ML20205H984

Forwards Draft Amends 18 & 23 to Licenses DPR-24 & DPR-27, Respectively, & Safety Evaluation.Amends Revise Tech Specs to Add Surveillance Requirements & Place Limit on Max Weight of Spent Fuel Shipping Cask Used

ML20205H984
Person / Time
Site:	Point Beach
Issue date:	07/06/1976
From:	Lear G Office of Nuclear Reactor Regulation
To:	Burstein S WISCONSIN ELECTRIC POWER CO., WISCONSIN MICHIGAN POWER CO.
References
TAC-07727, TAC-08074, TAC-7727, TAC-8074, NUDOCS 8810310238
Download: ML20205H984 (20)

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Dockets Mos. 50-266 TJCarter

! cnd 50401 CParrish l Jn'etnor a OELD OIf>E (4)

Visconsin T.ltetric Power Conpany BJones (8)

Visconsin Michican Tover Co pany BScharf (10) i J1tcCough Arr'?: Mr. Sol 3ursteln JSaltzman i Executive Vice Presidcat Citebron 231 Vent ?tichigan Stroot tillvaukee, k'isconsin 53 01 AESteen ACRS (16)

C' tile s Cen t le.~en t Dross j

TSo conMssion has isrued the enclosed Aaend ents Uos.18 and 23 to Facility Operating Licennaa Nos. DPR-24 rad DPR-27 for the Point Ec'.ch Uuelear Plant. Unita "os.1 en! 2 The aner.hentn concist of chw;cs to tha Technical 'paef ficatloas and ere in accordanca with yoar application dstad P.sy 13. 1976.

~he ancahent consists of channes in the Technics 1 Specifications that vill a3J surveillance require ents ara will placa a liutt on the eninta veight of the spent fut.1 shipping cask that nay be vei.

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Copies of the related Safety Eval':ation and the Tederal T.erister Motice

. also are encloced. ,

t l Sincerely.

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George Irar. C.ief '

Berating Ecactor: T rant's #3 Division of Reactor Licensing rneiosurest

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Anenhent ".a.1P to Liceve TPR-24 1, Aten3N at Po. 23 to license DPR-27  ;

) Safety rysluation  !

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1lashington, D. C. 20006 fir. Arthur 't. Fish Docuaent Departr.cnt University of 'tisconsin ,

Stevens Point I.ibrary Stever.s Point,1lisconsin .541S1 Mr. Nornan Clap, Chairran

• Public Senice Co .21ssion of ilisconrin 11111 Paras State Office Building Madison,llisconsin 53702 1

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- VISCONSIN ELECTP.IC POLTR CO?tPANY WISCC0:51N !!!CHICAN PO*.s'LR CO:7A'iY DOCKET NO._50_-166_ ,

_ POINT BEACILNUCLQR PLB'T dPdIT NO.1 A' FEND: TENT TO FACILITY OPERATING LICENSE i Amendtent No. 18 I,1 cense No. !>pR-24

1. The Nuclear Regulatory Comission (the Comisstori has found that:

A. The application for amendeent by Wisconsin Electric Fever Company and Visconsin !!ichigan Power Conpany (the licensees) dated l P.ay 13, 1976, complies with the standards and requirc:ents of the Atocic Energy Act of 1954, as amended (the Act).

i and the Cor:sission's rules and regulations set forth in 10 CTR Chapter It B. The facility vill operate in conformity with the application, j the provisions of the Act, and the rules and regulations I of the Comission; C. There is reasonable assurance (1) that the activities authorized i by this acendeent can be conducted without endangering the health and safety of the public, and (11) that such activities vill be conducted in eccpliance with the Consission's regulations; and D. The issuance of this amendeent will not be ininical to the cot =on defense end security or to the het.ith and safety of the public. ,

i E. The issuance of this a:endment is in accordance with 10 CTR Part 51 of the Comission's regulations and all applicable require =ents have l been satisfied. ,

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2. Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license

e. enonent.

