ML19290D924

Fifty-Fourth Quarterly Rept for Jul-Sept 1979, Per Provisional License CSF-1

ML19290D924
Person / Time
Site:	West Valley Demonstration Project
Issue date:	10/25/1979
From:	NUCLEAR FUEL SERVICES, INC.
To:
Shared Package
ML19290D923	List: ML19290D922 ML19290D924
References
14525, NUDOCS 8002290484
Download: ML19290D924 (59)

Text

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TABLE OF CONTEflTS ENVIRONMEllTAL MONITORIllG LOW LEVEL LIQUID EFFLUENTS GASE0US EFFLUENTS SURVEILLANCE TESTS LOW LEVEL LIQUID WASTE TREATf1ErlT PLANT PERFORMANCE TABLE 1 LIQUID EFFLUENTS - 1979 TABLE 2 GASE0US EFFLUEflTS - 1979 TABLE 3 SURVEILLANCE TESTS TABLE 4 FILTER REPLACEMEtiT PROCESSING

SUMMARY

NUCLEAR FUEL

SUMMARY

TABLE 5 NUCLEAR FUEL STATUS - SEPTEMBER 30, 1979 RADI0 ACTIVE WASTE FACILITY PERFORMANCE AND MODIFICATIONS D

800e290 % S j$ 4

ENVIRONMEftTAL M0flITORIflG 131I was dis-As a result of changes in Technical Specifications, sampling milk for continued on September 21, 1973.

Thirty-nine (39) samples were obtained during the third quarter from the perimeter monitoring stations and were analyzed for alpha and beta activity.

The algha activity ranged from 1.38 (10 16) to 1.14 (10 15) uCi/ml for an average of 3.29 (10 16)uCi/ml.

The beta activity ranged from 5.84 (10 15) to 5.57 (10 14) pCi/ml with an average of 1.86 (10 14) uCi/ml.

LOW LEVEL LIOUID EFFLUENTS The amounts of radioactivity in liquid discharged from the plant during this period and their relationship to the maximum permissible concentration (MPC) in the Cattaraugus Creek are shown in Table 1.

GASE0US EFFLUENTS The amount of particulate radioactivity discharged via the plant stack and the relationship to the release limit in the Technical Specifications is shown in Table 2.

Change 20 to the Technical Specifications discontinued the reouirements of Krypton-85 and Iodine-131 monitoring while plant operations are suspended.

SURVEILLANCE TESTS During this period, tests were performed in accordance with Section 6 of the Technical Specifications.

The completion dates are shown in Tables 3 and 4.

LOW LEVEL LIQUID WASTE TREATMENT PLANT PERFORMANCE During this period, the LLWT was in operation a total of 11 days and treated 1,149,000 gallons of water.

Forty (40) drums of concentrated sludge were removed, each having a radiation level of <10 mr/hr.

Decontamination of waste water continues to be good.

All water discharged has been below 2.0 x 10 s _Ci Csl37/ml. Average removal factors for this period are shown below.

AVERAGE REMOVAL FACTOR Isotope Previous Quarter This Quarter Cs-137 82.6 89.2 Sr-90 98.3 Not Yet Available Ru-Rh-106 Below Detection Limits Below Detection Limits Gross Beta 95.7 93.9 No significant developments or modifications to the facility have occurred during the past quarter and operation has been routine.

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Table 1 LIQUID EFFLUErlTS--1979

[ Curies) a

% MPC Measured 90 129 Month Gross a Gross 8 Tritium Sr I

In Cattaraucus Creek c

Jan 0.000001 0.00004 0.0007 0.00001 tiR 0.41 c

Feb 0.000001 0.00001 0.0004 0.00001 flR 0.38 Mar 0.00013 0.016 3.3 0.0027 0.00010 0.25 c

Apr 0.000001 0.00003 0.0004 0.0001 f;R 0.39 c

May 0.000001 0.00002 0.0001 0.0C001 f;R 0.27 c

Jun 0.000001 0.00003 0.0008 0.00001 fir 0.48 c

b Jul 0.000001 0.00005 0.0008 0.00001 fir NA b

b Aug 0.00033 0.031 3.0 flA 0.00012 NA b

c b

Sep 0.000001 0.00006 0.0004 fiA NR 11A d

1979 0.00046 0.047 6.3 0.0028' O.00022 0.36 a

MPC (8) = 3.0 (10 7) pCi/ml when Sr90 analyses are n;' available MPC (8) = 1.0 (10 s) pCi/ml when Sr90 analyses are included separately MPC (a) = 5.0 (10 6) pCi/ml briot yet available cNot required; there were no Lagoon 3 effluent releases for the month d

MPC through June 1979

' Release through July 1979 1d E.7']

Table 2 PARTICULATE GASEQUS EFFLUENTS Month Curies

% Monthly Limit January

.00008 0.03 February

.00008 0.03 March

.00004 0.01 April

.00016 0.07 May

.00007 0.03 June

.00007 0.02 July

.00012 0.05 August

.00007 0.03 September

.00028 0.09 1979

.00097 0.046 1d5.'?3

Table 3 SURVEILLAtlCE TESTS Spec. #

Subject Completed This Quarter Comments 6.1 Raschig Ring Tanks Tanks are to be scheduled prior to

