ML18040B030

Control of Heavy Loads at Nuclear Power Plants,Susquehanna Steam Electric Station,Unit 2 (Phase I), Draft Technical Evaluation Rept

ML18040B030
Person / Time
Site:	Susquehanna
Issue date:	09/30/1983
From:	Friederichs S EG&G, INC.
To:	NRC
Shared Package
ML17139B963	List: ML18040B030
References
CON-FIN-A-6457, REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8310310199
Download: ML18040B030 (37)

Text

CONTROL OF HEAVY LOADS AT NUCLEAR POMER PLANTS Susquehanna Steam Electric Station Unit 2 (Phase I)

Docket No. [50/388]

Author S. L. Friederichs Principal Technical Investigator T. H. Stickley Publ i shed September 1983 EGEG Idaho, Inc.

Idaho Fa'l l s, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Under DOE Contract No. DE-AC07-76IDO 1570 FIN No . A6457

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ABSTRACT The =Nuc:lear:Regulatory Commf-ssion (NRC) ~has requested,Shet"all nuclear plants, either operating or under construction, submit a response of compliancy with NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants." EG8G 1daho, inc., has contracted with the NRC to evaluate the responses of those plants presently under construction. This report contains EGKG's evaluation and recommendations for Susquehanna Steam Electric Station, Unit 2.

EXECUTEYE

SUMMARY

Based on the in'formation prov'ided Susquehanna Steam Electric Station Unit 2 is in compliance with the intent of the requirements of NUREG 0612.

CONTENTS ABSTRACT .

EXECUTIVE

SUMMARY

1. INTROQUCT ION 1.1 Purpose of Review ..

1.2 Generic Background ....,

1.3 Plant-Specific Background ~ ~ 3

2. EVALUATION ANQ RECOMMENQATIONS . ~ ~ ~ ~ ~ 4 2.1 Overview ..........,....

2.2 ,Heavy Load Overhead Handling..Systems .

2.3 General Guidelines ~...... 10 2.4, Interim Protection Measures

3. CONCLUOING

SUMMARY

. 25 3.1 Applicable Load-Handling Systems . 25 3.2 Guideline Recommendations ........ ........ ... ........ .. 25 3.3 Interim Protection ......,. 31 3.4 Summary . 31

4. REFERENCES 32 TABLES

2. 1 Nonexempt Heavy Load-Handling Systems ..

2.2 Exempt Heavy Load-Handling Systems ~ ...... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ 9

3. 1 NUREG-0612 Compliance Matrix ... ..

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Control of Heav Loads at Nuclear Power Plants Sus uehanna Steam Electric Station Unit '2 (Phase I)

l. INTROQUCTION 1.1 Pur ose of Review This technical eva'luation report documents the EG&G Idaho, Inc.,

review of general load-handling policy and procedures at Susquehanna Steam Electric Station, Unit 2. This evaluation was performed with

.the .objective iof;assessing conformance .io the.general -load=handling guidelines of NVREG-0612, "Control of Heavy Loads at Nuclear Power Plants" [1], Section 5.1.1.

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

Nuclear Regulatory Commission (NRC) staff to systematically examine staff applicant 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 Hay 17, 19?8 [2],.to al~l:power a eactor -applicants, requesting information concerning the control of heavy loads near spent fuels The results of Task A"36 were reported in NUREG-0612, "Control of

.Heavy Loads at Nuclear Power Plants." The staff's conclusion from this evaluation was that existing measures to control the handling of heavy loads at operating plants, although providing protection from certain potential problems, do not adequately cover the major causes of load-handling accidents and should be upgraded.

In order to upgrade measures for the control of heavy loads, the staff developed a series of guidelines designed to achieve a two-phase objective using an accepted approach 'or pro'tection philosophy. The first portion of the objective, achieved through a set oi general guidelines identified in NUREG-0612, Article 5. l.l, is to ensure that all load-handling systems at nuclear power plants are designed and operated such that their probability of failure is uniformly small and appropri'ate for the 'critical tasks in which they are employed. The ~ ~

second portion of the staff's objective, achieved through guidelines identified in NUREG-0612, Articles 5. 1.2 through 5. 1.5, is to ensure that, for load-handling systems in areas where their failure might result in significant consequences, either (a) featu> es are provided, in, addi.tion to those required for all load-handli-ng.systems, .to ensure that the potential for a load drop is extremely small 'e.g., a single-failure-proof crane) or (b) conservative evaluat>ons of load-handling accidents indicate that, the potential consequences of any load drop are acceptably small. Acceptability of accident consequences is quantified in HUREG-0612 into four accident analysis eva'luation .criteria.

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

o Provide sufficient opera.~or training., handl'ing system design, load"handling instructions, and equipment inspection 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 o Provide mechanical stops or electrical interlocks to prevent movement of.,heavy leads .over irradfahed fuel .or i.n proximity to equipment associated with redundant shutdown paths.

Staff guidelines resulting from the foregoing are tabulated in Section 6 of NUREG-0612.

