ML20125D203

Application for Amend to License DPR-40,consisting of Proposed TS 2.8,3.2,4.4.2,5.10.3 & Figure 2-10 Re Storage Capacity of Spent Fuel Pool

ML20125D203
Person / Time
Site:	Fort Calhoun
Issue date:	12/07/1992
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20125D184	List: LIC-92-0340, Forwards Application for Amend to License DPR-40,revising TS to Provide for Addl Storage Capacity in Spent Fuel Pool & Licensing Rept for Spent Fuel Storage Capacity Expansion ML20125D203 ML20125D223 ML20125D226
References
NUDOCS 9212150048
Download: ML20125D203 (8)

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i BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION ,

In the Matter of p i

Omaha Public Power District i Docket No. 50-285 (Fort Calhoun Station h Unit No. 1)- ll APPLICATION FOR AMENDMENT OF OPERATING LICENSE Pursuant to Section - 50.90 - of: the regulations of the: U._ S. Nuclear Omaha Public Power District holder of Regulatory Facility Operating Commission License No. ("the Commission"), herewith ; requests that the,: Technical-DPR-40,--

Specifications set forth in Appendix A to that License be' amended to provide for '

additional storage-capacity in the-Spent Fuel.Poolifor the Fort Calhoun Station Unit No. 1. 1 The proposed chan A to this Application.ges A inDiscussion,-Justification Technical Specifications and are No.Significant provided in Attachment Hazards Consideration Analysis, which demonstrates that the -proposed changes- do -not involve significant hazards considerations -.is appended in Attachment- B. The proposed: changes in specifications would not-authorize any changerin the; types or any increase in the amounts of: effluents or a change.in the1 authorized power:

level of the facility.

(Table < WHEREFORE,

3-5), 4.4, 5.10;3, ApplicantFiresand:pectfully requests that Specifications '2.8,"3.2 License- No. DPR-40. be amended'inthe gure-form 2-10attachedof Appendix hereto=as A to- Facility 0perating Attachment.A~.

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1 2-A copy of this Application, including its attachments, has been submitted to the Director - Nebraska State Division of Radioleyical Health, as required by 10 CFR 50.91.

OMAHA PUBLIC POWER DISTRICT By Vice President-Subscribed and sworn to before me this day of December,1992.

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hik stEMt souny.ste g m Notary Public (T M n a t.c m Mrcean C -/i4TL' lll \,,\, , , , . -

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. Regulatory Conunission ATTACHMENT A

2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Operations (Continued)

(6) Direct communication between personnel in the control room and at the refueling machine shall be available whenever changes in core geometry are taking place.

(7) When irradiated fuel is being handled in the auxiliary building, the exhaust ventilation from the spent fuel pool area will be diverted through the charcoal filter.

(8) Prior to initial core loading and prior to refueling operations, a complete check out, including a load test, shall be conducted on fuel handling cranes that will be required during the refueling operation to handle spent fuel assemblies.

(9) A minimum of 23 feet of water above the top of the core shall be maintained whenever irradiated fuel is being handled.

(10) Storage in Region 1 and Region 2 of the spent fuel racks shall be restricted to fuel assemblies having initial enrichment less or equal to 4.02 weight percent of U-235.

(11) Storage in Region 2 of the spent fuel racks shall be restricted to those assemblies whose parameters fall within the " acceptable" regioniUea of Figure 2-10. Storags in the"psriphiral hellf0f._R'ehioifj2~shall_ beirestricted_ to'those issemblics whose parameters [ fall'withinLthe noted are{of Figure 2-10j 7

(12); Wmiisin brii'borbn 66tidentrstionlof7100" ppm shhllibe~ maintained in the~ Spent Fuel Pool.whenever-storing 1unitradiatedl fuel in the SpentLFuel Pool; If any of the above conditions are not met, all refueling operations shall cease immediately, work shall be initiated to satisfy the required conditions, and no operations that may change the reactivity of the core shall be made. However, refueling operations may commence and continue with less than 5 containment atmosphere and plant ventilation duct radiation monitors provided that gross, particulate and iodine monitors are monitoring the stack effluent. These three plant ventilation duct radiation monitors will initiate closure of the containment pressure relief, air sample and purge system valves and shall employ a one-out-of-three logic for the initiation of VIAS.

The spent fuel assembly may be transferred directly from the reactor core to the spent fuel pool Region 2 provided the independent verification of assembly burnups as dched in Special Procedure SP-BURNUP-1 has been completed and the assembly burnup meets the acceptance criteria identified in Technical Specification Figure 2-10.

Irradiated fuel movement shall not be initiated before the reactor core has decayed for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the reactor has been operated at power levels in excess of 2%

rated power.

