ML18026A231

Forwards Responses to NRC 801222 & 810203 Ltrs Re NUREG-0612, Control of Heavy Loads - Final Rept.

ML18026A231
Person / Time
Site:	Susquehanna
Issue date:	09/24/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0612, RTR-NUREG-612 PLA-937, NUDOCS 8109290183
Download: ML18026A231 (101)

Text

REGULATJRY INFORMATIO(V DISTRIBUTION SYSTEM; (RIOS)

ACCESSIOV NSR: 8109290183( DOC ~ DATE': 81/09/24 NOTARIZc,D:: NO DOCKET' FACILI050-387 Susquehanna Steam Electric Station> Unit 1F Pennsylva 05 50 388 Susquehanna Steam Electric Station> Unit 2< Pennsylva 0 0 AUT+, NAME AUTH JR AFF ILIAT'ION CURTIS P Ve H 0 Pennsylvania ?ower U Light Co ~

REC IP. VAN=i RECI?IEIVT AFFILIATION E ISE VHUTIF 0 8 G ~ Oi vi si on of Li censing 8UOJECT:: Forwards responses to RRC 801222. 8 810203 I trs re NJREG 0612< "Control of Heavy Loads Final Rept;"

8 DISTRIB'JTION CODE;: 8030S COP IcS RECEIVED:LTR ENCl TITL=l: Control of Heavy Loads Near Soent'uel (USIrA 36) RE OLE VOTES: I3E:3( cooies CLIENT FSAR 4 all amends ~ LPOR:2cys 05000387'5000388 ICE".3 coo.ies FSAR 8, all amends ~ LPDR:2 cys RECI COPIES RECIPIENT'D COPIES IO CODE/NAMKl I.TTR E(VCLI CODE/NAME LTTR" c,NCL ACT'IONe A/D LI "E VS(VG EQUAL 1 0 LIC BR 42 BC 1 0.

C'L MENSONFF ~ 04 4 L'IC BR 42 LA 1>> 0.

STARKER'0 1 1 INTERNAL(a ACC ID =,PAL 8 92b 1 1 AUX SYS BR ',

27 1 CH=M E'VG BR 11 1 1 CONT SYS BR 09 1 1 P RF BR 10. 'ORE 1 1 EFF TR SYS 1 1.

JIP IENCES BR12'FOSC EQ 8%(1 3 3 28 1 1 HU'i rA"T ENG 40. 1 2 HYD/GEO BR 30 2 2, IKC( SYS BR 1 1 IEE 06 3 31 35 lb'E'/EPDSI 1 1 IE/EPLB 36 3 3 L'I ' GUID BR 33( 1 1 L'I C QU 4L. BR 32 1 1 MATL EVG BR 17 1 1 UiECH EVG BR 18 1 1 HPAI 1" 0 OELO 1 0 OP LIC BR 34 1 1 PO'HER SYS BR 19 1 1 PROC/TST REV 20, 1 QA BR 21 1 1 RAOI AS4 BR22( 1 1 REAC, SYS BR 23- 1 1 LF( c 01 1 1 REQUAFG ~ 1 1.

'I < ANAL BR 24 1 1 STRUCT ENG BR25 1 1.

EXTERNALI: ACRS 41 1b 16 FEMA REP DIY 39 1 1 LPDR 03( NRC POP 02 1 1 NSIC 05( 1 1 CC @(

TOTAL RUR822( OF COPZE8 REOUIREO: I.TTR p5 ERCL, 00

0 R- 887 Pennsylvania Power 8'Light Company >ST Two North Ninth Street ~ Allentown, PA 18101 ~ 215 l 7705151 Norman W. Curtis Vice President-Engineering & Construction-Nuclear 215/ 770-5381 September 24, 1981 t

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Mr. Darrell G. Eisenhut Director Division of Licensing United States Nuclear Regulatory Commission Washington, D.C. 20555

)t l Lp SUSQUEHANNA STEAM ELECTRIC STATION NUREG-0612 CONTROL OF HEAVY LOADS FINAL REPORT ER 100450 FILE 842-06 PLA-937

Dear Mr. Eisenhut:

In reply to your letters dated December 22, 1980 and February 3, 1981, attached please find PP&L's review of controls for the handling of heavy loads final report.

Ve truly ours, N. . Curtis e President-Engineering & Construction-Nuclear CFB/mks Attachment 5 copies

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810924 8109290i83 05000387 PDR ADOCK PDR

8109290183 RESPONSE TO RE UIR~~~WTS IN NUREG 0612 "CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS" TABLE OF CONTENTS 1~0 Introduction 2.0 Information Requested from Licensee 2.1 General Requirements 2.1.1 Plant Arrangement Review

2. 1. 2 Exclusion of Overhead Handling Systems 2.1.3 Compliance with Guidelines of NUREG 0612, Section 5.1.1 2.2 Specific Requirements for Reactor Building 2.2.1 Tabulation of Overhead Handling Systems on Refueling Floor 2.2.2 Exclusion of Overhead Handling Systems on Refueling Floor 2.2.3 Single Failure Proof Handling Systems 2.2.4 Other Overhead Handling Systems 2.3 Specific Requirements for Other Areas 2.3.1 Exclusion of Overhead Handling Systems in Other Areas Tables

l. Tabulation of Overhead Handling Systems on the Refueling Floor

2. Reactor Vessel Servicing Equipment J

1.0 INTRODUCTION

As required by NUREG-0612 "Controls of Heavy Loads in Nuclear Power Plants," PPaL is submitting this document in order to enable the NRC to evaluate the controls provided for= overhead crane loads at Susque-hanna Steam Electric Station. This document is PPGL's second eport and covers Sections 2.2 and 2.3 of Enclosure 3, "Request for Additional Information or Control of Heavy Loads," to the staff's letter of December 22, 1980( ) ~ Additionally, this report contains some in-formation which was required in PPGL's first report, but unavailable at the time of submittal.

PP&L's objective in this report is to insure that the handling of overhead loads in the vicinity of new or spent fuel, or nuclear safety related equipment does not cause:

1. radioactive releases in excess of the requirements of 10 CFR Part 100,

2. damage to fuel that will result in a K ff greater than

.95,

3. damage to RPV or spent fuel pool that would result in uncovering fuel, and

4. damage to equipment that would result in the loss of safe shutdown capability or the loss of the capability to re-move decay heat.

For the purposes of this response, a heavy load was considered to be any load in excess of one thousand pounds. This was the most realistic weight limit to evaluate because many cranes, monorails and hoists were rated in units of k, 4, or 1 ton units. In addition, the weight of some loads were estimated and a convenient unit (5 ton) was con-servatively used for relatively small loads.

2.0 INFORMATION RE UESTED FROM LICENSEE 2.1 General Re uirements NUREG-0612, Section 5.1.1 identified several general guidelines related to the design and operation of overhead load-handling systems in the areas where spent and new fuel is stored, in the vicinity of the reac-tor core, and in other areas of the plant where a load drop could re-sult in damage to equipment required for safe shutdown or decay heat removal. The information supplied in Section 2.1.1 through 2.1.3 of this response is intended to provide the Staff with the results of our reviews and identify any potentially hazardous load-handling operations which would require special procedures or equipment modifications to insure the intent of NUREG-0612 is met.

(1) On December 22, 1980, the NRC requested all applicants for operating licenses to implement NUREG-0612, reference letter from Darrell G.

Eisenhut, Director, Division of Licensing.

Page 1 of 9

2.1.1 Plant Arran ement Review (2)

(2) 2.1.2 Exclusion of Overhead Handlin S stems 2.1. 3 Com liance with Guidelines of NUREG-0612, Section-5.1.1 (2)

This compliance was addressed in PPGL's first report; however, attached to this report is a copy of PPGL's "Crane Operator Certi-fication Training Program" which was not available for submittal on June 22, 1981. o(See Attachment A.)

2.2 S ecific Re uirements for Reactor Buildin The information provided in this section is intended to demonstrate that PPGL has adequate controls concerning the design and operation of overhead load handling systems in the vicinity of spent fuel (either in the reactor vessel or in the fuel storage pool) and new fuel. The review is based upon the guidelines contained in NUREG-0612, Section 5.1.4.

2.2.1 Tabulation of Overhead Handlin S stems on Refuelin Floor Statement of Requirement:

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 over spent fuel in the storage pool or in the reactor vessel.

Interpretation:

This section addresses those cranes located on the refueling floor of the Reactor Building. There are other cranes and monorails in the Reactor Building; but, load drops from these other cranes and monorails cannot impact new or spent fuel, or the reactor pressure vessel. These other cranes and monorails will be discussed in Section 2.3 of this report.

Statement of Response:

Table 1 identifies those cranes, monorails, and hoists which are capable of impacting new fuel, spent fuel or the reactor pressure vessel in the event of an uncontrolled load drop.

2.2.2 Exclusion of Overhead Handlin S stems or Refuelin Floor Statement of Requirement:

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 heavy loads over stored fuel or into any location where, following any failure, such load may drop into the reactor vessel or spent fuel storage pool.

Interpretation:

None required.

Statement of Response:

The following cranes, hoists and monorails from Table 1 are excluded for the reasons indicated.

(2) This information is contained in PPsL's first report submitted to the NRC on June 22, 1981.

Pace 2 of 9

a. 1H201, Refueling Platform Fuel Grapple - The fuel grapple has a maximum design capacity of 1200 lbs. which is roughly the weight of one fuel bundle and its handling tool. Because a heavy load is defined as "a load whose weight is greater than the combined weight of a single spent fuel assembly and its handling tool ," this hoist is exempted from analysis. In addition, the platform is designed such that 1) "no single probable event< electrical or mechanical, shall result in the loss of control of the load on any hoist (4) ," and 2) "all

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parts of the crane lifting system are designed to have a minimum factor of safety of 5, based on the ultimate strength

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of the material used with capacity load on all hoists, the bridge at rest, moving, or stopping

b. 1H203, Refueling Platform Auxiliary Hoist The auxiliary hoist has a maximum design capacity of 1000 lbs. with a load cell controlled lifting limit of 450 lbs. As defined by NUREG-0612, this is not a heavy load. Additionally all design fea-tures described in "a" above apply.

c. 1H214, Refueling Platform Auxiliary Trolly Hoist The auxiliary trolly hoist has a maximum design capacity of 1000 lbs. with a load cell controlled limit of 450 lbs. As defined by NUREG-0612, this is not a heavy load. Additionally, all the design features described in "a" above apply.

d. 1H211, Refueling Jib Crane The refueling jib crane has a maximum design capacity of 1000 lbs. As defined by NUREG-0612, this is not a heavy load.

e. 1H212, Channel Handling Boom The channel handling boom has

.a maximum design capacity of 200 lbs. As defined by NUREG-0612, this is not a heavy load.

f. 1H213, Reactor Building Crane Auxiliary Hoist The auxiliary hoist has a lifting capacity of 10,000 lbs. and is used pri-marily for reactor vessel servicing. Table 2 "Reactor Vessel Servicing Equipment" is a listing of all servicing equipment which the auxiliary hoist may be used to lift. Of the loads listed on Table 2, only the following had weights which class-ified them both as a heavy load and within the 10,000 lb.

capacity of the hoist.

1. head holding pedestal 1450 lbs.

2. service platform 6000 lbs.

3. dryer/separator sling 3500 lbs.

4. stud tensioner 2500 lbs.

5. head strongback 8,700 lbs.

(3) Reference NUREG-0612, Section 1.1.

(4) Reference General Electric Purchase Specification, Doc. No. 21A1976 Revision 4. SEE ATTACHMENT B.

Page 3 of 9

Each load was evaluated to determine whether new fuel or spent fuel could be damaged, or whether spent fuel could be uncovered by a potential load drop for any of the above loads.

The results are as follows:

head holding pedestal The head holding pedestal is permanently located on the refueling floor of building. It is used to support the reactor the'eactor pressure vessel head when the head is removed from the pressure vessel; this precludes any movement of the pedestal when the core is uncovered.

2; service platform The service platform is stored on the refueling floor and placed around the reactor pressure vessel when servicing or maintenance is required on the vessel internals. The working plat-form is one piece supported by box beam that encircles the vessel when in use. The physical size and con-struction of the platform prevents it from damaging fuel or causing fuel to be uncovered in the unlikely event it was dropped on the reactor vessel. (The diameter of the service platform is approximately 22 feet).

3~ dryer/separator sling The dryer/separator sling is used exclusively with the reactor building crane main hoist which is single failure proof (see Section 2.2.3).

The auxiliary hoist. may be used to remove and return the sling from storage; but, it, is not used during any lifts of the dryer or separator. In removing the sling from storage, it does not travel over either the vessel or the spent fuel pool.

4. stud tensioner The stud tensioners for the reactor pressure vessel are handled over or near the reactor pressure vessel only when the head is in place. They are not used at any time when the head is removed; therefore, this precludes dropping a tensioner into the reactor vessel and damaging fuel.

5. head strongback The head strongback is used exclu-sively with the reactor building crane main hoist which is single failure proof (See Section 2.2.3).

The auxiliary hoist may be used to remove and return the strongback from storage; but, it is not used during any lifts of the strongback. In removing the strong-back from storage, it does not travel over either the vessel or the spent fuel pool.

In the vicinity of the spent fuel pool, two loads may be handled by the auxiliary hoist; they are the temporary covers for the spent fuel pool and,

2. new fuel Page 4 of 9

The temporary covers for the spent fuel are in place to protect the spent fuel pool and facilitate keeping the spent fuel pool clean. The covers will be removed prior to storing fuel. Once fuel is loaded into the fuel pool, the covers will remain off. The covers weigh approximately 200-300 lbs.,

The new fuel handled by the auxiliary hoist will be moved from the new fuel receiving area, to the inspection area and into the new fuel storage vault. This move will be controlled by a crane load handling procedure along specified load paths. The new fuel will not travel over the spent fuel except when handled by the refueling platform fuel grapple.

g. XHXXX, temporary hoist (mounted on the reactor building crane platform). This temporary hoist has the capacity of 40,000 lbs.,

the purpose is to access the valve/filter pits by removing the shield plugs in the refueling floor. The hoist will be mounted only when needed to remove these shield plugs. At all other .

times it will be stored. 'The lift of each shield plug will be.

controlled by a load handling procedure along specified load paths. The shield plugs will not travel over the spent fuel storage pool or the reactor pressure vessel. In addition, the shield plugs will not pass over any nuclear safety related equip-ment required to shutdown the plant or remove decay heat.

2.2.3 Sin le Failure Proof Handlin S stems Statement of Requirement:

Identify any cranes listed in 2.2-1, 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 al-ternative or additional design features). For each crane so evaluated, provide the load-handling-system (i.e., c ane-load-combination) information specified in Attachment 1 to the "Request for Additional Information on Control of Heavy Loads."

Interpretation:

None required.

Statement of Response:

The following is in direct response to the requirements of Attach-ment 1 of "Request for Additional Information on Control of Heavy Loads'! (See Reference (1) on page 1 of this report):

1. Statement of Requirement:

Provide the name of the manufacturer and the designated load (DRL). If the maximum critical load (HCL), as defined in NUREG 0554, is not the same as the DRL, pro-vide this capacity.

Statement of Response:

The Unit 1 reactor building, crane for Susquehanna SES was manufactured by Harnischfeger Corp. The reactor building crane was sized such that the design rated load (DRL) would be the maximum critical load (MCL) of 125 tons. Thus, DRL = NCL = 125 tons capacity.

Dago 5 n<

2. Statement of Requirement:

Provide 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 spec-"

ified 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 alter-native to demonstrate its equivalency.

1/ 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-ASB9-1, please reference the date of the staff's safety evaluation report or approv-al 1'etter in lieu of providing the information requested by item 2.

Statement of Response: .

The Unit 51 reactor building crane for Susquehanna SES has been approved by the NRC staff as satisfying BTP-ASB9-1.

The following excerpt was taken from the Safety Evaluation Report for Susquehanna SES Units 1 and 2, NUREG 0776,

p. 9-5, dated April 1981:

"Based on our review, as described above, we conclude that the fuel handling system meets the requirements of General Design Criterion 2 with respect to protec-tion against natural phenomena, and General Design Criterion 51 as it relates to adequate safety under normal and postulated accident conditions.

