ML20062H164
| ML20062H164 | |
| Person / Time | |
|---|---|
| Site: | Shoreham, 07002884 File:Long Island Lighting Company icon.png |
| Issue date: | 05/09/1979 |
| From: | Novarro J LONG ISLAND LIGHTING CO. |
| To: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| SNRC-388, NUDOCS 7906110421 | |
| Download: ML20062H164 (4) | |
Text
{{#Wiki_filter:_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ uk 2. -{fffg@ LONG' ISLAND LIGHTING COM PANY en w rawaway SHOREHAM NUCLEAR POWER STATION j P.O. Boy 618 NORTH COUNTRY ROAD
- WAQiNG RIVER, N.Y.11792
,' f..; '~ 2 23 May 9, 1979 U 5NRC-389 '.1 Mr. Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety U. S. Nuclear Regulatory Commission Washingcon, D. C. 20555 Shoreham Nuclear Pow tatkon - Unit 1 Docket No. 50-322/
Dear Mr. Cunningham:
V i' The Long Island Li Application to receive, possess, ghting Company (LILCO) and store special nuclear material in the form of unirradiated new fuel assemblies does not specifically address dry storage of the initial core in the spent fuel pool. This method of storing the initial core was discussed in telephone conversations on April 5 and 30, 1979 between the NRC Staff (J. Delaney and C. Marotta) and LILCO (P. Lemberg and J. Morin). The NRC asked LILCO to provide an analysis for dry scorage under optimum :toderator conditions. Such an analysis has been parformed based on the following: 1. Fuel assemblies for the initial core will be stored dry in the spent fuel pool in alternate rows of the racks, as shown in Figure A, such ,m that each fuel assembly will have only two (._ adjacent fuel assemblies. 2. No fixed automatic fire spray headers are located over the spent fuel pool area where they could flood the pool with foam or water fog. This analysis demonstrated that k-eff would be less than 0.95 for all values of moderator density. It was perfermed as a function of uniform moderator density using the PDQ-7 1 computer program with LEOPARD macroscopic cross-section input employing methods as described in Shoreham FSAR I Appendix 9A. Conservatively assuming a nominal enrichment of 2.35 weight percent U-235 throughout the core, the infinite multiplication factor km reaches a peak value of only 0.76 at the optimum water density condition of five percent (0.05 g/cc). M DSPI 1zsss 7 906(11ot/A/ g
1 Mr. R. E. Cunningham May 9, 1979 Re: Dry Storage of the Initial Core Page 2 in the Spent Fuel Pool l 4 i The results of this analysis, as shown in Figure B, conclude that dry storage of the initial core in the spent fuel pool is feasible and that K-eff will be maintained significantly below 0.95 under optimum moderation conditions, ery ly yours, b% % %O o J. P. Nova ro, Project ager Shoreham uclear Power Station JPM/c1 Attachs. 1 l i i l S e 12S18
u. ~ FIGURE A SHOREllAM NUCLEAR POWER STATION - UNIT 1 i SPENT FUEL STORAGE RACK PROPOSED LOADING PATTERN i FOR DRY STORAGE OF NEW FUEL ~ l c 000000 .0000 00 Water l l q-Boxes N /N / N /N y N yh y f / N/ N / N. / N/ N/ N I OOOOOOOOCOOO I l I Loaded Rc' \\ / \\O /~\\ /N^/ X N / of Fuel t / 'X \\'^N/ X X \\/ N/ N/ N. Storacel Ihpty Rows l l l Boxes-of Fuel "=:" OO!OOOO OOOO OO n I i i o s m -s n X-s m'><- 1 X X '>N / >< x - / N/ 'N / N f 's I l l 000000iO00000 r i Fuel Asse.-Slies e 12S18 1 g y., p
.( e FIGURE B S!!OREilAM NUCLEAR PO' ER STATION - U:iIT 1 5 SPENT FUEL STORACE RACK k,vs WATER DENSITY l 1.0 0.95 h t 0.90 k, p. 0.85 O.829 0.80 0.761 0.75 3.1 w/o U-235, Alternate Rcws Loaded 0.70 C '.i 0.65 a m u 0.608 2.35 w/o U-235, Alternate Rows Loaded i i O.554 i i i i i .1 .2 .3 .4 .5 .6 .7 .8 .9
- 1. 0 0
3 Water Density, gm/cm 1231S e -}}