ML20236H272

Application for Amend to License SNM-1107,revising Pp IV & Chapters 1.0 & 4.0

ML20236H272
Person / Time
Site:	Westinghouse
Issue date:	06/30/1998
From:	WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20236H270	List: ML20236H268 ML20236H272
References
NUDOCS 9807070143
Download: ML20236H272 (20)

Text

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TABLE OF CONTENTS

' NUMBER' AND TITLE PAGE y

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TABLE OF CONTENTS.......................................................................

REVISION RECORD '............................................................................

. CHAPTER 1.0 -

' GENERAL INFORMATION.................................................. 1.0 I.1

. FACILITY AND PROCESS DESCRIPTION............................... l.0 '

,1.2:

' INSTITUTIONAL INFORMATION......................................... 1.4

\\-

.2 1.3 SITE DESCRIPTION...............

1.5

• 1.4 TERMS AND DEFINITION S.................................................. ' 1. 8

. CHAPTER 2.0 MANAGEMENT ORGANIZATION....................................... 2.0 -

f 2.1 ORGANIZATIONAL RESPONSIBILITIES AND

~

AUTHORITIES................................................................... 2.0 2.2 S AFETY COMMITTEES...................................................... 2. 8 A

CHAPTER 3.0

' CON DUCT OF OPERATIONS.,...............................................~ 3.0 m o

3..F CONFIGURATION MANAGEM ENT...................................... 3.0

,m.

3.2. :

MAINTENANCE............................................................... 3.2 3.3 -

QUALITY ASSURANCE...................................................... 3.4 y

3.4 PROCEDURES, TRAINING AND QUALIFICATION................. 3.8 13.5-HUMAN FACTORS........................................................... 3.14 3.6 :

' AUDITS AND S ELF-ASSESSMENTS..................................... 3.15 3.7; INCIDENT INVESTIGATIONS............................................. 3.17.

3.8 "

. RECORDKEEPING AND REPORTING................................... 3.21 CHAPTER 4.0 -

INTEGRATED SAFETY ASSESSMENT.............;....................... 4.0

.' CHAPTER 5.0 '

RADIATION SAFETY......................................................... 5.0 d

5.1

' ALARA' (As Low As Reasonably Achievable) POLICY.................

5.0 J5.2 ~

RADIATION WORK PERMITS (RWP)................................... 5.1 '

5.3 :

VENTILATION YSTEMS.................................................... 5.2

, 5.4.

AIR SAMPLING.

.............................................................5.4 1

5.5 CONTAMIN ATION CONTROL............................................. 5.5

- 5.6

- EXTERNAL EXPOSURE..................................................... 5.'8

5.7 -

INTERNAL EXPOSURE....................................................... 5. 8

/5.8

- RESPIRATORY. PROTECTION............................................. 5.10 i 5.9_

INSTRUMENTATION......................................................... 5.12 i

L 5.10 SUMMING INTERNAL AND EXTERNAL EXPOSURES........... 5.12 i.M 9907070143 990630 PDR ADOCK 07001151; C:

PDR i r,

-. Docket No.

70-1151 Initial Submittal Date:

30APR90

. Page No.

i L License No. SNM-1107 -

' Revision Submittal Date: 30JUN98 Revision No. 12.0

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' TABLE OF CONTENTS (Cont'd).

4

- NUMBER ~AND TITLE PAGE

{ CHAPTER 6.01-N UCLEAR CRITICAUTY S AFETY........................................ 6.0 6.1

' PROGRAM ADMINISTRATION............................................ 6.0

6.2 j CONTROL' METHODOLOGY AND PRINCIPLES..................... 6.8 6.3 -

1 ALARM SYSTEM.............................................................. 6.

i 6.4 CONTROL DOCUMENTS................................................... 6.21 p6.5:

- ALARM SYSTEM S s........................................................... 6.22 CHAPTER 7.0 /

CHEMICAL l SAFETY.......................................................... ; 7.0 -

7.1

' CHEMICAL SAFETY PROCRAM........................................... 7.0 -

7.2

. CHEMICAL SAFETY HAZARD EVALUATIONS......................

7.0

7.3_

CHEMICAL SAFETY PROGRAM STRUCTURE....................... 7.1 7.4 E

' ADDITIONAL CHEMICAL SAFETY COMMITMENTS.............. 7.2

CHAPTER 8.0 '

FI RE ' S AFETY............................................................

