ML20053B097
| ML20053B097 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 04/07/1982 |
| From: | Jennifer Ford BABCOCK & WILCOX CO. |
| To: | Page R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 20564, NUDOCS 8205280034 | |
| Download: ML20053B097 (60) | |
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United States Nuclear Regulatory Commission kbOE/V{g g gg33 g
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REFERENCE:
(1) SNM-1168, Docket 70-1201 ru Gentlemen:
The Babcock and Wilcox Company, Commercial Nuclear Fuel Plant requests amendment of SNf1-1168. The changes are necessary to incorporate the reorganization of CNFP Staff members and Departments. Accordingly, a check for $150 is attached to cover the administrative licensing fee.
Attachment I contains the following revised pages of Section I - General Information:
1,12 Appendix A, and 13 Appendix A, and 14 Appendix A.
Attachment II contains the following revised pages of Section III-Nuclear Safety Analysis:
5, 114, and 123.
Attachment III contains the following revised pages of Section IV - Health Physics:
13, 14, 38, and 40.
Attachment IV contains the following revised pages of Section V - Conditions:
6, 7, 9, 11, 12, 13, 14, 15, 16, 17, 18, 19, 23, 24, 25, 26, 27, 32, 34, 35, 36, 41, 45, 47, 51, 76, 77, 80, 82, 84, 85, 90, 91, 93, 95, 95a, and 96.
Attachment V contains the following revised pages of Section VI - Emergency Plan dated 3-15-82:
2-1, 4-2, 7-1, 7-2, and 8-1.
If there are any questions, please feel free to call me at (804) 522-5966.
Thank you.
Sincerely, e
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ATTACHliENT I Section I - General Information u
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FAC00( 8 WILCDX CDPRf(, CalERCIAL 'lVCUR REL PLAIT USilRC LICENSE St4r1-1168 DOC' T 70.1201 E
SECTIO 4 I - GENERAL INFORMATION BABC0CK & tlILC0X COMPANY Commercial Nuclear Fuel Plant P. O. Box 800 Lynchb. g, Virginia 24505 Application for Renewal SPECIAL NUCLEAR MATERIALS LICENSE N0. St!M-1163 SECTION 1 General Information DATE 4-07-82 REVISIOl NO.
1 PAGE I
CURRENT REVISICN:
SUPERSEDES: PAGE 1
USNRC APPROVAL REFEREilCE DATE 4/30/75 p5V! sic;
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l TAC 00( & WILGX C0FPAN, COREPflAL.'lUCLEAR REL PLAIT USNRC LICENSE SNtt-ll68 DOCKET 70-1201 I - GENERAL INFORMATION SECTim tlAME:
David W. Zeff TITLE:
Manager, flaterials llanagement CITIZEN OF UNITED STATES EDUCATION:
1972 University of Wisconsin - B.S. Physics 1973 Purdue University - H.S. Industrial Administra-tion EXPERIENCE:
1973-1974 Planning analyst, Babcock & Wilcox Company, Lynchburg, Virginia. Responsible for capital appropriation requests, market j
i analysis, acquisition analysis, advanced planning, P & L analysis, cash flow analysis, etc.
1974-1978 License Administrator, Babcock & Wilcox Company, Comercial Nuclear Fuel Plant, Lynchburg, Virginia.
Responsible for licens-ing activities associated with nuclear fuel assembly plant, interpretation and applications of NRC regulations, measurement control pro-grams, and statistical methods application in Nuclear Materials Control.
1978-1982 tianager, Health-Safety and Licensing, Babcock and Uilcox Company, Commercial Nuclear Fuel Plant, Lynchburg, Virginia.
Responsible for all safety and licensing activities associated I
with nuclear fuel assembly plant.
1982-Present Manager, Materials Management, Babcock and Wilcox Company, Commercial Nuclear Fuel Plant, Lynchburg, Virginia.
Responsible for license administration, Safety Review Board, i
l safeguards, and production control activities.***
1 Professional Organizations Sigma Pi Sigma (Physics)
Institute of Nuclear Materials Management B&W Nuclear liaterials Control Committee l
DATE 4-07-82 REVISIQ4 NO.
1 PAGE CURREtlT REVIS!Q4:
SUPERSEDES: PAGE Appendix A, Page 12 USNRC APPROVAL REFEREHCE DATE 4/30/75 pgygggg;
B/BOXX & WILCDX CUPAff, C0ffEsCIA'L $UClB$ FLEL Pl#ff '
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4 UStJRC LICENSE Stitt-31b8 DOCKET 70-1201
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SECTIO 1 FLAME:
Charles !!. Speight TITLE:
Manager, Facilities Control CITIZEft 0F UtlITED STATES EDUCATION:
Matriculation Certificate, Hebden Bridge Gramar School, Hebden Bridge, England (1941). National Certificate Electrical Engineering, Coventry, England (1950) l EXPERIEllCE:
1944-1946 Royal flavy 1946-1947 S. Sutcliffe & Son, Ltd., Mytholmroyd, Yorkshire, Enaland - Office Clerk.
1947-1948 Government Training Center, Leeds, England -
Draftsman Trainee.
1948-1949 General Electric Co., Ltd., Coventry, England -
Draftsman. Made drawings of equipment control panels for telephone communication.
1949-1950 Arme trong-Siddeley Motors, Ltd., Coventry, England - Draftsman.
Made drawings of a facility for testing aircraft jet engines.
1950-1952 Raleigh Industries, Ltd', Nottingham, England -
Draftsman.
Designed production and service equipment for use in manufacture of bicycles.
1952-1953 A. V. Roe (Canada) Ltd., Malton, Ontario, Canada - Draftsman.
Made layouts of the machine shop for aircraft jet engine manufacture.
1953-1956 Canadian Westinghouse Company, Hamilton, Ontario, Canada - Draf tsman, Plant Engineering Department.
Designed miscellaneous equipment for use in manufacture of Westinghouse products.
1956-1960 H. G. Acres and Company, Ltd., Niagara Falls, Ontario, Canada - Draftsman. Made drawings of piping arrangements for fossile fired power plants.
1960-1961 Babcock & Wilcox Company, Fossil Power Genera-tion Division, Barberton, Ohio - Draf tsman.
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Made drawings of plant equipment and property j
plots.
Appendix A DATE 4-07-82 REVISIQ1 NO.
PAGE 13 CURREtiT REVISION:
SUPERSEDES: PAGE usnac APPROVAL REFERENCE i
DATE REVISIUi
FAC00( 8 WILCDX C& PAW, CORERCIAL NUCEAR FEL PLATT LEtJRC LICENSE Si4tt-llba occ<rr 701.201 SECTIOJ
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EXPERIENCE:
1961 flew Zealand Ministry of Works, Public Works Department, Wellington, New Zealand - Draftsman.
Made HVAC ducting drawings for government buildings.
1961-1968 Babcock & Wilcox Company, Fossil Power Genera-tion Division, Barberton, Ohio - Senior Drafts-man until 1967 then Assistant Project Engineer until 1968.
Responsibilities included design of plant equipment and machines.
1968-1980 Babcock & Wilcox Company, Nuclear Materials and Manufacturing Division, Commercial Nuclear Fuel Plant, Lynchburg, Virginia - Works Industrial Engineer.
Responsible for the design and procure-ment of equipment, services, and facilities in support of manufacturing.
1980-April 1, 1982 Babcock & Wilcox Company, Nuclear Materials and Manufacturing Division, Commercial Nuclcar Fuel Plant, Lynchburg, Virginia - Manager, Facilities Engineering.
Responsibilities included management of Facilities Engineering and administration of Capital Projects.
April, 1982 to Present Babcock & Wilcox Company, Nuclear Power Generation Division, Commercial Nuclear Fuel Plant, Lynchburg, Virginia - Manager, Facilities Control.
Responsi-bilities include manageinent and planning for health physics, safety, security, and facilities engineering, and administration of Capital Projects.
nppenoix n DATE 4-07-82 REVISIOJ No.
PAGE 14 CtRRENT REVISim:
SUPERSEms: PME LENRC APPROVAL FEFERE?tCE DATE RI'/IS !O;
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i ATTACHMENT II Section III - Nuclear Safety Analysis e
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MCOC< & WILCDX COPAf/, CORERCIAL.1UClfAR REL PlM USNRC LICENSE SNft-ll60 DOCKET 70-]201 III flVCLEAR SAFETY ANALYSIS SECTIO 1 7.1 General Requirements 7.1.4 Continued modifications to product specifications or design when re-lating to nuclear safety must be reviewed and approved by the Manager, Materials flanagement or his qualified designee prior to initiation.
In those cases where proposed modifications may involve a change in the bases on which nuclear criticality safety was originally assensed, a technical evaluation by the nuclear criticality safety Function will be initiated by the fianager, flaterials Management or his qualified designee.
The nuclear criticality safety function noted above is a separate component within the corporate structure and thus is organizationally independent of the CNFP, with no interest in plant operations, other than the nuclear criticality safety aspects.
By established procedure, analyses performed by the nuclear criticality safety function involving potential changes in the bases upon which plant safety was orginally assessed are reviewed for appropriateness of method, validity of assumption, and accuracy of the results pricr to application in the plant by a qualified individual not involved in the ori-ginal evaluation.
Qualifications of the evaluator and re-viewers are given in Section V.
DATE 4-07-82 REVISIO4 NO.
