ML20024A604

Control of Heavy Loads at Nuclear Power Plants, Susquehanna Steam Electric Station,Unit 1,(Phase I).

ML20024A604
Person / Time
Site:	Susquehanna
Issue date:	04/30/1983
From:	Stickley T EG&G, INC.
To:	NRC
Shared Package
ML17139B649	List: ML20024A604
References
CON-FIN-A-6457, REF-GTECI-A-36, REF-GTECI-SF, REF-GTECI-SP, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR EGG-HS-6261, ESG-HS-6261, TAC-51717, NUDOCS 8306210390
Download: ML20024A604 (26)

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CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 (PHASE I) i Docket No. 50-387 '

l Author T. H. Stickley Principal Technical Investigator T. H. Stickley

. Published April 1983 EG13 Idaho, Inc.

Idaho Falls, Icaho 53415 Prepared for the .

U.S. Nuclear Regulatory C:=ission Under DOE Contract No. OE-AC07-76ID01570

_j FIN No. A6457 XA Copy Has Been Sent fo,PDR!

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ABSTRACT The Nuclear Regula: cry Commissicn (NRC) has recuested tnat all nuclear

=iants, eitner coerating or uncer construction, suomi: a esocese of ccmcitancy with NUREG-0612, " Control of Heavy Leacs at Nuclear Power Plants." EG&G Idaho, Inc., has contracted with the'NRC to evaluate the res:enses of those plants presently under construction. Utilities are recuired.to re ort in two chases. This report contains EG&G's evaluation anc ec:mmenca:icns for Susquehanna Steam Electric Station Uni: No.1 (35E5 No. 1). Caly Pnase I'is addressed. Phase II will :e covered in a secarate recort.

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i EXECUTIVE

SUMMARY

Based upon the information proviced, EG&G Idaho concludes -hat Susquehanna Steam Electric Station, Unit 1 is in comoliance with the intent of the requirements of NUREG 0612.

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ABSTRACT .......... . ... . .... .. ..... ............ ...... ........ 11 EXECUTIVE

SUMMARY

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l '. INTRODUCTION ........ .. ................ ....................... I 1.1 Purpose of Review .. . .. ..... ... . . .................. 1 1.2 Generic Backgrounc ........................................ 1 1.3 Pl ant-S peci fi c Bac kg ro und . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

2. EVALUATION AND RECOMMENDATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2.1 Overview ... ... .. ........ ................ . . . . . . . . 4 2.2 Heavy Lead Overhead Handling Systems ...................... 4 2.3 General Guidelines ......................... .............. 7

3. CONCLUDING

SUMMARY

. ....................... .... ...... . . . . . . 17 3.1 Applicable Load-Handling Systems ..................... .... 17 3.2 Guideline Recommendations .................... ..... . . . . 17 3.3 Interim Protection ........................................ ,

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4. REFERENCES ...........................:.... .. .................. 21 TABLES Table 3.1 Suscuehanna Steam Electric Station No.1 NUREG 0612 Compliance Matrix ........... ... . . . . . . . . . . . . 15 i

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l CONTROL OF HEAVY LOADS AT NUCLEAR PO'WER oLANTS SUSOUEHANNA STEAM ELECTRIC STATION, UNIT 1 (PHASE I)

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1. INTRODUCTION 1.1 Purcose of Review This technical evaluation report cocuments tne EG&G Icano Inc. review of general loac-handling policy and procecures at Susquehanna Steam Electric Station ' Unit 1. This evaluation was performed with'the objective of assessing conformance to the general load-handling guicelines of NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants" [1], Section 5.1.1.

1.2 Generic Backoround Generic Technical Activity Task A-36 was establishec by the U.S.

Nuclear Regulatory Commission (NRC) staff to systematically examine staff licensing criteria and the acequacy of measures in effect at operating nuclear power plants to assure the safe handling of ieavy -

loads and to recommend necessary changes to these measures; *

.is activity was initiated by a letter issued by the NRC staff on May 17, 1978 [2], to all power reactor applicants, recuesting information concerning the control of heavy loacs 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 conclusion from this evaluation was tnat existing measures to control the nandling of heavy loads at operating plants, altnough providing protection from certain potential problems, do not adeouately cover the major causes l of load-handling accidents anc should be upgracec.

