ML20207Q143
| ML20207Q143 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook |
| Issue date: | 01/12/1987 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207Q135 | List: |
| References | |
| R-093-A-003, R-93-A-3, NUDOCS 8701230108 | |
| Download: ML20207Q143 (19) | |
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k UMTED STATES NUCLEAR REGULATORY COMMISSION E WASHINGTON, D. C. 20006
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l NATIONAL AERONAUTICS AND SPACE ADMINISTRATION DOCKET NO. 50-185 l
AMENDMENT TO FACILITY LICENSE Amendment No. 3 l
! License No. R-93
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment to Facility License No. R-93,(the filed by)the licensee National
, dated July 26, Aeronautics 1985, compliesand with Space the standard.= Administration and requirements of the Atomic Energy Act of 1954, as amended (the Act),
! and the Commission's regulations as set forth in 10 CFR Chapter It B. The facility will be maintained in conformity with the amended license, the provisions of the Act, and the rulus and regulations of the Comission; C. There is reasonable assurance: (1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i conducted in compliance with the Comission's regulationst
! D. TheNationalAeronauticsandSpaceAdministration(NASA)istechnically l
and financially qualified to engage in the activities authorized by
' the amended license in accordance with the rules and regulations of the Comission; E. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the publict l
F. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have l
been satisfied.
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- 2. Facility License No. R-93 is hereby amended in its entirety tg read:
A. This license applies to the heterogeneous light water-cooled and -moderated research and testing reactor (herein referred to as the " reactor") owned by the National Aeronautics and Space Administration, an independent agency of the United States
- Government, and located at the NASA Plum Brook Reactor Facility
! near Sandusky, Ohio. The reactor is described in the application .
l dated March 15, 1961, and amendments thereto. '
- 3. Subject to the conditions and requirements incorporated herein, the Nuclear Regulatory Commission hereby licenses NASA: ,
(1) Pursuant to Section 104c of the Act and 10 CFR Chapter I, Part 50,
" Licensing of Production and Utilization Facilities", to possess.
but not operate, the reactor as a utilization facility; i (2) Pursuant to the Act and Title 10 CFR Chapter I, Part 30, " Licensing of Byproduct Material," to possess, but not to separate, such !
byproduct material as may have been produced by operation of the i l
reactor.
- 4. This license shall be deemed to contain and be subject to the conditions specified in Part 20. Section 30.34 of Part 30. Sections 50.54 and 50.59 I
of Part 50,10 CFR Chapter I, and to all applicable provisions of the Act and to the rules, regulations, and orders of the Comission now or hereafter in effect and to the additional conditions specified below: :
(1) NASA shall not reactivate the facility without prior approval of the Commission; and :
(2) NASA shall not dismantle or dispose of the facility without prior approval of the Commission.
- 5. Technical Specifications ;
! The Technical Specifications contained in Appendix A to this license are hereby incorporated in this license and changes therein may be made only '
when authorized by the Commission in accordance with the provisions of l
10 CFR Part 50, Section 50.59.
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. 6. This license amendment is effective as of its date of issuance and shall expire ten years from the date of issuance. '
FOR THE NUCLEAR REGULATORY COMISSION c:a ])r N.
Frank fra a Director Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Attachment:
Appendix A Technical Specifications Changes Date of Issuance: January 12, 1987 4
ATTACHMENT TO LICENSE AMENDMENT NO. 3 .
FACILITY OPERATING LICENSE NO. R-93 ,
DOCKET NO. 50-185 Revised Appendix A Technical Specifications in their entirety.
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., . . l APPENDIX A TECHNICAL SPECIFICATIONS l FOR THE
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l' M0CK-UP-REACTOR [MUR]
J NATIONAL AERONAUTICS AND SPACE ADMINISTRATION h
DOCKET N0.'50-185 LICENSE N0. R-93 January 1987 t
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TABLE OF CONTENTS Page
- 1. Introduction ------------------------------------------------- 1 1.1 Scope 1.2 Definitions
- 2. _ Requirements ------------------------------------------------
3 2.1 Access 2.2 Canal H 2.3 Control Area 2.4 Designated Storage Area for the MUR 2.5 Access to Radiological Control Zones 2.6 Minimum Procedures 2.7 Inspection, Tests and Surveys
- 3. Administrative Controls ------------------------------------- 7 3.1 Organization !
3.2 Procedures 3.3 Reports 3.4 Records
- 4. References ----------'---------------------------------------- 12 !
