ML20058N336

Application for Amend to License SNM-1097,reflecting New Numbering Scheme of 10CFR20,new Methodology for Dose Limitations,New Exposure & Action Limits & New Definitions

ML20058N336
Person / Time
Site:	07001113
Issue date:	12/09/1993
From:	Winslow T GENERAL ELECTRIC CO.
To:	Pierson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9312210335
Download: ML20058N336 (31)

Text

7HNL GENuclear Energy n,cu a rw s an,w-man sv i

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PD Dm 7:D Wimt r, a NClWl n gi:a smo December 9, 1993 I

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Director Office of Nuclear Materials Safety & Safeguards U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Mr. R. C. Pierson Chief, Licensing Branch Division of Fuel Cycle Safety and Safeguards OWFN, Room 6H6, Mail 6H3

Subject:

License Amendment Request (Revision #43)

Reference:

SNM Material License SNM-1097, Docket # 70-1113 I

With reference to activities authorized by NRC License SNM-1097 at the General Electric Nuclear Energy Production (NEP) facility at Wilmington, NC, GE hereby requests approval, effective January 1,

1994, for the enclosed page changes to Part I of our current l

application.

1 The proposed changes to the application are necessary to' conform j

to the requirements of the revised 10 CFR 20.

The changes reflect the new numbering scheme of 10 CFR 20, the new methodology for dose limitation, the new exposure and action limits and the new definitions.

Additionally, the respiratory protection program has been modified to include a pr'otection factor of 10 for half mask respirators.

We are also providing notification that our facility name has I

changed from Nuclear Fuel and Components Manufacturing (NF&CM) to Nuclear Energy Production (NEP).

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200048 f@

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Mr. R.

C. Pierson l

December 9, 1993 l

Page 2 i contains an explanation of the requested changes by page and section. contains a list of the license pages by date of revision. contains the revised page changes to conditions of Part I of our current license application.

Changes to the amended pages are indicated with an asterisk (*)

in the right-hand column of each page.

In accordance with 10 CFR 70.21(a) (2), six copies of this appiication are being provided.

If you require additional information or would like to discuss this matter further, please contact me at (910) 675-5461.

Sincerely, GE NUCLEAR ENERGY fh,1 = - :S5 T. Preston Winslow, Manager EPS and MC&A

/sbm cc:

TPW-93-104

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Mr.

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Pierson December 9, 1993 i

Page 1 of 2 i

1 ATTACHMENT 1 EXPLANATION OF THE REQUESTED CHANGES i

i Existing Page (s)

Section Explanation 8

Changed " Revision by Page" section to reflect changes made in this submittal.

1-1.1 1.1 & 1.2 Changed the facility name from Nuclear Fuel and Components Manufacturing (NF&CM).to Nuclear Energy Production (NEP).

I-1.9 1.7.5.3 Changed references to be consistent with I-1.12 1.8.3.2 the new numbering scheme in 10 CFR 20.

I-1.19 1.8.8 &

1.8.9 I-3.5 3.2.1 I-3.17 3.2.4.3.1 Changed to include the new (10 CFR 20)

I-3.19(a) 3.2.4.3.3 methodology for dose limitation, the new I-3.20 3.2.4.3 exposure and action limits and the new I-3.26 3.2.4.9 definitions.

The lung counting frequency matrix was removed because the need for routine lung counting has been minimized based upon intakes determined solely by assigned airborne exposures.

J I-3,21 3.2.4.5.1 Changed to include wording describing that the respiratory protection program has been i

modified to include a protection factor of 10 for half mask respirators.

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Mr. R. C.

Pierson December 9, 1993 Page 2 of 2 i

Existing Page (s)

Section Explanation I-5.5 5.1.1.2 Changes made to implement meaningful action I-5.6 5.1.1.4 limits and wording pursuant to the new 10 I-5.8 5.1.2.3 CFR 20.

In addition, text changes were I-5.9 5.1.2.5.1 made to correct terminology references.

