Text

Rev 1 to Control of Heavy Loads,Response to Generic Ltr 81-07 for South Texas Project Units 1 & 2
	ML20107A013
Person / Time
Site:	South Texas
Issue date:	10/31/1984
From:	; HOUSTON LIGHTING & POWER CO.
To:	;
Shared Package
ML20106J966	List: ML20106J961; ML20107A013;
References
	REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 2348N-0151N, 2348N-151N, GL-81-07, GL-81-7, NUDOCS 8411010420
	Download: ML20107A013 (188)
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CONTROL OF L

HEAVY LOADS l

RESPONSE TO NRC GENERIC LETTER 81-07 L

FOR THE i

SOUTH TEXAS PROJECT UNITS 1 & 2 L

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_ CONTROL _0F HEAVY LOADS

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l RESPONSE T0 NRC GENERIC LETTER 81-07 FOR 6

SOUTH TEXAS' PROJECT UNITS 1 AND 2' REVISION 1

-OCTOBER 1984 h,.-

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CONTROL 0F HEAVY LOADS

-RESPONSE TO NRC GENERIC LETTER 81-07

.FOR SOUTH TEXAS PROJECT

-UNITS 1 AND 2 REVISION 1-TABLE OF CONTENTS PAGE

SUMMARY

OF REVISION 1 iii

-INTRODUCTION 1

GENERAL REQUIREMENTS FOR OVERHEAD HANDLING SYSTEMS, SECTION 2.1 0F GENERIC LETTER 81-07 2

SPECIFIC REQUIREMENTS FOR OVERHEAD HANDLING SYSTEM OPERATING IN THE VICINITY OF FUEL STORAGE POOLS, SECTION 2.2 0F GENERIC LETTER 81-07 10 SPECIFIC REQUIREMENTS OF OVERHEAD HANDLING SYSTEMS OPERATING IN.THE CONTAINMENT, SECTION 2.3 0F GENERIC LETTER 81-07 12 SPECIFIC REQUIREMENTS FOR OVERHEAD HANDLING SYSTEMS OPERATING IN PLANT AREAS CONTAINING EQUIPMENT REQUIRED FOR REACTOR SHUT 00WN, CORE DECAY HEAT REMOVAL, OR SPENT FUEL-POOL COOLING, SECTION 2.4. OF GENERIC LETTER 81-07 16 REFERENCES 22 TABLES 1

Cranes Identified in Item 2.1 23 2

Overhead Handling Systems Excluded from Item 2.1.1 42 3

Tabulation of Exceptions to ANSI N14.6-1978 Requirements for the South Texas Lifting Devices 47 2348N/0151N i

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I TABLE OF CONTENTS (Cont'd)

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FIGURES 1 through 15 Safe Load Paths 16 through 38 Safety-Related Equipment and Spent Fuel ATTACHMENTS A

Safe Load Paths B

Summary of Results of Stress Calculations for Lifting Devices for STP C

Critical Items List per ANSI N14.6-1978 D

Single - Failure Proof Handling Systems P

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' Summary of Revision 1 to the

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Control of Heavy Loads Report for South Texas Project Units 1 & 2 On July 2, 1984 NRC transmitted copies of the Technical Evaluation Reports prepared by EG&G Idaho, Inc. for the South Texas Project Control of

Heavy Loads Report (ST-AE-HL-90421). As. requested by the NRC, a conference

. call was conducted on August 13, 1984 to discuss the comments in the Technical Evaluation Reports. The agreements reached in the conference call are reflected in Revision 1 to the Control of Heavy Loads Report fer the South

, Texas Project. A summary of the revisions follows.

1.

Coment -

Confirm that the information shown on Figures 1 through 38 of the Control of Heavy Loads Reporc is also on plant equipment layout drawings.

Resolution Safe Load Paths are shown on Figures 1 through 38 of the Control of Heavy Loads Report in lieu of including the Safe Load Paths on plant equipment layout drawings.

2.

Comment The method (s) of physically marking or indicating the safe load paths in the load handling area should be specified.

The paths include loads handled by single failure-proof cranes.

Resolution It is not practical to permanently mark the safe load paths in the load handling areas. Administrative controls will be used to ensure o

safe load paths are followed. The administrative controls will l

include items such as temporary markings (ropes, cones, etc.),'a signalman to lead the load along the safe load path, etc.

l The responses to items 2.1.3.b and 2.1.3.c have been revised to reflect this resolution.

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Coment

The' weight recognized as a heavy load at STP should be specified.

Resolution A heavy-load is defined as~a load weighing more than the sum of the eights of a-fuel element, a control rod, and its handling tool.

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. Based on this criteria, a heavy load for STP is defined as 2300 lbs.

The introduction to the report has been revised to reflect this res'ol ut ion.- -

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Comment

. The interface lift points for. five heavy loads handled by the FHB

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overhead crane should be upgraded to meet NUREG 0612 -

Article 5.1.6.

Resolution It is Houston Lighting & Power's position that the combination of a single failure proof crane and the use of safe load paths provides adequate assurance in lieu of upgrading the interface lift points for the loads in question.. These loads are not carried near the spent fuel pool or safety related equipment.

If any of the loads were dropped during movement along the safe load path, no damage to safety related equipment would occur.

Item 5 of Attachment D to this report has been revised to reflect

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'this position.-

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Information for proper evaluation of the auxiliary hook of the FHB

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Resolution I-l:

!No heavy loads have been identified for which the auxiliary hook l'

would be used.

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..The response to item 2.1.3.a has been revised to reflect this resolution.

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Comment Mcchanical stops or electrical interlocks are needed to supplement i

administrative contro) for heavy loads handled over the

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in-containment fuel holding pool when it contains fuel.

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Resolution-The RCB' Polar Crane Main Hoist will be used to move the Containment 1 Fuel Pool Gate and Reactor Vessel Internals Lif t Rig when-they are

- moved over the in-containment fuel storage pool while fuel is stored

.in the pool. The Safety Factor for the RCB Main Hoist and the-interfacing lift points for these loads exceeds 10/1 and is considered acceptable.

The response to items 2.2.1, 2.2.4 and 2.4.2.b has been revised to

- reflect this resolution.

7.

- Comment Information for proper evaluation of the Containment Building Polar Crane Auxiliary Hook is needed.

Resolution The RCB Polar Crane Auxiliary Hook meets the same design requirements as the Main Hook except with a lower capacity.

It is used depending on the size of the load and other circumstances discussed in the report.

The reference to usage of the RCB Polar Crane Auxiliary Hook has been

- revised.

8.

Comment

' Complete' tabular information on heavy loads subject to NUREG 0612

- criteria is not provided. Either-complete the tabular entries, or justify their omission.

Resolution A note has been added to Table 1 to better explain the entries in the Table and the format of Table I has been revised. All the information requested is included in the Table.

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~ CONTROL OF HEAVY LOADS RESPONSE TO NRC GENERIC LETTER 81-07 FOR SOUTH TEXAS PROJECT

_s m UNITS 1 AND 2 REVISION 1 INTRODUCTION NRC Generic Letter (GL) 81-07 requested a review of the methods of handling heavy loads at the South Texas Project (STP), the implementation of certain recommendations regarding these methods, and information to demonstrate that these recommendations have been implemented. This report provides the required information specified by Enclosure 3 of GL 81-07.

Item numbers c rrespond to those in GL 81-07. Tables are provided which identify cranes of

- c;ncern (which are defined as being capable of carrying heavy-loads) their leads, lifting devices, potential targets, and locations. A heavy load is d: fined as a load weighing more than the sum of the weights of a fuel assembly, control rod, and a handling tool.

Based on this criteria, a heavy load for STP is defined as 2300 lbs. : 2348N/0151N

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R V.

-GENERAL REQUIREMENTS'FOR OVERHEAD HANDLING SYSTEMS,

-SECTION 2.1 0F. GENERIC LETTER 81-07 IWtC STATEMENT lNUREG:0612,~Section 5.1.1,-identifies several general guidelines related to

' Lthe' design and operation of. overhead -load-handling systems in the areas where spent fuel'is' stored, in the vicinity of the reactor core, and in other areas of-the plant where a load drop:could result-in damage to equipment required f

'for.' safe shutdown ~or decay heat removal.

ITEM NO. 2.1.1 Report the'results of your review of plant arrangements to identify all overhead-handling systems from which a load drop may result in damage to any system required for plant shutdown or-decay heat removal (taking no credit for

.any interlocks, technical specifications, operating procedures, or detailed

structural ' analysis).-

5STPResponse-p HL&P-~ has conducted a detailed review of plant arrangement to identify all L

foyerhead handling systems from which a load drop may result in damage to any system required for plant shutdown or decay heat removal.

A list of the overhead-handling systems identified is provided in Table 1.

P.lant general arrangement drawings and the plant model were reviewed to t,

determine if any handling system-capable of carrying heavy loads could carry

' loads over. components in systems required for safe shutdown or decay heat P

1 removal. The location of components of interest with respect to the handling systems was determined by review of general arrangement drawings, the STP 90-list-(Design Criteria NQ1000) and area surveys. A brief description of the cranes identified in Table 1 is provided below.

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Reactor Containment Building (RCB) Polar Crane: Each polar crane consists of two crane girders and a trolley.

The Unit 1 main hoist 1,

'has a capacity of 417 tons; the Unit 2 main hoist has a capacity of 500 tons. Both cranes have.a-15-ton auxiliary hoist.

Circular rails

. supported from the containment walls at elevation.141' support the crane girders and provide for 360* rotation..The. polar cranes were manufactured-by Whiting Corporation.

!2)

Fuel Handling Building (FHB) Overhead Crane: The fuel handling building overhead crane is located at elevation 101'. -The crane Ltrolley has a 15-ton main hoist with redundant reeving system'and a 1

L 2-ton auxiliary hoist. The main' hoist meets the intent of NRC r

Regulatory Guide 1.104.

The 15/2 ton cranes were manufactured by

.Kranco, Inc.

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Essential Coolino Water (ECW) Intake Structure Gantry Crane: The ECW 0

gantry crane is 'ocated on the top deck of the ECW intake structure and travels on rails.

The crane has a 20-ton capacity and is f

. manufactured by Kranco, Inc.

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iDiesel Generator Building (DGB)~0verhead Cranes: The'three'DGB

. overhead cranes each have a capacity of-3 tons and each is located

'over a. diesel generator train. The cranes are manufactured by Crane c

x Hoist Corp.

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-Monorailsi Monorails are used throughout the plant and have hoist

- capacities from 0.5 tons to 7.5 tons..

ITEM NO.-2.1.2:

- fJustifytheexclusionof.anyoverhea'dhandlingsystemfromtheabovecategory i

by verifying.that there is sufficient physical separation from any load-impact

point,and any' safety-related component to permit a determination by inspection that no-heavy: load drop'can result in damage to any system or component irequired for plant shutdown or decay heat removal..

_ STP Response'

. Table 2-identifies overhead handling systems capable.of carrying heavy loads 1

-which have-been excluded from the item 2.1.1 and the justification for their

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. exclusion..These exclusions.were. developed during the review described in the F

[ previous section.-

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' ITEM NO. 2.1.3-

NRC STATEMENT With' respect to the design and operation of heavy-load-handling systems in the 1 containment and the. spent-fuel-pool area and those load-handling systems 1

identified in 2.1.1, above,. provide your evaluation concerning compliance with

.the. guidelines of NUREG 0612, Section 5.1.1.

The following specific

=information should be included.in your reply.

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Item 2.1.3.a.

Drawings or sketches sufficient.to clearly identify the location of safe load

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paths,fspent. fuel,andsafety-relatedequipment.

STP Response

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. Table 1 identifies cranes that operate in the containment or the spent fuel pool' area or:that travel over equipment required for safe shutdown or decay heat removal. The fuel handling machine and refueling machines located in the

.FHB and RCB, respectively, have been excluded from this study because their

heaviest load, a single spent fuel element, control rod and handling tool, is l

by' definition not a heavy load.-

The. location of safe load paths, spent fuel and safety-related equipment of

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concern for these cranes are identified on Figures 1 through 38.

Safe load

-paths are' described in~ Attachment A.

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The-safe. load paths follow, where practical, structural floor members, beams ctc.; such that, if the load is dropped, the structure is more likely to

' withstand the impact.

The FHB overhead crane's 15-ton main hoist has been designed to meet the intent of Regulatory Guide 1.104, Rev. O, i.e., single-failure-proof cranes.

No heavy loads have been identified for which the Auxiliary Hoist would be used; therefore, this hoist is not addressed in this report. Although the designation of safe load paths.is not necessary for this crane since its single-failure-proof design provides adequate assurance that a load drop will not occur, Attachment A also includes descriptions of the load paths for this crane.

Should changes to the safe load paths become necessary through design cvaluation or operating constraints, revised safe load paths will be cstablished and incorporated into plant procedures in accordance with the guidelines used to establish the initial safe load paths.

= Item 2.1.3.b A discussion of measures taken to ensure that load-handling operations remain within safe load paths, including procedures, if any, for deviation from these paths.

STP Response Procedures will be prepared to cover requirements to move heavy loads over safe load paths.

Load paths will be explicitly defined in the procedures.