Also, based on our review we conclude that the Unit 1 reactor building (cask handling) crane is designed in accordance with our Branch Technical Position ASB9-1. In meeting the above criteria the applicant complied with the guidelines of Regulatory Guide 1.13 therefore, conclude that the fuel handling system 'e, is acceptable."

3. Statement of Request:

With respect to the seismic analysis employed to demon-state that the overhead handling system can retain the load during a seismic event equal to a safe shutdown earthquake, provide a description of the method of analysis,

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the assumptions used, and the mathematical model evaluated in the analysis. The description of assumptions should include the basis for selection of trolley and load posi-tion.

Page 6 of 9

Statement of Response:

The Unit 51 reactor building crane was analyzed by Harnisch-feger Corp., the manufacturer, for qualification as Seismic Category I. A description of the analysis is provided in Attachment C. An analysis for concurrent seismic and hydro-dynamic loads presently is being made. A report on this analysis is not available at this time.

4.. Statement of Requirement:

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.

Statement of Response:

The permanent lifting devices for most of the Heavy Loads in NUREG 0612, Table 3.1-1, (3) BWR-Reactor Building, as yet have not been obtained. Those lifting devices which have been obtained,aie discussed below.

Lifting devices are classified as either (a) special lifting devices, or (b) lifting devices which are not specially designed. "Lifting devices which are not specially designed" is taken to mean lifting arrangements consisting principally of slings attaching the load to the hook of the hoist.

"Special lifting devices" is taken to mean lifting devices involving more than simple slings.

S ecial Liftin Devices The loads in NUREG 0612, Table 3.1-1, (3) BWR-Reactor Building, for which special lifting devices have been provided are the reactor vessel head, the steam dryer, and the moisture separa-tors. Each of these components and its lifting device is supplied by General Electric Co. General Electric Co. is presently preparing an evaluation of the lifting devices for these Heavy Loads for compliance with ANSI N14.6 1978 "Standard for Special Lifting Devices Weighing 10,000 lbs or More for Nuclear Materials". The evaluation will be amended to this report when it is'ompleted (no later than Jan. 1, 1982).

Liftin Devices that are not S ecially Desi ned The load in NUREG 0612, Table 3.1-1, (3) BWR-Reactor Building, for which a lifting device that is not specially designed has been provided is the vessel service platform. This component and its lifting device is supplied by General Electric. General Electric Company is presently preparing an evaluation of the lifting device for the vessel service platform for compliance with ANSI B30.9 1971 "Slings". The evaluation will be amended to this report when it is completed (no later than Jan. 1, 1982).

5. Statement of Requirement:

Provide an evaluation of the respect to the guidelines of interfacing lift points with NUREG 0612, Section 5.1.6.

Page 7 of 9

Statement of Response:

The guidelines of NUREG 0612, Section 5.1.6 for interfacing lift points call for a factor of safety with respect to the ultimate strength of five times the concurrent static and dynamic loads for redundant lift points, and ten times the concurrent static and dynamic loads for non-redundant lift liftlift points. A, point system is considered redundant if a single point failure will safely retain the load. For the Heavy Loads in NUREG 0612, Table 3.1-3, (3) BWR-Reactor Building, lift point redundancy and lift point safety factors are tabulated below.

The design of interfacing many of the "Heavy Loads" does lift points on lifting devices for not meet the guidelines of NUREG 0612, Section 5.1.6. No standards or guidelines for interfacing lift points were available at the time these lift-ing devices were designed. A summary of the lift data is provided in Attachment D as an alternative to the point design requirements of Section 5.1.6. Interfacing lift point infor-mation for General Electric supplied components is contained in Attachment E.

2.2.4 Other Overhead Handlin S stems Statement of Requirement:

For cranes identified in 2.2-1, above, not categorized according to 2.2-3, demonstrate that the criteria of NUREG 0612, Section 5.1, are satisfied.

Interpretation:

None required.

Statement of Response:

There are no cranes which are evaluated under this category.

2.3 S ecific 'Re uirements for Other Areas NUREG 0612, Section 5.1.5, provides guidelines concerning the de-sign and operation of load-handling systems in the vicinity of equipment or components required for safe reactor shutdown and decay heat removal. The information supplied in this section is intended 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 con-tinued 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 these safety-related functions.

2.3.1 Exclusion of Overhead Handlin S stems in Other Areas The remaining sections of this report does not follow the format of the "Request for Additional Information on the Control of Heavy Loads" because in the final evaluation of those cranes hs identi-fied in Section 2.1, Table 1, part B of our first report submitted on June 22, 1981) of concern, it has been determined that load drops will not impact safety related equipment or that load drops will not prevent safe reactor shutdown or prohibit continued decay heat removal.

Page 8 of 9

The cranes that had been identified as potential problems in other plant areas are listed below along with the justification for elimi-nating the crane from further review:

l. OH501 A,B,C and D, diesel generator building crane These cranes (one per diesel)'ravel over portions of the diesel generators and'everal associated components. The cranes are used to move heavy loads only during and in preparation for maintence. = In view of the controls provided by the Technical Specifications, the principle of divisionalized equipment is considered as a hazard elimination category for these handling systems., For example, if a Technical Specification allows one diesel to be declared temporarily imperative, administrative controls will ensure main-tenance be performed on that diesel only; system redundancy will preclude the loss of capability to shutdown the reactor and main-tain it in a safe condition.

4

2. 1H205, recirculation pump monorail hoist - The hoist moves in close proximity to the Hydraulic Control Units (HCU). A detailed review, including physical dimensions of all loads, determined that there are no heavy loads moved during plant operation that could impact the HCU's if the load were dropped. Heavy loads which could impact the HCU's (i.e. recirculation pump, recircula-tion pump stator and recirculation pump rotor) are only moved during plant maintenance periods.

3. 1H209, ECCS pump removal monorail hoist Hoist traverses near MCC 1B226, a power supply for Residual Heat Removal and Core Spray motor operated valves, and 1D264, a power supply for por-tions of the High Pressure Coolant Injection System. For an impact to occur when using this crane, the load must, swing later-ally 3 to 4 feet to strike cables running along the wall. The implementation of a load handling procedure will insure safe load handling. In addition, in view of the controls provided by the Technical Specifications, the principle of divisionalized equipment, is considered as a hazard elimination category for this monorail hoist.

4~ 1H210, Core spray pump and cooling water heat exchanger hoist This hoist travels over the Reactor Building Closed Cooling Water Heat Exchanger, which is located between raceways which feed to the Emergency Service Water Transfer "A" and "B" electrical sys-tems. Heavy loads in this area are only handled during mainte-nance periods.

5. 1H219, Reactor Building equipment access door monorail hoist-The end stop for this hoist places loads in close proximity to a lE raceway (E1PH81) that 'Contains cables for the Resi'dual Heat Removal Reactor Head Spray Isolation Valve, High Pressure Coolant Injection Inboard Supply Isolation Valve and Core Spray Pump (1P206A). The raceway runs vertically up a wall at the end of the monorail track. The end stop will be relocated to maintain a distance of approximately 8 feet; this will preclude any pos-sible impact.

6. 1H403 (5) , main steam relief valve removal hoist These hoists are located in the primary containment and cannot be accessed except during shutdown. They are used exclusively to remove the mainsteam ~ relief valves; this maintenance task can only be performed during cold shutdown and will not impact decay heat removal.

(5) Also hoists 1H404, 1H406, 1H407, 1H408 and an additional 14 hoists cur-rently being purchased for valve removal.

Page 9 of 9

Tabl Tabulation of Overhead lin Systems on the Refueling Floor (ELEV. 818')

Equipment Equipment Type Capacity Remarks Number Name (lbs.)

18201 Refuel Platform hoist 1200 (Fuel grapple hoist) Load cell limits lifting capacity to 840 to 1060 lbs. dependent upon position.

11I203 Refuel Platform hoist 1000 (Auxiliary hoist) Load cell limits lifting capacity to 400 + 50 lbs.

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trolly cell limits lifting capacity to V

1H214 Refuel Platform hoist, 1000 Load 400 +

50 lbs.

1H211 Refueling Jib crane, boom 1000 Crane lH212 Channel Hand-. hoist, boom 200 ling Boom 1II213 Reactor Bldg. crane, bridge 250,000 (Main hook)

Crane lH213 Reactor Bldg. crane, bridge 10,000 (Auxiliary hook)

Crane XHXXX Reactor Bldg. hoist 40,000 (Auxiliary hoist) Temporary hoist; to be Crane used for lifting floor shield plugs

Table 2

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~] P VEISEf.t'SI!I~i I'EAnOR a, L'jil i'0 E UIPHENT DOCUIIENT REVISION PART NO. thPPROXDIATE

'h I'.IGIIT (LBS . )

Blade Guide IF 131510 0301 N/A 145-180 8856-Ifl-F20-3-1 FF 131510 2301 8856-Hl-F20-23-6 Shroud Ilead FF 131010 0601 36 Bolt IJrench 8856-Hl-F19-6-1 Ilead Ilolding Pedes tal FF 131010 1801 N/A 1450 (0-ring shelf, pos t, 8856-Hl-F19-18-1 gusset, base plate, pcdesta plat'op L

pad, pedestal)

Ilcad Nut & FF 131010 2301 Masher Rack 8856-Hl-F19-23-4 Ifead Stud Rack FF 131010 2401 163.12 8856-Hl-F19-24-3 Steam Line Plug FF 131010 2501 $ 20 8856-Hl-F19-25-2

REACTOR VESSEL'~SLkVICX O;CIIUII>lIW14: j:b.fj'i ([L ':.'" It '2 EQUIPHENT DOCK IENT REVISION PART NO. APPROZIHATE WE1GiiT (1.BS.)

'F Instrument Strongback PF 131510 0101 2 N/A 300 8856-Hl-F20-1-2 I Control Rod Guide 131510 0201 N/A Tube Grapple 8856-Hl-F20-2-3 Peripheral Orifice FF 131510 0401 N/A 120 Holder 8856-Hl-P20-4-3 350'fully loaded) 1'uel Bail Cleaner FF 131510 0601 N/A 50 8856-Hl-P20-6-1 Control Rod PF 131510 0801 N/A 74 L:ltch Tool 8856-Hl-F20-8-1 PF 131510 2501 8856-Hl-P20-25-2 Fuel Support Grapple PF 131510 0901 N/A 87 (c.r.

8856-H1-F20-9-1 v/dravn)

PF 131510 2401 147 (c.r.

extended) 8856-Hl-F20-24-6

6 VR~t REACTOR VESSEd SER'

! i I'z rqvxpiii'ENTRE i

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II I

P, 1%NUIPI fHNT DOCUHENT REVISION PART NO. APPROXIHATE

~i(RYGllT ~LBS.

Grid Guide FF 131510 1001- 3 N/A 32 8856-Hl-I'20-10-3 I Peripheral Orifice FF 131510 llol N/A 30 Grapple 8856-Hl-F20-11-2 In-Core Guide FF 131510 1201 N/A Tube Seal 8856-Hl-1'20-12-3 Control Rod Grapple FF 131510 1301 N/A 17 46 8856-Hl-F20-13-1 1F 131510 2701 8856-Hl-F20-27-3 Control Rod Guide FF 131510 1501 55 Tube Seal 8856-Hl-F20-15-2 Peripheral Fuel FF 131510 1601 N/A 16 Support Plug 8856-Hl-F20-16-3

<r REACTOR VESSEL SERI/CCIlC L UTLllKET ~ i 7

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~ S EQUIPHENT DOCUHENT REVISION PART NO. AP PROX PilATE HETGIIT (LBS.

Instrument FF 131510 N/A 65 70 Ilandling Tool 1801'856-Hl-F20-18-1 FF 131510 2101 8856-Hl-F20-21-1 Fuel Bundle Grapple 761E219 400 Steam Plug F19-E012 182 Installation Tool (Based on shipping wt.)

Service Platform F19-E010 6,000 (service platform (Based on shipping wt ~ )

support, Inc.)

Dryer/Separator Sling IOH 378 3,500 (sister hook, hook box, 8856-Hl-A41-94-2 hook pin, pin insertion tool, actuating cylin-der, socket pin, con-trol box, drill gig, hose, clamp)

Ilead Strongback F19-E009 8,700

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ATTACHMENT A

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-NUCLEAR TRAINING INSTRUCTION NTI-gA 3180 Rev. A, 8/10/81 SUSQUEHANNA CRANE. OPERATOR CERTIFICATION TRAINING PROGRAM Pa e 1 of 4 Senior Instructor Originating Manager Title Signature Pevie;ving "nd Concurring.Manag rs-".

Title Signature Sinai iat Ure Supervisor-Tech. Trng.

Supervisor-Trng. Sup. Serv.

Supervisor

'. of Maint.

A,ppf OYBd

l. 0 PURPOSE This instruction delineates the crane operator 16 certification training program at Susquehanna SES.

2. 0 . SCOPE This instruction applies to. all personnel who operate cab, romote or floor operated cranes 1'ted in Attachment A.

NDI-QA-3180 Rev. A, 8/10/81 Page 2 of 4

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3. 0 REFERENCES 3;1 ANSI B30.2.0 - 1976 and Gantry Cranes"

'Ovexhead 3.2. NUREG-0612 "Contxol of Heavy Loads at Nuclear Power Plants" 3.3 Darrell G. Eisenhut letter of December 22, 1980 "Control of Heavy Loads" 4- 0 DEFINITIONS 4.1 Certified crane 'operator The term used to indicate that the particular person has completed the required training and meets the physical re-quirements to be a crane operator.

4.2 Qualified c ane operator A person has been certified and then evaluated by the appropriate supervisor, and is accepted by the supervisor to be a crane operator.

0 RESPONSIBILITIES 5.1 .Manager - Nuclear Training shall be xesponsible for providing crane operating certification training to crane operators prior to crane operation.'.2 Superintendent of Plant Susquehanna Shall be responsible to insure only qualified personnel pexform crane operation.

5. 3 First Line Supervisors shall be responsible to:

5. 3.1 Identify the need for qualified crane operators.

5. 3.2 Submit a training request to the Nuclear Training Group to have operators trained prior to assigning them to crane operator duties.

5.3.3 Have periodic evaluation conducted on all -crane operators to ensure they are still qualified for the specific crane, they are operating.

5.3.4 Disiminate any modification or change notices to'the crane operators and ensure they read and sign off as read the notices.

6 0 INSTRUCTION 6;1 Training for crane operators of cab/remote operated cranes.

6.1.1 Training shall be provided to individuals as required to supplement previous experience and training prior to assignment as a crane operator.

6.1.2 Training should include the following topics:

6.1.2.1 Instruction on the crane to be operated.

6.1.2.2 Instruction on proper rigging and crane operation.

, NDI-QA-3180 Rev. A, 8/10/81 Page 3 of 4 6.1.2.3 On-the-job training on the crane to be operated.

6.1.2.4 The effectiveness of this will be veiified by suc-cessful completion of a written exam. Passing shall be 70%. Documented on Nuclear Training Form NTI-QA-3180 B.

6..1.3 Perform a practical operating examination which will be docu-mented on Poxm NTI-QA-3180 A.

6.1.4 Physical qualification of crane operators and operator trainees.

6.1.4.1 Hive vision of at least 20/30 Snellen in one eye and 20/50 in the other, with or without corrective lenses.

6.1.4.2 Be able to,distinguish .colors, regardless of position of colors, tion.

if color differential is xequired for opera-6.1.4.3 Hearing, with or without hearing aid, must be adequate for a specfic operation.

6.1.4.4 Have sufficient strength, endurance, agility, coordina-tion and speed of reaction to meet the demands of equip-ment operation.

6. l. 4.5 Evidence of. physical, or emotional inst'ability which could rendor the operator a hazard to himself or others, or which in the opinion of the examiner could interfere with the operator's safe performance may be sufficient cause for disqualification.

