ML20151P387
| ML20151P387 | |
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|---|---|
| Site: | 05000199 |
| Issue date: | 07/31/1998 |
| From: | MANHATTAN COLLEGE, RIVERDALE, NY |
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| NUDOCS 9808030154 | |
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APPENDIX C TECHNICAL SPECIFICAi :ONS POSSESSION ONLY STATUS AMENDMENT NO. 12: July 1998 9808030154 DR 980721 ADOCK 05000199 PDR ,
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! REVISION 11 I
REVISION RECORD REVISION NUMBER COMMENT 0 Submitted to U. S. NRC on August 26,198,3 as part of the Safety Analysis Report for the Manhattan College Zero Power Reactor (MCZPR) 1 Complete revision submitted on January 12,1984 2 Complete revision submitted on November 15,1984 3 Revisions as noted on pages: 16-1,16-2,16-10,16-11,16-13,16-16,16-23, t 16-25, and 16-26 on December 19,1984 4 Page numbering changes from 16-1 to 1-1, etc.
- Cover sheet revised from section 16 to Appendix A per USNRC request Revisions as noted on pages i, ii, iii, and 1 -1, 2-1, 2-2, 3- 1, 3-2, 3-3, 3-4, 3-7,4-1,4-2, 4-4,4-8,4-11,5-1,5-2,5-3,5-4,5-5, 6-1,6-6, 6-8,6-9,6-11, 6-13, and 6-14 on March 15,1985 5 (HEU core) Revisions as noted on pages i, ii, and 1-1,1-2,3-1, and 3-2 on February 20, 1989
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I 6 (LEU core) Revisions as noted on pages i, ii, and 2-1,2-2,3-1,3-2,5-1, and 5-3 on L
l March 10,1989 7 Revisions as noted on pages i, ii, iv 6-1, and 6-8 on March 26,1987 8 Revisions as noted on pages i,ii, 1-1,1-2,2-1,2-2,3-1,3-2, and 5-3 on March 12,1990 ~
9 No changes 10 Revisions as noted on pages i, ii,4-8,4-9,4-10,4-11,4-12,6-15, and 6-16 l
+ on April 13,1992 I
11 Revisions as noted on pages i, ii, and 6-5 on November 22,1994 l
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Amendment No. 12 l
l REVISION RECORD (cont.)
REVISION NUMBER COMMENT 12 Revisions as noted on pages 1-1, 1-2, 2-1, 3-1, 4-1, 4-2, 4-3, 5-1, 6-1, 6-2, 6-3, 6-4, 6-5, 6-6, 6-7, 6-8, 6-9.
Submitted with Decommissioning Plan and request for Possession-Only License, decommissioning and license termination after decommissioning l
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- TABLE OF CONTENTS Contents Pace No.
Title Page Revision Record Table of Contents 1.0 DEFINITIONS 1-1 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 4.0 SURVEILLANCE REQUIREMENTS 4-1 5.0 DESIGN FEATURES 5-1 6.0 ADMINISTRATIVE CONTROLS 6-1 Figures 6-1, Table of Organization 6-2
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{ l 1.0 DEFINITIONS The terms Safety Limit, Limiting Safety System Setting, and Limiting Condition for Operation are as defined in paragraph 50.36 in 10 CFR Part 50.
ALARA - ALARA is a concept introduced by the Nuclear Regulatory Commission (NRC) to all reactor facilities. The basis of ALARA is that all exposure to radiation should be kept "as low as reasonably I achievable" (ALARA). j channel - A channel is the combination of sensor, line, amplifier .
and output devices which are connected for the purpose of measuring the value of a parameter. j 1
channel calibration - A channel calibration is an adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures.
Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include a channel test.
channel check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shall include comparison of the channel with other independent channels or systems measuring the same variable.
channel test - A channel test is the introduction of a signal into the channel for verification that it is operable.
control rod - Plates fabricated with neutron absorbing material used to establish neutron flux changes and to compensate for i routine reactivity losses. This includes safety-type and regulating rods.
core - The portion of the reactor volume which includes the fuel elements, the source and the control rods.
measured value - The measured value is the value of a parameter as it appears on the output of a channel.
reactor secured - A rector is secured when it contains insufficient fissile material or moderator present in the reactor, adjacent experiments or control rods, to attain criticality under optimum ,
conditions of moderation and reflection, or when the fuel has been '
l removed from the core and place into storage.
