ML20024A004

Control of Heavy Loads (C-10),TVA,Browns Ferry Nuclear Power Station,Units 1,2 & 3, Draft Technical Evaluation Rept

ML20024A004
Person / Time
Site:	Browns Ferry
Issue date:	04/05/1983
From:	Ahmed N, Bomberger C, Sargent I FRANKLIN INSTITUTE
To:	Clemenson F NRC
Shared Package
ML20024A000	List: ML20024A004
References
CON-NRC-03-81-130, CON-NRC-3-81-130, REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR TAC-07974, TAC-07975, TAC-08438, TAC-7974, TAC-7975, TAC-8438, TER-C5506-337-3, TER-C5506-337-338-33, NUDOCS 8306150266
Download: ML20024A004 (25)

Text

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TECHNICAL EVALUATION REPORT CONTROL OF HEAVY LOADS (c-10) . _ . _ _ _

TENNESSEE VALLEY AUTHORIT BROWNS FERRY NUCLEAR POWER STATION UNITS 1, 2, AND 3 L

NRC DOCKET NO. 50-259, 50-260, 50-296 FRC PROJECT C5506 NRC TAC NO. 07974, 07975, 08438 FRC ASS!GNMENT 13 NRC CONTRACT NO. NRC-03-81-130 FRC TASKS 337/338/339 Preparedby Franklin Research Center Author: C. Bomberger, N. Ahmed 20th and Race Streets Philadelphia, PA 19103 FRC Group Leader: I. H. Sargent Prepared for Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer: F. Clemenson .

April 5, 1983 l

i This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, appa-

ratos, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.

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s TER-C550 6-337/338/339 CONTEATS Section ~ Title Page 1 INTRODUCTION. . . . . . . . . . . . . . 1 1.1 Purpose of Review . . . . . . . . . . . 1 1.2 Generic Background . . . . . . . . . . . 1 1.3 Plant-Specific Background . . . . . . . . . 2 2 EVALUATION . . . . . . . . . . . . . . 4 2.1 General Guidelines . . . . . . . . . . . 4 2.2 Interim Protection Measures. . . . . . . . . 17 3 CO}CLUSION . . . . . . . . . . . . . . 20 3.1 General Provisions for Icad Handling . . . . . . 20 3.2 Interim Action . . . . . .' .- . . .. . . 21 4 REFERENCES . . . . . . . . . . . . . . 22 l

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TER-C5506-337/338/329 FORENORD This Technical Evaluation Report was prepared by Franklin Research Center under a contract with the U.S. Nuclear Regulatory Commission (Office of Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support of NRC operating reactor licensing actions. The technical evaluation was conducted in accordance with criteria established by the NRC.

Mr. C. R. Bomberger and Mr. I. H. SaIJent contributed to the technical preparation of this report through a subcontract with WESTEC Services, Inc.

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1. INTRODDCTION 1.1 PUR.OSE OF REVIEW This technical evaluation report documents an independent review of general load-handling policy and procedures at Tennessee valley Authority's Browns Ferry Nuclear Station Units 1, 2, and 3. This evaluation was performed with the following objectives: _

o to assess conformance to the general load handling guidelines of NUREG-0 612, " Control of Heavy Ioads at Nuclear Power Plants" [1],

Section 5.1.1 o to assess conformance to the interim protection measures of NUREG-0 612, Section 5.3.

1.2 GENERIC BACKGROUND Generic Technical Activity Task A-36 was established by the Nuclear Regulatory Commission (NRC) staff to systematically examine staff licensing criteria and the adequacy of measures in effect at operating nuclear power plants to ensure the aafe handling of heavy loads, and to recommend necessary .

changes in these measures. W is activity was initiated by a letter issued by the NRC staff on May 17, 1978 [2] to all power reactor licensees, requesting information concerning the control of heavy loads near spent fuel.

