ML20041D908

Forwards Response to Questions Generated by Lasl Site Visit & Fuel Incident Rept Interpretation of Damage to Flip Fuel During Operation of Nuclear Science Ctr Reactor at Tx A&M Univ

ML20041D908
Person / Time
Site:	05000128
Issue date:	03/05/1982
From:	Randall J TEXAS A&M UNIV., COLLEGE STATION, TX
To:	John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20041D909	List: A16613, Interpretation of Damage to Flip Fuel During Operation of Nuclear Science Ctr Reactor at Tx A&M Univ ML20041D908
References
NUDOCS 8203090523
Download: ML20041D908 (27)

Text

l TEXAS ENGINEERING EXPEBIMENT STATION THE TEXAS A&M UNIVERSITY SYSTEM

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COLLEGE STATION. TEXAS 77843 l

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NUCLEAR SCIENCE CENTER 5 March 1982 713/845-7551 l

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Mr. James R. Miller, Chief

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Standardization and Special O

l Projects Branch

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Division of Licensing

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a U.S. Nuclear Regulatory Commission

'vec Washington, D.C.

20555 Ref: Docket No. 50-128, R-83 Y

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Dear Mr. Miller:

Our response to the questions generated by the Los Alamos National Laboratory i

site visit is enclosed including copies of the fuel incident report

" Interpretation of Damage to the FLIP Fuel During Operation of the Nuclear Science Center Reactor at Texas A&M University", by M. T. Simnad, G. D. West, J. D. Randall, W. J. Richards, and D. Stahl.

We are in the process of preparing for submittal a rework of our technical specifications to conform to ANS 15.1, " Standard for the Development of Technical Specifications for Research Reactors" and a supplement to the SAR.

We plan to submit this material for NRC review of our license renewal application by March 31, 1982.

Sincerelv Jo' D. Randall rector JDR/ym

Enclosures:

3 copies - Formal Questions 8

3 copies - Fuel Incident Report

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k 8203090523 820305 PDR ADOCK 05000128 P

PDR RESEARCH AND DEVEL W A'T FOR MANKIND A

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o TEXAS A&M (NSCR) FORMAL QUESTIONS 1.

WilAT IS Tile LEAKAGE llISTORY OF Tile REACTOR POOL LINER?

ANS: A pool water leakage rate of approximately 1000 gallons / day necessitated the installation of a new stainless steel liner in March, 1966 which was completed within a four month period. The initial raw water test of the liner after installation resulted in a leak rate of approximately 1500 gallons / day.

Several inspection and repair cycles were performed before a second raw water test was conducted.

This test indicated a leak rate of approximately 25 gallons / day, and shortly thereafter this de-creased to zero due to self-sealing with no further leakage observed to date.

2.

DESCRIl3E TIIE FILTERS INSTALLED IN Tile POOL WATER PURIFICATION SYSTEM.

ANS: The final filtration in the pool water purification system during normal recirculation is accomplished with the use of 3-5 micron cotton wound cartridges. The filter holder houses either 6 large filters or 18 small filters stacked 3 deep.

On certain occasions such as during cleaning of the pool floor 100 micron acrylic filters are used.

3.

DESCRIBE Tile REACTOR POOL WATER RADI0 ACTIVITY MONITORING PROGRAM.

ANS: A daily 3000 ce sample is counted on Scorpio for 5000 secs. to determine gamma isotopes. A 100 cc sample is evaporated to dryness and beta activity is determined using a GM system.

4.

Il0W IS LACK OF FLOW OF PRIMARY SYSTEM WATER PROMPTLY ANNUNCIATED TO Tile OP.?RATOR?

ANS: The only annunciator associated with primary flow is an alarm for primary pump power failure, llowever, the operator does have avail-able a flow rate neter and multipoint recorder for system temperatures.

S.

IS POOL WATER MAKEUP SYSTEM AUTOMATIC OR MANUAL?

ANS: Pool water makeup is manual and is normally done on a weekly basis.

6.

UNDER WHAT CONDITIONS IS Ti!E CORE DIFFUSER SYSTEM OPERATED?

ANS: As per SOP II-C the diffuser pump is run any time reactor power is

> 400 kw.

a

1 7.

WHAT IS Tile AVERAGE NEGATIVE PRESSURE IN THE REACTOR CONFINEMENT BUILDING AND Tile RELATION TO OIllER AREAS IN THE NUCLEAR FACILITY?

ANS: The average negative pressure in the reactor confinement building is approximately 0.05 in. water relative to atmospheric pressure. This pressure is maintained by the automatic control of exhaust air f rom the upper research and lower research areas.

8.

WilAT FUNCTIONAL TESTS ARE CONDUCTED ON TllE VENTILATION ISOLATION SYSTEM 7 HOW IS DAMPER CLOSURE VERIFIED? IIOW FREQUENTLY ARE TiiESE TESTS PERFORMED?

