ML17319B392

Forwards Phase Ia Response to NUREG-0612 Re Control of Heavy Loads.Phase Ia Is Resubmittal of Part of Response to Section 2.1 of Encl 3 of DG Eisenhut .Response to Technical Evaluation Rept Also Encl

ML17319B392
Person / Time
Site:	Cook
Issue date:	06/18/1982
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR AEP:NRC:0514C, AEP:NRC:514C, NUDOCS 8206290388
Download: ML17319B392 (53)

Text

REGULATORY

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AOCBSSION NBR:8206290388 DOC ~ DATE! 82/06/18 NOTARIZED:, NO.

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DOCKET FACIL:50-315 Donald O,

Cook Nuclear Power Plants Unit is Indiana tz

'05000315 50-316 Donal d G,

Cook Nucl ear Power Pl ant+ Unit 2R Indiana 8

05000316

'AUTH,NAME AUTHOR AFFILIATION HUNTERER ~ ST Indiana 8 Michigan Electr ic Co.

~R BC IP. NAME RECIPIENT AFF ILIATION DENTONIH ~ RE office of Nuclear Reactor Repulationi Director W

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SUBJECT:

Forwards Pgase Ia response to NUREG-0612 re contr ol qf.

heavy loads. Phase ia is r esubmittal of part of, response to Section

2. 1 of Encl 3 of DG Eisenhut 801222 ltr.Response to technical evaluation rept also encl.

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TITLE: Conrtol of Heavy Loads Near Spent Fuel (USI A-36) Operating Reactor NOTES:

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INDIANA fir MICHIGAN ELECTRIC COMPANY P. O.

BOX 18 BOWLING GREEN STATlON HEW YORK, N. Y. 10004 June 18, 1982 AEP:NRC: 0514C

.Donald C. Cook Nuclear Plant Unit Nos.

1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 CONTROL OF HEAVY LOADS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

Our response to NUREG-0612 is being submitted in two phases as suggested by your staff.

This letter and its attachments are Phase Ia.

Phase Ia is a resubmittal of part of our response to the "Control of Heavy Loads",

Section 2.1 of Enclosure No.

3 to Mr. D. G. Eisenhut's letter dated December 22, 1980.

This letter also includes our response to the draft Technical Evaluation Report (TER) which we discussed with your staff and your consultant in a telephone conversation on December 17, 1981.

Therefore, in the interest of clarity, we are hereby superseding AEP:NRC:00514 in its entirety by this letter.

Phase Ia is a partial response to "Control of Heavy Loads" Section 2.1, and provides a detailed review with respect to cranes that operate over the reactor, in the vicinity of the spent fuel pit, and the major Turbine Building Cranes.

Phase Ib will respond to all other cranes and hoists encompassed by Section 2.1.

This Phase Ib detailed review will be presented at a later date.

Phase II of our response will address Sections 2.2, 2.3, and 2.4 of Enclosure No.

3 to Mr. D. G. Eisenhut's December 22, 1980 letter.

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Mr. H. R. Denton AEP:NRC:0514C This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, R. S. Hunter Vice President RSH/sag Attachments cc:

John E. Dolan Columbus R.

W. Jurgensen W.-G. Smith, Jr.

Bridgman R.

C. Callen G.,Charnoff Joe Williams, Jr.

Resident Inspector at Cook Plant Bridgman

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ATTACHMENT TO AEP:NRC:0514C DONALD C.

COOK NUCLEAR PLANT CONTROL OF HEAVY LOADS NUREG-0612 2.1 GENERAL REQUIREMENTS FOR OVERHEAD KQlDLING SYSTEMS.

NUREG

0612, Section 5.1.1, identifies several general guidelines related to the design and operation of overhead load-handling systems in the areas where spent fuel is stored, in the vicinity of the reactor

core, and in other areas of the plant where a load drop could result in damage to equipment required for safe shutdown or decay heat removal::

Information provided in response to this section should identify the extent of potentially hazardous load-handling operations at a site and the extent of conformance to appropriate load-handling guidance.