Additionally, procedures will require the use of techniques to ensure that safe load paths are followed, for example, marking the path with cones or ropes or having a signalman lead the load. Deviations from established load paths will require written alternatives which have been approved by the plant safety review committee.

Item 2.1.3.c A tabulation of heavy loads to be handled by each crane which includes the load identification, load weight, its designated lifting device, and verification that the handling of such load is governed by a written procedure containing, as a minimum, the information identified in NUREG 0612, Section

~5.1.l(2)..

STP Response Table 1 provides a tabulation of heavy loads to be handled by each crane including load identification, load weight, and designated lifting device.

l A procedure is being developed to cover handling of these heavy loads.

This procedure will include:

1.

Identification of required equipment, i 2348N/0151N

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Inspection and acceptance criteria required prior to load 1

movement, 3.

The steps and proper sequence to be followed in handling the load'

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The safe load path, 5.-

~ Administrative controls to ensure the safe load path is

~followed, and 6.

.Other.special precaution's.

-Item 2.1.3.d

. Verification that lifting devices identified in 2.1.3.c above, comply with the requirements of: ANSI N14.6-1978, or ANSI B30.9-1971 as appropriate. For lifting devices where these standards, as supplemented by NUREG 0612, Section 5.1.l(4).or 5.1.l(5), are not met, describe any proposed alternatives and demonstrate their equivalency in terms of load-handling reliability.

STP Response

- Description The special lifting devices are identified in Table 1 and are described below.

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Reactor Vessel Head Lift Rig Assembly The individual-items,that comprise the lifting assembly used to handle the reactor vessel head are an integral part of the

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integrated head package (IHP). The IHP is.a system that combines the head lifting rig, control rod drive mechanism (CRDM) seismic supports, lift rods, reactor vessel missile shield, CRDM cooling system, and the power-and instrumentation cabling (Figures B-1 and B-2) into an efficient one-package reactor vessel head design. The IHP is permanently mounted on the reactor vessel head and helps to minimize the time, manpower, and radiation dosage associated with head removal and

,f replacement during refueling.

The lift rods, missile shield, and seismic tie rods comprise the 1

CRDM seismic support system. The cooling shroud combined with the lif t rods, missile shield,.and cooling fans comprise the CRDM cooling system. The lift assembly consists of the lift rig, missile shield, lift rods, and the intermediate L

attachments. The upper internals lift rods are used in the rapid refueling mode to lift the upper internals along with the Reactor Vessel Head. The evaluation in this report only o

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q concerns the items-of the IHP and upper internals lift rods that-

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'are utilized during the lifting and lowerir.g of the reactor

~ vessel. head and upper internals. The major components that are Lused for lifting are:

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LLift Rig

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.The reactor vessel head lift rig is a four-legged carbon

' steel structure approximately 7 feet high weighing about 8,800 pounds permanently attached to clevises on the missile-shield.

During lift'of the IHP, a load cell linkage connects the rig to the polar crane.

b.

' Missile Shield The missile shield is a 5-inch thick circular carbon steel F

-plate about 12-1/2 feet in diameter weighing about 30,000 pounds.

It is attached to four lift rods that extend down to the reactor vessel head and has four welded lugs which attach.to the lift rig.

The missile shield prevents any missiles that may be ejected from atop the reactor vessel head from penetrating other reactor coolant system pressure boundaries and/or the F

containment structure.

The missile shield provides seismic support for the CRDM's.

Extensions on the CROM rod travel housings protrude through holes in the missile shield plate, limiting.the displacement of the housings during a seismic occurrence. The missile shield is in turn attached to the seismic tie rods, which are attached to clevices on the 1

refueling cavity walls.-

The missile shield serves as a spreader for the head lift rig, and transfers the reactor vessel head load to the lift rig during lift of the head. Only the latter function is

' considered in this report.

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Lift Rods Four <:arbon steel solid 5-1/2 inch diameter lift rods 25 feet long, weighing about 2000 pounds each, extend from the head up to the missile shield. The rods are threaded into bosses on the reactor vessel head and are bolted to the missile shield.

These rods support the missile shield and serve as a seismic support. They also transfer the head load during a head lift from the head to the missile shield. Only the latter function is considered in this report.

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Upper Internals Lift Rod Assembly The upper internals lift rod assembly cMsists of three 3-3/4 inch ~ diameter stainless steel rods, 14 feet long,-

-extending from the upper internals flange through a 2

. penetration on the reactor vessel head.

The rods are i

, permanently bolted to the upper interna's flange and bolted..

with a removable nut to the vessel head penetration. When L

the plant is not-in.a " rapid refueling" mode, these rods

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are disconnected from the head.

2.<

Reactor. Vessel Internals Lift Rig-The internals lift rig (Figure B-3) is a three-leggeo carbon and t

= stainless steel structure, approximately 30 feet high and 14 feet in diameter weighing approximately-21,000 pounds.

It is used to handle the upper and lower reactor vessel internals g

packages.

It is attached to the main crane hook for all

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lifting, lowering, and traversing operations. A load cell linkage is connected between the main crane hook and the rig to fmonitor loads during all operations.

I The internals lift rig is attached to the internals package by means.of three rotolock studs which engage three rotolock l

inserts located in'the internals flange.

These rotolock studs are manually. operated from the internals lift rig platform using l

c handling tool which is an integral part of the rig.

The studs L

are normally spring retracted upward and are depressed to engage

.the inserts. Rotating the mechanism locks it in both positions.

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Load Cell And Load Cell Linkage The load cell is used to monitor the load during lifting and lowering-to ensure no excessive loadings occur.

The un<t is a load sensing clevin type, rated at 700,000 pounds.

This load cell is a part of the' load cell linkage which is an 4

assembly of pins, plates,'and bolts that connect the polar crane main hook to the lifting blocks of both the reactor vessel head and the internal lift rigs.

4.

. Reactor Coolant Pump Lifting Device A special' lifting device for the reactor coolant pump motor is

.being purchased from Westinghouse.

It will consist of a spreader assembly to provide equal lift at four points.

The specific design for STP is still pending. 2348N/0151N

r i-Sunnary of Results The reactor vessel head lift rig assembly, internals lift rig, load cell and

-load' cell linkage generally meet the intent of the ANSI N14.6-1978 requirements for design and manufacture.

The assembly and detailed manufacturing drawings and purchase order _ documents contain requirements equivalent to design specifications..The multi-functional items of the head lift rig assembly (a Class 1 support) have a design specification. Some

-exceptions are taken to the ANSI N14.6 requirements for acceptance testing, maintenance, and verification of continuing compliance.

The reactor coolant pump'special lift device will.be built to ANSI N14.6 requirements.

A st ess report has been prepared for these devices, excluding the RCP lifting' device,.and a summary of the applicable results is included in Attachment B.

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

These devices were manufactured under Westinghouse (and in some instances, ASME Code) surveillance with identified hold points, procedure review, and personnel qualification which meet the related ANSI requirements. A 125 percent load test was performed on the head lift rig assembly, the upper internals lift rods, the internals lift rig, load cell and load cell linkage.

The load test was performed at a fabricators shop and was followed by the appropriate non-destructive testing.

Exceptions to ANSI N14.6 and the justification of-present design acceptability

.are presented in Table 3.

Slings may be used throughout the plant to lift equipment. All slings will be procured to the requirements of ANSI B30.9-1971 as modified by NUREG 0612.

The rating identified on the sling will be in terms of the " static load" which produces the maximum static and dynamic loads. Where this restricts sling-use to certain. cranes, the slings will be clearly marked as.to the cranes with which they may be used.

Item 2.1.3.e Verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect

'to crane inspection, testing, and maintenance. Where any exception is taken to this standard. sufficient information should be provided to demonstrate the equi _ valency of the proposed alternative.

STP Response A procedure has been approved which covers the inspection and testing of all plant cranes. This procedure is based on the requirements of ANSI B30.2-1976, Chapter 2-2, ANSI N45.2.2-1972, OSHA 2206 (29CFR1910), and the Manufacturers Instruction Manuals.

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-All preventative and corrective maintenance will be performed using procedures

.which invoke ANSI B30.2-1976, Chapter 2-2.

Item 2.1.3.f

. Verification that crane design complies with the guidelines of CMAA

. Specification 70 and Chapter 2.1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design requirements for instances where specific compliance with these standards is not provided.

STP Response The design of the Polar Cranes, the FHB 15/2 overhead cranes and the ECW

-gantry crancs comply with the guidelines of CMAA-70 and Chapter 2.1 of ANSI B30.2-1976.

The criteria in CMAA-70 is not directly applicable to the DGB crane because it

-is a top running single girder overhead crane.

The design of this system was compared to the guidelines of CMAA-74 " Specification for Top Running and Under Running Single Grider Electric Overhead Traveling Cranes." The crane meets the requirements of CMAA-74 and Chapter 2.1 of ANSI B30.2-1976.

Because the criteria in CMAA-70 and ANSI B30.2 are not directly applicable to monorails and their hoists, the design of these handling systems was compared to the guidelines of ANSI B30.11-1973 " Monorail Systems and Underhung Cranes" and ANSI B30.16-1973 " Overhead Hoists". All of the monorails identified in Table I were designed to meet these guidelines.

Item 2.1.3.g Exceptions, if any, taken to ANSI B30.2-1976 with respect to operator training.. qualification, and conduct.

STP Response HL&P takes no exceptions to ANSI B30.2-1976, Chapter 2-3, " Qualifications for Operators." 2348N/0151N

R SPECIFIC REQUIREMENTS FOR OVERHEAD HANDLING SYSTEMS OPERATING IN THE VICINITY OF FUEL STORAGE P0OLS, SECTION 2.2 0F GENERIC LETTER 81-07 NRC STATEMENT' NUREG 0612, Section 5.1.2, provides guidelines concerning the design and operation of-load-handling systems in the vicinity of stored spent fuel. Per the guidelines, information provided in response to this section should-demonstrate that adequate measures have been taken to ensure that in this area, either the likelihood of a_ load drop which might damage spent fuel is extremely small, or the estimated consequences of such a drop will not exceed the limits set by the _ evaluation criteria of NUREG 0612, Section 5.1, Criteria I through III.

-ITEM N0. 2.2.1 Identify by name, type, capacity, and equipment designator, any cranes physically capable (i.e., ignoring interlocks, moveable mechanical stops, or operating procedures) of carrying loads which could, if dropped, land or fall into the spent fuel pool.-

STP Response The Fuel Handling Building Overhead Crane and the Containment Polar Crane are the only cranes capaile (ignoring interlocks, movable mechanical stops, or operating proceduresi of carrying heavy loads which could, if dropped, land or fall into a spent 6 el pool.

The type, capacity, and equipment designator are identified in Table 1.

The Polar Crane is considered in this section because the STP design includes an in-containment fuel pool for temporary fuel holding capability during refueling.

ITEM NO. 2.2.2 Justify the exclusion of any cranes in this area from the above category by verifying that they are' incapable of carrying heavy loads or are permanently prevented from movement of the hook centerline closer than 15 feet to the pool boundary, or by providing a suitable analysis demonstrating that for any failure mode, no heavy load can fall into the fuel-storage pool.

STP Response The Cask Handling Crane and the New Fuel Area bridge Crane were excluded from the response to Item 2.2.1 because they are incapable of carrying heavy loads within 15 feet of the FHB pool boundary. The new fuel area crane is located at a level below the spent fuel pool.

The rail for the Cask Handling Crane stops at the edge of the cask loading pool, more than 25 feet from the pool i 2348N/0151N

o boundary. Th2 fuel handling machina and refu211ng machina were excludtd because they ds n:t carry h:avy lords. There are s:v ral monorails located in

the FHB and in the Containment. However, these monorails are located at levels below the spent fuel pools and are not considered in Item 2.2.1.

ITEM NO. 2.2.3 Identify any cranes listed in 2.2.1, which you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis'for this evaluation (i.e.,

complete compliance with NUREG 0612, Section 5.1.6 or partial compliance supplemented by suitable alternative or additional design features). For each U

crane so evaluated, provide the load-handling-system (i.e.,

crane-load-combination) information specified in Attachment 1 of GL 81-07.

STP Response The FHB overhead crane design makes the likelihood of a load drop extremely small for all loads based on the fact that it is designed to meet the intent of RG 1.104. The information requested in Attachment 1 of the generic letter is provided in Attachment D of this report.

Curing refueling it may be necessary to move the containment fuel pool gate and/or the Reactor Vessel Internals Lift Rig over the in-containment fuel pool while it contains fuel.

If this need arises, the polar crane main noist will be used (capacity 417 tons for Unit 1, 500 tons for Unit 2). As the two loads in question are 8,520 lbs. and 21,000 lbs., greater than a 10/1 safety factor is maintained. Additionally, the interfacing lift points on these two loads exceed the 10/1 safety factor criteria.

ITEM NO. 2.2.4 For cranes identified in 2.2.1, not categorized according to 2.2.3, demonstrate that the Criteria of NUREG 0612 Section 5.1, are satisfied.

Compliance with Criterion IV will be demonstrated in response to Section 2.4 of GL 81-07. With respect to Criteria I through III, provide a discussion of your evaluation of crane operation in the spent fuel area and your determination of compliance.