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. 1. Introduction i 1.1 Scope These Technical Specifications apply to portions of the facility which contain a nonoperable research reactor, its support facil,ities, and its inventory of radioactive material generated as a result of {
previous operations. The Mock-Up Reactor (MUR) was shut down in 1973 after approximately 200 kilowatt-days of operation. The MUR contains no fuel and no special nuclear material. Therefore, these Technical Specifications apply only to systems, components, or areas which are radioactive, contaminated, or are needed to maintain a protected safe storage condition.
1.2 Definitions 1.2.1 General i
Authorized Entry - Entry by people authorized by management with a legitimate need to enter the PBRF who have knowledge of the I conditions, the hazards, and procedures of the facility or who are accompanied by someone with this knowledge.
Kept Dry - The condition of an ' area which is .normally dry, or drained and mopped dry as socn as practical when becoming inadvertently wet.
Nonoperable - The condition of a component or system which has been intentionally disabled to prevent it from performing its intended function.
_ Protected Safe Storace - The custodial state of undefined duration characterized by physical and procedural access control and periodic monitoring, maintenance and inspection.
Shall - The word "shall" is used to denote a requirement.
. Surveillance Frequency - Unless otherwise stated in these specifications, periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified .
surveillance intervals. In case where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval. Allowable surveillance intervals, as defined in ANSI /ANS 15.1 (1982) shall not exceed the following:
- 1. Annual (interval not to exceed 15 months).
- 2. Semiannual (interval not to exceed seven and one-half months).
- 3. Quarterly (interval not to exceed four months).
- 4. Monthly (interval not to exceed.six weeks).
1.2.2 Radioactive Materials Contaminated Materials - Irradiated or nonirradiated items containing particles of radioactive materials on their surfaces.
Radioactive Material - Items which have been activated as a result of previous reactor operations. These items may also be contaminated, t
1.2.3 Radiological Control Zones Magenta Zone - For purposes of contamination control, levels will be as low as reasonably achievable but can exceed the magenta-yellow limit. For purposes of direct radiation control, a magenta zone is any area which could expose major portions of the body to direct radiation levels of 100 mrem /hr or more.
Magenta-Yellow Zone - For purposes of contamination control, levels will not exceed 100 dpm alpha /100 cmr and 10,000 dpm beta-gammafiOO cmr transferable; 2500 dpm alpha /100 cmr and 8,000 dpm beta-gamma t
fixed. The magenta-yellow zone, for purposes of direct radiation control, is any area which could expose major portions of the body to direct radiation levels from 2.5 to less than 100 mrem /hr. -
White Zone - Is an area with contamination levels below 2,0 dpm alpha /
2 2 100 cm and 1,000 dpm beta-gamma /10 cm transferable; 500 dpm alpha and 1500 dpm beta-gamma fixed. In this area, direct radiation levels to major portions of the body shall be less than 2.5 mrem /hr and no protective clothing is required.
- 2. Requirements 2.1 Access Applicability - This specification applies to location and protection of the facility.
Obiective - The objective is to prevent unauthorized entry and provide protected safe storage.
Specification:
- a. The Plum Brook Reactor Facility (PBRF) access shall be controlled through two fences. The outer fence surrounds the Plum BrookStation(PBS). An inner fence surrounds the PBRF within the station,
- b. The MUR shall be located in Canal H (a reinforced concrete pool 21 x 21 x 25 feet deep). Canal H is located outside the containment vessel for the Plum Brook Test Reactor in the southeast corner of the Reactor Building, v Bases:
Specification 2.1 a. provides two physical barriers of security before gaining access to the locked buildings of the PBRF. The MUR is located inside the locked Reactor Building. Specification 2.1 b.
provides a protected safe storage area.
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. 2.2 Canal H Applicability - The specification applies to protected safe storage for the Mock-Up Reactor located in Canal H. .
Objective - The ob.iective is to provide conditions for protected safe storage of the MUR.
Specification:
- a. Canal H shall be cleaned, drained, and kept dry. The Canal H drain shall be covered and the drain valve locked shut.
- b. The Canal H recirculation system shall be cleaned, drained and valves shall locked shut.
- c. The deionized water service supply to Canal H shall be isolated and valves locked shut.
- d. MUR components may be stored in the fuel storage basket, which shall be locked.
Bases:
Specification 2.2 a. provides a clean, dry canal for the MUR.
i Specifications 2.2 b. and c. prevent the entry of process water.-
Specification 2.2 d. provides additional locked storage.