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 1

l f'est portior of :ne :cjec-ive, 2:.- i.ac :nrougn a set of generai

! suicalines icentifisc in NCRE2-OsII, A-ticle 5. .;, is to ensure ina:

I all load-nandling systems at nuclea ;ower plants are casignec and t - ,.-:.- _,

! c:eratec such that neir procability of failure is uniformly small anc accropriate for tne cri-1:si tasks in wnich :ney are emoloyed. .The second portion of the stafs objective, achieved :nrough guicelines identified in NUREG-0512, Articles 5.1.2 througn 5.1.5 is to ensure tnat, for load-nandling systems in areas where their failure might result in significant consecuences, ei-her (a) features are oroviced, in accition to those recuired for all load-handling systems, to ensure '

that the potential for a load drop is extremely small (e.g. , a single-failure-proof crane) or (' ) oconservative evaluations of lead-handling accidents indica e tha: :ne potential consequences of any lead drop are acceptably small. Acceptability of accident consequences is cuantifisc in NUREG-0612 into four accident analysis evaluation criteria.

The aporoacn used to cevelop tne staff guicelines for minimi:ing the potential for a load croc was basec on defense in depth and is summarized as follows:

i e Provide sufficient coerator training, handling system design, load-handling instructions, and equipment insoection to assure reifacle operation of the handling system

. e Cefine safe load travel pa:ns througn crocecures anc operator training so that, to the extent practical, heavy loads are not carried over or near irradiated fuel or safe snutoown ecuipment e Provide mechanical stoos or electrical interlocks to prevent movemen of heavy loads over irradiatec fuel or'in proximity to equipment associated with redundant shutdown oaths. .

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

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1.3 Plant-Soecific Backcround

~0n Decemcer 22, 1980, the NRC issued a letter [3] :o the Pennsylvania Power and Light Co. (PP&L), the Applicant for SSES No.1, recuesting that the Applicant review provisions for nandling and centrol of heavy loads at SSES No.1, evaluate these provisions with respect to the guidelines of NUREG-0612, and provide certain additional info'rmation to be used for an independent determination of conformance to these guidelines. On June 22, 1981, PP&L provided the initial resconse. [4]

to this recuest.

On September 24, 1981, PP&L submittec a final response [4a] to the generic letter. DP&L submitted anotner report [ib] on June 4, 1982.

A telepnone conference among PP&L, NRC, anc EG&G Icano was held on '

June 23, 1982. A response to the telechone call. [4c] was suositted by.

PP&L on November 18, 1982.

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2. EVALUAT:CN AND RECOMMENCA7! NS 2.1 Overview

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The following sections summari:e PP&L's review of neavy leac-hancling at SSES No. 1 ac 0mpanied by EG&G's evaluation, conclusions, and rec mmendations to :ne Applican for cringing :ne facilities more c:mpletely int: ccm liance witn the intent of NUREG-0612. The Applicant nas indicated the weign of a heavy load for this facility (as cefined in NUREG-0612, Article 1.2) as over 1000 councs.

2.2 Heavy Load Overhead Handlino Systems This section reviews :ne Acolicant's list of overneac nancling systems w-icn are sucject to tne criteria of NUREG-0612 and a aev ew of :ne i

justifica icn for excludin,,g 'overnead handling systems from the a:ove-T.entienec list.

2.2.1 Sce:e .

" Rep' ort the results of your review of plant arrangements to '

icentify all overhead handling systems from which a load crop may result in damage to any system reouired for plant snu:down or decay heat removal (taking no credit for any interlocks, technical s:ecif' cations, coerating procedures, or detailed structural analysis) and justify tne exclusien of any overneac handling system from your lis Dy verifying nat there is sufficient pnysical separation from any load-impact point anc any safety-related ccmponent to permit a determination by ins:ection tna: no heavy load drop can result in camage to any system or component repuired for plant shutdown or decay neat removal."

A. Su= mary of Acelicant Statements The introduction to PP&L's submittal c:ntained this statement.

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"PP&L's basic cojective in responding to NUREG-0612 is to insure that the nandling of the overnead loads at 4

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f 5555 is perfcrmed in a safe and efficient manner oy l orovicing operators witn tne proper training, coerating j procecures, and tne ecuipment safeguards necessary.'and l by insuring tnat as many overreac operations as possible are perfctmenhfdefinec ' safe lodc patns.

l Where loads must be handled in the vicinity of new or spent-fuel, or nuclear safety related equipment, the ultimate objectives are to insure:

1. radioactive release as a result of a potential load crop is within the requirements of 10 CFR Part 100,

2. damage to fuel will not result in a k,77 greater than 0.95.