6. l. 4.'6 Eviaence that an operator is subject to seizures or loss of phvsical con"rol shall be sufficient reason for dis-qualification.

6.1;4.7 This shall be oocumented on Form and attached to Nuclear Training Form NTI-QA-3180 B.

6.2 Operators of floor operated cranes shall pass a practical opexating examination. Qualification shall be limited to the cranes listed in Attachment A, and documented on Nuclear Training Foxm NTI-QA-3180 A.

6-3 Personnel with previous experience can be waived from, portions or all of the training by utilizing Training Program Waiver Form, O'TC-GA,- P-~ +

6. 4 Requalification 6.4.1 A vision examination shall be performed annually. .Documented on 6.4.2 Description of any crane modifications which effect operation of the crane will be distributed to personnel qualified on the parti-cular crane by'he'.appropriate first line supervisor. This will be documented by a sign off sheet Nuclear Training Form NTI-QA-3180C to be forwarded with a copy of the change to the Nuclear Training Group for incorporati*on into the records system.

7. 0 RECORDS 7.1 Form NTI-QA-3180A, when completed, will be attached to Nuclear Training Form NTI-QA-3180B and entered in the employees training record.

NDI-QA-3180 Rev. A, 8/10/81 Page 4 of 4

'I 7.2 Form NTI-QA-3180 B will be entered in employees training record with a copy to the supervisor.

7.3 Form NTZ-QA-3180 C will be entered in the employees training record.

NTI-QA-3180 Rev. A, 8/10/81 r

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Page 1 of 1 T

ATTACHMENT A C

CRANES REQUIRING QUALIFIED OPERATORS Cab/Remote Operated

1. Reactor Building Crane (1H213)

2. Turbine Building Crane "A" (OH102A)

Floor crated

1. Refueling Platform Fuel Hoist (lH20)

2. Recirculation Pump Hoist (1H205)

3. HPCI, RCIC, MR Pumps and Turbo.ne Horst (lH209)

Core Spray Pump and Cooling Mater Heac Exchanger Hoist (1H210)

5. Refueling Jib Crane (1H211)

6. Reactor Building.Ecuipment Access Doo Hoist (1H219)

7. Drywell Main Steam Relief Valve Removal Hoist

8. Diesel Generator Bridge. Cranes (OH501 A, B, C, 8,D)

Nuclear Training Form NDI-QA-3180 A Rev. 0, 8/10/81 Page 1 of 1 CRANE PRACTICAL EXAM Trainee Date Conducted By Position Crane Floor Descri tion of Move Main 8oist/Lift Aux. Hoist/Lift (As Applicable),

Bridge Movement (As Applicable)

Trolley Movement (As Applicable)

Other

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Nuclear Training Form

. NDX -" QA -, 3180 B

,Bpv. 0, 8/10/81 Page 1 of 1 CBPPE QUALXFXCATZON AND CERTXFXCATXON DOCUMENTATXON Operator Employee I

1. Eye Exam Sheet Attached

2. Rigging Lecture Date

3. Crane Lecture Date

4. Practical Examination attached.

Date

5. written Examination Pass Date Score Pail This, certifies the above operator has satisfactorly completed all required tiaining.

Nuclear Training Group The above operator has been. observed in operation of this specfic crane and is qualified to operate this specific crane.

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Section Head or Designee

c. c.: First Line Supervisor Operator

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Nuclear Training Form NTX-QA-3180C Rev. 0, 8/10/81 Page 1 of 1 SIGN OFF SHEET The attached changes/modifications have been incoxporated into crane. Read the changes and sign and date below.

Changes Date Changes Date Changes Date I acknowledge having read and undexstand the attached changes.

Name Date

0 ATTACHMENT B ALVISIOt'TATUSSHEET 21Al976 REV.

0 E !! E II A L O': EI.ECTHtC 236X350 PZG) &2 APPLICATIOII NUCLEAR EHBRGY OIYISlott G

SPECIFICATIOtl QDRII>II!IG QOTIICII TYPE PURC!IASE SP" CIF! GATI 0'I ~

QX OOCU!.IEt! T TITLE PLATFORM, REFUFI.ING (DUAL), G!;4EPJIL FJ'.QUIREI IEN fS QL gyp'ans.7&

- DE>BOOTES Ch LilGE GeP ~ G-

'ic(- ~

R E YISIO>MS tch 0 Control issue.

tr 1 1 Pet ECH hE 3"2cl . Gen>eral Occur..ent Change. Revisicns too extensive to be i den ti fi ed on the docur!ent. SUSQUEHANNl> SES

, AU6 3 19< ER 100450 pr Per ECH HE 38397.

12, and 18 affected.

Paces 3, 8, 9, Revisions ll FILE No. P identified with a spade (,>).

Y""/!'!:.0

'er al p 3 ECH's NE 71197 and HE 73503.

Sheets 9,13,14,17, and 24 affected. HQCPfg ~D Revisions indicated by a'pade ( P,".).

~ ~~ 'OE013 197>.. MOV97 8 Checked By: W. Bruce. S>>'.n>-

~Ã OCT 0 41978,@>g r~E89809 746 A,.sl. C~y 115 CHKD BY: A.R. GC' 372 312 DESCRIPTION OF GROUPS PRltiTS TO

~AOE, >>T C HOL'IES / .s.r<:6 ~A C~

'~>'Ih!;Tt!Aq L g'//-0'- .

Y C!IANG SM JOSE LocATIoN @Ace No, l C

NCO G>)O > ~ -)Z>

0( f)4+k I j)/g

aaa OEN EPiA'L Qo, ELECTRIC DocUaacNT Hca 21A1 976. <<~ ~o 4 PACC NO.

C3

'ABLE OF CONTENTS

~Paraara N ~Pa e I. SCOPE 3

2. APPLICABLC DOCuffENTS, CODES, A<<D STAf<OARDS 3

3. DESCRI PTIOi<

4. REQUI REl1ENTS 5 4.1 Ambi ent Condi tions ~

5

4. 2 Fuel lloi s t 5 4.3 Auxiliary Hoists 5 4'. 4 Opera ti on 6 4.5 Design 6.

4.6 Fabrication 9

.7 <<aterials 25 INSPECTION AfiD TESTS 26

6. CLEA!lING PAIIITII!G/COATIllG, ANO PREPARATION FOR SflIPHEflT 29 6.1 Cl eaning 29 6.2 Painting 29 6.3 Preparation for Shipment 30 7, SUBHITTALS TO THE BUYER 30

C.

6LNERALELEGYRiC DOCUMENT No. 21A197G REV. No. 4 SHEET NO. 3

1. SCOPE

.1.1 This speci, ication defines the general functional and engineering requirements for the refueling platform for a boiling water reactor.

1.2 The work done by the Seller in accordance with this specification shall include all necessary design, development, analysis, drawings, fabrication, shop testing, inspection, and preparation for shipment of the refueling platform.

1.3 The Seller shall accept full responsibility for his work and for compliance with. this specification. Review or approval of drawings, data, or specifications by the Buyer with regard to general design and controlling dimensions, does not con-stitute acceptance of any designs, materials, or equipment which will not fulfill the functional or performance requirements established by the purchase contract.

2. APPLICABLE DOCUMENTS, CODES, AND STANDARD 2.1 The refueling platform described by this specification shall be designed, fabricated, erected, and inspected in accordance with the following documents to the extent specified herein.

2.2 General Electric Com an Documents 2.2.1 Su ortinL Documents

a. Process Specification - Inorganic Zinc Prime Coat - P50YP1238 2.3 Codes and Standards 2 .3.1 The following Codes and Standards of the issue in effect on the date of award of contract form a part of this specification to the extent specified herein.

a. American Institute of Steel Construction, Inc. (AISC)-

Manual of Steel Construction

b. American Society for Testing and f1aterials (ASTtl) - Standards

1) Part 2, Ferrous Castinqs; Ferro-Alloys.

2) Part 3, Steel Sheet, Strip, Bar, Rod, Hire, fletallic Coated Products.

(3) Part 4, Steel - Pressure Vessel, Forgings, Railway, Reinforcino Structural.

c. American Society of Mechanical Engineers (ASHE)

(1) Boiler and Pressure Vessel Code,Section IX, Helding qualifications.

d. American Melding Society (AHS)

(1) AHS D14.1 - Code for Helding of Industrial and Mill Cranes.

GEIST EAAI. Hajji ELECTRIC DO CVIA LN T Ng. 21 Al 976 PACC HO. 4 2.3.1

~ ~ (continued)

e. American National Standards Institute (ANSI)

(1) ANSI 83.5 Tolerances for Ball and Roller Bearings

,(2) ANSI Cl National Electrical Code Institute of Electrical and Electronics Engineers (IEEE) - Standards Publications 112A Test Procedure for Polyphase Induction Motors and Generators 113 Test Code for Direct-Current Machines

g. National Electrical Hanufacturer's Association (NEHA)

(1) NEViA Pub. No. IC1, Industrial Control Standard Publication (2) NE)N Pub. No. MGl, Motors and Generators Standards Publication

h. Steel Structures Painting Council (SSPC) Surface Preparation Specification (SP)

(1) SSPC-SP1, No. 1 Solvent Cleaning (2) SSPC-SP5, No. 5 White Metal Blast Cleaning

i. American Gear Manufacturer's Association (1) Gear Classification Manual.

Occupational Safety and Health Standards (OSHA)

(1) Part 1910.179.

3. DESCRI PT ION 3.1 The platform will be used for refueling operations in a nuclear power plant.

Fuel and other reactor components will be removed from the reactor core, trans-ported to the fuel pool, and then returned to the reactor as required. Fuel and reactor components are at all times handled remotely underwater.

3.2 The equipment to be furnished in accordance with this specification includes the following:

a. One platform complete with fuel hoist, hoist trolley and frame, bridge drive, all necessary controls and wiring, lights, limit switches, control panel, control consoles, and position indica-ting. system.

b. One 1000 lb. electrically operated, monorail mounted, motorized trolley, pendant controlled, auxiliary hoist.

c. One 1000 lb. electrically operated pendant controlled auxiliary hoist (to be mounted on trolley frame).

'. d. Air Compressor Any special tools required for erection, dismantling, and normal maintenance.

f. Miscellaneous platform mounted conduit, conduit fittings, power outlets, etc., as required for normal operation and as required by this specification.

0 E H E ll A L gl E LE C TB I C..

'ocuMc~v PAGC NO.

iso 21A1976 C3 REQUIREYiENTS 4.1 Ambient Conditions. The equipment shall operate as specified herein under the fo lowing ambient conditions:

a. Temperature: 60'F to 110'F

b. Relative Humidity: 12% to 100%; mean, 72%

4.2 Fuel Hoist. The fuel hoist shall meet the requirements of Table I.

TABLE I FUEL HOIST SPEED RANGE, LOAD, LIFT AND CABLE LENGTH RE UIREtiENTS I

JO'Dti c t Re uirement Hoisting Speed .1-40 fpm Pange'ift 50 ft (Wrap-up on drum)

Cable Length: As required to reach the connection (on fuel grapple-supplied by others) which is 2'6" below the centerline of gimbal pins and to allow the fuel grapple to travel 46'6" plus two dead turns on drum.

Startup Load (Jammed load) 1200 lb Normal Hoisting 5 Lowering Load* 840 lb to 1060 lb Zero Load Hoisting 5 Lowering Load* 135 lb to 300 lb 4.3 Auxiliar Hoists. The auxiliary hoists shall meet the requirements of Table TABLE II AUXILIARY HOIST SPEED, LOAD, LIFT, AND CABLE LENGTH'RE UIREfPENTS 0 eration or'Com onent Re uirement Hoisting Speed (approximate) 60 cycle service 10 fpm and 30 fpm (dual) 50 cycle service 8 fpm and 25 fpm (dual) l1onorail tlounted Hoist Traversing Speed (approximate) - 60 cycle Service 30 fpm (Soft start and stop)

- 50 cycle Service . 25 fpm (Soft start and stop)

Lift 85 ft (Wrap-up on drum)

Cable Length As required -to extend 85 ft below operators cab floor Load Capacity 1000 lb As the hoist is raised or lowered, the load on the hoist cable changes in three discreet steps within the range of loads indicated.

P

GENEP4AL L~kl ELL:CTAlC 0

oocuM'Eeet No. 21A1976 REv, No. 4 PAGE t40. 6 4.4 0 eration 4.4.1 During refueling operations the main hoist, hoist drive and hoist controls shall be capable of continuously repeating the duty cycle shown in Figure 1, 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />

.per day for 60 days per year.

4.4.2 During refue'ling operations the bridge and trolley drives shall be capable of intermittent operation 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> per day for 60 days per year. Use of the bridge and trolley will occur between the duty cycle blocks shown for the main hoist in Figure l. Operation will consist of a random combination of starts, stops, and reversals at any speed between 1.6 ft/min and maximum speed. The maximum number of starts, stops, and reversals in any 27 minute cycle as defined by Figure 1 will.be as follows:

Starts Reversals

~2

~Sto s zm ~8 4.4.3 During the remainder of the year the platform will be used intermittently for a total period of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> in the manner described in Paragraphs 4.4.1 and 4.4.2.

4. 5 ~Des i n 4.5.1 The refueling platform shall be designed in accordance with the AISC Manual of Steel Construction.

4.5.2 Screw fasteners, pins and other devices used for connecting purpose shall be positively locked in place. Particular attention shall be paid to linkages, drive components and other devices which could come apart and drop into the reactor or affect the operation of the machine. The use of locktite or staking process is not permitted. The positive locking method shall be shown on drawings submitted for review. Omissions shall be cause for seller rejection of the design, 4.5.3 The platform shall be designed for a 40 year li'fe and shall provide that no single probable event, electrical or mechanical, shall result in the loss of control of the load on any hoist. Each hoist shall have two full capacity brakes so arranged as to ensure that either one will prevent an uncontrolled descent of the load. The Seller shall show that a failure between the brakes and the hoist drums is not a probable event.

4.5. 4 The entire refueling platform shall be under the control of a single opera-tor who shall at all times have an unobstructed view of the fuel at the end of the fuel hoist grapple (supplied by others) which extends down through the trolley frame.

4.5.5 Reactor Selector Switch. The control system and associated safety interlocks shall incorporate a key operated, two position reactor selector switch which will be used to permit the platform interlock logic to discriminate between two adjacent re-actors.

GEHEAAL (j~T5 ELECTlllC e '

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oocUMl HT Ho, 21Al 976 Rcv. aeo. 4 AGF Ho. 7 4.5.5 The purchase part drawing indicates the critical dimensions and is a guide to the equipment desired, but does not necessarily indicate the best way to meet all the requirements of this specification. The Seller shall retain full responsibility for the design of the equipment to meet the requirements of this specification.

4.5.7

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Id

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Safety Factor. All parts of the crane lifting system shall 'be designed

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to have a minimum factor of safety of 5, based on the ultimate strength of the ma-terial used with capacity load on all hoists, the bridge at rest, moving, or stopping.

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4.5.8 Platform Loads.

d.'.I.l ~TI I I I . Tl b ldd bly h 11 b d lb d 1>>1th I d formly distrsbuted static load of 50 lb/ft2 of treadplate due to personnel and equipment, in addition to dead weight. The maximum deflection of any girder section under these loads shall not exceed one three-hundredth of the span.

b'd 4.5.8.2 dead weight

~The su of h~il erstructure.

d the beams and The maximum th 1 lb trolley shall deflection of the superstructure 1 pl hp not exceed one t dl 1 when did five-hundredth of the span. The calculations shall be based on the rail span. When the hoist brakes from full to zero speed, the maximum dynamic deflection shall not exceed the sta-tic deflection by more than 50 percent, The superstructure shall be capable of withstanding an acceleration of 3.0g horizontal and 2.0g vertical without causing

'permanent deformation of the structure. The platform structure shall be designed s r~

to have the dynamic characteristic that its natural frequency at first mode is at or greater than 10 Hz.

4.5.8.3 Calculations. All calculations and sizing of all structural members shall be based on a span as defined in 4.5.8.2. The primary stresses due to horizontal (3.00) and vertical (2.0) seismic loads shall be considered to act simultaneously and shall be added directly, The combined stresses, due to seismic load and other live and dead load, shall not exceed 150 percent of the code allowable stress defined by AISC.

