 33.7 4 l
\?]
2/r ~80
.i.
s j; 61268:1/022883 5-3 9
--r. -;_ . _ _ . ._._ . .- . _
s i O Therefore the total stress j P ; I. t l must be less than or equal to the material yield stress. ! For the case of the internals lift rig spreader;
= 6530 psi QToul =
which is less than the material yield strength (Sy ) ': i
= 36,000 psi Then to find the ultimate' column load, let omax " Sy
~
3 Then the maximum column load is the ratio of 36,000
= 5. 5 -
, max /, total 6,530 Thus the ultimate coltan load is 5.5 times the nominal value.
The internals lift rig spreader members are considered acceptable for this condition of axial compression. S - 1
5.2 CONCLUSION
Application of the ANSI N14.6 criteria of (3 and 5) to these special - lifting devices results in acceptable stress limits for tensile and shear stresses. Application of this criteria to all structural members - subject to other types of loadings tend to result in oversimplified convervatism and with some stresses exceeding the accompanying allowable limits.- However, when using the more appropriate criteria for those cases not addressed by the ANSI N14.6 criteria the stresses are within the appropriate allowable limits. Further, these calculations are b'efng
~
applied to an existing structure and if we were designing a new structure, the materials and member sizes would be changed to ensure _ i.
?
61268:1/030283 5-4 .
.x u .
- v. , . . - _ _ _ .- . _
l P' these limits would be satisifed for all loading conditions. In conclusion, these special lift devices adequately meet the ANSI N14.6 criteria for tensile and shear stresses and meet other appropriate [ e criteria for loading conditions that result in combined, bearing, and buckling stresses. l J
=
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.' 61268:1/030283 j -
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*' TABLE S-1 M
SUMMARY
OF RESULTS ; 4 ..
" REACTOR VESSEL HEAD LIFT RIG
'o IM 4.
i 8' * .t w Calculated Stresses (ksi) Material Allowable , 4 value (ksi) ; ] Item (a) Part Name ICI
' Designation W II 3W SW S y
S ult And Material I No. I. 1- i 39.9 66.5 100 130 13.3 f., I' 7'1/2" Dia. Hook Pin Bending 3.9 11.7 19.5 ASTP1 A434 Shear i . Bearing on Pin S.8 17.4 29.0 i 1 Class-BD 38.5 Bearing on Side Plate 7.7 23.1 !I* 6 i 6.9 20.7 34.5 90 100 2 Side Plate Tension 9 8" Dia. -Hole ! Shear # 8" Dia. Hole -6.9 ,20.7 34.5 ! ASTM AS14 i or USS Tl Bearing 9 7 1/2" Dia. Hole 7.7 23.1 38.5
' (a) See figure 5-1 for location of item nunbers and section l- (b) W is the total static weight of the component and the lifting device ,
(c) S yis the yield strength of the material usi) l-(d) Sg is the ul?imite strength of the material (ksi)
~
l
., ;,a. . , . - . . - . - . - . . - . - . . . . ~ . . . . ., a n . - -.. . . .-._-._.- . - . _ .. . . . - . . . . .
c
ls$N$li)&$)$? ME5NIW MkiU6 W'S*" e?' Y W^N W M R 21
- g f ac LL 5- t (cce t )
y StM.AxY Of RESUL T5 REACTOR VESSEL HEAD LIFT R16 8 9: ( 8 Calculated Stresses (ksi) Haterial Allowable Item (a) Part Name Value (ksi) l No. And Material Designation W(b) 3W SW Sj (c) S ult 3 8" Dia. Bottom Pin Bending 10.9 32.7 54.5 100 130 I, ASTM A434 Snear 3.4 10.2 i 17.0 Class BD Bearing on Lug 5.4 ' 16.2 27.0 i Bearing on Side Plate 7.2 21.6 36.0 { , 4 Sling Assembly Tension 0 Hole 5.0 15.0 25.0 50 80 Link Shear 0 Hole 5.0 15.0 25.0 ASTM A237 Bearing 0 Hole 5.4 16.2 27.0 Class A Tension 9 Shank 6.6 19.8 33.0 1 (a) See figure 5-1 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi) (d) S ult is the ultimate strength of the material (ksi) i
7 L- '
-. 1 7
T< \ .x,J. Q' ;.
.] TABLE S-1.(cont) -
S
SUMMARY
OF RESULTS ! REACTOR VESSEL HEAD LIFT RIG l
..{
N w < i Calculated Stresses (ksi) Material Allowable i Item (a) Part Name Value (ksi) No. And Material , Designation W(b) 3W SW Sy (c) S ult 5 Link Lug Tension 9 Hole .4.0 12.0 20.0 50 80 ASTM 237 Shear Tearout 9 Hole 4.0 12'.0 20.0 Class A Bearing 9 Hole- 6.3 18.9 31.5 { Maximum Tension 9 Hoot of Lug' Vertical Shear 9 Root of Lug-3.7 1.4 11.1
.4.2 18.5 7.0 6 5" Dia. Bending .10.5 31.5 52.5 105 135 Clevis Pin Shear 3.2 9.6 16.0 ASTM A434 Bearing on Clevis 5.3 .15.9 26.5 Class BD Bearing on Lug 6.3 18.9 31.5
* (a) See figure 5-1 for location of item numbers and section (b) W is the total static weight of the component and the lif ting device (c) S, is the yield strength of the material (ksi)
(d) Stil t is the ultimate strength of the niaterial (ksi) W h k*V 'L_
^
.__HW _. f;,,3
. . Age 64 dghtGWeshi ^ ' B" % .h / 1 - -;
Y g TABLE 5-1 (cont) M
=
SUMMARY
OF RESULTS REACTOR VESSEL' HEAD LIFT RIG Dm 8 Calculated Stresses (ksi) Haterial Allowable ItemI ") Part Name Value (ksi) , No. And Material Designation W(b) 3W SW Sy (c) S ult t 7 Upper Clevis Tension 0 Hole 3.2 9.6 16.0 50 80 t ASTM A237 Shear 0 Hole 3.2 9.6 16.0 # Class A Bearing 0 Hole 5.3 15.9 26.5 ui Thread Shear 2.3 6.9 11.5 E , 8 Arm Thread Tension 7.1 21.3 35.5 35 70 ASTM A306 Thread Shear 2.3 6.9 .11.5 Gr. 70 # 9 Bottom Clevis Stresses are the same as Same as' Same as 5ame as 50 80 ASTM A237 It'em 7. Item 7 Item 7 Item 7 Class A , (a) See figur.e 5-1 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) 5, is the yield strength of the material (ksi) (d) Sg is the ultimate strength of the material (ksi)
- y. ... -
[' -( 4 TABLE' 5-1 (cont) - S St99tARY OF RESULTS
'h REACTOR VESSEL HEAD LIFT RIG k .
b Calculated Stresses (ksi) Material Allowable .b Item (a) .Part Name Value (ksi) i No. And Material Designation. W(b) g 3W SW S,(c) ult 9 : 4 10 5" Dia. Stresses are the same as Same as Same as Same as 105 135 i I Bottom Clevis Pin Item 6 Item 6 Item 6 Item 6 ASTM A434 a { Class BD L i y'- 11 Support Lug Tension 9 Hole , 4.0 12.0 20.0 38 70 o . ASTM ASIS Shear 9 Hole 4.0 12.0 20.0 f 3 Gr. 70 Bearing 9 Hole 6.5 19.5 32.5
- 12 Ring Girder Total-Shear 3.2 9.6 16.0 30 55 a ASTM A285 Maximum Bending 2.6 7.8 13.0 Gr. C Maximum Tensile Stress 4.8 14.4 24.0 Ring Girder to Support Weld 3.2 9.6 16.0 18I 'I l
) 3 (a) See figure 5-1 for location of item numbers and section (b) W is the total static weight of the component and the lifting device . (c) S yis the yield strength of the material (ksi) l (d) Sult is the ultimate strength of the material thi) (e) Stress limit for fillet weld fron. ASME Boiler a Pressure Vessel Code, Section III, Division 1 - , Subsection NF 1980 Edition. Table NF - 3292.1-1 page 50
-A gg. , + mw - -4N 8 5 HMW * *'.. - * ^ * " " " . " ' ' " ^ _ s2 .- u ' o,
- TABLE b-1 (cont)
M
=
SUMMARY
OF HESULTS REACTOR VESSEL HEAD LIFT RIG ' D E 8 ' Calculated Stresses (ksi) Material Allowable item (a) Part Name Value (ksi) ' No. And Material Designation (d) W(b) 3W SW Sy (c) 3] 9 ; a 13 Leg Tension 9.7 29.1 48.5 38 70
. ASTM A36 14 Clevis Plate Weld 5.6 16.8 28.0 18(e)
ASTM A515 Tension 3.2 9.6 16.0 38 70 : Gr. 70 Shear 3.2 9.6 16.0 Bearing 7.3 21.9 36.5 15 3.9" Diameter Pin Bending 18.9 56.7 94.5 110 140 ASTM A434 Shear 4.7 14.1 23.5 Class BD Bearing on Lug 7.3 21.9 36.5 Bearing on Clevis 7.0 21.0 35.0 (a) See figure 5-1 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi) (d) S is the ultimate strengt
9
- . . - -3. , ,
i 73 Hoon Pin Q t
.. (L,I SIDE PLATE @
( y M OMPIN @ i UNK LUG h
@ UNK s oiAuETER urPER w f
#"**b !
@ CLEVl3 PIN O }
ARM @ g
' clevis @
5* 01AMETER PIN h O h SUPPORT LUG RINGGIRDER h
\D b '
f %
- ()1 ,
_/- LEG h
/
CLEVISPLATE h yvi 38 DIAMETER PIN h
% i k
y I ::::! 8 Figure 5-1. Reactor Yesse) Head Lift Rig
.'sp) 6126:l/021183 5-12 d
. ?'k
- g. ,,
. c, wa - A;4aUV0:i, ; -
N " MP * * '#- } TABLE 5-2 m g SlNMARY OF RESULTS m REACTOR VESSEL INTERNALS LIFT RIG,
- s 2 LOAD CELL AND LOAD CELL LINKAGE D: ' 9 w"
i Calculated Stresses (ksi) Material Allowable d item (* Part Name - Value (ksi) . No. And Material Designation W(b) 3W SW Sy (c) S ult 1 Hook Pin Shear 3.6 10.8 18.0 120 ' 135 ASTM A434 Bearing (Hook) 5.2 15.6 26.0 AISI 4340 Bearing (Side Plate) 10.9 32.7 54.5 L Bending 12.1 36.3 60.5 ! u 2 Side Plate Tension 0 7 1/2" Dia. hole 10.9 32.7 54.5 38 70 ASTM ASIS Bearing 9 6" Dia. hole 13.6 40.8 68.0 Gr. 70 Shear Tear-out 14.0 42.0 70.0 41(e) 77(e) 1 (a) See figure 5-2 for location of item numbers and section ' (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of thie material (ksi) (d) Sult is the ultimate strength of the material (ksi) , (e) Actual certified mechanical properties i
(~:
~
. ,-m
^
_) i , 3 TABLE 5-2 (cont) t E .St#91ARY OF RESULTS
$ REACTOR VESSEL INTERNALS LIFT RIG, ,.
$ LOAD CELL AND LOAD CELL LINKAGE i e
! Calculated Stresses (ksi) Haterial Allowable . Item (*} Part Name Value (ksi) k j No. And Material Designation W(b) 3W SW S,IC I S ult i i I i 3- Adaptor Pin Shear 5.7 17.1 28.5 120 135 ) ASTM A304 Bearing (Adaptor) 6.5 19.5 32.0
- { AISI 4340 Bearing (Side Plate) 13.6 40.8 68.0
>
- Bending 23.7 71.1 118.5 ,
i 4 Upper Adaptor Tension 9 Pin Hole 14.8 44.4 74.0 120 135 3 AISI 4340 Bearing 9 Pin Hole 6.4 19.2 32.0 j Tension 9 Thread Relief 5.7 17.1 28.5 i Thread Shear 13.7 41.1 68.5 i Shear Tear-out 6.8 20.4 34.0 l l
; (a) See figure 5-2 for location of item numbers and section I -
(b) W is the tctal static weight of the component and the lifting device l (c) S, is the yield strength of the material (ksi) (d) S ul t is the ultimate strength of the material (ksi) 1 .
-..r..-. ,__. _-- _ _ _ _ _ _ _ _ _ . . . . . . - . . . _ _ _ _ . . _ _ _ . . . . . - _ . . _ _ _ . - - . _ . _ _ _ _ _ - - , , -.
gie - V H ndi.-> -t - em '~'sa
' fV @
(. m TABLE 5-2 (cont) C
SUMMARY
OF RESULTS
.h -
HEACTOR VESSEL INTERNALS LIFT RIG, ! h LOAD CELL AND LOAD CELL LINKAGE O E w Calculated Stresses (ksi) Material Allowabl'e , Item (a) Part Name Value (ksi) ! No. And Material Designation W NI 3W ' 5W Sy (c) S ult 5 Load Cell Tension 9 Thread 23.9 71.7 119.5 115 140 17-4-pH Thread Shear 13.7 .41.1 60.5 m sis Cond L Hil100 m - i 6 Lower Adaptor Tension 9 Pin Hole 15.9 47.7 79.5 120 135 AISI 4340 Bearing 9 Pin Hole 8.5 25.5 42.5 Tension 9 Thread Relief 7.4 22.2 37.0
- Thread Shear 13.7 41.1 68.5 Shear Tear-out 8.7 26.1 43.5 i
. (a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (Est)
(d) Sg is the ultimate strength of the material (ksi)
<m N, '
%) .
w)
. TABLE 5-2 (cont) m,
SUMMARY
OF RESULTS y REACTOR VESSEL lhTERNALS LIFT RIG, LOA 0 CELL AND LOAD CELL LINKAGE l3 El Calculated Stresses (ksi) Material Allowable - ItemI *I Part Name Value (ksi) No. And Material Designation W(b) 3W SW Sy (c) S ult 7 Removable Pin Shear 5.0 15.0 25.0 120 135 ASTM 'A304 Bearing on Adaptor 7.6 22.8 38.0 4 AISI 4340 Bearing on Top Lug 7.9 23.7 39.5 y' Ben' ding , 21.0 63.0 105.0 i 5 j 8, Top Lug Tension 9 Hole 8.0 24.0 40.0 8, 38 70 ASTM ASIS Bearing 9 Hole 7.9 23.7 39.5 l Gr. 70 Tension 9 Weld 4.0 12.0 20.0 i Shear Tear-cut 8.0 24.0 40.0 8 ASTH A533 8 50 80 b b Gr. B, Cl 1 4 (a) See figure '5-2 for location of item numbers and section (b) W is the total static weight of the componr..it and the lifting device ! (c) S yis the yield strength of the material (ksi) (d) Sult is the ultimate strength of the material (ksi)
,' i. .. . I- t \w -~ w i _
..a. <. _.
f / T
- NY TABLE 5-2 (cont)
[
SUMMARY
OF RESULTS y REACTOR VESSEL INTERNALS LIFT RIG, C - LOAD CELL AND LOAD CELL LINKAGE 2 E8 - Calculated Stresses (ksi) Material Allowabi'e ItemI *I Part Name Value (ksi) l No. And Material Designation W(b) 3W SW Sy (c) S ult 9 Support Pipe Tension 3.1 9.3 15.5 30 48 ASTM A106
,Y' 10, Support Plate Tension .7 2.1 3.5 38 70 ASTM ASIS Gr. 70 (a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi) .
(d) S ult is the ultimate strength of the material (ksi) - L -
I i
,, ,- , l I ) (w a (w) i l
} TABLE 5-2 (cont)
,Ed
SUMMARY
OF RESULTS
$ REACTOR VESSEL INTERNALS LIFT RIG, j LOAD CELL AND LOAD CELL LINKAGE I
i Calculated Stresses (ksi) Materia; rillowable .
! Item (a) Part Name Value (ksi)
No. And Material Designation W IDI 3W SW Sy (c) S,jg M 10 b ASTM A533 Tension 1.1 3.3 5.5 50 80 Gr. B, Cl. I un . l 11 a Side Lug Tension 9 Hole 5.1 15.J 25.5 38 70 m ASTM ASIS Combined Stress 9 Weld 6.5 19.5 32.5 Gr. 70 Shear 9 Weld 2.0 6.0 10.0 Bearing 9 Hole 7.5 22.5 37.5 Shear Tear-out 4.5 13.5 22.5
~
(a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lif ting device
~ (c ) Sy is the yield strength of the material (ksi)
(d) Sult is the ultimate strength of the material (ksi) )
. - ....]~ .- l t - - - - - - - - - - - - - - - - - . -.- .
- p fi,3:s *!
, y -~
t ) L w) 9 TABLE 5-2 (cont)
~
g
SUMMARY
OF RESULTS h REACTOR VESSEL INTERNALS LIFT RIG,
$ LOAD CELL AND LOAD CELL LINKAGE w
Calculated Stresses (ksi) Material Allowabib ItemI *I Part Name Value (ksi) No. And Material Designation W IDI 3W SW Sy (c) S ult i li b Side Lug Tension 9 Hole 5.2 15.6 26.0 50 80 ASTM A588 Combined Stres 9 Weld 6.7 20.1 33.5 Gr. A, C1. 1 Shear 9 Weld 2.0 6.0 10.0
$ Bearing 9 Hole 7.7 23.1 38.5 Shear Tear-out 4.5 13.5 22.5
, 12 Clevis Pin Shear 4.7 14.1 23.5 120 135 ASTM A434 Bearing On Side Lug 7.5 22.5 37.5 AISI 4340 Bearing on Upper Clevis 7.5 22.5 37.5 Bending 19.2 57.6 96.0 (a) See figure 5-2 for location of item numbers and section j (b) W is the total static weight of the component and the lif ting device I (c) S yis the yield strength of the material (ksi) (d) Sult is the' ultimate strength of the material (ksi) L' .-
L O O O 7 TA8LE 5-2 (cont) -
$ SLMMARY OF RESULTS I.
