Text

Discusses Westinghouse Reanalysis of Proposed Expansion of Spent Fuel Storage Facilities.Applicable Requirements of OT Position Paper Met W/O Any Controls
	ML17346A823
Person / Time
Site:	Turkey Point
Issue date:	02/01/1985
From:	Williams J; FLORIDA POWER & LIGHT CO.
To:	Varga S; Office of Nuclear Reactor Regulation
References
	L-85-30, NUDOCS 8502060153
	Download: ML17346A823 (21)
	v • d • e

P'EGULATORY FORMATION DISTRIBUTION SY M (RIDS)

ACCESSION'BR i 8502060153 DOC DATE) 85/02/01NOTAR'I'ZED'O DOCKET' FACIL'$50 250 Tur key Po jnt Pl ant~

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05000251 AUTHQNAME AUTHOR AFFILIATION'ILLIAMS~

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RECIP ~ NAME RECIPIENT AFFILIATION VARGAiS ~ AD Operating Re'actors Branch 1

SUBJECTS Discusses Hestinghouse>> reanalysis of proposed expansion of sPent'.fuel storage facilit.ies,Applicable requirements of OT'osition paper me,t w/o any controls, DISTRIBUTION CODE!

A001D COPIES RECEXVED:LTR ENCL SIZE';

TITLE). OR Submittal! General Distribution NOTES!

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$ +85 "L-85-30 office of Nuclear Reactor Regulation Attention:

Mr. Steven A. Varga, Chief Operating Reactors Branch t/ I Division of Licensing US. Nuclear Regulatory Commission Washington, D.C. 20055

Dear Mr. Varga:

Re:

Turkey Point Units 3 & 4 Docket Nos. 50-250 & 50-25 I S ent Fuel Stora e Facilit Ex ansion In support of the FPL request to amend the facility operating licenses to permit expansion of the spent fuel storage facilities at Turkey Point Units 3 and 4, the rack vendor (Westinghouse) analyzed the spent fuel storage racks for overturning and sliding displacements due to earthquake loading for the cases of full, partially filled and empty fuel racks.

The analysis results met and exceeded the stability criteria of the NRC "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications." The results showed that the racks did not lift off the spent fuel pit embedment plates under seismic event conditions.

This information was provided to you in FPL letter L-84-263, dated September 28, I 984.

I Thereafter, in a letter dated October l9, l984, Westinghouse informed FPL that administrative controls on fuel loading would be needed for those spent fuel racks whose outer rows overhang the support pads.

Westinghouse stated that liftingof a rack could occur during a seismic event if the outer rows are fully loaded while the rest of the rack remains empty.

Six (6) Region II racks with a one row overhang, one (I) Region I rack with a one row overhang and one (I) Region I rack with a two row overhang are affected.

Although not indicated in their October l9th letter, these controls were required to be consistent with an assumption made by Westinghouse in its analysis (i.e.,

that the overhanging rows would not be loaded while the rest of the rack was empty).

Neither the preliminary seismic/structural analysis report nor the basis provided by Westinghouse for FPL's September 28th letter specified this assumption or identified the need for administrative controls.

Consequently, at an October 24, l984 meeting, FPL requested that Westinghouse provide clarification regarding the basis for its recommendations for controls.

Westinghouse responded in a letter dated November 16, l 984 and received by FPL on November 27, 1984.

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Page 2 Office Of Nuclear Reactor Regulation Mr. Steven A. Varga After review of the November I6th letter, and additional discussions with Westinghouse, FPL directed Westinghouse to reanalyze the affected rack modules with the assumption that overhanging rows are loaded while the remaining rows of the racks remain empty.

Preliminary results of the reanalysis, which showed liftoff could occur during a seismic

event, were discussed with Mr. D. G.

McDonald on December l9, I984. By letter dated January IO, l 985, Westinghouse provided FPL with the final verified results of the reanalysis.

The reanalysis shows that the applicable requirements of the OT position paper are met without any controls.

The worst case loadings are 3 outboard rows (2 overhang rows plus the row above support pads) for a Region I module and 2 outboard rows (I overhang row plus the row above support pads) for a Region II module while the rest of the module remains empty.

For these loadings a more than adequate factor of safety against overturn is maintained.

The following summarizes the results of the analysis:

The factor of safety against overturn is 8 for Region I and 220 for Region II, with support pad liftoffof O.I8 inch and 0.0l inch, respectively, during a seismic event.

The rack support pads will not slip off the embedment plate under any condition.

The racks will not at any point contact other racks or the pool wall. A revised tabulation of displacements is shown in Table I.

Resulting pool floor loads and structural stresses. are enveloped by the condition of a fully loaded rack.