STP Response L

For Polar Crane loads not categorized in 2.2.3 administrative controls will prevent movement while spent fuel is stored in the containment fuel pool with the following exception.

l At inservice inspection intervals requiring removal of the lower internals from the vessel (or.ce every 10 years), the internals are moved to the adjacent lower internals storage stand.

It is not reasonable to postulate the movement j

of this load over the fuel pool.

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SPECIFIC REQUIREMENTS OF OVERHEAD HANDLING SYSTEMS OPERATING IN THE CONTAINMENT, SECTION 2.3 of GENERIC LETTER 81-07 NRC STATEMENT NUREG 0612, Section 5.1.3, provides guidelines concerning the design and operation of load-handling systems in the vicinity of the reactor core.

Information provided in response to this section should be sufficient to demonstrate that adequate measures have been taken to ensure that in this area, either the likelihood of a load drop which might damage spent fuel is

-cxtremely small, or that the estimated consequences of such a drop will not exceed the limits set by the evalution criteria of NUREG 0612, Section 5.1, Criteria I through III.

ITEM N0. 2.3.1 Identify by name, type, capacity, and equipment designator, any cranes physically capable (i.e., taking no credit for any interlocks or operating procedures) of carrying heavy loads over the reactor vessel.

STP Response The Polar Crane is the only crane physically capable (i.e. taking no credit for any interlocks or operating procedures) of carrying heavy loads over the reactor vessel.

Its type, capacity and designator are identified in Table 1.

ITEM NO. 2.3.2 Justify the exclusion of any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads, or are permanently prevented from the movement of any load either directly over the reactor vessel or to such a location where in the event of any load-handling-system failure, the load may land in or on the reactor vessel.

STP Response There are no cranes physically capable of passing over the vessel area which were excluded from Section 2.3.1.

ITEM NO. 2.3.3 Identify any cranes listed in 2.3.1, above, which you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e, complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features).

For each crane so evaluated, provide the load-handling-system (i.e, crane-load-

-combination) information specified in Attachment 1 of GL 81-07.

STP Response There are no single-failure-proof cranes in the Reactor Containment Building. 2348N/0151N

d 3

g

~

ITEM NO.:2.3.'4 I

t Mtc STATEMENT For cranes ' identified 'in"2.3.1, :above, not categorized according to 2.3.3, demonstrate that the evaluation criteria:of NUREG 0612. Section 5.1, are l

3 satisfied.

Compliance with Criterion IV will be demonstrated in your response to'Section 2.4 of GL 81-07 With respect to Criteria I through III, provide a E

Ediscussion of your evaluation of crane operation in the containment and your

' determination.of compliance. This response should include the following

^

.information for each crane.-

Y ITEM NO. 2.3.4.a

-Where relisnce is placed on the. installation and use of electrical interlocks ~

c r

'~

or mechanical-stops, indicate circumstances under which these protective Jdevices can be removed or bypassed and.the administrative procedures invoked l

to ensure proper authorization of such action. Discuss any related or L

. proposed technical-specification concerning the bypassing of such interlocks.

l i

STP Response To prevent loads from being carried over the reactor vessel, the polar crane will be equipped with an interlock to prevent the trolley from moving within a

~

1

.given radius'of the reactor vessel (the~ zone of the interlock is shown in figure 38)ithout the head in' place on the vessel) are the upper and lower

. -Heavy 11oads that are required to pass within the interlock zone (with or w

. internals, the in-service inspection rig, the integrated head package, the stud carrier rack containing twelve studs, nuts, and washers, the stud

~

t

[

Ltensioners,-and the Internals Lift Rig.

jThe-polar crane.is used only during shutdown and refueling. Once the~

Lintegrated head package is removed, the only loads required to be carried "through theJinterlock while fuel is in the vessel are the internals lift rig' Lwhich is required to change the 0-rings and the' upper internals if they are removed separately from the IHP.

The interlocks are active at all times unless bypassed by key.

The bypass

will be in effect as'long as the key is inserted. The key cannot be removed

'without reactivating the. interlock.

.Anlintegratedhead-package (IHP)dropanalysiswhichisapplicabletoSTPwas

. erformed by Westinghouse and submitted to the NRC by Westinghouse letter p

LNS-CE-1101 dated June 11, 1976 on the RESSAR-41 docket. This analysis

~ determined that uropping the head would not result in an unacceptable degree

of core damage.

It received NRC approval on~ November 30, 1976.

The internals lift rig is shown on figure.B-3.

It is 14 feet in diameter and k

30 feet high. Because of its size and shape it is impossible for it to hit the fuel. The effects of a drop of this rig onto the vessel are enveloped by the Westinghouse Head Drop Analysis since the rig is much lighter than the IHP.

l r 2348N/0151N-

m e

y

The effects of a drop of the upper internals are also enveloped by the

_ estinghouse Head Drop Analysis.

W

The lower' internals and inservice inspection rig are moved only when all the

- fuel has been removed from the vessel.

The key to the vessel interlock _will be under the control of the refueling

~

director. The interlock will be bypassed to remove the IHP. Once the IHP.is

_ removed from the' vessel and clears the area above the vessel, the' interlock uill be restored. During rapid refueling, bypass will only be permitted for

~

replacement of the 0-rings.

During nonrapid refueling bypass will be permitted to remove the. internals as well. The interlock will be bypassed to replace the IHP.

Administrative & Testing Requirements The k'y for bypassing the vessel interlock of the polar crane will be e

, controlled by the refueling director and released only upon proper authorization.

Procedures will also control the use and bypass of the interlock; additional technical specifications are not' warranted.

The interlock boundaries will be tested before the interlocks are bypassed and following replacement of the IHP.

The tests will be run without load on the crane hook.

ITEM (10. 2.3.4.b

. Where reliance is placed on other, site-specific considerations (e.g.,

refueling sequencing), provide'present or proposed technical specifications and discuss administrative or physical controls provided to ensure the continued validity of such considerations.

STP Response r

y For the Polar. Crane, reliance is placed on other site specific considerations E

- cnly for the movement of the lower internals and the inservice inspection rig. Movement of these loads is performed once every 10 years and will only occur after all'the fuel has been removed from the vesspl.

Consequently bypassing the interlock at this time poses no hazard to the fuel.

Movement of' loads over the in-containment fuel pool is discussed in response to item 2.2.4.

Since the lower internals are never removed and the. inservice inspection rig l

is never used while fuel is in the vessel, no additional adninistrative,

' physical controls, or technical specifications over those described in section

'2.3.4.a are required for these items.

i 2348N/0151N

ITEM N0. 2.3.4.c Analyses performed to demonstrate compliance with Criteria I through III should conform with the guidelines of NUREG 0612, Appendix A.

Justify any exception taken to these guidelines, and provide the specific information requested in Attachment 2, 3 or 4 of GL 81-07, as appropriate, for each analysis performed..

STP Response The Polar Crane meets Criteria I to III.

The Westinghouse head drop analysis covers compliance for all large loads less than 636,000 lbs.

, 2348N/0151N

SPECIFIC REQUIREMENTS FOR OVERHEAD HANDLING SYSTEMS OPERATING IN PLANT AREAS CONTAINING EQUIPMENT REQUIRED FOR REACTOR SHUTDOWN, CORE DECAY HEAT REMOVAL, OR SPENT FUEL P00L COOLING, SECTION 2.4 0F GENERIC LETTER 81-07.

NRC STATEMENT NUREG 0612, Section 5.1.5, provides guidelines concerning the design and operation of load-handling systems in the vicinity of equipment or components required for safe reactor shutdown and riecay heat removal.

Information provided in response to this section should be sufficient to demonstrate that adequate measures have been taken to ensure that in these areas, either the likelihood of a load drop which might prevent safe reactor shutdown or prohibit continued decay heat removal is extremely small or that damage to such equipment from load drops will be limited in order not to result in the loss of +hese safety-related functions.

ITEM NO. 2.4.1 Identify any cranes listed in 2.1.1, above, which you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e, complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features).

For each crane so evaluated, provide the load-handling system (i.e., crane-load-combination) information specified in Attachment 1 of GL 81-07.

STP Response There are no single-failure-proof cranes capable of passing over equipment required for safe shutdown, core decay heat removal or spent fuel pool cooling.

ITEM NO. 2.4.2 NRC Statement For any cranes identified in 2.1.1 not designated as single-failure-proof in 2.4.1, a comprehensive hazard evaluation should be provided which includes the following information.

ITEM N0. 2.4.2.a The presentation in a matrix format of all heavy loads and potential impact areas where damage might occur to safety-related equipment.

Heavy load identification should include designation and weight or cross-reference to information provided in 2.1.3.c.

Impact areas should be identified by construction zones and elevations or by some other method such that the impact area can be located on the plant general arrangement drawings. 2348N/0151N

4-STP Response

' Table l' presents the crane, crane type, crane capacity in tons, loads, load

weight -lifting device, potential targets and target locations.

Note that the targets identified are specific to a crane or monorail and are

-not specific to a particular load.

ITEM NO.'2.4.2.b For each interaction. identified, indicate which of the load and impact area combinations can be eliminated because of separation and redundancy of safety-related equipment, mechanical stops and/or electrical interlocks, or

.Gther site-specific considerations. Elimination on the basis of the aforementioned considerations should be' supplemented by the following specific information:

. (1)- For load target combinations eliminated because of separation and redundancy of safety-related equipment, discuss the basis for determining that load drops will not affect continued system

-operation (i.e. the ability of the system to perform its safety-related function).

(2) Where mechanical stops or electrical interlocks are to be vided, present details showing the areas where crane travel 1 be prohibited. Additionally, provide a discussion concerning the procedures that are to be used for authorizing the bypassing of interlocks or removable stops, for verifying that interlocks are functional prior to crane use, and for-verifying that interlocks.are restored to operability after

-operations which require bypassing have been completed.

- (3). Where load / target combinations are eliminated on the basis of other, site-specific considerations (e.g., maintenance sequencing), provide present and/or proposed technical specifications and discuss administrative procedures or physical constraints invoked to ensure the continued validity of such considerations.

.STP Response Table 1 includes categories for elimination as follows:

SR - separation and redundancy IL - interlocks SS - site specific AN - analysis SF - single-failure proof crane NA - not required for safe shutdown, decay heat removal, or spent fuel cooling 2348N/0151N

e r

STP has been designed to ensure that redundant safety-related trains are provided with adequate separation and protection to ensure their continued function following a wide variety of events and conditions. This report also considered the consequences of floor failures where there is an intervening floor (s) between the load and the target.

Justification for the elimination of load / target combinations are provided be.l ow.

A.

Containment Building Containment will not be entered to perfor.n heavy maintenance or for refueling operations until safe shutdown is achieved.

The following targets will not be needed for core decay heat removal.

Mafi. Steam Piping Reactor Coolant Pamps Steam benerators HVAC Ducting Cable Tray Pressurizer Hydrogen Recombiner The RHR system is the only operating system directly required for the maintenance of cold shutdown.

1.

Polar Crane Loads /RHR System Three trains of RHR are provided, only one of which is required for decay heat removal.

If a load must be moved over an RHR train when both redundant trains are not available (i.e., other train (s) are inoperable, or a load drop could impact all operable trains), the polar crane main hoist will be used in conjunction with adequate interfacing lift points to ensure that greate. than a 10/1 safety factor is provided.

Administrative procedures will provide cperational restraints to prevent movement of, or potential for damage to,componentsinanotherplantarea(CCWpumps.ECWpumps.

SI Piping in Containment El. - 2') associated with the operating RHR system (s); no additional technical specifications are warranted.

2.

RCFCFan/SIPiping(toRHRSystemTrainAHeatExchanger)

Administrative procedures will state that in the event the RHR system associated with this piping is the only operating RHR system, a move over this component will not be permitted; no additional technical specifications are warranted.

2348N/0151N.

F 3.

RII Pumps, Pump Motors /RHR Piping, Pumps and Heat Exchangers

'These combinations (monorail lifts) can be eliminated because of redundancy, separation and operational

-restrictions as stated above.

B. ' Mechanica! Electrical Auxiliary Building 1.

CCW Pumps, Pump Motors, Supplementary Coolers /CCW Piping and Pumps-These load / target combinations can be eliminated because of

-redundancy-and separation..Three trains are provided (each uses a separate monorail and is'in a separate room).

Two are needed for achieving shutdown and only one for decay heat removal.

Administrative procedures will address operational restrictions as described in 2.4.2.b - A-1; no additional technical specifications are warranted.

-2..

Charging Pump Components, Supplementary Coolers / Charging Pump Piping and Pumps These interactions can be eliminated by redundancy and separation.

Two pumps, in separate rooms using separate monorails, are provided. Only one is required.

3..

Hatch Covers / Letdown Filters, Seal Water. Injection Filter, Seal Water Return Filters, Reactor Coolant Filters These targets are not essential for safe shutdown or decay heat removal.

4.-

Hatch Covers / Boric Acid Tanks

'Two Boric Acid tanks-are provided.

Safe shutdown can be achieved with one.

The tanks-are separated such that no load drop could impact both tanks.

