ML18051A638

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Control of Heavy Loads (C-10),CPC Palisades Plant, Technical Evaluation Rept
ML18051A638
Person / Time
Site: Palisades 
Issue date: 10/14/1983
From: Bomberger C
FRANKLIN INSTITUTE
To: Singh A
NRC
Shared Package
ML18051A639 List:
References
CON-NRC-03-81-130, CON-NRC-3-81-130, REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR TAC-47129, TER-C5506-378, NUDOCS 8310190076
Download: ML18051A638 (25)
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TECHNICAL EVALUATION REPORT CONTROL OF HEAVY LOADS. cc-10>.

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  • l CONSUMERS PQWER COMPANY PALISADES PlJ\\NT

. NRCOOCKETNO. 50-255 NACTACNO. 47129 NRC CONTRACT NO; NRC-03-81-130.

Prepared by Franklin Research Center 20th and Race Streets Philadelphia, PA 19103 Prepa~dloi Nuclear Regul~tory Commission Washington, O;C. 20555 FRC PROJECT 05506 FRC ASSIGNMENT 13 FRCTASK 378 Author: C. Bomberger N. Ahmed FRC Group Leader: I. H. Sargent Lead NRC Engineer:

  • A. Singh This report was prepared as an account of work sponsored by an agency of the United States

. Govemment.<Neither the United States Government nor any agency thereof; or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the re'sults of such use, of any information, appa-

  • ratus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately. owned rights.

Prepared by:

. t!fo,,~

Principal A~ \\);

Date:.1e:J/l~/8'"

Reviewed by:

Approved by:

/JlA. f dhfupLe!der Date:

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anklin Research Center A Division of The Franklin Institute The Benjamin Franklin Parkway, Phila.* Pa. 191 03 (215) 448* I 000

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CONTENTS Section*

l-INTRODUCTION.

2.

3

- 4 l.l Purpose of Review l.2 Generic Background l.3 Plant-Specific Ba.ckgroµ~d

  • EVALUATION 2.l General Guidelines 2.2 Interim Protection Measures.

CONCLUSION 3.1 General Provisions for Load Hand+ing 3.2 Interim Protection Measures.

REFERENCES iii

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TER-CSSOG-378 FOREWORD This-Technical. Evaluation Report. was prepared by Frankl.in Research Center under a. contract**with the U.S *. Nuclear. Regulatory Commission (Office of Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support. of NRC operating reactor licensing actions.

The technical evaluation was conducted in accordance with criteria established by the NRC...

  • Mr *. I. H. Sargent and Mr. c. R. Bomberger contributed to the technical preparation of this report through a subcontract with WESTEC Services, Inc~

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  • e TER-CS506-378
l.

INTRODUCTION l.l PURPOSE OF REVIEW This technical evaluation report documents an independent review of gen~ral load handling policy and procedur~s a~ Consumers Power Company's (CPC)

Palisades Plant. This evaluation was performed with the following objectives:

o to assess conformance to the general load handling guidelines of NOREG-0612, *control of Heavy Loads at Nuclear Power Plants* [l],

Section 5.1.l o

to assess conformance to the interim protection measures of NUREG-0612, Section 5.3.

la2 GENERIC BACKGROUND Generic Te6hnical Activity Task A-36 was established. by the u.,s. Nuclear l

Regulatory Commiss~on (NRC) staff to systematically examine staff licensing I

I criteria and th~ adequacy-of measures. in-effect at operating nuclear power plants to assur~ ttje safe handling of heavy loads and to recommend necessary*

changes to thesemeasures.

This activity was initiated*by a letter issued by

~

i i;he NRC staff o~ May; 17,.1978 (2.1 to all _power reactor licensees, requesting

',. I information conqern!ir;ig the. control of hea~ loads near spent fuel*.'

*1
  • The results of!Task A~36 were reported in NUREG-0612, "Control of Heavy Loads at Nuclear Po~er Plants.'* The staff 1 s conclusion from this evaluation was that existing measures to control*the handling of heavy loads at operating plants, although providing protection from certain potential pr?blems, do not adequately cover the.major causes of load*handling accidents a.rid should be upgraded.

In order to upgrade measures for the control of heavy. loads, the staff developed a series of guidelines designed to achieve a two-phase objective using an accepted approach or protection philosophy.