1.3 Plant-Specific Back round I~

5 On December 22, 1980, the NRC issued a letter I'3] to Pennsylvania Power & Light Company, the applicant for Susquehanna Steam Electric Station, Unit 2 requesting that the applicant review provisions for I handling and control of heavy loads at SSES No. 2, evaluate these provisions with respect to the guidelines of NUREG-0612, and provide certain additional information to be used for an independent

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r determination of conformance to these guidelines. On July 22, 1983, Pennsylvania Power .& .Light Company ~provided the initial e.esponse I 4]

to this request.

2. EVALUATiON ANO RECOMMENOATIONS

2. 1 'Over vi ew The following sections summarize Pennsylvania Power & Light Company's review of heavy load handling at Susquehanna Steam Electric Station, Unit 2 accompanied by EG&G's evaluation, conclusions, arid recommendations to the applicant for bringing the facilities more completely into compliance with the intent of NUREG-0612.

Pennsylvania Power & Light Company' review of the facilities does not differentiate between the two units so it is assumed that both units are of identical design. The applicant has indicated the weight of a heavy load for-thi;s .;faci,l.i.ty (as dei'4ned i:n NUREG-0612, Article,1..23

's 1000 pounds..

2.2 Heav Load Overhead Handlin S stems This section reviews the applicant's list of overhead handling systems which are subject to the criteria of NUREG-0612 and a review of the justification for excluding overhead handling systems from the above mentioned list.

2.2.1 ~Sco e "Report .the results of your review of plant arrangements to identify all overhead handling systems from which a load drop may result in damage to any system required for plant shutdown or decay heat removal (taking no credit for any interlocks, technical specifications, operating procedures, or detailed structural analysis) and justify the exclusion of any overhead handling system from your list by verifying that there is sufficient physical separation from any load-impact point and any safety-related component to permit a determination by inspection that no heavy load drop can 'result in damage to any system or component required for plant shutdown or decay heat removal."

A. Summar of A licant's Statements The appliaan ' review of overhead handling 'systems identified the cranes and hoists shown in Table 2. 1 as those which handle heavy loads in'he vicinity of irradiated fuel or safe shutdown equipment.

The applicant has also identified numerous other cranes that have been excluded from satisfying the criteria of the general guidelines of NUREG-0612, These are indicated in Table 2.2. These various overhead handling systems were reviewed by the applicant with regard to criterion NUREG .0612 .and .were ..excluded based on .plant specific conditions of plant shutdown or because the loads were not greater than 1000 lbs. The applicant also stated that a heavy load was considered to be any load in excess of 1000 lbs. This was the most realistic weight limit to evaluate because many cranes monorail.s and hoists were rated in units of 1/4, 1/2 or 1 ton units. In addition the weight of some loads was estimated and a convenient unit ( 1/2 ton) was conservatively used for relatively small loads. The applicants introductory remarks in the submittal indicate that the main objective in responding to NUREG 0612 is to insure that all handling of overhead loads at SSES No. 2 is accomplished:in a safe and efficient manner by .providing operators with proper training, operating procedures and the equipment safeguards necessary, and by insuring that as many overhead operations as possible are performed along defined safe load paths. When loads are to 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 drop is less than the requirements of 10 CFR Part 100.

2. damage to fuel will not result in Keff of greater than .95.

3. damage to the reactor pressure vessel will not result in uncovered fuel

4. damage to equipment will not result in loss of safe shutdown capability to remove decay heat.

PP&L review of the overhead load handling systems consisted of a physical walk down of all cranes, monorails, and hoists in the reactor building, visual inspections to verify that loads with l.arge physi.cal dimens.i.ons cauld -be .safely moved within defined load paths without impacting safe shutdown equipment in the event of a load drop, and by reviews of the affected drawings with cross checks of the SSES equipment index. Consideration was also devoted to the lateral movement of loads due to deflections caused by the possibility of loads striking structural members. Where cranes or monorails travel over hatches or access ways, the lower areas were visually inspected for the potential impact of a load drop.

Table 3 of the submittal, I'43 lists the "cranes requiring Detailed Review", the heavy loads associa ed -with each handling system from which a load drop could potentially impact safety-related equipment or fuel. The table includes crane identification, crane location, (building and elevation), load identification and weight, safety related equipment that could be impacted, and hazard elimination category.