5.

Hatch Covers /CVC Cation Bed Demineralizers and CVC Mixed Bed Demineralizers

-These targets areinot essential for safe shutdown or decay heat removal.

^

LC.; -Fuel Handling Building

' Safety Injection (SI) System Components, Containment Spray

-System. Components / Safety Injection Pumps,-Containment Spray Pumps i.2348N/0151N

/,

t

A r,

c rThese~ combinations are eliminated because of-redundancy and

! separation. Each set of pumps (l'High Head SI, 1 Low Head SI, I

. Containment Spray) uses a separate monorail and is sufficiently separated from the other sets._ Additionally, administrative procedures will. state that'a set will'be isolated before a lift of any of its components is attempted during operation.

The administrative controls identified will be implemented by

' plant procedure; no additional technical specifications are 2:

. arranted.

w D.' -

Diesel Generator Building

The load / target combinations in the Diesel Generator Building 4

-are' eliminated because'of. separation and redundancy.- Each of the three separate rooms'has its own crane and a load drop on one-generator cannot. impact the others.

7, E.

Essential Cooling Water Intake The load / target combinations _at the ECW Intake are eliminated r

"because..of separation and redundancy. Additionally,

~

F administrative procedures will state operational restrictions as

' described in 2.4.2.b-A-1; no additional technical specifications are warranted.

ITEM 2.4.2.c

For. interactions:not eliminated by the analysis of 2.4.2.b,-above, identify any handling systems for_ specific loads which you have evaluated as having Lr'

' sufficient. design' features to'make the likelihood of a load drop extremely small and the basis for this evaluation (i.e., complete compliance with NUREG

~

-0612, Section 5.1.6, or partial compliance-supplemented by suitable Ealternative.or additional design features).. For each crane so evaluated, provide the; load-handling l system (i.e,' crane-load combination) information specified in~ Attachment 1 of GL 81-07.

~ 1STP Response All: interactions have been discussed in 2.4.2.b..

ITEM NO.'2.4.2.d For--interactions not' eliminated in 2.4.2.b or 2.4.2.c, above, demonstrate using' appropriate analysis that damage would not preclude operation of tsufficient equipment to allow the system to perform its safety function i following a~ load drop. (NUREG 0612,:Section 5.1, Criterion IV). For each analysis so conducted..the following information should be provided.

. (1) An indication of whether or not,.for the specific load being investigated, the overhead crane-handling system is designed and constructed such that the hoisting system will retain its load L

.in the event of seismic accelerations equivalent to those of a

^

safe shutdown earthquake (SSE).

[ 2348N/0151N ~

f.

-s:

~ -.,,

- - +,, -..

.--....,.,.~_.___,-_.m.-._,,--.m_,,

m.. -,----. -

m,-

s

' (2) ;The basis for_any exceptions.taken to the analytical guidelines of NUREG 0612, Appendix A.

(3).1he Information requested in Attachment 4.

STP Response

~

All_ interactions have been discussed in 2.4.2.b.

w i

+

h 9

['

J 21-2348N/0151N

I REFERENCES 1.

George, H., Control of Heavy Loads of Nuclear Power Plants Resolution of Generic Technical Activity A-36, NUREG 0612, July,1980.

2.

WCAP - 10215 " Evaluation of the Acceptability of the Reactor Vessel Head Lift Rig Assembly, Reactor Vessel Internals Lift Rig, load Cell and Load Cell Linkage to the Requirements of NUREG 0612 for Houston Lighting and Power Company, South Texas Proiect Electric Generating Station".

3.

NS-CE-1101 dated June 11, 1976, " Consequences of Dropping the Upper

[

Package During A Refueling."

=

,=

m 2348N/0151N

TABLE 1 CRANES IDENTIFIED fN ITEM 2.1

(,KANt/ l Ali NU.

GANE/ LOAD G ANE/ TARGET (CAPACITY IN TONS)

INFORMATION INFORMATION 5pec i al Target tiimination l

Load (s)

Weight Lifting Targets Elevation ft/

Category (Ibs.)

Device (Note 2)

Location (Note 1)

Reactor Reactor Vessel Internals 21,000 Load Cell Mainsteam Piping 68/

NA Containment Lift Rig Link age Figure 16, Building (RCB) 18, 19 Polar Crane Unit 1 7C10lNCP101A (417/15)

Lower Internals

,131,000 Internals RC Pump 52/

SS, NA Lift Rig Figure 16 RC8 Load Cell Linkage 3,000 None Vessel 68/

SS, IL Polar Crane Figures 16, th i t 2 18 7Cl02NCP201A (500/15)

Containment Fuel Pool 8,520 None Steam 102/

NA Gate Generators Figures 16, 18, 19 Reactor Coolant Pump 16,500 RCP Lift HVAC Ducting 120/

NA Flywheel Device Figures 16, 18, 19 Reactor Coolant Pump 97,600 RCP Lift Cable Trays 68/

NA Motor Device Figure 16 Reactor Coolant Pump 36,800 RCP Lift Pressurizer 101/

NA Rotor Device Figures 16, 19 Inservice Inspection Rig 3,600 None Hydrogen Recombiner 68/

NA l

Figure 16 RHR Pump 6,900 None RHR Piping, Conduit

-?/

SR, SS Figure 17 7860N/0202N TABLE 1 (Cont'd.)

CRANES IDENTIFIED IN ITEM 2.1 LRANE/ TAG NO.

CRANE / LOAD CRANE / TARGET (CAPACITY IN TONS)

INFORt% TION INFORMATION Special Target tiimination Load (s)

Weight Lifting Targets Elevation ft/

Category (lbs.)

Device (Note 2) location (Note 1)

PCB RHR Pump Motor 5,700 None Polar Cranes (Continued)

' RHR Heat Exchanger 29,000 None RHR Heat Exchanger 14,000 None Tube Bundle Integrated Head 612,000 Head Lift Package (includes Rig the following items to be lifted together during rapid refueling) a.

Head Lift Rig 8,800 b.

Missile Shield 30,000 c.

Cooling Shroud 30,000 d.

Cables on Shroud 5,000 e.

Cooling Fans and 2,400 f.

Vessel Head Plus 230,000 Water g.

Cable Tray 7,50 0

'in60N/0702N

., ' :l

.?-{-l. } _ :. ~.'.)& '.] g.:['.l.;, } ' W } }. y'- Q g ';.~ Q.l.. h _;.%.Q f.? % p }:.;;[';[#. ::q 6. y.> l;.;..

. 3 ~.

N...

',0

.. uf t.

4 9

%. {'

a TABLE 1 (Cont'd.)

i.

^"

CRANES IDENTIFIED IN ITEM 2.1

[

c

. ?

4..

i

[

CRANE / TAG NO.

CRANE / LOAD CRANE / TARGET f

(CAPACITY IN TONS)

INFORMATION INFORMATION

.l Special Target Elimination Load (s)

Weight Lifting Targets Elevation ft/

Category

,1 (lbs.)

. Device (Note 2) location (Note 1)

.3 4.-(

FHB H.H. Safety Injection 7,155 None HH SI Pump

-19/

SR 4-Monorail Pump Figures 29, 9F10lNCM104E 33, 34 34 9F102NCM204E

.R (5)

H.H. Safety Injection 5,820 None t.'.

Pump Motor H.H. Safety Injection 3,924 None Pump - Outer Barrel t.c A

tHB Containment Spray 7,155 None Containment

-19/

SR

/.-

Monorail Pump Spray Pump Figures 29, 4

9F10lNCM104F 33, 34 6.;

9F102NCM204F B)

Containment Spray 5,820 None Pump Motor Containment Spray 3,924

.None

{

Pump - Outer Barrel s,.

Y FHB L.H. Safety Injection 7,155 None LH Safety Injection

-19/

SR Monorail Pump Pump Figures 29, 9F10lNCM104G 33, 34

~: :

9F102NCM204G (S)

L.H. Safety Injection 5,820 None Pump Motor e

M L.H. Safety Injection 3,924 None Pump - Outer Barrel

._ e.

.,r

?.

PR60N/0202N s i.> :

m $..-..

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? '".; jN !?ig :;.gg; f w 4.y0Tf;.'. c';. [u :.6':g ', % & p. j.

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-t ipp g "

.., ' ' ~. ~, ( 5. "

a n.,.: y + y y ::n};;$.dY fl

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. x e s;s a;4 ; 2. o,.%. Q,.g.:: n:

.,. ;. p. :p: W.:

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y e. M m:r.: =. 3

yy yy

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+.

u. 7. c.., :.a:.. y j "

. x.. a.

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w.

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~

TRBLE 1 (Cont'd.)

CRANES IDENTIFIED IN ITEM 2.1 LKANt/ LAG NU.

CRANE / LOAD CRANE / TARGET (CAPACITY IN TONS)

INFORMATION INFORMATION Special larget Elimination Load (s)

Height Lifting Targets Elevation ft/

Category (lbs.)

. Device (Note 2) location (Note 1)

FHB H.H. Safety Injection 7,155 None HH SI Pump

-19/

SR Monorail Pump Figures 29, 9F10lNCM104H 33, 34 9F102NCM204H (5)

H.H. Safety Injection 5,820 None Pump Motor H.H. Safety Injection 3,924 None Pump - Outer Barrel THB Containment Spray 7.155 None Containment

-19/

SR Monorail Pump Spray Pump Figures 29, 9F10lNCM104I 33, 34 9F102NCM204I (5)

Containment Spray 5,820 None Pump Motor Containment Spray 3,924 None Punp - Outer Barrel 9n60'!/0702N.... - r- - - _ _.,,. _ _ - - - - - -

TABLE 1 (Cont'd.)

CRANES IDENTIFIED IN ITEM 2.1 LHANL/ LAG NO.

CRANE / LOAD CRANE / TARGET (CAPACITY IN TONS)

INFORMATION INFORMATION Speci al Target Elimination Load (s)

Weight Lifting Targets Elevation ft/

Category (lbs.)

. Device (Note 2) location-(Note 1)

Essential Cooling ECW Pump 26,300 None ECW Piping 34/

SR Water (ECW) and Motor Figure 36 Intake Gantry 7P200NCG001C (20)

Traveling 19,700 None ECW Pumps 34/

SR Screen Figure 36 Strainers (Wet) 19,467 None ECW Screens 34/

SR Figure 36 Stop Log 5,300 None Strainers 31.5/

SR Figure 36 Hatch to Screens 38,250 None Hatch to Pumps 24,500 Noite Hatch to Strainers 25,500 None

?k60N/0?02N.

TABLE 1 (Cont'd.)

CRANES IDENTIFIED IN ITEM 2.1 u(ANL/I AG NO.

CRANE / LOAD CRANE / TARGET (CAPACITY IN TONS)

INFORMATION INFORMATION Special Iarget EIimination Load (s)

Weight Lifting Targets Elevation ft/

Category (lbs.)

. Device (Note 2) location (Note 1)

Diesel Generator Starting Air Tank 2,710 None Diesel Generators 29/

SR Figure 37 Building (DGB)

Overhead Crane 8010lNCB101A 80102NCB201A Flywheel 4,450 None (3)

Bearing & Stand 2,300 None Air Filter 5,400 None DGB Starting Air Tank 2,710 None Diesel Generators 29/

SR Figure 37 OverM ad Crane 8DlGINCB101B 8D102NCB2018 Flywheel 4,540 None (3)

Bearing & Sta.d 2,300 None Air Filter 5,400 None ?R60N/070?N

.r

l

- n l g-g -

TABLE 1 (Cont'd.)

CRANES IDENTIFIED IN ITEM 2.1 CRANE /IAG NO.

CRANE / LOAD CRANE / TARGET (CAPACITY IN TONS)

INFORMATION INFORMATION Speci al Target tiimination Loaa(s)

Weight Lifting Targets Elevation ft/

Category (lbs.)

. Device (Note 2) location

_[ Note 1)

DGB Starting Air Tank 2,710 None Diesel Generators 29/

SR Figure 37 Overhead Crane 8010lNCB101C 8D102NCB201C Flywheel 4,540 None (3)

Bearing & Stand 2;300 None Air Filter 5,400 None Notes In the elimination category column the following abbreviations are used to indicate the method of elimination.

1.

SR = separation and redundancy IL = interlocks SS = site specific AN = analysis SF = single-failure-proof crane NA = not required for safe shutdown, decay heat renoval or spent fuel cooling The targets and elimination categories identified are applicable to all loads handled by the crane.

2.

=c n.pqonon 1 I

I 1141 1

M I

I I

II I I

I I

I fl mmWm

TABLE 2 OVERHEAD HANDLING SYSTEMS EXCLUDED FROM ITEM 2.1.1 General Capacity Reason for Arrangement Crane Tag No.

(Tons)

Exclusion

Drawing No.

Reactor Containment Building Monorail 9C101NCM101A 3

0 6-18-9-N-5002 9C102NCM201A Monorail 9C10lNCM103A 3

0 6C-18-9-N-5002 9C102NCM203A Monorail 9C10lNCM1048 4

A 6C-18-9-N-5002 9C102NCM2048 Monorail 9C10lNCM105A.