4.5.9 Seismic hfotion. The platform shall notyslide off the tracks or overturn due to a seismic acceleration of 3.0g horizontal and 2.0g vertical.

4.5.10 Auxi 1 i ar Hoi sts Li ft Limit 4.5.10.1 To preclude the possibility of raising radioactive materials out of the water, the cables on the auxiliary hoists shall incorporate an adjustable, remov-able stop which will jam the hoist cable against some part of the structure thereby preventing hoist rotation when the free end of the cable is at a preset distance below water level.

4.5.11 Hain Fuel Hoist Lift Limit. The main fuel hoist grapple geometry is such that it cannot be hoisted vertically out of the water. However, it can swing

( out of the water if the fuel grapple comes in contact with the fuel pool wall.

To limit this swing, a removable bar shall be placed across the open end of the operator cab floor. The bar.and operator cab structure shall have sufficient strength to stall the bridge drive motor thus preventing further bridge movement.

GENERALELECTRIC , ~

DOCUMENT No. 21A1976 REv. No. 4 sREET No. 8 4.5.12 Brid e Drive. The centrally-located bridge drive shall consist of an electric motor, se f-contained gear reducer, and brake. The cross shaft shall be connected to two of'the bridge wheels. If a chain drive is used, the drive sprockets on the cross'haft shall be positively restrained to prevent axial movement along the shaft. A sprocket with a screw restrained tapered bushing shall not by itself be considered as positive restraint. The bridge drive machinery shall be located below the floor plate and above a readily removable drip pan to prevent contamination of the. water. The deck plate directly above the bridge motor shall be readily removable for motor maintenance.

4.5.12.1 The cross shaft shall be supported at frequent intervals along the bridge in permanently mounted, sealed, self-aligning roller or ball bearings re-quiring no additional lubrication.

4.5.12.2 Sleeve type couplings shall be used to facilitate handling and maintenance of the drive unit, and wherever couplings are required.'.5.

12.3 The bridge shall be capable of a safe, vibrationless stop within 2 seconds from full speed. The decelerating force on the superstructure shall not exceed 1/18 g. This may be accomplished by incorporating a dynamic braking sys-tem, however, the bridge drive shall also include a magnetically operated fail-safe brake.

4.5. 12.4 The motor shall be capable of driving the platform either forward or reverse at any speed over a minimum controllable speed range of 30:1 up to the maximum speed forward or reverse.

4.5.12.5 The bridge shall be capable of moving either forward or reverse at the speed from 1 to 50 fpm or faster.

4.5.13 Platform Power Su 1 . Cable reels shall be mounted on the inside of the platform to bring power and telephone wires to the platform. The reel will place the power cable and telephone wires flush with the floor. Both the cable and wires shall have a minimum extended length of 80 feet. The power cable con-sisting of four conductors (12 A"!G), with ten additional conductors (18 RIG) shall be mesh shielded, neoprene or hypalon jacketed and shall be terminated into a NS3106A-32-13P connector. Telephone wir es shall be Belden 8723 or the equivalent and shall be terminated into a MS3106A-18-19P connector. Both above connectors shall have their mating. receptacles included in the supply scope. A 40-foot ex-tension cable of the same configuration as the power cable and communication cable with matching connectors at each end shall be provided.

I 21A1976 sH. No, 9 NUCLEAR ENERGY DIVISION REv. 4 4.5.13.1 At least six duplex outlet 115 v two-wire, three pole grounded "twist lock" receptacles shall be provided equally spaced along the front and rear of the platform. These outlets shall be on two separate 20 amp circuits with ground fault protection, wired inside conduit, and conforming to receptacles as manufactured by GE, t<o. GL-4700 or Buyer approved equivalent. In addition, on a third 20 amp circuit, with ground fault protection, two outlets conforming 6

to the above requirements shall be provided in the operators cab, one each on the rear corner posts located 4 feet above the cab floor.

4.5.13.2 All motors and other electrical equipment shall be grounded through a suitably sized ground wire which shall be included as a part of the power cable.

Maximum resistance to ground to be 2 ohms.

4.5.14 dti 3~bit Platform Railings.

y A permanently installed stainless stee'l railing extending dpi t hit b p idd. Th tp fi h continuous span of 2 inch schedule 40 pipe. Where pipe lengths are jointed by welding the ends shall be weld prepped and the weld ground flush with the pipe surface. The lib vertical IIembers shall be l-l/4 inch schedule 40 pipe welded into socket no greater than the 2 inch diameter which in turn shall be welded to the walkway structure. The span socket to socket shall not be greater than 5 feet. The intermediate horizontal members shall be l-l/4 inch schedule 40 pipe welded to the vertical members.

4.5. 14.1 Personnel openings to operator's cab shall be provided. Chain and

-suitable spri ngs clips shall be provi ded to close the opening.

4. 6 Fabri cati on 4.6.1 The refueling platform shall be fabricated in accordance with the AISC Manual of Steel Construction.

4.6.2 Welding methods and welder qualification shall be in accordance with the ASHE Boiler and Pressure Vessel Code,Section IX, or American We')ding Society Standard Specification "Code for Welding of Industrial and t'ai ll Cranes."

d b<<, ~yttyf 4.6.3 Brid e Trolle and Frame. Insofar as possible, the bridge superstructure hilb f 11 166 t The number of bolts or rivets located directly above the pool shall be minimized.

Where bolts or nuts are used, they shall be positively locked to prevent loosening.

Yeans other than locktite shall be provided. All lubricated parts that could be positioned above the pool shall be provided with drippans or other means to prevent lubricant from falling into the pool. Facilities for field welded assembly can be provided. Installation Instructions must be provided.

'1.6.3.1 ~TTT h 1. Th t lly>>h 1 d yt h hl'Ib d .16 d as to take adequate account of positioning accuracy and shall be such that the equipment could be operated on 408 ASCE rails if desired. If machined rails are required, such rails shall be made from 408 ASCE rails.

8 6 fJ 6 R 4 L (~Pj 6 L6 CT il l C .

DocvMENT No. 21A1 976 ftcv. uo. 4 s acL No 10 4.6.4 Platform Br~id e 4.6.4.1 Brid e structure. The bridge structure comprising the girders, end truck, drive units, etc., s a Me designed and fabricated as a complete integral structure with only such parts removable as required to facilitate erection, shipment and main-tenance. A ladder shall be provided on each end frame to permit access to the upper wa 1 kway.

4.6.4.2 Tread late. Tread plate shall be installed on the superstructure to pro-vide a wa,way extending along the'ength of the platform at the upper level and lower level.

4.6.4.3 Ilain irders. The two main girders and end ties shall be fabricated into a rigid one piece we ded structure. The gantry leg shall be fabricated into a unit weldment with gusset plates provided for field bolting or welding to the main girder.

All such bolt holes if used shall be reamed at final shop assembly.

4.6.4.4 pl when the turd End trucks.

trolley The end 1

trucks shall d-b is at either end of the platform.

i>>d be constructed to structural members and ig d ih d3.oh i 11 d 4.6.4.4.1 Rail wipers faced with a rubber sweeper shall be provided at the front and rear of each end truck.

4.6.4.5 Wheels. Thi. wheels shall be designed so as to take adequate account of the positionino accuracy requirements of this specification. The wheel design shall be such that the equipment could be operated on 40ff ASCE rails if desired. If;machined rails are required, such rails shall be made from 40/f ASCE rails. The drive wheels shall be match ground.

4.6.4.5.1 Stationary or rotating axles may be used, fitted with roller or ball bear-ings. The bearings shall be sealed, self-lubricated, and require no additional lubri-cation. Care shall be taken to prevent the leakage of lubricant.

4.6.4.6 Kick lates. Four-inch high kick plates shall be attached around the entire periphery of top ec on the platform walkway and trolley.

4.6.4.7 Refuelin interlock switches. Two three-position; momentary contact type limit switc es, G ype or engineering approved equivalent), shall be mounted on one end truck, each switch operating as a functional part of the control system. Switches shall be mounted approximately one foot apart and .be suitably pro-tected from external damage. The two outermost positions of these switches shall be designated "Refueling Interlock Switches lA and lB and 2A 8 2B" respectively.

V C)NLaltt.L'<<naiC DocUMENT No. 21A1976 nEv.No.

SHEET NO. 1 1 4'.6.4.8 Platform- transfer switch. Another limit switch with two non-overlapping snap acting contacts GE Type CR115G or engineering approved equivalent) shall be mounted on the same end truck as the switches specified in Paragraph 4.6.4.7. Each switch shall operate as a functional part of the control system and be suitably pro-tected from external damage.

4.6.4.9 Guide Rollers. Guide rollers shall be provided to regulate the direction of bridge travel on the rail. The guide rollers shall be capable of taking the load of the platform when 3.0g horizontal acceleration is applied. Therefore, it is recommended that both end trucks bo equipped wi th guide rollers.

4.6.5 Hoist Trolle and Frame 4.6.5.1 General. The hoist trolley and frame shall be a rigid, all-welded structure.

The troll~ey rame shall be attached to the trolley bolting or welding.

4.6.5.1.1 Mounted to the trolley frame shall be the control panel, hoisting units, including auxiliary hoist, and fuel grapple to which is attached the control consoles. Structural members at the bottom of the trolley frame shall be desiqned to withstand a uniformally static live load of 50 lb/ft2 and shall be held to a minimum to permit the operator maximum underwater visibility.

Switched fluorescent lighting, a cabinet for binocular storage, and a small writing table shall be provided in the operator's cab.

4.6.5.1.2 All parts of the trolley and trolley frame shall be accessible for in-spection or replacement. The intermediate and upper cab levels shall be enclosed with safety rails.

4.6.5.1.3 Splash proof metal covers shall be provided to enclose the fuel grapple hoist mechanism and all those mechanisms located at the top of the trolley frame parts of which enter the water below. The covers shall be designed to collect drippage from the cabling and minimize contamination of the trolley or platform structure. Drippans shall be designed so that- the collected water will not drain back to the pool.

4. 6. 5. 1.4 The trolley shall be capable of moving at speed 1 to 30 fpm.

4.6.5.2 Hoist sheave. A sheave shall be supplied over which the hoist cable passes. The sheave shall be designed for the maximum cable loading and incorporate a guard to prevent cable jump. A drop plate shall be provided to ~ii thstand full hoist load in the event of a sheave shaft bre'ak.

4.6.5.3 Fue') qra ole. A mount shall be provided for attaching a grapple (supplied by others . The additional dead load applied to the trolley as a result of the grapple shall be taken as 500'pounds.

4.6.5.3.1 A power winch shall be provided for stowing the fuel grapple when not in use.

GENF AALQd" ELECTHIC oocuMEN T No. 21A1976 nEv.wo. 4 SHEET NO.

4.9.5.9 Cleats. Four cleats of 1/2 inch bar shall be supplied, one on each corner support o~t e operators cab, for tying off'ight and small tools, etc. The cleats

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shall be mounted on the outside surfaces of the supports. In addition, a hook or ioount shall be supplied to which the control pendant can be attached to enable one handed operation of the controls.

4.6.5.5 Hoist trolley ower su~1 . An enclosed electrical system shall be used to supply power to tie oust tro ey. Power shall be brought to the trolley usinq a "power trak" arrangement.

4.6.5.5.1 Two electrical disconnects containing not less than 25 pins and suit-able for 125V and 5 Amps shall be provided between the trolley structure or elec-trical panel and grapple near grapple mount. One side of each disconnect shall be wired to the control panel and the other to the consoles.

4. 6. 5. 6 Hose reels . Reels shall be provi ded for the supply of air and electric power to the grapple, (supplied by others). The reels shall be mounted 'on the trolley frame approximately as shown on the purchase part drawing.

4.6.5.6.

~ ~ 1 The air line reel shall be such that it can handle two 150 psi g Gates 1/4 inch dual air hose or Buyer approved equivalent. Hoses shall terminate

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I/2B with "Pari er cata'log "l/4-20630-4-4-e, triple-lot swivel nut 37 degree cone fitting."

4.6.5.6.2 The air hose reel shall wrap 50 ft of hose on the drum with the free end of the hose connected 2-1/2 ft below the center line of the gimbal pins:. Air shall exhaust through a muffler to atmosphere. The reel shall. at all times be capable of maintaining a retrieving force on the air hose so as to ensure positive retrieval.

4.6.5.6.3 Separate reels and air lines similar to those previously specified are required for use with the frame-mounted auxiliary hoist and monorail-mounted auxi-liary hoist to supply air to a tool which, during operation, may be attached to the end of each. auxiliary hoist'cable. 'The drum shall have a capacity sufficient for an 85 foot lift, the total hose length shall be as required to extend 85 feet below the operator cab floor.

4.6.5.6.4

~ ~ ~ ~ The electrical reel shall be suitable for handling a 4 conductor elec-trical cable. Two conductors shall be suitable for 30V a-c, 10 amp service and the other two conductors shall be suitable for 30V a-c, 1 amp service. The cable shall be suitable for operation in demineralized water. The reel shall have a drum capacity of 50 feet. 'he cable shall have an electrical connector as specified on the purchase part drawing and a length sufficient to extend 50 feet below the platform track.

4.6.5.7

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connects. ~

Air lines. ~

Disconnects

'irto lines shall be be terminated wi th "Hanson" quick dis-Series 2HKlG equipped with elastomer II143 seals.

Hale Fitting - Catalog Number 2-KlG16 Female Fitting - Catalog Number 2-H1G16

,21A1 976 SH. NO. 13 OENF.AIL Qi':j LuLEI:TBliC NUCLEAR ENERGY DIVISION BEY. 4 C..)

4.6.5.7.1 Male fittings shall be attached to the hose supplying air when the solenoid operated air control valves are deenergized.

4.6. 6 Fuel Hois t 4.6.6.1 ~Sco e. The fuel hoist unit shall consist oi' variable speed motor, brakes, limit switches, hoist cable, speed reducer, drum, and any other equipment required to make a Workable unit in accordance with currently accepted practice and thi s speci fi cati on. The hois ting equipment shall be built into a compact, readily accessible unit supported on the hoist trolley.

4.6.6.2 S eed control. The hoisting unit shall provide regulated variable speed contro from 3 to 100 percent of full load speed either hoisting or lowering and shall incorporate regenerative braking which will provide rapid slowdown for speed changes. The hoist motor brakes shall set immediately whenever the position control switch is returned or passes through its neutral position.

If a motor reversal is called for, the motor drive shall berelease brakes will only when the adjustable voltage motor is capable of reversing the load. The an d-c system incorporating a General Electric Maxspeed motor-generator set. The system shall include an overriding, motor armature current limit in addition to any other features needed to meet the requirements of Paragraph 4.5.3. (No single probable event, electric or Ioechanical, shall result in the loss of'ontrol of the load on any h'oust.)

4.6.6.3 Bearin s. Sealed, lifetim,.high grade, antifriction bearings shall be used throug out the. hoist system. Means shall be provided to prevent the entrance of moisture into and emission of lubricant from the bearing housings.

Ball bearings shall have tolerances equal to or closer than ABEC-3; roller bearings shall have tolerances equal to or closer than RBEC-5.

4.6.6.4 Brake. An electrically operated, fail-safe, automatic brake shall be provided ~v~ch is sized to bring the hoist and load to a safe, vibrationless stop from full speed wi.thin approximately 2 seconds. The bral;e shall be capable of hOlding 150 percent of normal hoisting load when power to motor is cut off, or in case of complete power failure.

4.6.6.5 Limit switches. Adjustable limit switches shall be supplied as follows:

4.6.6.5.1 One switch shall interrupt hoist power and actuate a light labelled "Grapple Full Down" when the grapple hook is approximately 4 inches below the fuel bundle handle, i.e., approximately 54 feet below the platform. The light shall be located on the control console.