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This license amend:sent is effective us o; the data of ich issuance. l Tort 71 t WCLTJJL RICt1AT0FY C0:::15SION .

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• i Georgu Lear, Chief  !

! Operatint, Reactors Branth P3 j Division of Operating Reactors '

L Attachnent:

Changes to the

, Technical Speeffications '

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Date of Issuance

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ATTACINENT TO LICE!!SE_ MidNDMENT NO.18,

, TO THE TECHNICAL SPEITICATIONS FACILITY OPERATING LICU;SE NO. DPR-24 DOCKET NO. 50-28,6 ,

Add page's 15.4.14-1 and 15.4.14-2.

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15.4.14 SUWE*r.fA'iCC Of AUXILIARY hu!LDING CPRil!

A5plicabilig: ,

Applies to survoillt.nce requirc:.cnts for the auxiliary *autiding crane tefore and during handling of the spent fuel shipping ca >*a.

• Objective: _

To vorify that the crane brid7 e and trolley interlocks to prevent nover.ent over the south, spent fuel pool are operational and to specify the raxinu:n veight spent fuel shipping cask allowable.

frecification:

1. The five auxiliary' building crane bridge and trolley psitive acting linit svitches, which provent r.otien of the r.ain crane bwk over the south spent fael pool, shall be deronstrated to be cperable within one veck prior eo spent fuel shipping cask tc.over.ent e.nd at letist once per s .;k thereaf'ter during, spent fuel shipping eask revenent T.

operations.

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! 2. Die r.uirua allevable spent fuel shipping cask weight shall l

be limited to 52,500 pounds.

I ag,1 s,,a In order to prevent darage to spent fuel asserblies stored in the

, south spent fuel pool in the event of a postulated drcpped cask in:ident, positive acting lir.it switches have Leen mounted on the bridge to' restrict the auxilian buildir.g crane reve: ent. Die switches are located to prevent l cask roverents over the south spent fuel pool.

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( An 'initicting signal from tho limit switchos will shut cff driva pow:r to the crana and not the brakes. The controls r e;such that the trolicy can be moved only in the north direction af ter the limit rwitches have operated I  !

l and the switches vill autcratically reset upon reverse nove-ent.

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t The specified eayidum Voight Of the spunt fuel nhi,pping Cask is based upon the heaviest s;ent fuel shipping cask presently expected to be l

l used at the Point Poach Nuclear Plant and is consistent with the analyses i

1 done for the potential effec *: upon spent fuel stored in the south spent fuel 9

pool in the event of a postulated cask drop in the north spent fuel pool.

Referencet 1

(1) TfD3AR Aprendix T l .

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k endient No. 18 ,

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DOCKET ;o. 50-301 POINT BEACll :.TCLEAR PLA'iT, UNIT NO. 2.

• A'END'EST TO FACILITY OPERATING LICE!;SE Amendment No. 23 License :;o. DPR-27

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment'by Wisconsin Electric Power Company and 1 isconsin !!ichigan Power Cocpany (the licensees) dated May 13, 1976, complies with the standards and requirements of the Atonic Energy Act of 1954, as arended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Co==ission; C.

There is reasonable assurance (1) that the activities authori::ed by this amendnent can be conduc'ted without endangering the health and safety of the public, and (ii) that such activities will be conducted in co=pliance with the Cocaission's regulations; and D.

The issuance of this atendment will not be inimical to the common defense and security or to the health and safety of the public.

E.

The issuance of this acendment is in accordanco with 10 CFR Part 51 of the Co= mission's regulations and all applicable requircments have been satisfied.

2. Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment.

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This license atendment is effective'cs of the date of its issuance.

FOR Ti22 !.TCLEla TIG**: '.!CTll CC". :!SSION George Lear, Chief Operating Reacters Branch #3 Division of Operating Reactors Attachnent:

Changes to the Technical Specifications Date of Issuance:

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ATTACHMENT TO LICENSE A!E!.'DMENT NO. 23 TO THE TECHNICAL GPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NO. 50-301_

Add pages 15.4.14-1 and 15.4.14-2. .

