ML20127H261

Forwards Revised Pages to Sar,Rev 1,addressing Issues Discussed in 930131 Telcon Re Amended Facility License,Leu Reactor Startup Plan,Reactor Core & Control Elements,Safety Sys Settings & Beryllium Lifetime

ML20127H261
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	01/13/1993
From:	Tehan T RHODE ISLAND, STATE OF
To:	Mendonca M Office of Nuclear Reactor Regulation
References
NUDOCS 9301220271
Download: ML20127H261 (8)

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Rhode hiand Atomic Enern Comminion NUCLEAR SCIENCE CENTER South Ferry Road Narragansett, R102382-1197 January 13, 1993 Docket No. 50-193 Mr. Marvin Mendonca, Senior Project Manager Non-Power Reactora, Decommissioning and Environmental Project Directorate Division of P.eactor Projects - III/IV/V U. S. Nuclear P.egulatory Commission Machington, D.C. 20555 ,

Dear Mr. Mendonca:

Enclosed you will find Revised pages for the Safety analysis Peport Revision One which address the issues discussed in our January 13, 1993 phone conversation. Action has been taken as follows:

amended facility licence add antimony-beryllium source LEU Reactor Start-up Plan verify that temperature coefficient .ts negative and of similar magnitude Reactor Core and Centrol correct typographical elements errors Safety System Settings delete high pool temp, to prevent resin damage Beryllium Lifetime Add annual inspecti'a

, and flux calculation for reflectors and flux trap.  %

1 Sincerelyi

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e OPERATING LICENSE R-95 Rhode Island Nuclear Science Center Docket 50-193 January 31, 1993 RHODE ISLAND ATOMIC ENERGY COMMISSION RHODE ISLAND NUCLEAR SCIEtJCE CENTER Docket 50-193 OPERIsTING LICENSE R-95 A. This license applies to the Rhode Island Nuclear Science Center reactor owned by the Rhode Island Atomic Energy Commission. The facility is located in Narragansett, Rhode Island and is described in the application dated January 31, 1993 as supplemented. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Rhode Island Atomic Energy Commission: (1) Pursuant to Section 104c of the Act and 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the designated location in Narragansett, Rhode Island in accordance with the procedures and limitations cet forth in this license, (2) Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material, to receive, possess and use up to a maximum of 10.4 kilograms of ccntained uranium 235 at enrichments equal to or less than 20% in connection with operation of the reactor and up to 32 grams of plutonium encapsulated in two pluton'.vm-beryllium neutron sources for reactor startup., (3) Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material", to possess, but not to use, a maximum of 8 kg of contained uranium at greater than 20% enrichment until the existing inventory of high enriched uranium is rer.oved from the faci 2ity. (4) Pursuant to the Act and 10 CFR Part 30," Rules of General Applicability to Domestic Licensing of Byproduct Material," and Part 70 " Domestic Licensing of Special Nuclear Material," to receive, possess and use an antimony-beryllium neutron source, which will be activated to a miniumum neutron source strength of 10 curies in connection with operation of the reactor; and to pcssess, but not to separate, such byproduct material as has been or may be produced by operation of the reactor. Page 1

j)'I '~ _O y OPERATING LICENSE R-95 Rhode-Island Nuclear Science Center Docket 50-193 January 31, 1993 C. This license.shall be deemed to contain and is subject to the conditions specified in Parts 20, 30, 50, 51, 5 5,. 't 70, and 73 of 10 CFR Chapter I, to all applicable provisions of the Act, and,to the rules, regulations and . ~ orders of the Commi,csion now or hereafceriin effect and-to the additional conditions specified below: ' (1) Maximum Power Level The licensee is authorized to operate the facility at power levels not in excess of two megawatts ' (thermal). b (2) Technical Specifications j Tre Technical Specifications contained in Appendix A, as revised through Revision 1, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the technical specifications. (3) Physical Security Plan The licensee shall maintain and fully implement'all . provisions of ~the Commission-approved physical security plan, including amendments and revisions made pursuant to the authority of 10.CFR 50.90 and 10 CFR 50.54(p), which are part of the license. The approved security plan consists of a~ document

withheld from pubic disclosure-pursuant to 10 CFR _

73.21 entitled " Security Plun Rhode Island Nuclear Science Center Reactor." This license is effective as of the date of issuance and D. shall expire forty years from its date of issuance. I

