ML20059E723
| ML20059E723 | |
| 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 9311030319 | |
| Download: ML20059E723 (7) | |
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UNITED STATES 5
iE NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
,e SEP 2 91993 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. 23, ENTITLED " NUCLEAR CRITICALITY SAFETY AND FIRE PROTECTION PROGRAM REVIEW FOR LICENSE RENEWAL FOR SIEMENS POWER CORPORATION, RICHLAND, WA" UNDER CONTRACT NO. NRC-02-90-009 In accordance with the task order procedures of the subject
- contract, this letter definitizes the subject task order and confirms the verbal authorizations provided to you on September 15 and 21, 1993 by Ms. Amy Siller of my staff.
This effort shall be performed in accordance with the enclosed Statement of Work, and the Contractor's proposal dated August 26, 1993.
Task Order No.
23 shall be in effect from September 16, 1993 through January 30, 1995, with a cost ceiling of $101,579.00.
The amount of $15,000.00 is obligated at this time.
This amount is inclusive of the temporary ceiling of $5,000.00, $1,000.00 provided on September 15,1993 and $4,000.00 provided on September 21, 1993, that was verbally authorized pending definitization of this task order.
The amount of $93,106.00 represents the total estimated reimbursable costs and the amount of $8,473.00 represents the fixed fee.
4 The accounting data for the subject task order is as follows:
B&R No.:
35019401300 Job Code No.:
J-5025 Appropriation No.:
31X0200 BOC No.:
2542 Obligated Amount:
$15,000.00 NMSS Unique Identifier:
FFS# 5093RO46
.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.
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. Contract No. NRC-02-90-009 Task Order No. 23 Your contacts during the course of this task order are:
Technical Matters:
Mr. David Tiktinsky Project Officer (301) 504-2656 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 Commission,-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, k
Mary n Scott, Contracting Of ficer Contract Administration Branch No.1 Division of Contracts and Property Management Office of Administration 1
Enclosure:
As stated ACCEPTED:
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T TASK TITLE NUCLEAR CRITICALITY SAFETY AND FIRE PROTECTION PROGRAM REVIEW FOR LICENSE RENEWAL FOR SIEMENS POWER CORPORATION, RICHLAND, WA. LICENSE NO. SNH-70-1227 DOCKET NO. 70-1257 JOB CODE J5025 l
TASK NUMBER TASK ORDER 23 CONTRACT FUEL CYCLE LICENSING TECHNICAL ASSISTANCE, SAIC, NRC-02-90-009 B&R~ NUMBER 35019401300 NRC OFFICE NMSS PROJECT OFFICER DAVID TIKTINSKY TECHNICAL MONITOR MARY ADAMS TAC NUMBER L21656 1.0 Ba'ckaround Siemens Power Corporation (SPC) conducts licensed activities at its Richland, Washington, facility. SPC manufactures fuel assemblies for light water reactors using the ammonium diuranate (ADU) and dry conversion processes to convert enriched UF, to 00,.
Because SPC uses special nuclear material (SNM), as defined in 10 CFR 70.4, the operation is sub,1ect to licensing and regulation by the Nuclear Regulatory Commission, in accordance with 10 CFR Part 70.
Prior to the license expiration date of September 30, 1992, SPC submitted a renewal 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).
As part of the license renewal ap)1(cation, and pursuant to 10 CFR Part 70.22(a) and 70.23(a), the licensee must c emonstrate that the equipment, faci'lities, and pr)cedures are adequate to protect health and minimize danger to life or These must include equipment, facilities, and procedures to prevent poperty.
accidental criticality and to protect health and life in the case of criticality accidents.
They must also ir.clude equipment, facilities and procedures to prevent fires from occurring and, if a fire does occur, to implement emergency Technigal procedures to suppress the fire and to mitigate its consequences.
assistance is required in this task to review the applicant's nuclear criticality safety (NCS) and fire protection programs and prepara portions of the Safety Evaluation Report for the renewal application.
2.0 Work Recuired d
This task is to provide licensing technical assistance to the NRC in its review of SPC's license renewal application, emergency plans, and other relevant from the docket file, and prepare review comments and a Safety material Evaluation Report (SER) of the license renewal application.
