ML20100B273

Control of Heavy Loads at Nuclear Power Plants,Cleveland Electric Illuminating Co,Perry Nuclear Power Plant,Units 1 & 2 (Phase I)

ML20100B273
Person / Time
Site:	Perry
Issue date:	04/30/1983
From:	Sekot J, Stickley T IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML20100B265	List: ML20100B273
References
CON-FIN-A-6457, REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR EGG-HS-6264, NUDOCS 8412040268
Download: ML20100B273 (30)

Text

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. EGG-HS-6264 APRIL 1983 CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT, UNITS 1 AND 2 (PHASE I)

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• s I J. P. Sekot T. H. Stickley

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This is an informal report intended for use as a Dreliminary or working document 8412040268 841120 PDR ADOCK 05000440 E PDR l Prepared for the -

! U.S. NLjCLEAR REGULATORY COMMISSION 0

yD g g g G Idaho Under DOE Contract No. DE-AC07-76ID01570 FIN NO. A6457

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EGG-HS-6264 CONTROLOFHEAVYLOAOSATNUCLEARPOWERPLhNTS THE CLEVELKiD ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT, UNITS 1 AND 2 (PHASE I) 4 Docket Nos. 50-440 and 50-441 Author J. P. Sekot

. Principal Technical Investicator T. H..Stickley i

Published April 1983 '

EG&G Idaho, Inc.

Idaho Falls, Idano 83415 Prepared for the U.S. Nuclear Regulatory Commi'ssion Under DOE Contract No. DE-AC07-76ID01570 FIN No. A6457 b

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ABSTRACT The Nuclear Regulatory Commission (NRC) has requested that all nuclear

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p1 ants, either operating or under construction, submit a response of compliancy with NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants." EG&G Idaho, Inc., has contracted with the NRC to evaluate the responses of those plants presently under construction. This fina,1 report is a result of EG&G's review of the responses submitted for the Perry Nuclear Power Plant, Units 1 and 2 'to the requirements of Section 5.1.1 of NUREG-0612 (Phase I). Sections 5.1.2, 5.1.4, 5.1.5, and 5.1.6 (Phase II) will be covered in a separate report.

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EXECUTIVE

SUMMARY

Perry Nuclear Power Plant, Units 1 and 2 comply with the intent of the

.equirements of NUREG-0612.

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CONTENTS.

ABSTRACT .......................................................

. . . . 11 EXECUTIVE

SUMMARY

.............................................. ..... i ii

1. INTRODUCTION ................................. .................. I 1.1 Purpose of Review ......................................... I 1.2 Generic Background ........................................ 1 1.3 Plant-Specific Background .............................. . 3

2. EVALUATION AND RECOMMENDATIONS .................................. 4 2.1 Ov'erview .................................................. 4 2.2 Heavy Lead Overhead Handling Systems ...................... 4 2.3 General Guidelines ........................................ 12 2.4 Interim Protection Measures ............ . . . . . . . . . . . . . . . . . 21

3. CONCLUDING

SUMMARY

............................ . . . . . . . . . . . . . . . . . 23 3.1 Applicable Load-Handling' Systems .......................... 23 3.2 Guideline Recommendations ................... . . . . . . . . . . 23 4 RECERENCES .. ... ......... ...... .. . .......... . ..... .... . 25 TABLES 2.1 Nonexempt Heavy Load-Handling Systems ..... . . . . . . . . . . . . . . . . . . . . . 6 2:2 Exempt Heavy Load-Handling Systems .................... ......... 7 2.3 Emergency Service Water Pump House Crane--PNPP Units 1 and 2 . . . . 9 2.4 Fuel-Handling Building Bridge Crane--PNPP Units 1 and 2 ......... 10 2.5 Reactor Building Crane--PNPP Units 1 and 2 ..................... 11 3.1 NUREG-0612 Compliance Matrix .................................... 24 v

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CONTROL OF HEAVY LOADS AT NUCLEAR' POWER PLANTS THE CLEVELAND ELECTRIC ILLUMINATING COMDANY PERRY NUCLEAR POWER PLANT, UNITS 1 AND 2 (PHASE I)

1. INTRODUCTION 1.1 Purpose of Review This technical evaluation report documents the EG&G Idaho, Inc.,

review of general load-handling policy and procedures at The Cleveland Electric Illuminating Company (CEICO), Perry Nuclear Power Plant, Units 1 and 2. This evaluation was performed with the objective of assessing conformance to the general load-handling guidelines of NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants" [1],

Section 5.1.1.