2 PAGE 5
CURRENT REVISION:
SUPERSEDES: PACE 5
USNRC APPROVAL REFERENCE 1
DATE 1-9-80 ggyigig;
B20lG( & WILODX CDPh#, C0ffERCIAL NUCLEAR REL PLM USNRC LICENSE Stift-ll68 DOCKET 70-1201 SECTIQ1 III NUCLEAR SAFETY AtlALYSIS - PELLETIZING 7.4 Pelletizing 7.4.4 Moderation Control 7.4.4.2 Unit tioderation Control Criteria ADf1INISTRATIVE CONTROLS (cont'd) accuracy, by a second individual at least as well qualified as the one per-forming the initial evaluation.
Further processing of the SNM is prohibited until the above approval is obtained. The following points are typical of those in the process which require dual signature:
- Initial moisture analysis of as-received powder
- Prior to addition of powder lubricant to blender or transport container
- Prior to addition of re-cycle material to a moderation controlled unit, if the ma-terial has been exposed to an uncontrolled environment.
Adherence to the above procedure will be audited by the Health-Safety Supervisor or the flanager, Facilities Control at least monthly.
2.
The addition of powder lubricants to the blender or transport containe-has been shown to be safe under crediole accident conditions.
However, in 2
DATE 4-07-82 REVIS!Of NO.
PAGE 114 CURRENT REVISION:
SUPERSEDES: PAGE 114 LENRC APPROVAL REFEREilCE 1-9-80 1
DATE REVISICti
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B/BC00( a WILCDX CDPMY, C0"IERCIAL NUCLEAR FLEL PLAIT USNRC LICENSE SNtt-1160 DOCKET 70-1201 SECTIci III NUCLEAR SAFETY ANALYSIS - PELLETIZING 7.4 Pelletizing 7.4.4 floderation Control 7.4.4.3 Unit Area Moderation Control (continued) over moderation controlled units or arrays, the overhead shielding essentially serves as a technique for providing "second order" protection.
The shield-ing is not required to protect the array from accidental moderation due to pipe rupture since that contingency has been provided for through baffling and double containment.
PERIODI'C EVALUATION OF MODERATION CONTROL EQUIPMENT The routine calibration and standards analysis pro-gram for moderation control instrumentation has been described previously. While safety within an operational area is the responsibility of the area supervisor, Health-Safety conducts routine system audits to verify that all activities are conducted safely and in accord with license conditions.
Additional nuclear safety and health physics audits are conducted by qualified B&W personnel, from outside the CNFP, at least quarterly.
At least monthly, a detailed inspection will be con-ducted by the Manager, Facilities Control, or his qualified designee.
Inspection scope, DATE 4-07-82 REVISIG1 NO.
2 PAGE 123 CURRENT REVISICt4:
SUPERSEDES: PACE 123 USNRC APPROVAL REFEREi1CE 1-9-80 I
DATE REY!SICti
4 ATTACHMEllT III Section IV - Health Physics I
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F4 COG ( & WILCDX C0FFA7/, CORERCIAL NUCLEAR PE.L PLAIT USNRC LICENSE SNft-1160 DOCKET 70-]201 sgcjig; IV HEALTH PHYSICS 8.2 Cont'd linited to the following (10 CFR 20.101)
- Whole body, trunk and head, active blood forming organs, lens of eyes, and gonads 1.25 Rem / Cal. qtr.
- Hands and forearms, feet and ankles 18.75 Rem / Cal. qtr.
- Skin of whole body 7.50 Rem / Cal, qtr.
However, NRC Form 4 documentation is provided for each permanent employee and in specific cases the Manager, Facilities Control and the Plant Manager may authorize exposures greater than the above provided 10 CFR 20.101 (b) and 20.102 requirements are satisfied.
In these cases, the " maximum permissible exposure" is taken to be:
- 3 rem per calendar quarter to the whole body,
- 5 rem per calendar year to the whole body,
- And, accumulated dose is < 5(N-18) rem where N is the individual's age at last birthday.
8.3 Exposure of employees to airborne contaminants is limited by the concentrations set forth in 10 CFR 20, Appendix B, Table 1 averaged over 520 working hours per calendar quarter.
DATE 4-07-82 REVISIO4 NO.
2 PAGE 13 CURRENT REVISICN:
SUPERSEDES: PAGE 13 USNRC APPROVAL RErtRE!1CE
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1-9-80 DATE REVISICJ
BABCDC< & WILCDX C0fPAlY, C0flERCIAL ituClfAR FIEL PLAff USNRC LICENSE SNft-1168 DOCKER 70-1201 IV HEALTH PHYSICS SECTIQ1 8.3 Con t' d Permissible exposure levels are adjusted based on the actual time the individual is present in the area. Additionally, respirators may be used and exposure results adjusted according to the protection factors as defined by NRC.
In actual practice, exposure to airborne activity is usually maintained ***
as low as practicable by engineered or other controls and a design / operational criteria of < 25% of Appendix B concentration levels is applied.
8.4 Minors (persons under 18 years of age) are limited to doses not greater than 10% of those specified in 8.2.
Exposure of minors to airborne contaminants will not exceed the levels contained in Appendix B, Table II of 10 CFR 20.
Minors are not employed at CNFP as a matter of policy.
8.5 Exposure of visitors in all cases is limited to 10% of the levels specified for occupational exposure in 10 CFR 20, unless documen-tation of the radiation exposure history is available.
8.6 Eating and smoking are prohibited in controlled areas.
Smoking may be permitted in change rooms if assurance of adequate radiological hygiene practices are maintained. At the discre-tion of the Manager, Facilities Control drinking fountains may be located within controlled areas where non-transportable materials are being processed.
Drinking facilities are provided in change areas.
DATE 4-07-82 REVISIOl NO.
2 PAGE 14 CURREffr REVISICN:
SUPERSEDES: PAGE 14 USNRC APPROVAL REFEFSICE DATE 1-9-80 ggyi3gaj 1
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.4 BEOG( & WILQX COPAf(, C0ffERCIAL.'luCLEAR REL PLM USNRC LICENSE St#4-ll68 DOCKET 70-1201 SECT!al IV HEALTH PHYSICS 16.
Cont'd 16.2 In addition to the above, logs are established and maintained to document all routine monitoring activities including:
- Air sampling
- Radioactive Material shipments
- Bioassay and Environmental samples
- Source control and leak tests
- Smear and penetrating radiation surveys
- Equipment history, use and calibration
- Pre-operational and operational evaluations
- First aid (per OSHA requirements)
- Contaminated air handling system inspections
- Health physics, nuclear safety, and industrial safety inspections and audits.
16.3 In-plant records, and reports submitted to regulatory bodies, are reviewed periodically by the Manager, Facilities Control and in the course of routine audits provided by other BMI components.
Record retention requirements are in accord with 10 CFR 20.
16.4 Uhere applicable, all records are maintained using thrminology equivalent to 10 CFR 20. Where because of type of sample or the analytical technique employed, other units are more i
descriptive or useful, Health-Safety may maintain records in i
the units most appropriate.
Typically, unit terminology will be as noted below:
DATE 4-07-82 REVISIQ1 NO.
2 PAGE 38 CURRENT REVISION:
SUPERSEDES: PAGE
't R USNRC APPROVAL REFEREilCE I-9-80 DATE ggygggg; 1
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BABCDG( & ',IILCDX C&PKiY, CalERCIAL.'luCLEAR FLEL PLAlT USNRC LICENSE SNft-1163 DoCxET 70-1201 SECTIOJ IV HEALTH PHYSICS 17.'
Continued posting plant entrances with signs incorporating the radiation symbol and the following warning:
CAUTI0ft RADI0 ACTIVE ftATERIALS ANY AREA OR CONTAIllER WITHIN THIS PLANT MAY CONTAIN RADI0 ACTIVE f1ATERIAL.
This system has been applied effectively at the CNFP for the past two years.
17.1 Personnel access to the plant and supporting buildings is con-trolled through a guard station which is constantly manned.
The plant area is surrounded by a chainlink fence, and all access points, other than the main gate, are locked when not in use.
Key control is the responsibility of Facilities Control.
For purposes of plant and personnel protection and access control, the CNFP " restricted area" is considered to consist of all areas within the perimeter fence.
In specific instances, CNFP manage-ment may modify the restricted area as defined above in order to accommodate unusual or temporary conditions.
17.2
" Controlled areas" within the CflFP are established as neces-sary to assist in the protection of personnel or in the control of contamination spread.
Criteria specified in 10 CFR 20.202 and 20.203 are applied to the determination for the necessity of establishing controlled areas.
40 DATE 4-07-82 REVISICt1 NO.
2 PAGE CURREffT REVISION:
SUPERSEDES: PACE 40 USNRC APPROVAL REFEREilCE DATE 1-9-80 1
pgygg;cg;
t ATTACHMEtiT IV Section V -
Conditions i
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BECOG( & WILWX COM#, CORERCIAL NUCLEBR FLEL PIM USTJRC LICENSE SNIT-ll68 DOCKET 70-1201 ONDITIONS SECTICN 5.0 Administrative The following features of administration provide control to assure nuclear and radiation safety.
5.1 Management is responsible to assure the safety of the operation and compliance with license conditions.
Control is established by designation of responsibilities to qualified individuals, review and approval of Facilities Control procedures designed to ***
assure continuing safety and compliance, review of program effectiveness, and assuring correction of non-conforming conditions.