The first portion of the objective, achieved through. a set of general guidelines identified in NUREG-0.612, Section 5.1.l, is to ensu.re that all load *handling systems at

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TER-CSS06-378 nuclear power plants are designed and operated such that their probability of

. *failure is uniformly small and appropriate for the critical tasks in which

. tjley are.em12loyed.

'l'he second portion of the staff *s objective,. achieved -

through. guidelines identified in NUREG-0612, Sections S.l.2 through 5.l.S, is to ensure that, for load handling systems in areas where their failure.might result in significant consequences, either (l) features are provided, in addition to those required for all load handling systems, to ensure that the potential for a load* drop is extremely* small (e.* g., a single-failure-proof crane) or* (2) conservative evaluations o~ load handling accidents indicate that the potential consequences of any load drop are acceptably small.

/

Acceptability of accident consequences is quantified in NUREG-0612 into four accident analysis evaluation criteria.

A defense-in-depth approach was used to develop the staff guidelines to ensure that all load handling systems are designed and operated so that their probability of failures is appropriately small.

'l'he intent of the guidelines is to ensure that licensees of all operating nuclear power plants perform the following:

o define safe load travel paths thr~ugh procedures and operator training so that, to the extent practica;i., heavy loads are not carri.ed over or near irradiated fuel or safe shutdown equipment o

provide sufficient operator training, handl~ng system design, load handling instruct;ons, and equipment inspection to. assure.reliable

. operation of the handling* system.

Staff 9uidelines resulting from the foregoing are tabulated in Section 5 of NUREG-0612.

Section 6 of NUREG-0612 rec:ommended that a.program b!=! initiated to ensure that these guidelines are implemented at operating plants.

1.3 PLANT-SPECIFIC BACKGROUND On December *22, 1980, the NRC issued a letter [3j to Consumers Power Company (CPC), the. Licensee for the Palisades plant,. requesting that the

  • Licensee review provisions for handling and control of heavy loads, evaluate these provisions with respect.to the guidelines of NUREG-0612, and provide certain additional information to be used for an independent determination of

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TER-C5506-378 conformance to these guidelines.

On July 6 [4] and Sf.!ptember 23, 1981 [S.],

Palisade~ persoll!lel provided fnitial and subsequent response~ to this request.

Based on this information, a draft technical evaluation report (TER) was prepared and informally transmitted to the-r.1censee for-review.and.*

comments.

On January 13, l98J, a telephone conference call involving the NRC, FRC, and CPC was held to discuss the draft TER concerning control of heavy loads at the Palisades plant.

In response to this telephone call, CPC provided additional i~ormation on February 18, 1983 [61,, *August 15, 1983 [7],

and* September 12, 1983 [8], which has been incorporated into this final teclmical eva.luationG

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TER-C5506-378

2.

EVALUATION This.section presents a point-by-point evaluation of load handling provisions at the Palisades Plant with respect to NRC staff guidelines provided in NUREG-0612.

Separate subsections are provided for bot.~. the general guidelines of NUREG-0612, Section S.l.l an~ the interim measures of NUREG-0612, Section 5.3. -In each case, the guideline or interim measure is presented, Licensee-provided information is summarized and evaluated, and a conclusion.as to the extent of compliance, including recommended additional action where ap.propriate, is presented.

These conclusions are summarized in Table 2.l.

2*~ l GENERAL GOIDELih"ES The NRC has established seven general guidelines which must be met in

'order to provide thedefense-in-depth approach for the handling of heavy loads. These guidelines consist of the following criteria from Section s.1.1 of.NUREG-0612:

Guide+ine 1 Guideline 2 Guideline 3 Guideline 4 Guideline 5 Guideli~e 6 Guideline 7 Safe Load Paths

- :i:.oad Handling, Procedures

-_Crane Operator Training Special Lifting Devices

- Lifting µevices * (Not Specially Designed)

Cranes (Inspection,. Testing, and Maintenance)

Crane Design.

These seven guide.li.nes should be satisfied for all overhead handling.

systems* and programs in order to handle heavy ioads in the vicinity of th~

reactor vessel, near spent fuel in the spent fuel pool, or in other areas where a load* drop may damage safe.shutdown systems.

The Licensee's verifica-tion of the extent to which. these guidelines have been satisfied and FRC's evaluation of this veri~ication are contained in the succeeding paragraphs.