3 D

6C-18-9-N-5002 9C102NCM205A Monorail 9C101NCM106A 3

0 6C-18-9-N-5002 9C102NCM206A Monorail 9C10lNCM1078 4

A 6C-18-9-N-5002 9C102NCM207B Monorail 9C101NCM107C 4

A 6C-18-9-N-5002 9C10L:'CM207C Refueling 3R231NCB101A 1 1/2 A, C 6C-18-9-N-5007 Machine 3R232NCB201A IVC Monorail 9110lNCM109A 4

A 6G-01-9-M-0025 9I101NCM209A Mechanical and Electrical Auxiliary Building Monorail 9M10lNCM109A 2

A 6M-18-9-N-5017 9M102NCM209A Monorail 9M10lNCM110A 1 1/2 A

6M-18-9-N-5017 9M102NCM210A Monorail 9M10lNCM110A 1 1/2 A

6M-18-9-N-5017 9M102NCM210A Monorail 9M10lNCMlllA 1 1/2 A

6M-18-9-N-5017 9M102NCM211A Monorail 9M10lNCMillB 1 1/2 A

6M-18-9-N-5017 9M102NCM211B 2362N/0151N

n TABLE 2 (Cont'd.)

OVERHEAD HANDLING SYSTEMS EXCLUDED FROM ITEM 2.1.1 General Capacity Reason for Arrangement Crane Tag No.

(Tons)

Exclusion

Drawing No.

Mechanical and Electrical Auxiliary Building (continued)

Monorail 9M10lNCMlllC 1 1/2 A

6M-18-9-N-5017 9M102NCM211C Moncrail 9M10lNCMll10 1 1/2 A

6M-18-9-N-5017 9M102NCM2110 Monorail 9M10lNCM113A 2

A 6M-18-9-N-5017 9M102NCM213A Monorail 9M101NCM129A 2

A 6M-18-9-N-5020 9M102NCM229A Monorail 9M10lNCM131A 3

A 6M-18-9-N-5022 9M102NCM231A Monorail 9M10lNCM132A 3

A 6M-18-9-N-5022 9M102NCM232A Monorali 9M10lNCM139A 1 1/2 A

6M-18-9-N-5025 9M102NCM239A Monorail 9M10lNCM140A 3

A 6M-18-9-N-5025 9M102NCM240A Monorail 9M10lNCM143A 3

A 6M-18-9-N-5025 9M102NCM243A Monorail 9M10lNCM144A 3

A 6M-18-9-N-5026 9M102NCM244A Monorail 9M10lNCM145A 3

A 6M-18-9-N-5026 9M102NCM245A Monorail 9M10lNCM146A 3

A GM-18-9-N-5026 9M102NCM246A Monorail 9M101NCM147A 3

A 6M-18-9-N-5026 9M102NCM247A Monorail 9M10lNCM148A 3

A 6M-18-9-N-5026 9M102NCM248A Monorail 9M10lNCM149A 3

A 6M-18-9-N-5026 9M102NCM249A 2362N/0151N

6 TABLE 2 (Cont'd.)

OVERHEAD HANDLING SYSTEMS EXCLUDED FROM ITEM 2.1.1 General Capacity Reason fc-Arrangement

?

Crane Tag No.

(Tons)

Exclusion

Drawing No.

~

Mechanical and Electrical Auxiliary Building (continued)

I Monorail 9M10lNCM1498 3

A 6M-18-9-N-5026 j

9M102NCM249B Monorail 9M10lNCM150A 3

A 6M-18-9-N-5026 1

9M102NCM250A

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9M102NCM251?.

/

Monorai1 9M101NCM152A 3

A 6M 18-9-N-5026 9M102NCM252A Monorail 9M101NCM154A 7.5 A

6M-18-9-N-5029 9M102NCM254A

]

Monorail 9M101NCM154B 7.5 A

6M-18-9-N-5029 b

9M102NCM254B Monorai1 9M101NCM154C 7.5 A

6M-18-9-N-5030 9M102NCM254C Monorail 9M101NCM1540 7.5 A

6M-18-9-N-5030 9M102NCM2540 s

Monorail 9M10lNCM154E 7.5 A

6M-18-9-N-5030 9M102NCM254E Monorail 9M10lNCM155A 5

A 6M-18-9-N-5029 9M102NCM255A

-i Monorail 9M101NCM157A 5

A 6M-18-9-N-5030 9M102NCM257A Monorai1 9M101NCM158A 6

A 6M-18-9-N-5030 1-9M102NCM258A I:

Monorai1 9M101NCM159A 3

A 6M-18-9-N-5030

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A 6M-18-9-N-5030 9M102NCM260C Monorail 9M10lNCM161A 5

A 6M-18-9-N-5032

)

9M102NCM261 A

= 2 2362N/0151N

TABLE 2 (Cont'd.)

0VERHEAD HANDLING SYSTEMS EXCLUDED

" 2.1.1 General Capacity Reason fc.

Arrangement Cry Tag No.

(Tons)

Exclusion

awing No.

Mechanical and Electrical Auxiliary Building (continued)

Monorail 9M10lNCM163A 3

A 6M-18-9-N-60159 9M102NCM263A Monorail 9M10lNCM162A 5

A 6M-18-9-N-5026 9M102NCM262A Radwaste Crane 20 A

6M-18-9-N-5038 Fuel Handling Building Cask Handling 7F101NCB102A 150 A

6F-18-9-N-5064 Crane 7F102NCB202A New Fuel Area 7F101NCB101A 5

A 6F-18-9-N-5064 Bridge Crane 7F102NCB201A Fuel Handling 3R231 NOB 102A 1 1/2 A, C 6F-18-9-N-5064 Machine 3R232N08202A Monorail 9F10lNCM105A 2

C 9F102NCM205A (heaviest load 6F-18-9-N-5058 1400lb.)

Monorail 9F10lNCM1058 2

C 9F102NCM205B (heaviest load 6F-18-9-N-5058 1400 lb.)

ECW Intake Structure Jib Crane 9Q190MH0001 5

A 60-01-9-M-0020 9Ql90MH0002 Turbine Generator Building (TGB)

Overhead Crane 9Q191MCG0138 200/40 B

9-M-0016 9Q191MCG0138 Overhead Crane 9Ql91MCG0238 10 B

9-M-0016 9Q192MCG0238 Overhead Crane 9Q191MCG0338 135/30 B

9-M-0016 9Q192MCG0338 2362N/0151N

l l

TABLE 2 (Cont'd.)

OVERHEAD HANDLING SYSTEMS EXCLUDED FROM ITEM 2.1.1 General Capacity Reason for Arrangement Crane Tag No.

(Tons)

Exclusion

Drawing No.

Machine Shop _

Overhead Crane 9PO40ACB01-054 50/20 B

(Bridge)

Warehouse Overhead Crane 9P030ACB02-054 10 B

(Bridge)

Pumping Structure (Reservoir Makeup Pumping Facilities)

Gantry Crane 8Y500 HCG 001 35 B

0-H-4912 Screen Intake Structure (Reservoir Makeup Pumping Facilities)

Gantry Crane 8Y500 HCG 002 15 B

0-H-4903 Circulating Water Intake Structure Gantry Crane 9P220 HCG 003 30 B

0-M-0029 Fire Pump House Monorai1 9Q100NCM001 A 2

B 90-27-0-M-0037 Monorail 9Q100NCM002A 2

B 9Q-27-0-M-0037 Monorail 9Q100NCM003A 2

B 9Q-27-0-M-0037

Reasons For Exclusion A = Crane is not capable of passing over equipment required for safe shutdown or decay heat removal.

B = There is no safe shutdown or decay heat removal equipment located in this building.

C = Crane does not carry any heavy loads.

D = The load is a component cf the piece of equipment required for safe shutdown or decay heat removal; therefore, the target equipment is not functional at time of lift. 2362N/0151N

TABLE 3.

. TABULATION OF EXCEPTIONS TO ANSI N14.6-1978 ' REQUIREMENTS ^

FOR THE SOUTH TEXAS LIFTING DEVICES T81 ANSI N14.'6 REQUIREMENT JUSTIFICATION OF. ACCEPTABILITY OF STP DESIGN ~

Paragraph 3.1.4 - req'uires the designer.to indicate Any repair to these special lifting devices is considered permissible repair procedures and acceptance criteria to be in the form of welding. Should pins, bolts or fer the repair.

Other-fasteners.need repair, they will be' replaced, in lieu of repair, in accordance with the original or-equivalent requirements for material and non-destructive

-testing. Weld repairs will 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, Subscction NF.

Acceptance criteria will be that i

identified in the applicable code section.

Paragraph 3.2.1.1 - requires the design, when using Materials for these rigs were chosen for their excellent materials with yield strengths above 80 perceni. of.2 fracture toughness characteristics. The stress design their ultimate strengths, to be based on the material's factors listed in 3.2.1 of and 5 were used in the fracture toughness and not the listed design factors.

analysis and the resulting stresses are acceptable..

Paragraph 3.2.6 - requires material for load-bearing Fracture toughness requirements were.not identified for i

members to be subjected to drop-weight or Charpy impact all the material used in these special lifting devices.

l tests.

However, the material selection was based on its excellent i

fracture toughness characteristics.j d

Paragraph 5.1 lists Owner Res>onsibilities and 5.1.2 The Westinghouse Qualit) Release verifies that-the criteria requires the owner to verify tlat the special lif ting for the letters of compliance for materials and devices meet the perfomance criteria of the design specifications required by Westinghouse drawings and specification by records and witness of testing. '

. purchasing documents were satisfied.

(I) a.

Load Cell Linkage b.

Reactor Vessel Internals Lift Rig l

c.

Reactor Vessel Head Lift Rig,

2827N/0151N

TABLE'3-(C:nt'd)-

TABULATION OF EXCEPTIONS TO ANSI N14.6-1978 REQ)UIREMENTS

'FOR THE SOUTH TEXAS LIFTING DEVICES 4' ANSI N14.6 REQUIREMENT JUSTIFICATION OF ACCEPTABILITY OF'STP DESIGN Paragaph 5.1.5,.5.1.5.1, and 5.1.5.2 requires special It is obvious from their designs that these rigs are=

identification and marking to prevent misuse.

specific-lifting devices and can only be used for their intended purpose.

Paragraph 5.2.1 requires the rigs to be initially tested These lifting devices'were proof tested, upon completion, at 150 percent maximum load followed by non-destructive.

with a load of approximately 125% of design weight in testing of critical load bearing parts and welds, accordance with industry standards. All parts, particularly welds, were visually inspected for cracks or

. obvious deformation and critical welds were magnetic particle inspected.

Paragraph 5.2.2 requires replacement parts to be Replacement parts, should they be required, will be made individually qualified and tested.

of identical (or equivalent) material and inspections as originally required. Only pins, bolt and nuts are considered replacement parts for.the reactor vessel head and internal lift rigs.

Paragraph 5.3 requires testing to verify continuing These special lifting devices are used during plant compliance and annual 150 percent load tests or annual refueling. During plant op ration these devices are non-destructive tests and examinations to be performed.

inaccessible since they remain in Containment. Load testing to 150 percent of the total weight before each use would require special fixtures and is impractical to i

i perform.

In addition, the movement of a 150 percent test load in containment for the purposes of annual testing would initiate an unnecessary safety risk. A 100% load test will be performed on each device (exclusive of the i

1 I

(I) a.

Load Cell Linkage b.

Reactor Vessel Internals Lift Rig l

c.

Reactor Vessel Head lift Rig i

28274/0151N

TABLE 3 (C:nt'd)

TABULATION OF EXCEPTIONS TO ANSI N14.6-1978 RJ.QUIREMENTS '

. FOR THE, SOUTH TEXAS-LIFTING-DEVICES lil ANSI N14.6 REQUIREMENT JUSTIFICATION-0F ACCEPTABILITY OF STP DESIGN upper internals lift rods, the load cell and load cell linkage) at each refueling, followed by a visual' check of critical welds. This check (visual) of critical welds and parts will 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.

No check of the upper internals lift rods will be done since these items remain either inside the head penetration or on the upper internals and are highly-radioactive. The upper internals lift rods are purposely preloaded to'a higher load than is present at lifting.

(l) a.

Load Cell Linkage b.

Reactor Vessel Internals Lift Rig c.

