ML20215L448
| ML20215L448 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook |
| Issue date: | 10/20/1986 |
| From: | NATIONAL AERONAUTICS & SPACE ADMINISTRATION |
| To: | |
| Shared Package | |
| ML20215L431 | List: |
| References | |
| NUDOCS 8610290040 | |
| Download: ML20215L448 (28) | |
Text
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S APPENDIX A TECHNICAL SPECIFICATIONS LICENSE N0. TR-3 NATIONAL AERONAUTICS AND SPACE ADMINISTRATION PLUM BROOK STATION SANDUSKY, OHIO DOCKET N0. 50-30 8610290040 861020 PDR ADOCK 05000030 P PDR
1 TABLE OF CONTENTS PAGE
- 1. Introduction - - - - - - - - - - - - - - - - - - - - - - - 1 ,
1.1 Scope 1.2 Application 1.3 Definitions
- 2. Requirements - - - - - - - - - - - - - - - - - - - - - - - 4 2.1 Control of Access to PBRF Site 2.2 Reactor Tank (RT) 2.3 Containment Vessel (CV) 2.4 Primary Cooling Water System and Primary Pump House 2.5 Alarm System 2.6 Quadrant and Canal System 2.7 Radiochemistry Laboratory 2.8 Hot Drains 2.9 Hot Laboratory 2.10 Hot Pipe Tunnel 2.11 Waste Handling Building 2.12 Emergency Retention Basin 2.13 Hot Retention Area 2.14 Contaminated Air System
- 3. Surveillance - - - - - - - - - - - - - - - - - - - - - - - 16 3.1 Designated Storage Areas Within PBRF 3.2 Access to Radiological Control Zones 3.3 Alarm Response 3.4 Facility and Environmental Monitoring 3.5 Minimum Procedures 3.6 Inspection, Tests and Surveys
- 4. Admini stra tive Control s - - - - - - - - - - - - - - - - - 21 4.1 Organization 4.2 Procedures l 4.3 Reports l 4.4 Records
- 5. References - - - - - - - - - - - - - - - - - - - - - - - - 26 ,
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APPENDIX A PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS LICENSE N0. TR-3 ,
NATIONAL AERONAUTICS AND SPACE ADMINISTRATION DOCKET N0. 50-30
- 1. Introduction Where applicable, these technical specifications follow the format of the American National Standard ANSI /ANS-15.1-1982.
1.1 Scope These technical specifications apply to all portions of the Plum Brook Reactor Facility (DBRF), with the exception of the Mock-up Reactor (MUR) which is separately licensed. The PBRF contains a nonoperable test reactor, its support facilities, and its inventory of radioactive materials generated as a result of previous operations. The reactor was shutdown in 1973 after 98,000 megawatt days of operation.
The radioactive inventory, with the exception of distributed radioactive material existing as contamination within process systems and laboratories, is stored in four locations. These are located inside of the Containment Vessel, in the Reactor Building Canal G, in the Hot Laboratory, and in the Waste Handling Building. The PBRF contains no fuel and no special nuclear material.
1.2 Application These technical specifications govern the condition of the National Aeronautics and Space Administration's PBRF in the possess-but-not-
operate status. The PBRF is described in the Design Manual and Hazard Analysis submitted for the original PBRF license and now contained in Docket No. 50-30. The PBRF systems which are radioactive, contaminated, or required to maintain a protected safe storage condition, are covered in these technical specifications. These systems are listed in the table of contents for these technical specifications under the Requirements Section (Items 2.2 thru 2.14).
1.3 Definitions 1.3.1 General Authorized Entry - Entry to the PBRF which is sanctioned by the PBRF Engineer or his designee, for those persons having a legitimate need to enter and who have knowledge o' th conditions, hazards, and procedures at the facility, or who are accompanied by an authorized person with this knowledge.