TABLE 2.1 NON EXEMPT IIEAVY LOAD-IIANDLIHG SYSTEH SUSQUEIIANNA STEAM ELECTRIC STATION UNIT 2

~Ca s' Crane T e eav Loads lland led 2H 201 Refue I ing bridge Fuel 1000 Ibs 2II 203 (Aoactor Building Flovation 818')

2II 214 2II 205 Rec i rcu la t Ion pump Aoc i rcu la t Ion pump 27,200 Ibs lloist (24 tons capacity) Acc i rcu I a t I on pump s ta to r 21 860 Ihs (Reactor Building Elevation 719') Aec i rcu I a t ion pump rotor 10,315 Ibs 2II 206A Equipment access Access door 6<<,000 Ibs 2ll 2068 Door with porsonnol lock lloist ( 16 tons oach capacity)

(Aoactor Building Elevation 719')

2ll 208A RIIA liest Exchangors RIIR Ilcat Exchanger 48,000 Ibs 28 2088 Ilolsts (12 tons each)

(Roactor Gul lding Elevation 683')

2II 209 IIPCI, RCIC and AllA pump and Turbine llolst Coro Spray Pump Motor 6,330 Ibs (12 ton capacl ty) Coro Spray Pump Rotor 1,379 Ibs (Reactor Building Elovation 683') Coro Spray Pump Stator 2,700 Ibs Core Spray Pumps 7,115 Ibs Iligh Pressure Coolant 6,200 I bs In.)ection Pump IIPCI Booster Pump 3,900 Ibs IIPCI Gear Aeducer 1,260 Ibs IIPC I Stop Ya I ve 2,900 Ibs IIPCI Turblno Upper 7,500 Ibs liood Case

, IIPCI Turbine Rotor 1,<<00 Ibs Reactor Coro Isolation Cooling Pumps 5,275 Ibs Reactor Core Isolal,ion Cooling Turbine 3,<<90 Ibs Aos I dua I lloa t Removal Pump 20,650 Ibs RIIA Pump Motor 18,020 Ibs Alllt Pump Rotor 4,690 Ibs AIIR Pump Sta.tor 6,960 Ibs 2H 210 Core Spray Pumps and RBCCW )leat Exchanger llolst RGCCW Ileat, Exchanger 2<<,715 Ibs (12 ton capacity) Co ro Sp ray Pump 7, 115 Ibs (Aeactor Building Elovatlon 683') Coro Spray Pump Motor 6,330 Ibs Coro Spray Pump Actor 1, 3/9 I bs Core spray pump Stator 2,700 Ibs

TABLE 2.1 (continued)

~da e n CacTo Ilea Loads Iland ed ~Load of he 2ll 213 Reactor Oui Idlng Crane Aux I I I a ry llo I s t ( 5 ton ca pac 1 ty) llead llolding Pedesta I 1, ll50 I bs (Roactor Building Elevation 818 ) l)ryor/Separator Sl'Ing 3,500 Ibs Stud Tensioner 1,500 Ibs Vessel Ilcad Strongback 6,500 Ibs Jib Crane 5,200 Ibs llatch Covors 6,000 lbs Support Beams 3,000 Ibs Hain Ilolst ( 125 tons) Reactor Cavity Shield Blocks 71.5-98.5 tons (Reactor Building Elevation 818') Dry Wol I Ilcad IQII.5 tons Reacl.or llead lnsul at ion 18.2 tons Reactor llead 91.8 tons Steam Dryor IIQ.Q tons Stcam Soparator 73.3 tons Fuol Pool Plugs 12.0 tons, Wator Tight Gates 3.0-II.5 tons Equipmenl. Pool Plugs 63.0 t,ons Reactor Ilcad Carousel 5.0 tons Sorvlce Platform 6.5 tons 2ll 215 Equlpmcnt Shaft Crane Hiscellaneous II8,000 Ibs (2II tons cilpacl ty)

(Reactor Building Elevation 799')

2ll 216 Truck Oay Jib Crane Hiscellaneous II,000 Ibs (2 tons CApacity)

(Reactor Building Elevation 670')

2II 218 Reactor Building Concrete Shield 20,000 Ibs 2II 219 Concrotc Shiolding Block Block Iloists (Capacity not indicated)

(Reactor Building Eleval,ion 719) ill XXX Floor Plug Iloist Resin Bed Shield Cqvers 30 500 Ibs (Capac I ty IIot indi ca ted) Equipmcnt Access Plugs 27,200 lbs Reactor Building Elevat.lon 818')

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TABLE 2.2 EXEMPT HEAVY LOAD-HANDLING SYSTEMS SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 Location 1 H-E Category Crane ID Buildin 719'azardous El evati on Tar et 2 3 2H 204 Reactor Building None H 207A, B Orywell 719'ecirc. pump A 2H 211 Reactor Building 818'18'83'uel 2H 212 Reactor Building Fuel 2H 217 Suppression Pool Various

.2H F39-242 Reaqtor Building 739'ain .Steam Isolation Valves A

2H 243 Reactor Building 719'H 402A, B Orywel1 752'eedwater Isolation Valves 2H 403, 4 Orywell Steam Relief I 738'38'ain Valves 2H 406-422 Orywell Main Steam Relief Valves Notes: 1. Only cranes in Unit 2 reactor building are considered for this report. Buildings common to both units were covered in the Unit 1 reports. These are Radwaste, Diesel Generator, ESSM pumphouse, and Circulating Mater Pumphouse).

2 ~ Hazardous targets are items if impacted by a load drop, could contribute to one of the adverse consequences as listed in Secti on S. 1 o f NUREG 0612.