2.1.1 "Report the results of your review of plant arrangements to identify all overhead handling systems from which a load drop may result in damage to any system required for plant shutdown or decay heat removal (taking no credit for any interlocks, technical specifications, operating procedures, or detailed structural analysis)."

Our review has identified 'the following overhead handling systems at the Donald C. Cook Plant which fall under the scope of this section:

(a)

Auxiliary Building Crane, located in the Auxiliary Building at elevation 683'.

(b)

Polar Crane, one located in each Containment Building at elevation 715' 74".

(c) 30 Ton Bridge Crane, located in the Circulating Mater Pump and Screen House at elevation 621'.

The detailed review of this crane will be presented at a later date.

For excluded systems, see our response to Section 2.1.2.

2.1.2 "Justify the exclusion of any overhead handling system from the above category by verifying that there is sufficient physical separation from any load-impact point and any safety-related component to permit a determination by inspection that no heavy load drop can result in

~ damage to any system or component required for plant shutdown or decay heat removal."

Our review has identified the following overhead handling systems at the Donald C. Cook Plant which fall under the scope of this exclusion section:

(a)

The turbine room is equipped with one 240/50T main overhead crane-at elevation 685' 8", and two 10/4T auxiliary cranes at elevation 670' ll".

None of these cranes pass over equipment required for plant shutdown or decay heat removal as can be seen on color coded General Arrangement Drawing numbers 12-5161, 12-5164, 12-5165 and 12-5170 submitted in response to item 2.1.3a.

(b)

Manipulator

Crane, one located in each Containment Building at elevation 652'-74".

Each manipulator. crane is designed for the shuffling, removal and replacement of new, partially

spent, and spent fuel assemblies, one at a

time; therefore by definition, these cranes do not handle heavy loads.

(c)

New and Spent Fuel Handling

Crane, Building at elevation 650'.

Similarly item (c) above, the New and Spent Fuel to handle single fuel assemblies and heavy loads.

located in the Auxiliary to the manipulator

crane,

'andling Crane is designed therefore does not handle

2.1.3 "Nith respect to the design and operation of heavy-load-handling systems in the containment and the spent-fuel-pool area and those load-handling systems identified in 2.1-1, above, provide your evaluation concerning compliance with the guidelines of NUREG 0612, Section 5.1.1.

The following specific information should be included in your reply:

a.

"Drawings or sketches sufficient to clearly identify the location of safe load paths, spent fuel, and safety-related equipment."

The attached General Arrangement Drawing numbers; 12-5161, 12-5162,-

12-5163, 12-5164, 12-5165, 12-5166, 12-5167, 12-5168, 12-5169, and 12-5170 have been color coded to identify load handling

areas, and equipment required for safe reactor shutdown and decay heat removal.

Equipment required for safe reactor

shutdown, as defined in FSAR Appendix 0, and decay heat removal is shown in red.

The load handling areas are shown in yellow.

The hatched yellow areas indicate the projected load handling area below separating floors or ceilings; spent fuel is stored in the spent fuel pit after discharging from the Reactor Vessel through the Fuel Transfer System.

Safe load paths are being developed for the heavy loads indicated on Tables 2.1.3.C.l and 2.1.3.C.2, found in the response to item 2.1.3c below, and'ill be incorporated into the appropriate procedure as soon as possible.

These component specific safe load paths remain within the indicated load handling areas and are based on the general concept of-handling heavy loads as close to the operating floor as is feasible, in order to minimize the potential load drop impact energy, and with the maximum possible horizontal separation from spent fuel.

Many of the tabulated heavy loads handled in the Reactor Containment Building must pass over the Reactor Vessel.

En these

cases, the safe load path is established by considering the minimum time spent over the reactor

vessel, the minimum height required for obstacle clearance, and the minimum number of crane operations which require load direction changes.

All safe load paths for the heavy loads identified remain within the load handling areas indicated on the attached General Arrangement Drawings.

