ML20005E303

Forwards Response to Environ Questions Providing Necessary Clarification for Final Review of License Renewal

ML20005E303
Person / Time
Site:	07001201
Issue date:	12/19/1989
From:	Lester K BABCOCK & WILCOX CO.
To:	Horn M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
26205, NUDOCS 9001050033
Download: ML20005E303 (9)

Text

RETURN TO 3 o 7A'N/

B&W FuelCompany fM3 An Awican company wim Y

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P.O. Box 11646 worlowice menoveces ysgpe Lynchburg, VA 24500 1646 C

DEC27}&% D r

19, 1989 NieSS MML SicTION

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. x. :p on Ms. Merri Horn y,,,

Uranium Fuel Section u:NRc Fuel Cycle Safety Branch

- g' DEC271339 y J0 Division of Industrial and Medical Nuclear Safety, NMSS kuss MM EDON fj United States Nuclear Regulatory Commission

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DOCKU CLERN Washington, D.

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20555 N

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REFERENCE:

(1)

SNM-1168 License Renewal, Docket 70-1201

Dear MS. Horn:

Enclosed la B&W Fuel Company's written response to the six environmental questions received by you on November 14, 1989.

We hope they provide the necessary clarification for final review of the environmental portion of our license renewal.

I may be reached at (804) 522-6202 if I can be of any assistance.

Sincerely, B&W FUEL COMPANY COMMERCIAL NUCLEAR FUEL PLANT 01mu,~ S. hu K.

S.

Lester License & Control Administrator l

l 9001050033 891219 PDR-C ADOCK 07001201 PDC

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ENVIRONMENTAL QUESTIONS COMMERCIAL NUCLEAR FUEL PLANT DOCKET NO. 70-1201 t

i 1.

In the June 21, 1989, response to question 9, CNFP indicated that the SERF operations are moving to the main building.

When this move is completed, will the operations discharge through the main atack or a separate stack?

If the I

discharge is through a separate stack, provide the specifications for the atack (i.e.,

diameter, height, i

location in comparison to main stack).

The Field Operations Department began operation of the Service Equipment Refurbishment Facility (SERF) on December 2, 1989.

It utilizes the same stack as the plant operations.

As of December 2, 1989, the air samples are analyzed for alpha and beta / gamma.

Although operations began on December 2 in the SERF, the ECHO 330 building la still in operation.

The specifications for two stacks that we are currently using was provided to you in the previous report.

2.

Provide a copy of your current NPDES permit.

We are still operating under our expired permit.

After much discussion with the State Water Control Board, we have submitted proposed modifications for their approval.

We have taken the initiative on this issue and feel that the State is pleased with the direction we are taking.

Upon approval of the proposed changes, the necessary modifications will be made and the receipt of the NPDES should follow.

A copy of the permit will be forwarded to you upon receipt.

l l

3.

How much mixed waste is currently onsite?

How much does l

CNFP generate on an annual bseis?

What are CNFP's plans for disposing / storing any mixed waste generated by CNFP7 l

We presently are storing two 55 gallon drums which contains i

acetone and uranium rags and one 55 gallon drum which contains TCE and uranium rags.

Approximately three 55 gallon drums are generated on an annual basis.

The Naval Nuclear Fuels Division has agreed to accept this waste for storage.

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4.

In 1988, a time when radioactive particulates were no longer i

being introduced to the retention tanks, over 280 microcuries of uranium was discharged via the liquid effluent.

This compares to a 1987 total of about 180 micrccuries of uranium, the last year in which discharges were made.

The total for the first half of 1989 was 150 microcuries of uranium.

This is not consistent with the statement the all radiological contaminated water is routed to the evaporator.

While some accumulation in the collection system from past operations is to be expected, the recent releases are higher than would be expected from residual contamination.

Explain.

The unusually high uranium discharge for the first half of 1988 was a result from the flushing of the liquid effluent discharge line on April 23, 1988.

The total uranium released that month was 103 microcuries compared to the monthly average of 22 microcuries for the sut month period.

This brought the semi-annual discharge total above normal for the first half of 1988.

See Attachment I for documentation of the flushing release.

Another contribution for the above normal releases in 1988 was due to the water linen leading to the retention tanks being leak tested in the month of March.

Attachment II and Attachment III are the monthly liquid effluents records for March and April.

[

Presently, we release an average of less than one percent of MPC.

l 5.

