ML20065C358

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Control of Heavy Loads at Nuclear Power Plants,Byron Units 1 & 2 & Braidwood Units 1 & 2, Draft Technical Evaluation Rept
ML20065C358
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 07/31/1982
From: Jensen S
ENERGY ENGINEERING GROUP
To:
NRC
Shared Package
ML20065C323 List:
References
REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8209230357
Download: ML20065C358 (30)
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2 CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS BYRON UNITS 1 AND 2 BRAIDWOOD. UNITS-1 AND 2 Docket Nos. 50-454, 50-455, 50-456, and 50-457 Author-S. A. Jensen Principal Technical Investigater T. H. Stickley I

! '- EG&G Idaho, Inc.

July 1982-t I

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' G209230357 820802 PDR ADOCK 05000454 A PDR

ABSTRACT 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 those plants presently under construction. This report contains EG&G's evaluation and recommendations for Byron /Braidwood.

EXECUTIVE'

SUMMARY

Byron /Braidwood does not totally comply with the guidelines of NUREG-0612. In general, compliance is insufficient in the following areas:

o Satisfactory action on Guidelines 2 and 3 has been promised but not completed.

o Commonwealth Edison has not satisfactorily responded to Guidelines 1, 4, 5 and 7.

The main report contains recommendations which will aid in bringing the above items into compliance with the appropriate guidelines.

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CONTENTS ABSTRACT ............................................................. i EXECUTIVE

SUMMARY

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1. INTRODUCTION .................................................... I 1.1 Purpose of Review ......................................... I 1.2 Generic 5ackground........................................ I 1.3 P l an t-S peci fi c Ba c kg round . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
2. EVALUATION AND RECOMMENDATIONS .................................. 4 2.1 Overview .................................................. 4 2.2 Heavy Load Overhead Handling Systems ...................... 4 2.3 General Guidelines ........................................ 9
3. CONCLUDING

SUMMARY

.............................................. 20 3.1 Applicable Load Handling Systems........................... 20.

3.2 Guideline Recommendations ................................. 20'

4. REFERENCES ...................................................... 22 TABLES 2.1 Crane / Hoist Systems Considered as Potential Sources for Damage of Safety Components ................... 7 3.1 NUREG Compliance Matrix ................................... 23 4

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objective using an accepted' approach or protection philosophy. The first portion of the objective, achieved through a s.t of general

  • l guidelines identified in NUREG-0612, Article 5.1.1, is to ensure that all load handling systems at nuclear power pitnts 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, f.or load handling systems in areas where their failure.might result-in significant consequences, either'(1) 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 of load handling accidents indicate that the potential consequences of any load drop are acceptably small. Acceptability of accident i consequences is quantified in NUREG-0612 into.four accident analysis-evaluation criteria.

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

o Provide sufficient operator training, handling system

( design, load handling instructions, and equipment inspection to assare reliable operation of the handling system I

t j o Define safe load travel paths through procedures and l operator training so that, to the extent practical, heavy loads-are not carried over or near irradiated fuel or safe shutdown equipment 4

o provide mechanical stops or electrical interlocks to prevent movement of heavy loads over irradiated fuel or in proximity to equipment associated with redundant l shutdown paths.

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TECHNICAL EVALUATION REPORT FOR , ,

BYRON /BRAIDWOOD -

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1. INTRODUCTION 1.1 Purcose of Review This technical evaluation report documents the EG&G Idaho, Inc. review of general load handling policy and procedures at Byron /Braidwood
  • This evaluation was performed with the objective of assessing j

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 Background Generic Technical Activity Task A-36 was establir.hed 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 handling 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 licensees, requesting information concerning the control of heavy loads near spent fuel.

I The results of Tast 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 providing protection from certain potential probTems, do not adequately cover the major causes of load handling accidents and should be upgraded.