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sH.No. 14 GEHEIIAL Qi"cj ELECTBIC 21A1 976 NUCLEAR ENERGY DIVISION nev. 4 4.6.6.5.2 One normally closed switch (mounted on the grapple - supplied by others) requiring interconnection to the control system. The switches shall interrupt hoist power and actuate a light labelled "Grapple Normal, Up" when the grapple hook is approximately 8 feet. below the platform tracks. The light shall be located on the control console. To resum the hoist power and continue the hoist operation, a momentary contact override button shall be provided on the control 'console. Final stop shall occur when the grapple hook is approximately six feet below the platform tracks.

4.6.6.5.3 A third normally closed switch (backup over hoist swi tch mounted on the grapple - supplied by others) requires interconnection to the control -Asystem.

Nhen the switch is actuated, power to the hoist motor shall be cut off. con-venient connection shall be provided for field wiring of this switch.

grapple - supplied by others)

'ill 4.6.6.5.4 One be connected normally opened micro-switch (mounted on to two conductors in the cable specified in Paragraph 4.6.5.6.4.

The switch shall actuate a green light labelled "Hook Engaged" when the grapple hook is properly engaged to fuel bundle lift bai l. The light shall be located on the control console.

4.6.6.6 Hoist cable. Dual hoist cable shall be used on main hoist. Either one shall be capable of taking the full load. The hoist cable shall be waterproof lubricated stainless steel and of proper size to give a factor of safety of 5

.when fully loaded. Attached to the end of the cable shall be a stainless steel Tru-Loc fitting with a 3/4 x 10 UNC-2A thread with wrench flats or Buyer approved equivalent.

4.6.6.7 a

t~phgpllft.pl Hoist drum.

slack cable.

The drum and cable In lieu of this, means may be shall be so selected that the cable

<<lththd provided to maintain ttlggl the cable in the drum grooves. The drum shall be so designed that not less than 2 usable complete wraps of hoisting cable remain on the drum when the grapple hook is in the full down position. No overlapping shall occur when the grapple is lifted to its highest position, approximately 6 feet below the platform tracks.

4.6.6.7.1 The pitch diameter of the drum shall not be less than 28.5 times the diam ter of the hoist cable.

4.6.7 Motors 4.6.7.1 ~Dut . The bridge, hoist trolley, and hoist motors shall be selected to conform to et duty cycle, speeds, and loads specified.

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4.6.7.2 per NEt% ~

Enclosure. The motors shall be totally enclosed, nonventilated (TENV) f26 Type A, rated suitable for continuous 30 minute operation at the ambient conditions specified.

OENEIssP.I. Qi() ELECTRIC 21A1976 sH. No. 15 NUCLEAh EI'PEAGY DIVISION REV. 4 C 4.6.7.3 Overload rotection. All motors shall be provided with adequate over-load protection.

4.6.7.4 All motors shall reversible, of built especially fr crane Rotation. be type a

serv>ce.

4.6.7.5 Bearin . Sealed for life high grade antifriction ball bearings shall be used. n the latter case all grease openings shall be plugged and provisions shall be made in the structure to prevent lubricant leakage to the water or permanent platform structure below. Ball bearings tolerances shall be equal to or closer than ABEC-3; roller bearings tolerance shall be equal to or closer than RBEC-5.

4.6.7.6 ~Set s eed. All motors and controls shall be selected to maintain a set speed with a maximum error of 10 percent of set speed at any set, speed and load.

A.6.8 ~C1 S 4.6.8.1 ~Sco e. The control system shall include the hoist, bridge and trolley motors, the control panel, control consoles, all interlock switches, indicator lights, protective devices, wiring, interlocking and interconnected circuitry, and cabinetry which houses this equipment.

4.6.8.2 ~Seed ran e.. The bridge and trolley motors and associated controls shall be capable of providing a minimum controllable speed range, forward and reverse, of 30: l.

4.6.8 ~ 3 Aux',liar control e ui ment. All auxiliary equipment such as reversing controllers, starters, relays, fusible disconnects, a-c - d-c conversion units, etc., not required to be mounted directly on or near the driving unit or in the control consoles, shall be mounted in a control panel mounted on the trolley frame.

All such auxiliary control equipment shall be enclosed in a housing m eting the requirements of NEt1A IC 1-2.68 Type 1 (or better) and of suitable noncorroding construction to withstand the ambient conditions and radio-frequency requirem nts of this spe'cification. All auxiliary control equipment whose operation results in an uncomfortable level of airborne or structureborne noise shall be so de-signed or mounted as to reduce the noise level to a value which will not cause undue discomfort to an operator standing for extended periods of time in the cab.

For example, the cooling fan, if used, on the hoist motor shall be controlled by a thermostatic switch which will turn the fan off when hoist motor cools down and turn it on when motor is in operation.

21A1976 sH.No 16 8 E II F II A L Q$~R E LL 0 T II I ENERGY DIVISION I'OCLEAB nEv. 4 4.6.8.4 Control safety features. The control system shall include, as a minimum, the following safety features:

a. Thermal overload protection devices for all motors

b. Short circuit protection for each load component including lights and auxiliary a-c motor loads

c. Hain a-c power line disconnect switch with short circuit protection located convenient to operating personnel

d. N chanical interlocking of the control panel to prevent access while power is on

e. Under voltage protection

f. Hotor field loss protection

g. All switches that control the motion of any bndge, trolley or hoist shall be deadman's type as defined in HEHA IC 1-1.015.

h. Torque proving on main hoist motor.

4.6.8.5 Control circuitr . Solid-state circuitry shall be used wherever possible throughout the contro system for minimum size and to provide instant startup.

All components shall be adequately encapsulated to provide long life in the ambient conditions specified.

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4.6.8.6 Vibration isolation. The control components shall be adequately iso-lated from any amagi ng vi ration whi ch may occur duri ng operation of the platform.

4.6.8.7 Brid e-in-motion annunciator. A warning device such as a gong or horn shall be provided w ich shall actuate automatically and continuously whenever the bridge is in motion. An intermittent warning device is desirable and shall be mounted on one end truck.

4.6.8.8 Radio fre uenc filterin . Radio frequency (R.F.) filtering is required on the loa side of the power supply transformer as well as on all lines leaving the control panel to reduce externally radiated R.F. from the control equipment to a value which will keep pickup on type RG6 A/U (Hil spec. HIL-C-170 identification) coaxial cables 12 feet away below 0.2'mV. Assume each outgoing wire is 20 feet long and parallel to the coaxial cable. In addition to line filters, all external sparking devices such as commutators, motor brake contacts, etc., shall be adequately shielded to further minimize R.F. pickup below 0.2 mV. Shielded cable shall have a neoprene jacket or equivalent.

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21A1 976 sH.NO. 17 GEWERILL Qcj ELECTRIC NUCLEAR ENERGY DIVISION REv.

I 4.6.8.9 Control interlocks. The following interlock and indicator functions are to be incorporate within the control system. The interlocks shall be initiated over either reactor, (where a sensing device is provided by others, suitable pre-tagged wiring to the device shall be supplied to permit convenient field connection).

The relays associated with the reactor selector switch permit the control system to discriminate between reactors. See circuit schematics on purchase part drawing.

Circuit panel indication of block function shall be included.

a. Reactor selector switch. Bridge travel between adjacent reactors shall be blocked by acti vati on of the platform transfer swi tch as described in paragraph 4.6.4.8 to return bridge power and permit continued travel in the same direction it shall be necessary to turn a key in the reactor selector switch. This switching sequence shall apply to both forward and reverse bridge motion. (See interlock schematics on Purchase Part Drawing). The selector switch position which permits continued reverse travel shall be clearly and permanently marked "NORM". The position which permits continued forward travel shall be clearly and permanently marked "REAC2".

b. Fuel hoist n'ormal u interlock to stop hoist motor. Actuation is to be from a limit switch on grapple. (Supplied by others.) The hoist power can be resumed by an override switch as mentioned in Paragraph 4.6.6.~.2.

c. Fuel hoist refuelin interlock to cut power to fuel hoist motion when t e A contact of refue i ng interlock switch 1 or the "B" contact of refueling interlock switch 1, depending upon whi ch reactor is selected, and an external swi tch (supplied by others) actuate simultaneously.

d. Fuel hoist back-u overhoist switch to stop hoist motor. Actuation to be from a normally closed posi tion switch. Pretagged wiring from this swi tch to the console disconnect shall be provided.

e. Fuel hoist full down interlock to cut power to fuel hoist motor.

ctuation is to be from a imit switch.

f. Slack cable interlock to stop hoist motor. Actuation to be by switch on the fue Ioist load cell.

g. Fuel hoist overload interlock to stop hoist motor. Actuation to be.

by switch on the fuel hoist load cell. Fuel hoist load indicators-to light three indicator lamps on control console. Actuation to be by switches on the fuel hoist load cell through the disconnect.

h. Auxi liar hoist re fuelina interlock to cut up power to ei ther auxi 1-iary hoist upon the simultaneous actuation of the following switches, interlock switch 1 or the "B" contact of auxiliary hoist load sensing switch, the "A" contact of refueling interlock switch 1, depending upon which reactor is selected, and an external switch (supplied by others).

Gra le liftin interlock. When grapple is loaded, actuation is on oa sensing switch, hoist power is blocked upon opening of hook engage circuitry.

21A1 976 sH.No. 18 BENEl'i%I. Qi::('; I!LECTAIC NUCLEAR ENERGY DIVISION 4 REv.

C' 4.6.8.9.1 Rod block interlock to de-energize two circuits (provided by others) when the "A" contact in refueling interlock switch is open or the "B" contact of refueling interlock switch number one is open, depending upon which reactor is selected and any one of the following contacts are open:

a. Fuel hoist load cell switch (set to de-energi ze at 485 lb.).

b. Auxiliary hoist load sensing switch (set to de-energize at 400 lb.

+ 50 lb. - either auxiliary hoist).

4.6.8.9.2 An additional rod block interlock shall be provided to de-energize a further two circuits when the "A" or "B" contacts in refueling interlock switch number 2 is open, depending upon which reactor is selected and any one of the following con-tacts are open:

a. Fuel hoist load cell swi tch

b. Auxiliary hoist load sensing switch (either auxiliary hoist)

c. Deleted 4.6.8.9.3

~ ~ ~ ~ Reverse bridge motion block. An interlock shall be provided to block

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reverse motion of the bridge (normal movement toward the reactor) with the simultan-eous operation of the following:

a. Opening of external contact (supplied by others)

b. Openino of the "A" contact of refueling interlock switch number 1

c. Interruption of control power to either the fuel hoist load cell (opening of contact set at 550 lb) on the auxiliary hoists load cells (opening of contact set at 400 lb) 4.6.8.9.4 Additional reverse bridge motion block. An interlock shall be provided to block reverse motion of the bridge with the simultaneous opening of the "A" con-tact of refueling i'nterlock switch number 2 anda contact supplied by others. This interlock shall be independent of those specified in Paragraph 4.6.8.9.3.

4.6.8.9.5 Forward bridge motion block. Since the platform will be used over an adjacent reactor, forward motion of the bridge shall be blocked with simultaneous operation of the followi.ng:

a. Opening of an external contact (supplied by others)

b. Opening of the "B" contact of refueling interlock switch number 1

c. Interruption of control power to either the fuel hoist load cell on the auxiliary hoist load cells

GENEHP.L Qi!g ELEtl'fIiItl 21A1976 sH. No. 19 NUCLE/eR ENERGY OIVISION REV.

C3 Addition forward bridge motion block. An interlock shall be provided 4.6.8.9.6 to block forward motion of the bridge with the simultaneous opening of the "B" con-tact, of refueling interlock switch number 2 and a contact supplied by others.

This interlock sha11 be independent of those specified in Paragraph 4.6.8.9.5.

1.6.9 ~6 4.6.9.1 S ace heaters. Space heaters shall be provided for all motors and the platform contro panels, except for air compressor motor and power winch motor.

6.6.9.2 9 control panel

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and consoles .

9 g p dig hill p ldd 11 1 1 gl th 4.6.9.3. Acceleration limiter. A timed acceleration feature shall be i ncorporated tl llgg,l t lly, dllt. t 1 yt . A 1 tl t 611 9 6 shall be limited to not less than 1 second nor more than approximately 3 seconds.

4.6.9.4 Master switch. haster "on" switch keeping system "warm" to permit instant operation of individual electrical components.

4.6.10 Control Consoles. Control consoles shall be supplied and shall contain all those controls required to operate the platform and fuel hoist through any of the directions of motions and through the speed ranges specified. The consoles shall be mounted directly to the grapple and shall be approximately 4 x 6 x 10 inches high, each. It shall be possible for the operator to conveniently actuate the various motor speed controllers with his hands on the console grips. The con-soles shall be of sufficient rigidity to withstand a force of approximately'50 pounds applied to either grip by the operator.

4;6.10.1. The left hand console shall contain the master switch controlling trolley motion. The master switch shall permit bidirectional variable speed control and contain integral reversing.contactors with forward and reverse mo-tion accomplished by merely moving the controller through neutral. A single multidirectional jog control button shall be provided convenient to the con-sole grip permitting bridge and trolley forward and reverse control while grasping the grip. The jog control shall include timed acceleration permitting only smooth continuous acceleration to a maximum of 2 fpm. The left hand con- .

sole is the preferred location for the key operated reactor selector switch.

In the event that this is impractical, relocation is permissible by negotiation with the Buyer.

4.6.10.2 The right hand console shall contain the master bidirectional variable speed controller switches for the bridge and hoist and the central station selec-tor switch. A jog control, similar to above, button shall be provided convenient to the console grip permitting fuel hoist lowering control while grasping the Ql"i p.,

BENEHAL g) LLECTBIC 21A1976 sH. r"o. 20

< NUCLEAR ENERGY Dl VlstON nev.

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4.6.10,3 The console mounted equipment shall include but not necessarily be limited to the following:

al Fuel hoist load indicator lamps indicatin'g "fuel hoist loaded,"

"jam" and "slack-cable."

b. Fuel hoist normal up and down indicator lamps indicating "grapple normal up" and "grapple full down."

C. Master "on" switch Grapple hook engaged lamp (green) indicating "Hook Engaged"

e. Maintained contact push buttons switch to actuate 4-way valve (Paragraph 4.6. 13.6) operating double acting cylinder on grapple.

One button is to be labeled "engage" while the other is to be labeled "release."

f. Grapple override switch button.

4.6,10.4 A toggle switch shall be provided convenient to the hoist controller.

This switch is to turn on and off lights (supplied by others). The lights are 30Y a-c, 10 Amps total. Suitable electrical components shall be provided to supply the lighting current.

4.6. 10.5 All wi ri ng .for control purposes shall be stranded and color-coded, or otherwise identified and shall be wired into a protected terminal board within the control pane'l.

4.6,10.6 All leads into the consoles shall enter through quick disconnect:

'type multipin electrical connectors to permit rapid disconnection of either one or both of the consoles should it be necessary. These leads and both con-nector halves shall be prewired and brought to the main grapple connectors.

4.6.10.7 All panel buttons and lamps shall be identified by letters not less than 1/4 inch high.

i.i.ii ~iiii li i i (tl ii M i i) 4.6.11.1 The hoist unit. An electrically-operated single cable auxiliary hoist unit shall be provided complete with integral reducer, brake, drum, and limit stops.

The hoist shall be complete with its own motor-driven trolley suitable for operation on the platform superstructure. The hoist cable shall hang a minimum of 6 inches from the platform structure. The hoist shall operate on the same external power supply as the remainder of the platform assembly. Projection of this hoist shall be minimized to provide maximum working space above the operator.

21A1976 sH. No. 21 MUCLEAB EI'sEIiGY DIVISION REv. 4 A.6.11.2 Brake. A fail-safe brake shal'I be provided to control cable drift and to hold a full capacity load.

4.6.11.3 Cab1e. The hoist cable shall be nonspinning, naterproofed lubricated stainless steel vlith a minimum factor of safety of 6 at capacity load. The cable fitting shall be stainless steel Tru-Loc with a 1/2 x 13 UHC-2A thread with wrench flats or Buyer approved equivalent.

4.6.11.4 Enclosure. The entire hoist assembly shall be adequately enclosed to prevent the emission of lubricant and/or the entrance of water.

