ML19210C000
| ML19210C000 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/24/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Whitmer C GEORGIA POWER CO. |
| Shared Package | |
| ML19210B996 | List: |
| References | |
| NUDOCS 7911130128 | |
| Download: ML19210C000 (2) | |
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cr i NUCLEAR REGULATORY COMMISSION
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% w p August 24, 1979 Docket Nos. 50-321 and 50-366 Mr. Charles F. Whitmer Vice President - Engineering Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302
Dear Mr. Whitmer:
By your letter dated July 9,1979 you requested an amendnent to Operating License No. DPR-57 and NPF-5 for the Edwin I. Hatch Nuclear Plant Unit Nos.
I and 2.
The proposed anendmr;nt related to an increase in spent fuel capacity.
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During our review we identified certain items for,<hich we require additional infomation.
These are identified in the enclosure.
In order to maintain our review schedule of this item, we request that the additional infomation be submitted within 30 days of your. receipt of this request.
Sincerely, Thomas. Ippolito, Chief Operating Reactors Branch 93 Division of Operating Reactors
Enclosure:
Request for Additional Infomation ec w/ enclosure:
See page 2 o
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Mr. Charles F. Whittner Georgia Power Company August 24, 1979 cc:
G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1B00 M Street, N. W.
Washington, D. C.
20035 Ruble A. Thomas Vice President P. O. Box 2625 Southern Services, Inc.
Bimingham, Alabama 35202 Mr. Harry Majors Southern Services, Inc.
300 Office Park Bimingham, Alabama 35202 Mr. William Widner Georgia Power Company Power Generation Department P. O. Box 4545 Atlanta, Georgia 30302 Nr. L. T. Gucwa Georgia Power Company Engineering Department
- P. O. Box 4545 Atlanta, Georgia 30302 Appling County Public Library Parker Street Baxley, Georgia 31413 Mr. R. F. Rogers U. 5. Nuclear Regulatory Cornission P. D. Box 710 Baxley, Georgia 31513 1319
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i ENCLOSURE 1 OUESTIONS FOR THE E.1. HATCH 1/2 SPENT FUEL POOL MODIFICATION
- 1) Provide an estimate of the nan-rem exposure that will be received during the removal and disposal of the old racks from Unit 1 and installation of the new high density racks. The estimate should include the nunber of workers involved in each phase of the opera-tion in'cluding divers, if any; the duration of the operation; the ex;osurt rate during each phase of the operation and the total nan-rem received by all workers involved. Relevant experience nay be cited. Discuss how the estination of the man-rem exposure above would be effected if the Hatch 2 SFP should become contami-nated prior to its modification.
- 2) Provide an estimate of the annual man-rem expected from all opera-tions in the SFP area, including refueling, based on the fission an corrosion product concentrations in the spent fuel pool water indicated in Table 10-1 of your July 9,1979 submittal.
Al though Se: tion 10.1 states that *the increase in the SFP storage capacity is not expected to aporeciably affect the annual man-ren dose,"
es-i.a.e the increase of this nan-rem dose as a result of the nodi-
'i:aticn cf Hatch I and 2 since the Oodification should increase the
-a:icactive source inver. tory in the SFr at sone tine in the future.
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. 3) Provide the estinated volume of contaninated material (e.g., spent fuel racks, seismic restraints) expected to be shipped from the plant because of the pool nodification to a licensed burial site.
- 4) Discuss in some detail the ir. pact of the propcsed pool nodification on radioactive liquid effluents from the plant.
Include a dis-cussion of the pool leak collection systen, pool leak detection systen and history of leakage fron the pool.
- 5) Provide the estinated failed fuel fraction for each fuel cycle at Hatch Unit 1.
- 6) You stated in Section 8 of your submittal dated July 9,1979, that the design pool bulk water temperature will be above the rSAR design value of 125 F during nornal refuelings after the eighth refueling.
If the actual expected value of the bulk water temperature, not the design value, nay be above the 125 F under realistic conditions, discuss when this will occur during any refueling, for what period of time it will occur, the maxinun value of the temperature and the effect of this on releases of radi; iodine and tritian from the pools.
- 7) Discuss the effect of the spent fuel novenents during the nodifica-tic 3 c' the Hatch 1 ;001 on the a. ant of crud in the pool water and the radiation levels in the vicin,ity of the pool during the occ'
.;f fication.
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- 8) Identify any heavy load or cask drop analyses performed to date for your facility.
Provide a ccpy of all such analyses not previously subnitted to the fGC staff.
- 9) Provide a list of all objects that are required to be moved over or near the spent fuel storage pool.
For er.ch object listed, pro-vide its approximate weight and size, a diagran or description of the transfer path utili::ed, and the frequency of movenent.
- 10) For our evaluation of the difference between the maximum calculated koo of 0.87 given in your submittal and the maximum actual keff that might occur in the spent fuel pool, the following information should be provided:
The q'uantity and distrihution of the uranium-235 in the fuel a.
pool storage lattice calculation for this maximum koo.
b.
The quantity and distribution of gadolinium-155 and gadolinium-157 in the fuel pool storage lattice calculation for this maxi'.um koo.
The quantity and distribution of the fission products and actinides c.
in the fuel pool storage lattice calculation for this maximum koo.
- 11) On page 7-3 of your submittal ycu itate, "The results in Table 7-1 show that the nominal pitch (Case 2) has a higher koo result than the minimum pitch casc (Case 6)."
Since the statistical error bounds given on Table 7-1 do not preclude the oppcsite conclusion, and since all other calculations for'similar storage lattices show the opposite to be true, provide a justification for this conclusion.
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