3. damage to the RPV or'soent-fuel pool will not uncover fuel, and

a. camage to epuipment will not result in the loss of safe shut cown cacability nor tne capability to remove decay heat.

For the purposes of this resconse, a heavy load was considered to be any load in excess of one thousand pounds. This was tne most realistic weign: limit to evaluate because many cranes, menorails and heists were rated in units of 1/4, 1/2, or I ton units. In addition, the weight of some loads was estimated and a convenient unit (1/2 ton) was conservatively used for

• r.elatively small loads."

PP&L's review of load-handling ecuipment and assessment of those cranes which could be excluced from further load crop analysis was conducted by a walkthrough of the plant, drawing

, reviews (drawings supplied), and a cross check with tne SSES Equipment Index. Consideration was also given to the lateral movement of loads due to deflections, caused by the possibil-

ity of loacs striking structural members.

Where cranes or monorails travel over hatches or access ways, the lower areas were also visually inspected for the potential impact

! of a load drop.

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l Tacle 1, Dar 3 of :ne submittal calls cut, Oy ecuicment numcer, tnose pieces of ecuicmen; wnien fall into PD&L's.categcry indica'ted by Note (3):

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" Note (3) Hancling this loac recuires further review :c determine whe:ner modifications or precedural recuirements are :c be inclemented to meet NUREG 0612. Results of ne review will ce in PP&L's final recort."

Attachment A, intendec to succlement Table 1, Part 3, exclains the nature of the hancling proclems and incicates "eitner-cr"'

solutions.

In reference [a c] PP&L states:

"CD&L did not rely on off-site calculations c justify postulated leac crocs. For this reason, cur analyses are valid egardless of the allowacle dese rate used; however, if :nis type of analysis is done in tne future,' the criterien of '7ess than 25 per cent of the receirements of 10 CFR ".~~ ' will ce usec."

3. - EG&G Evaluation PP&L's evaluation is tnercugh and app =ars to accress all imoortant ceints. The techniques usec are good.

PD&L nas cefined a heavy leac as any load in excess of 1000 lb. EG&G assumes that this meets the NUREG 0612 definition, "any load, carried in a given area after a plant ,

becomes coerational, that weighs more than the ecmcinec weight of single spent-fuel assembly and its associa:ec nandling too-1 for the specific plant in question."

B C. EG&G Cc ciusdens and Reccenencatiers .

Based upon the information providea, EG&G Idaho concludes that PP&L is in ecmoliance with the requirements of 2.2.1, above, at SSES No. 1.

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2.3 Gene-al Guicelines Inis section acdresses the extent to which the applicable nandling sys-

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tems ecm61y witn she gene'r al 'gili2e~ Teies 6' TnMEG-0612 Article 5.1.1.

u EG&G's conclusions and recommendations are proviced in summaries for each guideline.

The NRC has established seven general guicelines which must be met in order to provice the defense-in-cepth aporoach for tne handling of heavy loads. These' guidelines consist of the following criteria from Section 5.1.1 of NUREG-0612:

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

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

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t 2.3.1 Safe Load Patns [Guiceline 1. NUREG-0612. A -icie 5.1.1(;','

" Safe load pa ns snoulc ce defined for One oevement of neavy

_ _ _ leacs to minimi:e tne :cten-tal fc;sneavy : a ee ;_1f crcpced, ::

imcact irraciated fuel in :ne reactor vessel anc in the scent-fuel pool, or to imcact safe shutd:wn ecuicment. The Oath should follow, to ne extent practical, s ructural flece mem ers, ceams etc., sucn that if :ne loac is crop ec, :ne structure is more likely :: withstanc the im act. These loac patns shoule ce cefined in prc:ecures, snown on equipment layout crawings, and clearly marked on :ne f1cer in tne area wnere the Icac is to be nandlec. Deviations free cefinec lead pa:ns should recuire writter alternative prececures appr:vec Oy :ne iant safety review committee."

