ML20063G113
| ML20063G113 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 01/31/1994 |
| From: | RHODE ISLAND, STATE OF |
| To: | |
| Shared Package | |
| ML20063G099 | List: |
| References | |
| NUDOCS 9402150329 | |
| Download: ML20063G113 (70) | |
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RHODE ISLAND-NUCLEAR SCIENCE CENTER TECHNICAL SPECIFICATIONS DOCKET 50-193, LICENSE R-95 REVISION 1-9402150329 940131-if:
.PDR-ADOCK 05000193 6
P, PDR 2 :.
TABLE OF CONTENTS-1.0 DEFf NITI ON S........................................................................ I 1.1 Certified Operator.....................................................
1 1.2 Confinement........
...................................................I 1.3 E x p c ri m e n t...........
...........................................1 1.4 Explosi ve M aterial.......................................................... 2 1.5 Instrumentation C h a n n e 1................................................ 2 1.6 Limiting Conditions of Operation (LCO)............................... 3 1.7 Limiting Safety System Setting (LSSS)............................... 3 1.8 M easured Channel.................................................... 3 1.9 Mcasured Value..
....................4 1.10 V. r a b l e...............
...............4
- 1. I 1 Operating..........
..............................4 1.12 Operational Reactor Core.............
............................4 1.13 Protective A c t i o n.............................................. 4 1.14 Reactivity Excess..............
.....................................4 1.15 Reactivity Limits......................................
...............4 1.I6 Reactivity Worth of an Experiment.
......................5
- 1. I 7 Reactor Operating...
........................................5
- 1. I 8 Reactor Safety Systems.......
.....................................5 1.19 Reactor Secure.......
.................................................5
- 1. 2 0 R e a e t o r S h u t d a w n.........................................
................6 1.21 Readily Available on Call......................................... 6
- 1. 2 2 Reference Core Condition............................................ 6 1.23 Regu1ating Blade......
...............................................6 1.24 Removable Ex periment...
............6 1.25 Reportable O c c u r re n c e................................................. 7 1.2 6 Research Reactor......
...............................................8 1.27 Rundown..
.........................................8 1.2 8 Safety Channel..............
............................8
- 1. 2 9 S a fe ty Li mi ts.......................................
...................8 1.30 Scram Tir.i...
..........8 1.31 S h i m S a fe t y B 1 a d e.......................................................... 9
- 1. 3 2 S h all, S h ou Id a n d M ay.................................................... 9
[
f 1. 3 3 S h u t d o w n. M a rg i n................................................................... 9 1.34 Secured E x p e r i m e n t.................................................................... 9
- 1. 3 5. S t a t i c R ea e t i vi t y - Wo rt h........................................................... 9
' 1. 3 6 S t a n d ard Re a c to r. Co re....................................................... I 0 1.37 Surveillanee A e t i v i t i e s................................................................ I 0 1.38 Suryei11ance I n t e r v a 1 s................................................................ I 0 1. 3 9 Tru e Val u e..................................................................................... 1 1 1.40 Unschedu1ed S h u t d o w n............................................................. I 1
~2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM S ETTI N G S............................................................................. 1 2 2. 1 S a fe t y Li m i t s............................................................................... I 2 2.2 Limiting Safety System Settings (LSSS).................................I 4~
3.0 LIMITING CONDITIONS FOR OPERATION........................................ I 7 3. I Reac t i vit y Li mi t s............................................................................ I 7 :
3. 7 Reactor S afety Sy ste m................................................................... I 9 Table 3.1...........
...................................................................21 Table 3.2..........................................................................................23-3. 3 Cool a n t Wate r................................................................................ 2 5 3.4. ". 5, 3.6 Confinement and Emergency Exhaust System and Emergency Power................................................ 2 7 3.7 Radiation Monitoring Systems and Effluents....................... 2 8 3. 8 Li mi t atio n s o n Experi m e n ts......................................................... 3 2 -
3.9. Reactor Core Com ponen1s............................................................. 3 5 -
4.C S URVEILLANCE REQUIREMENTS...................................................... 3 7 er 4. I Reac ti vit y Li mi ts............................................................................ 3 7 4. 2 Reactor S afety System................................................................... 3 8 -
4. 3 Wa t er Cool ant S y s t em..................................................................... 4 0 4.4, 4.5, 4.6 RINSC Confinement B uilding........................................ 4 3 4.7 Radiation Monitoring ~ Systems and Effluents....................... 4'5
- 4. 8 S u rveill an ce E of Ex peri m e n ts......................_.............................. 4 6 4. 9 React or Core Componen ts.............................................................'.4 7 d
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5 5.0 DES I GN FEATURES................................................................................. 5 01 1
'f 5.1 De scri pti on....................................................................................... 5 0 '
5. 2 R e a c t o r Fu e l................................................................................ 5 0 5. 3. R e a c t o r Co re......................................-.......................................... 5 0 '
5. 4 R e a c t o r B u i l d i n g.......................................................................... 5 1 1
5. 5 Fu e 1 S t o ra ge..................................................................................... 5 2 5
6.0 ADMINISTRATIVE CONTROLS.................................................... 5 3 '
6.1 Organization a n d M a n a ge m e n t............................................... 5 3 h
Figure 6.1 - Organizational Chart............................................... 5 4
- 6. 2 Q u alifica t io n s of Perso n n e1........................................................ 5 5 i
- 6. 3 Responsibilities of Personnel.......................................................5 5 6. 4 R evie w an d A u d i t....................................................................... 5 8 I
6.5 Operating Pro c e d u re s............................................................... 6 0 ' '
6.6 Action to be Taken in the Event of a Reportable
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O c c u r r e n c e................................................................................ 6 1 6.7 Action' to be Taken in the Event a Safety Limit is.............
Exceeded.................
..............................................................61.
- 6. 8 Reportin g Req uirem e n ts.............................................................. 6 2 -
6.9 P1 ant O p e ra t i n g R e c o rd s........................................................... 6 5 -
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i TEC1INICAL SPECIFICATIONS Rhode Island - Nuclear Science Center-Docket 50-193. License R-95' Revision 1 4
1.0 DEFINITIONS i
1.1 Certified Operator l
An individual authorized by the U..S.
Nuclear Regulatory.
Commission to carry out the responsibilities associated with the position requiring the certification.
I 1.1.1 Senior Reactor Operator An individual who is licensed to direct the activities of reactor operators.
Such an individual may be referred to as.
a class A operator.
1 1.1.2 Reactor Operator An individual who is licensed to manipulate the controls of a reactor.
.Such an individual may be referred to as' a. class B operator.
1.2 Confinement
)
Confinement means an enclosure ~ on the overall facility which
(
controls the movement of air into it and out through' a i
controlled path.
i 1.3 Experiment t
Any operation, component, or target (excluding devices such as detectors, foils, etc.), which is ~ designed to investigate non-routine reactor characteristics or which ~ 's intended for irradiation wie in the pool, on or in a be..m t
tube or irradiation facility and which is not rigidly secured to a core or shield structure so as to.be part of their design.
1.3.1 Experiment, Moveable i
A moveable experiment is one where it - is intended 'that 'all v
or part of the experiment may be moved in or near the core 1
or into and out of the reactor while the reactor.is operating.
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TECIINICAL SPECIFICATIONS Rhode Island-Nuclear; Science Center 4-Docket 50-193, License R-95 '
Revision l-1.3.2 Experiment, Secured A
secured experiment is any.experime'nt,_ experiment facility, or component of an experiment that is held in.a stati.onary position relative to the reactor by ' mechanical-The restraining force must.be substantially greater means.
than those to which the experiment :might be subjected by__
hydraulic, pneumatic, buoyant, or. other. forces.which are normal to the operating environment of the experiment, 'or by forces which can arise as a result of credible conditions.
1.3.3 Experimental Facilities I
S An experimental facility is any structure or. device which is.
intended to guide, orient, position, manipulate, or otherwise '
e facilitate a multiplicity of experiments of similar character-1.4 Explosive Material r
Explosive material is any solid or liquid _ which. is. categorized as a severe, dangerous, or very dangerous explosion hazard in '
i DANGEROUS PROPERTIES OF INDUSTRIAL MATERIALS by N.I; Sax, third Ed. (1968), or is given an identification of Reactivity.
~(Stability) Index of 2 3, or 4 by the National Fire Protection y
Association in its publication 704-M,1966.
i 1.5 Instrumentation Channel A channel is the combination of sensor, line, amplifier, and.
j output device which are connected for the purpose of measuring the value of a parameter.
1.5.1 Channel Test i
Channel test is the introduction of a signal _'into the channel for verification that it is operable.
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3 TECHNICAL' PECIF1 CATIONS S
Rhode Island Nuclear Science Center Docket. 50-193,- License-R 95 Revision 1 1.5.2 Channel Check l
Channel check 'is a qualitative verification of -acceptablet
-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.
1.5.3 Channel Calibration
-3 Channel calibration is an adjustment of the channell such j
that its output corresponds with acceptable accuracy to i
known' values of the parameter which the channel measures.
Calibration shall encompass the entire channel, - including l
equipment actuation, alarm, or trip and shall be deemed to include a channel test.
1.6
. Limiting Conditions of Operation (LCO)
Lowest functional capability or performance levels of equipment required for safe l operation of the reactor (10CFR50.36).
1.7 Limiting Safety System Setting (LSSS)-
I Settings.for automatic protective devices _ related to those variables having significant safety functions, and ~ chosen so _that.
j automatic protective action will correct. an abnormal situation :
before a safety limit is exceeded (10CFR50.36).
1.8 Measured Channel l
q A measured channel is the combination of sensor, amplifiers,.
l and output devices which are used for the 'pur' pose ? ' of measuring the value of a parameter.
1.9 -
Measured Value The measured value of-a parameter is the value of the variable as indicated by a measuring channel.
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TECilNICAL SPECIFICATIONS
' Rhode - Island Nuclear Science : Center,
~
Docket.50-193, License R-95 Revision ~ l
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1.10 Operable 1
1 Operable means that a component' or system is capable of.
I performing its ; mended function.
1 1.11 Operating.
4 Operating means that a component or system is performing 'its i
intended function.
7-1 1.12 Operational Reactor Core An operational core -is a standard core for which the core i
parameters of excess reactivity, shutdown margin,- fuel temperature, power calibration, - and reactivity. worths-of control rods and experiments have been determined-to satisfy the requirements set forth-in the Technical Specifications.
1.13 Protective Action a
Protective action is the initiation -of a signal or the operation of-equipment within the reactor safety system in response to a-variable or. condition of the reactor facility ~ having reached 'a L 4
specified limit.
