ML20094G961

Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internal Lift Rig,Load Cell & Load Cell Linkage to Requirements of NUREG-0612

ML20094G961
Person / Time
Site:	Summer
Issue date:	04/30/1983
From:	Sandner H WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20094G907	List: ML20094G899 ML20094G930 ML20094G961
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, TASK-A-36, TASK-OR WCAP-10233, NUDOCS 8408130480
Download: ML20094G961 (190)

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., WESTINGHOUSE CLASS 3 A

g Although infonnation contained in this report 7 is nonproprietary, no distribution shall

& be made outside Westinghouse or its y _

licensees without the customer's approval.

EVALUATION OF THE ACCEPTABILITY OF THE REACTOR YESSEL HEAD LIFT RIG, REACTOR VESSEL INTERNALS LIFT RIG, LOA 0 CELL, AW LOAD CELL LINKAGE TO THE REQUIREMENTS OF NUREG 0612 for SOUTH CAROLINA ELECTRIC Am GAS COMPANY VIRGIL C. SLNMER PLANT APRIL, 1983 H. H. SA)0NER, P. E.

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d. T. Mar'5 hall, P.E. Manager Refueling Equipment Engineering WESTINGHOUSE ELECTRIC CORPORATION l

, Nuclear Energy Systems  !

P.O. Box 355 Pittsburgh, PA 15230 62608:1/031783 8408130480 840901 PDR ADOCK 05000395 P PDR

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• ABSTRACT ' ,

An evaluation of the Virgil C. Summer reactor vessel head and internal lift rigs, load cell and load cell linkage was performed to determine-the acceptabi11ty 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 recommendations to enable these ' devices to demonstrate compliance with the intent of NUREG 0612 and ANSI N14.6.

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. TABLE OF CONTENTS '

l Section Title Page .

ABSTRACT 111

-1. INTROD UCTION 1 -1 1.1 Background 1 -1

2. COMPONENT DESCRIPTION 2-1 2.1 Reactor Yessel 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 3.2 Stress Report 3-1 3.3 Recommendations 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 Recommendations 4-2

5. CONCLUSIONS 5-1

6. RECOMMENDATIONS 6-1 l

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LIST OF ILLUSTRATIONS Fffjre Titie Page-2-1: Reactor Vessel Head' Lift Rig 2-3 2-2 Reactor Vessel Internals Lift Rig 2-4 I

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e ATTACINENTS I

- 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 South Carolina' Electric and Gas Company, Virgil C. Sunner Plant.

B. Stress Report - Reactor Yessel Head Lift Rig, Reactor Yessel Internals Lift Rig, Load Cell and Load Cell Linkage for South Carolina. Electric and Gas Company, Virgil C. Summer Plant.

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\' SECTION'3

-. SCOPE OF EVALUATION J.

1?m 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. Recommendations to demonstrate compliance with NUREG 0612, .

c - Section 5.1~1(4). .

Discussion of these items follows.

3.1 REVIEW OF ANSI N14.6-1978 A detailed comparison was made of the information contained in ANSI N14.6'with the information that was used to design, manufacture, inspect and test these special lifting devices. The detailed comparison i is provided in three parts:

1. Overall item by item comparison of requirements

2. Preparation of a critical item list per ANSI N14.6 Section 3.1.2, and

3. Preparation of a list of nonconforming items.

This detailed analysis is contained in Attachment A to this report.

i 3.2 ' PREPARATION OF A STRESS REPORT Section 3.1.3 of ANSI N14.6 and NUREG 0612 Section 5.1.1(4) require a stress report to be prepared. Special loads and allowable stress criteria are specified for this analysis. The stress report is Attachment B to this report. *

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3.3 RECOMENDED ACTIONS An' obvious resul-t from the previous evaluations is a list of items that can be performed to demonstrate to the NRC that these special lifting

. devices are in compliance with the guidelines' of ANSI N14.6 and NUREG 0612 Section 5.1.l(4). These 'reconenendations are identified in Section 6.

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~SECTION 4-DISCUSSION OF EVALUATIONS 4.1i ST00Y OF ANSI'N14.6-1978 '

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' A review of ANSI N1'4.6Lidentifies certain analyses to be perfonned and l 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 h'as been prepared 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 perfonned.

A detailed item by item comparison of all the requirements of ANSI N14.6 i and those used for the design, manufacture and inspection Uf these lifting devices is contained as Table 1 of Attachment A. The comparison 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 i functional 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 reconnended actions that may be used to demonstrate acceptability to the NRC.

4.2 STRESS REPORT l

i As part 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 perfonned in accordance with the criteria of ANSI N14.6. A discussion is included which responds to the NRC qualifying conditions of NUREG 0612. All of the tensile and shear stresses, meet the design 62608:1/031783 4-1 l

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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. In

~ 1 addition, all of the tensile and~ shear stresses meet the requirements of l the AISC(5] code.

4.3 RECO M ICATIONS The recommendations 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 recommendations 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 recomendations do' not involve'any equipment changes.

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SECTION 5

.- CONCLUSIONS The following conclusions are apparent as a result of this evaluation:

1. The kRSI N14.6 requirements for design, fabrication and quality assurance are generally in agreement with those used for these ,

special lift devices.

2. The ANSI N14.6 criteria' for stress limits associated with certain stress design factors for tensile and shear stresses are adequately satisfied.

3. These devices are not in strict compliance with the ANSI N14.6 requirements for accepteccc testir.g, i::cinter.2nce 2nd verification of continuing compliance. Reconnendations are included to identify actions that should enable these devices to be considered in compliance with the intent of ANSI N14.6.

4. The application of the ANSI N14.6 criteria for stress design factor of. 3 and 5 are only for shear and tensile loading conditions. Other loading conditions are to be analyzed to other appropriate criteria.

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SECTION 6

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RECOMEtIDATIONS

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The following recommendations address the areas of' ANSI N14.6 which are incompatible with the present lifting devices and which are considered

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-.most important'in demonstrating the continued reliability of these

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. devices. They consist of suggestions and proposed responses to identify compliance to the NRC and future considerations.

o 6.1 Recommend' that no changes be made' to the reactor vessel internals lift rig should the' stresses, discussed in Attachment B, be considered excessive by others because:

a. The design weight used in the stress calculations is based on 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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i required (once/10 years).

b. Prior to removal of the lower internals, all fuel is removed.

Thus the concern for handling over fuel is non-existent in this particular case.

c. Normal 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 approximately 50 percent and consioered well within the ANSI N14.6 criteria for stress design factors.

1 6.2 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 identification

and marking; maintenance, repair, testing and use. Westinghouse remarks on addressing these sections are listed in Attachment A,

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Appendix B, Items 5, 6, and 7. -

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6.3. A proposed response to the requirement of ANSI N14.6, Section 5.2.1,

• requiring an initial acceptance load test prior to use equal to 150 percent of the maximum load is that the 125 percent of maximum load test that was performed be accepted in lieu of the 150 percent load I test.

6.4 A proposed response to ANSI N14.6 Section 5.3 which requires,

' annually, either a 150 percent maximum load test or dimensional, visual and non-destructive testing of major load carrying welas and critical areas follows. (Since the 150 percent load test is very impractical, the approach identified in the following recommendation is to perfonn a minimum of non-destructive testing. )  ;

a. Reactor Vessel Head Lift Rig Prior to use and-after reassembly of the spreader assembly, lifting lug, and upper lifting legs to the upper portion of the lift rig, visually check all welds. Raise the vessel head slightly above its support and hold for 10 minutes. During this time, visually inspect the sling block lugs to the lifting block welds, and spreader lug to spreader ann weld. If no problems are apparent, continue to lift, monitoring the load cell readout at all times.

b. Reactor Vessel 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 the assembly slightly off its support and hold for 10 minutes.

l During this time, visually inspect the sling block lugs to the l lifting block welds. If no problems are apparent, continue to lift, monitoring the load cell readout at all times.

62608:1/031583 6-2

The above actions do not include a non-destructive test of these I welds because:

a. Access to the welds for surface examination is difficult.

These rigs are in containment andsome contamination is present.

b. All tensile and shear stresses in the welds are within the allowable stress.

c. The iten:s that are welded remain assembled and cannot be misused for any other Itft other than their intended function.

.d. To perform non-destructive tests would require:

(1) Removal of paint around the area to be examined which is contaminated.

(2) Perfonnance of either magnetic particle inspection or liquid penetrant inspection and (3) Repainting after testing is completed.

(4) Cleanup of contaminated items.

Perfonning non-destructive tests on these welds every refueling would increase the critical path refueling time.

Dimensional checking is not included since these structures are large (about 13 feet diameter by 43 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 an examination of these items would require disassembly of the special lift devices.

62608:1/031583 6-3

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.. :645 ' Recommend ,that'a p:riodic non-dastructive surface. examination of .

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critical welds and/or parts 'be perforned once every ten years as part of. an'inserWce inspection outage.

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WESTINGHOUSE CLASS 3 3

Although-information contained in this report ATTACHMENT A is-nonproprietaryr no distribution shall to WCAP-10233 be made outside Westinghouse or its

-licensee's without the customer's approval.

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 the Load Cell Linkage for South Carolina Electric and Gas Company Virgil C. Summer Plant APRIL, 1983 4

H. H. Sandner, P.E.

Approv O - b zy J. R. Marshall, P.E. , Manager Refueling Equipment Engineering 6259B:1/032183

ABSTRACT The requirements used in the original design, fabrication,-testing, maintenance and quality assurance were compared to the ANSI N14.6-1978 trequirements forf the Virgil C. Summer reactor vessel head and internals lift rig, load cell and load cell linkag'e. 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 Virgil C. - Summer lifting devices has been prepared.

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I TABLE'Oc CONTENTS Section T'itle Page ABSTRACT- iii

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l' -PURPOSE' 1-1 2 INTRODUCTION. 2-1 2.1 Background 2-1

2.2 Component Description 2-2' 2.;2.1 Reactor Vessel Head Lift Rig 2-2 2.2.2 Reactor Vessel Internals Lift Rig 2-2 2.;2. 3 Load Celi and Load Cell Linkage- 2-3 3 DISCUSSION 3-1 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 VIRGIL C. SUMMER SPECIAL LIFTING DEVICES E

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=.,v; LIST.0F ILLUSTRATIONS y Figure- Title Page-A Reactor Vessel Heid Lift Rig' A-6 1s 4

A-2 ER eactor' Vessel-Internals. Lift Rig,. A-10~

Load Cell' and L.inkage 4

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LIST OF TABLES Table' Title Page

~2-1 Comparison of the Requirements of ANSI N14.6 2-4 and.. Virgil C. Summer Special Lift Devices

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A-1 Reactor Vessel Head Lift Rig, Critical Items A-3 List of Parts per ANSI N14.6-1978 A-2 Reactor Vessel' Head Lift Rig, Critical Items A-5 List of Welds per ANSI N14.6-1978 A-3' Reactor Vessel. Internals Lift Rig, Critical A-7

- Items-List of Parts per ANSI N14.6-1978 A-4 Reactor Vessel Internals Lift Rig Load Cell A-9 and Load Cell Linkage, Critical ~ Items List of Welds per ANSI N14.6-1978 l

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REFERENCES' .

. L I. Westinghouse Drawing 1098E56 Looo Lif ting - Rig - Head, General Assembli.-

'2.. Westinghouse Drawing 1143E65 - South Carolina Electric and' Gas Company, Virgil C. Summer Plant-Internals ~ Lifting Rig General Assembly.

3. Manual of Steel Construction, Seventh Edition, American Institute of Steel Construction.

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-SECTION 1

<jn -. - PURPOSS The purpose of this report is to compare the requirements of the special lifting rigs used to' lift the reactor. vessel head and reactor vessel

. upper and lower internals with the requirements' contained in ANSI N14.6 for special-lifting devices.

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1 SECTION 2 INTRODUCTION.

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ANSI N14.6-1978 "American National Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More for Nuclear Materials" contains detailed requirements for the design, fabrication, testing, maintenance and quality assurance of special lifting devices.

NUREG 0612 " Control of Heavy Loads at Nuclear Power Plants", paragraph 5.1.1(4),- specifies that special lifting devices should satisfy the guidelines of ANSI N14.6-1978. Subsequently the Nuclear Regulatory Commission (NRC) has requested operating plants to demonstrate compli-ance with NUREG 0612. To demonstrate comoliance with this document, a detailed comparison of the original design, fabrication, testing, main- .

tenance and quality assurance requirements with those of ANSI N14.6 is necessary.

Thus, the ANSI N14.6 document has been reviewed in detail and compared to the requirements used to design and manufacture the reactor vessel head lift rig, the eactor~ vessel internals lift rig, load cell, and the load cell linkage. This comparison is listed in Table 2-1,

2.1 BACKGROUND

The reactor vessel head and internals lifting rigs were designed and built for the Virgil C. Summer Nuclear Power Plant, circa 1974-76.

These devices were designed to the requirement that the resulting stress in the load carrying members, when subjected to the total combined lifting weight, should not exceed the allowable stresses specified in the AISC[3] code. Also, a 125 percent load test was required on both devices, followed by appropriate non-destructive testing. Westinghouse also required non-destructive tests and inspections on critical load path parts and welds both as raw material and as finished items. These requirements of design, manufacturing and quality assurance were identified on detailed manufacturing drawing and purchasing documents.

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r Westinghouse also ' issued field assembly and operating instructions, where applicable.

-2.2 COMPONENT, DESCRIPTION 2.2.1 Reactor Vessel Head Lift Rig The reactor vessel head lift rigb13 -is a three-legged caroon steel

~ structure, approximately 43 feet high and 12 feet in diameter, weighing approximately 21,000 pounds. It is used to handle the assembled reactor vessel head.

The three vertical legs and control rod drive mechanism (CRDM) platform 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 removed and the three vertical legs and platform assembly remain attached to the reactor vessel head.

2.2.2 Reactor Vessel Internals Lift Rig The reactor vessel internals lift rig [2] is a three-legged carbon and stainless steel structure, approximately 30 feet high and 13 feet in 4

diameter weighing approximately 20,000 pounds. It is used to handle the upper and lower reactor vessel internals packages. It is attached to the main crans book 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.

The reactor vessel internals lift rig attache,s to the internals package by means of three rotolock studs which engage three rotolock inserts located in the internals flange. These rotolock studs are manually operated from the internals rig platform using a handling tool which is 62598:1/032183 2-2 l

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.an integral part of the rig. The studs are normally spring retracted upward and are depressed to engage the inserts. Rotating the mechanism locks it in both positions.

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. The unit is a load sensing device type, rated at 500,000 pounds.

This load cell is a part of the load cell linkage which is an assembly of pins, plates, and bolts that connect the polar crane main hook to the lifting blocks of both the reactor vessel head and internals lift rigs.

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TABLE 2-1 L COMPARISON OF THE REQUIREE NTS OF ANSI N14.6 AND VIRGIL C. StMER SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device' Requirements ,

Section '

1 Sco and Definitions - These sections These sections are definitive, and not 1.1 ne the scope of the document and requirements.

to include pertinent definitions of 1.3 specific items 2

3 Design A. No design specification was written con-3.1 llesTgiier's Responsibilities - This section cerning these specific requirements, to 3.1.1 contains requirements for preparing However, assembly and detailed manu-

1. to a design specification and its' contents, facturing drawings and purchasing 3.1.4 stress reports; repair procedures; limi- documents contain the following tations on use with respect to environ- requirements:

mental conditions; marking and nameplate

! information; and critical items list. (1) Material ' specification for all the j critical load path items to ASTM, ASME specifications or special listed l requirements.

(2) All welding, weld procedures and welds to be in accordance with ASME.

Boiler and Pressure Vessel Code -

Section IX.

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(3) Special non-destructive testing for i specific critical load path items to be performed to written and approved procedures in accordance with ASTM or specified requirements l 62598:1/032283

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COMPARIS0N OF THE REQUIREMENT OF ANSI N14.6 AND VIRGIL'C. SIM4ER SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement ~ Actual Special Lift Device Requirements

• Section (4) All coatings to be perfonned to strict complianc.e with specified requirements.

(5) Letters of compliance for materials and specifications were required for verification with original specifi-  !

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N j b. B. A stress report was not originally i

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 infonnation was not addressed.

F. Critical item lists have been prepared for each device and are identified as Appendix A to this Attachment A.

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TABLE 2-1 (cont)

COMPARISON OF THE REQUIREMENT OF ANSI N14.6 AND VIRGIL C. SIM4ER SPECIAL LIFT DEVICES ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section '

3.2 Design Criteria 1. These devices were originally 3.2.1 Stress Design Factors - These sections designed to the requirement that the to contain requirements for the use of stress resulting stress in the load carrying 3.2.6 design factors of 3 and 5 for allowable members, when subjei:ted to the total stresses of yield and ultimate respec- combined lifting weight, should not tively for maximum shear and tensile exceed the allowable stresses specified stresses; high strength material stress in the AISC code. A stress report design factors; special pins; wire rope (Attachment B) has been generated which m and slings to meet ANSI B30.9-1971; and addresses the capability of these rigs l:n drop-weight tests and Charpy impact test to meet the ANSI design stress factors.

requirements *

2. High strength materials are used in some of these devices (mostly for pins, load cell). Although the fracture toughness was not deter-mined, the material was selected based on its fracture toughness character-istics. However, the stress design factors of ANSI N14.6 Section 3.2.1 of 3 and 5 were used in the analysis and the resulting stresses are acceptable.

3. Where necessary, the weight of pins was considered for handling.

62598:l/032283

i TABLE 2-1 (cont)

! COMPARISON OF THE REQUIREBENT OF AtlSI N14.6 AND I

VIRGIL C. SLSOER SPECIAL LIFT DEVICES AtlSI N14.6 Description of ANSI N14.6 Requirement Actual Special-Lift Device Requirements ,

Section

.1 3.3 - Design Considerations - These sections Decontamination was not specifically

, 3.3.1 contain considerations for; materials of addressed. Locking plates, pins, etc.

j to construction, lamellar tearing; decontam- am used throughout these special i 3.3.8 ination effects; remote engagement provi- lifting devices. Remote' actuation is

sions; equal load distribution; lock only used when engaging the internals

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devices; position indication of remote lift rig with the internals and position actuators; retrieval of device if disen- indication is provided from the operating j gaged; and nameplates. platfone. '

i n 4 3.4 Design Considerations to Minimize Decontam- Decontamination was not specifically 3.4.1 ination Efforts in Special L1fting Device addressed. Howver, the design and.

to Use - These sections contain fabrication, manufacture included many of these liieTding, finishes, joint and machining i

3.4.6 ite.as, i.e. lock devices, pins, etc.

requirements to pensit ease in decontamination.

3.5 Coatings - These sections contain provisions The requirements for coating carbon I 3.5.1 for ensuring proper methods are used in steel surfaces are contained in a -

l to coating carbon steel surfaces and for Westinghouse process specification

3.5.10 ensuring non-contamination of stainless referenced on the assembly and detail 1 steel items. drawings when applicable. These speci--

i fications require a proven procedure, l proper cleaning, preparation, applica-

! tion and final inspection of the coat-1 ing. These requirements meet the intent

{ of 3.5.1 through 3.5.8. No provisions i were included in these designs for con-sideration of decontamination materials or the use of noncontaminating contact materials for use in stainless steel parts.

62598:1/032283 1

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TABLE 2-1 (cont)

COMPARISON OF THE REQUIREDENT OF AttSI N14.6 AND VIRGIL C. St90ER SPECIAL LIFT DEVICES i

i ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirements Section ,

l 3.6 Lubricants - These sections contain On the head lifting rig, threaded con-4 3.6.1 requirements for special lubricants to nettions and 63 finishes are coated witle

. minimize contamination and degradation of to Fel/ pro N-1000 as indicated on the

! 3.6.3 the lubricant and contacted surfaces drawings. On the internals lift device, i

or water pools threaded connections am coated with i

neolube. On the load cell linkage, silicone grease and neolube are used where applicable as indicated on the drawings.

5 4 Fabrication All the manufacturers welding pro-

4.1 Fabricators Responsibilities -These 4.1.1 cedures and non-destructive testing pro-l sections contain specific requirements cedures vem reviewed by Westinghouse prior i to for proper quality assurance, document to use. All critical load carrying members

, 4.1.12 control, deviation control, procedure require certificates of compliance for l control, material identification material requirements. Westinghouse per-and certificate of compliance. fonned certain checks and inspections during t

various steps of manufacturing. Final West-inghouse mview includes visual. dimen-I sional, procedural, cleanliness, personnel

, qualification, etc. and issuance of a quality miease to ensure confonnance with drawing requirements.

l l 62598:1/032283 i . .

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TABLE 2-1 (cont) t i COWARISO4 0F THE REQilIREE4T OF A4SI 414.6 A40 _

VIRGIL C. 9900ER SPECIAL LIFT DEVICES

[!

! A4SI 414.6 Description of ANSI 414.6 Requirement Actual Special lift Device Requirements, i Section 4.2 Inspectors Responsibilities -These Westinghouse Quality Assurance personnel *

! 4.2.1 sections contain requirements for performed some in-process and final 1 to a non-supplier inspector. inspections similar to those identified i 4.2.5 in these sections, and issued a Quality

! Release. ( Also see comuments to Section 4.1 4

above) 3 l 4.3 Fabrication Considerations -These General . good manufacturing processes i 4.3.1 sections contain special requirements were followed in the manufacture

' of these devices. However, the to for ease in decontamination or control

!  ? 4.3.3 of corrosion. information defined in these sections ~

i

= was not specifically addressed.

j 5 Acceptance Testing Maintenance, Both the Reactor Vessel Head and Internal

and Assurance of Continued lift Rigs were proof tested upon comple-  ;

- Coupliance ouner's Responsibilities - tion with a load of approximately 1.25 5.1 Sections 5.1.1 and 5.1.2 require the times the design weight. lipon the comple-

{

l 5.1.1 owner to verify that the special ' tion of the test, all parts, particularly

to lifting devices meet the performance .welds, were visually inspected for cracks j 5.1.8 criteria of the design specification or. obvious deformation. Critical welds J by reviewing records and witness were magnetic particle inspected.- In i of testing. addition, the Westinghcuse Quality Release verifies that the criteria for letters of compliance for materials and specifications required by the Westinghouse drawings and purthasing documents was satisfied.

j Section 5.1.3 requires periodic functional Maintenance and inspection procedures j testing should be revised to include a visual check

< of critical welds and parts during lifting l to comply with this requirement for functional testing.

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} 62598:1/032483 i

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TABLE 2-1 (cont)

COMPARISON OF REQUIREMENT OF THE ANSI- N14.6 AND VIRGIL C. St90ER SPECIAL LIFT DEVICES i

ANSI N14.6 Description of ANSI N14.6 Requirement

, Section Actual Special Lift Device Requir M nts

~

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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Sections 5.1.5, 5.1.5.1 and 5.1.5.2 It is obvious from their designs that these

require special identification and rigs are special lifting devices and can only j marking to prevent misuse. be used for their intended purpose.

j 7 Specific identification of the rig can be

5 made by marting, with stencils, the rig name i

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 assure j tion on the maintenance, repair, testing that they contain the requirements to and use of these rigs. . address maintenance logs, repair and testing history, damage incidents etc.

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52598:1/032283

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TABLE 2-1 (cont) l COMPARISON OF THE REQUIREENT OF ANSI N14.6 AND VIRGIL C. Sl##ER SPECIAL LIFT DEVICES j ANSI N14.6 Description of ANSI N14.6 Requirement Actual Special Lift Device Requirencnts,I '

j Section 5.2 Acceptance Testing and Testing to Verify The head and internals lift rigs were l'oad j and Continuing Compliance - These paragraphs tested a's indicated in Section 5. At each

5.3 require the rigs to be initially tested refueling it is suggested that a check of' 5.2.1 at 1505 maximum load followed by critical welds and parts be included in the

] to non-destructive testing of critical load maintenance procedures for both_ lifting 1 5.2.3 bearing parts and welds and also annual devices. Preferably, during the initial'11ft i and 1505 load tests or annual non-destructive at each refueling, a visual inspection should 5.3.1 tests and examinations; qualification of be made. Further note that with the use of

$ , to replacement parts. the load cell for the head and internals,

! O 5.3.8 lifting and lowering is monitored at all

! times. Replacement parts should be.in j accordance with the original or equivalent i

requirements.  ;

i i 5.4 Maintenance and Repair - This ser. tion- Maintenance and repair procedures should 5.4.1 requires any maintenance and repair to be contain, as much as possible, require-l to performed in accordance with original ments that were used in the original j 5.4.2 requirements and no repairs are pensitted fabrication. The critical items list'of .