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'15.4.1W ~ 'SUsVEILIRICE'OP AUXILIARY BUILDING CPM lE .

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Applies to*survoiilance requirements for the' auxiliary buildidg 7

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crane before~and during handling of the spent fuel shipping casks. ' . f[* .

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Objectives .1- ' N f . '. -

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% verify' that the crane bridge and trolley interlocks to f,

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prevent movement'over the south spent fuel pool are operational'and to  ;

. . ... a ... s' specify the maximum weight spent fuel shipping cash allowable. . * "

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i specification: * * '- - I~*'* I

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1. The five auxiliary building crane bridge and trolley ,

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, positive acting lin,it switches, which prevent notion of ,

l the main crane hook over the south spent fuel pool, shall

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t be demonstrated to be operable within one week prior to i spent fuel shipping '

cask movement and at Icast once por  !

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. h-week thereaf ter during spent fuel shipping cask covement

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2. The maximum allowable spent' fuel shipping cask weight shall be limited to 52,500 pounds. ,

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Basis: .. .

• a In order to prevent damage to spent fuel asse:.blies stored in the south spent fuel pool in the event of a postulated dropped eask incident, positive acting limit switches have been counted on the bridge' to, restrict the auxiliary building crane cover.ent. The switches are located to prevent cask movecents over the south spent fuel pool.. .

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s Amendment No. 23 15[4.'1G1 4

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. . Aa initiating nignal from the lir.it switches will shut off drive'povar to ,

, . , .i the crane and set the brakes. The controls are such that the trolley. can be

. moved only in the north direction af ter the limit switches have operated and the switches will automatically roset upon reverse revement.

The specified maximun weight of the spent fuel shipping cask is

. ' based upon the heaviest spent fuel shipping cask presently expected to be used at the Point Beach fluclear , Plant and is consistent with the analyses done for the potential effects upon spent fuel stored in the south spent fuel ,

pool in the event of a postulated cask drop in the north spent fuel pool.

References (1) FFDSAR Appendix F e , .

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• 15.4.14-2 ..

Anendnent No. 23

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, SAFETY EVALUATION BY THE OFFICE CF NUCLEYtt REACTOR REGULATION SUPPORTING A'!ENDINTS NOS.18 AND 2 TO LICENSES DPR'-2 *. A'O 2 7_

1 UISCONSINELECTRICTjiERCOMPANY POINT. BEACH NUCLEAR PLA C , UNITS NOS. 1 AND 2

, DOCKETS NOS. 50-266/301 Introduction On February 27, 1974, we requested h'isconsin Elcetric Power Company

('5FCO) to provide us with analyses and other relevant infornation nceded to determine the possible damage in the event of a spent fuel cask drop caused by a system failure at Point Beach, Units Nos. 1 and 2. We also asked the licenace to consider appropriate design or procedural modifica-tions to reduce the probability of occurrence of a cask drop accident.

WEPCO responded to our request by letters dated May 21, 1974, May 15 and October 2, 1975, and February 26, 1976. Also, per our request of April 15, 1976, UEPCO submitted proposed changes to the Technical Specifications on May 13,1976 to (1) add surveillance requirements for the limit switches associated with the auxiliary building crane trolley and bridge notions, and (2) establish the maximun weight of the spent fuci shipping cask that may be used.

D_iscussion

'The spent fuel storage facility at the Point Beach Nucicar Plant is shared by both Units Nos. 1 and 2. The spent fuel pool is constructed of reinforced concrete and is a seismic Category I structure. The entire interior basin face is lined with stainless steel plate. The pool itself is divided into two parts (north and south) by an internal dividing wall. A "notch" is provided in the divider wall to facilitate the transfer of spent fuel assemblica between the north and south pools. At its lowest point the divider wall "notch" is approximately three feet above the top of the stored spent fuel. The north portion of the spent fuel pool is reserved for the loading of the spent fuel cask, while the south pool is used to store fuel. There are some spent fuel storage racks located in the north pool but they are only used, as needed, to accommodate the temporary unloading of an entire reactor core. No spent fuel cask handliag is undertaken when fuel is tcmporarily stored in the north pool. Ordi arily, spent fuel that i is routinely discharged frem the core during refueling is only stored in the south portion of the spent fuel pool.