In order to upgrade measures for the control of heavy loads, the staff develcped a series of guidelines designed to achieve a two phase

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2. EVALUATION AND RECOMMENDATIONS-2.1 Overview The following sections summarize Commonwealth Edison's review of heavy load handling at Byron /Braidwood accompanied by EG&G's evaluation, conclusions, anc recommendations to the-licensee for bringing the facilities more completely into compliance with the intent-of NUREG-0612. Commonwealth Edison's. review of the-facilities does not differentiate:between-the unitt so'it is assumed that all units are of identical design. The licensee has indicated the weight of a heavy load for this facility (as defined in NUREG-0612, Article 1.2) as 2000 lbs.
  • 2.2 Heavy Load Overhead Handling Systems This section reviews the licensee'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 list.

2.2.1 Scoce

" 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 system or component required for plant shutdown or decay heat removal."

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

1.3 Plant-Soecific Backaround . .

On December 22, 1980, the NRC issued a letter [3] to Commonwealth Edison, the licensee for Byron /Braidwood requesting that the litensee review provisions for handling and control of heavy loads at Byron /Braidwood, evaluate these provisions with respect to the guidel'ines of NUREG-0612, and provide certain additional information to be used for an independent determination of conformance to these guidelines. On April 7, 1982, Commonwealth Edison provided the initial response (4] to this request. -

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recommends that the Licensee clarify whether the cranes mentioned in our evaluation should be incl.ded in Table 2.1 ' -

or not. We have presently included them in the table.

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A. Summary of Licensee Statements The Licensee's review of overhead handling systems identified the cranes and hoists shown in Table 2.1 as those- .

which handle heavy leads in the vicinity of irradiated fuel or safe shutdown equipment.

The Licensee has also identified other cranes that have been excluded from satisifying the criteria of the general guidelines of NUREG-0612.

B. EG&G Evaluation 1

The Licensee appears to have included all applicable handling systems in their tables showing handling for which a load drop could damage equipment. However, it is unclear whether certain handling systems are to be exempted based on redundancy of the equipment or on the basis that the equipment is not required for safe shutdown. The handling systems in question include: Trolley Beams 53 and 54, PTS-4 and 5, SG-1, SG-2, SG-3, SG-4, Trolley Beams 28 and 29, and the cable tray drawbridge. The cranes to be exempted on the basis of redundancy of safety equipment which they are used to service should not be used except when such equipment is out of service. Damage to the equipment could have an impact on plant operation and therefore should be of concern to the Licensee.

C. EG&G Conclusions and Recommendations Based on the'information provided EG&G concludes that the Licensee has included all applicable hoists and cranes in their list of handling systems which must comply with the 4

requirements cf the general guidelines of NUREG-0612. EG&G f

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TABLE 2.1' (contineud).

a.

System Designations PTS-4 PTS-5 (Unit 2)

Trolley Beam 23 Trolley Beam 55 SG-11 (Byron) .

Turbine Building Crane Unit 1 and Unit 2 PTS-5 and PTS-9 Trolley Beam-42 (Braidwood) f G

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TABLE 2.1 CRANE / HOIST SYSTEMS CONSIDERED AS' POTENTIAL SOURCES FOR DAMAGE OF SAFETY COMPONENTS.

System Desicnations ,

Polar Crane SG-12 (Unit 1)

SG-13 (Unit 2)

Manipulator Crane Cable Tray Drawbridge Winch Reactor Coolant Pump Seal Removal Cranes for Loops 1, 2, 3, and 4 RCP Seal Removal Jib Crane, Loop 1 RCP Seal Removal Jib Crane Loop 2 RCP Seal Removal Jib Crane Loop 3 RCP Seal Removal Jib Crane Loop 4 Stud Tensioner Hoists (3) .

Loop 3 Jib 5 Loop 4 Jib 3 Loop 4 Jib 4 Loop 1 Jib 5

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Loop 1 Jib 6 Loop 2 Jib 3 Loop 2 Jib 4 -

Loop 3 Jib 6 Fuel Building Crane Spent Fuel Pit Bridge Crane >

Trolley Beam 10 Trolley Beam 11 Trolley Beam 24 Trolley Beam 25 Trolley Beam 28 Trolley Beam 29 Trolley Beam 53 Trolley Beam 54 SG-1 l SG-2 SG-3 SG-4 PTS-2

! PTS-3 (Unit 2) 7

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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. 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.

