ML20216F824

Submits Response to NRC Request for Addl Info Re Assessment of Loss Water from Spent Fuel Pool at Decommissioned Plant

ML20216F824
Person / Time
Site:	Maine Yankee
Issue date:	04/13/1998
From:	Zinke G Maine Yankee
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GAZ-98-23, MN-98-27, TAC-MA0659, TAC-MA0660, TAC-MA659, TAC-MA660, NUDOCS 9804170256
Download: ML20216F824 (49)

Text

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MaineYankee RO. box 408 + WISCASSET, MAINE 04578 * (207) 882-0321 April 13, 1998 MN-98-27 GAZ-98-23 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington, DC 20555

Reference:

(a) License No. DPR-36 (Docket No. 50-309)

(b) Letter: M. J. Meisner to USNRC: Request for Exemption From the Financial Protection Requirement Limits of 10CFR50.54(w) ed 10CFR140.11: MN-98-01, dated January 20, 1998 (c) Letter: USNRC to M. J. Meisner: Request for Additional Information For Exemption From Financial Protection Requirerrent Limits (TAC Nos. MA065P a d MA0660; dated April 9, 1998

Subject:

Response to NRC Request for Additional Information For Exemption From Financial Protection Requirement Limits: (TAC Nos. MA0659 and MA0660)

Gentlemen:

In Reference (b), Maine Yankee submitted a request for exemption from the financial protection requirement limits of 10CFR50.54(w) ar.J 10CFR)40.11. In Reference (c),

NRC requested additional information that the NRC believes is necessary to assist in reviewing the licensing requests.

In response to Item No. 43, we are attaching a decay heat curve which properly represents the total spent fuel pool decay heat generation of the Maine Yankee fuel.

We strongly urge the NRC to use this curve rather than the generic one found in the Branch Technical Position.

In reviewing Reference (c), we find that a number of requested parameters were not required as a part of Maine Yankee's analysis or are inherently included as a standard subroutine in the analytical techniques utilized (see Attachment 11 to Reference (b)). Those parameters that fall into this classification are request nos. 2, 12, 13, 15-20, 22, 23, 26-36, 38, 39, and 42-44. In each case, we have attempted to provide the best answer available; however, we are limited to the work being done in response to this RAI. With respect to those requests dealing with the properties of materials, we have derived these values from engineering texts, the internet and vendor information. These derived values may not necessarily agree with subroutine values.

t 9804170256 980413 IkU PDR ADOCK 05000309 H PDR

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l. MaineYankee i UNITED STATES NUCLEAR REGULATORY COMMISSION MN-98-27 Attention: Document Control Desk Page Two l

The designated point of contact for this information is Mr. Robert P. Jordan, )

Manager, Engineering Analysis, (Phone No. (207) 882-5688). If you have any i questions, please contact us.

Very truly you s,

[ bb George A. Zinke, Director Nuclear Safety & Regulatory Affairs I c: Mr. Hubert Miller Mr. Mike Webb Mr. Mike Masnik Mr. Singh Bajwa Mr. R. A. Rasmussen Mr. Clough Toppan 1 Mr. Patrick J. Dostie Mr. Uldis Vanags l

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ATTACHMENT RESPONSE TQ RE0 VEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT

1. Location (region) in pool (if applicable): See Table 1 (Spent Fuel Pool (SFP)

Region Stored)

2. Number of assemblies per batch: See Table 1 below

3. Fuel burnup (MWD /MTU): See Table 1 below (Batch Average)

4. Enrichment (%): See Table 1 below (Batch Average)

5. Metric tons of uranium per assembly (MTU): See Table 1 below (Batch Average)

6. Batch discharge date: See Table 1 below TABLE 1 Batch Number of SFP Fuel Enrichment Metric tons of Final No. assemblies Region Burnup  % Uranium per Discharge Stored MWD /MTU assembly Date MTU 0100010 12 11 10611 2.027 0.393887 06/29/74 0101010 56 II 11912 2.407 0.358295 06/29/74 I 2.944 0102010 2 6522 0.395219 06/29/74 0103010 1 I 10470 2.957 0.368196 06/29/74 0104010 1 1 10359 2.957 0.358808 06/29/74 0100011 57 II 15695 2.023 0.393993 05/02/75 0101011 24 II 15994 2.410 0.358201 05/02/75 0102011 22 I 8565 2.947 0.394659 05/02/75 I - 20 0103011 35 13330 2.950 0.367985 05/02/75 II - 15 0104011 7 11 14884 2.953 0.358410 05/02/75 0110011 2 1 2769 2.341 0.395455 05/02/75 0111011 2 II 4316 1.938 0.395323 05/02/75 0112011 2 II 5058 1.930 0.386173 05/02/75 0113011 1 II 5150 2.006 0.380050 05/02/75 0110030 12 11 15850 1.938 0.395273 07/14/78 0111030 53 II 16223 1.935 0.386436 07/14/78 0200020 69 II 18042 1.950 0.389669 04/09/77 Page 1