The results of Task A-36 were reported in NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants." @e staff's conclusion from this evaluation was that existing measures to control the hanaling 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 provided to control the, handling of heavy l loads, the staff developed a series of guidelines designed to achieve a l

two-part objective using an accepted approach or protection philosophy. te first part of the objective, achieved through a set of ge.aeral guidelines l

identified in NUREG-0612, Section 5.1 1, is to ensure that all load handling gy 4... Frank!in Research Center A Ows.on of The FrsQ 1%!dD _ _, . , .__

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4 TER-C550 6-337/338/339 cystems at nuclear power plants are designed and operated so that their

, , probability of failure is uniformly small and approgate for the critical ,

tasks in which they are employed. We second part of the staff's objective, cchieved through guidelines identified in NUREG-0612, Sections 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 (1) features are provided, in addition to those required for all load handling systems, to ensure that the potential for a load drop is extremely small- (e.g.', a single-failure-proof crane) or (2) conservative evaluations of load handling cccidents indicate that the potential consequences of any load drop are r ccceptably small. Acceptability of accident consequences is quantified in NUREG-0612 into four accident analysis evaluation criteria.

A defense-in-depth approach was used to develop the staff guidelines to ,

casure that all load handling systems are designed and operated so that their probability of dailure is appropriately small. Se intent of the guidelines is to ensure that licensees of all operating nuclear power plants perform the followings 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 sufficient operator training, handling system design, load handling instructions, and equipment inspection to ensure reliable l operation of the handling system.

t Staff guidelines resulting from the foregoing are tabulated in Section 5 of NUREG-0 612. Section 6 of NUREG-0612 recommended that a program be initiated to ensure that these guidelines are implemented at operating plants.

1.3 PLAIC-SPECIFIC BACKGROUND On December 22, 1980, the NBC issued a letter (3) to, Tennessee Valley Authority (TVA), the Licensee for Browns Ferry Nuclear Plant Units 1, 2, and 3, requesting that the Licensee review provisions for handling and control of heavy loads at Browns Ferry Units 1, 2, and 3, evaluate these provisions with respect to the guidelines of NUREG-0612, and provide certain additional I,d. Frank'iri Research Center

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TER-C550 6-337/338/33 9 information to be used for an independent determination of conformance to these guidelines. On June 3,1982, WA provided a response [4] to this request. Based upon this information, a draf t .'Itchnical Evaluation Report (TER) was prepared and informally transmitted to the Licensee for review and comment.

On October 28, 1982, a telel tone f conference call was held between the NRC and TVA to discuss the draf t TER. In response to this telephone call, TVA provided additional informa. tion on January 25, 1983 [5], which has been incorporated into this final TER.

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2. EVALUATION This section presents a point-by-point evaluation of load handling provisions at Browns Ferry Units 1, 2, and 3 with respect to NRC staff guidelines provided in NUREG-0612. Separate subsections are provided for both the general guidelines of NUREG-0612, Section 5.1.1 and the interim measures of NUREG-0 612, Section 5.3. In each case, the guideline or interim measure is presented, Licensee-provided information is summarized and evaluated, and a conclusion as to the extentrof compliance, including recommended additional cetion where appropriate, is presented. These conclusions are summarized in Table 2.1.

2.1 GENERAL GUIDELINES The NBC has established seven general. guidelines which must be met in crder to provide the defense-in-depth approach for the handling of heavy loads. These guidelines consist of the following criteria from- Section 5.1.1 of NUREG-0612:

o Guideline 1 - Safe Inad Paths o Guideline 2 - Ioad Handling Procedures o Guideline 3 - Crane Operator Training o Guideline 4 - Special Lifting Devices o Guideline 5 - Lifting Devices (Not Specially Designed) o Guideline 6 - Cranes (Inspection, Testing, and Maintenance) o Guideline 7 - Crane Design.

l These seven guidelines should be satisfied by all overhead load handling systems and programs used 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 Licensee's verification of the extent to which these guidelines have been satisfied and the evaluation of this verification are contained in the succeeding paragraphs;.

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gm y Capacity safe load Crane operator special Lifting Crane - Teet Technical Special

,? o Heavy toads Itons! rathe Proced.,ree Traintne Deelces Silnee and Inspection Crane Deelen Speelffcatione Attention N

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.In rrane 125/5 - -- C - -- C C = --

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• 3 a. Peactor Well 99.5 C C ~~ ~~ F -- -- == --

Q shield Blocks b rquipment 50 C C -- - P -- .- - --

tvol shield Plugs

c. Drywell Head 65 C C - 1 -- -- -- -- --

d. Reactor Head 105 C C -- I -- -- -- - C

e. Steam Dryer 45 'C C -- 1 - - - -- C Y f. Refueling Slot Shield 5.5 C C -- - P -- -- -- --