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

A. Summary of Licensee Statements The Licensee has evaluated load path locations for Byron /Braidwood. The Licensee states that load movement follows the safest and-shortest route with-the load as close-to the floor as possible. Due:to the nature of the. load paths, the Licensee states that marking the load paths on the floor is generally not feasible nor would it contribute to reactor safety.

B. EG&G Evaluation The Licensee response and drawings submitted indicates that Guideline 1 criteria have been partly satisfied at Byron /Braidwood. Load paths.have been developed for all heavy loads which have-been identified.

The Licensee's position on the unfeasibility of marking load paths on the floor is not acceptable. EG&G does agree that for some areas and/or loads floor marking is not the best method for designating a load path, but for certain loads it may be the best method available.

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i-2.3 General Guidelines 2

This section addresses the extent to which the applicable handling i

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.

TheNRChas[stablishedsevengeneralguidelineswhichmustbemetin 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:

A. Guideline 1--Safe Load Paths .

B. Guideline 2--Load Handling Procedures C. Guideline 3--Crane Operator Training D. Gui eline 4--Special Lifting Devices E. Guideline 5--Lifting Devices (not specially designed)

F. Guideline 6--Cranes (Inspection, Testing, and Maintenance)

G. 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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A. Summary of Licensee Statements s.

The Licensee states that procedures will be' developed to cover load handling operations for 'the heavy loads identified in Table 3.1-1 of NUREG-0612. These procedures will identify the required equipment, the inspection-and acceptance criteria prior to load movement, the steps and.

sequence in handling the load and define the safe load path and other special precautions. They also state that approved procedures will be in effect prior to fuel loading.

B. EG&G Evaluation The. Licensee has stated that ioad handling procedures will be developed which will comply with the requirements of Guideline 2. These guidelines should-be available for-possible review by the possible NRC prior to fuel loading.

C. EG&G Conclusions and Recommendations A

The Byron /Braidwood Stations do not presently comply with Guideline 2. In order to ccmply with the guideline the Licensee should complete the development of load handling procedures for the applicable cranes and loads. These

! procedures should be available for possible NRC review prior to fuel loading, i

l 2.3.3 Crane Operator Training [ Guideline 3, NUREG-0612, Article 5.1.1(3))

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

' Overhead and Gantry Cranes' [5]."

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Load path markings are meant to be used by load handling operators and their supervisors as a means for monitoring d.

proper areas where movements of heavy loacs will take place so that personnel not directly involved in* load handling -

will be alerted to keep these pathways clear of non-related materials. By consolidating the various load paths, the Licensee should be able to develop a systematic sequence of pathways for the movement of heavy loads to their lay-down or staging areas which is not overly complex or confusing to operators and supervisors, thus contributing to the general safety of plant personnel by minimizing interference with load handling operations. For some crane systems such as monorails the load paths are defined by the routing cf the monorail and the marking necessary would be minimal.

C. EG&G Conclusions and Recommendations

- EG&G concludes from the Licensee's response that the Bryon/Braidwood Stations partially comply with Guideline 1.

In order to adhere to the criteria of this guideline, EG&G recommends that the Licensee clearly mark safe load paths on the floor or by some other means in areas where heavy loads are handled.

2.3.2 Load Handling Procedures [ Guideline 2, NUREG-0612, Article 5.1.1(2)]

" Procedures should be developed to cover load handling operations for heavy loads that are or could be handled over or in proximity to irradiated fuel or safe shutdown equipment. At a minimum procedures should cover handlin'g of those loads listed in Table 3-1 of NUREG-0612. These procedures should include:  ;

identification of required equipment; inspections and acceptance criteria required before movement of load; the steps and proper i sequence to be followed in handling the load; defining the safe .

l path; and other special precautions."

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A. Summary .of' Licensee Statements The Licensee statements are as follows: .

The lifting devices have been or will be designed in accordance with indu9 trial standards using good engineering practices.

Special lifting devices 7for the reactor vessel head and

' upper.-internals have been provided'by Westinghouse. Both lifting rigs have been designed for 200% of the dead load using AISC allowables and load tested to 125% of their rated load. ,

B. EG&G Ev'aluation 1

The Licensee has identified only two (2) special lifting devices. The-information given on the design of these devices is inadequate for-a comparison of the criteria-used.

for design versus the requirements of Guideline 4.