Keot Dry - The condition of an area which is normally dry, or drained and mopped dry as soon as practical after 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 Storage - The custodial state of undefined duration characterized by physical and procedural access control and periodic monitoring, maintenance and in;pection.
Shall - The word "shall" is used to denote a requirement.
Clean - The condition of an area wherein contamination levels do not 2
exceed 20 d/m/100 cm2 alpha and 1000 d/m/100 cm beta-gamma transferable; 500 d/m alpha and 1500 c/m beta-gamma fixed.
o 1.3.2 Radioactive Materials f
I Contaminated Material - Irradiated or non-irradiated items containing
-J surface particles of radioactive material.
Radioactive Material - Neutron activated materials resulting from i
previous reactor operations. These items may also be contaminated.
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- 1.3.3 Radiological Control Zones
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Magenta Zone - For purposes of contamination control, levels will be as low as reasonably achievable but can exceed the magenta-yellow I
limit. For purposes of direct radiation control, a magenta zone is any area in which major portions of the body could be exposed to
- direct radiation levels of 100 mrem /hr or more.
Magenta-Yellow Zone - For purposes of contamination control, levels
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2 will not exceed 100 dpm alpha /100 cm and 10,000 dpm beta-gamma /100 f
l cm2 transferable; 2500 dpm alpha and 8,000 dpm beta-gamma fixed.
For purposes of direct radiation control, a magenta-yellow zone is any area in which major portions of the body could be exposed to direct radiation levels from 2.5 to less than 100 mrem /hr.
White Zone - Is an area with contamination levels below 20 dpm alpha j
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/100 cm2 and 1,000 dpm beta-gamma /100 cm transferable; 500 dpm alpha and 1500 dpm beta-gamma fixed. In this area, direct radiation
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levels to major portions of the body shall be less than 2.5 mrem /hr and no protective clothing is required.
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- 2. Requirements j 2.1 Control of Access To PBRF Site ,
Applicability - This specification applies to protection of the PBRF Site by control of access.
Objective - The objective is to prevent unauthorized entry.
Specification:
Access to the PBRF shall be controlled by means of two fences with locked gates. The outer fence surrounds the Plum Brook Station; the inner fence surrounds the PBRF. In addition, access to all buildings within the PBRF is controlled by means of locked entrance doors.
Bases:
Access to the PBRF is limited by two physical barriers (fences) each with locked gates. Access to keys for the gates in the outer fence surrounding the Plum Brook Station is controlled by the Plum Brook Station Management Office. Access to keys for the gates in the inner fence surrounding the PBRF is controlled by the PBRF Engineer and is limited to authorized personnel.
i 2.2 Reactor Tank (RT)
Applicability - This specification applies to the contaminated and radioactive material which makes up the reactor tank, and the contents within.
Objective - The objective is to safely store the irradiated materials and control radiation levels.
Specification:
a) The reactor tank, which is surrounded by a thick concrete biological shield, shall be drained and maintained in a dry
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condition. All tank nozzles and penetrations which could stream radiation shall have shields fixed in place.
b) The.three shrapnel shields (20 tons each) shall be positioned above the reactor tank.
c) Radiation levels at accessible reactor tank surfaces shall be less than 100 mrem /hr.
d) All openings shall be closed, except those openings required for a dry gas purge through an absolute filter to the stack.
i e) The sub-pile room door shall be closed and locked except for authorized entry.
Bases:
! High radiation levels inside the RT, and streaming through RT penetrations, are contained by the shielding methods described.
a) Twelve years of safe protected storage experience at PBRF has demonstrated that the shielding described in this section is adequate to permit classifying of all accessible quadrant areas around the reactor tank as magenta-yellow zones.
b) The reactor tank top is covered with three shrapnel shields for i
radiation shielding.
c) Additional shields are tack welded in place where needed to reduce radiation levels to below 100 mrem /hr in all accessible areas.
d) In addition, during the past twelve years of protected safe storage, airborne contamination has never exceeded MPC in unrestricted areas. Therefore, additional protection against airborne radioactivity is not required outside the tank.
e) Access to the sub-pile room is per approved written procedures.