1.2 Generic Backaround-Generic Technical Activity Task A-36 was established by the U.S.

Nuclear Regulatory Commission (NRC) staff to systematically examine staff licensing criteria and the adequacy of measures in effect at operating nuclear power plants to assure the safe han'dling of heavy loads and to recommend necessary changes to these measures. This-activity was initiated by a letter issued by the NRC staff on May 17, 1978 [2], to all power reactor applicants, requesting information concerning the control of neavy loads near scent fuel.

The results of Task A-36 were reported in NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants." The staff's conclusion from this evaluation was that existing measures to control the. handling of heavy loads at operating plants, although provic'ng protection frcm certain potential problems, do not adecuately c:,e- the major causes of load-handling accidents anc should be upgraded.

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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-0612, Article 5.1.1, is to ensure that all load-handling systems at nuclear power plants are designed and

- operated such that their probability of' failure is uniformly small and appropriate for the critical tasks in which they are employed. The second portion of the staff's objective, achieved through guidelines .

identified in NUREG-0612, Articles 5.1.2 through 5.1.5, is to, ensure that, for load-handling systems in areas where their failure might result in significant conseque'nces, either (a) 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 (b) conservative evaluations of 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.

The approach used to develop the staff guidelines for minimizirg the potential for a load drop was based on defense in depth and is summarized as follows:

e Provide sufficient operator training, handling system design, load-handling instructions, and equipment insoection to assure reliable operation of the handling system e Define safe load travel paths through procedures and operator training so that, to the extent practical, heavy loads are not carried over or near irradiated fuel or safe shutdown equipment -

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e Provide mechanical stops or electrical interlocks to prevent

• movement of heavy loads over irradiated fuel or in proximity to equipment associated with redundant shutdown paths.

l Staff guidelines resulting from the foregoing are tabulated in Section 5 of NUREG-0612.

1.3 Plant-Specific Background On December 22, 1980, the NRC issued a letter [3] to,.the Cleveland Electric Illuminating Company, the applicant for the Perry Nuclear Power Plant, Units 1 and 2, requesting that the applicant review provisions for handling and control of heavy loads at PNPP Units 1 and 2, evaluate these provisions with respect to the guidelines of NUREG-0612, and provide certain additional information to be used for an 'ndependent determination of conformance to these guidelines. On June 19, 1981, CEICo provided the initial response [4] to this request. Based on this information, a preliminary draft of this report was prepared and discussed with the applicant. Additional information was provided by the applicant in References [9,10,11].

The current (final) draf t of this report was prepared from information i

contained in all these submittals.

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2. EVALUATION AND RECOMMENDATIONS 2.1 Overview The following sections summarize CEICo's review of heavy load-handling at Perry Nuclear Power Plant, Units 1 and 2 accompanied by EG&G's evaluation, conclusions, and recommendations to the applicant for bringing the facilities more completely into compliance with the intent of NUREG-0612. The applicant has indicated the weight of a heavy load for this facility (as defined in NUREG-0612, Artic,le 1.2) as 1048 pounds.

2.2 Heavy Load Overhead Handling Systems This section reviews the applicant's list of overhead handling systems which are subject to the criteria of NUREG-0612 and a review of the justification for excluding overhead handling systems from the above-mentioned li st.

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2.2.1 Scope

" 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) and justify the exclusion of any overhead handling system from your list 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 syste= or component required for plant shutdown or decay heat removal."