The application Safety contains two. parts, Part !- ticense Conditions, and Part II Demonstration.,, Part I must contain the applicant's comitments to provide Part II must adequate nuclear criticality safety and fire protection programs.
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 1
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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 Healtt and_ Safety Sections of license Renewal Ano11 cations for Uranium Processino anc Fuel Fabrication, and the Branch' Technical Position on Fire Protection for Fuel Cycle Facilities, August 1992.
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2.1 Staffino The principal investigators represent the technical expertise provided by the i
performing 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 renewh1 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.
The reviewers who perform the actual work shall provide detailed technical records of the methods used to evaluate all aspects of their areas of responsibility.
Upon completion of an evaluation, the reviewer shall distill this record to suitable documentation for inclusion in NRC reports.
2.2 Scoce The requirements of 10 CFR Part 70.22, 70.23, and 70.24, in conjunction with the following specific elements, will define the overall scope of the nuclear criticality safety and fire protection program reviews.
The review of the renewal application shall assure that it contains:
1)-
Assignments of responsibility and authority for criticality safety and fire protection of licensed activities, 2)
Conclitments to staffing levels that are adequate to assure nuclear criticality safety and fire protection, 3)
Hanagement 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, 2
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,4-i Management oversight of nuclear criticality configuration control evaluations.
Management control of safety reviews of process changes, Management 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, Criticality alarms that meet industry standards, Acceptance criteria for nuclear criticality controls.
5)
The following elements, which assure that the licensee has provided an adequate criticality safety analysis:
Demonstration that the licensee has full and accurate knowledge of facility configuration.
Demonstration that the licensee has considered the consequences of process upset conditions and has taken measures to ensure that the double contingency principle is fulfilled in all processes.
Documentation of controls that are necessary to ensure that the doubic contingency principle is fulfilled for each contingency Programs to assure barriers remain adequate.
6)
Fire safety analyses considering:
e Building construction, Ventilation systems, Process fire safety, a
Fire detection and alarm systests, Fire suppression equipment,
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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 toay also need to meet with the applicant to discuss the original or additional information.
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 As indicated in the background section above, the license renewal application was received in August 1992, and its review can begin immediately.
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 responses to NRC requests for information, and resolution of outstanding concerns.
1 day Start-up Meeting at NRC 8 weks Identify outstanding concerns and complete first RAI 2 days Site visit 6 weeks Complete second RAI Technical meetings with Licensee at NRC 2 days 6 weeks Complete Draft SER 1 day Coordination meeting at NRC 2 weeks Complete Final SER 23 weeks TOTAL 3.0 Deliverables The following are the deliverables to be prepared under this task:
P 1)
First letter report identifying additional concerns and requesting additional information 2)
Second letter report requesting additional information 3)
Draft SER 4)
Final SER 4
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Draft and Final SERs shall be submitted as described in NRC-02-90-009.
In addition, the Final SER shall be provided in diskette form compatible with HRC's Wordperfect word processing system.
Monthly reports shall be submitted in accordance with the terms and conditions of the basic contract.
4.0 Travel It is expected that there will be one start-up and one coordination meeting between the P0 and NRC staff throughout the duration of this task.
Selected reviewers (assume 4 people) will make a site visit after completion of the first RAI and before preparation of the Draft SER.
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 NRC Furnished Materials The NRC will furnish the PO copies of documents docketed under Docket No. 70-1257 which are appropriate for this review.
1 6.0 Comoletion Date The completion date for this technical assistance task is January 30, 1995.
If required, a separate task order will be initiated to utilize selected reviews from this task in public hearings associated with this licensing action.
i 7.0 Technical Direction Mary Adams is designated the HMSS Technical Monitor. Technical instructions may be issued from time to time during the duration of this task.
Technica) instructions shall not constitute new assignments of work or changes of such nature as to justify an adjustment in cost or period of performance. Directions for changes in scope of work, cost or period of perfomance will be coordinated through the HMSS Project Manager and the NRC Contracting Officer.
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8.0 Level of Effort The level of effort estimated for this task is 6.0 staff-months.
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