3. Hazardous Elimination Categories A. These load handling Systems are only used doing a shutdown..

B. The capacity of this load handling system is 1000 lbs or less.

8 EG&G Evaluation

'PP&L'-s evaluation'is similar to the subm:ittal for Unit 1, PP&L has provided the results of .heir review and identify any potentially hazardous load handling operations which will require special procedures or equipment modifications to insure the intent of NUREG 0612 is met. The review appears to be adequate.

C. EG&G Conclusions and Recommendations

'Since there is no information to the contrary, EG&G concludes that..the. applicant Ihas .incl,uded:all applicable hoists and cr nes in their list of handling systems which must comply wizh the requirements of the oeneral guidelines of NUREG-0612.

2.3 General Guidelines This section addresses the extent to which the applicab'le handling systems comply with the general guidelines of NUREG-0612, Article 5. l. l. EG&G's conclusions and recommendations are provided in summaries for each guideline.

The NRC has establ-i shed .seven general guidel'ines'which must:be met in order to provide the defense"in-depth approach for the handling of heavy loads. These guidelines consist of the following criteria from Section 5.1.,1 of NVREG-0612:

o Guideline 1 Safe Load Paths o Guideline 2 Load-Handling Procedures o Guideline 3 Crane Operator Training 10

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pl I o Guideline 4 Special Lifting Oevices o Guidel~ne '5 Lifting 'Oev'ices (rrot specially designed) o Guideline 6 Cranes (Inspection, Testing, and Maintenance) o Guideline 7 Crane Oesign.

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

2.3. 1 Safe Load Paths Guideline 1 HUREG-0612, Article 5. 1. 1 1 "Safe load paths should be defined fo- the movement of heavy loads to minimize the potential for heavy loads, if dropped, to impact irradiated fuel in the reactor vessel and in the spent"fuel pool, or to impact safe shutdown equipment. The path should follow, to the extent practical, structural floor members, beams, etc., such that if the load is dropped, the structure is more likely to withstand the impact. These load paths should be, defined in procedures, shown on equipment layout drawings, and clearly marked on the floor in the area where the load is to be handled. Oeviations from defined load paths should require written alternative procedures approved by the plant safety review committee."

A. Summar of A licant's Statements The applicant states "Plant Staff engineers have reviewed the load handling systems for the purpose of identifying safe load paths relative to safety equipment and spent fuel. Figures 1 thru 10 were marked to indicate the safety related equipment, spent fuel and paths chosen. These paths were defined for handling systems, that fall under the area of concern with respect to NUREG 0612, and were of the 11

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~ ~ ~ i bridge crane type. Monorails were excluded from this analysis, since load movement is dedicated by the monorails itself'. 'Safe load paths will be clear'ly marked on the refueling deck prior to initial fuel loading."

B. EG8G Evaluation EG&G has reviewed the applicant's response regarding safe load paths and the drawings provided, and considers the intent of guideline 1 of NUREG 0612 to have been satisfied.

PPEL has indicated the manner in which implementation of a temporary change to .existing defined safe load paths is to be made and the method of obtaining approvals for this deviation.

C. EGEG Conclusions and Recommendations Based on the information provided EGEG concludes that SSES No. 2 is in compliance with the intent of guideline 1 of NUREG 0612.

2.3.2 Load-Handlin Procedures Guideline 2 NUREG-0612 Article 5.1.1 2 "P. ocedures should be developed to cover load-handling operations for heavy loads that are or could be handled over or in proximity to irradiated fuel or safe shutdown equipment. At a minimum, procedures should cover handling of those loads listed in Table 3"1 of NUREG-0612, These procedures should include:

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

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A. Summar of Applicant's Statements

'The appl icant states "'PP'&L has 'prepared 'general operating procedures for overhead handling systems. These procedures include precautions and guidelines to be observed while operating the systems. In addition to crane operating procedures, PP&L has developed special handling procedures for major heavy loads. Such procedures supplement the general crane operating procedure by providing additional precautions, and a safe load path for the unique load.

Generic safe load paths have been incorporated into the Reactor Building Crane .operating,.procedures. .Work instructions for specific lifts include the saf~ load paths for the particular. loads.

The safe load paths are recorded in "quality" procedures which fall under the auspices of AD-gA-101 "Procedure Program". The provisions of this procedure allow the implementation of a temporary change which involves signatures of the plant shift supervisor and one other member of the plant management prior to implementation and review by the plant operational Review Committee within

)4 days of the implementation of the change."

Specific procedures have been written for the following loads

1. Reactor wall shield plugs

2. Orywell head

3. Vessel head

4. .Steam dryer 13

5. Steam separator

6. 'Pool pates

7. Dryer/Separator pit shield plugs

8. Slot plugs

9. Vessel service platform

10. Vessel heat, insulation The reactor .bui lang .crane;operating .pnrcedur e HT-99"001 includes a generic safe load path and general instructions for miscellaneous loads not covered by specific instructions. Included in the general procedure will be the transport of the replacement fuel racks, the crane load block and plant equipment.

Written procedures for the handling of the Spent Fuel Shipping Cask, and the Waste and Debris Cask have not yet been prepared since the casks have not yet been purchased.