1-1 Amendment No. 12 l
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1.0 DEFINITIONS l
The terms Safety Limit, Limiting Safety System Setting, and I Limiting Condition for Operation are as defined in paragraph 50.36 ;
in 10 CFR Part 50.
ALARA - ALARA is a concept introduced by the Nuclear Regulatory Commission (NRC) to all reactor facilities. The basis of ALARA is that all exposure to radiation should be kept "as low as reasonably achievable" (ALARA).
channel - A channel is the combination of sensor, line, amplifier and output devices which are connected for the purpose of measuring the value of a parameter.
channel calibration - A channel calibration is an adjustment of the channel such that its output corresponds with acceptcble accuracy to known values of the parameter which the channel measures.
Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include a channel test.
channel check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shall include comparison of the channel with other independent channels or systems measuring the same variable.
channel test - A channel test is the introduction of a signal into the channel for verification that it is operable.
control rod - Plates fabricated with neutron absorbing material used to establish neutron flux changes and to compensate for routine reactivity losses. This includes safety-type and regulating rods.
core - The portion of the reactor volume which includes the fuel elements, the source and the control rods.
measured value - The measured value is the value of a parameter as it appears on the output of a channel.
reactor secured - A rector is secured when it contains insufficient fissile material or moderator present in the reactor, adjacent experiments or control rods, to attain criticality under optimum conditions of moderation and reflection, or when the fuel has been removed from the core and place into storage.
1-1 Amendment No. 12 l
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l 1 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS i
2.1 Safety Limits 2.1.1 Applicability This specification applies to the storage conditions of the fuel. I l
2.1.2 Objective To assure that fuel is stored in a manner that prevents criticality.
2.1.3 Specifications !
I A. 'uel shall not be placed back into the reactor.
B. For all conditions of moderation and reflection, the k effective during storage shall be less than 0.6.
C. Fuel storage shall be in containers as described i herein.
2.1.4 Bases Specification A reflects the proposed change from operating to Possession Only status.
i Specification B requires that storage be in an area l
and manner that precludes criticality of the stored fuel.
Specification C identifies the containers for storage prior to shipment of fuel off site.
l 2-1 Amendment No. 12 1
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.O a 3.0 -LIMITING CONDIT'10NS FOR OPERATION 3.1 Radiation Monitoring System 3.1.1 Applicability These specifications apply to the radiation monitoring instrumentation needed during decommissioning.
3.1.2 Objective To specify the type and sensitivity of radiation i monitoring instrumentation. l 3.1.3 Specifications A. Survey instrumentation shall be maintained in operatrisc condition at all times.
B. Instrumentation shall be capable of measuring:
gamma radiation fields in excess of 10 microR/hr; alpha and beta / gamma surface contamination; neutron fields 3.1.4 Bases Specification A requires that instrumentation be available to characterize the radiological conditions in i any area in which decoramissioning actions will occur. I Specification.B ensures that instrumentation is sufficient to meet ALARA requirements and the radiological facility license termination criteria.
3-1 Amendment No. 12
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, 4.0 SURVEILLANCE REQUIREMENTS Actions specified in this section are required to be performed during the specified surveillance period.
4.1 Radiation Monitoring System l
4.1.1 Applicability This specification applies to the surveillance requirements for the radiation monitoring system.
4.1.2 Objective l
To specify the frequency and type of testing to assure that the radiation monitoring system is operable 4.1.3 Specifications A. A channel check of the portable radiation survey instruments shall be performed semiannually.
B. The portable radiation survey instruments shall be calibrated annually.
C. The environmental film badge and smear surveys in the fuel and source storage area shall be performed semi-annually.
D. An ALARA program shall be established and monitored by a Radiation Safety Officer (RSO).
E. The 5 millicurie source shall be tested semi-annually for leakage and/or contamination (unless it is in storage) by:
- a. The licensee, or
- b. Other persons specifically authorized by the Nuclear Regulatory Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
4.1.4 Bases I
The periodic surveillance and calibration of the I
radiation survey' instruments in Specifications A and B will assure that the radiation survey equipment is operable. Based on experience at this facility, specifications C-E are adequate to verify radiation l 4-1 Amendment No. 12
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protection. The provision in Specification E that the source not be leak tested while in storage limits occupational radiation exposure to ALARA levels.