A. Summary of Aoplicant's Statements The applicant conducted a revie#'of plant arrangements and provided tables and drawings in Reference 10 icentifying 4

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cranes, hoists, or other overhead handling devices that have the capacity to lift more than 1048 pouncs in buildings housing fuel or safe shutdown equipment. Separate tables  ;

were presented for each handling system. The tables f

included the impact area, loads and weights to be lifted, safety-related equipment, floor elevation, category for  ;

hazard elimination, and capacity of the handling system. I l

Hazard elimination categories were defined and justification I for the load classification.was provided. The overhead handling systems used for the heavy load movements are identified in Table 2.1. All overhead handling systems excluded'from further concern are listed on Table 2.2.

B. EG&G Evaluation The applicant's response to the identification of overhead handling systems is very complete and well documented in Reference [10). The drawings in this reference indicate that a notable amount of handling-is accomplished by dollies, however, the applicant states that they will not be pulled by cranes [11]. EG&G is in agreement with the logic chart used as a basis for evaluation and analysis of the movement of heavy loads and commends CEICo's method of clear presentation. Tables 2.3, 2.4, and 2.5 identify weights, lift equipment, procedures, and analysis for loads that are to be handled by the Overhead Handling Systems icentified in Table 2.1.

C. EG&G Conclusions and Recommendations The Perry Nuclear Power Plants, Units 1 and 2 comply with the requirements of 2.2.1 above, of NUREG-0612 on Heavy Load Overhead Hancling Systems.

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TABLE 2.I'. . OVERHEAD HANDLING SYSTEMS USED FOR THE MOVEMENT OF HEAVY LOADS IN VICINITY OF SAFE SHUTDOWN EQUIPMENT PERRY, NUCLEAR POWER PLANT, UNITS 1 AND 2 Capacity Handling System (1b) Location Emergency Service Water Pump 30,000 ESW Pump House House Crane Reactor Building Crane 250,000 Reactor Building Fuel-Handling Building Crane 250,000 Fuel-Handlinij Building

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2.3 General Guicelines This-section addresses the extent to which the applicable handling systems comply with the general guidelines of NUREG-0612 Article 5.1.1. EG&G's conclusions and recommendations are provided in .

summaries for ,each guideline.

s The NRC has established seven general guidelines which must be met in order to provide the defense-in-depth approach for the handling of heavy loads. These guidelines consist of the following criteria from Section 5.1.1 of NUREG-0612: '

e Guideline 1--Safe Load Paths e Guideline 2--Load-Handling Procedures e Guideline 3--Crane Operator Training-e Guideline 4--Special. Lifting Devices e Guideline 5--Lif ting-Devices (not specially designed) e Guideline 6--Cranes (Inspection, Testing, and Maintenance) e Guideline 7--Crane Design.

These seven guidelines should be satisfied for all overhead handling systems and programs in order to handle heavy loads in the vicinity of the reactor vessel, near spent fuel in the spent-fuel pool, or in other areas where a-load drop may damage safe shutdown systems. The succeeding paragraphs address the guidelines individually.

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4 2.3.1 Safe Load Paths [ Guideline 1, NUREG-0612, Article 5.1.1(1)]

" Safe load paths should be defined for the. movement of heavy loads to minimize the potential 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. Tne path should follow, to the extent practical, structural floor members, beams, etc., such that 11f 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." .

A. Summary of Applicant's Statements Refererce [10) contains "information packets thu. sere assembled for each elevation or section of the plant. The packets consist of general arrangement drawings that show:

(1) location of equipment necessary for safe shutdown and

- continued decay heat removal with the respective emergency power division (2). Coverage areas for the lifting devices

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(3) Individual transport paths, both as elevation lifts and

, along the floor via dollies.

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, f. Where necessary, piping composite drawings have been added i to cetter show critical safety piping. The results of the heavy I '

' ' load movement study are listed in tables accompanying each packet

' . . . a separate table is presented for each lifting cevice."

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In response [11], the applicant stated:

(1) Load patns will be clearly marked on the floor where L-the load is to be handled and appropriate procedures will be implemented. The load will be walked through by the lift supervisor only in areas where it is difficult to clearly, mark the load path on the floor.

(2) No alternate load-paths are presently defined in the Perry Equipment removal scheme;. however, it is ;

currently under evaluation. The plant operation review committee will designate individuals authorized to approve procedural variations, typically- the maintenance or shift supervisors.