This approach of utilizing individual component safe load paths contained within the component's specific handling or maintenance procedure was developed in lieu of providing fixed load paths oa facility structures such as markings on floors, walls and crane rails or supports.

The limited space available for handling loads in an ice condenser containment, the tight configuration of the Auxiliary Building and the lack of prominent structural members over which to handle heavy

loads, would require the application of many multi-color safe load paths that over"ap and would most likely lead to crane operator confusion.

Markings on crane rail support structures and/or walls would require the crane operator to divert his/her attention from the load and obstacles near its load path for observation of such

markings, since crane operation is radio or pendant controlled from the operating floor.

Therefore, we have concluded that the safe load paths contained within specific handling procedures is the correct method to pursue.

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

The maintenance supervisor or leadman directs the crane operator and is responsible for ensuring that heavy load handling remains within the established safe load paths.

Anyone observing load handling operations which depart from the safe load path can signal for the crane operator to stop all crane motion.

When circumstances require deviations from established, safe load handling paths an alternate safe load path will be formulated and incorporated into the handling procedure by temporary sheets as provided for in Plant Manager' Instruction PMI-2010.

Miscellaneous loads within the Reactor Containment Building will normally be handled only when the missile shields are in place over the Reactor Vessel and will follow the general safe load path practice stated in response to 2.1.3a above.

Should the need arise to handle a

heavy load when a specific procedure is not available and the missile

~

shields are not in

place, a

safe load path will be prepared and incorporated into a

special procedure.

In the Auxiliary Building, miscellaneous loads will be handled as prescribed for in procedure 12 MHP 5021.001.036 "Control of Heavy loads in Auxiliary Building".

For inclusion of heavy load paths into specific procedures, see our response to Item 2.1.3.a.

c.

"A tabulation of heavy loads to be handled by each crane which includes the load identification, load weight, its designated lifting device, and verification that the handling of such load is governed by a written procedure containing, as a minimum, the information ident"f'ed in HURZG 0612, Section 5.1.1(2)."

Attached Tables 2.1.3.C.1 and 2.1.3.C.2 indicate the heavy loadk handled in the Auxiliary Building and Containment Building respectively'.

These tables identify the loads

handled, the load weights, lifting devices utilized, the appropriate handling procedure and the crane used for the lift.

Table 2.1.3.C.3 is a partial index of plant procedures which are used to control the handling of heavy loads.

A review of the procedures listed in tables 2.1.3.C.1 and 2.1.3.C.2 indicates partial compliance with the recommendations of NUREG

0612, Section 5.1.1 (2).

As the component specific safe load paths are being incorporated into these procedures, additional updating will be performed to assure the adequate inclusion of:

required equipment identification, prereq'uisite inspection and acceptance criteria, step by step sequences, and special precautions.

The D.

C.

Cook Plant does therefore does not have a specific Prior to spent fuel cask handling will be both consistent with FSAR intent of NUREG-0612.

not currently ship spent fuel and spent fuel cask handling procedure.

a procedure will be prepared which commitments and responsive to the

d. "Verification that lifting devices identified in 2.1.

3-c, above, comply with the requirements of ANSI N14.6-1978, or ANSI B30.9-1971 as appropriate.

For lifting devices where these standards, as supplemented by NUREG 0612, Section 5.1.1(4) or 5.1.1(5),

are not met, describe any proposed alternatives and demonstrate their equivalency in terms of load-handling reliability."

Arrangements are currently in progress to provide for verification of lifting devices identified in Tables 2.1.3.C.1 and 2.1.3.C.2.

Design criteria for the reactor vessel head and internals lifting rigs have been requested from Westinghouse Electric Corporation.

The remaining lifting devices indicated on Tables 2.1.3.C.1 and 2.1.3.C.2 are being evaluated as to compliance with ANSI N 14.6-1978 or ANSI B30.9-1971.

This response to 2.1.3d supersedes our response given in AEP:NRC:0514 which incorrectly referenced ANSI N14.6-1978.

e. "Verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect to crane inspection,

testing, and maintenance.

