ML20053C376
| ML20053C376 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/31/1982 |
| From: | Dixon B, Stickley T EG&G, INC. |
| To: | NRC |
| Shared Package | |
| ML20053C374 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612 NUDOCS 8206020024 | |
| Download: ML20053C376 (46) | |
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CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS CDMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 00cxec Nos. 50 445, 50-446 Author
- B. W. Dixon l
Principal Technical Investigator -
T. H. Sticxley EG&G Idano, Inc.
Maren 1982 8206020024 820520 PDR ADOCK 05000445 A PDR
ABSTRACT The Nuclear Regulatorf Commissioa (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 tne-responses of those plants presently under construction. This report contains EG&G's evaluation and recommendations for the Comanche Peak Steam Electric Station Units 1 and 2.
EXECUTIVE
SUMMARY
Comanche Peak Units 1 and 2 do not totally comply witn the guidelines of NUREG-0612. In general, compliance is insufficient in the following areas:
o load paths have not been fully developed or properly implementeo; v lif ting devices nave not Deen rated and marxed to account for dynamic effects; o some cranes are not designed per all of the indicated regulations; o The minimum weignt for a " heavy load" per NUREG-0612 definition has not been established.
The main report contains recommendations which will aid in bringing the above items into compliance with the appropriate guidelines, i
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CONTENTS Page Section Title 1
ABSTRACT .............................................................
E XE CU T IVE S UMMAR Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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- 1. I N TR O D U CT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.1 Purpose of Review ......................................... I Gen er i c Ba ck gro u nd . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.2 P l ant-S peci f i c Ba cxgro und . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1.3 4
- 2. EVALUATION AND RE00MMENDAT IONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
4 2.1 Overview ..................................................
4 2.2 Heavy Load Overhead Handling Systems . . . . . . . . . . . . . . . . . . . . . .
0 2.3 Ge n er a l Gu i d e l i n e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
19 2.4 Int erim Protection Measures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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- 3. CO NCL U D I N G S UMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
23 3.1 Ap pl icable Load Handl ing Systems . . . . . . . . . . . . . .. . . . . . . . . . . .
23 3.2 Guideline Recommendations .................................
25 3.3 In t er i m P ro tect i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
S u mmary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 3.4 27
- 4. REFERENCES ......................................................
TABLES 2.1 Handling Systens With Potential for Hazardous Load Drop ......... 28 2.2 Handling Systems not Requiring Adat tianal Review . . . . .. .. .. . .. . . . 31 34 3.1 f;U REG-0612 Compl i anc e Matri x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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TECHNICAL EVALUATION REPORT FOR CCMAur oEAK STEAM ELECTRIC STATION UNITS 1 AND 2
- 1. INTRODUCTION 1.1 Purcose of Review This technical evaluation report documents the EG&G Idaho, Inc. review i
of general load handling oolicy and procedures at the Comanche' Peak Steam Electric Station. 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 3ackercund Generic Technical Activity Task A-36 was estaolished by the U.S.
Nuclear Regulatory Commission (NRC) staff to systematically examine staff licensing criteria and the adequacy of measures in effect at coerating nuclear power plants to assure the safe handling of heavy loads and to recommend necessary changes to these measures. Inis activity was initiated by a letter issued by the NRC staff on May 17, 1973 (2) to all power reactor licensees, requesting information concerning the control of neavy loads near spent fuel.
The results of Task A-36 were reported in NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants." The staff's conclusicn from this evaluation was that existing measures to control the handling of neavy loacs at coerating plants, although providing crotection from certain potential problems, do not adeauately cover the major causes of load handling accidents and 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, acnieved througn a set of general guidelines identified in NUREG-0612, Article 5.1.1, is to ensure tnat all load nandling systems at nuclear power plants are designed and operated sucn that their probability of failure is uniformly small and appropriate for the critical tasks in which they are employed. The
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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 t*1t, for load handling systems in areas where their failure mignt 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 loao 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 deco are acceptably small. Acceptability of accident
. consequences is quantified in NUREG-0612 into four accident analysis eveluation criteria.
The approach used to develoo the staff guidelines for minimizing the potential for a loao 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 insoection to assure reliable operation of the handling system; o 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; 2
o provide mechanical stops or electrical interlocks to prevent movement of ieavy loads over irradiated fuel or in proximity to equipment associated with redundant shutdown patns.
Staff guidelines resulting from tne foregoing are tabulated in Section 5 of NUREG-0612.
1.3 Plant-Soecific Background On Decemoer 22, 1980, the NRC issued a letter [3] to Texas Utilities Generating Company (TUGC), the licensee for Comanche Peak requesting that the licensee review provisions for handling and control of heavy loads at Comanche Peak Units 1 and 2, evaluate these provisions with respect to the guidelines of NUREG-0612, and provide certain additional information to be usea for an indepencent cetermination of conformance to these guidelines. On August 7,1981, TUGC provided the initial response [4] to this request. Additional information was provided on October 8, 19 81 [5].
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- 2. EVALUATION AND RECOMMENDATIONS 2.1 Overview The following sections summarize Texas Utilities Generating Company's ,
(TUGC) review of heavy load handling at Comancne Peak 1 and 2 accompanied by EG&G's evaluation, conclusions and recommenaations to the licensee for bringing the facilities more completely into compliance with the intent of NUREG-0612. TUGC's review of the facilities does not differentiate between the two units so it is assumed that both units are of identical design. The licensee has not directly indicated the weight of a heavy load for this facility (as defined in NUREG-0612, Article 1.2), however, a value of 1,700 pounds has been inferred from the load data provided.
2.2 Heavy Load Overhead Handling Systems i This section reviews the licenseCs list of overhead handling systems which are subject to the criter'.. of NUREG-0610 and a review of the justification for excluding over lead 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 interlocxs, tecnnical specifications, ooerating procedures, or detailea structural analysis) and justify the exclusion of any overnead handling system from your list by verifying that there is sufficient pnysical separation from any load-impact point and any safety-relatec component to permit a determination by inspection tnat no neavy load croo can result in camage to any system or component required for plant shutdown or decay neat removal."
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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 loads in the vicinity of irradiated fuel or safe shutdown and decay heat removal equipment.
The licensee has also identified numerous other cranes tnat have been excluded from satisifying the criteria of the general guidelines of NUREG-0612, (Table 2.2). Exemption was based upon " sufficient physical separation from systems required for plant shutdown or decay neat removal to prevent damage to these systems, as determined by visual inspection." Also, the loads carried by the cranes do not travel "in or near" th'e spent fuel storage area.
B. EG&G Evaluation The lack of detailed " separation criteria" and Jther information such as drawings showing the relationship between crane coverage and location of safety equipment makes evaluation of the licensee's statements difficult.