(3) Analysis and criteria used for hazard elimination, the PNPP Equipment Removal Scheme, and special Handling /

Safe Load Path procedures will be maintained on file and available for review.

B. EG&G Evaluation EG&G finds CEICo's identification of the various load paths to be very detailed and well presented. Included drawings are very informative and most of the hazard elimination categories are self-explanatory and readily ac :eptable.

C. EG&G Conclusions and Recommendations Perry Nuclear Power Plant, Units 1 and 2 comply with the criteria of NUREG-0612, Section 5.1.1(1), Safe Lead Paths.

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2.3.2 Load-Handling procedures [ Guideline :2, NUREG-0612. Article 5.1*.1( 2 )]

' Procedures should be developed to cover load-handling coerations for heavy loads that are or could be hancied over or in proximity to irradiated fuel or safe shu.down equipment. At a minimum, procedures should cover handling of those loads listed in Table 3-1 of NUREG-0612. These procecures should include:

identification of required equipment; inspections and acceptance criteria required before movement of load; the steps and proper

' sequence to be followed in handling the' load; defining the safe path; and other special precautions."

A. Summary of Applicant's Statements

. The applicant provided the following response in Reference [11].

"The load-handling procedures are being written and will be open for review on-site when they are complete. Attached is a draft copy of Control of Heavy Loads Procedure MAP-1301. Additional orocedures on crane operating guidelines, and guidelines for rigging are provided for your information. Dollies will be used in the movement of heavy loads, but will not be pulled by cranes, i .e. , cranes are not used as mechanical mules."

B. EG&G Evaluation With the applicant preparing the necessary load-handling pro-cedures, EG&G concludes that the criteria of Guideline 2 will be accomplished. Draft Procedure MAP-1301 specifically addresses those load movements requiring administrative procedure control as identified in the summary conclusion of the PNPP Control of Heavy Loads Study. The appplicant states (in MAP-1301) that the handling of Category A and B items will be in accercance with written-approved procedures and associatec instructions or draw-ings. Items that are to be included in the procecures address identification of required equipment, inspections, and acceptance criteria required before movement of the'l ed, the steps and pro--

per sequence to be followed in handling tr.e load, and s;ecial pre-cautiens. MAP-1301 also adcresses safe Icac paths. Tne crane operating guidelines require performance c# a caily pricr-to use inspection.

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'. C . EG&G Conclusions and Recommendations.

EG&G concludes. that Perry NuclearIPower Plant, Units 1 and 2 are fin full compliance with the criteria'of NUREG-0612,

.Section 5.1.1(2), Load-Handling. Procedures.

.2.3,.3 Crane Operator Training [ Guideline 3. NUREG-0612 Article 5.1.1(3)1

" Crane operators should be trained, qualified, and conduct themselves-in accorcance with Chapter 2-3 of ANSI B30.2-1976,

' Overhead and Gantry Cranes' [6]."

A. Summary of Applicant's Statements An overhead Crane Operator Qualification guide (MAP-0201) has been written and a draft copy provided by the applicant in Reference [9]. This guice states- that operators shall be trained to ANSI B30.2-1976, ASME/ ANSI N45.2.15-1981, and ANSI E30.9-1971.

The Qualifications guide contains-reference to NUREG-0612 for operation of the Polar, Fuel Handlings, and ESW Cranes. The.

following guidelines from NUREG-0612 are listed in the qualifications guide: " Operator qualification will require familiarity with the PNPP Equipment Removal Scheme and Special handling safe load path procedures. Knowledge will be checked by interviews, written exam, and practical demonstration.

.Completien of these requirements will be documented on a qualification card which will be reformed in the operations training file."

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B. .EG&G Evaluation EG&G has determined that the program proposed by CEICo is very commendable.