,8.1:

STRUCTURE OF THE FIRE SAFETY PROGRAM..................... 8.0 L 8.2 '

FIRE S UPPRESSION SERVICES........................................... 8.10 -

CHAPTER 9.0 EMERGENCY MANAGEMENT PROGRAM............................ 9.0

'9.1:

EMERG ENCY PLAN........................................................... 9,0 9.2 L

EMERG ENCY EQUIPMENT.................................................. 9.0

+ ^

l CHAPTER 10.0 ENVIRONMENTAL PROTECTION....................................... 10.0

= 10.1 EFFLUENT AIR TREATMENT............................................ 10.0 -

10.2 -

UQUID WASTE TREATMENT FACIUTIES...........................10.0

-10.3 SOUD WASTE DISPOS AL FACIUTIES..................................' 10.1 10.4'

- PROGRAM DOCUMENTATION........................................... 10.1 L 10.5

EVALUATIONS................................................................. 10.2 10.6 -

. OFF-SITE DOSE................................................................ 10.2 LCHAPTER 11.0 DECOMMISSIONING........................................................... 1 1.0 11.11 CONCEPTUAL DECOMMISSIONING PLAN..........................11.0 F

(11.2 '

DECOMMISSIONING FUNDING. ' PLAN AND FINANCIAL L

fASSURANCE.................................................................... 1 1.1 CHAPTER 12.0 AUTHORIZATIONS AND EXEMPTIONS............................... 12.0 m

12.1 AUTHORIZATIONS........................................................... 12.0 l 12.2 '

EXEMPTIONS................................................................... 12.4 ~

1 lhket No.

70-1131 Initial Submittal Datei 30APR90 Page No.. _ii u

1 License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0 2

~

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1 Llfy 1

> o.h REVISION RECORD ;

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REVISION: DATE OF

-PAGES NUMBER ' REVISION'

. REVISED REVISION REASON

,1.0

~.30APR95 L All -

Update to current operations.

o 2.0 l 28JUN96

- iii,' 6.8 Clarify - Criticality Safety Basis for the ' compaction operation.

3.0.

30AUG961-;

iii,1.7,1.9,12.6,12.7 Incorporate Safety Condition S-3, into Application; correct.

reference to Figure 1.3

~ instead of 2.3, E to ' reflect expansion: of '.the CAA1in :

order to climinate need for gate.

4-

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4.0 30SEP96;

. iii, 6.11,' 6.12 Clarification of Criticality.-

. Safety Basis for : the Pellet Stripping System Equipment

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and Hoods & Containment.

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. f5.0 L 08NOV96

~ iii,1.12, 3.18, and 3.19 Incorporation of a definition, (Reprinted all document

.and incident notification L

pages in Microsoft Word.

criteria, recently approved format)

. by NRC Staff.

'6.0~

I 05MAY97 -

6.12 (Reprinted all Clarify Evaluation document pages in!

Bounding Assumptions

-- Microsoft Word format.)L for Storage of Annular Pellets.

7.0 14JUL97 '

' iii,12.2 and 12.3.

~ Withdraw an.

existing authorization, and expand.

l

~

another authorization to enable cement manufacturing with CaF -

2 8.0 l 11AUG97 iii,2.4 and 8.1 (Reprinted" Change emergency exercise all document pages in frequencies for consistency p

L Microsoft Word format.)

with Emergency Plan.

p Docket No. 1151' Initial Submittal Date:

30APR90 Page No.

iii i

j z,x License No.1 SNM-1107:

' Revision Submittal Date: 30JUN98

' Revision No. 12.0' pp L_>

u 1

gp.

f l 9.0

• ~

.23SEP97 iv, Chapter 6 To respond to NRC' Staff

. request for additional information.

To revise table to correlate to CSE organization and clarify discussions regarding margin of safety with respect to normal operations,' expected process. upsets and credible 4

process upsets.

i

~ 10.0 31 MAR 98 Table of Contents i-iv To replace Revisions Chapters 3.0 and 6.0.

Numbers 2.0, 4.0, 6.0, and 9.0; and respond to SMIP j

initiative regarding SNM-1107, Chapter 6.0. (Chapter 3.0 shown with bars & 6.0 Major Rewrite).

11.0 ;

03APR98 Table of Contents i-iv, To reflect common 1.12, 3.18 - 3.20.

understanding on notification criteria with NRC Staff.

12.0 30JUN98 Table of Contents (iv),

To update and enhance Chapter 1.0 (1.12),

Integrated Safety Assessment Chapter 4.0 (all).

commitments.