C. EG&G Conclusions and Recommendations Since there is no information to the contrary EG&G concluces tnat the licensee has included all applicable hoists and cranes in their list of nandling systems wnich must comply with the requirements of tne general guidelines of NUREG-0612.
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2.3 General Guidelines This section addresses the extent to which the applicable nandling systems comply with the general guidelines of NUREG-0612 Article 5.1.1. EGLG's conclusions and recommendations are provided in sunnaries for each guideline.
The NRC has established seven general guidlines whicn 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:
A. Guideline 1--Safe Load Paths B. Guideline 2--Load Kandling Procedures C. Guideline 3--Crane Operator Training D. Guideline 4--Special Lif ting 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 tne reactor vessel, near spent fuel in the spent fuel pool, or in otner areas wnere a load drop may damage safe shutdown systems. TSe succeeding paragrapns address the guidelines individually.
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2.3.1 Safe Loaa Patns [ Guideline 1, NUREG-0612, Article 5.1.l(1)]
"Saf e load paths snould be derined for the movement of heavy loads to minimize the potential f or heavy loaas, if dropped, to impact irradiated fuel in the reactor vessel and in the spent fuel pool, or to impact safe snutdown equipment. The patn snould follow, to the extent practical, structural floor members, beams, etc., sucn that if the load is dropped, tne structure is more ,
likely to withstand the impact. These load patns should be defined in procedures, shown on equipment layout drawings, and clearly marked on tne floor in the area wnere tne loaa is to be hancied. Deviations from defined load patns should require written alternative procedures approved by tne plant safety review committee."
A. Summary of Licensee Statements
"' Safe load areas' (areas serviced by a particular crane in which a load drop will not result in damage to shutdown or decay nect removal equipment or spent fuel) have Deen identified where applicable for tne cranes listed ia (Table 2.1]. Equipment hanoled by these cranes will be transported whenever possible within the identiriad saf e load areas. The ' safe load areas' will be clearly identified for each crane by a comoination of placaras, procedures, and marked off areas near plant snutdown and decay neat removal equipment or wnere spent fuel is storea."
"'Saf e load patns' will be establisned f or equipment handled outside the safe load areas and will be incorporated in tne particular load handling procedures. The ' safe load patns' will be estaolished with the purpose or transporting equipment over safe shutcown or decay neat removal equipment or spent fuel via the sarest and snortest route to the nearest 'saf e load area' . The equi;: ment will then ce transported witnin the ' ,af e load area' to its final cest.ination."
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" Safe load paths will also be identified for those loads which will require a load drop analysis in order to satisfy the NUREG-0612 requirements. These safe load paths will be described and illustrated as part of any load drop analysis performeu in response to the Part II requirements of the NRC Decemoer 22, 1980 letters."
- 8. EG&G Evaluation The licensee's response states that " safe load areas" have been developed for each crane, where applicable. However,
" safe load paths" for eacn heavy load have not yet been established.
EG&G feels that the idea of " safe load creas" is only partially sound. An extremely large load, if dropped, may have sufficient momentum to penetrate structural barriers that would contain a smaller " heavy load". Thus a marked
" safe load area" may in, duce a f alse sense of security. The licensee should take steps to ensure that marked safety zones clearly indicate the maximum applicable safe load.
For overly large heavy loads specific load paths should De marked across the safe zones.
The licensee has not indicated that safe load paths will ce marked on equipment layout drawings, as specified in the guideline. The licensee has also failed to indicate that deviations from defined paths will require written alternatives approved by the plant safety review committee.
Since tne development of safe load paths is not complete a more thorougn evaluation is not possible at this time.
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C. . EG&G Conclusions and Recommendations Comanche Peak 1 and 2 are not in compliance with the criteria of Guideline 1.. The licensee snould implement the following actions:
(1) complete the development and implementation of safe load paths for all heavy loads; (2) insure that all safe load paths and areas are appropriately marked on equipment layout drawings; (3) implement administrative controls requiring written alternatives for load path deviations.
2.3.2 Load Handling Procedures [ Guideline 2. NUREG-0612, Article 5.1.l(2)]
" Procedures shouk 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 snoulo cover handling of those loads listed in Table 3-1 of NUREG-0612. These procedures should include: identification of required equipment; inspections and acceptance critria required before movement of loaa; the steps and proper sequence to be followec in nandling the load; defining the safe path; and otner special precautions."
A. Summary of Licensee Statements "For some heavy loads, it may De necassary to operate outside the ' safe load areas' and transport tne neavy load over or near plant shutdown or decay heat removal equipment or spent fuel. In tnat event, special precautions or procedures will be utilized with the purpose of minimizing the risk of a heavy load drop in these areas. The procedures will consist of load drop prevention measures 9
such as a list of required equipment, inspection, acceptance .
criteria for the movement of the load, sequence of steps, etc."
B. EG&G Evaluation The licensee has stated that procedures are being developed for loads carried outside of " safe load areas." The substance of these procedures are consistent with the requirements of NUREG-0612. These procedures should be extended to include overlarge loads carried in " safe load areas." The procedures should be available for possible NRC review prior to plant operaton.
C. EG&G Cnnelusions and Recommendations Comancne Peak 1 and 2 are not presently in compliance witn the criteria of Guideline 2. The licensee should implement the following actions: {
i (1) comolete the procedures mentioned in Section A aoove g and retain them for possible NRC review; j
l (2) ir'2ure that the orocedures cover overlarge loads in f
" safe load areas" when these loads exceed the rated
. capacity of the structural components in these areas.
Dynamic effects must be considered wnen developing capacity ratings. j 2.3.3 Crane Ooerator Training IGuideline 3. NUREG-0612 Article 5.1.l(3)]
" Crane operators should be trained, qualified and conduct tnemselves in accordance with Chaoter 2-3 of ANSI B30.2-1976,
'Overnead and Gantry Cranes' [6]."
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A. Sunnary of Licensee Statements "No exceptions to ANSI 830.2-1976 with-respect to operator training, qualification, and conduct are anticipated at tnis time, however, if it is later determined that exceptions are required, written notification will be made to the foclear Regulatory Commission."
- 8. EG&G Evaluation The licensee's statement contains insufficient information to determine compliance. The statement infers that procedures governing operator training, etc., are not complete at this time. Sufficient information would be provided by verifying the implementation of sucn procadures.
. C. EG&G Conclusion and Recommendations Comanene Peak 1 and 2 may be in compliance with the criteria of Guideline 3, however, insufficient information has been provided to the reviewer. The licensee should verify implementation of the procedures governing operator training, qualificatior.s and conduct.