Flugs

g. Refueling 12 C C -- - F - - -- --

Canal rhleld

h. Mninture 70 C C -- I -- - - -- C, 3eparator i arv Head 4 C C -- - r -- -- --

4 Insulation 6

j. Skip Bon J.25 C C -- -- P -- -- -- --

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k. prv Service 7 C C -- = r -- -- -- --

Platform l f

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1. rautreent 1.5 C C -- -- F -- -- -- ta rnal covere o S

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-- = Hr>t appilcable. to I = Licensee han proesded insufficient information. 2 N

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35 weight Interin interla D- or culdeline 1 culdeline 2 culdeline 3 Outdeline 4 omidettne 9 h idellae 4 Ouldeline 7 neenere 1 Meaeore 5 N

g Heavy toads Capacity (t onal safe toad Fatha Procedures Crane operator Specist t.irting Training Devices Sllnee Crane - Test Techalcal 8 racial and Inspectlen Crane Deelen Speelficatione Attention a c.

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n. na seta 2.5 C C -- -- P - -- - -

O n. Tensioner I C C -- - P - - -- -

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o. Spent ruel 67 C C - - P - - C -

Cask

p. Surge Tank' 2.1 C C ~ - P - -- C --

Plug

q. For table Jib I C C -- - P -- -- C --

Crane 8

m r. New rue! 0.5 C C - - P -- - C - #

8 Asurabiles

s. ruel emt 2 C C -~ -- P - -- C ,.--

Cates  ;

t amw fue! 4.25 C C -- - P - -- C --

st or age ',}

vault Covers f .

u. mutu ocain 6 C C -- -- P C vault Pluge

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pend T. Control mod 9.5 C C - -- P -

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2. Self Propelled 1 -- -- C -- - C C -- -- gn Truck Crane O m

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a. menctor 1700lb C C - - P - - - -- W Ibstiding M r.,,a..t rana .

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Weight interin interla or ontdeline 1 m tdeline 2 caldeline 3 ontdeline 4 estdeline 5 ostdeline 6 estdeline 7 mesure 1 Measure 6 Capacity Safe load Crane Operator Special Lifting Crane - h et Technical Special -

guy toads Itons) _ rathe Frecedures Training Devicae Stings and Inspectica crane Deelge Speelfleettene Attention

c. Cof rump 24.35 C C - - P - == -- --

mtor e g d. Fire rumps 25 30 th C C -- -- P -- -- -- --

=4 8 e. RIIR Ser vice 1.7 C C -- == P = = -- --

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3. Hook Type Manual 4 -- -- C -- -- C C -- -

Chain Italet 1478 and 47C) I

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b. CpD Pump 1.25 C C - -- P - == -- '--

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2.1.1 overhead Heavy Load Handling Systems

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a. Summary of Licensee Statements and Conclusions " '

The Licensee's review of overhead load handling systems has identified the following handling systems to be subject to the criteria of NUREG-0612:

1 o ~ reactor building crane (Units 1, 2, and 3) o two-operator, self-propelled, full-revolving, truck-type, rubber-tired, diesel-powered truck crane (yard) r o 4-ton, hook-type, manual chain hoist nmits 1, 2, and 3)'.

Th's Licensee has also provided an extensive list of more than 100 overhead load handling systems which have been excluded on the basis that a load drop would not result in damage to any system required for plant shutdown or decay heat removal for one of the following reasons:

1. There is sufficient physical separation of the overhead handling system from any system or component required for safe shutdown or decay heat removal.

2. The system or component over which the load is carried is 'out of service while the load handling system is used. ,

3. The load weighs less than 1000 lb and is not considered to be a heavy load. This weight is a conservative estimate of a fuel assembly and its handling device.

In a subsequent submittal [5], the Licensee provided additional information to substantiate exclusion of the following:

o 3-ton iib crane: The Licensee made a commitment to initiate a design ch3nge report by June 1,1983 requiring a stop to be installed to prevent the 3-ton jib crane from swir.ging into the critical electrical panels within its area of coverage.

o 7.5-ton electric wire rope hoist: The Licensee confirmed that sufficient physical separation exists to preclude any safety impact on an 18-inch EECH header shown within the hoist area of coverage on drawings 47W200-6 and 47W200-13.

b. Evaluation and Conclusion The Licensee's exclusion of above-mentioned systems and numerous others from compliance with NUREG-0612 is acceptable on the basis of TVA's justifica-

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tions and additional commitment to incorporate a stop on the 3-ton jib crane to prevent its swing into the critical electrical-panels within its area of coverage.

