ML20052F832

Control of Heavy Loads at Nuclear Power Plants,Wh Zimmer Nuclear Power Station, Draft Technical Evaluation Rept

ML20052F832
Person / Time
Site:	Zimmer
Issue date:	01/31/1982
From:	Shaber C EG&G, INC.
To:	NRC
Shared Package
ML20052F827	List: ML20052F832
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8205140016
Download: ML20052F832 (29)

Text

,

, -9 .

i '

l i

i j CONTRO:. OF HEAVY LOADS AT NUCLEAR PC'WER PLANTS l WM. H. ZIMMER NUCLEAR PC'WER STATION Docket No. [50-358]

, C. R. Shaber Principal Technical Investigator

! T. H. Stickley EG&G Idaho, Inc.

January 1982 I

I, 4

1 k

i i

8205140016 820429 PDR ADOCK 05000358 A PDR

_ _ - - . - . ~ . - . . .- ... . .

I __

d , ,

ABSTRACT The Nuclear Regulatory Commission (NRC) has recuested 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 reco=mendations for Wm. H. Zimmer Nuclear

!I Power Station.

EXECUTIVE

SUMMARY

4 i

i + Wm. H. Zimmer Nuclear Power Station does not totally comply with the guidelines of NUREG-0612. In general, comoliance is insufficient in the following areas:

. o identification of heavy loads, (what is the weight of a fuel

} assembly and its handling tools)

II i

o sling construction details for safety analysis (ANSI B30.9 Sections 9-2.2.1 and 9-2.2.2) o plans for physical identification of heavy load paths in the j plant area when a heavy load is handled i

t o status of crane testing and maintenance l

o lif ting device evaluation to verify their adequacy for static and dynamic loading 13 o interim protective measure analysis.

.l 1

The main report contains recommendations which will aid in bringing

} :ne above items into compliance with the approcriate guidelines.

l 4

ii

4 .

l . . .

CCNTENTS Section Title Page -

, j

!.1 A B S T RA C T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 il EXECUTIVE

SUMMARY

.... .. ... ........ ... ...................... .. 11

1. INTROCUCTION .................................................... 1 ,

, 1.1

• Purpose of Review ......................................... I 1.2 Generic Sackground ........... ............................ 1

'7 1.3 P l an t-S peci fi c Bac kg round . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 i,

i. 2. EVA LUATICN AND RECOMMENDATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2.1 Overview ........... ....... .. ... ..... ................. 4 i

2.2 Heavy Load Overhead Hancifng Systems .. .. ............. 4

>' 1 2.3 General Guidelines .. ..................................... 6 2.4 Inte rim P rotecti on Mea sures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16

3. CC N C LU D I NG S U MMA RY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20

3.1 Aeplicable Load Handling Systems ......... ................ 20 3.2 Guideline Recommencations .... ............. .............. 20 1

j 3.3 Interim Protection ........................................ 23 4

4 REFERENCES ...................................................... 24 1

i 4

4 kii

-. _ _._ - - - . , . - - - ~ . . - -

-i 1

TECHNICAL EVALUATION REPORT

[0,,,3 WM. H. ZIMMER NUCLEAR PCWER STATICN j (Cincinnati Gas anc Electric Company)

1. INTR 00UCTICN 1.1 Purcose of Review f This technical evaluat'on report documents the EG&G Idaho Inc. review of general load handling policy and procedures at the Cincinnati Gas and Electric Company, Wm. H. Zimmer Nuclear Power 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.

i 1.2 Generic Background I

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

4 i Nuclear Regulator / 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, I

j 1978 [2] to all power reactor licensees, requesting information

! concerning the control of heavy loads near spent fuel.

I The results of Task A-36 were reported in NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants. The staff's conclusier from this evaluation was that existing measures to control the handling of

heavy loads at operating plants, although providing protection from

, certain potential problems, do not cover adequately the major causes of load handling accidents and should ce upgraded.

I

l . . .

j -

o

,9 j In order to upgrace measures for the control of neavy leads, the staff i developed a series of guidelines designed to achieve a two phase f' objective using an accepted accroacn or art *.ection philoscohy. .The first portion of tne ocjective, achieved tnrough a set of general guicelines icentifiec in NUREG-0612 Article 5.1.1, is to ensure that

~

all load hapdling systems at nuclear cower clants are designed and '

j operated such that their procacility of failure is uniformly small and .

appropriate for the critical tasks in whicn tney are emoloyed. The second oortion of the staff's objective, acnieved through guidelines j identified in NUREG-0612, Articles 6.1.2 tnrougn 5.1.5 is to ensure j .

that, for load handling systems in areas where their failure might I

result in significant consecuences, either (1) features are provided,

)