2.3.4 Soecial Lif tinc Devices [ Guideline 4, NUREG-0612, Article 5.1.l(4)]
"Special lifting devices should satisfy the guidelines of ANSI N14.6-1978, ' Standard for Special Lif ting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More for Nuclear Materials' [7]. This standard should apply to all special lirting devices whicn carry heavy loads in areas as defined above. For operating plants certain inspections and load tests may oe 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 snould be based on the combined maximum static and dynamic loads tnat could be imparted on tne handling device based on characteristics of the crane wnicn will be used. This is in lieu of the guideline in Section 3.2.1.1 of 11
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 nandling device."
A. Summary of Licensee Statements "Although a special lif ting device for a spent fuel shipping container weighing 10,000 pounds or more has not as yet been procured, ANSI N14.6-1978 will be invoked when this special lifting device is obtained. Although it is anticipated at this time tnat the standards for the lifting devices will be met, it may later be determined that alternatives to the standard are required. In tnat event, written notification will be made to the Nuclear Regulatory Commission descrioing the alternatives and their equivalency in terms of load handling reliability.
Comanche Peak Steam Electric Station (CPSES) and Westinghouse Nuclear Division are currently reviewing the design and construction specifications of the Reactor Vessel Heaa and Reactor Internals lifting rigs. The results of this review will be submitted with the Part II response of CPSES compliance with NUREG-0612."
- 8. EG&G Evaluation Guideline 4 states that all special lifting devices involved with heavy load lifts will comply with ANSI N14.6-1978, not just those devices useo to handle spent fuel snipping containers. A review of the lif ting device and heavy loads lists provided by tne licensee indicates tnat the criteria of Guideline 4 should be met for at least the following devices:
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(1) Spent Fuel Cask Lifting Device; (2) Reactor Vessel Head Lifting Rig; ,
(3) Reactor Internals Lifting Rig; (4) Failed Fuel Assembly Lifting Tool.
EG&G has included item (4) above as we feel that a failed '
assemoly is a special case not exemoted by the definition of a
" heavy load" contained in NUREG-0612 Section 1.2 The criteria of Guideline 4 is more restrictive than that of ANSI N14.6 in that dynamic loads must ce considered. Thus the licensee snould ensure tnat ANSI N14.6 Section 3.2.1.1 is ort?erly appended wnen applied to the special lifting devices covered by the guideline. .
The licensee should take all reasonable steps to ensure that item (1) above, wnen procured, meets the appended requirements of ANSI N14.6 as NRC approval of exceptions to required criteria is not insured.
C. EG&G Conclusions and Recommendations Comanche Peak 1 and 2 are ,ot in comoliance with the criteria of Guideline 4. The licensee should imolement the following actions:
(1) append At4SI N14.5-1978 Sectan 3.2.1.1 to include dynamic effects as specified in tne guideline; (2) cemonstrate that all special lifting devices at the f acility covered oy NUREG-0612 meet tne appended requirements of ANSI N14.6.
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2.3.5 Lifting Devices (Not SDecially Designed) (Guidatine 5, NUREG-0612, Article 5.1.l(5)] -
" Lifting devices that are not specially designed should be installed and used in accordance witn 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 maximum dynamic load. The rating identified on tne 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 snould be clearly marked as to the cranes with which they may be used."
A. Summary of Licensee Statements "Lif ting devices... will comply with ANSI B30.9-1971 where applicaole."
- 8. EG&G Evaluation The licensee has only addressed ANSI B30.9 in the reply.
Guideline 5 is more restrictive than ANSI B30.9 as tne marking procedure is appended and the rated working load must be factored to account for dynamic effects.
C. EG&G Conclusions and Recommcndations Comanche Peak I and 2 do not comply with the criteria of Guideline 5. EG&G recommends that the licensee implament the following actions:
(1) for all slings used on heavy load lifts verify compliance witn ANSI B30.9 cased on working loads that correspond to tne sum of tne static and maximum dynamic load; (2) review sling markings and verify compliance with tne marking procedures of ANSI 330.9 and NUREG-0612 Article 5.1.l(5).
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2.3.6 Cranes (Insoection, Testins , and Maintenance) [ Guideline 6, NUREG-0612, Article 5.1.l(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 830.2 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 durir.g power operation. ANSI B30.2, however, calls for certain inspections to De performed daily or mnnthly. For sucn cranes having limited usage, the inspections, test, and maintenance should be performed p;ior to tneir use)."
A. Summary of Licensee Statements ANSI B30.2-1976, Onapter 2-2, will be invoken with respect to crane inspection, testing and maintenance.
With respect to Section 2-2.1.1.1 of ANSI 830.2-1976, cranes locateo within Containment will be inspected per the required visual inspection schedule only d; ring the periods of crane operation (generally during refuelings and cold shutdowns). This is necessary because periodic inspections during power operations are impractical due to hign radiation levels in Containment.
No other exceptions to the standard are anticipated at this time, newever, if it is later determined that exceptions are required, written notification will be made to the Nuclear Regulatory . Commission.
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- 8. EG&G Evaluation The licensee's statement indicates that measures consistent with the requirements of Guideline 6 will be invoked. EG&G assemes that these measures will be implemented prior to 15
fuel handling at the f acility. Proceoures, inspection records, and otner documentation should be retained and available for possible NRC review.
C. EG&G Conclusions and Recommendations Comanene Peak 1 and 2 will be in compliance witn the criteria of Guideline 6 when the measures listed in Section A above are invoked. The licensee should retain documentation of these measures for audit purposes.
2.3.7 Crane Design [ Guideline 7, NUREG-0612, Article 5.1.l(7)]
"The crane should be designed to meet the applicaDie criteria and guidelines of Chapter 2-1 of ANSI B30.2-1976, 'Overneaa ano Gantry Cranes,' and of CMAA-70, ' Specifications for Electric Overnead Traveling Cranes' [9]. An alternative to a specification in ANSI 830.2 or CMAA-70 may be accepted in lieu of specific compliance if the intent of the specification is satisfied."
A. Summary of Licensee Statements i The licensee has supplied a table consisting of all the cranes listed in Table 2.1 ano tne associated " applicable codes and standards" specified in the Equipment Purcnase Specifications for tne plant. The table indicates that all the cranes in Table 2.1 were design:d to the criteria of CMAA 70 wnile cranes 1, 2, 3, 8 and 20 were also designeo per ANSI B30.2-1976 Chapter 2-1. Exceptions were taken for cranes 22 and 23 as tnese cranes are aesigned to handle a i fuel assemoly and its associated handling tool, wnicn, by the NUREG-0612 definition, is not a heavy load.