{ . for bolts, studs and nuts. Appendix A contains the original type of j non-destructive testing. The procedure should j

also define bolts, studs and nuts as -

non-repairable items. *

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4 TABLE 2-1 (cont)

~i COMPARISON OF THE REQUIREENT OF ANSI N14.6 AND VIRGIL C. St90ER.SPECIAL LIFT DEVICES )

Actual .Special lift Device Requirements 8 1 Description of ANSI N14.6 Requirement l

ANSI N14.6 j Section Liquid penetrand, magnetic particle,-

Mon-destructive Testing Procedures, ultrasonic and radiograph inspections 5.5 Personnel (paitrications, and Acceptance _ were perfomed on identified items.

5.5.1 criteria - Ints section requires non- These were in accordance with ASIN speci-to destructive testing to be performed in fications, ASME Code, Westinghouse .

!- 5.5.2 accordance with the requirements of the process specifications or as noted on l ASE Boiler and Pressure Vessel Code detailed drawings and provide similar l results to the requirement of the . ASME Code.

f .

- 7 It is assumed that compliance with 1 G . Special Lifting Devices for Critical NUREG 0612, Section 5.l' has been 6 Loads - These sections contain special 6.1 demonstrated and therefore this section .

! requirements for items handling critical is not applicable to these devices.

.! 6.2

! 6.3 loads.

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SECTION 3 DISCUSSION The reactor vessel head and internals lift rigs, load cell and load cell

' linkage generally meet the intent of the ANSI N14.6 requirements for design and manufacture. However, they are not in strict compliance with the ANSI N14.6 requirements for' acceptance testing, maintenance and verification of continuing compliance.

Although no specific design specification was written, the assembly and detailed manufacturing drawings and purchase order documents contain equivalent requirements. A stress report has been prepared for these devices. These devices, for the most part, were manufactured under Westinghouse surveillance with identified hold points, procedure review and personnel qualification which adequately meet these related ANSI requirements. A 125 percent load test was performed on both the head and internals lift rigs followed by the appropriate non-destructive testing.

It is anticipated that 100 percent load test, performed on each device, at each refueling, followed by a visual check of critical welds would be sufficient to demonstrate compliance. This may require modification of Virgil C. Summer operating and maintenance procedures.

Upon completion of the field assembly of the reactor vessel head lifting rig, the assembly procedure calls for a 100 percent load test (lifting of the assembled head), with a visual inspection for any signs of l distortion.

62598:1/032183 3-1

• . e.;

SECTION 4 CONCLUSIONS

.The review of the ANSI N14.6 requirements and comparison with the origi-nal Westinghouse requirements has shown that these items are generally in agreement for the design, fabrication and quality assurance of the lifting devices. However, the lifting devices are not in strict compli-ance with the ANSI N14.6 requirements for acceptance testing, mainte-nance 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, fabri-cated, 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 dotailed requirements.

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APPENDIX A CRITICAL ITEMS LIST PER ANSI N14.6-1978

1. GENERAL -

Scction-3.1.2 of ANSI N14.6-1978 specifies that the design specification shall include a critical items list, which identifies critical compo-nents and defines their critical characteristics for material, fabrica-tion, 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." ,

s.

Load carrying members and welds of these special lifting devices are considered to be the critical items.

Tables A-1, A-2, A-3 and A-4 are the critical items list of parts and welds for the reactor vessel head lift rig, the reactor vessel internals lift rig and the load cell and load cell linkage. 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 all 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 almost all of the critical items. Westinghouse required all welding, welders, and weld procedures to be in accordance with ASME Boiler and Pressure Vessel Code Section IX 62598:1/032183 A-1

n s . -

for all welds. -$estinghouse required a certificate, or letter of compliance that the materials and processes used by the manufacturer Lwere in accordance with the purchase order and drawing requirements.

Westinghouse.also performed final inspections on these devices and issued quality' releases for the internals and head lifting rigs.

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I 62598:1/032183 A-2 l

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TABLE A-1

~

REACTOR-VESSEL HEAD LIFT RIG, LOAD CELL. AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF PARTS

'.- PER ANSI N14.6-1978-Non-destructive' Testing Item (*)- -

. Description Material Material Finished l',3,7 Hook Pin ASTM'A564, Ultrasonic Magnetic Adaptor Pin Type 630 Particle Removable Pin 2 Side Plate ASTM A588- , Ultrasonic Magnetic Gr. A-Q&T Particle 4,6,8 Upper Load Cell' ASTM A508 Ultrasonic Magnetic Adaptor Class 2 Particle Lower Load Cell' Ad.aptor Sling Block 5 Load Cell 17-4 pH, SS Ultrasonic Liquid Cond. H-1100 Penetrant 9 Link Lug ASTM A588, Ultrasonic Magnetic Spreader Lug- Gr. A, Q&T Particle 10,14, 4" Dia Upper ASTM A434 Ultrasonic Magnetic 18,21 Sling Leg Pin AISI 4340, Particle 4" Dia Lower Cl. BD Sling Leg Pin Upper Lifting

. Leg Pin 3 1/2" Lower Lifting Leg Pin 11,13, Upper Sling Leg ASTM A237, Ultrasonic Magnetic 17,20 Cl evi s- AISIE 4340 Particle Lower Sling Leg Steel, C1. G.

Clevis Upper Lifting Leg Clevis Lower Lifting Leg ,

Clevis l l

(a)See figure A-1 62598:1/032483 A-3 1

.,m- --_-

f-TABLE A-1 (cont)

REACTOR VESSEL HEAD LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITEMS LIST OF PARTS

. PER ANSI N14.6-1978 Non-destructive Testing Item (*) Description Material Material Finished 12,19- Arm ASTM A306 Ultrasonic Magnetic

-Leg Gr. 70 Particle ,

16- Spreader Arm ASTM A106, -- --

Gr. B

(*)See figure A-1 t

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l 62598:1/032183 -

A-4 -

w..n+--.-y.p , .ee,,w-a.,,,&.--,--on- - - - , , , , - - ,---.--,.-~,---e-,.e --s-. , , - - - -oe-ne- -w, -

,,,,.,-,,.-,-+--o- ,--nr,w--- ---e,-

l

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'd p TABLE A  !

REACTOR VESSEL HEAD LIFT RIG, LOAD CELL, AND LOAD CELL. LINKAGE

. CRITICAL ITEMS LIST OF WELOS

, PER ANSI N14.6-1978 Non-destructive Testing Item . Description Root Pass Final 8,9 . Lugs to Lifting Block Magnetic Magnetic-(Full Penetration) Particle Particle Radiograph 15,16 Spreader Arm Magnetic Magnetic Lug to Spreader Arm Particle Particle

-(fillet) t r

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i

j. .62598:1/032183 A-5 ,

. _ - , . . _ . ._ _ . _ _ . . _ _ _ . _ _ . . . __,,-,..__m_ _ _ . - _ _ . . - . . _ . - -

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Figure A-1. Reactor Vessel Head Lift Rig 62598:1/032183 A-6

', s 3

~

TABLE A-3 REAC' TOR VESSEL INTERNALS LIFT RIG CRITICAL ITEMS LIST OF PARTS-

- PER ANSI N14.6-1978 Non-destructive Testing Item (* Description Material Material Finished s

1 Sling Block ASTM A508, Ultrasonic' Magnetic Class 2 Particle 2 Sling Block Lug ASTM A588, Ultrasonic Magnetic Grade A Particle 3,7 Upper Clevis Pin ~ ASTM A564, Ultrasonic Liquid Lower Clevis Pin -Type 630 Penetrant 4,6 Upper Sling ASTM A471 Ultrasonic Magnetic Clevis Steel Forging, Particle

' Lower Sling Class 3 Clevis 5 Sling Rod ASTM A306 Ultrasonic Magnetic Grade 70 or 80 Particle 8 Spreader Lug ASTM A516 Ultrasonic Magnetic normalized or Particle ASTM A637, Grade B Q&T 9,13 Spreader and ASTM A350 LFI -- --

Mounting Block Forging Ultrasonic Magnetic Particle 10,12 Spreader Arm ASTM A36 -- --

Leg Channel --

Visual 11 Leg Lug ASTM A516, Ultrasonic Magnetic Grade 70 Particle

(*)See figure A-2  !

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62598:1/032483 A-7 p - - -

9 - --. - p

TABLE A-3.(cont)-

. REACTOR VESSEL' INTERNALS' LIFT RIG CRITICAL ITEMS LIST OF PARTS

'PER ANSI'N14.6-1978-Non-destructive Testing ItemI ")-

. Description Material. - Material Finished 14' Load Nut ASTM A276, -- --

Type 304, Hot Rolled,,

. Condition A

< 15,16 Rod Housing ASTM A276, Ultrasonic- --

Guide Sleeve - Type 304, Liquid Hot Rolled,. _ _ Penetrant Annealed

& Pickled, Condition A 17 .Rctolock Stud ASTM A564, Ultrasonic Liquid

' Type 630, Penetrant 17-4-pH

[ H-1100 i

e (a) See figure A-2 9

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L 62598:1/032183- A-8

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l y g. ,.w--,-A g77., y .% s

,.,, c .- g.., , , ewe *MM * -P'**

l TABLE A-4 REACTOR VESSEL-INTERNALS LIFT RIG CRITICAL ITEMS LIST OF WELDS -

PER ANSI N14.6-1978 Non-destructive Testing Item- Description Root Pass Final 1,2 Lugs to Lifting Block Magnetic Magnetic (Full Penetration) Particle Particle Radiograph 8,9 Lug to Spreader Block Magnetic Magnetic (Full Penetration) Particle Particle 11,12 Leg Lug to Channel Leg - Magnetic Magnetic

-(fillet) Particle Particle 12,13 Mounting Block to Magnetic Magnetic Channel Lag Part'cle Particle (fillet) 62598:1/032183 -

A-9  ;

v y- ,

s e e

Moonm=

tot Platt uppt A Loao

,~ /AoAPtom Pl=

CELL AoAPron /-

LoAo CELL Lowtm L

. au ao.o,ao. ro 1

REMOVASLE PIN ' f,4 g j amanocc e sano moenLu g

, .{ j _ {\

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@ u'rea etsvis mm - j?,if

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- @ usena suma ctsvis

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Figure A-2. Reactor Vessel Internals Lift Rig 62598:1/032183 A-10

APPENDIX B TABULATION OF ANSI N14.6-1978 REQUIREMENTS INCOMPATIBLE WITH THE VIRGIL C. SUMMER 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 compli-ance with all the ANSI N14.6 requirements. Listed below is a tabulation of those sections of ANSI N14.6 considered most important in demonstra-ting the continue'd load handling reliability of these special lifting devices. Associated Westinghouse remarks are also listed and'could be used as suggested actions and/or responses to demonstrate compliance to the NRC.

la. Requirement:

Para. 3.1.4 - requires the designer to indicate permissible repair procedures and acceptance criteria for the repair.

Ib. 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 identified in NF-4000 and NF-5000 (Fabrication and Examination) of the ASME Boiler and Pressure Vessel Code,Section III, Division 1 Sub-section NF.

2a. Requirement:

Para. 3.2.1.1 -requires the design, when using materials with yield strengths above 80 percent of their ultimate strengths, to be based on the material's_ fracture toughness and not the listed design factors.

16259B:1/032183 B-1 6

1 2b. Remarks:

High strength materials are used in these dev. ices. Although the fracture toughness was not determined, the material was selected based onit's fracture toughness characteristics.

HowevIr, in lieu of a different stress design ~ factor,- the stress design factors listed in 3.2.1 of.3 and 5 were used in

~t he'an'alysis and.the resulting stresses are considered acceptable. -

3a. Requirement:

Para 3.2.6 requires material for load-bearing members to be subjected to drop-weight or Charpy impact tests.

3b. Remarks:

Fracture' toughness requirements were not identified for all the material used in these special liftir.g devices. However, the material selection was based on its fracture toughness charac-teristics.

4a. Requirement:

Para. 5.1 lists Owner Responsibilities and 5.1.2 requires the owner to verify that the special lifting devices meet the performance criteria of the design specification by records and witness of testing.

4b. Remarks:

There wasn't any design specification for these rigs. A 125~ percent load test followed by the appropriate non-destructive testing was performed. In addition, the Westing-house Quality Release, may be considered an acceptable alternate ~to verify that the criteria for the letters of compliance for materials and specifications required by West-l inghouse drawings and purchasing document were satisfied.

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62598:1/032183 8-2

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l Sa. Requirement:

Para. 5.1.3 requires. periodic. functional testing and a system

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'to indicate' continued reliable performance.

Sb. ' Remarks:

Maintenance and inspection procedures-should include a visual check of critical welds and. parts during lifting to comply with t'is n requirement for functional testing.

6a. ; Requirement:

Para. 5.I'.5, 5.1.5.1 and 5.1.5.2 require special identification and marking to prevent misuse.

6b. 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.

7a. 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.

7b. Remarks:

Operating instructions and maintenance instructions should be reviewed to assure that they contain the requirements to address maintenance logs,. repair and testing history, damage incidents and other items mentioned in these paragraphs.

8a. 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.

62598:1/032183 B-3

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8b. Remarks:

Both the reactor vessel head and internals lifting rigs and load cell were. proof tested-upon completion with a load of approximately 1.25 times the design weight. .Upon completion of the test, all parts, particularly welds, vere visually inspected for cracks or obvious deformation and critical welds were magnetic particle inspected. In addition the Westinghouse Quality Release verified that the criteria for letters of compliance for materials and specifications required by the Westinghouse drawings and purchasing documents were satisfied.

9a. Requirement:

Para 5.2.2 requires replacement parts t.- be individually quali-ficd and tested. ,

9b. Remarks Replacement parts, should they be required, should be made of identical (or equivalent) material and inspections as origi-nally required. Only pins, bolt and nuts are considered replacement parts for the reactor vessel head and internal lift rigs.

10a. Requirement:

I Para 5.3 requires testing to verify continuing compliance and j annual 150 percent load tests or annual non-destructive tests and examinations to be performed.

I I 10b. Remarks These special lifting devices are.used during plant refueling which is approximately once per year. During plant operation these special lifting devices are inaccessable since they are permanently installed and/or remain in the containment. They cannot be removed from the containment unless they are disas-sembled and no.known purposes exist for disassembly. Load testing to 150 percent of the total weight before each use 62598:1/032183 8 - - . _- .

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-: .would require special-fixtures and is impractical to perform.

Crane capacity could also be limiting. It is suggested that a

-check (visual) of critical welds and-parts be conducted at

~

initial lift prior to moving to full. lift and movement.for

-these devices. Further note that with the use of the load cell

-for the head and internals' lift. rig, all lifting and -lowering is' monitored at all times.

2.

SUMMARY

.The ANSI requirements for periodic checking and functional load testing appear to be-most difficult to demonstrate compliance. It is almost impractical to perform the 150. percent load 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-destructive testing, (visual-only) in the' critical parts and welds.

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-62598:1/032183 8-5

WESTINGHOUSE CLASS 3 ATTACHMENT B to WCAP-10233 Although information contained in this report is nonproprietary, no distribution shall

__ . be_ made outside Westinghouse or its licensees without the customer's approval.

' STRESS REPORT REACTOR VESSEL HEAD LIFT RIG, REACTOR VESSEL INTERNALS LIFT RIG

.AND'THE LOAD CELL LINKAGE FOR .

SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER' PLANT f.pril, 1983 H. H.-Sandner, P. E.

Appr ved: /3 --

1. 14

. R. 7arshall, P. E., Mmeger Refueling Equipment Engineering l

62658:l/032483

o ABSTRACT A stress analysis of the Virgil C. Summer reactor vessel head and

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internal lf_ft rigs load cell and load cell linkage was perfonned to detennine the acceptability of these devices to meet the design requirements of ANSI N14.6.

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. ACKNOWLEDGMENT

' Acknowledgment is hereby made to the following individuals who contri-

' buted to the structural analysis presented in this report.

J. S.-Urban l F. Peduzzi J. ' Richard 3

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TABLE OF CONTENTS Section _

Title Page ABSTRACT 111~

l INTRODUCTION 1-1 1.1~-Background. 1-1

'2 CDMPONENT DESCRIPTION 2-1 2.1 Reactor Vessel Head Lift' Rig 2 2.2 Reactor Vesse1' Internals 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 4 MATERIALS 4-1 4.1 Material Description 4-1 i

5

SUMMARY

OF RESULTS 5-1 5.1 Discussion or hesults 5-1 5.2 Conclusion 5-3 APPENDIX /L DETAILED STRESS ANALYSIS - REACTOR VESSEL HEAD LIFT RIG A-1 i

APPENDIX B DETAILED STRESS ANALYSIS - REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LINKAGE' B-1 6265B:1/032483 v

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, c- . LIST OF ILLUSTRATIONS Figure '-

Title Page

.5-1 Reactor Vessel-Head Lift Rig 5-14 2 Reactor Vessel Internals Lift Rig, Load Cell and Linkage 5-25 r

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LIST 0F TABLES Table

' Title ~ Page 4-1 Reactor Vessel Head lift. Rig Material and Material Properties 4-2 4-2 Reactor Vessel Internals Lift Rig, Load Cell'and Load Cell Linkage Material and Material Properties 4 5-1 Summary of_Results - Reactor Vessel Head Lift Rig 5-4 5-2 Summary of Results - Reactor Vessel Internals Lift Rig, Load Cell and Load Cell Linkage 5-15 4

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REFERENCES

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1. George, H., Control of Heavy Loads at Nuclear Power Plants Resolu-tion of _ Generic Technical Actiitty A-36, NUREG 0612, July,1980.

i- 2. ANSI N14.6-1978, "Special Lifting ' Devices for Shipping Containers

- Weighing 10,000 Pounds (4500kg) or More for Nuclear Material,"

i' American National Standards Institute, New York,1978.

3. Westinghouse Drawing 1098E56 Loop Lifting Rig-Head, General Assembly

4. Westinghouse Drawing'1143E65 - South Carolina Electric and Gas Company. Virgil C. Summer Internals Lifting Rig Assembly

5. Lin, C. W., " Approximate Evaluation of Dynamic Load Factors for

' Certain Types of Load Factors for Certain Types of loading," ASME Paper 70-WA/NE-2.

6. Biggs, J. M., Introduction to Structural Dynamics, McGraw-Hill, New York,1964.

7. Gwinn, Jr., J. T., "Stop Over-Designing for Impact Loads," Machine Design, 33, pp.- 105-113 (1961).

< 8. Manual of Steel Construction, Seventh Edition, American Institute of Steel Construction.

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SECTION 1 INTRODUCTION The Nuclear _ Regulatory Comission (NRC) ' issued NUREG 0612 " Control of-Heavy Load at 'sclear. Power Plants"U 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 .

o'peration 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 "4nerican . National Standard for Special Lifting Devices for Shippin Containers Weighing 10,000 Pounds or More for Nuclar i . Materi al s". 2] In general ANSI N14.6 contains detailed requirements for the design, fabrication, testing, maintenance and quality assurance of special lifting devices. ,

This report contains the stress analysis perfomed on the' Virgil C.

Sunner reactor vessel head lift rig, reactor vessel internals lift rig and the load cell and load cell linkage to detemine the acceptability of these devices to meet these requirements.

1.1 BACKGROUND

The reactor vessel head lift rig, the reactor vessel internals lifting rig and load cell and load cell linkage, were designed and built for the Virgil C. Scmmer Nuclear Power Plant, circa 1974-1976.. These devices were designed to.the requirements that the resulting stress in the load ,

carrying members when subjected to the total combined lifting8]w[eight should not exceed the allowable stresses specified in the AISC 1 code. Also a 125 percent load test was n! quired on both devices, followed by appropriate non-destructive testing. These items were not

classified as nuclear safety components and thus requirements for fonnal documentation of design requirements and stress reports were not applicable. Thus, stress reports and design specifications were not i

62658:1/031783 1 -1 '

. formally documented. Westinghouse defined the design,: fabrication and quality assurance requirements on detailed manufacturing drawings and purchase order documents. Westinghouse also issued field assembly and operating instructions, where applicable, f

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SECTION 2-

.' COMPONENT DESCRIPTION

'2.1 REACTOR VESSEL HEAD LIFT RIG The reactor vessel head lift rig [3] is a thrte-legged carbon steel structure, approximately 43 feet high and 12 feet in diameter, weighing approximately 21,000 pounds. Iti is .used-to handle the ass'embled reactor -

ves.cel head.

The three vertical legs'and control rod drive mechanism (CRDM) platfonn assembly are pennanently attached to the reactor vessel head lifting il 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 removed and the three

vertical legs and platfonn assembly remain attached to the reactor vessel head.

' 2. 2 REACTOR VESSEL INTERNALS LIFT RIG The reactor vessel internals lift rig E43 is a three-legged carbon and stainless steel structure, approximately 30 feet high and 13 feet in j diameter weighing approximately 20,000 pounds. It is used to handle the upper and lower reactor vessel internals packages. It is attached to l ~ 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.

The reactor vessel internals lift rig attaches to the internals package '

l by means of three rotolock studs which engage three rotolock inserts located in the internals flange. These rotolock studs 'are manually

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operated from. the internals lift rig platform using a handling tool which is an integral part of the rig. The studs are nonna11y spring retracted upward and are depressed to engage the inserts. Rotating the mechanism locks it in both positions.

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. The unit shall be a load sensing clevis type rated at 500,000 pounds. This load cell is a part of the load cell linkage which is an assembly of pins, plates, and bolts that connect the polar crane main hook to the lifting blocks of both the reactor vessel head and

. internals lift rig.-

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SECTION 3 DESIGN BASIS l l

I 3.1 DESIGN.fRITERIA NUREG 0612, para 3raph 5.1.1(4) states that special lifting devices should satisfy the guidelines of ANSI N14.6. Further, NUREG 0612, 5.1.1(4) states: "In addition, the stress design factor stated in Section 3.2.1.1 of ANSI N14.6 should be based on the combined maximum static and dynamic loads that co'uld be finparted on the handling device based on characteristics of the crane which will be used. This is in lieu of the guideline-in Section 3.2.1.1 of ANSI N14.6 which bases the stress design factor on only the weight (static load) of the load and of the intervening components of the special. handling device".

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-sive. Also, it can be inferred that the specified ANSI N14.6 stress design factors should be increased by an amount based on the crane dynamic characteristics. ,

The dynamic characteristics of the crane would be based on the main hook and associated wire ropes holding the hook. Most main containment cranes use sixteen (16) or more wire ropes to handle the load. Should the crane hook suddenly stop during the lifting or lowering of a load, a ,

shock load could be transmitted to the connected device. Because of the elasticity of the sixteen or more wire rores, we consider the dynamic i factor for a typical containment crane to be not much larger than 1.0.

l Even if the worst conditions existed, the maximum design factor that is reconnended by most design texts , 6, 7] is a factor of two for 2 i

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loads that are suddenly applied. The stress design factors required in Section 3.2.1.1.o'f ANSI N14.6 are:

3 x (weight) < Yield Strength 5 x (weight) < Ultimate Strength The factor of 3 specified, based on yield strength, is certainly large

.enough to compensate for suddenly applied loads, where the dynamic impact factor would be as high as 2.0.

To provide flexibility on stress design factor, the analysis of the devices was performed with stress design factors of 1. 3 and 5. Thus, any stress design factor may be easily applied to satisfy any concerns.

3.2 DESIGN WEIGHTS

! The following design weights were used in the analysis of the lifting devices:

3. 7. 1 Reactor Vessel Head Lift Rig The design weight is 270,000 pounds which is the total weight of the assembled head and the lifting device.

3.2.2 Reactor Yessel Internals Lift Rig

(

i The design weight for:

a. The Lower Assembly, Items 13 through 17 of calculations; is 202,000 pounds.

b. The design weight for the rest of the rig is 230,000 pounds.

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SECTION 4 MATERIALS ,

4.1 MATERIAL DESCRIPTION )

The materials and material properties for the reactor vessel head lift rig, the reactor vessel. internals lift rig and load cell linkage are listed in Tables 4-1 and 4-2.