2.1.2 gfe Icad Paths [ Guideline 1, NUREG-0612, Section 5.1.l(1)]

" Safe load paths should be defined for the movement of heavy loads to minimize the potential for heavy loads, if dropped, to impact irradiated fuel in the reactor vessel and in the spent fuel pool, or to ' impact safe shutdown equipment. The path should follow, to the extent practical, structural floor members, beams, etc., such that if the load is dropped, the structure is more likely to withstand the impact. These load paths should be defined in procedures, shown on equipment layout drawings, and clearly marked on the floor in the area where the load is to be handled.

Deviations from defined load paths should require written alternative

, procedures approved by the plant safety review committee."

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a. Su :: mary of Licensee Statements and Conclusion The Licensee has stated that loads, safe load paths, and handling procedures for the reactor building crane are contained in Browns Ferry -

-Mechanical Maintenance Instruction (MMI) 119.

Safe load paths for the truck crane are shown in Browns Ferry drawings 37W300-1, 47W220-1, and 47W220-2.

The 4-ton manual chain hoist (47B/C) is used over hatches to remove various equipment from lower floors to the elevation-565 floor as shown on Browns Ferry drawing 44N330. When operating over the hatches shown on Browns Ferry drawings 47W220-6, -7, -13, and -14 during unit operation, the hoist must not lift heavy loads over the core spray pumps and piping.

In a subcequent submittal [5), the Licensee made a commitment to complete the following actions:

1. MMI-il9 will be revised by June 1,1983 to require the person in charge of each heavy load lift to walk the predetarmined load path for the . benefit of the crane operator and the flagman.

2. MMI-119 will be revised by June 1,1983 to require plant operational review committee '(PORC) approval for any deviation from a safe load path which will require a heavy load to be lif ted over spent fuel or functional safe shutdown equipment.

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x; I>eewings indicate that the Licensee has. identified. safe load paths for s 'the reacto2 building crane and safe load areas for the 24-ton truck crane and the Nrious hqists.AIn addition, these load, paths and areas are defined in plant procedures cedained in MMI-119. - t , ,

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accomplished by having,the person in charge of tne lift walk the predet' ermined load path to ensure that. the path is clear prior to the start of the lift.

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However, the Licensee sh'odid' ensure that the du' ties of the path walker and the flagman are clearly definedsin appcopriatA procedures, v

Further, the method prohaed to implement the review and approval of safe load path deviations is consistent with the intent of NUREG-0612.

c. Conclusion and Recommendations Browns Ferry Units 1, 2, and 3 comply with Guideline 1 of NUREG-0612' i l i l contingent upon Licensee verification that proposed changes in MMI-119 have  ;

l been acceptably implemented and that the duties of the flagman with regard to' l

I safe load handling are defined in appropriate procedures.

2.1.3 Load Handling Procedures (Guideline 2, NUREG-0612, Section 5.1.l(2)]

"Procedttres 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 load path; and other special precautions."

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a. Summary of Licensee Statements and Conclusions The Licensee ha.: stated that handling procedure.s for the reactor building

( crane are contained in MMI-119. Handling procedures for the truck crane will l

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TER-C550 6-337/338/339 be developed and implemented to meet the requirements of the interim guidelines delineated in NUREG-0612.- Administrative-controls for the 4-ton manual chain hoist will be invoked to ensure that safe handling operations are maintained over these hatches dcring unit operation. In a subsequent submittal, the Licensee made a commitment to incorporate administrative controls for the truck crane and the 4-ton manual chain hoist into MMI-119 by June 1,1983 and to provide the information on this change by June 30, 1983. ,

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b. Evaluation MMI-119 provides procedural controls consistent with NUREG-0612 for the movenent of heavy loads en the refueling floor by the reactor building crane.

Fur thM , the Licensee's commitment to iaplement administrative controls for the loads handled by the truck crene and the 4-ton manual hoist meets the intent of Section 5.1.l(2) of NUREG-0612.

c. Conclusion and Recommendation Browns Ferry Units 1, 2, and 3 comply with Guideline 2 of NUREG-0612 co'n tingent upon implementation of acceptable administrative controls for the truck crane and the 4-ton manual chain hoist.