The air concentration (Table 11) for the third quarter of 1986 are about a factor of ten higher than other quarters, there does not appear to be a corresponding increase in gaseous effluents.

Provide en explanation for this increase.

L At the time of question, environmental air samples were l

being taken one per month not on a continuous basis.

One sample from each location (A, C, and F) was taken on August 1,

1986.

During this time frame the CNFP was on their annual shutdown and not in operation.

Therefore, the abnormal results do not appear to be related to CNFP operations.

The gaseous effluent results from the stack (Table 1) reported normal air concentrations which further supports this conclusion.

l

1 i

The above normal resulta did not warrant investigation.

The procedure in place at this time, AS-1127, and at the time in l

question, does not addrosa evaluation levels.

This has been an oversight and corrective action will include adding evaluation levels for environmental air samples and TLD exposures to AS-1127, Exhibit C.

6.

Provide a legible site map (figure 9.1, page 9-7) that is suitable for copying.

A new site map la attached.

The original, before reduction to license format, la also attached.

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3 ATTACHMENT I To:

W.

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En el e May 27, 1988 From: K.

E.

Subjt Liquid Effluent Releases On April 23, 1988 flushing of the liquid effluent discharge line,to remove all residual sludge was cornpleted At that time, all flush water passing through the line analy:ed below minimum detectable levels for radioactive particulate. From April 23 through May 24 we have had 28 batch releases (27,129 gallono). Two of the batch releases have analyzed positive for radioactive particulate. However, both releases were approaching our minimurn det ect able level.

Assurning the ef fluent did contain radionuclides an effort was made to determine possible sources. The following areas are potential contributors:

• A small residual of Uranium remains in the discharge line.

-

• Radioactive particulates were released through the 2 open floor drains in the plant controlled area.

• There is a sludge residual containing radioactive particulate in the controlled area floor drains (These lines were not flushed).

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Radioactive particulate was passed through the Met Lab discharge line.

It is my opinion the open floor drains in the plant controlled area have the most potential for release of radioactive particulate. It is my recommendation that all open floor drains leading to the liquid effluent discharge line be closed to prevent the unintentional release of hazardous waste to the environment.

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ATTACHMENT II B B W FUEL C3MFANY G -52 (1/291 CCMMEECIAL NUCLEAR FUEL FLANT LIQUID EFFLUENT REC 3RD TOTAL VDLUME LELEAEED 26495 6ALS. 1.00E+0B al MFC 3.0E-05 utilal TOTAL ACTIV!iY RELEASED 4.13E+0! ut!

TOTALURAh!UMFELEABED 22.B15 BRATS MDNITOK! ' *RIOD: MARCH 1969 AVEFABE MFC

!.3901 SIBNATURE,,,,,,,,,,,,,,,,,,,,,

T XIMUM MPC 9.141%

NPDESFERMli4VA0004774 i

sts ::::::::::::::::::::::::::::::: 38 ::::::: 23 ::::::::13 ::: 8 ::13 ::::::::::::::::::::::::: st:8 ::::::::::::::::::::::

REL.

GROSS COUNT FKBD COUNT NET TOTAL pH ADJ. SLUDBE 1

4 DATE TIME BALS. COUNT TIME COUNT EFF.

CF M DFM/ti uti/el ge U pH.

MPC

.C

stratamesestessassesses Satessantenetsastasssastattass:::::::::::::::::::::::::::::38 : 8 :::::::::::::::: t ::::::::