ANS:

On a weekly basis functional tests are performed including a check of all automatic and manual shutdown features. The check is done-by electronics personnel using NSC Form 316 (see attachment).

Extensions on the pneumatic operators for the dampers are marked to allow visual verification of damper position.

9.

WilAT ARE TiiE SIZE AND TYPE OF Tile PARTICULATE FILTERS IN Ti!E EMERGENCY EXHAUST SYSTEM?

ANS: The emergency exhaust filter system contains high efficiency particulate filters of 0.3 micron rating. The filter system also contains throw-away particulate prefilters positioned upstream from the HEPA filters.

10.

HOW ARE THE LOG POWER AND LINEAR POWER CHANNELS CORRELATED TO THE ACTUAL THERMAL OUTPUT OF THE REACTOR? HOW OFTEN IS TilIS CALIBRATION PERFORMED?

ANS: A power calorimetric is performed on an annual basis or following any core change. This is done by establishing reactor power at 400 kw as indicated on the linear channel. Pool heatup rate can be correlated to actual reactor power based on data obtained previously using a 100 kw heater.

The linear detector is then repositioned such that indicated power agrees with that determined during the calorimetric.

If necessary, the safety channel detectors and the log power detector will also be repositioned.

11.

PROVIDE A COPY OF A RECENT BIOLOGICAL SIIIELD RADIATION SURVEY PERFORMED Wi!ILE OPERATING AT FULL POWER WITil THE REACTOR AT EACll NORMAL OPERATING POSITION.

REACTOR IN STALL, AGAINST BP #4, POOL.

ANS:

Enclosed are surveys for both these positions.

(See attachment).

12.

DESCRIBE THE RADIATION PROTECTION STAFF.

IDENTIFY Tile NUMBER, LEVEL, AND RESPONSIBILITIES OF PERSONNEL AND TiiE LINES OF COMMUNICATION BETWEEN THEM.

ANS:

The radiation staff consists of a NSC senior health physicist and a health physics technician.

In addition, a full-time graduate student f rom the Nuclear Engineering. radiation protection engineering degree program is assigned on a full-time basis.

The senior health physicist is responsible to the University RSO.

The technician and student are responsible to the senior health physicist at the NSC.

13.

OUTLINE Tile MINIMUM QUALIFICATIONS (TRAINING AND/OR PREVIOUS EXPERIENCE)

FOR EACl! 0F YOUR llEALTH PHYSICS-RELATED POSITIONS.

ANS:

Senior health physicist must have a Bachelors degree and 5 years health physics experience, preferably at an operating reactor.

The health physics technician must have an AAS degree in radiation protection or 4 years experience in health physics. The student must be a Texas A&M graduate student in the Nuclear Engineering Department. graduating with a radiation protection engineering degree.

14.

DESCRIBE ANY ReDIATION PROTECTION TRAINING FOR NON-ilEALTli PliYSICS STAFF.

IF POSSIBLE, PROVIDE A TOPIC OUTLINE OF THE COURSES INDICATING Tile NORMAL DURATION OF EACll COURSE OR LECTURE.

ANS: All designed non-radiation workers must attend a two-hour initial radiation protection related lecture on hiring.

An annual lecture is given in February to all non-radiation employees as a r',qualifica-e tion.

Operation personnel are on a facility requalification lecture series that incorporates health physics.

(See attachment).

15.

SUMMARIZE YOUR GENERAL RADIATION SAFETY PROCEDURES.

IDENTIFY Tile MINIMUM FREQUENCY OF SURVEY, ACTION POINTS, AND APPROPRIATE RESPONSES, I.E., FOR NON-ROUTINE CONDITIONS.

ANS:

Wipe and instrument surveys are performed on a routine monthly basis at the NSC.

Question 16 incorporates health physics surveillance in other than routine cases. Two hundred (200) disinte-grations per 100 cm 2 are the allowable limit for all wipes.

Action is taken if the level is greater than 200.

Area radiation levels are most generally known and because llP's are required to do all instru-ment surveys; special surveys are handled on a one-to-one basis.

Any radiation level in excess of 2.0 mrem is investigated by II.P.

personnel.

16.

DESCRIBE Tile PROGRAM TO ENSURE TilAT PERSLNNEL RADIATION EXPOSURE AND RELEASES OF RADI0 ACTIVE MATERIAL ARE MAINUINED AT A LEVEL THAT IS "AS LOW AS REASONABLY ACilIEVABLE" (ALARA).