. in addition to those recuired for all load handling systems, to ensure that tne cotential for a load droo is extremely small (e.g. , a

single-failure proof crane) or (2) conservat vei evaluations of load hancling accicents incicate tnat tne potential consecuences of any ,

load Orop are acceptably small. Acceptacility of accident I consequences is quantified in NUREG-0612 into four accident analysis i

evaluation criteria.

i l

> The aporoach used to develoo tne staff guidelines for minimi:ing the potential for a load drop was based on defense in teoth and is su=mari:ed as follows:

i

-t j o provice sufficient operator training, handling system i design, load handling instructions, and equipment insoection

.I j to assure reliable coeration of the handling system i

1 i

! o define safe load travel paths through procacures and coerator training so that, to the extent practical, heavy l4 loads are not carried over or near irradiated fuel or safe

' 1

j~ shutdown equipment i i i

l J

l 4 o provide mechanical stops or electrical interic-ks to prevent l

l movement of heavy loads over irradiated fuel or in proximity l

to equipment associated with recundant snutdown paths.

4

- m

~ .

- ~

-.-~~e-- . _ _ . . .

i , ,

'I

) Staff guidelines resulting from tne foregoing are tabulated in t

j Section 5 of NUREG-0612.

i II 1.3 Plant-Soeciff e Backcround -

On Decemcer 22,-1980, tne NRC issued a letter [3] to Cincinnati.' Gas and Electric Company, the Licensee for Wm. H. Zimmer Nuclear Power

~

Statien requesting that the Licensee review provisions for handling and control of heavy loads at Wm. H. Zimmer Nuclear Power Station,

!! evaluate these orovisions with respect to the guidelines of NUREG-0612, and provide certain additional information to be used for an independent determination of conformance to these guidelines. On May 13, 1981, Cincinnati Gas and Electric Comoany provided a response [4] to this recuest. On June 24, 1931 a seconc response [5]

was submitted with suoplemental information, on wnich tne evaluation i

2

! and recommendations nere are made.

'i i

i I

i 4

3

.< . - - ~ . - . - . . . . . -- .

I i

1 I

, _ z_

l 2. EVALUATION AND RECC.MMENDATICNS t

2.1 Overview

! The following sections summari:e Cincinnati Gas and Electric Comoany's review of heavy load handling at the Wm. H. Zimmer Nuclear Power Station accompanied by EG&G's evaluation, conclusions and recommendations to the licensee for oringing the facilities more comoletely into ecmpliance witn the intent of NUREG-0612. The l licensee has not indicated the weight of the power stations single

) spent fuel assemoly and its handling tool, which is the criteria

! listed in NUREG-0612 for classification as a heavy load. Therefore the average SWR fuel assemoly weignt of 1100 pounds will be considered to be a Wm. H. Zimmer Nuclear Power Station, heavy load.

2.2 Hetvy Load Overnead Handlino 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 overnead hancling systems from the acave mentioned list.

2.2.1 Scoce i

" Report the results of your review of plant arrangements to i identify all overhead handling systems from which a load drop may j result in damage to any system recuired for plant snutdown or

, decay heat removal (taking no credit for any interlocks, technical specifications, operating procedures, or detailed 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-imoact point and any safety-related component to permit a determination by inspection i that no heavy load drop can result in damage to any system or t component required for plant shutdown or decay heat removal."

4 9

'. . ., _. . ,_ . . _ , ~ , - . ...

i .

l 1

i '

f

i A. Summary of Licensee Statements

.I The Licensee's' review of overhead handling systems provided a

.{ Tacle wnicn icentified the cranes anc hoists wnicn handle heavy i

icads in the vicinity of irradiatec fuel or safe shutdown ecuipment. .

The Licensee report identified numerous other cranes tnat have 3

been excluded from satisifying the criteria of the general tj guidelines of NUREG-0612. The exclusions were mace because the i

licensee verifies that there is sufficient pnysical secaration

! from any load impact point to any safety related component.

4

3. EG&G Evaluation Information included in the Licensee's res onse reveals at least fifty-two hoisting units on plant equipment removal drawings.

i The twenty-eight hoisting units the licensee ilsted for consiceration was reduced by individually justifying removal of ten on specific grounds anc three accitional hoists because their caoacities are incapaole of handling heavy loads.

The justifications given for the hoisting items removed cannot be verified from data in the recort.

I e C. EG1G Conclusions and Reccmmendations i

Sin:e there is no information to the contrary EG&G must conclude that tne Licensee has incluced all applicable hoists and cranes ,

in their list of handling systems wnica must cc cly with the i requirements of the general guidelines of NUREG-0612. However, EG&G does recommend that the Licensee be prepared to verify the j justification for the exclusion of cranes and hoists from their list if it becomes necessary.