4.6.11.5 Controls. Pendant-type controls shall be provided mounted in a corro-sion resistant metal housing. These controls shall be independent of the main platform control panel. The pendant shall also include controls for single speed {approx. 10 fpm) operation of the bridge. Interlocks shall be provided to prevent bridge operation from any two controllers simultaneously.

6.6.11.6 ~ld 1 . Al d 1gd 1 661 1 1 glh 1 d the auxiliary hoist cable shall be provided with four switches permitting 2 in-dependent circuits. One circuit shall be adjusted to open with a load of 400 lbs. Each switch shall be capable of sensing the set hook load with a maxi-( mum error of + 50 lbs. and shall reset within 200 lbs. of set load.

these switches will be called "auxiliary hoist load sensing" switches.

out of the load shall be mounted on the control pendant.

Hereafter, Dial read-4.6.11.6.1 The second independent circuit shall be adjusted to rated hoist load and automatically stop the hoist on an overload signal when a load of 1000 lb or over i s app1 i ed to the hoist cable.

4.6.11.6.2 Adjustable time delays shall be included (if necessary) to avoid open-ing of these swi tch contacts due to acce 1 erati on.

4.6.11.7 Position switches. The auxiliary hoist shall be equipped with adjust-able position switches which shall function as follows:

4.6.11.7.1 Automatic hoist stop when the hook is approximately 8 feet below the platform tracks. It shall be possible to override this limit by depressing a mom ntary contact override button together with the normal hoist up controls.

Automatic hoist stop swi.tch shall reset. within 2 feet of the set point. The limit switch override button sha11 be protected by an easily operated cover which will prevent acci dental operati on.

4.6.11.7.2 Viaximum up travel limit stop. Two independent switches in series shall perform this function.

BENI! tdfiL Q ELEt:TBII: 21Al 976 22 I. NUCLEAR EI'eERGY DIVISION REV. 4 4.6.12 Auxiliary Hoist (Trolley Mounted) The auxiliary hoist shall conform to the requirem nts specified for the monorail mounted auxiliary hoist except as follows:

4.6.12.1 The hoist shall be mounted on the trolley previously specified and shall be pendant controlled by an operator standing in the operator cab.

4.6.12.2 The hoist shall wrap the cable on the drum such that the cable is closest to the operators cab, and the platform valkvay uhen the cable is fully ivrapped 4.6.13 ~ld C 4.6.13.1 The com ressor. The platform shall be supplied with a tank type oil-free air compressor Bell and Gossett Model SYCT 104-1 or Buyer approved equivalent) capable of delivering a minimum of 2 cfm at 150 psig. The tank shall have a mini-mum capacity of 10 gallons with an automatic blowdown feature, for moisture removal, dumping to the bridge track area. The compressor shall be mounted on l dh I

the platform fram preferably on a bracket welded to the platform columns to keep the walkway clear. Compressor motor shall be wired for 3 phase power.

4.6.13.2 Auxiliaries.

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~ The compressor shall be supplied with the following accessories:

Automatic pressure switch; cut in at 70 psi or less,

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a. ~

cut out at 110 psi b, Tank drain

c. Exhaust muffler

d. Self-relieving strainer and 5 micron filter

e. ASTM Coded tank 4.6.13.3 Control. A starter for the compressor motor shall be conveniently located relative to personnel on the ualkuay 4.6.13.4 ~64 11 . 41 ppl 11 hit lip 4 h 1 td h trolley frame and the reel attached to the monorail hoist.

4.6.13.5 Hand operated shut off valves conveniently located on or near the end frame to which compressor is mounted shall be provided to permit isolating the air supplies to each hoi s t.

4.6.13.6 Air control valves. Solenoid operated 4-way two position air control valves shas be supp ie for each of the 3 hoist stations suitable for operation of double acting air cylinders. Each cylinder shall be controlled from each hoist operator station by maintained contact push buttons. The push buttons shall in-corporate a ring guard which protects the button and prevents inadvertent actua-tion of the air control valves. The respective solenoids shall be wired so that

( their operation is independent of any other switch or control function on the re-fueling platform wi th the exception of the master "ON" swi tch.

21A1976 SH.NO. 23 GEl'lL'PiP L Q()) ELL'CTBIC NUCLCAR I:.MERGY DIVISION 4 nEv.

4.6.14 Position Indicator System 4.6.14.1 Brid e and trolley osition indicator. A bridge and trolley position indicator system shall be provided with digital position readout in the operator cab. The respective transmitter m'odules are mounted on the platform end truck and trolley as shown on the purchase part drawing. The position transmitter is actuated by movem nt over a floor mounted chain or alternate fixed reference. The Seller shall supply the chain or alternate fixed reference required for position transmitter actuation together with IA ans for adjustment, mo nt, if required. The total length of the bridge transmitter chain is given on the purchase part drawing.

t 4.6.14.2 The receiver assembly shall be supplied as a part of the platform in accordance with instructions on the purchase part drawing.'.6.14.3" The bridge and trolley position indicators shall readout coordinates which are 6 inches apart and numbered as shown on the purchase part drawing. The dIsplay shall be such that the following accuracy requirem nts are visually re-sol ved:

The bridge and trolley structure shall be sufficiently rigid and accurate to permit trolley positioning in two mutually perpendicular axes with an error not to exceed 1/8 inch as the bridge traverses 22 feet in either direction and the trolley traverses the center 22 feet of the span. The total indicated position error shall not exceed

-1/8 inch.

4.6.14.4 Fuel ra D)e osition indicator. A fuel grapple depth position indicator shall also e supp ie in t e operator cab. The travel of the hoist cable can be detected by an encoder device connected to the hoist drum and shall be readout in inches.

The total indicated position error shall not exceed 1/8 inch.

4.6.14.5 Fuel ool cell osition indication. A high intensity spotlight (GE guartzline f250 PAR 38 SP, 120Y, 250 watts or equivalent) shall be mounted on each end framo in line with the grapple center line. The light shall be shielded so as to produce a rectangular strip of light approximately 3-1/2 inches wide on the curb-ing alongside the fuel pool. The light wlliilluminate numbers (by others) which identify the rows of fuel storage cells. The general arrangement of the lights is shown on the purchase part drawing. A switch shall be supplied permitting the lights to be extinguished when they are not in use. Average bulb life shall be no less than a manufactured rating of 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br />. An electrical digital readout system shall also be> considered incorporating with the same system as requested in Paragraph 4.6.14.1.

'21A1976 sH.wo. 24 OL:hlEPil'cl. Q( ELECTBIC NUCLEAR ENERGY DIVISION REV.

4.6.15 Fuel Hoist Load Cell. A load cell including necessary electrical contacts shall be supplied to signal varipus load levels on the fuel hoist cable. The cell shall contain three independently adjustable electrical switches set at 485 50, 550 50, and 1200 + 50 lb. cable load. The load cell shall be wired functionally

.into the control system as described elsewhere and shown on the purchase "down" part drawing. A slack cable device shall be supplied which provides a hoist interlock set at 50 = 10 lbs. cable tension (combined).

,4.6.15.1 The switches shall be prevented from vibrating out of adjustment during operation and shall be enclosed in a tamper-proof enclosure. Access for switch adjustment shall be by key only.

4.6.15.2 The load cell on each hoist shall incorporate a device or m thod which will permit load readout without the necessity for introducing additional electrical or electronic equipment such as amplifiers etc., into the refueling safety interlock circuits. The intent is to keep the safety. interlock circuits as simple as possible so that refueling operations will not be held up by the malfunction of equipment not directly associated with the interlock contact logic. The readout dials shall be calibrated to read actual cable tension and shall be located in the operator cab for the main hoist and on the pendants for the auxiliary hoists.

(" -. 4.6.16 A display panel with indicator lights shall be provided in the operator cab to show the interlock conditions which arise to prohibit certain refueling motion from being operated. The light can provide supervision of a correctly operating system and act as a guide in troubleshooting. Thus, an interlock light would be lit to give the reasons which disable the operation of the refueling platform.

The following conditions shall be covered:

a ~ Fuel is overhoisted

b. Fuel hoist interlock resulting from refueling interlock switch No. 1 and load switch.

C. Auxiliary interlocks resulting from refueling interlock switch Ho. 1 and load switch.

Rod block interlock No. 1 as specified in Paragraph 4.6.8.9.1.

e. Rod block interlock Ho. 2 as specified in Paragraph 4.6.8.9.2.

Revise bridge motion block as specified in Paragraph 4.6.8.9.3 labeled "Bridge Reverse Stop Ho. 1."

g, Reverse bridge motion block as specified in Paragraph 4.6.8.9.4 labeled "Bri dge Reverse Stop Ho. 2."

GEIIEBAL i ELECTBIC 21nl g76 ....,.. 4

@~ac ceo. 25 7 Material s 4.7".1 t~iaterials for fabricating the refueling platform shall be as shown in Table IY or Buyer approved alternate.

C.'. TABLE IY REFUEL IifG PLATFORH f"IATERIALS

~Com onent t'later ial Designation Permanent structural parts of Carbon Steel, ASTt1 A36 the platform girders, end trucl;s, etc.:

'ridge and Trolley Wheels: Cast Steel ASTf'i A27 Drive Shafts: Carbon Steel per ASTff A108 or equal Conduit: Aluminum or Steel Removable Tread Plate and Aluminum 5036 or 6061-T6, or as specified Handrails: Stainless Steel, ASTth 276. Carbon Steel, ASTff A36 Hoist Cables: Stainless Steel, waterproof lubricated Cables Attachments: Stainless Steel (Cylinder and Swivel Joints)

Control Panel and Console: Aluminum Sheet or Steel Bolting: ASTN A325 Gears, Pinions and Sheaves: Cast Steel ASTfl A27 or equal Fuel Hoist Drum: Cast Steel ASTH A27 or equal with magnetic par icle test or 'liquid penezranr, test after machining.

Q

GEr<anai Q zvecvntc oocu~csv No. 21A1 976 wcv. No. 4 s ~c;c No. 26 4.7.2 Alternate tlaterials. The Seller shall be free to suggest alternates to the specified ASI'>E or ASTli materials an'd shall bring such alternates to the attention of the Buyer, but shall not make substitutions without written approval of the Buyer.

The proposed alternate materials shall be presented with the scope of application and a copy of materials specifications equivalent to ASf',E or ASTVi specifications for similar material or detail information equivalent to that furnished in the ASIDE or ASTH specifications for'imi')ar materials.

5. IllSPECTIOll AND TESTS 5.1 The Seller shall conduct and be fully responsible for the following inspec-tion and tests.

5. 2 Seller 's Sho Tests 5.2.1 Platform Assembl . The platform shall be completely assembled and tested at the Se er's p ant prior to shipment to ensure that all equipment comprising fully operational unit performs according to the requirements of the specifica-on. Hires shall be pulled through conduit and tagged for identification purposes iere connections are necessary. All testing shall be performed with the controls

'g which will operate the platform and associated equipment when in service.

5.2.2 Dimensional Re uirements. The dimensional requirements of the purchase part drawing sha e chec,ed and actual dimensions recorded on a check sheet.

Wheel span shall be measured with both zero and 1200 lbs, ')oad suspended on the main hoist cable with trolley at center span.

5.2.3 Interlocks. All electrical interlocks shall be checked to ensure conform-ance with specification requirements. This shall include testing vrith operational and limiting loads on the load cells and checks to ensure that electrical travel limits are functioning correctly.

5.2.1 ~C.

is leak tight vri th Th all hose p 4 li reels installed b h and kd th<<h y the ends of the hoses capped.

5.2.5 Hain Hoist Lift and S eed Tests. hoist shall

~

~ ~ The main be loaded with a 1100 lb. load and tested as fol ows:

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The load shall be lifted a total of 45 feet at the following set speeds

.First 15 feet - 1 fpn Second 15 feet - 20 fpm Third 15 feet - 40 fpm

G E ll E l) A L .~(':a E LE C 7AI C

,,, 21A1976 ,. 4 C

b.2.5.1 After each hoisting, the load shall be lowered reversing the speed sequence.

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Two minutes shall, elapse between each of the hoisting and lowering cycles.

5.2.5.2 The above cycle shall be performed six times with no overheating in the drive system as defined by hEl% SP-HGl, Para. h61-12.39 and NG1-12.59.

~ 5.2.5.3 Field minding temperature rise shal'I be determined by the resistance

method in accordance with the latest revisions of IEEE Ho. 112A, and, IEE Ho.

113A.

5.2.5.4 The instrumentation used for measuring difference in resistance shall be of sufficient sensitivity to measure fractional changes.

5.2.5.5 The current and voltage in to the drive system shall be measured for each speed and direction.

5.2.5.6 All test results and calculations shall be recorded in a logical, or-derly fashion.

2.6 Alternate Hoist Lift and Speed Test. In lieu of the lift and speeds ecifie in Paragrap ..5, the main oist should be loaded to 1100 pounds inimum and tested as follows:

1(f/i) D Distance (ft) 1 Up 15 20 Down 15 10 Up 15 20 Down 15 20 Uo 15 Rest 2 minutes 20 Down 15 20 Up 15 10 Down 15 20 Up 15 1 Down 15 Rest 2 minutes 5.2.6.1 The tests of Paragraph 5.2,6. must be performed six times and meet

'the requirements of Paragraphs 5.2.5.2 through 5.2.5.6.

5.2.7 Allowable S eed Variation. Whichever test procedure is used, speed shall remain within +10 percent of the selected speed.

GENEBAI. 21A19 j6 sH.No. 28

~g(jj ELt:CTBII'UCLEAR EMERGY DIVISION REU. 4 5.2.8 Hain Hoist Breakinq Test. The hoist shall be loaded with 1100 lb and operated at ull speed. lviven tthe'1100 lb load is travelling at full speed the brakes shall be set by depressing the control system stop button. The load shall then be operated at full speed in the reverse direction and the brakes set as before.

5.2.8.1

~ ~ ~ This test shall be repeated until the brakes have been set a minimum of 30

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times.

5.2.8.2 fach brake operation shall bring the load to an immediate chatter-free

stop, 5.2.8.3 The brakes shall show no deterioration of performance.

5.2.8.4 If any components in the braking system should be damaged, the Buyer shall be notified before replacements are made.

5.2.8.5 When the load is braked from full speed in the downward direction, the superstructure deflection shall be shown to be less than 1/300 of the span.

5.2.9 Hain Hoist Load Float Capabilit . The load float, if used, capability 'of the main hoist shall be teste by suspending a 1100 lb load on the main hoist cable and releasing the brakes by operating the load float switch. The load shall remain stationary with no overheating of the drive system for a period of 90 seconds.

5.2.10 Platform Rail Test. The platform shall be tested by running the unit along rails temporari y mounted on Seller's plant floor. The rail length shall be such as to permit a full 20 foot of platform movement. The platform rails shall simu-late the worst installation requirem nt permitted on the Seller's rail installation drawing. The trolley, including fram, shall be run on the rails provided for that purpose on the platform girders.

5.2.10.1 Platform and trolley motors shall be disconnected and each moved by hand or mechanical puller for full rail length at approximately 2 feet per minute. Aver-age force required to keep the trolley and platform in motion shall be recorded.

If at any point along the rails, the force required exceeds the average force by The platform a factor of 2 this shall be indication of unacceptable binding.

structure shall be corrected and the test rerun.

5.2.10.2 An alternate method for Paragraph 5.2.10.1 would be to monitor trolley and bridge motor armature currents (with drive couplings connected) in lieu of measuring pull force. Average motor current at approximately 2 feet per minute shall be recorded. If at any point along the rails, the motor current exceeds the Motor average current or a factor of 2, this. shall be indication of unacceptable binding.

field current should reIIain constant during this test.

GL-IlF.BP.L (Pj)@ ELF.CTIIIIl 21A1976 sH.No. 29 NUCLEAR ENERGY DIVISION REv. 4

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5.2.11 Position Indicating S stem. The Seller sha',1 submit a test procedure, for Buyer approval, concerning tie position repeatability of the trolley and platform.

