ML19344A881

Forwards Response to 780612 Ltr Re Task Action Plan for Category a Technical Activity A-36, Control of Heavy Loads Near Spent Fuel.

ML19344A881
Person / Time
Site:	Indian Point
Issue date:	07/14/1978
From:	Early P POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Schwencer A Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR IPO-129, NUDOCS 8008220460
Download: ML19344A881 (14)

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D POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLUMaus CIRCLE NEW YORx. N. Y.10019 (212) 397 4200

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CMIEP ENGINEER FC ERICK R. CLARK MANa

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CELCCE L. INGALLS CO WN.a EL E R=4 E N E R AL VtCE CMAIAMAN WIk"",,  ;,f,R,OTNeN S,E AL f.fCH ARD M. FLYNN M AN AGE R.FNGINE $ AING CECORT t. MILLONZl JOHN W. BOSTON WILLIA M F. LtJDDY reaaa oes=atioN.

July 14, 1978 THO M AS IPO-129 C,R,AN N. JR.

Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission THIS DOCUMENT CONTAINS Washington, D. C. 20555 POOR QUAUTY PAGES Attention: Mr. Albert Schwencer, Chief Operating Reactors Branch No. 1 ,

Subject:

Indian Point 3 Nuclear Power Plant Control of Heavy Loads Near Spent Fuel

_ocket No. 50-286 _

Dear Mr. Schwencer:

In response to your letter dated June 12, 1978, regarding the Task Action Plan for Category A Technical Activity No. A-36, " Control of Heavy Loads Near Spent Fuel", we are enclosing the requested information as an attachment to this letter. j i

Should you or any of your staff require additional information, l we would be pleased to provide it.

Very truly yours, i 1

4 Paul J. Early 1 Assistant Chief Engineer-Projects l

Att.

cc: Hon. George Begany White Plains Public Library b

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ATTACHMENT

1. Question: Provide a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the refueling floor.

Response: We are enclosing the following drawings:

1) A202079 - Containment Building General Arrangement Section "B-B".

2) A202081 - Containment Building Refueling Equipment Laydown & Storage Plan.

3) A202086 - Fuel Storage Building General Arrangement Plans & Elevations.

2. Question: Provide a list of all objects that are required to be moved over the reactor core (during refueling) , or the spent fuel storage pool. For each object listed, provide its approxi-mate weight and size, a diagram of the movement path utilized (including carrying height) and the frequency of movement.

Response: The reactor vessel head, core components and tools required for the placement or removal of core components will be handled over an open reactor vessel.

Frequency Carrying of Movement Height Est. Weight During Above Size Re fueling RV Flange Component (lbs)

See response to 2 35' Reactor Head Q 9.27(b) 1& 2 of FSAR.

See response to 2 15' Uppe r.

Inte rnals Q 9.27 (c) 1 of FSAR Lifting ditto 2 30' Rig .

r Frequency Carrying of Movement Height Est. Weight During Above Re fueling RV Flange Component (lbs) Size 230 506"Hx18"D 2 12' Specimen Handling Tool 235 353"Lx12"D 16 15' Thimble Plug Handling Tool 1500 160"Hx8.5"W 400 6' Fuel Assemblies Spent Fuel Pool 364"Lx12"D 130 Below pool Spent Fuel Tool 352 surface 800 396"Lx15"D 90 BPRA Tool Thimble Plug 235 353"Lx12"D 16 Handling Tool 1500 160"Lx8.5"W 320 Fuel Assemblies The transfer path of the reactor vessel head and the upper internals is from the reactor vessel to their respective storage locations and back , as shown on the enclosed drawings.

3. Question: What are the dimensions and weights of the spent fuel casks that are or will be used at your facility?

Response: At the present time the design is based on the use of a 40 ton cask when fully loaded. The spent fuel storage capacity of the Indian Point 3 spent fuel pool has been increased from Z<4 to 840 assemblies. This increased capacity would provide storage space for all spent fuel discharged until 1990 (with full core reserve). A decision on the type and capacity of the spent fuel shipping cask will be made in the future. l

4. Question: Identify any heavy load or cask drop analyses per-formed to date for your facility. Provide a copy of all such analyses not previously submitted to the NRC s taff.

Response: Section 9.5.3 of FSAR identifies a cask drop analysis and lists the assumptions made in the analysis.

1) The drop is assumed to be from the cask's highest position which is 5 feet above the water surface.

2) The cask is fully loaded and weighs 40 tons.

An analysis is also presented in Section 14.2 of the FSAR concerning damage to one complete outer row of fuel elements in an assembly, assumed as a conservative limit for evaluating environmental consequences of a fuel handling incident.

Section 9.1.4 of SER refers to results of calculations pro-vided by the licensee to verify that the shear stress of all supports and piping would not be exceeded if heavy objects like shield plugs, reactor vessel head or upper internals were dropped a onto the reactor vessel.