I-5.10 5.1.2.5.2 I-5.12 5.1.4 I-5.14 5.1.5 I-5.16 Table 5.1 I-5.19 5.2.1.2 I-5.21 5.2.1.2 I-5.22 5.2.2.2 I-5.25 Figure 5.5 I-5.26 5.2.3.1 l

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Mr.

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C. Pierson December 9, 1993 Page 1 of 1 ATTACHMENT 2 PAGE REVISIONS BY DATE J

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i REVISIONS BY PAGE Application Application Application Pace Date Page Date Page Date TABLE OF CONTENTS I-1.20 04/20/92 CHAPTER 3 I-1.20 (a) 05/10/93 1

10/23/87 I-1. 20 (b) 05/10/93 I-3.1 10/23/87 2

10/23/87 I-1. 2 0 (c) 05/10/93 I-3.2 10/23/87 3

10/23/87 I-1. 2 0 (d) 05/10/93 I-3.3 10/23/87 4

10/23/87 I-1.21 Or/16/88 I-3.4 10/23/87 5

10/23/87 I-1.22 0's/16/88 I-3.5 12/09/93 6

10/23/87 I-1.23 05/16/88 I-3.6 10/23/87 7

10/23/87 I-1.24 05/16/88 I-3.7 03/18/93 I-3.8 10/23/87 8

12/09/93 CHAPTER 2 I-3.9 10/23/87 9

12/09/93 10 09/07/93 I-3.10 10/23/87 11 10/29/93 I-2.1 02/06/89 I-3.11 10/23/87 12 10/13/92 I-2.2 02/06/89 I-3.12 10/23/87 I-2.3 02/06/89 1-3.13 10/23/87 I-2.4 02/06/89 I-3.14 10/23/87 I-2.5 02/06/89 I-3.15 10/23/87 PART I I-2.6 02/06/89 I-3.16

.10/23/87 I-2.7 02/06/89 I-3.17 12/09/93 I-2.8 02/06/89 I-3.18 05/06/92 CHAPTER 1 I-2.9 02/06/89 I-3.19 12/09/93 I-2.10 02/06/89 I-3.20 12/09/93 I-1.1 12/09/93

• I-2.11 02/06/89 I-3.21 12/09/93 1

I-1.2 05/16/88 I-2.12 02/06/89 I-3.22 05/06/92 I-1.3 05/16/88 I-2.13 09/07/93 I-3.23 10/34/87 I-1.4 10/22/91 I-2.14 02/06/89 I-3.24 10/23/87 I-1.5 05/16/88 I-2.15 02/06/89 I-3.25 10/23/87 I-1.6 05/16/88 I-2.16 09/07/93 I-3.26 12/09/93 I-1.7 12/03/90 I-2.17 09/07/93 I-3.27 05/06/92 I-1.8 05/16/88 I-2.18 02/06/89 I-3.28 05/06/92 I-1.9 12/09/93

• I-2.19 02/06/89 I-1.10 05/16/88 I-2.20 02/06/89 I-1.11 05/16/88 I-2.21 02/06/89 I-1.12 12/09/93

• I-2.22 02/06/89 I-1.13 05/16/88 I-2.23 02/06/89 I-1.14 05/16/88 I-2.24 02/06/89 I-1.15 05/16/88 I-2.25 02/06/89 I-1.16 05/16/88 I-2.26 02/06/89 I-1.17 05/16/88 i

I-1.18 05/16/88 I-1.19 12/09/93

• LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43.