5 l

., l j

k, 1

i I 2.3 General Guidelines g

i This section acdresses tne extent to which the acclicaole hancl.ing j systems comply with tne general guicelines of NUR'3-0612 *

) Article 5.1.1. EG&G's conclusions and -ecommencations are orovicec in summaries for eacn guiceline. ,

The NRC has estaclishec seven general guidlines wnica must be met in

}

-j order to provice tne cefense-in-deoth aporoach for the handling of i heavy loads. These guidelines consist of ne following criteria from 2

Section 5.1.1 of NUREG-0612:

A. Guiceline 1--Safe Lead Paths

3. Guiceline 2--Load Handling :rocecures C. Guicaline 3--Crane Coerator Training D. Guiceline 4--Icecial Lif ting Cevices E. Guiceline 5--Lifting Devices (not scecially designec)

F. Guiceline 6--Cranes (Inspection, Testing, anc Maintenance)

G. Guideline 7--Crane Design.

! These seven guicelines should be satisfied for all overnead handling systems and programs in order to handle heavy loacs in the vicinity of tne reactor vessol,1 ear scent fuel in the scent fuei pool, or in other areas where a load creo may damage safe shutcown systems. The

! succeeding caragraons accress the guicelines incivicually.

i j 2.3.1 Safe Load Paths TGuideline 1. NUREG-0612. Article 5.1.1(1)]

" Safe load oaths snoulc be definec for the movement of-heavy loads to minimize tr.e potential for heavy loads, if drooped, to -

imoact irraciated fuel in the reactor vessel and in the spent 1 -! fuel pool, or to i=cact safe snutdown equipment. The path snould l, follow, to the extent practical, structural floor memoers, beams, I etc., such that if the load is drooped, the structure is more i

1 t - . , - , ,- ~ - - - - . - .-. ,- . , ,.

- . . _ . . _ - _. .m - . _ . __ _ . ~ . .

~ ... . -. . ~ . .-a 5

'1 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 wnere the load is to be

'adled. C'eviations from defined load paths should require w..: ten alternative procedures approved by the clant safety aeview committee."

A. Summary of Licensee Statements The report submitted states, " Equipment removal paths have been identified and are shown on the equi ment removal

]

i plans. Particular drawings for each lead handling system j are being developed from these eouipment removal plans."

J

3. EG&G Evaluation j The oaths identified have been shown on tne scuipment l' removal plans. Cevelopment of accitional drawings anc actions to meet the other five details for " Safe L:ad Paths" .

are not addressed in this report by the licensee.

i j C. EG&G Conclusions and Rec =mendations It is concluced from the information reported that actual work is started only. The licensee should continue the 1

j required development work cr. the items listed below:

1

?

j (1) Definition of load paths for each hoist involved

.I (2) Develop auditable information that shows the safe load l paths follow structural floor members, beams, etc., so -

j far as possible t

(3) Assure that safe load paths are adequately defined in procedures issued for guidance for control of, " Heavy

. Loads" i

- , - - - - - - - - . , , . - _ . - - ,.w, ,

l .

i

-l ,

(4) Include in procedures the method to clearly mark en floors or otherwise icentify the area (load oaths) .

! where loacs snall be handled, when fuel or scecial i . lifts are to be mace t

(5) Develop a crecedural plan that repuires written 1

alternative plans and appropriate approvals before allowing ceviations from regular precedures tha: guide

+ c:ntrol of heavy loads.

t I

! 2.3.2 Load Hanclinc ?recedures (Guidelice 2. NUREG-0612. Article

) 5.1.1(2)]

"D-Ocecures should ce Ceveloced to cover ! cad nancling : erations for neavy loacs that are or 00ulc te handled over or in oroximity to fr-aciated fuel or safe shutcown ecuipment. At a minimum crocecures snould cover nancling of tnose loads listec in Ta:le 3.1-1 of NUREG-C612. These crececures snould

! include: identification of required equipment; ins:ec-ions and i acceptance critria required before movement of loac; the steos

' and procer sequence to be followed in handling ne loac; defining the safe path; and otner special precau fons."

i A. Summary of Licensee Statements

! Acministrative c:ntrols are being develoced anc shall be in

) 31 ace prior to initial fuel loading. The acministrative f controls shall recuire saecific implementing precedures "er l the handling of heavy loads over or in close oroximity to 5 irradiated fuel on ne plant refueling floor. These imolementing procedures shall include; identification of recuired equipment, any inscections recuired before load ,

$ movement, and ne hancling sequence to be followed including

! a drawing of tne equipment removal path.

i 3

.-.w--. -: -

~c-- - ~ - ~

1 -

8. EG&G Evaluation.

s

t 1

'j There is nothing to be evaluated as the statement incicates that, ":entrois are ceing ceveloped."

C. EG&G Conclusions and Recommendations- .

(1) Assure that the control procecures owing developed

. include other special precauti uns as may e necessary

(2) The licensee should have the control procedures

! preparec, accreved, in service and suitacle for an audit before fuel handling is permitted.

