ML20005A477

Summary Rept Review of Crane Design & Load Paths for Rancho Seco Nuclear Station,Unit 1

ML20005A477
Person / Time
Site:	Rancho Seco
Issue date:	06/30/1981
From:	Chidambaranatha, Estes T, Kaul P QUADREX CORP.
To:
Shared Package
ML20005A471	List: ML20005A470 ML20005A477
References
QUAD-1-81-811, TAC-08079, TAC-8079, NUDOCS 8106300375
Download: ML20005A477 (22)

Text

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SUMMARY

REPORT REVIEW OF CRANE DESIGN AND THEIR LOAD PATHS FOR RANCHO SECO NUCLEAR STATION UNIT 1 Prepared for:

SACRAMENTO MUNICIPAL UTILITY DISTRICT Sacramento, California l

Prepared by:

QUA09EX CORPORATION 1700 Dell Avenue Campbell, California 95008 June 1981 i

l 8106300375 l

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QUAD-1-81-811

.Imi t d7 CONTROLLED No., t -

SUMMARY

REPORT REVIEW OF CRANE DESIGN AND THEIR LOAD PATHS FOR RANCHO SECO NUCLEAR STATION UNIT 1 Prepared for:

SACRAMENTO MUNICIPAL UTILITY DISTRICT Sacramento, California Prepared by:

QUADREX CORPORATION 1.'00 Dell Avenue Campbell, California 95008 2ne 1981 bObO M k Prepared by

~~

Reviewed by a

P. Kaul S. Chidambaranathat

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e Estes /

MD Approved b s.

Q. A in Revision No.

Date Released By Charge Number 0

f./f#/ [

A3 SMD-0109

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• TABLE OF CONTENTS PAGE

1.0 INTRODUCTION

1-1 2.0 REVIEW SUDMARY 2-1 2.1 List of Overhead Handling Systems 2-1 2.2 Exclusion of Overhead Handling Systems 2-1 2.3 Identificaiton of Safe Load Paths 2-2 2.4 Measures to Ensure Load Handling Within Safe Load Paths 2-2 2.5 Tabulation of Heavy Loads, Lifting Devices, and Verification that Load Handling Procedures Exist 2-3 2.6 Review of Lifting Devices 2-4 2.7 Crane Inspection, Testing, and Maintenance 2-5 2.8 Review of Cranes 2-5 2.9 Crane Operator Training 2-5

3.0 REFERENCES

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• * " " ' 1. 0 INTRODUCTION This report, prepared by Quadrex Corporation for Sacramento Municipal Utility District (SMUD), summarizes the results of the review of the overhead load handling systems at SMUO's Rancho Seco Nuclear Generating Station. This review was performed to assist SMUD in preparing their six-month report in respone to USNRC's letter of December 22, 1981 (reference 1).

One Quadrex engineer surveyed the Rancho Seco Plant and interviewed the plant personnel to prepare a list of overhead handling systems and associated lifting devices, to locate the load paths and to identify the safety-related components. Other Quadrex engineers reviewed the design of cranes and lifting oevices to evaluate their adequacy per NUREG-0612.

Results of this survey and review have been summarized in section 2.0 of this report.

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2.0 REVIEW SUMARY Review results for the overhead handling system are presented in the following subsections. The order in which the e have been arranged is identical to that shown in section 2.1 of ene tsure 3 to reference 1.

2.1 List of Overhead Handlina Systems The overhead handling systems from which a heavy load drop may result in damage to safety-related components required for plar.t shutdown or decay heat removal are listed below:

o Polar Crane in the Reactor Building, o

Jib Crane in the Reactor Building, o

Stop Log Hoist in the Spent Fuel Building, o

Gantry Crane in the Turbine Building, o

. Monorail Hoists in the Auxiliary Building, and o

Auxiitary Bridge Crane in the Reactor Building.

2.2 Exclusion of Overhe'ad Handlina Systems.

The following cranes are excluded from the above list because these handle only fuel assembly or other loads which, by definition, are not heavy loads (reference 2):

a.

Spent Fuel Handling a-e in Fuel Storage Building,

.v b.

Main Fuel Handling Bridge in Reactor Building, c.

Auxiliary Fuel Handling Bridge in Reactor Building, and j

d.

Boom Crane in the Reactor Building.

No overhead handling system listed in section 2.1 above has yet been excluded from evaluation on the justification that sufficient physical separation exist from any potential load-impact point and safety-related component. Evaluation necessary for exclusion on this justification is l

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]p underway. Monorafi hoists in the Auxiliary Building may be excluded on this justification since a floor slab separates the movements of heavy loads from the safety-related components.

The Jib Crane in the Reactor Butiding can be excluded from the list of cranes in section 2.1, but from different justifications as stated below:

This crane moves the in-core instrumentation transfer cask. There are no safetv-related components in the vicinity of its load path, but, the crane is capable of moving the load over the reactor vessel. However, SMUD is undertaking modification of this crane.