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or Guideline 1 Guideline 2 Gu!dell!le J Guideline t Guldell_na 5 Guideline 6 Guideline 7

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ID Bulldlng Polar Crane RCCR-1 Incore Shipping 10.l c

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Cask N_ew Fuel Assembly 0.7 c

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Primary Coolant 16.l c

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Reactor Vessel 5.0 c

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Fuel Building 100/15 c

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  • Licensee action complies with NUREG-0612 Guideline.

Not applicable.

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  • L~censee has proposed revlalona or llOdlfloatlone which, when Implemented, will be In c~llance with NURE<l-0612 Guideline.
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TER-C5506-378

- 2.1.l Heavy Load Overhead Handling Syctems

a.

Summary of Licensee Statements and conclusions I

The Licensee has identified the following. to be the only permanently installed overhead handling systems capable of carrying ioads which could damage plant systems required for safe shutdown or. decay heat removal:

o reactor building polar crane (Ll) o reactor building jib crane (LlA) o fuel building crane (L3).

o fuel building jib crane.

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Of the cranes *identified; the Lice:hseE: states th~t the l=toll] reactcn: and fuel building*. jib cranes have been excluded. from compliance with

  • NUREG-0 612 guidelines because they are limited to loads less than 1300 lb and because

. load paths are restricted to prevent movement over irradiated fuel or equipment

.required for safe shutdown or decay heat removal.

In addition, the turbine building servic~ crane has been excluded by the Licensee since no equipment" requi.red for safe shutdown or decay beat removal lies within the load path of the*crane.

.b.

  • Evaluation and COnclusion

. I The Licensee's conclusions concerning load handling systems subject to the general guidelines of Section 5.l.l are* consistent with the objectives of NUREG-0612.

2.1.2 Safe Load Paths [Guideline 1, NUREG~06l2, Section 5.1.1(1)]

"Safe load paths should be.defined for the movement of heavy loads to minimize the* potentipl *for heavy loads,. if 'dropped, to. impact irradiated fuel in the reactor vessel and in the spent fuel pool, or to impact safe shutdown equipment.

The path should follow, to the extent practical, structural floor members, beams,.etc., such that if the load is dropped, the structure is more likely to withstand the impact.

These load paths should be defined in procedures, shown on equipment layout drawings, and clearly marked on the floor in the area where the load is to be handled.

Deviations from defined load paths should require written alternative procedures approved by the plant safety review committee."

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a.

Summary of Licensee Statements and Conclusions The Licensee states th~t,. as a' result of a cask drop analysis (dated July 1974), safe load paths have been defined to control movement of heavy loads in the vicinity of the spent fuel pool.

A new procedure* is currently being developed to cover deviations from the safe load paths required by existing procedure FHS-M-23.

The* new procedure will require that deviations from safe load paths b~ approved by both the reactor engineer and the shift supervisore FHS-M-23 will refer to the new procedure. Further, safe load paths are shown on an equipment layout drawing and defined in procedmFHS-M-23. Efforts' are currently under*way to revise procedure'FHS-M-23 to-1.~clude requirements that the crane operator take movement signals from another individual who has knowledge of safe load paths and procedures.

  • The Licensee states that safe. load paths for the containment building will be shown on con~ainment layout drawings.

These drawings will be made part of procedure FHS-M-2* along with instructions for the manner in which the safe load.paths are to be followed.

b.

Evaluation Safe load pa1;hs developed by. the Licensee in. the fuel: pool b~ilding, and based upon the cask drop analysis.of July 1974, satisfy the criteria of this guideline.

Additional proposed actions, such as development and use of load paths for specific heavy loads in. the containmen.t building and designation.and inclusion of these lo~d paths. in layout drawings and procedures, are consistent with the intent of this guideline.

In addition, 'the use of a knowledgeable signalman to direct load* movements* is an acceptable *alternative to load path marking~ However, the Licensee should ensure that the duties and responsibil-ities of the ~reposed signalman are specifically delineated in appropriate procedures to ensure that load movement is controlled within the established safe load paths.

The proposed handling of load path deviations requiring approval by the reactor** engineer and. shift supervisor meets the intent of this* guideline

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TER-C5506-378 provided. that delegation* of such an' authority* is, well documented and emanates-

  • from> the, pl~t'& Safety Review Committee.

c:-.