_ REACTOR VESSEL INTERNALS LIFT RI6, h LOAD CZLL AND LOAD CELL LINKAGE S S Calculated Stresses (ksi) Material Allowable Item
- Part Name Value (ksi)
No. And Material Designaition W(b) 3W SW S ICI S y ult i- 13, Upper Clevis Tension 9 Pin Hole 7.7 23.1 38.5 13, 50 80 ] SA-508 C1. 2 Bearing on Pin 7.5 ' 22.5 37.5 13 110 135 b } 13 ASTM A668 Thread Shear 3.3 9.9 16.5
- b l
L AISI 4340 Tear-out Shear 7.7 23.1 38.5 Cl. M l j I (a) See figure 5-2 for location of item mnbers and section ] (b) W is the total static weight of the component and the lifting device l, (c) S yis the yield strength of the material (ksi) (d) Sult is the ultimate strength of the asterial (ksi) i
' 'N- *'
_ _ _ , _ _ e__.m__._ -
~~
. g x9
- s ,
e ' S_ __9 0
$ TABLE 5-2 (cont)
.h
SUMMARY
OF RESULTS { REACTOR VESSEL INTERNALS LIFT Rib,
$ LOAD CELL AND LOAD CELL LINKAGE 5
Calculated Stresses (ksi) haterial Allowable, itemI "} Part Name Value (ksi) No. And Material Designation W IDI 3W SW Sy (c) S ult 14, Sling Leg Thread Shear 3.2 9.6 16.0 45 69 AISI 1117 Tension 9 Thread 10.7 32.1 53.5 or Hot Rolled or 32 60 g 1018 Cold Rolled 14 b Sling leg Thread Shear 3.2 9.6 16.0 85 110 l ASTM A434 Tension 9 Thread 11.6 34.8 58.0 C1. BC . AISI 4340 (a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) 5, is the yield strength of the material (ksi)
~
(d) Sult is the ultimate strength of the material (ksi) L '
O O O ' l S TABLE 5-2 (cont) i h SIM4AR( OF.RESUI.TS 3E' REACTOR VESSEL INTERNALS LIFT RIG,
- j. $ LOAD CELL AND LOAD CELL LINKAGE i M
l Calculated Stresses (ksi) Material Allowable ! ItemI *I Part Name Value (ksi) f No. And Material Der.ignation W(b) 3W SW Sy (c) S ult 15, Lower Clevis Thread Shear 3.3 9.9 16.5 15, 50 80 ! SA-508 C1. 2 Combined Stress 30.6 91.8 153.0 15b 110 135 III III ASTM A668 0.87 Ratio <1.0 7
- . n 15 b
AISI 4340
) Cl. M l
l (a) See figure 5-2 for location of item numbers and section . (b) W is the total static weight of the component and the lifting device . (c) S yis the yield strength of the material (ksi) - j (d) Sult is the ultimate strength of the material (ksi) ) (e) Actual certified mechanical properties l (f) Stress ratio Limit for combined bending and tension from AISC manual Chapter 5. Sect.1.6.2 1 j. w _ _ __ _ _ . _ .__. _ . _ , _ . , _ _ _ __ _ _ _. ..._. . . _ _ _ _ . _ . _ __ _ _ _ _ . . _ _ s
( *
, .. v ggs ,
. TABLE 5-2 (cont) ,
h
SUMMARY
OF RESULTS 5 REACTUR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE w E
~
Calculated Stresses (ksi) Material Allowable. Item (a) Part Name Valbe (ksi) No. And Material Pesignation W(D) 3W 5W Sy (c) S ult i t 16 Clevis Bolt Shear 5.6 16.8 28.0 85 110 ASIM A434 Bending 7.8 23.4 34.0 Cl. BC Bearing 14.9 44.7 74.5 T AISI 4340 U i 17 Spreader Leg Compression 6.5 19.5 32.5 36 58 ASTM A36 F, = 18.9 I9) (a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lif ting device , (c) S yis the yield strength of the material (ksi) (d) Sult is the ultimate strength of the raaterial (ksi) (g) F, is the compressive buckling strength of the material (ksi)
j i p p (b Q,) 0 E TABLE 5-2 (cont) m g;
SUMMARY
OF RESULTS g' REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE I Calculated Stresses (ksi) Material Allowable Item
- Part Name' Value (ksi)
No. And Material Designation W IDI 3W SW Sy (c) S ult 18 Backing Block Bearing on 11.7 35.1 58.5 30 75 ASTM A276 Spreader Leg Type 304 Compression in 7.9 23.7 39.5
,m E Cond. A Block 4- ,
19 End Plate Bearing on Channel 6.5 19.5 32.5 36 58 ASTM A36 I (a) See figure 5-2 for location of item numbers and section ' (b) W is the total static veight of the component and the lifting device
, (c) S yis the yield strength of the material (ksi)
, (d) Suyg is the ultimate strength of the material (ksi)
( 4 4 i
.~ .,
. 3,(. . , . /
3
;* l'
, 4+.y
- ./
\
l 3 TABLE 5-2 (cont) y SUP9tARY OF RESULTS RE5CTOR VESSEL INTERNALS LIFT RIG, 8 L0AD CELL AND LOAD CELL LINKAGE M w . Calculated Stresses (ksi) Material Allowable 1 Item (a) Part Name Value (kni) No. And Material Designation W(b) 3W SW S ICI S IdI y g l 20 Spacer Bearing 14.9 44.7 74.5 50 70 ASTM A588 Combined Stress 9 Hole 25.3 75.9 126.5 I 61 .5 'I 88.6I 'I
. u. Gr.- A and B . 0.995 Ratio <1. 0 III O Shear in Weld .
1.8 5.4 9.0 21 Leg Channel Bearing 14.9 44.7 74.0 36 58
- ASTM A36 Tension 9 Cross-section 8.7 26.1 '43.5 4
(a) See figure 5-2 for location of item numbers and section , ; j , (b) W is the total static weight of the component and the lifting device !
- j (c) S yis the yield strength of the material (ksi)
(d) S ult is the ultimate strength of the material (ksi) (e) Actual certified mechanical properties (f) Stress ratio Limit for combined bending and tension from AISC manual Chapter 5, Sect.1.6.2 L e
,., ,~ ,,,
q'
~
m TABLE 5-2 (cont)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT HIG,
@ LUAD CELL AND LOAD CELL LINKAGE E
w Calculated Stresses (ksi) Material Allowable Item (a) Part Name Value (ksi) No. And Material Designation W(b) 3W SW Sy (c) 3 ult t 22.23, Leg Support Shear (weld) 4.8 14.4 24.0 18 I} Block Bearing on 8.8 26.4 44.0 36 58 AISi 8620 , Adaptor Nut , Y' m Brace Plate . ASTM A36 4 j (a) Se 3' figure 5-2 for location of item numbers and section ! (b) W is the total static weight of the component and the lifting device l (c) S yis the yield strength of tM material (ksi) (d) Sult is the ultimate strength of the material (ksi)
~
1 ] ,
, (h) Stress limit for fillet weld from ASME Boiler & Pressure Vessel Code, Section III, Division 1-
, Subsection NF 1980 Edition, Table NF-3t R.1-1. page 50 3
,-(
. .- l 6 . . -
y r w-
/
f f _ O 4 lw,)). 9 TABLE 5-2 (cont)
SUMMARY
OF RESULTS h REACTOR VESSEL INTERNALS LIFT RIG, y LOAD CELL AND LOAD CELL LINKAGE 8 w Calculatea Stresses (ksi). Material Allowable' . ItemI *) Part Name Value (ksi) No. And Material Designation W(b) 3W SW Sj (c) S ult 24,III Adaptor Thread Shear 2.3 6.9 11.5 30 75 ASTM A276 Tension 9 Thd Relief 8.3 24.9 41.5 Type 304 T Cond. A O 25,III outer Tube Thread Shear 5.7 ' 17.1 28.5 30 70 ASTM A312 Tension 9 Thd Relief 9.6 28.8 48.0 Type 304 1 (a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lif ting device (c) S yis the yield strength of the material (ksi) (d) Sult is the ultimate strength of the material (ksi) (i) These items will be replaced in the forthcoming modifications L '
f) ( () g TABLE 5-2 (cont) SIMMARY OF RESULTS i h REACTOR VESSEL INTERNALS LIFT RIG', Q LOAD CELL AND LOAD CELL LINKAGE 5 Calculated Stresses (ksi) Material Allowable - a) Item Part Name Value firsil No. And Material Designation W(b) 3W SW S,(c) S ult 26, I N Guide Sleeve Bearing On Engaging Screw 17.0 51.0' 85.0 30 75 ASTM A276 Thmad Shear 5.7 17.1 28.5
, Type 304 Compression 10.1 30.3 50.5 h Cond. A 27,III Engaging Screw Bearing on Guide Sleeve 17.0 51.0 85.0 115 140 ASTM A564 Tension 9 Thread Relief 12.6 37.8 63.0 Grade 630' Thread Shear 6.6 19.8 33.0 158 I8I 168(
rand. 1100 27 ( Bearing on Guide Tube 12.4 37.2 62.0 b
. (a) See figure 5-2 for location of item numbers and section '
(b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi) (d) Sult is the ultimate strength of the material (ksi) (e) Actual certified mechanical properties (1) These items will be replaced in the forthcoming modificatic;.. y YY n - ~~ g-
.,f a t'~ < -
* * 't -
[ / ') .
- Q g TABLE 5-2 (cont)
SUMMARY
OF RESULTS
@ HEACTOR VESSEL INTERNALS LIFT RIG,
$ LOAD CELL AND LOAD CELL LINKAGE
=
w Calculated Stresses (ksi) Material Allowable " Item (a) Part Name Value (ksi) No. And Material Designation W(b) 3W SW S ICI S,yg W y
; 28 b
Load Nut Bearing 8.8 26.4 44.0 30 75
; ASTM A276 Thread Shear 4.7 14.1 23.5 Type 304
~
Y' Cond. A e (a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)
~
(d) Sult is the ultimate strength of the material (ksi) , (i) These items will be replaced in the forthcoming modifications
. -.-spoemen ee seeiner me mip -*BN
m
; \ , m. (3 N-] Y N_.- ]
S TABLE S-2 (cont) m
SUMMARY
OF RESULTS g REACTOR VESSEL INTERNAL.S LIFT RIG, M LOAD CELL AND LOAD CELL LINKAGE w Calculated Stresses (ksi) Material Allowable Item (a) Part Name Value (k s i) No. And Material Des ignat ion W(b) 3W 5W Sy (c) S ult 29 (I Tube Housing b Thread Shear 4.1 12.3 20.5 30 75 ASTM A276 Tens ion 9.0 27.0 45.0 Type 304 E m Cond. A O 30 ('} Gu ide Sleeve Thread Shear 4.1 12.3 20.5 30 b 75
, ASTM A276 Tens ion 10.3 30.9 S1.5 Type 304 Bear ing 12.4 36.8 62.0 Cond. A .
, (a) See figure S-2 for location of item nuntiers and section (b) W is the total static weight of the component and the lif ting device (c) S yis the yield strength of the mater tal (ksi)
(d) Sult is the ultimate strength of the nutzt.JI GM) (i) These items will be replaced in the forthcoming modifications a.. .
.. vw x. ,, s +' -
l
- t. .
. wc;hy >> -
i G 9 y TABLE 5-2 (cont)
$ SlbMARY OF RESULTS
{ REACTOR VESSEL INTERNALS LIFT RIG, y LOAD CELL AND LOAD CELL LINKAGE 3 w Calculated Stresses (ksi) Matertal Allowable item (a) Part Name Value (ksi) No. And Material Des ignation W II 3W SW Sj (c) S ult , IdI Load Nut 31 3 Bearing to Mounting Block 8.7 26.1 43.5 30 75 ASTM A276 Thread Shear 4.5 13.5 22.5 Type 304 u, 32, IdI Rod Hous ing Tension 9 Thread Relief 9.1 27.3 45.5 30 75 ASTM A276 Thread Shear on Upper 4.5 13.5 22.5 Type 304 Threads Lower Threads Shear 4.5 13.5 22.5 I (a) See figure 5-2 for location of item numbers and section
. (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi)
(d) Sult is the ultimate strength of the saatarl*1 (ksi) (j) These items are tne new items to be installed
. L '
f 7
~J Y j $ TABLE 5-2 (cont) ,E
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, { h LOAD CELL AND LOAD CELL LINKAGE 8 Calculated Stresses (ksi) Material Allowable itemI 'I Part Name Value (ksi) No. And Material Des ignation W(b) 3W $W S ICI S y ult 32 II Rod Housing Tenston 9 Thd Relief 1.8 23.4 39.0 30 75 b ASTM A276 Thread Shear in Upper 4.2 12.6 21.0 Type 304 Threads Lower Threads - Shear 4.5 13.5 22.5 33 I3I Guide Sleeve Thread Shear 4.5 13.5 22.5 30 75 ASTM A276 Tension 9 Thread Relief 9.7 29.1 48.5 ; Type 304 SST Bearing to Stud 9.9 29.7 49.5 (a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) S yis the yield strength of the material (ksi) (d) Sg is the ultimate strength of the material (ksi) (j) These items are the new items to be installed ., . L
~ ~
f , ,- , .
~., o v TABLE 5-2 (cont)
M StHMARY OF RESULTS 5 REACiORVESSELINTERNALSLIFTRIG, i b LOAD CELL AND LOAD CELL LINKAGE S O . 1 Calculated Stresses (ksi) Material Allowable Item
- Part Name Value (ksi)
No. And Material Designation W(b) 3W SW S ICI S y uit 34 IdI Rotolock Stud Tensile Stress 9 Cross- 27.7 83.1 1 38.5 115 140 ASTM A564 Section Type 630 Shear Stress on Land Root 9.7 29.1 48.5 [ 17-4 pH HIl00 Bearing on Land Surfaces 50.3 150.9 2 51 . 5 Bearing on Guide Sleeve 25.9 77.7 129.5 Bending in L.inds 9.9 29.7 49.5 (a) See figure 5-2 for location of item numbers and section (b) W is the total static weight of the component and the lifting device (c) S, is the yield strength of the material (ksi) (d) Sult is the ultimate strength of the material (ksi) (j) These items are the new items to be installed
- I g
a f%. O f O O
, TABLE 5-2 (cont) h SLMMARY OF RESULTS
[ REACTOR VESSEL INTERNALS LIFT RIG, y LOAD CELL AND LOAD CLLL LINKAGE S S
~
Calculated Stresses (ksi) Material Allowable Item
- Part Name Value fl:sil No. And Material Designation W(b) 3W SW S ICI S (d) y g 35 Upper Internal Bending In Lands 13.7 41.1 68.5 115 170 Insert Shear Stress on Land Root 5.6 16.8 28.0 ASTM A637 8 earing on Land Surfaces 41.5 124.5 207.5 l
{ Gr 688 , Thread Shear 2.3 6.9 11.5 i Type 2 36 Lower Internal Bending Stress 19.8 59.4 99.0 115 170 Insert l ASTM A637 Shear Stress on Land Root 8.1 24.3 40.5 i Gr 688 Bearing on Land Surfaces 59.9 179.7 299.5 Type 2 Thread Shear 6.9 20.7 34.5
~ (a) See figure 5-2 for location of item numbers and section 3 (b) W is the total static weight of the component and the lifting device (c) Syis the yield strength of the material (ksi)
(d) S ult is the ultimate strength of the material (ksi) L. - , ,
4 WHERE P3E AND PNJ RIGS DIFFER.THE PSE ITEMS ARE DISTINGUISHED BY AN "A" SUFFIX.THE PNJ ITEMS BY A "B" SUFFIX 7 p j-SIDE PLATE @
@ UPPER ADAPTOR ADAPTOR PIN h I
l @ LOADCELL BOTTOM ADAPTOR @ l A&B @ TOP LUG 6"DIA REMOVABLE' PIN @ A&B h 4"DIA CLEVIS PIN SUPPORT PLATE @ A&B A&B h SIDE LUG SUPPORT PIPE h A&B i}! O # A&B h UPPER CLEVIS SPACER @ A&B @ LOWER 5 C6Evis , 4" DIA CLEVIS @ BOLT d END PLATE @ p ~. . *3 , h SPREADER" LEG ASSEMdLY
# 'l,
@ BACKING ,g gh l BLOCK ,
y ,, , Lm f[ ' f, h23B
\ PNJ '288 'b ;
24A
@B LOAD NUT ,
\~ e I h PSE 25A
@ B TUBE HOUSING r - l .
@B GUIDE SLEEVE %
L
> l, ll .
i- 27
\ J
@ BRACE PLATE -l A&B @ LEG $UPPORT BLOCK
\ ,
ADAPTOR @ A RING GIRDER OUTER TUBE @ A GUIDE SLEEVE @ A ENGAGING SCREW h A&B Figure 5-2. Reactor Yessel Internals Lift Rig, I Lead Cell, and Linkage l t
!rm (x ) 61268:1/021183 5-35 A
m I c. e 7 r
- LOAD NUTh A eLEG SUPPORT yR /
/
[
/ BLOCKh
^
A l N \
- gh fp 'RODHOUSINGh
; ;=i 9 L Eh i i '
$g 'ROTOLOCK $. 7 j
/
p l STUDh j ~ i s -- - y
'H $ . (r- ;,d l d '
n (,/ j 8 :; LOWER INTERNALS ([ i
, r! l r-UPPER INTERNALS l g
- LOWER
' UPPER I 9TERNALS - ' % P -
i INTERNALS
/
/ '
INSERTh INSERTh UPPER INTERNALS LOWER INTERNALS ARRANGEMENT ARRANGEMENT
'NEWITEMS LETTER "A" SUFFlX IS FOR UNIT 1 ONLY (PSE)
I 4 Figure 5-3. Rotolock Studs and Inserts Arrangement kJ 61268:1/021183 5-36 s - Je l
APPENDIX A DETAILED STRESS ANALYSIS - REACTOR VESSEL HEAD LIFT RIG j This appendfx provides the detailed stress analysis for the Salem reactor vessel head Ifft rig in accordance with the requirements of ANSI N14.e. Acceptance criteria used in evaluating the calculated stresses are based on the material properties given in section 4. G I enes:uoum
SKE,TCH ett 0.eu0wst SHEET to.as $4202 v
)
s.o. ...a e , ,,,, A PTNP-188- Salem Units I and !! I o, 33 R.V.Headi.iftRigAssembly pD F. Peduzzi $ f ,f M Lv73 j , to, AMy J. Richard ou .ress ..a .ss sss, ua y
- 1. The purpose of this analysis is to determine the acceptability of this rig to the requirements of ANSI N14.6.