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REVISIONS BY PAGE Application Application Application Page Date Pace Date Page Date CHAPTER 4 CHAPTER 5 CHAPTER 6 I-4.1 10/23/87 I-5.1 10/23/87 I-6.1 10/13/92 I-4.2 10/23/87 I-5.2 10/23/87 I-6.2 10/13/92 I-4.3 10/23/87 I-5.3 10/23/87 I-6.3 10/10/91 I-4.4 10/23/87 I-5.4 10/23/87 I-6.4 10/10/91 I-6.5 10/10/91 I-4.5 10/23/87 I-5.5 12/09/93 t

I-6.6 10/10/91 I-4.6 10/23/87 I-5.6 12/09/93 I-4.7 10/23/87 I-5.7 10/23/87 I-6.7 10/10/91 I-6.'8 10/10/91 I-4.8 10/23/87 I-5.8 12/09/93 I-6.9 10/10/91 I-4.9 10/23/87 I-5.9 12/09/93 I-4.10 10/23/87 I-5.10 12/09/93 I-4.11 10/23/87 I-5.11 10/23/87 CHAPTER 7 I-4.12 02/14/92 I-5.12 12/09/93 I-4.13 02/14/92 I-5.13 10/23/87 I-7.1 10/23/87 I-4.14 02/14/92 I-5.14 12/09/93 I-4.15 02/14/92 I-5.15 10/23/87 I-4.16 02/14/92 I-5.16 12/09/93 I-4.17 02/14/92 I-5.17 10/23/87 CHAPTER 8 I-4.18 02/14/92 I-5.18 10/23/87 I-4.19 02/14/92 I-5.19 12/09/93 I-B.1 05/03/93 I-4.20 02/14/92 I-5.20 10/23/87 I-4.21 02/14/92 I-5.21 12/09/93 I-4.22 02/14/92 I-5.22 12/09/93 I-4.23 02/14/92 I-5.23 10/23/87 I-4.24 02/14/92 I-5.24 10/23/87 I-4.25 02/14/92 I-5.25 12/09/93 I-5.26 12/09/93 I-5.27 10/23/87 I-5.28 10/23/87 r

I-5.29 10/23/87-I-5.30 10/23/87 I-5.31 10/23/87 LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43

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Mr. R.

C. Pierson December-9, 1993 Page 1 of 1

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ATTACHMENT 3 i

REVISED PAGE CHANGE TO CONDITIONS OF PART I OF OUR CURRENT LICENSE APPLICATION-A I

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I CHAPTER 1 STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS l

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1.1 CORPORATE & FINANCIAL INFORMATION l

l This licensing information document is filed by the l

Nuctear Energy Production (NEP) facility (identified in l

this document as GE-Wilmington) of the General Electric l

t Company, a New York corporation with the principal place of business at Schenectady, New York.

t 1.2 LOCATION & GENERAL DESCRIPTION OF WILMINGTON PLANT.

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GE Nuclear Energy Production operates a nuclear fuel l

fabrication plant in Wilmington, North Carolina.

At this site, GE occupies buildings for administrative, laboratory and manufacturing activities.

A site plan is j

included as Figure 1.1.

Fuel manufacturing activities are conducted within the fuel manufacturing area.

The full address is as follows:

GE Nuclear Energy, Nuclear Energy Production, (name of person and mail code),

P.

O. Box 780, Wilmington, NC 28402.

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l LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-1.1

1.7.5.2 Decontamination of non-combustible contaminated wastes to reduce uranium contamination levels, and subsequent shipment of such low-level radioactive wastes to licensed burial sites for disposal.

1.7.5.3 Treatment or disposal of combustible waste and scrap material by incinerar. ion pursuant to 10 CFR 20.2002 and 10 CFR 20.2004.

1.7.6 Offsite Activities Testing, demonstration, non-destructive modification, and storage of materials and devices containing unirradiated uranium, provided that such materials and devices shall be in GE control at all times.

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1.8 EXEMPTIONS & SPECIAL AUTHORIZATIONS 1.8.1 Recuirements for Prior Authorization of Activities by License Amendment Prior authorization by license amendment shall be required for the following activities:

1.8.1.1 Major changes or additions to existing processes which

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may involve a significant increase in potential or r

actual environmental impact resulting from utilizing such changes or additions.