This test shall verify that the platform and trolley can be repeatedly positioned within 1/S inch. of any predetermined true position. The test procedure shall include data sheets on which test data is to be recorded.

5.2.12

~ ~ Additional Test b Seller, The Seller shall conduct and be fully respons-ible for any additional tests necessary to provide a refueling platform which will

~

meet the performance requirements of this specification.

5.2. 13 Notification of Tests. The Seller shall give a minimum of 10 days notice to allow the Buyer or his representative to witness those tests to be run at the Seller's plant.

5.3 Dismantlin After Tests 5.3.1

' After testing (which includes both Buyer and Seller tests) and before dismantling for shipm nt, all wiring and mechanical connections shall be match-rked or tagged to ensure proper field assembly. ~

Q 6. CLEANING, PAINTING/COATING, ANO PREPARATION FOR SHIPMENT 6.1 ~Cleanin 6.1.1 The entire assembly shall be thoroughly degreased. Heavy deposits of. oil or grease shall be removed by the methods outlined in SSPC-SP-1.

6.1.2 Exterior carbon steel surfaces shall be cleaned of oil and grease, after which mill scale, rust, rust-scale, paint, and other foreign matter shall be thoroughly removed by such means as sandblasting. All surfaces shall be brushed, or air cleaned to remove all traces of sand or grit and shall then be dried.

6.1.3 Exterior carbon steel surfaces prepared for painting shall meet the require-m nts of near white metal blast cleaned surface as defined in SSPC-SPID-63T.

6.1.4

~ ~ Exterior Surfaces (machined). All exposed, machined, carbon-steel surfaces shall be protected against rusting using a rust preventative such as Valvoline Oil Company "Tectyl: No. 846.'orrosion preventive compounds shall not be allowed to contami nate austenitic stainless steel.

6.2 ~Paintin 6.2.1 One coat of Carbo-Zinc II (GE P50YP123B. Inorganic Zinc Prime Coat, Carbo-Zinc II) shall be applied to all exterior surfaces so as to ensure coverage and rotection from the elements. Paint shall be applied to dry surfaces at temperature above 50'F.

DocUMKtaT lao. 21 A'} 976 IlCY. NC Pa.GE wo. 30 o.3 Pre aration for Shi ment 6.3.1 Al.l equipment shall be adequately protected from damage during handling, shipment, and stoi age. Handling equipment, blocking, strapping, or hold-down devices shall be applied so the components are not marred in any way. During shipment the components shall be further separated by dunnage as is necessary to prevent damage. Packaging for sflipment shall be applied in a manner to maintain

, cleanliness of the equipment. Inside unheated storage of the equipment may be as long as 24 months, 6.3.2 All small loose pieces, including bolting, tools, etc., shall be boxed for protection during shipment. All boxes shall be marked itith F15-E003 and F15-E004.

7. SUBfiITTALS TO THE BUYER 7.1 Submittal requirements to the Buyer shall apply to the Seller and to the Seller's Subcontractors. The Seller shall be responsible for all submittals in-cluding those of Seller's Subcontractors. ~ If any changes are made by either the yer or Seller on the Submittals, a nevi revision shall be sent to the Buyer by ie Seller. ~

> 7.2~ The following Drawings, Procedures, Calculations, Reports, Hanuals, and Cer tf tifications shall be submitted in accordance with the requirements of Attachment "A", "Document Submittal Requirements." Attachment "A" lists the documents to be submitted by the Seller to the Buyer, the number of copies, required submittal dates, and whether these submittals are for information, approval, or certification.

7.3 ~Drailin s 7.3.1 To Assembl Drawin - A drawing depicting the arrangement of the equipment indicating over-all dimensions, location, and size of supports and shipping and operating weights.

7.3.2 Second Level Assembly Drawings - Drawings depicting the arrangement of the functional parts and showing construction of internal parts, parts lists, and material designations. A field assembly drawing shall be supplied.

7.3.3 Subassembl Drawin s - Drawings depicting the arrangement of detail parts

>(hich are use to pro uce t e second level assembly drawings enumerated in Para-graph 7.3.2 above.

G EH ERE;L f~i! ELECTPiiC aocu~v.uv ~o.21A1976 Rcv, No 4

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( P Ac c Ho.

31 7.3.4 Detail Drawinqs - Drawings of all parts which the Seller or the Seller'

'endor has produced for the manufacture of the equipment herein specified.

7.3.5 Rail Installation Drawinq - This drawing shall define all the necessary tolerance requirements for p atform rail installation to assure position repeat-ability of the platform. Such tolerances as rail parallelism, camber, span shall be noted.

7.3.6 Drawin s for Ap royal - Top assembly and subassembly drawings as enumerated in Paragrap >s .3. , ).3.2, and 7.3.3 together with wiring and interconnection diagrams and functional test procedures shall be submitted for approval.

7.3.7 Drawin s to be Certified - Top assembly, second level assembly, and sub-assembly drawings as enumerated in Paragraph 7.3.1, 7.3.2, and 7.3,3 together with wiring and interconnection diagrams shall, upon conpletion of the as-built design, be certified to be correct with no further changes required.'.4 En ineerino Schedule

.5 Fabrication Schedule 7.6 Procedures 7.6.1 Heldin procedures 7.6.2 Hagnetic particle inspection or liquid penetrant test procedures - to meet re-quirements of magnetic particle inspection or liquid penetrant test of the Fuel Hoist Drum - cast steel ASTH A27 or wrought steel.

7.6.3 Cleaninq, Coatin and Paintin Procedures 7.6.4 Harkinq, Packin and Packa inq Details and Procedures 7.6.5 A copy of procedures for all final inspection and tests conducted by the Seller on the assembled platform.

7.7 Instruction Manuals c 7.7.1 General. The instruction manual will be comprised of an overall manual and manuals for the major assemblies and components. The assembly and component manuals

>>i'll be bound behind the overall manuals with index tabs separating them.

GElJ El";/eL l";:)) ELECTBlC pocvMcov No. 2 1~1 g76 R CV ~ HO. 4

= pAcc No. 32

,.7.2 S ecific Re uirerients. The overall manual in conjunction with the component

. and assemb y manua s, s>a 1 provide the following information on the refueling plat-form, and the components and assemblies of which it is comprised.

'7.7.2.1 Equipment description, The equipment description shall describe the in-tended use, capabilities, limitations, and physica1 arrangement of the eouipment.

The descrip.ion of the physical arrangement shall be sunported by illustrations or c engineering drawings that allow all of the major components and assemblies to be located and identified. Text covering the physical arrangement shall be brief, avoiding unnecessary or repetitious details that are easily illustrated.

7.7.2.1.1 The following tabular data will be included as part of the equipment description:

a. Descriptive data which identifies manufacturer, type, model and component identification (CID) number, as applicable for all major components;

b. Capabilities and limitations, such as operating speed, load limits, minimum and maximum ranges, degree of coverage, reso'lution, and accuracy.

.7.2.2 Functional descri tion

, /

7.7.2.2.1 General. The functional description shall include a discussion of the overall principles of operation of the equipment and its major functions. This manual must contain precise and detailed design information on the refueling plat-form, its major subsystems and component parts. This should include schematic drawings and detail drawings as necessary to clearly depict how the component is designed and how it functions. (Detailed information Iincluding drawings and parts lists] for components and major assemblies that have separate instruction manuals will be presented in those manuals.) Operating and design parameters must be included. Performance data, including necessary curves, must be included. The development of the eouipment outputs in each mode of operation shall be described.

Functional diagrams shall be used as the primary means of cormunication; text shall be used to support the diagrams as necessary for c'larity. The descriptions shall be presented in successive levels of increasing detail.

7.7.2.2.2

~ ~ ~ Mechanical schematic diagrams. Where applicable, mechanical schematic diagrams will be created. These diagrams shall show sufficient detail to exp'Iain the operational sequence and arrangement of a mechanical device including the elec-trical control circuits. Nomenc)ature, symbols, part identifying numbers, and necessary descriptive data shall be shown as required. Gears, shafts, clutches, levers, mechanica'Ily-driven swi tches, motors, synchros, etc., shall be shown in functional arrangement. Gear ratios or number of teeth and direction of rotations, etc., shall be given.

GEfiEflALf~cl ELECTlllC 2'lA1976 sat:v. uo. 4

'.7.2. 3 ~0eration 7.7.2.3.1 Introduction. An introd'uction supported by illustrations, shall be pro-vided that locates and identifies all operator controls and indicators.

7.7.2.3.2 Controls and indicators. A table which lists all of the controls and indicators shall be included. In addition to the front panel designation, the table will list the reference designator and will define the function of each con-trol and the meaning of each indication.

7.7.2.3.3 Operating procedures. Operating procedures which include the following shall be provided:

a. Star~t-U . This procedure shall include all steps necessary to b>.ing the equipment from "OFF" to "FULL" operation.

b. Shutdown . This procedure shall include all steps necessary to 5rrng t7e equipment from "FULL" operation through "STA'igBYU to "OFF" condition.

7.2.3.4 Cautions and warnings. Throughout the procedures any operation that uld result in injury to personnel will be prefaced with a ")!ARNIHG" that points out the possible hazard. Any operation thatt could result in damage to equipment will be preceded by a "CAUTION" thatt explains the hazard. These cautions and warnings will be presented so that they standout from the text of the procedure.

7.7.2.4 Maintenance 7.7.2.4.1 Introduction. An introduction shall explain the purpose, scope, and arrangement of the scheduled maintenance data. When a scheduled maintenance proce-dure is critical to the operation of the equipment and the schedule for servicing is absolute (not just recommended), this information shall be conspicuously written as a precaution.

7.7.2.4.2 Scheduled maintenance action index. An index which includes all scheduled inspections, performance tests, and preventive maintenance procedures shall be pro-vided. This index will indicate how often each scheduled maintenance action should be performed. The following symbols shall be used.

INTERVAL SYHGOLS Daily lleel;ly Honthly quarterly (3 months)

Semiannually (6 months) S Annually (12 months)

A Overhaul cycle C As specified (explain circumstances) R

G 2 W E II A L Qi E L2 C T ll I C DocUsscNT No. 21A1 976 scv. Ho. 4 PANG No. 34

...7.2,4.3 Scheduled maintenance procedures. These procedures shall include the in-

'ormation required to inspect, clean, lubricate, and adjust the equipment.

7.7.2.4.3.1 Precautions. Precautions preceeding each instruction requiring pre-cautionary notes shall be stated.

7.7.2.4.3.2 Equipment. Tools, parts, materials, and test equipment required, shall be listed.

7.7.2.4.3.3 Safety devices. Instructions for properlv maintaining all safety devices and interlocI;s, with warnings and cautions, shall be given.

7.7.2.4.3.4 Lubrication. Instructions for lubrication at operating temperatures; also types and quantities of lubricants to be applied shall be given.

7.7.2.4.3.5 Access. Instructions for obtaini.ng access to subassemblies or sub-components shall be clearly described in a step-by-step manner.

7.7.2.4.3.6 Other. Instructions for in-place adjustments, inspection procedures

~

or parts which deteriorate, illustrations to identify lubrication points, and ther pertinent data shall also be given.

', 7.7.2.4.3.7 Honrepairable parts. Parts that are nonrepairable shall be so ident-

-'fied. ~

7.7.2.4.4 Scheduled performance tests. Procedures for performing the tests nec-essary to verify that the eouipment is operating within standards in all modes of operation shall bo provided. The procedures shall contain precautions, a list of tools and test equipment identified by type, manufacturer, and model number, the title of the test to be performed, and detailed instructions for accomplishing the test.

7.7.2.4.5 Overhaul, maintenance and repair standards. This manual shall provide detailed overhaul, maintenance, and repair standards which include evaluation tests, maintenance inspections, and a list of items to be replaced and criteria for deciding upon repair or reconditionino.

7.7.2.5

~ ~ ~ Corrective maintenance 7.7.2.5.1 Adjustments and alignment. All information and procedures required to perform all necessary adjustments and alignments shall be presented.

GEfdERfiL "';)I ELEI;TAIC oocusAcss T sso. 21A1976 s s:v. sets. 4 7 ACC WO, 3g

- 3 .-7.2.5.2 Procedures. All procedures required in the corrective maintenance of assemblies and repairable parts shall be presented. Repair procedures shall in-clude but not be 'limited to removal, disassembly, and inspection; repair or re-placement of piece parts; and cleaning, reassembly, adjustment, installation, cal-

~ibration and checkout. Applicable instructions for corrective maintenance activi-ties located in 'other parts of'he manual such as those for scheduled maintenance may be referenced.

7.7.2.6 Troubleshoo~tin 7.7.2.6.1 Introduction. An introduction shall explain the approach and logic of the troubleshooting principles presented in the manual and shall describe the troubleshooting data and show how they relate'o one another.

7.7.2.6.2 . Troubleshooting guides. Troubleshooting guides shall be prepared in accordance with this section for the detection and logical isolation of faults.

Information shall be provided as to design and initially measured equipment per-formance characteristics for comparison with current indications.

.7.2.7 Reference data

.7.2.7.1 This section shall include all of the assembly drawi ngs and parts lists, wiring (connection) diagrams, elementary di agrams, and the detailed drawings (as-sembly drawings, parts lists, and, if applicable, electrical drawings) for the repairable components or assemblies that do not have their own instruction manuals.

7.7.2.7.2 Parts lists. Parts lists shall be provided that list all replaceable parts.

These parts lists shall be keyed to the parts location drawings (or illustrations) and they shall identify the part by its common name, value or size, reference desig-nator (if applicable) manufacturer and part or catalog number.

7.7.2.7.3 Parts location drawings. In most cases the assembly drawing will probably be adequate for use, as a parts location drawing if it is drawn so that it is legible after reduction to a vertical height of 9-1/2 inches. Other types of illustrations such as photographs, exploded views, etc., are also acceptable to fulfill the require-ments of this section.

7.7.2.7.4 Electrical drawings. All the electrical drawings (elementary diagrams, interconnection diagrams, etc.) shall be included in this section, These drawings should be drawn so that they are legible after they are reduced to a vertical height of 9-1/2 inches.

7.8 Ins ection and Test Re orts 7.8.1 A copy of all inspection records and test reports made by the Seller on the platform and its components before and after assembly.

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G E lb E [I A L r'I'j) E LECT B I C

~ wN Ipgeddggbs e gdA%sea'a'eqwggs %ifppk amer Docvsdck T H< 21 Al 976 st I v. sao. 4 I As'r No 36 C",

'i .8. 2 Cer ti fi cati on of Hateri a 1 s 7.8.3 The Seller shall classify all parts shoirn on the subassembly drawings as either critical load bearing or non load bearing. Load bearing members shall be identified on these parts lists with an easily recognized symbol, Certification of chemical and physical properties is required for load bearing members. A certificate of compliance is required for non load bearing members. For purchased items such as gear boxes, bearings, brakes etc, the manui'acturers guaranteed load rating will be sufficient. The Buyer will normally review and approve member classification during the drawing approval cycle. However, to avoid unnecessary delays, the Seller may, prior to drawing submittal, submit a list of members classi-fied as load bearing. The Buyer will approve such a list providing it is made after stress calculations have been completed.

7.8.3.1 Seller shall obtain certification of rated load tests for all hoist cables and their associated fittings.

7.8.3.2 Prior to any fabrication, weldor qualifications and weld procedures shall be submitted for approval.

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~

~

I~

.9

~

I Initial

~ ~

Installation and CheckoutI II II I

Installation (I~ 7.9.1 and the necessary

~

~ Procedures. ~ Procedures, j s supporting drawings, that prov> e a step- y-step sequence for installation shall be supplied. These oro-cedures shall include handling instructions (with estimated weights) for those pieces that can't be moved by ha>>d.

7.9.2 b I. e' Initial Checkout.

1 dbfinitial checkout An b ltd procedure, including precautionary l gt d, I lib ldll d.

Nor SfRRxs &'oPs

&4&@ A'r Szse7.s Sroas Zo~os C/8)

Qz 8/P Qi gqy- loco pg,C 1040 q/0 0< ggy l060 k~

O~ gqg -1050 4.