5.2 Operational Area Supervision Operational Area Supervision is that supervision directly responsible for the control of materials, personnel, equip-ment, and activities in specific areas. Those responsibilities include assuring that approved control procedures developed with Facilities Control are available in writing to operators and ***
other concerned personnel and are adhered to.
5.2.1 Minimum qualifications of operational area supervision shall include:
DATE
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REVISIQJ NO.
1 PAGE 6
CURREffT REVISIOJ:
SUPERSEDES: PAGE 6
USNRC APPROVAL REFEREi1CE DATE 4/30/75 ggyyggg;
B/BC00( a WIL(DX C0FPAf(, CORERCIAL NUCLEAR FLEL PLAIT USNRC LICENSE SNM-ll60 DOCKET 70-1201 SECTIOJ 5.0 Administrative 5.2.1 Continued (a) A high school education or equivalent and a minimum of 6 months experience in the nuclear industry.
Experience shall include the practical application of criticality control techniques and a familiarity with the applicable specific limitations imposed on CNFP operations.
(b) Sufficient experience of industrial supervisory nature for recognition of the responsibilities of the position and achievement of the required control.
5.3 The Facilities Control Section is responsible to interpret the license ***
conditions, provide monitoring facilities, develop safe operation guidelines, maintain training programs, and review and approve operating procedures to assure safe operation and license compliance.
These responsibilities include nuclear safety and radiation safety
.sith the approval authority limited to authorized specific or general license conditions.
The Facilities Control Section is responsible to provide management ***
with assurance of the effectiveness of the safety program by DATE 4-07-82 REVISICN NO.
I PAGE 7
CURREfff REVISIG1:
SUPERSEDES: PAGE 7
USNRC APPROVAL REFEREilCE DATE 9/19/75 ggygggg;
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FAC00( & WILCDX COM#, C0fERCIAL NUCLEAR REL PLAIT USNRC LICENSE SNtt-llb8 DOCKET 70-]201 V CONDITIONS SECTIO; 5.0 Administrative 5.4 Independent Auditors are responsible to ascertain the overall performance of the plant functions in providing adequate controls, surveillance, and followup to assure safety and license compliance. This will be accomplished by periodic inspection of the facilities and records resulting in a written report to the Plant Manager.
5.4.1 Qualifications of the independent auditors will include competence in the areas of health physics and nuclear physics at least equivalent to those resident at CNFP.
The independent auditors will have no direct responsi-bilities for the functions being reviewed.
5.4.2 Designation of the independent auditors ~will be the responsibility of the Commercial Nuclear Fuel Plant Manager.
4-07-82 I
9 MTE REVISIQ1 NO.
PAGE CURRENT REVISION:
SUPERSEDES: PACE 9
USNRC APPROVAL REFERENCE 4/30/75 DATE REVISICri
1 MC00( & UILCDX COPAff, CWERCIAL NUCLEAR REL PIM USNRC LICENSE SNft-ll68 DOCKER 70-3201 Y CONDITIONS SECTICN 6.0 General Specifications - Implementation of the technical specifications will be accomplished through application of the following general specifications.
6.1 Control Program Specifications and design criteria for purchased or locally fabrication equipment where nuclear and radiological safety considerations are involved are approved by a knowledgeable representative of Facilities. Control.
Before being released for production operation, new equipment is tested to assure that safety specifications are satisfied.
Safe geometry equipment will be measured by a knowledgeable person to ascertain that it is of proper dimensions before it is put into service.
Where operational safety is based wholly or in part on the use of electrical or mechanical interlocks, the proper functioning of interlocks shall be verified upon installa-tion and on an annual basis thereafter.
Sintering furnace safety interlocks will be tested prior to each startup.
Routine plant inspections place added emphasis on new operations.
No equipment is used after being removed from service until an equipment checkout for continued effectiveness of safety related parameters is performed.
DATE REVISICN NO.
2 PAGE 11 CURREffT REVISION:
SUPERSEDES: PAGE 11 USNRC APPROVAL REFERENCE 1
DATE 1-9-80 ggyg g g g.
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BABCOG( & WILWX C&PM/, C0ttERCIAL.1UClfAR FLEL PIM USNRC LICENSE SNtt-ll68 DOCKET M-1201 V CONDITIONS SECTICN 6.5 General Specifications 6.1 Radiation instruments are calibrated at the frequency indicated in Section V, Part 8.3.4.
Calibration is performed by Facilities Control personnel.
Ventilation, containment, and air cleaning equipment is routinely inspected by Facilities Control personnel to assure continued effectiveness and compliance with license specifications.
These inspections are recorde'd and a periodic review is per-formed by the Health-Safety Supervisor, and Manager, Facilities Control.
The Health-Safety Supervisor or qualified designee is responsible for control of the air sampling and contamination survey pro-gram, and evaluates sample results on a daily basis. Sample and survey records are periodically reviewed by the Manager, Facilities Control.
Instances of inadequate control of contamination or air effluent levels, and of equipment operation not in accordance with established nuclear and radiation safety and license l
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DATE REVISIO1 NO.
PAGE 12 i
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SUPERSEDES: PAGE 12 USNRC APPROVAL REFERENCE DATE 1-9-80 REVISICri 1
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BABC00( & WILWX C& PAW, CafERCkAL.'lUCLEAR REL PLAIT USNRC LICENSE SNft-ll60 DOCKET 70-1201 V CONDITIONS SECTIO 1 6.0 General Specifications 6.1 Control Program (continued) parameters are reviewed by either the Health-Safety Supervisor or the Manager, Facilities Control who may order the operation suspended if timely compliance cannot be assured.
Disciplinary action can be recommended if warranted.
SAFETY REVIEW BOARD A Safety Review Board shall be established to consider the effect of new or revised facilities, to analyze equipment and processes involving radioactive materials and to evaluate the continuing effectiveness of established controls and safeguards, including maintenance of "as low as practicable" criteria.
In the case of minor, procedural changes and where existing safety practice remains unchanged, the Manager, Facilities Control may determine that Board review is not necessary. The Board shall be chaired by the Manager, Materials Management, and the permanent membership shall consist of representatives of CNFP operational and technical management.
Technical representatives of consulting organi-zation shall be included as necessary (LRC, Nuclear Criticality Safety Group).
The Manager, Facilities Control reviews all requests for changes in process and equipment which involve radioactive material and determines if Board l
4-07-82 2
DATE REVISION NO.
PAGE 13 CURRENT REVISION:
SUPERSEDES: PAGE 13 USNRC APPROVAL REFERENCE DATE 1-9-80 ggyg3 gg; 1
BMC0C< & WILCOX COWA#, CGIERCIAL NUCLEAR FLEL PLAIT USNRC LICENSE SNtt-ll68 DOCKER 70-3201 SECTICU 6.0 General Specifications 6.1 SAFETY REVIEW BOARD (continued) review is necessary. The Board will not approve any new or revised facility, equipment, or process until it has received written determination (from the Manager, Materials Management) for the necessity of a nuclear safety evaluation and/or license amendment, and has reviewed where required, a properly documented nuclear safety evalua-tion or approved license amendment.
Board meetings may be convened at the discretion of the Manager, Facilities Control, but shall be held at least quarterly.
Records of Safety Review Board proceedings, including support-ing calculations and approvals, will be retained for at least six months after the completion or termination of the subject activity.
REC 09'1S_
Operating logs and records of reviews, tests, inspections, personnel qualifications, and audits shall be maintained on file for review by B&W management and regulatory agencies.
Duration of reccrd retention is based on existing federal regulations, license specifications, customer raquire'aents, and prudent management practices.
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SUPERSEDES: PAGE I4 USNRC APPROVAL REFERENCE 1-9-80 I
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BMC00( & WIL(DX C&PhlY, CGIERCIAL,'lUCLEAR FLEL PIET USNRC LICENSE SNft-llb8 DOCKET 70-1201 SECTIQ4 V CONDITIONS THIS PAGE IS RESERVED FOR FUTURE USE.
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DATE 4-07-82 REVISION NO.
2 PAGE 15 CURREffT REVISICN:
SUPERSEDES: PAGE 15 LENRC APPROVAL REFEREi1CE DATE 10-13-78 REVISICri 1
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BABC0C< & WILCOX COPA#, CD'IERCIAL.1UCLEAR REL PLAIT USNRC LICENSE SNtt-ll60 DOCKET 70-1201 SECTIOJ V CONDITIONS 6.0 General Specifications 6.3 Personnel Training Initial indoctrination of newly hired employees into nuclear and radiological safety will be the responsibility of Facilities Control and shall conform with 10 CFR 19. The extent and depth of the training, relative to the detailed aspects of the health physics and nuclear safety programs, is dependent on the employee's assignment.and potential exposure to radio-active materials as determined by Facilities Control.
The initial Health-Safety training program shall be reinforced (as appropriate to tne individual's job assignment) by the employee's imediate supervisor with respect to individual unit safety requirements, location of emergency exits, con-tamination control techniques, specific local controls, and operating procedures.
A continuing safety training program will be conducted. by Facilities Control to the extent necessary to assure the maintenance ***
I of acceptable safety practices.
Such training may be c mJucted on an individual or group basis. The content of retraining l
t programs may be varied by Facilities Control with emphasis placed i
on new or revised safety criteria or areas in need of re-inforcement.