25 3/01/88 945 915 4

15 0.12 0.33 0.268 0.5421 2.44E 07 0.4669

7. 0 0

0.8141 26 3/01/8B 1340 101B 1

15 0.12 0.33 0.269 0.5421 2.44E-07 0.5195 6.5 0

0.8141 27 3/02/88 1410 915 5

!$ 0.14 0.33 0.290 0.5E55 2.64E-07 0.5043 B6 0

0.6791 f

28 3/03/BB 1340 E45 4

15 0.12 0.33 0.268 0.5421 2.44E-07 0.4312 7.4 0

0.8141 29 3/04/EB 1500 000 47 15 0.12 0.33 3.013 6.0E75 2.74E-06 4.5B44 6.5 0

9.14116 30 3/05/EB 740 200 9

15 0.13 0.33 0.470 0.9495 4.2BE-07 0.7150 6.7 0

1.42618 31 3/05/EB 1150 1018 15 0.13 0.33 0.603 1.2169

'.49E 07 1.16B0 6.7 0

1.63018 22 3/07/SB 920 950 B

15 0.14 0.33 0.393 0.7946 3.5EE-07 0.7106 6.7 0

1.19316 33 3/07/EB 1400 350 6

!$ 0.14 0.33 0.290 0.5855 2.64E 07 0.1929 7

0 0.8791 34 3/07/BB 1555 360 6

15 0.14 0.33 0.290 0.5E55 2.64F-07 0.1964 10.0 7.4 0

0.B791 35 3/09/BB B40 895 9

20 0.16 0.33 0.290 0.5B59 2.64E 07 0.4936 7.3 0

0.BB01 36 3/10/BB 1400 915 15 30 0.21 0.33 0.290 0.5B59 2.64E-07 0.5046 7.0 0

0EB01 37 3/11/88 1510 B60 0

30 0.22 0.33 0.257 0.5190 2.34E-07 0.4202 0.6 0

0.7791 38 3/12/BB 1510 965 10 30 0.29 0.33 0.295 0.5959 2.6BE-07 0.5413 7.1 0

0.B951 39 3/13/BB 1555 101B 7

IO 0.20 0.33 0.300 0.6061 2.73E-07 0.5000

6. 9 0

0.9101 40 3/14/BB 1015 E45 32 30 0.26 0.33 0.807 1.6296 7.34E-07 1.2963 7.3 0

2.4471*

41 3/14/BB 1340 1018 46 30 0.26 0.33 1.340 2.7071 1.22E-06 2.5941 7.2 0

4.0651e 42 3/15/0B 1215 360 21 30 0.26 0.33 0.440 0.BES9 4.00E-07 0.3012 6.9 0

1.3351 43 3/15/BB B55 1016 12 30 0.29 0.33 0.295 0.5959 2.6BE-07 0.5710 6.3 0

0.E951 44 3/15/EB 1450 101B B

30 0.29 0.33 0.295 0.5959 2.lBE-07 0.5710 7.0 0

0.6951 45 3/16/BB 900 101B B

20 0.16 0.24 0.205 0.7906 3.56E-07 0.7576 6.4 0

.1971 46 3/16/SB 1405 1016 12 30 0.24 0.33 0.260 0.5421 2.44E-07 0.5195 6.1 0

0.8141 47 3/17/88 1020 1018 12 30 0.26 0.33 0.279 0.5642 2.54E-07 0.5407 5.1 6.9 0

0.8471 4B 3/IB/EB 720 950 9

30 0.26 0.33 0.279 0.5642 2.54E-07 0.5046 6.1 0

0.6471 49 3/21/BB 1240 1018 4

30 0.24 0.33 0.260 0.5421 2.44E-07 0 !!95 0.0 0

0.E!41 50 3/22/B9 1400 915 6

20 0.1B 0.33 0.225 0.5750 2.59E-07 0.4952 B.6 0

0.8631 51 3/25/BB 1030 950 11 20 0.20 0.33 0.350 0.7071 3.19E-07 0.6323 E.5 0

1.0621 52 3/2E/BB 915 950 10 30 0.24 0.33 0.260 0.5421 2.44E-07 0.4848 7.0 0

0.8141 f

53 3/29/EB 1210 B60 12 30 0.29 0.33 0.295 0.5959 2.6SE-07 0.4624 B.4 0

0.6951 54 3/30/EB 1300 915 B

30 0.29 0.33 0.295 0.5559 2.6EE-07 0.5132 B.6 0

0.B951 4 A RESULT OF THE WATER LINES LEALINS TO THE RETENil0NTANKSIEINSCOMPLETELYFILLED WITH WATER IN ORDER TO EE LEAK TESTED.

WHEN THE WATER WAS FELEASED INTO RETENTION TANK i 1, THE SLUDBE IN THE LINES WAS DRAWN INTO THE TANK ALONS WITH THE WATER.

WATER WAS DRAWN OUT OF FETENTION TANK l 1 INTD RETENil0N TANK 4 2, LEAVINS THE SLUDBE THE B011CM. SLUDBE hAS EEROVED ON 3/14/BB.

RETENil0N TANK 4 i WAS NOT IN USE FROM 3/4/BB 10 3/14/B6.

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ATTACHMENT III v

B 6 W FDEl. COMFANY

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COMMERt!A1; huCLEAR FUEL PLANT.