S. EG8G Evaluation The applicant has prepared a list of the load handling procedures which have been written, In this list is also indicted these loads which are to be handled within the scope of the Reactor building crane operating procedures.

Generic safe load paths have been incorporated into the Reactor Building Crane operating orocedures.

The applicant has adequately addressed the requirements of this guideline.

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~ 5 C. EGKG Conclusions and Recommendations

'Based on "the information 'provided, 'EGKG concludes that SSES No. 2 meets the intent of guideline 2 of NUREG 0612.

2.3.3 Crane 0 erator Trainin Guideline 3 NUREG-0612 Arti cl e 5. 1. 1 3 I

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

'Overhead and Gantry Cranes'6j."

A. Summar of A licant's Statements The applicant states "We make no exceptions to ANSI 830.2-1976. The crane operator's training program was developed to meet the requirements of Chapter 2.3 of ANSI B30.2"1976 "Overhead and Gantry Cranes". A procedures has been written by plant staff mechanical maintenance section'o formalize the program and furnish the necessary forms to document the training. All crane operators are qualified to this procedure."

B. EGEG Evaluation

'Based on the applicant's statement the crane operator training program meets the intent of guideline 3 of NUREG 0612.

C. EGIG Conclusions and Recommendations Based on the information submitted, EG8G concludes that SSES No. 2 has met the intent of guideline 3 of NUREG 0612.

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2.3.4 Special Li ftin Devices Guideline 4 NUREG-0612, "Special lifting devices should satisfy the guidelines of ANSI N14.6-1978, 'Standard for Special Lifting Devices for Shipping Containers Neighing 10,000 Pounds (4500 kg) or Nore for Nuclear Haterials'7]. This standard should apply to all special lifting devices which carry heavy loads in areas as defined above. For operating plants, certain inspections and load tests may be accepted in lieu of certain material requirements'n the standard. In addition, the stress design factor stated in Section 3.2. 1. 1 of ANSI N14.6 should be based on the combined maximum static and dynamic loads that could be imparted on the handling device based on characteristics of the crane which will be used. This is in lieu of the guideline in Section 3.2. 1. 1 of ANSI N14.6 which bases the stress design factor on only the weight (static load) or the load and of the intervening components of the speci'al handling 'device."

A. Summar of A licant's Statements SSES No. 2 will employ the same special lifting devices which are used at Unit 1. Sling selec ions for loads which do not have special lifting devices will be governed by the same procedures as previously reviewed for Unit 1.

The applicant stated in his submittal for Unit 1 "Slings and Special Lifting Devices have not been procured for use at SSES except the strong back used for the RPV head and the

'lifting device for the dryer and separator.

These items have been designed and supplied by the NSSS vendor. Sufficient information is not yet available for determining full compliance with ANSI 830.9-1971: however the strong back for the RPV has been proof load tested to 125 tons, inspected by magnetic particle examination and used to move the RPV head for Unit 1, and the dryer/separator lifting device meets the proof loading requirements of ANSI 830.9-1971 and has been inspected by 16

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II O 0 magnetic particle examination. All other slings and/or lifting devices which wi11 handle heavy loads that could impact safety-rel'ated:equipment:or fuel wil"1 'be installed and used in accordance with guidelines of ANSI 830.9-1971.

In selecting the proper sling, the load used will be the sum of the static and the maximum dynamic load (SSE will not be included in the dynamic load imposed in the sling or lifting

~ device). The rating identification on the sling will be in terms of the "static load" which produces the maximum static and dynamic load. Mhere this restricts slings to use on only certain cranes, the slings will be marked as to the cranes with which they may be used. Special lifting devices

.to be .used-wi.th spent-fuel .shipping containers .will .be designed, installed, and used in accordance with the guidelines of ANSI N14.6-1978."

B. EGAG Evaluation SSES No.' will use the same special Lifting devices as used for SSES No. 1.

C. EG8G Conclusions and Recommendations SSES No. 2 will use the same lifting devices as used for SSES No. 1. Si:nce SSES No..J. 'i.s-in 'compl'i'ance with 'the intent of the guideline 4 of NUREG 0612, this compliance also applies for SSES No. 2.

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2.3.5 Liftin Devices Not S eciall Desi ned Guideline 5 NUREG-0612, Article 5.1.1 5 "Lifting devices that are not specially designed should be installed and used in accordance with the guidelines of ANSI B30.9-1971, 'Slings.'8]. However, in selecting the proper sling, the load used should be the sum of the static and maximum dynamic load. The rating identi fied on the sling should be in terms of the 'static load'hich produces the maximum static and dynamic load. Mhere this restricts slings to use on only certain cranes, the slings should be clearly marked as to the cranes with which they may be used.".

A. Summar of Ao licant's Statements

'The wppl'leant sta'tes-that '"the sling selection 'for 'loads which do not have special lifting devices will be governed by the same procedures as previously reviewed for SSES No. 1.." It is stated in reference 5, Section 2.3.5A for SSES No. 1 "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 installed and used in accordance with the guidelines of ANSI B30.9-1971. In selecting the proper sling, the load used will be the sum of the static and the dynamic load imposed on this sling or lifting device. The rating identification on the sling will 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 will be marked as to the cranes with which they may be used."