Where any exception is taken to this standard, sufficient information should be provided to demonstrate the equivalency proposed alternatives."

Cranes and hoists at the D.

C. Cook Plant are classified into the following two groups:

Re ular Service, which corresponds to "Normal Service" stated in ANSI B30.2, include:

Auxiliary Building Crane Turbine Building Hain crane Two Turbine Building 'Auxiliary cranes gtandb gesvice or ~store e, corresponding to "special or infrequent service" as stated in ANSI B30.2 include:

Two Polar Cranes Two Manipulator Cranes New and Spent Fuel Handling Crane Circulating Water Pump and Screen House Crane.

Crane inspection, testing and maintenance at the D.

C.

Cook Plant is primarily controlled by hfaintenance Head Instruction - MHI 5030 and

attachments

thereto, the AEP safety

manual, maintenance procedures, preoperational test procedures, quality control inspection procedures and the crane manufacturer's parts list, operation and maintenance instructions.

These documents were reviewed against the item by item criteria set forth in chapter 2-2 of ANSI B30.2.0-1976.

The re'suits of this review are presented on Tables 2.1.3.E-1

" through-4, and are structured to the format of the ANSI standard.

Crane inspection and testing direction is in close agreement with the ANSI B30.2 criteria with the single exception indicated on Table 2.1.3.E-1.

As can be seen on Tables 2.1.3.E-3, and -4, prescribed crane maintenance is not in conflict with the ANSI B30.2 criteria; however,:

there are several B30.2 maintenance items which have not been specifically addressed as indicated on Table 2.1.3.E-4.

f. "Verification that crane design complies with the guidelines of CNAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design requirements for instances where specific compliance with these standards is not provided."

The Auxiliary Building Crane and the two Polar Cranes were designed and manufactured in 1969-1970 by the Whiting Corporation according to the guidelines of E.O.C.I Specification 61 and ANSI B30.2-1967.

These two standards were the predecessors of C~i Specification 70 and ANSI B30.2-1976, respectively.

In order to determine -compliance, studies were made comparing the specifications item by item, under which the cranes were designed and manufactured, against the more recent versions of the specifications.

The cranes were then analyzed in those areas where a change in the specifications occurred.

The study comparing the ANSI standard and the resulting analysis of the cranes in the areas of difference, indicated that the cranes were in compliance.

The study comparing CF~ Specification 70 with E.O.C,I.

Specification 61 was performed by the Whiting Corp.

and indicated several areas where detailed calculations were required to verify compliance.

These calculations showed that there were eight areas in which the cranes did not meet C>fAA Specification 70 Revision 75 design standards.

These eight areas are discussed below:

150/20 Ton Auxiliar Buildin Crane The drum pinion strength of the reduction gearing is exceeded by durability is exceeded by 45%.

main hoist extra 8%

and the gear Disposition Load lifting will be limited to 75 Tons'aximum until this item is resolved.

2.

The main block bronze sheave bushing is overstressed by 28%.

Disposition Whiting states that the 1,000 psi working pressure stated in CNAA //70 - Rev.

75, is not related to any specif ic type of bearing material supplied.

The existing bushings in the block sheaves are l/79 bronzoid, which has an ultimate compressive stress rating of 10,000 psi, and, Whiting further states, at a safety factor of 5

as specified by CNAA

//70, the bushing should be adequate for working loads up to compressive stresses of 2,000 psi.

Therefore, the bushing is satisfactory.

3.

The auxiliary hoist sheave material is Class 35 cast iron with an ultimate tensile strength of 35,000 psi, instead:

of the Class 40 cast iron with an ultimate tensile strength of 40,000 psi as specified in CHAA-70.

Disposition - Whiting states that sheaves are generally stressed in compression between their rope contact area and hub.

Tensile stresses are usually of minor consequence at bearing hubs and at rope entry points in their flanges.

We concur that the sheave material is satisfactory.

4.

