ML20077H211

Forwards Drawings of Individual Load Paths for Removal & Insertion of Each Spent Fuel Storage Rack

ML20077H211
Person / Time
Site:	Fort Calhoun
Issue date:	08/01/1983
From:	William Jones OMAHA PUBLIC POWER DISTRICT
To:	Clark R Office of Nuclear Reactor Regulation
References
LIC-83-180, NUDOCS 8308090661
Download: ML20077H211 (10)

Text

_ _ - - - -

1 Omaha Public Power District 1623 Hamey Omaha, Nebraska 68102 402/536-4000 August 1, 1983 LIC-83-180 Mr. Robert A.

Clark, Chief U.

S.

Nuclear Regula tory Commission Of fice of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.

20555

Reference:

Docke t No. 50-285

Dear Mr. Clark:

Spent Fuel Storage Rack Modification In Omaha Public Power District's letter to the Commission, i

dated April 29, 1983, the District stated that it would pro-vide the Commission with drawings of the individual load paths for removal and insertion of each spent fuel storage rack.

These drawings are included as part of the attached I

procedure description for the removal of the old racks and installation of the new racks.

The procedure summary and preliminary load path provided as Appendix A of the revised licensing submittal, dated January 21, 1983, were modified to incorporate a load path for removal of the existing racks to the decontamination room area.

The differences between the draft procedure summary and this final procedure summary are denoted by vertical bars in the margins.

Sia

rely, i

W.

C Jones

)

Diviyion Manager l

Production Operations WCJ/DJM:jmm Attachment cc:

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D.C.

20036 Mr.

E.

G.

Tourigny, Project Manager Mr.

L.

A.

Yandell, Senior Resident

/ [)d7!

l Inspector 1

[

8308090661 830801 Murnen5NFNa#fe p rturnty d'2d l

PDR ADOCK 05000285 P

P@CG

Attachment SAFE LOAD PATH FOR REMOVAL AND INSTALLATION OF SPENT FUEL POOL RACKS

.I.

INTRODUCTION The District is planning to replace the existing spent fuel pool racks with high density racks in 1983.

The existing racks will be removed from the spent fuel pool, decontaminated and shipped off-site.

New high density racks will be moved from the railroad bay area to spent fuel pool for reracking.. The existing racks are 49.625" x 90.125" x 168.5" and weigh approximately 9,600 pounds.

New racks are 80.23" x 90.165" x 168.5" high and weigh approximately 15,800 pounds.

These loads are greater than the combined weight of a single spent fuel assembly and its handling -tool (approximately 1,500 pounds) and therefore, fall under the category of heavy loads as defined in the NUREG-0612. " Control of Heavy Loads at Nuclear Power Plants".

A _ procedure meeting the intent of NUREG-0612 was developed.

II.

ASSUMPTIONS The load path developed is based on the"following assumptions:

1.

New racks will be lifted or lowered in the southeast part of the railroad bay area (See Figure A-1).

2.

The racks will not be carried over the in-place new or existing racks containing fuel, in the spent fuel pool.

3.

The spent feel storage gate is closed and the fuel transfer canal drained, while racks are being moved in the area.

4.

The lifting mechanism and its lugs are designed in accordance with the requirements of ANSI 14.6,1978, " Standards for Special Lifting -

Devices for Shipping Containers Weighing 10,000 Pounds or.More for Nuclear Materials".

5.

All racks are carried to the cask - decontamination areas as per Figure A-2.

6.

The auxiliary building crane will be operated over the spent fuel pool in accordance with Fort Calhoun Technical Specifications 2.11 and Operating Instruction 01-HE-5.

7.

Rack removal sequence is per Section 3.5 and paragraph 3 of this document.

III.

PREREQUISITES S

1.

A piece of ~ hand rail at "B" location should be cut to provide a space wide enough to allow passage of the racks.

These pieces. of handrail should be welded back after the reracking.

2.

The auxiliary buil ding crane should be inspected,

tested, and maintained in accordance with the applicable requirements of ANSI B30.2-1976, " Overhead and Gantry Cranes".

3.

Proposed load paths have been di.scussed with the crane operator and signal man and a dedicated signal man is available to guide the crane operator.

. IV.

CRITERIA FOR SELECTION OF THE LOAD PATH Criteria for selection of the lcad path are as follows:

1.

No safety related equipment or irradiated fuel is impacted by the dropped load along the load path.

