ML20237E249

Forwards Revised Licensing Rept Describing Design, Fabrication & Safety Analysis of High Density Racks.Current Schedule for Installation of Racks Listed

ML20237E249
Person / Time
Site:	Byron
Issue date:	12/22/1987
From:	Ainger K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20237E251	List: ML20237E249 ML20237E272
References
2841K, NUDOCS 8712280234
Download: ML20237E249 (19)

Text

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• . V Commonwealth Edison

/]i / Oro First Natiorul Plart Chicago Illinois v' Addrtss Rip'y to: Post Offics Box 767 Chicago, Illinois 60690 0767 December 22, 1987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

Byron Station Units 1 and 2 Application for Amendment to Facility Operating Licenses NPF-37 and NPF-66, Appendix A, Technical Specifications NRC Docket Nos. 50-454 and 50-455 References (a): September 3, 1986 letter from K.A. Ainger to H. R. Denton (b): January 12, 1987 NRC Meeting Summary -

Structural Analysis of Spent Fuel Pool Expansion Reference (a) requested a license amendment to increase the storage capacity of the spent fuel racks at Byron Station. That application included a licensing report which described the design, fabrication, and safety analysis of the high density racks. Enclosed with this letter is a revised licensing report. Attachment A FummariZes the changes to the report.

Since the high density spent fuel racks are designed to store fuel with a higher burnup than was previously considered in the PSAR, a question was raised concerning the effect of the stored higher burnup fuel on radiological consequences previously analyzed. Attachment B of this letter addresses this NRC question.

The schedule for. installation of the racks, outlined in reference (a), has changed because the racks were not delivered within the time frame originally expected. The current schedule for installation of the racks is as follows.

The next refueling outage for Byron Unit 1 is scheduled to begin in September of 1988. Receipt of new fuel-for that outage should.begin July 1, 1988. ' Installation of the high density racks must be complete by that date so fuel handling building space and lifting equipment will be available for

-receipt of the new fuel. It will take about three months to move the existing DC

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i December 22, 1987 US NRC spent fuel, install the high density storage racks, and decontaminate and remove the old racks. Consequently, the installation effort should begin in April, 1988. We are requesting NRC approval of this amendment between February and April of 1988 to allow some margin and flexibility in the installation schedule.

Please direct any questions you may have concerning this matter to this office.

Very truly yours, K. A. Ainger Nuclear Licensing Administrator es Enclosure Attachments cc: Byron Resident Inspector NRC Region III Office l L. N. Olshan - NRR M. C. Parker - IDNS i

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.- l REVISION 1 NOVEMBER 1937 ATTACHMENT A SUMARY OF CHANGES CONTAINED IN BYRON LICENSINu REPORT,0N rilGH OENSITY SPENT. FUEL RACKS Page or Figure Number Description Page iii Editorial. Title of Section 6.4.1 revised.

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Page iv Added Sections 6.10.1 and 6.10.2 Page y Added Appendix B, "NRC Questions from December 22, 1986, Meeting."

Page 1-1 Revised the quantity of the spent fuel assemblies 2nd paragraph stored in the spent fuel pool and corrected the date .j Unit 2 went into commercial operation Page 1-1 Revised the pool storage capacity and the date this '

3rd paragraph capacity will be reached.

Page 1-1 Revised to add descrip, tion for fixed height support 4th paragraph legs.

Page 1-2 Revised to reflect the scope of work performed by 1 1st paragraph dif ferent companies.

Page 1-3 and 1-4 Revised to reflect the remaining storage capacity with l Table 1.1 the proposed expansion.

Page 2-1 Revised total number of storage cells.

1st paragraph l Page 2-1 Revised the size of girdle bars and nominal' gap 3rd paragraph between cell walls of adjacent iradules.

Page 2-1 Revised the description for Table 2.1 and 2.2.

3rd paragraph Page 2-2 Revised the nominal dimension of cell pitch for racks Table 2.1 in Region 2 and added notes to indicate the variation of flux trap gap and cell pitch.

Page 2-3 Revised module data for type D4, F1, G1, and added Table 2.2 module data for type K1, L1-L2, and M1.

