ML19332G239

Corrected Application for Amend to License SNM-1227, Consisting of Part I, License Conditions, Covering Nuclear Criticality Safety,Process Analyses,Operating Procedures & Initial Training

ML19332G239
Person / Time
Site:	Framatome ANP Richland
Issue date:	12/01/1989
From:	Malody C SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
26162, CWM:89:130, NUDOCS 8912200380
Download: ML19332G239 (5)

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U.S. Nuclear Reg tory 4cmnfis' on Attn: Mr. L. C. Ro j

i Fuel Cycle Safety Branch Division of Industrial & Medical Nuclear Safety Washington, DC 20555 License No. SNM-1227 i

Dear Mr. Rouse:

Advanced Nuclear Fuels Corporation (ANF)-submitted application for amendment to License No. SNM-1227 by letter dated June 14, Ic89.

It has come to our attention that certain revised pages submitted in support of that application contained editorial errors.

Enclosed are six copies of corrected pages to replace those containing the errors.

Very truly yours, C. W. Malody, Manage Regulatory Compliance jrs Enclosures As Stated I

1 8912200300 891201 PDR ADOCK 07001257 A Siemens Company am? 2(olR l l

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Y ADVANCEDNUCLEARFUELS CORPORATION gnp.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS REV.

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CHAPTER 4 NUCLEAR CRITICALITY SAFETY Nuclear criticality safety shall be assured through both administrative and technical practices. Administrative practices clearly include establishing the responsibilities for nuclear criticality safety, providing adequate and skilled personnel, preparing written standards and procedures, process

analysis, materials and operational

controls, operational and incident reviews, and emergency procedures.

Technical practices include exercising control over the mass and distribution of significant quantities of special nuclear materials, and the mass, distribution, and nuclear properties of all other materials with which special nuclear materials are associated.

4.1 Administrative Conditions The responsibilities and authorities for nuclear criticality safety are as described in Chapter 2 of this Application, as well as the professional requirements for criticality safety personnel.

4.1.1 Process Analyses (Critically Safe Determinations) l-Before any operation with special nuclear material is begun or changed, it is determined that the entire process will be subcritical under both-. normal and credible abnormal conditions, and within the technical requirements specified in Section 4.2.

Criticality safety

. analyses are performed on all applicable processes in accordance with Section 2.1.12, and all determinations of nuclear criticality safety are reviewed and approved by a second-party reviewer in accordance with the requirements specified therein.

Criticality safety analyses are performed and/or reviewed by Advanced Nuclear Fuels or contractor personnel who meet the professional requirements specified in Section 2.2.5.

Records of criticality safety analyses of processes shall be documented and retained in accordance with Section 2.1.12.

Additionally, basic criteria, data, methods, and references pertaining to nuclear criticality safety shall be documented and retained in Company files by the Criticality Safety Component.

Operations, in which nuclear criticality safety is pertinent, are governed by written procedures, and all persons participating in these operations are required to be familiar with the procedures.

Each major process step is described-by a written Process Specification which, together with the respective Criticality Safety Specification (CSS),

provides the basis for written Operating Procedures.

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AMENDMEhi APPUCATION DATL PAGE NO -

December 1, 1989 4-1 ANF 3830.051 (G/89)

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22 11.4 Operatino Procedures Plant operations are conducted according-to written procedures.

The procedures are written by the Manager, Plant Operations, or his designee.

They are approved by the Manager, Plant Operations, Quality Control, Safety, Security, and Licensing, Equipment and Maintenance Engineering, and Process Support Engineering.

These procedures include, by reference, appropriate Criticality Safety Specifications, Radiation Work Permits, and other safety-related, or pertinent, documents or procedures.

The procedures are documented and issued by Document Control to appropriate personnel and locations.

There are Mini-Libraries located within the various operating facilities which contain copies of the approved operating procedures for ease of access by operating personnel.

l 11.5 Trainina l

11.5.1 initial Trainina l

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Each employee is provided initial instruction adequate to allow them to safely start on-the-job training by his/her manager or supervisor.

This initial instruction includes emergency procedures.

If the employee routinely works with special nuclear material, radiation protection, and criticality safety, requirements and procedures will be included.

Within two weeks after starting work, full instruction in Standard Operating Procedures (including instrumentation and control, methods of dealing with process malfunctions, control of hazardous chemicals, control of contamination, and decontamination procedures), industrial safety, ' fire protection, emergency response procedures, radiation

. protection (including ALARA practices, nature and source of radiation, i

interactions of radiation and matter, biological effects of radiation, a

and the use.of radiation monitoring equipment and step-off pad procedures), and criticality safety, requirements and procedures will be provided.

The degree of training is commensurate with each employee's position. in the Company (related to general and special responsibilities), and' with the extent of the employee's contact with radioactive and fissionable materials.

Employee instruction is provided by personnel knowledgeable in the various training topics.

Prior to assignment to independent operation, each employee is required, by signature, to indicate that he has been instructed in radiation protection, criticality

safety, and emergency response requirements and procedures.

AMENDMENT APPUCATION DATE' ggggggp }

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ANF-3830.051 (C489)

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22-11.6;4-Review / Concurrence /Anoroval The ECN^ receives one. approval, that by the User / Operator Manager.

Prior to that approval, however, several other managers have reviewed and concurred with the package.

Following sign-off by the review group, the ECN package is routed in accordance with the Approval and Responsibility

-l Matrix (Figure 1-2.3).

11.6.5. Execution Work begins upon receipt by either Maintenance or the Construction Engineer of _ copies of the-fully approved ECN package issued by the Design and Drafting Clerk.

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11.6.6 Acceptance l

L-For_ projects not involving fissile material, acceptance of the work I

is documented by -signatures 'of the Project Engineer, the Manager, Plant Maintenance, and the affected manager.-

For projects. involving fissile material, a physical review of the installation is mado prior to introducing fissile - material by a

Criticality Safety Review Team, consisting of the Criticality Safety i

Component-and the Project Engineer.

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i The Supervisor, Radiological and -Industrial Safety, documents the l

team's approval by signing the ECN form.

11.6.6.1 Slartuo Council A separate overview of certain projects is provided by a Startup Council prior to acceptance and operation of facilities, services, and l

equipment which have incurred significant change.

Projects requiring Startup Council review are:

Those having impact on production.

Those with new safety issues or implications.

New major projects (facilities / operations).

Others as determined by the Chairman.

Membership of the Council consists of:

Chairman:

Manager, Process & Equipment Engineering Secretary:

Manager, Equipment & Maintenance Engineering PAGE NO :.5$ AMENDMENT APPLICATION DATE December 1, 1989 ANF-3830.051 (Cv89)

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