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- 8. EG&G Evaluation EG&G nas performed a cursory review of both CMAA 70-1975 and ANSI B30.2-1976 Chapter 2-1. It is our belief that conformance to CMAA-70 does not give sufficient' coverage of all topics contained in 0; apter 2-1 of ANSI B30.2. The actual design of the cranes in question may meet the criteria of Chapter 2-1 as many of the criteria are based on sound engineering and safety practices; however, the licensee nas supplied insufficient information to make tnis determination.
The licensee's exemption of crane 22, the Fuel Building Fuel Handling Bridge Crane, is questioned by EG&G. The licensee has supplied the weignt of a " fuel assemoly and lifting tool" for the containment Fuel Handling Bridge Crane as 1,700 lbs. We have adopted this value as the minimum weignt of a heavy load at the plant (see Section 2.1). The largest load listed by the licensee for crane 22 is a "f ailed fuel assemoly and lifting tool" at 3,000 lbs. We reel that this f ailed fuel assembly is not equivalent to the " spent fuel assemoly" used in the definition of " heavy load" (NUREG-0612, Section 1.2), based on the information given.
If the licensee wishes to continue to pursue an exemption for crane 22 we suggest that a more thorougn argument be supplied.
i Based on the load information provided, EG&G feels that the Containment Fuel Finaling Bridge Crane (crane 3), the Main l
Steam Safety Valves Hoist (crane 19) and tne Containment Dome Access Rotating Platform Hoist (crane 21) may qualify for exemption to this guideline based on the magnitude of loads carried and the " heavy load" cefinitions. The licensee may wisn to address exemption for tnese cranes.
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Review of the load weights and crane capacity ratings provided by the licensee reveals two cranes with listed loads heavier than the listed capacity. The RHR Pump Hoist (crane No.10) has a capacity given as 3 tons wnile its heaviest load, the Pump Motor Assembly is 4.8 tons. The RCP Hoist (crane No.14) nas a capacity of 40 tons indicated with a maximum load (RCP Pump and Lifting Rig) of 43.7 tons. In addition, six other cranes (Nas. 9,13,15, i 16,17, and 24) have maximum loads equal to the rated capacity. The licensee needs to explain the apparent discrepancy concerning capacity ratings on cranes 10 and 14 EG&G feels that cranes 9, 13, 15, 16, 17, and 24 may also be underrated wnen dynamic load effects are considered altnough we presently have insufficient information to support (or disprove) this position.
C. EG&G Conclusion and Recommendation Comanene Peak 1 and 2 are in partial compliance with the criteria of Guideline 7. The licensee should implement the following action:
(1) demonstrate compliance witn ANSI B30.2-1976, Chapter 2-1 for all cranes listed in Table 2.1 with the f exception of crane 23, tne Containment Building s Refueling Machine; (2) explain the apparent discrepancy concerning rated capacity and maximum loads for some cranes.
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- The licensee may wisn to pursue exemptions to tha criteria sg for some of the other cranes in Table 2.1 as mentioned in ,
Section B above. .; [
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2.4 Interim Protection Measures
- I The NRC staff has estaolished (NUREG-0612, Article 5.3) tnat six measures should De initiated to provide reasonable assurance that handling of heavy loads will De performed in a safe manner until final imolementation of the general guidelines of NUREG-0612, Article 5.1 is complete. Four of enese 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:
o Heavy load technical specifications; o Special review for heavy loads nandled over the core.
Licensee implementation and evaluation of these interim protection measures is contained in the succeeding paragraphs of this section.
2.4.1 Interim Protection Measure 1 - Technical Soecifications
" Licenses for all operating reactors not having a single-f ailure-proof overhead crane in the fuel storage pool area should be revised to include a specification comparaole to Standard Technical Specification 3.9.7, ' Crane Travel - Spent Fuel Storage Pool Building,' for PWR's and Standard Technical
.Soecification 3.9.6.2, ' Crane Travel,' for B'aR's, to prohibit handling of heavy loads over fuel in the storage pool until
'imolementation of measures wnich satisfy the guidelines of Section 5.1."
A. Summary of Licensee Statements The licensee did not address this measure.
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9
'4,
-, g ,
.,I._
B. EG&G Evaluation, Oue to a lack of information, a true evahation is impossible at this time. The following po'ats should be noted:
(1) Comanche Peak is not yet operating, so it will be some time before the facility produces spent fuel to be stored in the Spent Fuel Storage Pools; (2) the only crane with access to the pools, the Fuel Building Fuel Handling Bridge Crane, may be exempt from NUREG-0612 guidelines due to the definition of "neavy loads."
C. EG&G Conclusions and Recommendations Comanche Peak 1 and 2 may b 3 exempt to Interim Protection measure I due to the plant completion schedule. EG&G feels that the licensee should n' t ba required to addr%s this measure unless compliance with Guidelines 4, 5 and 7 will not be completed before plant operation.
2.4.2 Interim Protection Measures 2, 3, 4, and 5 - Administrative Controls
" Procedural or administrative measures (including safe load paths, load handling procedures, crane operator training, and crane inspection]... can be acccmplished in a short time period and need not be delayed for completion of evaluations and modifications to satisfy the guidelines of Section 5.1 of
- [NUREG-0612]."
A. Sur::aary of Licensee Statements Summaries of licensee statements are contained in discussions of the respective general guidelines in Sections 2.3.1, 2.3.2, 2.3.3, and 2.3.6, respectively.
20
1
- 8. EG&G Evaluations, Conclusions, and Recommendations EG&G evaluations, conclusions, and recommendations are contained in discussions of the respective general )
guidelines in Sections 2.3.1, 2.3.2, 2.3.3, and 2.3.6. l 2.4.3 Interim protection Measure 5--Special Review for Heavy Loads Over the Core "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 snould include the following for these loads: (1) review of procedures for installation of rigging or lifting devices and movement of the load to assure that sufficient detail is provided and that instructions are clear and concise; (2) visual inspections of load bearing components of cranes, slings, and special lif ting devices to identify flaws or deficiencies that could lead to f ailure of the component; (3) Napropriate repair and replacement of defective components; and (4) verify that the crane operators have been properly trained and are f amiliar with specific procedures used in handling tnese loads,. e.g., hand signals, conduct of operations, and content of proceourts."
A. Summary of Licensee Statements "The interim actions discussed above will be developed and implemented prior to fuel load of Comanche Peak Unit 1. The action discussed above will not ce necessary until that time since no pacential adverse effects to public health exist from a heavy load drop during the construction phase at Comanche Peak.
"The procedures described above will be reviewed to ensure sufficient detail and tnat they are clear and concise af ter those procedures are written. Visual inspections of components mentioned above will be perf ormed to detect flaws or deficiencies that could lead to f ailure a..d that, if 21
defects are found, appropriate repairs will be made. Also crane operators will be properly trained and familiarized with procedures as discussed in Interim Action (3) above."