I lt is requested that the NRC review the above information and concur that the reanalysis is acceptable.

Until NRC concurrence is obtained, FPL will provide administrative controls on fuel placement in order to preclude the possibility of any liftoff, maintaining the validity of the analysis and results submitted in our September 28th letter. If you have any questions, please contact us.

Very truly yours,

~

J. W. Williams, Jr.

Group Vice President Nuclear Energy

,JWW/TCG/cab

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TABLE I>>

RACX DISKACEMENTS FOR AFFZCTEO Ra; RACe CAST CAS! LOADIHGS Seismic + hAaximvrn Normal Thetrnal RFGION I REGION II

/SF-Seismic +

gormaI Thor!TNI Max. Sliding Distance, Q e.2 (N-Linear Results}

in.,0001 Oe007 Max, Structural Defi~,

w I.8 (N-linear Results)

Total Displacement One Rack 6 ',s i 6 SRSS Combined Displacement 2 Racks with only 1 sliding 4

a i

+

Max. Normal Thermal Dispiacernent in

.4501 0.093

~636 0.127 0.087 in,450 0.086 Max. Combined Thermal 8 Seismic Oisplacernents

~ * ~I'nnax Rack to Rack Cap (Rl Rll)

Rack to Rack Gap (RI)

Rack to Rack Gap (Rli) in

.724 In in 2.5S 0<214 2.90

+See response to Qvest fan 4a of FPI. Letter i-84 263 dated September

28) 1984>>

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-hw REGULATORY

.FORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR:8502060153>>

DOC ~ DATE: 85/02/01 NOTARIZED;- NO FACIL:50-250 Turkey Point Planti Unit 3P Florida Power and Light C

50 251 Turkey Point PlantE Unit QE Florida Power and Light C

AUTH BYNAME AUTHOR AFFILIATION WILLIAMS'

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FlOrida PoWer 8 Light CO ~

RECIP ~ NAME REC IP IENT 'AFFILI ATION VARGAES ~ AD Operating Reactors Branch 1

SUBJECT:

Discusses

)westinghouse reanal ysis of pr oposedexpansion of.

spent fuel storage facilities'pplicable requirements of OT position paper met w/o any controls.

OISTRISUTION COOE 1

A0010 COPIES RECEI/EO:CTR /

ERCI.

SIZE:-

T'ITLE:

OR Submittal; General Distribution DOCKET NOTES; OL: 07/19/72 OL ~ 04/10/73 05000250 05000251 RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNALS ACRS 09 ELD/HOSP NRR/DL DIR NRR/DL/TSRG NRR/DS I/RAB RGN2 COPIES LTTR ENCL 1

1 1

RECIPIENT ID CODE/NAME ADM/LFMB NRR/DE/MTEB NRR/DL/ORAB NRR/DSI/METB o~l COPIES LTTR ENCL'-

1 1

EXTERNAL: LPDR, NSIC 03 05 NRC,PDR 02 TOTAL NUMBER OF COPIES REQUIRED:

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. L-85-30 Office of Nuclear Reactor Regulation Attention:

Mr. Steven A. Varga, Chief Operating Reactors Branch 8 I Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20055

Dear Mr. Varga:

Re:

Turkey Point Units 3 & 4 Docket Nos. 50-250 & 50-25 l S ent Fuel Stora e Facilit Ex ansion ln support of the FPL request to amend the facility operating licenses to permit expansion of the spent fuel storage facilities at Turkey Point Units 3 and 4, the rack vendor (Westinghouse) analyzed the spent fuel storage racks for overturning and sliding displacements due to earthquake loading for the cases of full, partially filled and empty fuel racks.

The analysis results met and exceeded the stability criteria of the NRC "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications." The results showed that the racks did not lift off the spent fuel pit embedment plates under seismic event conditions.

This information was provided to you in FPL letter L-84-263, dated September 28, 1984.

I Thereafter, in a letter dated October l9, l984, Westinghouse informed FPL that administrative controls on fuel loading would be needed for those spent fuel racks whose outer rows overhang the support pads.

Westinghouse stated that liftingof a rack could occur during a seismic event if the outer rows are fully loaded while the rest of the rack remains empty.

Six (6) Region Il racks with a one row overhang, one (l) Region l rack with a one row overhang and one (l) Region 1 rack with a two row overhang are affected.

Although not indicated in their October l9th letter, these controls were required to be consistent with an assumption made by Westinghouse in its analysis (i.e.,

that the overhanging rows would not be loaded while the rest of the rac'k was empty).