, 2.3.3 Crane Coerator Traininc [ Guideline 3. NUREG-0512.

,. Article 5.1.1(3)]

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

' Overhead and Gantry Cranes' [6]."

iu i A. Summary of Licensee Statements

, All personnel who operate cranes or hoists at the l; '4m. H. Zimmer Nuclear Power Station have received documented 1f classroom training in the areas of rigging, lifting, hand I signals and rigging inspection. In aedition, personnel who

{

operate cab-operated cranes have received hands-on training on such equipment during the preoperational testing programs at the plant. -

i i S. EG&G Evaluation

.i 1

The statement indicates that progress has been made toward-l compliance with requirements of ANSI 330-2 Chapter 2-3. The

quality of training, its adequacy, operator physical l s

, 9 i

l l

L; - -

n

- l, . . . L i

i 4

i t

conditions anc' conduct of operations cannot ce evaluated

.! from the statement alone. f I C. EG&G Conclusion and Recommendations (1) The licensee snoulc be prepared to verify, ucon aucit, ,

that their operators meet the specified. requirements.

I

} 2.3.4 Soecial Liftino Devices iGuideline 1. NUREG-0612.

j Article 5.1.1(all 1

! "Scecial lifting cevices snould satisfy tne guidelines of ANSI

N14.6-1978, ' Standard for Special Lifting Devices for Shipoing Containers Weighing 10,0C0 Pouncs (1500 kg) or .More for Nuclear Materiais' [7]. This stancarc snould acoly to all saecial lifting devices wnich carry neavy loacs in areas as defined acove. For coera

Ing oiants certain insoections anc loac tests s may de accepted in lieu of certain material recuirements in :ne i stancarc. In accition, the s;ress casign factor stated in

' Section 3.2.1.1 of ANSI N14.6 snould Oe based on the comoined maximum static and cynamic loads that could be imoarted on the handling device based on cnaracteristics of the crane wnich will be used. This is in lieu of the guideline in Section 3.2.1.1 of 4  ; ANSI N14.6 which bases the stress design factor on only the I weignt (static loac) or ne load and of the intervening components of the soecial hancling device."

A. Summary of Licensee Statements i

The licensee report discusses two strongbacks :nat need to i i jj conform to ANSI N14.5 as soecial lifting devices. These are j a reactor head strongback listed by nameplate data at 30 ton capacity, and a dryer /secarator strongback at 60 ton hook block cacaci*.y. Details of construction were in accordance ,

with General Electric Co. design, and one licensee is attemoting to obtain detailed design data from GE.

[ Information presently established is that " Proof Tests were made a: 100 ton and 104 ton rescectively on :ne strongbacks. Structural welds were magnetic particle 10

. . ~ . _ . -

-. . . .. . . . .r.

4 . .

.l .

inspected and welders and procedures were qualified to ASME

.! Soiler and Pressure Vessel Code Section IX.

! 8. EG&G Evaluation i

i There is insufficient information to determine whether or

.) not additional lifting devices should be included in the

~I category of, "Special Lif ting Devices" at Wm. H. Zimmer J

Nuclear Power Station. They should be able to verify, upon l

I audit, that no other special lifting devices are used.

t l The term " Proof Test" is not specific in meaning. A designer usually specifies what constitutes a valid proof test based on tne service planned for the equipment. This

. is done before the equipment is accepted for use. The 1 requirements of ANSI N14.6 specify an acceptance test, prior j to use, of 150% of the maximum load. The reactor head load is reported to be 65 tons but it is not clear whether the f

] strongback, snackles, turnbuckles, etc., are, or are not included in the load. The requirement of ANSI N14.6 sets

{'

the criteria that must be met. The reactor head serongeack

, loading is very close to maximum for the acceptance. All j details should be obtained and considered.

l!

1

, l C. EG&G Conclusions and Recommendations 6

i Pursue the collection of correct design criteria until it is

. obtained for the special lifting devices. When obtained, evaluate both strongbacks to assure that each meets the

. ANSI N14.6 requirements. If compliance discrepancies are

,  ! icentified proceed with establishing acceptable alternates I

allowed in NUREGs 0612.

t 11

_ _ _ _ _ . ~ . _ _ . ~ . . _ . _ _ . . _ _ . - _ . . -

I 1

i i

2.3.5 ' Liftino Devices (Not Scecially Oesicned) IGuideline 5, NUREG-0612. Article 5.1.1(5))

i

" Lifting devices tnat are not soecially cesignec shoulc be installed anc used in accorcance witn :ne guidelines of ANSI 330.9-1971, ' Slings' [3]. However, in selecting.the prooer sling, :ne load used snould ce the sum of the static and maximum

'l dynamic load. The rating icentifiec on :ne sling should ce in terms of the ' static load' wnich produces the maximum static and cynamic load. Where this restricts slings to use on only certain cranes, the slings should be clearly marked as to tne cranes with whicn :ney may be used."