1.14 Reactivity Excess t
t Excess reactivity is that amount of reactivity that would exist.if-
]
all the control rods were moved. to the maximum reactive '
condition from the point where the reactor. is exactly critical.
i 1.15 Reactivity Limits-
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The reactivity limits are those limits imposed. on the reactor.
~
core excess reactivity.
Quantities are ' referenced to a reference'
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core condition.
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TECilNICAL SPECIFICATIONS 3
Rhode Island Nuclear Science Center-Docket 50-193. License R Revision 1 1.16 Reactivity Worth of an' Experiment-The reactivity worth of an experiment. is - the maximum absolute value of the reactivity change that would occur as-a:
result of intended or anticipated changes or ' credible malfunctions that alter equipment position or configuration.
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1.17 Reactor Operating i
The reactor is operating whenever it is - not secured or shut j
t I
down.
The reactor has two modes of operation:
natural circulation - not to exceed 0.1 MW and forced circulation - not i
to exceed.2 MW.
1.18 Reactor Safety Systems Reactor safety systems are those systems, including. their.
1 associated input channels, which are designed to '. initiate i
automatic reactor protection or to provide information 'for l
initiation of manual protective action.
1.19 Reactor Secure i
The reactor is secure when:
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1.19.1-Suberitical:
There is insufficient fissile material or. moderator. present in
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the reactor, control rods or adjacent experiments, to attain criticality under optimum available conditions of moderation and reflection, or the following conditions exist:
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The minimum number of ' neutron ' absorbing control rods are fully inserted in' shutdown 1
- position, as required by technical specifications.
j b.
The master switch is -in the off ~ position and.
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the. key is removed from the lock.
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'.h TECifNICAL SPECIFICATIONS Rhode ' island Nuclear Science Center.
Docket 50193. License R-95 Y
~-
Revision 1 j
i No ' work is-in progress involving core fuel, core -
i c.
structure, installed control;-rods,' or control rod drives unless. they are physically decoupled -
j from the control rods.
.i d.
No experiments are being moved or serviced.'
l.20 Reactor. Shutdown i
a The reactor is shut down if it is. suberitical by at ' least - the' l
shutdown margin in the. reference. core condition with: the-reactivity of all installed experiments included.
1.21 Readily Available on Call-I l
Readily available, on call shall mean a licensed senior operator
'I shall insure' that he can be contacted within ten minutes and is within a. 30 minute driving-time from the reactor ' building.
i when the reactor is; being operated by a licensed ' operator.
y 1.22 Reference Core Condition The condition of the core when it is' at ambient ~ temperature (cold) and the reactivity - worth. of' xenon is negligible <.05%
0 Ak/k.
li 4v 1.23 Regulating Blade
'The regulating blade is a control blade of low reactivity worth s
fabricated from stainless steel and used ' to. control reactor j
power.
The blade may be controlled by the. operator with-a -
manual switch or by an automatic controller.
1 1.24 Removable Experiment
-A removable experiment is any experiment, experimenta1';
- facility, or. component. of an experiment, other -than a
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permanently attached appurtenance ' to. the' reactor system, -
which can reasonably -be anticipated to be moved one 'or more times during the : life of the reactor.
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. TECHNICAL SPECIFICATIONS.
I Rhode.' island ^ Nuclear Science Center Docket 50-193. ' License R-95 Revision I j
1.25 Reportable Occurrence I
i A reportable occurrence is any. of the. following:
T 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; l
3.
A. safety system component malfunction or other i
component or system malfunction which could, or threaten to, render the safety system incapable. of q
performing its intended safety functions;.
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^j 4.
Release of fission products from a failed fuel j
element:
5.
An uncontrolled or unplanned ; release of radioactive material from the restricted area of the facility,.
6.
An uncontrolled, or unplanned. release ' of radioactive' i
o material which results in - concen trations :of 4
radioactive materials within the, restricted area in
- j excess of the limits specified in Appendix.B, Table 1 J
of 10 CFR20; a
7.
An uncontrolled or unanticipated chang'e in-
~h reactivity in excess of 0.5 %AK/K; 8.
Conditions. arising from. natural orf man-made I
events that affect or threaten to'. affect the safe.
l operation of-the. facility; M
l, 9.
An observed-inadequacy in.the implementation. of administrative or procedural. controls ~ such - that Lthe'
' ~
,s inadequacy causes or' threatens ' to cause ' the existence L or; l
development of an unsafe condition in connection' with:
j the operation of the facility.
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S TEC11NICAL SPECIFICATIONS Rhode-Island Nuclear Science Center 1
Docket 50-193, License R-951 Revision 'I t
t 1.26 Research Reactor i
A research reactor is defined as a device designed to support a
.i self-sustaining neutron chain. reaction -
for-research, _
development, educational training, or experimental purposes, and which may have provisions for the production. of; radioisotopes.
1.27 Rundown A rundown is the automatic insertion of 'the shim safety ' blades.
l 1.28 Safety Channel q
A safety channel is a-measuring channel in the reactor safety system.
1.29. Safety Limits i
Safety' limits are limits on important process variables which I
are found to be necessary to reasonably protect the -integrity of l
the principal barriers which guard against the uncontrolled release of radioactivity.
The principal barrier is. the fuel 2
element cladding.
1.30 Scram Time
.i Scram time is the elapsed time between reaching a limiting
]
safety system set point and specified control rod movement.
1 i
1.31 Shim Safety Blade A shim safety blade is' a control' blade fabricated from borated-d aluminum which is use'd to. compensate for. fuel burnup, 1
temperature,. and poison effects.
A shim -safety - blade is.
j magnetically coupled to its -drive unit allowing it to _ perform the function of a safety. blade when the magnet is deenergized.
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TECHNICAL SPECIFICATIONS ~
Rhode Island Nuclear Science ' Center L
Docket 50-193. License R-95" Revision 1 1.32 Shall, Should'and May i
i The word "shall" is - used ' to denote a; requirement..
The' word.
"should" is used to denote a recommendation.. The word "may"
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is used to denote permission, neither a requirement nor a recommendation.
,i 1.33 Shutdown Margin Shutdown margin shall mean the minimum shutdown reactivity necessary. to provide confidence that the reactor can be made suberitical.by means of the control and safety systems:
i starting from any permissible operating condition and with the most reactive rod in its most reactive position, and that -the reactor will remain subcritical without further operator action.
1.34 Secured Experiment A
Any experiment, experimental. facility, or component. of. an experiment is deemed to be secured, or'in a secured -position, if it is held in a stationary position relative to.:the reactor 1. by.
l mechanical means.
The restraint shall exert sufficient force on the experiment to overcome the expected effects. of hydraulic,.
pneumatic, buoyant, or other forces which are normal to,the i
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operating environment of the experiment -or of. forces which_-
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might arise as a result of credible malfunctions.
e 1.35 Static Reactivity Worth The static reactivity worth of an experiment is the rabsolute.
value of the reactivity change which is measurable by:
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calibrated control rod comparison methods.
1.36 Standard : Reactor Core j
A standard core is an arrangement of (14) 22-plate LEU fuel-1 elements in the reactor grid plate and may include installed.-
1 experiments.
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TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License. R-95 Revision 1 1.37 Surveillance Activities Surveillance ' activities (except those-specifically required. for.
safety when the reactor is shutdown), may be -deferred during reactor shutdown, however, they must be completed prior to reactor startup unless teactor. operation is necessary for-3 performance of the activity.
Surveillance activities scheduled to occur during an operating cycle which cannot be performed with ' the reactor operating may be deferred to the. end of the-cycle.
1.38 Surveillance Intervals
'i Maximum intervals are to provide operational flexibility and to 1
reduce frequency.
Established frequencies shall be' maintained over the long term.
Allowable surveillance intervals shall not exceed the following:
- 1. 5 years (interval not to exceed 6 years).
- 2. 2 years (interval not to exceed 2 1/2 years).
- 3. Annual (interval not to exceed 15 months).
5
-4. Semiannual (interval not to exceed 7 1/2, months).
- 5. Quarterly (interval not to exceed 4 months).
- 6. Monthly (interval not to exceed 6 weeks).
- 7. Weekly (interval not to exceed 10 days).
- 8. Daily (must be donc during the-.ucadar day) 1.39 True Value n
The true value is the actual value of a parameter.
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- TECliNICAL SPECIFICATIONS
,{
Rhode Island ' Nuclear Science ' Center-Docket 50-193, License R-95 Revision -.. I-5 1.40 Unscheduled Shutdown i
An ~ unscheduled shutdown is definedT as. any unplanned -
i shutdown of the reactor caused by actuation. of the reactor safety system, operator error, equipment malfunction, or a
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manual. shutdown in response to conditions. which. could adversely affect safe operation, not including ' shutdowns 'which
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. occur during testing or check-out. operations.
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TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193. License R-95 Revision i 2.0 SAFETY LIMITS AND LIMITING SAFETY:
SYSTEM SETTINGS 2.1 Safety-Limits n
2.1.1 Safety Limits in the Forced Convection - Mode 1
Applicability:
This specification applies to the interrelated variables associated with core thermal and hydraulic performance in the steady state with forced convection flow.
These variables are:
i Reactor Thermal Power, P a
Reactor Coolant Flow through the Core, m Reactor Coolant Inlet Temperature, Ti Height of Water Above the Top of the Core, H Objective:
To assure that the integrity of the fuel clad is maintained.
Specifications:
r 1.
The true value of reactor power (P) shall not exceed 2.4 MW and the true value of flow (m) shall not be less than Ib80 gpm.
.2.
The true value of reactor coolant inlet ~
temperature (T ) at power levels up to 2 MW -
i shall not exceed 1150F.
s 3.
The true value of the reactor coolant outlet temperature shall not exceed 1250F.
4.
The true value of water height above the active core (H) shall not be less than 23.54 i
feet while the reactor is ' operating at any power level.
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- TECHNICAL SPECIFICATIONS
'Rhode Island ~ Nuclear Science CenterT c
Docket 50-193, License R-95.
Revision -1 Bases:
i The basis for forced' convection : safetyflimitsi is. that ' the -
calculated maximum cladding temperature' in :he hot channel of the most compact core-will not be exceeded.-
The inlet -- temperature shall apply-to all power levels? up-to the 2-MW licensed power level.
The thermal hydraulic analysis (Part B, of.the SAR) shows that with l this inlet j
temperature, the outlet temperature will not exceed the?
outlet temperature scram setting.- technical. specification i
even at the' safety limit of 2.4 MW-.
j 2.1.2 Safety Limits in the Natural Convection Mode -
l!