A formal retraining of radiation workers shall l
be conducted at least annually.
Documentation of formal training i
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1 PAGE 16 CURREtiT REVISIQ4:
l SUPERSEDES: PAGE 16 USNRC APPROVAL REFEPEHCE l
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BABC00( & ',!!UDX CDPAf/, C0f1ERCIAL.4 REAR FEL PLAIT USNRC L! CENSE SNtt-31b8 DOCKET & l201 SECTIm V CONDITIONS 6.0 General Specifications 6.3 Personnel Training (continued) is maintained by Facilities Control.
The training of personnel assigned to the Facilities Control function is the responsibility of the Manager, Facility Control. The extent and depth of the training is based on the specific job assignment involved.
Heal th-Safety monitoring personnel shall re'ceive a combination of formal and "on-the-job" training such that they can successfully demonstrate their proficiency in basic nuclear and radiation physics monitoring and control techniques and regulatory re-quirements.
The degree of proficiency will be determined on an individual basis by practical and written exaninations, the results of which will be maintained on file by Facilities Control.
Members of the CNFP emergency monitoring team shall be trained by Facilities Control in the proper technique of accident control.***
Training program content shall be as outlined in 6.3.1 through 6.3.3.
DATE 4-07-82 REVI5104 Go, 2
PAGE 17 CURRENT REVISim:
SUPERSEDES: PAGE 17 (ENRC APPROVAL REFERENCE l-9-80 1
DATE ggygg;g;
.. a......
PRC0C< & WlLCDX C&PMY, CORERCIAL NUCLEAR REL PIM USNRC LICENSE SNtt-ll68 DOCKET 70-L?01 SECTIO 1 V CONDITIONS 6.0 General Specifications 6.3 Personnel Training (continued) 6.3.1 New Employee Training Program A.
Introduction 1.
Type of !!aterials Handled 2.
Introduction to Applicable Federal Regulations, License Conditions, and CNFP Procedures 3.
Purpose, Authority, and Responsibility of Facilities Control B.
Radiation Safety 1.
External Exposures a.
Sources of External Radiation Exposure b.
Methods of Control of External Exposures c.
Survey and Monitoring Instruments d.
Dosimetry 2.
Internal Exposures a.
Modes of Entry to the Body b.
Techniques of Control of Contamination, including Air Sampling, Surface Contami-nation, Ventilation Techniques, Respira-tory Protection, and Protective Clothing, Change Rooms, Controlled Areas, Handling Techniques, and Contamination Limits 4-07-82 10 DATE REVISICtf NO.
1 PAGE CURREffT REVISICf4:
SUPERSEDES: PAGE 13 USNRC APPROVAL REFERENCE DATE 4/30/75 REVISICfi
..,--:,~......,.,.
FAC00( & WILCOX C0FPMY, CORERCIAL MUCEAR REL PLM USNRC LICENSE SNtt-1168 DOCKET 70-]201 SECTIOJ V CONDITI0tlS 6.0 General Specifications 6.3 Personnel Training 6.3.1 New Employee Training Program B.
Radiation Safety (continued) 2.
c.
Internal Contamination Measurement Tech-niques Including Bioassay C.
Nuclear Safety 1.
Basic Concept of Nuclear Fission 2.
Techniques for Criticality Control (Geometry, 4
flass, Moderation) 3.
Application of Procedural Requirements and Established Limitation to CNFP Operations -
Local Safety Rules 4.
Possible consequences of Unauthorized De-viations from Established Procedure 5.
Criticality Monitoring System and Emergency Plan 6.
Requirements for Facilities Control review of New or Modified Operations 6.3.2 Health-Safety Monitoring Personnel In addition to the training specified in 6.3.1, Health-Safety monitors shall receive theoretical and applied training in the following areas:
DATE 4-07-82 REVISION NO.
1 PAGE 19 CURREtiT REVISICN:
SUPERSEDES: PAGE 19 USNRC APPROVAL REFEREilCE DATE M/3n/75 REVISICl
,-:,~...
BABC00( & WIL(DX C(IPM, C(NERCIAL.'lUClfR REL PLATT USNRC LICENSE SNft-llb8 DOCKET E.1201 V CONDITI0flS SECTIOJ 6.0 General Specifications 6.4 Postings Nuclear safety postings approved by Facilities Control shall be maintained specifying nuclear safety parameters that are subject to procedural controls.
Area postings may be used for those parts of the process where nuclear safety is maintained by means of " area-wide" require-ments.
Operations for which specific (dedicated) controls are applicable shall be individually posted.
Local safety rules approved by Facilities Control providing personnel ***
and supervision with specific cirections essential to assuring radiation safety will be posted in areas where appropriate.
With the exception of the requirement for posting containers used to store sealed sources (Section V, Part 3.6), the CNFP shall be exempt from the requirements of subparagraphs 20.203 (e)(1) and (f)(1) of 10 CFR 20 for all areas and con-tainers within the plant, provided that all entrances to the plant are conspicuously posted in accordance with subparagraph 20.203 (e)(1) and the words "any area or container within the plant may contain radioactive materials."
6.5 Enrichment Control Provision of different nuclear safety limits for different enrichments implies knowledge of the enrichment level of SN!1 involved.
Silf t identity as to enrichment must be maintained at all times.
If unidentified, SNf1 must be stored and handled as if it were the most reactive enrichment authorized pending i
DATE 4-07-82 REVISIQ1 NO.
2 PAGE 23 CURRENT REVISION:
SUPERSEDES: PAGE 23 USNRC APPROVAL REFEREi1CE DATE 9/19/75 ggyIsta; 1
BABQC< & WIUDX COPAf(, CORERCIAL NUGER REL PLAff USNRC LICENSE SNT4-ll68 DOCKET 70-1201 V CONDITI0flS SECTIQ4 6.0 General Specifications 6.5 Enrichment Control (continued) re-establishment of the identity.
6.6 Procedure Control Written procedures for the conduct of specific operations in-cluding maintenance and development work within the plant are prepared by the functional component responsible for that activity and are reviewed and approved by appropriate representatives of plant management. Where the activity under consideration involves SNM or radioactive materials, specific
~ ~ 'en approval by the Manager, Facilities Control or his designee is required prior to implementa-tion of the procedure. Adherence to procedure is required of all personnel.
Procedures for operations where nuclear and radiological safety are involved shall include specific reference to applicable safety requirements.
Procedure and format shall be such that operations are clearly detailed and specific directions are provided for operation under both normal and abnormal conditions, Deviation from written pro-cedures for the handling of SflM shall be approved by the Manager, Facilities Control or his qualified alternate.
Procedural control of activities at the CliFP are categorized as follows:
l DATE 4-07-82 REVISIQ4 No.
2 PAGE 24 l
CURRENT REVISIOJ:
SUPERSEDES: PAGE 24 USNRC APPROVAL REFERENCE DATE l-9-80 ggyIsta; 1
L
.s -....
FACDC< & WILCDX CaPM/, C&fEPflAL l1UGBR R.EL PLAlT USNRC LICENSE SNti-ll68 DOCKER 70-3201 V CONDITIONS SECTIO 4 6.0 General Specifications 6.6 Procedure Control (continued)
- Procedures developed by Facilities Control specifying the method by which safety related functions are to be accom-plished.
Such procedures may be for internal Health-Safety use or may be intended for general distribution to affected individuals within other components.
Health-Safety proce-dures shall be approved in writing by th: Plant Manager, the Manager, Facilities Control, and other members of plant management / supervision if it is determined by Facilities Control that their area of responsibility is affected by the procedure.
- Safeguards procedures provide techniques for the accountability and measurement of SNM. Such procedures will be approved in writing by the Manager, Facilities Control and by affected plant management.
- Manufacturing, Quality Control, and selected liaintenance/
Engineering procedures, where nuclear and radiological safety, license conditions, or regulatory requirements are involved require prior approval by the Manager, Facilities Control, as well as approval by affected members of plant management.
l l
DATE 4-07-82 REVISION NO.
3 PAGE 25 CURREfff REVISION:
SUPERSEDES: PAGE 25 USNRC APPROVAL REFEREi1CE DATE 6-12-80 REVISICN 2
BABC00( & WILCOX COPAlY, CORERCIAL NUCLEAR FEL PLAIT USNRC LICENSE StJtt-ll68 DOCKET 70.1201 V C0flDITI0tlS SECTIOJ 6.0 General Specifications 6.6 Procedure Control (continued)
Revised procedures shall be subject to approval in the same manner as new procedures.
Health-Safety procedures will be reviewed at least annually for technical correctness and applicability.
Procedure distribution and control is the responsibility of plant supervision.
6.7 Audits and Quality Assurance-An internal audit and quality assurance program shall be maintained to provide assurance that plant activities are conducted safely and in accord with license specifications.
The audit program shall be the responsibility of the flanager, Facilities Control.
Facilities Control supervision shall conduct, at least weekly, a i
formal audit of plant status relative to nuclear and radio-logical safety.
At the discretion of Facilities Control, the audit may consist of an in depth evaluation of a specific area or may be of a generalized nature providing an overview of total plant activities.
Audit results shall be documented, reported to plant management and supervision as appropriate, and will be maintained on file by Facilities Control for at least ***
6 months.
Health-Safety audits shall be conducted by personnel technically qualified in operational nuclear and radiological safety and in i
the application of license specifications.