5. Question: Identify any heavy loads that are carried over equip-ment required for the safe shutdown of a plant that is operating at the time the load is moved. Identify what equipment could be affected in the event of a heavy load handling accident (piping, ,

cabling, pumps, etc.) and discuss the feasibility of such an Describe the basis for your accident affecting this equipment.

conclusions.

l Response: There are no heavy loads moved over operating equip- I ment required for the safe shutdown of the plant.

1

6. Question: If heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at your facility, discuss the feasibility of a handling accident which could result in water leakage severe enough to uncover the spent fuel. Describe the basis for your conclusions.

Rosponse: This is discussed in Section 9.5.3 of FSAR which analyzes the consequences of a cask drop incident. The result o2 the analysis indicate that very little water will be lost from the pit and under no conditions will the fuel be uncovered.

7. Question: Describe any design features of your facility which affect the potential for a heavy load handling accident involving spent fuel, e.g., utilization of single failure-proof crane.

Response: The design features are covered in response tc FSAR questions 9.14.3, 9.14.5 and 9.14.6. In the future the type and capacity of the spent fuel pool bridge crane will be determined consistent with the choice of the cask.

8. Question: Provide copies of all procedures currently in effect l at your facility for the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or equipment required for the safe shutdown of a plant that is operating at the time the move occurs.

Response: The following procedures which are currently in effect are included with this response: ,

1) SOP-CM-2, Rev. 1 - Fuel Storage Building Crane Operation j

2) SOP-CM-1, Rev. 0 - Polar Crane Operation l

9. Question: Discuss the degree to which your facility complies with the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Revision 1, December, 1975) regarding Spent Fuel Storage Facility Design Basis.

Response: Compliance to the eight regulatory positions delineated in Regulatory Guide 1.13 (Revision 1, December 1975) is fully discussed in the response to Question 9.14.1 of FSAR.

POWER AUTHORITY OF T81E STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT F '

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SOP-CM-2 Rev. 1 i FUEL STORAGE BUILDING CRANE OPERATION D

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SOP-CM-2 s ion

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Fuel Storage Building Cran _e_Operat 1.0 Intent tion of the Fuel" Storage To provide a procedure for the opera Building Crane.

2.0 Precautions and Limitations d by Technical Specifi-The following requirements are impose 2.1 d over any region cations: ,

j Thespentfuelcakh)shallnotbemove ruel pit which contains irradiated fuel. fu 2.1.A of the spent if the spent h ll be moved ' j Additionally, fuel, no loads in excess of fuel 2,000 pounds s a pit.

over any region of the spent irradiated fuel Hoists or cranes utilized in handlingl movement for thisbegins. i },

2.1.B shallload The be.deadload assumed by tested the hoists before fue maximum load orhcranesthe i during the fuel l

test must be equal to or greater t anto be f i a

/"N handling operation.the hoists or cranes shall be made a ter test and prior to fuel handling. authorization to fuel pit, When irradiated fuel is in the spent h d crane may be i

2.2 remove the mechanical stops on thed over ea However, the crane t in use. The lock t

granted by the Operations iSuperinten en . contro of the Shift Superviscr.Jl may be removed only under the author tyll be moved over the No loads greater than 2,000 pounds shald not be left sus All loads assumed by the Crane shou 2.3 when the crane is left unattended. h main hook 40 tons, 2.4 Do not exceed. maximum rated loads of t e and auxiliary hook 5 tons.

I ipulate the controls j i ds.

2.5- Only aLqualified crane operator may manof the 3.0 Initial Conditions he crane.

MCC-37 is energized to supply power tott fuel it must ~

3.1 js If the crane is'to be used to handle spen t and inspection 3.2 have successfully completed a dead load tes refueling period.

for the current

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4.0 Procedure r% -4.1 Startup 4.1.A Ensure that the pendant control switch is turned off.

4.1.B Close the disconnect switch on MCC-37 for the Fuel Storage Building Crane.

4 .- l . C Close the power disconnect switch for the Fuel Storage Building Crane located on the FSB 95 ft, elevation.

4.2 Operation 4.2.A Depress the pendant control ON switch.

4.2.B There are two speeds for each direction of crane hoist, Trolley and Bridge movement. A short time interval (several seconds) should be allowed between low and high speed switching to permit the motor to pick up speed before actuating the high speed contactor.

4.3 Shutdown 4.3.A Move crane to position over the Truck Bay.

4.3.B Depress the pendant control OFF switch.

/*' 4.3.C Open the power disconnect switch at the FSB 95 ft.

elevation.

4.3.D Open the disconnect switch on MCC-37 for the Fuel Storage Building Crane.