Applicability:
This specification applies to - the interrelated variables -
(
associated with core thermal and hydraulic performance in the natural convection' mode of: operation.
These variables are:
9 Reactor Thermal Power, P j
Height of Water Above 'the Top of the Core, H '
Pool Temperature, Tp
~ Objective:
.t 1.
To assure that the' integrity of the' fuel clad -is :
maintained, f
system parameters.
j 2.
To assure consistency 'with other defined - safety.
l Specification:
1.-
The true value of the' reactor. thermal? power shall not exceed 217 kw.
2.
The height.of pool water above the core shall not be less than 23.54 feet.
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TECilNICAL SPECIFICATIONS Rhode Island Nuclear Science Center
' Docket 50-193,- License R.s Revision. I'-
3 3.
The pool temperature :does not exceed 130oF.
Bases:
d The basis for natural convection safety -limits' is ~thatL 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 Convection Mode Applicability:
LEU Fuel Temperature - Forced Convection Mode
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Objective:
This. specification applies to the-setpoint - for ' the safety.
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channels monitoring. reactor power, primary coolant flow, pool level and core inlet and _ outlet temperatures 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:
q The limiting safety system settings for reactor-
,3 thermal power (P), primary coolant flow through the.
core -(m), height of water above the top.of the core (H),
and reactor coolant inlet (T ) -and exit i
temperatures (Te) shall be as follows:
Parameter LSSS-P (Max) 2.30 MW Max ~
r m
(Min) 1600.00 gpm.
H (Min) 23.70 ft Ti (Max) 111.00F Te (Max) 121.0oF
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J TECliNICAL SPECIFICATIONS '
Rhode Island Nuclear Science. Center Docket 193, License R-95
~ Revision L1 -
Bases:
These specifications were determined - to prevent fuel temperatures from exceeding NRC temperature limits ' of 1
5300C.
This temperature was' 'found acceptable as a a
result of NUREG-1313, " Safety Evaluation Report related to the Evaluation of -Low-Enriched Uranium ~ Silicide--
aluminum Dispersion Fuel for Use in Nonpower : Reactors".
The SAR - (Part B) provides. the analyses showing fuel cladding temperatures well below-the NUREG ~ limit... at.
4 normal operation.
Flow and temperature limits - were chosen to' prevent incipient ~ boiling. even if transient power rises to the 2 MW trip limit of-2.4 MW.
Variables,
l used in the SAR were analyzed using uncertainties in flow measurement (3%) and temperature. measurement (3%). __ These uncertainties were incorporated.. in the - hot channel factors (1) used in the SAR _ thermal. hydraulic studies.
These same uncertainties were applied..to ' the inlet and outlet temperature measurements.
The LSSS for the pool level is set for a scram' upon a 2" i
drop in water level.
The reference height. of 23.7'. (16" below suspension frame base. plate. elevation) isi the
~
depth of water above the top of the active fuel sitting;in the existing reactor grid box.
This depth 'was used. in the SAR Loss of Coolant Analysis (Part B of the SAR).
The.
- t safety limit settings chosen. provide acceptable safety margins to the maximum fuel cladding temperature.. The-startup accident transient analysis l(Part A,Section XI of the SAR) also provides results showing that ' the cladding temperature limit is not exceeded.
The LOCA analysis (Design Basis Accident, Part A, Section. IX and Part B,Section X and Appendix D of the SAR) shows that the fuel cladding limit 'is not exceeded.
1 The LSSS for. the pool level.results in a higher number since the pool level scrams upon a 2" drop in water level.
- 0)
Reference:
Report on the Determination.of ~ Hot Spot Factors for the RINSC Research Reactor, August, 1989 s
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TECHNICAL SPECIFICATIONS
' Rhode Island ' Nuclear Science Center.
1 Docket 50-193. License R-95 Revision 1 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),
1 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:
~ 1.
The limiting safety system setting for reactor thermal power.(P), height of water above ' the-top of the core (H),
andi pool' water temperature (T ) shall be as follow' :
p s
Parameter LS1S P
(Max) 115.0 kw H - (Min) 23.7. ft. above top of a
'the a'ctive. core.
T (Max) 126.00F p
Bases:
The-SAR has determined that up to 217-kw 'can be removed by natural convection, however, the' existing license requirement of 100 kw operation will be maintained and with a 15% overpower trip, Il5 kw will-be the LSSS.
The pool level scram (2" drop) is the. same:
as the forced convection mode.
The pool temperature 130oF 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, e
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TECilNICAL SPECIFICATIONS -
Rhode~ IslanJ Nuclear Science Center Docket 50-193, License R-95 '
Revision 1 3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Reactivity Limits Applicability:
This specification applies to the reactivity. of the reactor core and to the reactivity worths of control rods and experiments.
Objective:
To assure that the reactor can be controlled and shut down at all times and that the safety limits will not be exceeded.
Specification:
1.
The shutdown margin relative to the reference core-condition shall be at least 1.0 %AK/K with the most reactive shim' safety rod and the regulating rod fully withdrawn.
2.
The overall. core excess reactivity including movable experiments shall not exceed 4.7 %AK/K.
3.
The total reactivity worth of ~ all experiments shall not exceed 0.6 %AK/K.
4.
The reactivity worth of each experiment shall be limited as follows:
Experiment Maximum Reactivity Worth Moveable 0.08 %AK/K Secured 0.60 %AK/K
- 5. The reactor shall be subcritical by at least 3.0
%AK/K during fuel loading changes.
6.
The reactivity worth of the regulating rod shall-not exceed 0.6 %AK/K.
1 i
Page 17 l
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TECIINICAL SPECIFICATIONS -
Rhode-Island Nuclear. Science Center.
Docket 50-193. License R-95 f,
Revision 1 1
7.
Experiments ' which could increase reactivity' by flooding, shall not' remain. in or adjacent to the core
-l unless the shutdown m argin. _ required
'in
}
Specification 3.1.1 would be satisfied after flooding.
q 8.
The temperature coefficient will be negative and surveillance will be conducted at initial startup and y
change in fuel type.
~
9.
For operation at power levels in excess of 0.1 MW; i
in the forced convection mode, all grid positions a
shall contain fuel
- elements, baskets, reflector elements, grid plugs or experimental facilities.
10.
For operation at powers in excess of 0.1 MW, the pool gate must be in its storage location.
Bases:
1 Specification 3.1.1 assures that the reactor can be shutdown from any operating condition and will remain suberitical after-cool down and xenon decay even if the rod. of the. highest.
reactivity worth should be in the fully withdrawn position.
The SAR (Part A,Section V) demonstrates; that.the' shutdown margin conservatively exceeds the.1%l in Specification'. 3.1.1.
Specification 3.1.2 limits the allowable excess ~ reactivity to. the value necessary to overcome the combined ; negative reactivity-effects of:
(1) an increase in primary coolant temperature;-(2) fission product xenon and samarium buildup in a clean core; (3) power defect due to increasing from a zero power, cold core 'to a 2 MW, hot core; (4) fuel burnup during sustained operation; and (5) moveable experiments.
Specification 3.1.3 limits the reactivity worth of experiments to values of reactivity which, if introduced as positive step _
changes, will not cause fuel melting.
i Page 18
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TECliNICAL SPECIFICATIONS I
Rhode Island Nuclear Science Center Docket c50-193. License R-95 Revision 1 Specification 3.14 limits the individual reactivity worth-of an i
experiment to a value that will not produce a' stable period of
+
less than 30 seconds and which can be compensated for by the action of the control and safety system. without exceeding any j
safety limits.
Specifications 3.1.5 provide assurance-that. the core will remain:
l suberitical during fuel loading changes.
j Specification 3.1.6 assures that. failure of the automatic control-system will not introduce sufficient - excess. reactivity to produce a prompt critical condition.
]
Specification 3.1.7 assures that ' the shutdown margin required-by Specification 3.1.1 will be met in the event of 'a positive reactivity insertion caused by the flooding of -an experiment.
Specification. 3.1.8 assures that the' power increase-is self-limiting.
Specification 3.19 will prevent the degradation of. flow rates due to flow bypassing the active fueled region _ 'through an:
unoccupied grid plate position.
Specification 3.1.10 assures that - the full volume" of the - pool water is available to provide ~ cooling of: thel core' during normal operation and in the event of a loss of coolant accident.
3.2 Reactor Safety System Applicability:
These specifications apply to the reactor -safety system and other safety related instrumentation.
. Objective:
t To specify the lowest L acceptable' level of: performance or: the minimum number of acceptable components for.the _ reactor 3
safety system and other safety.related instrumentation.
Page 19.
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4 TECHNICAL SPECIFICATIONS -
Rhodc~. Island Nuclear Science Center.
Docket 50-193, License R-95.
L(
Revision 1 1.
i To specify. the lowest acceptable level of performance or the I
minimum number of acceptable components for the reactor
. safety system and other safety related instrumentation.
a 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 of channels and the indicated maximum or-1 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 j
exceed I
second in_ accordance with Technical l
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:
l Neutron flux level scrams provide redundant automatic i
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, j
Section XI and predicts a safe fuel clad temperature.
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_Page 20 l
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r
t TECHNICAL SPECillCATIONS Rhode. Island Nuclear Science Center Docket 50-193, License R-95 Revision :1 i
TABLE 3.1 REQUIRED SAFETY CHANNELS
~ Reactor-Reactor Safety Minimum Operating Mode System Component / Channel Required Function in Which Required -
[
l Reactor Power Level 2
Automatic Both Modes scram when t
2115% of l
range scale with 2.3 MW max Coolant Flow Rate 1
Automatic Forced Convection scram at above 0.1 MW 51600 gpm-1 Seismic Disturbance 1
Automatic Both Modes.
scram at Modified Mercalli Scale IV I
Bridge Misalignment 1
Automatic ~
Forced Convection scram above 0.1 MW Pool Water Level 1
Automatic Both Modes scram at 16" below suspension l
frame base plate elevation i
Coolant Outlet Temperature 1
Automatic
. Forced Convection-scram above 0.1 MW 121oF i
Page 21 l
TECilNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 Revision 1-Reactor
~
Reactor Safety Minimum Operating Mode System Component / Channel Required Function in Which' Reauired Bridge Mov'ement 1
Automatic Both Modes scram Coolant Gates Open 1
Automatic Forced Convectica scram if above 0.1 MW either the coolant riser or coolant
~
downcomer gates open Detector High Voltage Failure 3
Automatic Both Modes scram if Voltage decreases 50V max Log N Period 1
Automatic Both Modes' scram if period s4 see No Flow Thermal Column 1
Automatic Forced Convection scram above 0.1 MW Manual Scram 2
Manual Both Modes Switch (console, bridge) scram Page 22
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TECilNICAL SPECIFICATIONS -
2 Rhode Island Nuclear Science Center.
Docket 50-193, License R-95 Revision 1 TABLE 3.2 Required Safety - Related Instrumentation Minimum
. Reactor Number Operating Mode Instrumentation Setpoirn Required Function In Which Reqd.