Reactor Vessel Head Lift Rig 2827N/0151N

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ATTACHMENT A SAFE LOAD PATHS A description of the safe load paths for loads identified in Table 1 is identified below:
Reactor Containment Polar Crane Reactor Vessel Internals Lift Rig (see Figure 1)
The internals lift rig is stored on the head laydown area.
It is used to change the 0-rings during any refueling operation. During non-rapid refueling the rig is used to lift the vessel internals to their storage areas.
(Removal of vessel internals is covered in item 2). The rig is lifted vertically from the head laydown area and is moved clockwise, around the perimeter of the containment, to the fuel storage pit.
It is then moved north to the vessel for 0-ring removal or replacement. The same path is followed for return.
Lower Internals (see Figure 2)
The internals lift rig together with the load cell linkage on the main hoist is used to move the lower internals.
The load is moved a short distance directly scuth of the vessel to the lower internals storage area.
Upper Internals (see Figure 2)
During non-rapid refueling the upper internals may be removed and moved to their storage stand (North of the vessel) using the main hoist, the load cell linkage and the internals lift rig.
Load Cell Linkage The load cell linkage is used to monitor loads being lifted by the polar crane main hoist.
It follows the path of the particular load being moved and no separate safe load path was developed.
Containment Fuel Pool Gate (see Figure 3)
The polar crane is used to lift the fuel pool gate vertically 30 feet l
and place it in the storage area on the south side of the refueling cavity. For repair, the gate will be placed on the deck.
4371N/0151N A-1
i Reactor Coolant Pump Flywheel, Motor and Rotor (see Figure 4)
The RCP components will be lifted by the main hoist during refueling operations. Some HVAC ducting will be removed to lift these components.
Each load will be raised to clear the top of the secondary shield wall (elevation 83') and will be moved south past
~
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the fuel pool. From this point the load will be moved along the perimeter in:
a) a counter clockwise direction to the laydown area adjacent to the personnel hatch, or b) a clockwise direction to the equipment hatch.
The components are returned by the same path.
Inservice Inspection Rig (see Figure 3)
The inservice inspection rig will be used three times in a ten year period. Some of its components will be leased, brought in through the equipment hatch, and transported counter clockwise around containment to an assembly / storage area near the pressurizer. This move is completed prior to head removal. The main hoist is used.
The assembled rig is moved clockwise to a point before the head laydown area, lifted to clear elevation 76', moved along the top of the secondary shield wall until even with tha vessel.
The same path is followed for return.
RHR Pump Components (see Figures 5 and 6)
The two pumps on the north side of the building will be mnved by cart (elevation - 11') to an area accessible by polar crane through the 8' X 6' equipment hatch.
All pump components will be lifted through the hatch to the 68' level and transported counter-clockwise to the personnel hatch.
RHR Heat Exchanger Components (see Figure 6)
These components are lifted by the main hoist through the heat exchanger removal hatches at level 68', moved to perimeter of containment, and transported in a clockwise direction to the equipment hatch.
4371N/0151N A-2
{
' Studs, Nuts, Washers and' Stud Tensioners
. (see Figure 8)
The. stud, nut, and washer carriers are moved from their laydown-area along the wall of the north side of containment to a point near-the head laydown area (the internals lift rig will be on the head laydown area), raised to clear main steam piping and moved south to the' cavity floor, as close as possible to the flange.
Studs, nuts, and washers.are placed 12 to a carrier (36 total) and
.ne ed to the operating deck.
The stud tensioners follow a similar path from the east side of the head laydown area.
Haten Covers (see Figure 1)
Hatch' covers are lifted only enough to clear the hatch and are placed on the deck adjacent to the hatch.
The Northeast hatch will be moved North over the main steam line since the area closest to it is.to be used for the reactor cavity filtration system.
RCB Monorails Fan (see Figures 17)
The fan follows the monorail path to the 6 X 6 hatch.
RIE Puriip Components (See Figure 5)
RHR pump components follow'the monorail path and are placed on
. carts.
IVC Monorails AFW Pump Components
.(See Figure Ba, 8c)
These components are lifted by monorails, transported by cart (el. 10') to the area below the equipment removal hatch.
They are then lifted by monorail (roof) and moved to the equipment laydown area.
4371N/0151N A-3 1
m
MSIV Components, Main Steam Safety Valve Components (See Figure 8b, 8c)
These components are lifted by monorail (el. 58') and moved under the equipment hatches. They are then lifted by monorail (roof) and transported to the equipment laydown area.
FWIV Compon;3nts (Figure 8c)
These components are removed by special devices and placed under the aquipment hatch for lift by monorail (roof).
MEAB Monorails CN Pump Components (see Figure 9, 10, 11)
These components are lifted by monorails and then transported (El 10') by cart to area below equipment hatch in Area L, elevation 60'.
They are then lifted by monorail (figure 10) and moved (figures 10 & 11) to the equipment removal doors in Area K, elevatior 60'.
Charging Pump Components and Supplementary Coolers (see Figures 9,10,11)
These components are lifted by monorails, placed on carts and follow the same path as CCW components.
Hatch Covers - Boric Acid Tanks (see Figure 12)
The hatch covers will be raised to clear the hatch and placed adjacent to the hatch Hatch Covers (see Figure 10)
The Demineralizer hatch covers are lifted to clear the hatch and placed next to the hatch.
Hatches closest to grid line #28 will be moved to the laydown area for the adjacent hatch.
This will provide clearance for the access doors.
The filter hatch covers will be removed and placed on top of another hatch where they will not restrict monorail movement.
4371N/0151N A-4
FHB Monorails Containment Spray Pump Components Safety Injection Pump Components (see Figure 13)
These components are moved by the indicated monorails to an area below the removable hatch. The components can then be accessed by the FHB overhead crane.
-FHB Overhead Crane Spent Fuel Pool (SFP) Heat Exchangers low Head Safety Injection Pump Components High Head Safety Injection Pump Components Containment Spray Pump Components (See Figure 13a)
These components are lifted through the removable hatch to the elevation 68' operating floor and moved to the railcar area where they can be laid down or removed for repair.
SFP Gates (See Figure 13b)
The gates will be lifted, moved along the perimeter of the pool and stored in the storage slots located on the sides of the pool, or laid on the operating deck for repair.
Hatches (See Figure 13b)
Hatches will be lifted and moved to the laydown area as indicated.
Shipping Cask Head (See Figure 13c)
The head will be moved from the railcar area to the cask loading pool and laid down on a storage shelf.
New Fuel Containers (See Figure 13c)
New Fuel containers are lifted from the railcar area and may be moved to either the 68' operating level or into the New Fuel Handling Area on the 30' level.
4371N/0151N A-5
'l
' ECWl Intake Grantry Crane
. Essential. Cooling Water Components
~
~(see Figure 14)
These. loads will be moved as indicated to the laydown' area at the
.end of the structure.-
- Diesel Generator Building Overhead Crane Miscellaneous loads (see Figure 15)
'Small loads on the lower level of the DGB will be moved to the north end of the building to an area under the equipment hatch.
Large loads will removed through a knockout panel at the north end of the building.
4371N/0151N A-6
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.. - o. ; :..- 1 ATTACHMENT B
SUMMARY
OF RESULTS OF STRESS CALCULATIONS FOR LIFTING DEVICES FOR STP Tables 8-1 and B-2 summarize the stresses on each of the parts which make up the reactor vessel head lif t rig assembly, load cell and load cell linkage and the internals lift rig.
In general, the tensile and shear stresses, meet the design criteria of section 3.2.1.1 of ANSI N14.6, requiring aoplication of stress design factors of three and five with accompanying allowable stress limits of yield and ultimate strength, respectively.
In addition, the tensile and shear stresses met the requirement of not exceeding the allowables of the AISC( } code. Additional details are provided below.
1.1 DISCUSSION 0F RESULTS 1.1.1 Application of ANSI N14.6 Criteria Both the reactor vessel head lift rig assembly, internals lift rig, load cell and linkage, were originally designed to the requirement that all the resulting stresses in the load carrying members, when subjected to the total combined lifting weight, should not exceed the allowable stresses specified in the AISCI } code.
The design criteria of section 3.2.1.1 of ANSI N14.6, requiring application of stress design factors of three and five with the accompanying allawable 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. Reference 11 discusses compliance with ANSI N14.6 and AISC criteria in greater detail.
B-1 2830N/0151N i
l'. l. 2 -~
Parts Exceeding the 3W Criterion
'The rod housing (Table B-2 Item 14) of the reactor vessel internals lift rig does not meet the ANSI N14.6 criteria of 3W when analyzed for tensile stresses. This stress (32,400 psi) exceeds the minimum allowable yield stress (30,000 psi). However, since the actual mechanical properties for this item list the yield strength;as 41,500 psi and the ultimate strength criterion of SW is met, this item is considered acceptable.
-The guide sleeve (Table B-2 Item 15) of the reactor vessel internals lif t rig does not meet the ANSI N14.6 criteria of 3W when analyzed for tensile stresses. This stress (31,800 psi) exceeds the allowable yield stress (30,000 psi).
However, since the actual properties for this item list the yield strength as 35,000 psi and the ultimate strength criteria of 5W is met, this item is considered acceptable.
2.0 CONCLUSION
Application of the ANSI N14.6 stress design criteria to these special lifting devices results in acccptable stress limits for tensile and shear stresses.
3.0' REFERENCES 1.
George, H., Control of Heavy Loads at Nuclear Power Plants Resolution of Generic Technical Activity A-36, NUREG 0612, July, 1980.
2.
ANSI N14.6-1978, "Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500kg) or More for Nuclear Material," American National Standards Institute, New York, 1978.
3.
WCAP-9942, Stress Report 4XLR Integrated Head Package CRDM Seismic Support Assembly for Houston Lighting and Power, South Texas Units 1 and 2.
B-2 2830N/0151N
l m : 4F
! eferences (Cont'd)
R 4.
ANSI N18.2 -' Nuclear Safety Criteria for the Design of
Stationary. Pressurized Water Reactor. Plant.
5.
Manual of Steel Construction, Seventh Edition, American m
Institute.'of Steel Construction.-
6. -
Westinghouse D'rawing 7011747 - Opper Head Package General Assembly..
7.
. Westinghouse Drawing J?.17E10 - TGX/THX South Texas Internals Lifting Rig and 0-Ring Change Fixture. General Assembly.
8.
.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.
9.
Biggs, J. M.',_ Introduction to Structural Dynamics, McGraw-Hill,
.New York, 1964.
10..Gwinn, Jr., J. T., "Stop Over-Designing for Impact Loads,"
Machine Design, 33, pp. 105-113 (1961).