B. EG&G Evaluation PP&L indicates in reference 5 Section 2.3.5 B that the slings for general purpose rigging will be sized for a minimum 155 dynamic load. Tne information as presented in the submittal for this report and by reference 5 is

-sufficient 'to -cons'ider..~ha't:PP&L 'has met the intent 'of guideline 5 of NUREG 0612.

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4 C. EG&G Conclusions and Recommendations Based on the information. presented that '1'i'ftirrg d'evices '(Not Specially Oesigned) for SSES No. 1 will be same devices to be used at SSES No. 2, and since SSES No. 1 is in compliance with the values of this guideline, SSES 2 is considered to be in compliance with the intent of guideline 5 of NUREG 0612.

2.3.6 Cranes Ins ection Testin and Maintenance Guideline 6 NUREG-0612 Article 5.1.1 6 "The..crane .shoul.d be inspected, tested, and .maintained -in accordance with Chapter 2-2 of ANSI 830.2-1976, 'Overhead and Gantry Cranes,'ith 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 ior 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 PMR containment may only be used every 12 to 18 months during refueling operations, and is generally hot accessible during power operation. ANSI 830.2, however, calls for certain inspections to be performed daily or monthly. For such cranes having limited usage, the inspections, test, and maintenance should be performed prior to their use)."

A. Summar of Ao licant's Statements The applicant states "PP8L has developed a preventative main'te'nance program to include al'1'cranes and hoists. This program will include requirements for inspection, testing and maintenance in accordance with the guidelines of chapter 2-2 of ANSI 830.2-1976 with the exception that tests and inspections will 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.

The diesel building cranes (OH 501A, 8, C and 0) and the 19

reactor building crane (2H213) have been used during plant construction. The construction group has performed the necessary .itrspecting, testing, 'and 'maintenance requirements of Chapter 2-.2 ANSI 830.21967."

BE EG&G Evaluation The projected preventive maintenance program is in accordance with ANSI B30.2 1976 except that tests and inspections will be performed prior to use where it is not practical to meet the frequencies of ANSI B30,2 for periodic inspection and test, or where frequency of crane use is less than the specified inspection .and .test frequency. In .these inst aces the change in inspections frequencies is acceptable.

PP&L states that those cranes used for construction were inspected tested and maintained by the construction organization in accordance with ANSI 830:2-1967.

C. EG&G Conclusions and Recommendations Based on information provided, EG&G concludes that SSES No, 2 is in compliance with the intent of Guideline 6 of NUREG 0612.

2.3.7 Crane Oesi n Guideline 7 NUREG-0612 Article 5.1.1 7 "The crane should be designed to meet the applicable criteria and guidelines of Chapter 2-1 of ANSI B30.2-1976, 'Overhead and Gantry Cranes,'nd of CMAA-70, 'Specifications for Electric Overhead 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 sat i sf i ed. "

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A. Summar of A licant's Statements The applican states "Design requirements for th'ose cranes from which a load drop could impact safety related equipment or fuel, are in accordance with the Crane Manufacturers Association of America (CMAA) Specification 70 and ANSI 830.2. The reactor building crane (ZH 213) and the diesel building cranes (OH 501A, 8, C and 0) are designed in accordance with CMAA-70 class C and ANSI 830.2-1967. The monorail hoists are designed in accordance with ANSI 830. 16 and the jib crane in accordance with ANS! 830.2-1976 and CMAA-70.

B. EG&G Evaluation The applicant states that monorail hoists are designed in accordance with ANSI 830. 16. Guideline 7 states that 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. EGKG considers ANSI 830. 16 as an acceptable equivalent to ANSI 830.2.

C. EGKG Conclusions and Recommendations Based on the information reoei,ved, EG4G concl.udes that SSES No. 2 is in compliance with the intent of Guideline 7 of NUREG 0612.

2.4 Interim Protection Measures The NRC staff has established (NUREG"0612, Article 5.3) that six measures should be initiated to provide reasonable assurance that handling of heavy loads will be performed in a safe manner until final implementation of the general guidelines of NUREG-0612, Article 5. 1, is complete. Four of these six interim measures,consi.st of .general 21

~ 1 ~

Guideline 1, Safe Load paths; Guideline 2, Load-Handling Procedures; Guideline 3, Crane Operator Training; and Guideline 6, Cranes (Inspection, Testing, and'Maintenance). 'Th'e two -remaining i'n'terim measures cover the following criteria:

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

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

..2.4. 1 Interim .Protection Measure 1 Technical:S ecifi.cations "Licenses for all operating reactors not having a 'single-failure-proof overhead crane in the fuel storage pool area should be revised to include a specification comparable to Standard Technical Specification 3.9.7, 'Crane Travel - Spent Fuel Storage Pool Building,'or PWRs and Standard Technical Specification 3.9.6.2, 'Crane Travel,'or BWRs, to prohibit handling of heavy loads over fuel in the storage pool until implementation of measures which satisfy the guidelines of Section 5.1."