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ATTACfNENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT TABLE 1 8atch Number of SFP Fuel Enrichment Metric tons of Final No. assemblies Region Burnup  % Uranium per Discharge Stored MWD /MTV assembly Date MTU 0201020 1 II 20434 2.515 0.354183 04/09/77 0200030 12 II 29423 2.517 0.353782 07/14/78 0201030 28 II 24409 2.887 0.389028 07/14/78 0202030 12 11 28842 2.884 0.372158 07/14/78 j 0203030 16 II 29262 2.884 0.363271 07/14/78 0200040 61 II 29696 2.517 0.353710 01/11/80 l 0201040 12 11 33193 2.888 0.389409 01/11/80 0200050 1 11 28070 2.506 0.351636 05/08/81 0200060 1 II 28812 2.524 0.352289 09/24/82 0200070 1 II 30476 2.517 0.354361 03/31/84 l 0200080 1 II 31865 2.530 0.353373 08/17/85 I

l 0200090 1 11 33819 2.517 0.354368 03/28/87 '

0200100 1 11 33676 2.518 0.353516 10/15/88 0300050 16 II 31944 2.741 0.388814 05/08/81 l

0301050 4 II 33035 2.744 0.379997 05/08/81 0302050 12 II 33687 2.738 0.380382 05/08/81 0303050 40 II 31461 3.036 0.387765 05/08/81 0400060 48 II 31912 3.035 0.388812 09/24/82 0401060 24 II 35405 3.032 0.378882 09/24/82 0500070 48 II 32726 3.003 0.381481 03/31/84 0501070 4 II 38235 3.003 0.372852 03/31/84 0502070 20 II 34873 3.003 0.363991 03/31/84 0600080 48 II 35509 3.002 0.380831 08/17/85 0601080 4 II 38341 3.004 0.371499 08/17/85 Page 2

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, l 6II6CHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT TABLE 1 l Batch Number of SFP Fuel Enrichment Metric tons of Final l

No. assemblies Region 8urnup  % Uranium per Discharge l Stored MWD /MTU assembly Date l MTU i

0602080 20 II 35685 3.002 0.363157 08/17/85 ,

0700090 8 II 39684 3.288 0.379564 03/28/87 0701090 12 11 41717 3.288 0.371060 03/28/87 0702090 40 11 35804 3.288 0.362447 03/28/87 0703090 4 II 41988 3.288 0.354176 03/28/87 I

0700110 8 II 36536 3.288 0.379415 04/07/90 0800090 3 II 32218 3.303 0.362029 03/28/87 0801100 28 11 39152 3.303 0.370051 10/15/88 0802100 28 II 39543 3.302 0.361453 10/15/88 0800110 1 II 46045 3.299 0.362537 04/07/90 0800120 1 11 47079 3.300 0.362544 02/14/92 0800130 1 II 44257 3.304 0.361651 07/30/93 0800140 1 II 43206 3.299 0.361722 01/14/95 0800150 8 II 36718 3.301 0.378931 12/06/96 0801150 1 II 38137 3.302 0.361382 12/06/96 0900100 8 II 32305 3.301 0.369564 10/15/88 l

0900110 4 11 40182 3.307 0.388183 04/07/90 l 0901110 24 II 41781 3.303 0.378365 04/07/90 l 0902110 36 II 39721 3.302 0.370192 04/07/90 1000120 20 11 39592 3.502 0.389140 02/14/92 1001120 20 II 45284 3.501 0.379850 02/14/92 1002120 16 II 42939 3.500 0.370907 02/14/92 1000130 8 II 43601 3.496 0.371834 07/30/93 1000140 8 II 39401 3.502 0.389811 01/14/95 Page 3 l

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l ATTACHMENT RESPONSE TO RE0 VEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT l