The horsepower and torque rating of the auxiliary hoist motor is exceeded by 1. 5% when handling a rated load of 20 tons.

Disposition -

The horsepower and torque rating. of the auxiliary hoist motor is exceeded because the weight of the load block was added to the 20 ton capacity of the hoist.

The gears,

bearings, and brake are all adequate for the additional load.

Therefore, no modification is

'ecessary since at worst the motor would stall when attempting to lift a full-capacity load.

The longitudinal stiffeners are not located proper3y and do not meet moment of inertia requirements.

6.

Disposition A design change will be initiated to add longitudinal stiffeners to the outside face of each main girder web plate.

In the event of an axle failure, the bridge end truck ~

drop 1 7/8", instead of the allowed 1".

Disposition-A design change will be initiated to weld bars to the truck plates across the runway rail head near each bridge wheel.

250/35 Ton Containment Polar Cranes 7.

The auxiliary hoist sheave material is Class 35 cast iron with an ultimate tensile strength of 35,000 psi, instead of the class 40 cast iron with an ultimate tensile strenght of 40,000 psi as specified in CMAA-70.

Disposition Same as Item 3

above; no modification is necessary.

8.

The girder longitudinal stiffener is not located properly.

Disposition According to the evaluation by Whiting, the location of the longitudinal stiffeners was determined by the weld length required to transfer bridge rail loadings through the intermediate short depth stiffeners to both webs of each

girder, as well as the overall depth required in these short depth stiffeners to transfer the rail load moment across the span between girder webs.

Whiting believes that the longitudinal stiffener location specified in CMAA-70 has been established based on the extreme case where only full depth internal stiffeners may be used and that it neglects the reduction in effective unsupported web panel lengths provided by the short depth internal stiffeners.

We concur with Whiting's conclusion that the probability of web buckling in this critical web compression area is reduced to an extent equal to or exceeding the reinforcement required by the present specification.

Therefore, girder stiffener modification is not needed.

The above review indicates that the containment polar cranes are entirely adequate.

Two modifications will be made for the auxiliary building crane - installation of additional longitudinal stiffeners and the installation of bars to reduce end truck drop.

Table 2.1.3.F.l has been included to help identify where concerns expressed in the December 17, 1981 telephone conference among

NRC, Franklin Research Center and AEP have been addressed.

The two (2) "No" entries in the compliance column for the Auxiliary Building crane have been addressed in the preceding item descriptions.

g.

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

A review of crane operator skill Training lessons, QC inspection procedures and the safety manual utilized at the D.

C.

Cook Nuclear Plant for operator training, qualification and conduct, was made against the provisions of chapter 2-3 of ANSI B30.2.

The verification tables 2.1.3.G-1,2,3,

& 4 indicate the comparison of ANSI B30.2 - 1976 with D, C.

Cook Plant procedures and programs.

In some instances ANSI standard items are not specifically addressed but no stated exceptions are taken.

A Maintenance Head Instruction (MHI) will be prepared to address this ANSI Standard on Operator Training.

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Load Table 2.1.3.C.3 handling Procedure Index Identification Number 12 MHP 5021.002.001 MHP 5021.002.002 12 MHP 5021.001.036 12 MHP 5021.001.032 Title Maintenance Repair Procedure for Reactor Coolant Pump Maintenance Repair Procedure for Reactor Coolant Pump Motor Control of Heavy Loads in Auxiliary Building Containment Airlock and Equipment Hatch Removal and Replacement.

Revision No.

and Date Revision 2

6-17-78 Revision 1

4-29-75 Revision

//1 11/24/81 Revision 0

5-17-79 MHP 5021.001.002 Reactor Vessel Head Removal and Replace ment.