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-Docket No.-

70-1151 Initial Submittal Date:

30APR90 '

Page No.

iv l:

h License No. SNM-1107 Revision Submittal Date: 30JUN98 '

Revision No. 12.0 l-l L-_r-___-----.--_-

m, CHAPTER 1.0

~

I GENERALINFORMATION 1.1~

' FACILITY. AND PROCESS DESCRIPTION The~ Columbia Fuel Fabrication Facility:(CFFF) of the Commercial Nuclear Fuel

- Division'(CNFD) will be primarily engaged in the manufacture of fuel assemblies for '

commercial nuclear reactors. The manufacturing operations to be authorized by this license will consist of receiving low-enriched,;less than or equal to 5.0 'w/o U-235,'

uranium hexafluoride; converting the hexafluoride to produce uranium dioxide powder; and processing the uranium dioxide through pellet pressing and sintering, fuel rod loading and sealing, and fuel assembly. fabrication. These operations will be governed by the technically sound radiation and environmental protection, nuclear criticality safety, Eindustrial safety and health, SNM safeguards, and quality assurance controls described in detail in this License _ Application, tTwo' general' systems are used-to_ convert uranium.hexafluoride to uranium dioxide powder-Integrated 1 Dry - Route L(IDR) and = Ammonium Diurste (ADU).

IDR conversion equipment has been designed to receive and process uranium in enrichments

~

fup to'5.0 w/o'U-235, through fuel rod loading. ' ADU conversion equipment has also been designed to receive and process uranium in enrichments up to 5.0 w/o U-235, through fuel assembly fabrication and shipping. These operations an: supported by absorber coating, laboratory, scrap recovery, and waste disposal systems. Additional details concerning the facility and process systems are presented in the Site Safeguards

! documents described 'in Paragraph 1.1.1(e) of.this. Section. and in the SITE EMERGENCY PLAN described in Chapter 9.0 of this License Application.

1.1.1 SITE UTILITIES'AND SERVICES (a)

Electrical Supply

The CFFF will be served by a single, 115,000 volt, electrical supply line. Four

' diesel-powered standby generators will be installed and maintained to meet the

emergency electrical power requirements of the site in the event of a temporary outage'of the normal supply. source. Emergency ~ power will be automatically provided to crucial. process equipment; emergency lighting systems; cooling

~

system pumps;Lall' fire alarm, hazard alarm, and other designated safety alarm systems; Conversion Control Room alarms; health physics sampling systems; and, emergency ventilation systems, including scrubbers.

b

, - Docket No.-

70-1151

. Initial Submittal Date:

30APR90 Page No.

1.0 1 License Nh. SNM-1107-

~ Revision Submittal Date: 30JUN98 Revision No. 12.0 I

i U"

y Lr i(b)'

Water Supply -

'A ten-inch main from'the Columbia Municipal Water Authority supplies water to the site.

3

.'(c)

Gaseous and Liquid Effluent Management i e..

Gaseous exhausts, with potential for contamination, from process areas will be routed through HEPA filtration, to remove entrained uranium particulate, prior to discharge to the environment. Exhausts containing uranium in soluble form Lwill be passed through aqueous _ sembbers, preceding ' the. HEPA filters.

Following filtration, the gases will be continuously sampled, to enable ~ analyses-for assuring compliance with the limits specified in this License Application.

. Liquid process wastes will be treated, prior to discharge to the Congaree River.

Waste treatment, for'the removal of uranium, ammonia, and fluorides,.will

. consist of filtration, flocculation, lime addition, distillation, and precipitation (in a-series.of holding lagoons). Site sanitary ' sewage will be treated in an extended aeration package plant prior to <lischarge, either directly or through a polishing -

-lagoon. The discharged effluent will be chlorinated, and mixed with treated.

liquid process waste, at the facility lift station. 'Ib mbined waste will then be -

passed through a ' final aerater, followed by pH adjustment as required, and.

subsequently pumped to the river via a 4-inch pipeline.' Compliance with licensed limits will be verified by passing.the waste streams through on-line ' monitoring

. systems, or by manual sampling and analysis on a batch-basis.. The treatment

'I systems will have sufficient holdup capacity to assure the limits are continuously

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met.

Storm water from the site enters ~a system of drainage ' ditches and ultimately flows to the Congaree River.

(d)

' SOLID WASTE STORAGE AND DISPOSAL c1 l

+

Solid wastes will be sorted-into appropriate combustible and noncombustible fractions, and placed in specially designated collection containers located h

throughout the work area. (The wastes consist of paper, wood, plastics', metals, j

floor sweepings, and similar materials which are contaminated by, or contain, i

uranium.) Following a determination that the wastes are in fact properly sorted,

{

the contents will be transferred to a' waste processing station.

j L

~ M' aterials that: are suited for thorough survey may be ' decontaminated for i

free-release, or re-use, in accordance with provisions of this License Application.

4-Combustible wastes will be packaged in compatible containers, assayed for grams Docket No. --70-1151:

Initial Submittal Date:

30APR90 Page No.

1.1

License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0 i

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1 U-235, and stored 'to await incineration. Noncombustible wastes, and selected combustible' wastes, will be packaged in compatible containers, compacted when

~ '

appropriate, measured to verify the uranium content, and placed in storage to await shipment for further treatment, recovery, or disposal.