2.

The load path will follow structural floor members, beams, etc., to extent practical.

In the event of a load drop, and structural member failure, no safety-related equipment on the intermediate floors or basement floors will be damaged.

V.

DESCRIPTION OF PROPOSED LOAD PATH The proposed load paths are shown on the attached _ figures A-1 and A-2.

If any deviations are planned to be made from the proposed path, they will first be reviewed, and approved by the Plant Review Committee prior to moving the racks.

a.

Removal of Existing Racks The existing SFP racks will be removed from the spent fuel pool in a sequence as outlined in Section 3.5 paragraph 3.

The racks will be moved from the spent fuel pool to the cask decontamination area in l

the following manner.

1.

The racks will be carried over to the cask IA), the rack is raised to elevation 1039'-6" pit area (location (position 18) and moved di rectly west to location 2A.

From this position, the rack is lowered to the floor of the decontamination area (elevation 1025'-0") where the rack is to be packaged.

The' rack may be set down anywhere within the decontamination area for the decontamination process.

e t

er r

---vv-y

%,r

---

y gr---e~w+---w+--wt1 r'---*----Se a

'w

-t-r

-ww----s**tet

' wr-r r -e 4e--*--rrr-rreMe v

er--daw a ww w-w-e-e--r,-*-ww+=T-v--e waa--

t 2.

Onco the rack is ready for shipment, the rack is raised 6" to elevation 1025'-6" (pesition 28) and moved sout" to location 3 where it is then turned and moved east to location 4A.

The rack is then raised to elevation 1039'-6" (position 4B) to clear the decontamination area wall.

3.

From location 4B, the rack is next moved further east to position 5 where it is turned and moved south to location 6B above the platform at elevation 1036'-4".

Position 6A may be one of the locations where the handrail needs to be cut in order to allow passage of the rack..

4.

With the bottom of the rack still at elevation 1039'-6", the rack is next moved east over the fuel transfer canal to location 8.

By stopping here the Safety Injection Refueling Water Tank will be cleared.

Position 7 is the other location where the handrail is to be cut to allow the rack to pass.

5.

The rack is now turned south and moved to position 9A where it is lowered from elevation 1039'-6" to elevation 1034'-0" (location 9B) to clear both the fuel handling machine rail stop and the handrail located near column line 2d.

From location 98, the rack is finally moved south to the centerline of Beam B-64 located at elevation 1004'-0".

From this position the rack is loaded onto the truck for shipping.

If the cask needs to be moved further west in order to facilitate loading, it should be lowered to elevation 1004'-6" and moved along the centerline of beam B-64.

b.

Installation of New Racks The new racks shall be lifted from the railroad bay area at location "A" to an elevation of 1039'-6".

The racks should be moved north to location "B"

along the centerline of beam B-64 located at elevation 1004'-0".

The handrail may have to be cut to allow the rack to pass at position "B".

The racks will be moved from position "B" to position "C".

By stop-ping here, the Safety Injection and Refueling Water Tank will be cleared and the rack will not interfere with the fuel handling machine distance gap.

The new racks will be brought directly over the fuel transfer canal and will move west over the transfer to location "D".

The racks will be moved north from point "D"

and will then be lowered into the pool.

5

+

y w

e---.

+

w-3-r---

c-

-y

1 IV.

AREAS AFFECTED BY PROPOSED LOAD PATH The following areas will be affected by the proposed load path.

a.

Railroad Bay Area - The southeast area of the railroad' bay will be affected by this load path.

There is no safety-related equipment beneath this structure.

The safety injection and refueling water tank is not endangered as the load path avoids that.

~

i b.

New Fuel Storage and Uncrating Area - The loads in this area travel over a series of different slabs and beams at different elevations.

A load drop along the proposed path in this area could conceivably fail the various intermediate slabs and fall to the basement floor (elevation 989'-0").

However, since there is no safety-related equipment in this area, this fall would not cause a plant safety problem.

c.

Fuel Transfer Canal - A load drop in the fuel transfer canal would not damage spent +n1, since no spent fuel is stored in the canal.

The bottom of the transfer canal consists of a stainless steel liner plate over 12-foot thick concrete mat on cais sons.

The worst postulated damage would be the puncturing of the stainless steel liner plate but the concrete behind the plate would retain its integri ty.

I d.