- 2. The results show that all stresses are within the allowable stresses, r4 .
63 ( ! 1 JOSEPH W. RCHARD x- .. c .c aerios -
'4 P e Yo hf Original Issue atvisios u.
l oatt j ocsemiptios l or f I g _-,) L
WESTINGHOUSE NUCLE AR TECHNOLOGY OlVISION 73 i PAGE TITLE R. V. Head lift Rio 1 on 33 pmoat CT
- AwfMOA DATE CM n*0. s v QATE C M E' O. S v QATE PSE/PNJ 4.6.toAnu _- tlE QRowP S O. CALC.NO. GQ #1LE NO.
PTNP-188 CHE y """ " O ' SIDEPLAft @ ,
,eonm P,N @
LINE LUG h UPPER CLtvis @ CLEVIS PIN CLEVIS @ S* 01AmtTER P N @
/
f h SUPPORf LUG
/ s
% . J ) RINOGIRDER h
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
)
TITLE ,,gg V *mOJECT R. V. Head Lift Rio AwfMQm 3 os. 33
, 0476 CM E'O. S v ATE CME *D. a v OATE S 0.
PSE/PNJ 7.C. b c l/yg CALC.A-Q " ljAd gM y68 NO. Qmove PTNP-188 . CHE DES tG N W ElGHT Sto;oco Ib5 F ec m ASSY o wc, (6 tsJ ost) 17,ooo lb5 R ig w ei i onn Ib c.on t ingn e.g c-l'e shi
'345)o. Ib5 s LING L E C, A NGLE c 11.'l5 5
v/ o I 19 f. 6 0 9 l SUX1.- ' - l Tan a r (TLeo - n 7 4 = kl.l.5 = .96b0 M 7. to o 197.60
- d. = IS* .
i A
) a g v. mgy. Av7 Mon QAft CMn'D. s v OAft CM a'Q. S v Daft
.m/ NO DATE WESTINoMoygg ponM 883130 o
=
Wi!STINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE 8 AGE L R. V. Head lift Rio 4 e. 33
' mOJE CT . AwTMom DATE CME ~O. A v , QATE CMn'O. s v OAft s o.
psr/pr
#A6C.c.f.L No.
yi l/n p.t.2 Au J omove Fws No. PTNP-IS8 CHE
.S H E AR, STREE 1.s "om PIN \ .
rear u Asm A 933 com eo f, . P / 2. A ,, i
~'
P= 395,coe A,,- Trd% . l g *; %A P 4 Av. Tr h.sts )% i a '- Av= 49 n.o in' :
~ ~
d s ( 3 95,000) M* 94.00) q : L. ; hv
-. s l " I fv = 39Io P S T.
-e6 .s I
O P. be. ecUng on ausmhlyilk, BE ARIN4 STRESS l l d = cli m.5 e of p in, in. l 4 1.w3* of h..rin3 such f- P/A, or c.. s.se 5.a,,,in. P = 2 95;oo 0
' a = 1.ngw of h..n3 urk TNNER ,
en s.t.i of %w ho4 3 ,iA. Av ci .9 - 6.995 x r.co )
= ( 59.9 6 Jins g . ipp b bun b.arin3 surfe o,in.
S . (395,cco )/( 51.90 L 4e w ac s 1 5 u .f pib pa [c_ = 5754 psr , J + 2(a +3 ) OUTER P - 185,coe is. A 2.ad 2( s.cc )(,.us) lr d- 7.895 in. = ( 99.97 )ins - J= r.co x ( = h9s,eco )/( 43 37 ) Q
&= 3,c 0 i in 9* ,(175 in [c.
- n 1 2. PtT Ciw M S - meo) - f] h.
O mg y,
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ag y, OAft vv58719eeMOwse pORM 963130 Awfmon CAft CME'O 0 v OATE CMR'O. S v OATE i l J
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- t. / R. V. Head lift Rig emostCT . awfMon oaTE CMn'O. s v 5 o. 33 g caTE CMnQ.sv Catt PSE/PNJ 91,0. ibi l/f 3 0,W, #4LJ so Cacc ~o. =# *p a ~o caov.
PI N -
) i BENDrN6 STRE554)
- Md(t- a, S 4 0) -
.q. mar
.I - y d%9 .
L =- d /2. ' 6.i(h+puXth) p .w(% +tJ )/N') !
\ }
= 1bP( Y + l W f*)/'rn.ul
%- @ ( C3756)
= % s,0 0 C (,,0 3 T56)
= 13)D5 PSI ADAPIT.D PROM EN.TENI% AND Jor.NIN 6 ,
@ td,a munm.t a u,e, .
m e. m n e st o n , m e n pua tt u m
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
, \
776 eson R. V. Head Lift Rio Cano.e, b ca 33 ontg peo45CT , AwTMOm 04TE Can'O. e v g AT4 PSE/PNJ %f _haLuA llT% Uf V.l)4 kh21hD .- Gacwe S Q. CALG Nd. fwl NO
- CHE PTilP-188 S IDE PLATE At T M A- 514 oc USS -T I 2.
= ib.5 5
- i p
- a g.g !
l
. B '
i 1515p , N Y
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O,
\v f
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I 7.020 y / ss' b+'i } ' Q' s _.
\ v B _'3.oo _
l . T6nston ni f.03 o Hot
- r.56 e x ,50 DEEP __.
Counitrbort on F = my rs = i lh 500 one Pt.aie
~1.
&3 ( i f..S - 7 0 5 o)(3.0 c) - (T.S t -T.03 ) (.5 0) = 1s. ly ra n*
Ft= E = \M Gno A 15.145 Pt = 6T60 p sI ( )
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/~'] TITLE paos PAostCT R. V. Head lift Rio 7 o, 33 Aw? mom GATE CME O. t v
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TE CME'O. O v o.oo, caTa S hear a t f.o 3 0 Hole - P v .E h,= l 16,so - rose)o.co) lt.s L - 7.o so)(.so)
- 2. A y t 1 t <
2 fv: 17 h 4 er- , A v = is ,513 n 1 (12.5 13 ) Pv= 6 f6o P SI l b e.a r in g q t '7,515" p H ol e e) ' The .maximurn bearing Si r esS is the sainy5 _ the outer beariny stress on th< hook pin U, l f c. : D 4 5,oor ) / 'f 4.9 7 7 L7 2. 9SI i t 9 Alv. NO. Alv, 0478 WESTINOMOW88 PomM $53130 AwTmom QAft CM E'Q. s v QATE CM E'Q. s v DATE m
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**GS (V) title #j R. V. Head lift Rio ATS q=n g gy Sf os 33 rmostct
- Astmon QATS cMn'O. a v j CATS s o, PSE/PNJ
- h (.ilkuutI cA6c.Nb. y#
llT3 AM, AM omove f/wa mo PTNP-188 CHE 7" OlA. S H E AR, STRESS PIN 3 - l mru As tn Aus c.t.a ss to F - P/2 A, - pa 195,c00 l A,* Trd %
! % 3 3 % Av = TP( 7 000 )*/4 Av=
I A so. n int o d (395,coe ) /(2.+ 50.$ 1)
- t. ; fv s
., 1 l fy = 393i p sr.
-- - -- s p4 g l
C(') P 6 .<.ung on amaly,L BE ARINC, STRESS d = dian..t.se of p cn, in. S linSth of buring wrfeu:. -C.
- P/ A,,
e r c.e ,A sr bo a , ,i s. P= 3 9 5,e
- a = 1.r p w of t=4 iq 3er k TNNER cne. s. de of oar bed3,th . Av - ci 3 - ( r.o o )( r.or )
9 s pp bdw.n btarin3
= ( 69.9T lins s.crfeco,in.
Sc, = ( 39S;Cco)/( le9MT ) L +cw aas i.- +.x of pA pa (= 5150 pu:
= .9 + 2(a +g )
OUTER P - 3ss,o* is. A, 2 ad 2(3.x x2.co ) d= 7.co cn. = ( 4 T.o Jin s
.E = 0.0L th. 7.i:-1(c,Ns) ( = ( 3M,Cco )/( 9l.o )
a= .3.c0 ,.n 95 1575 fn [c, * ;if7 P E:'. (^x C4.375- U S ro)- f fG /2 i a l v, m g v. AwfMom OAft cMn'O. a v QAft CMn'o. s v Q4ft
'" NO D.TE WESTINGMQW54 PQmM S42130 .
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE 84GE (q] N PAoJECT R. V. Head lift Rig AwTmon oarE CME'o. S v AYE C a n Q. . ' 9 o, 33 M g cars S O. PSE/PNJ ^ 5 f.$0A>- -l CALC.40. pG IN % Aub $hL A f La No GMOwP ,, PTNP-188 CHE '. I PI N 3 . BENDrN6 STRE554) Mg!(t a+ 3 +if) l [b
- h C !I-
! I
- Vd%4
- i 1 t= d/a ! .
i 4. i(6p uXtX&)
=
P(3a43+%) )/(Trday , ; e I kP[ Y 4 .l315 * )[TTT.CM . i 9 (.03l56)
- 3 45,000 (. 03f S4)
(b : 10,7T1r p5I -
. I l
I , I U) ADAPIT.D PROM IkTENING AND JotNTN(a , ' j @ Ed , A mtssasNr.L n.u op j MMa.TN . enruw , Natu pusmnun j
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~ WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION eaQs TITLg
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10 o. 33 R. V. Head lift Rio QATE Can O av LAYL cng Q e, cats emostCf Awinom g PSE/PN[ k(.idw/ l/D {,,4d. /MM c =o
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f n.w - 4.oir)(r.isy 0 - 4.u.ossf u. sis in fe.1 A At h - 3 4 5. 002 M.515
'l Ft = db3 PSI ,'
i b { I I h
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l Pv=.E. A> ( T.1T - 4.oir)(7.15 k2) - SH.o9 59 VI.5'IS in'
. Av i !
I fu : 3 9 e oce =. 4 ') to 3 P S I - l G 9. 5I 5 Bear n3 on T.oo p Pin j i The, b earing s tres s is the samt 45 the inner j bearing s tress on the bottom pin connecj.qd i throog h the side plate. The pin is item Q). i f I - f c. " M5', coo / b4 W = 5550 PSI : Te n si on d C.3 l ind rica l S e c.i io n fk: .f A: II ( T.l T N =. 5 1 . l b f i n nr 4 p+, mm = f.bl3 PSI hlelkf l
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WESTINGHOUSE NUCLEAR TECHNCLOGY DIVISION aca vina R. V. Head lift. R W
,- . ..,. e-..., ,,m...e.
11 os 33 j .
....e, PSE/PNJ -
h[ i) Masyst' (/ B y.s
- d.r~oW, h $ a d .cw. 1 io gc46c o PTNP-188 ! CHE f
. 5 .
I LINK LVG h5 T M A W C,La$ $ A l VIEW
!l! I
'/ 0-0 l 3 4.0 thK /
', 4 j full Penetration Weld
- 3. ot 4 o F v = M cco = 115j 00o tia l l "Vie.c *LS f b pH 9
" 6.5 K F=.Eg =
i i2e,yttibs l 154' c,3 sq j t 7 05 g :. Fv F Fw
- fv ton W = 5 3,6 2.5 %
IC 0 $ lon qt 5.01"phole, f e
- E. h,= 1( b.5 '. 5l)9.0
- 31.3 1 in t he f* = 19 t. Ver = 1975 f SI 2191 S hear Tear at hele Pv: .F. , i ,L. 7tr A,= 1((,,5 1.51) i ' 31. 91 in*
6v 31D. Fv= 597s psT Avtaum OAft CMa'O e v caft Gwn o av pata agv agy NO Oaft W88tl40M oust ponne383130 "a e & W u.
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
~ ' 'N T1768 8.G4 R. V. Head Lift Rig ;3 o, 33 anoJ6CT .wf=vn O.74 cm. Q e v .TE cm. O e v Q.ft 3O PSE/PNJ' @fAndswi (/73 W, W. R.* A Yb lC.6C NO MF be NO GaQwp PTNP-188 I CHE
Dearing ctt 5.o1" # ho le. ,
the b e ari ng s t r<5s i s ih t. Same as th Aind e e bencing 5 t e c 55 en %e UPf# c levis f i n Lbl. f c = 116, T7T / 2 0.01
- b 2 9 i P S I.
Combined Stre ss f tem Tension cind Bending i M= t.D5 Fv - 3.5 FH - I, l h 5 ( SM5(IIS,0ct) - (3 5)(53 b1C 3
~ ') Mr 709937 3
in - lb. I ft: En y ti A 2. 64 60(10): 7 010'
- 2. = 1 h)(2o)2- = 141 in 3 h
P( = 5 3 m- , fe99st . TO 1(o 7 Ct= (,7 0 + 2033 ha 37c2 P51 9 .v.
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, n PAGE '#- TeTLE R. V. Head Lift Rio "- TE gma Q, a v I4 ee 33 OAft M
- AwfmQn DATE CME'O ev
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- 10 G'A LC. Nd p l' $6t NO.
CHE PTNP-188 v<rtical shee at futt Pene_tca&n weta S v r Es. A 5 ( S hol = 7 0 in' M fv imyn =1937 PSI 70 I l I l l I QATS GmnD.tv QAT4 mgy ggy, AWiMA QAft C H".' O S v
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
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R. V. Head lift Rig ..o. ($ o. 33 j
. 1-o. o. . .
6-, o. . . c., Ef A bpqi l/fM.rp, 4.V d.
,.1 ... o.,,
PSE/PC ' so casc ~a. 7,s. ~o
-0.o .
O er clevis S H E AR STRESS N N . mru A sTm A-m aos E0 f - P/2 A, i
' P= n. b,Tf r ,
A,, Ted% A g *M "
'4 A, n-(r.co25 )W j a Av= 14.65 in' i
- 1 T~ L.
~
F d v s ( 11b f fr )4, tq,LS )' j ,
,_.. , 1 1 fy . 3n9 pu
.c ,
Pf g- ' C')^ P 6 .cungnu d p. BE ARING STRES5 , d = diam.tcr of p in, in, ; S'lenSth of burin 3 sudeu. .f,. P/Av i
" or u.a. b.a v ,in. P= 116,nr a = 1.w$ w of be4,.iq 24,. T.N N E R che. ddt. t# oAe body ,in . Av a .9 - (sats X 4.e )
9 s pp bd.*un b..an'n3 * ( 10.0I lin t Luddle.b in. j g, a l1bj IYT )!(3 C.Cl L +ciet se.wv i. q u of
=
pib ph
.9+2(aq)
(= L34I pu: OUTER P = IlbT7f lb. A d- 5 0015 j 2 ad 2(2.9 X5.Oon) in. = ( 24.on. )in'
.P = 4. O o % ( = ( lib,V77 )/( 2.4.017, )
a= 1,90 iw a
, t . A (,8 4 f) 9= . l 'f D r,s
[e = 5 -) 9 y ? t':". t9,u. u t4a nw cus)-9 cea li 6, ,,y. . 1- . o.,i c- o e, omia ca o.s' oa's [e0 cate VWast Nonovatpomu 363130 e k 4 I
w_ ~ um, WESTINGH^USE NUCLEAR TECHNOLOGY OlVISION r n *aos vir6: (V) R. V. Head lift Rio 16 os 33 - DATE Cna'O. e v TE GnnO.av gatt g. Mt awTaon Y PSE/PNJ. h f.inli-41 l/T3 &.W.Of*1 4 aaowe no es6c:~ o. ya gi.a ~o.* i CHE PTNP-188 PI N g , i
;\
W BENorN6 STRES5 , M M at 4tJ)
.ru , u t.t 2.vd%s :
c a. d /2. 4! t. 4..w(3up ((h 3 dA fXt%) -l' g) ) )/N8) - s
= ib e ( 2.s v .no sprs.od 3 b ')r sm, 1 tbj TT f (.01199 ) ,
;j
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FMTENIM(.s AND JCLNTN Gr , MDid,A m nhNf.L w.u* OF MMN.IN" CELION , ht4EH py3(ItMWh
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WESTINGHOUSE NUCLEAR TECHNOLOGY OlVISION
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R. V. Head lift Rio
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. a c .u... o.,e PSE/PNJ h,( fjtdu el (/f1 '
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- f. ~o CHE 3 VPPEC. ( E C TTOM C t.Evb ASTH A-13 7 ddAss BD q g . _ 9. m u _
6.5 A. - 6' T 01# T e.rm on of Scic p mta b -
', E
\
ft*_E.. tn 71L ,/ Q is: 7- %p r,- 1o* 2 ( i1. vita l scew2 , te = 11T 1 PSI 1.L b' b "
- -.8 -
9.37
. .ie.e .
s heo r at 5.010 ( Bete ,
) '
f v = .E. = n G X t.2 4AV 4 (1. t 73 ) 84' (13 5.01)(2.5) - 't ([,(,05O' de = 11.9 9ti,in ' fv= 3tfi P51 . Av = ( L 5- !4! )(2.3) 2.fi)(,c9d2 6 e o ring at 5.01 (> liole Av = 9173 in 1 The bearing $ trest is thgome, as he. cuty bcottog S trcss en the c. levis pin Q) for both(7)and W. f c. : lib,TTT/1.4.017. : Sif4 PSI Tbc thrend S henc is j-Q s a m e ns +he, 4. Keen d S h eae f o r i h e ne m U7 for both and V1 Pv8 11.6,it's / SS .0 9 7. 1303 P ST , g a... NO 04?0
. 1-ca u.ri c-. o . , u.te ... .., o.es waiti~o ovie noa. ..ma
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION ( ,,,se *~ i R. V. Head lift..i-a Rio. IT o' 33 I
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P$(/PNJ ' N.(.f hp/ l/I3 4. ~o c .a ~. AcWe_ k*: A wawwa. PTNP.188 d CHE
'THstEAD SH E A14, ARM g p/A, Av. tkww)/2.
i NATt. l\ S T M - A 3 Cb t,8.10 ren ae. un m men. I S.u.s b .6495a.M l
% =(( = 'F } .(e4952.A 'f )
t.757b)h, M e hiajor a n ne. h of enkme) See ad h mes.,har of areuk/4 "P
./=sg4emmi m.A p l s' m Nm ( 55.0'll)Q \d i i P- iw,etr tw l l .
