ML20148D965
| ML20148D965 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 05/20/1997 |
| From: | RHODE ISLAND, STATE OF |
| To: | |
| Shared Package | |
| ML20148D915 | List: |
| References | |
| NUDOCS 9706020205 | |
| Download: ML20148D965 (10) | |
Text
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TECHNICAL SPECIFICATIONS 1
Rhode Island Nuclear Science Center Docket 50-193, License R-95 1.25 Reportable Occurrence i
A reportable occurrence is any of the following:
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1.
A safety system setting less conservative than the limiting setting established in ' the Technical f
Specifications; l
2.
Operation in violation of a limiting condition for operation established in the Technical i
Specifications; l
3.
A safety system component malfunction or other component or system malfunction which could, or i
threaten to, render the safety system incapable of l
performing its intended safety functions; l'
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Release of fission products from a failed fuel
- element, 4
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J 5.
An uncontrolled. or. unplanned release of radioactive material from a restricted area which results in concentrations of radioactive materials inside or outside the restricted area in excess of the limits specified in Appendix B, of 10CFR20; 6.
An uncontrolled or unanticipated change in reactivity in excess of 0.5 %AK/K; 7.
Conditions arising' from natural or man-made events that affect or threaten to affect the safe operation of the facility; 8.
An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with the operation of the facility.
9706020205 970520 PDR ADOCK 0500 3 -
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Page 7 Admendment 23
4 TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 Specification:
The reactor shall not be made critical unless:
1.
The reactor safety systems and safety related i
instrumentation are operable in accordance with Tables 3.1 and 3.2 including the minienum number of channels and the indicated maximum or minimum setpoint; i:
2.
All shim safety blades are operable in accordance with Technical Specification 4.1.1 and 4.1.2.
3.
The time from initiation of a scram condition until the control element is fully inserted shall not exceed 1
second in accordance with Technical Specification 4.2.5 and 4.2.6.
4.
The reactivity insertion rates of individual control l
and regulating Nedes will not exceed 0.02 %AK/K j
per second.
r Bases:
Neutron flux level scrams provide redundant automatic j
protective action to prevent exceeding the safety limit on l
reactor power.
The period scram limits the rate of rise of the reactor power to periods which are manually controllable without reaching excessive power levels or fuel temperatures.
The loss of flow scram assures that an automatic loss of flow 1
scram will occur in the event of a loss of flow when the reactor 1r is operating at power levels above 0.1 MW.
i The reactivity insertion rate limit was determined in the SAR, 1
Section XI and predicts a safe fuel clad temperature.
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Page 20 Admendment 23
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g.
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193. License R-95 i
reactor ' operation, ' fuel movement and handling of radioactive materials in the reactor building.
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Objective:
1 To assure that radiation monitoring equipment is-r available. for evaluation of radiation conditions and that the release of airborne radioactive material is maintained below the limits established in 10CFR20.
Specification:
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When the reactor is operating, gaseous and particulate sampling of the. stack effluent shall be
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monitored by a stack monitor with a readout in j
the control room.
The particulate activity monitor and the gaseous activity monitor for the facility exhaust stack shall I
be operating.
If either unit is out of service for more than one shift (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />), either the reactor shall be shut down or the unit shall be replaced by one of comparable monitoring capability.
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l 2.
When the reactor is operating, at least one j
constant air monitoring unit (Table 3.2.11) located in the confinement building shall be operating.
Temporary shutdown of this unit shall be limited as in 3.7.1 above.
3.
The reactor shall not be continuously
- operated without a minimum of one area radiation monitor (Table 3.2.8) on the " ground floor level" of the reactor building and one area monitor (Table 3.2.6) over the reactor pool -(reactor bridge) operating and capable of warning personnel of high radiation levels.
