ML20059E726
| ML20059E726 | |
| Person / Time | |
|---|---|
| Issue date: | 09/29/1993 |
| From: | Michael Scott NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Rodehau T SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| References | |
| CON-NRC-02-90-009, CON-NRC-2-90-9 NUDOCS 9311030321 | |
| Download: ML20059E726 (7) | |
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION j[
l WASHINGTON, D.C. 20555-0001 SEP 2 91993 l
Science Applications International Corp.
Attn:
Mr. Thomas Rodehau Deputy Contracts Manager 11251 Roger Bacon Drive Reston, VA 22090
Dear Mr. Rodehau:
SUBJECT:
TASK ORDER NO. 24, ENTITLED " NUCLEAR CRITICALITY SAFETY AND FIRE PROTECTION PROGRAM REVIEW LICENSE AMENDMENT FOR i
DRY CONVERSION EXPANSION, SIEMENS POWER CORPORATION, l
RICHLAND, WA" UNDER CONTRACT NO. NRC-02-90-009 l
i In accordance with the task order procedures of the subject contract, this letter definitizes the subject task order.
This ef fort shall be performed in accordance with the enclosed Statement of Work, and the Contractor's proposal dated August 26, 1993.
I Task Order No.
24 shall be in effect from September 29, 1993 through January 30, 1995, with a cost ceiling of $63,732.00.
The i
I amount of $23,400.00 is obligated at this time.
The amount of
$58,309.00 represents the total estimated reimbursable costs and the amount of $5,423.00 represents the fixed fee.
The accounting data for the subject task order is as follows:
B&R No.:
35019401300 Job Code No.:
J-5026 s
Appropriation No.:
31X0200 BOC No.:
2542 Obligated Amount:
$23,400.00 l
NMSS Unique Identifier:
FFS# 5093RO49 The following individuals are considered to be essential to the successful performance of the work hereunder:
Tom Storey, Ken Ridgeway, Jim Maddry, Dan Leung and Jim Hammelman.
The Contractor agrees that such personnel shall not be removed from the effort under the task order without compliance with Contract Clause H.1, Key Personnel.
i Your contacts during the course of this task order are:
Technical Matters:
Mr. David Tiktinsky Project Officer (301) 504-2656 1
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i 9311030321 930929 PDR CONTR NRC-02-90-OO9 PDR
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. Contract No. NRC-02-90-009 Task Order No. 24 Contractual Matters:
Ms. Amy Siller Contract Administrator (301) 492-8027 The issuance of this task order does not amend any terms or conditions of the subject contract.
Please indicate your acceptance of this task order by having an official, authorized to bind your organization, execute three (3) copies of this document in the space provided and return two (2) copies to the U.S.
Nuclear Regulatory Comraission, ATTN:
Ms. Amy
- Siller, Division of Contracts and Property Management, P-902, ADM/DCPM/ CAB 1, Washington, D.C.
20555.
You should retain the third copy for your records.
Sincerely, M
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Mary Lynn Scott, Contracting Of ficer Contract Administration Branch No.1 Division of Contracts and Property Management Office of Administration
Enclosure:
As stated ACCEPTED:
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NUCLEAR CRITICALITY SAFETY AND FIRE PROTECTION PROG t
i TASK TITLE LICENSE AMENDMENT FOR DRY CONVER$10N EXPANSION SIEMEN J
CORPORATION, RICHLAND, WA, LICENSE NO. SNM-70-1227 DOCKET NO.
70-1257 JOB CODE JS026 TASK NUMBER TASK ORDER 24 B&R HUMBER 35019401300 NRC OFFICE NMSS PROJECT OFFICER DAVIO TIKTINSKY TECHNICAL MONITOR MARY ADAMS TAC NUMBER L30547 1.0 Backaround j
Siemens Power Corporation (SPC) conducts licensed activities at its Richland, SPC manufactures fuel assemblies for light water reactors Washington, facility.
using the ammonium diuranate (ADU) and dry conversion processes to convert Decause SPC uses special nuclear material (SNM, as defined in 10 CFR 70.4, the operation is subject to licensing and regul)ation enriched UF, to 00,.
