ML19208C804
| ML19208C804 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/27/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7909270525 | |
| Download: ML19208C804 (4) | |
Text
-fER ik 8
UNITED STATES 8 hg
~%,
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 L
%g' b
/
August 27, 1979
' 9 7 4 E;[/
~4 Docket No. 50-317 Mr. A. E. Lundvall, Jr.
Vice President - Supply Baltimore Gas & Electric Company P. O. Bc,x 1475 Baltimore, Maryland 21203
Dear Mr. Lundvall:
~
In the process of reviewing your July 3,1979 request regarding Spent Fuel Pool Modification for Calvert Cliffs Unit No.1, we find that additional information as detailed in the enclosure is needed to complete our review.
In order to complete our review in a timely manner, please~ provide the additional information at your earliest convenience.
Sincerely,
[4 obert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Request for Additional Information U
C e wt 0
70
'iG
~ T,0 25
. b N 00.a
?.
o 1042 2'29
iiitincre Gas & Electric Company cc:
Janes A. Biddison, Jr.
Mr. R. fi. Douglass, Manager
~
General Counsel Quality Assurance Departmer.:
G and E Building Room 923 Gas & Electric Building Charles Center P. O. Box 1475 Sal timore, Maryland 21203 Baltimore, Maryland. 21203 George F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, H.U.
Washington, D. C.
20036.
- r. R. C. L. 01 son Baltinore Gas and Electric Company Room 922 - G and E Building Post Office Box 1475 Saltimore, Maryland 21203 Mr. Leon 3. Russell, Chief Engineer Calvert Cliffs !!uclear Power Plant
~
Baltinore Gas and Electric Company Lusoy, Itaryl and 20657 Bechtel Power Corporation ATT!!:
ilr. J. C. Juod Chief Nuclear Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 Conbustien Engineering, Inc.
ATill:
11r. P. W. Kruse, Manager Engineering Services Post Office Box 500 Windsor, Connecticut 06095 Calvert County Library Prince Frederick, tiaryland 20678 D
0 ek3 U']FT 5 f gh [0]ddd " b g
1042 230
ENCLOSURE RE0 VEST FOR ADDITIONAL INFORMATION SPENT FUEL POOL CAPACITY EXPANSION CALVERT CLIFFS NUCLEAR POWER PLANT A.
The amount of boron that you are proposing to put in the plates in the proposed racks does not appear to be sufficient to keep the kaff in the proposed racks at or below 0.95 for a fuel assembly loading limit of 48.5 grams of uranium-235 per axial centimeter of fuel assem ly.
In o
view of this please provide the following additional infonnation:
1.
Provide the change in your calculated keff for the proposed stcrage lattice when the fuel assembly loading is changed from 48.5 to 43.8 grams of uranium-235 per axial centimeter of fuel assembly.
2.
Provide a description of the calculations you made'for the above change in fuel loading and also the one for the kef,of the minimum lattice pitch (i.e., 9.625").
Include a statement 6n whether or not you generated a neutron energy spectrum for each of the above cases to get accurate, effective, neutron reaction cross. sections for every case.
3.
Since it is our understanding that the 16 group Hansen-Roach cross section set was developed for fast spectrum reactors, provide justification and verification of its use in a primarily thennal neutron energy spectrum.
4.
Provide a proof that the effective boron region cross sections you used in the KENO-IV verification calculation are accurate.
5.
Provide a copy of NES 81A0567, " Nuclear Design Analysis Report for the Calvert Cliffs Unit #1 Nuclear Plant High Density Spent Fuel Storage Racks," dated March 1979, which is referenced in your submittal.
6.
The NRC requires verification that the amount of boron used for the calculations is actually in all of the storage containers which are put into the spent fuel pool.
Part of this required veritication is an on-site neutron attenuation test for missing plates. Provide a description of the way you will verify that the amount of boron you used in your calculations is actually in the storage containers.
Include a description of the on-site neutron attentuation test that you will perform.
7.
The NRC requires the licensee to have a method to verify that the amount of boron used for the calculations remains in the plates throughout the life of the racks.
Provide a description of this verification method.
1kkb q
, g,7 g 6 RL aj Ju R 1042 231
~
B.
The following information regarding personnel radiation exposure, waste handling and cask drop analysis is needed. _
l.
A collective dose of 3.75 man-rem has been estimated for modification of the North pool. Provide a breakdown of this estimation in accordance with a) the number of workers involved in each phrase of the operation, b) the exposure rate (mr/hr) to the workers during each phase of the-operation and c) the time the workers will spend in this radiation field.
Include in your breakdown the exposure rate from the contaminated racks and comensurate
~
exposure to workers during removal, decontamination, crating and shipping of the racks.
2.
Provide the additional occupational exposure (man-iem/yr.) that will be received by workers in the SFP area during normal operations, including refueling, as a result of the modification.
3.
Provide the estimated volume of contaminated material (e.g., spent fuel racks, seismic restraints) expected to be shipped from the plant because of the pool modification to a licensed burial site.
4.
Discuss in some detail the impact of the proposed pool modification on radioactive liquid and gaseous effluents and solid radwaste shipments from the plant.
Include a discussion of the pool leak collection system and history of leakage from the pool.
5.
Provide the estimated failed fuel fraction for each fuel cycle at Calvert Cliffs Units 1 and 2.
6.
Identify any heavy load or cask drop analyses performed to date for your facility.
Provide a copy of all such analyses not previously submitted to the NRC staff.
7.
Provide a list of all objects that are required to be moved over or near the spent fuel storage pool.
For each object listed, provide its approx-imate weight and size, a diagram or description of the transfer path utilized, ana the frequency of movement.
D@]D
)}
- mpya7q, aJU A Judas 1042 232