2.1.4 Crane Operator Training [ Guideline 3, NUREG-0 612, Section 5.1.l(3)]

" Crane operators should be trained, qualified, and conduct themselves in accordance with Chapter 2-3 of ANSI B30.2-1976, ' Overhead and Gantry Cranes' [6]."

a. Sune.ary of Licensee Statements and Conclusions The Licensee has stated that qualification requirements for reactor building crane operators are in Browns Ferry Standard Practice BF 4.3, " Crane Operator Qualification and Authorization," which implements the requirements of ANSI B30.2-1976.

Operators for the truck crane are journeyman operators from the International Unit of Operating Engineer s, Incal 320. The Licensee stated in a subsequent submittal that, by June 1,1983, a review will be performed to 4

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l , TER-C550 6-337/338/33 9 determine compliance with ANSI B30.5 with regard to truck crane operator i

training .and qualification.

- ,. _._.__m Qualification of operators of hand-powered chain hoists is not required,

b. Evaluation Crane operator training, qualification, and conduct described in BF 4.3 is consistent with the intent of Section 5.1.l(3) of NUREG-0612. Further, although operator training outlined in ANSI B30.2-1976 is not required for er such handling systems as the truck crane and the 4-ton manual chain hoist, the Licensee should ensure that indoctrination and training covering Brcuns Ferry administrative controls for these load handling systems are in effect and that this program complies with applicable requirements of ANSI B30.5, " Crawler, Locomotive, and Truck Cranes", and ANSI B30.16, " Overhead Hoists (Underhung) ."

c. Conclusion Browns Ferry Units 1, 2, and 3 comply with Guideline 3 of NUREG-0612.

2.1.5 Soecial Lifting Devices (Guideline 4, NUREG-0 612, Section 5.1.1 (4)] -

"Special lif ting devices should satisfy the guidelines of ANSI N14.6-1978

[7 ] , ' Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 pounds (4500 kg) or More for Nuclear Materials. ' This standard should apply to all special lif ting devices which carry heavy loads in areas as defined above. For operating plants certain inspections and load tests may be accepted in lieu of certain material requirements in the standard. In addition, tne 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 (stactic load) of the load and of the intervening components of the special handling device."

a. Summarv of Licensee Statements and Conclesions The Licensee states daat all nuclear steam supply system special lif ting devices, cuch as the drywell/ reactor vessel head stronyback ar.d steam dryer and moisture separator lifting devices, were supplied by General Electric

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s TER-C550 6-337/338/33 9 Corporation (GE) and specified in terms of performance data rather than design ,

criteria. The Licensee is currently negotiating with_ GE for the review of these special lif ting devices. Such review. along with the Licensee's own review, will be completed by July 31, 1983.

Special lifting devices used with the reactor building crane that were designed by the Nuclear Engineering Branch, Division of Engineering Design (EN DES) are being analyzed using the guidelines of ANSI bl4.,6-1978 and ANSI B3 0.9-1979 and supplemented by Sections 5.1.l(5) of NUREG-0612. Results of this review will be submitted by July 31, 1983.

b. Evaluation Insufficient informotion has been provided to allow a determination of compliance with respect to Guideline 4. We Licensee should provide an evaluation concerning compliance with ANSI N14.6 for all special lifting device s. Further, in performing this evaluation, the Licensee should address

, the imposition of both static and dynamic loads when assessing design stresses.

The intent of Guideline 4, in addition to determining that special lif ting devices have been designed and f abricated in a manner consistent with .

high reliability, is also to make certain that appropriate steps are taken to ensura that these devices are inspected, tested, and maintained so as to ensure continued reliability. Guidance for a program to achieve the goal is contained in Section 5 of ANSI N14.6.

c. Conclusion and Recommendation It cannot be determined if Guideline 4 of NUREG-0612 is satisfied at Browns Ferry Units 1, 2, and 3. We Licensee should provioq a design comparison of the special lif ting designs relative to the criteria in ANSI N14. 6-197 8. Further, the Licensee should implement a continuing compliance testing program for special lifting devices in accordance with Section 5 of ANSI N14.6 prior to the~ next use of these devices.