C. EG&G Conclusions and Recommendations .

EG&G concludes that Perry Nuclear Power Plant, Units 1 and 2 are in compliance with the criteria of NUREG-0612, Section 5.1.1(3),

Crane Operator Training.  ;

2.3.4 Soecial Lifting Devices [ Guideline 4, NUREG-0612, Article 5.1.1(4)]

"Special lifting devices should satisfy the guidelines of ANSI N14.6-1978, ' Standard for Special Lifting Devices for Shioping Containers Weighing 10,000 pounds (4500 kg) or More for Nuclear

• Materials' [7]. This standard should apply to all special lifting devices which carry heavy loads in areas as cefined above. For operating plants, certain inspections and load tests may be-accepted in lieu of certain material requirements in :ne standard. In addition, the stress design factor stated'in Section 3.2.1.1 of ANSI N14.6 should be based on the ccmbined maximum static and dynamic loads that could be impartec on the handling device based on~ characteristics of the crane wnich will be used. This is in lieu of the guideline in Section 3.2.1.1 of ANSI N14.6 which bases the stress design factor on only the weight (static load) or the load and of the intervening components of the special handling device."

A. Summary of Applicant's Statements The applicant, in response [9], submitted a craft copy of MAP-1301, a procedure for the control of Heavy Loads.

Section 6.1.3.1 states "Special Lifting devices used for the movement of Heavy Loads shall meet the requirements stated in NUREG-0612, Article 5.1.1 guideline 4 and ANSI N14.6-1978."

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.B. EG&G Evaluation J

EG&G considers the contents of draft procedures ~provided as being commitments toward_ compliance; therefore, on the basis of the

applicant's statement,.EG&G concludes.that CEICo intends to comply with the NUREG-0612 criteria.

C. -EG&G Conclusions anc Recommendations

'EG&GLconclu' des that Perry-Nuclear Power ' Plant, Units I and 2 are in compliance with the criteria of NUREG-0612, guideline 4, Special Lift Devices.

2.3.5 Lifting Devices (Not Specially Designed) [ Guideline 5, NUREG-0612. Article 5.1.1(5)]-

" Lifting devices that are not specially designed should be installed and used in accordance with the guidelines of ANSI B30.9-1971, ' Slings' [8]. However, in selecting the proper sling, the load used should be the sum of the static and maximue dynamic load. The rating identified on the sling should be in terms of'the ' static load' which produces the' maximum static and dynamic load. Where this restricts slings to use on only certain cranes, the slings should be clearly marked as to tne cranes with which they may be used."

A. Summary of Apolicant's Statements The applicant, in response [9], submitted a draft copy of MAP-1301, a proceoure for the control of Neavy Loads.

Section 6.1.3.2 states " Lifting devices that are not specially designed, used for the movements of ' Heavy Loads,' shall meet the requirement stated in-NUREG-0612, Article 5.1.1, guideline 5 anc ANSI B30.9-1971." :CEICo further stated "Each' sling will be pr,operly identified as to its lifting capacity, applicability to specific load-handling operations, and if appropriate, restriction of'its use to specific cranes." *

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. ' B. EG&G. Evaluation

, EG&G considers 'the contents of draft. procedures provided as being commitments.toward compliance; therefore, on the basis of the applicant's statement,'EG&G concludes that CEICo intends to-

-comply.with the NUREG-0612 criteria.

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C. EG&G-Conclusions and Recommendations e

EG&G concludes that Perry Nuclea.r Power Plant,: Units 1. and 2 are. '

in. compliance with the criteria of NUREG-0612, guideline 5, Lift bevicesNotSpecia.llyDesigned.

2.3.6. Cranes (Inspection. Testing, and ' Maintenance) [ Guideline 6, NUREG-0612, Article 5.1.1(6)]

"The crane should be inspected, tested, and maintained in accordance with. Chapter.2-2 of ANSI B30.2-1976, ' 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, o'r 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, calls for certain-inspections to be performed daily or monthly. For such cranes having limited usage, the inspections, test, and maintenance should be performed prior to their use)." '

A. Summary of Apolicant's Statements '

"The crane inspection, testing, and maintenance program is written in detail 'in the Perry Maintenance Section procedures.

For example, the Reactor Polar Crane monthly Preventative Maintenance, Reactor Polar Crane Quarterly and semiannual Preventive Maintenance,'and. Reactor Polar Crane Yearly Preventative Maintenance procedure (see attached) are written in detail'and Reference ANSI B30.2-1976. CEI will meet the:

specifications of. ANSI 830.2-1976" [9].

