ML20042A004
| ML20042A004 | |
| Person / Time | |
|---|---|
| Site: | 07002936 |
| Issue date: | 03/04/1982 |
| From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| To: | Page R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 20347, AECM-82-82, NUDOCS 8203220540 | |
| Download: ML20042A004 (6) | |
Text
70- M
[jfj MISSISSIPPI POWER & LIGHT COMPANY @[
Helping Build Mississippi
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B O X 16 4 0. J A C K S O N, MISSISSIPPI 39205
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NUCLE AH PROoUCTioN DEPARTME NT e
N U.S. Nuclear Regulatory Commission kEC[W{Q Uranium Fuel Licensing Branch k
2 Division of Fuel Cycle and M4f?
flaterial Safety, NMSS dSh r
ny Attention:
Mr. R. D. Page g,,, ; *-
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Dear Mr. Page:
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SUB'JF T:
Grand Gulf Nuclear Station com no V.
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File 0272/10260/L-869.0/
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015175/M-001.0 f_I i'
Amendment Request for NRC IWA 6
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Materials License No.
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Reference:
MAEC-81/156 Q
,Y AECM-82/82
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In accordance with 10 CFR 70.34 (Amendment of Licenses),
Mississippi Power & Light Company (MP&L) requests that License SNM-1882 dated July 15, 1981, be amended to permit receipt, possession, inspection, and use of fourteen (14) neutron souces enriched in Sb-124 with up to 2800 Curies / source. These neutron sources will replace the fourteen Sb-124 sources (source strength up to 1400 Curies / source) previously licensed to t!P&L in License No. SNti-1882.
As discussed with your Mr. N. Ketzlach by our Mr. J. Harrington on March 4, 1982, the increased source strength is required due to the scheduling of the neutron sources out of the irradiation facility and subsequent shipment to the Grand Gulf site in order to support installation of the sources and checkout of the neutron monitoring system required prior to loading of nuclear fuel.
The fourteen neutron sources will be shipped in two casks (7 sources / cask) and will arrive on-site between April 11-13, 1982.
Attached are eight (8) copies of the necessary page changes to our license application dated April 27, 1981 and as further amended by our letters of October 9, 1981 (AECM-81/383) and December 8, 1981 (AECM-81/478).
Please note that Page 30A and 32A were previously submitted to you in our April 27 and October 9, 1981 letters, respectively.
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8203220540 820304 AA PDR ADOCK 07002936 C
PDR 203W AE1J1 Member Middle South Utilities System
AECM-82/82 MISSinlPPI POWER Ct LIGHT COMPANY Page 2 Your continued prompt consideration and approval of this amendment request is appreciated. Should you require further clarification or have any questions, please contact Mr. Charles Tyrone (601-969-2631) or Mr. Jacky Harrington (601-969-2490).
Your truly,
- }+>
I L. F. Dale Manager of Nuclear Services JDH:1m Attachments cc:
Mr. N. L. Stampley (w/a)
Mr. G. B. Taylor (w/a)
Mr. R. B. McGehee (w/a)
Mr. T. B. Conner (w/a)
Mr. Richard C. DeYoung, Director (w/a)
Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 i
f i
20347 AE1J2 i
SNM License March 6, 1982 Page 30 8
Special Nuclear Material (In-core Detectors)
Quantity Description Grams U-235 Activity (microcuries)
(See Note Per Per Below Detector Total Detector Total
-6
-5 12 SRM Detectors
.0027
.0324 5.85 x 10 7.02 x 10 5.1x10}6
-5 16 IRM Detectors
.00074
.01184 1.62 x 10 2.592 x 10 352 LPRM Detectors.00022
.07744 1.7952
-6
-5 10 TIP Detectors
.000744
.00744 1.62 x 10 1.62 x 10 NOTE: All of the above devices are sealed sources.
Neutron detectors may be temporarily stored in the MP&L warehouse under the auspices of the Interim Security Plan. The neutron detectors will be stored in a locked area while in the warehouse.