- 8. EG&G Evaluation The licensee's response indicates that proper compliance with Interim Measure 6 will be completed and initiated before fuel is handled over the core at the facility.
C. EG&G Conclusion Comanche Peak 1 and 2 are in compliance with the requirements of Interim Measure 6, e
l 22
. m, -
- 3. CONCLUDING
SUMMARY
3.1 Aoplicaole Load Handling Systems The list of cranes and hoists supplied by the licensee as being subject to the provisions of NUREG-0612 is probably adequate (see Section 2.2.1).
3.2 Guideline Recommendations Compliance with the seven NRC guidelines for heavy load handling (Section 2.3) are partially satisfied at Omnanene Peak 1 and 2. This conclusion is represented in tabular form as Table 3.1. Specific recommedations to aid in compliance with the intent of these guidelines are provided as follows:
Guideline RecommenoatP.n
- 1. (Section 2.3.1) -
- a. Complete the development and implenentation of safe load paths for all heavy loads, indicating the results of load drop analyses.
- b. Demonstrate that all safe load paths are marked on equipment layout drawings.
- c. Implement administrative controls requiring written alternatives f or load path deviations.
23
Guideline Recommendation
- 2. (Section 2.3.2) r a. Complete the procedures under development and retain them for possible NRC audit.
- 3. (Section 2.3.3)
- a. Retain complete information on the procedures governing operator training, qualifications and conduct for possiole NRC review.
- b. Verify implementation of said procedures.
- 4. (Section 2.3.4)
- a. Submit verification that all special lif ting devices used on heavy load lifts meet the requirements of ANSI N14.6-1978 as appended by NUREG-0612 Section 5.1.l(4) concerning dynamic effects.
- 5. (Section 2.3.5)
- a. Submit verification that all slings used on heavy load lif ts meet the requirements of ANSI 30.9-1971 as appended by NUREG-0612 Section 5.1.l(5) concerning dynamic effects and sling marking.
24
~ , . . . .
1 Guideline Recommendation
- 6. (Section 2.3.6)
- a. Retain and have readily availaole documentation demonstrating compliance with Section 5.1.l(6) of NUREG-0612.
- 7. (Section 2.3.7) b 4h @
- a. For cranes 4 7, 9 19, 21, 22 and 24 of Table 2.1 either submit verification of compliance with ANSI B30.2 Chapter 2-1 or provide an ample argument for exemption from the criteria of the guideline.
- b. Provide an explanation of tne load rating for cranes 10 and 14 and any otner cranes for which the rated capacity is less tnan the maximum load.
3.3 Interim Protectiun If compliance with the seven guidelines of NUREG-0612 Section 5.1 cannot be ensured before the plant operation date interim protection must ce implemented. EG&G's evaluation of information provided oy tne licensee indicates tnat the following actions are necessary to ensure that the six NRC staff measures for interim protection at Comanene Peak 1 and 2 are met:
25
-. .---. .- . . .. . - . . _a . . .
Interim Measure Re~ commendation
- 1. (Section 2.4.1) Supply a response to tnis measure
- 6. (Section 2.4.3) Retain verifying documentation of the '
implementation of procedures, inspections, training and repairs.
3.4 Summary The Comanche Peak Steam Electric Station Units 1 and 2 are in partial compliance with the guidelines of Section 5.1 of NUREG-0612. The f acilities are basically in non-compliance in the areas of safe load patas and lif ting devices and in partial compliance in the area of crane design. The f acilities are in full compliance concerning crane testing and inspection, load handling procedures and crane operator training, pending documentation. Insufficient information has been received to establish compliance in so.ne areas.
26
4 2 ._ _ _ . __
- 4. RENCES
- 1. NUREG-0612 Control of Heavy Loads at Nuclear Power Plants NRC
- 2. V. Stello, Jr. (NRC)
Letter to all licensees.
Subject:
Request for Additional Information on Control of Fkavy Loads fear Spent Fuel NRC, 17 May 1978
Subject:
NRC' Request for Additional Information on Control of Heavy Loads Near Spent Fuel NRC, 22 Decemoer 1980
- 4. H. C. Schmidt Texas Utilities Services Inc. (TUSI)
Letter to S. Burwell (NRC)
Subject:
"Comantne Peak Steam Electric Station Control of Heavy Loads: NUREG-0612" August 7,1981.
- 5. H. C. Schmidt (TUSI)
Letter to S. Burwell (NRC)
Subject:
"Comanene Peak Steam Electric Station Control of Heavy Loads: NUREG-0612" October 8, 1981.
" Overhead and Gantry Cranes"
" Standard for Lifting Devices for Shipping Containers Weigning 10,000 Pounds (4500 kg) or more for Nuclear Materials"
" Slings"
- 9. CiAA-70
" Specifications for Electric Overhead Traveling Cranes" i
27 ;
TABLE 2.1. '
OVERilEAD LOAD llANDLING SYSTEMS WITil POTENTIAL FOR LOAD DROP ON SPENT FUEL OR SYST FOR PLANf SilUIDOUN OR DECAY llEAT REMOVAL--COMANCilE PEAK 1 AND 2 l
Capacity Equipment and/or
,l Crane /lloist Name Location (Tons) Piping Along the Load Path
- 1. Fuel building overhead crane fuel building 130-17-5
. Spent fuel pool cooll'ng piping, i spent fuel transfer area. j
.Jj
- 2. Containment auxiliary upper Containment building I
cranes
- 5 Reactor vessel. !
i 3. Containment polar cranes Containment building 175-20 Reactor vessel, steam generatur, reactor coolants pumps, reactor 4
coolant piping. :
4 Moderating HX and letdown Safeguards building 2 Train "A" electrical tray (cabling chiller HX holst.a 6 for AUXa feedwater System. -
>> Component Cooling Water System
. k,
, Motor operated valves) located near
, the monorail. i
- 5. Component cooling water pump Auxiliary building 4 Component cooling (CCW) water pump
,) hoist and associated piping, r, 6. Safety related chiller hoist Auxiliary building 1-1/2 CCW piping connected to the chiller, Chiller. -
I
- 1. Centrifugal charging pumps ' Auxiliary building ' 4 Centrifugal chargisig pump and assoc-
- hoist l
lated piping and valves.
- 8. Containment fuel handling Containment building i
bridge crane 1-1/2
- Containment fuel transfer area and fuel rack.
1 9.
Safety injection pumps holsts Safeguards building 3 Service water piping.