Conclusion Implementation.'of: safe:' load paths. at. the Palisades: plant. is. performed in a:. manner consistent* with: thisguidel.ine contingent upon the Licensee's verification-* that proposed actions are' acceptably implemented.

2.1... 3' Load 'Handling Procedures [Guideline 21 NUREG-0612, Section 5.l.l(2)J.

  • procedures should be* developed:. to cover. load handling operations for heavy loads that are or could be handled over or in proximity to irr~diated fuel: or safe shutdown equipment.. At a. minimum, procedures*

should* cover handling.of those loads listed* in Table 3-l of NUREG-OEil2.

These procedures should include:

identification of required equipment1 inspections and acceptance criteria required before movement of load1 the steps and proper sequence to be-,followed in handling the load7 defining

  • the safe path; and other. spec:Jµ_precautions.*
a.

Summary of Licensee.Statements and Conclusions

~ovement of any load greater than 1300.lb {we~ght of a fuel assembly)

  • within. the *reactor and f.uel* handling buil~ings* at the Palisades plant* is controlled by at least one written procedure that includes, as a minimum:

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identification of required equipment

2. *. inspection and acceptance criteria. required before movement
3.

steps and proper sequence to be followed.

4. defined safe load paths.
s.

other special precautions and instructions.

Specifically,. for the reactor building Polar crane, two.. procedures have been* implemented by the Licensee to govern load handling.

These procedures are FHS-M-24, *Movement of Heavy Loads. in the Containment Building Area (649 ELEV) I. and FHS-M-25,. nspecific~. Requirements for Moving Heavy Loads Inside the Containment Near the Reactor Vessel.* '!'he.Licensee states that the second procedure, FHS-M-25, identifies site-specific requirements f°or movement of. the reactor missile shields and other heavy loads over or near the reactor vessel which are typically handled during refueling.

Individual* procedures are.. also

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TER...CSS06-378 prepared, if not already in existence, for movement of any other loads within

  • 19 ft of the center line of the reactor vessel.

In the fuel handling building, a procedure has been developed in conjunction with the cask drop analysis entitled *Movement-of Heavy Loads in the Spent Fuel Area** (FBS-M-23), which satisfies the *intent of NU:REG-0612, Section S.l.1(2).

b.

Evaluation and Conclusion The criteria of this guideline ere satisfied at the P~lisades plant on the basis-of the Li¢ensee's verification that procedures contain the information identif:ied in NUREG-0612 *

. 2.J..4. Crane Operatbr 'rraining [Guideline 3, NUREG-0612, Section S.l.1(3)]

  • crane operators should be trained, qualified and conduct themselves in accordance with Chapte-r2-3 of ANSI BJ0.2-1976, *overhead and Gantry Cranes* [9J.*

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a..summary of Lice~se~ :statements *and Conclusions

...i The Lic*ensee stat~~ that *programs and p~ocedures at the Palisades plant l

for* c*rane operator 1traj,.njing, qualification, and conduct have been reviewed and are in compliance withiand meet tile intent of Chapter 2-3 of ANSI BJ0.2-1976.

  • b.

Evaluation and Conclusion The Palisades program for crane operator training satisfies the criteria of this guideline on the basis of the statement* that these programs have been reviewea and are in compliance with ANSI 830.2-1976.

2Property "ANSI code" (as page type) with input value "ANSI 830.2-1976.</br></br>2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..l.S.Special Lifting Devices [Guideline 4, NUREG-0612, Section S.l.1(4)]

"Special lifting devices should satisfy the guidelines_ of ANSI Nl4.6-1978,

.'Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More for Nuclear Materials' [10].

This standard should apply to* all special lifting devices which carry heavy loads in areas as defined above.

For operating plants certain inspections and load tests may be accepted in lieu of certain material

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TER-C5506-378 requirements in the standard.

In addition, the stress design factor stated in Section 3.2.l.l of ANSI Nl4.6 should be based on the combined

  • maXimum static and dynamic loads that could be imparted on the handling

. device* based on characteristics of the-crane which will be used. This is in lieu of the guideline in Section 3.2.l.l of ANSI Nl4.6 which bases the stress* design factor on only the weight (static load) of the load and of the intervening components of the special handling device.~

aQ Summary of Licensee Statements and Conclusions

  • The Licensee has identified the.core* support barrel (CSB), upper guide structure (UGS), nactor vessel (RV) head, and missile shield. lifting devices to.be subject to the requirements of.~his guideline.