" Administrative controls will be in effect to assure that only authorized materials are packaged' for ' disposal.

(These include verification 'of package contents,

. container security to. minimize the probability of unauthorized additions to the containers, documentation of package contents, and routine overchecks to verify :

that the above referenced controls are effective.) Wastes designated for disposal will be ' packaged in DOT approved 55-gallon metal drums or in metal boxes.

Materials packaged in metal boxes will be pre-measured in standard containers.

)

prior to transfer to the boxes. Filled containers will be stored in designated areas within the manufacturing or waste storage' buildings; or, they may be stored -

outdoors, if protected from the elements.

Wastes consigned to disposal will be shipped to a licensed burial facility.

Shipments will be made in compliance with all applicable NRC, DOT and State regulations; and, in conformance to burial site criteria.

L(e)

SITE SAFEGUARDS Nuclear Ma'erials Control and Accounting at ths CFFF is described.in the t

~

' NRC-approved FUNDAMENTAL NUCLEAR MATERIAL CONTROL PLAN

. FOR THE COLUMBIA FUEL FABRICATION FACILITY, dated April 1, 1987, and subsequently revised in accordance with the regulations. Physical L

' Security at the CFFF is described in the NRC-approved PHYSICAL SECURITYJ j

l PLAN ' FOR THE COLUMBIA ' FUEL FABRICATION FACILITY, ' dated j

September 1,1984, and subsequently revised in accordance with the regulations.

These Plans detail the measures employed at the facility to detect any potential loss of, and mitigate the opportunity for theft of, Special Nuclear Material of Low Strategic Significance, in accordance with applicable requirements of 10CFR73

)

and 74.

l 1;1.2 " SCOPE OF LICENSED ACTIVITIES l

Compliance with all applicable Parts of Title 10, Code of Federal Regulations will be I

required, unless specifically amended or exempted by NRC staff.

(a)

' Authorized Activities:

p L

(a.1)' ' Authorized activities at the Columbia Fuel Fabrication Facility will include: (1)

L

. Receipt,. handling, and storage of Special Nuclear Material as uranium Docket No.

70-1151

-Initial Submittal Date:

30APR90 Page No.

1.2 License No. : SNM-1107 -

.- Revision Subm',ttal Date: 30JUN98 Revision No. 12.0 i

l o,,

c.

5.

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hexafluoride, uranium nitrates, uranium oxides; and/or contained in pellets, fuel rods, fuel assemblies, samples,' scrap, and wastes; (2) Receipt, handling, and storage of other licensed radioactive material; (3) Chemical conversion processing by the Ammonium Diuranate Process and the Integrated Dry Route - including vaporization and hydrolysis, precipitation and. centrifugation, drying, calcining,

. comminution, and blending; (4) Fuel fabrication - including powder preparation, die-lubricant mixing, pelleting, sintering, grinding, pellet coating with nuclear absorbers, fuel rod loading and inspection, and final fuel assembly;. (5) Quality

. assurance and control inspection. activities; (6) Analytical Services Laboratory operations - including - wet-chemistry and spectrographic techniques; (7)-

Metallurgical Laboratory operations - including sample preparation, polishing,'

- testing, and examination; (8) Chemical Process Development. operations -

including: laboratory-scale process research, prototype development, and equipment check-out; :(9). Mechanical Process Development operations --

including laboratory-scale research and development; (10) Health Physics Laboratory operations - including sample. preparation and analysis,- instrument repair and: calibration, respirator fit-testing, and bioassay. sample and sealed-source storage; (11) In-house, and contracted, scrap recovery operations -

l

' including scrap batch processing, solvent extraction, coated-pellet recovery, ' scrap l

blending, and hydrofluoric acid recovery; (12) UF. cylinder washing, hydrostatic testing and re-certification;~(13) Equipment and facility maintenance activities;

. (14) Equipment and facility decontamination activities - including clothing; (15)

Waste storage and disposal preparation operations - including HEPA filter i

testing, conversion liquid waste treatment, advanced waste-water treatment,.

lagoon storage, ' incineration, radioactive waste = packaging for, disposal, and i

calcium fluoride disposition; (16) ' Ancillary mechanical operations.- including l

non-radioactive' component fabrication and assembly; and (17) Shipping container; and overpack refurbishment.

'(a.2) ' The licensed activity may also perform work for other Westinghouse Divisions, j

- or outside customers, which is within the authorized capabilities of the facility.