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i 4-2 Amendment No. 12 ,
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4.2 Reactor Area 4.2.1 Applicability l These specifications apply to surveillance requirements for the reactor area other than the reactor structure.
l 4.2.2 Objective 1 1
To assure the physical and radiation safety of the l
! reactor area.to protect the reactor fuel.
l 4.2.3 Specifications !
! A. The operational condition of the fire alarm shall be l
tested on an annual basis.
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B. The physical barriers (door locks) shall be inspected quarterly.
i l C. An inventory of the fuel and the sources shall be l performed semi-annually.
D. A radiation survey of the area shall be performed semi-annually.
4.2.4 Bases Based on experience with reactors of this type, the frequency of inspection and monitoring in Specifications A-C will assure security for the physical safety of the t fuel and sources. The inventory period in Specification I
C is consistent with the inventory requirements for material accountability and combining both inventories maintains occupational exposure ALARA>
Monitoring is performed under Specification D to insure l that ALARA will be achieved.
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l 4-3 Amendment No. 12 l
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5.0 DESIGN FEATURES 5.1 Reactor The reactor is described in the Safety Analysis Report for Conversion of Manhattan College Zero Power Reactor (MCZPR) to Low l Enriched Uranium (LEU) Fuel dated April 1989. 1 The reactor has been modified by removing the fuel to make the reactor incapable of achieving criticality. The control console !
has been disconnected from the power supply and the reactor. I I
i 5.2 Fuel Storage j l
Fuel shall be stored in containers in the temporary storage area located on the first floor level of the Nuclear Engineering Facility pending return to the Department of Energy.
l 5-1 Amendment No. 12
6.0 ADMINISTRATIVE CONTROLS 6.1 Organization 6.1.1 Structure The organization for the management of the reactor facility in Possession Only status and during decommissioning shall be structured as shown in Figure 6-1. Levels of authority indicated divide responsibility as follows:
Level 1: Responsible 1for the facility license and site administration.
Level 2: Responsible for safe accomplishment of the reactor decommissioning program.
Level 3: Responsible for carrying out decommissioning actions.
The Radiation Safety Committee is responsib'le to the Dean of Engineering fer review and evaluation of all proposed operations ano procedures in order to insure that the fuel and sources are I stored, and transferred and the reactor facility is decommissioned in a safe and competent manner. 1 6.1.2 Responsibility l Individuals at the various management levels shown in Figure 6-1, ;
in addition to having responsibility for the policies and ;
management of the facility, shall be responsible for safeguarding 1 the public and facility personnel from undue radiation exposures ;
and for adhering to all requirements of the License and Technical !
Specifications.
In all instances, responsibilities of one level may be assumed by designated alternates, or by higher levels, conditional upon appropriate qualifications.
l The detailed description of duties of each individual in Level 2 and Level 3 are as follows:
l A. The Dean of the School of Enaineerina has been directed by the ,
College Administration to assume direct responsibility for the I safe management of the reactor facility while in Possession Only status and to assure safe completion of decommissioning.
B. The Actina Reactor Administrator shall provide final policy decisions on all phases of reactor and materials possession and on regulations for the facility as a whole. He/she must be qualified and may assume the added position of the 6-1 Amendment No. 12
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FIGURE 6-1 i ORGANIZATIONAL STRUCTURE l MCZPR DECOMMISSIONING 1
P MANHATTAN COLLEGE CORPORATION j BOARD OF TRUSTEES John P. Lawler, Ph. D., Chairman Level 1 PRESIDENT OF THE COLLEGE Bro. Thomas Scanlon, F.S.C., Ph.D.
PROVOST Weldon Jackson, Ph.D.
DEAN OF THE SCHOOL OF ENGINEERING Level 2 HEALTH PHYSICIST Larry Luckett, C.H.P.
QUALITY ASSURANCE MGR.
Robert E. Berlin, D.P.H.
lRADIATIONSAFETYCOMMITTEE l ACTINbREACTORADMINISTRATOR Catherine C. Stanton, M.S.
Level 3 l MAINTENANCE STAFF l l STUDENT ASSISTANTS l 6-2 Amendment No. 12
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reactor Radiation Safety Officer and carry out the duties of this position when dictated by staffing requirements. He/she will be advised in all matters concerning the safe management of the facility by the Radiation Safety Committee. The Acting Reactor Administrator shall be appointed by the Provost of ;
Manhattan College.