- 10. Residual heat removal pumps Safeguards building 3 imist RHR pJap and assOclated piping and 1' -
valves.
i
. r I
l TABLE 2.1. (continued)
Capacity Equipment and/or Craneilloist Name Location (Tons) Piping Along the Load Path
11. Auxiliary feedwater pump hoist, Safeguards building 4 Motor driven auxiliary feedwater (electric'nutor driven pump) pumps, piping and valves. l
- 12. Auxiliary feedwater pump holst, Safeguards building 3 Turbine driven auxiliary feedwater
'! (turbine driven pump) pump, piping and valves.
~
6 13. Auxiliary building filters Auxiliary building 8 Various systems filters.
"j legist
- 14. Reactor coolant pumps hoist Containment building 40 Same as polar crane. See Note 1.
.] 15. Diesel generator (piston) Safeguards building i Diesel generator and its assoc-hoist. lated piping and instrumentation. !
,( 16. Spent fuel pool HX holsta Fuel building 4 Spent fuel pool heat exchangers,
-]3 . piping and valves.
- 17. Service water traveling screen Outside of service 20 Traveling screen.
3 hoist water structure e
- 18. Residual heat removal (RHR) HX Safeguards building 10 RHR and CSS heat exchanger and its and Containment Spray System associated piping and valves.
i (CSS) hoist i
- 19. Main steam safety valves hoist Safeguards building 1 Main steam safety valves. ,
<! 20. Service water intake structure Service water 7-1/2 Service water pumps and its assoc- l crane structure lated piping and valves. ,
Reactor vessel, fuel storage rack,
~
- 21. Containment d'meo access Containment building i rotating platform hoist steam generator, reactor coolant '
, pumps, reactor coolant piping.
i
. 7 e
TABLE 2.1. (continued) '
capacity Equipment and/or Crane /Holst Name Location (Tons). Piping Along the Load Path
- 22. Fuel building fuel handling fuel building 2 Spent fuel pool, refueling canal,
, bridge crane new fuel storage pit.
- 23. Containment building Containment building Reactor vessel, containment fuel
'I refueling machine 2
transfer area.
4 24. Service water intake stop Service water intake 8 Service water pumps.
t gate hoist structure NOTE: 1. Reactor Coolant Pumps Holst is attached to the Polar Crane Hooks during the maintenance operation of the
.j Reactor Coolant Pump.
U '
.'.. a. HX = Heat Excnanger, AUX = Auxiliary *
~l
'l e
4
\
- )
i -
1 j / .
TABLE 2.2. OVERHEAD LOAD HANDLING S'/ STEMS, CRANES, AND H0ISTS WHICH 00 NOT REQUIRE ADDITIONAL REVIEW AND EVALUATION--00MANCHE PEAK 1 AND 2 Capacity Crane / Hoist Nmne (Tons) Location
- 1. Drumming storage area 15 Fuel building crane. -
- 2. Maintensnce building 25 Maintenance building bridge crane. -
- 3. Turbine building gantry Main hoist - 210 Turbine building crane. Aux. hoist - 50
- 4. Circulating water intake Main hoist: Circulating water structure gantry crane. Inside span - 25 intake structure Outside span - 12 Aux. hoist: 5
- 5. Equipment hatch door 10 Containment building hoist.
- 6. Waste gas compressor 1 Auxiliary building hoist.
- 7. Positive displacement 6 Auxiliary building charging pump hoist.
- 8. H2 reccaniner hoist. 1 Auxiliary building .
- 9. Letdown cniller package 2 Auxiliary building hoist.
- 10. HLV chiller hoist (near 6 Auxiliary building H-A line),
- 11. H&V chiller hoist (near 1 Auxiliary building J-A line). .
- 13. Condenser vacuum pumps 4 Turbine building hoist.
14 Turoine plant cooling 6 Turoine building water pump hoist.
- 15. Heater drain pump hoist. 4 Turoine ouilding 31
TABLE 2.2. (continued)
' Capacity Crane / Hoist Name (Tons) Location -
- 16. Control fluid tank pumps 3 Turbine building hoist.
- 17. Personnel lock hoist. 2 Safeguard building
- 18. Reactor vessel stud 1/2 Containment building hoist. See drawing Al-0505
- 19. Steam generator feed water 10 Turbine building pump and turbine drivers hoist.
- 20. Equipment hatch @ 790'-6" 4 Safeguard building for miscellaneous equip-ment hoist.
- 21. Equipment naten @ 810'-6" 4 Safeguard building for miscellaneous equip-ment hoist.
- 22. Equipment hatch @ 873'-6" l Auxiliary building for miscellaneous vent-ilation equipment hoist.
- 23. Equipment hatch @ 886'-6" 1 Auxiliary building for miscellaneous vent-ilation equipment hoist.
- 24. Decontamination of 2 Unit 2 turbine miscellaneous equipment building hoist.
l 25. Decontamination of 1/4 Unit 2, turbine miscellaneous equipment building
( hoist.
- 26. Dry waste compactor hoist. 2 Fuel building
- 27. Chlorine containers hoist. 2 Service water cnlor-ination building
- 23. Chlorine containers hoist. 2 Circulation water enlarination building l
32
TABLE 2.2. (continued)
Capacity Crane / Hoist Name (Tons) Lacation
- 29. Auxiliary steam condensate ? Auxiliary building cooler hoist.
- 30. Containment equipment 40 Outside containment hatch hoist.
- 32. Demineralizers hoist. 8 Auxiliary building
- 33. Radial arm stud tensioner 2 Containment building hoists.
3 o
33
e f .
TAett 3.1. CONANQsE PCM SIDM [t[CiltlC SIAlloty UNIIS l Amp 3/nupts.0612 CoWtlAseCE estala Welfit Guideline I Galoellne 2 Guidellne 3 Guideline 4 Guideline 5 Guldeltne 6 Guideline 1 Interia laterte e or Crane Special Crane-Test Measure I, Measure 6 ,
Capacity Safe toad operator Lifting and Technical Special e lleavy loads _(tons) Paths Procedures Training Devices Slings Inspection _ Design Specifications Attention i g (1) Fuel build-130-17-5 -- -- 1 -- -- C C I -- !
lag overhead P crane i !
Spent fuel 125 lec R -- hc -- -- -- -- -- l cask i
New fuel 0.9 E E -- E -- -- -- -- --
asendely and ,
j handling tool ~
l me. fusi 3.. e R -- -- x -- -- -- --
l shipping cask .
fuel transfer 6 NC R -- -- HC -- -- -- --
canal stup .
9ates
(. )
b l(2)
Containment aualliary 5 -- -- I . - - -- *C C -- --
I upper crane Reactor 2 E R -- -- NC -- -- -- C vessel ten- .
sioning device j Reactor ves- 2.2 leC R -- -- IgC -- -- -- c sei stud .
transfer basatets
- Reactor ves- 0.4 E E -- -- E -- -- -- E sel studs '
I I
. I i.
l !