DATE 4-07-82 REVISIQ1 NO.
3 PAGE 26 CURREffT REVISIG4:
SUPERSEDES: PAGE 26 USNRC APPROVAL REFEREilCE DATE 1-9-80 ggyg 3 gg; 2
,.s....
PAC 00( & WILCDX COPAlY, C0ffERCIAL.'lUGEAR REL PLAIT USNRC LICENSE SNft-llb8 DOCKET 70-1201 V CONDITIONS SECTIGJ 6.0 General Specifications 6.7 Audits and Quality Assurance (continued)
Health-Safety personnel shall, as part of their routine duties, conduct informal daily audits of plant activities.
Independent auditors shall conduct inspections as follows:
- Nuclear Safety
- quarterly
- Health physics
- quarterly The audit program shall include physical inspections and records review for the industrial, nuclear, and radiological l
safety elements of plant activities including:
- Effectiveness of procedural controls impacting on operational safety parameters
- Review of equipment design, layout, and operation for continued compliance with safety design criteria
- Audit of operating records, where such records provide a means of verifying procedural compliance with safety specifications
- Periodic review and evaluation of contamination survey data Independent auditors' reports shall be submitted to the Plant fianager.
The Manager, Facilities Control shall review audit findings for the satisfactory completion of any necessary remedial actions.
I Audit findings are reviewed by the Safety Review Board.
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DATE 4-07-82 REVISIQ1 NO.
2 PAGE 27 l
l CURRENT REVISIG4:
l SUPERSEDES: PAGE 27 USNRC APPROVAL REFERENCE 1
DATE l-9-80 REVISICN
BABCCG( & WILCDX CEPAW, CGIERCIAL,1UCLEAR REL PLM USNRC LICENSE
&ll68 DOCKET 70-1201 V CONDITIONS gggg4 7.0 fluclear Safety - Technical Specificat1ons 7.1 General Requirements (continued) 7.1.2.1 The Manager, Materials itanagement (or his qualified designee) with the concurrence of the LRC Nuclear Criticality Safety Group, will determine which arrays are more reactive than those used as a basis for a, b, and c or best represented as slabs for nuclear inter-action purposes.
In these cases, the interaction acceptance criteria will be evaluated on an individual basis by the LRC Nuclear Criticality Safety Group or it will be the equivalent of eight inches (20.3 cm) of water or as defined in 7.1.2 (d) or (e).
7.1.3 Isotopic enrichment of Still will be verified by shipper's certificaticns with added assurance by Quality Control statistical overchecks.
DATE 4-07-82 REVISIO1 NO.
2 PAGE 32 CURRENT REVISIO4:
SUPERSEDES: PAGE 32 USNRC APPROVAL REFERENCE DATE 80 pgyggrg; 1
l
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BABCOG( & WIL(DX CaPAf/, CalEf AL.1UCEAR REL PLM USNRC LICENSE SNftll68 DOCKET 70-lT1 SECTIOJ V CONDITIONS 7.0 Nuclear Safety - Technical Specifications 7.1 General Requirements (continued) 7.1.4.1 Proposed modifications shall be demonstrated to satisfy the following criteria to approval:
a.
The license condition specified in this part are not modified.
b.
Nuclear safety calculations are performed in a manner equivalent to those originally utilized to demonstrate safety for the area and type of operation under consideration.
Calculations shall consider both individual unit and interaction safety and shall apply the basic assumptions and input parameters used in the original calculations.
c.
Calculated reactivity levels do not increase based on the assumptions and input parameters described below.
7.1.4.3 The review and approval procedure shall be as follows:
a.
A written request shall be submitted to the Manager, Materials Management or his qualified designee describing the proposed change.
b.
The proposal will be reviewed by the flanager, Materials Management or his qualified designee for content, completeness, and compliance with license DATE 4-07-82 REVISION NO.
2 PAGE 34 CURRENT REVISION:
SUPERSEDES: PAGE 34 USNRC APPROVAL REFEREHCE 1-9-80 1
DATE EEVISICri
PAC 00( & WILCOX CDPAi#, COREPflAL.'lUGEAR FLEL PLAlT USNRC LIGNSE SNtt-ll68 DOCKET 70-1201 SECTIOJ V C0flDITIONS 7.b Nuclear Safety - Technical Specifications 7.1 General Requirements (continued) 7.1.4.3 Continued b.
specifications and, where nuclear safety evalua-tion is required, forwarded to the Nuclear Criticality Safety Function (NCSF).
c.
The NCSF performs necessary calculations inaccord with 7.1.4.2 b and forwards the results in writing to the Manager,. Materials Management or his qualified designee.
Evaluations performed by the NCSF are re-viewed as specified in Part 5.5 of this section.
d.
The results of the nuclear safety calculations and the recommendations of the NCSF are reviewed by the Plant Safety Board and the permissibility of the change determined and documented.
e.
Appropriate personnel are notified in writing of the result of the review.
f.
The proposed change will not be implemented until a pre-operational audit ~ (Ref.Section V, Part 6) has been satisfactorily completed'.
9 Correspondence calculations and other material will be maintained on file.
i DATE 4-07-82 REVISION NO.
2 PAGE 35 I
CURRENT REVISIO4:
SUPERSEDES: PAGE 35 USNRC APPROVAL REFERE11G 1
DATE 1-9-80 p3yy3;g;
BMC00( & ',IIL(DX C&PAf(, CalERCIAL llVQBR REL PLAff USNRC LICENSE SfM-ll68 DOCVEr 70-1201 SECTIO 1 V CONDITI0flS 7.0 fluclear Safety - Technical Specifications 7.1 General Requirements (continued) 7.1.4.3 Continued g.
for at least 6 months following termination of the operation.
7.1.4.4 Nuclear safety evaluation is not required where the anticipated change does not affect existing nuclear safety controls or bases.
The Manager, Facilities Control or his qualified designee determines when a change in product, process, or equipment requires a nuclear criticality evaluation or license amendment.
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i DATE 4-07-82 REVISIQ1 NO.
2 PAGE 36 CURRENT REVISIO4:
(.
SUPERSEDES: PAGE 36 USNRC APPROVAL REFERENCE I
l DAT5 1-9-80 REVISICfi 1
.a....
.. a.
BABQXX & WILCDX CDPAN, CORE 9CIAL.1UCLEAR FLEL PLM USilRC LICENSE Stitt-ll68 DOCKET 70-1201 SECTIO 4 V C0flDITI0flS 7.0 fluclear Safety - Technical Specifications 7.3 Fuel Pellet Receiving and Temporary Storage A single shipment of pellets may be stored in the shipping containers in an array no more reactive than as received pending transfer to planned storage facilities.
The shipment will be isolated from other SNf1 as specified in 7.1.2.
7.3.1 The containers will be examined for transit damage, and Facilities Control notified if damage is found.
Facilities Control will examine the damaged container for evidence of water entrainment and other conditions that might constitute a hazard.
Damaged containers will bo opened one at a time and as the material is removed, it will be immediately placed into storage within safe geometry slabs or 850 grams U235 accumulations in accord with appropriate license conditions for storage.
7.3.2 Damaged containers containing SNM will not be r'eturned to the shipper.
DATE 4-07-82 REVISIQ4 NO.
2 PAGE 41 CLERENT REVISIQ4:
SUPERSEDES: PAGE 41 USf4RC APPROVAL REFERENCE 1
DATE 10/13/78 ggyggig; 1
..a.,,.
PRCDC< & illLWX CDPM/, C0fTEPbAL.1UCLEAR REL PLM USNRC LICENSE SNtt-ll68 DCCKET 70.1201 V CONDITIONS SECTIGi 7.0 fluclear Safety - Technical Specifications 7.4 Fuel Pellet Fabrication 7.4.3.1 Area lbderation Control (continued)
C.
Continued that unit.
D.
Monthly inspections shall be conducted by Facilities Control to verify the continued integrity of baffles, seals, shields, or other protective devices.
E.
The contents of any vessel other than process units containing liquid modera-tors shall be limited to 3.5 gallons.
F.
A fire protection program will be de-veloped such that
- Fire fighting agents available in the area will be limited to non-hydrogeneous types such as CO, "Halon," or dry chemical.
2 Water sprinkler systems are pro-hibited.
- Flammable wastes are accumulated in fireproof containers and are removed from the area daily.
- The plant fire brigade and area fire departments will be famil-iarized with the restrications on the use of hydrogeneous agents DATE 4-07-82 REVISIQ1 NO.
2 PAGE 45 CURRENT FEVISION:
SUPERSEDES: PAGE 45 USNRC APPROVAL REFERENCE DATE 10/13/78 REvista; 1
FAC00( & WILCDX COPAf/, C0ffERCIAL.10 CLEAR FLEL PLAfT i
USNRC LICENSE SNtt-ll68 DOCVEr 7[}-1201 V CONDITIONS SECTICtj 1
7.b _ Nuclear Sciety - Technical Specifications 7.4 Fuel Pellet Fabrication 4
1 1
7.4.3.2 Unit Moderation Control (continued)
B.
Continued exposed to non-moderation controlled conditions.
I C.
Positive mechanical connections or enclosures will be utilized for the transfer of oxide between moderation controlled units or process steps.
D.
Other than when required for opera-tion, all penetrations into modera-tion controlled units shall be closed.
Infrequently used penetrations shall be capped, or bolted (or screw type) flanges installed.