Design calculations for these lifting devices have been reviewed, and it has been determined that all lifting devices were designed with stre*ss design factors greater than 3 on yield strength and greater than 5 on ultimate strength.

As further proof of design adequacy, the*Licensee notes that the 'EW.head, UGS, and CSB. lift devices have been used numerous times in the past 10 years with no indication Of excessive.,strain or other adverse effects.

In add'ition,* these devices were built-and designed by a.NSSS vendor and were subject to.the vendor's*quality control and quality assurance programs.

'l'he*Licen:see notes that the.missile shield lift device was recently purchased and was proof tested to 150% of rated load.

However, no load tests were performed on remaining.lifting devices.

Evaluation of these lifting devic~s conducted by the Lic.ensee indicates that such load tests are not considered necessary for t;he following reasons:

l. Design: stresses for these devices are substantial.

2.* The devices are simple and held together, for the most part, by

  • mechanical joints.
3.

Welds that do exist on critical parts were performed under procedures developed py Combustion Engineering (CE).

4.

All material and workmanship were subject to CE's quality assurance.

  • program. *
5.

All.devices received a load test to a least 100% of rated load.

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'l'ER-C5506-378 The Licensee states that lifting devices are used.with the reactor build-

. _-,ing polar,crane; which has a. m~imum hoist speed of 6 fee.t per. minut.e. (fpm).*

Therefore, the dynamic loading experienced by these lifting devices is considered negligible.

A program for ensuring continuing compliance consistent with the requirements of ANSI Nl4.6-l978, Section 5.3 has been implemented. Critical

, welds of these lifting devices will be subject to nondestructive examination (NDE) at intervals no greater than 5 years.

This is considered adequate since the devices are used during refueling outages.

b.

Evaluation Although it cannot be determined that the specific requirements of ANSI Nl4.6-l978 for component designand fabdcation.have been satisfied for.the

. Palisades lifting devices, it'. is evident that these de 0vices wil:l provide a 1

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I high degree.o*f load h~ndling reliability.

Informaton provided. by the. Licensee indicates that* stress design factors for these ~evices satisfy ANSI requireme~ts,and. that.quality controls *were p~ac~d *on these devices during, their fabrication by the vendor..

Further, although all.devices with the exception of the missile sheild lift device were not proof tested, sufficient information has been provided.to*substantiate the workmanship of these devices.

Specificall.y, the use of conservative design margins, unc.omplicated designs, maximum use of mechanical joints, fabrication control of welds,. and a load test to 100%, of rated load provide proof of workmanship consistent with that required by ANSI Nl4.6-l978~

  • In addition, the Licensee's program of annual visual examinations supplemented by NDE of critical welds at intervals less than 5 years provides reasonable assurance of continued reliability consistent with ANSI re~ire ments, based upon the limited usage of the devices.
c.

Conclusion Design, testing, and continued* use of special.lifting devices at.the Palisades plant* is performed*in a manner consistent with that contained. in Guideline 4 of NUREG-0612.

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TER-CS506-378 2.l.6 Lifting Devices (Not Soecially Designed) [Guideline 5, NUREG-0612, Section 5.1.1(5)1

  • Lifting devices that are not specially designed should be installed and used in accordance with the-guidelines of ANSI B30o9-l97l, 'Slings'

[11].

However, in selecting the proper sling, the load.used should be the sum of the static and mi!Ximum dynamic load.

The r~ting identified on the sling should be in terms of the 'static load' which produces* the maximum static and dynamic load. Where this re.stricts slings to use on only certain cranes, the slings should be-clearly marked as to the cranes with which they may be 'used.*

a*.

Summary of Licensee Statements and Conclusions The Licensee has reviewed ANSI B30.9-197l requirements and determined that the use of slings for handling heavy loads at the Palisades plant meets the. intent of ANSI B30.9-l971.

Those slings. which are used exclusively on the main hoist of either the reactor building crane or fuel pool crane will be marked as to their limited use and will be rated for static load only.