2.3 Containment Vessel (CV) s Applicability - This specification applies to protected safe storage of the reactor and contents inside the CV.
Objective - The objective is to control personnel access to the CV and to prevent entry of water which could be a vehicle to spread contaminated material.
Specification:
a) The CV shall be provided with two primary openings designed to breathe the CV to atmosphere through absolute filters.
b) One of the two existing personnel doors shall be used for controlled personnel access. This door shall be locked to prevent
) unauthorized entry. The other door shall be operable only from the inside as an emergency exit.
c) The truck door shall be closed and dogged in place except during temporary controlled periods to accommodate transfer of equipment which is too large to fit through the personnel door, d) All original liquid-containing process lines penetrating the CV i
shall be drained and blank flanged or capped to prevent liquid from entering the CV. The blank flange or cap shall be secured against
! unauthorized opening. All other process penetrations shall be closed with locked or welded valves, or capped to prevent unauthorized j opening from the outside.
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Bases:
Specification 2.3(a) provides authorized personnel an inhabitable atmosphere in the CV eliminating the need for air packs or other respiratory equipment. Specification 2.3(b) and(c) limits entry to authorized personnel and specification 2.3(d) eliminates all outside sources of water entry which could spread contamination from the CV.
The only other source of water is from moisture condensation. A dry, protected, safe storage, with access control, is provided by these specifications.
2.4 Primary Cooling Water System and Primary Pump House (PPH)
Applicability - This specification applies to protection and safe storage of the primary cooling water system outside the CV. This includes piping to the primary pump house, primary pumps, heat i
exchanger and deionizers.
. Objective - The objective is to isolate the RT from the PPH, control 1 access and prevent spread of contaminated materials.
Specification:
l a) The primary cooling water supply and return headers shall be blank-flanged to isolate the reactor tank from the Primary Pump House.
Lines between the blank flanges and the Primary Pump House (PPH) shall be drained.
b) The PPH roof hatch plugs shall be in place. The roof hatch plugs and personnel doors of the PPH shall be locked except for authorized l entry.
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Bases:
These specifications provide a dry primary cooling water system outside the CV and prevent unauthorized access to the system in the PPH.
2.5 Alarm System Applicability - This specification applies to the alarms listed below as a, b, c.
j Objective - The objective is to receive a warning of off-normal conditions.
i Specification:
- An alarm system shall be operating to provide local alarms at the PBRF and a summary alarm at the Plum Brook Station Communication i
Center. The individual alarms at the PBRF include:
! a) CV Entry b) Loss of Power c) Sump Alarms i The alarm response is provided in Section 3.3.
Bases:
This specification provides a warning system to alert the communication center of an off-normal condition. These off-normal alarms are as follows:
a) Entry Alarm will indicate entry to the CV; b) Loss of Power Alarm will indicate a loss of electrical power at the PBRF; c) Sump Alarm will indicate a high level in one of the PBRF cold sump areas.
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l 2.6 Quadrant and Canal System 1 Applicability - This specification applies to the Quadrant and Canal
- t System for protected safe storage, except for Canal H which is
! covered under the R93 license. .
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- Objective - The objective is to provide a safe storage area for contaminated and radioactive materials.
! Specification:
- a) The quadrants and canals are clean, drained and shall be kept dry.
b) The deionizer system was flushed and drained and shall be l isolated by valves and flanges. The deionizer shall not contain ion i
i exchange material.
f c) The quadrants and canals within the CV are Magenta-Yellow Zones.
j Small localized fenced areas within the quadrants are Magenta Zones i because of the field from the reactor core.