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Page 29 Admendment 23
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TECHNICAL SPECIFICATIONS i
Rhode Island. Nuclear Science, Center j'
Docket 50-193, License R-95 l
i Bases:
i The limits established. in -specification 3.7.2 incorporate a
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dilution factor of 4x104 for effluent concentrations-released through the exhaust stacks. This' dilution factor is based on a L
dispersion factor (X/Q = 10-5 sec/M3) ' calculated from actual-meteorological data which is. determined ' using the highest i
L frequency of wind in any sector. Because of' the use of the '
j l-most conservative measured values of' wind directional L
frequency and dispersion factors, this dilution ' factor will assure that. concentrations of. radioactive-material in unrestricted areas around the Rhode Island Nuclear' Science 4
Center will be far below the limits of 10CFR20.'-(Refer to -
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letter dated April 16, 1963. sent to the. NRC -in connection with license questions.) This dilution factor is' used for calculating maximum ground concentration 'of noble gases-down wind vs. exhaust stack effluent concentrations. The SAR contains calculations for doses from the' iodine at the 48 j
meter distance.
d b.
Liquid Effluents l
Applicability:
This specification applies to the - monitoring of radioactive liquid effluents from the Rhode Island Nuclear Science Center.
Objectives:
The objective is to assure that exposure to the public resulting from the release of liquid effluents will be within the regulatory limits and consistent with as low-as reasonably achievable requirements.
Specification:
L The liquid waste retention - tank discharge shall be batch sampled and the gross activity per unit volume l
Page 31 Admendment 23
i TECHNICAL SPECIFICATIONS l
Rhode Island Nuclear Science Center Docket 50-193, License R-95 i
Experimental materials, except fuel materials, which could off-gas, st - hme, volatilize, or. produce aerosols under: (1) normal operating conditions of the experiment or reactor, (2) credible accident conditions in the reactor, and (3) possible accident conditions in the experiment shall be limited 'in activity such that: if 100% of the gaseous activity or radioactive aerosols produced escaped to the reactor room or the atmosphere, the airborne concentration of. radioactivity averaged over a year would not exceed the occupational limits for maximum permissible concentration.
I In calculations pursuant to the above, the following.
assumptions shall be used:
(1) If the effluent from an experimental facility exhausts through ductwork
. which closes automatically on high radiation level, at least 10% of the gasenas activity or aerosols produced will escape.
(2) If the effluent from an experimental facility exhausts through a
filter installation designed for greater than 99% efficiency
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for 0.3 micron particles, at least 10% of these j
vapors can escape..(3) For materials whose boiling point is above 550C and where vapors formed by boiling this material can escape only through an undisturbed - column of water above the core, at least 10% of these vapors can escape.
(4) Limits for
. maximum permissible concentrations are specified in the appropriate section of 10CFR20.
Bases:
Specifications 1 through
.5, 8 and 9 are intended to reduce the likelihood of damage to reactor components and/or radioactivity releases resulting from experiment failure and, along with the reactivity restriction of pertinent specification in 3.1, serve as a guide for the review and approval of new and untried experiments by the operations staff as well as the l
Nuclear and Radiation Safety Subcommittee.
Specifications 3 and 4 are self explanatory.
Page 34 Admendment 23 i
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f TECHNICAL SPECIFICATIONS.
Rhode Island Nuclear Science-Center
. Docket 50-193, License R-95 i
e.
the. negative differential pressure between I
the inside and outside of the building is at i
least 0.5 inches of water.
This is determined J
by reading the pressure gauge in the control j
room; 1
f.
the exhaust rate through.the - emergency cleanup. system shall' not be more than 1500 CFM coming from the. reactor building and passing through the scrubber filter.
. Dilution air ' will be provided by a separate blower from an uncontaminated source.
2.
The condition of the following equipment shall be inspected in accordance with written operating procedures every 6 months.
1 a.
Building ventilation blowers and dampers (including solenoid valves, pressure switches, 1
piping, etc.);
l b.
Personnel access and reactor room overhead doors.
L 3.