The

-maximum hois~ speed of ~ fpm on the fuel pool crane and 6. fpm on the reactor

'building crane does hot permit a dynamic load of any con~equence*~*

Slings which are used with auxiliary hooks (both cranes are capable of up.

to -35 fpm) will be analyzed.for t;>oth static and dynamic loading.

If the dynamic load_ is gre~-ter than 10% *of the presently* rated static load, the combined dynamic and static* load will be used to rate the sling.

b.

Evaluation

  • Ose of slings at the Palisades plant satisfies the criteria of Guideline 5 on the basis of the Licensee's-verification that use of these slings meets the intent of ANS~ BJ0.9-1971.

In addition, CPC has satisfied-criteria for use and selection of slings and procedures for restricting slings for limited use on certain cranes.

Since the main hoist speeds of the reactor building crane or fuel pool crane are relatively low, the dynamic loads imposed on dedicated slings are reasonably small and may be disregarded in determining the slings' maximum rated load.

Considering the nominal allowance for dynamic loading provided in CMAA-70 for crane design (dynamic load = 0.5% x static load per foot per minute of hoist speed), it can be concluded that the maximum-dynamic

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TER-C5506-376 loading in the auxiliary hook slings will be 17.5%.

The Licensee's decision

  • to provide an additional allowance for dynamic loading only in'cases'where such loading* is greater than 10% of static load is reasonableo*

c. Conclusion

Selection and use of slings at the Palisades plant is in accordance with Guide.line s..

2.1.. 7, Cranes (InsEection, Testing, and Maintenance) [Guideline 6, NOREG-0612,

  • Section 5.1.1(6)]
  • The crane should be inspected, tested, and maintained in accordance with Chapter 2-2 of ANSI 830.2-1976, 'Overhead and Gantry Cranes,' with the exception that. tests and inspections should be performed prior to use where* it is not practical to meet the frequencies of ANSI B30.2 for periodic.inspection and test, or where frequency of crane use is less
  • , than the specified inspection and. test frequency '(e~g.., the polar crane inside a'PWR containment may only be used every 12 to 18 months during refueling.operations; and* is generally not accessible during power

'operation. 'ANSI B30. 2,* 'however I calls._for certain. inspections to be performed daily or monthly.

For such cranes *having limited usage, the inspections, test, and maintenance should be perfo'rmed prior* to their use).*

a...Summary of Licensee Statements and Conclusions The Licensee states that the cranes identified are tested, inspected, and maintained in accordance with written procedures that meet the intent of guidelines provided in ANSI'B30.2-l976 *. With the exception of a daily limit switch test1 which is performed monthly by plant electricians, Section 2-2 of ANSI B30.2 is complied with.

Because each.operator has a different interpretation.of how to test.limit switches, limit switch testing is included in monthly maintenance inspections.

b.* Evaluation The criteria of this guideline are satisfied at the Palisades plant* on the basis that the program in use meets the intent of ANSI B30.2-1976 with the

  • exception of limit switch testing being monthly rather than daily.

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TER-C5506-378 exception is acceptable in view of exceptions allowed by Section 5.l.1(6) of

'NtraEG-0 612.

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c.

Conclusion Inspection, testing, and maintenance of cranes-at the Palisades plant is performed in a manner consistent with Guideline 6.

2.l.8 Crane Design [Guideline 7, NUREG-0612, *Section 5.Ll(7) J

  • The crane should* be designed to meet the applicable criteria and guidelines of Chapter 2-l of ANSI BJ0.2-1976, 'Overhead and Gantry
  • cranes, I and of. CMAA-70, 'Specifications. for Elec'tric Overhead Traveling

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Cranes' [12] **

  • An alternative to a specification in ANSI B30.2 or CMAA-70 may be accepted in lieu of specific compliance if the intent of the

. specification is satisfied.*.

a~

Summary of Licensee Statements and Conclusions The Licensee states*that the ~eactor buil(!ing polar crane and the auxiliary building.crane were ori~inally designed and manufactured in acco'rdance with Electric Overhead*:Crane Institute Specification 61 (EOCI-61)

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'l'he crane manufacturer, Dresser Industries, has Compared the design of these cranes with the requirements of CMAA-70 and ANSI B30.2-l976 and has concluded that the auxiliary building crane meets the mandatory electrical, structural,.. and. mechanical design requirements.