Revision 0

10-16-74 MHP 5021.001.003A Reactor Vessel Upper Internals Removal and Replacement Revision 0

9-12-74 MHP 5021.001.003B 12 MHP 4050 FDF.025 Reactor Vessel Lower Internals Removals and Replacement Containment Building Polar Crane Operating Instructions Revision 0

9-12-74 Revision

//1 10-20-81 12 i&PP 4050 FDF.026 Removal and Reinstalla-tion of Reactor Vessel Missile Blocks and Vertical Wall Sections Revision 1

12-8-81 12 MHP 4030 STP.015 12 MHP 4050 FDF.041 Auxiliary Building Crane Interlock Verification-Fuel Handling Inspection of Irradiated Fuel Assemblies (Using the Auxiliary Building Crane)

Revision 1

11-21-78 Revision 80 4-19-79

TABLE 2.1.3.C.3-1 12 MHP 4050 FDF.042 12 MHP 4050 FDF.011 Load Monitoring Device Verification Instructions Auxiliary Building Crane Operating Instructions Revision 80 10-16-80 Revision 1

11-21-78 12 MHP-SP-006 Shipment of Reactor Vessel Materials Surveillance Capsule Using SWRI Cask and Equipment Revision 0

1-24-80

Table 2.1.3.E 1

Verification of 'ANSI B30;2 -'1976'A lication B30.2.0 Section D. C. Cook confirmed A lication Comments 2-2.1 Inspection 2-2.1.1 Inspection Classification A.

B.

1 2

YES YES YES Not firmly stated.

2-2.1.2 - Frequent Inspection A.

1 2

YES Partial Limit switches tested prior to load movement.

6 7

8 YES YES YES YES Not specifically addressed.

Not normally used at D. C..

Cook Plant.

See exceptions below Not specifically addressed.

2-2.1.3 Periodic Inspection A-E and G-I F

2-2.1.4 - cranes not in regular use YES Partial YES Load monitoring devices only

TABLE 2.1.3.E-1-2 B30.2.0 Section D. C. Cook confirmed A

lication Comments 2-2.1.5 - Inspection Records YES Report compiled for each PM Inspection.

l.

Attachment No.

18 to >HiI 5030 allows 4 broken strands per lay prior to sling replacement while ANSI B30.9-1971 allows only 3.

Inspection for heat damage is not specifically addressed.

~

~

Table 2.1.3.E-2 Verification of ANSI B30.2.0-1976 A lication B30.2.0 Section D. C. Cook confirmed A lication Comments 2-2.2 Testing 2-2.2.1 Operational Tests 1

2 3

4 YES YES YES YES Includes all 5 speeds.

2-2.2.2 - Rated Load Test A

YES Polar cranes Tested in excess of 125%

rated load for special Lifts of Reactor Vessel and steam generator.

B 1

2 3

4 YES YES YES YES

TABLE 2.1.3.E-2-2 B30.2.0 Section D.

C. Cook confirmed A lication Comments C

1 2-2.3.4 Lubrication Not Specifically:

addressed Not Specifically addressed Not Specifically addressed Not Specifically addressed Not Specifically addressed Not Specifically addressed Manufacturers Parts List, operating and maintenance Instruction A

B YES Not Specifically addressed

~

~

~

Table 2.1.3.E 3

Verification of ANSI B30.2.0 1976 A lication B30.2.0 Section 2-2.3 Maintenance D. C. Cook Confirmed Comments 2-2.3.1 Preventive Maintenance A

Partial Crane maintenance conducted in accordance with manufacturers Parts List, operating and maintenance Instructions.

B Not specifically addressed.

2-2.3.2 Maintenance procedure Not specifically addressed 2-2.3.3 Adjustments and Repairs A

Manufacturers Parts List, Operating and Maintenance Instructions B

1 2

3 4

YES YES YES YES

Table 2.1.3.E 4

Verification of ANSI B30.2.0'-

1976 A lication B30.2.0 Section D. C.

Cook Confirmed A lication Comments 2-2.4 Rope Inspection, Replacement and maintenance 2-2.4.1 Inspection A

YES Not Specifically addressed 2-2.4.2 Rope Replacement Not Specifically addressed 2-2.4.3 Rope Maintenance Not Specifically addressed

TABLE 2.1.3.F.1 Item "f".