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B. EG&G Evaluation The draft copy of the PNPP Preventative Maintenance Instructions appear to be very complete and well presented. EG&G considers the content of draft procedures provided as being commitment toward compliance; therefore, on the basis of the applicant's statement, EG&G concludes'that CEICo intends to comply with the NUREG-0612 criteria.

C. EG&G Conclusions and Recommendations  ;

EG&G concludes that Perry Nuclear Power Plant, Units 1 and 2 are in compliance with the criteria of NUREG-0612, guideline 6, Cranes (Inspection, Testing, and Maintenance).

2.3.7 Crane Design [ Guideline 7, NUREG-0612, Article 5.1.1(7)]

"The crane should be designed to meet the applicable criteria and guidelines of Chapter 2-1 of ANSI B30.2-1976, ' Overhead and Gantry Cranes,' and of CMAA-70, ' Specifications for Electric Overhead Traveling Cranes' [9). 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 Applicant's Statements "All Cranes identified in this report that handle loads in safety-related buildings are designed to CMAA Specification 70 anc ANSI B30.2-1976 [10]." The applicant provided additional information in Reference [9] that includes crane manufacturer, l

type, serial number, load capacity, and purchase data.

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.B. EG&G Evaluation-On the basis'of.the applicant's statement and the additional information provided, EG&G feels that the criteria of guideline 7 will be satisfied.

C. EG&G Conclusions and Recommendations EG&G concludes that perry Nuclear Power Plant, Units 1 end 2 are in compliance with the criteria of NUREG-0612,. guideline 7~ Crane Design.

. 2.4 Interim protection Measures The NRC staff has established (NUREG-0612, Article 5.3) that six measures should be initiated to provide reasonable assurance that handling of heavy loads will be performed in a safe manner until final implementation of the general guidelines of NUREG-0612, Article 5.1, is complete. Four of these six interim measures consist of general guideline 1, Safe Load paths; guideline 2, Load-Handling Procedures; guideline 3, Crane Operator Training; and guideline 6, Cranes (Inspection, Testing, and Maintenance). The two remaining interim measures cover the following criteria:

e Heavy load technical specifications e Special review for heavy loads handled over the core.

Applicant implementation and evaluation of these interim' protection measures is contained in the succeeding paragraphs of this section.

EG&G recommends that because CEICo Perry Nuclear Power Plant, Units 1 and 2 are not yet. operational, and will not be operational for cuite some time, it is more appropriate tnat the time be spent ccmpleting 4

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i those' commitments toward compliance with the guidelines in NUREG-0612,

- Article 5.1 rather than addressing ' interim measures. Proper compliance with these' guidelines negates the necessity of interim protection measures.

.CEICo stated that their present position is to be in full compliance

-with the guidelines of NUREG-0612 prior'to fuel load-[9].

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3. CONCLUDING

SUMMARY

3.1 Applicable Load-Handling Systems The list of cranes and hoists supplied by the applicant as being subject to the provisions of NUREG-0612 is complete (see Section 2.2.1). The Applicant also fulfilled the requirements of

- NUREG-0612 concerning _exclu.ston aof various Overhead Handling Systems.

3.2 Guideline Recommendations  :

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Compliance with the seven NRC guidelines for heavy _ load-handling (Section 2.3) are satisfied at Perry Nuclear Power Plant, Units 1 anc

2. This conclusion is represented in tabular form as Table 3.1.

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IA8tt 3.1.

s COMPLI AN.E f%1Ris PtRRV miFLE AR POWER PL ANi$,12115 I AND 2 Guideline 1 Guideline 3 Guldeline 4 Geldeline 6 Guldeline 7.