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s The main hoist of the auxiliary building crane'is used to lift the spent l

- fuel shipping cask from the transportation' vehicle to the fuel loading :

l areainthenorthspentfuelpoolandback{othetransportationvehicle.

l The auxiliary building crane is of the electric overhead travelling-l

' bridge, single tro11cy type. i Our evaluation of WEPCO's analysis of postulated-spent fuel cask drop' accidents at Point Beach Units Nos.1 and 2 and associated det ign changes and proposed Technical Specifications follows.

Evaluation _ -

i Our inquiry of February 27, 1974 and request of. April 15, 1976 were f prompted by several specific areas of concern which have been resolved as follows: j

1. Intecrity of spent fuel storage pool The licensee has analyzed the effects of dropping or tipping the  !

NAC-1/NFS-4 fuel shipping cask (25 tons loaded) at various locations >

in the north pool. The cases analyzed involved several drops at various i locathns in the north pool including a direct vertical drop onto the divider vall "notch", a lateral impact on the divider vall, and a c.3 k overarning while aitting on the pool floor. These analyses ,

, indicated that failure of the structure could occur at the divider vall "notch" and at a location in the pool floor slab including the cask loading area. Analyses of drops at other locations showed that ,

I the structure vould not fail.

To preclude the possibility of the cask dropping on the divider vall "notch", the licensee has proposed installing limit switches that vill t prevent the crane esin hoist from travelling near the "notch". This  ;

proposed modification vill be evaluated below in item 2. For the case i of a cask drop on the north pool floor slab at a distance away from the l l divider vall, the slab would be expected to fail with attendant perforation '

! of the stainless steel liner. But, the licensee ha's concluded, and I ve agree, that the integrity of the south pool (which would contain the spent fuel) would be eaintained, With the failure of the north pool ,

slab and perforation of the pool liner so=e outleakage of water would be expected. However, the rate of outleakage is expected to be small J because (1) the floor slab is over five feet thick and would restrict leakage through cracks in the concrete, and (2) the floor is seven feet below grade in the red clay Niagara Dolomite overburden, which would also tend to linit the leakage rate.

!' , Nevertheless, the outicakage could Icad to a decrease in pool water inventory. To co=pensato any inventory loss, the licensee has indicated that various sources of makeup water would be availablet treated vater at ceveral hundred gallens per riinute for the short term, and untreated

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2 vater at several thousand gallons per minute for the' long term. In l

- the unlikely event that these sources could not be effected or vere .

l not adequate to keep up with the leak rate, the pool inventory would begin to decrease. As the level of water decreased in the north pool the south pool level vould also decrease, since the pools co=municate through the divider vall "notch". If the level continued to decrease, 'q eventually it would drop to the level of the divider vall "notch" in l

both pools. At that point the water level in the south pool vould remain at that level (about 3 f t. above the top' of the fuel) while the north pool continued to drain. The licensee has determined that the direct radiation level at the top of the pool, from the fuel stored in the south pool, would be 690 Rem /hr. ,

k l To preclude this possibility, the licensee has proposed to construct a barrier that could be installed in the divider vall "notch". The j

barrier would be availableifor prompt installation in the "notch" in the event of a cask drop accident that resulted in an uncontrollable loss of water level in the spent fuel storage pool. The barrier would be designed to maintain a level of ten feet of water shielding over the  ;

spent fuel in the south pool.

We have reviewed the licensees calculations of the resultant radiation i levels at the top of the pool with ten feet of water shielding over the i spent fuel. Based on our review, we have concluded that the calculated [

l value of 29mr/hr is acceptable. Moreover, in consideration of (1) the [

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l fact that no spent fuel cask drop could violate the integrity of the l . south pool where fuel is stored, (2) the sources of makeup water  !

l available, and (3) the availability of a barrier to maintain an [

l adequate water level over the spent fuel in the south pool, we have >

concluded that relative to fuel pool integrity, the results of a cask ,

l drop accident are acceptable.