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4. Reactor Power Calibration

a. methods and measurements that assure operation within the license limits

b. comparison between HEU and LEU nuclear instrumentation' setpoints, detector positions,'and detector output

5. Shutdown Margin

a. measurement ' with HEU

b. measurement with LEU

c. comparison between HEU and LEU

6. Thermal Neutron Flux Distributions

a. measurements of the core and measured experimental-facilities with HEU and LEU

b. comparisons with calculations of each y

7. Comparison - of the various results, and discussion of the  !

comparison, including an explanation of any significant k

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differences that could' affect projected normal. operation. ] ;

8. - Measurements _ made during . initial loading e of' . LEUD fuel, presenting subcritical -multiplication- measurements, I "

redict_ ions of multiplication ' for next fuel additions, and perdition and verification of final- criticality >

conditions.

                        .9. Verify that the temperature coef ficient is-negative andi of comparable magnitude in- the- LEU core as-.was-experienced _in the HEU core.

Future measurements, to be conducted a s . e x p e r i m e n t's , will' be

- performed when funds are available and may include pa,rametersEsuch as temperature " coef ficient, void coefficient, etc. Mapping -of

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- fluxes 'in experimental' f acilities such'as beamtubes, pneumatic-c- system, thermal column,-' dry gamma facility etc., shall be~on an,as needed basis in support-of experimental work, t 39 n- 6 - - - - ,- 4- ,. ge ,- a , , , _- - g , , . - ,

E, PEACTOR OCRE AND COMIBOL FLEMENTS The reactor core and control elements shall have the following characteristics and nomina.'. d'monsions:

1. Princloal Core Materials U3S1

• Fuel matrix 2 -Al dispersion Approximately 20%.
• U-235 enrichment 6061 alum.inum
• Fuel clad Fuel element side plates 6061 aluminum End fittings 356-T6 or 6061 aluminum Moderator Water Feflector-Graphite AGOT grade (or equivalent -

graphite and/or water Reflector-Beryllium Beryllium-aluminum clad

• Control elements Mixture of B 4C and aluminum, clad with aluminum Servo Elament Stainlees steel 304 *

2. ruel Eieronts Plate width overall 2.81 inches

• Active plato width 2.40 inches maximum
• Plate 1,ongth overall 25.00 inches Active plate length 23.50 inches
• Plate thickness 0.06 inch Clad thickness 0.02 inch
• Fuel matrix thickness 0.02 inch
• Water gap between plates 0.08 inch
• l

I= l . Number of plates per f uel 22

• element 275 grams, nominal
• U-235 per fuel element I

overall fuel element dimensions 3 in x 3 in. x 40 in.

3. Ecflector Elements - Graphite and Beryllium overall reflector element 3 in x 3 in. x 40 in.

dimensions, nominal Nominal clad thickness .1 .in . Nominal graphite dimensions 2.8 in. x 2.8 in. x 2.8 7.in. Standard Beryllium element dimensions 2.94 in. x 2.94 in. x 29 in. *

33. Deryllium Flux Trao 2.94 in. x 2.94 in. x 29 in. *'

with a 1.5 inch diameter thru hole

4. control Elements Width 10.6 in.

Thickness 0.38 in. Overall length 54.1 in. Active length 52.1 in.

5. servo Regulatine Element Shapo Squaro stainless steel

• Width 2.1 in.

Overall length 28.8 in. Active 24.9 in.

6. Control Element Drive Type Electromechanical screw Crive to safety element Electromagnet connection Stroke 32 in, maximum

TABLE F_1 - REACTOR SAFETY SYSTEM Sensor or Trip Device No. of Switches Trip Set Alarm Set or Sensors Point Point Short Period 1 3 sec. min. 7 sec. min. High !;eutron Flux 2 Max, of 115% of 110% max, full scale with a 2.3 trd max. High Temperature of Primary ll30F max. Coolant Entering Core During Forced Convection Cooling

• High Temperature of Primary 1250F max. 1230F max.