U
- l. *
.1 -
1 i I
IA8tE 3.1. (continued)
- Guidelica 7 Inter 6m lateria I Weight Guldeline I Guideltne 2 Guideline 3 Guldeline 4 Guldeline 5 Guideline Crane-Test 6 Measure i Measure 6 l or Crane Special Special :
) and Techalcal 6 Capacity Safe toaJ Operator Lifting Design Specifications Attention
- j Tra6ning Devices Slings Inspection l Paths Procedures Heaar toads Jtons)
J l C C -- --
175-20 -- I -- --
i (3) Containment
- polar crane 4
-- -- -- -- C , :
NC R -- NC ;
Reactor ves- 110 .
set teead and
- l {
lifting rig
} -- -- C j A -- NC I
.I laternals 75 NC 4
. lifting rig B
~ -- -- C e R -- NC Ructor ves- 66 NC l
set upper internals
-- hC -- -- -- -- C- )
Reactor wes- 140 NC R sel lower i 1
Internals MI, l
Reactor 27.6 NC A -- -- NC -- -- -- C s
coolant pump .
internsis ,
- -- -- NC -- -- -- C g
! Reactor 43.8 NC A -
l
' coolant pump
-- -- NC -- -- -- C I Reactor 5.5 nc A I I coolant pump '
motor stant
-- NC -- -- -- C I Fuel storage 6 NC R --
area stop gate +
-- -- 8 I -- -- C NC (4) Moderating 2 -- --
heat enchanger holst ,
4 Moderating HK 0.1 E E -- -- f. -- 1 -- -- --
o channel head i
! e I
\,
l-
l TAat 3.1. (continued) h Guideline .' laterls Interia Weight Guldeilne I Guideline 2 Guldeline 3 Guideline Special 4 Guldeline 5 Guideline Crane-Test6 Measure 1 m asure 6 or Crane Technical Special 1 operator Lifting and I i Capacity Safe Load Slings inspection Design Specifications Attention Paths Procedures _ Training Devices
! Heavy loads (tons)
-- -- E Moderating HX 0.8 E E - ,
l tube bundle A -- -- NC n>Jerating HX l.3 NC t
j shell C NC 4 -- -- I -- --
(5) Ca+onent cooling water i pump hoist ! !
-- MC -- -- -- l Component 3.3 NC R cooling water l CCW pump base 1.7 NC A -- -- NC .. --
l
-- -- -- -- j a -- -- NC CCW pu , 3.s NC motor Ml - -- -- -- --
-- -- E 24 inch 0.5 E E ,
valves i
a
-- -- E Emergency 0.1 E E F m/ coll unit motor i4 C NC '
(6) Safety re- 1.5 -- -- I -- --
lated chiller i hoist
-- -- -- 1 R -- -- NC t Processing 1.5 NC l tank .
I e -- -- E Acid tank and 0.5 E I
Pug .
\ --
. -- -- NC --
t Chlller 1.2 NC r l.
~
l t
. i 4
ia
i IAK E 3.l. (continued) .. i*
Weight Guideline I Guidellne 2 Guideline 3 Guldeline 4 Guideline 5 Guideline 6 Guideline 7 Interle lateria or Crane Special Crane-Test Measure i Measure 6 Capacity Safe LoaJ Operator Lifting and Technical Special Heavy loads Paths gocedures Training Devices Slings laspectica Design Specifications Attention
_ (tons) i E lectrical 0.8 E E -- -- E --
! cabl st Mutor and 0.2 E E -- -- E compresor NC --
j Precooler 1.2 leC R -- --
heat enchanger i
i '
' (7) Centrifugel 4 -- -- I -- -- C E -- --
charging pump ,
hoist g I
Centrifugal 3.8 NC R -- -- K -- -- -- --
l.
charging pump .
i 1(p gear 1.4 E a -- -- hC -- -- -- --
l
- -e! assembly CCP motor 2.9 feC R -- -- E -- -- -- -- -
l k l
j CCP motor 0.9 E R I -- NC -- -- -- --
rotor I --
Lutte oil 0.1 E e -- -- E -- -- --
cooler (shell) '
Emergency 0.1 E E -- -- E -- --
fan / coll ,
unit motor (8) Containment 1.5 -- -- I -- -- C C.E -- --
fuel handling bridge crane
- I
. Fuel assembly 0.9 E E -- E -- -- -- E aol lifting tool ,
\!-
f-
IAR E 3.1. { continued)
Weight Guideline i Guideline 2 Guldeline 3 Guideline 4 Gundeline 5 Gu6deline 6 Guldeline 7 Interim lateria or Crane Special Crane-Test Measure i Measure 6 C apacity Safe Load operator Lifting ad Technical Special 8-Heavy toads *
(tons),, Paths Procedures iralning Devices Slines Inspection Deslen Specif6 cations Attention l (9) Safety injec- 3 .. .. I .. .. C E .. ..
Lion pump holst }-
l 5.1. Pump 3 E A .. .. E .. .. .. ..
i 5.1. Pump 2.4 E R .. .. E .. .. .. .. ,
motor l -
l.
(i/) RHR Pump Holst 3 .. ..
l .. .. C E .. .. 4 h e t l
e RIN pump 2.2 E R .. .. E .. .. .. ..
RIR pump 2.6 E R .. .. E .. .. .. .. I motor 0.9 E i g Ria pump R .. .. K .. .. .. ..
col.
casing i
Riat pump I.3 E R ..
. .. E
- rotor .
- I Riht pump 4.8 E R .. .. E .. .. .. ..
I ;
motor assembly ,
t t
(11)Ausillary 4 .. .. I .. ..
C E .. .. *;
feedwater pump ,
lolst (motor , I driven) ,,, ,
i A.F. Pump 2 E R .. .. E .. .. .. ..
A.F. Pump 3.6 E R .. .. g .. .. .. ..
motor g
~
, A.F. Pump 0.6 E E .. .. E .. l .. .. . . .
rotor e
I I
e I-4 ,'
I,i
- .
- l l t IA8tE 3.1. (continued) +
1, e i Weight Gu t s.,: ine I Guideline 2 bu Jeline 3 Guideline 4 Guidellae 5 Guidelind 6 Guideline / Interle Interin or Crane Special j Crane-fest Measure I Measure 6 Capacity Safe Load Operator Lifting and
. t licavy toads (tons) paths Training Technical Special e i
Procedures Devices Slings inspection Design Specifications Attention '
j A.F. pump 0.6 E E -- --
upper casing E -- -- -- -- '
(12)Aunillary 3 -- --
1 -- -- C NC -- --
feedwater pump hoist (turbine -
driven) !
