ML20198F187
| ML20198F187 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 07/31/1997 |
| From: | RHODE ISLAND, STATE OF |
| To: | |
| Shared Package | |
| ML20198F184 | List: |
| References | |
| NUDOCS 9708110209 | |
| Download: ML20198F187 (13) | |
Text
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TECllNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R 95 Revision 1 1.25 Reportable Occurrence A reportable occurrence is any of the following:
1.
A safety system setting less conservative than the limiting setting established in the Technical Specifications; 2.
Operation in violation of a limiting condition for operation established in the Technical Specifications; 3.
A safety system component malfunction or other component or system malfunction which could, or threaten to, render the safety system incapable of performing its intended safety functions; t
4.
Release of fission products from a failed fuel element; 5.
An uncontrolled or unplanned release of radioactive material 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 cr 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.
1.26 Research Reactor 9700110209 970731 Page 7 Admendment 24
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TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193, License R 95 Revision 1 3.
The pool temperature does not exceed 1300F.
Bases:
The basis for natural convection safety limits is that the calculated maximum cladding temperature in the hot channel of the most compact core will not reach nucleate boiling of the water coolant at a pool depth of 23.54 feet.
2.2 Limiting Safety System Settings (LSSS) 2.2.1 Limiting Safety System Setting in the Forced Convectior Mode Applicability:
LEU Fuel Temperature - Forced Convection Mode l
Objective:
This specification applies to the setpoint for the safety channels monitoring reactor power, primary coolant flow, pool level and core outlet temperature to assure that the maximum fuel temperature permitted is such that no damage to the fuel cladding will result in the forced convection mode.
Specification:
The limiting safety system settings for reactor thermal power (P), primary coolant flow through the core (m),
height of water above the top of the core (H), and reactor coolant outlet temperature (To) shall be as follows:
Paramein LSSS P
(Max) 2.30 MW m
(Min) 1600.00 gpm H
(Min) 23.70 ft To (Max) 121.0 oF Bases:
Page 14 Admendment 24
TECIINICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193 License R 95 Revision i 2.2.2 Limiting Safety System Settings in the Natural Convection Flow Mode Applicability:
These specifications apply to the setpoint for the safety channels monitoring reactor thermal power level (P),
monitors for pool level (H), and pool water temperature (T ) in the natural convection mode.
p Objective:
To assure that automatic protective action is initiated to prevent a safety limit from being exceeded.
Specification:
l 1.
The limiting safety system setting for reactor j
thermal power (P), height of water above the top of the core (H),
and pool water temperature (T ) shall be as follows:
p Parameter LSES.
P (Max) 115.0 kw H
(Min) 23.7 ft.
l T
(Max) 126.0 oF p
Bases:
The _ SAR has determined that up to 217 kw can be removed by natural convection, however, the existing license requiremen' of 100 kw operation will be maintained and with 15% overpower trip,115 kw will be the LSSS.
The pool level scram (2" drop) is the same as the forced convection mode.
The pool temperature 1300F safety limit, having a 3% error, results in a LSSS of 1260F.
The LSSS for natural convection assures that automatic protective action will prevent a safety limit from being exceeded.
Page 16 Admendment 24
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TECilNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R 95 Revision 1 Specification:
The reactor shall not be made critical unless:
1.
The reactor safety systems and safety related instrumentation are operable in accordance with Tables 3.1 and 3.2 including the minimum number l
of channels and the indicated maximum or i
minimum setpoint; 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 I
second in accordance with Technical Specification 4.2.5 and 4.2.6.
4.
The _ reactivity insertion rates of individual control and regulating blades will not exceed 0.02 %AK/K per second.
Bases:
Neutron flux level scrams provide redundant automatic protective action to prevent exceeding the safety limit on 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 scram will occur in the event of a loss of flow when the reactor is operating at power levels above 0.1 MW.
The reactivity insertion rate limit was determined in the SAR,Section XI and predicts a safe fuel clad temperature.
Page 20 Admendment 24
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R 95 Revision 1 3.3 Coolant Water (a)
Primary Coolant Water Applicability:
This specification applies to the limiting conditions for primary coolant pH, resistivity, available pool water volume and radioactivity.
Objective:
To maintain the primary coolant in a condition to minimize the corrosion of the primary _ coolant system, fuel cladding, and other reactor components, and to assure proper conditions of coolant for normal and emergency requirements.
Specification:
1.
The primary coolant pH shall be maintained between 5.5 and 7.5.
2.
The primary coolant resistivity shall be maintained at a
value greater than 500Kohms/cm (conductivity 2micromhos/cm).
3.
The primary coolant shall be analyzed for radioactivity.
Bases:
Experience at this and other facilities has shown that the maintenance of primary coolant system water quality in the ranges specified in specification 3.3.1 and 3.3.2 will control the corrosion of the aluminum components of the primary coolant system and the fuel element cladding.
Conductivity Specification 3.3.2 also insures adequate Page 25 Admendment 24
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193, License R 95 Revision I reactor operation, fuel movement and handling of radioactive materials in the reactor building.
Objective:
To assure that radiation monitoring equipment is available for evaluation of radiation conditions and that the release of airborne radioactive material is maintained below the limits established in 10CFR20.
Specification:
I 1.