(b)-

Material Possession Limits and Constraints The following will be the maximum quantities of Special Nuclear Material that may be possessed by the licensed activity at any one time; and, constraints for procurement, use, and transfer of such material.

h

. (b.1) ' Material possession limits - (1).5-grams' of U-233 in any chemical or physical L

form, limited to laboratory.use as individual 1-gram maximum quantities in-f

' ventilated hoods; (2) 350-grams of U-235, as uranium of any enrichment, in any L

chemical or physical form; (3) 75,000-kilograms of U-235, as uranium enriched p

L Docket No.

70-1151

. Initial Submittal Date:

30APR90 Page No.

1.3 V

1 License No.- SNM-1107 Revision Submittal Date: 30JUN98

- Revision No. 12.0

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to no greater than 5.0 weight-percent, in any chemical or physical form except metal; and, (4) 1.5-grams of Pu-238/239 as sealed sources.

i_

(b.2)' Material constraints -- The procurement of Special Nuclear Materials will be in

- accordance '. with. licensed activity. needs.

Production,. utilization, and/or significant loss of special nuclear materials will not be authorized. Transfers of -

Special Nuclear Materials will be only as arranged with facilities authorized to receive and possess such materials.

L 1.2 -

INSTITUTIONAL INFORMATION-This application requests a ten year renewal of License SNM-1107, Docket 70-1151',

twhich authorizes the receipt, possession, storage, use, and transfer of Special Nuclear

- Material at the. Westinghouse Electric Corporation's Columbia Fuel Fabrication Facility (CFFF).

There is no control' or ownership exercised over Westinghouse Electric Corporation by any alien, foreign corporation, or foreign government. In accordance with the requirements of.10 CFR 70.22(a)(1), the following additional information is submitted:

.1.2.1 APPLICANT AND STATE OF INCORPORATION

' W.Jinghouse Electric Corporation -

j Pennsylvania i

1.2.2 L : LOCATION OF THE PRINCIPAL OFFICE Pittsburgh,- Pennsylvania 1.2.3 L NAMES (CITIZENSHIP) AND ADDRESSES OF PRINCIPAL OFFICERS

.- Michael H. Jordan (USA)

Chairman'& Chief Executive Officer -

. Westinghouse Executive Offices 11 Stanwix Street

- Pittsburgh, Pennsylvania 15222-1384

. Nathaniel D. Woodson (USA)

Vice President and General Manager, Energy Systems h

a" Westinghouse Energy Center i

P. O. Box 355 Pittsburgh, Pennsylvania 15230-0355 ~

Docket No. 1151' Initial Submittal Date:

30APR90 -

Page No.

1.4 o

License No. ; SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0 L

us_

_1______________

Ronald H. Koga (USA)

General Manager, Commercial Nuclear Fuel Division Westinghouse Energy Center l

P. O. Box 355 Pittsburgh, Pennsylvania 152304)355 James A. Fici(USA)

CFFF Plant Manager Westinghouse Columbia Plant Drawer R Columbia, South Carolina 29250 1.2.4 CORPORATE CONTACT FOR LICENSING MATTERS Griff Holmes Manager, Energy Systems Regulatory Affairs Westinghouse Energy Center P. O. Box 355 Pittsburgh, Pennsylvania 15230-0355 1.2.5 SITE CONTACT FOR LICENSING MATTERS Robert A. Williams Licensing Project Manager Westinghouse Columbia Plant Drawer R Columbia, South Carolina 29250 1.2.6 ADDITIONALINFORMATION Additional corporate financial and business information is provided in the Westinghouse Annual Report, available from:

Westinghouse Electric Corporation P. O. Box 884.

Pittsburgh, Pennsylvania 15221 1.3 SITE DESCRIPTION The Columbia Fuel Fabrication Facility (CFFF) is located near Columbia, South Carolina and is situated on an approximately 1,158 acre site in Richland County, some 8 miles j

southeast of the city limits of Columbia (see Figures 1.1 and 1.2) along South Carolina j

i Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

1.5 License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0

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FIGURE 1.1 CFFF SURROUNDING AREA 1

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Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

1.6 License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0

m, FIGURE 1.2 CFFF PROPERTY BOUNDARY l

I (S.C. RT. 48) py BLt/F RD. TO COLUMB(A.

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l Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

1.7 License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0

' Highway 48. The region around the site is sparsely settled, and the land is characterized by timbered tracts and swampy areas, penetrated by unimproved roads.

Farms, l-single-family dwellings, and light commercial activities are located chiefly along nearby I

highways.

The site is bordered by abutting properties, as presented in the PHYSICAL SECURITY PLAN described in Paragraph 1.1.1(e) of this lJcense Application. Approximately 1098 '

l acres of the site remain undeveloped. Of the total 1,158 acres, only 60 acres (about 5 l

percent) have been developed 'a secommodate the fuel fabrication facilities, holding ponds, and landscaped areas. A sia plan is shown in Figure 1.3.