I i
A.F. pump 2 NC r -- --
NC -- -- -- --
Turbine 1.4 E R -- --
leC -- -- -- --
driver A.F. pump 0.6 E e -- --
E --
rotor -- -- --
A.F. pump D.? E E -- --
g casing E -- -- -- --
(13) Auxillary 8 -- --
I -- --
C build:ng filter leC -- --
area holst i Filter ele- 3.4 NC R -- --
IIC -- --
- ment transfer .
Cask Filter com- 8 NC R -- --
IIC -- -- --
partment con- --
crete floor .
plugs (man) ,
(14)Reactorcool- 40 -- --
I --
ant pump
-- C llc -- -- !
, telst ,'
I I-
TAst[ 3.1. (continued) -
Weight Guideline I Guideline 2 Guideline 3 Guideline 4 Guideline 5 Guideline 6 Guideline 7 Interle Interte or Crane Special Crane-Test steasure I h asure 6 i.
Capacity Safe load Operator Lifting and Technical Special Heavy loads (tons) paths procedures Training Devices Sitnes Inspectica Design Specifications Attention !
) Reactor cool. 27.6 hC R -- -- E -- -- -- C ant pump Internals lleach,r cool- 43.7 leC R -- -- NC -- -- -- C f ant pump motor .
and lifting rig ,
heactor cool- 5.5 hC R -- -- NC -- -- -- C 3
ant pump motor stand .
g e a e
(15) Diesel gener- I -- -- I -- -- C leC -- --
ator hoist
- Miscellaneous i E R u
o pipin9 and structural
-- -- NC -- - -- --
components . ,
(16) Spent fuel 4 -- -- I -- -- C leC I --
rod heat en-e changer hofst -
5.F. cooling 1.3 leC R -- -- Isc pump 5.F. cooling I.1 NC R -- -- IIC -- -- -- --
motor * ;
f f 5.F.H.E shell 3.8 teC R -- -- leC -- -- -- --
5.F.H.E tube 3.7 seC R -- -- sec -- -- -- -- l bwidle l I !
Concrete 4 NC R -- -- NC -- -- -- --
- floor plugs , I
. e l
. I
\ . .i; 5
4 .
,I t . .
i .
- 1 TABLE 3.1. (continued) . ,
Weight GuiJeline I Guideline 2 Galdeline 3 Guideline 4 Goldeline 5 Guideline 6 Guideline 7 lateria Interte Crane Special Crane-Test Measure 1 Measure 6
, or ,
I Capacity 5tfe Load Operator Lifting and Inspection Teshnical Special Specifications Attention
[
! Heavy LeaJs (tons)_ Paths Procedures Training Devices Slings Oesten
' I
-- -. I -- .. C NC l (17) Service water 20
- traveling
{
screen hoist
-- NC Miscellaneous 1.8 NC R ..
Items (eas)
-. -- I .. .. C NC i (18) RIN and CSS 10 i heat enchanger hoist CSS H.E. 3.7 NC R -- -- NC shell body I
NC --
CSS H.E. tube 8.5 NC A -- --
bunJte s-kHit H.E. 3.9 NC R .. -- NC slie1I body I
RHR H.E. tube 8.3 NL R -- -- NC .-
t,undle i Compartment 10 NC R -- -- NC -- -- -- .-
i I
e concrete floor .
plugs (eaa) ,
t i ^
I,E -- .. P (Ig) Main steam 1 -- -- I .. -- C safety valves hoist .
M55 valves 0.8 E E -- -- E ..
l a
, (20) Service water 7.5 .- -- I .. -- C IC -- --
intake struc- t ture bridge cra.ne 9 t-
. I
TAR E 3.1. (continued) .
Weight Guideline I Guidellae 2 Guideler.e 3 Guideline 4 Guldeline 5 Gu wellne 6 Guideline 7 Interte Interia .
or Crane Special Crane-Test Measure i Measure 6 P.
Capacity Safe toad Operator Lifting and Techalcal Special Heavy Loads (tons) Paths Procedures Training Davices $1lnes Inspection Deslan Specifications Attention 5.W. pump 4.9 NC R -- -- seC --
motor Fire pump Jockey Puop 0.3 E E --
\ -- E -- -- -- --
F.P.J.P. 0.1 E E -- -- E -- i autor t igg -- -- !
, F.P. diesel 2.4 feC R -- -- -- --
driven pump ,
F.P.D.O.P. l.7 NC R -- -- E -- .. -- --
driver F.P.O.D.P. 0.7 E E -- -- E --
gear '
, F.P. diesel 0.1 E E -- -- E -- --
lm coupling
, F.P. electric 2.4 Ist R -- ' --
E -- -- -- --
g driven punp
. F.P.E.D.P 2.4 leC R -- .- E -- -- -- --
motor }
,, (21) Eontalanent I -- -- I -- --
- C 1.E -- --
. done access I rotating plat- ,
form k ist Miscellaneous 0.1 E E -- -- E -- -- -- E .
tools .
Welding 0.2 E E -- -- E -- .. -- E equipment g }
I t I .
l . t i 'h -l
! j- '
-- ~ * - - * *
's .
~
o .
l l T C E 3.1. (continued) g. n I
Guideline 7 Interna laterls Weight GulJeline I Guldeline 2 Guideline 3 Guideline Special 4 Guideline 5 Guideline Crane-Test6 Measure i Measure 6 or Crane Technical Special l-Operator Lifting and Speelfications Attention Capacity Safe Load Training Devices Slings Inspection _ Deslan ileavy toads Paths Procedures _
! Jtons) n -- C I .K ! --
-- I --
(22) f uel building 2 --
fuel handling .
bridge crane i
-- -- -- l 1.5 hc R -- K -- --
Failed fuel I assembly and . [
lifting tool fuel asse=Lly i K R -- K -- --
anJ tool .
a
-- C E 2 -- -- I --
(23) Containment g building re- ,
fueling machine f
-- -- -- -- E u Fuel assed ly 0.8 E E Ls 1
C K -- --
-- -- I (24) Service water 8 -
Intake stop p l gate holst 3
-- NC -- -- ,
NC R --
- 5.W. pump B compartment e
stop gates !
e C = Licensee action complich ulth himLG-0612 Guideline. -
NC = Licensee action does not comply ulth huREG-0612 Guideline ,
I R = Licensee has proposed revisions / modifications designed to couply wth IIUNEG-0612 Guideline.
I = Insuf ficient information provided by the Licensee. -
E = Esempt from huutG-0612 guidelines per definition of 'hcavy load'.
- 1
's '
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