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TNBLE 4-1 REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE MATERIAL AND MATERIAL PROPERTIES Yield Ultimate

. _ Strength Strength ItemI ")--

Description Materi al S y (ksi)' S ult (ksi) 1,3,7 Hook Pin ASTM A564, 105 135 Adaptor Pin Type 630 Removable Pin-2 Side Plate ASTM.A588, Grade A, 60 80 Q&T 4,6,8 Upper Load Cell ASTM A508,- 50 80 Adaptor Class 2 Lower Load Cell Adaptor Sling Block

, 5 Load Cell 17-4 pH, SS 115 -140 Condition H-1100 9,15 Link Lug ASTM A588, Grade A, 60 80 Q&T 10,14, 4" Dia. Upper Sling ASTM A434 110 140 18,21 Leg Pin AISI 4340

! Class 80 4" Dia. Lower Sling Leg Pin t

Upper Lifting Leg Pin 3 1/2" Lower Lifting Leg Pin 11,13, Upper Sling Leg ASTM A237, 110 135 17,20 Clevis AISI 4340 Lower Sling Leg Steel, Class G Clevis Upper Lifting Leg Clevis Lower Lifting Leg g Clevis l

(a) See figure 5-1.

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i TABLE 4-1 (cont)

REAbTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE MATERIAL AND MATERIAL PROPERTIES Yield Ul timate ,

Strength Strength Item (a) Description Material S S y (ksi) ult ('ksi) ,

12,19 Aru ' ASTM A306 35 70 Leg Grade 70 16 Spreader Am ASTM A106 35 60 Grade B (a) See figure 5-1.

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, TABLE 4-2 REACTOR VESSEL INTERNALS LIFT. RIG MATERIAL AND MATERIAL PROPERTIES Yield Ultimate Strength Strength ItemI ") Description Material S S y (ksi) ult (ksi) 1 Sling Block ASTM A508, Class 2 50- 80 2 Sling' Block Lug -ASTM A588, Grade A 60 80 3,7 Upper Clevis Pin ASTM A564, - l'05 135 Lower Clevis Pin Type 630 4,6 Upper Sling Clevis ASTM A471, Steel 95 110 Lower Sling Clevis Forging, ClassL 3 5 Sling Rod ASTM A306, Grade 35 70 70 or 80 8 Spreader Lug ASTM A516 Normalized 38 70 or ASTM A637, Grade B, Q&T 9,13 Spreader and . ASTM A350 LFI 30 60 Mounting Block Forging 10,12 Spreader Arm ASTM A36 36 58 Leg Channels 11 Leg Lug ASTM A516, Grade 70 38 70 14 Load Nut ASTM A276, Type 304 30 75 Hot Rolled, Cond. A 15,16 Rod Housing ASTM A276, Type 304 30 75 Guide Sleeve Hot Rolled, Annealed and Pickled, Cond. A 17 Rotolock Stud ASTM A564, Type 630, 115 140 17-4 pH, H-1100

(a) See figure 5-2. '

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i SECTION 5 SLNMARY OF RESULTS Tables 5-1 and 5-2 sumarize the stresses on each of the parts which make up th'e reactor vessel head, load cell and load cell linkage and the  !

internals lift rig. 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 accompanying allowable stress limits of yield and ultimate strength, respectively. In addition, all of the tensile and shear stresses meet the requirement of not exceeoing the allowables of the AISC EO code.

5.1 DISCUSSION OF RESULTS 5.1.1 Application of ANSI N14.6 Criteria Both the reactor vessel head and internals lift rig were originally designed to the requirement that all resulting stresses in the load carrying members, when subjected to the total combined lifting weight, should not exceed the allowable stresses specified in the AISC 03 code.

The design criteria of Section 3.2.1.1 of ANSI N14.6, requiring applica-tion of stress design factors of three and five with the accompanying allowable 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 stresses. Application of these design load factors to other loading conditions is not addressed in ANSI N14.6. - However, these two stress design factors have been used to determine the stresses of the load carrying members when subject to other loading conditions, viz. bending, bearing. This is an extremely conservative approach and in several instances the resulting stresses exceed the accompanying allowable stress limit.

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d 5.1.2 -Structures Loaded in Bearing 6 The parts of the internals lift rig that do not mee.t the ANSI N14.6 criteria'(3 and 5) when analyzed for bearing stresses are the lower

-sling leg clevis (item 6), the lower clevis pin (item 7), the spreader lug (item 8), the leg lug (item 11), and the rotolock stud (item 17).

However, since bearing stresses are localized stresses, they can, if necessary, be considered 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, all of the bearing stresses meet the design criteria of the AISC E03 code.

5.1.3 Combined Stresses The combined tensile stress from bending and tension, in the spreader lug (item 8), of the internals lift rig exceeds the Section 3.2.1.1 l criteria.

Bending, however, is not a uniform stress, but a local fiber stress, and is at maximum at the outermost fiber. Even if the fiber stress reached anywhere near the yield stress, the rest of the cross-section could assume the additional load. As indicated above, bending too can be considered under Section 3.2.1.2. Bending contributes to the major portion of the stress shown in the table, and, as a result, as shown, the tensile stress without bending is extremely low and well within the Section 3.2.1.1 criteria. The combined stress also meet the AISC code criteria.

5.1.4 Fillet Weld Stresses l

l The fillet weld connecting the leg lug (item 11) to the leg channel (item 12) on the internals lift rig meets the ASME criteria for weld l 6265B:1/032483 5-2 n, ,- , - , . , , , - - , . - , , , - - , ,

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- stresses based on base material properties. However, when applying the ANSI N14.6 3W an' d SW criteria to the nominal stress value, the ASME Lallowable stress value is exceeded. But, since the ANSI N14.6 criteria is satisfied for this weld, it is considered acceptable.

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 conservatism 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. In conclusion, these special lift devices meet the ANSI N14.6 criteria for tensile and shear stresses and meet other appropriate criteria for loading conditions that result in combined and bearing stresses.

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TABLE 5-1

SUMMARY

OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD. CELL LINKAGE-ii Calculated. Stresses (ksi) Material Allowa'ble

Item a) Part Name Value ' (k s'i ) ' -

W IDI-e No.: And Material. Designation -

3W 'W:

5 Sy (c) 3 ult 1 ' Hook Pin Shear 3.1 9.31 - 15.5' 105 135-ASTM A564, -Bearing on Pin 4.1 12.3' 20.5 Type 630 Bearing on Side Plate 4.5 13.5 22.5

^

Bending 11.8 35.4 59.0 k.

2 Side Plate Tension at 7.515" hole 3.8. 11.4 19.0 60 '~ 80

, ASTM A588 Bearing at 6.515" hole 5.2 15.6 . 26.0

! Gr. A, Q&T Shear Tear-out l at 7.515" hole 3.8 11.4- 19.0 at 6.515" hole E.2 6.6 , 11.0 i

(a) See figure 5-1 for location of item number 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) y

'(d) S ult is the ultimate strength of the material'(ksi) 62658:l/032483 . ,

. ;. .o TABLE 5-1 (cont)

SUMMARY

OF RESULTS.

REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE Calculated Stresses (ksi) Material A11pwable Iten I8) Part Name Value (ksi)

No. And Material Designation W(b)- 3W SW S,(c) S ult 3 Adaptor Pin Shear 4.1 12.3 20.5 105 135 ASTM A564 Bearing on Pin 5.2 15.6 26.0 Type 630 Bearing on Upper 5.4 16.2 27.0

$ Load Cell Adaptor '

Bending 19.5 58.5 97.5 4 Upper Load Tension at 6.515 hole 3.3 9.9 16.5 50 80 i Cell Adaptor Bearing 5.4 16.2 27.0 ASTM A508, Thread Shear 7.0 21.0 35.0 Class 2 Shear Tear-out 3.3. 9.9 16.5 at 6.515" hole (a) See figure 5-1 for location of item number 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 6265B:l/032483

4 TABLE 5-1 (cont)

SlMMARY OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE t

Calculated Stresses (ksi) Material Allowable Item

• Part Name Value (csi)

No. And Material Designation W(b) 3W SW Sj (c)- 3 (d) 5 Load Cell Tension 14.4 43.2 72.0 115 140 17-4 pH Thread Shear 7.0 '21 . 0 35.0 S/S va

!n 6 Lower Load Tension at Pin Hole 3.3 9.9 16.5 50 80 Cell Adaptor Bearing 6.9 20.7 34.5 ASTM A508 Thread Shear 6.7 20.1 33.5 Class 2 Shear Tear-out 3.3 9.9 16.5 at Pin Hole

. 7 Removable Pin Shear 4. 2 12.6 21 . 0 105 135 ASTM A564 Bearing on Pin 5.1 15.3 25.5 Type 630 Bearing on Link 5.7- 17.1 28.5 Bending 16.9 50.7 84.5

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(a) See figure 5-1 for location of item number 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)

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TABLE 5-1 (cont)

SUMMARY

OF RESULTS 4

REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE Calculated Stresses (ksi) Material Allowable Item (a) Part flame Value (ksi[-

No. And Material Designation W ID) 3W SW Sy (c) 3 ult 8 Sling Block Tension at 6.515" hole 3.3 9.9 16.5 50 -80 Link Shear at 6.515" hole 3.3 9.9 16.5 ASTM A508, Bearing on Pin 5.1 .15.3 25.5 .

[ C1 ass 2 Tension at Cylindrical 5.4 _16.2 27.0 Section 9 Link Lug Tension at 4.015" hole 3.5 10.5 17.5 60 80 ASTM A588 Shear Tear at hole 3.5 10.5 17.5 Gd.A, Q&T Bearing at 4.015" hole 6.1 18.3 30.5 Combined Stress 5.7 17.1 28.5 froe Tension and Bending Vertical Shear 1.8 5.4 ' 9.0 (a) See figure 5-1 for location of item number and section (b) W is the to'al 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 6265B:1/032483

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TABLE 5-;l(cont)

StMMARY'0F RESULTS' ,

. REACTOR VESSEL HEAD LIFT RIG AND' LOAD CELL LINKAGE 2 l

2

- i, Calculated Stresses (ksi) Material Allowable Item

• Part Name Value (ksi)-

Designation -W IDI Sy (c) 3 (d)

$ No. And Material 3W, 5W 10 4" Dia. Upper Shear 3.8 ,11.4 19.0 :110 140 I Sling Leg Bearing on Pin 6.1 -18.3 30.5:

Pin Bearing on Upper .6.4 19.2 - 32.0 -

ASTM A434 Sling Leg Clevis Bending 14.6 .43.8 73.0

[ 11 Upper Sling Bearing . 6.4 19.2. 32.0 -110- 135' i Leg Clevis- Thread Shear 2.7 8.1 13.5~

t ASTM A237 - Tension at Thd Relief 1.7 5.1 8.5

,- AISI E4340 Tension at Pin ible 5.4 16.2 27.0-

! Steel,'C1. G Shear Tear-out 5.4 16.2 27.0 I

12 Arm Thread Shear 2.7 8.l -13.5 . 35 70 ASTM A306 Thread Tension 8.9 26.7 44.5 I (a) .See figure 5-1 for location of item number 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 material.(ksi) ,

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4 TABLE 5-1 (cont)

SlMMARY OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE Calculated Stresses (ksi) ' Material -Allowable '

Item

• Part Name Value (ksi)

Designation 3g . Sy (c) 1 (d)

No. And Material W(b) SW 3]

13 Lower Sling Bearing 6.4 19.2 32.0 110 135 Leg Clevis Thread Shear 2.7 8.1 13.5 ASTM A237 Tension at Thd Relief 1.8 5.4 . 9. 0

, AISI E4340 Tension at Pin Hole 5.4 16.2 27.0 1 ,

$ Steel, Class G Shear Tear-out 5.4 16.2 27.0

^

14 4" Dia. Lower Shear 3.9 11.7 19.5' 110 140 Sling Leg Bearing on Pin 6.9 20.7 34.5 i Pin Bearing on Spreader Lug 6.4 19.2 32.0 ASTM A434 Bending 13.6 40.8 68.0 l (a) See figure 5-1 for location of item number 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) y

(d) Sult is the ultimate strength of the material (ksi)

)

l

TABLE 5-1 (cont)

StMMARY OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE Calculated Stresses (ksi) Material Allowable Item

• Part Name Value (ksi

• No. And Material Designation W II 3W SW Sy (c) S (d) ult 4

15 Spreader Lug Bearing on 4.005" Hole 7.0 21 . 0 35.0 60 80 ,

4 ASTM A588 Tension at Upper Hole 4.7 14.1 23.5 Gd.A Steel Shear Tear-out 4.7 14.1 23.5 Plate V' 16 Spreader Arm Nominal Compression 1.7 5.1 ' 8.5 35 60 5 ASTM A106 Stress F= 19545I *I Gd.B Seamless Weld Shear 1.0 3.0 5.0 lhfI (a) See figure 5-1 for location of item number and section i (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)

(e) F, is the compressive buckling strength of the material (ksi)

(f) Stress limit for fillet weld from ASME Boiler and Pressure Vessel Code,Section III Division 1 -

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Subsection NF 1980 Edition, Table NF-32921-1, page 43.

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TABLE 5-1 (cont)

SIMMARY OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LIKAGE Calculated Stresses (ksi) Material Allowable Item

• Part Name Value (ksi) -

Designation II Sy (c) g No. And Material W 3W SW ult 17 Upper Lifting Bearing 5.9 17.7 29.5 110 135 Leg Clevis Thread Shear 2. 5 7.5 _12.5 ASTM A237 Tension at Thd Relief 1.7 5.1 8.5 u, AISI E4340 Tension at Pin Hole 5.0 15.0 25.0

$; Steel Class G Shear Tear-out 5.0 15.0 25.0 18 Upper Lifting Shear 3.6 10.8 18.0 110 140 Leg Pin Bearing on Pin 6.4 19.2 32.0 ASTM A434 Bearing on Clevis 5.9 17.7 29.5 Bending 12.5 37.5 62.5 (a) See figure 5-1 for location of. item number 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) 4

TABLE 5-1 (cont)

StMMARY OF RESULTS -

REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LIIKAGE Calculated Stresses (ksi) Material Allpble Item Part Name Value (ksi)

• No. - And Material . Designation W(b) 3W SW S ICI- S y ult 19 Leg Thread Shear 2.5 7.5 12.5 35 70 ASTM A306 Thread Tension 8.1 24.3 40.5 Gd.70 3 20 Lower Lifting Bearing 6.7. 20.1 33.5- 110 '135-

" Leg Clevis Thread Shear 2.5 7.5 .12.5 ASTM A237 Tension at Thd Relief ,1. 8 5.4 9.0 AISI E4340 Tension at Pin Hole 4.5 13.5 22.5 Steel, Class G Shear Tear-out 4.5 13.5 22.5 .

(a) See figure 5-1 for location of item number 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) 9

p TABLE 5-1 (cont) ,

StMMARY OF RESULTS REACTOR VESSEL HEAD LIFT RIG AND LOAD CELL LINKAGE Calculated Stresses (ksi) Material A11'owable Item

• Part Name Value fksil Designation W(b) ICI (d}

No. And Material 3W SW S y

S ult 21 31/2" Lower Shear 4.7 14.1 23.5- .110 140 Lifting Leg Pin Bearing on Lug 8.6 25.8 43.0 ASTM A434 Bearing on Clevis 6.7 20.1 33.5 AISI 4340 Bending 18.0 54.0 90.0 Class BD T

C (a) See figure 5-1 for location of item number 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)

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Figure 5-1. Reactor Vessel Head lift Rig 62658:1/03g4g3 S-14 e

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_ 1 TABLE 5-2 t SIMMARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable:

. ItemI " (ksi) l Part'Name Value I

W ID} N' :S IC)

No. And Material Designation .W y Q dI' >

6 1 Sling Block Tension at 6.515" Dia. Hole 2.8 8.4 14.0 50 - 80 ASTM A508- Bearing at-6.515"-Dia. Hole 4.4 13.2 22.0-Class 2 Shear Tear-out at 6.515" Dia. Hole 2.8 8.4 14.0 ,

Tension at 8.00" .

Cylindrical Section -4.6 13.8- 23.0 m 2 Sling Block Lug Tension at 4.015" Dia. Hole 3.6 10.8 18.0 60 80' .

h ASTM A588 Bearing at 4.015" Dia. Hole 6.3 18.9 31.5 Grade A Steel Shear Tear-out at 4.015" Dia. Hole 3.6 10.8 18.0

~

Vertical Shear at Lug '

Root Weld 1.5 4.5 7.5 Combined Tension from 8end-ing and Tension at Lug Weld 5.2 15.6 26.0 (a) See figure 5-2 for location of item number 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) S ult is the ultimate strength of_the material (ksi) 62658:1/032483 ,

.- _ _ _ _ _ _ m

(

TABLE 5-2 (cont)

SUMMARY

OF RESULTS

-REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi). Material Allowable Item (*) Part Name -

Value (ksi)' a No.- And Material Designation W(b) .3g. SW S IC) S y ult s

3 upper Clevis Shear Stress 4.0 12.0 20.0 105 _135 Pin Bearing Stress ASTM A564 on Sling Block Lug 6.3 18.9 31.5 Type 630 Bearing on Upper Sling Clevis 5.2 15.6 26.0 j" Bending Stress 15.7 47.1 78.5 5

4 Upper Sling Tension at 4.015" Dia. Hole 4.0 12.0 20.0 95 110 Clevis Bearing at 4.015" Dia. Hole 5.2 15.6 26.0 l ASTM A471 Shear Tear-out at 4.015" Steel forging Dia. Hole 4.0 12.0 20.0 Class 3 Thread Shear 4.2 12.6 21.0 (a) See figure 5-2 for location of item number 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 j is the ultimate strength of the material (ksi)

• 62658:l/032483

, .b

z-s3

.p,- >g .

, a TABLE 5-2 (cont) .,

SLMMARY OF RESULTS. ,

REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) ' Material Allowable Item (a) Part Name Value (ksi)

No. And Material Designation W(b) 3W SW- S ICI S j uit 5 Sling Rod Thread Shear 4.2 12.6 '21.0 _35 ~70 ASTM A306 Thread Tension 9.0 27.0 45.0 ,

Grade 70 or 80 Tension at Thread Relief 9.7 29.1- '48.5 6 Lower Sling Tension at 4.015" Dia. Hole 4.0- 12.0 20.0. 95 110-Leg Clevis Bearing 30.0 90.0 150.0

^

ASTM A471 Bending at 4.015" Dia.. Hole 17.8 153.4 89.0 Steel Forging Combined Max. Bending and Class 3 Tension at 4.015" Dia. Hole 21.9 65.7 -109.5 Thread Shear 4.2 12.6 21.0 (a) See figure 5-2 for location of item number 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).

l 62658:1/032483

_ __ . _ . ~ _ , __ _ . .. . . __ . _

TABLE 5-2.(cont)

SLMMARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable Item

• Part Name value fksi)

No. And Material Designation W(b) 3W . 5W S ICI S j ult 1 7 Lower Clevis Maximum Shear at Clevis 8.0 24.0 40.0 105 135 Pin Maximum Bearing at Clevis 30.0 90.0 -1 50.0 m ASTM A564 Bending 15.3 .45. 9 . 76.5 h Type 630 Precipitation Hardening Stain-less Steel Age l Treated at 1150*F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, air-cooled 135,000 psi Min. Tensile l Strength RC 28-31 l

(a) See figure 5-2 for location of item number 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) y (d) Sult is the ultimate strength of the material (ksi)

.cs - . = - ?.

.s ?

f,

~

TABLE 5-2.(cont)  : g

SUMMARY

OF RESULTS'

. REACTOR VESSEL INTERNALS LIFT RIG-Calculated Stresses (ksi) Material A11cjw~able ,

ItemI *I Part Name Value  :(ksi) - '.

No. And Material Designation W(b) y .

3 (c) 3 (d) i s

8 Spreader Lug Tension at 4.015" Dia. Hole 2.2 6.6 11.0- 38 < .70l ASTM A516 Bending at 4.015" Dia. Hole 13.3 39.3 66.5 46.2 77.0-Steel Plate, Combined Tens'on and Bending 15.4 Normalized, or Bearing ,

23.1 69.3 119.5' m A637, Gr. B, G Q&T 9 Spreader Block Bearing on Spreader Block 3.0 9.0 15.0: 30 .60 2 ASTM A350 LFI Forging Steel .

(a) See figure 5-2 for location of item number 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 l(ksi) .

(d) S ult is the ultimate strength of the material (ksi) 62658:1/032483

I TABLE 5-2 (cont)

StMMARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG .

Calculated Stresses (ksi) Material Allowable Item (a) Part Name Value (ksi)'. ,

No. And Material Designation W(b) 3W SW S ICI S y ult 10 Spreader Arm Nominal Compression 3.0 9.0 15.0 36 . . 58 ASTM A36 Steel Stress I 18,929 'I F,=

~

11 Leg Lug Tension 4.015" Dia. Hole 2.6 7.8 13.0 38 70 g ASTM A516 Bending at 4.5" Dia. Hole 7.9 23.7 39.5 Grade 70 Steel Comb. Max. Bending Tension at 4.015" Dia. Hole 10.4 31.2 52.0 Bearing 18.8 56.4 94.0 Weld Stresses 9.4 28.2 47.0 21 III (a) See figure 5-2 for location of item number 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) y (d) Sult is the ultimate strength of the material (ksi)

(e) F =a allowable compression stress to prevent buckling in absence of bending moment (f) Stress limit for fillet welds from ASE Boiler and Pressure Vessel Code,Section III, Division 1 - -

Subsection NF 1980 Edition, Table NF-3292.1-1, page 43. '

6265B:l/032483

- - - = - -

. ~..-. .n h'

TABLE 5-2 (cont)

SLMMARY OF RESULTS

~

REACTOR VESSEL INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable ItemI '} Part Name Value (ksi) l No. And Material Designation W II 3W SW Sy (c). S ult <

j 12 Leg Channels Tension in Legs 5.6 16.8 28.0 36 ~ 58 ASTM A36 Steel 4

13 Mounting Block Bearing of Load Nut to

[ ASTM A350 Mounting Block 1.8 5.4 9.0 30 60 l

~

LFI Forging Shear in Mounting Block Welds 3.1 9.3 15.5 18 III Steel (No CVN

, Test Req'd.)

j Welds: E70-18 Electrodes i

l J

(a) See figure 5-2 for location of item number and section l

. (b) W is the total static weight of the component and the lifting device (c) S, i: the yield strength of the material (ksi) q (d) S ult is the ultimate strength of the material (ksi)

(f) Stress limit for fillet welds from ASME Boiler and Pressure Vessel Code,Section III, Division l'-

l Subsection NF 1980 Edition, Table NF-3292.1-1, page 43.

1 i

62658:1/032483

TABLE 5-2 (cont) '

SLSMARY OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG ~

Calculated Stresses (ksi) Material Allowable Item

• Part Name Value (ksi)

• No. And Material Designation W(b) 3W SW S ICI' 1 S,j g 14 Load Nut ihread Shear 4.1 12.3 20.5 30 75 ASTM A276 Bearing of Load Nut T Type 304, to Mounting Block 1.8 5.4 9.0 0 Hot Rolled, Cond. A

, 15 Rod Housing Thread Shear 4.1 12.3 20.5 30 75 ASTM A276, at 4.00-4UNC-2A Thd.

Type 304 SST, Thread Shear at 3.5 10.5 17.5 Hot Rolled, 5.0-6UN-2A Thd.

Annealed and Tension at Thread Relief 8.4 25.2 42.0-Pickled, Cond. A (a) See figure 5-2 for location of item number 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) y ,

(d) Sult is the ultimate strength of the material (ksi)

__m

- r

..b'l. l3 l '

t

?

, z..-

~

TABLE 5-2 (cont) - t SL9 MARY OF RESULTS -

?-

REACTOR. VESSEL INTERNALS LIFT RIG g:.,

Calculated Stresses (ksi) . Material Allowable ItemI "I Part Name Value- fksi)- -* -

m; No. And Material- -

Designation .W(b) y 9 3 (c): 3 (d).

16 Guide Sleeve Thread Shear 3.5 ~10.5 17.5- 30 75 ASTM A276, . Tension at Thd Relief 8.2 24.6 41.0-Type .104 SST, Bearing of Guide .9.9 29.7. 49.5 ,

r Hot Rciled, Sleeve to Rotolock Stud

} ,

Annealed, and Pickled, ,

Cond. A (a) See figure 5-2 for location of item number 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) ..