I

! A. Summary of Licensee Statements t

1 j The crimary statement mace by the licensee is, "The rigging equioment listed in the licensee's Table 2 satisfies tne recuirements of ANSI 330.9. The rigging slings were

, selectec with a minimum cesign cacacity of 110% of :ne static load. Based ucon a maximum hoisting speed of

! 5.5 ft/ min. the 10% margin is ceemed adeouate for the applied cynamic loads."

I The data provicea in the licensees Table 2 identifies fifteen loads including the two soecial cevices included

l. acove in 2.3.4 The table gives :ne loac weight and basic i data on tne lifting device and a reference to a controlling i

,; document,(not provided). The table acclies only to loads handled on :ne plant refueling floor. Other loads are, "

lII

. acministratively controlled through the station work

']

2

, f, request."

l I .

2  :=&G Evaluation t

) The general selection criteria of, "110% of the static loac"

' fatis to provice sufficient information to determine if the

! slings satisfy the recuirements of ANSI 330.9. Comoaring

! !t the data given with Sections 9-2.2.1 and 9-2.2.2 of the 1

12

. . ~.

l -

'i '

i ANSI Code reveals numerous needed details that are not s

l provided. The assumption that a maximum hoisting speed of a

5.5 feet per minute with a 10% margin fo- acclied dynamic

~

i loading appears sufficient for the largest load, once tne 11C% design capacity is verified.

C. EG&G Conclusions and Recommendations -

1 I (1) It is concluded that the statement, "the rigging satisfied the requirements of ANSI 330.9" leaves many 1

4 details that the licensee should be able to verify to a i field auditor. Recommendations concerning refueling floor lifting devices shown in the Licensee's recort are given in (2) below. General ~ recommendations in'(3)

below relate to lifting devices used for handl.ing heavy loads in other areas of the plant.

(2) Some of the information given by the licensee on

?

lifting devices used in the refueling floor area j indicate sizes larger than : nose listed in ANSI B30.9.

Also, one shackle appears to be underst:ed and several slings would be adequate only wnen used with very small deviation angles from tne vertical. The licensee

, shculd collect suitable suoporting information on the j lifting devices that verifies that the device provides j the required safety factor of five for the combined a

static and dynamic load.

t (3) Cevices for handling heavy loads in other areas of the .

plant are mentioned collectively witncut details. The reference to, "acministratively controlled through the station work request," does not satisfy the NUREG recuirement. The licensee should be able to verify the following

the hoist travel speeds in feet per second, tne sling construction and type, the sling leg angles 13

. . - - . . . . . . . - - . . . . . ~ . . -

. . - - . -. -.= . . _ -

1

~

i 1

1 as used, method of eye attacnment (for wire rope slings) and tnat the recommended safe working load is .

l based uoon the combined ststic and dynamic load.-

2.3.5 Cranes (Insoection. Testinc. and Maintenance) TGuideline 6, NUREG-0612. Article 3.1.1(6)]

"The crane should be inspected, tested, and maintained in accorcance with Chapter 2-2 of ANSI 330.2-1976, ' Overhead and Gantry Cranes,' with tne exception that tests anc inspections 3

i shoulc be performed prior to use wnere it is not practical to i meet the frequencies of ANSI 330.2 for periodic inspection and i test, or where frecuency of crane use is less than the specified

inspection and test frecuency (e.g., the polar crane inside a FWR containment may only be used every 12 to 13 months during refueling coerations, and is generally not accessible during cower coeration. ANSI 330.2, however, calls for certain inspecti.ons to be performed daily or monthly. For such cranes having limited usage, tne inspections, test, anc maintenance should be performed prior to neir use)."

i A. Summary of Licensee Statements I All cranes at the Wm. H. Zimmer Nuclear ?cwer Station, which are uncer control of the Electric Production Department, are <

periodically inspected as required by ASNI 330.2.0. All

, cranes are cesignated as either regular or stancby service.

Cranes used more than twice a week are designated as regular

j use. All cranes and hoists uncergo a before use i inspection. All regular use cranes or stancby use cranes t

lj being operated regularly for more than a month, undergo a

~

documented monthly inspection. All cranes undergo a yearly documented insoection.

l

, 3. EG&G Evaluation i

The licensee statement is given in its entirety. It indicates inspection meets requirements of ANSI 330.2. No I

t 14 l

i -

..-.s_

-i .

1 actual detail of the inspections are given. Also no information or statements are made to report the program for '

tes-ing or maintenance.

i C. EC&G Conclusions and Recommendations 1

4 .