A. Summary of Acolicant Statements

" Plant Staff engineers have reviewec the leac-handling sys-tems for :ne cur;cse of identify'rg sa'e icad ca:ns relative to safety ecui; ment and scent-fuel. :igures 1 :nru 25 were marked Oc'incicate the safety relatec ecuicment, scent-fuel anc tne patns encsen. Aisc inciucec in :ne figures are s ructural steel prints used := cetermine :ne mos: feasible safe lead patns. Tnese ca:ns were defined for nandling sys-tems that bctn fell uncer ne area Of concern witn respect to NUREG-0612, and were of tne Ocidge crane type. Mencrails were exclucec from :nis analysis, since lead movement is i dedicated by the menerail itsaif Safe lead paths will be -

clearly marked on :ne ficer of the clant by the constructor.

PP&L's Mechanical Maintenance is ccmmitted to incorporate ne safe lead paths into the appropriate operating procedures."

The Novemcer 13, ".932, su mittal [dc] accresses the marking of safe load ca:ns and ne methec of obtaining accroval f:r deviations from safe loac patns.

3. EG&G Evaluatien EG&G's review of the A:plicant re.spense, and drawings submitted, indicates tnat SSES No. 1 may be considered to be in compliance witn Guideline 1.

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• PP&L's re' view seems to se ccmprenensive anc :ne resconse indicates an uncerstancin'g of :be scints coverec by

. Guideline 1 of' NUREG 0612. PP&L adequately accresses tne *

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marking of safe load paths a~nc the metnc.c of o::aining approval'for ceviation from safe load paths.

C. EG&G Conclusions and Recommendations Based ucen the informat. ion provided. EG&G Idaho concluces that SSES No.1 is in compliance with the intent of Guideline 1 of NUREG 0612.

2.3.2 Lead-Handline Procedures [ Guideline 2. NUREG-0612, Article- _

5.1.1(2)]

" Procedures shculd be cevelopec to cover leac-nandling caerations for heavy loacs that are or could ce banaleo over or in proximity to irraciatec fuel or safe'snutcewn equicment. Af a minimum, cro-cedures should cover handling of those loads listec in Tacle 3.1-1 of NUREG-0512. These procecures shculd incluce: icentification of recuired equipment; inspections anc' accectance criteria recuired before movement of load; the steps and procer sequence to be foi-icwed in, handling the lead; defining the safe patn; and otner .

special precautions."

, A. Summary of Acolicant Statements "PP&L is currently preparing general operating procedures for l overhead handling systems. These procedures will include pre-cautions and guidelines to be observed while operating the sys -

tems. A general operating procedure for the Unit 1 Reactor Building Crane is currently being prepared'by PP&L and will be available for. use prior to fuel lead date (apercximate impie-

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mentation date is July 1981). A draft copy is attached for information purposes (see Attacnment B, " Reactor Building Crane Operating Procedure"). The draft copy indicates how compliance with N'JREG-0612 wi.11 be accomplished; it cescribes in detail tne operational procecure the precautiens to be taken to insere safe handling of 1 cads. In addition to crane operating procedures, PP&L is develocing special handling procedures for major heavy Icads. Such procedures will supple-ment the general crane operating procedure by providing ~addi-tional precautions and a_ safe load path for that unique load.

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! A craf: cocy of tne crocecur.e "~eac o- P essure Vessel head

'nstallation and Remova'." is a :acrec for information parcoses (see At acnment;C). .N ow :na: ne nar. cling sys e=s tr.at coulc

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icoact safe snutcown eckioment have been icentified, ?P&L will

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ceveToo procedure.s governing *PJe$ents U tnTn :nese areas.

All specific fuel handling processes anc icac movements on 'tne Refueling Floor will be coverec by accencing a soecial loac-handling crocedure for that particular evaluation, to tne general coerating' procedure for the cra.ne to be used."

2. EG&G Evaluation Insofar as EG&G can determine, :ne sample procecures~

submitted by PP&L are well cone. In Reference [ac], PP&L states that generic safe load paths have been incorporated into crane operating procecures. In support of :nis, PP&L nas suomitted a cnart comoaring their actions witn :ne

-souirements of Table 3.1-1 of NUREG C612.

PP&L has cevelooed crane coerating procedures (not sucmitted) and special heavy-load-handling procedures (MT-99-C01, Rev. O was submitted as a samole). The concept is accestacle and tne procecure suomitted seemec to be tnorougn.

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t The submittal adequately addresses the requirements of Guideline 2 of NUREG C612.

C. EG&G Conclusions and Reco=cencations Based on the information providec, EG&G Idaho concludes that SSES No. 1 is in compliance with the intent of Guideline 2 of NUREG 0612.