Capac ity Safe Load Guideline 2 Crane Operator Special Lift Guideline 5 Crane-Test Crane ,

igulpacnt Designation Heavy (Ib)- Paths Procedur es Training Devices and Inspection

$ lines Desien Emeryncy Service Water C 30,000 C C C C C C .C -

Pump House Crane Reactor suliding Crane C ' 150,000 C C .C C C C C fuel-Handling Building Crane ,

C. 250,000 C C C C C C 'C C= Applicant action complies with leuRCG-0612 guideline.

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4. REFERENCES

1. NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, NRC.

2. "

. Stello, Jr. (NRC),~ ' Letter to all applicants.

Subject:

Request for Additional Information on Control of Heavy Loads Near Spent Fuel. NRC, 17 May 1978.

3. .USNRC, Letter to CEICo.

Subject:

NRC Request for Additional Information on Control of Heavy Loads Near Spent Fuel, NRC, 22 December 1980.

4 Letter to NRC,

Subject:

Control of Heavy Load Study from "

D. R. Davidson, Vice President, The Clevelano Electric Illuminating Company to D. G. Eisenhut, Director, USNRC,19 June ;1981.

5. ANSI B30.2-1976, " Overhead and Gantry Cranes".

6.

ANSI N14.6-1978, " Standard for Lifting -Devices for Shipping Containers -

Weighing 10,000 Pounds (4500 kg) or more for Nuclear Materials".

.7. ANSI B30.9-1971, " Slings".

8. CMAA-70, " Specifications for Electric Overhead Traveling Cranes".

, 9. Letter to NRC,

Subject:

Response to Draft Technical Evaluation Report. Control of Heavy Loads, from D. R. Davidson, The Cleveland Electric Illuminating Company to A. Senwencer, USNRC,

., 15 September 1982. -

10. The Cleveland Electric Illuminating Company GAI Report No. 2329, Rev. 2 (7 January 1982), Control of Heavy Lead Study.

11. Letter to NRC,

Subject:

Revision of Response to Technical Evaluation Report--Control of Heavy Loads, D. R. Davidson, Cleveland Electric Illuminating Company to A. Schwencer, USNRC, 8 November 1982.

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U.S. NUCLEAR REGULATORY COMMISSION BIBLIOGRAPHIC DATA SHEET EGG-HS-6264 4 TITLE AND SUBTITLE , 2. (Leave ceases Control of Heavy Loads at Nuclear Power Plants The Cleveland Electric Illuminating Company 3 AECirtENT S ACCESSION NO l Perry Nuclear -Power Plant, Units I and 2 (Phase 1) I 7 AUTHOR *Si 5 DATE REPORT COMPLE TED I MONvw lvEAR ,

J. P. Sekot, T. H. Stickley April 1983 i 9 PE AFORVING ORGANIZATION N AME AND MAILING ADDRESS (incivor I.a Cooes DATE REPORT ISSUED l MONYM lVLAR June 1983 EG&G Idaho, Inc, s it ,,v, .,, . ,

Idaho Falls, ID 83415 8 (tenve conneI 12 CPONSORING ORG ANIZ ATION N AME AND M AILING ADDRESS Itactuce I,a Coort Division of Systems Integration -

Office of Nuclear Reactor Regulation 11 FIN NO U.S. Nuclear Regulatory Commission Washington, DC 20555 A6457 13 T Y PE OF REPO AT et mico cov E at o fracius+e oeras8

'5 SUPPLE *?E N TA Av NOTES 14 nt e ere on s'a s 16 ABS T k AC T 1200 aorns or sem The Nuclear Regulatory Commission (NRC) has requested that all nuclear plants, either operating or under construction, submit a response of compliancy with

NUREG-0612. " Control of Heavy Loads at Nuclear Power Plants." EG&G Idaho, Inc.,

, has contracted with the NRC to evaluate the responses of these plants presently

' l under construction. This final report is a result of EG&G's review of the responses submitted for the Perry Nuclear Power Plant, Units 1 and 2 to the requirements of Section 5.1.1 of NUREG-0612 (Phase I). Sections 5.1.2, 5.1.4, 5.1.5, and 5.1.6 (Phase II)'will be covered in a separate report.

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' ? N E V A O R CS AND DOCUME N T t.N A L YS'S 17e DESCH'P TO AS i

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Make available only as specifically approved Unclassified by program office. Mclassificd s c.e van . . ,

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