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2. Integrity __of the spent fuel l As stated earlier, no fuel is stored in the north pool during spent fuel I cask handling operations. During these operations, all spent fuel.is i stored in the south pool. The licensee has shown by analysis that if I

the cask is handled over the north pool at a sufficient distance from f the divider vall, a postulated cask drop (1) could not result in the  ;

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tumbling of the cask into the south pool, and (2) could not result in  !

A any damage to the south pool from impsets in the north pool.  ;

L To ensure that the cash is handled properly, the licensee has instituted [

operational procedures to prohibit cask travel over or near the south  ;

pool. In addition, the licensee has proposed the installation of limit l 1 -

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'4 switches on the crane trolley and' bridge motions to ensure that the

. cask is never close enough to the divider wall to allow it to tumble' '

over into the south pool, or to fall directly onto. the divider wall' "notch". ,

t Based'on our review, we have concluded that this modification, coupled . . ,

with the operational procedures will preclude' damage to spent fuel j stored in the south pool; and therefore. is acceptable. ,

l Furthermore, per our April 15, 1976 request, WEPCO proposed a new

Technical Specification (Technical Specification 15.4.14.1) that -

' would add surveillance requirements for the limit switches associated i

with the auxiliary building crane trolley and bridge motions. ,,

We have concluded that the proposed Technical Specification would provide additional assurance that the limit switches would remain '

operable during cask handling operaiions; and thus s is acceptable.

l 3. Integrity of critical systems and equipment The licensee has provided a listing of equipment that the spent fuel cask would pass over in moving from the transportation vehicle to the cask loading area in the north pool. The licensee has determined, i

and we agree, that damage or destruction of any'o: all of this

• equipment by a postulated cask drop accident would not cause the loss ,

of or jeopardize the integrity of systems or equipment important to

] safety. Therefore, relative to the integrity of critical systems and  :

equipment, the consequences of a cask drop accident are acceptable.  :

, 4. Design of the crane and cask handling equipnent r r

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The licensee has provided a description of the auxiliary building crane '

i that is used to lift the spent fuel cask. It is an cicetric overhead travelling bridge, single trolley type. The main hoist, which would 1

be used to lift the 25 ton spent fuel shipping cask, is rated at 130 tons.  !

1 The licensee has indicated that the design includes a minimum factor of l

l safety of five, under static full rated load stresses, based on the i ultimate strength of the materials used. Also, since the cask only weighs )

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) approximately 25 tons whereas the crane is rated for 130 tons, the crane l has an additional safety factor of about six for cask handling operations. 1

• Each of the two brakes for the main hoist is capable of holding 150% -

of the rated load, or 150% of the full motor torque.

4 The licensee has also provided a description of the cask lifting devices l

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and a listing of all tests that have been performed as part of the 1

final check-out of the crane. ,

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Based on our review of the information submitted, we have c$ncluded that the design of the crane and cask lifting devices provides adequate '

assurance that the probability of a spent fuel cask drop accident, caused by a system failure, is very low; and thus, is acceptable.

Furthermore, per our April 15, 1976 request, the licensee proposed a new Technical Specification (Technical Specification 15.4.14.2) .

l that would establish the maximum weight of the spent fuel shipping cask that may be used. The proposed Technical Specification will j prohibit the use of a spent fuel shipping cask heavier than that >

assumed in the accident analysis. Therefore, it will provide i

additional assurance that the validity of (1) the accider.t analysis, -

and' (2) the calculated safety factors in the crane will be maintained; and thus, is acceptable.

Sumary WEPCO has analyzed the consequences of a spent fuel cas drop accident.  ;

The results show that a drop in the north pool loading area could violate the leak tightness of the north pool, but the south pool would be

, unaffec ted . Fuel is not stored in the north pool during cask handlinc ,

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operations.