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- Bases
i' These specifications provide for a secure and dry Quadrant and Canal 1
i System through the following:
a) The Quadrant and Canal systems are visually inspected for any
+ accumulation of water under written approved procedures; b) The Quadrant and Canal systems are surrounded by fence and locked gates to prevent unauthorized access; c) Since there is no water in the Quadrant and Canal systems, there is no longer a need for a purification system.
O 2.7 Radiochemistry Laboratory Applicability - This specification applies to the chemical fume hoods of the Radiochemistry Laboratory.
Objective - The objective is to prevent unauthorized personnel access and uncontrolled entrance of water to these areas.
Specification:
The chemical fume hood doors shall be welded closed to prevent i opening and hoods shall be kept dry. The outside of the hoods are not contaminated.
Bases:
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Contamination spread is minimized by access prevention. Periodic
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inspection and surface smears assure control of contamination.
2.8 Hot Drain System Applicability - This specification applies to the protected safe storage of the Hot Drain System throughout the PBRF.
Objective - The objective is to prevent spread of radioactive materials remaining in the hot drains.
I Specification:
The Hot Drain System shall remain " nonoperable" as defined in Section i 1.3.1. ,
a) All accessible (white zone) external surfaces shall be clean.
b) All hot drains, sumps, and lines were flushed, and a reasonable effort to eliminate residual contamination per NRC Regulatory Guide 1.86 was made in 1973 when the PBRF was placed in a standby condition.
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c) All floor drains and other flow paths supplying a hot sump shall f be plugged or sealed.
d) The hot drain pump motors shall be de-energized from the power bus at the motor control centers.
Bases:
These specifications provide for a static, relatively clean, Hot Drain System through the following:
a) Decontamination of external surfaces will remove loose radioactive material; b) Flushing contaminated lines will remove all easily removable
- radioactive material, leaving the remainder immobile; c) Plugging access to the hot drain system prevents inadvertent entry of water into the system;
- d) Draining the hot drains and maintaining them dry eliminates the need for the hot drain pumping system.
2.9 Hot Laboratory and Hot Dry Storage
! Applicability - These specifications apply to protected safe storage in the Hot Laboratory including the Hot Dry Storage.
Objective - The objective is to prevent unauthorized entry to contaminated or radioactive material storage areas.
Specification:
Hot cell doors and the 80 ton access door to the Hot Dry Storage area shall be locked. Access doors to the Hot Laboratory shall be locked.
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Bases:
Authorized access with procedural control prevents personnel exposure and spread of contamination.
2.10 Hot Pipe Tunnel (HPT)
Applicability - This specification applies to the protected safe storage of the Hot Pipe Tunnel.
Objective - The objective is to prevent personnel access and entrance of water to this area.
Specification:
a) The Hot Pipe Tunnel entrances at each end of the tunnel shall be padlocked closed.
b) The tunnel shall be kept dry.
Bases:
These specifications provide for control of the Hot Pipe Tunnel through the following:
a) Authorized access with written procedural control prevents personnel exposure; b) Inspection of the tunnel per authorized written procedures assures that it is kept dry.
2.11 Waste Handling Building (WHB)
Applicability - This specification applies to protected safe storage of the Waste Handling Building.
Objective - The objective is to prevent unauthorized entry to the Waste Handling Building.
Specification:
a) Access doors leading to the Waste Handling Building shall be locked closed.
b) Access doors to the evaporator room and waste packaging room shall be locked closed.
Bases:
I These specifications provide for control of radioactive materials and contamination in the Waste Handling Building through the following:
a) Authorized access through written procedural control prevents personnel exposures. This applies to all areas described in specification 2.11 section a and b.
2.12 Emergency Retention Basin (ERB)
Applicability - This specification applies to the protected safe storage of the ERB.
Objective - The objective is to minimize the accumulation of water in r
the ERB and to prevent the release of a potential source of contaminated liquid to the environment.
Specification:
a) The ERB drain line shall remain open to prevent rain water accumulation in the basin.