Page 2-4 Revised the spent fuel pool layout Figure 2.1

. REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Figure Number Description Page 2-5 Revised the girdle bar for racks in Region 1 Figure 2.2a Page 2-6 Revised the girdle bar for racks in Region 2 Figure 2.2b Page 3-1 Revised to reflect additional material used.

1st paragraph Page 3-1 Revised the components name (" Tube" changes to " Box").

3rd paragraph Page 3-1 Revised the component name (" Tube" changes to " Box).

Sect. 3.1.1.a Page 3-2 and 3-3 Revised to add a description for short adjustable Sect. 3.1.1.f legs.

Page 3-3 Revised the component name (" Tube" changes to " Box").

Sect. 3.1.2 Page 3-7 Revised the component name (" Tube" changed to " Box")

Figure 3.1 and connecting gap element.

Page 3.8 Revised the tolerance for the channel elements.

Figure 3.2 Page 3.8 Revised the size and shape of the gap elements.

Figure 3.3 Page 3-9 Revised the component name (" Tube" change to " Box").

Figure 3.4 Page 3-10 Revised to identify the base plate in Section Z-Z.

Figure 3.5a Page 3-12 Revised the figure number (Figure 3.6 changed to Figure 3.6A 3.6A).

Page 3-13 Added new figure for short adjustable support.

Figure 3.6B Page 3-14 Added new figure for small fixed support.

Figure 3.6C 2

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REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'O.)

Page or Figure Number Description l

Page 3-15 Revised the component name (" Tube" changed to "Bux")

l Figure 3.7 and added note to reflect the variation in thickness

' of connecting strips. ,

J Page 4-4 Editorial correction.

1st paragraph Page 4-6 Revised the dimension of lattice spacing.

Sect. 4.3.3 Page 4-15 Revised the dimension of lattice spacing.

Sect. 4.6.3 Page 4-18 Editorial correction.

Sect. 4.7.5 .

Page 4-30 Revised the dimension of lattice spacing. ,

Figure 4.3 {

j Paragraph 5-1 Editorial correction, f 1st paragraph Page 5-2 Revised to add the third fuel discharge mode involving both units.

Page 5-3 Added a description for the third fuel discharge mode.

1st paragraph i i

i Page 5-3 Revised to add the third fuel discharge mode. 1 3rd paragraph Page 5-4 Editorial correction to add-temperature scale.

Pages 5-5 and 5-6 Editorial correction to add symbols.

Page 5-7 Editorial correction.

1st paragraph Page 5-7 Revised the referenced figure numbers and included-Sect. 5.1.3 editorial corrections.

Page 5-9 Revised the dimension of nominal pitch.

Sect. 5.2.1 2nd item 3 ,

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4 REVISION l' NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Figure Number Description Page 5-9 Editorial correction.

Sect. 5.2.1 3rd item Page 5-11 Editorial correction.

Page 5-12 Revised to add case 3 for the fuel discharge mode.

Pages 5-14 and Revised to add case 3 for the fuel discharge nou..

5-15, Tables 5.1 and 5.2 Page 5-16 _ Revised the title and headings of the table and added Table 5.3 case 3 for the fuel discharge mode.

Pages 5-17 and Revised to add case 3 for. the fuel discharge mode.

5-18 Tables 5.4 and 5.5 Page 6-1 , Revised to identify the cases studied.

Page 6-2 Deleted the nearly empty rack case, included an Items 1 and 2 editorial correction and added symbols.

Page 6-2 Revised fuel weight used in. analyses and added a 1st paragraph description for the case of nearly empty racks.

Page 6-2 Editorial corrections.

2nd and 3rd paragraphs Page 6-3 Revised seismic model description for fuel mass nodal Section 6.2.1.a locations and connectivity.

Page 6-3 Revised the number of lumped masses.

Section 6.2.1.b Page 6-4 Revised the referenced section.

Section 6.2.1.1 Page 6-4 Revised to include a description of rack-to-rack Section 6.2.1.k misalignment considered in the seismic analyses.

Page 6-5 Editorial correction. l 2nd paragraph e!

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REVISION l' NOVEMBER 1937 ATTACHMENT A (CONT'D.) J

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Page or Description Figure Number.

Page 6-5 Revised the description for the model of fuel 3rd paragraph assembly.

Page 6-5 Revised the model of fuel assembly.