62658:1/032483

9 TABLE 5-2 (cont)

SUMMARY

OF RESULTS REACTOR VESSE'L INTERNALS LIFT RIG Calculated Stresses (ksi) Material Allowable Item (*} Part Name Value (ksi)

No. And Material Desigriation W IDI 3W SW .Sy(c) S ult 17 Rotolock Stud Tension at Section A-A 19.5 58.5 97.5 115 140 ASTM A564, Shear of Stud Lands 10.5 31.5 52.5 Type 630, Bearing on Stud Head 9.9 29.7 49.5 17-4 Precipita- Bending in Lands 14.4 43.2 72.0 tion Hardening Compressive Bearing Stress 29.8 89.4 14 9.0 Stainless Steel On Land Surfaces Age Treated at 1100*F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and air cooled T min =

. 140,000 psi (a) See figure 5-2 for location of item number and section -

(b) W is the total stacic weight of the component and the lifting device (c) S is the yield strength of the material (ksi) y .

(d) Sult is the ultimate strength of the material (ksi) 62658:1/032483 . .

9'

• .e.

'e p ,

p Moon Pig

$8DE PLAf t

/

UPPtA Loa 0

. CELL AoaPfon . .4 Aoarfon pig p

l LoAo CELL L

4 ',

8 tantaLoao f .

CELL AoaPfoR a.=ov>= a 3@ u N

n a noc= O L

j j =>=a moc= Lu. e e uma cuv . . f,, 4 s.

- t e u . ..

CLEVIS ,

c - {. .a

- f

1. m NTg ch - m aoo @

n- QAs c

1- r m

'q % c

5. .

E - .. A: .i. 'l F @ ==aosa *a= ,! , ;t *f 3 fi)

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.-[

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w!< ., r .i d ._

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+

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@ LoAoNUT h

$ = =ri noc.

@ aoo ou. F

. h.

' @ outosstasvs h.

@ noTotocauruo Figurs 5-2. Reactor Vessel Internals Lift Rig, Load Cell, and Linkage 62658:1/031783 5-25 L

7 W

APPENDIX A DETAILED STRESS ANALYSIS - REACTOR VESSEL HEAD LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE-This appendix provides the detailed stress anai/ sis for the Virgil C. .

Summer reactor vessel head lift rig and the load cell and load cell 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.

62658:1/031783 A-1

r e

a e.

. SKETCH SHEET stSilNGM00$( FORM 54202 S 0* PROJECT p ar,g  !

UCG-27694 Virgil C. Suniner 1 y 42 IIILE CALCULATtONS NO.

R. V. Head Lift Rio Assembly PDC -

AUTH0R & OATE C H E( i((O SV & QATE h.b'.f[hl?/TA 4kMy Il NO F. Peduzzi J. Richard euRross A=0 AsSUtfSr

, 03' G

1. The purpose of this analysis is to detennine the acceptability of this rig to the requirements of ANSI N14.6.

2. The results show that all stresses are within the allowable stresses.

,q ff.34W ..

W........+t..<g JOSEPH W. RICHARD f>

.e NO.007167E mN _ M y, <;

/

Original Issue F. Peduzzi

, REVISION NO. DATE DESCRIPTION BY

{

RiluLflNG REPORTS, LETTERS 04 MEMORANDAt

= . .

-. WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . .

AGE TITLE ~L o, 42 ReactorVesselHehdLiftRig OATE CMCp.gY QATE AUTHOR OATE CMsCO. a v PROMCT CGE V7.6fajo ut 2/73 u,

&MA4[J# caov, su. c Acc. ~O. ,g. ~0.

aomo.,,,, g

@tm..toao.

au.aomo manceu @

e == . ,,,, ,,

j TWo. @

a e/a,=. moe.u.

, Ny.==- . .

u tu. @

@ =.a su u. e

\

@ am .

' \,' o j ,

f""..'a.-su u...

u. ,,,, g

.tu. \ [s[ t

.e

@ w i. uen uo ,.. y

, . - . - . ..... o l'

. P.

O u. N -

TYW C.o.8

' ~

~\

N ~""~ N D

~ '

@ Lo.ws.uen u new

/,gi_ _

u, a

/

0 n.r em- x%e

\

. . .ys ,

OATg OATE CM.L G. s v AUTHOR Omit CMCD.av REV. MEV.

NO DATE WESTINGHoggg PORM 552130

f; WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE ,

PAGE Reactor-Vessel Head Lift Rig 3 oP 42 PROJECT AUTHop OATE CHK' .sv CH K'D. B Y OATE p,OATE s.o.

CGE $ffoluu!.1/13 0, M M M Up caoua CALC.no. g'E %.

DESIGN WEtGHT .

190,000 lbs f rom ASS N OwG ( loit ESQ ll; 00 o I b.5 9 p o rt Ib3 M Cong't ing enciesan d Pl.gtform A5 1 1 o 00o \b5 3 ,

SLING LEG ANC3LE n

4 I

c4 = 1 1, 7 *

\ -

MEV MEV. AUTHOM OATE CH K'O. s v QATE CH K'O. 8 V OATE NO. DATE WESTINOHOUSE POMM 902130

}

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , .

l L TIT LE **s

, Reactor Vessel Head Lift Rig 4 0, 42 PROJECT AUTHOR OATE CHK'O.SY Cpfs CME'O. e v OATE S O.

CGE 5.C.ib .W2/13 & k M fff CALC. NO.. 9t E NO. ORou9 UCG-27694 REE loa 0 CELL LINK %E A55D46LY Y

C ~1- MOOK S

\ NN '

-H  : HOOK PIM t

4  : S10E Pl. ATE

/>h  :

AD6PToR PIN ~6

((tLEEQ,fppoR q L0 AD C.El.L 5

lower LO AD 6 x CE LL A D APToR

-l- l

Rem ova b le g em g

I W

REv. mgy, AUTHOM OATE CHn0.av OATE CH K'O. av OATg NO. DATE WESTINGHOUSE FORM 802130 L.

• - WESTINGHOUSE NUCLEAR TECHNOLOGY DIV!SION TITLE PAGE Reactor' Vessel Head Lift Rig 5 on 42 P R OJECT AUTHOH DATE CH K' Sy ATE CH K'O. a v OATE S .O .

CGE T1.d '992m'2/73 CALC. NO. VD (rK '

.E NO. GROUP UCG-27694 REE

$ H E A R, STRE SS.

g

, m ar't.: hSTM k 564 ;T1PE 630 fy = P/2.A, p= p o,cco

'*- Hoo k Ay= Trd%

. t 3 >T .,_

%' As = Td u W4 LI4. lf in t a

Av=

L.

~

v = ( 170 OOC)/h*

j qq,[T )

I

., 1" l [v =

305b P i!.

-e, gs P/ y'2 Load c4LL A'nV.

Sid e P Ld*

P = b=. a c.M3 o n a cq,16. BE ArsING STRESS d = diameter of p cn , in .

.f lenph of bearino :.urfecc. '

-fc = P/As of e.eser hosyn. P = D oicoD a'= IAwph of beank serLc. TNNER er . Mac. ef ea/ bea3,,s - Av - a .9 = ( 7s X 7.05) g = cpp Lbeen Wri$ =( h 6. 56 )ins se efecc.s, in. Sc. = (llo,000)/( b6.5b)

L w i ac s . w +.x 3 of o

pA pa +c = 405b F3

= b 2(a +g )

OUTER P = mee is. A,- 2 aa= 2(y.co )( 7.s 3 d = 15 in. =( 6 o. o hn' J = S. Os is. ( = ( 270,000 )/( 6 o. o )

a = 4,0 o tw g= .0615 rn [c. = 4500 Pc.

r A te -wi.oo) - (7.Tuh.7i3 h .

REV. REV. AUTHOR OATE CH K'O.SY DATE CH K'O. S Y DATE NO. DATE WESTINGHCUSE FORM 552130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

TsTLE ,

PAGF Reactor Vesse1 Head lift Rig b On 42 PROJECT DATE CH K'O. v OATE C M K'U. S W DATE ApTHOR

-CGE 4,0.TSh 2/73 MK -

S O. C A LC. No. UQ NO. GROyP PI N g BENDEN6 STRE55 W M=$(Iav3'+4J)

~

.f3 = M c /I I = v clWi c= d /2.

b* $ b* E Y 'b

=lGP(3a+g$*h.9 +

)/(Trd )

3 5

g({t.opsf%/g7.5

= 170;oo o (.0430)

=.11JToPSI i

l N ADAPTY.D PRCM FKTENI% AND JOININ(5, MD Ed , A e s ss as N c t s '.4.u OF M ALMIN% CE'. r6N , BN1CM P43tILHth .

hA4E 19 REV. REV, AUTHOR OATE CH K* 0. 3 Y CATE CH K

• 0. S Y DATE NO. DATE ,

. WESTINGHOUSE FORM 552130

, . . WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE

.so;ECT Reactor ~ Vessel Head Lift Rig Aur-oa oATE Csx o.av CHCO.SY 7 o, 42 QATE 6,C.8)ul' 2FC $M M yg g care CGE S.o. CA cc. ~o. yg gE wo caoue 1 SIDE P L A TE - ASTM - Asn c, R. A ,

o47 P

n

.- 7.515

,' N A ./

A .

t 4 t

% 9.00 ThK B B II.o 1  % b.515 l

%s .

ff Tens ion @ 7.515 H ole, fi.=.P/22 k:g ( l6.5  ?.5IS )b1.O) 3S. 99 I n

• At Pt as joon =. 3 75% P S I 3s,14 i

Seacing @ 6516 $ Hole S:c P/z :- ns;oot -

Slfo PSI k ( b. Sis)(4 )

l l

l REV. REV. AUTHOR OATE CHK'Q. S Y QATE CH K'O. S Y DATE NO. DATE WESTINGHCuSE FORM 552130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

TITLE ,

PAGE Reactor Vessel Head Lift Rig T OP 42 PROJECT AL THOR DATEICHK'O ATE CHK'O. e v QATE CGE- 6.f, M M 2/73 CM2eY '

L{l'if2 s .O . CA G.NO. W E NO.

~

GROUP S hear Tear out

%= A 1AV

@ '1. 5 l 5 $ h al t -

fv: 13 5 mm = 3156 PSI

.~2iTlTGb.3L1 4 -

t . t

@ 6.5'l5 & H ole fv= ns oon = 0.170 P S I

2. f '\ \.0 - foSid ( 4 )

\ 2. )

e e

AUTHOR OATE CHK'O. S Y CATE CH K'O. S Y DATE R E V. REV.

NO. DATE WESTIN3C'.'SE FORM "5J130

0-o . WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l

TIT L E PAGE j Reactor Vessel Head Lift Rig 9 On 42 l PROJECT AUTHOR DATE CHK'O gy jOATE CH K'O. 8 Y C A 'E S .O .

CGE QI.diflim' -2/75 CALC.NO, G()

h F@ NO.

GROUP UCG-27694 REE k0h 9 T o R SHEAPs STRE.ss 3

PIN m ar't.: hSTM A5U T1PE b30 f v-= P/2. A.

P = 1M000 lb.

w ~ uqst a onnet Ay= Trd%

g 4 > , _; ,g As = TM 6.so )%

a Av= 33.iT in'

= ( Do o00 ) /(2.* 33,lT )

- ~~

L-  ; v j La ._, I "'I hv =

4 0 b9 P si.

.e s Y2 qs

% sips Pt. ATE P= 6 c.e en3on a m a,,is, sgAgrmc., stats 3 d - diamdce of p in, in .

S=len$th of heartn3 :.urfke.

-f,. - P/ As of c.cdce body in. P = rz o,co o ib.

a = lsw3w of beari 3 serb.c. TNNER en:. s.{de. of omkr bed3 ph . Av = a .9 = (. 6.so X ,.n )

g g ap b.b can 6 cih3 =( $0,3 f )int surfacc.h in. -fc. = ( 120,000)/( 50.37')

L wei ac.p i.5+.x of pik A 3 [c.= 5 3 T9 Ps.I

= J + '2(a +g )

OUTER P = no, coo is. A,- z ad= 2( 9,00 )( c.50 )

d= b.50 in. =( 51.o ')in' J = 7.75 is. 7.15 -u.25 ) -fc = ( T70,00o )/( 52,o )

a= 4,00 tw g= 615 in [c, = 5l91 es:r.

C n,o o + 7 / .153 -7(9,co')-1,15T?.

REV. REV. AUTHOR QATE CH n'O. a v OATE CH K'O. SV GATE NO. DATE WESTINGHOUSE FORM 552130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . .

TITLE PAGE Reactor Vessgl Head Lift Rig ( 0 On 42 PROJECT AUTHOR QATE CH K'Q. S V QATE CH K'O. S Y QATE S 0.

CGE $.f. f E 2/73 4RM CALC.NO. OG FI LA NO. GROUP UCG-27694 REE PI N 3 BENDrN6 STRE55(2) ~

M- = f(i a+ S +4 J)

.f3 = Mc /t 1=va%s t= d /2 ~

fs, ? (ia +p A f)(t)(O)

=%P(3 a4g + 6, ) )/(Trda)

= l(o9 ( % 4 O i

= (rl0,000)(.OMb

. \ 9 ) 5 0 % 9 5 1 ADAPTY.D PROrq I

FMTENI% AND JOININ C:r , ,

MD Ed, A amasNf.t. zwua op t'.ACHIM% DELI 6M , MtGM Pu3C!.Hth PME *i. 9 REV. REV. AUTHOR OATE CH K'O. S Y DATE CH K'O. S V OATE NO. DATE WESTINGHCUSE FORM 552130

I.

. . . WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE 4 P A C.E Reactor Yessel Head Lift Rig ll o, 42 PROJECT AUTHOR OATE CHK'O. S Y OATE CH K'O. S Y DATE CGE .~

6.C.fah' 7&3 h,9

• S .O . CA LC. NO. V" F Q E ND. GROUP UCG-27694 REE U P PE R LO AD C ELL A D APTo R M W L. ASTM A- sor, cla s s 2.

"wi.75__,

FvLLR -

b.515 p _ .7.5 ^ 9 5 A \ -

Both ends t

4' g 3 t \"

xxy ., .Y1 Thd. Ret'ei P ~ 24 i i N

w is g i t i O k f13-*  % s.co- Tun u A S.co DEE P *

.: lb.50 >

Tension q+ 5ection A- A (Pm hole)

P te _P_ /H (I b. 5 - b. 51$ XT.I.5) - 6) l.159= T2.15 ln' .

At Pe= Co. coo- = 6M3 PSI 31.1 5 beetring Sicess T h-c bf a rincy Si0e56 i s t h f <>ct g e q $ t- h e t vin e r bearing Sif ess on the pin Q)

PC= riornn  : 5 '5 5 1 P S I 50,37 REV. REV. AUTHOR OATE CH K* 0. 3 Y DATE CHK0.SY DATE NO. DATE WESTINGHOUSE FORM 552130 I

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . .

TITLE PAGE Reactor Vesse1 Head Lift Rig 11 On 42 PROJECT AUTHOR OATE CH K'O. S V ATE CH K"D. S Y DATE S .O .

CGE $f.

CALC. NC bh 1173

. (/ I N

QE NO.

~

GROUP UCG-27694 REE Theegd Shene '

f v = _2. 3 A v : n D pitc h t L/ 2 AV p pitc h = D nom ~~ . L'i 3 51 l n -

. Dpitch = (5.00) ~.b9957/7 -

=

9 ilT1!iI tA.

D nom = ma3 oc dia m*if e of extended th rod n = numbe e of +hre<d / in 1 = Le ngih c-f + bread engage ment

= 5.00 i n.

TheftTore hv = 1 F. b 3 m*

tv= r e nem = b9 79 PSI 39.63 s h ear Tear out Pa en L L e I + o Sectio n 6- P; ( Pin Hole) fv= _P__ Av= '( T.25 - b.si9 (T.15)-2.(l)(,15)2 H,11 i n

)

la v 2.

Fv : uo. con - 3113 PSI II41.11)

REV. REV. AUTHOR OATE CH K'O. 3 Y OATE CH K'O. S Y DATE NO. DATE WESTINGHOUSE FORM 552130 '

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Reactor' Vessel Head Lift Rig . 13 On 42 PROJECT AUTHOR DATE g DATE CH K'O. 8 v OATE CHKK.SY S .O .

CGE Qt.C.f Mwu2/73 kK CALC.NO. .E N O.' ~

' ;bd '

GROUP UCG-27694 REE hLOA0 CELL - M af L . [1 - 4 P H S / S 6hR uP F

A k 4 t

\ 5 -TUN 1h Tension at 4-A P6 .f_

66 From Mark's 1%dbek eor MEs 7% Ed 3 PT-13 04= ( F. l m l Ft = 7 7 0, 0 0 n = typ3q PSI I T.'?

Thrend 5henc The +hrend shencin st ress is th e s a m e as For tht. q d a pior s fv= 69 71 P SI REV. REV. AUTHOR OATE CH K'O. S Y DATE CHK'O SY DATE NO. DATE WESTINGHOUSE FORM 552130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION o .

flTLE . .

PAGE I Reactor Vessel Head Lift Rig 14 c. 42 PROJECT A THOR- DATE CH K'O. a v ATE C H K" O SY OATE s.o.

~CGE dif ihi 2fB CALC,NO. U$

3k Fil.# NO. GROUP

-UCG-27694 REE

(, L o w E R. L o 60 CE LL A-D APT 0R.

M d'L. bT M A -30 7 3 Class t

!: lb50  :

5 - TVN-LB 2

.//) Y l -

uo

'/,!~~ I/

- x -. s .

,., tsus e g,1 69

, , N -

g_ q ve x xxx x xxx xx x s Isj ld r us,i te 4 4 50 -

sl i, si

_ _ _.J y _a L_ _ _

l A i A a

3 x

- .- 'N .

B~ .

Ng REV. REV. AUTHOR OATE CH K'O. 3 Y CATE CH K*O. S Y OATE NO. DATE WESTINGHOUSE FORM 552130

• 1

.. . WESTINGHOUSE NUCLEAR TEdHNOLOGY DIVISION TITLE .

PAGE Reactor Vessel Head Lift Rig . l5 On 42 PROJECT AUTHOR DATE CHK*O SY # ATE C H K' O. S Y ~ OATE S.0, CGE 6. C. b cM2/73 CALC. NO.

0. NUM ~

GROUP pE NO.

-Ttnston at S echi o n- A- A ( Pin hol#.)

ft= !L2. ) At:(.16 5-6.515X4,115)-U.265-L.515)(.5): 9 o,Yi inl ftt Et= l3 S ooo /40.T1 = 33 0 T P SI j

h e ei n g . s t c ess. @ Pin Hole The bearing stress the same n 45 the outer-beqring stress on the pin U7 f c = 17 0,000  :. 1439 PSI a.s t \

Thregi Shenc f v = 1_ 3 4 v = n 0 pikk V L / 2,

/tv 0 p itch = Dnom' . b'i952 / n D p ltch = ( 5 00) .69952 /T

= H.311rTl in.

Onom = rn ojor dia m eic r of ext ernal th rend n = numb er of %ce.qd / in  ;

i l

REV. REV. AUTHOR OATE CH K'O. 3 V OATE CH K*O. S Y OATE NO. DATE

. WESTINGHCUSE FORM 552130 I

[s' WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . -

1

. l TITLE ,

PAGE Reactor Vessel Head Lift Rig [6 on 42 AUTHOR DATE CH K'O Y p CM K'O. S v OATE EROJECT CGE & (* '93 AJ 21n (yYYn)YTE s .o . - CALC.u o. as age No: Gaour JL = Len$ th of thrend enojayemeni

= 5.15 in .

TherefOre A v= ,90. 5 6 9 in' fv = 17o;oon- = 6656 P5I H0.564 Shee rear -out Paralle t ta sec % (Pin Hole) f v = _P__ a y = ( F.25- 6.515 (9.125)-(7.%5-6.515)(.5)

)

lov 1 Av : .~1. 0 . 1 '2. ( n1 fv= 13 5; o00 - = 3337 PSI 1 (10.123 i

l l

l l

l AUTHOR OATE CH K*D. 3 v OATE CN K'O. S Y DATE REV. REV, NO. DATE

' WESTINGHOUSE FORM $52130

.' . " WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Reactor' Vessel Head Lift Rig DATE CH K'O. ATE CHK'O BY 17 or 42 PROJECT AUTHOR .

Y CATE S .O .

CGE 6.C.NDS CALC. NO OM 9

p E'ND .

GROUP UCG-27694 REE REMOV AB LE. S H E AR, STM55

' PIN l mru astm 4-ses r#E63o f, - P / 2. A ,

P= 1,o;oco ib A,= in(a -4tF/4 g A, = n(6.s t-i.11s9 /y

.T.>% "%

a Av= n.19 in t g

d [v = { 1-fo,cco ) /(?_= 31l9 )

c.  ;

at ,,

, -a w l "I hv =

L+ 1 9 4 PSI T \s

% tower Led cett. Adapter - .

P= fonc ecun3 on as:cmW y,th. BE ARINC, STrsESS j

d = diam.kse of pin,in.

9=lenSW of bears'n3 surfme. -fc. - P/A, of c.cw4. e body ,in. P= llo,cco ib a - 1.w3 w of b. riq surb TNNER .

en . side of car bed 33 th . Av - a .9 = (. L.5 X s.0 w )

g = q ap bdween barth3 = ( 51. S 4 )ins surface.g in. -fc= ( 170,00'0)/( 52.99)

L w e aa&e.i.mp of pA pA . [e._ = 5)99 psi J + 2(a +9 )

OUTER P - n o;000 lb. A,- zad 26.t2s)( c.s )

d= 4.5 in. Leing = { % l.13 )in' I =. S. 0 6 7 ik, consecudNe -fc, = ( llo,oco)/( 91.i3. )

! a= 3.1.15 h (Wnimum a))

9= .1515 A (marimumg) -

(c. = 5 T2.9 esr ff.25 -% . 09)/1 + .0 6 REV. REV. AUTHOR QATE CHK'O. 3 Y DATE CH K'D. SY CATE i I

NO. DATE I WESTINGHOUSE FORM 552130 l s

- -. , - . _ . . , ,,..,--..._..--.-- ,..,_.,_,,.,,,,,,, ...,. ,~ ,

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVIS!ON . -

TITLE PAGE Reactor Vessdl Head Lift' Rig 17 O, 42 PROJECT AUTMOR OATE CHK'gSy O TE C M K' O. ts Y CATE CGE 6,C,fg h i 7./T3 k k'h M #p$ I i s .O. .

- CALC.NO, Up yLG NO. - GROUP UCG-27694 REE REM 0s1 AB LE. l 7

i\N ,

BENO\NG $UESS W l

Mrur= k Psa +3 OO fb" McII I = trd4 / L4 c= d/2-fb (k4f $4h dU

= tb ( hat 340. )(aJ/(cl."-a0)

= M(%24. isis 79%.sMs.5"-i.ns")

~

= 230,000 L . O h1hD

=

1(919 PSI A D h?TED FKOM E ,a $ T v w t N C, AND T o t N t W C,-

9th. Ed . ) h REFERENC E I.55VE OF M hcBINE DESIGN ; PENTON ?UBLISHERSj P A C> E r 1 l

AUTHOR OATE CH K'O. 3 v OATE CHCO.sv OATE REV. REV.

NO. DATE WESTINGHCUSE FORM 552130

F

-a WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION' TITLE PAGE

~

Reactor 9essel Head Lift Rig M on 42 pro;ECT AursoR oATE Csg av g ArE Cns o. s v oArE S.O .

CGE @ C .b ' 2/73 CALC.NQ.

A 'M '

GROUP W Q' GLE NO.

UCG-27694 'REE S LING BLOCK LINK -

A ST M A 5 o r Clas s '2 i A-A

., P

~

Li K

s. sis 4 _ g.in _

f.15 R -+ A 'i

+

) .

3 TY P.

\ /

'~

ocus' & -

i)

Y P

T* $sRAnw rP Tension cs+ L.515 p Hele.

fe=_f_ At= ( T.15 - 3.157)(7.til)(t) ~ { 4(.069 = Tl.15 in At Fe T70. c o o 71.'1 3 C+= 3309 PSI I

l REV, REV. AUTHOR QATE CH K'O. 3 Y CATE CH N*O. S Y OATE NO. DATE WESTINGHOUSE FORM 552130 l

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION

~

TITLE . ,

PAGE

' Reactor Vessel Head Lift Rig 70 On 42 PROJECT AUTHOR- DATE OATE CHK'O. S V OATE CGE Mf hk W1/73 CHK'[O 4e Sy S .O . C"A LC . N O . ' FffE N'O. GROUP UCG-27694 REE s h esc at Usts Hole FV = P_ Ay: (T.25 3.2Sd(T.(Tl) - 4.2l.06)1=10.5 id qv '

f v = 17 0; 0 CR = 3 3 l 1 PSI 2 (H o.1'd Beaeing on b.500 p Pin .