1
<} A TMCAD 'T F. M b a C M y {t = P/At pn smsmau.y wenAsia pamn Y4( D, . 9'7643/n Y i
Ag*5(
- 5 .m3/4)'*ll.Mwi '
l l .q . nu,rrt V(n.wl) i ,,ui ,.
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CESTINGHOUSE NUCLEAR TECHNOLOGY DIVISICN r.,64 r:;r;m R. V. Head t.ift Rio
..oe li o. 33 g
4.r-ea oiva c . o e. c., e . . .. n
. ~oIf/jg*t lJg.rs
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.o PSELPN1 ' f ed n_w' \l1A J s... a gp ,
6 eao . PTNP.188 - CHE Bottom cl.tyt. I O S H E A R, STRESS 5' 01 A, PIN mrs Asin 6339 c.t Ass..to f, . P / 2. A , P n.6i f t r r A, red /4 n-
- 7. ' A "-% Av. M s,co25) W Av= 19.b5 in5
; -d 7- i, f, s ( 114,tt7 ) /9 + 19,(5)
- . ,I "l fy . mq nas e P/
1 P/g
) P. 6 s wngon w ouA BE ARINC, STRESS d i diam tse of pin,in, I
'i S linph of hearing i.urfm -
.C.= P/Av
,,, or . air L.a v ,in.
- P= n.t.,, ris
}L a=1.nph of W4riS a A T.N N E R , e n s i.ta i. .t a 4 , w . a i . Av ciS 6.co2sX 2.si ) v
=( 19,500 hs
- 9. q =p LL n t. rin3 .
i,ur k u ,in. . C., - (ingn)/(is, slo) L . hw eaiv i. ps.f p.a ii . E= t9n ns: J + 2(4 + g ) OUTER, P - tsc,in it, A,azaa.26.3.X5.cce da 5.co25 in. = 19. 0l1 hn' -
.? . 3.1 # is1(I,2.5bl't2I.cm (e((in,fr1)/(vt, oil) 61 = 1,4 o tn 1,14 1 (,043)
,185 9*
t w . we la ft
- R1i( t'C G ,,,
40 04f8 vv84 fibeM9 Wet PO.48 Stille m..tC4es Unhu sef( ca. e e. eart ia. a e + e n n. 4 en
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION s
,i,6s *os
-' R. V. Head lift, Rio 10 os 33
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.o cm ~o PTNP.188 CHE PI N to BENDrN6 STRES5(2) l M; E(I a4 3 + 4 .0)
.q.ns.t .
2 va%s (.,
- d /2.
[d a S h a +3 + $ 1Nh) r 16P(3aph J )/(wa') ite(Yc.usM)h.mu> u nl.jTl'l (. c f M t) (
= t o , fc 47 PLI N AcAmb enom .
EMEDTMb M4 JCCNTN6,
$1D %d , A MesniNts u m op I4 M Mte?. CttrQN , hf44.teD'J3 m m n
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE
'U/ R. V. Head Lift Rig 1l 0, 33
- P R OJ E CT AUTMOR DATE CH n'O. a v j DATE CM n'O. S Y DATE PSE /PNJ- $ fiM.' ~
I /D 1.td. OMM S.O. CALC.NO. G) p LE NO. GROUP PTNP-188 CHE ll S U P PO RT Luc, ASTM A-615 ca, lo W 4.T Fv= 115,000 lb. F = lib,TTT lb. , q,o .,
- 5. 01 o d 7.03 R -
6.5 R t- - 1
' Fa = 5%25lb. I i
\ '
>..a 0 : G.00 ;
.ONSX93*1 li l
Tension ett Pin Hole l f t.
- f At= ( L 3. 00 - S. 0 2.) 9 -
1 ( T)( C'l5/ = 61.CllbIn - A+ Ft = nb;T77 -.197 6 PSI 31.ilb S hear csi . fin Hole F3: 2 - i1 A; f N = 3916 P 5I ) A = y(b5-1.51)(4) - 2 (il' .045b l 1/tv 3 t. 'l l fo A v = 15. 9 5 ~7 I n* r% ( ,,y, ,,y, AvTmom OATE CunD.sv OATE CMn0.sv OATE
'w NO. DATE WESTINGMOUSE FORM 852130 b 9
,w- ,m.- g- - - . . _ -m-.- -- >-e- - _ - - - - - , - -- ._;
. . . ~. . - .
a..... . . . thng i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION O rirts R. V. Head Lift Rio a.as 21 or 33 h '
.,4 Auf OR OATE C-.'O. 8 v TE c .o.av DATE 0- w , 8 A L E v PROJECT 5
PSE/PNJ 5 0 $t5n m' 1/73 omove s.o. c'Acc. No. gg grus No. CHE PTNP-188
~
Bencing a t 5.of hole The bearing. st 0 eGS is the same .o e the inner bearing s tress on the. citvis pin O. S c. = (1 6, $ tti / (9.S 6 o = 6 4 8 7 PSE 4 w i l l l O .... NO. DATE WESTING OUSE FORM 882130 . 4
e v WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l l PAGE R. V. Head Lift Rig 77, naonCr Aur-ca oAra CMm.o. s v On 33 Are Cm o. a v oars 50. PSE/PNJ kf,P.aA%: I / 73 A w, 4 te - - e C'A LC. NO. G)- (/LE NO. group _ PTNP-188 CHE 11 LING GIRDER ASTM A-175 ca. C. a
, ; Fu = 53,625 lb,
- I T.2 5 -
3.565 : lus%
.50 .
y_h I I - [30 gg a a a. n.%t
* +_ 2 n.us 35.us A
( ) t- ~ i I t, [ ,
- l. i>d ;
R = 91.115 TC05iOri f ret
- T Len t.% 3RD E DITION tt ( A-tV B-td Pag e 176 ) C.ec 11 ,
T* ( T.sb 5 t n.%%)(.55,fo25) T: ),911 T31 lb - in . 3 FTOR = 1. m m = 116 't 9 5 I. l } tU ,5)b 5.335 .s YIf.15 .50) REV. R E V. AUTHOR OATE CM K'D. a v OATE CM K'O. 8 v OATE NO. DATE WESTINCHOUSE FORM $52130
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3 4 L.
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mu R. V. Head Lift Rig 74 On 33 i PROJECT AUTHOR DATE CM K'O. 8 v p ATE CM K-Q. S V QATE I PSE/PNJ M.ipkd l@ L,, W. MM_d i S O. CALC.NO. yp LE No. G R O UP PTNP-188 CHE sh enc , s %2s :
.ev = En = s u,, e - =
A (3s.gssx it.2s) -(59.s35)( rz.259 55.tts j Sv: loof PSI l Tota) Sheqe : fToR + V y n 6141003 Toint Shev = 311 o PSI l
*= ~
O seaara3 stress t. ecee.isr>cese9 , h m sx = .t_ w R _L _. .L 6etween Loads w/ : . . 1 s e l; M max = .L ( 53 625)(3 t. Ils) ! I __ _L ) i sin e &> l
- 2. ,
e = 60 G = 1.0 9 1 b 1. J_ = t. t s 9 _L: . 355 Rad,
)
sine e Meu : ( s%2.sM 41. I 2.s-)(l.154 .155)
- M ma X 911919 lb -in.
- M mq x-:
_L
- 2. W R e ( _L __ / Cot eh ) ai cach Icod '
t D e= bo , e = i.o rr R a d , _L- = .3 5 s R a d . (J 3 AUTHOR QATE CM K'O. s v DATE CM K'O. 5 Y OATE R E V. REV. NO. DATE WSSTINGMOUSE FORM SS2130 , P
"!V WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l I TITLE PAGE ;_ R. V. Head lift Rig 15 Os 33 P ROJE C T AUTHOR QATE CHK'O. s v OATE CH K'O. S v QATE s O.
PSE/PNJ 6[.iMvo (/E e),2,/, CAcc. ~O. tE ~O. - J7&4 4 e l caOL-PTNP-188 CHE CO $ 9 = .5 T7 M mq( _L ( 53 bls X9 I,1 15 X . 'IS S .577 ) 2
) - M ma x = - n.3 56 3 l b - i n . ; 2. =
hih} - khl - (3 5.%5X W.2SN - (39.%5)(n .159 11(h,11) (6 X 1T.25) l ,
- hi q 2: 35-) in 3
.':.l l 1 I fe= M - v_ = e3sbA -
= 157 7 psr es b' i 2 357 I
l
.c ,
Maximum Tensile stress i h' - f max : EA 4 EB.
- _}. lf V P-J[(1 1
L'. f mqr : i s r1 4 (15nji 9 (3n of 3^ 1 (1/ E mq x =- n.33 5 + ./ l b13 I 41 + io b919 0 0 Pm a x = 1113.5 t 35 l ~7 rmqx= 9FII PSI ( ) REV. R E V. AUTHOR DATE CM K'O. SV OATE CMK'O. B y DATE NO. DATE
- WESTINGHOUSE FORM 552130 h ,
1
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f i /' WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION v) .- TIT LE , PAGE i R. V. Head Lift Rig AUTHOR OATE CH K'O. By CH K'O. S Y
% 0, 33 DATE PROJECT PSE/PNJ h.6h'U# l/G S w , 8 d'[ ATE GROUP S.O. CALC.N . / LE NO.
I PTNP-188 CHE W E LD O F S U P PORT Luc, To EtNG G lR0 E R. I i n.15 --- l t h. Nu /asy ^ N - Fn = 5%25 @. a l g.sks T z/
\
h n.15 g.56 s l
\ \ \\\ \\ \\ \\\\ jb
" I s s
- A i k
s ( v. ': O Mit ; q t . D \. N 35 435 V 35.us ! 7$ \ O A f 8 S - 4 , t E tf.'. Shigle.y's hec.hanical Enyncering Design 3 LD Edition ;
--- d .
i Y l G a b From Table 1-1 - ! j= b* . = 1 s. 4M* = Pi.19 9 in. 1btd 2 (3s,935) t 17,15 I = .d. = 112.5' = 1. l.15 n , (') v 1 1 l MEV. R E v. AUTHOR OATE CMK'O. S Y DATE CHK'O.SY DATE NO. DATE WESTINGHOUSE PORM SS2130 N- '
r-WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R. V. Head Lift Rig 2 '7 Os 33 PROJE CT AUTMOR DATE CMK j ATE CM K'O. 8 v OATE PSE/PNJ Nf.Orluel J/93 s yu). 0 ,"D. 42 LM S .O . - CALC.No. Q[ pE No. GROUP
.PTNP-188 CHE M = (Fn)(I4.Mi + 7.5 (,5)
M = (53 615X 11. T li ) ' 11U 4 00 lb.-in. 7= DP + b b d * + A3 __ bN n 1b&d b = 3 5, 4 35 , d = n .25 " Ju : 7(E9359 4 L ( 35 't TC( h.159 + nad _ 2s 9Ts"
! 'l 265.H5hird Iv = 35361- n sql = 11470 in' l L -
J = C .707 w Jul 1 W: . 3 f f L L e-t weld J= .7o7 L.3Of M 47o h. J= 9 3%7 in" t
- Aw= 7 07 w ('2b + d)
Aw = (.-) 07)(,3O[1 GS.935) t 11,15] 2. = 4 7.35 ini t'x = b S A t,7 5 = 1133 PSI Aw ' 47.35 W. = 5 c.cc = 106 P 51 t'y = A w 47.35 i > R E Y. R E V. AUTHOR OATE CMK'O. SY DATE CMK'O. S V OATE i NO DATE WESTINGHOUSE FORM 552130 , i l 1 m
i p WESTINGHOUSE NUCLEAR TECHf10 LOGY DIVISION V ! TITLE ' AGE R. V. Head lift Rig AUTHOR DATE CH K'O.87 ATE CH K'O. S T 17 OP 33 P R OJ E C T OATE PSE/PNJ Mfikku (/73 (b, uA 8A !Y 1 JGROUP 5.0. CA LC. Nd. Of $E NO. PTNP-188 CHE w = 5000 ( downwed loo d ') ty = ELo = f i m 400 T( 7. t,2 sl = t ils P SI J 93% 7 t'x * $ = lin3 4 00)l l4.7 49) = 1757 PSI J i 3 T.7
) 4= = tx ..
O
'J f s
'l Re.Sultant stress in Weld t* /Tyl t t{ -
T= ) 0 obt iluf + (1133+ itsf . t- 3133 P 5I a
. R E V. R E V. AwTMOR OATE CH K'O. 3 Y OATE CH K'O. 8 Y CATE NO. DATE WESTINOMOUSE FORM 882130 u_ .
T n- - WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i I TITLE pact R. V. Head lift Rig li or 33
,RoncT aur~oa o4Te c- o. v cm.c o. .v o,T.
50. PSE/PNJ 6.C.i M ' lN3 CALC NO. Ug buA 8/AgNff are MLE NC. GRoVP PTNP-188 CHE g3 LEG ASTM A -56 Tens lon in Leg Tubing Pt= F At For 1r" x 6" / .5o" wall Tubing 3 At = 11,3 in' ( A I sc ) fe = Lis onn J 9bb4 PSI kN R E V. R E V. AUTMon CATE W D. 8 Y M NED M NO, DATE WesTINoHousE FORM 552130
- 2 i U
JLm
? 4 i
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I 'V , TITLE aAcE l R. V. Head Lift Rio 30 On 33 PROJE C T AUTHOH DATE CMK'O. s Y ATE CMK'O. S v OATE S 0. PSE/PNJ h. b M d . l/Th fl . td. $ h4 --R CALC.NO. GQ $E NO GROUP PTNP-188 CHE i A - 5.l5 C,fl. l o gy C LEvts P L ATE a iT
'[j_ lI 9- r<:m :
T*
; I a
,7-
/ .'c 'T - a l ll \\
l I n.00 b.00 n.00 i i, - - l ii !
- i lh , , -11 ,,
l - p , Q
; 7.00 :
M2.25( WHusj-- t W ELD 0F L LB/ t s ?L RTE To 5.EG, .; Length oV Available we L4 Aq = 9 (11) + 9(Lis .'135) t 1 ( b ) = 6'). 7 b Fw: _E._ = t i s . 0 00 = 17 t o ib lin 0q bi.16 Sw: fw = nin : 5 bl5 PSI . l.1OT)(.13) @ 07)(.4 3)
~'
(v) ngy, n g y, AUTHOR OATE CHK'O. S Y DATE CH K*O. 8 Y DATE NO. DATE wSSTINGHOUSE FORM 952130
v WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R. V. Head Lift Rig '{I On 33 P ROJECT AUTHOR OATk CMK0.av OATE C M E ' O. S v OATE 50. PSE/PNJ 9.R Jb'. CALC ND. #4 I /T3 & w. Mld GROUP FGE NO. PTNP-188 CHE a F T.gl - :
=s tub -4.x -
j
- q. --
-)
! r j- - - ~
hu h - l 3.93'15 9 Pin _31519 L / ,,, l 6.o R / . os if R -. _ _. 9 - I . I l *
~
I Te nsio n qt Pin hie ' Pt=_E 3 Ap (( 11- 3.9 51.Mus) - HM(.otfh= %.19 u.2 A6 ft : u 5 or c__Q. = 311% PSI 36.li Shear a t Pin liole i l P v = _E 3 6=(I b - 1.3%X2.25) - M.c#h = 1T 09 In : 1Av Pv = l_l 5 , 0 0 0-- = 3177 PSI ! 2 ('lt. 01) l I The bevin9 $nkss is ihe sam eas the cuter hearing stress c.nibe 5.9 M 5' P mOS fc.: 7307 P5I R E V. RE V. AUTHOR DATE CHK'O.SY DATE CHK'O. S Y DATE
. NO. DATE
.h WESTINGHOUSE FORM 552130
~
a'% o
T ! WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i TITLE PAGE ' R. V. Head Lift Rig 37_ os 33 i PROJECT AUTHOR DATE CHK'O. S Y DATE g) O A,T E C M K'O. S Y s O. PSE/PNJ hf 3M'.(y l /D CALC so. (l. (t). R'
~
oaOuP pE ~O. PTNP-188 CHE 3.9 395'& PIN mru asm e39 ads.s E o f, - P/2. A, ' ^ P= t i s, c oa Ar Trd%
% .T. T ._ g A,= Tch.9345)%
A " Av= n tst in t a f, =. ( \ \ 5,0c0) /(2.* n.153 )
- t. ;
-. , I
" l f, - ma est
.e % %e
- (v, P 6. .cun3 on asadl ,th. y BE ARING STRESS j d = diam.Ese of pin,in.
8=len$th of bearing surface. -fc = P/Av of c. ate body sn. P = .t is,cco a - 14p% of buriq suc h . I.NNER . ens sla c# Owk, bedpis. Av - a .9 - (3.933sX 9.0o ) i g ~= g ap be.bn harth3 = ( 15 7 3% )ins surfeco,ik Sc. = ( l15,000)/(15 137') L woi acs i.mp of [c =
~
pik pA 13 O ~7 pu-
! + 2(a +9 ) .