This modification will include installation of mechanical and/or

~

electrical devices which would prevent inadvertent movement of the in-core instrumentation transfer cask over the reactor vessel.

The Stop Log Hoist in the spent fuel building can also be excluded, since SMUD is undertaking upgrading this hoist, or if necessary, will replace it to minimize the possibility of heavy load drop over the spent fuel stored in the pool.

The Auxiliary Bridge Orane in the Reactor Building is also excluded since it does not carry any heavy load over the reactor vessel or any safety-related component.

2.3 Identification of Safe Load Paths Load paths for heavy loads handled by the overhead handling systems listed in section 2.1 (except Jib Crane, Stop Log Hoist, and Auxiliary Bridge Crane, which are excluded) are identified in general arrangewnt drawings shown in figures 1 through 10 (see also table 1).

Locations of safety-related components in the vicinity of these load paths are also identified in these drawings.

2. 4 Measures to Ensure Load handlina Within Safe Load Paths Movements of heavy loads handled by the overhead handling systems listed in section 2.1 are governed by approved operating procedures. These 2-2

QUAD-1-81-811

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• Q Mfdhproceduresprovideguidanceformovingloadsfromonelocationtothe other. Even though load paths for the movement of heavy loads have not been explicitly. stated in these operating procedures, the load paths identified in figures 1 through 10 are the safest and, in general, the shortest routes. Due to plant changes, and changes in the operating conditions, in the future, it may be necessary to follow loads paths other than those shown here. Any such movement, however, will be in accordance with the approved operating procedure governing the crane or the load. This practice is consistent with SMUD's general safety rules and practices.

All movements of heavy loads are performed by qualified operators who are supervised by experienced foremen. These personnel have achieved these positions by demonstrating their craft knowledge and ability in performing the required work. Adherence of these experienced persorinel to the operating procedures ensures that the movements of heavy loads follow the safest path possible.

2. 5 Iabulation of Heavy Loads, Lifting Devices, and Verification that Load Handling Procedures Exist Heavy loads handled by each crane listed in section 2.1, their weight, and the lifting devices used are listed in table 2.

Handling of these heavy loads are governed by written procedures. These procedures, in general, include se:.:tions such as Purpose, Refereices, Limitations and Precautions, Special Tools and Equipment, Testing and Acceptance Cri-teria, Prccedurcs, Checklists, etc., and meet the requirements of section 5.1.1.(2) cf NUREG-0612.

In the future, due to plant changes, it may be necessary to use the cranes listed in section 2.1 to handle additional heavy loads not' listed in table 2.

Handling of any such additional loads, however, will be performed after engineering and safety review and in accordance with approved written procedure.

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l The Gantry Crane will be used in the future to move spent fuel casks which constitutes a heavy load.

The consequences of potential cicps of 2-3

QUAD-1-81-811

., a.o n i l it hspentfuelcaskswereanalyzedearlierbyBechtelandsubmittedtothe NRC.

However, before the Gantry Crane is actually used to move the spent fuel cask, this analysis will be reviewed.

2.6 Review of Lifting Devices Lifting devi es listed in table 2 were designed according to industry standards which were applicable at the time these were procured and using good engineering practice. Within the time frame allowed, all.of thse lifting devices could not be reviewed for compliance with the applicable requirements of ANSI N14.6-1978 or ANSI B30.9-1971.

Further evaluation is under way. However, these devices are proof-tested before actually used and are periodically load-tested and inspected in accor-dance with apprcved written procedures. Thus, even though evaluations of these devices per ANSI N14.6-1976 or ANSI B30.9-1971 are not complete, SMUD considers these to be safe.

These lifting devices used with the Polar Crane were evaluated to deter-mine their adequacy in accordsnce with the applicaole sections of

. ANSI N14.6-1978 and ANSI B30.9-1971.

In this evaluation, a dynamic 0

loading factor of 1.25 was used which is consistent with the previous evaluation reported ir. amendment 15, appendix 9A of the FSAR.

Evalua-tion results shcwed that the lifting devices satisfy the ANSI stress criteria except that the evaluation of the Internals Handling Extension is under way. The nominal lifting load for this device is 357 kips, and ths test load is 528 kips. The actual lcad is 237 kips.

Thus, even though the capacity per ANSI N14.6-1978 has net yet been determined, since the test load far exceeds the actual load, the device is con-sidered adequate.

It is noted here that the above evaluation was based on stress design factors specified in section 3.2.1.1 of ANSI N14.6-1978:

three for checking with the yield stress, and five for checking with ultimate stress. Doubling these factors per section 6 of ANSI N14.6-1978 (i.e.,

using six times and ten times the static plus dynamic loa'ds for checking with the yield stress and the ultimate stress, respectively), is not considered justified for the following reasons:

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a.

For conventional structural and stress analysis of tension members, a safety-margin of 1.5 is typically used, which is equivalent to using a stress design factor :f 1.5.