. Insufficient--information has been provided by the Licensee-for EG&G to verify that periodic testing is performed to maintain continuing compliance in accordance with

Section 5.2 of ANSI N14.6-1978.

l C. EG&G Conclusions and Recommendations f

Byron /Braidwood Stations do not comply with Guideline 4. In f

i order to satisfactorily comply with the criteria, the Licensee should perform the following:

(1) rev,iew, evaluate and report on the design and ,

fabrication of all special lif ting devices w'th respect to the requirements of ANSI N14.6-1978 and Guideline 4.

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, e A. Summary of Licensee Statements 2

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The Licensee states that Byron /Braidwood will comply with ANSI B30.2-1976 with respect to operatof training, -

qualification, and conduct.

B. EG&G Evaluation No information on operator training, qualifications or conduct was given by the Licensee other than their statement that they will comply with ANSI B30.2-1976. This compliance should be complete before fuel loading occurs.

C. EG&G Conclusion and Recommendations Based on the Licensee's statement Byron /Braidwood will comply with Guideline 3. Procedures and program records should be readily~ available for possible review and inspection by the NRC staff.

2.3.4 Special Lifting Devices [ Guideline 4, NUREG-0612, Article 5.1.I(4)1 "Special' lifting devices should satisfy the guidelines of ANSI N14.6-1978, ' Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More for Nuclear Materials' [6]. 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 requirements in the standard. In addition, the stress design factor stated in Section 3.2.1.1 of ANSI N14.6 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 3.2.1.1 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."

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4 (2) submit. verification that procedures exist'for all special lifting devices which satisfy the requirements e.

of Section 5 (Acceptance Testing, Maia:enance, and Assurance of Continued Compliance) of ANSI A14.6-1978.

Compliance with this guideline should be complete for each lifting device before they are used in a critical ,

, situation.

2.3.5 Lifting Devices (Not Soecially Desioned) [ 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' [7]. However, in selecti'ng the proper sling, the load used should be the sum of the static and maximum 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 the cranes with which they may be used."

A. Summary of Licensee Statements The Licensee states that all lifting ' devices were designed according to industrial standards using good engineering practices.

i B. EG&G Evaluation Insufficient information was given for EG&G to properly evaluate the slings used at the Byron /Braidwood Stations.

C. EG&G Conclusions and Recommendations 4

The Byron /Braidwood Stations do not comply with Guideline 5. In order to comply the Licensee should submit verification for the following:

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i (1) slings.are installed and used in accordance with ANSI B30.9-1071 e.

(2) sling selection is based upon the sum of the static and -

maximum dynamic. loads t

(3) . slings are marked with the " static load" which produces the maximum static and maximum dynamic loads (4) clings restricted in use to only certain cranes are clearly marked to so indicate.

2.3.6 Cranes (Insoection, Testing, and Maintenance) fGuideline 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 performe'd prior to use where it is not practical to meet the frequen-ies 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, 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 Licensee Statements Cranes will be inspected, tested and maintained in accordance with Chapter 2-2 of ANSI B30.2-1976, 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 cranes having limited usage, the inspections and tests will be performed prior to their

. use. Approved procedures will be in effect prior to fuel load.

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S. EG&G' Evaluation-I The Licensees state that crane inspection, testing, and '

maintenance programs will comply with ANSI B30.2-1976 with exceptions as allowed by Guideline 6.

C. EG&G Conclusions and Recommendations Byron /Braidwood. Station complies with Guideline-6 on -the; basis of the Licensee.'s' statement.

2.3.7 Crane Desian fGuideline 7, NUREG-0612. Article 5.1.1(7)1 "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 .

i Overhead. Traveling Cranes' [8]. 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 The polar cranes and fuel han'dling building crares were designed in accordance with the 1975 Revision of CMAA-70 and the AISC specifications for those portions not covered by CMAA-70. Welding was performed in accordance with i

AWS 0.1.1. Both cranes are. designed.for Class "A" service-per CMAA-70 and have a minimum -safety factor of 5 on all lifting tackle and gearing.