There is insufficient information to evaluate the adequacy of inspections. If :ney are in fact meeting ne ANSI 330.2 j

3 reouirements aceouate reco-ds should be maintained to verify tnis upon audit. Records snculd be proviced to verify that

'j  ;

testing and maintenance comoly witn ANIS 330.2, Chaoter 2-2.

' 2.3.7 Crane Desien fGuideline 7. NUREG-0612, Article 5.1.1(7)) .

, "The crane should te designed to meet the aoplicable criteria and j guicelines of Chapter 2-1 of ANSI E30.2-1976, 'Overnead and Gantry Cranes,' anc of CMAA-70, 'Soecif' cations for Electric l Overnead Traveling Cranes' (9]. An alternative to a j specification in ANSI 330.2 or CMAA-70 may be acceptec in lieu of .

specific compliance if the intent of the specification is

' satisfied."

l

.I

' A. Summary of Licensee Statements 3 As described in the Wm. H. Zimmer Nuclear Power Station a

1 Final Safety Analysis Report, the Reactor Building crane is i

1 designed per the requirements of ANSI 230.2.0 and CMAA-70.

9

' Cther overhead hoists installed at the Zimmer Station are

! specified to meet the recuirements of ANSI 330.16, overnead hoists.

l .

i -

,, 3. EG&G Evaluation

! The above statement and whether some small hoists are electrical, chain or manual operated is the only data on i construction or design given in the report.

4 i

15

- - ~ - ,

4 4

C. EG&G Conclusion and Recommendation ine licensee should maintain suitable data to verify.that

{ :ne Reactor Building Crane meets the design requirements of ANSI 330.2 1976 and CMAA-70.

,4 .

The use of ANSI B30.16 crane design for monorail heists is h acceptaole. Since CMAA 70 does not acoly to nis tyce of

'}, hoist tnere appears to be acecuate comoliance with

! guiceline 7 for the menorail hoists.

I N

] 2.4 Interim Protection Measures i

1 The NRC staff has estaolished (NUREG-0612, article 5.3) that six i measures snoulc ce faitiatec to crovide reasonaole assurance that i

hancling of heavy loacs will De performec in a safe manner until final implementation of ne general guicelines of NUREG-C612, Article 5.1 is I complete. Feur of these six interim measures consist of general Guideline 1, Safe Loac paths; Guideline 2, Loac Handling Procedures;

} Guiceline 3, Crane Coerator Training; anc Guideline 5, Cranes f (Inscection, Testing, and Maintanance). The two remaining interim measures cover the fcilowing criteria:

1 o Heavy load technical soecifications o Special review for heavy loads handled over the core.

}

, i I Licensee implementation and evaluation of these interim protection measures is contained in the succeeding caragraons of this section.

2.4.1 Interim Protection Measure 1 - Tecnnical Soecifications s

i " Licenses for all operating reactors not having a

} single-failure-proof cvernead crane in the fuel storage pool area

', should be revised to incluce a soecification comoaraole to i

16

.3 j . .

i 1

Standard Technical Specification 3.9.7, ' Crane Travel - Spent 3

Fuel Storage Pool Building,' for PWR's ar.d Standard Technical -

t Specification 3.9.6.2, ' Crane Travel,' for SWR's, to prohibit

hancling of heavy loads over fuel in the storage cool until

! implementation of measures anich satisfy the guidelines of Section 5.1."

A. Summary of Licensee Statements No discussion or statament is mace concerning tne fuel i storage pool ecuipment.

I t

4'

' 2. EG&G Evaluation i None. The Wm. H. Zimmer Nuclear Power Station is not i operational at present.

! C. EG&G Conclusions and Recommendations j

i Interim Protection Measure 1 should be recogni:ed and i

,j addressed, as approcriate for the Wm. H. Zimmer Nuclear

! Power Station prior to handling spent fuel.

2.4.2 Interim Protection Measures 2, 3, 1 and S - Acmir.istrative l Controls i

" Procedural or administrative measures [ including safe load paths, load handling procedures, crane operator training, and cranainsoection].. can be accomplished in a short time period i and need not be delayed for completion of evaluations and

modifications to satisfy the guidelines of Section S.1 of

[NUREG-0612]." .

1 1 :

I A. Summary of Licensee Statements j Summaries of Licensee statements are contained in ciscussions of the rescective general guicelines in i

Sections 2.3.1, 2.3.2, 2.3.3, and 2.3.6, respectively.

l' l

17

, -- w . -~ =.a + -

1

? -

3. EG&G Evaluations, Conclusions, and Recommendations a

~I EG&G evaluations, :enclusions, and recommendations are contained in ciscussions of the respective general guidelines in Sec-ions 2.3.1, 2.3.2, 2.3.3, and 2.3.5.