Neither the preliminary seismic/structural analysis report nor the basis provided by Westinghouse for FPL's September 28th letter specified this assumption or identified the need for administrative controls.

Consequently, at an October 24, l 984 meeting, FPL requested that Westinghouse provide clarification regarding the basis for its recommendations for controls.

Westinghouse responded.

in a letter dated November l6, l 984 and received by FPL on November 27, l984.

8502060i 53 85020i PDR ADOCK 05000250 PDR I

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Page 2 Office Of Nuclear Reactor Regulation Mr. Steven A. Varga After review of the November l6th letter, and additional discussions with Westinghouse, FPL directed Westinghouse to reanalyze the affected rack modules with the assumption that overhanging rows are loaded while the remaining rows of the racks remain empty.

Preliminary results of the reanalysis, which showed liftoff could occur during a seismic

event, were discussed with Mr. D. G.

McDonald on December l9, l984. By letter dated January IO, l985, Westinghouse provided FPL with the final verified results of the reanalysis.

The reanalysis shows that the applicable requirements of the OT position paper are met without any controls.

The worst case loadings are 3 outboard rows (2 overhang rows plus the row above support pads) for a Region I module and 2

outboard rows (I overhang row plus the row above support pads) for a Region II module while the rest of the module remains empty.

For these loadings a more than adequate factor of safety against overturn is maintained.

The following summarizes the results of the analysis:

The factor of safety against overturn is 8 for Region I and 220 for Region II, with support pad liftoffof O.I8 inch and 0.0l inch, respectively, during a seismic event.

The rack support pads will not slip off the embedment plate under any condition.

The racks'will not at any point contact other racks or the pool wall.

A revised tabulation of displacements is shown in Table I.

Resulting pool floor loads and structural stresses are enveloped by the condition of a fully loaded rack.

I It is requested that the NRC review the above information and concur that the reanalysis is acceptable.

Until NRC concurrence is obtained, FPL will provide administrative controls on fuel placement in order to preclude the possibility of any liftoff, maintaining the validity of the analysis and results submitted in our September 28th letter. If you have any questions, please contact us.

Very truly yours, J. W. Williams, Jr.

Group Vice President Nuclear Energy JWW/TCG/cab

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0 REGULATuR Y INFORMATION O IS TR I BU T ION SYSTEM (R ins 1 ACCESSION NoP:8502060 i5$

OVC ~ DATE. 85/02/Ol FACIL'50 250 Turkey Point Plants Uni t 3e Flor 50-25i Turkey Point Planti Unit 4i Flor AUT~.riAME AUTHDR AFF1LIATIDN HILLIAHSJJ ~ yI ~

F 1 or f da Power 8 Light Co ~

RECCP.NAME RECIPIENT AFFILIATION VARGA,S ~ A ~

Operating Reactors Branch NOTARIZED:

NO 00CKET ¹ ida Power and Liuent C

05000250 ida Power and Liuent C

0500025i

~

SUBJECT:

Discusses l4estinghouse reanalysis of proposed expansion of spent fuel storage facilities ~ Applicaole requirements of Dr position paper met w/o any controls, DISTRIBUTION CODE:

AQOlD COPIES RECE.IVEO:LTR ENCL SIZEi TITLE:

OR Submi ttel:

Gener al Disti'ibuti on NOTES:

OL: 07/19/72 OL '4/14/73 05000250 05000251 RECIPIENT IO CODE/NAME NRR ORoi RC Ol INTERNAL: ACRS 0')

.ELO/nOS4

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<4Rii/uL/TSRG ERR/OS I/RAB RG>42 COPIES LT(R FNCL RECIPIENT ID CODE/NAME ADM/LFMO NRR/DE./MTE8 NRR/DL/DRAB NRR/DS I/METB 04 COPTES LTTR ENCL EXTERNAL; LPDR ris Ic ns Ob NRC POR a~a P~>

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TOTAL NUMBER OF COPIES REQUIRE,O:

LTTR 2S ENCL 3

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FLORIDA POWER 8( LIGHT COIYIPAi'4Y pgg

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. L-85-30

'Office of Nuclear Reactor Regulation Attention:

Mr. Steven A. Varga, Chief Operating Reactors Branch 8 I Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20055

Dear Mr. Varga:

Re:

Turkey Point Units 3 & 4 Docket Nos. 50-250 & 50-25 I S

nt Fuel Stora e Facilit Ex ansion In support of the FPL request to amend the facility operating licenses to permit expansion of the spent fuel storage facilities at Turkey Point Units 3 and 4, the rack vendor (Westinghouse) analyzed the spent fuel storage racks for overturning and sliding displacernents due to earthquake loading for the cases of full, partially filled and empty fuel racks.