The polar crane is provided with limit switches for bridge overtravel, pl'us two upper and one lower limit switch for each hoist. Mechanical end stops are also provided on the bridge, u e

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, The Fuel landling Building Crane is provided with end stops on the runways and bridge, plus upper and lows ~ limit ' -

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switches on both hoists.

.l The maniuplator crane was designed for Class C service per EOCI-61 and in accordance with the 1970 revision of -

CMAA-70. The manipulator crane is provided with interlocks to prevent fuel assemblies from colliding with the cavity

, walls and other objects.

The spent fuel pit bridge crane was designed for Class A service, and in acccrdance with the 1970 Revision of CMAA-70 and AWS D14.1. The spent fuel pit bridge crane is provided with end stops on the trolley beam and runway, plus upper and lower limit switches on each of the two 2 ton capacity hoists. The hoists are interlocked so that they cannot both be operated at the same time.

B. EG&G Evaluation The cranes mentioned by the Licensee in their response comply with or meet the intent of Guideline 7 based on the Licensee's statements.

f The Turbine Building Cranes were not mentioned in the Licensees response to this section. Monorails and other cranes which do not easily fall into the classifications for which CMAA 70 and ANSI B30.2 apply were not included in the Licensee's response. EG&G was therefore unable to evaluate their conformance to Guideline 7.

C. EG&G Conclusions and Recommendations Byron /Braidwood Stations comply with Guideline 7 to a substantial degree on the basis of the Licensee's statements. However, no information was available on design 18

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standards for the majority of the cranes listed as being j subject to the guidelines. EG&G recommends t* the -

Licensee perform the following: -

  1. t (1) Submit verification that menorails, jib cranes, etc., ,

i were designed and fabricated to applicable industrial

{ sta,ndards comparable to CMAA 70 and ANSI B30.2.

j (2) Submit verification that the Turbine Building Cranes l were designed and fabricated in accordance with CMAA 70

and ANSI B30.2 or justify their design and fabrication to some other standard.

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3. ,CONCt.UDING SU.V!ARY a.

3.1 Applicable load Handlino Systems The list of cranes and hoists supplied by the licensee as being subject to the provisions of NUREG-0512 is adequate (see .

Section 2.2.1). Ho, wever, clarifications should be made as to whether certain cranes are to be excluded. .

3.2 Guideline R' ecommendations Compliance with the seven NRC guidelines for heavy load handling (Section 2.3) are partially satisfied at Byron /Braidwood. This conclusion is represented in tabular form as Table 3.1. Specific recommendations to aid in compliance with the intent of these guidelines are provided as follows:

Guideline Recermendation

1. (Se:tiva 2.3.1) a. Clearly mark safe load paths on the floor or by some other means.
2. (Section 2.3.2) a. ' Complete development of load handling procedures.
3. (Section 2.3.3) a. Operator training records, and programs should be available for NRC review or inspection.

. 4. (Section 2.3.4) a. Fully review evaluate and report on the design and fabrication of special lifting devices with

, respect to ANSI N14.6

b. Submit verification that continued

-- testing of special lifting devices will comply with ANSI N14.6.

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Guideline Recommendation <
5. (Sectici. 2 3.5) a. Submit verification that slings ' -

are installed and used in accordance with ANSI B30,9. ,

b. Submit verification that sling

. selection is based upon the sum of the static and maximum' dynamic loads.

c. Mark slings with the " static.

load" that produces the maximum-static.and dynamic loads.

4 i d. Clearly mark slings restricted

'. in use to only certain crancs.

! 6. (Section 2.3.6) a. Byron /Braidwood complie,s with l this guideline i

7. (Section 2.3.7) a. Submit verification that the Turbine Building Cranes, monorails, jib cranes, etc.,

where designed and fabricated to

, applicable industrial standards comparable to CMAA-70 and ANSI B30.2.

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4. REFERENCES

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1. NUREG-0612 l

Control' of Heavy Loads at Nuclear Power Plan!s l 'I NRC j 2. V. Stello, Jr.. (NRC)

Letter to all licensees.

Subject:

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

3. USNRC Letter to (Company).

Subject:

NRC Request for Addition'al Information on Control of Heavy Loads Near Spent Fuel NRC, 22 December 1980 1

4. Commonwealth Edison Letter to' Director of Nuclear Regulatory Regulation.

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2.