2.t.3 Interim Protection Measure 6--Soecial Review for Heavy Loads -

Over the Core l

1{ "Special attention snould be given to procecures, ecuio=ent, and

!i personnel for the handling of heavy loads over tne core, such as c;

j vessel internals or vessel inscection tools. This soecial review

'; snould include the following for there loacs: (1) review of a procecures for installation of rigging or lifting devices and movement of the load to assure that sufficient detail is provided and tna instructions are clear and concise; (2' visual inspec:1ons of load cearing comocnents of cranes, slings, and

special lif ting devices to icentify flaws or ceficiencies tna coulc lead to failure of the comoonent; (3) aoprocriate recair and reolacement of cefective comooner.:s; and (t) verify that the j crane operators have oeen oroperly trained and are 'amiliar with specific procedures used in hancling these loads, e.g., hand signals, conduct of operations, and content of procedures."

i l A. Summary of Licensee Statements No specific statements are made relative to interim protective measures. The references made concern planned general operations and are aimed at actions that will be r

{

j_ taken or are in planning. Controlling documents listec in

• i their recort are not provided or indicated whether functional or under development.

1 2

l

3. EG&G Evaluation

,1

}

There is no information to evaluate on Interim Protection measures.

l 1

i l

1 i

i

\

18

. -_.am_-_.__.-.. . . . _ . _ .. .

. - . w .. - =

C. EG&G Conclusion l

The licensee should distinguish wnich if any heavy load handling activities are belcw the stancards specified in tne guidelines of NUAEG-0512. Then establish the required interim crotective measi;ees, t

.i dP h

o 1

1 I

i.

t :

) :

1 I

11 I

1 i

C 4

19 j

l

[

~

i ~

.)

1 .

4

3. CCNCLUDING

SUMMARY

?

5 3.1 Acolicable Load Hanclino Systems 4

1 i

The list of cranes and noists supplied by the Licensee as being sucject to ne provisions of NUREG-Col 2 is procaoly acecuate (s,ee Section 2.2.1). However, EG&G does, recommend that a more tnorougn

,1 justification be proviced for excluding those cranes which are not 1

i included.

\

'l 4

1 3.2 Guideline Recommendations i

I j Compliance with the seven NRC guicelines for heavy load handling (Section 2.3) are partially satisfied at the '4m. H. Zimmer Nuclear Power Station. This conclusion is reoresentec in tacular form as

~

1 -

Tac 1e 3.1. Specific recommedations to aic in compliance with the intent of these guicelines are provided as follows:

{

Guideline Recommencation I -i i

1. (Section 2.3.1)

a. Continue tne required development S

work to meet the guiceline for Safe Load paths.

lj b. Assure that each of five

, requirements are adequate and suitable for aucit.

i i 2. (Section 2.3.2) i

'i i 4. Expedite C0mpletion of the load hancling procecures.

20 i

. . . -...- - .. . . . . . . .. ~ .-~ -- - --

, .. ._ . . . m -,

I - -

Guideline Recommendation

+

i -

l

b. Assure the precedures are approved t

and in service before fuel handling

j is permitted.

j

3. (Section 2.3.3)

a. Be prepared to show that operators

{

! are adequately trained for safe i

handling of heavy loads.

'i

4. (Section 2.3.4) a. Obtain the design criteria for the scecial lifting devices and evaluate it to determine if the requirements of ANSI N14.6 are complied with. If not proceed with f

t

- establishing acceptable alternates.

5. (Section 2.3.5)

a. Conduct a much more thorough l evaluation of lifting devices to assure that the many detailed ll requirements of ANSI 330.9 are i complied with.

(

,' b. Assure that each device is suitable for both the static and cynamic ,

stresses applied in the method it

) is being used.

w 4

l j l

l i 21

~ ~ ' ' '

-  ; -- 4-: _ _

~

" ~ ~ ~ " ' ' ~~

_ - . . ......---..u .. .- ~ u

-l t

.a

6. (Section 2.3.6)

a. Provide adequate information and recorcs on each crane to show that specified inspection, testing, and maintenance, is cerformed. .

7. (Section 2.3.7) l I

a. Maintain data that verifies snat

.I l the reactor building crane meets t

i, , the design recuirements of ANSI 330.2 and C.MAA-70.

4

b. Estacli sh recorcs to verify .

! acequacy of tnose menorail hoists

! in the plant snat are designed to 1

ANSI 330.16 requirements.

t i

?

lI i

'I i 1 i

l i

i i

t 5

22

• /-*---

, . . . - . - . - - . . - , . .. - - ~ ~ ~

,1

4 ii 3.3 Interim Protection 4 .

l:

i. EG&G's evaluation of information provided by the Licensee indicates

+

.i .that the following actions are necessary to ensure that the six NRC staff measures for interim protection at Wm. H. Zimmer Nuclear Dower I !. -

Station are met:

t ii i'..