2.3 Control Areas
~Abplicability - This specification applies to protected safe storage for the MUR.
Objective - The objective is to prevent unauthorized entry to the MUR.
Specification:
Personnel access to both the MUR Control Room and Canal H shall be controlled by fence and locked doors to prevent unauthorized entry.
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This specification controls access to the MUR.
2.4 Designated Storage Area for the MUR Applicability - This specification applies to the radioactive material storage at the MUR.
Objective - The objective is to identify the area for radiological control.
Specification:
Radioactive material associated with the MUR shall be stored in the bottom of Canal H. Canal H shall be properly posted.
Bases:
These specifications define the MUR radioactive material storage area and controls.
2.5 Access to Radiological Control Zones Applicability - This specification applies to the radiological control zone at the MUR.
Objective --This objective,is to provide access controls for this zone.
Specification:
Access to magenta-yellow zones shall require health physics monitoring and control and use of personnel dosimetry.
Bases:
This specification defines the requirement.
2.6 Procedures Applicability - This specification applies to procedures that
. help administer the protected safe storage condition.
Objective - The objective is to list the important procedures.
Specification: .
Detailed procedures shall be in effect covering the following areas:
- a. Entrance to the Canal H area,
- b. Canal H area radiological monitoring.
- c. Emergencies such as fire, floods, and tornadoes.
- d. Facility Changes.
These procedures shall be approved by the PBRF Safety Committee.
Bases:
This specification ensures that protected safe storage procedures are provided.
2.7 Inspection and Surveys Applicability - This specification applies to selected inspections, and surveys used to preserve a protected safe storage condition.
Objective - The objective is to provide a minimum inspection and survey program for continued protected safe storage.
Specification:
The following inspections and surveys shall be performed:
Frequency
- a. PBS Fence Integrity Inspection Quarterly
- b. PBRF Fence Integrity Inspection Monthly
- c. Reactor Building Locks Inspection Monthly
- d. Canal H Area General Condition Inspection Monthly
- e. Canal H Area Radiological Survey Quarterly
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. The P8RF Engineer shall review the results of the inspections and surveys and assure necessary corrective actions are taken to preserve the protected safe storage condition. .
Bases:
This specification ensures that protected safe storage inspections and surveys are provided.
- 3. Administrative Controls I
3.1 Oroanization The MUR is owned by the National Aeronautics and Space Administration ;
(NASA), which shall be responsible for maintaining the protected safe storage condition as required by these Technical Specifications.
NASA shall provide whatever resources are required to maintain the MUR in a condition that poses no hazard to the general public or to the environment. Figure 1 charts the generic organization.
3.1.1 Level 1 Directorate The Director shall be responsible for assuring compliance with the reactor facility's license and providing regulatory reports and correspondence. He shall have overall responsibility for the protected safe storage of the MUR.
3.1.2 Health Safety and Security Division This Division shall provide the resources to maintain the MUR in protected safe storage.
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.,_ G~ENERIC ORCANIZATION CHART NASA lek'IS RESEARCH ,
CENTER DTPPPTOR EXECUTIVE LEVEL 1 SAFETY DIRECTORATE BOARD DIRECTOR
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INTERNAL HEALTH SAFETY AND AUDIT SECURITY DIV.
PBRF LEVEL 2 RADIATION SAFETY P B STATION SAFETY CO.WITTEE MANAGEMENT OFFICER OFFICE _
PLANT -SECURITY -
LEVEL 3 HEALTH PHYSICS AND PBRF ENGINEER AND INSPECTION MAINTENANCE
- Contract) _
(Contract)
RESPONSIBLE FOR LEVEL 1 - Compliance LEVEL 2 - Survellance and Maintenance LEVEL 3 - Day to Day Oversite FIGURE 1 h
, 3.1.3 Internal Audit An annual internal audit shall be performed at the PBRF and will include the MUR. The audit shall be performed by NASA personnel not directly associated with the facility who have nuclear experience.
I Special attention shall be given to compliance with procedures, the NRC licenses, regulations and record keeping. The auditor shall submit a report on each audit for the Executive Safety Board.
Reported discrepancies shall be resolved by the PBRF Engineer. The PBRF Safety Committee shall review and insure the proper disposition of each discrepancy.