LIQUID EFFLUENT RECOLD I

'27AL' VOLT;ME FELEASED 20133 SALS. 7.62E+07 al MPC = 3.0E 05 utiis!

72iAL ACTIVITY EELEASED 1.03E+02 uC!

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172T;.L URAN 1llM FELEASED 56.904BRAMS PDNliCRINB TER ' FFIL, 19 c

t AVEF. AGE MPC-4.5271

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MAI! MUM MFC 50.25B1 NFDESPERMlfBVA0004774 c:::::::::::::::::::::::::::::: :::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::e-h, AEL.

BALS. COUNT T!rE COUNT EFF.

CTM LFM/El uCl/tl ge U pH.

- MPC BROSS COUNT $LBD COUNI NET TOTAL pH AW. SLUDBE :1 l

t 5 ATE f!ME 48%858283388888888:8859858: 38TB88:85238888 8888884:188888888 88888:3888FE8888343:3333333838838888888888888:28888888:88888888888

!! 4/01/EB.

1000 965 20 0.18 0.;; 0.370 0.7475 :.;7E-07 0.6790 B.7 0

1.122%

!6. 4/04IBB 1440-

,101B '

6 30 0.23 0.33 0.263 0.5307 2.39E-07 0.50B5 6.3 0

0.7971' 57'L4/06/BB 1010 915 10 30 0.23 0.33 0.263 0.5307 2.39E-07 0.4571 B.4 0

0.797%

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P 4/07/89 1215 965 3

15 0.14 0.33 0.290 0.5855 2.64E-07 0.5:19 B7 0

0.879%

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$7, 4/08/98 1315 895 4

20 0.20 0.33 0.000 0.6061 2.73E-07 0.5106 10.0 7.9 0

0.9101 M~4/11/BB 945 1018.

9 30 0.29 0.33 0.295 0.5959 2.6BE-07 0.5710 B.0 0

0.8951 M 4/12/BB 1410 '

B25' B

20 0.18 0.33 0.295 0.5750 2.59E-07 0.4465 7.3 0-0.8631 M 4/15/BB B00 915 6

20 0.17 0.33.0.277 0.55BB 2.52E-07 0.4813 6.7 0

0.8391 63 4/16/BB 1025 B60 62 30 0.23 0.33 1.637 3.7104 1.67E-06 3.00!B 7

0 5.5722 64.4/16/98

-1330 B95 64 30 0.23 0.33 1.903 3.8451 1.73E-06 3.2395 6.8 0.5.7741 65 4/16/88 1710 950 81 30 0.23 0.33 2.470 4.9899 2.25E-06 4.4623 6.8 0

7.4931 66 4/19/BB 1220.

860 27 30 0.24 0.33 0.660 1.3333 6.01E-07 1.0794 7.0 0

2.002%

67 4/21/88 B10 895 22 30 0.30 0.33 0.433 0.8754 0.94E-07 0.7375 7.3 0

1.3151 68 -4/21/88 2120 965 506 30 0.30 0.33 16.567 33.46B0 1.51E 05 30.4021 6.9 0 50.2561

.. 6 9 4/23/5B

!!00 710 145 30 0.25 0.33 -4.583 9.2593 4.17E 06 6.1864 6.3 0 13.9041 70-.4/26/BB 840 915 12 30 J.30 0.33 0.300 0.6061 2.73E-07 0.5220 6.7 0

0.9101 71 4/27/88 1400 1018 8

20 0.20 0.33 0.300 0.6061 2.73E-07 0.5808 7.1 0

0.9101 12 4/29/BB 640 1018 7

20 0.16 0.33 0.268 0.5421 2.44E-07 0.5195 6.2 0

0.8141 73-'4/2B/88 B55' 995 B

20 0.16 0.33 0.268 0.5421 2.44E-07 0.5077 6.1 0

0.814%

P74 4/29/BB 1400 101B 14 30 0.23 0.33 0.263 0.5307 2.39E-07 0.50B5 3.3 7.4 0

0.7971 75 4/29/SB

!!!5 1018 18 30 0.23 0.33 0.370 0.7475 :.37E-07 0.7163

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1.122%

1,76 4/29/BB 1550 500

.9 30 0.23 0.33 0.263 0.5307 2.39E-07 0.249B 2.9 7.5 0

0.7971 L

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.B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1160,. DOCKET 70-1201 i

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