When the reactor is operating, gaseous and particulate sampling of the stack effluent shall be monitored by -a stack monitor with a i
i readout in the control room.
The particulate activity monitor and the gaseous activity monitor for the facility exhaust stack shall be operating.
If either unit is to be out of service, either the reactor shall be shut down or the unit shall be replaced by one of comparable monitoring capability; 2.
When the reactor is operating, at least one 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 v
warning personnel of high radiation levels.
Page 29 Admendment 24
TECilNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193, License R 95 Revision i Bases:
The limits established in specification 3.7.2 incorporate a dilution factor of 4x104 for effluent concentrations released through the exhaust stacks. This dilution factor is based on a dispersion factor (X/Q = 10-5 sec/M3) calculated from actual meteorological data which is determined using the highest frequency of wind in any sector. Because of the use of the most conservative measured values of wind directional frequency and dispersion factors, this dilution factor will assure that concentrations of radioactive material in unrestricted areas around the Rhode Island Nuclear Science Center will be far below the limits of 10CFR20. (Refer to letter dated April 16, 1963 sent to the NRC in connection with license questions.) This dilution factor is used for t
calculating maximum ground concentration of noble gases down wind vs. exha'ist etack effluent concentrations. The SAR contains calculations for doses from the iodine at the 48 meter distance, 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:
The liquid waste retention tank discharge shall be batch sampled and the gross activity per unit volume determined before release.
All off-site releases shall be directed into the municipal sewer system.
Page 31 Admer.dment 24 1
c TECilNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193, License R-95 Revision I 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 acrosols 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.
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 gaseous 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 for 0.3 micron particles, at least 10% of these 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 cornponents 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 Nuclear and Radiation Safety Subcommittee.
Specifications 3 and 4 are self explanatory.
Specification 6 assures that no physical or nuclear interferences compromise the safe operation of the reactor by, for example, Page 34 Admendment 24
TECilNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193, License R 95 Revision i e.
the negative differential pressure between the inside and outside of the building is at least 0.5 inches of water.
This is determined by reading the pressure gauge in the control room; 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 filters.
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, a.
Building ventilation blowers and dampers (including solenoid valves, pressure switches, piping, etc.);
b.
Personnel access and reactor room overhead doors.
3.
The testing and maintenance of the emergency generator will be performed in accordance with the RINSC operating procedures and manufacturer recommendation.
4.
The efficiency test for the charcoal filter shall be tested annually as specified in the operating procedures.
Bases:
The weekly check of. the confinement system provides assurance that the automatic function will be actuated when confinement isolation is required.
The semiannual inspection of valves and doors will-provide assurance that the closures will perform their function of limiting leakage through these-Page 44 Admendment 24
7, ;
TECliNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193 License R 95-Revision 1 Objective:
To prevent physical damage to the beryllium - reflectors in the core from accumulated neutron flux exposure.
Specification:
'The-maximum accumulated neutron flux shall be -1x1022:
neutrons /cm2 The exposure shall be determined annually in accordance with _ the operating procedu.es.
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 method to monitor the beryllium lifetime.)
b.
LEU Fuel Elements l
Applic~ ability:
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 24
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TECllNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193, License R 95 Revision 1 c.
Review and audit of proposed changes to the facility systems or equipment, procedures.
and operatiens.
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.
c.
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 I
retention of staff quality.
g.
Review changes to the NRSC charter.
h.
Review, at least annually, the radiation safety aspects of the facility.
3.
The NRSC 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.
All minutes of the previous Reactor Utilization Committee shall be retained for the life of the facility.
4.
A quorum of the NRSC shall consist of not less than four (4) member s and shall include the Radiation Safety Officer or designee, the Director or the Assistant Director for Operations and the Chairman or designee.
Page 59 Admendment 24 n.
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50193, License R-95 Revision 1 1.
The reactor will be shut down and reactor operations will not be resumed until authorization is obtained from the NRC.
2.
Immediate notification shall be made to the NRC in accordance with paragraph 6.8 of these specifications and to the Director.
3.
A prompt report shall be prepared by the Senior Reactor Operator.
The report shall include a
complete analysis of the causes of the event and the extent of possible damage together with recommendations to prevent or reduce the probability of recurrence.
This report shall be l
submitted to the NRSC for review and appropriate l
- action, and a
suitable similar report shall be i
submitted to the NRC in accordance with Paragraph 6.8 of these specifications and in support of a request for authorization for resumption of operations.
6.8 Reporting Requirements In addition to the requirements of applicable regulations, all written reports shall be sent to the U.
S. Nuclear Regulatory Commission, Attn:
Document Control Desk, Washington, DC - 20555, with a copy to the Region I Administrator.
The written reports include the following:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a report by telephone through the NRC Operations Center, Washington, DC and the NRC Region 1:
a.
Any accidental release of radioactivity to unrestricted areas above permissible limits, whether or not the release resulted in property
- damage, personal injury or
- exposure, b.
Any significant variation of measured values from a
corresponding predicted or Page 62 Admendment 24
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TECHNICAL SPECIFICATIONS Rhode Island - Nuclear-Science -Center -
Docket 50193.- License R 95 Revision 1 previously measured value of safety related operating characteristics occurring during operation of the reactor, c.
A'ny 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 y
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 t
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; l
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 within thirty (30) days in the event of:
1 Page 63 Admendment 24 l
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