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! In the unlikely event that outleakage from the north pool exceeded makeup

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capability, the prompt installation of a barrier in the divider wall "notch" (

would ensure that an adequate icvel of water was maintained over the '

spent fuel stored in the south pool. We find the proposed barrier to be acceptable.

i To preclude a cask drop directly.into or tumbling into the south pool,  :

' the licensee has instituted operating procedures, and has proposed the installation of limit switches on crane travel. We have determined that

• this modification as well as the proposed surveillance reouirements are j

acceptable. Moreover, the licensee has shown that no critical systems j

could be affected by a cask drop, and that the factors of safety in the crane i

reduce the probability of a cask drop accident, caused by a system failure,  ;

j to a very low value. The Technical Specification limit on the' weight of the cask that nay be used provides additional assurance that the validity of 4

these findings will be maintained. Consequently, we have found the spent ,

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fuel cask drop accident analysis and associated design changes and proposed '

Technical Specifications are accep*able.-

l i Environmental Finding I I t t

We have determined that the amendnent does not authorize a change in *

[ effluent typer, or total amounts nor an increase in power level and will not result in any significant environmental impact. ~Having made this -

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l. determination, we have further concluded that the scendment involves an 4 i j 1 . ..

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. i action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR 551.5(d)(4) that an 9' nviron= ental statement, negative declaration, or environmental inpadt appraisal need not be prepared

. in connection with this issuance of this amondment.

Conclusion .

I We have concluded, bas'd e on the considerations discussed above, that:

(1) because the change does not involve a significant increase in the probability or consequencea of accidents,previously considered and does not involve a significant decrease in a safety margin, the change does not involve a significant hazards consideration, (2) there is reasonabic assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security

! or to the health and safety of the public.

Dated:

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UNITED STATES' NUCLEAR RECULATORY COMMISSION-f . '. .

. DOCKETS NOS. 50-266 AND 50-301-i WISCONSIN ELECTRIC POWER COMPANY _

WISCONSIN MICHIGAN POWER COMPANY

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NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY

0PERATING LICENSES Notice is hereby given that the U.S. Nuclear Regulatory Commission (the Commission) has issued Amendments Nos. 18 and 23 to Facility Operaciag Licenses Nos. DPR-24 and DPR-27 issued to Wisconsin Electric Power Company and Wisconsin Michigan Power' Company, which revised Technical Specifications 1 for operation of the Point Beach Nuclear Plant Units Nos. 1 and 2, located i

in the town of Two Creeks, Manitowoc County, Wisconsin. The amendments are effective as of the date of issuance.

The amendment will,' change the Technical specifications to (1) add

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• surveillance requirements for the limit switches associated with the auxiliary building crane trolley and bridge motions and (2) establish the maximum weight of the spent fuel shipping cask that may be used.

The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as auended (the Act), and l the Commission's rules and regulations. The Commission has made i

I appropriate findings as required by the Act and the Commission's rules j

and regulations in 10 CFR Chapter I, which are set forth in the license

] f amendments. Prior public notice of t.hese amendments was not required since

] the amendments do not involve a 'significant hazards consideration.

j The Commission has determined that the issuance of these amendments

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will not result in any significant environmental impact and that pursuant

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to 10 CFR 551.5(d)(4) an environmental statement, negative declaration or environmental impact appraisal need not be prepared in connection with issuance of these amendments.

For further details with respect to this action, see (1) the application for amendments dated May 13, 1976, (2) Amendment No. 18 to License No. DPR-24, (3) Amendment No.'23 to License No. DPR-27, and (4) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street N.W., Washington, D. C. and at the University of Wisconsin -

Docu=ent Department. ATIN: Mr. Arthur M. Fish, Stevens Point Library, Stevens Point, Wisconsin 54481.

A copy of itens (2) and (4) may be obtained upon request addressed I

to the U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, Attention: Director, Division of Operating Reactors.

Dated at Bethesda, Maryland this day of FOR THE NUCLEAR REGULATORY Com!ISSION George Lear, Chief 6

Operating Reactors Branch #3 Division of Operating Reactors l

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