Section 6.2.2 1st paragraph Page 6-5 Revised the number of degrees-of-freedom for the spent Section 6.2.2 fuel rack model.

2nd paragraph Pages 6-5 and 6-6 Editorial correction to add symbols for acceleration.

Section 6.2.3 Page 6-6 Revised the referer.ce number and added an editorial 2nd paragraph correction. j Page 6-7 Revised the number of degrees-of-freedom.for the spent Section 6.3 fuel rack and number of nonlinear gap elements, j Page 6-8 Revised to rephrase the entire paragraph (editorial).

1st paragraph Page 6-9 Editorial correction.

1st paragraph Page 6-9 Revised the title of Section 6.4.1.

Section 6.4.1 l Page 6-9 Revised to add a description for system kinetic energy i' Section 6.4.1 and added symbols for acceleration in the equations.

1st paragraph Page 6-10 Revised to change the name of'the computer program.

l 2nd paragraph Page 6-10 Revised to reflect the change in model of fuel ,

4th paragraph assembly.

Page 6-11 Editorial correction.

Section 6.4.2 l

Page 6-14 Editorial corrections.  ;

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REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Figure Number Description Page 6-15 Revisad module configurations for which results are Section 6.3 presented.

2nd paragraph Page 6-16 Revised the modules and referenced Table numbers.

1st paragraph Page 6-16 Revised to rephrase the paragraph (editorial).

2nd paragraph Page 6-16 Revised to delete the description for the tolerance of 3rd paragraph rack dimension to show the actual stress ratio instead of bounding values and to add the weight of the consolidated fuel. Also revised the referenced Table numbers.

Page 6-17 Revised the description for OBE analyses and added the 2nd paragraph comparison between OBE and SSE conditions.

Page 6-17 Revised to add the referenced Tables.

Section 6.9.2 Pages 6-17 and Revised Section 6.10 to add two subsections, 6.10.1 6-18, Section 6.10 and 6.10.2, which give a more detailed description of the weld stresses.

Page 6-19 Revised the weight of the fuel assembly.

Section 6.11.a Page 6-20 Revised the uplif t force applied at the top of the Section 6.11.c rack.

Pages 6-22 and Revised Table 6.1 and 6.2 to reflect the change in. the 6-23, Tables 6.1 spent fuel rack model.

I and 6.2 Page 6-25 Editorial changes.

l Table 6.4 Pages 6-26 through Added analysis results tables.

6-37, Tables 6.5a through 6.51 Page 6-39 Revised Figure 6.2'to reflect the appropriate time Figure 6.2 history in the north-south direction.

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REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Description Fioure Number Page 6-41 Revised to reflect the change in spent fuel rack Figure 6.4 model.

Page 7-1 Revised the storage capacity of the spent fuel pool.

1st paragraph Page 7-3 Revised the quantity of the spent fuel presently Section 7.4 stored in the spent fuel pool.

Page 7-4 Revised net reactor core power level, average assembly Section 7.6.1 discharge burnup, and time after shutdown for dose rate calculation.

Page 7-5 Revised to delete the photon energy production rates ist paragraph of a peak power spent fuel assembly.

Page 7-5 Revised to reflect the evaluation of the shielding Section 7.5.2 capability of the spent fuel pool walls.

2nd paragraph ,.

Page 7-5 Revised the referenced Table number.

Section 7.6.2 3rd paragraph Page 7-5 Revised the referenced Table number. i Last paragraph Page 7-6 Kevised the schedule to install the new spent fuel Last paragraph racks.

Page 7-7 Revised to reflect the condition of the spent fuel 1st paragraph pool at scheduled installation of the new racks.

Page 7-7 Revised to delete the assumption of the " wet" 2nd paragraph installation.

Page 7-7 Revised the device to prevent the crane from carrying 2nd paragraph racks over the stored fuel assemblies.

Page 7-8 Revised to delete the " dry" reracking operation.

3rd paragraph Pages 7-10 and Revised Table 7.1 for photon energy production' rates

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7-11, Tables.7.1 of an average spent fuel assembly and replaced and 7.2 Table 7.2 with original Table 7.3 (original Table 7.2 deleted).

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REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Figure Number Description Page 9-1 Revised to reflect the change in storage capacity.