Unless the uncertainties of the load, the material, and the analyses method are extreme, the use of a very high stress design factor does not increase the real margin of safety.

In other worris, if the reliability is likely to be close to 100 percent with a stress design factor of 3.0, increasing this factor to six cannot increase the reliability any further.

b.

Lifting devices used in Rancho Seco Plant uTjergo periodic inspection and load test. This reduces the uncertainties significantly and should enable the use of lower stress design factors.

2.7 Crane Inspection, Testina, and Maintenance Crane inspection, testing, maintenance, and surveillance procedures have been developed on the basis of the requiremen'ts of ANSI 830.9-1976, chapter 2-2.

f 2.8 Review of Cranes The cranes listed in table 2 were designed in accordance with industry standards which were applicable at the time these were procured. The Polar Crane and the Gantry Crane were designed according to EOCI and AISC specifications and USAS 830.2 standard. The design specifications of these cranes were reviewed for complirece with the apolicable guide-lines of CMAA specification 70.

The review result showed that the cranes satisfy the general guidelines of CMAA specification 70 which are applicable for evaluating the potential for heavy load drop.

I j

2.9 Crane Operator Training 1

A training program has been developed in accordance with chapter 2.3 of ANSI 830.2-1976. Additionally, an administrative guideline delineating the control of crane operator trening has been developed for implemen-tation. This action is considered adequate and meets the intent of section 5.1.1(3) of NUREG-0612 for the training, qualification, and conduct of crane operators.

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TABLE 1 LOAD PATHS FOR MOVEMENT OF HEAVY LOADS Load Path Identification Figure No.

Safety Related Equiement A.

REACTOR BLDG.

1.

Polar Crane a) Plenum Assembly Transfer Path 1

Reactor Vessel b) Core Support Transfer Path 2

Reactor Vessel c) Missile Shield Transfer Path 3

Reactor Vessel d) RPV Closure Head Transfer Path 4

Reactor Vessel e) Basket Cask Transfer Path 5

None f) Basket Cask Transfer Path 6

Noae g) Reactor Handling Tools Transfer Path 7

Reactor Vessel B.

TURBINE BLDG.

1.

Gantry Crane a) New Fuel Handling Transfer Path 8

None C.

AUXILIARY BLDG.

1.

Monorail Hoist High Press. Inject.

Equipment Hatch (Floor 9 & 10 Pumps P238A, P235, Makeup Plugs) Moving Path Pump P-234, Decay Heat Removal Coolers E260A, E260B

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TABLE 2

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LIST OF CRANES, LCADS AND LIFTING DEVICES Bldg./ Crane Loads Handled Wt. (lbs)

Lifting Devices Used A.

REACTOR BLDG.

1.

Polar Crane Plenum Assembly 110,000 (dry)

1) Head & Internals 96,000 (wet)

Handling Fixture (includes Adapter)

11) Internals Handling Extension 111) Internals Handling Adapter Pendant iv) Internals Indexing Fixture Basket Cask 12,000 225,000(dry),fead& Internals Cora Support Assembly Handling Fixtures &

197,000 (wet)

Adapter & Internals 5 Indexing Fixture Missile Shield 178,000 Slings Closure Head 162,400 i) Head & Internals Handling Fixture Closure Head 34,600 11)

Internals Handling Service Structure 12,000 Extension iii)

R.V. Head & Service Structure-Fixed Pendants Lifting Assembly iv) Turnbuckle Pendant Assembly Reactor Handling Tools a) Head & Internals Handling Fixture 12,000 b)

Internals Indexing Fixture 12,000 l

.a,

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{g;g QUAD-1-81-811

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M TABLE 2 (Continued)

LIST OF CRANES, LOADS AND LIFTING DEVICES Bldg./ Crane Loads Handled Wt. (1bs)

Lifting Devices Used t

2. ' Jib Crane In-core Instrumentation 10,300 Slings Transfer Cask 3.

Apxiliary None Identified Slings Bridge Crane 8.

SPENT FUEL BLDG.

1. 'New Fuel Fuel Assembly 1,600 Slings Handling Bridge Crane 2.

Stop Log Hoist Stop Logs 3,081 Air Winch & Wirerope (Tuggers C,

TURBINE BLOG.

1.

Gantry Crane -

New Fuel Cask 7,300 Slings Spent Fuel Cask-136,000 D.

AUXILIARY BLOG.

1.

10-Ton Floor Plugs 16,540 Slings Monorail Heat Exchanger 5,800 Hoist Pump Motors 4,925 (Item A-1 in Referi.ne #8) 2.

10-Ton Hoist Floor Plugs 13,500 Slings (Item A-5 in Reference #8) a

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3.0 REFERENCES

a. Letter dated 12/22/80 from Nuclear Regulatory Comission to all licensees of Operating Plants. b. NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, USNRC, July 1980. 8 o l l 3-1 L}}