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b) Any accumulated water shall be sampled quarterly to verify that limits of 10 CFR Part 20 for an unrestricted area are not exceeded.
c) The pumps shall be removed from the supply line.
Bases:
Water samples per authorized written procedures assure that ERB water discharges have not exceeded the limits of 10 CFR Part 20 for unrestricted areas.
2.13 Hot Retention Area (HRA)
Applicability - This specification applies to protected safe storage of the HRA.
Objective - The objective is to control access and prevent release of contamination frc.,this source.
Specification:
a) The HRA tanks, which were flushed and decontaminated to a practical level, shall be kept dry.
b) All hRA entrances or access plugs are welded closed, except that one entrance to the annulus and the tunnel area shall be locked to allow only authorized entry.
Bases:
These specifications provide for authorized access and preclude inadvertent exposure of personnel. These specifications also mitigate against liquid accumulation and release of potentially contaminated liquid.
2.14 Contaminated Air Systems (CAS)
Apolicability - This specification applies to protected safe storage of the Contaminated Air Systems (CAS) which includes the Stack.
Objective - The objective is to provide controlled-access into relatively clean Contaminated Air Systems.
Specification:
a) These systems shall include the 5-foot diameter, 100-foot-high stack and all contaminated air ventilating systems except those presently serving the reactor tank, CV and HRA.
b) The fan motors shall be de-energized from the power bus at the motor control centers.
c) All manual and automatic operated valves shall be disabled in a fixed closed position.
d) The CAS which were vacuumed, decontaminated as practical and purged, shall be kept dry with absolute filters removed.
Bases:
The CAS has been vacuumed to remove loose contamination, was purged, and is maintained in a dry condition for use, if required. The CAS can, with minor repairs, be placed in operation, when and if required. Twelve years of monitoring under the above conditions verifies the absence of airborne radioactivity. The above program j will continue to maintain the CAS in a low radiation condition. l l
- 3. Surveillance 3.1 Designated Radioactive Storage Areas Within PBRF Applicability - This specification applies to the monitoring and surveillance of the radioactive storage areas within the PBRF.
Objective - The objective is to identify the areas for radiological control.
Specification:
a) Radioactive material, with the exception of distributed radioactive material existing as contamination within process systems and laboratories, shall be stored in four areas:
- 1. The Containment Vessel
- 2. The Reactor Building Canal G
- 3. The Hot Laboratory which includes the Hot Cells and the Hot Dry Storage Area
- 4. The Waste Handling Building b) Storage areas shall be pocted as Radiological Control Zones, defined in Section 1.3. Access to these areas shall be controlled as specified in Section 3.2, Access to Radiological Control Zones.
Radiological monitoring of these areas shall be by approved written procedures described in Section 3.6.f.
Bases:
The specifications identify the areas used for radioactive material storage and define the control for these radiological control zones.
3.2 Access to Radiological Control Zones Applicability - These specifications apply to surveillance of radiological control zones at the PBRF.
Objective - The objective is to provide surveillance systems for these zones.
Specifications:
a) Magenta zones shall be posted. Access to magenta zones shall require continuous radiation monitoring by health physics personnel, use of a safe work permit, and use of personnel dosimetry.
b) Magenta-yellow zones shall be posted. Access to magenta-yellow zones shall require health physics monitoring, and control and use of personnel dosimetry.
c) White zones - Access to white zones shall be by authorized personnel, without health physics personnel monitoring.
Bases:
Written procedural control, implementation of ALARA, and conformance to 10 CFR 20 standards assure satisfactory surveillance of the radiation control zones at the PBRF.
3.3 Alarm Response Applicability - This specification applies to alarm response.
Objective - The objective is to control access to the CV, monitor facility electrical power, and c'ontrol ground water infiltration.