C. The Ouality Assurance Manaaer shall be responsible for the review and evaluation of the proposed radiation surveys and recordkeeping, including the final verification survey.
He/she will verify that surveys conform to the requirements of NUREG/CR 5849.
D. The Radiation Safety Committee shall be responsible to the Dean of the College of Engineering for the review and evaluation of all proposed operations and procedures in order to insure that possession and transfer of the fuel and sources and facility decommissioning shall be performed in a safe and competent manner. The Radiation Safety Committee shall advise on and be available for advice and assistance on any problems relative to the safe possession of radioactive materials and facility decommissioning.
E. The Reactor Radiation Safetv Officer shall be responsible for the promulgation and day to day enforcement of rules, regulations and operating procedures which conform with the regulations set forth in 10 CFR Part 20. The Reactor Radiation Safety Officer in conjunction with the Radiation Safety Committee shall approve suggested procedures for the possession, storage and disposition of all radioisotopes consistent with Reactor License No R-94 and the approved Decommissioning Plan. The Campus Radiation Safety Officer in conjunction with the Radiation Safety Committee shall be available for advice and assistance on problems involving radiological safety arising from the decommissioning of the facility.
F. The Health Physicist shall be responsible for monitoring records of exposure on film badges. He/she shall also review the reactor log, periodic radiation surveys of the critical reactor laboratory, the subcritical laboratory, the storage area, and the counting room. The Health Physicist will review the surveys performed in conjunction with fuel and source shipment off site and confirm that the packages comply with all applicable NRC and DOT regulations.
H. All other personnel using the facility shall be instructed in 6-3 Amendment No. 12
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1 i the hazards involved, and given a copy of the lacoratory regulations concerning use of radioactive material.
6.1.3 Staffing This Specification related to staffing requirements for reactor operation. It is not applicable for Possession only status because the reactor will remain secured.
I 6.1.4 Selection and Training of Personnel The Acting Reactor Administrator shall meet the minimum qualifications set forth in ANSI /ANS 15.4, " Standards for Selection and Training of Personnel for Research Reactors.
The Radiation Safety Committee members shall have at minimum five (5) years of professional experience in the field represented by the member or a baccalaureate degree plus at least two (2) years experience. Generally, these committee members will be College faculty but outside experience may be i sought if necessary. In this case, a baccalaureate degree plus five (5) years experience will be required. i 6.2 Review and Audit The o diation Safety Committee shall perform the independent !
review and audit of the safety aspects of the reactor facility decommissioning.
6.2.1 Composition and Qualifications The Radiation Safety Committee is composed of faculty and administration knowledgeable in the safe use of radioactive materials by virtue of training and professional experience.
Members of the Radiation Safety Committee are appointed by the Provost.
6.2.2 Charter and Rules
- 1. The Radiation Safety Committee shall meet at least annually and more frequently as circumstances warrant, consistent with effective monitoring of facility activities. Written records of its meeting shall be kept.
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- 2. The Radiation Safety Committee may appoint one or more qualified individuals to perform the audit function.
! 6-4 Amendment No. 12
I Review Function l
6.2.3 The following items shall be reviewed:
- 1. Proposed changes in the Technical Specifications or the Operating License. .
- 2. Reports of external (NRC, state and local authorities, and insurers) inspectors and auditors.
- 3. Revisions to procedures affecting facility and fuel storage that have a radiological significance.
6.2.4 Audit Function The Audit Function shall include selective (but comprehensive) examination of operating records, logs and other documents.
The audit will be performed biennially by an outside individual or group familiar with the research reactor operations. They shall submit a report to the Acting Reactor Administrator and the Radiation Safety Committee. The following items shall be audited:
l 1. Conformance to Technical Specifications and applicable l license conditions.
- 2. The results of all actions taken to correct those deficiencies that may occur in the reactor facility l equipment, systems, structures, or methods of operation
- that affect radiation safety.
l 3. Emergency and Physical Security Plans and implementing l procedures.-
l 6.2.5 Changes to the Decommissioning Plan The Radiation Safety Committee shall have the authority to approve changes to the Decommissioning Plan requested by the Acting Reactor Administrator when necessary to respond to unanticipated conditions. Such changes may only be approved if:
- 1. All regulatory requirements will be met and no reduction in safety is involved.