7 April 1982

5. ANSI B30.2-1976

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" Overhead and Gantry Cranes" i

6. ANSI N14.6-1978

, " Standard for Lif ting 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" j 4

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SVRON/8RAIDWOOD NUR(G C001PLIANCC 9%TR11 . l Ittelo 3.1 I s

Weight a or Guideline I Guideline 2 Guideline 3 Guldeline 4 Guideline 5 Guideline & Guideline 7 5 Equipment Capacity Safe Load Crane Operator Special Lifting Crane - Test i

.Designa t f on lleavy Loads (tons)' Paths Procedures Training Devices Slings and inspection Crane Desten l t.

Palar Crane 230/40 ton Reactor Vessel llead 411.750 lb. leC E R I I C C Reactor Upper Inter- 145,000 lb.

nals Reactor Lower Inter. 269.600 lb. -

nals Reactor Coolant Pump~'

77.500 lb.

Ntors Reactor Core Barrel 217.300"*

lb.

Assembly '

Main flook Lower Load 6783 lb. .

Block Auxillary Nok Lower 1770 lb.

Load Bls,ct 50-12(Unit 1) Reactor Vessel llead I ton K R R I I C I Stud Collar's - 20 SG-13(Unit* 2) Reactor Vessel Head I ton -

Studs - 806 ' .

  • Reactor Vessel Head Stud llole Plugs -

30(est.) '-'

m ilpulator
  • Crane Fuel Assembly - I ton IIC R R I I C C 1700 lb.  : 1 Cable Tray .

Drawbridge llinch Cable Tray Drawlerfdge 10 ton IIC R R I I 'C 9000 lb -I

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R:act:r Coolant

  • Reactor Coolant Pump I ton MC 'R R I I C I Pump Stal Removal Seal flousings -

Cranes for Loops 1500 lb '

l.2.3.4 Reactor Coolant Pimp Couplings - 1500 lb j

RCP Stal Removal Reactor Coolant Pump I ton NC R R 'I I C I #

Jib franc toop 1 Seal flousing -

1500 lb Reactor Coolant Pump Coupilng - 1500 lb C = Licensee action campiles with falREG-0612 Guideline.

NC

  • Licensee action does not comply with NUR[C-0612 Guideline. I j R = Licensee has pomposed sevisions/ modifications desinned to comply with NURfG-0612 Guideline.

I - Insufficient inioinution provided by the Licensee,

^

s ,

I

e ,

.. _ - - _. ._ ~

Tabla 3.1 (Cont'd)

/

Weight or Guideline 1 Guideline 2 Guideline 3 Guideline 4 Guideltne 5 Guideline 6 Guideline ?

Equipnent Capacity Safe Lead Crane Operator Special Lifting Crane - Test Designation Heavy Loads (tons)_ paths Procedures ___ Training Devices Sitngs and inspection Crane Design RCP Seal Removal Reactor Coolant Pump 1 Lon NC R R I I C I Jib Crane Loop 2 Seal liousing -

1500 lb Reactor Coolant Pump Coupling - 1500 lb f(CP 5m1 Removal Reactor Coolant Pump I ton NC R R I I C I Jib Crane Loop 3 Seal llousing -

1500 lb Reactor Coolant Pump ,

Coup 1Ing - 1500 lb .

.3, RCP Sssi Removal Reactor Coolant Pump I ton NC R R I I C I Jib Crane Loop 4 seal flousing -

1500 lb Reactor Coolant Pump Coupilng - 1500 lb -

Stud Tecsfoner Reactor Vessel llead 2 ton NC R R I I C I .

Iloists (3) Stud Tensioner - N/A Reactor Vessel itead Studs - 806 lb Loop 3 Jtb 5 RC toop Stop Valve 2 ton NC R R I I C I Operator - 2160 lb toop 4 Jib 3 RC loop Stop Valve 2 ton NC R R I I C I Operator - 2760 lb ,

Loop 4 J1b 4 RC toop Stop Valve 2 ton NC R R I I C . I Operator - 2760 lb Loop I J1b 5 RC toop Stop Valve 2 ton NC R R I I C I Operator - 2760 Loop 1 Jib 6 RC toop Stop Valve 2 ton NC R R I I C I

Operator - 2760 lb ,

loop 2 J1b 3 RC Loop Stop Valve 2 ton hC R R I I C I Operator - 2760 lb Loop 2 J1b 4 RC toop Stop Valve 2 ton NC R R I I C 1 Operator - 2760 lb .

