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
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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 I Ci 1.975 l 1
S.
)
l
- Mat'1s disposed of under our allocation at Barnwell by vendor when said items could not be decontaminated.
I
~
8708310238 B70820' 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
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 * = Inferred - Not Measured on Site J
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) 1
- 3. Solid Waste Disposition: j Number of Shipments Mode Destination 5 Truck Richland, Wash. I l
1 Truck Barnwell, S.C.
I B. Irradiated Fuel Shipments: j (N
%.)
Number of Shipments Mode Destination 1
l 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-
,s tions or setpoint determinations.
O 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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