3.1.4 RadiationSafetyOfficer(RS0)
A RSO shall be appainted to organize, administer, and direct the radiological control and monitoring program, as required by these Technical Specifications. The RSO shall assure the program is adequately performed. The RSO shall be reponsible for providing on-site advice, technical assistance and review in all areas related to radiological safety. The RSO shall be a person specifically trained in the radiation health sciences and appropriately.
experienced in applying this knowledge to the management of the radiation protection program. The RSO shall have a bachelor's degree in physical science or biological science with a minimum of two years of applied health physics experience in a program with radiation safety considerations similar to those associated with the PBRF/MUR program.
1 3.1.5 ExecutiveSafetyBoard(ESB)
The ESB serves as a Lewis Research Center safety policy and decision making board, and is responsible to the Center Director for the overall direction of the Lewis Safety Program. The ESB establishes a system of safety committees to conduct detailed third party reviews of specified Center operation.
3.1.6 PBRF Safety Committee (PSC)
The PSC was chartered by the ESB to conduct safety reviews of all matters with safety implications relative to maintaining protected safe storage of the Plum Brook Reactor Facility and the MUR. The purpose of the reviews is to assure that operations, written procedures and future plans comply with NRC licenses and regulations, do not involve unreviewed safety questions, and provide protection to the workers, the facility, and the environment. A prime consideration in the PSC activities is to ensure that all public and employee radiation exposures are maintained as low as reasonably achievable. Items of review shall include routine operation, proposed changes, new and revised procedures, facility changes in Technical Specifications, and audit reports.
The PSC shall consist of a minimum of four persons and shall meet at least twice each year. The PSC shall have at least one member with nuclear background and one other member familiar with the conditions of the facility. In addition, the Radiation Safety Officer shall also be a member. A quorum cf the PSC shall be two-thirds of the members but not less than three members, whichever is greater. In specific instances, the PSC may designate the Chairman to act in its
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stead, and the Chairman will report his actions to the committee at its next regular meeting. Meeting minutes will be distributed to all members and be retained on file. -
3.1.7 Plumb Brook Station Management Office (PBMO)
The Chief, PBM0, shall be knowledgeable of the station activities that may affect the protected safe storage condition at the MUR. The Chief, PBM0, is responsible for administering a program to ensure that proper operation, control and safeguards are maintained for the station. This includes a key control system. Keys for the MUR are authorized by the Chief, PBM0, on a "need-to-have" basis to persons having knowledge of the conditions, the hazards and procedures of the MUR. Implementation is by an authorization letter issued to the key distributor. The P8M0 shall provide for the services of Plant Security, Inspection, Health Physics, and Maintenance as necessary at the MUR.
3.1.8 PBRFEngineer(ReactorManager)
The PBRF Engineer shall-be appointed'to manage' and assure the protected safe storage condition is maintained in accordance with these Technical Specifications. The PBRF Engineer shall have the following qualifications:
- a. A bachelor's degree in engineering or a related physical science,
- b. Be knowledgeable in radiation hazards and radiation protection.
- c. Have successfully completed the training class for familiariza-tion with the duties of the Reactor Manager.
The PBRF Engineer shall assure protected safe storage conditions are maintained and necessary inspections are performed with records to support the inspection. He shall train and/or qualify personnel to maintain protected safe storage conditions. He shall rev,few maintenance procedures and results to assure butidings and grounds remain in an acceptable quality condition. The PBRF Engineer shall assure unusual occurrence reports, facility changes, and new or revised procedures are prepared approved and issued. He shall approve all PBRF and MUR facility changes, and new or revised procedures.
He shall approve all major material or equipment transfer in and out of the PBRF. The PBRF Engineer shall prepare license change requests for submission to the flRC.
3.2 Procedures All new or revised procedures will be reviewed by the PBRF Safety Committee and approved by signature of the PBRF Engineer and the Chairman of the PSC.
3.3 Reports Reports required under license and applicable regulations shall be provided. In addition, the MUR shall be included in the annual report for the PBRF, 3.4 Records NASA shall keep records required by applicable licenses and regulations including the following:
- a. Records of radioactivity levels in the Canal H areas.
- b. Equipment maintenance records (EMRs) of nonroutine maintenance l
i operations involving substitution or replacement of vital components.
- c. The end condition statements and the procedures used to place the facility in the shutdown condition. These procedures shall reflect the condition of the facility in the Possession-Only status.
- d. Up-to-date facility drawings.
- 4. References (1) Code of Federal Regulations Title 10. " ENERGY", Government Printing Office, Washington, D.C.
(2) "American National Standard for the Development of Technical Specifications for Research Reactors," ANSI /ANS 15.1-1982 American Nuclear Society, LaGrange Park, Illinois.
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