The b egoinj 5 t ress is t h e same as W inn <c bearing stress en t h < cc. movable pin. The pin

\s ste m (7). l 1

' f c. = 17 0,00 0 / S2. 4 4

• sl49 PSI Tension cd T.co p cyundeicd sec1 ion M = .E_ Ag IT (Loof r 50 2.1in' bb $

Fe : 17 0;oon = 5 6 7 Psr 50.17 AUTHOR OATE CHK*D.3v OATE CH K'O. 8 v OATE REV. REV.

NO. DATE WESTINGHOUSE FORM 552130

- . . WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l

i TITLE PAGE I

~

Reactor Vessel Head Lift Rig ')_ l 0, 42 P ROJECT AUTHOR OATE CH K'O SY OATE CH K'O. B Y OATE CGE $ f,$ 4 s "2/13 k2 JAM S.O . CALC. NO. .Up @E NO. GROUP UCG-27694 REE h LINK LUG, Mst'L, hSTM A-Sys G R. A I

. -v i Ew

---

. y 9.0 thk ,

/I !il o-o 04 j full Pene.fration Weld '

4.015 4'

'23 E .[ FV = UC,000 - 90,000 lbs.

,Y QM' g b0 F=.h_ = T1,Io1T \ b s

't

~

. cas n v Fv F F ti = Fv tan n.P=31,7331b5 Ten sion cd 'i.ois & Hole F t = E_ Ae: ( 5,5 0 -2.c07)9 -n(,06F = n.9 6 Y i n 1b Fe= qu,r = 33 96 esI s (13,9 6'f)

S hear TEne aY Flole

, Pv _.E. : 0;b17 /}:( 5.50 - 2.Cc?)9 -2 h (,o 6)l= I 3.%' fint 1kV '1 (B,%'()

fv = 3 't 16 PSI REV, REV. AUTHOR OATE CH K'O. 3 Y CATE CH K'O. SY CATE l NO. DATE j WESTINGHCUSE FORM 552130 l

l

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

TITt.E - ,

' AGE Reactor Vessel Head Lift Rig 22. O P 42 PROJECT AUTMOR OATE CHKO ev OATE CHK'O SY QATE i

'CGE M f .is MWG 2/t3 4k' CALC. NO. GROUP l

S .0. $5 NO.

UCG-27694 REE 6 earing t 9.015 & hol<

The bencing stress n the same a s the innac bencing stress on %e vpfer clevis pin i + e rn t o

' Pc = T161T / (3.%5-IlM 0(T)= 6 l 09 f 5I 3 l C.ombined st ress Rovn Tension and Bending l N\ = . (o .c o F v .7 5' F H l t4 = 6. o o (90,0 coy .')H3),g33)

M= Sil 625 in- tb 3

f e = Di t li A 2.

&= (n.5)( 4 ) = 50 i n '

3 1= _L ( 4 )(12 5)* = 10 4 . Il s'n 6

ft= 3,, e , v n . L2X ,

so los.M F t =- 757 t 991l-4t= 566% P5I REV. REV, AUTHOR OATE CH K'O. a v OATE CHK"D. S V .DATE NO. DATE WESTINGHCUSE FORM 552130 4

[ '..

. . - WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Reactor -Vessel Head Lift Rig 7 3 Oa 42 )

k M.av PROJECT AUTHOR DATE CHK' OATE CHK'O. B Y DATE CGE $,6. b; 1/73 ~

s.O. CALC.NO. Up (f.E NO. GROUP UCG-27694 REE

. v teticgL shenc at Futt beh+ ion Weld fv =_Eg Av: 61)(11.0 = so in' A v-Fv= y nno = t goo p5g 5o REV. REV.. AUTHOR OATE CHK'O. 3 Y DATE CH K'0. a v OATE NO. DATE WESTINGHOUSE FORM 552130 1

O WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

TITLE ,

PAGE Reactor Vessel Head Lift Rig 19 Os 42 PROJECT AUTHOR DATE ATE CHCD.SV OATE CH sC O.Av S .O .

CGE Mf?D1u' 2/f3 F4/E CALC.NO.

&KLNO'. ' GROUP

. UQ UCG-27694 REE 4 t/PPER SL(NC' S H E AR, STRESS.

L E C, PIN I0 msw't.: ASTM -A934i fy = P/2.A.

AI sI M 39 0 C Lass 80 p = 97,61%

^

A, = Tray 4 g- "

y 3 ,' * *z Av = n(3.9as )W a

Av= r2. 53 in t .

d fy = ( D, b1T ) /{2.* (1.53 )

t.  ;

, . m _, 1 I fy =

3 sci b e sr.

-n _ -- s vf fhr Clevis a 2 BE ARINC, STRESS P= Fene. .ain3 on ammblyi lb.

d = diam.ter of p cn, in.

P/ As

.f=len$th of hearin3 :.urfece. -C. -

of c.cvace boa 3,in. P=

a = 1.w3w of beariq sur6 T_N N E R en. d de ofc a r bed n +. Av - a S = (3.99s X 9.o o )

S= qap L % =n karin3

=( 13.9 7 lins surfeco, in.

fc. = ( D,6M )/( 1s,17 )

L hw acu. i.n3+.h of l PA pa Oc = 6109 99 l J + 2(a +9 )

l OUTER l .P = n,c15 is. A,- 2 ad= 2( 3.91x 3.9 i d - 3.195 in. =( is.3y hns L J = 4.00 is , ( = ( O A u )/(l5.39 )

a= 1.91 ik1-7.(.04) 9= - .u to .fc. = c wy m:.

f T.3 T + II.ot0 1/100 b 4.009/2 care oAre

^urHOa OATE CHwO.av CHec.av

l. REv. REv.

NO. DATE WESTINGHOUSE PORM 552130

1 i

, , .WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TIT LE PAGE ,

Reactor #essel Head Lift Rig 25 OP 42 l PROJECT AUTHOR OATE CH K'O Sy CH K'O. S Y QATE CGE &f An)>,.a 2l7% W h J 2 b [CATE

~

S.O. C A LC', NO. GROUP QQ GE Nd.

UCG-27694 REE PI N 10 BENDrNG STRE55 W -

M; f(I a + 3 + 4 .4)

.f3 = Mc /I 1 = id%H t =- d /2.

[b=LP = { ((3 a43)/(Trd + h) .9$a+3+$.9)$M),)

3

= g( f & .n & k)/ln3.395')

= 9pir ( . t 'i90

= igsn Ps1 ADAPTY.D FROM ,

FMTENI% r%ND JOININ(s , -

@ Ed , A R W h Nf.C. U W % OF mmh 1N1 CE' "bN , BNTCM 943LT.htRRh PA(eE ?.O REV. REV. AU THO R OATE CHK'O. 3Y DATE CH K'O. S Y DATE NO. DATE WESTINGHOUSE FORM $52130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

PAGE TITLE Reactor Vessel Head Lift Rig , 2.6 On 42 CGE & f $ u s ; 2)T3 0, CALC.NO. UD L E' N D . GROUP s.O. '

UCG-27694 REE Uf 9ER SONG THREAD SHEAR LEG,ctEVIS uswmo m m n m.snE wen wlE ARM IT. h MAT'L; Pr5T M A -131 > f, = 97hlt /%.19 AISI E -9340 4v = 1. 6 9 t m a L ASS C, fo na TENSION 2.THD ret.IEF lll N N 84

• P/At

' g , 97,62Tlb ill g \ "M.'{\ &p= - ( r.so X t.st )-i(9.06i l ] q,cc , ft = 17A2.f/5T.M

! \ 4 tc,s m V:::.

~~~~ " ~ ~ ~ ~

_%t

\,\

\ \

- i TENSIONG sEc. A-A{rtM wat) f t= P/As

\v \ P= 97,617 \b

+g[ A Ap[( s.5 )-Ui.' cc5{ =2.D.cc) 9 17i9 7 iQ

- 4 (.C 4 7 =

4jos&

T .oy f3

-[t- 97,62T I n.97

, , y,25 n fi= 59'51 =

--s 2.co w h P

ky,3% d ~SHENt, TuR-00T PARALLEL.

m m - a a S rrx m t.)

sec.A-A BEARING STRESS f,- P/A, Tue a Anznc.sram u r.s P= 97,6n ib THE SAME AS Outer Bearin by* k

• l'I.97 'In*

STRis s oN THE em ITEM ,, p

,f Sc = 9 7,615/ LS.3 9 f' t 5'433 '"

It . lA L9 Pst AUTHOR OATE CH K'O. 3 v OATE CH K'O. B y OATE REV. REV.

NO. DATE WESTINGHCUSE FORM 552130

(__ _ - _

' WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Reactor Vessel Head Lift Rig . 17 OP 42 PROJECT AUTHOR OATE C O y ATE CMCO.SY DATE s.O.

CGE h,d,f M 2/g3 Y CALC.NO. 80

$E NC.

NI '

GROUP UCG-27694 REE-ARM a TwREA.D SHEAR, G.P/Av Av. EkuttrJ/2.

MAT'L

• A3TM A -3o 6 Fca Au sunset. umeAo

. Dr .w = b . 64 S52. A

% =((.4.0

- 3 . m 0) ,fo4952./I 4) 6 ) s,.

Q.= major cashme;ter-of enfernaf khw.ad W= numbe.c cl thrench/6 P l=8 4 head ge3emt j l .

- Av= ( 36.161 he i

l i

l P- q u r ibs 8

l s .

I YI .

4 THRY.Ao TsmzoM p [t* Nbt een sm sm my mm m . **an, Ai= 9 ( b .9 w s/n ?

l l 4(M .m2/9 )'- it.on #

l I

l 4 b u n y oi.o m I

l I  ! $= ?T 09 Psr 9.00- 90m.-u

,,y. ,,y. AUTHOR QATE CHWO.aY DATE CMCO.8Y OATE NO. DATE WESTINGHoySE FORM 552130

_ _._ , 7 e

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

4 TITLE _

PAGE Reactor Vessel Head Lift Rig 2.T on 42 PROJECT AUTHOR OATE CHKT y p' O TE C H K'O. 8 v OATE CGE & C,hk,: 2 /75 t/ M jds,,

s .o . C Acc. ~o. w { yea cROur

~

lower SLING SHEAR, THREAD LEG CLEVIS w wue yn m. nm eon wa ARM Q2.).

MAT'L; A ST '4 A -2*>7 .f,-9Q17/%.l*l AlsI t-4599 .C, = 169 r =

LL&SS G

+o ~

no '

TE% TON O THD Rt. LIEF

4 3 N fg = P/Ag i , g N i

~

- P= 97,62T Ae ( ?.5 o X 7.ss )-j(9.o6),,

ll g

\W5.'{

lI yqcc h , , ft - s7,6u / 54.o3 l $" N 4 \ s o, m

e-- .:.:..h i\

--- 1 - - - - -

\

\ \

',% runsrowe, sc. A-Mern me)

( = P/Ae

\k v

\

i P= 9M1 rib g @ App.soo)-N. cod =2(1.co{

- 4(.oq ) - n.87 m k T ,oy I* /T .[t. 37;t2T /17 97 b= 5433 =

. . 9.1s a

-,too - 4 P

b 7. n 1 SHEAR, TV.AR-WT PARAu.EL.

m m-a a (erra not.c.)

sec. A-A BEARINC:, STRESS f, P/A, we unarne. stnas,s r.s P= 97 THt! 5 AMt. Pc THE OUTER k y

• b .n., -

• 6'l'I. 2.

9 7 T \' th* b BEattNt, STRE5s o HE .

PIN ITF M ee MV

• t.

yq33 p>g

.Ec = ctlb2T/ 15.34 {t.

E, . (o369 m REV. REV. AUTHOR OATE CH K' O. iB Y CATE CH K'O. S Y O A T ai NO DATE WESTINGHOUSE FORM 552130

4 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE ,

PAGE Reactor-Vessel Head Lift Rig . 29 on 42 RO;scr a T-Os care c- .c o s v c co. uv oars CGE f , h ~2/73 O/ 9 M g oare S.O. CA LC. NO. US E:4d, GROUP UCG-27694 REE 4" @ LO WE R. S LI NC' S H E. M STME U:C, PIN H mar'u ASTM A-134 fy - P / 2. A ,

AIsT.439o CLA15 60 p= T7;42f

- - m- A3 = Trd%

g

• M ._

% Av = w( 3.195 )W Av= n. 53 in' d fy = ( 9 7 62 f ) /(2.+ 12.53 )

t.  ; j fy

,_.. , I "l =

$ r9 6 P11

.c .

% %mLoher c.Levig.

P= force. ecun3 on assem'cl yi lb. BE ARTNC, STRE.55 d = diamd.se of p in, in .

S=len$th of hearing :.urfecc. -[c - P/Ac of c.ceur body ,in. P = qy2r a = 13w of beariq su r b .c. T_N N E R ens s.ta._ Oc C a , soa p s. Av = a .9 = b.95 X 35 )

S = g ap bd.we.cn bearin3

• ( 13.3 T )int ,

surfe m ,in.

Sc = ( 9y2.5 )/( t3.ar )  ;

L weiwcs.t.wpxof l pt'w pA [c = L 4 T 2, Psr

' J + 2(a +9 )

OUTER

, P - O,615 is. A,- z aa= 2( i,s s )(3.sso c1 = '5 395 in. = ( l 5,3 q Jin'

.P = 3,50 is. ( = ( T7; 627 )/( l5.34 )

a= 1 91 (w 2. ~1-(.0 4 )

9= .13 in. [c.,

• Io % 't PET E 7. Tf t 1 (od-w 1.00 b 3.503 /1 REV. RE v. AUT OR OATE CH K"D. S Y DATE CH K'O. S Y OATE NO. DATE l

l WESTINGHCUSE PORM 552130

- e - - =

s WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

PAGE TITLE Reactor Vessel' Head lift Rig 30 oP 42 PHOJECT AUTHOR OATE Cr4K'O v OATE CH K'D. S Y OATE

~CGE h,d. b a d 2/73 ' kpfM 5.0 . CALC NO. W E ND. GROUP PI N }q BENDrN6 STRESS W M=L'<ta,S+4f)

.Cs MJr x=va%s t= d /1 6- i(ia +p i d(t)(4's)

.we(3a4g + A .9 )/(,rai)i

- a K Yh.n +'4)(n.W T7;41r ( ,13931r)

= 13;607 PSI ADAPTED PROM FRTENIMb AND JOININ(a ,

MD Ed , A am nNC.Lzww.,CF MACHIM% CEL.C(sN g MNT.M Pu3C.Shuli PA4C 'd.L AUTHOR OATE CH K'O. 3 Y DATE CH K"O. S Y CATE REV, REV.

NO. DATE WESTINGHOUSE PORM 552130

E - 4 H ,' l WESTIN'GH'OUSE NUCLEAR TECHNOLOGY DIVISION

l. .

TITL.E PAGE Reactor Vessel Head' Lift Ri9 3 'l O n 42 PROJECT AUTHOR _

QATE CH K'O. y CH K'O. S Y QATE CGE &,( b)]nu: ~2}D M'" GATE GAOOP-S .O . CALC NO. 5# F6/E NO.

UCG-27694' REE hSPREADER, LUG Mn Hrial, A STM h5 TT GMD E A STEEL Pl.8TE

, 't.005 Y AT 5.00 R T't 9 3.E M k. -

~%w ~~

l , I 3#

O . bi ,

l ' n.o o ': ie.oo [

~ 330'  !

.50 7 b h

!\ / s.co asV30*

H 6 %k- t I

? v 13

$ 10.00  ;

S eei n g Siress

~

The beneins 54ress f or %e oper hole- is th e '

l .,

samkas th< b eacin3 stcess on th e s Ling lv7 s Lowfe p inQ4). Usin3 the in nec stress:

fc %61T /(3.33 = L973 PSI l The beacing stress Poc +he Lcwer hole is he l S4one 95 t e b eaNng strtSS on the LtMing It3'S U -e p pi p li . U 5 incj tht inner Stre5S!

Pc= 90, coa /131Y = M3T PSI A E V. A E V. AUTHOA OATE CHK'O.3Y OATE CH K'O. S Y QATE NO. DATE WESTINGHOUSE FORM 652130 .

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION e

~

v r-rts Reactor Vessel Head Lift Rig 4 2. or 42 DATE CH K'O. Y OATE C H K'O. b V QATE AUTHOR PAOJECT CGE $ f $0L.u: Tith O. Wld h; D .

oRour so. C AuC. no. u0 ry ud:

T Cn Sl o n At Up{fr Hole 3

f+ 2 _E. A+* ( 5.00 LO 4.0o5 ) 3. G = 2o.cl r3 i n At Pt = 3 l tw - H 6 55 P SI j

lo.i n Shenc Tencout at vpf<r Hole

=

F v = _l- ; A v = 4. M ) Fv-H %53 Ps1 1Av SPREADER ARM WELD

& e. ene cously con sectaMe ( assumt, ihnt the wel is ciLL 75 v an d thgt the ivy and ativi d o n o t co n+4 ci S o ihat a ll +he fo rc e t r ee +eci 4 5 oc+ing throug h the weld. Att Sires s in Fdlets nte ymd 'tiona ll y i-ceded as sh ene across th< ihcca4 Uen.

L. l'

- m g f f_L- -

r / /f 3 i

& = out s i d e. RgOv3 of p[pe = (Ic 41-()[ L Nh4ce-t = W A L L ihick nes s, CATE CH %'O. B y Q A Tli AUTHOR OATE CHAQ.3Y REV. REV.

No. DATE WESilNGHOUSE FORM $52130

, WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l TITLE .

PAGE Reactor Vessel Head Lift R19 - 3 3 os 42  !

pro;E:T AUTHom DATE CHK0. y- ATE CH K'O. S V QATE I CGE h,0,iodnw 2]B // .

s.o. C ALC, No. UI e E No. oRoup UCG-27694 REE

, ' A = ( 1, k15 + 1(..sooD / 2 3 9 3 l 2 5 .I'n .

L A. = f erimeter l eng1 h 2

Rir(l/sina+l) =

'l o. to 4 ti in S v = 2. , hv = .30] WL wktre w = weld ,

A V-

=

Le9 width

,.10 7 (. 7 s )(9 o. 64 4 )

• ll. 5 5 ( n 2 P= '2.l T9 3 lbs ( Fcom 5 prende r or m ca)culation )

j fv 11;T'i h = l 0 1. 4 95 E 11.55 4

k l ,

l

• F rom hek's Han d boo k 7% ed, P t-140 For 3.00 S C.it 70 p i ps, t = . 5 0, I D = 7 62 s s

i, REV. , REV/ AUTHOR QATE CH K-Q. a v D ATE CH K 0. B y DATE

NO. I' OATE ) ,

,. ;, 552130.

a. 4 WESTINGHOUSE FORM

.....__ T . _ . _ . -

- WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION 1

TITLg PAGE Reactor Vessel Head Lift Rig 34 On 42 PROJECT A THO QATE CH K' D, ATE CMK'O. s v OATE CGE d.OT.adAw212/T3 uo b~ caour s.0, cA tc. ~o. Pp:

I S PR E AD E R h &M - h5TM A lob GRADE 6 SE6MI.ESS K k

', s Ks Fv tans t r.

X x g' , p/ s = 10,000 tan n.r*

sak/4 =

P, 37,5 33 lbs ,

e m.n I e  %.).y.j

'/

/l' 2

x = 57,T33 lbs K '2. P cos So : K = 3-),733 I b 5.

P: V);T%; - 1 I )T 'i31 bs ucs 30' NOMINat c.omf RE%ivE STRESS IN SPRE ADER ARM Fo g S.oo ScH. TO P1PE j ( M ac k 's Hand bccR , 7th td. , P t - 157) l Ot=l1.JLm l ' =- c stow c;ect i c n ql a re q l3 10 S . 7 i n 4 = mom ent o f T. n t r+ ia S: 19.52 i n 3 = Sedion Mcd ul.us P = 2,777 in  :

radlvs of g y rd ico Fe: 2 -- ll ; 7 a : 1llL PSI At 11.1 4 AUTHOR OATE CH K'O. G Y CATE CH K*Q. a v QATE REV. REV.

NO. DATE ,

WESTINGHOUSE PORM $52130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l

l TITt.E PAGE Reactor Vessel Head Lift Rig .

35 o, 42 PROJECT A THOR QATE CHK'O.SY CH g' O. ,8 v QATE CGE 7.C.*b 2/13 O M M' CATE

'5 GROUP S.O. CA LC. NO. pE hD.

Allowable C.omprewiv e- stress

( A.ts c M anv40 i th Ed . P s -137 k * . 65 4 j R e commended for Fixed - Fixed Ends J . U. (. t s V ind = lu o s r 2.77 r -

C. c. = , Trl F _

1 171 14 oce.ono Fy 35,50o '

= l17,77f case : .k.1 4 C c. -

r Fn= allowable c.ompressise stress in the abs 24nce of bendincy m .enis L et A = f LA) c c.

t C/

then Eq = / t # Fy [5 v .3 A _1 A 3

1) t3 i t -

A= T1 bow =.11ST15 F y = 35,000 PSI m.TtT F4 = 34174,bi /l.741 = 19 5 95 PSI REV. REV. AUTHOR OATE CHg'O.av OATE CHg'O. av OATE NO. DATE WESTINGHOUSE PORM 552130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TI T t.E

' AGE -

Reactor Vessel Head Lift Rig 3h OP 42 PROJECT AUTHOR DATE CH 'O.g ATE HK'O a v OATE S.O.

CGE %C hku C A L.C. NO.

' 1}T3 -M Asdd A '

QQ NO. GROUP U P PE R L t FTt NC, THREAD SHEAR LEG, CLEVIS m m m m nn sam m a ma LEC> noo MAT'L: ASTM A-131 f, = ioP o / 36,161 hISI E-43tio Sv = 1977 m CLASS G.

+o na' TE% ION Q.THD Rt. LIEF

s;  ; 4 i y s (ip.= P/At '

I 90,000 \b

'! l(l W

\ Ae (r. so X7,Tr )-j(9.ohf H ll qu \ , fi = %mo /54,o3 .

l 6.

. __tg.x b

!\

4- 16 M m

- - - ' " J----

\ 7% \ TENSIONG SEc. A-A(Prm wn.t)

\

\v \ fe = P/As

p. 9o,000tb k i @

g _.._ _ -. --,-

Apl7s )-Mmsi=2(Loo)

- Q (,09 ) . n.97 ic Q' Ycy /T 9.cos+

4- q o,Ooo / n,97 a* 4.15 R ft= 5003 m

-, 1.00 -

4 k 3,7r SHEAR T1.AR-Our PARAu.El.

P m m - a a W n m t.) i sec. A-A BEARING STRESS f, P/A, ru l umac. smas.3 r.s P=  % c m ib j THE 5AME As THE ourER BEARING STR SS CN TtiE Av

• k

• 17.11 td PIN d ** pV f+-

Sc = 90,om /> .3v f-L. . se o m t soor Pa REV. REV. AUTHOR OATE CH K'O. 3 Y CATE CH K'O. a v OATE NO DATE WESTINGHOUSE FORM 552130

.- . WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE . . PAGE.

Reactor Vessel Head Lift Rig 37 oF 42 PROJECT AUTHOR OATE CHK*O ATE sHK0.sv QATE s,0.

CGE @.(.'IMUQ 1/B CM CALC. NO. GROUP Fgi Nd.

l y

• U PPE R U FTlNG, S H E AR, STREE L eo, PI N -- - -

\1 M w't.: ASTM A -13 4 Ov - P/2.A, AIsr ti34 o CL Ass B_0 P= % coo tb ~

v- -

A, __ 7yd%

~>~

i ~

n s, e &a Av = Tr-( 3.s9 5 #4 a

Av= 12.53 i n'-

d fy = ( 9 opoo ) /(2.+ t 153 )?

t.  ;

L_. , 1 "

"l [v =

3s9l Psz

.e .-s.

% *z u PeEg, thin 3 Lt3 c.LeJis P= b=. .wn3 on av.cq,lh. BE APsING STRES5 d diameter of p in, in ,

f i.np of sc.rcn3 .urr . C. 4= P/A,,

cf c.cdte body m. P = 30,0c0 tb a = ler$w of beanh surb.c TNNER en . sicle ef oar bCd 3ph . Av - J.9 = b.1w X 3.s )

• ( 13.i f lin t 9 . g ap b bun bacin3 se rbo, in, fc= ( 90,oco )/( [3.9 r ')

L m i ac. G .i.m p of pA sa 3 [c = 6933 Pu-

=

_J + 2(a +9 )

OUTER

, P = 9o,coe is. A,- 2 aa= 2( t.n)hm) l d = 5 995 in. = ( l5,3 4- )int .

i ,

.P = Y.5 is -fc= ( 90;00 0 )/( is.3 9 )

l 3= l.9 L iw 7 - 2(.04) 9= .13 in [c. = 5 t 6'? P51 l' 1.TT+ 2/.oO-7(IMib3.50'] /~2.

REv. REV. AUTHOR OaTE CH K'O. a v QATE CHgc.av O A f ti NO. DATE WESY NGHOUSE FORM 552130

=

' WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . .

7 lrirtt *Act Reactor Vessel Head Lift Rig 39 On 42 PROJECT AUTHOR OATE CH K'O. S Y ATE CM K'O. O V OATE

+

s.O.

CGE $, @,8)m tot"1/73 CA LC. NO. 5)

MkdM F@ hd. GROUP UCG-27694 REE rn UPPER LtFTING E LEt, Pr N ~

\$

BENDrN6 STRES5 W L

M=- t(t a 3 +O)

-Cs= Malz '

r=vd%9 -

L= d /2 E

F

[8=LP(3

= 5 ($ asqa+ +3 )/(wd + h)5fXO$,)

j3 t

5 l =l6 P( L? t.n N)/tr Mis L

= $ O,000 ( .l ~6 9 3D E

= -

11544 PSI 3

?

s b

1

[ ADAPTED PROM .

[ FMTENINb AND JOr.NIN(.7, f @ Ed , A RtSGENLL %%Q% OF

,_ MMMIN c c.r ew , m atu pua m Hun y PME19 AUTHQR R E V. REV. OATE CH K"O. 3 Y CATE CH K"O. a v OATE s NO. DATE WES'INGMObSE FORM 552130 T

m

, ., WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Reactor Vessel Head Lift Rig 39 o, 42 PROJECT AUTHOR OATE CH K'O DATE CHK'O.SY OATE s.o.

CGE 6.f.ijl2Auai 7/Z5 CALC. NO. O I G R QU f' p .NQt 1 UCG-27694 REE

~

LEG, gg THREAD SHEAR, f, P/A ,

Av.CharJ/2.

MAT'L*. ASTN A -306 GRADE 10 rm nu sm==nt vmeno Q.w=Q, .ro4S52.M C)Mid M ) .fe4952A 9 )

= ( 3.73% ) 6,.

Q ,= major dahmdr.r-  :

of ente.rnaJ 1hw.act

. h = nuenbu- of threads /ii

./ = 8 % of 4 head g e3 o emt b.00

=

j l A= ( x.iut M i

i i

i P= 9 0;ooo Ib i

i I i N. = 1 LI TT Psr f THREAD TEMbrOM y ft =- P/A t-SCR MTt%NAu.Y WEACES PART5.

At ( b '*9 M i l =4(1 .vns/ y )'-il.ou l

I l [t 3 ( 0,000 ,)/ ( l1.073 )

I l i l 1,4= T l -) ] Psr 4,00 -90 E-2A yP TYP l

REV. REV AUTHOR OATE CH K'O. 3 Y CATE CH K'O. S Y 5 No. DATE l WESTINGHCUSE FORM 552130 1______. . _ . . . _ . . -_ . . . . . _ _ _ . _ - .

~

l ..

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . .

l ' TITLE PAGE i

Reactor Vessel Head Lift Rig Vn 0, 42 PROJECT AUTHOR QATE CH K' O. Y ATE CM K'O.tsY

$ DATE S.O.

CGE h. ( chiWT3 h,*

CALC. NO. 4$ 1 Nd. GROUP i UCG-27694 IV REE I LOWER LIFTING i

t THREAD SHEAR. -

LE4 CLE.VIS m m ue m an. n vs.sa m m rom MAT'L:

ma t_ EC, IT.h -

h5TM A -137 -f, - 9 0,000 / %.I M AISI E -9390 fv = 19 rr m C. L A 55 G.

+p no TE!ETON 2.THD RELIEF a "

N (% fg = P/At lll I

l , ij 8

i i LN p. 3 0,000 ) b MU NC 2E ll =- Ae (r.so X7.so ) g(s.o6 g )2.

\ ,3b i ll

-ll '! S w fi 9 0,*c / so. rov

!!'iF 0:::=-& -

N L\

4= nn ,,,