Section 9.1 Page 3-2 Revised the year when the cost of replacement power was estimated.

Appendix B Added Appendix 8: NRC questions and responses from Pages B-1 to B-9 the December 22, 1986, meeting.

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l ATTACHMENT B 1

The Byron high density spent fuel storage racks will be capable of j storing fuel with an average discharge burnup of approximately 45,000 MWD /T.

Since the current FSAR analysis has considered fuel with an average discharge burnup of 38,000 MWD /T, the NRC raised a concern regarding any effect on the offsite radiological consequences of a fuel handling accident as a result of l increasing the discharge burnup.

I Westinghouse has reviewed the Byron, Braidwood and Zion FSAR's ard has provided the following comparative information on the radiological consequences associated with extended burnup fuel:

"By approval of the Westinghouse Topical (Extended Burnup Evaluation of Westinghouse Fuel), WCAP-10125-P-A (Proprietary), the NRC SER has extended the application of the Westinghouse design criteria and analysis methods of Zircaloy-clad fuel design up to the extended burnup level of approximately 48,000 MWD /T (region average burnup).

Extending fuel burnup would have little impact on the radiological consequences presently reported in the Zion / Byron /Braidwood Units 1 and 2 PSARs. As discussed in response to an NRC question (see Section H of WCAP-10125-P-A, Extended Burnup Evaluation of Westinghouse Fuel, December i 1985), extended fuel burnup does increase the radiological consequences of a fuel handling accident to a minor extent (approximately four percent increase in the thyroid dose). The impact of extended fuel burnup on the radiological consequences of the rod ejection accident was identified as l being a slight increase increase in thyroid dose (about 2%) and a decrease in whole body dose. This same effect on radiological consequences would also be seen in other accidents involving the release of reactor coolant l activity. It is judged that these increases in doses are insignificant, I

being within the uncertainty of the calculations. Thus, there is no need to recalculate the radiological consequences of any of the accidents due 1 to extending region average fuel burnup. It is noted that the 1 radiological consequences of accidents reported in the FSAR are well l within the limits of 10 CFR 100; thus, if increases such as those  !

mentioned above were applied to the doses reported in the FSAR, there I would be no impact on their acceptability." l l

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REVISION 1 NOVEMBER 1937 ATTACHMENT A SU:4:4ARY OF CHANGES CONTAINED IN BYRON LICENSING REPORT ON HIGH OENSITY SPENT FUEL RACKS Page or Figure Number Description Page iii Editori al . Title of Section 6.4.1 revised.

Page iv Added Sections 6,10.1 and 6.10.2 Page v Added Appendix B. "NRC Questions from December 22, 1986, Meeting."

l Page 1-1 Revised the quantity of the spent fuel assemblies 2nd paragraph stored in the spent fuel pool and corrected the date Unit 2 went into commercial operation Page 1-1 Revised the pool storage capacity and the date this 3rd paragraph capacity will be reached.

Page 1 ' Revised to add description for fixed height support 4th paragraph legs.

Page 1-2 Revised to reflect the scope of work performed by 1st paragrapn different companies.

Page 1-3 and 1-4 Revised to reflect the remaining storage capacity with Table 1.1 the proposed expansion.

Page 2-1 Revised total number of storage' cells.

1st paragraph Page 2-1 Revised the size of girdle bars and nominal gap 3rd paragraph between cell walls of adjacent modules.

Page 2-1 Revised the description for Table 2.1 and 2.2.

3rd paragraph Page 2-2 Revised the nominal dimension of cell pitch for racks Table 2.1 in Region 2 and added notes to indicate the variation i of flux trap gap and cell pitch.

i Page 2-3 Revised module data for type D4, F1, G1, and added Table 2.2 module data for type K1, L1-L2, and M1.

Page 2-4 Revised the spent fuel pool layout Figure 2.1 4 1

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REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Figure Number Description Page 2-5 Revised the girdle bar for racks in Region 1 Figure 2.2a Page 2-6 Revised the girdle bar for racks in Region 2 Figure 2.2b Page 3-1 Revised to reflect additional material used.

1st paragraph Page 3-1 Revised the components name (" Tube" changes to " Box").

3rd paragraph Page 3-1 Revised the component name (" Tube" changes to~" Box).