! OUTER l P = 1l5,000 lb. A,- z ad= 2( us )(3.9mc i d. 3.9395 in. = ( 1e. 93 6 )ins l .P =. 4. e en m . A ( = ( 115,000)/( 16.444 ) a= 2. o 9 iw 2.25 - M o D O e- .us h.u + 2I.00 AUTHOR
-O /1.
t= ces3 es=. R E V. R E V. CATE CM K'O. S V QATE CH K"D. S Y DATE NO. DATE WSSTINGHOUSE FOmM SS2130 ,
-_.___,._._._-,,_.__.___,...___..,......,_,.._-._,.._..~.m
't WEi(INGHOUSE NUCLEAR TECHNOLOGY DIVISION t
TITLE PAGE i R. V. Head Lift Rig i' P ROJE CT AUTHOR CATE CM K'O. S V 33 On ATE CM K'O. S v ' ~ 33 j CATE s.O. PSE/PNJ 07.efa2du.uz 1/73 CA LC. ~O. vu
- 4. w. RW ptE NO. GRou, PTNP-188 CHE ;
Pr N 15 BENDEN6 STREW 2) M;l(I.a+.3+4.J)
.fg = Mc /r 1 = y d%H '
t =- d /2. a+ { } [b-lGP = { ('ha4g$+ i + t 3 )Muda)$ d h ras)
% u,n V 4.usi)/uud Eb= IISj oce ( . t Mo3) tb=IT,TO 951 -4 l
l N ADAPTED PROM FRTENI% AND JOfNIN 6, MD Ed , A RkSthNG. hW% OF MMcNT. ettrew , BNicu puscwm l l PME19 gg g g y, AUTMOR OATE CH K'O. sv OATE CHK'O. 8 v OATE NO. DATE
., WESTINGHOUSE FORM 552130 .,n.
e' . h
v l I APPENDIX B DETAILED STRESS ANALYSIS - REACTOR VE3SEL INTERNALS LIFT RIG, LCAD CELL AND LINKAGE This appendix provides the detailed stress analysis for the Salem reactor vessel internals lift rig ,1oad cell and linkage, in accordance with the requirements of ANSI N14.6. Acceptance criteria used in evaluating the calculated stresses are based on the material properties given in section 4. l I 4 ~ i i t i > 1 6116B:1/021083 L__g L
v~ '
-_- :.s . - . . . - .
? l l H l SKE,TCH
,,, ins = oust SHEET roeu 54202 I
*=ossct I' ,
l .... .... I PTNP-188 Salem Units I and II 1 a 67 I l m ,.: catcutario~s ... R.V. Internals Lift Rio PDC- ,i J. S. Urban {, . Richar fg k((p[E[fy ,' p...es: . o assu'tsi (y y
- 1. f ;his analysis is to detemine the acceptability of this 'l The rig topurpose the requ 4 jirements of ANSI N14.6.
[ i 1: l 2. The results show that all stresses are within the allowable stresses. l l t o$y l O peers seioma6
, [ JOSEPH W. RICHARD [
, ..... u no.co71st tV ,
+M *g <
1
'1 Mkf< 4 O .V' .
- Original Issue J. Urban REV151ON NO. DATE DESCRIPT1ON BY l
*isust ino espoets. Latttes oa usuceanoa !
i l l
$ i k . . _
v
. _ . . __ . . . ~ . _ . ., .. ..
9 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION [O TITLE PAGE R. V. Internals Lift _ Rig 7 0,67 PROJEC1 AU ~O DATE CM K'D. S V . DATE CM K"D. S Y DATE PSE/PNJ b 2/g3 jypj g g S.O. C C'. N O. FI FJO .' GROUP WHERE PSE Ah3 PNJ RIGS DIFFER,THE PSE ITEMS ARE DISTINGUISHED BY AN "A" SUFFIX.THE PNJ ITEMS BY A ~B" SUFFIX 71/2 DIA HOOK PIN @ SIDE PLATE @ h UPPER ADAPTOR ADAPTOR PIN @ h LOADCELL g BOTTOM ADAPTOR @ A&B h TOP LUG 6"DIA REMOVABLE PIN @ A&B h 4"DIA CLEVIS PIN SUPPORTPLATE h A&B SUPPORT PIPE h A&B , A&B h SIDE LUG - SLING LEG h A&B A&B h UPPER CLEVIS ['N A&B h LOWER CLEVIS 4" DIA CLEVIS @ \, % BOLT -
,o, c 0L END PLATE @
h SPREADERS
' ANNELS h EMBLY , ,
h BACKING [ gi g 238 f , 238 1 M8 2A PNJ
@ B LOAD NUT PSE . ., 25A hB TUBE HOUSING h hB GUIDESLEEVE ~
, ?
l .
\
h BRACE PLATE A&B h LEG SUPPORT BLOCK r ADAPTOR hA RING GIRDER i - OUTER TUBE @ A GUIDE SLEEVE h A / ENGACING SCREW h A&B
\
AUTHOR OATE CM K'D. S Y DATE CH K*D. 8 Y DATE REV. R E Y. NO. DATE WESTINGHOUSE PORM 552130
w WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i l TITLE PAGE R. V. Internals Lift Rig P ROJE C1 AUTH 3 ., g 7 A OATE CH K'O. S Y DATE CM E'O. S Y CATE PSE/PNJ h 4)?pt 9.g gu y s O. put no. oROUP p_ Cgc. MO. _ DEST $N WETIOH IS-
~ WCI6HT OF LOWtR INTtR N ALS = 26.C OOOE i
~ENTtRM ALS LIFTINb RIG w t.I6HT- 14,500 #
C.ONTIN G ENCIE.h 10,000 d 2.84,500 *
'THE- Drr_brGN b 16 IGHT- FOF I,.n.Mb
~1 ranoveH Co wItt GE 32.0,000 lb As. r%Y A R t_ AL50 Usto to MONITOR.
THE HE.AD LIP T5 P.I Cs LIFT NOMENC_LNruPs E . , A= awa, e Tha- worwendolua oC CS C1 \> Lt. M C.Cdt- t tkrmm Or VaftMb [ - of flo,ua -lo ex-he.ma. Mcyi dcGid ok i ro he63nch i d = chaMr 3 A. two.e,. h M as s -7pM ( > be.rcAsq s%, pi -\c -W., oJOove. hit, Wkts 4, 3= dlLT*15 "Sk%% , p $ b O SC) A MY\\ Oh 8+ - ha. shn , ps i t.h. -ke rn3 am cLeCl4 l . -9 y - skaar sb, vai uaN -hb-. co 0<.o \< d o k
*- %o M O lhadlb ,lh $W WGLk.
I K= ou+ ~ Gra ~.r u b s ?E. 91,9518 [. = padar 3 iem d thhA.mg'*b*318 *l I M Yviomaw3, th-Ib l 9: g wcro ! Mrw.i k l , T= +emA ix W% = 118,%
- l W = cbfw ump (A 6hh S k Mghg k Web RE V. R E V.
AUTMOR DATE CHK'O. S Y DATE CH K'O. SY DATE a NO. DATE l F#ESTINGMOUSE FORM 852130 -
I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . I TITLE
- PAGE ;
R. V. Internals Lift Rig aq o, 4 7 PROJECT AUTH DATE CH K'O. sy OATE C M K' O. S Y DATE d R(, 4 g pmg M
,R f PSE/PNJ h, S.O. C . N O. f)LE NO. group PTNP-188 CHE I
I LOAD CELL LINK AGE WEMM) hw l [- F HOOK spActa 1 em h_M-J x
"L
~
Hook PIN 1 Ec r - ') i SIDE PLATE. 2 ; O ? h a _ b__ ACAPTOR PIN 3 .
" ' A -UPPER ADAPTOR 4 LOAD CELL 5
.g r g _m -rom e
+ g -
W V~ O AUTHOR OATE CMK"D. e v OATE CHK'O. S Y DATE i R E V. REV. I NO. DATE WESTINOMOUSE FORM B42130 a i
7 .
.., . - ~ ~ ~
h l WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l I l TITLE R. V. Internals Lift Rig ' 5-PSE/PNJ
^"khg gi$(('""(j' f g{ * * * ' ' ' ^
-' PTNP-188 Y"' 'D ' " ' "" "'
CHE W OOK PIN 1 SHEAPs STRESS mei.- AsTn x434 cau ao f, , P/2 A, i Arsr 4 340 STEE L P=W
. As- Trd % !
7'7 ._
% Av = Tr M.4n )% ;
=, , Av = 44.os4 in'
]
d T- ] [v =( W ) 5 44.0PA
~
t ;
= w(o.ous42) :
m, 1 I fy - S co 2 9 esz ( ) % % . i P 6. ach on3 ass.-bt yilk. BE ARING STRES5 , d = diam.tse of p in, in. I 8 len$th of bearsg surfem .ft = P/Av l of c.cn4.tr body ,i- P=w '
=
a = 1.wpw of be.nq surk T.N N E R . ene sJde. of coke bedpih. Av = ci .9 - D.49t X a23 ) l g = gap bekwcan bearin3 ' s ( Gl. @ )(n* surfem,in.- S, - ( 'w )/(Gt.%) L8 wai acs i.5 xt of = w (o.ou.2is pik s . &= 5190 n= J + 2(a y ) - ! OUTER l P- W 16. 220,000< A,- 2 ad 2( i.% )(9.492J d ,.sm/h.m .iw. = ( 29. 25s ),ns 3 - 8.zs a - 2.Ov i.% s x (=( w(wo.o 34)/(29.%
=
or) 9 .) l 4 i s o.oS x 'fc. = l O dC, nc ! L= 13.99/11.0 2 rs REV. REV. AUTMGM OATE CH K'D. 8 Y DATE CH K'O. 8 V OATE NO- CATE WESTINGHOUSE PORM E52130 ' i d
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLg
- AGE P. V. Internals Lift Rig b Or 57 PROJECT AUTMGR DATE CMK'O. av OATE CMCO.av OATE PSE/PNJ hhw%it/gt 4ggM s.O. pE ~O. caQue p ,
C9. ~O. CHE M15cELLANEOuh C.Att.utATIONS
, BEN DT.NG STRESS, 2 $ = L- J - 2 a - 2 s.pua.r.i Atm, f h=(P/2 )( % +9 + #4[d3cy n. 99- ( B.n )-2(i.w) - a(.u)
* = o.os b ( w )/z-(l&/2+o.08
+ 8 23 /4 %32/(ir('1M2)$
= w (os1%)
E- I2,0 9 1 m . V k I l
- touart= cenxvtocM P(t})
- l. O l
I
, V AUTHOR OATE CME *O. S v CATE CHK*0. 8 7 OATE MEV. R E V.
NO. DATE WESTINGHOUSE PORM 582130
I t :l o WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I
*j -
i I ' ' ,,gg R. V. Internals Lift Rig
'" 7 AUTHOR DATE CM K'O. B Y 7 On (> 7
., f 9,A T E CM K'O. S V QATE PSE/PNJ d4 d i'f, 'pty g M IDA CAL 4.NO. '
gbE No. GROUP
* ' PTNP-188 -
CHE
- B E N t." N b STRP.W FOR MU. A Oc MVATT ON -
A%UMINCs FORCEE IN touh?. LUG TO ALT g 7 9 e. LyG (.,E NTE.P& AND "rHE F ORLE, n iHt.
~
cmng s.u c. To ALT AT wo Pt.Ach % WM NTO rHE LOG : h '+ 2 " l
&s y% k4 me '
3 . ,, m., .< l L. k\N' MY /'9 hMY, bearav-' wr fous f l a= l d
$4 o f one M s ,
of doubk.-igb ea4 [ 2 h h 1 "5 " [' M \\ % surb. ..
- 3. w 3m c we,s iv) hh j surba. of cenke I
- p. u a.3 on e.1a -
% Y d- cuiTv.br J pm t-M ah4.%d 3 4 ti-"% '*
Es - Mc .
%1 I.
- , - c. . d4.
.7.mayg
*I-P I"
_ ,,m , = , .(b- M4 /13
- - L
- et) 4 g,.@(by4)ya N .B. ~ rk'A~ wr' a m * = ~'** ' '
mHT moman+ abe occuri uks Od. *
, _ foru.s as anos,ed CM/*
--g diMr~b. k l otrow e a. lug
( ) - - ---
- . Mr,k = k (k *3 * ~
agv AUTHOR R E V. DATE CMK'O. g y QATE CH K'O. g y OATE
"_O DATE WEETtNCHOVSE FORM 552130 D
I r WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION O, L
. TITLE PAGE
- I R. V. Internals Lift Rig 7 OP 67 !
PROJECT AUTHOR QATE CH K*D. 8 Y ATk CH sC D. S Y DATE ( PSE/PNJ M& Wgt p y py 3 i S.O. CA @ NO. # LE NO. GROUP ! PTNP-188 CHE i i SIDE. PLATE { TEN s. ION G. set A-A
-fi = P/ As !
P = w/2. t M AT'L ASTM- ASIS GR.90 At= 04.*-7 su) t.% ; QUtNCHLD At10 "T1.MPt. RED . = l 4. 597 O i
, ft = W ( O.034 3) !
R 7.1523
# 4 W/ l ft- 'Q39(oP1T .
l
,A. A, j
, BE A R E.MG C SEC. G -E wt mun.a sTam t sic a-a j, 15 THE S Amt. At TH E ourt. A I
- 6. - ;
at Aa:Nb i nuu CN W. AMCA ! 4.04 PIN I 2.c 4 a fe, = W ( 0.04 2.59 ) ! l.9 (= i TNICM ' r* PSI.
~ ,
I o ! O+/n - 22.% SHEAR TlAR.-O D t E-E i G" w/z gp ; yf G , . . eenww wa un. ,,. .
, ,,. m _
~m,m _ ,, m . s , . .. .
n.n ' fy= P/2Av l P = W / 2. l W 32.0,000
- A
. C ., 5.%- ' is.cs- u.c nh) i.* .
O. c. wk.o i H 3 Be26. ) a3a ! REv, R E v. AUTHOR CATE CH K'O. S Y CATE CH K'O. S Y OATE ! NO. DATE WESTINGHOUSE FORM 803130 r e , - - , - - - .,-----,---+-e-. -
^ WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION ( l TiTi.E '
, ace R. V. Internals Lift Rig PROJECT DATE g ,, 4 7 [
A U T HgR ATE CHK'O. a v OA TE 5 O. PSE/PNJ bgj&Wgt CHK'O.av[ CA uc. ~O. ag M ptE ~O. caOve ADAPTOR PIN v z S H E AR, STRESS ' MAft.: ALTM ^434 c.t.Au tio f, - P / 2. A , AIkI 4 340 STEEL , pW
' - k om A, .Wd%
% ~ $ e P
4 ( . p.(5,992 )/4 l a Av = 28.199 i n'- t d fv s.( W ) /7 *28.199')
-- 43 = W ( 0.ot 9 9 3)
-e--, 1 "l
__m fv = 5 6 9 'l esz. .
.m . =, wt- 1 I ) 5 5 P= b .cunprass.aiy,ii sa Agrnc, srats3 l d = diam.hr of p cn, in , i 9 lenSth of bearA 3 surk .ft = P/A, :
of e.=n4.sr boa v in. P=w a = 1.w3 w of b..riq suc k TNNER . en side of ook, bedpiA. Av = a .9 - (s.su x s.u ) , 9 = g ap bdwcan bearih3 = ( 49.314 lins ! f sur h ,ie. -
&.( w )/(4uie) '
l L woi aas i.mp f = w ( o.ozosa) pii , ,e fc- M90 nz. J + 2(a +3 ) OUTER . l P- W 16.= 220,000
- A, = z ad 2( i.sc Xs.992.H l d =4. coo //sm2. in. = ( 1 3.4 3 )in' :
J = 8.27//8.2 3 th. k=( W )/(7.3.49 ) a = 2. cot.o A ik = W( O.04 2 59) < s o os s fc. = 13Co22.ec. ! I l L= nm//nns iw l REV. REV. AUTHOR DATE CHK'O 8V OATE CH K"O. 8 Y CATE t NO. DATE WESTINGHOUSE FORM 552130 il> - w . _ - . . ._
_ _ _ _ _ ._____._ _ _ _ _ _ _ _ . _ _ _ _ _ .__m.__.._______ _ _ [ i WESTINGHOUSE NUCLEAR TECHNOLOGY CIVISION l f TITLE PAGE - R. V. Internals Lift Rig g ,, g 7 i PROJECT AUTHOR OATE CH K'O. S y ATE CM K*Q. S V QATE S.O. PSE/PNJ hh4lMt CAL (jeO. FS.E q u) gML NI. NO. GROUP PTNP-188 CHE MthELLANECOS BEN DT.NCm STRES5* 2$ = L- J - 2(a) - 2. spuur hka*= fg(W2 )( % +g + J4)[p 2p i3.99- e.23 - 2.0.%) - 2 (.u) 3* O.08 !
- 6. ( W )/a*(14/0/2+o.ca i
+ .8.2% /4)*32/(1rkm)$
- wco.o?% o; :
E- R3,Caf(4 m. f i I O .
~
t ' l I l l I l l
- i o touArrow meexvto CM P(r7)
U R E v. mEv. AuTMOR QATE CH K'D. SY DATE CH K*O. S Y DATE NO. DATE , WSSTiteGMOUSE PORM 882130 i e
. . - - _ _ - . . - . . - . ...,__..--...m-- - - . ,-_<>r. - -
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l I TITLE Di R. V. Internals Lift Rig '"O
'/
PROJECT AUTH DATE CHn'O. av _ gi O, 67 g g ATE CMn'O. a v OATE 3.0. PSE/PNJ k \% ) y) Aska PTNP-188 Cw. ~0. pE aO. *ve CHE LOWER. ADAPTO R _ *dH AND UPPEP, ADAPTORs A ra Dww 108 0058 H01 AND HO2. ' 'N
- - b 1
M AT'L. ' Nrdr 434O BooY AREA cQuaNc.nto AND whFtRtc As 2 Ae + Tr(2ef/4 Tc"
'ftstD : \2o,000 N c.osx = A/s itutt.www. 135,cco PSr. -
6= i B2 -4 pq A = 'i a B" D wuA
..o A, 11 b2 - a' + nt(50 4 y s ;g co m . a/h At , ,tA Foc, Lowu, A DAPTOR a- su 3 b a 9.94
- m. g.Ag ~ u , , ..