2.3.3 Crane Oeerator Train 1nc fGuideline 3. NUREG-0512. Article'5.1.I(3)1 5

" Crane coerators snould be trained, cualified, anc concuct :nem-selves in acecrdance with Chacter 2-3 of ANSI 230.2-1976, 'Over-nead and Gantry Cranes' [5]."

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4 A. Summary of Acol! cant Statements "We made no exceptions to ANSI B30.2-1976. The crane oper-

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ator's training prograhas%evetcp?d to meet tne recuire-ments of chapter 2.3 of ANSI 330.2-1976 "Overnead anc Gantry Cranes." A procedure is currently being written by plant staff mechanical section to formali:e tne program and fur-

. nish the necessary forms to document the training. All crane operators will be qualified to this procedure."

3. EG&G Evaluation Based upon the Applicant's statement, the crane operator training program satisfies the criteria of Guideline 3.

EG&G Idaho assumes that the'" crane' operator's training

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. program" mentioned in 2.3.3 A is tha same as "AD-00-015, Crane Operator Qualification program," referenced in 3.1 of MT-99-001.

C. EG1G Conclusion and Recommendations Based on the information provided, EG&G Idano concluces that SSES No. 1 is in compliance with the intent of Guiceline 3 of NUREG 0612.

2.3.4 Soecial Liftinc Devices fGuideline 4 NUREG-0612. Article 5.1.1(4)1 "Special lifting devices should satisfy the guidelines of ANSI N14.6-1978, 'Stancard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More for Nuclear 1 Materials' [6]. This standard shoulc apply to all special.

lifting devices whicn carry neavy loacs in areas as defined above. For operating plants, certain inspections and lead tests may be accepted in lieu of certain material reputrements'in the standard. In addition, the stress design factor stated in Section 3.2.1/1 of ANSI N14.6 should be basgd cn the combined maximum static a.nd dynamic loads that could be imparted on the handling device based on characteristics of the crane _which will-be used. This is in lieu of the guideline in Section 3.2.1.1 of ANSI N14.6 which bases the stress design; factor on only the weight (static load) or the load and of the intervening components of the special handling device."

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A. Summary c' 'ecifcan: Statemeats

" Slings.anc special lif:1ng cavi:es nave no: ceeh pr:cureo

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'for use a: 5555 excect tre s:M.4gt'a G r ?cr the RPV heac anc the lifting cevice for :ne cryer anc se:arator. These items nave ceen cesignec anc sue: lied cy :ne NSSS vendor.

Sufficien; information is not yet available fer determining full comeliance witn ANSI 330.9 1971; however, :.ie strong-back for the RPV has been =rcef-icad tes:ec to 125 tons, inscected by magnetic carticle examina:1cn and used to move the RPV neac for Unit 1, anc :ne cryer/ separator lifting cevice meets :ne proof-leac recuirements of ANSI E30.9-1971 anc nas ceen inspectec cy magnetic particle examination.

All other slingF anc/or lifting devf Ces which wfil handle heavy loads that could imcact safety-relatec equipment or fuel will be installed and used in accordance with the guidelines of ANSI E30.9-1971. In selecting the proper sling, :ne loac usec will be :ne sum of the static and the maximum cynamic loac (SSE will not ce inclucec in the dynamic lead imcosed in the sling or lifting cevica). The rating icentification on the sling will ce in terms of :ne

" static lead" which procuces :ne maximum static and cynamic lead. Wnere tnis restricts slings to use en only certain cranes, the slings will ce marked as to the cranes with which they may be usec. Saecial lifting cevices to :e usec with scen -fuel shiccing containers will be cesignec, installec and usec in acc:rcance witn the guicelines of ANSI N14.6-1978."

Accisional information sup'pliec in subsequent submittals

[4a], [4b], and [4c], by means of a point-by point comp-ari son with ANSI N14.6-1978, addresses comoliance with Guideline 4 of NUREG C612.

S. EG&G Evaluation Information contained in references [4], [da], [4b], and .

[4c] is sufficient to make an assessment of compliance with Guideline 4 of NUREG 0612. Where PP&L has tested to 125% of the rating, instead of the 15C% stated in ANSI N14.6-1973, EG&G Icaho considers this to be in compliance with the intent of Guiceline 4 12 h #

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l PP&L has stated, "Special lifting devices to be used with spent-fuel shipping containers will be designed, installed and used in accordance with_.the guidelines of ANSI N14.6 ~

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1978." Guideline 4 sta.tes "This stancarc shoule apply to all special lifting devices which carry heavy loads in areas as defined above." This guideline also states that the stress cesign factor in Section 3.2.1.1 of ANSI N14.6 shcult be based on the combined maximum static and dynamic icacs that could be imparted on the handling device based on characteristics of the crane which will be used.