.xt processing use 6.2 Sump Alarms and Eductors XC-2 7-17, 8-7, 8-28, 9-18 Satisfactory XC-3 7-17, 8-7, 8-28, 9-18 Satisfactory PPC 7-17, 8-8, 8-28, 9-18 Satisfactory 6.3 Waste Storage Tank Pan Instrumentation 8D-1, 8D-2 7-17, 8-10, 8-28, 9-18 Satisfactory 8D-3, 8D-4 7-17,8-10, 8-28, 9-18 Satisfactory 6.4 Emergency Utility Equipment 30T-1 7-3 Satisfactory 31K-1 7-3 Satisfactory 32G-4B 7-3 Satisfactory 31G-2, 2A 8-12 Satisfactory 31K-2, 2A 8-12 Satisfactory 32G-2A, 2B 8-12 Satisfactory Diesel Fuel 7-2, 7-9, 7-16, 7-23, 7-30, 8-6, 8-13, 8-20, 8-27, 9-3, 9-10, 9-17, 9-24 Satisfactcry Propane Fuel 7-3, 7-9, 7-16, 7-23, 7-31, 8-E, 8-14, 8-20, 8-28, 9-4, 9-11, 9-18, 9-25 Satisfactory 15K-10A 7-3 Satisfactory 15F-21 7-3 Satisfactory 6.5 Filters 7-6, 7-13, 7-20, 7-23, 8-3, 8-10, 8-17, 8-24, 8-29, 9-6, 9-14, 9-19, 9-28 Satisfactory 6.6 Dilution Air Not required this period 6.7 Boric Acid Not required this period 6.8 Locking Out Not required this period 6.9 Water Activity Alarms 9-28 Satisfactory 6.10 Poisoned Dissolver Baskets Not required this period 6.11 Solvent Analysis Not required this period LOTI:3

Table 4 FILTER REPLACEMENT The following filters were changed during this reporting neriod.

9/2/79:

Waste Tank Farm Off Gas Filter 8T-1 9/18/79:

Vessel Off Gas Filter 6T-2A 9/18/79:

Vessel Off Gas Backup Filters 6T-3, 3A

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PROCESSING

SUMMARY

During this period there was no processina of fuel.

O E -asdo J

NUCLEAR FUEL

SUMMARY

The following information is based upon nuclear material accountability records and indicates the disposition of nuclear material in fuel at the reprocessing plant.

A.

INVEfiTORY The total on-site inventory on September 30,1979 was 166,759 kilograms of uranium and 1,041,760 grams of plutonium. An inventory description by source and material type is presented in Table 5.

B.

RECEIPTS AND SHIPMENTS During the quarter, there were no shipments or receipts of spent fuel assemblies at the West Valley site.

C.

MEASURED WASTE AND ADJUSTMENTS There was no loss of uranium or plutonium during the reporting period as measured waste.

No adjustments for uranium and plutonium to NFS Lot 27A were required.

D.

LOSS ON DECAY During the period 3/31/79-9/30/79 there was a reduction of 1,979 grams of plutonium in stored fuel due to the radioactive decay of the Pu-241 isotope.

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Table 5 NUCLEAR FUEL. STATUS AS OF SEPTEMBER 30, 1979 Kilcarams Grams Total U U-235 U-233 Total Pu I.

INVENTORY (7/1/79) 306 NFS 3,271 8.01 Dresden-1 20,429 144.03 0.30 117,362 RG&E 46,156 722.48 286,856 64,282 Consumers 11,130 238.68 339,932 WEPC0 43,017 462.61 235,001 Jersey Central 42,756 463.42 TOTAL 166,759 2,039.23 0.30 1,043,739 II.

RECEIPTS (7/1/79-9/30/79)

No receipts during this period.

III. REMOVALS (7/1/79-9/30/79)

A.

Measured Waste Lot 27A 0

0 0

0 B.

Adjustments Lot 27A 0

0 0

0 C.

Radioactive Decay 0

0 0

1,979 TOTAL 0

0 0

1,979 IV.

INVENTORY (9/30/79) 306 NFS 3,271 8.01 20,429 144.03 0.30 117,122 Dresden-1 46,156 722.48 286,315 RG&E 64,199 Consumers 11,130 238.68 339,154 WEPC0 43,017 462.61 234,664 Jersey Central 42,756 463.42 TOTAL 166,759 2,039.23 0.30 1,041,760 1535

RADI0 ACTIVE WASTE A.

Solid Waste The radioactive plant waste buried during this quarter consisted of 1178.99 cu ft containing 228.472 curies. This material was buried in the NRC-licensed burial area.

B.

High Level Liauid Waste As of September 30, 1979, the high level storage tank 8D-2 con-tained 559,600 gallons of neutralized waste with an activity of 4,685 uCi Cs-137/ml and 91 uCi Cs-134/ml.

FACILITY PERFORMAtlCE Afl0 MODIFICATIO:15 This section describes:

1.

Major modifications that were either initiated or completed at the processing plant during the reporting period.

1.1 After review of the I&E Bulletin 79-08, a new breathing air line with dual filters was installed for the Fuel Receiving and Storage area.

1.2 The surface of the used portion of the t!RC burial area was regraded, covered with topsoil, and seeded.

2.

A description of malfunctions of any equipment listed in Appendices 5.2, 9.51, 9.53 and 9.56 of the Final Safety Analysis Report which are important to safety.

There were no malfunctions during the reporting period.

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