[SEE ATTACllED PACE 30A]
The TIP detectors will be stored inside the vessel in the TIP guide tubes or in the TIP storage tubes located between the weir wall and drywell wall. The areas containing these detectors will be designated and posted as radiation areas if required.
The Radiation Protection Manager has overall responsibility for radiation protection (see Figures 11 and 12).
[SEE ATTACilED PAGE 30B]
9
SNM License March 4, 1982 Page 30B
[ INSERT 30B]
Radioactive Sources Maximum Description Quantity Isotope Est. Activity Each Ope ra t i ona l 14 Sbl24 2800 Curies / Source Source (Seven (7) operational sources with two (2) 2800 Curie (maximum) pins each)
The operational sources will be shipped in two lead filled drums approximately 48" tall and 31" in diameter, which meet DOT package specifications (Figure 13). The source is positioned within a 7" diameter x 25" long cavity which is centered in the drum and surrounded by lead shielding.
The cavity is scaled with a lead plug. This shipping container is a General Electric Model 1500 Shielded Container, licensed with the DOT under S.P. No. 5939.
Seven sources will be contained in each Model 1500 container.
Consistent with recommendations of Regulatory Guide 8.8, MP&L has committed to establish a health physics program to maintain occupational and general public exposure to radiation "As Low As Reasonably Achievable" (ALARA). An MP&L Corporate ALARA policy is in force and the methods for its implementation are described in GGNS Administrative Procedure No.
01-S-08-2.
9
SNM License March 4, 1982 Page 32 5.
The shipping container will then be transferred through the equipment hatch to Elevation 166'-0" and into the Containment Building.
6.
The shipping container is then lifted to Elevation 208'-10".
7.
The jacket is then lif ted off the Icad cack and IIcalth Physics will survey the lead cask.
8.
The shielding cask lid bolts are removed, the lid will remain in place.
9.
The lead cask containing the Sb sources is then lowered into the upper containment pool and brought to rest on the bottom of the pool at Elevation 184'-6".
The pool will be filled with water. When pool level is established at Elevation 207'-10", the cask lid may be removed. The individual sources will then be loaded into the seven source holders (see Figure 14).
The estimated dose for this procedure is less than five millirem per hour. When all source holders are loaded and in place in the source holder rack, the source holder rack will be transferred to the reactor cavity. The top of the source holder rack will be submerged at least five feet at all times during trans fer operations. The source holders may then be installed in their designated positions inside the reactor vessel. The source holders will remain submerged at least five feet at all times during installation. The estimated exposure rate for installation of the seven source holders is expected to be less than 20 millirem per hour.
[SEE ATTACHED PAGE 32B]
To minimize exposure, access to the Containment Building will be restricted during source handling, transfer, and installation to those personnel directly involved with source handling operations or radiation monitoring.
Radiation protection personnel will be continuously present during all source handling operations. Radiation protection personnel will be responsible for operating standard radiation survey instrumentation including a portable tisste equivalent neutron detector. TLD's and self-reading dosimeters will be provided to all personnel to monitor personal exposure. Radiation surveys will be conducted of the area after the transfer has taken place.
Consistent with MP&L's ALARA policy, a minimum of 5 feet of water will be maintained above the sources when moving them to provid-proper shielding. Also, a minimum of 5 feet of water shielding will also be provided above the lead cask containing the sources upon removal of the cask lid.
It will be MP&L's ALARA goal to limit the maximum exposure to any individual involved in source handling operations to less than 30 millirem (whole body), and to limit exposure to all iudividuals involved in source handling to less than 0.2 man rem.
[SEE ATTACllED PAGE 32A]
SNil License
+
March 4, 1982 Page 32B
[ INSERT 32B]
Dose rates are estimated to be 60 millirem per hour at. the surface of the cask and 4-5 millirem per hour at 3 feet from the cask (in air).
S 9