ML19323D741
| ML19323D741 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/20/1980 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8005220257 | |
| Download: ML19323D741 (3) | |
Text
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,.s BALTIMORE GAS AND ELECTRIC COMPANY P. O. D O X 1475 D ALTI MO R C, M ARYLAN D 212 O 3 May 20, 1980 AnTHUR E. Lu novAL.L. JR.
V.c t PHL 5tDE N T sum <
Office of I!uclear Reactor Regulation U. S. Iinclear Regulatorv Commission Washington, D. C.
20555 Attn:
Mr. Robert A. Clark, Chief Onerating Reactors Branch #3 Division of Licensing Cubject: Calvert Cliffs Iluelear Power Plant Units Hon. 1 & 2, Dockets I!os. 50-317 & 50-318 Spent Fuel Pool Modification Referenecc: a) BGLE letter dated 7/3/79 from J. W. Gore, Jr. to H. R. Denton, Request for Amendment b) BG&E letter dated h/1h/80 from A. E. Lundvall, Jr.
to R. W. Reid, same subject.
Gentler.en:
Reference (a) requested an amendment to allow increased suent fuel storage capacity at Calvert Cliffs.
The following additional infor-mation has been requested by your Staff.
)
Radiation Exnosure In reference (b)', Attachment 1, the response to question B.1 contains a math error.
Rack removal is expected to result in a 2 7 man-rem exncsure rather than the 0.27 man-ren stated.
This yields a total of 9 93 man-rem for the complete modification.
Waste Handlinc The racks currently in the spent fuel pool vill be hydrolazed to remove gross contamination as they are removed from the nool.
The racks vill then be vrapped in plastic and crated for temnorary storage.
At a later date they vill be electropolished to remove the surface layer of the rack steel.
Because ve do not anticipate that the racks will be irradiated, the electropolishing should remove all contamination. The racks could, therefore, be sold as scrap or buried in nn ordinary landfill.
The liquid runoff from the electropolishing process vill be processed as normal liquid vaste through ion exchangers.
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800s220 2 5 7
Mr. R. A. Clark May 20, 1980
+
Structurni Analycis, 4
On page 6 of Attachment 2 to Reference (b) the second paragraph should read:
i "It has, therefore, been concluded that neither the straight j
dron of the fuel assembly on top of the storace cell nor the straight j
drop of the fuel assembly throuch the storage cell with innact on top of the rack hace structure vill adversely affect the value of Kerr or the leaktight integrity of the pool."
t The following additional questions were asked:
1.0 Question
What type of analysis was used to check the spent fuel I
pool structure?
t j
Response: The spent fuel pool was analyzed using a 3-dimensional linear finite element model. Stresses were checked at critical sections at the pool vall and the pool floor.
ACI 318 is the code used in the analysis.
2.0 Question
What type of loading combinations were used in the analysis of the pool structure?
Resnonse: The loading combinations of the spent fuel pool conforms to j
FSAR TABLE 5-3, Section 5.6.1.2., combined with the loading j
due to overall temperature chance and thermal gradient.
3.0 Question
What stress limits were used in the analysis of the pool structure?
Response:' All stresses are limited to the stress limits established by Section 5A of the FSAR.
s h.0 Question: What type, of analysis was used to check the spent fuel pool l
liner adequacy?
Response: The pool liner was analyzed for the most critical loading i*
cases, as deternined by the rack analysis and design. The analysis consisted of checking the plate for bearing and 3
tearing at each support leg and checking the concrete 4
i beneath the plate for local bearing.
l
5.0 Question
What type of loading combinations were used in the analysis of the liner plate?
1 f
Response: The most severe of the loading combinat. ions resulting from j
analysis of the poison racks performed by Nuclear Energy Services, Inc. were used - the dead load plus live load and design basis earthquake.
3
fir. R. A. Clari May 20 1980 0
6.0 Question
What stress limits were used in the analysis of the pool liner?
Response: The following stress limits were used to check the liner plate:
Concrete Bearing:
(2) d.85 f'c (Code allowable ACI 318)
Steel Plate:
Dead Load plus OBE 0.60 Fy (AISC Code allowable for tension)
Dead Load plus DBE, or accident case 1.33 (0.60) Fy In addition, reference (b) requested that you consider the amendment chance to be for 1830 fuel assemblies instead of the 1760 spaces ve requested earlier. BG&E vishes to postpone the requent to increase storage canacity from 1760 to 1830 spaces.
Our schedule calls for the installation of 830 of these spaces in the sunner of 1980 and the remainder in 1981 or 1982. We feel the prenotice which must accoppany the request for additional space could innact our installation schedule for the first 830 spaces, and therefore, BGLE withdraws the request of the 1830 spent fuel storare spaces at this time. At a later time ve vill request an anendment to store 1830 spent fuel assemblics.
Very truly yours e
/ V r. J. knn%azp-s i
cc:
J. A. Biddison, Enquire G. F. Trowbridge, Esquire Mr. E. L. Conner, Jr. - IIRC t
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