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2.1.6 Lif ting Devices (let Specially Designed) (Guideline 5, NUREG-0 612, section 5.1.l(5)1

" Lifting devices that are not specially designed should be installed and used in accordance with the guideline 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. ' Die rating identified on the sling should be in terms of the ' static load' which produces the maximum static and dynamic load. Were this restricts slin9s to use on only certain cranes, the slings should be clearly marked as to the cranes with which they may be used."

c. Surmary of Licensee Statements and concitsione The Licensee states that all slings used with load handling systems cubject to NU1GXN)612 criteria are inspected and tested in accordanca with l

Browns Ferry MMI-102 (Rigging Equipment Program) which implements the requirements of ANSI B30.9-1971. With regard to the guideline criteria that slings should be selected and marked with rated loads based on maximum static and dynamic loads, the Licensee indicates that a review is already under way and that results of such , review.will be submitted by July 31, 1983.

.b. Evaluation Browns Ferry Units 1, 2, and 3 satisfy the requirements of this guideline to a large degree on the basis that current procedures implement the require-ments of ANSI B30.9-1971. Review of these procedures, however, indicates that selection and marking of slings are not based upon the maximum static and l dynamic loads which may be experienced by the particular sling. 'Io fully satisfy this guideline, the Licensee should (1) select and mark slings on the basis of the maximum static and dynanic loads or (2) demonstrate that dynamic l loads that are generated for the crane speeds in question constitute a reasonably small percentage when compared with static loads. The latest submittal indicates that selection and marking of slings are being reviewed  !

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c. Conclusion and Recommendation

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Browns Ferry Units 1, 2, and 3 ' parti ~ ally compDj~with this guideline. 'Io fully comply, the Licensee should verify that slings are selected a.d marked with rated loads based on the maximum static and dynamic loads.

i 2.1.7 Cranes (Insoection, 'Iwsting and Maintenance) [ Guideline 6, NUREG-0 612, t Section 5.1.1. (6)]

"2e crane should be inspected, tested, and maintained in accordance with Chapter 2-2 of ANSI B30.2-1976, ' Overhead and Gantry Cranes,' with the exception that tests and inspections should be performed prior to use where it is not practical to meet the frequencies of ANSI B30.2 for periodic inspection and test, or where frequency of crane use is less than the specified inspection and test frequency (e.g., the polar crane inside a PWR containment may only be used every 12 to 18 months during refueling operations, and is ~ generally not accessible during power ,

operation. ANSI B30.2, however, calls for certain inspections to be performed daily or monthly. For such cranes having limited usage, the inspections, tests, and maintenance should performed prior to their use.)" -

a. Summary of Licensee Statements and conclusions L

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The Licensee has stated that inspection, testing, and maintenance  ;

requirements for the reactor building crene are contained in Browns Ferry i MMI-117, which implements the requirements of ANSI B30.2-1976.

ANSI B30.2-1976 is not applicable for inspection, testing, and .

maintenance of the truck crane. mese requirements are imposed by ANSI f

B3 0. 5-196 8 (Crawler, Incomotive, and Truck Cranes), and implemented in Browns

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i Fer ry MMI-13 0. Periodic inspections are performed by the TVA Power Services l

l shop crane inspection team in accordance with the requirerents of MMI-130.

i Inspection and test requirements for the 4-ton manual chain hoist are contained in Browns Ferry MMI-102 which complies with ANSI B30.16-1973,

" Overhead Hoists (Underhung)."

In a subsequent submittal, the Licensee stated that:

i o Browns Ferry electrical maintenance instruction EMI-2 currently provides an adequate electrical checkout of the reactor building crane I

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o mpe reeving diecks are currently required in frequent. inspections by Division Procedure Manual DPM N74M15. Browns Ferry MMI-ll7 will be

., revised to reflect this requirement by June 2 1 1983.

b. Evaluation ,

Crane inspection, testing, and maintenance at Browns Ferry Units 1, 2, and 3 are consistent with the guidance in NUREG-0612 in that MMI-ll7 is based on ANSI B30.2-1976. The Licensee has indicated that MMI-ll7 is being revised to incorporate frequent inspection requirements for rope reeving and that  !

I' olectrical checkout of the reactor building crane is adequately covered by DtI-2.

In addition, the use of ANSI B30.5 and ANSI B30.16 inspection, testing, cnd maintenance requirements for the yard crane and the 4-ton manual chain hoist meets the intent of NUREG-0612.

c. Conclusion and recommendation

. Browns Ferry Units 1, 2, and 3 comply with Guideline 6 of NUREG-0612

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based on the Licensee's verification of compliance with ANSI B30.2,' ANSI B30.5, and ANSI B30.16. .