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LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-1.9 i

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4 1.8.3.2 Nitrate-Bearing Liquids f

Authorization, pursuant to 10 CFR 20.2002, to dispose of

• nitrate-bearing liquids, provided that the uranium concentration does not exceed a 30-day average of 5 i

parts per million by weight of the liquids and the nominal enrichment does not exceed 6 weight percent U2:n, by transport to an-offsite liquid treatment system-located at Federal Paper Board Corporation, Riegelwood, North Carolina, in which decomposition of the nitrates; will occur and from which the denitrified liquids will l

be discharged in the effluent from the system.

The environmental. monitoring program as described in I

Section 5.1.4.2 is used to cont rol these activities.

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1.8.4 Use of Materials at Off-Site Locations l

1.8.4.1 Authorization to use up to 15 grams of U2:n at otner sites within the limits of the United States and at temporary job sites of the licensee anywhere in the United States where the Nuclear Regulatory Commission maintains jurisdiction for regulating the use of i

licensed material.

l The manager of the radiation safety function shall establish the safety criteria for material being used at

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of f site' 'locati~ons'.

It is also his responsibility'to designate the individual who will be responsible to 3

carry out these criteria.

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I LICENSE SNM-1097 DATE 12/09/93 Page DOCKET

~10-1113 REVISION 43 I-1.12 i

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1.8.8 Incinerator Operation i

l Authorization, pursuant to 10 CFR 20.2002 and 10 CFR 20.2004, to treat or dispose of waste and scrap material containing special nuclear material by incineration.

1.8.9 Posting l

For those areas within the Controlled Access Area in

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l which radioactive materials are processed, used, or stored, where it is deemed impractical to label individual containers pursuant to 10 CFR 20.1904, a sign

• stating "Every container in this area may contain radioactive material" shall be posted.

r 1.8.10 Uranium Recycle Enrichment Control j

Maximum enrichment in the Uranium Recycle (UPMP) l operation shall not exceed the minimum U235 enrichment approved by the nuclear safety function for any Uranium l

Recycle process.

i 1.8.11 Sanitary Sludoe Accumulation Authorization to accumulate treated sanitary. sludge containing trace amounts of uranium, in the sanitary sludge land application area pending final disposal.

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l DOCKET 70-1113 REVISION 43 I-1.19-l

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Each change room includes a " hot" side and a " cold" l

side, with a step-off area provided between the hot and cold sides.

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The personal clothing and other worker belongings are stored on the cold side in the change _ rooms.

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protective clothing (described in Section 3.2.4.4) _ is j

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made available on the cold side to personnel entering a controlled area.

Used protective clothing is stored on the hot side and collected there for processing through

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l the laundry facility.

Disposable protective clothing is used, where applicable.

Entry points to controlled areas are posted in t

I accordance with 10 CFR 20.1902.

Instructions controlling entry and exit from controlled areas are posted at the entry points.

Special instructions regarding reporting time in the controlled _ areas, personnel dosimetry badges, protective clothing, personnel surveys and emergency evacuation, etc., may also be posted as necessary.

Personnel survey meters are provided in the step-off area of each change room for use by personnel leaving the controlled areas.

Posted instructions address the l

use of the survey meters and appropriate decontamination methods.

Notification instructions regarding. _ _.. __

contamination detected during 'he exit survey are also t

included.

Personnel are instructed to notify the radiation protection function befcre performing decontamination activities if they detect any l

contamination on their face, or if the prescribed 1

LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-3.5 i

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i these special operations are burning, welding, and cutting operations which may result in increased airborne concentrations.

3.2.4.3 Internal Exposure Measurements 3.2.4.3.1 Airborne Exposure Assignment & Control Individual airborne exposure assignments are made based on airborne concentrations in the areas in which the individual worked and the time the individual spent in each area.

Internal control actions are provided to prevent an individual from exceeding the occupational exposure limits specified in 10 CFR 20.

Control' actions

• include restricting the individual from working in an area containing airborne radioactivity,-and actions are taken as necessary to assure against recurrence.

3.2.4.3.2 Bioassay Program Urine sampling action levels are established based on the appropriate biokinetic models for individuals assigned to work in areas where highly soluble and soluble uranium compounds are processed.