1.
Reactor Coolant s llloF 1
Alarm FC20.lMW Inlet Temperature 2.
Reactor Coolant s 1190F 1
Alarm FC20.l MW.'
Outlet Temperature 3.
Log Count Rate
<3 cps 1
Rod with-
'Both Modes -
drawal interlock 4.
Servo Control 230 sec 1
Auto Control Both Modes Interlock (fullout)
Interlock -
~
Facility. Radiation (a)
Monitoring System 5.
Building Air Gaseous 2.5 x l-
' larm Both Modes A
Exhaust (Stack) normal particulate 2 x normal 6.
Reactor Bridge 2 x normal Alarm Both ' Modes 7.
Fuel Safe 2 x normal Alarm Both Mo' des -
or 5mR/hr, which ever is higher Page 23
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7 TECIINICAL SPECIFICATIONS.
Rhode Island Nuclear Science. Cente.
~ Docket 50-193. License R-95
. Revision 1 Minimum Reactor Number Operating : Mode j
Instrumentation Setpoint Reauired Function In Which Read.~
l 8.
Thermal Column
.2 x normal Alarm Both Modes -
or 2mR/hr,
~
which ever is higher 9.
Heat Exchanger 2 x normal
'Ala rm
.Both Modes-10.
Primary 2 x normal Alarm Both Modes Demineralizer (Hot DI) 11.
Continuous Air 2 x normal
-1 Alarm Both Modes Monitoring Unit NOTES 1
r (a)
The facility radiation monitoring system consists of 8 radiation detectors which _ alarm and readout in the control room except for #11 which has ~a local alarm and readout only..
The normal setpoints for this system are. shown in Table 3.2.
.Use of higher than normal setpoints will require approval-of the -Director or the Assistant Director.
Any senior operator : member may -
adjust a setpoint lower than the normal value.
.a (b)
- The reactor shall not be continuously operated : without a minimum of one radiation monitor on the experimental level of the reactor building and one monitor ' over the reactor ' pool.
operating and capable of warning personnel of high-radiation levels.
)
Page 24
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TECHNICAL SPECIFICATIONS j
1 Rhode Island N6 clear - Science Center:
1
' Docket 50-193. - License R-95 i
Revision 1 3.3-Coolant Water
,l (a)
Primary Coolant Water 3
Applicability:
This specification applies' to the limiting conditions for primary coolant pH, resistivity, available pool water-volume and radioactivity.
Objective:
q To maintain ' the primary coolant in a condition to a
minimize the corrosion of the primary coolant system,-
fuel cladding, and other -reactor components, and 'to assure proper conditions of coolant for normal and 3
cmergency requirements.
1 Specification:
1.
The primary 1 coolant. pH shall be maintained
.i between - 5.5 and 7.5.
2.
The primary coolant resistivity shall be maintained
'at a
value -
greater than 500Kohms/cm (conductivity-2micromhos/cm).
i 3.
The r ncentration of radioactive materials in j
the pamary coolant is maintained at a' level such that.the reading on - the reactor bridge radiation monitor does not exceed 10. mrem /hr.
I Bases:
Experience at this and other facilities. has shown. that the j
maintenance of-primary coolant system - water quality cin 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
(
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TECHNICAL SPECIFICATIONS-Rhode Island Nuclear-. Science ~ Center j
Docket 50-193. License R-95 Revision.. I
]
water purity to control activation of coolant water impurities.
1
- The requirement in specification 3.3.3 ensures that - the presence of unusual impurities or corrosion products' is J
detected.
(b)
Secondary Coolant Water Applicability:
--v This specification applies to the limiting conditions for secondary coolant pH, cycles of chloride, resistivity and radioactivity.
Objective:
To maintain the secondary coolant in such a condition as-
-3 to minimize corrosion and/or scale buildup on the. heat exchanger tubes and to detect a primary' to secondary system leak.
j Specification:
d 1.
The secondary coolant water pH shall be maintained between 5.5 and 9.0.
2.
The sample will be analyzed for the presence of-.
=
sodium-24.
1 Bases:
d 1
a The facility has maintained the above _ coolant _ water.
J conditions for many years based on consultant -
recommendations and have good results. in' maintaining H
heat exchanger tube and shell cleanliness.-
Radioactivity in the secondary system would indicate a leak and therefore samples are analyzed for detectable' i
concentrations of sodium-24.
Page 26
q eN TECHNICAL SPECIFICATIONS -
l Rhode Island Nuclear Science Center l
7 Docket 50-193 License R-95 i
Revision 1-3.4,' 3.5, 3.6 Confinement and Emergency Exhaust System j
and Emergency Power Applicability:
This specification applies to the operation of the. reactor l
confinement and emergency exhaust ~ system which must be operable during reactor operation, ' fuel handling.and an'y operation that could cause the spread of' airborne radioactivity' j
in the ' confinement area.
l Objective:
To assure that the confinement and emergency exhaust system is capable of operation to mitigate the consequences of possible release of radioactive materials resulting' from reactor j
operation, fuel movement and handling of radioactive: material.
.q Specification:
-?
.i The reactor shall not be operated unless the 'following equipment is operable and/or conditions met:
Equinment/ Condition Function-Personnel access doors To maintain to reactor closed. (except confinement ~
j for entrance ' and egress).
system integrity Roof hatch closed.
l Truck door closed; 1
1 Reactor Room fresh air To maintain intake valve and exhaust confinement ventilation valve _ to-the system -integrity '
stack are open; Initiation system for
.To initiate -
confinement ~ isolation, system-i.e.' evacuation buttons operation and-and alarm ' horns; alert personnel' l
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.Page.27 i;
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TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center -
Docket 50-193, License. R-95 Revision ~1 Equipment / Condition Function Emergency cleanup exhaust To maintain a system; negative buildings pressure without?
unloading any
~ large fraction 'of.
possible airborn'e ?
l activity
'i Emergency generator.
To insure. power.
source to clean upj3 system.and ~otherf 4
designated systems Bases:
i The confinement system will be activated by. depressing _ any one. of five emergency evacuation buttons when an unsafe l
radiological situation develops as defined in facility-operating and emengency procedures.
In. the unlikely event of a ~ release o
of fission products, or other airborne radioactivity, the confinement isolation initiation system will' secure the normal ventilation exhaust - fan, will bypass 'the normal ventilation.
j supply up. the stack, and will close the normal" inlet and. exhaust j
valves.
In confinement, the. emergency exhaust system will tend to maintain a
negative ' building pressure with a
[
combination of controls intended to prevent. unloading - any large fraction of airborne..' activity.
The emergency exhaust -
1 purges the building air through. charcoal and - absolute filters and controls the discharge which 'is ' diluted' by. supply ' air through a 115 foot stack.
3.7 Radiation Monitoring Systems and -Effluents s
3.7.1 ~ - Radiation Monitoring Systems ly Applicability:
This specification applies to the availability of radiationi monitoring equipment which must be - operable during Page 28
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TECHNICAL SPECIFICATIONS-'
Rhode ' Island Nuclear Science Center Docket 50-193. License R-95 Revision 1 reactor operation, fuel movement and handling' of radioactive materials in the reactor building.
i Objective:
J 1
To assure that radiation monitoring equipment is available for evaluation of radiation conditions and that the release of airborne radioautive material is maintained 4
below the limits established m 10CFR20.
j Specification:
1.
When the ' reactor is operating, gaseous ~ and particulate sampling of the stack effluent shall be monitored by a stack monitor with a readout in the control room.
The particulate activity monitor and the j
gaseous activity monitor for the facility exhaust stack shall be operating.
If either
~
unit is to be out ~ of service, cither the reactor shall be shut down or the unit ~ shall V
be. replaced by one of comparable-f monitoring capability;
.s
.2.
When the reactor is operating, at least one-constant air monitoring unit ' (Table 3.2.10) -
j 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 minimurn of ~. one area radiation monitor- (Table 3.2.7) on the " ground 1
floor-level" of the reactor buildin'g and one l
area monitor (Table 3.2.5% over the reactor-pool -(reactor bridge)- operat ng and capable; of.
warning personnel of high radiation levels.
j 1
h 9
Page 29
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.. i TECliNICAL SPECIFICATIONS
+
.Rhode Island Nuclear Science Center Docket 50-193. License R-95 Revision 1
- In order to continue operation of the reactor, 1
replacement of an inoperative monitor must be. made within 15 minutes L of recognition of
- failure, except that the. reactor may be i
operated in a. steady-state power mode 'if the monitor is replaced ; with portable gamma-
~'
sensitive instruments hav'ing their own alarm.
Bases:
l i
9 A continuing evaluation of the radiation levels within the,.
reactor building will. be made to assure the safety, ofr l
personnel.
This is accomplished by the moriito'ri.ng, a
systems described in Table 3.2.
3.7.2 Effluents a.
Airborne Effluents
-i i
Applicability:
This specification applies to the - monitoring or. airborne effluents from the Rhode Island Nuclear Science ~ Center (RINSC).
Objective:
l To assure that containment integrity is maintained during j
reactor operation and that the release of airborne radioactive' material from the RINSC is maintained below ;
the limits established. in 10CFR20.
i Specification:
i
!q 1.
The concentration of radioactive materials in the l
effluent' released from the facility exhaust stacks shall not: exceed 105. times the' concentrations specified in 10CFR20, Appendix B,: Table _II, when averaged over time periods permitted by 10CFR20.
I Page 30 l'
m JTECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center _
' Docket 50-193. License R-95 Revision 1
[
Bases:
f The limits established in specification 3.7.2. incorporate ;a dilution factor of 105 for effluents released L through the.
exhaust stacks.
This dilution factor is more ' conservative.
than that calculated from actual meteorological data.
j which represents the lowest dispersion factor determined ~
l and 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.
j Rhode Island Nuclear Science Center will be far below the:
i lin'its of 10CFR20.
(Refer to letter dated April 16, 1963 j
sent to the NRC in connection-with license questions.)
This dilution factor is used for calculating maximum i
ground concentration down wind for noble gases. The SAR contains calculations for doses from the iodine at the 48 l
meter distance.
a.