The reactor building crane also. meets these standards with one exception:

when a 135-ton load is carried within 6 feet of the rail, a stress of 15. 25,ksi is formed in the bridge end ties which exceeds the allowable stress (14.4 ksi) by o.as ksi1 the Licensee considers this overstress to be insignificant.

b.

Evaluation and Conclusion Design of cranes at the Palisades plant is considered to be consistent with this guideline on the basis of the Licensee's comparison of existing crane design with the more restrictive requirements of CMAA-70.

Further, it is agreed that.an overload of O. 85 ksi: (106%)' is not significant, but load movements in this area should be limited by procedure, if possible.

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TER-C5506-378 2.2 INTERIM PROTECTION MEASURES The NRC has. established six interim protection measures to be implemented at operating nuclear power plants to provide reasonable assurance that no heavy loads will be handled over the spent fuel pool and that measures exist to reduce the potential. for accidental load drops to impact on fuel in the core spent fuel poole Four of the six interim measures of the report consist of Guideline l, Safe Load Paths: Guideline 2, Load Handling Procedures; Guideline 3, Crane Operator Training1 and Gu.ideline. 6, Cranes. (Inspection, Testing, and Maintenance).

The two' remaining interim measures cover the following.criteria:

l. Heavy load technical specifications
2.

Special review for hea,,Y loads handled over the core.

Licensee implementation and evaluati9n of these interim protection measures are contained in *the succeeding paragraphs. of this section *

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2.2.i Technical Specifications [Interim Protection* Measure 1, NUREG-0612, Section 5~3(1)]

  • Licenses for all operating reactors not having a single-failure-proof
  • overhead crane in the fuel storage pool area should be revised to include a specification*comparable to Standard Technical Specifibation*3.9.7,

'Crane Travel - Spent Fuel Storage Pool Building,' for PWR's and Standard Technical Specification 3.9.6.2, 'Crane Travel,' for BWR's, to prohibit ha~dling of heavy loads over fuel in the storage pool until implementation.

of measures which satisfy the gµidelines.of Section.'Sel."

a.

Summary of Licensee Statement and Conclusion The Palisades plant procedure FHS-M-23 prohibits movement of heavy loads over the fuel pool.

b.

Evaluation and Conclusion The. Palisades plant complies with Interim Protection Measure la

~nklin Research Center A Dlvislon cl The Franklin Institute

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TER-CS506-378 2'.2.2* Administrative Controls [Interim Protection Measures 2, 3, 4, and 5, NUBEG-0612, Sections 5.3(2) - 5.3(5)]

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... -*- *.. *.~Procedural: or. administrative measures~ [l"ncluding safe* load paths, load

.. :-:.-=:- -=-bctndling**procedures:;-crane~operator *t*raining, and* crane inspection]. o*

can<< be: accomplished in* a: short time period and need not be, delayed for ccmpletion of evaluations and modifications to satisfy the* guidelines of Section. S.l. of [NOBEG-0612) **,

a..

Summary*of Licensee Statements and* conclusions

  • summaries. of. "Licensee statements and conclusions are contained in discussions of the respective general guidelines in Sections 2.1.. 2, 2~1.3, 2.1.4, and 2.1.7.
b.. Evaluations, Conclusions, and Recommendations The.**evaluations, conclusions, and recommendations are* contained in discuss.ions of the respective. general guidelines in Sections 2.1.2, 2.l.3, 2.1.4, and 2.1.7.

2.2*;..3*

  • Special Reviews for HeavY Loads Over* the Core [Interim Protection Measure 6, NUBEG-0612, Section 5.3(6)]

.*special' attention should be given to procedures,'equipment, and personnel

.. for the handling of heavy. loads* over the core, such as vessel internals or vessel. inspection tools*.. This special review should include the following for these l9ads:

(l) review of procedures for installation of rigging or lifting devices* and movement of the load to assure that

\\ufficient detail is provided and that instructions.are clear and concise1 (2) visual inspections of load bearing components of cranes, slings, and special lifting devices to identify flaws or deficiencies that could 'lead to failure of the component1 (3) appropriate repair and replacement of defective components1 and (4) verify that the crane operators have been properly trainedand:are familiar with specific procedures used in handling these loads, e.g., band signals, conduct of operations, and content of procedures.*

aa Summary of. Licensee Statements and Conclusions The Licensee states that a. special review for handling heavy loads over the core bas been completed in compliance with Section 5.3, Interim Protection Measure 6 of NUREG-0612.