2.1.8 Crane Design [ Guideline 7, NUREG-0612, Section 5.1.l(7)]

"'Ibe c:ane thould be designed to meet the applicable critoria and guidelines of Chapter 2-1 of ANSI B30.2-1976, 'Ovarhead and Gantry Cranes' and of CMAA-70, ' Specifications for Electric Overhead Traveling Cranes' [9] . An alternative to a specification in ANSI B30.2 or CMAA-70 may be accepted in lieu of specific compliance if the intent of the specification is satisfied."

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E. Summary of Licensee Statements and Conclusions The Licensee has stated that a review of the reactor building crane design indicates that the crane meets the requirements of CMAA-70 (1975) and ANSI B30.2.

The truck cr itne was not analyzed in accordance with CMAA-70 and ANSI B30.2 because these standards address the design of multiple girder, overhead, LC Franklin Research Center A Desen of The Franda hat. nee

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e , o TER-05506-337/338/339 and gantry cranes. Purchase specifications of this crane required that all

, - applicable parts of ANSI B30.5-1976.be met._ .._ ,_ _ _

b. Evaluation Crane design for the Browns Ferry reactor building crane and the yard truck crane meets the intent of NUREG-0612 based on compliance to CMAA-70/ ANSI B30.2 and ANSI B30.5, respectively.

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c. Conclusion Browns Ferry Units 1, 2, and 3 comply with Guideline 7 of NUREG-0612.

2.2 INTERIM PROTECTION MEASURES The NBC has established six interim protection measures to be implemented at operating nuclear power plants to provide reasonable assurance that no heavy loads will be handled over the spent fuel pool and that measures exist to reduce the potential for accidental. load drops to impact on fuel in the -

core or spent fuel pool'. Four of the six interim measures of the r'eport are Guideline 1, Safe Ioad Paths; Guideline 2, Ioad Handling Procedures; Guideline 3, Crane Operator Training; and Guideline 6, Cranes (Inspection, Testing, and Maintenance) . The two remaining interim measures cover the following criteria:

1. Heavy load technical specifications

. 2. Special review for heavy loads handled over the core.

The status of the Licensee's implementation and the evaluation of these interim protection measures are summarized in the succeeding paragraphs of this section.

2.2.1 Technical Soecifications (Interim Protection Measure 1, NUREG-0612, Section 5.3 (1))

" 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,' for PWR's and Standard

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'Itchnical Specification 3.9.6.2, ' Crane Travel, ' for BWR's, to prohibit handling of heavy loads over fuel in the storage pool until implementa-

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tion of measures which afatisfy the guidelinesrof Section 5.1."

, n. Evaluation Review indicates that Browns Ferry Technical Specifications Section 5.5.C z

prohibits loads in excess of 1000 lb from being carried over spent fuel in the cpent fuel pool. .

b. Conclusion Browns Ferry Units 1, 2, and 3 comply with this interim protection measure.

2.2.2 Administrative Controls [ Interim Protection Measures 2, 3, 4, and 5,

_UREG-0 N 612, Sections 5.3. (2)-5.3 (5) }

" Procedural or administrative measures [incleding 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 i

Section 5.1 of [NUREG-0 612] ."

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a. Summary of Licenses Statements and Conclusions Summaries of Licensee statements and conclusions are contained in discussions of the respective general guidelines in Section 2.1.2, 2.1.3, 2.1. 4, and 2.1.7.

b. Evaluations, Conclusions, and Recommendations Evaluations, conclusions, and recommendations are contained in discussions of the respective general guidelines in Sections 2.1.2, 2.1.3, 2.1. 4, and 2.1.7. .

2.2.3 Special Reviews for Heavy Ioads Over the Core [ Interim Protection j; Measure 6, NUREG-0612, Section 5.3 (6) }_

"Special attention should be given to p:ocedures, equipment, and personnel for the handling of heavy loads over the core, cuch as vessel h.) Frenk!in Research Center a %. a n. r . wow.

TER-C550 6-337/338/339 internals or vessel inspection tools. Tnis special review should include the following for .these loads: (1) review of procedures for installation of rigging or lif ting devices and movement of the load to assure that sufficient detail is provided and that instructions are clear and concis e; (2) 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; (3) appropriate repair and replacement of defective components; and (4) 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."

a. Summary of Licensee Statements and Conclusions The Licensee stated that a special review for this interim measure was performed during the implementation of interim guidelines for the reactor building crane and is currently in MMI-119. ,

b. Evaluation and Conclusion Browns Ferry Units 1, 2, and 3 comply with the criteria of Interim

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Protection Measure 6 on the basis of the Li'censee's verification that specific requirements are completed. .