Rz~z~r 2

sraRv pro 0

0 g 4 6 8 to rz rw tc ra . zo zz z~ z~

7 lkfE - AfrwurE5 FIGURE 1 HAIN HOIST DUTY CYCLE

ATTACHMENT C Seismic Analysis of the Reactor Building Crane X. General Desi n Criteria Class l Seismic equipment shall withstand simultaneously the horizontal and vertical accelerations caused by the "Operating Basis Earthquake" (OBE) and the "Design Basis Earthquake" (DBE) as defined herein, in conjunction with other applicable loads.

D namic Anal sis (1) ~Res onse S ectra Curves Response Spectra Curves are based upon the seismic analysis of the supporting structure and represent the seismic response of a single degree of freedom system at a particular location within the structure.

Response Spectrum Curves, plotted .in terms of accel-eration versus frequency, correspond to various loca-tions within the buildings and are identified with respect to the points noted on the mathematical model for each direction of vibration to be considered.

This includes the vertical as well as both the N-S (Continued on next page).

and the E-W horizontal directions. In addition, each Response Spectrum Curve corresponds to a particular damping ratio, i.e., the ratio of damping of the single degree of freedom system to critical damping.

The Horizontal Response Spectrum Curves provided have been generated with resp'ect to a maximum horizontal ground acceleration of 0'.05g corresponding to the OBE, and a maximum horizontal ground acceleration of 0.10g corresponding to the DBE. The Vertical Response Spectrum Curves are based on ground accelerations which are 2/3 of the horizontal accelerations.

Response spectra curves listed below are shown on the following pages.

8856 DSM 22 1A E-W Horizontal OBE 8856 - DSM 22 1B N-S Horizontal OBE 8856 DSM 22 1E Vertical OBE 8856 DSM 22 1C E-W Horizontal DBE 8856 DSM 22 1D N-S Horizontal DBE 8856 DSM 22 1F Vertical DBE (2) Methods and Procedures a) Equipment Model For the purpos'e of analysis, the equipment was idealized as a mathematical model consisting of lumped masses connected by massless elastic structural members. The frequencies and mode shapes were determined for vibration in the ver-tical and two orthogonal horizontal directions, termed global directions. The effects of coup-ling between vibrations in all three global directions were considered, The if significant.

spectral acceleration per mode was obtained from the appropriate response spectrum curve, which has been provided for the appropriate damping value. For determining the spectral acceleration from the response spectrum curves, the value chosen was the largest value on the curve when the frequency in question is varied by +10%. Seismic response in terms of inertia forces, shears, moments, stresses, and deflec-tions was determined for response to seismic excitation in each of the global directions for each mode. The results of the individual modes were combined by the square root of the sum of the squares method. For modes which have frequencies which do not differ by more

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DOE

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than 10%, the responses of these modes were combined by the sum of the absolute values method before combining with other modes by the square root of the sum of the squares method.

For the consideration of stress or deflection at any point;, the total seismic load consists of the most severe seismic load in one of the horizontal global directions combined by the sum of the ab-solute values method with the vertical seismic load.

The equipment models are, shown in the attached figures.

b) Damping values of 2% for OBE and 5% for DBE (SSE) were used.

(3) Load Combinations and Allowable Stress Limits Seismic Category I equipment are designed to withstand the more severe of the following load combinations:

a) 0 eration Basis Earth uake Conditions The load combinations include gravity loads and operation loads including trolley live load, combined with the seismic loading of the "OBE".

Allowable stresses in the structural steel portions are increased to 125% of the allow-able working stress limits as set forth in the AISC Manual of Steel Construction.

b) Desi n Basis Earth uake Conditions The load combinations include gravity loads and operating loads including trolley live load, combined with the seismic loading of the "DBE".

Allowable stresses in the structural portions may be increased to 150% of allowable working stress limits, but not to exceed 0.9 Fs in bending, 0.85 Fs for axial tension and 0.5 Fs in shear, where Fs.equals'he material minimum yield stress at the design temperature.

The load combinations considered with their allow-able stresses are given in the following table.

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I SVSQVE}.AhHA STEAl4 FLEC.

I STATIOts ~ UNIT I PEtihSYLYAh IA PO'HER 4 LIG))T Cv.

BECl(1VL SPEC 885e-N-."2 Phil CRADLE NCH-2i918

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LOAD CCt'1BINATIONS AND ALIENABLE STRESS F = ALLO'ABLE BENDING STRESS G4KR l1AT) L. ASXH A-588

'Ihe following load canbinations were satisfied:

CASE I DEAD URD Fs = BASE = 24.5 ksi = 49K of Y.P.*

LXVE LCM) = TRDLLEY + 125 ION LIFZED DAD IbPACT 8 15't ULTIMATE STREfK'IH 70 14 ~ 0 ksi LATERAL 9 5t F 5 5 (FOR SERT. DL + LL ONLY)

CASE II READ IDAD

=

Fs = 1.5 x BASE = 36.7 ksi LIVE LOAD TBDLLEY ONLY 9 END

'IORNADO WIND LCAD CASE III A. DEAD LOAD Fs = 1.25 x BASE = 30.6 ksi LIVE LOAD = TROLLEY ONLY OPERATING BASIS EARTHQUAKE (OBE) [TROLL Y 8 4., 1/4 PT.,

VERTICAL 'O LIFZED IBAD & END OF SPAN]

HCRXZOÃZK NO LXFZED ZCM)

CASE XII Bo DEAD LOAD Fs = 1.25 x BASE = 30.6 ksi

=

LIVE LOAD TRDLLEY + 125 LIFZED LOAD OPERATI¹ BASIS EARTHQUAKE (OBE) [TRDLLEY 8 ~ 1/4

) PTr

& END OF SPAN]

VERTICAL LXFZED LOAD INCLUDED HORIZONTAL LIFTED URD XN LUDED DEAD LOAD Fs = 1.5 x BASE = 36.7 ksi LIVE LOAD = TROLLEY ONLY BASIS EARTrQUAKE (OBE) [TRDLLEY 9

'ESICÃ

6) 1/4 PTg & END OF SPAN]

VERTICAL - NO LIFZED LOAD HORIZONTAL- NO LIFZED IlRD CASE IV B. D~ LOAD = Fs = 1.5 x BASE = 36.7 ksi LIVE URD TRDLLEY + 125 KN LIFZED LCM)

DESIGN BASIS EARTHQUAKE (OBE) [TRDLLEY Q 4 ~ 1/4 PTg & END OF SPAN]

VERTICAL LIFTED LOAD INCLUDED HORIZONTAL- LIFTED ZlRD IN LUD" D

• BASE ALIDRQ3LE BENDING STRESS PER CMAA 70 EQUALS 0.49 Y.P. I.E. g FOR ASSN A-36 STEEL, 17.6 ksi : 36.0 ksi = 0.49

ATTACHMENT D TABULATION OF INTERFACING LIFT POINT DESIGN DATA LIFT POINT DESIGN FACTOR COMPONENT REDUNDANCY (R) OF SAFETY PER ACTUAL (HEAVY LOAD) ~ OR NON-REDUN- NUREG 0612, FACTOR OF DANCY (NR') SEC ~ 5 '.6 SAFETY

1. Missile or Shield Plugs (a) around reactor well NR 10 3 (b) above reactor well NR 10 3

2. Drywell Head NR 10 1.9

3. Reactor Vessel Head (Information not available from G.E.)

4. Steam Dryers (Information not available from G.E.)

5,. Steam Separators { Information not available from G.E.)

6. Spent Fuel Pool Shielding P

{ a) Gates R 5 (b) Plugs NR 10

7. Dryer/Separator Storage Pit Shield Plugs NR 10 3

8. Refueling Slot Plugs NR 10 3 Spent Fuel Shipping Cask (Casks have not been obtained)

Vessel Service Platform (Information not available from G.E.)

1 . Naste and Debris Shipping Casks (Casks have not been obtained)

12. Vessel Head Insulation NR ~

10 10.4 13,. Replacement Fuel Storage Racks for Spent Fuel (Not applicable, these are permanently installed)

14. Crane Load Block (Not applicable)

15. Plant Equipment>

Other Removable Shield Plate (Cattle Chute) 10

ATTACHMENT E GENERAL ELECTRIC SUPPLIED DESIGN DATA The requested information for heavy-load-handling systems as defined by NUREG-0612 is provided as it can be extracted from the design record files for the particular equipment.

RPV HEAD STRONGBACK NPL rrF19 E009 Drawing 767E187P2, rated capacity 100 tons.

Complete assembly has proof load tested at 125 tons (31.25 tons on each leg) and all structural welds were mag. particle inspected before and after. proof load test by the manufacturer. The reference design record file: DRF O'F13-ll. The components of the load chain are as follows:

ANCHOR SHACKLES G213 (4 Total)

Commercial cat. item, Safe Work Load 110 tons Proof Load 2. 2 times S.W. Load minimum ultimate strength is 6 times the S.W. Load.

6 X 110 = 660 tons, rated load per leg

= 100 = 25 tons.

660 S.F. = 25 = 26.4 > 5 TURNBUCKLES 2-3/4 X 24 G228 (4 Total)

Commercial Cat. item. Safe Work Load 37. 5 Tons Proof load twice safe working load Minimum ultimate load is 5 times the safe working load.

5. X 37. 5 = 37. 5 = 187. 5 tons, rated load per leg =. 100 = 25 tons.

4 S:F. = 25

'7.5>

187. 5 5

THE FABRiCATED STRONGBACK was designed with a total safety factor of 4,0 minimum with respect to the material yield stress. The safety factor was established as follows:

a. Strongback rated load (100 tons) = 80Ã design load (125 tons).

b. Allowable unit stress = 61Ã of yield stress.

c. Total load applied to only one of the two cross arms.

Using this criteria, the safety factor designed into the stronbgack is 1 1 2 x .80 x .61 = 4.1 > 4.0. Based on this criteria, the calculated values for following components are:

STRONGBACK ATTACHMENT LUGS (4 total)

Material: ASTM A-36 Bearing Str ess In Lug: 12,850 psi < 33,000 psi allow.

Tensi 1 Stress In Plate: 18,939 psi < 22,000 psi allow, Shear Stress Due To Tear Out: 8,350 psi < 14,400 psi allow.

Linear Melds:

Allowable Load = 143,000 lbs.

Applied Load = 125,000 lbs. < 143,000 lbs.

Circular Welds:

Allowable Load = 126,000 lbs.

Applied load = 125,000 lbs < 126,000 lbs.

HOOK PINS Material: ASTM A-519 Applied Bending Stress = 27,000 psi < 46,200 psi allowable Applied Shear Stress = 6,070 psi < 21,000 psi allowable Applied Bearing Stress (in Hook Box, A-36) = 16,700 psi < 33,00 psi

'l 1 ow.

THE BEAM VELDMENT was analized for its varying cross-sections.

Material: ASTM A-36 Highest Bending Stress Applied 16,200 psi < 22,000 psi allowable.

DRYER & SEPARATOR SLING MPL @F19-E008 Drawing 767E438P3, rated capacity 73. 5T at 224.75" spacing.

The complete assembly was proof load tested at 140 tons (35 tons on each leg) and all structural welds were mag. particle inspected before and after proof load test by the manufacturer.

The ref. design record file: DRF ~F13-9. The Dryer 8: Separator Sling is designed for a safety factor of 5 or better with respect to ultimate material strength.

The components of the load chain are as follows:

SOCKET PINS, 117C4772P2 (4 total)

Material AMS 6414 at R 45-49, Ult. Tens. Str. St = 210,000 psi.

c Bending Stress At Rated Load SB

= 38,200 psi < 210,000 psi 210,000 osi 38,200 psi Shear Stress At Rated Load SV = 7,500 psi < 71,000 psi 71 000 osi 9 46 p 5 7,500 psi

Shear Stress In Eye = 2,900 < 14,500 psi allowable Sy design stress.

S.F. = 14,500' 5 with resp to allowable 2,900 Shear .at 'Pin Hol e Sy 1,960 psi < 14,500 psi allowable S. F.

la 500 =

7.4 > 5 with resp. to allowable 1,960 Tensi 1 Stress Across Eye ST 8,250 psi < 58,000 psi 58 000 =7>

S. F. 5 8,250 Mel'ds For Socket Mails to Lug Plate (3/8" Fillet)

SM

=

2,060 S.F. = 58,000 '28>

2,060

< 58,000 psi 5

Melds for Tubes to 2" Plate (4" Fillet),

= 6,100 psi < 58,000 psi SM 58 000 =9.5>

S. F. 5 6,100 HO~ID BOX 7675765 Materi al ASTM A-36, Ul t., Tens., Strgth. ST

= 58,000 psi.

Shear Stress to

~

Due Tearout At Hook Pin Holes Sv

= 2,187.5 psi < 14,500 psi allowable.

S.F. = = 6.6 > 5 with resp to allow.

Tensi 1 Stress Across Hold ST

= 2,932 psi < 58,000 psi 58,000 = 19.8 > 5 with resp. to allow.

S. F.

2,932 Bearing In Mall Sp

= 5,250 psi < 33,000 psi allowable.

33,000 = 6.3 > wi resp. to allow.

S. F. 5 h 5,250 Lugs on bottom of Hook Box are the same or stronger as lifting lug on Socket Box, therefore S. F >5

Melds For Lug Plates To Hook Box SM

=

~3,182 psi S.F. = 58 000 = 18 3,182

> 5 13,600 psi allowable with resp. to al1ow.

HOOK PINS 131C9228 Material ASTt1 A-519 Grade 4140 or 4142 RB 95 min.

l~iin. Yield Strength SY

= 70,000 psi.

Bending Stress SB 8,866 psi < 70,000 psi 70 000 =

S. F.

8,866

7. 9 > 3 Mith resp. to yield.

Shear Stress S 2,055 psi < 28,000 psi allowable 28 000 =

S. F. 13.6 With resp. to allowable.

2,055 WIRE ROPE (4 Total) 1-3/4" Dia. Imp. Plow Steel, Galv., Breaking Strength = 120 tons.

(Fittings are rated same or better) 120 Applied Load V2 = 20 tons S.F 20 TURNBUCKLES 2-3/4" " 24" G228 Rated Load: Safe Load 75,000 lbs.

Breaking Load: 5X75,000 = 375,000 lbs.

Applied Load:, V2 = 20T = 40,000 lbs.

REFUELING E S.F. =

UIPMENT SERVICE TOOLS 375,000 40)000 9.375 APL NF21-E001

> 5 238X151G2 SERVICE PLATFORM SLING, 117C4530P1 Rated capacity 7. 2 tons at 45'eg angle or 5. tons at 1 30'eg angle.

Load applied is 5 tons at 38'4'.

This 3-leg sling consists of the following components:

OBLONG LINK 1<" Cross Section Dia.

Safe Working Load 52, 100 lbs.

Min. Ul imate Morking Load 6X52,100 = 312,600 lbs.

Applied Load (Platform Meight) 10,000 lbs.

SF. = '3126) 10,000 5

MIRE ROPE (3 Total) 5/8" dia. 6. 19 IWRC, Breaking Strength 17.9T = 35,800 lbs.

(Fittings are rated same or better)

Applied load V = 5,405 lbs.

s.~. = " "'

5,405

s. e > s SAFETY EYE HOOD (3 Total)

Size 029, Rated Load 4 tons = 8,000 lbs.

Ultimate Load (Straightening Load) 5 X Rated Load = 5 X 8,000 = 40,000 lbs.

'Applied load V = 5,405 lbs.

S.~. =4'"'=

5,405

. S TURNBUCKLE 1",- 24", Rated Capacity 5 tons = 10,000 lbs.

Ultimate Load = 5 X Rated Load = 5 X 10,000 = 50,000 lbs.

Applied Load V = 5,405 lbs.

S.F. =

5,405 I,

S. ZS > S LIFT EYES Ot< SERVICE PLATFORM Per. Detail On Drawing 731E973 sh. 2, Sect. U-U.

Ref. Design Record File DRF PF13-6.

Safety Factor In Excess of 5.

LES: hjr/286-90 iC