1 Interim Measure Reccmmendation

. f, t

None indicated Evaluate tne tecnnical specification to determine a

l

what is needed and the appropriate action to assure compliance with requirements 'c efore plant startup.

L

+

d

<l t

4 9

i l

i <

23

l -l  ;

l ' . . .

4 REFERENCES

1. NUREG-0612 i Control of Heavy Leads at Nuclear Dewer Plants

,I NRC I

2. V. Stallo, Jr. (NRC)

• Letter to all licensees. Su'fect:

o Request for Accitional Information j en Control of Heavy Leads Near Soent Fuel

! NRC, 17 May 1978

3. USNRC 1 Letter to (Company]. Sueject: NRC Request for Accitional Information on Control of Heavy Leads Near Soent Fuel i NRC, 22 Cecemoer 1980

,j 4 E. A. Borgman Letter to Mr. Harold Centon, U.S. Nuclear Regulatory Commission,

! Washington, DC 20555, dated May 13, 1981, Referencing Wm. H. Zimmer i

Nuclear Power Station Unit 1 - Control of Heavy Loads.

5. E. A. Borgman Letter to Mr. Harold Centon, U.S. Nuclear Regulatory Commission, Wasnington, CC 20555, dated June 24, 1931, referencing Wm. H. Zimmer Nuclear Power Station Unit 1 - Supplemental Information in response to NRC Letter of Decemoer 22, 1980 regarding Control of Heavy Loads.

! 6. ANSI 830.2-1976 i

"Cverhead and Gantry Cranes" ,

j 7. ANSI N14.6-1978 l " Standard for Lifting Cevices for Shipoing Containers Weighing

'0,000 Pounds (4500 kg) or more for Nuclear Matarials" 1

i.

24 l

. , , _ . , - . , , . , . , . . , - . - ~

....---.,.cv..,w_n- . - - - , - - - , - - - - . , . - --

i ,

I I

I

1

i 1

S. ANSI 330.9-1971

" Slings" 4

9. CMAA-70 "Sce:1fientens for Electric Cverreac Traveling Cesnes" l i

I i

l l -

s t

9 l

l 6

i l

f 25

a

.y 1

tat. 84. dieetill leutilm l'uuta SI Allose soubts,-4 642 ties tl Asett HAlait - _ _ _ _ _ _ _ _ _

lua 1 3. l .

Luldellene i

• Wight Luldeline I GulJellae 2 LulJelime b ane J Special GulJeline 4 k lJellne trane-lest $ Gu6deline b

• J or tiftlag and Capac it y Saf e lead Upes alue inspea- t lum toone Desig l tarvices $ 5 4,,ngs l<pels ent Jt usn) . F all.s Pr oc edus eL . le s tnian Nayy la,4Jg Wi lM*tlua __

C

> 4 W1 1 I

180 W4 W C W-3 I lui main it luaas to 90 Sun Mas. 10 W1 W C W-1 3 8

' lot osa 2 tu4Js to 4 lum Mas. W C 2900 lbs 2 i aempt does I I los .0 C W-8 I

40) W-1 W Wl its.S lues la C i

I lots 24.4% W-l W WI I 23.0 fun W-I W C W1 1 I 409 lust 15 2 W C l 4 lll luu 20 W1 WI 2

W-1 W C I I 142 I low 2.5 C W-1 li4 6. W-8 W 116 5 lun 3 i

W-8 W t I i 4 W-8 W-l 1.5 lan W C Ito 3 lua 4 W-l '

j

'. 169 B5 laewtlun J 120 4 laamptlun 128 2 faception 3 122 2 taeagtlun l2) 2 Latettlun 124 1.6 tatattlum W-8 I i W L 126 S W-1 h lum l utue e 128 I 203 S f utus e W-1 I i ,

W L I i tot 8 W1 W-8

} W C 1 til 3 W8 W-1 1 j J losa W t >

- 417 2 Ives 3 Wl 4til j -r I

lot, lui, 104, 106, - }'

llo, ll), llh, 147, heed un deaulays f 12$. 127, 202, tub, j

[-

2ia Wi, 3a?, m , p.v.saed.

104, MS, 306, 307, faciudeJ un t' Wil, W9, 408, 401, ll.e basis of . ,

40), 404, 405, 406, lut et ten. , l '

s -

4il, 413, 4th, 486, anJ 419. 1

• l le ensee at t less templies ultle ta*lG-ts662 Guld.:llue.

L line. '.

Id.

N

• Iltensee attluse Jues suet t umply ulth IItaptG iltalt b edellesc* I ltensee has pauputed sevis tuus/em6JI4 4444 lums Jeslipeed '

I

• Insuffltsee.t intuem tsuu psuelJcJ by ti.e iitensee, ,. __....._

W

• 68ue k ta ps oss ess isntIcated. --___.__...______..._____

• .y 1

+

e ,

9 t ,

" - - _ - .