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4'"l. Franklin Research Center

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. TER-C550 6-337/338/339

3. CONCLUSION

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This summary is provided to consolidate the results of the evaluation contained in Section 2 concerning individual NRC staff guidelines into an i

overall evaluation of heavy load handling at Browns Ferry Units 1, 2, and 3. l t

Overall conclusions and recommended Licensee actions, where appropriate, are i

1 l provided with respect to both general provisions for load handling 1

! (NUREG-0612, Section 5.1.1) and completion of the staff recommendations for '

interim protection (NUREG-0612, Section 5.3) .

l 3.1 GENERAL PROVISIONS FOR IDAD HANDLING ,

! The NRC staff has established seven guidelines concerning provisions for .

i handling heavy loads in the area of the reactor vessel, near stored spent fuel, or in other areas where an accidental load drop could damage equipment i required for safe shutdown or decay heat removal. 'Ihe intent of these guidelines is twofold. A plant conforming to these guidelines will have

,- developed and implemented, through procedures and operator training, safe load l

! travel paths such that, to the maximum extent practical, heavy loads are not .

carried over or near irradiated fuel or safe shutdown equipment. A plant conforming to these guidelines will also have provided sufficient operator training, handling system design, load handling instructions, and equipment inspection to ensure reliable operation of the handling system. As detailed in Section 2, it has been found that load handling operations at Brownc Ferry i Units 1, 2, and 3 can be expected to be conducted in a highly reliable manner consistent with the staff's objectives as expressed in these guidelines. A need for further Licensee action, however, was identified in the following areas:

l o Develop a program consistent with ANSI N14.6, Section 5 to maintain the assurance of reliability of special lif ting devices.

l o Complete the assessment of the design of special lif ting devices in comparison with sections of ANSI N14.6-1978.

Verify that slings are selected and marked with rated loads based on j c

the maximum static and dynamic loads.

l 000 Franklin Research Center m.onatm n.sen.u.

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TER-C550 6-337/338/339 3.2 INTERIM ACTIONS The NRC staff has estab .ished (NUREG-0612, Section 5.3) certain measures

- that 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, Section 5.1 is complete. Specified measures include the implementation of a technical specification to prohibit

., the handling of heavy loads over fuel in the storage pool; compliance with Guidelines 1, 2r 3, and 6 of NUREG-0612, Section 5.1.1; a review of load handling procedures ard operator training; and a visual inspection program, including compor. int repair or replacement, as necessary, of cranes, slings, and special lif ting devices to eliminate deficiencies that could lead to component failure. Evaluation of information provided by the Licensee indicates that these actions either have been satisfactorily implemented er will be implemented in a timely manner at the Browns Ferry plant.

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4. REFERENCES'

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1. " control of Heavy Loads at Nuclear Power Plants" NRC, July 1980 NUREG-0 612

2. V. Stello, Jr. (NRC)

Letter to all Licensees

Subject:

Request for Additional Information on Control of Heavy Icads Near Spent Fuel '

i May 17,1978 ,

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3. NBC

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Letter to Tennessee Valley Authority

Subject:

Request for Review of Heavy Ioad Handling at Browns Ferry l_ Nuclear Plant Units 1, 2, and 3 l December 22, 1980 l

4. D. S. Kammer (TVA) -

IAtter to D. B. Vassallo (NRC)

(

Subject:

Control of Heatry Icads l

June 3,1982 l

l S. D. S. Kansner (TVA)

Letter to D. B. Vassallo (NRC)

Subject:

Control of Heavy Ioads January 25, 1983

6. American National Standards Institute

" Overhead and Gantry Cranes" ANSI B3 0.2-19 76

7. American National Standards Institute

" Standard for Special Lif ting Devices for Shipping Containers Weigning 10,000 pounds (4500 kg) or More for Nuclear Materials" l ANSI N14.6-1978

8. American National Standards Institute l " Slings" ANSI B30.9-19 71

9. Crane Manufacturers Association of America,1975

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

f ELD Franklin Research Center A We on o'The Frs%n answie

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