These areas include portions of the chemical conversion, uranium recovery unit (URU), uranium recovery from lagoon

__ slugges JURLS) and.. Chemet _ lab areas.. The...bica s s ay.._

program is conducted to reflect the applicable guidelines outlined in 10 CFR 20, " Standards for l

Protection Against Radiation", ICRP Publication No. 3 0, -

" Limits for Intakes of Radionuclides by Workers", July, t

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LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-3.17

For non-routine operations, perturbations, or an incident where it is suspected that soluble materials may have been inhaled or ingested, the radiation safety or radiation protection functions may request additional bioassay sampling.

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3.2.4.3.3 In vivo Lung Counting r

In vivo lung counting is provided for the timely detection and assessment of individual intakes of radioactivity and as a method to verify the adequacy of the air sample program..

Routine in vivo lung counting frequencies are established for individuals who normally work in areas where non-transportable uranium compounds are-processed.

Individuals are scheduled for in vivo lung counting based upon their airborne exposure assignments and previous counting results.

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LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-3.19 4

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Appropriate actions are taken based upon in vivo lung counting results to ensure the Annual Limit on Intake (ALI) will not be exceeded.

3.2.4.4 Protective Clothing i

Protective clothing is provided to cll persons who are required to enter controlled areas whers personnel contamination potential exists as determined by the radiation safety function.

The amount and type of protective clothing required for a specific area or operation is determined by operational experience and the contamination potential.

Available clothing includes caps, hoods, laboratory coats, coveralls safety glasses, boots, overshoes, shoe covers, rubber and cloth gloves, safety shoes, and respiratory protection equipment.

The minimum clothing requirement for airborne controlled area entry is es follows:

Managers, Supervisors, Inspectors and Visitors Area Workers only observing operations i

Shoe covers or work a.ea Shoe covers shoes Coveralls Laboratory coats

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Head covers Head covers Rubber gloves Rubber gloves (as

_ appropriate).. _

Safety glastes Safety giusses l

LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-3.20

The protective clothing is removed upon exit in the controlled area change rooms.

In a few areas such as the Chemet Laboratory, personnel contamination is controlled by exit monitoring.

The minimum clothing requirement for entry into these areas is a laboratory coat and safety glasses.

I 3.2.4.5 Respiratory Protection Program l

l The respiratory protection program shall be conducted in accordance with the applicable portions of 10 CFR 20, 3.2.4.5.1 Respiratory Protection Equipment Respiratory protection equipment specifically approved l

by the National Institute for Occupational Safety and Health (NIOSH) is utilized.

Two types of respirators are commonly available - half masks and full face masks.

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Half mask respirators equipped with particulate filters are utilized as a precautionary measure and to further reduce exposures during routine operations which may generate uranium dusts.

A protection factor of 10 is taken for this type of respirator usage.

Full face mask respirators, equipped with an. applicable canister, are utilized _as a precautionary measure and to *

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Emergency evacuation drills demonstrate that the evacuation plan is effective.

3.2.4.9 Personnel Monitoring - External Radiation Whole body or partial whole body exposure from external sources of radiation are determined by individually assigned dosimeters.

These personnel monitors are scheduled for reading at least quarterly or sooner if there is an indication of an exposure in excess of established action guides.

Action guides for external exposures received on site are as follows:

Action Wholebody

~> 1 rem / quarter Restrict for remainder of quarter Skin

> 10 rems / quarter Restrict for remainder of quarter Extremities

>10 rems / quarter Restrict for remainder of quarter i

In event of accidents or evaluation of unusual exposure conditions, whole body or partial whole body exposures i

may be calculated by the radiation protection function on the basis of data obtained by investigation.

Extremity exposures may be determined and assigned on the basis of engineering evaluations when TLD measurements are not practical.

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5.1.1.2 Action Level for Airborne Effluents Data from the air sampling measurements are analyzed for comparison with the concentrations established as an internal action guide.

The occurrence of an individual stack value exceeding the internal action guide initiates review action.