TABLE 1 Batch Number of SFP Fuel Enrichment Metric tons of Final No. assemblies Region Burnup 1 Uranium per Discharge Stored MWD /MTU assembly Date MTU 1100120 4 11 34250 3.694 0.380873 02/14/92 1100130 28 II 42355 3.690 0.390712 07/30/93 1101130 32 II 44040 3.693 0.380545 07/30/93 1102130 8 II 49241 3.695 0.372789 07/30/93 1200140 36 II 39212 3.684 0.390577 01/14/95 1201140 12 II 46028 3.682 0.382465 01/14/95 1202140 20 II 47923 3.681 0.374061 01/14/95 l

1200150 4 11 40240 3.681 0.381497 12/06/96 '

1300140 4 II 30052 3.702 0.390455 01/14/95 1300150 16 Il 32739 3.702 0.390680 12/06/96 1301150 28 II 36864 3.701 0.381292 12/06/96 1302150 20 II 40535 3.702 0.372285 12/06/96 1400150 8 I 21222 3.918 0.391319 12/06/96 I - 16 1401150 28 24838 3.906 0.381947 12/06/96 I-4 1402150 36 25643 3.895 0.373550 12/06/96 1500150 8 I 7340 3.742 0.390342 12/06/96 1501150 32 I 9340 3.739 0.389643 12/06/96 1502150 28 1 9905 3.740 0.389498 12/06/96 l Page 4

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ATTACHMENI BESEQNSE TO RE0 VEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT Each Batch:

). Spent fuel array parameter (i.e. 16x15. 7x7): See Table 2

8. Number of active fuel rods per assembly: See Table 2

9. Outside rod diameter of the fuel (m): See Table 2

10. Rod center-to-center pitch (mi: See Table 2

40. Length of active fuel (m): See Table 2 I

TABLE 2 Batch Spent Fuel No. of Outside rod Rod center- Length of Array active fuel diameter of to-center active fuel Parameter rods per the fuel pitch (m) assembly (m) (m) 0100010 14 x 14 176 0.011176 0.014732 3.47218 0101010 14 x 14 160 0.011176 0.014732 3.47218 0102010 14 x 14 176 0.011176 0.014732 3.47218 0103010 14 x 14 164 0.011176 0.014732 3.47218 0104010 14 x 14 160 0.011176 0.014732 3.47218 0100011 14 x 14 176 0.011176 0.014732 3.47218 0101011 14 x 14 160 0.011176 0.014732 3.47218 l

0102011 14 x 14 176 0.011176 0.014732 3.47218 l

0103011 14 x 14 164 0.011176 0.014732 3.47218 l

0104011 14 x 14 160 0.011176 0.014732 3.47218 l 0110011 14 x 14 176 0.011176 0.014732 3.47218 0111011 14 x 14 176 0.011176 0.014732 3.47218 0112011 14 x 14 172 0.011176 0.014732 3.47218 0113011 14 x 14 171 0.011176 0.014732 3.47218 0110030 14 x 14 17' O.011176 0.014732 3.47218 0111030 14 x 14 172 0.011176 0.014732 3.47218 0200020 14 x 14 176 0.011176 0.014732 3.47218 Page 5

ATTACHMENT RESPONSE TO RE0 VEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT TABLE 2 Batch Spent Fuel No. of Outside rod Rod center- Length of Array active fuel diameter of to-center active fuel Parameter rods per the fuel pitch (m) assembly (m) (m) 1 0201020 14 x 14 160 0.011176 0.014732 3.47218 0200030 14 x 14 160 0.011176 0.014732 3.47218 0201030 14 x 14 176 0.011176 0.014732 3.47218 0202030 14 x 14 168 0.011176 0.014732 3.47218 0203030 14 x 14 164 0.011176 0.014732 3.47218 0200040 14 x 14 160 0.011176 0.014732 3.47218 0201040 14 x 14 176 0.011176 0.014732 3.47218 0200050 14 x 14 160 0.011176 0.014732 3.47218 0200060 14 x 14 160 0.011176 0.014732 3.47218 0200070 14 x 14 160 0.011176 0.014732 3.47218 0200080 14 x 14 160 0.011176 0.014732 3.47218 0200090 14 x 14 160 0.011176 0.014732 3.47218 0200100 14 x 14 160 0.011176 0.014732 3.47218 0300050 14 x 14 176 0.011176 0.014732 3.47218 0301050 14 x 14 172 0.011176 0.014732 3.47218 0302050 14 x 14 172 0.011176 0.014732 3.47218 0303050 14 x 14 176 0.011176 0.014732 3.47218 0400060 14 x 14 176 0.011176 0.014732 3.47218 0401060 14 x 14 172 0.011176 0.014732 3.47218 0500070 14 x 14 176 0.011176 0.014732 3.47218 0501070 14 x 14 172 0.011176 0.014732 3.47218 0502070 14 x 14 168 0.011176 0.014732 3.47218 0600080 14 x 14 176 0.011176 0.014732 3.47218 0601080 14 x 14 172 0.011176 0.014732 3.47218 Page 6

ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT TABLE 2 Batch Spent Fuel No. of Outside rod Rod center- Length of '

Array active fuel diameter of to-center active fuel Parameter rods per the fuel pitch (m) assembly (m) (m) 0602080 14 x 14 168 0.011176 0.014732 3.47218 0700090 14 x 14 176 0.011176 0.014732 3.47218 0701090 14 x 14 172 0.011176 0.014732 3.47218 0702090 14 x 14 168 0.011176 0.014732 3.47218 0703090 14 x 14 164 0.011176 0.014732 3.47218 0700110 14 x 14 176 0.011176 0.014732 3.47218 l 0800090 14 x 14 168 0.011176 0.014732 3.47218 0801100 14 x 14 172 0.011176 0.014732 3.47218 l 0802100 14 x 14 168 0.011176 0.014732 3.47218 0800110 14 x 14 168 0.011176 0.014732 3.47218 0800120 14 x 14 168 0.011176 0.014732 3.47218 0800130 14 x 14 168 0.011176 0.014732 3.47218 0800140 14 x 14 168 0.011176 0.014732 3.47218 0800150 14 x 14 176 0.011176 0.014732 3.47218 0801150 14 x 14 168 0.011176 0.014732 3.47218 0900100 14 x 14 168 0.011176 0.014732 3.47218 0900110 14 x 14 176 0.011176 0.014732 3.47218 0901110 14 x 14 172 0.011176 0.014732 3.47218 0902110 14 x 14 168 0.011176 0.014732 3.47218 1000120 14 x 14 176 0.011176 0.014732 3.47218 1001120 14 x 14 172 0.011176 0.014732 3.47218 1002120 14 x 14 168 0.011176 0.014732 3.47218 1000130 14 x 14 168 0.011176 0.014732 3.47218 1000149 14 x 14 176 0.011176 0.014732 3.47218 Page 7

l ATTACHMENT '

RESPONSE TO RE00EST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT TABLE 2 Batch Spent Fuel No. of Outside rod Rod center- Length of Array active fuel diameter of to-center active fuel Parameter rods per the fuel pitch (m) 1 assembly (m) (m) 1100120 14 x 14 172 0.011176 0.014732 3.47218 1100130 14 x 14 176 0.011176 0.014732 3.47218 1101130 14 x 14 172 0.011176 0.014732 3.47218 i 1102130 14 x 14 168 0.011176 0.014732 3.47218 1200140 14 x 14 176 0.011176 0.014732 3.47218 1201140 14 x 14 172 0.011176 0.014732 3.47218 1202140 14 x 14 168 0.011176 0.014732 3.47218 ,

1200150 14 x 14 172 0.011176 0.014732 3.47218

)

1300140 14 x 14 176 0.011176 0.014732 3.46075 1300150 14 x 14 176 0.011176 0.014732 3.46075 1301150 14 x 14 172 0.011176 0.014732 3.46075 1302150 14 x 14 168 0.011176 0.014732 3.46075 1400150 14 x 14 176 0.011176 0.014732 3.40075 1401150 14 x 14 172 0.011176 0.014732 3.46075 l 1402150 14 x 14 168 0.011176 0.014732 3.46075 l

1500150 14 x 14 176 0.011176 0.014732 3.46075 1501150 14 x 14 176 0.011176 0.014732 3.46075 1502150 14 x 14 176 0.011176 0.014732 3.46075 Page 8

ATTACHMENT RESPONSE TO RE0 VEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF FATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT

11. Fuel rack cell / channel dimension (s) (m): See Table 3 (Inner Dimensions) l

12. Thickness of the cell wall (m): See Table 3 l

13. Center-to-center pitch of assemblies (m): See Table 3

14. Diameter of baseplate hole (m): See Table 3

15. Thermal conductivity of the cell walls (W/m-K): See Table 3

16. Specific heat of cell walls (Joule /Kg-K): See Table 3

17. Density of cell walls (Kg/m ): See Table 3 3

TABLE 3 Region Fuel Rack Thickness Center-to- Diameter Thermal Specific Density Cell / channel of the center Pitch of Conductivity Heat of of Cell Dimension (s) Cell Wall of Assemblies Baseplate of the Cell Cell Walls Walls (m) (m) (m) Hole Walls (Joule /Kg- (Kg/m3 ) l (m) (W/m-K) K)

I 0.2256 0.001886 0.265 0.102 Table 3a Table 3a Table 3a 11 0.2256 0.001886 0.229 0.102 Table 3a Table 3a Table 3a The Following Racks are Region I Racks: AA, BB, CC, DD, EE The Following Racks are Region 11 Racks: A,B.C.D,E,F G.H,I,J.M,N,O P.

S.T.U.V.W,X Y.

See Figure 6-1 for Basic Fuel Storage Cell Cell Wall: 304L stainless steel Thickness: 0.0747 in.

l Sheath covering BORAL*- 304L stainless steel Thickness: 0.032 in.

l BORAL" Dimensions: Width: 7.75 0.0625 in. l Length: 140 10.0625 in, i

Thickness: 0.075 0.004 in.

BORAL"- 0.065 in. l i

Aluminum: 2 x 0.005 in.

I TABLE 3a Material Thermal Conductivity Specific Heat of Cell Walls Density of Cell Walls of the Cell Walls (Joule /Kg-K) (Kg/m3 )

(W/m-K) 304L Stainless 18.86 @ 500*F 502.42 7.831 x 103 Steel 21.11 @ 800 F BORAL* 85.9 936 2.481 x 103 Aluminum 162.1 919 2.713 x 103 Page 9

i I ATTACHMENT I RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT 1

18. Thermal conductivity of the fuel (W/m-K): See Table 4 l 19. Specific heat of fuel (J/Kg-K): See Table 4

20. Density of fuel (Kg/m ): See Table 4 2

TABLE 4 Batch Thermal Specific heat Density of fuel Conductivity of of fuel (Kg/m3 )

the Fuel (W/m-K) (J/Kg-K) 500 K 700*K 500"K 700*K 500*K 700 K All 6.86 5.29 279.58 296.93 10890 10830 Batches l l

l l I l \

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ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT

21. Cladding material: See Table 5

22. Thermal conductivity of the clad (W/m-K): See Table 5

23. Specific heat of clad (J/Kg-K): See Table 5

24. Deris1ty of clad (Kg/m 3): See Table 5

25. Thickness of the clad (m): See Table 5 TABLE 5 Batch Cladding Thermal Specific heat of Censity Thickness material conductivity of clad (J/Kg-K) of clad of the clad the clad (W/m-K) (Kg/m3 ) (m) 500*K 700 K 0100010 Zircaloy 15.48 306.9 327.3 6500 0.00066 0101010 Zircaloy 15.48 306.9 327.3 6500 0.00066 l 0102010 Zircaloy 15 48 306.9 327.3 6500 0.00066 0103010 Zircaloy 15.48 306.9 327.3 6500 0.00066  ;

0104010 Zircaloy 15.48 306.9 327.3 6500 0.00066 0100011 Zircaloy 15.48 306.9 327.3 6500 0.00066 0101011 Zircaloy 15.48 306.9 327.3 6500 0.00066 0102011 Zircaloy 15.48 306.9 327.3 6500 0.00066 0103011 Zircaloy 15.48 306.9 327.3 6500 0.00066 0104011 Zircaloy 15.48 306.9 327.3 6500 0.00066

( 0110011 Zircaloy 15.48 306.9 327.3 6500 ~.00066 0111011 Zircaloy 15.48 306.9 327.3 6500 0.00066 0112011 Zircaloy 15.48 306.9 327.3 6500 0.00066 0113011 Zircalcy 15.48 306.9 327.3 6500 0.00066 0110030 Zircaloy 15.48 306.9 327.3 6500 0.00066 l 0111030 Zircaloy 15.48 306.9 327.3 6500 0.00066 0200020 Zircaloy 15.48 306.9 327.3 6500 0.000711 0201020 Zircaloy 15.48 306.9 327.3 6500 0.000711 0200030 Zircaloy 15.48 306.9 327.3 6500 0.000711 Page 11