- 4. 2 , . ..
- s. m.e.
if Bt o, 8 g iB A, 57.59 # b 3 c'.- ' ) .L in l FOR, UPPt.R AORPTCR
\.}}'g4 (anarte m w) a s 8.2 3 4,2se. s N- 2.s b = 9. H r.os W x = 3 4. \ l *
, 4.97
',, . b g* S I . k 3 th t
u-E (j ,, , l% i~
. .u t g
i . G.23 _A,o 9.23g(, 1 ; ,,, g
;) ,
I ( \ REv. I REV. AUTHOR DATE CHE'O. S Y DATE C HE'O. S v OATE I NO. DATE elf WESTlh'JHOUSE PORM 562130 ,
.s WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
(~ TITLE 'AoE R. V. Internals Lift Rig n o, ff PROJECT AUTMo DATE CH K'D. e v ATE CM s. D. e v QATE PSE/PNJ Mi%s (j's4.m g 4 g1 omova
..o.
p p, Cy. ~o. ~o. LOWEA ADAProR 4/6 A' * *= G.023(c.. n ) AND UPPER ADAPTOR = 37.5 2. mt Mc4, W ( O.02 44 E) w = 32.0,000 6' TENSILE. STRESS e, A-A u.. @ 52 8 pm IA =i Al.- Aw umn : Ag = 71. I 3 - G.023 (8.23) TENutz srn,t.w e a-a t=w A = i 59.59- 4.o23(e.25)
..Si = P/As f,- P/A,.
P- W A i. A,- we'/4 d% ,= 4.3\
!] 4o,,,..= W (0.0 4 G 3 8) 91.is-r(u0% so.s4 Aiom Apsa=59.53 Tt(4.3i)'A= 43.00 L,,. - N ,9 Y2 Pc P=w fim. = v (0.04 9 B37 k,.. = W (O.O l %B9)
A L .. - 5'94692 R,.. 5GGQ ps' . . . - . l, f% w (o 023%) ~! BEA RING 5TREis G. A-A ( tota = _Q443 pg R= P/Ac ' P= W A.,,,,, = G.o23 ( 9.21') -
- 4 9. s c w . .
kom.,= W (0.02 d k u,,g a = [M Y b Y P 2 m t v, M t v, AUTHom DATE CM E'O. ev OATS CMCO.d' OATS NO. DATE WESTINOMOWSE FORM 883130 . c.
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l I TIT L E
' AGE R. V. Internals Lift Rig g ,, 4 7 enosacT Avr o cars ca o.ev en o. ev car.
PSE/PNJ ), d, ff. ( g g j g,J g arsJg s o. cag no. p p_ pa ~o. caova Lowp. WProR 4/g 8v .- P/2A, AND UPPER, ADAPTON c.cnamnow, str hv or. Tna AntA on Tut utcos sacrzoN Or.RtcTW AcoVF. THt. AAIL,
'iH R.E A D SHEAR ra vm t.om moarron A, s (s.98. LonA)(G.23 )
[v
- P[kv = 16. 4 94 M kv=71D ,=P/2. e o s vai. u reta. e o w ro m m .
Fluh thaans wA%esceu sta M.r.1 LugDTH CP TH A MacHpito 25tD, w. a , eos a Q- BN 2& ' uns Act rs 2, ( 4.S'l* -@.2'./1N* Dem 4.16BB = 5.5 9 4 in . 7en zs j =. 3.95 . 3 9 = 3.5Co in usiusTwi. acts $=0.023, Av = t'(4.lGB6)3.56/2. so av Twa. T*tt.AN m se. 2 3.si mt
- 2. ( 4.9e-(s.ewz1)b p.so7s P- W znsmo og e. a s i,.
f, w(o.o4290) A,, . b.90'T )( s.%- 4.on/d
~
I', s (3_Q2R m pw Rom. = W/(2+ 23.49) SHE AB. TE AR-OUT .fvom, . W ( O.02130) 4 m. =, . - %% Pg n (m., - w/(2, is.4%)
-g- 4 i.~sa W ( O.02r? O,4) -
E A GS3 m. 1 l m g y, ng y, AufM04 oAft cHn'o. s v oaf 8 cMa'o. s v oAft l
.g NO. DATs ? wastiNoHouse roau sestao .
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE ' AGE R. V. Internals Lift Rig ; q ,, (,7 P R OJ4 C T AwfMcH DATS cnn'O, av CMn'o. e v OAft E/ PSE/PNJ Q g & Pic A,pj pgl bQATE
- a. cv. ~o. ge68 mo. '
oaowe p p, LO AD C,E LL '"" "' ^~^ 5 Q = P/As ! MAT'L: tr7-4 gg 3/3 p=w (.oM O H 10 0* FRom Mhad HANonocit rea %c 5 , BSEdi P B-G ETRt:.h Ant A u 13.34 81 r At. Qw & = w / n.n ea l 6 W (o.o74B o) O . s . 23.92c esz M ! THRE AD SHEAR i Tkt TMittAD tetAnrNw LT2ths u THt,thMtAlFom.THE . AQAPTQRt tA tA [v = w ( O.0 4?.90) ! V g EN d-9N-2A' ! w ngoco
- O
%/
ng y, ag y, Awfmom oaf 8 CHn' D. 8 V OAft CH n 0. e
- QAft 40, 0478 WSSTiheHOUSS PORM 944130
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION I I TITLE PAGE R. V. Internals Lift Rig PROJECT R DATE CM K'O. a v 39 o, 47 3 ATE CM K'O. S V DATE PSE/PNJ AuhtHg112/St. Ogg Qd2 s.o. CyC:~o.~ caOva age so.
\N= 2 84 sOO4 i !
REMOVABLE PIN SHEAR STRESS r[ , R = (P/2)/AL A, = tr d274 m wr: i i 1. o *
= v (s.997 f/4 i N A.T't ASTM A434 CLb2 BD = 2.8, t 99 int A1sr. 4 s 4 o (P/2) = w/2. l fs. w/ (2 28.t%) >
- =
w ( . ot '7 731) ~ gp
; a= soc 4m
( l
=ra ea
.y
, BEARING STRESS m : O PIN TO BLOC.K A%f.MELY
& = (P/2)/Ac jP=w A = cit 3 (5.992)
^ = 19.9 8 e wsnm . P= w pmac.ss .c1 pJ g .". . "~ * - m q , g j(3 n,,g) ;
~
-*m & - w (..oz7 sis) l -
(c. 7s t3 =
% @ I PT,N TO A D APTO Ps
' ( l R- P/Au ' {
P/2 85. P= w ; TMT tip,"Othl A = dt=5.992(Co.13)=37.33#
.- M:R~ fc = w (.ozc 988) m es y 3.,,d i I, fc = '7 Co 2_ I m j 8 (GLALCLWEh AUTHOR QATE CM K'O. 8 Y DATE CM K'D. 8 Y OATE l REV. REv.
g', NO. DATE I WESTINOHouss FORM 552130 ,
I WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISICN TirtE - PAGE ! R. V. Internals Lift Rig (g ,, f 7 j PROJECT DATE CH K'O.SY / ATE CM et 'O. 8 v DATE
. PSE/PNJ j AUTMkR& 12g 4py g (
s.o. CQ. NO. GROUP PTNP-188 . N~ E NO. CHE f 4 REMOVABLE PIN 7 l it BENDING STRE% P= w ; a - 3. in ' J - c. 23 A - g: (6A05 - 4."23)/2 5 .005 5 cA. = 5 . % 1 A l r\ [b ' )( '3^ 4)T -
' W*($)*(3/2 +.osqs42V4)
- 32 hr/d 3 '
i
$ = 'W (, O'7 9M 5 ) rm g N l
I THE FORMULA FOR FIN BENCINL,
.5TRE%,OLED ON TMD., AND ALL wassQutNT PINS,IS DERIVED ON THE. POLLowING, PAGE. *
- PAst t7l -
O'Q/ m E V. REV. AUTHOR DATE CMK'O. SY DATE CH K*D. 8 V QATE NO. DATE WESTINGHOUSE PORM 882130 ..,
'T
.n- , . ..._--,,-------,m-- --n,,- . , _.
l l WESTINGHOUSE NUCLEAFs TECHNOLOGY DIVISION , I I I TITLE R. V. Internals Lift Rig PAGE J P R OJ E CT gr} o, f7 AUTHQR CATE C 4K*D. a v . CHK*D. s Y OATE s.o. PSE/PNJ fMA W CAty.r.o. gt 4, g pf d M DATE p.E Ho. caovP CHE CALC.ULATION OF c, s 6-b = Cfo# J TENSION T.N 5 LING LEG ELWS*) g e m a g n u g,- 1 ! umaPrn
,g /"A } rn. (oft %2 - tao 3g gu.)
A 'i
, j', , ---t
' LING LFG Q ,' l 7
, , I w/3 ci i i
r a s E ,,- i' . v 1 ,' " i v/=294;to4 - l M Pm .,Jy' t, W = wtzrowr op towgg gags. gag , gttt, g7, { l 'I*'**) ,e
-d- '
'T= rENEN .IM hIMb LEG, .
Y B(.. f. 3 ; K' CUTWARD FCRt E EwtrtTto , av we=ActR - l L = cowNWmo Fonu. tunTto
,i
; RY A LES = W/3
- Rre, q
'$ -l.an a. = kc, = N'S %
7; As Rrb Q, TO t0Mg PIM g s Sf fo3 C4, 3 D7.}}.
$ B. are s w uma azu q = lti.oct.c9 4 d= (A-B) - 72. G3 '
Tc.o: x = L =. W/3 T = (A181)W d
- DIFFlentLL TM t.uvATICN ABCvt T= 1 l R c)I(o o
;lr, HEAD OF gtmovAU,tg PIN AND LOWER PIN ( ENTE RLINEL Sih % u N l r = wa ice . es . n3- = .a w u l j b = cr cctur,c. T.w suv Airew -
.. K = (, ?_"I'ijw CT- Stf(CVAGLt. 9IN AND K= 7 9SL W VPPtit PI.N (FRO % ULour. Ah'Y) l I * ~7. 0 + 195 0 - 1. 0 - 9. 5 - n.n "
) y, M g y, g g y, AUTHQR OATE CHK'O. 8 Y DATE CHK'O. 0 V OATE I h NO. DATE I WESTINGHOUSE FORM $5213D e
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION f\ O TITLE PAGE R. V. Internals Lift Rig jg ,, g7 P ROJ E C'." R CATE CM K'D. S Y QATE CH K"D. S v OATE PSE/PNJ AUThHg d -lf t y pgd1 s.O. CgC. so. pE ao. oRove 1 6 4 BLOC,K ASEEMBl.Y I F5E I bicrw.c. thh page. lo identif) '
./,
Lh ter.ation of .%:.tian cvh
.M.,
,~-'s E NQ i'N[(,_ / \ .
h 1':: ;p I
$ \f)) ~' k e N - -M
' N..'l s
hA T OP Lu c, s REMOVAPifP:N A+- b 4A
@A ** I a n
.I
~-
W 9A i i 9 6+ 2 ' u+" '* h, j ( A noe tuc, ,,, .p. fff/p.; f?'/,/) uPeratthr g h -
\
s .
\.
u.rus Ltc, y l M/ .- .p1
- Y ~m AUTMCR Os TE CHK'D. S V DATE CH K'D. S Y DATE I REV. REV.
l NO. DATE l WESTINGHOUSE FORM 552130 l
~ * .....v . - ~ , -
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION f f TITLE PAGE R. V. Internals Lift Rig jg o, g7 A PROJECT AUTMo OATE CHK*O. 8 v CH K'O. S V OATE PSE/PNJ , 17(3 s.) ,ed )P MyIbATE s o. Cg no. n LE ~o. oRouP CHE
-Q = W ( 0.02B 19 )
TO P L. UG @A f+ = B020 9sr
,t h
--.uc 5W
,, _ _4??51 "-
E a
... _-e BEARING,G A-A 4 . _ _s A . _
; n-. _ _ _
..i Tne usuarus sratss n ,acsm c
- A5 "THE ourtG! EtARINu tiTREat Or1HE 1
8 fB i , ,
. n ,.
.samuute nw.@
i
+-ggg- "'2
( = W (.02'?8ts) I l MAT'L "
~ ~
fc_ - 9913 Pn i A STM A 515 g GR 70 (
"TENbrO4 0 wtLDeE-r:. f QuENLHED ( TEMPERED .W ] W= 2 s 4,500
- fg - (Ph.)/At - W/2A t 3
Ai li.99(3.m'p as.814
% f t= w-(o.ol390 a , fe = 3992- Psr. ,
SHEAR FOR TEAR-OUT I TEN SION e., A-'A S,,,(P4)/2 A, . W/4 Av
.[ 2 Av
- 3(itu.r,.ms) - 19.9% y, 4 = (P/2.)/At P=w
; & = W (o.o ?.819)
A = 3 ( ti.% - G. 028') , g, gg g g ,y
- t 9. 9 3 (8 i@
DATE CHK'O. S Y DATE CM %"O. a v OATE AUTMoA R E V. R E V. NO. DATE hh WESTINGMQUSE FORM 552130 a
-- 3 l
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R. V. Internals lift Rig D op 67 PROJECT DATE CH K'O. S Y j OATE CH K'O. 8 Y CATE PSE/PNJ AUTHh k g % g gMI s.o. C49:. no. pila no. omouP 10 A
***Sd'** I SUPPORT PLATE 4 TENSrON IN PLATE.
SUPPORT PIPE gg 4 P/At = W /At l At - tue M AT'L- n = t.co2 sis)w SUPPORT PIPE q= r71Q m , ASTM Aior. - l SUPPORT Pl. ATE. TENSION TN PT_PE i nsm asis ce P/A+= W /A O ""
,P s ww-m '
i .
- v/4 ( n.9 e- n.uM 7 et m ,.,, s .m.
= 89.94 9 i p % ,
W(0.0111BI) b 3181 a l l ma ; A
. I f
1 m.nl4 lLt.90k ; p lia 4 : 4
. n.91 I
l l
/)
L i m g V. REV. AUTHom DATE CH K'O. S Y DATE CH K'O. 8 Y DATE NO. DATE WESTINGHOUSE PORM 552130 0
-4
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l I
; TITLE PAGE 4 R. V. Internals lift Rig 3
' PROJECT AUTHOR DATE CHK'O. ey 11 on 67 TE CM K'D. e V OATE s.o.
PSE/PNJ
.'Q Cgs. No.
,fg %
i 3 y gM PimE so. caovP PTNP-188 CHE
, SIDE LUG ll 4 O = T/A = .418W/Ae Ag [s.941)- 4.o15] + ua 2.3. s i iwi MAT'L f+ = G.) (O.01'M32 )
ASTM A SIS GR '10 Q UENCHE0 ( 4= 5102. m. j TEM 9ERED
.e{
COMBINED ETRESS 1 Q WELD q i muon: 4 T a /.A, e . D 9 = .91lbw .in 39.*2.f/I1.3 4(3.90 { } OR ,. ,
= W( O.0 0530 9. )
o n swenn : -f, hu / Av. .
'lf.$
- 428W ce> 37.ll*/II.94(3.9B)
#;t
"" m [
4.o2 w b ntNorne fg Mc./I
=
~Tceso< 5A3][it.34/2 /).9s4li.d/a Pi
"~
o' tW \,m wwint D bhM2 gy
? ;;;- t6 = pilaw)(4.oisXr.sw)/su.n tom 4 7 i,_gg_.
t: 4.o29 ,pb ., g g,oi97j31) y
?:
i'.::
.W., s " ?#"a" - fp%(0.0(o fy-
- w(.oossow.orns) 9014 )_
- W: 29 4,e g. = W(.'ono19) ,
i TENSION G. mot.E. L =_. G55 4 52:,(
- m
' ..w( . u.noW)
I rat. AnA wnt c.owunv^ xw ]v. 19 9%d
=
EL Drd.N AS illt. M3u1Mu m i
- OUT ATHf.D FOR HORJ RONTAL FOE 11 3EbSDb
. I!(sessW Ih 7E'%t<%. h5 7HL' QML PINS 6
. TM Ntt, h MLiw * .02(o30W8H81 M
{ r r na v. mas. AuTMoa OATE CMn o. s v oars can o.sv OAT: No. oATE i (( wasTINcMouse ponu snaiso . ( . 1
_ . __ m . _ . . _ . _ _ . . _._-___..___...m...__ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _
=
l 4 ~
-s" ~ o"- s s ~ -" "c""
O '""'* s' " TIT LE PAGE ! R. V. Internals Lift Rig n o, f 7 l PROJECT AwTH m OATE CHK'O. a v OATE CH n'O. a v OA TE l i S 0, PSE/PNJ
. NO.
k lh j-4/ g ()LE NO. GROUP j i PTNP-188 CUL CHE ! i. l t OLEVIS PIN p4 j _. . . . . . I k e.iz ,,ea :l _ [ s n.
.m a \
. L Es wt : 40* 4.00o l Y
~ - '
MAT'L ASTM A434 c.i.Auso [ i
; AI.E.I A 34 O ETEEL p,h .
P :::" L %:.=r m
>>wi - i. .p-me .
MG c 3,500 - 4 Q N C.- 2 A s eru (=m sm 4 3,,, 3n natu $
= -
i WAq : N- \ W = 2. 8 4,500
- l 8=* % \ D c. tam i ,
SHEAR EMEM ! I
, row.s.i orn. fy = P/2Av l
. r z m a n m .s.s P= T .44W ;
Ar nd'/4 l , = Tr(3.m)Y4 l 12.s3 M i
- f, . 44sw/(2 n.ss) >
Ev = (. 01 %S)W - A 4 '7 4 5 m, l 1 h ! i QAIS CHE'O. S Y DAfg CH E'O. 0 7 QAfg { pgy, m g y, AUIMQA ao. oars wasTimonouse roam seasso j
. , - - . - , _ . _ - - . - _ . . . ~ . ~ . , , _ , - . . . . -_,.-_-_.,.._._.,r__,..., ,,...--,.p.~.%,-n-,-- -._ ,- ,_.,__.__.- , , _ -_-.