Personnel responsible for operating the exhaust-system l

are notified if any weekly stack result exceeds 3 x 1 0-12 Ci/ml.

In the event one of these values exceeds 1 x 10-11 pCi/ml nuclear safety and environmental protection personnel are also notified.

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5.1.1.3 Reportina Method l

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Uranium activity releases in the airborne effluents are summarized in a weekly stack program report.

This report includes pertinent information for each stack and l

for the total site.

Year-to-date summaries and data for the current week are included in the report.

In the event an action guide is exceeded, additional notification as described in Section 5.1.1.2 is initiated.

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The activity release data are also accumulated and c norted on a semi-annual basis to the Nuclear i

Regulatory Commission.

i 5.1.1.4 Lower Limits of Detection, Calibration and Standardization of Measurements 3

An alpha sensitive detector is used to determine the activity on the stack sample filters.

The system is calibrated for gross alpha using a standard traceable to the National Bureau of Standards.

This system provides a lower limit of detection of activity at the site boundary within the requirements of Appendix B of 10 CFR 20.

Background and efficiency checks are performed each operating shift.

The minimum detection limit for airborne effluent concentrations is 1 x 10-12 Ci/ml at the st ack which equates to approximately 1 x 1044 pCi/ml at the site boundary using a dilution factor of 100.

This lower limit of detection is 20% of the value 5 x 1044 pCi/ml, from Table II of Appendix B to 10 CFR 20.

5.1.2 Licuid Effluents The liquid waste streams containing uranium from the fuel manufacturing operations are segregated as nitrate waste, fluoride waste and rad waste.

This separation LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-5.6

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weir box above a 90-degree vee notch weir.

The volume flow is recorded, and an integrated value is generated by the recording instrument.

The composite samples are collected daily (except weekends and holidays) and chemically analyzed for uranium concentration.

A weekly composite of the daily samples is analyzed for gross alpha and gross beta activity.

5.1.2.2 Discharge Volume & Destination The daily discharge of treated process waste water to the Northeast Cape Fear River is approximately 500,000 gallons.

t 5.1.2.3 Action Levels for Liquid Effluents The action levels for the discharge of treated process wastes from the final process lagoons are specified in chemical uranium concentration (i. e., two-tenths (.2) parts per million (ppm) daily average for the month and 5 ppm any one day) and in activity concentration (i.e,

>3 x 10-5 pCi/ml on a weekly composite sample).

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.l.2.4 Reporting Method Uranium chemical analyses are available daily (except weekends and holidays) via the generation of a laboratory chemical analysis report on the discharge sample data.

These data are summarized on a monthly I

basis.

Daily and monthly values are reviewed against the internal action guides.

The NRC Regional Administrator is notified within 10 days of any violation of the facility's NPDES permit.

The activity release data are reported on a semiannual I

basis to the Nuclear Regulatory Commission.

l 5.1.2.5 Analysis, Lower Limits of Detection, Calibration and Standardization of Measurements 5.1.2.5.1 Chemical Analysis of Uranium l

The lower limit of detection for chemical uranium analysis on environmental samples is approximately 0.02 parts per million.

The test method is calibrated using standard. solutions made from National Institute of Standards and Technology (NIST) 950b U 0 or equivalent.

The method 3 8 is verified with each group of samples run by use of c verification standard.

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LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-5.9

4 5.1.2.5.2 Activity' Analysis for Liquid Environmental Samples l

Gross alpha and gross beta are currently determined by standardized laboratory counting techniques.

Lower limits of detection (for samples with low absorption) is typically 3 x 10-8 Ci/ml for gross alpha and 5 x 10-8 Ci/ml for gross beta.

The alpha calibration is accomplished using a standard calibrated by the National Institute of Standards and Technology (NIST).

5.1.3 Solid Wastes Solid wastes generated in the fuel manufacturing operation are packaged in boxes.

These boxes are assigned to centrolled access queuing areas where they await processing through a decontamination facility.