E.
Whenever practicable, the decontamina-tion of moderation controlled vessel interiors shall be accomplished using dry techniques.
If the use of liquid j
agents is required, the unit shall be inspected by Facilities Control and a written certification prepared that visible moisture is not present.
The accumula-tion of decontamination liquids in any single vessel in the vicinity of modera-tion controlled units shall be limited to 3.5 gallons (safe volume).
DATE 4-07-82 REVISIOi NO.
2 PAGE 47 CURRENT REVISION:
SUPERSEDES: PAGE 47 USNRC APPROVAL REFEREiiCE DAT 10/13/78 REVISICfl 1
BABC00( & WILCDX C0MilY, C0tiERCIAL llUCLEfR REL PLAfT USilRC LICENSE SNtt-ll68 DOCKET 70-1201 V C0tlDITIONS SECTIO 1 7.5 Nuclear Safety - Technical Specifications 7.4 Fuel Pellet Fabrication 7.4.4.3 Roderation Content Verification and Sampling (continued)
C.
Administrative Control (cont'd) 2.
tionthly audits shall be conducted by Facilities Control to verify con-tinued proper functioning of modera-tion control systems and procedures.
7.4.4 Individual Unit Safety The conditions in this part define the specific nuclear safety criteria to be applied to individual operations ar.d process units within the pelletizing area, Slab thickness specified below may not be increased with-out license amendment.
The arrangement and size of accumulations within the area may be varied except as limited in the specific conditions outlined below, and provided the requirements of 7.4.1 above are satisfied.
7.4.4.1 SNt1 Receipt and Storage A.
SNM may be temporarily stored in authorized shipping containers in an array that is no more reactive than that specified for the same material under transport conditions.
In ad-dition, individual containers (fiberpacks or equivalent) may be stored in the DATE 4-07-82 REVISIO1 NO.
3 PAGE 51 CURRENT REVISION:
ll-SUPERSEEES: PAGE 51 USNRC APPROVAL REFEREllCE 2
DATE 10/13/78 FEvlSICri l
.-:,~...
BAB0JG( & WIL(DX COPA#, COTERC}tt NUClfR FLEL PLAff USNRC LICENSE SNf t-ll68 DOCKET 70.1201 l
V C0tlDITI0flS SECTIOJ i
8.0 Technical Specifications - Radiation Safety 3
8.1 Effluents to Unrestricted Areas 8.1.1 Continued c.
The following program shall be instituted to assure that airborne releases to uncontrolled areas are main-tained as low as practicable:
Quarterly Average - % of 10 CFR 20 Appendix 8, Table 2 LIMIT ACTI0fl 110% of "f1PC" None required.
11 - 20%
Conduct investigation of system and correct if possible.*
21 - 75%
Visually inspect system. As soon as practicable, conduct efficiency test. Determine and correct cause.*
> 75%
Conduct immediate investigation to determine and correct problem in ventilation system.
Maintain addi-tional Health-Safety surveillance of system to monitor contamination levels until problem is corrected.
- end weld operation area - none required
Pre-filters serving equipment in the pelletizing area will be instrumented and monitored as spect-fied in 8.1.la above.
8.1.2 Potentially contaminated liquid effluents will be controlled through a retention tank system with dilution and mixing capabilities and shall be evaluated DATE 4-07-82 REVISIO4 NO.
3 PAGE 76 CURRENT REVISION:
SUPERSEDES: PAGE 76 USNRC APPROVAL REFERENCE DATE 6-12-80 rey! sic; 2
.. a.
B/BCDG( & WILOX C0FPMI, CONERCIAL NUCLEAR FUEL PLAIT USNRC LICENSE SNti-ll68 DOCKET 70-1201 SECT!at V CONDITIONS 8.0 Technical Specifications - Radiation Safety 8.1 Effluents to Unrestricted Areas 8.1.2 Continued for compliance with 10 CFR 20, Appendix B limits prior to release to unrestricted areas.
The following actions, at the contamination levels indicated, will be undertaken in order to maintain contaminated liquid effluent re-leases as low as practicable:
% 10 CFR 20 App. B. "f1PC" Action
< 20%
No action required.
21 75%
Individual releases authorized by Plant Manager or his alter-nate.
> 75%
Discharge prohibited. Waste routed for further treatment or disposal by burial.
Facilities Control shall maintain records of investigations and actions resulting therefrom, a.
Retention tanks will be inspected monthly for sludge accumulation.
l 77 DATE 4-07-82 REVISIO1 NO. 2 PAGE CURRENT REVISIQJ:
i.
SUPERSEDES: PAGE 77 USNRC APPROVAL REFERENCE 1-9-80 ggytsta; 1
DATE
FACOG( a WILCOX CEPA#, CORERCkAL Ml) CLEAR REL PLAIT USNRC LICENSE SNft-llb8 DOCKET 70-1201 SECTICN V CONDITIONS 8.0 Technical Specifications - Radiation Safety 8.2 Ventilation, Containment, and Airborne Activity Control 8.2.2 Hoods or equivalent airborne activity control devices will be installed and utilized so as to maintain air-borne contamination levels as low as practicable, con-sistent with operational requirements.
The degree and type of containment required for individual operations shall be determined by Facilities Control based on the dust ***
generation potential including the:
- potential for alteration of physical fona or characteristics of the material being processed.
- possibility for resuspension based on the mor-phological characteristics of the material and the nature of the operation.
- potential for development of abnormal or un-usual conditions.
- previous operational history and air sample documentation.
The following operations are representative of those that may require air capture techniques when evaluated in accord with the above considerations:
a.
UO2 p wder handling b.
Pellet pressing l
DATE 4-07-82 REVISIOJ NO.
1 PAGE 80 CURREtiT REVISION:
SUPERSEEES: PAGE 80 USNRC APPROVAL REFERENCE DATE 4/30/75 ggygggg;
.. a.
BABC00( & WILQX C0PA7/, CONERCIAL NUClfAR FLEL PlM USNRC L! CENSE St111-1168 DOCKET 70-1201 SECTIO 1 V CONDITIONS 8.0 Technical Specifications - Radiation Safety 8.2 Ventilation, Containment, and Airborne Activity Control (cont'd) 8.2.2 Continued on Health-Safety survey data.
1.
Glovebox negative pressures shall be monitored weekly.
2.
Face velocities shall be measured weekly.
" Elephant trunk" drops shall be used as required for maintenance or non-routine activities requiring ex-haust ventilation and where other, more permanent types of containment are not practicable.
" Elephant trunks" shall be utilized during the connec-tion and removal of transport containers from powder processing units.
Except as noted above, elephant trunks will not be used as a routine control measure without the specific approval of Facilities Control. Mini-mum velocity at the point of entrance to " elephant trunk" drops in the pelletizing area will be 1300 LFil and will be measured weekly.
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4-07-82 DATE REVISIQ1 NO.
1 PAGE 82 CURREffr REVISIG4:
SUPERSEDES: PAGg 82 USNRC APPROVAL REFEREi1CE DATE 4/30/75 ggyista;
I PAC 0CX & WILCDX CDP #ilY, CafERCiAL l1UCEAR REL PLAIT USNRC LICEtJSE Stift-ll6<3 DOCKET 70-1201 SECTIOJ V C0tIDIT!0flS 8.0 Technical Specifications - Radiation Safety 8.2 Ventilation, Containment, and Airborne Activity Control (cont'd)
The following action points shall apply to the routine air sampling program:
Exposure - % tiPC (Time Weighed Average)
Action
< 25%
No action required.
> 25%, < 50%
Report to Manager, Facilities Control ***
or designee.
Evaluate operation and containment.
Increase air sample frequency if indicated.
> 50%
< 75%
Report to flanager, Facilities Control.***
Take steps necessary to lower air-borne activity to acceptable range.
> 75%
Notify Plant Manager.
Terminate operation if > 100%
MPC.
tiodify or install air capture devices.
Increase air sample frequency.
Facilities Control shall maintain records of investigations and corrective actions taken.
The above action levels do not apply to non-routine operations conducted with the cognizance of DATE 4-07-82 REVISIO1 NO.
2 PAG 84 CURRENT REVISION:
SUPERSEDES: PAGE 84 USNRC APPROVAL REFEREitCE DATE 1-9-80 p3yI3Ig; 1
BABC0C< & WILCOX CGPMlY, CORERCIAL 'luClEAR FLEL PIAlT USNRC LICENSE SNft-ll68 DOCKET 70-1201 V CONDITIONS SECTIOJ 8.0 Technical Specifications - Radiation Safety 8.2 Ventilation, Containment, and Airborne Activity Control (cont'd) 8.2.3 Continued Health-Safety, and in accord with specific contamina-tion control measures (for example, certain maintenance activities).
8.2.4 Respirators may be used in unusual conditions where air-borne concentrations of radioactive material may cause personnel to receive exposures in excess of permissible level s.
Typical unusual conditions may be certain maintenance operations, startup periods, short-term operations, etc.
Procedures for maintenance of the respirators and training of personnel using respirators shall be under the cognizance of Facilities Control.
Respirators shall not be applied as a routine control measure in situations where engineered or procedural controls are feasible.
SCBA is available at the plant.
The following specific conditions apply:
a.
The individual uses respiratory er other appropriate protective equipment such that the total intake, in any period of seven consecutive days by inhalation, ingestion, or absorption, would not exceed that in-take which wouid result from breathing the concen-trations specified in Appendix B, Table 1, Column 1 DATE 4-07-82 REVISICN NO.