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Specification: 1 All alarms shall annur.ciate in the Communication Center (CC). The CC is continuously staffed. Response to alarms shall include visual inspection to deteriqine the cause. Response shall be within one hour of annunciation. The following conditions shall initiate alarms:
a) CV Door Open b) Loss of Facility Electric Power c) HotRetentignAreaSumpHighGroundWater Alarms shall be continuously operable except during maintenance. If alanns are to be replaced, the alarm system may be inoperable for periods not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Bases:
This specification ensures a response for abnormal conditions during the protected safe storage condition.
3.4 Facility Radiological Monitoring Applicability - This specification applies to routine radiological surveys at the PBRF.
Objective - The objective is to determine that radioactivity is confined to radiological control zones.
Specification:
Routine radiological surveys shall be performed quarterly by trained health physics personnel using survey and counting equipment commensurate with sound health physics practices.
Bases:
This specification ensures that radioactive levels are maintaired consistent with 10 CFR 20 limits and with ALARA.
3.5 Procedures Applicability - This specification applies to approved written procedures that help administer the protected safe storage condition.
Objective - The objective is to list the types of procedures required for protected safe storage conditions.
Specification:
Detailed written and approved procedures shall be in effect covering the following areas:
a) Response to alarms b) Entrance to the PBRF, PBRF building, Containment Vessel, and radiological control areas.
c) Facility and environmental radiological monitoring and surveillance.
d) Facility changes e) Response to emergencies that may arise from fire, floods, and tornadoes.
f) Training program for the PBRF Manager and Alternate.
g) Maintenance programs These procedures shall be approved by the FBRF Safety Committee.
B_a ses :
This specification ensures protected safe storage procedures are provided.
3.6 Inspection, Tests and Surveys Applicability - This specification applies to a program of inspections, tests, and surveys during protected safe storage.
Specification:
Inspections, tests and respective frequencies shall be performed as follows:
Current Minimum Frequency
- a. PBS Fence integrity (patrolled daily) Quarterly
- b. PSRF Fence Integrity Monthly
- c. Building and CV locks Monthly
- d. Building and CV General Condition Monthly
- e. Alarm Tests Quarterly
- f. Facility Radiological Surveys Quarterly
- g. Environmental Radiological Surveys Quarterly L. Absolute Filters Annually
- i. CV Integrity Annually Frequencies shall be approved by the PBRF Safety Committee. The PBRF Engineer shall review the results and assure necessary corrective actions are taken to preserve the protected safe storage condition.
Bases:
These inspections, tests, and surveys provide a reasonable assurance that radioactivity is controlled and personnel exposure is minimized.
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- 4. Administrative Controls 4.1 Organization The Plum Brook Reactor Facility is owned by the National Aeronautics and Space Administration (NASA), which sball be responsible for maintaining the protected safe storage condition as required by these l Technical Specifications. NASA shall provide whatever resources are i
required to maintain the PBRF in a condition that poses no hazard to the general public or to the environment. Attached Figure 1 charts the current generic organization. Significant changes in organization shall be reported in the annual report.
4.1.1 Level 1 Directorate The Director shall be responsible for assuring compliance with the j reactor facility's license and providing regulatory reports and correspondence. He shall have overall responsibility for the protected safe storage of the facility.
4.1.2 Health, Safety, and Security Division This division shall provide the resource to maintain the PBRF in protected safe storage and is under the management of a Level 1 Director. 1 i
... o C'E N E R I C ORGANIZATION CHART NASA LEWIS RESEARCH CENTER DTRFrTnP I
EXECUTIVE LEVEL 1 SAFETY DIRECTORATE BOARD DIRECTOR INTERNAL HEALTH SAFETY AND AUDIT SECURITY DIV.