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b.

Evaluation and Conclusion The Palisades plant complies with Interim Protection Measure 6 based on the Licensee verification.

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3.

CONCLUSION This. summary:.. is. provided to consolidate the results of the evaluation contained in Section 2-concerning individual NRC staff guidelines into an overall evaluation of heavy load handling at the Palisades plant.

Overall conclusions and recommended Licensee actions, where appropriate, are provided with respect to both general provisions for load handling *(NOREG-0612, Section 5~1.l) and completion of the staff recommendations for interim protection (NOREG-0612, Section 5.3).

3ol GENERAL PROVISIONS FOR LOAD HANDLING The NRC staff has established seven guidelines concerning provisions for handling heavy loads in *the area of the reactor vessel, near stored spent

. fuel, or in other areas where an accidental load drop could damage equipment required for safe shutdown or decay h~at removal.

  • The intent of these guidelines is twofold. *A.plant conforming to these guidelines will have
  • developed and implemented, through procedures, and op.era tor training, safe load travel paths such *that, to the maximum extent practical, _heavy loads are not
  • carried over or. near irradiated fuel or safe shutdown equipment.

A plant conform.ing to these guidelines will also have provided sufficient operator training, handling system design, load handling instructions, and equipment inspection to ensure reliable operation of the handling system.

As detailed in Section 2, it has been found. that.load handling operations at the Palisades plant can be.eXpec~ed to be conducted in a highly reliable manner consistent with*the staff's objectives as expressed in these guidelines

  • 3.2 INTERIM PROTECTION MEASURES The NRC staff* has established (NOREG-0612, Section 5.3) certain measures that should be.initiated to provide reasonab.le assurance that handling of

.heavy loads will be performed in a safe manner until final implementation of the,general guidelines of NUREG-0612, Section 5.1 is complete *. Specified measures include the* implementation of a technical specification to prohibit the handling of heavy loads over fuel in the storage pool; compliance with

.. ~nkiin Research Center A OMsion of The Franklin INlilute ;*

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TER-CS506-378

  • Guidelines l, 2, 3, and 6 of NPREG-0612, Section 5.l.l; a review of load
handling procedures~ and operator*.t'raining; and a v;.sual inspection program, including component repair or replacement as necessary of cra114'!_!, __ 13!_i~?!v_ ~~d special lifting devices to eliminate deficiencies that could lead.to component failure.

Evaluation of information provided by the Licensee indicates that the--Palisades plant complies with the staff's measures for interim.protection.

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4.

REFERENCES

l.

NUBEG-0612

  • eontrol' of Heavy Loads at Nuclear Power Plants*

NRC

2. v. Stello, Jr. (N!C)

TER-CSS06-378 Letter to all licensees.

Subject:

Request for Mditional Information on Control of Heavy Loads Near Spent Fuel May 17, *1978 3c USNRC' Letter to Consumers Power Co.

Subject:

NBC Request for Additional Information on Control of Heavy Loads Near Sp~nt Fuel

.December 22, 1980 4..

D. P. Hoffman (CPC)

Letter to D. M. Crutchfield (NRC).

Subject:

Control of Heavy Loads July 61 1981

5.

B. D. Johnson (CPC) **

Letter to D. M. Crutchfield (NRC).

Subject:

control of Heavy Loads Septeml;>er 23; l98l

6.

B *. D. Johnson (CPC)

Letter to D. M. Crutchfield (NRC).

Subject:

Control'of Heavy Loads February ~8, 1983 * *

'7* *. *. B~ D. Johnson (C~)

Letter to D. M~ Crutchfield (NRC).

Subject:

Control of Heavy Loads August 15, 1983

8.

B. D. Johns~n '(CPC)

Letter to D. M. Crutchfield (NRC).

Subject:

Control of Heavy Loads September* 12, 1983

9.

ANSI BJ0.2-1976

  • overhead and Gantry Cranes*
10.

ANSI Nl4.6-l978

  • standard for* Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More for Nuclear Materials"

.11.

ANSI B30.ll-1971 "Slings*

.12.

CMAA-70 "Specifications for Electric Overhead Traveling Cranes"

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'l'ER-C5506-378 l3o EOCI-61

  • specificat~ons for Electric Overhead Traveling Cranesa

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