1 PAGE 85 CURRENT REVISICN:
SUPERSEDES: PACE 85 USNRC APPROVAL REFERENCE CATE 4/30/75 ggyg3gg;
B/EC00( & WILCOX CEPAW, C0 tie.9CIAL llUCLEFR FLEL PLAIT USNRC LICENSE SNM-ll68 DOCKET 70-1201 V CONDITIONS SECTIOJ 8.0 Technical Specifications - Radiation Safety 8.3 Instr _umenta tion 8.3.1 Minimum detection capabilities of instruments available for general survey activities shall include:
a.
Gamma 0.1 to 250,000 mR/hr b.
Beta 0.1 to 225,000 mrad /hr c.
Alpha 100 DPli (portable) 10 DPf1 (fixed) d.
Neutron 25 CPM (< 1 mrem /hr.)
8.3.2 Analytical capability forevaluation of effluent samples shall be such that instrument sensitivity and sample preparation techniques allow:
0.5% of the appropriate MPC for liquid effluents a.
b.
10.0% of the appropriate f1PC for airborne effluents 8.3.3 A criticality monitoring system will be maintained in compliance with the appropriate sections of 10 CFR 70.
Response time for the facility shall be not greater than 4 seconds. The criticality alarm system will l
be function-tested at least quarterly and detector units calibrated annually.
Nuclear accident dosimeters
[
incorporating neutron activation foils shall be posi-tioned in the plant at locations selected by Facilities Control ***
to provide exposure estimating capability in the event of a nuclear incident.
l DATE 4-07-82 REVISIO4 NO.
I PAGE 90 l
l CURPEIT REVISICN:
SUPERSEDES: PACE 90 USNRC APPROVAL REFERENCE DATE 4/30/75 ggy;g yg;
BABC0CK & WILCOX C0FPAW, COMERCEAL NUCLEAR REL PLAY USNRC LICENSE SNtt-ll68 DOCKET 70-1201 SECTIO 4 V CONDITIONS 8.0 Technical Sr.ecifications - Radiation Safety 8.3 Instrumentation (continued) 8.3.4 All instrumentation will be calibrated upon initial installation, following major maintenance, and at other times as deemed necessary.
In any case, calibration will be performed at least semi-annually.
Laboratory counting instruments shall be calibration-checked daily when in'use.
8.3.5 Field check sources will be available for assuring functional response of instrumentation prior to use.
8'. 4 Personnel flonitoring and Contamination Control 8.4.1 Personnel monitoring equipment - film badges, thermo-luminescent dosimeters, detectors, etc., - will be used by persons having access to restricted or radia-tion areas, as deemed necessary by Facilities Control, and in accord with 10 CFR 20. The dosimeters will be processed routinely to determine radiation dose, Facilities Control will review and maintain the dose records ***
l and prepare such reports as are required by regulati.ons.
j Neutron dosimeters will be used by operators and other persons as deemed necessary by Health-Safety when a l
potential for measurable neutron exposure exists.
i 3
DATE 4-07-82 REVISIOl NO.
PAGE 91 l
CURRENT REVISIO4:
SUPERSEDES: PAGE 91 USNRC APPROVAL REFERENCE 2
DATE 5/25/79 REVISICt;
.. a.
BABC00( & WILCDX C0FPMY, CORERCIAL,1UCLEAR FLEL PLAff USilRC LICENSE StifPll68 DOCKET 70-1201 SECTIO 4 V C0f1DITI0f15 8.0 Technical Specifications - Radiation Safety 8.4 Personnel fbnitoring and Contamination Control 8.4.4 Personnel Contamination (continued) in the area under consideration.
Required protection may range from a minimum of lab coats and shoe covers over street clotSes to coveralls, haircaps, gloves, and special shoes for areas of higher contamination potential.
Radiation monitors, incorporating audible and/or visual alarms, shall be located at routine exit points from controlled areas.
The monitor alarm point shall be set as low as practicable taking into account the necessity for reducing spurious alarms induced by background fluctuations.
Health-Safety shall be noti-fied when initial decontamination attempts fail to reduce skin contamination to acceptable levels and will conduct further decontamination, as necessary, to levels as low as practicable, consistent with good health physics practice.
8.4.4.1 Routine use of anti-contamination clothing shall be limited to the controlled area.
Use of anti-contamir.ation clothing outside of the controlled area shall be approved by Facilities Control.and is limited to the restricted area when required for the performance of non-routine or special process related operations. The following limitations shall apply:
a.
Personnel entering the restricted area from the controlled area when wearing anti-contami-nation clothing will:
i v
DATE 4-07-82 REVISIQ4 NO.
2 PAGE 93 CURREffT REVISIGi:
i SUPERSEDES: PAGE 93 USf1RC APPROVAL REFEREilCE i
DATE 1/24/78 REyISIci 1
1 --
BABCOG( & WILWX CEPA#, C0ffERCIAL 1UCLEAR FUEL PLAIT USf1RC LICENSE SNftll68 DOCKET 70-1201 SECTIGJ V C0flDITIONS 8.0 Technical Specifications - Radiation Safety 8.4 Personnel Monitoring and Contamination Control 8.4.5 Surface Contamination Control (continued)
When general levels in excess of those noted above occur, prompt decontamination will be undertaken.
The levels established for Item "1" above are defined for the general area including floors and other exposed surfaces.
The contamination levels in hoods and on equipment that directly contacts SilM cannot be effectively specified.
Control siiall be maintained through frequent cleanup and limitation of powder accumulation.
Tools and equipment removed from controlled areas for uncontrolled use elsewhere in the plant shall not 2
2 exceed 1000 dpm/50 cm total alpha, or 100 dpm/100 cm removable alpha contamination.
Release of equipment or tools at contamination levels exceeding the above requires the specific approval of Facilities Control.
In such cases, Facilities Control may impose limitations on use or require other controls to preclude contamination spread.
8.4.6 Facilities Control may approve the performance of non-routine ***
or temporary operations in the manufacturing area outside the controlled area when the operation may result in contamination provided the following controls are established and documented:
- The area involved is identified and access controlled.
- flecessary area and personnel contamination control and monitoring programs are implemented including use of anti-contamination clothing if needed and air sampling as required.
DATE 4-07-82 REVIS!Q1 NO.
3 PAGE 95 CURREffT REVISION:
SUPERSEDES: PAGE 95 USNRC APPROVAL REFEREilCE DATE 10/13/78 ggygg gg; 2
PACOG( & WILCDX COPAN, C0ffERCIAL.10 CLEAR REL PLATT USNRC LICENSE SNtt-3168 DOCKET 70-1201 SECTici V C0flDITI0flS 8.0 Technical Specifications - Radiation Safety 8.4 Personnel Monitoring and Contamination Control 8.4.6 Continued
- During the course of the operation documentation will be initiated when general contamination levels in excess of 1000 DPM/100 cm2 (removable) or 2000 DPM/50 cm2 (total) are noted.
Following completion of the operation, decontamination to clean area levels specified in Paragraph 8.4.5 shall be accomplished.
8.5 Receiving Inspection 8.5.1 Stift receipts will be inspected for damage, and surveys conducted to ascertain if the level of contamination is acceptable for CflFP handling and storage.
Results in excess of contamination limits specified by the Department of Transportation will be reported to Facilities Control for notification of the shipper and evaluation of the need for decontamination.
8.6 Non-Exempt Sealed Source Control 8.6.1 Use of non-exempt sources for training and instrument calibration shall be limited to, or under the direct control of, qualified Facilities Control personnel.
8.6.2 Sources utilized as a functional cor.iponent of devices DATE 4-07-82 REVISIQ1 NO.
3 PAGE 95a CURREffr REVISICt4:
SUPERSEDES: PAGE 95a USNRC APPROVAL REFERENCE 5/25/79 2
DATE ggygg7g;
BMC00( a WILCDX CDPAlY, CORERCIAL tlUCLEAR REL PLM USNRC L! CENSE SNTt-ll68 DOCKET /0-1201 SECTIO: V C0flDITI0flS 8.0 Technical Specifications - Radiation Safety 8.6 flon-Exempt Sealed Source Control 8.6.2 Continued 1
designated for manufacturing and quality control purpose shall be operated only by approved personnel who have been instructed in safe practice by Facilities Control.
Health-Safety will provide appropriate monitoring support during maintenance or'other operations that may entail increased exposure levels.
l 8.6.2.1 A register of approved operators shall be main-tained in the Health-Safety Office.
8.6.3 flaximum whole body exposure rates in any constantly occupied area in the vicinity of operating manufacturing or quality control units utilizing by-product material sources will be less than 2 mrem / hour.
8.6.4 In addition to dosimetric devices routinely worn by all CNFP employees, appropriate self-reading dosimeters shall be utilized by personnel involved in source ma-nipulation in cases where the exposure rate may exceed 2 mrem / hour.
DATE 4-07-82 REVISICt1 NO.