C. EG&G Conclusions and Recommendations Based on the information orovided. EG&G Idaho concludes that SSES No. 1 is in compliance with tne intent of Guiceline 4 of NUREG 0612.

2.3.5 Liftino Devices (Not Soecially Desicned) [ Guideline 5.

NUREG-0612. Article 5.1.1(5)1

" Lifting devices that are not specially designed should be installed and used in accordance with the guicelines of ANSI B30.9-1971, ' Slings' [7]. However, in selecting the proper sling, the load used should be the sum of the static and maximum dynamic load. The rating identified on :ne sling shcule be in terms of the ' static load' which creduces the maximum static and dynamic load. Where this restricts slings to use on only certain cranes, the slings should be clearly marked as to tne cranes with which they may be used."

A. Summary of Aeolicant Statements "All other slings (not covered in 2.3.4) and/or lifting devices which will handle heavy loads that could impact safety-related equipment or fuel will be installec and usec in accordance with the guidelines of ANSI B30.5-1971. In selecting the proper sling, the load used will be the sum.of the static and the maximum dynamic load imposed in the sling.

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l or lifting cevice). The ra:f ig identification on :ne sling will ce in terms of :ne " stat.c icad" wnien procuces :ne maximum static anc cynamic Icac. Where tnis restric s slings to use on only certain cranes.,the slings wili' be

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...arted as to the cranes 'with '6T'dh i.Wm'Ty'ce usec."

FP&L also acdressec the use of slings in References [da],

[ab], and [4c].

B. EG&G Evaluation The information supplied in References [a], [aa], [4b], and '

[4c] is sufficient to make an evaluation of compliance with '

Guideline 5 of NUREG 0612. .PP&L fndicates that slings for general ourpose rigging will be sized for a minimum o' 15%

cynamic loading.

C. EG&G Conclusions ~and Recommendations Based on the information provided, EG&G Idaho concludes tnat SSES No.1 is in c:=cliance with the intent of Guiceline 5 of NUREG 0612.

1 2.3.6 Cranes (Inscection. Testing, and Maintenance) IGuideline 6, NUREG-0612. Article 5.1.1(611 "The crane should be insoected, tested, anc maintained in

' accorcance with Chapter 2-2 of ANSI B30.2-1976, ' Overhead and Gantry Cranes,' with tne exception tnat tests and inspections should be performed prior to use where it is not practical to meet the frequencies of ANSI 330.2 for periodic inscection and test, or where frecuency of crane use is less than :ne specified insoection and tes: frequency (e.g., :ne polar crane insice a PWR l

containment may only be used every 12 to 18 months during l

refueling operations, and is generally not accessible during oower coeration. ANSI B30.2, however, calls for certain inscections to be performed daily cr monthly. For such cranes naving limited usage, the inspections, test, anc maintenance snoulc be performec prior to their use)."

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A. Su ma-v of A:olican: Statements "PP&L is cre;ently cevelocing a cresenta:ive maintenance pro-gram to incluce all craneranc7 ::Mts . This program will incluce requirements for inscection, testing, and maintenance in accorcance with tne guidelines of Chapter 2-2 of ANSI B30.2-1976 with tne exceotion' :nat tests and inspections will

, be cerformed. prior to use where it is not practica.I to meet tne frecuencies of ANSI B30.2 for periodic inspection and test, or where frequency of crare use is less than the specified inspec-

' tion anc test frecuency. The diesel building cranes (OH501 A,

3. C. and D) and the reactor building crane (auxiliary hoist, 1H213') nave been usec curing plant construction. .The construc-tion group has performed the necessary inspecting, testing, and maintenance requirements of Chapter 2-2,. ANSI.B30.2-1967."

B. EG&G Evaluation The projected preventive maintenance program in accordance with ANSI B30.2.0 1976 is accectable for cranes in this clas- '

sification. Technically, monorail systems and undernung cranes should be inspected, tested, and maintained in accor-dance with ANSI B30.11-1980. In these instances, the requirements are not significantly different so that ANSI B30.2.0-1976 is acceptable.

PP&L states that those cranes used during construction were inspected, tested, and maintained, by the construction organization in accordance with ANSI B30.2.0-1976.