Sect. 3.1.1.a Page 3-2 and 3-3 Revised to add a description for short adjustable Sect. 3.1.1.f legs.

Page 3-3 Revised the component name (" Tube" changes to " Box").

Sect. 3.1.2 Page 3-7 Revised the component name (" Tube" changed to " Box")

Figure 3.1 and connecting gap element.

Page 3.8 Revised the tolerance, for the channel elements.

Figure 3.2 Page 3.8 Revised the size and shape of the gap elements.

Figure 3.3 Page 3-9 Revised the component name (" Tube" change to " Box"). lj Figure 3.4 Page 3-10 Revised to identify the base plate in Section Z-Z.

Figure 3.Sa Page 3-12 Revised the figure number (Figure 3.6 changed to Figure 3.6A 3.6A).

Page 3-13 Added new figure for short adjustable support.

Figure 3.6B Page 3-14 Added new figure for small fixed support.

Figure 3.6C 1

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REVISION 1 NOVEMBER 1937 )

ATTACHMENT A (CONT'O.)

Page or Figure Number Description Page 3-15 Revised the component name (" Tube" changed to " Box") ,

Figure 3.7 and added note to reflect the variation in thickness i' of connecting strips.

Page 4-4 Editorial correction.

1st paragraph Page 4-6 Revised the dimension of lattice spacing.

Sect. 4.3.3 Page 4-15 Revised the dimension of lattice spacing.

Sect. 4.6.3 Page 4-18 Editorial correction.

Sect. 4.7.5 Page 4-30 Revised the dimension of lattice spacing.

Figure 4.3 Paragraph 5-1 Editorial correction.

1st paragraph Page 5-2 Revised to add the third fuel discharge mode involving i both units.

Page 5-3 Added a description for the third fuel discharge mode.

1st paragraph ,

i Page 5-3 Revised to add the third fuel discharge mode.

l 3rd paragraph Page 5-4 Editorial correction to add temperature scale.

1 Pages 5-5 and 5-6 Editorial correction to add symbols.

Page 5-7 Editorial correction.

1st paragraph Page 5-7 Revised the referenced figure numbers and included Sect. 5.1.3 editorial corrections.

Page 5-9 Revised the dimension of nominal' pitch.

Sect. 5.2.1 2nd item 3

REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Figure Number Description Page 5-9 Editorial correction.

Sect. 5.2.1 3rd item Page 5-11 Editorial correction.

Page 5-12 Revised to add case 3 for the fuel discharge mode.

Pages 5-14 and Revised to add case. 3 for the fuel discharge: mode.

5-15, Tables 5.1 and 5.2 Page 5-16 Revised the title and headings of the table and added Table 5.3 case 3 for the fuel discharge mode.

Pages 5-17 and Revised to add case 3 for the fuel discharge mode.

5-18 Tables 5.4 and 5.5 Page 6-1 Revised to identify the cases studied.

Page 6-2 Deleted the nearly empty rack case, included an Items 1 and 2 editorial correction and added symbols.

Page 6-2 Revised fuel weight used in analyses and added a-1st paragraph description for t.he case of nearly empty racks.-

Page 6-2 Editorial corrections.

2nd and 3rd paragraphs Page 6-3 Revised seismic model description for fuel mass nodal Section 6.2.1.a locations and connectivity.

Page 6-3 Revised the number of lumped masses.

Section 6.2.1.b Page 6-4 Revised the referenced section.

Section 6.2.1.i Page 6-4 Revised to include a description of rack-to-rack Section 6.2.1.k misalignment considered in the seismic analyses.

Page 6-5 Editorial correction.

2nd paragraph

1 REVISION 1 NOVEMBER 1937 ATlaCHMENT A (CONT'D.)

Page or F_i,gure Number Description Page 6-5 Revised the description for the model of fuel 3rd paragraph assembly.

Page 6-5 Revised the model of fuel assembly.

Section 6.2.2 1st paragraph Page 6-5 Revised the number of degrees-of-freedom for the spent Section 6.2.2 fuel rack model.

2nd paragraph l Pages 6-5 and 6-6 Editorial correction to add symbols for acceleration.

Section 6.2.3 Page 6-6 Revised the reference number and added an editorial 2nd paragraph correction.