~~~~ ~~~

\ \ TENSIONG SE( A-A(Prm wn.t)

\

h b fg = P/Ag P= 9@co A I A 9

v '

App.ro H3'icsb2(2.od

-4(.oy7.go1p i%s g sjos$

T '(**=

i = / Th'

-ft ' 9 0 U1'97 4 I i

n. y,u n ft= 4, T0 b =

m1.00 4 7 50 SHEAR. MAR-Our PARAu.EL.

h To bac. - s.a (tPIM HC LE.)

, sec. A-A BEARING STRESS -f, - P/A, we uAnmc. srnas.s r.s P = 9 o,mo ib -

THE S AME. Ah ouTE R 6EARtn k e A, = 19 97 t/ gn t STRt95 ON TH E PlN h e

,{

Sc = 90f MO /13.N f' 9TO6 PM

n. t6% ,,=

t REV REV AvrHOH OATE CHK'O Jv OATE CHs3.av O A T hi NO. DATE WESTINGHOUSE PORM 552130 i

_ _ _ _ _ _ _ _ _ _ - -- - - - - - - - - - - --,r _~

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION 78TLE . PAGE Reactor Vessel Head Lift Ri9 4l on 42 PROJECY DATE CH K'O Y A E CHK'O. 8 v QATg 5.0.

CGE AhJTHOR.&,T&

CALC. NO.

n d 2/73 U9 hK

• E .NO f GROUP 3.58 lower LIFTING S H E M STREE 11 . . .

LEC, PIN M Ar't.: ASTrA A934, AISI 4340 f, - P / 2. A ,

sTd E I. class 80 P = 9 0i polb

' u nced Lvs A ,, 77d%

% 4 > 34 ,_  % Ay = Td 3,fo )%

a Av= 9.n in' t.

d fy =(90,000 } /M1. b'l )

% I "I fy =

4 6M e st.

.m ,

% %mtoker us1 5 1.eg cl..vis P= force. eacn3 on as:cm'ct y,Ib. BE AR ENG STRESS d = cliarnder of p in, in .

• \ tng t.h C hC artng i.urfdtc. c, = !by of c.cate boa v ,vn. P = 10/ coo Ib a = impw of bearim suck.c '

T_N N E R er,stae.=; a ,wCau- Av-aS=(3so X 3.a )

S = pp % w re3 =l 105 hn s w 6 o,in. -

S,. = ( 9 o,00o3/( Io.5 )

L towi aak torp.h of ,

pA pe +c = T5 7 l pu-

= .1 + 2(a +g )

OUTER P = 9 0 on is. A, 2 ad= 2( i.94(3sco) d = 5.50 in. =( 13.4t{)in' 13,4 4 )

.P = 3.00 nom, is. k = (90 Coo )/( /

a= l' O ih 1.00 - 24o4) 9= .19 in [c. = (, G 9 (, Psr.

t 15 m.oyM n.coH,c03h.

REv. REV. AUTHOR QAig CHK0.av OATE CHK'O.SY O A T ti NO DATE WESTINGHCLSE FORM 552130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , . .

TITLE .. PAGE Reactor Vessel Head Lift Rig 41 on 42 PROJECT AUTHQR DATE CH K 0. Ar CHK0.Sv

, OATE s.o.

CGE Ts f T a b n " d 2fT4 CAcc. no.

. Wb{u .

1. 1. egior oRove PI N- 7; _..

BENDIN6 STREW 2)

M;I(I. a+ f + 4 J) .

.fs = Me /r I = vcl% 9  :

t, =- d /2.

fd = i ($ a +p i .9)(OIC5,-)

=6P(3ug + h j )/(wd ) 3 5

= 1(,9( T t. ,19 cDit 3.5

= qo,000 ( . \ 9 RSb)

= th9bo PSI l

l l

l kM ADARD FRCM '

FMTENIN(.s AND JCENIN (7, 9E Ed , A' asssasmtt., nw 01:

MACM.TN7 CEM*GN BN1CN PuJLT.'-Huli i

PA4E 2.9 REV. REV. AUTHOR QATE CH K' O. 3 Y DATE CHK0.SY DATE NO. DATE j WESTINCHCUSE.PORM $52130

APPENDIX B DETAILED STRESS ANALYSIS -

]

REACTOR VESSEL INTERNALS LIFT RIG This appendix provides the detailed stress analysis for the Virgil C.

' ~

Sunmer reactor vessel internals lift rig 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.

I t

, 62658:1/031783 8-1

y.

$KETCHSHEET sestINsN0ust Poau 54202 S.o. PROJECT PaGE UCG-27694 Virgil C. Summer 1 y 48 7tTLE CALCuLATloN$ NO.

R.V. Internals Lift Rig Assembly PDC- .

aur .. a eart F. Peduzzi $ C, Toli m',3fg3 CNtC uo e, a o re J. Richard h- , 2ff,] g PunPost aNo nasutts: UQ e.

1. The purpose of this analysis is to detennine the acceptability of this rig to the requirements of ANSI N14.6.

2. The results show that all stresses are within the allowable stresses.

h p .......... e, o .

O paorsserouac A f JOSEPH W. RICHARD j a~o,~ u .  :;

• gNO 007167( ,/

NM),

~

[())f Original Issue F. Peduzzi REVISION NO. DATE DESCRIPTION BY l

RE$utitNG ALPORft, LETTERS OR wtuCAANDAt .

e

z WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . .

TITLE PAGE PROJECT naaetar Vaccal Internals lift Rio . 7_ os 48 AUTHOR OATE Cf K' SY p ATE C H IC O. S Y QATE CGE fp f j d ,,,,; zff3 l,/ hj _

S.O. CALC NO'. Ud 'e & f40. group UCG-27694 /t REE e.

MooK MN slot PLAf t et AoA#fon PtM LoAccsLL memovasta ew

• suNo Stock @

M i sung SLoCK LUG @

1. ! r

@ uptactiv?sem ,) 1  %

7I

% g ocean suNo .

@ clevis q -

q' ] sung Roo @ *

'g

,' \

]if  !

I

@ wataotn Anu

[ .

-l l ^i LowensuMG leo clevis @

f f l, i

l c FR$AoER 8LoCE @

, ,j (7' f:  ;

, ymeAotnLuo @

' l3 g l l t .

Lowan cLavis pin @

b . l

j. , LEGLuG h

' i ,

' i[.q'!+, ' '

• I j

" LaocMANNELs h N. '

,h Ei .

,a l .,

l[?

i l ,_,

j kN o l

@ LoAoNuf,

/

@ neouNiiNG block

~

@ mooHousimo l

r 1

@ cuict staave

@ nofotocMstuo/

i ZEV. R E V. AUTHOR DATE CH K'O. s Y OATE CHK*0.SV OATE NO. DATE WESTINGHOUSE "ORM 882130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Ranctor Vessel Internals Lift Rio 3 oP 48 P ROJECT AUTHOR DATE CHK*D. SY OATE CHK*O. 8 Y DATE CGE g.[QQ 3/73 4p4 4 d!

s.o. CALC.NO. 4l FTLE NO. GROUP UCG-27694 REE DEStGN Wei 3 ht

'2O}000[bS. wT . of Low e f' Internals 19,To o lb s. EST. vi, o F R \ e.

T. lot l b 5. Co nfingen ci f3 23o'ooo Ib5 Tota i v'

S LING LEG RNGLE

+ w.

>3 Fu = 13o,cnn = 7 6,66 7 ( bs.

SLINc, rod y 100 19 /Fr FT 51 _ i 00, n9 Ib3 co s go,g

/' F" F tt = Fv ra m so.fr I,4,30Cib.

Io R. Io3 y Fv = "/'3 Strl 6 : . b WI 3 G = 10.1 Fr = T!*NSicN IN 5 LING Roo F h = FORCE EX E RTE D ovTwhRD S PREADER 6tccK FV

• FORCE E X E RTED C N E ACH LEco A SS E MB L1

• ITE M S 13 Tit R00c,h 11 v3 e, w : 2.ol, c oo ! bs REV. R EV. AUTHOR DATE CH K'O. SY DATE CH K'O. S Y DATE NO. DATE WESTINGHOUSE PORM $52130

. WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION *

• TITLE PAGE

,RoaEc7 Reactnr vessel Internals Lift Rio 4 ~ ' on 48 avrHon oarE cHK o.sv CGE $fjfm. rfL3 n, g , f _ garE cHn o.sv o r.

s.o. ca uc. No. <a e6LE wo. Gaour S LING 6 Loc,k and Lu t, bb t.ITl thK -P 7.15 6.sisp /

x l

kk .ob XW Chamfer ,

Full ?ENETRarTion\ / both Sides  :

4 0 thk 7 "" \ /

, Fv = 130, coa = 76, 667 lb s, H.015 f h

' T#

ya

~

i FT= % 667 e tco,n1 Ib5,

\

cos No.l*

s.5o R Y"' ~

, F4= TA N 90.i',6,b67 t

FT

> = 6 9,560 lb s .

,,,, j l=

y o.co- >

. Fv v S LINC, 6 Lock - MdlL. ASTM k sot CL455 2 Ten s i on @ 6.T15' @ Hole 1

kT.1T)(O ' 6.516) 3.\T7 - 9 ($_)(.06) : Ab '

ht = Tl.190 In t l ft= 1 = 1%O, coo

= 1714 P S T

! At T l.~) 4'O l

EE V. aEV. AUTHOR QATE cHK'O. s v DATE cHKo.sv OATE NO. DATE WESTINGHOUSE FORM 582130

~ . _ . _ . , _ . . . ,__

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Reactor Vessel Internals lift Rio 5 on 48 PROJECT AUTHOR DATE CH K'D. Y CH K'O. S V DATE y g QATE CGE $,(*_.9 d m i 2,/73 h, '

sIg s.o. Catc. No. - 98 oRove UCG-27694 P@No?-

REE B eArtn3 @ lo.s'(5 p Hole Fc = -.f. 3 A c = cl A,= (b. El 5) { Ti lT 7 - 2.C.. ob) ) = 52.56 :n' bc P c. = M o;oon ) Io PSE 5'2.56 .

S h e a r Tea r -o ut @ b.515 H ole F v =_f. , A v = (3.15 - LSi s ' (T.1 $7) -28)(.06)\ 9 0. 57:n' 9< ( 1 /

Fv = 13o,000 = u t it PSI t Of o.77 )

Tenston @ T.c o p C7 LIN ORICA L S EC.TIO N P t = _P__

At= d = Trl%*) - so.2.-;in i A4 y y F t = no,noo - = 4su Psr S 0.T7 0

REV. REV. AUTHQR DATE CH K'O. 8Y DATE CH K'O.BY OATE NO. DATE WES?tNGHOUSE PORM SS2130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION *

• TITLE PAGE PROJECT Reactnr Vassal Internals Lift Rio b OP 48 AUTHOR QATE CHK OATE CH K' O.A Y QATE CGE Q (, h g 3fg 4 g'O. SYMm _

S.O. CA LC. NO. U# GROUP (I L'E 'N O.

UCG-27694 REE t

SLING 6 LOCK LVG, h Mr,rt, SSTM A 5ff c,R6DE h STUL Te n s i o n @ 9.o i s & tiole, , P = Fr F t =. 2 _ h t = L ( 5. 5 - g 4 = r7. 9 4 I n - ~2 At ( 1 '

Ft : Leo. n 't = 35F7 PSI '

17.3 9 l

b e aeing @) 9.015 p H ol e, , P = Fr The.beneing stress is egual to + e in ne r beatiny stCf 55 O n the, U ppe r C.lt vi s f i 3 fc.= t oo, n ct -

6 1. 6 9 PS I

) 1a. O o '

Shenc Te a r -o ut @ 9, o 15 $ H o le, , P = Fr fv # P Av*f5.T'0-LoiV (9 00) = 13.q 7 lov i 1 1

Pv =t oo net = 5571 Psr 1 (13.9 7 )

l l

EE V. R E V. AUTHOR QATE CH K"O. S Y DATE CM K*Q. 5 Y DATE N3. DATE l WESTINGHOUSE FORM SS2130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVI,SION TITLE PAGE Reactor Vasil Internals Lift Rio 7 On 48 PROJECT AUTHOR DATE CH K'O. av yr OATE CHK*D. a v OATE CGE g,, M L , zf73 3,R g glg U S.O. CALC.NO. Ud 1 E NO. GROUP UCG-27694 REE V f.c tical. S hen e @ LUC, Roo T WELD , P=FV '-

f v =_2 3 Avr (1.00 + 5 50X9 ) 50 i #

hv Pv= ~16, bk1 = ts 33 P ST 50 1

C ombined Tension f rom bending and tension @

L V G, w e Ld f t = 2. + uc.

A-e I

~'

I = idd - (W n 59 = L si, o 't i n 4 b

is 5

C. = t S Xo + i n n ) -

= 1,, 2. 5 i n .

2_

l M = b b = (4 X 11.5) : soin' P = h = 64,F60(bs M = Fv ( lo.c o \ - FH (~1,00 - 6,15)

L90)

= ,6,667 ( 6 ) - ut,sto (,7 3-)

= 9 113 sn in - lb, R E V. R E V. AUTHOR DATE CHK'O. S Y DATE CHK'O 8V DATE NO. DATE WESTINGHOUSE FORM 582130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

TITLE PAGE eno;Ec7 RAartnr Vessel Internals Lift Rio T on 48 Aurnon oArE cHK o.sv oArE can o..y s.o.

CGE q (,pgg yy3 /)6' /,gg-y oArt cAcc. no. vs a 9.a No.

caoue

~.

P 6: L 4,51,0 l'II1,stillb.1T) 50 lo S \. OH Pt= 1143

• 3951 : 5149 PSI i

,qg y, qqv, AUTHOR QATE CHK'Q 5Y DATE CHK'O. C Y DATE ND. DATE WESTINGHOUSE FORM S52130 *

~

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE . PAGE Reactor Vasse'l Internals lift Rio 4 op 48 PROJECT AUTHOR OATE CHK'O. SY DATE CH K'O.sY OATE CGE gfjpk. 3pgg (pjdid 8.0. CA LC. no. sr Pg E 80. Group REE U P 9E R . C. LEVIS S H E AR, STRE5l5 PIN 3 ~

emr%  % A,= w( 1 oo )%

a Av= n . 57 in'-

d fy =- ( ) oo,nq ) /(2.t n.57 ) -

~

t.  ; .

,_,_.,1 "I fy =

3 9 n est..

-e, g e P= b .ckn3 on asambl yilh. BE ARINC, STRES5 d = diam.kse of pcn, in.

P/Av

.0 1.nph of be.rin3 surf -fc =

of c..nur boa 3,in. P = t oo,n i .o a = 1.rgw of bE4riq surb.E.,

T_N N ER .

cnn. side., of owe bedph. Av - a .9 = ( 4.00 X 9,00 )

9 = q ap b.:E =n b. cA3 '

=( l 6.0 o lins su rface.>; in. Sc = ( l co,129 )/( \ L.0o )

.L -te.i acs i.mp of f pi pA. __ _ [c = fo 7. b 4 pu:.

=

! + 2(a +9 ). . _ . . . . _ .

_ _. . _ . . OUTER _._ i P - foo,ns is. .- A - 2 ad 2( 2.9 i X 9,m l l d, = . % oO in. . _ . . . . . =( l9. 7. 9 )ln'

.I a. 4. O C th, k (100,119)/(l1,L3) a= b1( iw 2.5- 2 (,045) gw . IlO in. [c., = yl19 PC.

[4 '.5 + 1(M9) - 7h,M -4,ocl /~2 l REV. REV. AUTHOR OATE CH K'O. S Y OATE CHK'O.SY OATE NO. DATE WESTINGHOUSE FORM SS2130 .

. , . , _ . ,. _,. _ , - , . . _ . . - . - - - - _ . - - . . . . _ . - . . _ _ _ . - - . - . - - . - - - - - ~ - - . - . - - - - - . - - - . - - - - - -

. \

. WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , ,

TITt.g PAGE ganctor Ven al Internals Lift Rio 10 'o r 48 PROJECT AUTHOR OATE CH K'O. E Y OATE CH K'O. S V OATE CGE Q,[,b,)ng njg3 kkl$ s.o. CAi.C. No.- go gj.s No. ouve REE PI N - 3 EENDrNG STREW 8) M = ll s. a + s* + 4- J )

                 .(s = n tr                                                                                                                                      .

1=wa%9 - t =- d /2, [3 = { (('$ a +$ + . h }=lGPhug+$.9NkkIdd

                                                          )/(uday
                   = 16 P( 9 +, no r$)[n 1 3 1

l = Toop.19( .l31031

                    =

1503 9 PS I ' ADAPTY.D PROM l FMTENIMb AND JOENIN(.7,

MD Ed , A Rt%hNf.L Zu.ut CP Mac.nzse. casrew , MNE,M PupCWM P A 4 E l ')

REV. REV. AUTHOR OATE CH E*D. S Y OATE CH K*D. 8 Y OATE l N3. DATE WisTtNOMOtJSE PORM 582130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Reactor Vesse'l Internals lift Rio iI or 48 PROJECT AUTHOR DATE CH K'O. SY DATE CH K'O. SY DATE s.O. CGE g,(pfg 3pgg c Acc. no, vi

                                                                 @ d1 rut no.

ca U P P E R S LIN C, C LE V 15 h - - MhT'L: Pr$TM h yll $ TEE L FO RG INC, (I A ss 3 w 9 ').5'  : w9.00 - 4 - 40 N C. - 1S a  ; i y i V h' i l 13 00 - I _._ __ 'r [

                                                                  /           FutLE 4,0 LT J                              ~5'                                        .cys BeeA c.oeners It n S i o n @ 4,0l9 f NOl6 St       P_.        h   A v = ($,1s - 9.1s-)(q ,00 -q,ois ) - y (,o35p av               h v = 2. 9. 91 i n '-

Et 100,12'l e. y o r 2, P s l a.s. O Bearing stress @ 4,ois p [yole The 6enning stres s @ +b e 4.015 / H ol+ 15 th e Sqm 45 the out e r bencing siress en + h c. DIN f c." 100 221/ L3.17 : sM9 95I 3 R E V. REV. AUTHOR DATE CH K'O. S V QATE CH K'O. 8 V OATE NO. DATE WESTINGHOUSE FORM 882130 m g- mm - - , , . . . ..

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . . TITLE PAGE P ROJECT Reactor vessel Internals Lift Rio l '2. o n 48 AUTHOR OATE CH K'O. S V CH K'O. a v OATE CGE G[jfg zm Q W lHip A MSATE s.o. CA uC. no. uu gE no.- anoue 3 hear Test-out @ 4,C(S $ Hole - h=P 3 Av = I9. 00- 4.ni s }( 9,'25- 4.25 ) 1 (.045N 1Av ( l / kVCII.9 6 ln

• fV: 100;n9 = 4 012 PSI 1.(l2.46) .

ThNqd Shta r Tht, thrend Shear 15 the Same qs th e Sting rod 's ihren d Shea r b FV= ino.n 4 9 1 5 '1 PS I 2.4.ll1 1 l RE V. REV. AUTHOM QATE CH K'O. 8 Y OATE CH K'O. 8 Y OATE NG). DATE wEsTINoHousE Pomu es2130 _ ~ - - , - , - - y

      *~  '

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE paartar Ve<<el Internals Lift Rio 13 on 48 PROJECT Av7 HOR OATE CHK OATE CH K'O. av OATE CGE $dh ' yyy fp'O avMg s.o. CALC.n o. vo esta no. oRove UCG-27694 REE - SLING Roo e THRIEAD SHEAR. _, Q. p/A. Av 4wtrJ/2. MATT: h5TM A -3 e 6 , , , , , , , , , , , , , , , , GRAPE lo odo . 9.u.= .6 S52. /h C)M.=(S 0 ) f 4952A 4)

                                                                                                                                                                                                    = ( 3.7376) 6..