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l I TITLE R. V. Internals Lift Rig '^h'3 ,, g 7 3.o. PSE/PNJ "h"hnh (( fnu so,h cAspo. onove
'" ^"
p CLEVIS PIN Qg BEN DING ST Ae.n P = T = A % lBiW 8 = ).9s BEARING STREM J = 398 g = (H.c4-3.gs/2 = 0;c3 i PIN To CLEVIS d = 3.%9 { - (Ph.) /Av E=@.)(,*/+c3+4)h2 2 (P/2.) = T/2 = (.9tBw/z) a t s.sss(i.9e) 6 . sew /z(i.ss/t+.os 3 9a'4)- Av
- 32 /(rr , 2.sW) 9.91 0 -
E - W ( 0.oG"l33) { } ( .918w /(2 7.9i -
- 6. W (.o?.G42)) R= 9, l6I m 7
L= ' G5 ' 9 m . V '. I PT.N % SI b t. Lut. 4 - P/Av
, P=T 4.mo w Av = dts 3 994( 3 98) 1 = 16,8% ?
( .418W/lsB96 h.= w ( .o.aso) - b 99Bi a
~
t '
?
I I y, mg y, ngy, AbfMOM OAft GHn D. s v QATE CM E'O. e v Dart NO. DATS l WESTINOMQUSE PonM $43130 , b
g
- WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
( V . TITLE PAGE R. V. Internals Lift Rig - 7q o,f,7 PROJECT AUTH DATE CH K'O. S V ATE CH K'O. S Y DATE PSE/PNJ jggPh ppq-S.0. C g .NO.' @E NO. GROUP PTNP-188 ' CHE 8 BLOGK ASSEMBLY f PNJ
/
RsCerw. kh6, page., b idtJ% -[ , A loc.abdn of .w Monevh , F - uso l
&T
/
i
~
l~r:/>
,t x
.1.< . . . .
\g/
y\\
~
l e
@a TOP LU6 .
REMOVABLEPZH A+- M 5
@e " tart
( w m W
+A "' 10 8 i 4 g
1 B+ , we * "n l g B n os Lue ., p
. cQ/////fffAi
].' (M AJPPER CLtd 1 .
Q \! ( 'O \,
,\
s xx% uc, {%N/O' jy (' (] l koom nm. REV. R E V, AUTHQR DATE CH K'O. 8 Y DATE CH K'D. 8 V OATE ' NO. DATE . e,- warmoMoun ,ORu usi20
. ,g
. , ty n k m . ., , _.mm.
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
'l I TITLE >
R. V. Internal: Lift Rig PROJECT A U T H O)il DATE CH K'O. 8 v
h0, 2 67 AATE CH L'O. a v DATE PSE/PNJ QIgd 11ft Qg 8-
~y ff S.O. CAuC.NO. F W.E NO. GROUP PTNP-188 CHE TOP LUG { = W ( 0.02819)
@B b
% BO2O nt
-h+e u;,,
s.eu set- s.msi -- g g+. , p .__ __; BEARINGO A-A _ ._i A . .
- . l Jt-- - - - -.j THE. DEARINt. STREu .T,3 ing 3Amg A5 THE ourt9. EEAEN4 hiRIT.W CC*THE N$h. dE , ,MMcvAGLE P3N, i I wgg;- #2 *
( = W (.0298ts) MAT'L b '7913 Par - ASTM A533GR.B 3 CLASS 1. QUtN.HE.D (Tf.MFt.1%D TENSION Ct wtLtc G-E a 5 W:. 254,500 d ft .(Ph.)/Ag - W/2A t A i 11.99(2.s) as.87.3 l f t= w (0.o 1396) l fe = 3992. Psr TEN SION e., A- A SHEAR Fox Te.An-car S, #4.)/2 Av W/4 Av f=(PA)/Ae t 2 Av
- 3(it3 +.c.ats) 19.934 e t
P= w & = W (o.o 2.si9) A = 3 ( 11.94 - G. 028)
- 19,7 3 G in1 n= 802.0 .st l
REV. REV. AUTHOR DATE CHK'O. a v OATE CHnD.sv OATE
, NO. DATE I
[h WESTINGHOUSE FORM 882130 O . . ' J i
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION p) L PAGE TITLE R. V. Internals Lift Rig 2(o op 67 i AUTH A OATE CMK'D. SY J O A T E 'CM K'D. S Y DATE P ROJECT PSE/PNJ 7
& 12/g Q gM,4 '
CAi.c. no. rpE so. GaouP s.o. p p_ i, W: Z B 4;Fo O *- SUPPORT PLATE 4 g TEMsrON IN PLATE. f SUPPORT PIPE O8 4 P/Ae1 - W/At A > "TT O.99 /4 - TdV4 ' MAT'L ,
- zs2.s w SUPPORT PIPE [t - W (O.003954) l AbTM AlOfo GRB ,
S'MLL. STEEL [t. II25 est 3.OPPOrd PLATE. l ASTM A 533 GR. G p ttAs.s i TENSION T N PT_PE r 4 t.J outnutotre.netne.o . fe .P/A+ - W /A tP Ag = IT/4(dj-d1.) 2 1 7 ' PATE - T/4( 17.9 si - 1%'m9
= 8 9.i+-t e
- c. + - fc i pt iier m
+p 5-W(6.0131B1) g b 3181 at
\
- l l
I
. 15 l
I
- N.9 7.11 -
- n. w -
\
t l c 19.ot, ; { 11.9+p . l p O j AUTMOM DATE CH K'O. S V DATE CM K'O. S V OATE REV. REV. NO. DATE WESTINGHOUSE SORM 882130
P W WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l I TIT LE ,,gg R. V. Internals Lift Rig g g PROJECT AUTMQR OATE CH K'O CH K D.ev DATE PSE/PNJ ,hggg g. a vg g Q(a" ATE S.O. Cp. NO. Fif NO. GROUP ll O 4 = T/ A.i = .4iaw/Ae SIDE LUG Ags.Qt) 4.oQ$ 3.s
= 22.40 M-M AT'L 41=CO-(.O1949sJ-ASTM A SBB C,R.A CLASS 1. 4= 52G3 esI.
QUtNCHtD G.,1650 F Tt MPtRt D e.,1200* F TEN 5II.E STilEN toTH - COPt BINED ETRE.S.S , oJ3,000 To 92,000 pn. Q. WELD
. t TENSION: fr T Ja / A,e . .
I l D T = . 9 1 o w d ., 3 7 . i f / Dt.9 4 o & l s.ou
+g s a w ( .00 s s 72. .)
n i.u t u s : -C, = h.s / Av. .
-l
~
ll.0 = ,918 w a.m.n */[p.u =2a]. p mmM t . N + mNorne
= fe Mc./I ,/,33*n.97/nl Tccu 5A3 [ti.94/2J '
E i I4 \,m w*nt T.- bwviz yg [*S$j4
.i a?*" A = PiiBW)(4 Ol!)Mm)/5*c>)
4.o29 4So
;, . -f b = w(.01828o-)
~
\=',W., "'" O!a'" " .j.(+ pp W(. eosw?2+.oise' ).
W:. 2 S d@ = W (.e2375 ) 7ENSION O.; i-l OLE. '
. mh =. 0 '7 58 mi
-l' A
WC .OO72.33)' THt. ARE A WIM C.OW5tRVATNtW ty : 2. F; 5' 8 psi EL W.in As T % recu m 3m oIIT AINt.C *CA HORIkONT AL F3La MAMN6 Efa M M3 D D \. M W h% D L' ( W O P D4h r uutt. Murub = b)(.o27ti): 7714nr mgy, n g y, .suTHOR OATE CHK'O. e v DATE CM K'Q. O V OATE
, NO. DATE h WESTINGMOUSE PORM 882130 '
,q WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION Y
TITLE PAGE R. V. Internals Lift Rig 23 o, g 7 PROJECT AUTH R OATE CH K'O. s v CH K'O. 8 v OATE
". .O .
PSE/PNJ ,) CA(f.NO. d r% p, g LE NO. I DATE GROUP C LEvr5 12 8 SH E AR STREE PIN m r t- Asw A e9 ces ao f, = P / 2. A ,, arsx m90 snu P r= .me,w
' ^
A,,- n d% Av = Tr(s.998 )W
, Av = 12. . s 2.9 in s
;- g.
; -- a f; = ( ,qigw ) /pu.s23 )
= w(.olGos2.)
- . , I
" I fy =
L4 "7 H 0 9::
.c
{} % %m . v P 6c. ac.ur 3 o n a m-blylb. BE ARING STRESS de ch arn t.cr e.f p m, in .
.0 leng.h of bc.rin .urf c
-fc - P/A,,
ef cc a te b. dy..n.. P = T= . hts W a = to g w of b.. rig suct.O TNNER " onnicle, of ov4.P kd y ,in Av - o .9 - ( tsw X a.ec4 ) 9 ppb.w.nbrik3 = (16.487 lins w Je.s ih. Sc - (.918 w)/(isa i? ) L .i.e4.i ac uv i.m. w of = w C. 02.7 i i) pia,e l R- 7 ~7 i 4 y
.f + 2(4 3 )
OUTER P - T=.wia w is.~ A,- a ad. 2( i.ea )s.w, i d .3.s99 in. = (t s. e i or )ins .
.P = 3. s c. is ( = ( . H i ek))/( ts.S t (. )
a = t,9 8 in = W (.07.443) o fc- 7 s i c) p. j I (] RE V, s -w.o.09 m t v,
< -2.eov z AufMOR OATE CHK'O. S Y OATE CM K'O. S Y OATE l NO. DATE WGSTINOMOUSE PCRM 943130 4
T WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i TITLE PAGE R. V. Internals Lift Rig '2 c) o, g 7 PROJECT DATE CM n'O. a v OATE C H n'O. S Y OATE S.O. PSE/PNJ AWJHhRgivg (} CAkC.No. pggg_j ffLE No. GHOUP
, PTNP-188 CHE BEN CTNC .STRES5*
f__;_(W2)(h...._._..M)'.n._. 5 +g+ ird3 - - - - -
. . . . m____._...._... ._ _ _ . . . . . . _ _ _
_._. - (.msWA'( i.% /2+.09,
+ 3.sc /4 v32/ 4 ;- . . . _ . . . . .
g
= W (. oW32 ) .
Tb- 1 9 , 't 4 O P5:t. _ _ _. i ( l .. .. . Y l I ... .. .. . .. t M M g y. m g y. AUTHOM OATE CH A'O. a v OATE CNE'O. a v OATE NO. DATE P.
,, YvESTINOMOWSE FORM 962130 i[ .
r
.I kf
. . . . . . . . :_ , . - - . .- . - . _ . .--.~c_-..
~
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R. V. Interhals Lift Rig 30 o or paOJECT DATE CH K*o. a v QATE cngo.av oATE PSE/PNJ AUTHOm h & 0a,4I Q py)g g jh s.o. cALq,no. eu.E no. onove
~
StrN6 LEG %$2.maty - UPPg g,
--@- ctsvn 13 ate l
l LHV LJ , Lq l4 MB e l 6 9 . +~i . i i' 43 y LOWIR. 15 - gj i ! cn, CtsvIs
. L.J_d 7 At B
. w l . me v. aav. AurHoa oars cHno.sv oars cHn o. s v oArE NO. DATE , I westinowouse eone seatso 6 .
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- WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION O
U TITLE PAGE R. V. Internals Lift Rig 32, o, c7 PROJECT DATE CHK'O. a v OATE CM K'O. 8 v OATE 5.0, PSE/PNJ ) AUTHQ NO. Ak b ) %. AthR44(([4 Pvt.E NO. GROUP PTNP-188 CALb< CHE SLING LEG 4 gg a l i
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WESTINGHOUSE NUCLEAR TECHNOLOGY DIYiSION
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wu.o=>e. nucz rrounttv, aAaruu OF Pru JCINTS It DONt reNoltr% v'
- M ax.8 toca,t. eacwwArrans amo u p e, woz r c.et. zr u ~~o bc "TH t.
PLPPRDPnI Att CALLOLAf304 FC E. TBAT AU. CDttC.t.'3 Aci ou r M L '. P Ac t. 2. LON TLH RWifD74Lb (A660W AtCLLk j A n onwruno.u.zs Tensow t n-a
.C.= P/At 6. = P/At P=. T= meow P= w/3 Act 3S91(2-oo)
[ fc. s ,Q:ow yis 4 9%. h.co N = 'l A . n d 2 M 4 9 9 /0 % ' ! (t = w(o. 030358) o p < w (. .os2 3s) p Cc = 1 4 , 8 c) 4 % 2. l G E =- 8(o40 vu a
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TITLE R. V. Internals Lift Rig yg 0, (,7 ! DATE CMK'O. av ., ATE CM K'O. a v QATE L PROJECT PSE/PNJ AuhHO4 dlVy. 3,9pg G y ' CALQ. NO. - QLE Ndi GROUP s .O . . CHE l PTNP-188 (/ 4 -A shse_a ht I she.as bc- form ac t l CucK oc mon f% =g $ /(e-9.o2i)/2-5,m smso -m ntsc. attruun (Es i/(8.s +2.) =mo% l 1
.f'" Myc/I li w = 2 8 4 500 * =hn)/21t]/(Sq*')
- .saum T= . 'u a w ,
K =. . 2s 2. w : n U 'TME TE%ILE. STRtth ( 7Mfc][1
=
/I 85 23[
knLL GL -DE.TLRtnINLO - (c'12.(, esr GY 5 PLETTIN 6 THE FORC.t. i T Auo THL homENTd IT c.5mWng h h p-naA- - PRODUC.E.h INTO c.0mPONENr5 o M L-.su m -of & :, p m AMD APPROKImPrTIN b TtiL (= Kt,{d ., gg ; i SN.t R.-CH ANNE L waLDMtur f3- ), Q rQ" = 18 CTQm - by 7H5._1:oLLow rN u . ' THL MtTttoo R)LuMED th srmnzst. A b/ % ' t.a-- t E CP la i th. to AND TworThKu arme soLTED ocut. von. e.m.rn uo otterr Tm. c.twzs$omt h$a
- 8~'
n N.gg
"'b Fy =3GM ustm m. uxmst vmb (Tm.cumu ),oc so c.mumatum me.tcrmo vm. newt l
v
- h .STRLAlb7?/ PfiduZtED BY THt.$PRt.kR($s:
q,, y forwh (1.6-lb') of c ter 5 4 .t 41 f
~L su- (u.-th)d Ar.c_ be.w% n_2.. s:,m).ztap
= c)95 i
o V 6, 461s,2.9% l DATE CHK'D.av OATE CM E'D. s v OATE Riv. mEV. AUTHOR l NO. DATE ,
,,7 ' !
wastimoHousa eonu seasso .s s
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r _. [ WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
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TiTte !; R. V. Internals Lift Rig ,4ce naoseCT aurn a oars enx o..y gy 47 .'! l PSE/PNJ can o.., s.o. (w, .( ryt pg gg,g[omre oars p_ cy. no. yus na: aaour I l THREAD 5 HEAR, W: Es4 paod A f8 ! t LEG SUPPORT ELOCK 23 A 7wevantao sacan2s,st ! AND BRAC.E VLATE 5^**^"*'" " ' " " ^ "" 22 9. Pi AT't , fy- W(0.019 8 '79) LE.G LUPPORT BLOC.M AnI BGE BRAfE.PtATE :hTM A-34 h :. 5G5 6 = I
,i :
("' L s - WELO s HE.Ars
" em.t. I
.- gg Tm umau wuo (.c) ann.:% i <
j i
.a a
1 = t2 rst. nu.x c.nmuu. nmaa m m.c.usu. uter on Tet. i l . m Wt.t.D DIhTILIQUTION ,714E. j g i j, f .- -- um.o a,zm ronsT*au vuu. "
.% m = Ta To m . 3 u u -9. m Aso.h 7
CONNtc.TTCN. SC THt. SHLhtt. l STRth IM TM Gre,1.T wttDS
- 3.o 8 m'
8.c 4 . ts '
/
a . 5: !P. . J v% ' a y. Ay- (.7o7X. SOX s.o u) e(4)-
.907 b y- .,
. B.7.Ho # -
p + s.o - Ev W(O.01G838) . j
,_ 6= E.991 m l ,
5 :J'S i - 4 1 i U d,/m W MEy, I p g y, AUTHOR DATE CH K*D. S Y DATE CHK"O. S Y OATE .l, NO. DATE WESTINaMOUSE FORM 552130 i A f
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lI WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE R. V. Internals Lift Rig q 3 ,, (,7 ; PROJECT CATE CH K*D. 8 Y CH K'O. 8 Y QATE
$ O.
PSE/PNJ AUTHQ h d p h MdlikATE FIL$NO. GROUP j CA LC.p. ! PTNP-188 CHE LEGr E U PpoRT EL%K 23 8 l f THE PN 3 L E Gr J.O P9CRT EL AGkE T T.g 7 H E S AME Ak "THE ME UteF(fcKMCbchggg f THAT*THE 4.50-4uu B THREActb H0LE. 7 5 REPL AED SY A iM00TM Dony.D MOLE LJ4CbE Or AMLTtis :L% f chs 9. si - '
%'75
- eeArnt. cv kur (utm s) oN Ltw ,
SvPPcRT ELL % ( i , U(% _ F /4c_ u- i P= w/2 ! Y4 Ac_ = [G.99 - 2(.20]* 9.Bl
= 10.'? G'? M ?
f [c = W/3/tO.'76'7 .