Details of the CFFF location, including proximity to nearby towns, industries, public facilities, the Congaree River, transportation links; and, site topography; are presented in Section 1 of the SITE EMERGENCY PLAN. Details of the site characterization are presented in Section 2.0 of the SITE EVALUATION REPORT.

1.4 TERMS AND DEFINITIONS Throughout this License, the following terms will be defined and used as indicated:

i ALTERNATIVE ACTIONS - Tests, procedures or other practices that may be substituted for prescribed activities as deemed appropriate by the Regulatory Component.

In 'such case, a detailed analysis will be performed and documented by the cognizant l

' Regulatory Functions. This analysis will include a comparison of the proposed action I

with that specified in the license; and, a demonstration that action levels and limits of the license will be met, and that health and safety of employees ed the public, and quality of the environment, will be protected.

l-CHEMICAL AREA -- An area where uncontained radioactive material is processed, the L

probability of contamination on floors and accessible surfaces is high, and protective clothing is required; such as, the UF Bay, the Conversion Area, the Pelleting Area, the 6

Rod leading Area, etc.

CLEAN AREA -- An area where radioactive material, if present, is completely l

contained and there is negligible contamination on the floors or accessible surfaces. Such L

locations include, but are not limited to, the Machining Area, Grid Assembly Area, Final Assembly Area, Office Areas, and the Cafeteria.

L COMPONENT - When used in an administrative context, an independent organizational unit distinguishable by its assigned responsibilities; such as, the Engineering Component,

' the Manufacturing Component, the Quality Component, and the Regulatory Component.

1 Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

1.8 i

License No. SNM-1107 Revision Submittal Date: 301UN98 Revision No. 12.0 i

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Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

1.9 i

License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0 i.

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SITE PLAN KEY l

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l Si:

Shipping / Receiving point for UF. Cylinders.

R1 S2 :

Shipping / Receiving point for Uranyl Nitrate.

R2 S3 :

Shipping / Receiving point for U Powders, U Pellets, R3 :

U Scrap, a ul U Waste.

S4 :

Shipping / Receiving point for U Rods and U Assemblics.

R4 SS :

Shipping / Receiving point for miscellaneous U Samples R5

. and U Standards.

1:

Fuel Manufacturing Building.

2:

UF. Storage Pad.

3:

Gatehouses (4).

4:

Administration Building.

5:

Parking Area.

6:

Lagoons (6).

7:

Waste Treatment Building.

8:

Waste Storage Area.

9:

Access Road.

10 :

. Controlled Access Area (CAA) Fence 11 :

Advanced Liquid Waste Treatment Building.

12 :

Uranyl Nitrate Storage Tanks.

. 13 :

Fuel Manufactunng Building Southwest Expansion.

14 :

Fuel Manufacturing Building Southeast Expansion.

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15 :

Nuclear-Poisoned Fuel (IFBA) Area.

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Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

1.10 l

l l

License No, SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0

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CONTAMINATION CONTROLLED AREA - An alternate name for the Chemical Area.

CONTROLLED ACCESS AREA - A physically defined area, represented on three sides by a ~ seven-foot high barrier of Number-11 American Wire Gauge fabric-fence topped by three strands of barbed wire, and on the fourth side by the Administration and Mam Manufacturing Building. This area is the " Controlled Access Area" described in the Physical Security Plan.

ENRICHMENT LIMIT - When used as an authorized enrichment limit,5.0 w/o U-235 means that, based on an enrichment measurement uncertainty no greater than 0.50 percent relative, the hypothesis that the true enrichment level is 5.0 w/o U-235 or less can not be rejected at the 0.05 level of significance.

EQUIVALENT EXPERIENCE - When used in a personnel qualification context to equate experience with education, eight years of applicable experience is equivalent to a baccalaureate degree.

FIXED LOCATION GENERAL AIR SAMPLE - Air samples used to assess general area radioactivity concentrations; and, to assess the adequacy of radioactive material containment and confinement within the processing areas of the facility; and, to establish airborne radioactivity areas.

FIXED LOCATION BREATHING ZONE REPRESENTATIVE AIR SAMPLE -

Air Lamples used for purposes of assessing and assigning operator intake.

FREQUENCIES - When measurement, surveillance, and/or other frequencies are specified in License documents, the following will apply:ive days; MONTHLY m DAILY means once each 24-hour period; WEEKLY means once each seven consecut twelve per year, with each covering a span of 40-days or less; QUARTERLY means four per year, with each covering a span of 115-days or less; SEMIANNUAL means two year, with each covering a span of 225-days or less; ANNUAL means or.ce per year, per not to exceed a span of 15-months; BIENNIAL means once every two years, with each covering a, span of 30-months or less. TRIENNIAL means once every three years, with each covermg a span of 45 months or less.