Ck.,,,- major ais,oan.r- . of ewkeneS Ahn.d

                                                                                                                                                                       .                     W = nue.ibar of thread /fi P                                                                                                                        .$ = S Q oS % md q u e sk
                                                                                                                                                                                               = 9.00
 -s                                             g                                                                                                                                 M                3          *         {tg J                                              i-i i

i

                                                                                                                                                                                            'P- loo,n9 t b*

l - i . N, = sis 7 nr 4 T H R Y. A e T a m r o w y ft = P/A t. m uw w m.y n m m ea m

                                                '                                2
                                                                                                                   . 30 WM-                                                                   4 ( D,,,,,, . 9 ') M 3 /n Y l                               l                                                                                     Reuef        A = 'h ( 9.o
                                                                                                                                                                                         =
                                                                                                                                                                                                            .m3/ q )'- it.co e l

8 [ln$3) -Q = 100,2.'2 9 1/ ( 11.o0) i j [x = 9043 Pu

                                                                                                                                                                                             ^                  ^              '

4 '90NC1A

                                                   'P                                                                                                                -

St : P/At At = Tr a2./9 - Tr(3,n)2/9 h t = 10. 3 9 9 I n' pe = !M;779 : 'i 615 P SI i o.3 9 5 mgy, mgy, AUTHOR DATE CH K'O. S V OATE CH K'O. S Y DATE NO. DATE WESTINGHOUSE FORM SS2130

                                     .                                                                                                                                                                                                         l

l

         ,                   WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE                                                                                                               pagg enosect Reactor vessel- Internals lift Rio                                                                          l 4 ~or 48 aufson                         o4TE can o. av                        omrE ca n.o. .v           o rE CGE                   ff gh,. 3m 3p M s.o.                            ca te. no.           90-                                                  onove yte no.

l S PREADER JolNT _. The s peeader aoin+ C.on sis ts o f t h e t) Low er clevis

1. ) Lowe r clevis in

3) 5prend4 c Bloct LUy -

4) The Leg Lug .

The bearing S icesses acting between thfse item s are calcula.te d on 1 h e, followiny paye s . Th e resolap moment 3 ; fo cce6 nn d s fress disicibution s are thfn ' vsed as inputs to deier min e the listed item s

                                                                                ~

Stres505 in th e to Ltowing c.alculafions on ihese dt m S ,

               ~24                    15J1                       d Wk                  1504                    :!!
                 .--.    --.      .                .- -    ---       .   . t-A _. A_.           /-                    i    x N

60tak Cof ter$ .o845 N

                                                                                          \ ,15 cli AMFER x                                                   S PRE ADER LEG                      _ towEE CLEvtS LUC, REV.       REV.                 AUTHOR                          QATE CH K'O. S Y                      QATE CH K*Q. S Y          QATE N 3.       DATE WE$flNQHOUSS POMM B52130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE paaetor Vassil Internals lift Rio lI on 48

                                                                                                                   ^"

CGE Mm ,. 3 f s.o. cAoc.n o. 9; our uo. GRoue

                                                                                                                            ~

The distribution o P +he bearing stress be+ ween Lug and pin is ctssumed to be similiar to the stress distribution +hd would be obtained in a rectangular cross Section o f width d. And depth t Subjected to a lond 9 nod homent.M as RSsumed to S ection (IS,1 3

                   "Lucj bearing Strength for Sintjlf shear j oints under un;Vecm axia.t Lead
 '                                               3  from Tec.hnolog In ci Repoc+

uq - ba-1'l , 0nyton , ohis ' weig hi- Pat ecson r i AFB sponsered. ALL Lug S are oF s'm,'lia e thickness ,50 +ht m ode L _ b ecomes A

          -               "                          d = d iameter P: Forc e 4-3d    l gap g
                                             "         t : +hichess of Lug F~1 TH                  ,

en ty two tog 3 cic e n e ed ed in +h e model as the leg ' carcies only vecticnt forces and the sprendoc carties onL 3 hochental forces. The clevis ha d both hori2ontal

                   + verijcal c.r:vigenents qcting on iti so ihai t 'n a n y on e plct 64 only two lug s qr e interacting.

l REV. REV. , AUTHOR DATE CHK'O. 8 V DATE CH K'O. 8 V OATE NO. DATE WESTINGHOUSE PORM S$3130

                                                                                                                         ~      '

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE PROJECT . RAarter Vassal Internals Lift Rio 16 On 48

                                 ,              AUTHOR                DATE CH E'O. Y     OATE CHK'O. 0 V               OATE
    %                                               . . _^^^^l       h       jN}       *
           ' 3.0.                              CALC.NO.       i' O                               Gaou'
     .                    UCG-27694                                        P0~E No-                           REE
                                                                                                                               ~

S P RE A DER J oirvT The c. levis has botn horh.ontal and verWL i Com ponents Acting on if; so the siresses wlLL b e S uperimposed f or th e clevis. Jh4 Conhcf Site S S d u e F o Yh e forc e P w ould b 4 , fcp :Pdt  : syv  ; 7u  ; ,,,v . , ..

                                                                                                                      ~
                                            ;                t                     d l

The contact sires 5 due io tht. mcment t4 w oui d b4-f c m = M Ca lI fcm N

                                                                 %        N     %

l w h en these, stresses are combined , th e rewit i $ A ho P /dt + MC/I D

                    ,                                                    h
                                              \
                                                                                                            \

E d. MEV. *.w r H O M OATE CH E'O. S Y DATE CH K*D. tv , . DATE NO. DATE W45flNGHOUSE POMM 583130 m,  ;

l- . . WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION p TITLE . PAGE n actor Veetal Internals lift Rio 17 OP 48 PROJECT AuTMOR OATE CHK'O. SY I) ,DATE CHK'O. S Y DATE CGE Q ( Q,,o,s m3 f,$ & I* Q s.O. . CA LC. NO. W

• pt NO. GMouP UCG-27594 .

REE For a re.tangulac Sedion - 1 h I,= b h 3/12. 4 nd C. = h /1. t h b q There Voce fc max

• 9 /dt + 6 t1/dP Th e ce e ntire. m o m en i oct in g on -the Jom4 will b e -

M tein l = P (.* +3 ) Divid ;ng th o J ein t moment be, tween ih< two ends. M2 (9 / tl * (tt3) ,

      ,                    In %e, vedical plan t 9= W/b' 130,000 /6 " 31, 3 3 3 lb s,
                          -6t 3 = 1.50 t ,o b                  t. 56 in NLea)"[3f;;31 1,56            99 0 66 (n-lb.

3 ( 1 /t in the h or;2ontal Pna i 9 = 64,s60 /2 = n ,2Tolb. t+3= 5,ov t,o6 tc6 = 5 12. M spuder

• I16,14 01($.11)

M 3 preadec : 11A 31 in -lb. - R E V. MEV. AUTHOR DATE CHK'O. S Y OATE CH K'O. S Y OATE NO. OATE WESTINGHOUSE FORM 882130

     .c       ,
             '"                                 E 1                                                                               .

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , , . TITLE PAGE , p actnr vessel Internals Lift Rio 17 'O, 48 PROJECT AUTHOA OATE CH K' SV DATE CH K'O. e v s.O. CGE Qf 9 4 , ,; gjg5 A, j f OATE CA cc. sO. uo gi.E'aO. CaOua REE a SP9EADIR Joint . ~ The combined effects of the hori2ontallsprended - add vectical (tec3) moments acting on +he sling le3 iug kre obtained using the me d of Sec_ t o-II,

                 -Pg e 33 4,y of L: P. - Po p ovl 3 M ECH ANicsof M A TER IALS
                 'i N    Edi+ i o n ,

s N M clevi5 : ) Mhprender t M I Loy M cl e v i S * [ ' M, 637 1 + y,o p * . M clevis * / L 13 X 10 i = 46,072. In-Ib The combined . b edn3 stresses q r e Ec m ax =fe,@Fep Pc ma x : P /d e + 6 ti /dt'2-For tht Clevis ; h 9 = \ 00,129/' = 50, \ \ 5 .bs d=& 7nn = 4,00 in. 6 250 - 2.(, o y S j = 1, 9 l i n , l Pcmat' 50 ; iis L ( 9 k 071L l ( 1,o o# 2.,yl ) 9 ,h ,o r g'2 ,9 / P f c max = F l 'l '1 ' i- 7. 4, T 11 Ec M4 X : 30 Oil PSI j !- R E V. REV. AUTHOR DATE CHK*O. a v OATE CHK'O. a v OATE N D. DATE WESTINGHOUSE PORM SS2130

. \

      ,  .                     WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE                                                                             PAGE Reactor Vantal Internals Lift Rio                                            19 oP 48 PROJECT                 AUTHOR              OATE CHK'O   Y           A E CM n'O. S v        omrg CGE              Q,g h ,. 3/y3              (   j       -

S.O. CA LC. NO. &14 PjlNO. GROUP

                                                                                                          ~

FOR +6e s pee a.c @ P 64 5 60 / s

• 32,160 lb, 4.=d p,.n 9.0 0 i n .

                     -t. = 1.S 0 In.

fc mg x = 31,1To bv7) b )( 2.T ) 4 k ( T 7('-l .oo)(2. 5)i - Ecm q t : ap.15 + ~19 T33 = e, o 6 I P ST .

   ,                Fo r %e l_e3 @
    )

P * %L = 23 o/ con = 3 7,33 3 l3 3 h h d = 4.00 t o

                      &     2. 5 0       2. *T : .1.15 gn ,

ei k1.2s > s < 4. 2.s> > fcmqY ~ 's,269 + 1%S7 7 7 O c. m q ( : 1 T i 'l 'l 1 P 5 I mgy, pay, AUTHOR DATE CHK'O.SY DATE CM K'O. SY OATE NO. DATE WESTINGHOUSS FORM 552130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION _ TITLE PAGE PAOJECT Reactor Vessel Internals lift Rio 'LO 'O r 48 AUTHOR DATE CH K'O. S Y DATE CH K'O. s v OArE CGE q.( 93)u u ; y73 fWf S.O. CALC.uO. uu m's NO- caOur g Check o F e,dreme fiber siresse5 to kISC CRITERI A _. R ea M na J The bearing ress Calculations f or th e lowf e

       'cA4vis , att                +ht Lowf r clpvis If d tiemQ
        +he s prende e lug , it44 and th t lec; lue) item @j ace done t-o determine the stress field                                           3
         +he only ccitecM being thd they be belovv y s' eld, Trad;+1onally bearing of pin joints is don e hnoring such local concentrations and so the appropciate Calcuktions for which reference allowables are.

obkinable s s Sc= 9 I At ', Tbe, A L5 c. allcwnble is Sc= o,qo Fy where.Fy c %eyield sirength of mqie cia ) Lowe r clevis and Lowee ctevis pin Beaciny Fc= Plac = FT /1/ AC

        /\ c. = d t = 9. o o ( 2 5 0        1 C.o 95))
             = 9. 6 9 i n'-

Er = l o o,nq lb3 / 2 = 50,115.l b5 Pc = 50.I15 . El 41 PSI

                 '1. M SPRERDE R lug 6eacincy                                                                .

Pc=P/Ac 3

                                 &c = d t = 9(2.5) : losh*

Pc: IJg un /d = 312 t PSI IO _ RE AUTHOR DATE CH E'O. S Y OATE CH K'O. S V OATE WESTINGHOUSE FORM SS2130 ,

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Ranctor Ve ne'l Internals Lift Rio . 11 op 48 PRCJECT AUTHOR DATE CH K'O. S Y O TE CH K'O. By DATE s.C . CGE $,6 f h j 3/y3 CAcc.uo. va ge no. 4RM oRouP REE LEG LUG. Beacing _

fc

_2 , A c = d t = (4.0 o X 2.5 17 ) = cl in '

hG - 9c = w/4-

                                                                                     =   %T; W .= '115 9 P SE kc           1
                                                                                                                                                                                                            ?

Clevi s .q do s, co o ) = 3(g500 2 5 139 Lowee clevis Pin 1 ( 15,600 ) = TS,Soo ). 5199

      ')              Sprendec Lug                                                               .3 ( 3 t,o oo ) : 39p_oo 2 3nt Leg Lug                                                                      . 9 (3 7,000 ) = 3 'i,lo o 1 i.f 2. 5'*l J.

All of the above it4rn s satisfy the kIS C Bearing critecia an d- are accqtable . How ever, in order te b e cons ervative the 3 higher numbecs generated in the N est s et of t.a\culations will be used to deterrnine. the ' sitesses for hems (o,7,2 and \ \, 4

    .                                                                                                                                                                                                           I M E V.                   REV.                                            AUTHOR          QATE CH K* O. 8 Y                                                      DATE CH K*O. SY         OATE NO.                     DATE WESTINGHCutS FORM S52130

                                                                                                                                                            ~      '

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE

                                                    -nemeter Ve<<s1 Internals Lift Rio                                                         2.2 on 48 PROJECT                                     AUTHOR            OATE CHKO.SV         DATE CHK*D. S Y               DATE CGE                                 6,( ,Mw; p n ,'Q 1 Q             3 s.O.                                        CALC.uO. ud         spruo.               oRoue UCG-27694 r                                REE
                                                                                                                                                                  ~~

LOW ER SLlNG LEG C. LEV 15 @ MWL i AST M A 911 S T E EL FORGtNG CL Ass 3 L*---tom  : W1.00 -.. I s I y - 9 U Nc-13 a

                                                              \v
                                                              \
                                                                                            \
                                                              \                             \

N 1100 n.w h x N is L 0

                                                                                            -s
                                                       ,                                               r y

i 2 FULL R Lt.0\S$ S.00-+ Cornets .C'j5

                                                             ~'

Tension @ 9.0ls $ Mole Pt = P 3 A v = (10.00 - 5.00 )(Cl.00 -9,0 ld - N C 09 sf Av Av = 7 4 n in i Pt = mo n9 - = Hon Ps1 2.'i,1 1 From s pceeder 3oint calcuidion t4= ct on in -ib. RE V. RE V, AUTHOR DATE CH K*O. e V OATE CH K'O. S Y OATE NO. DATE WESTINGHOUSE FORM SS2130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION l TITLE PAGE

n. actor vettal Internals lift Ria

                                                  ^

l'2; On 48 PROJECT AUTHOR OATE CHK O Y y O TE CHK0.sY DATE 8.0. CGE $,(th 3pg3 CA cc. no. uu

                                                               %*                                           onove gyE mO.

REE Sending s tress @ Sedion A-A ( Pim H ole ) -

                    %=MC                .) ' tw = vie,o 711bsn ; C = 2s-7(cud - 1,2oSin I                                                                      1 I -: $             L9 '4.014 ) /M9 = b . 9 909 in Y

12. It Fb: I 9 L jo 11 Y l 'l ov) =. M 135 PSI 3

( .'t 9 01 - Combined mex, bend!ny ( tenston @

m. .

                       'i.ot5 f hols
                     -P max = h +h = n ) 73s + %on : 11, T57 PSI Bencing Sitess From +he 5pread e n Joint calcula1/on:

Amx: s 111 t 19, $ t 1 : 30,0 t i P sr 3 Threqd shear Th e Wegd sheae is th e sa m e as-th e 0 7 Pod's thrend shear @ Pu- Inc m Ut.1 l 1 fv : L(57 i PSI ggy, p g y, AuTMOR DATE CH K'O. S Y OATE CHK'O. SY DATE NO. DATE [ j- WESTINOHOUSE PonM SS2130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION * ' e TITLE PAGE PROJECT

p. actor Vessel Internals lift Rio AUTHOR DATE CH K'O. Y D 71 On 48 LeMq E CH K'O. S Y DATE CGE q; f ,$ d g g 3/ 73 (),

S.O. . CALC.NO. W8 F) E 780', Gf1OUP UCG-27694 V REE LOWE R CLEvts PIN h MatlL: AdT M k sby T'l9 E 03o Prec iphilon Hordenly skinlew Sieet AC,E TREATE D AT ll50*F for 4 hours, 4.t 0 C oole d t3 5,000 PSI M I N T E fV S I L E Ytreng i b lic 2.7-3 l t  : 4.00 1 L 1 Forces and moments 4ctIncj on Pin

                                                                              ,y/6
                                                      /

FH Fa f3U p) /[>j)MSPreadec

l. M5preader

                                                        %        3    %d   a tes
                       ".E$'E~

tv d3.

           '                                              s-W.

6 j - - vectical Shear

                                                                                    - Worisontal S he A r S HE AR A\
                                                                      ,y   .

M0MENTS ngy, ggy, AUTHOR DATE CHK'O. S V DATE CHK0.SY OATE NO. DATE WESTINGHOUSE FORM 552330 L _ . . . ' .. i- ii .. . _ _ .- . . .

i. WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE paaetor vessel Internals Lift Rio 7S on 48 P R OJECT AUTHOR DATE CH K'O. S Y QATE CH K'O. S Y DATE (,( $ h ; 3/73 q#f j CGE s.o. up CA LC. no. spE no. oRour

                                                                                                                                    ~

The mqximum shene occurs g +he clevis fv = .f_ ) P = Fr , Ib> = U_d} =. Tja} = n s 7 ,n 1 AV 4 y F v = t oo;, M = 7 9 14 P s'I l 1.D The mqtimuw1 Beoin3 stress occurs atihe clevis a nd is c_oicu)nted i n the sprender Somt analpis Fc.ma x: 71 q q i 14, gl 1 Pcmqx: 30,olipsI 8ending 5 tress - From th e s prende Joinf analv3;5 +h e ma rimurvi 3 Mornent t s M clevis  : 9 6, 0 7 Z. i n - I b , Fb = tlc 3 c = d_ ': gag 1,0 0 i n I 1 1 I: IT O  : TT ( 4,00N _ 12, s-) i n 4 69 6 'i Sb= A h;0T1(2.oc) ' 11.57 fb= ~15,176 psi REV. REV. AUTHOR QATE CH K'O. SY DATE CH K"O, B Y DATE NO. DATE WESTINGHOUSE FORM SS2130

                                                           ---i--im.m. mei  n

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . . TITLE PAGE Reactor Vettil Internals Lift Rio 26 OP 48 PROJECT AUTHOA DATE CH K'O Y f DATE CH K'O. 5 Y QATE S .O . CGE $f,$ h a 3fy3 q CA LC. NO. W5

                                                                                             ~

F E NO, g]/h GROUP UCG-27694 REE 5 9 RE ADH A S S E M B l.1

                           .                                                                                                                         /                    /

(oO*

                                                                                                                                  /4 LOO X 7,00                                                                     '
                                                                                                               -l*
                                                                                                       / '/ ' b X .375 SQUARE \                                                 !                          ,
                                                                                                              /

W ALL TU6E  ! / '

                                                                                                                /                            ,                                                               l 3.6
                                              \:      'N
                                                                                                                       %.0\Sh                                                                                    ,

4 ,.__. \ ... L, __. / 250 j - g A ,

                                                                                                  ,. _,-7 Full &                                                  s           ,                                                   ,    Points of
                                                                                                                                 'y          '

iniW5 CCtion 10 0 j g 3pp of [.e3 k '$ . 1 i/ _bs REV. REV. AUTHOR DATE CH K'O. S Y DATE CH K'O. SY DATE N 3. DATE WESTINGHOUSE FORM 882130

~

          *    ..                  . WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION
 ,                                                                                                                                                          \
      ,       TITE.E                                                                                                 PAGE paaetor Vassel Internals Lift Rio                                                            D. / On 48 PROJECT ~                 AUTHOR              DATE CH K'O.                       Y      D TE C M K'O. S V                      DATE CGE'             (1.6. hve3/73 &                                         '

GRQuP S.C. CAi.C. no. agt ma.- 5 P RE ADE R A RM - M a Ti. . AsT M A - 3 6 s T eel. _.. Bloc k - ASTM A350 LFI FORC,1NC, STEEL ( N O CV N TE ST R E q' 0) S9RE ADER LVG h 'M AT'L i ASTM A-Slh GR /los 7 o STEE L Plf;TE , NORMAL l1ED , O R AD7, GS,, 6 j Q ( T FM-  % ( P AG E 16 ) Wi,5 bolbs(9 AGE 3),STRESS N:b E. ARlWC,, o 11 grg - lb s

                                                                                                                                                  '?

The beaeing M re55 t5 Cctlcolat<d N 'In 4he 5g ceqdf r 3oint c.Alcvlation 4 m-f c. ma 4 " 3 21 T t- 19,T3 3 = 2.3,0 6 l P T 1-Tension (D H.015 % Hole (PlN Hole ) Ft r l. = F w ,-

                                                     , A t = ( lo.co-4,oi5)(2.so) = 19,%3 i n2-A+           Ae P6     64;no/1 = 1,15'l P SI 19.% 3                                                                                                      .-

6 E N O INC, O tt.ol5 f Hol e fb max =E - T1 O'iIlTh) I .E I: W =hooo-use h d =,,73in N

                           ~I 2.                       l 2.

REV. REV. AurMOR DATE CH K*Q. S Y OATE CH K*D.8Y DATE NO. DATE WESTINGHOUSE FORM 582130

            ,                             -,                     , - - - , - - - , - ~ , - - -               -            ,-----.----en,          . ~-<

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION - - TITLE PAGE PROJECT Rt.actnr vessel Internals lift Rio 27 On 48 AUTHOR DATE CH K" BY / OATE CH K'O. SY s.O . CGE (C,f A ; 3/73 CALC.u o. r

                                                      $hh)J (p.Ev0.                            grove CATE gy = (#nn Y 2.5/2 )                  :     13,uo            psi 1.71 Combined Tension and Sending bomb = Fo + Fw                2,157 t 13,160 = 15 4 l 7 PSI       3 S 9 RE A DE R BLOCKh M h-T ' L . ASTM Pr 35o LFI FORC, LNG STEE L

( N O C VN TES T REQ'D) BEARtt/G ou SPREADER Block Thebearincj on the sprectd e r block is eovai to th a b c.c,n g r e ss iv e strew in 4h4 sp ead er u m P = BiL2. = 6 4;W G = 37,2n tbs cos,3o . T bb o Fc = 31 r) s = 19 t o P SI l0 13 l l l l l l REV. REV. AUTHOR DATE CH K'O. S Y DATE CH K'O. SY DATE NO. DATE WGSTINGHOUSE PORM 952130 \ _

 ,  ,                     WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE                                                                              PAGE PROJECT poactor Vesse'l Internals lift Rio AUTHOR          DATE CH K*     Y      DA 'E CMK'O. S Y 2.9 OP 48 carg s.o.

CGE 6,C.p h ; 3/g3 CA LC. no. vd

                                                           &             croup pE ao.
                                                                                                                ~

5 9REhD E A AR M h - M AT'L. 4-% ASTt4 MEEL L Mo M AISC. M ANU AL o f STER (_oN S TRticTrorv 7H ED, 9 3 .ij l 3 Le+ L 7'f.G (.1 co s 3 o9 = F19 4 i n. O 11. 0 ft. ~ Let Ks = e mdive Lengt h factor

                           =

1 Foc a pin-pi n Bea m

                . '. E F F E (/il v G L ENC,TH = L E E= 10. 7 f t.