Nuclear Regulatory Commissioni in accordance with 10 CFR Part 70.
Prior to the license expiration date of September 30, 1992 SPC submitted a renewai application for their licensed processes.
Because the renewal application was submitted 30 days prior to the expiration date, SPC has continued to operate according to the conditions of the previous license, under the provisions of 10 CFR 70.33(b).
On April 28, 1993, SPC requested NRC authorization to begin construction of a new facility to house an expanded dry conversion process at their Richland Manufacturing Facility, and notified the NRC that additional licensing actions will be needed as construction of the new facility progresses. SPC anticipated that the design of the new process would occupy the first year, and that most operating details would be specified near the and of that year. An application for a license amendment to authorize operation of the new dry conversion process would be submitted at that time. NRC, in a letter dated June 4,1993, authorized SPC to begin construction, recognizing that License SNN-1227 will need to be amended prior to the introduction of radioactive material into the new facility.
take the form of i
This dry conversion expansion amendment application will amendments to both the current license and to the renwal application.
As part of the license an(endment; application, and pursuant to 10 CFR Part j
and 70.23(a), the licensee must demonstrate that the equipment, 70.22(a) facilities, and procedures are adequnto to protect health and minimize danger to These must include equipment, facilities, and procedures to life or property.
prevent accidental criticality and to protect health and life in the case of criticality accidents.
They must also include equipment, facilities and procedures to. prevent fires from occurring and, if a fire does occur, to i
emergency procedures to suppress the fire and to mitigate its implement Technical assistance is required in this task to review the consequences.
applicant's nuclear criticality safety (NCS) and fire protection programs and prepare portions of the Safety Evaluation Report for the dry conversion amendment.
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2.0 Work Reouired This task is to provide licensing technical assistance to the NRC in its review of SPC's dry conversion amendment application, emergency plans, and other relevant material from the docket file, and prepare review comments and a Safety Evaluation Report (SER) of the amendment application.
The application will License Conditions, and Part II Safety contain two parts, Part I Demonstration.
Part I must contain the appilcant's comitments to provide adequate nuclear criticality safety and fire protection programs. Part II must provide sufficient supporting information in the form of process descriptions, analytical results, operational data, etc., to demonstrate that the comitments provided in Part I are adequate, in the context of the licensee's facility, to assure safety.
The scope of the reviews are principally based on 10 CFR Part 70.22(a) and 70.23(a), NRC Regulatory Guide 3.52 Standard Format and Content for the Health and Safety Sections of license Renewal Ano11 cations for Uranium Processino and Fuel Fabrication, and the firanch Technical Position on Fire Protection for Fuel Cycle Facilities, August 1992.
2.1 Staffino The principal investigators represent the technical expertise provided by the perforuing organization and provide technical continuity during the review process.
They should have professional credentials in the technical areas assigned to them that will qualify them as expert witnesses for testifying at public hearings. They should have experience in and a clear understanding of the depth of review generally required by the NRC and specifically required by a special nuclear material license amendment application for the disciplines they represent.
Reviews may be performed by the project manager, a principal investigator or any qualified support staff member.
In areas that can be accomplished by less experienced personnel, the principal investigators may act as overseers, providing quality control to task activities.
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The reviewers who perform the actual work shall provide detailed technical records of &! methods used to evaluate all aspects of their areas of responsibiliu.
Upon completion of an evaluation, the reviewer shall distill this record to suitable documentation for inclusion in NRC reports.
2.2 Sc.qn ~
The requirements of 10 CFR Part 70.22, 70.23, and 70.24, in conjunction with the following specific elements, will define the overall secpe of the nuclear criticality safety and fire protection program reviews.