11.. WCAP-10215, Evaluation of Acceptability of the Reactor Vessel Head Lift Rig Assembly, Reactor Vessel' Internals lift Rig, Load Cell, and Load Cell Linkage to the Requirements of NUREG 0612 for Houston Lighting & Power, South Texas Units 1 and 2.
B-3 2830N/0151N
p - - -- - --_____._.,..____...
TABLE B-1
SUMMARY
OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)(e) Haterial Allowable Item (a)
Part Name Value (ksi)
(c)
No.
And Material Designation W(b) 3W SW S
gult (d) y 1
Lifting Block Tension @ 8" Dia. Hole 6.5 19.5 32.5 85 105 ASTM A508 Shear @ 8" Dia. Hole 6.5 19.5 32.5 Class 4 2
Lug Tension @ 5" Dia. Hole 5.5 16.5 27.5 85 105 ASTM A508 Shear @ 5" Dia. Hole 5.5 16.5 27.5 Tension @ Weld 1.0 3.0 5.0 l
Shear @ Weld 1.9 5.7 9.5 (a)
See figure B-1 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-4 2831N/0151N h
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TABLE'B-1:(Cqnt'd) 11'
SUMMARY
OF RESULTS.
REACTOR _ VESSEL HEAD LIFT RIG.
CalculatedStresses'.(k'si)I')J Material Allowable Item ")
.Part Name Value (ksi)
I No.
.And Material Designation WW 3W 5W S
9 Sul t_. ( d) '
y 3
Upper Pin '
Shear.
4.9
.14.7-24.5'
.105;
'.135
~
ASTM A434 C1 ass BD' AISI 4340 4
Upper Clevis.
Tension @ 5" Dia. Hole 6.'4 19.2 32.0 110 135-ASTM A668 Shear Tear Out 6.4 19.2 32.0 Class M Thread Shear 4.2 12.6 21.0 AISI.4340 (a) See figure B-1 for location of item number and section.
(b)
W is the total static ' weight per unit area of the component and the lifting device (c) S is the yield strength of the material (ksi).
~
y (d)
S is the ultimate strength of the material-(ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-5 2831N/0151N
TABLE B-1 (Cont'd)
SUMMARY
OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)(e) Material Allowable Item (a)
Part Name Value (ksi)
W 3W SW S (c) g Id)
No.
And Material Designation W
y ult 5
Lifting Leg Tension @ Threads 10.8 32.4 54.0 85 110 ASTM A434 Thread Shear 4.2 12.6 21.0 l
Class BC AISI 4340 6
Lower Clevis Thread Shear 4.2 12.6 21.0 110 135 ASTM A688 Shear Tear Out 7.1 23.1 38.5 Class M Tension @ Thread Relief 6.4 19.2 52.0 AISI 4340 (a)
See figure B-1 for location of item number and section (b) W is the total static weight per unit area of the component and the lif ting device (c) S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-6 2831N/0151N
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.1 TABLE' B-l ?(C:ot 'd)..
s
SUMMARY
.0F RESULTS'
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M
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REACTOR VESSEL HEAD LIFTLRIG1 L
'CalculatedStresses(ksi)f') MaterialAllowhle.
' Item ( a)--
Part Name.
.Value
. (ksi)
W 3W SW
'S.(cf S
lid)
No.
And Material Designation:
lW y
ult 4.9 14.7-24.5 105 135-7 ~
Lower Pin
. Shear
=
ASTM A434 Class BD AISI 4340 8
Lift Lug
Shear @ Pin Hole 3.6 10.8-18.0 50 80 '.
ASTM A508 Tension @ Base of Lug Ear 2.7 8.1-13.5
. Class 2 Shear @ Base of Lug Ear 1.4 4.2 7.0 Snear-@ Lug Ledge-3.6
'10.8 18.0 Tension 0 Base 'of Lug Ear 6.2 18.6
'31.0
. Shear in Top Weld 5.1 15.3 25.5 l
Shear in Bottom Weld
,7.1.
21.3 35.5 (a) See figure B-1 for location of item number and section.
~
l (b) W is the total static weight per unit area of the component and the lifting device (c)
S, is the yield strength of the material (ksi) l (d) S istheultimate'strengthofthematerial(ksi) ult (e)
Stresses calculated are'those required by. ANSI N14.6 l
B-7 2831N/0151N-
TABLE B-1 (Cint'd):
s
SUMMARY
OFlRESULTS
~1 REACTOR. VESSEL HEAD LIFT RIG-
. Calculated Stresses'(ks'1)(*) Material Allowable Item (a)
- Part Name
'Value-(ksi)
~
No..
And Material Designation
'WW c3W
' SW
~ S, T c ) _ gult (d)'
9 Missile Axial 9 Lug Edge.
0.3 -
0.9 1.5-501 80 Shield Shearing @ Lug Edge 2.1 6.3 10.5 ASME Shear to Lift Nut:
0.9 2.7
.4.5 SA A533 Type B Class 1 10 Lift Nuts Shear 3.1 9.3
'15.5 50 80 ASME Thread Shear 2.6 7.5 12.5-SA A533 Type B Class 1 (a)
See figure B-1 for location of item number and section (b) W is the tctal static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 8-8.
2831N/0151N-
TABLE B-1 (Cont'd)
SUMMARY
OF RESULTS REACTOR VLSSEL HEAD LIFT RIG Calculated Stresses (ksi)I*I Material Allowable Item ( a)
Part Name Value (ksi)
No.
And Material Designation W@I 3W SW S (c)
Sult (d) y 11 Lift Rods Tension 7.2 21.6 36.0 85 110 ASTM A434 Shear 0 End 12.0 36.0 60.0 Class BC Thread Shear 2.4 7.2 12.0 AISI 4340 12 Crank Hand:a Thread Shear 1.8 8.4 9.0 30 75 Nut ASME SA-479 Type 304 (a)
See figure B-1 for location of item number and section (b) W is the total static weight per unit area of the component and the lifting device (c) S is the yield strength of the material (ksi) y (d) S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-9 2831N/0151N
TABLE B-1 (Cont'd)
SUMMARY
OF RESULTS REACTOR VESSEL HEAD LIFT RIG Calculated Stresses (ksi)I*) Material Allowable Item (a)
Part'Name Value (ksi) lDI (c)
No.
And Material Designation W
3W SW S
Sult (d) y 13 Upper Internals Tension @ 3.50" Dia.
4.9 14.7 24.5 30 75 Lift Rod Section ASME SA-479 Thread Shear 1.8 5.4 9.0 Type 304 On ACME Thd.
Thread Shear 4.9 14.7 24.5 On "V" THD Tension 0 3.6" Dia.
9.6 28.8 48.0 Section 14 Nut Thread Shear 4.9 14.7 24.5 30 75 ASME SA-479 Type 304 (a)
See figure B-1 for location of item number and section (b) W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-10 2831N/0151N
TABLE B-2
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)I*I Material Allowable Item (a)
Part Name Value (ksi)
(c)
No.
And Material Designation W(b) 3W SW S
3 ult (d) y 1
Lifting Block Tensile Stress @ 8" 3.6 10.8 18.0 36 70 ASTM A350 Dia. Hole Grade LF2 Shear Tear-out @ 8" 3.6 10.8 18.0 Dia. Hole Tensile Stress @ Central 5.8 17.4 29.0 Cylinder (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-11 2832N/0151N
TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE i
Calculated Stresses (ksi)(*)
Material Allowable Item (a)
Part Name Value (ksi)
IDI (c)
No.
And Material Designation W
3W SW S
g Id) y ult 2
Lifting Block Tensile Stress @ 4.015" 4.0 12.0 20.0 38 70 Lug ASTM A516 Dia. Hole Grade 70 Tension 0 Lug 1.2 3.6 6.0 Root Weld Shear Tear-out @ 4.015" 4.0 12.0 20.0 l
Dia. Hole l
Shear 0 Lug Root Weld 1.9 5.7 9.5 l
l
( a)
See figure 8-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device i
(c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 I
B-12 2832N/0151N ll
TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)I*I Material Allowable Item ( a)
Part Name Value (ks1)
(c) 3 ult (d)
IDI 3W SW S
No.
And Material Designation W
y 3
Upper Clevis Pin Shear 4.5 13.6 22.5 105 135 ASTM A564 Type 630 17-4 pH Hil50 l
4 Upper Clevis Tension 0 4.015" Dia. Hole 4.5 13.5 22.5 95 110 ASTM A471 Shear Tear-out @ 4.015" 4.5 13.5 22.5 j
Class 3 Dia. Hole Thread Shear 4.7 14.1 23.5 (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-13 2832N/0151N
.1
TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS -
REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)(e)
Material Allowable Item (a)
Part Name Value (ksi) 5,(c)
IDI gult (d) 3W SW No.
And Material Designation W
5 Sling Rod Thread Shear 4.7 14.1 23.5 85 or 46* 110 ar 67**
ASTM A434 Tension @ Thread Relief 10.2 30.6 51.0 Class BC Tension @ Thread 10.8 32.4 54.0 AISI 4340 (or)
ASTM A588 6
Lower Tension @ 4.015" 4.5 13.5 22.5 95 110 Clevis Dia. Hole ASTM A47' Thread Shear 4.7 14.1 23.5 Class 3 (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 85 for AISI 4340, 46 for ASTM A588 110 for AISI 4340, 67 for ASTM A588 B-14
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TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE CalculatedStresses(ksi)(*)
Material Allowable Item ( a)
Part Name Value (ksi)
(c)
No.
And Material Designation W(b) 3W SW S
Sult (d) y 7
Lower Clevis Pin Shear 9.0 27.0 45.0 95 110 ASTM A564 Type 630 17-4 pH H 1150 8
Spreader Lug Tensile Stress 1.9 5.7 9.5 38 70 ASTM A516 Grade 70 (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) j (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 c
B-15 2832N/0151N I
TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)(e)
Material Allowable Item (a)
Part Name Value (ksi)
S,(c)
No.
And Material Designation W(b) 3W SW 3 ult (d) 9 Spreader Arm Nominal Compression Stress 3.1 9.3 15.5 F,=23 ASTM A500 46 58 Grade B 10 Leg Lug Tensile Stress 3.2 9.6 16 38 70 ASTM A516 la 4.015" Dia. Hole Grade 70 (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 F = allowable compression stress to prevent buckling in absense of bending moment a
B-16 2832N/0151N
TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS
' REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)(*)
Material Allowable Item (a)
Part Name Value (ksi)
(c)
IDI Sult (d)-
3W SW S
No.
And Material Designation W
y 11 Leg Channels Tensile Stress 7.1 21.3 35.5 36 58 ASTM A36 12 Mounting Block Shear in Welds 1.8 5.4 9.0 30 60 ASTM A350 LFl 18 13 Load Nut Thread Shear 5.1 15.3 25.5 30 75 ASTM A276 Type 304 Cond. A (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 Stress limit for fillet welds from ASME Boiler and Pressure Vessel Code,Section III, Division 1 - Subsection NF 1980 Edition, Table NF-3292.1-1, page 43.
B-17 2832N/0151N
TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)(*)
Material Allowable Item (a)
Part Name Value (ksi)
S,(c)
IDI Sult (d) 3W SW No.
And Material Designation W
14 Rod Housing Tension @ Thread Relief 10.8 32.4 54.0 30 75 ASTM A276 Thread Shear on Upper 5.1 15.3 25.5 Type 304 Threads Cond. A Lower Threads Shear 4.5 13.5 22.5 37 81 15 Guide Sleeve Thread Shear 4.5 13.5 22.5 30 75 ASTM A276 Tension e Thread Relief 10.6 31.8 53.0 35 81*
Type 304 Cond. A (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 These are actual S and S taken from material certifications.
y ult B-18 2832N/0151N
TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE Calculated Stresses (ksi)
Material Allowable Item (a)
Part Name' Value (ksi)
(c)
Sult (d)
No.
And Material Designation W(b) 3W SW Sy 16 Rotolock Stud Tensile Stress @ Cross-19.0 57.0 95.0 115 150 ASTM A564 Section Type 630 Shear Stress on 10.7 32.1 33.5 17-4 pH H 1100 Land Root 17 Clevis Pin Shear 7.3 21.9 36.5 105 135 (Load Sensing)
ASTM A564 Type XM12 (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-19 2832N/0151N
_ wm
I TABLE B-2 (Cont'd)
SUMMARY
OF RESULTS l
REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE.
Calculated Stresses (ksi)(e)
Material Allowable Item (a)
Part Name Value (ksi) lD)
S,(c)
No.
And Material Designation W
3W SW 3 ult (d) 18 Side Plates Tension @ Upper Hole 6.6 19.8 33.0 100 115 ASTM A517 Tension @ Lower Hole 6.0 18.0 30.0 Grade F Shear Tear-out 0 Upper Hole 6.6' 19.8 33.0 Shear Tear-out @ Lower Hole 12.6 37.8 63.0 19 Removable Pin Shear 6.9 20.7 34.5 105 135 ASTM A564 Type 630 17-4 pH 11 1150 (a)
See figure B-2 for location of item number and section (b)
W is the total static weight per unit area of the component and the lifting device (c)
S is the yield strength of the material (ksi) y (d)
S is the ultimate strength of the material (ksi) ult (e)
Stresses calculated are those required by ANSI N14.6 B-20 2832N/0151N
b 9
E-
~L
't
'9 LfFTING BLOCK h IN
-1 gga g t
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a h UPPER CLEVIS
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h LIFTING LEG h LOWER CLEVIS g
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- <=gy 5
h LIFT NUT s
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M:i W4) l l
9 - HOUSING k
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g MissLE CRANK HANDLE 3
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!'I NUTh g
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' [R.V.IlEAD l
LIFT RODS h I
I Ih U
1 UFPER INTERNALS m
LIFTING RODh
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UPPER INTERNALS