Coolant Leaving Core During -- Forced Convection Cooling

• Low Flow Rate of Primary 1 1600 gpm, 1650 gpm,
• Coolant
• min, min.

Low Pool Water Level 1 2" max decrease 2" max. decrease Seinmic Disturbance 1 IV on Modified Mercalli Scale max. Bridge Misalignment

• 1 X X Coolant Gates Open* 1 per gate X X Neutron Detector High 1 per Decraase of Voltage Failure in Linear power 50 volts max.

Level Safety Channels supply Manual Scram (Switch at 2 X X _ bridge and on console) High Conductivity of 1 Equivalent Primary Coolant to 2pmho/cm at 250C, max. Safety Blade Disengaged 1 X Log N - Period Amplifier 1 X X Failure Regulating Rod at Either 1 X Limit of Travel Low Flow Rate of Seccndary 1 800 gpm, Coolant

• min.

Bridge Movement 1 X X 4 No Flow Thermal Column

• 1 X X

                   *These functions are bypassed when the Power Level Selector Switch is in the "0.1 MW" position.

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         ,,      (c)    Reactivity Coefficients 1    Temperature coefficient     approximatelf      *

(coolant + Doppler) -1.8 x 10-4 /0C (calculated)

2. Void coefficient approximately *

(core average) -2.7 x 10-3/% vcid (calculated) (4) Princ} cal Core Onerat inc Limit at iona (a) Excess Reactivity The cold, clean excess reactivity for any core used in the reactor shall not exceed 0.047. (b) Minimum Shutdown Marcin All reactor cores used shal] be such that they would be suberitical if any single control element and the servo regulating element were withdrawn. (c) Reactivity Coefficient L1mitation The reactor power coefficient (as inferred by the  ; control rod movements required to compensate for changes.in power) shall be negative. (d) Centrol Element Drive Performance Requirements f All control element drives shall meet the following specifications:

1. The control drive withdrawal rate shall not be more than 3.6 inches per minute.

2. For the electronic scram system, the . time -

from initiation of a scram condition until control element release shall not exceed 100 milliseconds.

3. The time f rom initiation of a scram conc': tion until the' control element is fully inserted shall not exceed 900 milliseconds.

4. It shall be demonstrated at least every 3 months that the above specifications are me*

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                                               *                 (e)    Servo Regulating Element Drive                       Performance Recuirements

[ I If in use during operation, the servo regulating l element drive shall meet the following specifications:

1. The drive withdrawal rate shall not be more than 78 inches per minute.

2. It shall be demonstrated at least once per month that the above specification is met.

Beryllium Reflector Lifetimo (f)

1. Maximum allowed accumulated neutron exposure is 1x 1072 NVT.

2. To prevent physical damage to the beryllium _

reflectors and flux trap, an inspection of the-components and a calculation of total exposure - will be conducted annually,

f. EcactnL_fiaf.cty_3ys t ems (1) The reactor safety system shall be - operable during all reactor operation. The safety system shall be checked out before ea^ start-up and functionally tested for calibration at least 'hly.

(2) It shall be permissible t.o continue operations with one or more of the safety system functions that produce only an alarm temporarily oisabled providing that additional procedural controls are instituted to replace the lost safety system alarm function (s) . (3) The control element withdrawal interlocks and the . servo system control interlocks shall be functionally tested at least once per month. (4) During reactor startup or during mechanical changes that could affect core reactivity, the startup range neut ron'. monitoring channel shall be operable and shall provide a neutron count rate of at least 3 counts per second with a signal to noise ratio at least 3 to 1. (5) The linwr level safety channels shall not read loss than 15% of full scale when the reactor is operating at power levels above 1 watt. (6) Following a reduction in power level, the operator shall adjust the servo power schedule to the new power level before switching to automatic operation. (7) An alarm condition from any one of the items listed in Section F.2.b. after working hours shall transmit coded irformation to a continuously manned central station in Providence, Rhode Island. The central station shell be provided with written instructions on the steps to bo taken following an alarm.

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