ANS: All personnel are badged with either film (bi-weekly) or TLD's (quarterly) as well as a non-self reading pocket dosimeter. Portable instruments are available throughout the building and area radiation monitors are in all areas where increased radiation levels may be expected. Health physics must approve any experiment, maintenance or on going procedures prior to enactment. All effluent systems, i.e.,

air and water, are maintained and monitored directly by health physics. Dosimeter results are constantly checked to indicate areas of greatest interest so that H.P. may further reduce exposures if reasonable and economically feasible.

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17.

FOR THE FIXED-POSITION RADIATION AND EFFLUENT MONITORS, SPECIFY Tile TYPE OF DETECTORS AND THEIR EFFICIENCIES AND OPERABLE RANGES.

ANS: No fixed monitors in liquid waste system. See Question and answer No. 28 for air monitors. Area Radiation Monitors - Tracer-lab GM meters 1000 mR/hr calibrated to + 10% at 1/3, 1/2 and 3/4 meter scale.

18.

FOR Tile FIXED-POSITION RADIATION AND EFFLUENT MONITORS, DESCRIBE Ti!E METHODS AND FREQUENCY OF INSTRUMENT CALIBRATIONS AND THE ROUTINE OPERATIONAL CllECKS.

ANS: Area radiation monitors are calibrated semi-annually with calibrated Co-60 sources. A daily internal (Sr-90) source check is performed by operations personnel prior to startup. Air monitors are checked daily for operational mode, monthly with a response check source and calibrated annually with a calibrated source.

19.

FOR THE RADIATION MONITORS THAT.RE ALARMED, SPECIFY THE ALARM SET-POINTS AND INDICATE Tile EXPECTED STAFF RISPONSE TO EACil ALARM.

ANS: All alarm set points are 1.0 mr/hr with some exceptions due to localized pre-planned activities.

Ilealth physics must respond to all alarms. Personnel in area are notified.

A portable instrunent survey is made.

If instrument failure, electronics is notified.

20.

IDENTIFY THE TYPE, NUMBER, AND OPERABLE RANGE OF EACll 0F Tile PORTABLE HEALTH PdYSICS INSTRUMENTS ROUTINELY AVAILABLE AT THE REACTOR INSTALLATION.

SPECIFY THE FREQUENCY AND METHODS OF CALIBRATION.

ANS:

Radector Ion Chambers - mR/hr - kR/hr 4 ca.

(One has a 6 foot extension)

Ludlum - CM - 500 mR/hr 2 ea.

Eberline - GM - 50 mR/hr 3 ca.

Ludlum 1" NaI(Th) - Response only 2 ca.

Eberline PNC Neutron Counter 1 ea.

Ludlum 15 Rem Ball - 2200 Scaler mRen/hr - 2 Rem /hr 1 ea.

(Calibrated with a PuBe-10 Ci Source)

NOTE:

(All gamma sensitive, instruments are calibrated against Co-60 and Cs-137 on our own range.

All instruments are callbrated semi-annually).

~

21.

IF YOU ANTICIPATE THAT ADDITIONAL OR SPECIALIZED hEALTil PHYSICS INSTRU-MENTATION MAY BE RFADILY AVAILABLE FROM OT!!ER TEXAS A&M FACILITIES, INDICATE THE TYPE, NUMBER, AND RANGE OF Tile AVAILABLE EQUIPMENT.

ANS:

Radector - mR/hr - kR/hr 4 ea.

CM's 8 ea.

Victoreen - 488A 2 ea.

BF Neutron Detector 1 ca.

Lu21um - cM - 500 mR/hr 2 ea.

Eberline - GM - 50 mR/hr 3 ea.

Ludlum 1" NaI(Th) - Response Only 2 ca.

Eberline PNC Neutron Counter 1 ca.

Rem Ball - Ludlum Model 15 or 2200 Scaler Ratemeter -

mrem /hr - 2 Rem /hr 1 ea.

All instruments are calibrated semi-annually or more often if required. We have a 0.111 CL Cobalt-60 and 2 Cesium-137 sources, 8.96 Ci and 0.798 C1, and 1 neutron source 10 C1.

1

22. ' DESCRIBE YOUR PERSONNEL MONITORING PROGRAM, INCLUDING BIO-ASSAY AND IN_ VIVO COUNTING CAPABILITIES.

ANS:

Described in Question 16.

In addition iodine and tritium analyses are available on campus. No whole body counter is available at A&M.

i 23.

DESCRIBE CALIBRATION PROCEDURES FOR Tile IN-HOUSE PORTIONS OF Tile PERSONNEL MONITORING PROGRAM.

DESCRIBE ANY QUALITY ASSURANCE STUDIES FOR THE COMMERCIALLY SUPPLIED PORTIONS.

4 ANS:

Pocket dosimeters are calibrated on our calibration range semi-i annually. The range exposure is checked using a calibrated MDil ion chamber. After a 24 or 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> leak test is performed instruments passing are taken to the range and are response checked at 15, 30, 50, 100 and 150 mR.