1 PAGE 96 CURRENT REVISICN:
SUPERSEDES: PAGE 96 USNRC APPROVAL REFERENCE DATE 4/30/75 REVISici
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ATTACHf1EllT V Section VI - Emergency Plan l
.\\
BABOXX & WILC0X C0FPM/, C0ftERCIAL NUCLEAR REL PIM USNRC LICENSE SNft-ll68 DOCKET 70-1201 SECTIOJ EMERGEfiCY PLAN 2.0 ENGINEERED PROVISIONS FOR ABil0RMAL OPERATIONS As described in Chapter 1 of this Plan, 'the CNFP operating scope is relatively uncomplicated and is comprised to a great extent of simple mechanical materials handling devices which are controlled by unit operators and supervision. By virtue of the localized nature of the unit operations and the opportunity for direct visual contact with the handling process, any abnormal conditions are noted and corrected without creating circumstances with the potential of releasing radioactive material.
2.1 Criteria for Accommndation nf Abnnrmal Cogitions 2.1.1 Process Systems Plant process systems are described in Section V of SNM-1168.
Specifications and design criteria for purchased or locally fabricated equipment where nuclear and radiological safety considerations are involved are approved by a knowledgeable representative of Facilities Control.
Before being released for produc-tion operation, new equipment is tested to as'sure that safety specifications are satisfied. Where operational safety is based wholly or in part on the use of electrical or mechanical interlocks, the proper functioning of the interlocks shall be verified upon installation and on an annual basis thereafter, except for sintering l
furnace interlocks which will be tested prior to each startup.
The safety interlock system was designed to take certain action on specified process equipment that developed malfunctions such as:
loss of ventilation, loss of gas, or an open door.
No equipment is used DATE 4-07-82 REVISIQ1 No.
1 PAGE 2-1 CURRENT REVISION:
SUPERSEDES: PAGE 2-1 USNRC APPROVAL REFEREllCE
- DAIG 2 REVISIG1
P B/EWO( & illl_QX CDPhlY, CGINRC 7N SUCliAR $ fl.AT USNRC LICENSE Snit-ll68 DOCKET 70-1201 EMERGENCY PLAfl SECTIQ4 4.0 ORGANIZATI0tl FOR C0flTROL OF RADIOLOGICAL CONTINGENCIES (cont'd) 4.1 Normal Plant Operations Normal Plant Organization Chart as of 4/1/32 l Fuel Department Manager l l
i l Virginia Operations Manager l f
I l
l l
l Materials Manage-5pecial Pro-Facilities Control Personnel ment Manager jects Mgr.
ing Manager Manager I
I Manufacturing Opera Manufacturing Engineer-Quality Assurance ing Manager Manager tions Manager j
4.2 On-Site Radiological Contingency Response Organization as of 4/1/82 PLANT MANAGER l
Manager, Va. Operations Manager, Manufacturing Engineering ( Alt.)
EMERGENCY OFFICER l
i flanager, Materials Management License Administrator ( Alt. )
SECURITY OFFICER HEALTH-SAFETh0FFICER EVACUATION OFFICER Manager, Safeguards Health Physicist Manager, Personnel Foreman, NMC Opera-Assoc. Health Physicist I
tions ( Al t. )
( Al t. )
Evacuation Officer Assistant Secretary, Personnel (Alt. for EV0)
I I
RADIATION MONITORING TEAf1 CAPTAIN FIRE BRIGADE CHIEF __
fREVIS!Q1NO. I PAGE 4-2 DATE 4-07-02 CURRENT REVISION:
4-2 SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISIQ1
BABC00( a WIL(DX COPM/, COMERCIAL NCLEAR REL'PtM'-
USNRC LICENSE SNrt-ll68 DOCKET 70-1201 SECT!04 EMERGErlCY PLAtt
- 7. 0' MAINTEtlAtlCE OF RADIOLOGICAL CONTIflGENCY PREPAREDtlESS CAPABILITY 7.1 Written Procedures, Review, and Updating ihe hanager, Facilities Control is responsible for assuring that the Emergency Procedure is reviewed for technical correctness and ap-plicability at least once each year, and updated as appropriate. Pe-vised procedures are approved by cognizant members of plant managcment, and are distributed with outdated versions removed from circulation.
7.2 Training Training in emergency response begins with the indoctrination of each new employee.
Facilities Control conducts the new employee indoctrination in accord with 10 CFR 19. A formal documented retraining of radiation workers shall be conducted by Facilities Control at least annually.
The Fire Brigade and Radiation Monitoring Teams receive annual training programs which include fire fighting techniques, rad monitoring techniques, and familiarization with new and old equipment.
The teams are familiarized with the unique hazards associated with radioactive materials. The teams are trained in the use of protective equipment and are medically qualified annual,1y for respirator use.
Members of the local fire departments tour the plant on an annual basis or as otherwise mutually agreed.
General employee training requirements for emergency monitoring personnel is specified in Section V, SNM-1168.
7.3 Tests and Drills Emergency drills and exercises are conducted to test the adequacy of timing and content of implementing procedures, to test emergency equipment, and to ensure that emergency organization personnel DATE 4-07-82 REVISION NO.
PAGE 7-1 CURREf1T REVISIW:
SUPERSEDES: PAGE 7-1. _
USNRC APPROVAL REFEREllCE DATE 3-15-82 REVISICf1
BABC00( & WILQX COPM, CalERCIN. MUCN M,M
USNRC LICEt4SE SNtt-ll68 DOCKET 70.1201 EMERGENCY PLAN SECTIO 4 7.b MAINTENANCE OF RADIOLOGICAL CONTINGENCY PREPAREDNESS CAPAB 7.3 Tests and Drills are familiar with their duties. A planned evacuation will be conducted annually for CNFP personn?l. Emergency drills (or a com-bined drill) of plant medical emergency and radiological monitoring capabilities will be held at least annually.
7.4 Review and Updating of the Plan and Procedure Health-Safety procedures are approved in writing by the Plant Manager, and other members of plant management / supervision if it is determined by Facilities Control that their area of responsibility is affected by the procedure. The Emergency Plan and procedure shall be reviewed and/or revised for technical correctness and applicability.
Procedures distribution and control shall be the responsibility of plant supervision.
7.5 Maintenance and Inventory of Radiological Emergency Equipment, Instrumentation, and Supplies Equipment, supplies, and instruments held in readiness for emergency use are inventoried and functionally tested on a quarterly basis.
Calibration of instruments is performed semi-annually.
$,550 I
7-2 DATE 4-07-82 REVISIQ1 NO.
PAGE CURRENT REVISIQJ:
SUPERS
- PAGE 7-2 USNRC APPROVAL REFERENCE DATE pgyrgIg;
r PRQXX & illLCDX C0PMI, COMERCIAL.'iUCIIAR FLEL PlM UStJRC LICENSE Silti-ll68 DOCKET 70-lT_1 SECTICf1 EMERGEftCY PLAti 8.0
_ RECORDS Afl0 REPORTS 8.1 Records of Incidents Record forms are maintained in the CNFP Emergency Procedure.
The record forms will document personnel statements concerning the incident, radiation survey data, evacuation checks, Health-Safety checks, Radiation Monitoring, and Environmental fionitoring.
Logbooks or equivalent will be used to record the cause of the in-cident, corrective actions taken to terminate the emergency includ-ing the e:. tent of injury or damage, offsite assistance requested, offsite assistance actuall.y received, and offsite organizations to which the situation was reported, and the action taken or planned to prevent a recurrence of the incident.
The Evacuation Officer will be responsible to assure employee record maintenance. The records will be retained for a minimum of five years.
8.2 Records Assuring Adequate Preparations Records are maintained by Health-Safety on training retraining, drills, exercises, inventory and maintenance of emer-gency equipment and supplies. Agreements with off-site support organizations are reviewed every two years and updated, if ne'cessary. The Emergency Procedure is reviewed every year as required by SNM-1168.
The appropriate personnel and off-site agencies are notified when the Plan and procedures are updated, provided the change affects such offsite agencies.
8.3 Reporting Arrangements The arrangements for reporting accidents and the titles and tele-phone numt ars of the offices that must be notified are specified in the CtlFP Emergency Procedure. The notification will be performed by telephone, telegram, mailgram, or facsimile.
The CNFP Plant Manager or his designee will notify and keep the appropriate agencies informed of the current state of events.
DATE 4-07-82 REVISIQ1 NO.
1 PAGE 8-1 CURRENT REVISICN:
EIR I
- SUPERSEEEs: PACE 8-1 USNRC APPROVAL REFEREi1CE 3'15 pan ggygggg;
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1 a
1
'" LICENSE AMENDMENTS" Docket No. 70 -/LO /
g 340 William O. Miller, License Fee Management Branch, ADM MATERIALS LICENSE AMENDMENT CLASSIFICATION Applicant:
/lH4/
License No:
8 A/41 - // 6 /
Fee Category:
/S
(
Application Dated:
<// )// 1 Received:
(/ //~// L Applicant's Classification:
td1C mDLOtd The above application for amendment has been reviewed by NMSS in accordance with 5170,31 of Part 170, and is classified as follows:
1.
Safety and Environmental Amendments to Licenses in Fee Catecortes 1A throuch 1H,~2A, 28, 2C. and 4A (a)
Major safety and environmental (b)
Minor safety and environmental (c)
Safety and environmental (Categories ID through 1G only)
(d)
/ Administrative-
~
2 Justification for reclassification:
. w-a 3.
The application was filed (a) cursuant to written NRC request and the amendment is being issued for the convenience of the ccmission, or (b)
Other (State reason):
Signature E d' Division of Fuel Cycle & Aaterial Safety Date M4 s,
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