, . l ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSE.0E WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT TABLE 5 Batch Cladding Thermal Specific heat of Density Thickness material conductivity of clad (J/Kg-K) of clad of the clad the clad (W/m-K) (Kg/m3 ) (m) 500*K 700*K 0201030 Zircaloy 15.48 306.9 327.3 6500 0.000711 0202030 Zircaloy 15.48 306.9 327.3 6500 0.000711 0203030 Zircaloy 15.48 306,9 327.3 6500 0.000711 ,

0200040 Zircaloy 15.48 306.9 327.3 6500 0.000711 0201040 Zircaloy 15.48 306.9 327.3 6500 0.000711 0200050 Zircaloy 15.48 306.9 327.3 6500 0.000711 0200060 Zircaloy 15.48 306.9 327.3 6500 0.000711 i 0200C70 Zircaloy 15.48 306.9 327.3 6500 0.000711 0200080 Zircaloy 15.48 306.9 327.3 6500 0.000711 l 0200090 Zircaloy 15.48 306.9 327.3 6500 0.000711 0200100 Zircaloy 15.48 306.9 327.3 6500 0.000711 1

0300050 Zircaloy 15.48 306.9 327.3 6500 0.000711 0301050 Zircaloy 15.48 306.9 327.3 6500 0.000711 0302050 Zircaloy 15.48 306.9 327.3 6500 0.000711 0303050 Zircaloy 15.48 306.9 327.3 6500 0.000711 0400060 Zircaloy 15.48 306.9 327.3 6500 0.000711 0401060 Zircaloy 15.48 306.9 327.3 6500 0.000711 0500070 Zircaloy 15.48 306 9 327.3 6500 0.000787 0501070 Zircaloy 15.48 306.9 327.3 6500 0.000787 0502070 Zircaloy 15.48 306.9 327.3 6500 0.000787 0600080 Zircaloy 15.48 306.9 327.3 6500 0.000787 0601080 Zircaloy 15.48 306.9 327.3 6500 0.000787 0602080 Zircaloy 15.48 306.9 327.3 6500 0.000787 0700090 Zircaloy 15.48 306.9 327.3 6500 0.000787 Page 12

ATTACHMENT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT TABLE 5 Batch Cladding Thermal Specific heat of Density Thickness material conductivity of clad (J/Kg K) of clad of the clad I the clad (W/m-K) (Kg/m3 ) (m) 500*K 700*K 0701090 Zircaloy 15.48 306.9 327.3 6500 0.000787 0702090 Zircaloy 15.48 306.9 327.3 6500 0.000787 0703090 Zircaloy 15.48 306.9 327.3 6500 0.000787 0700110 Zircaloy 15.48 306.9 327.3 6500 0.000787 0800090 Zircaloy 15.48 306.9 327.3 6500 0.000787 0801100 Zircaloy 15.48 306.9 327.3 6500 0.000787 0802100 Zircaloy 15.48 306.9 327.3 6500 0.000787 0800110 Zircaloy 15.48 306.9 327.3 6500 0.000787 0800120 Zircaloy 15.48 306.9 327.3 6500 0.000787 0800130 Zircaloy 15.48 306.9 327.3 6500 0.000787 0800140 Zircaloy 15.48 306.9 327.3 6500 0.000787 0500150 Zircaloy 15.48 306.9 327.3 6500 0.000787 0801150 Zircaloy 15.48 306.9 327.3 6500 0.000787 0900100 Zircaloy 15.48 306.9 327.3 6500 0.000711 0900110 Zircaloy 15.48 306.9 327.3 6500 0.000711 0901110 Zircaloy 15.48 306.9 327.3 6500 0.000711 0902110 Zircaloy 15.48 306.9 327.3 6500 0.000711 1000120 Zircaloy 15.48 306.9 327.3 6500 0.000711 1001120 Zircaloy 15.48 306.9 327.3 6500 0.000711 1002120 Zircaloy 15.48 306.9 327.3 6500 0.000711 1000130 Zircaloy 15.48 306.9 327.3 6500 0.000711 1000140 Zircaloy 15.48 306.9 327.3 6500 0.000711 1100120 Zircaloy 15.48 306.9 327.3 6500 0.000711 1100130 Zircaloy 15.48 306.9 327.3 6500 0.000711 Page 13

l ', I ATTACHMENT RESPONSE TO RE00EST FOR ADDITIONAL INFORMATION RF,GMDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT TABLE 5 Batch Cladding Thermal Specific heat of Density Thickness material conductivity of clad (J/Kg-K) of clad of the clad I the clad (W/m-K) (Kg/m )