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POLAR C.:A.;E OPERATION '

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o p:ccide a procedure for the cperation of the Polar Crane.

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2.2 O n lv. a c.ua'_ifiad crane crerator may manipulate the controls .

I of the crane (see GAD-TR-8).  !

2.3 -ior to any critical lift (i.e. Reactor vessel Head, Lower In ernals, Upper Internals) the crane and cables will be inspected for structural defcct and cable wear.

I 2.' Trior to refueling operation the' colar crane and manipulator  :

will be given an Interlock Test.

2.5 t'.e rails are Eefore

_ree : _crane cr a _1

. b-idge c.estructicnsmcVerentinensure t.ne cesirac that . area of movemen.

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2.6 W.en roving icads to and frcn the rcactor vcesel the crane c pe r:2 tor s h:.u? d re::.erber tha t the crane track is not con-c<_ntric .ith the Ecartor Vessel but off,et to the east .

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2.7 At nc tire thculd the polar crane hocks be allowed to i c l.o ra te un dc;wa ter .

i C. c.ne I n.cr: cation status shoulc. be chec.tec .r.e: ore use i

..c i after pcwer operaticn as excessive heat in containment l

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310 Znitiai Conditions 3.1 MCC-38 available te supply power to-the polar crane.

3.2 Prior to use in fuel handling the polar crane' interlocks have been tested according to 3PT-RP --;8 as specified in the' Technical 5.0ecifications. .

4.0 Instructions-1 4 . l' startup

-4.1.A. Ensure that the crane pendent control switch is in

.the "OFF" position.

4.1.B Close the supply breaker on MCC-38 for the polar crane (elevation 68' in containment).

4.1.C Place the crane interlock defeat selector switch (located .

adjacent to MCC-38 on elevation 68') to the "OFF" pos- l ition - the red indicating lamp should be lit. This  !

will place the interlock in service permitting crane ooeration.

i 4.1.D C1cse the power disconnect cwitch for the polar crane i I

to ON (located on containn.ent 95' : '. eva ti on , crane leg).

l l 4.2 Grerstien  !

4.2.A Place'the pendent control switch to the "ON" position.

4.2.S Usine the accrocriate bridce or trolle'v Lushbuttons ocsition tn.--e crane hoor.,over cesirec location.

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1 J 8 4.2.C McVe the r.ain hoist pushbutton in the uo or down direction '

as recuired.- 1  ;

NOTES: 1) In the hoist directicn-the drive brake ._11 .

release and slow hoisting speed will oe pro- '

vicec inccpencent of .noen a,cac. -

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master switch is further depressed, hook .

speed will increase steplessly in response

, to the master switch position At the end ,

of the r,.: ster pushbutton tra el, the drive will accelerate to maximum '.cist speed.

2) The drive can be decelerated by motor braking -1 1

'a t any time by returning the master push- '

button to a slower speed position.

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3) 'In the icwer direction, the brake releases and the lowering' speed obtained will be stepless and dependent on master pushbutton position. At the end of the master push-button travel, the hook will accelerate'to the maximum lowering speed. .

. 4) 'The drive will cuicki. 6 >celerate by motor

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braking C.en the master pushbut cn is ret-urned to a lower cp _ .'d e tep .

5) Moving the master switch from any position b to CFF will remove vcitage from the motor,

.and will also de-energize the brake relay i- thereby setting the brake and stopping the crive.

4.3 Critical Lift i

The critical lift selector switch is used when it is des-1 1 rec to operate the crane _at low speeds for critical loads

-(i.e. lifting R.V. Head, Lower Internals and Upper Internals).

Cperaticn is the same as normal operation except that the a

mcxraum. speed of the hoist is approximately 20% of normal f Speed. ,

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The-float circuit enables the cperator to float a load or i te raise.or-]cwer the load at verv. low speeds. When the FLOAT pushbutton is depressed, the brakes are released and the. speed of-the hoist is controlled by the FLOAT ADJUST

, .rotentiemeter. The setting of FLOAT ADJUST will depend upon the load on the hook.

l' CAUTION i

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I; hen ic.erinc a' load it is. advisable to calibrate the float

• f circuit at a peint well free of any cbstructions until the I c a:. :. cats, then move over to posi ion anc Iloat the loac.

down into; place.

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the OVEF.tiEAT- OVS?.IDE push'rutton on the per' dint.

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Ocerheat ccerride should bc used oniv durinc coerations - - -

vhere continuec movemen: 1s critical or necessary.

4.6 Shutdcwn 4 . 6 . .; Flace the pendant control switch to "OFF".

4.E.3 Open the power disconnect switch for the polar crane. .

"ON".

4.6.C Flace the crene interlock dafeat selector to This will prevent crane operation. I i

4.E.D Cpen the crane supply breaker in MCC-38.

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