AREA OF CONCERN

l. Impact Allowances REFERENCE IN CtfAA-70 3.3.2.1.1.3 REVIEMED BY MERITING CORP.

YES YES YES IS COMPLIANCE INDICATEDP AUX. BUILDING POLAR

2. Calculations Torsion 3.3.2.1.3 YES YES YES

3. Longitudinal Stiffeners

4. Allowable Compressive Stress 3.3.3.1.2 3.3.3.1.3 3.3.3.3 3.4.3 YES YES NO YES YES

5. Fatigue 3.10 3.3.3.1.3 YES YES YES

6. Hoist Rope 7.

Drum Design 4.2 4.4.1 4.4.3.1 YES YES YES YES YES YES

8. Drum Design-Groove Pitch 4.4.3.2 YES YES YES

9. Gear Design

10. Bridge Brake Design ll. Hoist Brake Design 12.

Bumper Stops 4.5 4.7.2 4.7.4

4. 12 YES YES YES YES NO YES YES YES YES YES YES YES

13. Rules for Static Control System

14. Restart Positioq 5.4.6 5.6.2 YES YES Not Applicable Not Applicable YES

~

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~

Table 2.1.3 G -

1 Verification 'of ANSI B30.2.0 - 1976 A lication B30.2.0 Section D. C. Cook confirmed A lication Comments 2-3.1 Qualifications for and conduct of operators 2-3.1.1 Operators of cab-operated and Pulpit-operated N.A.

Not used at D.C.

Cook Plant.

2-3.1.2 Qualifications for operators of cab-operated and Pulpit-operated cranes cranes.

N.A.

Not use at D. C.

Cook Plant.

2-3.1.3 Operators of Floor-operated cranes.

Not specifically addressed.

2-3.1.4 Qualifications for operators of Floor-operated cranes.

Partial Not specific enough.

2-3.1.5 Operators of Remote-operated cranes.

Not specifically addressed.

2-3.1.6 Qualifications for operators of Remote-operated cranes Not specifically addressed.

TABLE 2.1.3.G-1-2 B30.2.0 Section 2-3.1.7 Conduct of operators A

B C

9 E

F G

D. C. Cook confirmed A lication YES YES YES Partial YES YES Partial Comments Not specific enough Not specific enough H

N 0

Par tial Partial Partial NA NA Partial Partial Not specific enough Not specific enough Not specific enough Not specifically addressed; No outdoor cranes used.

No outdoor cranes used.

Not specific enough Not specific enough Not specifically addressed.

Table 2.1.3.

G 2 Verification of 'ANSI 'B30:2.0 1976 A lication B30.2.0 Section 2-3.2 Handling the Load 2-3.2.1 Load weight 2-3.2.1.1 Special Heavy Lifts A

B C

D E

F G

HI D. C.

Cook confirmed A lication YES Partial YES YES Comments Needs updated prior to Lift Not specif ically addressed.

2-30202 2-3.2.3 2-3.2.4 Attaching the Load i~foving the Load Hoist Limit Device A

B YES YES YES Prior to using crane.

Not specifically addressed.

Table 2.1.3.G 3

Verification 'of 'ANSI 'B30.'2;0 - 1976 A lication B30.2.0 Section D. C. Cook confirmed A lication Comments 2

3 ~ 3 Signals 2-3 '.1 Standard signals YES 2

3 ~ 3

~ 2 Hand signals 1 Multiple Trolley cranes 2

A B

C 3

YES NA NA NA NA NA NA Not used at D.

C..

Cook Plant.

Table 2.1.3 G 4 Verification of ANSl B30.2.0 - 1976 A lication B30.2.0 Section D. C. Cook confirmed A lication Comments 2-3.4 Miscellaneous 2-3.4.1 Ladders A

B Par tial Not specific enough Not specifically addressed.

2-3.4.2 Cabs A

NA NA Not used at D. C.

Cook Plant.

Not used at D. C.

Cook Plant.

2-3. 4.3 Fire Eztinguishers YES

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