C = Licensee action complies with'IfiRLG-0612 Guideline.

  • fic = Licensee action does riot comply with FAIRLG-0612 Guideline.

R = Licensee has proposol revisions /nodifications designed to comply with NUREG-0612 Guideline.

I - Insuf ficient infomation provided by the Licensee. -

4 5 . .

x --- . .

- - - _ - - - ___a

.. j itbla 3.1 (Cont'd)

Weight or Guideline 1 Guideline 2 Guideline 3 Guideline 4 Guldeline 5 Guideline 6 Guideline 7 .

Equfgeent Capacity Safe load Crane Operator Special Lif ting Crane - Test Designation Heavyh9ds (tons) Paths Procedures Training Devices Slings and Inspection Crane Design loop 3 jlb 6 RC Locp Stop Valve 2 ton MC R R I I C I Operator - 2760 lb

! Fuel ik.Ilding Spent Fuel Cask - 125 ton NC R R I I C C Crane '

218.000lb(TN-12)

Fuel Assembly - 1467 lb (Main Holst tower Load Block - 5600 l'2)

Aux 111ary Holst tower Load Block - (1500 lb .

est.) _,

~

failed fuel Cannister -

940 lbs Control Rod Cluster -

158 lbs

. Spelt full Pit New Fuel Assembly - 2 ton IIC R R I C

!BridgaCrane 1467 lb * - I ~C Spent Fuel Assembly - '

1467 lb $

Fuel Handling Tools -

375 lb max. .

Failed fuel Cannister -

940 lbs Control Rod Cluster -  !

158 lbs.

Tro11:y Beam 10 Motor Control Center 3 ton' NC R R I I .C I Components - 1500 lb .

Electrical Penetration '

Assembly Components -

2000 lb Pressurlier Heater Trans-former Components -

2000lb(Est.)

Trailsy Beam 11 Motter Control Center 3 ton IIC R R I I C I
    • Coroonents - 1500 lb '
  • Electrical Penetration Assenbly Components - '

2000 lb Pressurizer licater Trans-former Components -

200lb(Est.)

C = Licensee action es M ies with IN1 RIG-0612 Guldeline.

HC = Licensee action does not con 4.ly with NUR[C-0612 Guideline.

R = Licensee has pinnaned sevisions/piadificatinns desinned to comply with laNEG-0612 Guideline.

I - Insuf ficient infoiwlton provided by the Licensee. -

4. _ ^ _% .s .i : e uc . e a m w ex: . n r _. n _, m m, _ . _, _ . _ _ _ _ _ _ _ _ _ _ _ ____

1

  • Ce . . (ht t'd, .

height .

or Guideline 1 Guideline 2 Guiceline 3 Guideltrie 4 Guideltne 5 Gutoeltr.e E ktoeline 7 .

i Equipent Capacity Safe load Crane Operator special tsiting trane - Test Paths Proc edures Training Devices $ lings and lespection Crane Design ',

Designation Heavy loads (tons) t RitR lleat Exchangers 12 ton NC A R I I C I irs 11ty Beam 24 Tube Bundle -

14.500 lbs Concrete Plugs -

15,000 lbs Trollty Beam 25 RilR IIcat Exchangers 12 ton NC R R I I C I Tube Bundle -

14,500 lbs Concrete Plugs - ,

15,000 lbs .3 ,

irsllsy Beam 28 --- 3 ton NC R R I I C I Trs11ty Beam 29 Valve Operator for 3 ton NC R R I I C I ICVil2A - weight N/A Trclity Beam 53 Charging Purp - 8 ton NC R R I I C I ,

7500 lb Charging Pump Motor -

4345 lb ,

Tr:11cy Beam 54 Charging Pump - 8 ton HC R R I I C I

' 7500 lb ,

Charging Pump and l f

Motor - 4325 lb SG-1 Diesel Generator 2 ton NC R R I I C I Cylinder llead .  !'