Ituis The equipment and general procedures to be utilized during refueling operations are discussed in the USAR. Detailed instructions, the above specifications, and the design of the fuel handling equipment incorporating built-in interlocks and safety features provide assurance that no 2-38 Amendment No. 5,94,25,43,75,+33, 4

SPENT ~UEL .000L REGION 2 STORAGE CRITE' A Minimum Recuirea Fuel Assemoly Exoosure os a function f initici Enrienment to Permit Storage in Region 2 40.0 2 37.5 N I I I

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, I Acceo te W/0 CEA e in ecion 2 '

a 4_ .0 ll l -j/

. I 77 5 25 0 -.

w 22.5 l l l /

.h 20.0 / /\ '

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, ,' 3 '

/ / Accktable WITH CEA

/ iNRegion 2 u 15.0 '

$ 12.5 10 5 ,.0 /

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5.0 / l T acceptable p' in Region 2 2.5 0.0 / \

20 2.25 2.50 2.75 3.00 3.25 3.50 3.75 4.00 N25 4.50 Assembly initial Enrichment, w/o U-235

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SPENT FUEL POOL REGION 2 OMAHA PUBLIC POWER Dl STRICT STORAGE CRITERIA FIGURE FORT CALHOUN STATION-UNIT No.1 2-10 Amencment No.16,133 I

PROPOSED FIGURE 2-10 37500 35000 :

32500 :

30000 :

j' A LE

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27500

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j BURNUP DOMAIN ,

r 25000 f

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s 22500 ~

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$ 20000

& C84l. s'4' g 17500 _i ,e '

d 15000 '

2 12500 5 d f' e

!, M'/

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10000 s

! UNACCEPTABLE 7500 : , BUENUP DOMAIN 5000

, ( Re autres Region 1 Storage) j 2500 :

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0:./... ,,,, ,,,, , ,, ,,,, ,,,, ,,,,

1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 INITIAL ENRICHMENT, wt% U235 I

LIMITING BURNUP CRITERIA FOR ACCEPTABLE STORAGE IN REGION 2

, NOTE: 1. Any fuel essembly ( 24.2% U235 overage) mechanically coupled with a full length CEA may be located engwhere in Region 2.

2. Peripheral cells are those odjacent to the Spent Fuel Pool well or the cesk leydown oree.

2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Operations (Continued) incident could occur during the refueling operations that would result in a hazard to public health and safety,* Whenever changes are not being made in core geometry one flux monitor is sufficient. This permits maintenance of the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition. The shutdown cooling pump is used to maintain a uniform boron concentration.

The shutdown margin as indicated will keep the core suberitical even if all CEA's were withdrawn from the core. During refueling operations, the reactor refueling cavity is filled with approximately 250,000 gallons of borated water. The boron concentration of this water (of at least the refueling boron concentration) is sufficient to maintain the reactor suberitical by more than 5%, including allowance for uncertainties, in the cold condition with all rods witndrawn.m Per. odic checks of reiueling water boron concentration ensures the propa shutdown niargin. Communication requirements allow the control room operator to inform the refueling machine operator of any impending unsafe condition detected from the main control room board indicators during fuel movement.

In addition to tne above engineered safety features, interlocks are utilized during refueling operations to e"ure safe handling. An excess weight interlock is provided on the lifting hoist to prevent movement of more tnan one fuel assembly at a time. In addition, interlocks on the auxiliary building crane will prevent the trolley from being moved over storage racks containing irradiated fuel, except as necessary for the handling of fuel. The restriction of not moving fuelin the reactor for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the power has been removed from the core takes advantage of the decay of the short half-

life fission products and allows for any failed fuel to purge .tself of fission gases, thus reducing the consequences of fuel handling accident.

The ventilation air for both the containment and the spent fuel pool area flows through absolute particulate filters and radiation inonitors before discharge at the ventilation discharge duct. In the event the stack discharge should indicate a release in excess of the limits in the technical specifications, the containment ventilation flow paths will be closed automatically and the auxiliary building ventilation flow paths will be closed manually. In addition, the exhaust ventilation ductwork from the spent fuel storage area is equipped with a charcoal filter which will be manually put into operation whenever irradiated fuel is being handled.m Thelbasis'foFths;1.00)i inib 6ro666nceiXratiodjequireinsstMith'B6;rallpaisoned storage racksfisitoimai' ntainitheMbelovF0_.95;inj the{eventf almisplaced unirradiated fuel sssestilyfis/locitsdsneitLtola spentsf6ellasseinbly.i;Wmisplaced unirradiatedff6el

' ssemblylsfi.2%/d e'nrichmenicondition/ihiihe; absence of soluble poiso_n,.may result a

in exceeding the designTeffective stultiplicationlfactorRSoluble boron.ih the! Spent Fus!

P6olMaterf forMhich*cledit'iipermitted under 'thsse"conditiohsFwould assurelthatlthe 2

sffective sultiplisationfactor;is msintainsdlsubstantially1ess thunftheldesigircondition!

The bbroniconcestration'is pepodicallyisamp]ed in:accordanceLwith Specification 3.2;