ML20238A835

Solid Radwaste Disposal Semiannual Rept,870101-0701

ML20238A835
Person / Time
Site:	Prairie Island
Issue date:	07/01/1987
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20238A816	List: ML20238A812 ML20238A823 ML20238A835 ML20238A866 ML20238A885
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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