3 (m) 500"K 700*K 1101130 Zircaloy 15.48 306.9 327.3 6500 0.000711 1102130 Zircaloy 15.48 306.9 327.3 6500 0.000711 1200140 Zircaloy 15.48 306.9 327.3 6500 0.000711 i i

1201140 Zircaloy 15.48 306.9 327.3 6500 0.000711 1202140 Zircaloy 15.48 306.9 327.3 6500 0.000711 l

1200150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1300140 Z1rcaloy 15.48 306.9 327.3 6500 0.000711 1300150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1301150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1302150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1400150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1401150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1402150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1500150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1501150 Zircaloy 15.48 306.9 327.3 6500 0.000711 1502150 Zircaloy 15.48 306.9 327.3 6500 0.000711 l

l l

Page 14

ATTACitiENI RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT For soent fuel oool and buildina:

26. Thermal conductivity of the concrete [ pool encasement] (W/m-K): 1.7304

]

27. Specific heat of concrete (Joule /Kg-K): 628 I

28. Density of concrete (Kg/m 3): 2.35 x 102

29. Thickness of pool concrete encasement (m): 1.8288 See Table 6 for Item Nos. 30 throuch 33

30. Thermal conductivity of the storage building walls and ceiling (W/m-K): See Table 6

31. Specific heat of storage building walls and ceilling (Joule /Kg-K): See Table 6

32. Density of storage building walls and ceiling (Kg/m ): See Table 6 3

33. Average thickness of the storage building walls and ceiling (m): See Table 6 l TABLE 6 Thermal Specific Average i Material Conductivity l (W/m-K)

Heat (Joule /Kg-K) %1{ m kn Thigm)ess l

Ceiling Steel Plate 53 447.988 7801.74 0.0064 i Insulation .0361 66.989 96.12 0.0381 Combination 0.0421 0.0445 Walls Metal Siding 53 447.988 7801.74 0.000853 l Insulation .0361 66.989 96.12 0.0381 l

Combination 0.0370 0.0390

34. Total surface area of the storage building walls and ceiling (m ): 1739.3 2

35. Volume of storage building (m'): 2352.59

36. Total surface area of the pool floor (m ): 2 141.81

37. Height from pool floor to baseplate of the rack (m): 0.1389

38. Width of downcomer - distance between racks and the edge of the pool (m): See Answer to Item No. 45(a) )

39. Cross-sectional area of the border of the pool [ space between the pool wall and I 2 the cells] (m ): See Answer to item No. 45(a)

Total Free Surface Area Available to Act as Downcomer (m2 ): 44.06 i

40. Length of active fuel (m): See Table 2

41. Length from the top of the active fuel to the top of the spent fuel rack (m): 0.422 Page 15

I ATTACHMENT f RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING ASSESSHENT OF THE LOSS OF l WATER FROM THE SPENT FUEL POOL AT A DECOMMISSIONED PLANT l

l 42. To characterize the open volume in the racks that do not contain assemblies, please describe the amount of empty cells, water boxes, etc. in the pool.

Out of 1758 current storage location is the Fuel Storage Pool, the 1454 storage l locations are being used for the following objects

1431 complete spent fuel assemblies,  ;

l 1 partial spent fuel assembly, l i 2 partially consolidated spent fuel assemblies, 2 partially full failed fuei rod containers, and 18 trash baskets.

43. Decay Heat for each assembly (KW): Maine Yankee is providing our plant l specific Decay Heat Curve.

l See Figure entitled " Projected Spent Fuel Pool Power" l

The decay heat for the limiting assembly identified for this analysis was 2.90833 KW as of January 16, 1998.

l 44. Emissivity of pool walls and cladding: For a Temperature Range of 450-1725"F-Pool Walls: 0.54 to 0.63, Cladding: Not Available l

45. Provide diagrams showing elevations or distances for the pool:

! (a) Top View Provide a top view of the pool. Please include, but not limited to, une lengths and widths of pool, clearances / space around the edge of the pool, layout of the modules, open space, and cask loading area (if applicable).