Liquid Effluents Applicability:
i q
This specification applies to. the monitoring-of radioactive -
j liquid effluents from the Rhode Island. Nuclear _ Science l
Center.
i Objectives:
a The objective is :o. assure that ' exposure W theE public resulting from. the release.of liquid effluents..will be.
a within the regulatory limits arid consistent (vith as low' as' H
reasonably achievable requirements.
l i
Specification:
The liquid waste retention tank' discharge shall be j
batch sampled and the gross activity per unit ' olume i
v l.
Page 31 i
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i 0
TECHNICAL SPECIFICATIONS -
Rhode~ Island Nuclear Science Center -
i Docket 50193. License R-95 Revision I ~
determined before release.-
All off-site releases shall-be ' directed into the municipal sewer system.
Bases:
~
All radioactive liquid and solid wastes disposed of' off-site.
shall be within the limits established by.10CFR20 or.shall
-be removed from the site by a-commercial licensed organization.
3.8 Limitations on Experimen :s
- Applicability:
This specification applies to experiments to - be installed in the reactor and associated experimental-facilities.
4 Objectives:
To prevent damage to the reactor or release of radioactive materials in excess of 10CFR20.
Specification:
The reactor shall not be operated unless the following conditions-governing experiments exist; 1.
All materials to be irradiated shall-be either corrosion resistant 'or encapsulated within corrosion resistant containers-to prevent interaction with; reactor components or pool water.
Corrosive j
materials shall be doubly encapsulated.
2.
Irradiation containers to be used in the reactor, in which a static pressure will exist or' in which.. a pressure buildup is' predicted, shall be ' designed and_-
l test'ed for a pressure exceeding the maximum j
expected by a factor of 2.
Page 32 f
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P TECilNICAL SPECIFICATIONS Rhode Island' Nuclear Science Center-Docket 50-193. License R-95 '
Revision.1 3.
Fissionable materials shall 'have total iodine ' and strontium inventory less than that allowed by the facility by-product license.
-4.
Explosive materials, in _ any quantity, shall not. be allowed in the recctor pool or experimental:
facilities.
5.
All experiments shall be designed against failure from internal and external heating at the true values associated with the LSSS for reactor power.
a level and other process parameters.
i 6.
Experimental apparatus, material or equipment to be irradiated shall be positioned so as not to cause shadowing of-the nuclear j instrumentation, interference with contr_ol. blades, or other perturbations which may interfere with safe operation of the reactor.
7.
Cryogenic liquids shall not be used. in any' experiment within - the reactor pool without approval from the Nuclear Regulatory Commission.
]
8.
No highly water reactive materials shall-be used in an experiment in the reactor pool.
5 1
9.
No experiment should' be '. performed unless the l
material content (with the exception of trace' constituents) is - known.
~ 10.
If a capsule : fails -and releases ~ material which could damage' the reactor fuel or structure: by corrosion or-other means, removal and physical _ inspection shall
- be performed to-determine ' the ~ consequences. and
]
need for corrective : action.
The c results ' of the inspection -and any _ corrective action taken shall be T.
m reviewed-' by the Director,.or his ~ designated
~ lternate,_ and determined to be satisfactory before a
operation of the reactor is resumed.
Page 33
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a-
TECHNICAL SPECIFICATIONS Rhode Island. Nuclear Science Center -
Docket 50-193, License R-95 i
~
Revision l'
Experimental materials, except fuel materials, which could off-gas, sublime, volatilize, or produce aerosols under: (1) normal operating conditions of.
}
the experiment or reactor, _ (2)' credible; ac' ident c
conditions in the reactor, and (3) possible accident
'i conditions in the experiment. shall be' limited in activity such that: if 100% of the gaseous activity 'or radioactive aerosols produced escaped ~ to-the
.i reactor room or the atmosphere, ; th'e airborne concentration of radioactivity averaged over a ' year l
would not exceed the occupational limits for 4
maximum permissible concentration.
l In calculations pursuant to the above, the following assumptions shall be used:
(1) If the effluent' from.
an experimental facility exhausts 'through du'ctwork which closes automatically on high ' radiation level, at least 10% of the gaseous activity for 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
-i least 10% of these vapors can escape.
(4) Limits for?
maximum permissible concentrations are specified L 1
in the appropriate section of 10CFR20.
a Bases:
!o 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 ini 3.1,. serve as a _ guide for the review and approval ofy new and untried experiments by the operations' staff as well as the j
Reactor Utilization Subcommittee.
t Specifications 3 and 4 are self explanatory.
Page 34 a
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TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50;193, License R-95 Revision i Specification 6 assures that no physical or nuclear interferences compromise the safe operation of the reactor by, for example,;
tilting the flux in 'a way that could effect the peaking factor used in.the Safety Analysis.
. Specification 7 insures NRC review of experiments containing or using cryogenic materials.
Cryogenic ~ liquids present structural
[
and explosive problems which enhance the -potential 1 of an experiment failure.
' Specification 10 is self explanatory.
I 6
3.9.
Reactor Core Components a.
Beryllium Reflectors I
Applicability:
This specification applies to - neutron flux damage'.to the standard and plug type beryllium reflectors.
Objective:
A To prevent physical damage to-the beryllium reflectors =in-the core from accumulated neutron flux exposure.
j Specification:
1.
The maximum accumulated neutron flux shall be 1x1022 neutrons /cm2, Bases:
The RINSC-SAR (Part A =Section VIII) has addressed this-limit as a conservative limit.
b.
LEU Fuel Page 35
4 8
TECIINICAL SPECIFICATIONS.
Rhode Island Nuclear! Science Center -
1 Docket 50-193, License. R-95 Revision i i
i Applicability:
This specification applies to.the physical condition %1 the fuel elements.
Objective:
To prevent operation with damaged _ fuel elements.
-q Specification:
Fuel elements to be inspected for physical defects.
?
and reactor core ~ box fit -in - accordance. with; j
manufactured specifications.
Bases:
The RINSC inspects and tests each fuel element for reactor core box. fit in accordance with. written -
procedures to assure operation with. fuel elements f
that are not damaged and meet specifications:
i j
-i
.{
4 t
i
'I
~!
i fi i
l t
Page 36 i
'1 TECHNICAL SPECIFICATIONS Rhode Island Nuclear-Science Center Docket 50-193, License R-95
'I Revision - 1 4.0 SURVEILLANCE REQUIREMENTS Surveillance tests for Reactivity Limits (4.1), Reactor Safety j
System (4.2), Surveillance of Experiments (4.8) and ' Reactor 1
Components (4.9) may be. deferred - for periods of reactor shutdown providing they are performed prior to restart '(ANS 15.1, 4.1).
Surveillance tests for the following will be performed as stated in the appropriate sections:
Water Coolant Sytem (4.3) j Confinement and Emergency Exhaust System (4.4, 4.5, 4.6)
Radiation Monitoring System and Effluents (4.7) 1 4.1 Reactivity Limits Applicability:
This specification applies to the surveillance ' requirements for -
reactivity limits.
Objective:
To assure that the reactivity limits of Specification 3.1 are - not exceeded.
Specification:
1.
Shim safety blade reactivity worths and insertion rates shall be measured:
a.
annually; b.
whenever the core is changed from the startup core to the three other cores as-analyzed and specified in the. SAR (Part A, -
y Section V).
I 2.
Shim safety = blades shall be visually inspected and -
checked for swelling at least annually.
Page'37
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s
-.--.w-.
=,,
+
s.n s,
i
, t<.
TECliNICAL SPECIFICATIONS.
Rhode Island. Nuclear Science Center Docket 50-193. License R-95 t.
Revision 'l 3.
The. reactivity worth of all ' experiments shall be-measured prior to the experiment's initial use.
Bases:
Specification 4.1.1 will assure that shim. safety blade. reactivity.
worths are not degraded or changed by core arrangements.
Shim safety _ rod inspections are the single, largest source.of radiation exposure to facility personnel.
In order to-' minimize personnel radiation exposure and provide an inspection frequency ~ that will detect early evidence of swelling and cracking, an annual inspection interval was selected for Specification 4.1.2.
The specified surveillance relating to the - reactivity worth of experiments will assure that the reactor is not operated for; extended' periods before determining the reactivity. -worth ' 'of '
experiments.
This specification also provides assurance that-1 experiment reactivity worths do not-increase beyond th e_ '
established limits due to core configuration changes.
4.2 Reactor Safety System 1
Applicability:
This specification applies to tla surveillance of the.. reactor safety system.
Objectivei To - assure that-the reactor safety system is operable _as?
>i required -by ' Specification 3.2.
j Specification:
b i
~
1.
-A channel test of. the neutron flux level safety 1
- channels.and -period safety channel - shall be performed' i
.I Page 38
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TECHNICAL SPECIFICATIONS' i
Rhode' Island Nuclear Science - Center Docket 50-193, License R-95 Revision i 7
a.
Prior to each reactor startup following a period when the reactor was secured; b.
After a
channel has been repaired or deenergized.
2.
A channel calibration of the safety channels listed in Table 3.1, which can be calibrated, shall. be l
performed annually.
3.
The radiation monitoring system required in Table -
3.2 shall be operable prior to every reactor -
startup for which safety system channel tests are required as in 4.2.1.
-If the system _ has been.
repaired, the system shall be operable prior to use.
o 4.
Shim safety blade release-drop time shall~ be measured annually.
i 5.
Shim safety rod. release-drop time shall: be measured whenever the shim safety rod's c' ore.
location is changed or whenever maintenance is performed which could effect the rod's ~ drop ' time.
(Specification 3.2.3) 6.
Shutdown Margin (Specification 3.1.1)
The shutdown.. margin shall be- ~ determined annually.
It shall be determined when a new core is configured as described in.the1SAR '(Part - A, Section. V).
The determination ~ will be made in accordance with -operating-procedures.
7.
Excess ~ Reactivity. (Specification 3.1.2) i f
The' excess reactivity shall' ' be,. determined i
annually.
It shall be determined _ when a :new core' j
~
is - configured as described. in the SAR (Part-A, t
Section_ V).
The determination will be made. in accordance -with operating. procedures.
9 Page 39 a.
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TECilNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193. License R-95 '
Revision 1-l i
t 8.
Reactivity Insertion Rate (Specification 3.2.4)
{
The. reactivity insertion rate shall' be measured -
1 annually.
It shall be determined when a new core.
is configured as described in the SAR (Part A,Section V).
The determination will be made in accordance with written procedures.
Bases:
Prestartup tests of.the safety system channels ~ assure their operability.
Annual calibration detects any long term drift that is not J detected by normal intercomparison of channels.
The channel operability check of the~ neutron. flux level channels
- assures that the detectors are properly. adjusted tol accurately monitor the parameter they are measuring.
