ML20043J022

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Submits Info in Support of Tech Spec Change Request 175,Rev 1,Suppl 1 Re Spent Fuel Pool Storage Capacity at Plant
ML20043J022
Person / Time
Site: Crystal River Duke energy icon.png
Issue date: 06/21/1990
From: Beard P
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0690-05, 3F690-5, NUDOCS 9006270209
Download: ML20043J022 (3)


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1' C O R P 0 H A16 0 N .

June 21, 1990 3F0690-05 ,

l p U.S. . Nuclear Regulatory Commission ]

Attn Document Control Desk )

1. Washington, D. C. 20555 I '

Subject:

Crystal River Unit 3 )

Docket No. 50-302 i Operating License No. DPR-72 ]

Technical Specification Change Request No. 175 l

, Revision 1, Supplement 1 l spent Puel Pool Storage capacity 'l

Dear Sir:

l Florida Power Corporation's (FPC) October 31, 1989 letter submitted l Technical Specification Change Request No. 175 requesting an l

. increase in the capacity of spent fuel storage pool "B". The "B" L pool currently has 120 locations and after the rerack it will have-li 815 locations, for a net increase of 695. Section 5.1.5 of that letter stated in part  ;

i "section 2.2.4.2 contains a description of the following- 1

. considerations:- ...whether there will be any significant increase in the amount of heat release to the environment.

As discussed in section 2.2.4.2, the proposed increase in .,

storage capacity will-result in an insignificant impact on the environment."-

L This . letter 'is submitting information to support the above statement.

The effect of increasing Crystal River 3 (CR-3) storage capacity ,

.is shown in the attachment to this letter. A base case (Table 1) was calculated using the' current spent fuel pool configuration (120 ' l locations in "B" pool and 542 locations in "A" pool for a total of 662 assemblies). The following assumptions were used: a complete core off load to the pools at three days; a two year refueling 9006270209 900621 DR ADOCK 0500 j2 60\

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" POST OFFICE BOX 219

  • CRYSTAL RIVER, FLORIDA 326294J219 * (904) 7954486 k \\

A Florida Progress Company

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June 21, 1990 3F0690-05 l Page 2 l

l cycle; a seventy-six (76) assembly reload batch size; and an l-irradiation period of 1650 days. The decay heat load was calculated

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using ANS 5.1-1979 " Decay Heat Power in Light Water Reactors". The i l heat load generated by the current 662 assemblies is 8.059 Megawatt )

Thermal (Mwt). The second case (Table 2) involved the 695 l' additional assemblies after rerack.

L Using the same assumptions mentioned above, the heat load generated

l. by the additional 695 assemblies discharged over 10 years is only 0.47 Mwt. ' Summing this value to the base value of 8.859 Mwt gives a total heat load discharged to the environment of 9.329 Mwt.

The maximum heat discharged from the plant occurs during normal l plant operations. Assuming a plant efficiency of 34% and a l licensed power level of 2544 (Mwt), the heat discharged to the J environment is 1679 Mwt. Thus, the total heat discharged from the l 695 additional assemblies (or the 1357 total assemblies) is  !

l insignificant compared to the heat discharged during normal plant i L operations.

l I

sincerely, l

Yb\

M.. Beard, Jr.

Serior Vice President l

Nuclear Operations l

Attachment PMB/GMF Regional Administrator, Region II

)xc: Senior Resident Inspector l

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June 21, 1990-

'3F0690-05 Page 3 EEAT DISCRARGED TO TER ENVIRONMENT Table 1 - Base Case Assembly Reload Batch Individual Size Assembiv (Kwt) (Mwt) 177 Assemblies 9 3 Days = 8.400 76 Assemblies @ 2 Years- x 1.909 = 0.145' 76 Assemblies 9 4 Years x 1.000 = 0.076 76 Assemblies 9 6 Years x 0.802 = 0.061 76 Assemblies 0 8 Years x 0.729 = 0.055 76 Assemblies 9 10 Years x 0.678 = 0.051 121 Assemblies @ 10 Years x 0.678 = 0.071 Totalt 662 8.859 Table 2 - Rerack Case 662 Assemblies = 8.859 Mwt eigh Assemblies @ 10 Years = 0.470 Mwt Totalt 1357 Assemblies 9.329 Mwt

  • NOTE: .The additional 695 assemblies would have to come from cycles beyond 10 years, therefore 10 years is conservative.

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