ML20238A835
| ML20238A835 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/01/1987 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20238A816 | List: |
| References | |
| NUDOCS 8708310238 | |
| Download: ML20238A835 (7) | |
Text
.
PINGP 753, Rev..1 Retention:
Lifetime (3
Page 1 of 5 G
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-87 en 7-1-87 j
NORTHERN STATES POWER License No. DPR-42 i
SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT I
I Table I:
Solid Waste and Irradiated Fuel Shipments A.
Solid Waste Total Volumes and Measured Curie Quantities:
1.
Type of Waste:
Container j
Units Total Volumes 4
A.
Spent Resins CU-FT 690 172.5 m
in_69 B.
O V
C.
Non-Decontaminable CU-FT 350 Scrap Metal D.
Filter Media CU-FT 163 163 Ci 1.975 l
1
)
S.
- Mat'1s disposed of under our allocation at Barnwell by vendor when said items could not be decontaminated.
8708310238 B70820'
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PDR ADOCK 05000202 R
PDR l
1
,T PINGP 753,.Rev. 1 Retention:. Lifetime Page 2.'of 5 x.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-87 to.7-1-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:
Solid Waste and Irradiated Fuel-Shipments-(Continued) 2.
Measured Major Nuclide Composition by Type of Waste:
TYPE' (From Page 1)
Nuclide' Percent A
- H-3 34.1
- Fe-55 14.2 Cs-137 0.7
- Ni-63
-23.6 Co-60 5.6 Co-58 19.9 Mn-54 0.8 i
O D
- C-14 44.4 Co 10.4 Sb-125 1.1 I
I
- Fe-55 24.3
- N1-63 4.2
- Sr-90 1.0
- M-3 11.4 Cs-137 1.6 O
J
- = Inferred - Not Measured on Site 1
l
PINGP 753, Rev. 1 Retention:
Lifetime.
Page 3 of.5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-87 to 7-1-87 NORTHERN STATES POWER License No. DPR-42 i
l l
\\
SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT' Table 1:
Solid Waste and Irradiated Fuel Shipments (Continued) 2.
Measured Major _Nuclide Composition by Type of Waste (Continuation):
TYPE (From Page 1)
Nuclide Percent C
- Fe-55 24.8 Co-60 6.8
- Ni-63 13.7 Sb-125 54.0 1
l O
4 l
l ba
- = Inferred - Not Measured on Site
4 PINGP 753, Rev. 1 Retention:
Lifetime Page 4 of 5 k
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-87 to 7-1-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT i
Table I:
Solid Waste and Irradiated Fuel Shipments (Continued) 3.
Solid Waste Disposition:
j Number of Shipments Mode Destination 5
Truck Richland, Wash.
I 1
Truck Barnwell, S.C.
B.
Irradiated Fuel Shipments:
j (N
Number of Shipments Mode Destination
%.)
1 O
PINGP 753, Rev. 1 Retention:
Lifetime Page 5 of 5 O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-87 to 7-1-87 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REFORT Table I:
Solid Waste and Irradiated Fuel Shipments (Continued)
C.
Shipping Container and Solidification Method:
No.
Volume Activity Type of Container Solidify (Ft3)
(C1)
Waste Code Code 87-4 172.5 1.211 A
T.
MA 87-5 172.5 2.789 A
L MA 87-6 172.5 1.741 A
L MA 87-7 172.5 4.876 A
L MA 87-9 163 1.975 D
T NA 350 C
L NA CONTAINER CODES:
L = LSA A = Type A B = Type B Q = Large Quantity i
I SOLIDIFICATION CODES:
C = Cement TYPES OF WASTE:
A = Resins B = Dry Compacted C = Non-Compacted D = Filter Media S = Spent Fuel
- Mat'l was non-decontaminable items and disposed of by vendor under our allocation at Barnwell.
I REVISION 9 Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual i
l In accordance with the Prairie Island Technical Specifications 6.5 E, Offsite Dose Calculation Manual (00CM), the following changes to the ODCM are reported:
A.
A description of how the results of composite sample analyses are handled and reported was added (pp. 6,15,28,32);
B.
As a result of an NRC evaluation, an incomplete formula was clarified (p.12);
)
C.
As a result of an NRC review, the inhalation dose conversion factors were changes from INFANT to CHILD; and D.
The description of the Environmental Monitoring Program sampling
)
was changed to reflect a recent revision of the Technical Specifications (p. 60).
These changes do not reduce the accuracy or reliability of dose calcula-tions or setpoint determinations.
,sO These changes were reviewed and found acceptable by the Prairie Island Operations Committee on June 29, 1987.
i Instructions for Entering Revision 9 to the ODCM Manual Remove the existing contents of the ODCM Manual and replace with the attached pages.
R-2 LETTER
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