A. Summar of A licant's Statements Not applicable. Plant is not operational.

B. EG8G Evaluation Not applicable. Plant is not operational.

C. EGKG Conclusions and Recommendations Not applicable. Plant is not operational.

22

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 accomplished 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-0612j "

I A. Summar of A licant's Statements Summaries of applicant's 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.

B. 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.

2.4.3 Interim Protection Measure 6"-Special Review for Heav 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 should include the following for these loads: (a) 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; (b) visual inspections of load-bearing components of cranes, slings, and special lifting devices to identify flaws or deficiencies that could lead to failure of the component; (c) appropriate repair and replacement of defective components; and (d) verify that the crane operators have been properly trained and are familiar with specific procedures used in handling these loads, e.g., hand signals, conduct of operations, and content of procedures,"

23

A. Summar of A licant's Statements

'Not .applicable. -Plant 'is not operational.

8. EGKG Evaluation Not applicable. Plant is not operational.'.

EG8G Conclusion Not applicable, Plant is not operational.

24

3. CONCLUDING SUNi4IARY

-G.'-I A olicable Load-HamHin S stems

', The list of cranes and hoists supplied by the applicant as being

'subject to the provisions of NUREG-0612 is apparently complete (see Section 2.2. 1) .

3.2.,', Guideline Recommendations Compliance with the seven NRC guidelines for heavy load handling (Section 2.3) are satisfied at Susquehanna Steam and Electric Station,

,Unit 2. Thi.s .conclusion is represented in:tabular form as Table 3.1.

Specific recommendations to aid in compliance with the intent of these guidelines are provided as follows:

Guideline Recommendation

1. Section 2.3. 1 a. Consistent with guideline 1.

2. Sectior, 2.3,2 a. Consistent with guideline 2.

3. Section 2.3.3 ~

a. Consistent with guideline 3.

4. Section 2.3.4 a. Consistent with

'guideli:ne 4.

5; Section 2.3.5 a. Consistent with guideline 5.

6. Section 2.3.6 a. Consistent with guideline 6.

7. Section 2.3.7 a ~ Consistent with guideline 7, 25

>>.Ia'n,)'jaJ:l,,s ~,"s't>>'" ~~M<<;at~A'<<~~'<<a<<a .s'1 ~A~> ~ ~ <<'<<a oa<<<< . ~

" ~vws M>>s<<<<w wa 's.ssetIA1 ~ sne'a Isa '<<'<<a e>> ~ A I a ~ i * ~

~ ~

I'ADLE 3.1 SUSquEllnndns STEAH ELtCTRIC STATION Ukll' CWPLlnrlCE HATRIX

~ ~

Guide 1 ine Gui de 1 ine Guide I ine Guideline Guidel ine Guideline 'u idel ine I 2 3 4 S 6 7 Height or Crane Special C'rane Test Equipment Heavy Capacity Safe Load Operator Lifting and Crane nasljnatioo Loads Tons Paths Procedures ~lealaln Devices ~S>>tn s Sn~s est>>an ~least n

1. Refuelln g Oridge Crane Rot IZ>l ZOI Supplied IZII 203 (ZH 204

2. kecirulatlon Pump 24 Hoist IZH ZOb) a. Kecirulation pump 21,200 lbs

b. Recirculation pump stator ,21,860 Ibs

c. Rec irculat ion pump rotor 10,315 lbs

3. Equipment Access Door with Personnel Lock Hoist, IZH 206AJ Access Door 16 64,000 lbs (Z>l ZOoiI) 16

4. RHR liest Exchanges RIM Heat Exchanger Hoists 48,000 lbs (Zll 20@] 12 (Zll ZU&l) 12 HPCI RLIC t, Rill pump and turbine hoist

('hlZOgi a. Core spray pump 12 C C l

Hotor--6,330 1bs

b. Core spray pump Rotor--l,379 lbs

c. Core spray pump stator Z,T00 1bs

d. Core spray pump

7. Ilb lbs 26 a

n ew r! er 3 ' ~ h ~ 6 \4 e esp I v~'V "v>K w '-A 6 hhsl' '*e 'wer 444 fAIILt 3. 1 (continued]

Guideline Guideline Guide) ine Guideline Guideline Guideline Gdi de 1 inc 1 3 4 6 6 7 Weight or Crane Special Crane Test tquipment Ileavy Capacity Safe Load Uperator Lifting and ,Crane Desi nation Loads Tons Pnlhs prncennres ~Tralnln Oer lees ~Sl ln s ~lns eel Inn ~Iles' Icontidued) e. Iligh pressure coolant Injection pump--6,200 lbs

f. IIPC) Uooste pump 3,90U lbs

g. IIPCI gear reducer 1,2l)U )bs

h. IIPCI stop valve 2,900 lbs IIPC) turbine upper head case 7,500 lbs IIPC) turbine rotor 1,4UU lbs

k. Reactor core isolation cooling puTTy--5,275 lbs

l. Ileactor core isolation cooling turbine--3,490 lbs

m. Residual heat reTToval pump 20,650 )bs

n. Rial pump motor 10,020 lbs

o. kl8 pump rotor 4,690 lbs 27

's

~

6

~ 0's 4 ~ v <<n - 8 s n \. ns ' j ~ s s n-CNLf- 3,1 )continued)..