FUNCTION - When used in an administrative context, an individual (or individuals),

designated by the Component Manager, acting in coordination with the other personnel of a component, having the capability,igned duties; such as the Environmental Prot responsibility, and authority to make and implement decisions required to carry out ass Function, Radiation Safety Function, Nuclear Criticality Safety Function, Chemical Safety Function, Fire Safety Function, and Safeguards Function of the Regulatory Component.

LICENSED ACTIVITY - That combination of personnel, plant, and equ established by Westinghouse Electric Corporation to carry out the processm,ipme radioactive material authorized by this License Application.

MAY - Denotes implied permission by NRC Licensing Staff to take a stated action or

. course.

I PORTABLE AIR SAMPLE - An air sample that is not integrated into the plant's I

central air sample vacuum system.

Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

1.11 License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0

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_j REGULATORY-SIGNIFICANT PROCEDURES - Those procedures that contain, in whole or in part, actions that are important to environmental protection, health, safety, j

and/or safeguards.

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RESTRICTED AREA '- Areas such as the Manufacturing Building, or equivalent areas, to which access is restricted by physical or administrative methods and which is monitored on a scheduled basis by the site Security Function.

SAFETY MARGIN IMPROVEMENT CONTROLS - Controls that provide cost effective enhancements to the safe and effective operation of a process. These are controls that enhance an existing and adequate margin of safety.

SAFE MASS [3.7.3(b.2) and (c.5)] critical mass for a particular process or vessel given the credible material' geometry for that process / vessel, and the License Evaluation Bounding Assumptions for that material type (e.g., homogeneous UO ) and reflection.

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Optimum moderation and material density are assumed.

SAFETY-RELATED - Relevant to systems crucial or important to safety; and, those systems that improve the margin of safety (e.g., in the context of maintenance).

SAFETY-RELATED CONTROLS - Preventive and mitigative controls relied upon for environmental protection,- radiation safety, nuclear criticality safety and-safeguards, chemical safety, and fire safety. These controls, which include both

" Safety-Significant" and " Safety Margin Improvement" controls as sub-sets, will be identified through an integrated safety analysis which documents the design safety basis for a particular process.

SAFETY-SIGNIFICANT - Relevant to systems crucial or important to safety (e.g., in the context of quality assurance).

SAFETY-SIGNIFICANT CONTROLS - Controls crucial or important to, or deemed desirable for, the safe and effective operation of a process, and an adequate safety margin for the process. An adequate safety margin is made up of those controls necessary for the safe operation of the process plus those controls identified to ensure regulatory compliance, UNRESTRICTED AREA - An area, access to which is neither limited nor controlled.

WILL - Denotes a mandatory requirement to take a stated action or course.

I Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

1.12 l

j License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0 l

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.W CIIAlrfER 4.0 INTEGRATED SAFETY ASSESSMENT The Columbia Fuel Fabrication Facility (CFFF) will develop, and will maintain current through the Configuration Management process (Section 3.1 of this License Application), an Integrated Safety Assessment (ISA) for the Site. The ISA will identify and evaluate the various hazards that could arise from, or impact control over, licensed materials. The ISA will identify process equipment and safety control features that are relied upon for protection of the environment, and the health and safety of facility enployees and the neighboring public. Safety-Significant, and Regulatory-Specified Safety Margin Improvement, controls will be placed under an appropriate level of Quality Assurance (Section 3.3 of this License Application) to ensure their reliability, and an appropriate level of Maintenance (Section 3.2 of this License Application) to ensure their availability.

The Integrated Safety Assessment will include the following format and content:

Section 1.0; PROCESS DESCRIPTION, will present a narrative definition of normal operation as it relates to each defined system. A schematic representation of the system (flow diagram) and a narrative outline of the system equipment controls, with text references that detail normal operating boundaries (e.g., composition, concentration, flows, and safety-significant sampling) are typically included. Section 1.0 should be limited to the process itself; thus, information such as equipment interconnections, material types, or Safety-Related controls should be mentioned only if needed to present a clear understanding of process flows (since details concerning those items will be included in other appropriate sections of the baseline ISA document).

Section 2.0; PROCESS TIIEORY, will present a narrative description of the normal process operating parameters, including the ranges of conditions expected, for each defined system. Descriptions of upset conditions which have the potential for exceeding safety limits are typically included. References documenting the sources of the theory are also typically included.

Section 3.0; PROCESS DESIGN AND EQUIPMENT, will present the dimensions, construction materials, and design configuration of lines and vessels of each defined system. A narrative definition of system transfer interconnections, as related to the defined system, and a tabulation of relevant reference drawings are typically included.