The testing and maintenance of the emergency
-l generator..ill be performed in accordance with the RINSC operating procedures and manufacturer l
recommendation.
I 4.
The efficiency test for the charcoal filter shall be tested annually as specified in the operating l
l procedures.
Bases:
i The weekly check of the confinement system provides assurance that the automatic function will be actuated when
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confinement isolation is y :. red.
The semiannual inspection of valves and doors will provide assurance that the closures will perform their function of limiting leakage through these F
f Page 44 Admendment 23
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. TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science ' Center i
Docket 50-193, License R-95
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'l Objective:
To prevent physical damage to the beryllium reflectors in l
the core from accumulated neutron' flux exposure.
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' Specification:
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i The maximum accumulated neutron flux shall be lx1022 1
neutrons /cm2 The exposure shall be determined annually in accordance with the operating procedures.
Inspections and core fit shall be conducted annually.
Bases:
The RINSC SAR (Part A Section VIII) has addressed this limit as a conservative limit.
(Annual inspections and core box fit as well as calculated total exposure serve as a 1
method to monitor the beryllium lifetime.)
b.
LEU Fuel Elements l
Applicability:
This specification applies to surveillance of LEU-fuel elements.
Objective:
To prevent operation with damaged fuel elements and verify the physical condition of the fuel element.
Specification:
The fuel elements shall be visually examined and functionally fit into the core grid box annually.
Page 48 Admendment 23
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TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 Review and audit of proposed changes to the c.
facility systems or equipment, procedures, and operations, d.
Determination - of whether-a proposed change, test, or experiment would constitute an unreviewed safety question or which may require a change to the Technical Specifications or facility license.
e.
Review of all violations of the Technical Specifications and Nuclear Regulatory Commission Regulations, and significant violations of internal rules or procedures, with recommendations for corrective action to prevent recurrence.
f.
Review of the qualifications and competency of the operating organization to assure retention of staff quality, g.
-Review changes to the Nuclear and Radiation Safety Committee charter.
h.
Review at least annually, the radiation safety aspects of the facility.
3.
The Nuclear and Radiation Safety Committee shall have a written charter defining such matters as the authority of the Committee, the subjects within its purview, and other such administrative provisions as are required for effective functioning of the Committee.
Minutes of all meetings of the Committee shall be kept.
4.
A quorum of the Nuclear and Radiation Safety Committee shall consist of not less than a majority of the Full Utilization Committee and shall include the Radiation Safety Officer or designee, and the chairman or designee.
Page 59 Admendment 23
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 4
c.
Any reportable occurrences as defined in Paragraph 1.25 of these specifications.
d.
Any violation of a Safety Limit.
e.
Discovery. of any substantial ~ variance from performance specifications contained in the technical specifications and safety analysis.
2.
The written report shall be sent within ' 14 days. The report shall:
a.
- Describe, analyze, and
. evaluate safety implications; b.
Outline - the measures taken to assure that the cause of the condition is determined; c.
Indicate the corrective action
- taken, including any changes made to the procedures and to the quality assurance
- program, to prevent repetition of the occurrence and of similar occurrences involving similar components or systems; d.
Evaluate the safety implication of the incident in light of the cumulative experience obtained from the record of previous failure and malfunctions' of similar systems and components.
3.
Unusual Events A written report shall be forwarded v.ithin thirty (30) days in the event of:
a.
Discovery of any substantial errors in the transient or accident analyses or in the methods used for such
- analyses, as Page 63 Admendment 23
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 i
h.
Changes to procedures systems, components, and equipment.
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2.
Records to be retained for the life of the facility:
I a.
Gaseous and liquid radioactive effluents released to the environs;.
a b.
Off-site environmental monitoring surveys; c.
Personnel radiation exposures; d.
Updated, "as-built" drawings of the facility; j
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and j'
e.
Minutes of NRSC (and previous Reactor Utilization Committee) meetings.
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