Walls Around Spent Fuel Pool - The walls around the spent fuel pool at elevation 1039'-0", are approximately 4 feet thick.

A SFP rack drop may cause a local spalling of the concrete but will not cause 7

any significant damage.

1 e.

Spent Fuel Pool - The racks in the spent fuel pool will be moved in i

accordance with the sequence listed in Section 3.5 paragraph 3.

This procedure will ensure that the racks do not travel over the in-place new or existing racks containing fuel in the spent fuel pool.

f.

Decontamination Room Area - The slab in the Decontamination Area is 3' feet thick. A drop in this area would not damage any safety-related^

equipment or fuel.

The travel of both the main hook and the auxiliary hook is prevented over the spent fuel pool by electrical i nterlocks.

Fort Calhoun Technical Specification 2.11 and Operating Instruction 01-HE-5 state that the Auxiliary Building Crane should not be used to move any loads to the spent fuel pool without a written procedure.

This procedure will describe all the precautions and conditions and be approved by the Plant Review Committee.

A key to bypass the elec-trical interlocks can be obtained - from the Shift Supervisor after the procedures are complete.

Operating Instructions 01-HE-5 re-quires that a certified / qualified crane supervisor be in admini s-trative control when the electrical interlocks are inoperative.

The interlocks will be required to be bypassed in order to remove the racks out of the pool area.

The reracking sequence procedurcs and ad;inistrative control of the crane would preclude any possibility of a load drop over the stored fuel resulting in a radiological release.

VII.

SAFETY EVALUATION The SFP racks handling does not constitute an unreviewed safety question (per 10 CFR 50.59) for the following reasons:

1.

The probability of an occurrence or the consequences of an accident is not increased provided that the rack follows the prescribed path.

A load drop will not damage any safety equipment.

2.

The administrative control and reracking sequence procedures, would preclude the possibili ty of a load drop on any safety related equipment.

3.

Since the SFP racks line of travel does not effect any safety equip-ment, the margin of safety, as defined in the basis for any techni-cal specification is unaffected.

VIII. CONCLUSION U

The load path described above for the removal and installation of racks is safe and meets the intent of NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants".

IX.

REFERENCES

~'

1.

" Sample Cask Drop Analysis and Removal Procedures", at Fort Calhoun Station by Stone and Webster Engineering Corporation, dated June 7, 1978.

2.

" Control of Heavy Loads at Nuclear Power Plants, Response prepared by. Stone and Webster Engineering Corporation for Omaha Public Power District".

3.

Gibbs Hill, Durham and Richardson Drawings.

4

._r

...~,.m._.,_

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

-_,._.-_m.

,.,,. N

l APPROX. SIRWST I

I BOUNDARY ASSUMED NORTH

\\/

\\/

f rFUEL HAth

"/

DISTANCE o f

!~

5,-

p lA N E<

- t r-d 2

N "o 8'- O =

SPEilT FUEL POOL fm wz i

?. ]

N v

d v8 o

I E

Ej 2

(

\\

N I'

.- l > ; e 0 Syly; gr.gy;-y

.c ;.,;,. ;< :,

STD HAPORAll

\\

3 l..: v.;,c...i.

-..7

_. g.

.?!

I

'. li

..dm

23

' J I

PLAT A

EL IC l

d

-mSLOT CUT It i

i r - - - - -- - -

- - ~ - -

r-i f

-.s-----~~--------

- n------

,,I p

1

..---i

,5 i

I i

~d m

i i

8 l

lo i

8-4

')

e a

I I*

i 1

I u,

I I

I 3'-O' SL AB I

d l

8 21

--- DECONTAMINATION AREA 2,- 6' SU i

]-

f

, b'{-

~

2-Z _. _ _. _ _ _ __ __ 2 __

2_ _ _ g w r c-r ;-..; 'f.'

21'- S*

21'- 5'

's G

l.

LOAD PATil F0'1 IiiS

1 UNLCMDING AREA

/

i i

g

. LNG fi% CHINE l

l l

AGE

'~

"o

\\

• g *

-4 l

I PROPOSED TRAVEL OF RACK

[D 1

y

_.._,_ _ m y

.g I

I l

Y l

I co T_.__"'-~__%

~~ ~ ~

~9 NEW FUEL l

l

7. [' 7.--8 ~7M~ "?,~.: SIORAGE-&-

7 l

l-[

H ^^ ^

^

^ UNCR ATIN 3

I

)

3

1. j l

r

\\

l lt 7'- O'.