C. EG&G Conclusions and Recommencatiens Based on the information croviced, E3&3 Idaho concicdes that SSES No.1 is in compliance with the intent of Guideline 6 of NUREG 0612.

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

"The crane should be designed to meet the applicable criteria and guidelines of Chapter 2-1 of ANSI B30.2-1976, ' Overhead and Gantry' _,

15-

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_ _ - _ _ _ _ _ - _ - _ _ _ . _ - - - _ _ . - - - - - - - - - - - -- -A

Cranes,' anc cf CMAA-7C, '5:ecifica:10ns for Electric Overneac Tr2ve'ing Cranes' [3]. An alternative to a s:ecification in AN5!

330.2 or CMAA-70 may ce acces:ec in lieu cf s ecific cc==:iance if the inten; of One s:ecification 'is satisfiec."

A. Summary of Acclican: Statements Design requirements, for those cranes f-em wnich a icac creo could impact safety-related scuipment or fuel, are in accordance with the Crane Manufacturers Association of America (CMAA) Specification 70 and ANSI 330.2. The reactor building crane (IH213) and the diesel building cranes (OH501 i

A, B, C, and D) are cesignec in accordance with CMAA-70, Class C and ANSI 530.2-1967. The monorail noists are cesignec in accorcance witn ANSI B30.16. Tne cesign of :ne jib crane is in accorcance wi-h ANSI 530.2-1976 anc CMAA-70.

S. EG&G Evaluation -

The Applicant states tna; menorail hoists are cesigned in accordance with ANSI S30.16. Guiceline 7 states :na: an alternative to a specification in ANSI 330.2 or CMAA 70 may '

• be accepted in lieu of specific compliance if ne intent of

ne specification.is satisfiec. EG&G feels that, for this tyce of ecuicment, ANSI 330.16 is an acceptable equivalent to ANSI S30.2.

C. EG&G Conclusions and Reccmmendations Based :n the information provided, EG&G Icaho conciuces that SSES No. 1 is in compliance with the intent of Guideline 7 of NUREG 0612.

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4 IARi[ 3.l. $U5tlUlllANNA SitAH ttIClitIC SIAll0N No.1, NURtG 0612 CUWLI ANCE HAIHlX Weight Guideline I Guideline 2 Guideline 3 Guldeline 4 Guideline 5 buldeline 6 Cuidellre /

or Crane Special' Ceane-lest Equipment Capac it y Safe load tiptrator Lifting and Designatlon licavdoads jty)_ Paths re oc citus e s le a lu ing _ Devices _5Jyp Insges. t ton 9 anye o sep s

OH fM A, 8. C D 5tator Diesel Generator 24,200 lb f ulliiing 20 C C C C C C C ltotor 21.114 lb 164 210 24,7th Ib Not Reactor Building I,ll5 sagsplieil 6.330 must C C C C C C C l.319 lee 2,700 12.5 i IH 208 Nefueling L ist ed Nut lH 203 Platform only as supplied C C 2 C C C C 4:

10 214 *1 me l" .

g _ _ . - _ ___. _ _

d IH Zll lleactor fuel leundle flut C C C C C C , C Building 1600 lb sagsplied .

,j

. _ _ f___ _

let 213 Reacto.- phiclear b Sullding fuel (Ausillary Hook) fuel pool C C C C C C (.

covers I Weight not si, plied g (Hala Holst) Missle/ shield 12 5 .

block s C C C C' C C 191,000 lb man imune 4

+

f

i s. . .

. l .

s 1 ABL E 3.1. (Cor.t thued) '

Weight Guideline I Guldeline 2 Guideline 3 Guldeline 4 Guldeline 5 Guideline 6 Guideline 7 or Crane Special Crane-Test f Equipment Capacity Safe load Operator Lifting and Designation Heavy loads (tons) paths procedures leeining Devices Slings inspection trane Design Reactor Building RHXXX Resin bed *

' crane erot y*t sbleid covers C C C C C C C purchased 30,500 lbs ,

IH 2I9 Reactor Equipment Not C C C C C C C Building access door sigiplied .

lH 403,lH 401, Safety valve not #

IH 406, lH 401, 2000 lbs supplied C C C C C C '

C IN 408, XHXXX Reactis Sulleing , )l lN 205 Reactor Rec irculat ion y Sullding pump 21,200 lbs 24 C C C C C C C

lli 209 Reactor Reactor heat asut Building removal pump sivplied C C C C C f C C 20.650 lies (mislaum)

C = Applicant action compiles with NHitlG-0612 Guideline.