From 'b e AIsc Table P allowable = ~ los,00 0 lb . For Fyeld = 5 6,000 PSI A = i o.1r 3 i n' f 4 tiowable = P allowable / A Felowa%Ie = 10s, coa l to.D Fallowable : lf,% 'tPSI R EV. REV. AUTHOR DATE CH K'O. S Y DATE CH K* O. S Y CATE NO. DATE WESTINGHOUSE FORM 552130 l l

                                                                           -_-____-___--_____-----_-___n

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION . o TIT LE PAGE noactor Vesse'l Internals ~ Lift Rio 3D OP 48 PROJECT ApHOR OATE SY CH K'D. S Y DATE CGE m.(,&e 3;y CHK'O. Sg & ff} OA1E 5.0. CA LC. NO. Ug 1&f LE NO. GROUP UCG-27694 REE

                                                                                                                               ~'

CO M PRESstvE STRESS IN $PREADER ARM ( P s Frt 1 p c c3 3co = pn 9: En/t - Fu C05 50 (' = L4j SLO /l = ~5h 17 5 lb3 c.o S 3 0' Pc= 31 17 T = 19 f o PSI' so.T3 a G CEV. R E V. AUTHOR QATE CH K*O. SY DATE CH K'O. SY DATE NO. DATE WESf tNGHOUSE FORM 552130

WESTINGHOUSE NUCLEAR. TECHNOLOGY DIVISION TITLE PAGE paaetnr Vessel Internals lift Rio 3l oP 48 P ROJECT AUTHOR QATE CH K' Q. Y OATE CH K'o. e V OATE CGE h,f.Yad M 3/?5 6M '

                                                                                                         .'l S .0.                        C A LC. NO.        (/U            Pf%sE NO.                           GRQuP UCG-27694                                                                                               REE M AT'L :

LEG Ass E M BLY LE G lug,'. ASTM A s tk G R ROE lo STEEL, NORM AL11EI) E E Ch hN N EL5 '. AST M 4 -M STEEL,H. R.,

                                       ) "EE U" b
                    -                                                           Moo NTtNt, BLOCM f6TM c.MNNEth                  (AMo No cs/,LFI       N TEST  Port,1Nt, REQl D)STEEL                  -

wF t 0 5' E-loiT ELErTRn0E9 LEG D ETAIL5 mts ^E .h 95 .uuS* k _ 5.00 R

                                                                                                                                     - --y 1

J

                                                                                                                ,      .m __,Mo
                                                                    $0, 3.Tl l
                                                               ,                         r o s s a gianov\      q           \

{ 8

                               , l  :-                 140VNTING. g                    ,b').c0          ;       l                  ;   Wr-Block                          i s

i . y .- 7. li --.i '+_. 50 Tiit, w_ f 2" t.0C TYP. / 3.00

                                                                                 ]        ,     ,
                                                                                                    , N, d        -

4.00 in ThK. {S N ~ ~ ~l 4,50 Break

                                                              'So   \                                                                  Ehes 50 r     <-

V M ,so b;_ cd REV. REV. AUTHOM DATE CHK'O. S Y DATE CH K* 0. S Y DATE NO. DATE WESTINGHOUSE PQRM SE2130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION , , TITLE PAGE Reactor Vassel Internals lift Rio 32 ~ On 48 P ROJECT AUTHOR DATE OATE CH K'O. SY DATE' CGE q.C, ph; gfg3 CHK*D.8k t), ' g[3j s o. CA LC. no. y0 Pip ud. oROur L E G LUG h 3 p P

                                               ,           t 2.)

(-.)~

                                             ~

3% -

                                                         ~

M t. EC, = 9 9,0 6 b i n - Ib TE NS 10 N @ 4,015 % lio lC fb .E. 3 9 = W = 2 3o joon = 35,3 5 3 1 b s . At 6 6 . h: 1.5 l 10.0 0 - 9. 0 t s ) .151: 14.90 in' f4: W ll - - 37 V23 =.15 7 ~3 PSI 1910 1490 B E NOING @ 4.015 y liol e Pb = tic I : h.b2 = (.io, o o- 9 ci s ) h . O = 7, 7 9 3 i n 4

                         )

I t 1. rz. fb = 4 9enMe l'16/23 = 7 il o 9 51 - 7.1 9 3

                                 /

QEV, REY. AUTHOR DATE CHK'O.8Y DATE CH K'O. 8Y OATE NO. OATE WESTINGHOUSE PORM 882130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE Reactor Vassil Internals lift RfC 9'4 OP 48 PROJECT AUTHOR OATE CH K'O.SY *

                                                                      . , . DATE CH K'O. S Y '       gArg
                                        . . 11 M [  [D    /

S.O. CALC.NO. UQ pf No. GROUP C,Oh 6lNED M A1. 6 END\NCo AND TENS 1ON __

                           @ H.0ts f \40\E Fbcomb: Fb th                                                                              l Ft comb :      1Tloi2.513=l'Of939SI                                                         )

B E AR \NG . j The, bec.eing stress is calcU\dtd in the sprender ) l Joini caituldions And is

        ,              P c, mu       4,1.59 t 19,5 3 f = 1 T,7 0 psi v

l l l i l REV. REV. AUTHOR DATE CH%'D. S Y DATE CH K*Q.SY QATE l NO. 3 ATE

            - WESTINGHOUS FORM 882130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION ' e TITLE - PAGE paaetor Vessel Internals lift Rio AUTHOR DATE CH K'O. 8Y 34 On 48 PROJECT OATE CH K'O. a v OATE CGE Q ( Q L ; 3jy3 p, fQ)JQ S.O. C A LC. aQ. us yE NO. - oROve REE CHECK OF EXTREME FtSER. STRESS To AISc. CRtTERIA Co M otNED tension A rv o SE N D I NC, Com bined stresses - 5edion 5 -l,b For Lowen c. levi s @ fa = apn PSI Bb: 17; 735. P SI q = t 05,000 P51 For spcendec Lucj @ Pq = 1 ,I S 7 P S I Pb = 13360 PSI Fy = 3%,ooo psi For Le3 L ug h 4 F a = 2. S~) 3 P S I Pb= '? T70 P5'- . F) = 3 7, 000 f4= computed axial siress Fb = C om puted C.cmpre%lv4 be nd; ncy . F b = c.c mpre ss ive b en riq st ress t hat w ovid b a Fa = u permHied igi McessiPthewovid bendin.g be momeni permHtedaloneifex axelisTed, IC rC P. Q{on t eXiSId d Sec.iio n 1. b 1 Axial Tension f Bending governs, ,', Focmul9 (l k-lb) jouerns i R E V. REV. AUTHOR DATE CHK'O. SY DATE CHK'O. S Y DATE NO. DATE WISTINGMOUSE FORM 882130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION

    -      TITog                                                                                                 PAGei neactor vessel Internals Lift Rio                                                               35 on 48 enosec7                       AuTwon                     oATE can o.sY                     can o. v               oATE Q,(Jofw fjg3 f, PL Qg oATE I

CGE s.o. cAcc. No. V0 caour (".eNo- g F4 4. Eh + Eb.y 41.O ~ __ o.60 F F b4 F by 7 For ALL Thcee me m be05 wi% combined toads +h e cec 55 -Section is Solic! 50 Fb = .15 F7 pe c Sec ).5. l. 84,3

                 , Lowee clevi s b fa      , Eh_ 4 o                  -

_ 4; o,1 n , T 3 cr = ,190

                                  .15 Fb                   .b 00s,000) , .15(tos,cco)                                    -
                   . b F)                                                                                                           ,
                     . lio 4. l. O w                                                  m S preAde r Lug Q) fa        4 Eh       po=            1;10 -               L3, %o         =.560
                   .bFy             .75Fb                   .b(37,0c0) 7 .75C5%ccci
                      .560 A             1. 0 L E c, LUG, h
                  .fa-     9       .Eb. p o = 1s n                      ,p 7 t7 o           =    ,3T9
                                  . lS F b                  .b (3%cc c )        .7507,000)
                   .b F) 3 Ti         6. l .0 R E F '. to A N U A L oE %TEFl                       e nNSTRUCTIO N l

10 E Diric N MEV. REV. AUTHOR DATE CH K'Q. S Y DATE t. 4 K'O. S Y DATE NO. oATE WESTINGHOUSE PORM 952130

WESTINGHOUSE NUCLEAR TECHNOLOGY. DIVISION TITLE PAGE Reactor Vessel Internals lift Rio 34 OP 48 P ROJECT AUTHOR DATE CHK*O SY DAT E CH K'O. S Y DATE s.o. CGE @r.C, Q g yg CAcc.u O. 90 OMM OmovP

                                                      *(f E NO.                                        REE L EG, LVG W ELD                                                          .                                      -

P,E Ft RE NCE'. L) Nc.oLN ELECTRIC, ccM PANY i SolvTION To 0 Es tevN oF W EL 0 MENTS 0 Tioill P AC>E I 3 p[89 if the. Uppe r weld which ic, 3 a pf nf trailon (M _T_. weaker Pillet weid Joe simplicity 3 andwtId --

                                                                                                                ; i s assomed

_ w ia % 7.ai'  : it i s c.ons ervdiVel y usum ed that +be T.siif' - 3< thcoat width is ,3 7 use iht smaller ofI 3 l \q

        . 3 7 o r .s O (. ,7 01) i 50 the Weld mq be                                       4 modeled by 4 5implf Cctse .' . 50(.,7 07 )= 3 535 /                                                37
       \"b d O hl I              sw = k (.3b tM M'
                                    =     150. (.3 h) + 3.Tl)                    = 31,50c1 s

5 = 31,5 09(.3535 ) : II.13t in3 Fv bending : M i ao = 4 q o 64

                                                              = S4 05 P SI 5                  \\.\ 3 T Fv s h en c ro cce = P/At , P = w/ 6 , A = [. 2/') ' 2 (5.T f)] .3535= 7.b4f d Pvshene FO c c e. : Mc; cec /6 = 5 o l'7 P SI
                                      -) . 4 4 For Fil\et welds, bo% stesse s ctre. Trecded a s Shene S tresses    3 50   fv comb max = fv bendWf

• f nnem fccce.

F Vc_ombm ax 4405 tSol; = 9912P5I QEV. REV. AUTHOR DATE C64 K* D. S Y DATE CHK*D. 5Y OATE NO. DATE WESTINGMOUSE PORM 852130

e .. :

             ,  ,,                             WESTINGHOUSE NUCLEAR TE..CHNOLOGY DIVISION TITLS -                                                                                                                     PAGE Netar venal ~ Internals Lift Rio                                                                             37   OP 48                          -4 PROJECT                                                    DATE CHK                                        CHK'O.SY                               DATE CGE AhMOR.(OJm 3r73                  D p'O. SYgg_[hDATE S.O.                    .

CALC. NO. WW- MLE NO. GROUP UCG-27694 REE LEC> c H A NNELS @ M ATI L. h5TM A-% STEEL h R. calcula1 ion of crow-sedional area of Leg c,hann els Fo r one chan nel a = C t. ~l f 1 ( 1,0 0G ( . 50) + 1 C. 3.00- i.00 .5'l (. 5 0) 4

                                        %(k)(3.0-1.D1)                                                                                              -

3 A- L.5 T 3 m* J' TE N S\0 N I N L EC,5 h = .9. ) 9 = W. At b ht: : A cnuwst - b.553 IA* P-t, = Bo.000/1 =. 559% 951 , b.TS 3 l . m g y, mgy, AUTHOR DATE CH K* D. S Y QATE CHK*Q. SY DATE NO. DATE WESTINGHOUSS PORM 542130 l l

                                                                                                                     ~

I WESTINGHOUSE NUCLEAR TECHN' OLOGY DIVISION TITLE PAGE Itaartar vessel Internals Lift Rio

                     ~

PROJECT A)'TgCR DATE CH K' sY OATE C H K' O. B Y 37 OP 48

                                ,                                        y                             DATE S.O.

CGE tv.c.i M CALC. NO. W 3/73 $ L A I J E NO. GROUP R0T0-LOCK ASSE MBLN Tht SOTO - LOC.k Pr SS E MBLN Set.s only the Iniernals weigh t w = 1o1,o00 lb. 5o the remctin ing items will us e +his d e sign,weicj ht instead oP %e weighi QSSUm ed Po r %E p0evtCd5'devy1S Ro O HocsiNe T y T g

                                             \             \            LOAD NVT s x\             .
                                                           \   x1 MOLINTING                  ;

B LOCK. \ \ a _sJ . h GuiOE SLEEVE -

                                                        /
                                                    ///
                                             /             /

RCTO' LOCK h  ;'/ stuo  ;  ; I gg 1 1[ M 3 REV. REV. AUTHOR DATE CHK'O.SY DATE CH K'O. 8 Y DATE NO. DATE

 ' WESTINOMOUSS FORM SS2130

e e' WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION s

      .,.       TITLE                                                                                                      PAGE
   ,                       Reactor vessil Internals Lift Ric                                                                 39 oF 48 PROJECT                       AUTHOR           OATE CHKO.By                                         CHK'O.8v             OATE CGE                 $,C,fh 3/73 p,'QL),J3 W OATE vv s.O.                          CA cc. uO.
                                                                                &Ew.                                onOu, n                                                                                       _

MOUNTINc, block Q) t M AP L, ASTM A-350 LFI FORC,lNC, STEEL (No CUN TEST REo'p)' WELD S : E 7 0-1T ELECTRO 0ES 6 EhRtNCs 0F LOAD Nui To MOVNTIMG 6Leck Pc = Plot , P =wl3, As=%( Di 2-Of) - Ae= % ( 0,1 - Dl) = % ( ?.15U .9 5'd) 7 3'? . S S' t ri 1 fc : 101.000/1 ,

                                                        = 17 4 3 P sI
     ,,}

37,55 S HE AR I N MOu wTWG Bi Ock wEl.Ds F v = _2 Av= 0. (. soy.70 7) hv 1=4fbaTi-2.(\2.gud+(3.00-1,51)f9(4) . t= 1. l . IO 1 i n ' N = @ l. M )(, s oX,707 ) = 2.1. T 1i n ' I ! Fv = log eco/5 - 3o77 PSI _. 11, r1 REV. M E V. A U TH's M OATE CHK'O.SY DATE CH K'O. SV OATE NO. DATE WESTINGHOUSE FORM 852130

g & WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE neactnr Vossal Internals Lift Rio 840 or 48 PROJECT AUTHOR OATE CH K'O. . ATE CH K'O. S Y OATE CGE Q,bh 3m o jM s.o. CAuC.no. ua yE no: anove Load NUT - a.w--.. M AT't . AST M hl-]b, m m 4

           -T1 PE 30 4 , h o T                3         y        3.00 ROLLED, COND A -                   \         m            4.00 MV NC-1.6 Thch                 '

r ,-N b , ,

                                                - I

TM -

I Thread s hear fv=_E_ A v = n Opdch Q./1 - A slots

• Av Fo r a M - 9 uN '

c-1B TH O ,0 = H AN0 M 5FRoM 6cok, ARKS

D p i +c h

• 3.T M fo i n , .- . 00 in A v = Tr (3.T u L1/3) 3.2 5 ( 5) = 1 f0,4 S9 ih 2 ,

L Ev: 2:01; 000/3 - 1403l PS I l'o. 4 S i - 6 enein g of Loa d N ut to Moonfin7 8leck The bectring stress is calculnted For the mounting blCc.k And 15 Pc 101006/; .:- t-) % P S'.[ Yl .55

          + St ,btracted For Slot cut for locking tab m red housing 7,g y,     ggy,                AUTHoA              OATE CH K'O. SY         r$TE CH K'O.SV             QATE NO.        DATE L  wasTimowousa pomu seanO

l l.

                      . o                   WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE                                                                                    PAGE PROJECT Reactor vesse'l Internals lift Rio AUTHOR                DATE CH K'O.                  DATE CHK'O. s v
                                                                                                                    'il Op 48 OATE CGE              $d ,-9&h',3/B                   (Y M b s.O.                    CA LC. no. Og                                        GRoue egE No.

nso& L M AT't. ASTM A -1% , Roo HOUSING h - a

                                                               , lp I '

T1PE 309; hot ROLLED C ONO. A I! FULL R 3.00 ll II g 1

                                                                                    /

a M II / ,oo-9 0NC,- M Thd, i ;

                                                               \l ll I

lI I T I I i i  ! -

                                                                                                                                       ~

5i i l'+-- 3.65 # .50

          ,                                                        I         i                     1 a
               )                                            y      i p   9.n o u                                                   i j       i
                                                             '                                     J 3*            I                 '

i i s - 5 00- b ON - l h Thd.

                                                       ,     !               I       i Thread shear on Upper 9, oo-90NC-1A -Thd The uppec neend s sheae sie ess is the same o s the     t ca d Nut's 4' v r 'lfD CCC/3 - 404l 951 16.959 Thread Shear on Lcwe r S.0 0 -bOIV L A Tti DS.

Fv = .P. = w /s , A v = n 0 pac.h Q, / z AV hv

                                                                                                                                         \

R E V. REV. AUTHOR D AT E CH K"). uY QATE CMK'O. S Y DATE NO. DATE WESTINGHOU$5 PORM 55213D I I

WESTINGHOUSE NUCLEAR TECHNOLOGY DIV!SION i TITLE PAGE PROJECT Reartne vessel ' Internals lift Rio LI "? on 48 OATE OATE CH K'O.SY DATE CGE- AhTHon,(. N gu3pg3 , CHK'Oh. YQ, ,JbWD s.o. . CA 6C. Ho. ur gr.E No. omove

                                                                                                                 ^'
            . FC A 5.00- b VN l o TH D
           '(M ARkis T-lo)                   D pi kh = 0 - 3 6 =. s -1Et
                                              ,                          TN         1r(6) o pti ch = 9, ra n m J. : 3.00            , so : 1.5 0 i r1 hv= nj4.MllI(? En)                    ::-    19.110 iry-
                                        ~2 fV=          P
                             = Wl.3 -           10h 0004 = 3505 95I                                                      -

AV Av Itll T E N Slo N @ Ttf REhD REi.\EF 4 _ P_ = % _. 3 I

                                                &6 = i ( 0- d ?)= M3.f.s'- t.75 )= 7.057 m l

A6 At Ft 72n;noo / 3 = T3 56 eSI 8.05s 1 pgy, pgy, AUTHQR DATE CH K'O. S Y DATE CH K'O. SY DATE NS. DATE WESTINGHOUSE FORM sS2130 L

WESTINGHOUSE NUCLEAR TECHNOLOGY CIVISION TITLE PAGE

• n actor Veenal In'ternals Lift Rio 43 o, 48

             ; w eer                       Ausnon                                        o*Tu                      can oav           OAT    cMn o. eY A
                                                                                                                        / Lj m[hg 9                                    o.T.
                                                                                                                                               ~

CGE @ ,C . i ol_i_p_ c 3 / p  :

             ..o.                          cAuc.no.                   vv                                           e       o.               anove                      -            l UCG-27694                                                                                      C/                                   REE                          1
,                  Gul0E SLEEVE                           M6T'L. ASTM A 1. ;b ,T1PE 309 SST                                                                               "

hot RO LLE Dj A N NE ALEDi A ND P!Cb!.jE D, C oN D. A __ f, .o ctL._, l 3,isof ( s.o -buta-2.& Tbd.

                                               . j                                       g6
                                                                      \ Ti.L Ret;.e N f      \

s :i

                                                                      \

MAN $-.s i \ s l

                                                                                 .L e                                                                         **
                                                                        \W jk 3                                                                                                                .

h N s

                                                                                                                  }   -
                                                                        +-4.75$ 3 Thread shear The %ceed shear is the same as tb e lower thd,                                                                                            ' .

Shear on the red housincj Fv = P = w./.A - mn,em/3 _, 3 Sos PSI Av hv t s.u TENS no w @ ThD REUEF Ft=f_ p= w. ) ge = $( L.00*- S 06 2 )

• T lfo5 In*

l a+ ) 3 l I l g g y, g gy, AuTMon DATE CME'o. SY DATE CMa*o.SY DATE l No. oATO

   .      WESTlMGHouSS PonM SS313o
                        . - . , -                     . - - , , , - -     - - - , , . - - + - . . . - - - - - . - - -                    -r -

q:. ,t  :. 7' ~ Wi!STINGHOUSE NUCLEAR TECHNOLOGY DIVISION

                                         ~
                     \           <
 ^

rm.a n. Pact neietariana'l Internals Lift Rio - 99 On 48 PROJECT AjTHOR DATE Cg K' SV OATE CH K* 0. re y

                                      %.0,fojum; gfg3 C ,             nMI 'Uj                                OATE CGE'I S.v.                             CAi.C. ac. ut.       g.swo-                     caou'

_ REE N: M;non/3 ,,T19)P$1 ' t.165 Bearing o.P Guide. S te eve fo 4oto-\ock g tyd FC = 8 ) 9: W/3 , A C. : (dal dtl ) M: , d c = 3.311 + 1(..ill 3.551 in,

d. = it.19 0 + - M .ot ) = 9. 4 I t n .

l Ac= i ( 4.b t -3.s sf) = 6.151 in 2-Fc: 7o7onn/3 4,'7T L P c. = 1,11 T P S I. l i I 7,g y, ggy, AWTHOR OATE CH K'O. s v OATE CH K'O. s v OATE NO. DATE WESTINOMOUSS PORM 883130 -

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n. actor' Venal Internals Lift Ria .

4 I OP 48 PROJECT AUTHOR OATE CM E' .SY OATE CH K'O. S Y Q,( Ag),,u; 1m Q & ,g /I, Osrg CGE 8.0. CALC.NO. V9 flLS MO. GROUP UCG-27694 V REE R OTo Lock STVOh M AT' L. As rm Asb4 , TYPE lo3Oj I 1-4 P RECIPITATioN j h ARDENING STAINLESS' STEEL AGE TRiiMD AT \\00*F foR 9.MouRS AND AIR C.00 LEO Tmin i 190,000 P SI Nii0 f a l

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                                         ,L                                        .ll REV. R EV.           AUTHOR                   OATE ChK'O. S Y                    DATE CM K'O. S Y                                  DATn l                NO.      DATE
  .           . WESTINGHOUSE PORM 882130                                                                                                         .

                                                                   ,                                                          1 WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION                                   ,

TITLE PAGE PRO JECT n actne vencel Internals Lift Rio AUTHOR CATE CMK'O.SY OATE CH K"O. S Y 9h op 48

                      ~CGE                   gr.(;fodsw ; y)73 h R),u( $$f                           DATE S.C.                  .

CA LC. NO. PILE NQ' GRQUP UCG-27694 ., REE kl = NuM BE R O F L A ND S = 9 ~ TENSION @ S EtTl0N 4 -A

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ft=P_ 3 P 'W/3 ; A + = 1T d 2/9 = tT (2.o45F/4 "3.'141(n2 At f t = .W. L = - i ni; one/3 = 19,53 'i PSI A+ 3 'i '( 7 - j s HL AR o F STUD L6N05 .

                    -P v =.E.            ,    h: Lcd Av Lc =Le gn Th o f Land s                    d :Dep1h oflands t

l-Lt : Si 1T l 'l 095) T N

• T.If5 d ini in 340 ,

                   & = (f.Tr r )(.7 lo = 6. 37 r in t                                                        .

l PV lo7 cco / 3-

                                                  = to, Til          PSI L . '5 7 0 6E ARlNG STRESS CN Siv o HE AD The head's bacine; rirew ts caleviated 6 4he guid4 S Le ed.

PC, " ~1010 0n /1 9 Q1T & SI (o . 7 T 2. T.E V. REV. AUTHOR QATE CHK'O. 8 Y QATE CH K'O. I'.Y DATE

         'gN 3.       DATE WESTINGMOUSE FORM SS2130
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                      . TITLE                         ,                                                                            PAGE RAmetnr Ve<<e'l Internals Lift Rio                                                                47 op 48 PROJECT .                    AUTHOR                           DATE CM K'D. a v    /        DATE Cr* K D. S v          QATE CGE                  $,1,fM 3/73                           yp         /

s.O. . CALC.no. a g.E =0. onoue EE N DI NC, IN L8NDS - R 3N O Lui2 - INSERT __ * / 1 up _, 1 c.hamtees ,o3 x 95 *

    ,s                             w= width of beeing sur face i

v= m _.03-if ms t , 0 3) = .m i n .

2. k 1 X* IM - . 0 3 - "L 09 T _ ul = moment 4 0m cP fo rce 1 1 1 l

                                     %'       ~1 '114       __.03 _7f44                       -  .232 = .1637:n-                           -~

1 1 1 I Pb = M /2 t und = 1 cat /L

                                                = 5.1 tr ( 1,095)(.119)l/4 = 075 Iq*

360 M = BendinS Momeni 1 }- ngy, g g y, AUTHQR DATE CHK'O.SY OATE CH K'O. S Y DATE l NO. lDATE , .WSSTINGHOUSE FORM 582130

WESTINGHOUSE NUCLEAR TECHNOLOGY DIVISION TITLE PAGE PROJECT Rawtor Vessel Internals lift Rio AUTHOR OATE C K' 4 T On 48' SY ' O E CH K'O. av QATE CGE Qs,C fhy 3fy3 g S.O. CA LC. uO. vo (p.E no. oROuP

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I P a = E N/31/N 3(.163s ) =(lo2pae)/3 (,g35) : 1113 I b . Ob- ti n = i q) TT esI

                             .o s5 CO M MESStVE B E A &lNC, S TR E55 O N L A ND S URF ACES A i =- [. 2,1 l9 - 1 C.03W 5 " 5 5 53 m'                                                              -
  ;                  hO I_1 125 i H. 03)f $ = 3. 7 5o in

• Ac = S i -As" 1.T03 in 2 i

O b = N 3.'4 Ac, _ 2. N ( WX.o'i ) = L 1.6 3 i n2 360 F c. = E.  :: w//.3

                                        .          :     2.02. eco/ 3 A'C           Al C,           1.'163 fc

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