The decontamination operation provides a number of functions including recovery of uranium for recycle, separation of wastes into combustible and noncombustible categories, as well as decontamination of material for reuse where feasible.

After separation in the decontamination facility, the combustible wastes are designated for burning in an incinerator designed for processing uranium contaminated wastes.

Wastes which cannot be incinerated or reused are shipped to a licensed recipient for disposal.

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l 5.1.4 Contamination Free Licuid Two liquid streams (hydrofluoric acid and nitrate solutions) generated as a result of the conversion operation are transferred to unlicensed recipients and are not regarded as radioactive waste because of their low activity level, pursuant to Section 1.8.3.

5.1.4.1 Hydrofluoric Acid In the dry process for converting UFs to UO, a product 2

stream of hydrogen fluoride dissolved in water is generated.

This acid contains less than 3 parts per million of uranium by weight of the liquid.

This product is transferred to persons whose uses of the material are such that incorporation of uranium from the liquid is not likely to occur in any food, beverage, cosmetic, drug or other commodity designed for ingestion or inhalation by, or application to, a human-being such that the uranium concentration in such items would exceed that which naturally exists.

The acid is collected in a bulk storage tank to await shipment.

Material containing 3 or more parts per million uranium is not released for shipment.

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one Truck sample

> 25 ppm U - investigate cause

> 50 ppm U - stop shipment Composite of trucks

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> 3 ppm U

- 30 Day average

> 3 ppm U The lower limit of detection (LLD) utilized for uranium concentration in the one truck sample taken before a truck is released, is 10 ppm.

The LLD for uranium concentration in the daily composite sample is 0.02 Ppm.

The lower limit of detection for the gross alpha analysis is 5 pCi/1 (5 x 10-9 pCi/ml).

5.1.5 Effluent Control Responsibilities Effluent Responsible Function Stream Effluent Control y nitoring Airborne &

Applicable Area Regulatory Solid Effluents Manager Compliance Liquid Effluents o Final Process Tuel Production Regulatory Lagoons Compliance o Nitrate Wastes Fuel Production Regulatory Compliance o Hydrofluoric Fuel Production Regulatory Acid Compliance 5.2 ENVIRONMENTAL MONITORING PROGRAM The environmental monitoring program incorporates'the point of release measurements described in Section 5.1 LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-5.14

TAB 12 5.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Figure Collection Sample Point Ref.

Sample Type Frequency Parameter Action Level Detection Limit l AIR MONITORING Airborne 5.1, Composite Daily Gross alpha, 1x 1 0 -18 pC1/ml, gross 1x 1 0 -88 pC1/ml

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discharges -

5.2 gross beta a

gross a stacks Weekly Gross alpha,

>3 x 10 u pCi/ml, gross 1x 1 0 -12 pCi/cc gross beta a

gross a g

g H

Cn M

Ambient air 5.3 Composite Weekly Gross alpha 1x 10-H pC1/ml 0.5 x 10-u pCi/ml a

stations gross a (Isotopics CD on monthly j

basis) i I

l SURFACE WATER l p

F.a go w

Q 01scharge from Composite Daily U content 25 ppm one day,

>.2 ppm 0.02 part s per final process daily average for month million (ppm) lagoons Composite Weekly Gross Alpha

> 3 x 10-5 C1/ml 3x 10-8 pC1/mi Gross Deta gross Q gross a, 5 x 10-8 pC1/ml

[

h gross S Composite Semi-Technicium None 4

g g

g annually 99 tn H

O Northeast Cape 5.5 Grab Monthly U content 2 successive values 0.02 ppm Z

Fear River -

>0.06 ppm H

Upstream &

Downstream O

Hydrofluoric Grab Before U content 3 ppm 0.02 ppm acid tank or shipment a

go w

w truck l

Ds '

U1 (Q

O 64

l l

In the event that the calculated dose to any member of the public in any consecutive 12-month period is about to exceed the limits specified in 40 CFR 190.10, immediate steps shall be taken to reduce emissions so as to comply with 40 CFR 190.10.