Radiation monitors are checked-for. proper operation in l
Specification 4.2.3.
Calibration and setpoint verification involve j
use of a calibration source and significant personnel radiation j
exposure.
It is determined that annual calibration of radiation ~
monitors is adequate since they. displayed excellent ~ stability over many years of operation.
j; a
The. measured.- release-drop times of the shim safety blades.
have been consistent over many years.- - Annual check Lof these parameters is considered adequate ;to detect any ' deterioration
[
which could change theLrelease-drop. time.
Binding or rubbing -
caused by rod misalignment could result from maintenance:-
therefore, release drop times will be checked: after -such maintenance.
4.3 Water Coolant System a.
Primary Coolant System Applicability:
This ' specification applies to the surveillance ' of - the primary coolant system.
Page 40 tu-pe.
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TFCHNICAL SPECIFICATIONS Rhode id Nuclear Science Center L ket 50-193. License R-95 Revision 1 Objective:
To assure high quality pool water and to detect the deterioration of components in the primary coolant loop.
Specification:
1.
The pH of the primary coolant shall be measured weekly.
2.
The resistivity of the primary coolant shall be measured weekly.
3.
The radioactivity of the primary coolant shall be analyzed weekly for gross activity and quarterly for isotopic activity.
4.
Pool water level scram switch shall be checked for operation monthly.
5.
Pool inspections shall be made annually in accordance with operating procedures.
6.
Pool level shall be visually inspected daily in accordance with operating procedures.
Bases:
Regular surveillance of pool water quality and radioactivity provides assurance that pH and resistivity changes that could accelerate the corrosion of the primary system components would be detected before significant damage would occur, and that the presence of leaking fuel elements in the reactor is detected.
The low pool level switch is checked for operation monthly.
Upon a one inch pool level drop, the automatic fill begins; upon a two inch drop, the reactor scrams (if operating) and a local and remote alarm sounds.
The remote alarm is continuously monitored offsite.
Page 41
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TEC11NICAL SPECIFICATIONS.
Rhode Island Nuclear Science Center Docket 50a193, License R-95 Revision I Annual pool system inspections are made. to. provide assurance that other cooling system components (eg, gate valves, gasketing etc.) are functioning properly.
b.
Secondary Coolant System Applicability:
This specification applies to. the surveillance of the secondary coolant water.
Objective:
To assure the conditions of the coolant meet specification 3.3.(b) and to detect a primary to secondary water leak.
Specification:
1.
The pH shall be measured weekly during reactor operation.
t 2.
A sample shall be drawn and analyzed --weekly for sodium-24 activity, during reactor. operation.
3.
The gross radioactivity shall - be measured daily, during reactor operation.
Bases:
Proper -secondary coolant conditions are obtained by blowdown and makeup water systems which maintain ~
the proper water quality pH. Radioactive concentrations -
are measured in accordance with written procedures.
A radiation detector, mounted in the. cooling tower basin, displays gross radioactivity in the control room.
The system has an alarm to. notify the operator who will take.
action to secure blowdown wate.r:from entering the sewer system.
If this-system fails, sampling or another detection method can be employed.
Page 42 1
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Vi TECllNICAL SPECIFICATIONS -
i Rhode Island Nuclear Science Center Docket 50-193, License R i Revision I 4.4, ~ 4.5, 4.6 RINSC Confinement and Emergency Exhaust System i
Applicability:
This specification applies to the surveillance of the facility openings and dampers.
3
?
Objective:
1 To assure that the condition of the closure devices for the-building openings are in satisfactory condition and. to assure l
their ability..to provide adequate confinement of any airborne radioactivity.. released into the building.
Specification:
1.
The confinement and emergency exhaust system described in Specification 3.4 shall. be tested weekly for operability and after any maintenance that could affect system operability.
The system operation is as described in the operating procedures and as.herein discussed. The building cleanup system shall be activated, by pressing an
~
evacuation button, then automatically:
a.
the evacuation horn sounds b.
the building ventilation blowers deenergize (air conditioner,- exhaust. blower, 'off ~ gas blower, rabbit system blower, - heating > system-blowers);.
c.
. the building ventilation dampers close (air-intake and : exhaust system);
d.
the. cleanup system blower (through the
-scrubber filter) and air dilution ~ blower (chem
' lab) are. energized; Page 43 L
1
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TECIINICAL SPECIFICATIONS Rhode Island Nuclear Science Center 3
Docket 50-193, License R '
Revision -. I 4
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 a
room;
- j f.
the exhaust rate through. the. cleanup system shall not exceed 4500 CFM with not more-than 1500 CFM coming from the reactor building.and passing' through the scrubber filter.
The remaining 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.
9 a.
Building ventilation blowers: and dampers -
(including solenoid valves, pressure switches, piping, etc.);
b.
Personnel access and reactor room' overhead doors.
..t 3.
The testing and maintenance of the emergency.
generator will be performed in ~ accordance with-the-RINSC operating procedures and manufacturer recommendation.
e.
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 a
Page.44 I
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TECilNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193 License R-95 Revision I openings in the event of a release of airborne activity into the building.
The weekly testing of the emergency generator (operating procedure) assures reliable response and operation.
The monthly load testing (operating procedure) assures proper handling of expected system loads.
The emergency generator system has annual maintenance performed in accordance with manufacturer recommendations.
4.7 Radiation Monitoring Systems and Effluents a.
Airborne Effluents Applicability:
This specification applies to the surveillance of the monitoring equipment used to measure airborne radioactivity.
a Objective:
The objective is to assure that accurate assessment of airborne effluents can be made.
Specification:
1.
The particulate air monitors shall be calibrated annually.
2.
The gaseous activity monitor shall be calibrated annually.
3.
A channel check of the stack monitor and the main floor monitor shall be performed daily when the reactor is in operation.
Bases:
Experience with the electronic reliability and calibration stability of the units used by the Rhode Island Nuclear Page 45
m 4_
TECIINICAL SPECIFICATIONS Rhode Island Nuclear Science Center '
l
~
Docket 50-193. License R-95~
Revision 1 Science Center Reactor demonstrates th'at the above periods are reasonable surveillance frequencies.
b.
Liquid Effluents.
Applicability:
This specification applies to the surveillance of ~the monitoring equipment used to measure the radioactivity in liquid effluents.
-)
Objective:
The objective is to assure that accurate assessment + of.
A liquid effluents can be made.,
t Specification:
1.
The monitoring equipment used to measure.
l the radioactive concentrations in. - the waste retention tanks shall be calibrated ' annually.
2.
The contents of every tank released shall. be 9
sampled and evaluated for radioactive concentrations and pH prior to -its release.
i Bases:
j 1
Experience with the electronic reliability and. calibration'-
stability of the units used by the Rhode1 Island -Nuclear Science Center Reactor demonstrates that the.above-periods are _ua.;onable ~ surveillance frequencies.
1 4.8 Surveillance of Experiments u
{
Applicability:
/
This specification -applies to the surveillance of experiments
)
- and-the ' limitations on experiments as. described in Technical Specification 3.8.
.I
- i Page 46 I
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1 TECliNICAL SPECIFICATIONS-i Rhode Island Nuclear Science Center Docket 50-193, License R-95 Revision 1:
Objective:
To. assure that ' the experiments and their limitations are reviewed with respect to 10CFR50.59 for reactor.. operation and personnel safety and prevent. release of radioactive' materials in excess of 10CFR20.
Specification:
Experiments shall be
- reviewed, approved and. properly installed and operational in accordance with written operating procedures.
Experiments in progress shall undergo a review annually.
Bases:
J Review of the experiments _ using the appropriate LCO's and the Administrative Controls assures that the insertion.of j
experiments will not negate the consideration implicit in the Safety Limits.
4.9 Reactor Core Components Applicability:
This specification applies to the surveillance requirements for Icactor core components affecting reactor power.
l a.
Beryllium Reflectors 1
Applicability.:
This ' specification applies L to;. the - surveillance of beryllium.
lifetime for the ' standard and. plug ' type beryllium --
reflectors.
Page.47
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W TEC11NICAL SPECIFICATIONS' Rhode. Island Nuclear Science Center Docket 50-193. License R-95 Revision 1
[
Objective:
i To prevent physical ' damage to the beryllium reflectors in:
the core from accumulated neutron flux exposure.
Specification:
The maximum accumulated neutron flux shall ' be lx1022 neutrons /cm2 The exposure shall be ' determined annually in. accordance with the operating procedures.
1 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.)
' 2 c.
LEU Fuel Elements l
Applicability:
This specification applies to -surveillance of LEU fuel'.
elements.
l e
Objective:
To prevent operation with damaged l fuel elements and verify the physical condition of the fuel element.
Specification:
I
)
The ' fuel elements shall be visually examined.and
[
functionally. fit -into the core grid box annually.
l 1
-4 s
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TECHNICAL-SPECIFICATIONS Rhode Island Nuclear Science Center -
)
Docket 50-193, License R-95 Revision 1
=.
Bases:
l Fuel elements are initially inspected for ' manufactured.
specifications and then inserted into - the ~ grid box-in' accordance. with QA/QC program requireme'nts for functional-fit.
Core reloading is performed in accordance 4
with operating procedures.
Routine fuel movements - are logged and visual inspections are. conducted. during fuel movements.
Pool sampling - also is. used to detect a 4
ruptured element ~ Tech. Spec. 4.3.3).
The fission density,
(
limit for this reactor-cannot be exceeded ~(reference SAR, Part A,
Section VI).
Burnup calculations are made l
. quarter y (4.9.1).
3 e
W t
i
{
i h
^ i i
i s
. 7 i.-
I Page 49 1
l 1
-9 1
-l TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket.50-193. License R j Revision 1 5.0 DESIGN FEATURES The basic ' design features of the facility _ are described in s
" General Electric's Operation and Maintenance Manual-GEI-l 77793", Oct. 1962, also in the '" Safety Analysis Report for the Low Enriched Fuel Conversion of the' Rhode Island Nuclear j
Science Center Research Reactor". Rev.
1, 1992.
-These _
documents are on file at the Science Center.
A ' general-description of the important components is included -in the following sections.
1 5.1 Description The reactor is located at the Rhode Island Nuclear Science a
Center on 3
acres of a 27 ocre former military _
reservation, originally called Fort _ KearneyL and now called-the Narragansett Bay Campus of-the University of Rhode Island.
The 27-acre reservation' is controlled ' by' the State of Rhode Island through the University of Rhode Island.
The reservation is in the Town of Narragansett, Rhode
- Island, on the west shore of ~ Narragansett B ay,-
approximately 22 miles. south of ~ Providence, Rhode i
Island, approximately six miles north of the. entrance of the Bay from the Atlantic Ocean.