= W (,03 0C>59) l O 8, eo a m j 1
l i i R E V, REV. AUTHOR DATE CHK'O. S Y DATE CH K"O. S Y DATE NO. DATE WESTINGHOUSE FORM 852130 ' c
WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
\d TITLE R.. V. Internals Lift Rig p PROJECT q q . ,, g7 DATE CH K'O. S Y ATE CHK0.8V PSE/PNJ s.o. AUThHoA 0ft Q )) k h** ,$ p CAqj uo.
DATE pE no. caO e 1 I TORQUE.' T UBE ASSEM BLil PSE
. t WI N
- v' d 24 A V ^I A DA PTOR '
g THe toRqueTuat : 76 I j 6 AMEN ELY THREAD 1 1 1 7 znro me sureaar - / BbCCK DP A L EC, WMSW b
~ - "
- M '
OUTER TUBE i I 7 .s y ' 4 ! A GUIDE SLEEVE. k . h THE YLNGACatNG .5(84w hjis 27 A y ENGAGING Sc.REW - a THREA% INTO THE IM" TERN ALS l W/3 , l r ( REV. R E V. AUTHOR DATE CH K'O, S Y DATE CH K'O. S Y CUE' NO. DATE WESTINGHOUSE FORM 882130
. i L
i t 4
a . . . - _ _ . y - _ w. x l 1 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION ! l TITLE PAGE I R. V. Internals Lift Rig m o, (,7 PROJECT OATE CHK'O. S Y l OATE CH K'O. S Y DATE ; PSE/PNJ stu hHCd %t. p,,3 p d['k s.O. CAg. mO. gtE 80. oRove W 7 D4 g'800-ADAPTOR 4 2.g" g 5.5-4 TH R E A D SHEAR c. 5.5-4tm OUTERJ TUBE. f, P/Adw/3)/A,
}4AT'Lt 4" t -
I ADASTOR- hTM A-7.% TYPr. 304 IN ,Tf7
,9 N :
Q oute ttuar. i HOT Rol. LED ( M utb v II I v Twaeno cuatment ro wt.: auve
.curm. wet- Asix A-sia .h (.w. s?.) .s2 = 3 = 2.co TYPE. 304 A, vDr a h ,, SM Ls . c.F. ( hT. TR. Dp;% = Q . G 4 952/h, /
l C/ ) = s.s .G4ss2/4 = s.n%2. ya Tr(S.MM)(LCO)/2,= IG.%9 N fy = W (,Q13899) i wo. . -Ev - F 6% m
- m mr
- m- ro us -
, 4.so- - . a ~ l
,/ THREAD SHEM ti$-l(o THD
, p
! 77,/
/ / O= P/Ae(W/3)/Av
% M As 1rDg .P/:
D 4 j= s.ssi l hg%_._.h :Ji Dru= 4.4ss4 (=n, eu) A3- 2 (c.4s9+) s.ss h_ :: 41 889,0
- . 4 x y l
M ' ,3.es -fy = w/(1+ 4i.sse xy R,K, .C l i 4 . b w(c.co99ss) k--- i I l _N o a ruot: G.03 RM.140
. s.30 wn-28 I-v 22G 4 m
%7 Tua r.
- R E V. R E V. AUTHOR OATE CH K'O. SV OATE CH K'O. S Y DATE NO. DATE WESTINGHOUSE PORM 882130 .
l . l . , i
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- WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION s.
TITLE R. V. Internals Lift Rig ' PROJECT A U T MojR CATE CHK'O. ey 51 o, 67 s.o. PSE/PNJ $4,, Og /%t, gp RATE CH K'O. a v V P OATE _ c445. no. OLE ~o. caove
')
4I ADAPTOR ( 2. g A QUTER. TUBE. !!
- 'i k
I t.N SION e. THREAD nELIEF ' a ritc% meg 6 g Ang2x, , P esse, B*ta G.00 %H 110 ssT PIPt' hah AN i C.D. OF G.r,25 in . ' k = P/A+=lW/3)/At gJ At= '/ 4(d.2 df) - 7/4 ( utst-5.sW)
= 9.8 9 4 iO
{t = W ( O.033fo9) - fe 9 5 85 m. ' Ttunou e., 4V t muAo . Filom maad HANcton,9* Ed , rm. sraas anA on A 4 'i 160N-2A "TWttAD T.s N=15.4%'2.(J
' [t = P/Ae = (w/3 )/A t At* As - Ndi '
A 15.4W7. -(Tr/4X2.1Sf
- t1.383id b W(c.0292B) h+ = h3b P.u- %J nE v. a E v. ^u'"oa o^" C" *' ^" C**' ^"
NO. DATE WESTINOMOUSE PQRM 882130 l
. L
~
v v x r WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . C PAGE TITLE R. V. Internals Lift Rig 5 2. os 6 '7 Au Mo DATE CH K'O. sv g ATE C M K'O. S V DATE PROJECT PSE/PNJ ,. . QA P4s 3wffM g8 caove s o. CV. No. y'E No. w = m %scoe E GUIDE SLEEVE. 3A BE ARENG STRESS
- m. manuTru.ss etwitu ;
TM t. CauT.Ot. Stttyt ANO ENbha*.!% MAT'L : ASTM A 2.76 _ s a tw zsc. w .utAreo zu m . i TYPE 304 enemozw. satw sec.rrou . . HOT ROLLED / Pn.tuiD CON D. A . [c = W (0.059 61) ,
.:p.- . Il= \ G,958 m i , e.s o - % . ,
T (oj 1p 2 ccepsuncN Ar ma RMrc.F r - ' 3, -xu anx t.mtr ont.wrs-
%h 3 'M . 4 =(-1) P/A, =(w/0/At A,= v/4(d.2-al). 9(s. int-2.7s g g i
g 4fe-w=-w/(3* ( o.oss9.4c2.) 45 ) R 4 = - IO,OS(o nr g , i N N I % i ! 4 % THREAD SHEAR ! L L , 2^
. , ', * .fv= P/A, =(w/3)/Ay fl,14 -E S As-og a .D/2 nmdao,.wx . . .Q. 2.0 D - -
Av = 5.33H.Tr(2.OO)/2.
- lb.'M9 l l r-o n. e s'4.- 4uN -zA Tun Ao fy : W /(3. W/49) l Op;kh = 5.500 - qG 4952/4 fy = W (0.01 S B l 9) ,
l D3 . 464952./n A D = ma 3 jo, cb.hder. an d n = 4= 5'G56 m Mom hr* 6 b4d4 Dif* Imth DATE AUTHOR DATE CHE'D 8Y DATE CHK'D. 8v t REV. REV.
- NO. DATE WESTINGHOUSE PORM 882130 q
t .
.q
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i WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION (7 j i TITLE J R. V. Internals Lift Rig PAGE ' f
*RosEc7 Au so oATE c x o. s v 33 ,, g7 [
s.o. PSE/PN3 g kPf c qw g LfgATe g c w o... oATE '
. no. -l (f.E no. GRour l
W :-2B 4(TOO
- ENGAGIN G gr7 A BE APsING G B-B i SCREW i:
MAT'L: Ec. = P/Ac I P = (w/a) ASTM A-2.7G A c= (clos c_il)T!4 ,; TYPE 309 *(TrA) (4.%-2(.m)f-coNo. A. (s.m(2c.a))2 .
- s.s m a g R.= w/(3+s.s92.) ,
Sc= W (o.o s9G1) B Bg [:E74'4f , [c = \(o,9 59 psz O ,-'
- s.oi
, - TEN 5II.E 4 THREAD RELIEF (s. - P/A+ P = w /3 i As - %2 2,0ch3)4.s3'87 t ' 2.% 3.49 T 4 = w/(2 9.2% = w(o.owzz) ; M b,c3.110 wo .
.- $2y $ h1 p37,
===- unaneu 2.'15 MIN.
FOLLTMREAD
;i THREAD SHEAR w4so, Sv P/Av =(W/3)/Av t% Ac ogu n > /2 = 32m n 2.,s/2.
raem maas's m acow. For m.6/s aeta A = w (o.0 2.3i2.') , O ' ~='"""~~ ' (5" "'" i RE V. R E V. AUTHOR DATE CM K'D. 8 v OATE cM K'D. s v QATE NO. DATE WESTINGHOUSE FORM 882130 l
v- g- 1E l i I i l WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
%) .
TITLE PAGE R. V. Internals Lift Rig 59 OP 67 l PROJECT AUTHO CATE CM K"D. a v ., ATE CH K'D. S Y DATE PSE/PNJ 4 A ppt g g gphg j s.O. CA y. uo. oROvP p _ guE ~Oc r EN(s AGIN6 MEW 27 O ' h t. PNJ Etu.Wrm. C.s.tw n
% s w i m .. A s l e t m e s s . %
SCfh w E.M t.PT TH AT TML B*. A RINO, STRF.5% 2.5 As seg f
. .[
Acwe mutum. It ornsauar 4
' I
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.EE ARIN LT ON (.y u r b t 5Lt W t.
THt. FuerLING ts Tes umt g3 __ C M Lt.ui A h n R A T*4t G W DLSLisvt ',; TTtres "30-G .a 0 -c = * ( - "'" S 3 (c_= 12.,3 7 O pc - MNi'L INSTm rg -5b4 - 2 CRect. r,2o A* ! COMO llOO :$l -, t f i
\
V
~
REV. R E v. AUTMOR DATE CH K'O. S Y DATE CH K*D. S Y DATE f.O. DATE _ ;je WESTIuGHOUSS FORM 852130 .." ,
. i ; .g
w r , .. 3 ~ / s (._) WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE l R. V. Internals Lift Rig PAGE PROJECT I PSE/PNJ AUTkCg Ig gg OATE CHK"O, a v % OP 6/ i S.O. PTNP-188 CALgNO. 7LE No, jTE CHK *0. S Y gnoyp CATE 4 CHE I TORQUE TVEE. AhLEM ELY s PNJ I t i li I R s I
'a g si l l - ' '
' 28 8
. c[]' ,
l I : LOAD NUT !
' g g 1 Lt& Eu PPOR T ,'~ ~~
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'l1
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TUDE HOW.m & i LJ '
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- DATE !
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,- WESTINGHOUSE NUCLEAR TECHNOLOGY CIVISION l
I TITLE PAGE R. ). Internals Lift Rig g ,, p ypjg f OATE PROJECT OATE CH K'O. s Y CH K'O. S v OATE PSE/PNJ A UTr
,'9,j o0)f g i M l?f t I S.O . GROUP ' , PTNP-188 CAbC.NO. d/ LE NO. CHE LOAD NUT 28 8 I34 i M AT'L: '
s.O s t [/ r l ASTM A-2.~7(o TVPE 304 397 / 1' j) " HOT ROL.LE D 4 PrtXLCD f i C.CN Q A gg BE ARIM 6 4.soo-wn-2 a t Ttn. BkARTNb 4TREW H% Det M THD l C.A LE.uk AT1.D IN THL LM. SV1"V0RT j ( asoc.5icmuu ms xnm 2.2 e l b '
'[=
W C.Oso9s9) (=. % B O 9 PE I THREAD SH E AR I ' v- P/Av [
.P= W/3 Ay = De M 2.
.) =. ?. 9 '7. N !
. CoH 962 M j g = D3
=9.so .WS2A j l
= 4.337G A l
. Av = u3% ("Wh .
= 2 o.2.9 M l
.fy W/3 /20,2M l
- w(,og G99 2) l fv- 4 Co B Co Pbr REV. REV. AUTHOm DATE CME'O. S Y DATE CH E*0. S Y DATE *
, NO. DATE WSSTINOMOUSS PomM 883130 , . .]
.t
_ _ m s - g WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION i
\'
TITLE R. V. Internals Lift Rig PAGE I P ROJECT AU THOJ OATE CMM'O. a v g ,, (,7 PSE/PNJ O S.0. yg,,A ty t, p ,f ,* f, j*,1 U ATE ( CMK'O SY DATE , PTNP-188 Cg. NO. F E NO. ' GROUP CHE THREAD 5HEhk ON LOAD nut TOBE. HOUSIN(y 29 c A'c uthTeo AT Lono Nur B " " " - [v= W (.olG H '72.) Adm A-2Ho TYPE 304 .f = 4 (o 5 6 P m HOT ROLLIED i PIC.KLED con o. A. DWN AT MmImm sa.cTION i
> 2.is
- 4 ft :- P/A t p = w/3
!, jj A i = Ar -3(Lis? ,
i i li AT = s'F (q .9'N3/n/ 1 4.soo -*=-a l i i I 31 ( 4.5 .3992/-t[ I
=.
14.n.9 R l, i 4 19. n 9 '4 (2.13 f 8 I l ll ,
= 10. 599 M fg =. W/3/(to.T99')
. i =
i vv(.o314so) i i-l 4 = 8 9 9 8 eur. / 1l1 - i h,
.c 7
j l e iq cio
"' 44 THRP.M f.MEAR. ON (suroE LLEE.VE-fy = P/Av = (w/2)/Av 'jf l t ; 7 . l
' l 1 ut Av A 1rDp D/2.
l 2"8 l l , l Dp = D3 .G99s2/h. - i _t 1 s.sco r,wsv9 - s.33m, A s.sco- 4un -2 A .!s S 19s .53 .6 = 2.sooik S,c. n.t i 53 Av - u(s.nv.)(:.Bo )/2 = 23.9m*0
?
fy , w/3/23.m g2 bs;Dhm r i 2.m
= W ( .01919c))
__ ls4 i .e tint""" fv - Ho'lO PEI i O REV. r R E V.
.n
. sa.s .ss .ss AUTHOR OATS CME'O. S V l
i NO. DATE OATE CM E'O. S Y OATE WESTINOMOUSS PORM 982130 O _ _ _ _ _ _ _ . _ _ _ _ _
+. - -. _. . --- .. .- . ..
l l WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION V ! i PAGE , TITLE R. V. Internals Lift Rig 58 QP (47 ; PROJECT DATE CH K'O. B y CMKo.av OATE S.O. PSE/PNJ AUThoh/dih $LEg NO; CAL $jNO. a l d, DATE GROUP i l PTNP-188 v . CHE !
" THREAD ShtLAR, ON TOBF HOUhrNb ,
GUIDE. St EEVE 30 B m oano e ,e = = u m,
~
ITEM 19-8 .
~
8v = W (.Ot419c)) ' M AT'L', AhTM A"2.'74 "TN Pt. Soti fv = 404OP HOT- ROLLED i PIC.KLCD COND A . TENSION AT "THREAb RELIET h = P/ At-om *
- P2W/3
"' A-%(a;ce)-
c
,g
, = T%;(5.sv- s.ne) 7 w en n y' = 9.u t O
(* * "3 s _ J
*f p w
.{g __. W/2,/9.2.~21
, w( .02 4150 p ,s.s
.ww 9
.t e 1 o,2 8 9 psz
~
.- / p,gARIu.4 0h1 (NeA(sh MY.t.W
! I fc = P/Ac
'i _ { p . W /3
/_ A 'g.(af-a?)
i
, ; j do = w.99-u.m) - wss d =. 3.% 2.+ 2.C.is) = 3.*A7.
) A '?,Co9D
/- -( w /3 /7,0 7 e 3.f. 82%'#
( = w (.oH3M O
,3 341 . (c . I7 , 3 '/ O P5I.
3 p El: O i l AUTHOR OATE CHK0.SV OATE CHK*D. S V DATE REv. REv. NO. DATE UWESTINOMOUSE PORM 883130
. 't
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,e y WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE R. V. Internals Lift Rig ' '
^
PSE/PNJ k [4 j ", fpI'""'** o^'s
'- - PTNP-1c8 D" ' 0 " ' "" ""
CHE ROTO -LOC.K BAC.R FIT
~DiESE ITEMS se c. ONLN THL Lo A O V: Rom 7"L inn.RMht5. THE Lowt.p ruuuAu ustren M 2200,000LB. I m upFt.A t u rtrt N Att w tr*H Wu ' nc 000 s LB. A L' l
per., uttFr Tut ruktR75 An uno To wec.r novn-tut.-
\spFER AND LOwtm. TNTutMAlt 20 OJ= 2eo,000LO N -
"THEM., TTifM . W MtM ANhbMEIMio THL tN6 A(aLMhuT Of ;
-t1A S n> DL % "THt. 'tNbtRD rr uJILt. B t. C.OMht FMAT. Tut,ty AWMED THAT S our og g 2. L puts A gt. Ac.- V t. wHEM utm m L~m srso e ouro me mTu_ w.
(Nwumto AC.TI.VL tousu. Na ALNitrMb -twt. LrfT OCTBL bT'PERS. ~ _s d , l
- F
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--e m- - , w- --
,, .1F. . . S.. s..
I 4 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION O TITLE ** >: R. V. Internals Lift Rig (DO Or 67 ,
* " ' ' ' ' ' ^ '
8 o-PSE/PNJ / k * " ' g /[' L PTNP-188 CHE ; ROTO-LOCK EMKFIT THRE AD S H E A R-fy= P/As = Wi3l/Av 31 l LOAD Nur A A3v D y, l ti / 2. l vixTU og- os .o e s2./n l Asm A2'm 3,ue _,uou/4 . NPE 209 -
*9.OTlb !
MOT ROLLED p,3,oo l* CONO. A , 4,,, n.ct% (340Wll.
' )9.2 fo h d j p Ry s w /S /19,31 f
* - w (,0v1205) l 9 .
I
'{5 ,
{y . yggg r.I l
.O
! i i f B t A m N tv l *
' >-- $,, { - P/Au !
l P ; W/3 i p" A,_ = 5.:50 (4n5) - 2. (.W.ED ! (/ ,_ _ T gg " - W4 (H.not
/ '
.e c>.92 o s tn' l
f / i 5 ( w /3 /9.9205
- w (,o 3 % o ) !
s l [ y, .
\_' 2h' R. - 8 7 3 6 P'I
% 1 .,
@ L 7 i O .
TE : S - t i R
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' Sf, '
s
- _ . ._m . . - _ - WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE R. V. Internals Lift Rig '^
- I RoacT 6I o.67 PSE/PNJ Ao y
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