NC * $plicant act ton does not comply with IIUREG-0612 Guideline

, R = Applicant has proposed revisions /dtfications designed to comply ulth IduREG-0612 Guideline.

l = lnsufficient infomation provided by the 4plicant.

9 i

4 i

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3.3 -te-i- :-0 e: cr

.G!.2's evalua:d:n Of inf:r.mation ;:r:vicec

.,w Oy One A::li:1r- 19:1:ates tna; tre f0licwing ac-icns are cecessary to ensure :na: :ne six NRC staff measures f0r interim cr:tection a- 5555 No. I are met:

. Interim Measure Recommendation Interim Measures Net Acclicable, were not accressec 4

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t 4 REFERENCES

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

2.- V. Stello, Jr. (NRC), Letter toSM ahNms. Suoject: Request for I

Adcitional Information on Control of Heavy Loads Near Spent Fuel, NRC,

) 17 May 1978.

3. USNRC, Letter to Pennsylvania Power & Light.

Subject:

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

I i 4 Pennsylvania Power & Light, Letter to Darrell G. Eisenhut (NRC).

Subject:

Susquenanna Steam Electric Station, NUREG 0612. Control of

Heavy Leads - Six Month Report. 6/22/81, ER 100450 File 842-06 PLA 857.

Aa. Pennsylvania Power & Light, Letter to Carrell G. Eisenhut.

Subject:

Suscuehanna Steam Electric Station - Final Report, I 9/24/81 PLA-937.

ab. Dennsylvania Power & Light, Letter to A. Schwencer.

Suoject: Susquehanna Steam Electric Station, 6/4/82 PLA-1110.

4c. Pennsylvania Power & Light, Letter to A. Senwencer.

Subject:

Susquehanna Steam Electric Station, 11/18/82 P LA-1332. .

i

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

i

6. ANSI N14.6-1978, "Stancard for Lifting Devices for Shipping Containers 1 . Weighing 10,000 Pounds (4500 kg) or more for Nuclear Materials." .

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

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

4 21 l  :..

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i luc o . .5 ,AS NuctE Aa aEcut. ATCav c uussSica EGG-yS-62':1 sisuCCRA?H::  :.TA ; MEET l'

4 rirte .Ne SusrirtE l :. <t ,,.e .. . ,

Control of Heavy Leads at Nuc' ear Pcwer Plants 3 "ECE uT S Ac0ESsim Nc Suscuenanna Steam Electric Staticn, Unit 1 (Phase 1) i 7 au r-ca ts, 5 c ATE aEccat covPtETEo 1 T. H. Stickley T ap*r'il i "

1983 i

i

' 9 PE R8 0aWNG ORGAN 42 ATION N AM[ ANQ M AILING ACORE$5 (Jactuar 7,0 CJoes OATE REPOHf sSSuto i voNew j .taa ,

June 1983 i EG&G Idaho, Inc. e et, , . ,,,,

Icabo Falls, ID 83415 -

I 8 l Leave maant ,l 12 SPCNSORiNG ORGANt2 AfiCN N AME ANQ V Alt lNG ACORESS Itacevoo I,o Cooel

'"*"^**"

Division of Systems Integration Office of huciear Reactor nequiation ii. 5,u so.

U.S. Nuclear Regulatory Commission A6457 Washi:igton, DC 205S5 13 TVPE OF *EPORT *t aiCO C ov i *t C 'iaedus.ve seres

• l 15 SUPPLEVE*aTARY NOTES 14 (see e o'a'ai i 16 485Tm aCT COO . oros or wass l 1

The Nuclear Regulatory Commission (NRC) has requested that all nuclear plants, i I either operating or uncer ccnstructicn, submit a response of ccepliancy with j NUREG-0612. " Control of Heavy Loads at Nuclear Power Plants." EG&G Idaho, *nc., ,

has contracted with the NRC to evaluate the responses of nose plants presently under construction. Utilities are required to report in two pnases. This report l contains EG&G's evaluation and recomendations for Susquehanna Steam Electric Station l-Unit No. 1 (SSES No. 1). Only Phase I is addressed. Phase II wil1 be covered in a separate report.

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Ma'ke available only as specifically approved Unclassified by program office. M$'s s Nil ['"' s N ec some 33S iti esi

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