The _ Rhode Island Nuclear Science Center and various buildings used for:
research, education and training z purposes. are.-located. on this 27-acre campus.
5.2 Reactor Fuel The fuel assemblies shall be of-the MTR type, consisting of
-j plates containing uranium silicide fuel enriched. to less than 20% in the isotope U-235 clad with aluminum.
Each__
j fuel element will contain 22 plates for a total of 275-grams of U-235 per element.
tj li 5.3 Reactor Core The reactor core consists of a 9 x 7 array of 3" square; j
modules with the 4 corners _ occupied by posts.
The
-l reference core for these technical: specifications consists of l
I e
- [
Page 50 1
~. - -
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science : Center Docket 50-193, License R-95
-i Revision 1 l
14 standard LEU fuel elements arranged symmetrically within 4 safety control blades as-shown in Figure 4 of the -
SAR (Revision 1,Section V, Dec.1992) as approved by the l
17, 1992).
NRC in the conversion order (letter of March
?
5.4 Reactor Building f
reactor shall be housed in a building ' capable of The meeting the following functional requirements:
i In the event of an accident which could involve the release of radioactive
- material, the building air shall be exhausted j
l confinement through a clean-up system and ~ stack creating ~ a..
-l flow of air into the building with a ' negative j
differential pressure between the building and the The building shall be gas El outside atmosphere.
negative differential.
tight in the sense that a maintained dynamically with all I
pressure can be The confinement and gas leaks occurring inward.
shall become operative when a
cleanup systems l
building evacuation button is pressed.
This-action
- i turn off all ventilation fans and the air.
e (i) shall:
conditione.r system and (2) close the - dampers on.
j the ventilation intake. and - exhaust, other than No those which are a.part of the ~ clean-up system.
further action shall be required to establish
?
confinement and place the clean-up system in.
1
-j An auxiliary-electrical-power system -
operation.
shall be provided at the site to insure the' availability of power to operate the clean-up system.
The reactor building exhaust-blower. operates. kn
'i additional exhaust - blower (s) which conjunction, with provide dilution air from non-reactor building _ sources.
1 j
clean-up' system shall exhaust _ air Upon activation, the j
from the reactor building through a filter andL a 115 fo'ot:
]
a pressure less ' than atmospheric creating i
high. stack, clean-up filter shall contain a-roughing The pressure.
i Page 51
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m.
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TECHNICAL SPECIFICATIONS Rhode Island. Nuclear Science Center-Docket 50193. License R-95 Revision 1 filter, an absolute particulate filter, a ' charcoal filter for removing radioiodine and an: absolute filter'. for ' removing charcoal dust which may be; contaminated with radioiodine.
Each absolute filter: cartridge shall be individually tested and certified by the manufacturer to have an efficiency of not less than 99.97% when ~ tested with 0.3 micron -diameter dioctylphthalate smoke.
The-minimum removal efficiency of the charcoal' filters" shall j
be 99%,
based on ORNL data - and measurements performed locally.
Gases from the beam ports, thermal column, ' pneumatic -
system, and all other radioactive gas - exhaust points. shall-be exhausted to the stack through a roughing and absolute filter system.
7 5.5 Fuel Storage All reactor fuel element storage facilities shall be designed.
in geometrical configuration where kerr is 'less than 0.8 under flooding with water.
A maximum of. four. fuel elements will be stored in the-fuel safe with no two elements in ' adjacent positions in the storage box.-
-The-adjacent row will be an empty box.
Irradiated fuel is stored in the underwater storage racks as described in the SAR (Part A,Section XII).
- i 5
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f 1
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=
i TECilNICAL SPECIFICATIONS l
Rhode Island Nuclear. Science. Center
.[
Docket 50193, License R-95 Revision I i
6.0 ADMINISTRATIVE CONTROLS 6.1 Organizauan and Management 1.
The Rhode Island Atomic Energy Commission (RIAEC) shall have the responsibility for the safe operation of the reactor.
The organization of RIAEC is shown in Figure 6-1.
The RIAEC shall appoint a Director and a Reactor Utilization Committee consisting-of a
minimum of five members, as follows:
a.
The Director b.
The Radiation Safety Officer
[
h A qualified representative from the ' faculty c.
of Brown University d.
A qualified representative from the faculty of Providence College t
e.
A qualified representativ from the faculty of the University of Rhode Island A qualified alternate may serve in lieu of one of
.j the above. The Director and Radiation Safety Officer are not eligible for chairmanship of the Committee.
i 2.
An operator or senior ' operator licensed pursuant to 10CFR55 shall be present in the control room unless the reactor is. secured as defined in these specifications.
The minimum operating. crew shall be two individuals.
3.
A licensed senior operator shall be on duty or readily' available on call whenever the reactor 'is in 1
operation.
Page 53.
k TliCilNICAl. SPECIDCATIONS Ithode Island Nuclear Science Center Docket 50193, l.icense R-95 llevision 1 i
f Rev11/t7/93 F9ure 6.1 HINT.C tegarnatamal Chart RHODE ISLAB )
ATOMIC ENEl GY COMMISSION RAtMAT ON RfACTOR
~!
- aAf t1Y DIRfCTOR Lif R.lIAT ON COMMITM COMMfTTE E t
i i
g I
i J.-
8 a
i 8
- l I
St NOR Ct_f RK
'I ASST, DIRICTOR f OR CONI OINTIAL T YPIST I
Rf ACTOR OPE RAT ONS STLNO S[CRETARY f
I gg..--.
1 MADAllON OPIRATONS E NGINtLRING PROTICTON
~
RADIA10N
.3 sg,gyAcycm
- %N h mNn PROTECTON
.p
[Actyty OfflC(R LNrfNffR a
r Hi ALTH JANffOR UHNSI ogifRATOR ktACTOR
- FACTOR OP{ RATORf OPI R AlOR H P. Toch (LtCTRONC Se v
+
Page ",4
i TECHNICAL SPECIFICATIONS '
- I p
.Rhode Island Nuclear Science Center j
c '..
Docket 50-193, License R 1 Rev;sion 1 k.'-
4.
In accordance -with the emergency plan, a list of emergency personnel, management _and offsite
]
g agencies is posted in the control room.
l 6.2 Qualifications.of Personnel 1.
At the time of appointment to the position, the Director shall have a minimum of six years of nuclear.
a experience.
The Director shall have an advanced
+
degree in one of the physical sciences or engineering l and be a licensed senior operator.
The degree will-fulfill four years of the six-year requirement.
2.
The Radiati, Safety Officer shall have a ~ master's degree in health physics or radiological health and three years of applied health : physics experience in a i
program with radiation safety problems similar to those in the program to be managed.
3.
The reactor operators and senior. operators shall be
}
licensed in accordance.with the provisions 'of 10CFR55.
4.
In the event of temporary vacancy in the position -of Director or the Radiation Safety Officer, the functions of that position shall be assumed by qualified d
alternates appointed by the RIAEC.
6.3 Responsibilities of Personnel 1.
Director a.
The Director shall have responsibil'ty for all activities in the reactor facility which _ may affect reactor operations or involve, radiation hazards, including controlling the admission 1
of personnel to the building.
This responsibility shall encompass -
administrative contr'ol of.all experiments
-j Page 55 g
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,f TECHNICAL SPEC FIC/ TIONS:
Rhoh Island Nuclear Se enev' Center Docket 50-193, License. R-95L j
Revision 1 4
1 being performed in. th'e facility including' j
i those of outside agencies.
i i
b.
It shall be the responsibility of. the-Director-l to. insure that 'all' proposed' experiments, design modifications, or changes in ' operating.
and emergency procedures are performed in accordance with the ' license.
Where l
uncertainty exists. the. Director shall refer
{
the decision to. the Reactor Utilization Committee.
l 2.
Senior Reactor Operators d
A A licensed senior reactor. operator pursuam a.
to 10CFR55 shall be assigned : each shift and j
be responsible for all activities during' his shift which may affect.' reactor operation or 4
involve radiation hazards.. The reactor t
operators on duty ' shall be responsible j
' directly to the senior operator.
b.
The identity of and - method ' for rapidly.
j contacting the on-call senior.
reactor ~
?
operator shall be known to: the reactor i
operator on duty.. The on-call: senior reactor.
I operator must be. capable of 'being contacted
.j by the duty reactor operator within ten minutes.
The senior' reactor operator. shall.
.j be present at the facility during initial j
startup and annroach to power, recovery
)
from an uut '.nned Lor unscheduled:
l shutdown or significant reduction. in powei, and L refueling.
The -name of the person
{
x serving as senior reactor-operator as :well as j
the time he -assumes the duty 'shall be entered in the' reactor. log. - WF.en the 'seniorr operator' is _ relieved, he - ~shall turn. - the i
- senior operatar.
1 operation duties over'.to. another licensed l
- i Page.56
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I TECHNICAL SPECIFICATIONS i
Rhode' Island Nuclear Science Center l
Docket ' 50-193. Licenst R-95 l
Revision I t
In such instances, the change ~ of duty shall
~
be logged and. shall be definite, clear, and.
explicit.
The - senior reactor operator being
- j relieved of his duty shall ' insure that all pertinent information is logged. The s_enior -
reactor operator assuming duty shall check the log for information or instructions.
3.
Reactor Operators a.
The responsible senior reactor operator shall pursuant to 10CFR55 designate - for his shift a
licensed operator (hereafter called
" operator")
who shall have primary responsibility-under the senior reactor operator for the operation of the reactor' and.
all associated control-and safety devices, the A
proper functioning of which is essential to M
the safety of the reactorf or personnel in the facility.
The operator. shall be responsible-directly to the senior reactor operator.
b.
Only one operator shall have the above duty s
at any given time.
Each operator shall enter L
in the reactor log' the date and time hc IJ assumed du ty.
c.
When operations are pericrmed which may' j
affect core reactivity, a license'd operator y
shall be stationed in the control room.
When it is necessary for him to leave the control-I room during such an operation, he shail-' turn the reactor and the reactor controls 'over.to a designated relief, who shall also be a
-i licensed operator.
In ' such instances, the j
change. of duty. shall be. definite, clear. and
- 1 explicit.
The relief shall acknowledge his -
,j entry on duty - by. ' proper notation in :the
-i reactor log.
j i
I
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g TECHNICA1, SPECIFICATIONS Rhode Island Nuclear Science. Center Docket 50-193. License R-95 '
Revision' I i-d.
The operator, ' under the senior. reactor operator on - duty, shall be ' responsible for
' the -operation of the. reactor according to the approved operating; procedures.