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- 2. The changes are protective of health and safety of 6-5 Amendment No. 12 l
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workers and the public and in accordance with the Radiation Safety Program.
6.3 Procedures l
Written procedures shall be prepared, reviewed and
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approved prior to initiating any of the activities listed I in this section. The procedures shall be reviewed by the Radiation Safety Committee and approved by the Reactor Administrator.
- 1. Surveillance tests and calibrations required by the Technical Specifications or those that may have an effect on reactor safety.
- 2. Personnel radiation protection consistent with applicable regulations.
- 3. Administrative controls for operations and maintenance for the conduct of fuel and source transfer and facility decommissioning.
- 4. Implementation of the Emergency and Physical Security Plans.
l 6.5 Required Actions i 6.5.1 Action To Be Taken in the Event of an Occurrence of the l Type Identified in 6.6.2-1.a or 6.6.2-1.b.
l 1. Occurrence shall be reported to the Acting Reactor Administrator or a designated alternate and to the Nuclear Regulatory Commission. All written reports shall be sent within the prescribed interval to the Nuclear Regulatory Commission, Washington, D.C., 20555, Attn:
i Document Control Desk.
- 2. Occurrence shall be reviewed by the Radiation Safety Committee at its next scheduled meeting.
! 6-6 Amendment No. 12 I
6.6 Reports 6.6.1 Operating Reports Internal reports are kept as minutes of the annual meetings of the Radiation Safety Committee.
A report summarizing facility operations will be prepared annually where the reporting period ends August 31. A copy of this report shall be submitted to the Nuclear Regulatory Commission, Washington, D.C., 20555, Attention: Document control Desk by October 15. The report shall include the following:
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- 1. A narrative summary of facility experience.
- 2. A description of actions taken in accordance with the Decommissioning Plan.
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- 3. A summarized result of any radiation surveys performed by the facility personnel.
- 4. A summary of exposures received by facility personnel and visitors where such exposures are greater than 25%
of that allowed or recommended.
6.6.2 Special Reports i
- 1. There shall be a special report not later than the following working day by telephone to the Nuclear Regulator Commission Emergency Operations Center to be followed by a written report that describes the i circumstances of the event within 14 days of any of I the following:
- a. Release of radioactivity from the site above allowed limits.
- b. Any of the following:
- 1. Abnormal and significant degradation in reactor fuel, or cladding, or both which could result in exceeding prescribed radiation exposure levels to personnel or environment, or both.
- 2. An observed inadequacy in the implementation of administrative or procedural controls such that 6-7 Amendment No. 12
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the inadequacy causes or could have caused the existence or. development of an unsafe condition with regard to fuel and source storage.
- 2. A written report within 30 days to the Nuclear Regulatory Commission concerning the following:
- a. Permanent changes in the organization involving the Acting Reactor Administrator or the Radiation Safety Officer.
6.7 Records 6.7.1 Records to be Retained for a Period of at Least Five Years or for the Life of the Component if Less than Five Years
- 1. Normal reactor facility operation (but not including supporting documents such as checklists, log sheets, etc., which shall be maintained for a period of at least one year).
- 2. Principal maintenance operations.
- 3. Reportable occurrences.
- 4. Surveillance activities required by the. Technical Specifications.
- 5. Reactor facility radiation and contamination surveys l where required by applicable regulations.
- 6. Fuel inventories, receipts and shipments.
l l 7. Approved changes in decommissioning procedures, j
- 8. Records of meetings and audit reports of the Radiation Safety Committee.
- 9. Records of sealed source leak tests.
- 10. Records of annual inventory of sealed source material of record.
! l L 6-8 Amendment No. 12
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l 6.7.2 Recorils to be Retained for the Lifetime of the Reactor i Facil'.ty l
Applicable Annual Reports, if they contain all of the required information, may be used as records in this section. l
- 1. Gaseous and liquid effluents, if any, released to the environs.
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- 2. On-site environmental monitoring surveys required by '
the Technical Specifications.
- 3. Drawings of the reactor facility.
6.7.3 Records of radiation exposures for all personnel .shall be kept indefinitely or until the U. S. Nuclear Regulatory Commission authorizes their disposal.
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6-9 Amendment No. 12
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l APPENDIX D EMERGENCY PLAN
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