The review of 'the amendment application sha 1 assure that it contains:
1)
Assignments of responsibility and authority for criticality safety and fire protection'of licensed activities, 2)
Comitments to staffing levels that are adequate to assure nuclear g
criticality safety and fire protection, il
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3)
Management oversight programs that are adequate to support criticality safety and fire protection. These will include:
Management review of procedure development and implementation.
Management support of operator and supervisor training, Management audits of operations to assure that criticality safety and fire protection procedures are being followed, Management oversight of nuclear criticality configuration control evaluations, Management control of safety reviews of process changes, flanagement oversight of incident response and root cause analyses.
4)
The following specific nuclear criticality safety elements:
Adequate methods to perform nuclear criticality calculations Validation studies for each calculational method, Adequate safety margins, Crittaa'dity alarms that meet industry standards, Acceptance criteria for nuclaar criticality centrols.
5)
The following elecents, which assure that the licenses has provided an adequate criticality safety analysis:
Demonstration that the licensee has full and accurate knowledge of facility configuration.
Demonstration that the licenses has considered the consequences of process upset conditions and has taken measures to ensure that the double contingency principle is i
fulfilled in all processes.
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Documentation of controls that are necessary to ensure that the double contingency principle is fulfilled for each contingency Programs to assure barriers remain adequate.
6)
Fire safety analyses considering:
4 Building construction, Ventilation systems,
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e, Process fire safety.
Fire detection and alarm systems, Fire suppression equipment, Fire protection water supply.
If the nuclear criticality safety or fire protection information provided by the applicant is incomplete or inadequate, the p0 shall prepare a request for additional information (RAI) to be submitted to the applicant through the NRC.
The PO may also need to meet with the appitcant to discuss the original or additional infomation.
The scope of this task does not include any participation in a public hearing nor any additional review effort that could evolve from such participation.
2.3 Schedule The dry conversion amendment application is expected to be submitted to NRC in early 1994, and its review can begin as soon as NRC receives it. The following schedule is based on estimates of time intervals to accomplish steps in the review process. However, the overall schedule is dependent on SPC's submittal of the dry conversion amendment request, their responses to NRC requests for information, and resolution of outstanding concerns.
Start-up Hesting at NRC 1 day Identify outstanding concerns and complete first RAI 3 weeks Complete second RAI 5 weeks Technical meetings with Licensee at NRC 2 days Complete Drtft SER 3 weeks Coordination meeting at NRC 1 day Complete Final SER 2 weaks h M TOTAL 14 weeks 3.0 Deliverables The following are the deliverables to be prepared under this task:
1)
First letter report identifying additional concerns and requesting additional infomation 2)
Second letter ryort requesting additional information
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Draft SER 4)
Final SER Draft and Final SERs shall be submitted as described NRC's Wordperfect word processing system.
accordance with the terms and conditions of the basic contract.
4.0 Travel It is expected that there will be two coordination meetings between the P0 and NRC staff throughout the duration of the subtasks.
If an area of review requires technical discussions between the P0 and the licensee, the PO may be requested to attend up to two meetings with the licensee at NRC's offices in Rockville, Maryland.
5,0 HRC Furnished Materials 70-1257 The NRC will furnish the P0 copies of documents docketed under Dockot No.
which are appropriate for this review.
6.0 Comoletion Date 30, 1995, The completion date for this technical assistance task is Janus.ry If sssuming that SPC submits the license amendment appitcation in January 1994.
required, a separate task order will be initiated to utilize selected reviews from this task in public hearings associatad with this licensing action.
7.0 Technien1 Direction Technical instructions may Mary Adams is designated the NMSS Technical Monitor.
Technical be issued from time to time during the dcration of this task.~ changes of ibch instructions shall not constitute new assignments of va-Directions nature as to justify an adjustment ir, cost or period of pmforci..co.
for changes in scope of work, cost or period of performance will be coordinated through the NHSS Project Manager and the NRC Contracting Officer.
8.0 Level of Effort The level of effort estimated for this task is 4.0 staff-mont'hs.
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