Guideline Guideline Guidel ine Gui de 1 inc Guideline Guideline Gusidel ine 1 2 3 4 5 6 7 Weight or Crane Special Crane Test tq Uns jIglpmentinn 1 s lleavy Loads Capacity Tons Safe Load Paths . Procedures Operator Tsnininsi Litting Devices ~Sinn s ~lns and nnsinn Crane

~Desi n 5~ (cont 'lnued) p. Rial puinp stator 6,970 lbs

6. Core sjiray pumps and a. kgCCW heat 12 kUCCW hj:at exchanges exchaiiger lloist (2ll 210) 24,715 lbs

b. Core spray pump 7,115 lbs

c. Core spray pump motor--6,330 lbs

d. Core spray pump rotor 1.379 lbs e Core spray pump stator-2,700 lbs

7. keactor Uuilding Crane (2II 213)

Aux ll iar Iloist a. Ilead holding pedestal 1,450 lbs

b. Dryer/Separator Sling-3,500 lbs

c. Stud Tensioner 1,500 lbs

d. Vessel head strong back 6,500 lbs

e. Jib crane 5,200 lbs

f. Ilatch Covers 6,000 lbs

a '<<Zvqei 44 l'i~~ C1." w ~ 4 <<~'c i '>>ea A~-C aa',nevi . el'n p Se S e as

" *~' eA H ~ i n inULE 3.1 (cont inued) ..

Guidel ine Guideline Guideline Guideline Guideline Guideline Guidel ine 1 2 3 4 5 6 7 Meight or Crane Special Crane Test fquipment Heavy ~ Capacity Safe Load Operator Lifting and Crane Ues R nation Loads Tons Paths Procedures Icaininri Oeeices ~S)in s ~los eccinn ~llesi n

7. (continued) g. Support beams 3,000 lbs nain Hoist 125 tons

a. Reactor cavity shield blocks 71.5-98.5 tons

b. Orwell head 104.5 tons

c. Reactor head isolation 18.2 tons

d. Reactor head 91.8 tons

e. Steam Dryer 40.0 tons

f. Steam separator 73.3 tons

g. fuel pool plugs 12.0 tons

h. Mater tight gates 3.0-4.5 tons

i. Equipment pool plugs 63.0 tons Reactor head carousel 15.0 tons

k. Service platform 6n5 tons

u. tquipment Shaf t Crane 24 tons C (2II 215J Hiscel 1 aneous 4,800 lbs gn 1'ruck Day Jib Crade (20 216 Hi seel 1 aneous 4,000 lbs

TAutt 3. I Icontinued)

Guideline. Guideline Guidelind Guide I ine Guideline Guide) ine Guideline 1 2 3 5 6 . 7 Meight or Crane Special Crane Test Equipasent Ileavy Capacity Safe Load Operator Lifting and Crane Oesi nation Loads Tons Paths Procedures ~srs InIn Oev ices ~S'I ln s ~lns nnl Inn ~llns I n

10. Reactor Building Hot C C C C Concrete Shielding Supplied Block Iioists (2II 2t8) Concrete Shield (2II 219) Blocks 20.000 lbs II. Floor plug tiot C lloist . Sup'pl i ed I lli XXX) a. Resin Bed Shield Covers 30,500 lbs

b. Gqulpment Access plugs 27,200 lbs

3.3 Interim protection evaluation of information provided by the applicant indicates

'G5G's

'that'~he following-ections ere"necessary to ensure that the six 'NRG staff measures for interim protection at Susquehanna Steam Electric Station, Unit 2 are met:

Interim Measure Recommendation Interim measures Not applicable were not addressed.

3.4 ~Summa@

Not applicable.

31

4. REFERENCES

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

2. V. Stello, Jr. (NRC), Letter to all applicants.

Subject:

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

3. USNRC, Letter to Pennsylvania Power 5 Light Company.

Subject:

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

4. N. M. Curtis (PP8L Co.) Letter to A. Schwencer (NRC)

Subject:

Susquehanna Steam Electric Station NUREG 0612 Unit 2 six-month response July 22, 1983 PLA-1752.

5. Control of Heavy Loads of Nuclear Power Plants Susquehanna Steam Electric Station, Unit 1, Phase I Oocket No. 50/387 by T. H, Stickley dated April;1983.

6. ANSI B30.2-1976, "Overhead ar,~ Gantry Cranes".

7. ANSI N14.6-1978, "Standard for Lifting Devices for Shipping Containers Meighing 10,000'Pounds (4500 kg) or more for Nuclear Materials".

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

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

32