PBRF LEVEL 2 RADIATION SAFETY P B STATION SAFETY COMMITTEE MANAGEMEhT OFFICER OFFICE PLANT SECURITY LEVEL 3 HEALTH PHYSICS AND . . PBRF ENGINEER AND INSPECTION MAINTENANCE l Contract) (Contract)
_ RESPONSIBLE FOR LEVEL 1 - Compliance LEVEL 2 - Surveilance and Maintenance LEVEL 3 - Day to Day Oversite FIGURE 1 1
4.1.3 Internal Audit An annual internal audit shall be performed at the PBRF. The audit shall be performed by NASA personnel, not directly associated with the facility, who have nuclear experience. 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 Plum Brook Reactor Facility Safety Committee shall review and insure the proper disposition of each discrepancy.
4.1.4 Radiation Safety Officer (RS0)
A RSO, responsible to a Level 1 Director, shal' be responsible for organization, administration and direction of the radiological control and monitoring program, as required by these Technical Specifications, and shall assure the program is adequately performed. The RS0 shall be responsible for providing on-site advice, technical assistance and review in all areas related to radiological safety. The RS0 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 RS0 shall have a bachelors degree in physical science or biological science or the equivalent 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 program.
4.1.5 Executive Safety Board (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 tonmittees to conduct detailed third party reviews of specified Center operations.
4.1.6 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. The purpose of the reviews is to assure that operations, written procedures, facility changes, and future plans comply with NRC licenses and regulations, do not involve unreviewed safety questions, and provide protection to the public, on-site 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 maintenance, proposed changes, new and revised procedures, facility changes, 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 a 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 of the PSC shall be two-thirds of the
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- members but not less than three members, whichever is greater. In specific instances, the PSC may designate the Chairman to act in its 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.
4.1.7 Plum Brook Station Management Office (PBM0)
The Chief, PBM0 shall be knowledgeable of the station activities that may affect the protected safe storage condition at the PBRF. The Chief, PBM0 is responsible for administering a program to ensure that proper operations, control and safeguards are maintained for the station. This includes a key control system. Keys for the PBRF are authorized by the Chief, PBM0 on a "need to have" basis to perscns having knowledge of the conditions, the hazards and procedures of the PBRF. Implementation is by an authorization letter issued to the key distributor. The PBM0 shall provide for the services of Plant Security, Inspection, Health Physics, and Maintenance as necessary at the PBRF.
4.1.8 PBRF Engineer (Reactor Manager)
The PBRF Engineer shall be responsible for the daily management and shall assure the protected safe storage condition is maintained in accordance with these Technical Specifications. The PBRF Engineer shall have the following qualifications:
- a. A bachelors degree in engineering or a related physical science.
- b. Be knowledgeable in radiation hazards and radiation protection.
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- c. Have successfully completed the training for familiarization with the duties of the Reactor Manager.
4.2 Procedures All new or revised procedures will be reviewed by the PBRF Safcty Committee and approved by signature of the PBRF Engineer and the chairman of the PSC.
4.3 Reports Reports required under license and applicable regulations shall be provided. In addition, NASA shall report in writing to NRC within 90 days after each calendar year summarizing the following:
- a. Condition of systems and components needed to maintain the protected safe storage ccndition.
- b. An assessment of the effectiveness of security and surveillance.
- c. Significant changes in PBRF managenent organization.
- d. Results of facility and environmental radiological surveys.
- e. Changes to the facility pursuant to Section 50.59 of 10 CFR Part 50.
- f. Exposure range and total number of persons provided with monitoring per 10 CFR Part 20.407.
- g. Any release in excess of 10 CFR Part 20 of radioactive material from the PBRF site.
s-< a 4.4 Records NASA shall keep records required by applicable licenses and regulations including the following:
- a. Radiological survey results of PBRF and environment.
- b. Equipment maintenance records (EMR's) of non routine maintenance operations involving substitution or replacement of vital components.
- c. The end condition statements, the procedures used to place the facility in the standby condition, and the procedure completion reports shall reflect the facility condition in the possess-but-not-operate status.
- d. Any change which alters the end condition of Safe Protective Stcrage to any building, structure, system, equipment, or grounds shall be documented by a facility change.
- 5. 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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