See Drawing 03443-EM-1A-1 and Rack Final Positioning Measurement l Drawings for Racks A, B, C, D. E F, G H, I, J. M N, 0. P. S.

T, U, V, W, X, Y. AA, BB, CC, DD, EE (b) Top view Provide a top view of a cell showing the wall thickness and cell dimensions.

See attached Figure 6-1, 6-2, and 6-3 from MYAPC Letter to USNRC dated January 25, 1993, (MN-93-09)

(c) Side view Provide an elevation drawing of the fuel racks from the pool floor to the top of the racks. Please include, but not limited to. the space between the floor and the bottom of the spent fuel rack, the active fuel height, the distance from the top of the active fuel to the top of the cell.

See Spent Fuel Pool Elevation Drawing Page 16

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B i=93.375, B3 =61.875 inches hn477[ % Sif 3 s / / / n Yth+ di E gyn i s,,

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MAINE YANKEE ATOMIC POWER COMPANY I

lecRAt l icL AD l l SHE ATH l l80X l l WATER l e.a32 asi4s

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l H 0 0000000000000 s 0 0 0 0 0 0 00 0 0 0 0 0 0  ?

e'sase 000000 000000 72:e cess e 0 0 0000 000000 ,

0 0 000000000000 8 00 000000000000 s

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l FIGURE 6-1 BASIC FUEL STORAGE CELL

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MAINE YANKEE ATOMIC POWER COMPANY

-~ 1.4 15 -

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00 0 0000 0 0 0 000 0 00000000000000 000 0 000 0 0 0 000 0 l 000 0 0 0 000 0 0 000 'l OO f)OOO O O O f 0 0 '

00f3 0 0000 0 f)O0 i OO v 000 0 0 0 00 l OOVO O OOO O (>D5 i 0 0 0 0000 0 0 0 000 0 l 0:00 00 0 000 0 0 0_00 !

00 00000 00 0000 0 : 0100 00 00000 00'00 00 0 0 00r) o 0 000 0 l 000 0 0 0r30 00 000 l' OO O O O O(J O O OOO O \ 000 0 0 0 %JO 0 0 000 i 00 0 0 000 00 0 0 0 0 0 000 0 0 0 000 0 0 000 l OO O OOOO OTO O OOO O ! 000 0 0 0 000 0 0 0 00 '

OO r) OOO O O O f C O 00 (3 0 0000 0 r _hOO  !

00(/ 000 0 0 0 DD li OO V OO OOO O V OO l 000 0 000 0 0 00 000 l 000 0 0 0 000 0 0 0.00 i

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l FIGURE 6-2 REGIONI CONFIGURATION

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010000000000000 i OCCiOCiOCOCCOOICOd 0 0 0 0 010 0 0 0 0 01010 0 00000000000000 , OCCC O~OiOOClOOO!OC E C0000000000i0'00  ;

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CCO!CiciOiOOO!O OOOOE C00000010000000 1 OCOOOOACCOOOO i OC O C CiCf)CCOOOCE 000000G000000 000000\JO00000 1 OCOO!OiO\ J OiOOOOCE CC0000%JO00000 00000000000000 l 00000000000000W 00000000000000 00000000000000 i C0C00000000000 E 00000000000000 I QQfT000000fhQQ OO\JOOOOOOkJOO 1 QQOiOCOOCiOf)lQC CO%JICOOOCiO\/C s DQ DO 000000f)QQ OOOOOO\JOu 1 j

l 00000000000000 . CO#OICiCCOOCCOOiOOM 000iO000000C000 ,

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88088888808B C00C00000'0000'O 000C0000000000 OCOCOO/TQQOQQQ COOCOO\/GodOGO 00C00000c00000 00C00000000000 QQ MOOOOOOf)QQ 00 OGOOOOvv0 000000!O0000000 000iO00iO0000i000 j

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FIGURE 6-3 REGIONIICONFIGURATION l l i

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, Spent Fuel Pool Elevation Drawing l

l l

45'El. liigh Water Level Alarm 44' El. Normal Water Level 43' El. Low Water Level Alarm i

22.578 El. Top of flighest Rack 21.184' El. Top of Active Fuel (Ilighesej -

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l 7.5' El. 1 5.5" Minimum l

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Projected Spent Fuel Pool Power Based on Day 313 Measurement A Projected 7--

6 --

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4 1 - --- - --- - L Days After Shutdown

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