<,9\\

i 3-2_

__ __i F

l lA

,]--

d a

i L

I I

CA R J

'M' i

l D

red _. _ _m_.wzi r u.. _.

___t_____

lb la l

f

.;q n 'rt ;ro 442 lui.t

.n.g. M j_1 4 -QN:3::/4tC : \\WWQ

[

t a g

a I

a!

l l

I l "o

i l

G' U B N

-4

=-

. a FORM I I I

I i

$6'4 g a

l l

g g

g g,____,..r-------------1--

- _ J NI trJI l

l I

L r

,_7 _

,_o,_,.______________.r-l g

i Z

ig {I i

i i

i l

I Im i

I 8 l

l l 'e i

i i

Ne

, _~-

i i

i i

I l

I i 1

i I

lOSLA81 l

B i

t

.i EL IOO4' l

. E,J I

e a i

m. i.

it.

n_..

?

l l

n

(_-.I i

d X_ __ _

i w

j

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

\\,_...

.....n.

Q3)

___,_u.__

1

-. 21'- 5' 21'- 5' a l'- I t'.

s Also Available On g

g Aperture Card g

rAtt,mo:: 0F flE'l MCKS 8308090661 -o(

FI G U R E A-l

\\

l 1

8 APPRO X.

SIRWST I

BOUNDARY

'/

ASSUMED J NORTH

)

l

~~

\\

\\/

\\/

['

rFUEL HANDL

/

DISTANCE G

/

/

f,-

d ln$

a 5<

- t._r-o a

"o s'- o SPENT FUEL POOL.

s 1

2 2

E O IAJB b '

i d

u

).. a 2

/\\

'~

~

\\ NC l

\\

STD HAfDRAll d

3

.newc-+n new:.p=e:U2namtr. Mew.

g2 :\\*gjy g

i-ds j \\ L wk.,

C&l PtAri l -/-l 9

( T. A t' io (ji j

CStot tuTlW r-

-i

. i-___

_ f _ _.

i,I

~~~l Ih *[

4A,48 l

l

g I

l~o i

3 g

l A,28 s

l(/

3'.o' stas

() _'

t-l f

l 2* 6 LA DECONTAMINATION AREA i

n.s,

,n h

s 8

. h 5

8

- ;;, -;.:z:. L,.

J 21'- 5*

2 t'-5' t

5 LOAD PATH F0W

l l

m tl_NL.OADlhG AREA l

l E

/

6 I I

tNG MACHirE

.l g

l EE

.g

.5 l

l g

,3 b*

PROPOSED TRAVEL OF 8,ACK

[D i

.I

_ __,__ _ a y

w.

4 i I

i 9A,98 l

T l

l m

1 l

l.

l m.__.______

NEW FUEL l

l l-

?:uG ;-A n ;.ason^aee--UtXRAitt&m tT I

g

\\

3 _ -_.

p

+:

I I

J J n i

\\ V I

p 8

F l

~lA3ER

~.RE l

7'- O' 41 g

~'

.~

I'

[

~

h__ __

i

_J i

a t

^h l

.t I

'l

.i l

I l

'Gp 1

.I I

yj e

l l

I e

,I K".' :.,' '."?Q._.

-,W :.

- = 2Q'h i,

H1

[3 L M 1st+91:.iwAAcr=

. to%

l@ ';-+5%?Eymm>xe.wn,:;wc n; I 8 i

e I e l

l W

a

/

I I I

I g,* M B g

l-l

[.L N

o i

'a i.

i.__...

_4 1

I l'

l.

l

.I 5

g :,

a:

g g

g 1-gM, _,_.-

- i ; r - - -- - - - - - -

b_

ai i,si i

?

I I

~

ry-- --. r'ir

.T -' -'

l :.

!g I

l.

3 l

l

(

-l

. 6 in I

i I 8

% :l,1 l

l I

l

)

I a i

1 I

lo stAa l

l

?

)

8 I I

i i

/EL1004 d

-M_T;a l

-3 e e e r.r s e v t..

X di l

l 5

l h

7, ' I L

--,r..-'i.,.~,.,

21'- 5' 21*-5' 21'- Il'.

e Also Available On h

h Aperture Card h

'REi10 VAL OF EXISTING RACKS 8308090661 _

m