- y p

FLANGE 1
l 1
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a m
i Figure B-1 k
INTEGRATED HEAD PACKAGE 2
(LIFT RIG PORTION)
J e
! I l
~
i h
LIFT RIG MISS4LE SHIELD OPERATOR STAND s
\\;
MESSENGER TRAY
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Figure B-2 INTEGRATED HEAD PACKAGE
CLEVIS PIN (LOAD CELL)
SIDE PLATES REMOVABLE PIN 9
e
/
LIFTING BLOCK S
Ai%
,6 ib CLEVIS PIN -
,C.
g LUG CLEVIS N2, 3m>
C h
rt 4
N SLING ROD
</
CLEVIS ARM
/
SPREADER LUG f[,-
4 CLEVIS PIN
~
~
J 'i
.[c
" LEG LUG l
N! !
i.;
CHANNEL d ;
'1 0
i4;
)
l I, b
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'p,/'
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! c LOAD NUT C
MOUNTING BLOCK i
ROD HOUSING h
1 GUIDE SLEEVE ROTO-LOCK STUD Figure B 3 REACTOR VESSEL INTERNALS LIFT RlG
ATTACHMENT C CRITICAL ITEMS LIST PER ANSI N14.6-1978 1.
GENERAL Section 3.1.2 of ANSI N14.6-1978 specifies that the design specification shall include a critical items list, which identifies critical components and defines their critical characteristics for material, fabrication, non-destructive testing and quality assurance.
" Critical items list" is further defined in ANSI N14.6, Section 2 as:
" critical items list. A list that specifies the items of a special lifting device and their essential characteristics for which specified quality requirements shall apply in the design, fabrication, utilization, and maintenance of the device."
Load carrying members and welds of these special lif ting devices are considered to be the critical items.
Table C-1, C-2, C-3 and C-4 are the critical items list of parts and welds for the reactor vessel head lift rig assembly, the upper internals lif t rod, the reactor vessel internals lif t rig, the load cell and load cell linkage. These tables include the material identification, 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 non-destructive testing was not justified.
The material selection for all critical 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.
C-1 2837N/0153N j
l
Westinghouse' required all welding, welders, and weld procedures to be in
-accordance'with ASME Boiler and Pressure Vessel Code Section IX for all f-1 welds.Jhkstinghouse required a certificate, or letter of compliance, that the materials and processes used by the manufacturer were in accordance'with the purchase-order and drawing requirements.
Westinghouse also performed final inspections on these devices and issued qu'ality releases.
C-2 2837N/0163N
l TABLE C-1 REACTOR VESSEL HEAD LIFT RIG CRITICAL ITEMS LIST OF PARTS PER ANSI N14.6-1978 Non-destructive Testing Item (a)
Description Material Material Finished 1
Lifting Block ASTM A508 Ultrasonic Magnetic Class 4 Particle 2
Lug ASTM A508 Ultrasonic Magnetic Class 4 Magnetic Particle Particle 3,7 Upper & Lower ASTM A434 Ultrasonic Magnetic Pin Class BD Particle AISI 4340 4,6 Upper & Lowar ASTM A668 tiltrasonic Magnetic Clevis Class M Particle AISI 4340 5
Lifting Leg ASMT A434 Ultrasonic Magnetic Class BC Particle AISI 4340 8
Lift Lug ASTM A508 Ultrasonic Magnetic Class 2 Particle 9
Missile Shield A5ME SA 533 Ultrasonic Magnetic Type B Particle Clacs 1 10 Lift Nut ASME SA 533 Ultrasonic Magnetic Type B Particle Class 1 11 Lift Rod ASTM A434 Ultrasonic Magnetic Class BC Particle AISI 4340 12,13,14 Crank Handle Nut, ASME SA479 Ultrasonic L1guid Upper Internals Type 304 Penetrant Lift Rod, Nut (a)See Figure B-1 C-3 l
2837N/0153N
TABLE C-2 REACTOR VESSEL HEAD LIFT RIG CRITICAL ITEMS LIST OF WELDS-PER ANSI N14.6-1978 Non-destructive Testing Item (a)
Description Root Pass Final
^
8,9' Lift l'ug to Missile Magnetic Magnetic Shield Top and Bottom Particle Particle
'(fillet)
Radiograph (a)See Figure B-1 C-4 2837N/0153N
__________________________J
TABLE C-3
^
.' REACTOR VESSEL INTERNALS' LIFT RIG, LOAD CELL AND LOAD CELL LINKAGE CRITICAL ITEMS LIST-0F PARTS PER ANSI-N14.6-1978 Non-destructive Testing
-Item (a)
Description Material Material Finished 1
Lifting'.Blodk ASTM A350 Ultrasonic Magnetic GradeLF 2 Particle 2'
. Lifting Block ASTM A516 Ultrasonic Magnetic Lug Grade 70 Magnetic Particle Particle--
3,7-Clevis Pin ASTM A564 Ultrasonic Liquid Type.630 Penetrant 17-4 pH H-il50
~4,6-
' Clevis ASTM A471' Ultrasonic Magnetic Class 3 Particle 5:
Sling Rod.
ASTM A434
'Jitrasonic Magnetic Class BC Particle AISI 4340 or ASTM A588
'8,10 :
Spreader Lug, ASTM A516
-Ultrasonic Leg Lug GR 70 Particle Magnetic 11 Leg Channels.
ASTM A36
. Visual-12 Mounting' Block ASTM A350 LFI Ultrasonic Magentic Particle
((a)SeefigureB-3 C-5
-?837N/0153N-
s...
TABLE C-3 (Cont'd)-
. REACTOR VESSEL INTERNALS LIFT RIG, LOAD CELL AND LOAD ~ CELL LINKAGE jd [ e CRITICAL ITEMS LIST OF PARTS g[
'PER ANSI N14.6-1978 Non-destructive Testing Item (a) _
Description Material Material Finished 13,14-Load Nuts ASTM A276, Ultrasonic
. Rod Housing Type 304 Condition A 15-Guide Sleeve.
ASTM A276, Ultrasonic Liquid
-Type 304 Penetrant Condition A 16 Rotolock Stud ASTM A564, Ultrasonic Liquid Type 630 Penetrant 17-4 pH, H-1100 17 Clevis Pin ASTM A564
' Ultrasonic Magnetic
-(loadsensing)
Type XM12 Particle 18 Side Plates ASTM A517 Ultrasonic Magentic Grade F Particle
'19 Removable' Pin ASTM'A564 Ultrasonic Liquid Type 630 Penetrant 17-4 pH H-ll50
.t (a)See figure B-3 1
i C-6
'2837N/0153N
__m.
u 1
TABLE C-4 REACTOR VESSEL INTERNALS LIFT RIG.
CRITICAL ITEMS LIST OF WELOS-PER ANSI N14.6-1978
~
Non-destructive Testing
. Item (a).
Description Root Pass Final
~
1,2-Lugs to lifting Block Magnetic Magnetic (FullPenetration)
Particle Particle Radiograph 8,9~
Lug to Spreader Block Magnetic Magnetic (Full Penetration)
Particle Particle 10,11 Leg Lug to Channel Leg Magnetic Magnetic (fillet)
Particle Particle 11,12 Mounting Block to Magnetic Magnetic Channel Leg Particle Particle (fillet)
(a)See Figure B.
C-7 7837N/0153N
. ATTACHMENT D
- SINGLE-FAILURE-PROOF HANDLING SYSTEMS-
-ITEM 1*;
~
Provide the name of the manufacturer and the design-rated load (DRL).
If'the maximum critical load (MCL), as_ defined in NUREG 0554, is not the same as the
' DRL, ~ provide this capacity.'-
STP Response
The.FH6 overhead crane is manufactured by Kranco and rated for 15 tons.
The maximumLcritical load is a spent fuel pool heat exchanger which weighs 6.16
' tons..
1 ITEM 2
.Providei a~ detailed evaluation of the overhead handling system with respect to the features of design. fabrication, inspection, testing, and operation as delineated in NUREG 0554 and supplemented by the identified alternatives specified in NUREG 0612, Appendix C.
This evaluation must include a point-by-point comparison for each section of NUREG 0554.
If the alternatives of:NUREG 0612, Appendix C, are used for certain applications in lieu of complying with the recommendation of NUREG 0554, this should be explicitly stated..If'an alternative to any of those contained in NUREG 0554 or NUREG.
0612,. Appendix C, is proposed, details must be provided on the' proposed alternative to demonstrate its equivalency.
(If the crane in question has previously been approved by the staff'as satisfying NUREG 0554. Reg. Guide 1.104, or Part B to BTP ' AS8 9-1, please reference the date of the staff's safety evaluation report or approval. letter.in lieu of providing the Linformation requested by this item).
STP Response The FH6 overhead crane is designed :to meet the intent of RG 1.104 as descibed
,m in 9.1.of the FSAR. This was submitted to the NRC in revision 0 of the FSAR
!and there are no open items relating to this submittal. Table 9.1.3 of the
.FSAR compares crane design to RGfl.104 guidelines. The information is repeated here as Table D-1.
ITEM 3:
(With respect to the seismic analysis employed to demonstrate that the overhead handling system can retain the load during a seismic event ecual to a safe shu_tdown1 earthquake, provide a description of the method of analysis t
assumptionsused,andthemathematicalmodelevaluated1.-theanalysIs.he The description.of assus..ptions should include the' basis for selection of trolley-
.and load position.
~
M em numbers correspond to question numbers in Attachment (1) of Generic letter 81-07.
s D-1
+
.2635N/0145N q
L,
-z STP Response The finite element method of analysis was used to demonstrate that the overhead handling system can retain the load during a seismic event equal to a safe shutdown earthquake.
Stresses were examined for Dead Load + Live Load + SSE with the trolley at midspan, 1/4 span and the end of the span (hook at highest and lowest position).
The allowable stresses for structural steel are in accordance with Part I of AISC-1969.
The general layout of the model for the crane is shown in Figure D-1.
The large circles containing numbers, as well as the corresponding circles on the far girder, indicate the nodes at which the mass is assumed to be concentrated Nodes 1 through 4 and 8 account for all the mass of the bridge and trolley and include both transitional mass and rotary inertia.
Node 7 contains the translational mass of the load and bottom block.
The distances L1 and L3 was varied to account for different positions of the olley, and L4 was varied to account for different positions of the load.
All members shown as double lines were assumed to be infinitely rigid.
Members shown as single lines were treated, for the most part, in the conventional manner as beams in a three-dimensional framework.
The cable, from node 7 to node 8, is a pin-connected member subject only to axial distortion.
For all other members, axial distortion is neglected.
The two girt beams by means of which the trolley spans between girders bend only vertically; they are infinitely rigid in horizontal bending and have no resistance to torsion.
It was assumed that the two girders are identical, so that the structure is symmetrical about the Y-Z plane. The analysis is carried out separately for the symmetric and antisymmetric modes.
The symmetric modes are excited by building motion in the Y and Z directions and by rocking about the X axis.
The antisymmetric modes are excited by motion in the X direction and rocking about the Z axis.
It was assumed that rotation of the building about the Y axis does not excite the crane since it is free to rotate on the runway.
The springs shown at the four support points "A" represent the flexibility of the crane runway.
The vertical springs are always active.
The horizontal springs may be active at both ends of the crane, or only at one end.
If inactive, the spring constant is zero.
The boundary conditions at the four support points "A" are different for different excitations.
In general, they are free to move in all three directions subject to the restraint offered by the springs except that for motion in the X direction and rocking about the Z axis, the supports are fixed in the X direction. At the trolley support point "B", the trolley was assumed to be fixed to the girder in the X and Y directions, but it is free to move in the Z direction.
No moments were transmitted at any of these support points.
0-2 2635N/0145N t
p YThe varicus excitaticns prcduced by earthquakes acting in the X, Y, and Z
-directions.were combined (square root of the sum of the squares) to determine the total excitations to which the crane is subjected.
The response of the crane in each of the modes represented by the model was determined by conventional methods. Tne-stresses of interest due to the various modes were combined (square root-of.the sum of the squares) to cbtain the total seismic
stresses for which the crane should be designed.
ITEM 4 Provide an evaluation of the lifting devices for each single-failure-proof
~
handling system with respect to the guidelines of NUREG 0612, Section 5.1.6.
STP Response' There are no special lifting devices for heavy-loads used with the 15/2 ton crane.
Slings will be procured and used in accordance with ANSI B30.9-1971
- guidelines as modified by Sections 5.1.1.5 and 5.1.6 of NUREG 0612.
ITEM S Provide an evaluation of the interfacing lift points with respect to the
guidelines of NUREG 0612, Section 5.1.6.
'STP Response-STP follows.the guidelines of position C.3.a of RG 1.104, Rev. 0 with regard to lift points.. Interface lift points on the fuel pool gates and SFP heat exchanger hatches comply with NUREG 0612, Section 5.1.6, guidelines.
The cask head will be built to the NUREG 0612 guidelines, and slings will be procu.ad to these guidelines.
The new fuel containers, SFP' heat exchangers, LHSI pump components, HHS!' pump components and containment spray pump components have been fabricated with interface lift' points which are not designed with the margins specified by NUREG 0612. Section 5.1.6.
Safe load paths have been developed and'will.be
~ described in procedures regulating the movement of heavy loads lifted by the FH8 15/2 ton overhead crane (see Figures 13a, 13b-and 13c).- Although analysis of movement of these loads is not in strict accordance with Appendix A of NUREG-0612, the combination of a single failure proof crane and safe load paths governed by procedures provides adequate assurance that plant safety will not be jeopardized and-is considered to meet the intent of Appendix A and RG'1.104 These loads are not moved over safety related equipment or the spent fuel pool; a load drop on the safe lead path would not result in damage to safety related equipment.
D-3 l
~ 2635N/0145N i
b.
. TABLE D-1 FHB 15/2 TON CRANE - COMPLIANCE WITH REGULATORY GUIDE 1.104 Not Applicable by Either STP Meets the Rev. O or the Intent of Rev. O Proposed and Complies with STP takes Revision Regulatory-STP Complies a Proposed Revision Exception Dated January Position with Rev. O Dg ed January 1978 to Rev. 0 1978 C.1.a:
X
' 1. b X
.(3)
X (4)
X 1.c X
1.d X
1.e X
1.f X
C. 2.a -
X 2.b y
2.c h
2.d X
.C.3.a X
3.b X
3.c X
-3.d X
3.e X
3.f X
3.g X
3.h X
3.1 X
3.j X
3.k Y
3.1 X
3.m X
3.n X
3.0 See note 1 3.p
-X 34 X
3.r X
3.s See note 2 X
3.t 3.u X
D-4 2635N/0145N l
i TABLE 0-1 (Cont'd)
FHB 15/2 TON CRANE - COMPLIANCE WITH REGULATORY GUIDE 1.104 Not Applicable by Either STP Meets the Rev. O or the Intent of Rev. O Proposed and Complies with STP takes Revision Regulatory STP Complies a Proposed Revision Exception Dated January Position with Rev. O Dated January 1978 to Rev. 0 1978 C.4.a X
4.b X
X 4.c X
4.d C.S.a X
5.b X
Note 1: Controlled plugging measures shall be provided so that if the operator reverses a drive while it is in motion, the torque during reverse shall be automatically controlled to a predetermined torque limit during deceleration.
Note 2: The crane is designed to CMAA standards (i.c, a 5:1 minimum factor of safety for each component) for a 15-ton lift.
0-5 2635N/0145N
l A
i-I 9
L 1
V
(
B B
,/ Qs, o
s y
f s
i E
i j
d
';/
SOUTH TEXAS PROJECT UNITS 1 & 2 i
i Figure D 1 j
MODEL FOR SEISMIC ANALYSIS l
15/2 TON FHB CRANE l
i
.... -. -.., -, -,,. - - _ ~. - - - - - -..,..,..... -..,.. _..,.....,, - -,
- -. - ~ - - - - - - - - - -

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