ML17037C173

Submittal of Requested Additional Information Concerning Proposed Modification to the Spent Fuel Pool

ML17037C173
Person / Time
Site:	Nine Mile Point
Issue date:	01/07/1976
From:	Rhode G Niagara Mohawk Power Corp
To:	Lear G Office of Nuclear Reactor Regulation
References
Download: ML17037C173 (30)

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NRC DISfF 3TION FOR PART 60 DOCKET IVIA

.AXIAL

{TEMPORARY FORM) e CONTROL NO:

FILE W

FROM. Niagara Mohawk Power Cor

Syracuse, N.Y~

13202 Gerald K. Rhode

'ATE OF DQC 1-7-76 DATE R EC'D 1-9-76 LTR fWX OTHER TO:

Mr. George Lear CLASS UNCLASS PROPINFO ZZX ORIG lsigned INPUT CC OTHER NO CYS REC'D 1

SENTNRc PDR zx SENT LOCAI PDR~X DOCKET NO:'0-220 DESCRIPTION:

Ltr trans the following:

ENC LQSU R ES:

Addi info honcerning the proposed modification-to the Spent Fuel-

, Pool at Nine Mile Pt. Unit 1 'Plant:...

PLANT NAME ine Mile'Pt. Unit 1 Plant

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Regula Doclgk Fj NIAGARAMOHAWKPOWER CORPORATION p))~I ~m, NIAGARA l+)

MOHAWK 300 ERIE BOULEVARD WEST SYRACUSE. N. Y. 13202 January 7, l976 Director of Nuclear Reactor Regulation Attn:

Mr. George Lear, Chief Branch j/3 U. S. Nuclear Regulatory Commission

&washington, D. C.

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6'b Re:

Nine Mile Point Unit l Docket: No. 50-220

Dear Sir:

Your recent telecommunication requested additional f

information concerning the proposed modificati on to the Spent Fuel pool at Nine Mile point Unit l.

The attached information addresses itself to your request.

Very truly yours, NIAGARA MOMWK POVER CORPORATION GERALD K.

ODE Vice President ngineering MGM/sz Attachment

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Regulatory Docket file 1.

Question 4%4Ai>y~-

h'hat are the specific needs that require increased storage capacity in the spent fuel pool (SFP)?

Include in the response:

a) status of contractual arrangements, if any, with fuel storage'r fuel-reprocessing facilities, and b) proposed refueling schedule.

R~es esse The following table shows the present plans wi th regard to refuelings at Nine Mile Point Unit 1, through 1981.

Bundles Dischar ed Bundles in Pool 9/75 3/77 9/78 3/80 9/81 160 170 170 170 500 660 830 1000 1170 The present storage capacity of 800 bundles will be exhausted following the March 1977 refueling.

The proposed expansion would provide storage for 2140 bundles, enabling sufficient capaci ty until the 9/81 refueling.

Niagara Mohawk does not presently have any contracts for off-site storage or reprocessing of spent fuel.

Negotiations are in process with Allied General Nuclear Services QGNS) for storage and reprocessing services.

However, it is unli J'eely that these services would relieve the short-term problem.

jy WA 1'

2.

Question What is t'e total construction cost associated with the proposed modification of the SFP storage facilities?

R~es ense The total construction cost associated with the proposed modi-fication of the spent fuel storage facilities is estimated to be

$175,000.

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Question What are the alternatives to increasing the storage capacity of the SFP?

The alternatives considered should include:

a) shipment to a fuel reprocessing facility b) shipment to another reactor site c) shutting down the reactor The discussion of options (a) and (b) should i nclude a cost comparison in terms of dollars per KgU stored.

The discussion of (c) should include t'e cost for providing replacement power either from within or outside the licensee's generating system.

~Res ense At the present time spent fuel storage space is unavailable at reprocessing facilities.

This situation is not likely to change in the near future.

However, ifit were to change, the associated cost would be

$700,000 through 1981.

This is based on a cost of

$10 per year for each kilogram of uranium.

Each of the 370 bundles requiring storage contains approximately 190 kilograms of uranium.

Niagara Mohawk believes it highly unlikely that shipment to another reactor site would be practical, since many other utilities are experiencing similar storage problems.

I'f such an alternative were available, additional shipping charges of g5-$ 25/KgU would be incurred as compared to shipping directly to a reprocessor.

Storage charges imposed by the other reactor site would also be incurred.

The added shipping charges for the 370 bundles would be over

$1,000,000.

Two other storage alternatives, which would not be availablc for the short term, are as follows:

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Construction of a separate fuel storage facility (1981) 2.

Nine Mile Point Unit 2 spent fuel pool (late 1981)

.......Response Conti nucd

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~Ree once (Cont'd)

Nine Mile Point Unit 1 supplies approximately 18 percent of t'e Niagara Mohavk syst'm load. If the unit vere to be shut

down, 300 PN(e) of replacement capacity would have to be purchased, using 1979 as a representative year.