Section 4.0; DRAWINGS AND OPERATING PROCEDURES, will present a reference listing of all drawings and operating procedures used in performing the Process Hazard Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

4.0 License No. SNM-1107 Revision Submittal Date: 30.lUN98 Revision No. 12.0

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Analysis'(Section 6.0 of the ISA). (All other documents collected for review and/or

, information purposes will be retained as backup information for each system's ISA.) -

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' Section 5.0; SAFETY ANALYSES, will present the results of comprehensive, discrete

< safety reviews of each defined system. The objective will be to evaluate accident-scenarios, and to identify Safety-Related controls.

(This is the first of a two-step process where the system is independently evaluated by

, Environmental Protection, Radiation Safety, Nuclear Criticality Safety / Safeguards, Fire '

Safety, and Chemical Safety experts. (The final step in the analysis process will be described in Section 10.0 of the ISA, where the cognizant Safety Functions will deliberate -

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.as a group to Joptimize controls (as necessary), and =will, provide -consensus recommendations for cognizant Component Management review and ' disposition.)

'Section 6.0; PROCESS HAZARD. ANALYSIS, will' present tabular results of the

' system's Process Hazard Analysis (PHA). ~A PHA includes a hazard analysis of the r

subject process, using at least one (or an appropriate combination) of the following l

formal methodologies; Hazard and Operability (HAZOP), What-If/ Checklist,- Fault and/or Event Tree logic, and/or equivalent methodology.

Technical issues a PHA-typically addresses include potential hazards, previous incidents, engineered.and administrative controls, failure of controls, facility siting, human factors, and range'of effects. (The complete PHA', providing the details results in a narrative format, will be retained as backup information for the system's ISA).

Section 7.0; LICENSE COMPLIANCE VERIFICATION, will document reviews, by the cognizant safety experts, of License commitments specific to the defined system; and, will provide statements that applicable commitments were reviewed prior to. Safety

' Analyses of the system, and were confirmed to be (or not to be) in-place and operational, as part of the ISA process, ei Section 8.0; APPENDICES, will present a summary of ancillary information (such as consequence analyses, and nuclear criticality safety calculations and parametric sensitivity studies) for each defined system.

Section 9.0;- PHOTOGRAPHS, will present any photographs of the system / subsystem

= equipment that had relevance to (and were thus used during) the Process Hazard Analysis

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process (previously described).

Section 10.0; INTEGRATED SAFETY ANALYSIS, will present the results of the e

Cognizant Safety Functions' combined evaluation of each defined system. The objectives will be: 1(1) To optimize safety margin; (2) to assure compatibility of Safety-Significant, and Regulatory-Specified Safety Margin Improvement, controls; and (3) to classify such Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

4.1 l

< License No. SNM-1107 Revision Submittal Date: 30JUN98 Revision No. 12.0 c_ _ _ _-

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. controls as to their (Quality Assurance) importance.

Dbcumeritation of continuing progress toward completion of the facility ISA will be maintained at the CFFF Site for Regulatory Agency review. Integrated Safety Assessments for all systems processing licensed material will be complete within five (5) years of the approval date for this License Application. The ISAs for ancillary processes that might impact control over licensed material.will be completed; and, the placement of all ISA-identified controls under the 4

' appropriate level of Quality Assurance and Maintenance will be fully. implemented; and, the structured classification of all systems with respect to their relative risk will be concluded, within

. seven (7) years of the approval date for this License Application.

' As system Integrated Safety Assessments are completed, a sutnmary in the form of a License Annex'will be submitted to NRC Licensing Staff. These summaries will include (as applicable):

l (1) A condensed presentation of the Process. Description, Process Theory, and Process Design and Equipment; (2)'A listingfof key Drawings and Procedures utilized in the Process Hazard r

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i Analysis; (3) A listing of Environmental Protection and Radiation Safety controls; (4) A listing of Nuclear Criticality Safety / Safeguards controls,- and Fault Trees to demonstrate Double

' Contingency Protection; (5) A listing of Chemical Safety and Fire Safety controls; and (6) A

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. condensed presentation, including Fault Tree, of the Consequence. Basis accident analysis (where -

. appropriate). These summaries will be maintained as current doc' ments. Whenever CFFF u

regulatory management makes a decision to change the License Annex,' the NRC Licensing

. Project Manager will be apprised of the decision via e-mail or facsimile. Subsequently, within 30-days'of the apprisal, changed pages to update the License Annex will be submitted to NRC -

Licensing Staff..

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. Docket No.

70-1151-Initial Submittal Date:

30APR90 Page No.

4.2

License No. SNM-1107' Revision Submittal Date

30JUN98 Revision No. 12.0' L________.

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