The operator shall be: authorized at any time e.
to - reduce. he power of the reactor or to t
scram the reactor without reference to higher authority,. when in his judgment such' action cppears advisable or necessary for the safety 'of. the reactor, related equipment, e
or personnel.
Any person working on the.
reactor bridge shall be similarly authorized to scram the reactor by pressing a scram button located on the bridge.
4.
Radiation Safety Officer The Radiation Safety Officer shall-. be responsible;for j
assuring that adequate radiation ' monitoring. and.
)
control.. are in effect-to prevent undue exposure of individuals to radiation.
6.4 Review and Audit 1.
The Reactor Utilization Committee shall review j
reactor operations to assure that.the facility is operated in a manner consistent with public safety I
and within the terms of the facility license.
.j 2.
The responsibilities of the Reactor Utilization Committee include, but are not limited ' to, the:
following:
q a.
Audit of operating, and - emergency procedures and records.
- g
. b.
Review - and audit of proposed - tests and.... -
l h
experiments utilizing the reactor facilities.
O u
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TECllNICAL SPECIFICATIONS l
V Rhode Island Nuclear Science Center
~ Docket '50-193, License R-95 Revision 1
.l Review and audit of proposed changes to the-1 c.
s facility systems or ' equipment,' procedures, -
l and operations.
s 1
d.
Determination. of. whether - a: proposed
.l change, test, or experiment would. constitute l
an unreviewed safety question which may require a
change to the Technical.
+
Specifications or facility license.
J
.t e.
Review of all violations -of the Technical Specifications and Nuclear.
Regulatory.
1 Commission Regulations.
and significant violations of internal rules or procedures, q
with recommendations for ' corrective action i
to prevent recurrence, d
f.
Review of the qualifications and competency.
j of the operating organization ' to assure retention of staff quality.
+
M Lt g.
Review changes to the Utilization Committee
.' 1 charter.
h.
Review, at least annually, the radiation safety aspects of the facility.
3.
The Reactor Utilization Committee. shall have a
.{
j written charter defining such matters. as. 'the authority of the Committee, the subjects : within its j
purview, and other such-administrative provisions ~ as j
are required for effective functioning
.of- (the.
1 Committee.
Minutes of all meetings of the Committee shall be kept.
4.
A quorum of the Reactor Utilization 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.
j designee.
t 4
F Page 59
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TECHNICAL SPECIFICATIONS l
Rhode Island. Nuclear Science Center Docket 50-193. License ' R !
Revision !
5.
The ~ Reactor Utilization Committee shall meet at least
.I annually.
6.5 Operating - Procedu. _s
/;
. Written procedures, reviewed and approved by the-Reactor Utilization' Committee, shall be used for items 1-9 listed below.
The procedures shall be adequate to assure -
l the. safe operation 'of the reactor, but' should - not. preclude -
=t the use of independent judgment.~ and action should ' the situation require such.
j 1.
Startup, operation and shutdown of. the reactor;
}
2.
Installation and removal of fuel. elements, control blades and incore devices where necessary;
-i 3
Maintenance procedures which could have an effect-on reactor safety; 4.
Periodic surveillance of reactor instrumentation and safety systems, area monitors,. and continuous air-monitors; L
5.
Implementation of. the physical Security Plan and-
[
~
]i 6.
Radiation control procedures; 7.
Receipt, inspection, and storage of new fuel elements; I
8.
Storage and shipment of irradiated fuel elements.
9.
Experiment review on a. case-by-case _ basis assuring' that - section 3.8.3(2) of ANSI /ANS 15.1 is satisfied.
d Operational approval shall be by -written approval: by.
]
a ~ licensed senior operator.
Written procedures should be - established and supervision. of -the -
.i installation of such experiments shall be defined and" exercised.
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TECHNICAL SPECIFICATIONS -
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-Rhode Island Nuclear. Science Center.
l Docket 50;193, License R 95' Revision.1 l
Substantive' changes. to the above proce'dures shall' be j
made only. with the approval 1of. the Reactor Utilization Committee.
Temporary changes to the procedures that do i
not charige their original intent may be made by a. Senior-1 Operator. Temporary changes' to procedures shall; be' documented and subsequently reviewed by' the Reactor Utilization Subcommittee.
6.6 Action to be ' Taken in the Event of a Reportable -
Occurrence In the event of a reportable occurrence:
1.
The Senior Reactor Operator shall be notified promptly and corrective action shall be. taken immediately to place the facility in a safe condition ii until the cause of the reportable occurrence is determined and corrected.
2.
The Director shall report the occurrence.to the. Reactor -
Utilization Committee.
The report 'shall ' include an analysis of the cause - of the occurrence, corrective -
actions taken, and : recommendations - for appropriate action to prevent or reduce the - probability of a repetition of the occurrence.
3.
The Reactor Utilization Committee shall review the report and the corrective' actions taken.
4.
Notification shall be made to the NRC in-i accordance with Paragraph 6.8 of these l
specifications.
6.7 Action to be Taken in the. Event a Safety Limit is.
'[
Exce:ded In the event a Safety Limit h'as been exceededi
.l.
The. reactor will be shut down and reactor operations.
q will. not be resumed.until' authorization is obtained from the NRC.
]
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. TECHNICAL SPECIFICATIONS...
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- 1 Rhode. Island Nuclear Science Center:
Docket '5n-193, License R-95
-i Revision 1 q
2.
Immediate-notification shall' be made to',the :NRC in -
accordance with paragraph 6.8 of these specifications.
l and to the Director.
l d
3.
A prompt report shall be prepared L by! the Senior :
Reactor Operator.
The report shall' include a
1 complete analysis of the causes of the. event: and the-i extent of possible damage: -together
~ with '
recommendations to prevent or. reduce the
.j probability of recurrence.
This ' report shall-be -
submitted to 'the Reactor -Utilization Committee - for-review and. appropriate action,. and a suitable' similar-1 report shall be submitted to the NRC in accordance
- i with. Paragraph 6.8 of these specifications and in j
support ' of a request for authorization for resumption of operations.
i 6.8 Reporting Requirements j
.i In addition to the requirements of' applicable regulations, j
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 j
NRC Operation Center, 301-951-0550 -'and the NRC j
Region 1:
a a.
Any accidental release of radioactivity'.to unrestricted areas above permissible limits, l
whether or not the release resulted in d
~
property
- damage, personal; injury or exposure.
1 3
b.
Any significant variation of measured, values J
from a
couesponding predicted ' 'or -
previously. measured value ' of safety. related operating characteristics -occurring _during' operation of the reactor.
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TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center i
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c.
Any reportable occurrences as defined in Paragraph 1.35 of these specifications.
d.
Any violation of a Safety Limit-t e.
Discovery of any substantial variance from performance specifications contained in,the technical specifications -and safety. analysis.
2.
A written report within 14 days. in the event of'a reportable occurrence, as defined in Section 1.35,. a through e.
The report shall:
a.
- Describe, analyze, and evaluate safety implications-
~
b.
Outline the measures taken to assure that -
l the cause of the condition is determined;
~!
c.
Indicate the corrective action.
- taken, including any changes made to the
~
procedures and to the qu'ality assurance
- program, to prevent repetition of- : th'e occurrence and of.similar occurrences i
involving similar components or systems;
~l d.
Evaluate the safety implication.of tiie incident in' light. of. the cumulative experience obtained from the record of previous failure and malfunctions of similar systems and components.
l 3.
Unusual Events days in the ' event of-j A written report shall be forwa'rded - within thirty (30)
I i
a.
Discovery of any substantial errors. in the transient or accident analyses.or in-the methods.
used for such
- analyses, as.
j
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TECHNICAL SPECIFICATIONS Rhode Island. Nuclear Science Center.
. Docket 50-193, License R-95 Revision I.
~ described-in the _ safety analysis : orL in ' the bases for the technical specifications; a
Discovery of_. any condition involving a-possible single failure awhich,. for a1 system designed against assumed
- failure, could i
result in a loss of the capability 'of the -
system to perform -its safety function;
'~
,c b.
Permanent changes in-the facility.
1 organization-involving the Director or.
Assistant Director.
l 4.
An annual report shall be submitted'in writing.within:
60 days following the 30th of June of each year.
i The report shall include the following information:
1 Tabulation showing the energy generated -by.
a.
the reactor (in megawatt-days),f the number of hours. the reactor was critica!, and the cumulative total energy output 'since' initial
~
criticality.
1 b.
The number.of emergency shutdowns and inadvertent scrams, including the reasons.
c.
Discussion of the major ' maintenance 1
operations performed during the. period, including the effect, if any, on the safe operation of the reactor, and. the reasons for any corrective maintenance. required.
d.
A description of each change. to the facility 1
or procedures, ~ tests, and experiments.
l carried out under the' conditions of Section -
50.59 of 10CFR50 including a sum' mary Hr the. safety evaluation of each.
t A description - of a'ny environmental surveys j
c.
y performed outside the facility.
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TECilNICAL SPECIFICATIONS Rhode Island -Nuclear - Science Center.
Docket 50-193, License R-95 Revision 1'
f.
. A ' summary of annual ~ radiation exposures in L
excess L of 500 mrem received by facility i
personnel, including the " dates and times of
.]
significant exposures.
E g.
A summary of the nature. and -amount. of-radioactive effluents released 'or discharged to the environs beyond the effective control of the licensee as. measured at or prior to the point of such release or discharge.
6.9 Plant Operating Records In addition to the requirements of applicable regulations and in no way substituting therefore, records and logs - of' the following items, minimum, shall - be 'kept in a as manner convenient for review and shall be retained as-indicted:
1.
Records to be retained for a period of atLleast five -
years:
a.
Reactor operations; i
b.
Principal maintenance activities;.
a
- )
Experiments performed including aspects of c.
the experiments which could affect the safety of reactor-operation o r-have radiological safety implications; d.
. Reportable occurrences; i
1 Equipment and component surveillance -
c.
activities; 1
f.
Facility radiation monitoring surveys; I:l l
g.
Fuel inventories and transfers; and Page 65 1
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TECliNICAL SPECIFICATIONS
- Rh' ode. Island Nuclear Science ' Center
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Docket' 50-193, License R.95 Revision ~ l h.
Cha'nges' to procedures ' systems,. components, and equipment.
2.
Records to be retained for the life of the ' facility:
a.
Gaseous and liquid radioactive. effluents'
. released to the environs -
- b. ' Off-site environmental monitoring surveys; Personnel radiation exposuru; c.
d.
Updated, "as-built" drawings - of the facility; and i
- l e.
Minutes of Reactor Utilization Committee 4
meetings.
.l f
C i
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