The estimated cost of this is $11,800,000 per year. based on a purchase rate of $36,500/Mfd/year.

In addition, the energy from 600 IW(e) of generating capaci ty would be required from our present oil burning uni Cs, at 25-30 mills/kvhr.

Tne resulting total addi tional cosC Co replace Nine Mile Point Unit 1 would be approxi mately

$100,000,000/yr.

4.

Question Provide data on the empty weight of the new storage racks and the associated neutron absorbing racks if any are used.

Discuss t'e kinds and quantities of materials that would be used in the proposed modification, for example, the amounts of 'stainless steel or boral.

sees ense The empty weight of the new spent fuel storage racks is 1850 pounds.

A list of materials used in the racks is included in the following table.

Spent Fuel Rack Materials Part Name Lifting Lug End Channel Column Tube Numeral Channel Tube Divider Base Guide Block Materi al ASTM 8209, 8211, or 8221 Alloy 6061-T6 Alum.

ASTM 8221, Type 6063-T5 Alum; Extrusion ASTM 8221, Type 6063-T5 Alum. Extrusion ASTM 8221, Type 6061-T6 Alum.

ASTM 826-SG70A-T51 or ASTM 8108-SG70A-T6 ASTM 8221, Type 6061-T6 Alum.

ASTM 8221, Type 6061-T6 Alum.

ASTM 8108 Alloy SG70A-T6 ASTM 8108 Alloy SG70A-T6 ASTM 8209, 8211, or 8221 Alloy 6061-T4, or T6, or 6063-T5 ASTM 8209, Type 6061-T6

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Question What would be the additional time period that spent fuel assemblies could be stored onsi te. as a result of the proposed expansion?

R~es onse The proposed expansion of'he spent'uel pool would enable bundles to be stored for about an additional three years.

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Question (that would be the'additional heat load and the anticipated maximum temperature of the water in the SFP which would result from the proposed expansion7 R~es ense Our letter of October 31, 1975 to Hr. George Lear contains the requested heat load and temperature analysis.

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Ques tion How much additional solid waste would result from the proposed expansi on?

R~es oose Approximately six additional drums of solid waste would be generated annually because of the proposed modification of the spent fuel pool.

This additional waste is expected due t'o the more frequent filter changes which would be required for t'e spent fuel pool filtering and cooling system.

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Question Provide data on the quantities of Krypton-85, Tritium, and Zodine-131 Chat have been measured as releases t'o the environ-ment from Che fuel building ventilation system during each year from the last three years.

Xf data are not available from the ventilation system, provide dat'a measured from the overall plant.

R~es onsa The spent fuel pool is located in t'e Reactor Building at Nine Mile Point Unit 1.

Since all building ventilation air is routed t'o the stack, data on the request'ed isot'opes is avail-able only on an overall plant basis.

The follovingis a tabulation of'he overall plant stack releases for the period 1972-74.

Kr-85m Annual Curie Releases Tri Ci um X-131 1972 1973 1974 4.03 x 10 6 x104 4.3 x 104

18. 26 26.75 26.98 0.8934 1.962

0. 72 The vast majori Cy of these'eleases is attributed t'o the offgas system.

The spent fuel pool contribution to the tot'al is very small.

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Question What would be the maximum radionuclide concentrat'ion (u Ci/cc) in the SFP as a result of 0he proposed expansion?

Estimate the incremental dose rate above the surface of the SFP that vould result from t'e proposed modification.

Estimate the increased annual occupational man/rem exposure based on operations performed by personnel in the pool vicinity.

Response

The maximum radionuclide concentration expected in the expanded spent fuel pool vould be l0 ~ uCi/cc.

Most of the dose rate contributi on above the pool is due to activity in the vater from bundles recently discharged.

Since the proposed expansion vould not increase this number, the incremental dose rate above the pool vould be insignificant because of the expansion.

Presently the dose rate above the pool is controlled to bet'veen 5-20 mr/hr, by frequency of change of the spent fuel pool filter.

This policy is expected to continue with the proposed expansion.

Therefore, no increased occupati onal exposure is anticipated due t'o personnel working in t'e pool vicinity.

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Question Discuss the effect of'he proposed modification on the ef-ficiency of'he filter system in t'e fuel storage building.

~Res ense No significant change is anticipated in the efficiency of the filter system due to the proposed modification of the spent fuel pool.

Additional solid waste would be produced,

however, as detailed in the response to Question j/7, above.

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Question Discuss potential fuel handling and fuel cask accidents and address the resultant doses that could ensue from such accidents relative to the expanded SFP.

R~es oose Our letters of October 31, 1975 and November 25, 1975 to Hr.

George Lear discussed a worst case potential accident, and resultant

doses, from dropping a heavy object into t'e pool.

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Question Discuss the way in vhzch the original spent fuel storage racks would be removed and disposed of or stored.

R~es onse The proposed modification involves the addition of seventeen spent fuel storage racks.

All of the existing racks vill remain in the pool.

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