As provided in 40 CFR 190.11, a petition may be submitted to the NRC for a variance from the requirements of 40 CFR 190.10.

If a petition for a variance is anticipated, the request will l

be submitted at least 90 days prior to exceeding the limits specified in 40 CFR 190.10.

These reports or petitions will be submitted to the Director, Office of Nuclear Material Safety &

Safeguards, with a copy to the Region II Administrator.

l 5.2.1.2 Sampling & Measurement i

l l

Air sampling stations are installed and operated in the prevailing wind directions, i.e.,

SE, S,

SW and NE, as shown in Figure 5.3.

Air samples are collected continuously and, in addition to analysis for gross alpha, the samples at each location are composited and analyzed on a monthly basis for uranium isotopes with an analytical sensitivity of at least 1 0-16 pCi/ml.

1 l

LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-5.19

1 5.2.2 Soil & Vegetation Sampling I

5.2.2.1 Soil Sampling e

l Program Objective:

Determine if there is ascertainable deposition from stack discharges l

1 I

i i

l e

1 LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-5.21

Soil samples are collected and analyzed for uranium concentration to monitor for long term buildup of uranium concentrations attributable to plant operations.

The locations of these stations are concentrated along the predominant wind directions.

Figure 5.4 details the sample locations.

The samples are collected on a quarterly basis and analyzed for uranium concentration.

The results are recorded and evaluated against an internal action guide of 0.7 parts per million.

5.2.2.2 Drainage Ditch Soil Sampling i

Program Objective:

Obtain environmental monitoring information regarding the uranium concentration of the soil in the drainage ditch Process liquids which meet the NPDES discharge limits are released from the final process lagoons to the N.

E.

Cape Fear River.

Soil grab samples are collected from three locations within the ditches twice per year.

Samples are withdrawn in accordance with information in Figure 5.3 and Table 5.1.

Samples are generally taken during the periods of November through December and January through April of each year.

The samples are analyzed for uranium concentration and the information is retained as a part of the environmental monitoring program records.

LICENSE SNM-1097 DATE 12/09/911 Page DOCKET 70-1113 REVISION 43 I-5.22

4 d

5 9

FIGURE 5.5 i

TYPICAL UPSTREAM / DOWNSTREAM SAMPLING LOCATIONS i

f+

j,[

i

• ~

( r' A.

k'.

s a

\\.

\\

'i 8

e i

j 8#

i i

- c,:

l I

lll

&g, 2

%. ~. O l

[

~

/ / //.

~

+

GENERAL.

O ELECTRIC'/,

/ / /

(k w

/

I g

g

/

i II ick.

%,~

d

)

I.'

l l

C-p 9

,k

)I.... - f y

i '{y c.'*

I-

-l Sample Location Type Frecuency

1. 1 - Upstream Public Boat Dock Grab Monthly

1. 2 - Downstream Seaboard Coastline ~ Grab' Monthly Railroad Bridge

.l LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 PIVISION 43-LI-5.25

~

The data from the monitoring program are evaluated against an internal action level.

The uranium concentrations are typically less than 0.02 parts per million.

The action level utilized in this program is two successive values greater than 0.06 parts per million.

The upstream and downstream results are reported monthly to the State of North Carolina.

5.2.3.2 Treated Nitrate Waste Shipments Sampling Program Objective:

Confirm source point data One segment of the monitoring program is designed to address shipments of nitrate solutions to Federal Paper Board Company Inc., Riegelwood, N.

C.,

for use in their waste treatment system.

Samples of water and sediment are collected from selected locations in the Federal Paper Board waste treatment system (see Figure 5.6 for locations) as well as locations in the Cape Fear River that are upstream and downstream from the outfall of the Federal Paper waste treatment system.

These samples are analyzed for gross alpha and gross beta activity and uranium as detailed in Table 5.1.

These results are compared against the action guides also listed in Table 5.1.

l LICENSE SNM-1097 DATE 12/09/93 Page DOCKET 70-1113 REVISION 43 I-5.26 l

l

-