. Covers - 830 lb -

SG-2 Diesel Generator 2 ton NC R R I I C I .

Cylinder llead Covers - 830 lb SG-3 Diesel Generator 2 ton HC R R J I C 1 Cylinder llead Covers - 830 lb SG-4 Diesel Generator 2 ton NC R R I I C I Cylinder llead Covers - 830 lb .

C = LTcensee action conflies with f40 REG-0612 Guideline.

  • NC = tirensee action does not cwply with NURIC-0612 Guideline.

R = Licensee has proposed sevisions/nodifications desinned to comply with NUREG-0612 Guideline.

I - Insufficient info e tion provided by the Licensee. .

e b

.a_ _ _ _ .

.--.-.m

l

.I Tcble 3.1 (Cest'd) .

./ Weight or Guideline 1 Guideline 2 Guideline 3 Guideline 4 Guideline 5 Guideline 6 Guideline 7 .

Equipment Capacity Safe Load Crane Operator Special Lifting Crane - Test Designation Heavy loads (tons) Paths Procedures Training Devices Slings and Inspection Crane Design P15-2 Concrete Plugs - 6 ton NC R R I I C I 11.700 lb 4

PIS-3 (Unit 2) Contalement Spray Pump / Motor - i 7307 lb Charging Pump -

7500 lb Safety injection Pump - 5260 lb Cturging Pump Motor -

4345 lb .

Safety Injection .

Pump Motor - 4345 lb PTS-4 Safety Injection 6 ton NC R R I I C I Pump - 5260 lb -

PTS-5(Unit 2) Safety Injection Pump Motor - -

3100 lb Tr:11sy Beam 23 Charging Pump - 10 ton NC R R I I

' C I 7500 lb Containment Spray Pump /Phtor - 7307 lb RifR Pump / Motor -

6200 lb Safety Injection Pump - 5260 lb Safety injection

  • Motor - 4345 lb ,

ESW Pump - 9500 lb ESW Motor - 12,000 lb Tro11ty Beam 55 Charcoal filters - 8 ton NC R R I I C I 500 1b Fan. Motors - 2000 lb

  • Other HVAC Equipment -

12,000 lb '

SG-Il Essential Service 12 ton NC R R I I Water Makeup ' C I Pump - 7000 1b Circulating Water -

Nkeup Pump thter .

C = Licensee action complies with NUREG-0612 Guideline.

  • NC = Licensee action does not (omply with NUREG-0612 Guideline.

R = Licensee has proguned revisions / modifications designed to comply with MIREG-0612 Guideline.

I - Insuf ficient inloewution penvided by the Licensee.

. k a

~

Ytble 3.1 (Cont'd)

  • /' Weight or Guldeline 1 Guideline 2 Guideline 3 Guideline 4 Guideline 5 Guideline 6 Guideltne 7 Equipment Capacity Safe Load Crane Operator Special Lifting Crane - Test Heavy toads Paths Procedures Training Devices $11_ngs and Insnection Crane Design Designa tion (tons)

ESW Mekeup Pump Driver - 2250 lb ESW Makeup Pump .

Gearbox - 2250 lb Turbine Building Tuibine Components: 125/25 ton NC R R I I C I _

Cranes Unit 1 LP Spindles-294,000 lb

(* Unit 2) IIP Spindles-131,000lb 148/25 ton

  • HP Cylinder Cover -

166,000 lb .

LP Cylinder Cover - ..,

172.300 lb Other Lighter Loads PTS 8 & PIS-9 Circulating Water Pump 30 ton HC R . R I I C I Motor - 75,000 lb Trellty Beam 42 WS Pump - 41.300 lb 12 ton

  • WS Hotor - 22.500 lb . .

l C = Licensee action complies with NUREG-0612 Guideline. '

NC = Licensee action does not comply with NUREG-0612 Guideline. I*

R = Licensee has proposed revisions / modifications desinned to comply with NUR[C-0612 Guideline.

I - Insuf ficient infonnation provided by the Licensee. '. .

h .

.._ .

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