Page 6-7 Revised the number of degrees-of-freedom for the spent Section 6.3 fuel rack and number of nonlinear . gap elements.

Page 6-8 Revised to rephrase the entire paragraph (editorial).

1st paragraph Page 6-9 Editorial correction.

1st paragraph Page 6-9 Revised the title of Section 6.4.1.

Section 6.4.1 Page 6-9 Revised to add a description for system kinetic energy Section 6.4.1 and added symbols for acceleration in the equations.

1st paragraph Page 6-10 Revised to change the name of the computer program.

2nd paragraph Page 6-10 Revised to reflect the change in model of fuel 4th paragraph assembly.

Page 6-11. Editorial correction.

Section 6.4.2 Page 6-14 Editorial corrections.

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REVISION 1 l NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Figure Number _ Description Page 6-15 Revised module configurations for which results are Section 6.~3 presented.

2nd paragraph Page 6-16 _

Revised the modules and referenced Table numbers.

1st paragraph Page 6-16 Revised to rephrase the paragraph (editorial).

2nd paragraph Page 6-16 Revised to delete the description for the tolerance of 3rd paragraph rack dimension to show the actual stress ratio instead of bounding values and to add the weight of the consolidated fuel. Also revised the referenced Table numbers.

Page 6-17 Revised the description for OBE analyses and added the 2nd paragraph comparison between OBE and SSE conditions.

Page 6-17 Revised to add the. referenced Tables.

Section 6.9.2 Pages 6-17 and Revised Section 6.10 to add two subsections, 6.10.1 6-18, Section 6.10 and 6.10.2, which give a more detailed description of the weld stresses. l Revised the weight of the fuel assembly.  !

Page 6-19 Section 6.11.a l Page 6-20 Revised the uplift force applied at the top of the '

Section 6.11.c rack.

Pages 6-22 and Revised Table 6.1 and 6.2 to reflect the change in the  ;

i 6-23, Tables 6.1 spent fuel rack model.

and 6.2 Page 6-25 Editorial changes.

Table 6.4 Pages 6-26 through Added analysis results tables.

6-37, Tables 6.5a through 6.51 Page 6-39 Revised Figure 6.2 to reflect the appropriate time Figure 6.2 history in the north-south direction.

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REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Fi_gure' Number Description Page 6-41 Revised to reflect the change in spent fuel rack Figure 6.4 model.

Page 7-1 Revised the storage capacity of the spent fuel pool.

1st paragraph Page 7-3 Revised the quantity of the spent fuel presently Section 7.4 stored in the spent fuel pool.

Page 7-4 Revised net reactor core power level, average assembly Section 7.6.1 discharge burnup, and time after shutdown for dose rate calculation.

Page 7-5 Revised to delete the photon energy production rates 1st paragraph of a peak power spent fuel assembly.

Page 7-5 Revised to reflect the evaluation of the shielding Section 7.6.2 capability of the spent fuel pool walls.

2nd paragraph _

Page 7-5 Revised the referenced Table number.

Section 7.6.2 3rd paragraph Page 7-5 Revised the rtferenced Table number.

Last paragraph Page 7-6 Revised the schedule to install the new spent fuel Last paragraph racks.

Page 7-7 Revised to reflect the condition of the spent fuel 1st paragraph pool at scheduled installation of the new racks.

Page 7-7 Revised to delete the assumption of the " wet" 2nd paragraph installation.

Page 7-7 Revised the_ device to prevent the crane from carrying 2nd paragraph racks over the stored fuel assemblies.

Page 7-8 Revised to delete the " dry" reracking operation.

3rd paragraph Pages 7-10 and Revised Table 7.1 for photon energy production rates l 7-11, Tables 7.1 of an average spent fuel assembly and replaced and 7.2 Table 7.2 with original Table 7.3 (original Table 7.2 deleted). l l

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REVISION 1 NOVEMBER 1937 ATTACHMENT A (CONT'D.)

Page or Figure Number _

Description Page 9-1 Revised to reflect the change in storaga capacity.

Section 9.1 Page 3-2 Revised the year when the cost of replacement power was estinated.

Appendix B Added Appendix 8: NRC questions and responses from Pages B-1 to B-9 the December 22, 1986, meeting.

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