Only those dosimeters that are within j

i 20% average pass the test.

Others are kept and repaired.

Film badges are exposed semi-annually to a known source and sent to our supplier.

24.

IDENTIFY ANY ADMINISTRATIVE EXPOSURE LIMITS AND ANTICIPATED ACTIONS IF TilESE LEVELS ARE EXCEEDED. ALSO, IDENTIFY Tile OPERATIONAL CONSTRAINTS THAT ARE PLACED ON PERSONNEL ~ ENTERING POTENTIAL RADIATION /HIGH RADIATION OR CONTAMINATED AREAS.

ANS:

Film badges on a bi-weekly frequency are used by health physics and operations personnel.

An exposure of 100 mrem / exposure period is investigated to determine what evolutions the worker has been doing.

l If health physics was involved in the evolutions and it is determined that the exposure is in-conformance to ALARA guidelines then nothing j

is done.

If it is a routine exposure for which no criteria has been set then the senior health physicist determines remedial steps to be taken to reduce future exposures. The MllA is our most hazardous r

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r=-

m

area followed by neutron radiography in the lower level. The FEUL has been completely evaluated and exposure levels have been reduced over 20% in the past year.

Further refinements are made as operational procedures change. To enter the MHA foot covers are required and gloves are used on an as needed basis. A hand and foot monitor is used on leaving the posted area.

During neutron radiography the lower level is declared a "C-2" area and an canouncement is made over the inter-communication system.

In addition a flashing red light is continuously on at the entrance doors. Premission to enter the area by other than approved workers is given by a health physicist who cautions the worker on areas of high exposure.

Contaminated areas are always roped off and decontaminated irmnediately by health physics.

25.

WHAT IS Ti!E HEALTH PHYSICS REVIEW AND EXPOSURE CONTROL OF ONE-OF-A-KIND, S110RT-TERM, LOW-TO-INTERMEDIATE-RISK TASKS SUCll AS SIMPLE BUT NON-ROUTINE MAINTENANCE ACTIVITIES AND ONE-SHOT EXPERIMENTAL MEASUREMENTS?

IF SPECIAL WORK PERMITS (SWPs) ARE USED FOR THESE EVENTS, SPECIFY TiiE APPLICABLE REQUIREMENTS, LIMITATIONS, AND APPROVALS.

ANS: These non-routine procedures are approved at a NSC staff meeting and health physics, at that time, informs operations of precautions to take.

In addition a health physicist is assigned and fills out, as appropriate, a NSC-HP 30 form which is used as a local SWP.

The on-the-spot health physicist works within the guidelines set forth at the staff meeting.

26.

PROVIDE A SU) DIARY OF Tile NSCR ANNUAL PERSONNEL EXPOSURES (Ti!E NUMBER OF PERSONS RECEIVING TOTAL ANNUAL EXPOSURE WITilIN THE DESIGNATED EXPOSURE RANGES, SIMILAR TO THE REPORT DESCRIBED IN 10 CFR 20.407(b) FOR THE LAST 5 YEARS OF OPERATION.

ANS: See attachment.

27.

DESCRIBE Tile PROCEDURES FOR MONITORING AND CllANGING FILTERS AND/OR DEFENERALIZER MATERIAL IN Tile VENTILATION AND WATER PURIFICATION SYSTEMS.

ANS:

Cuno filters are changed periodically in the pool water system by maintenance personnel under the guidance of a health physicist.

The area is roped off.

Diaper paper is used as a drape and the filter water drained into a bucket. The filter material is monitored and removed to a plastic bag.

The new filter material is replaced and the area is cleaned up, wiped and released.

The llEPA filters in the air handling system have not been changed but if the need ever arises an isolation technique similar to that described above will be used. Our HEPA filters are not normally in line so no air is being filtered.

28.

DESCRIBE THE CASEOUS AND AIR PARTICULATE EFFLUENT SAMPLING EQUJPMENT INCLUDING DESCRIPTIONS OF LOCATION, STACK FLOW RATES, SAMPLING RATES, AND PROBES.

ANS: Sampling Equipment:

Ch 1 Stack Particulate - End window GM tube eff:

approximately 3% Range: 6.65 E-11 pCi/cc to 6.65 E-08 pCi/cc Ch 2 Fission Product - End window C&! tube eff: approximately 15% Range:

4.44 E-12 pCi/cc to 4.44 E-09 pCi/cc 104 scale only Ch 3 Stack Gas - NaI(Tl) Scintillation 3 x 3 crystal Range:

4.93 E-09 pCi/cc Ch 4 Building Particulate - End window GM tube eff:

approximately 12% Range:

9.16 E-12 pCi/cc to 9.46 E-07 pCi/cc Ch 6 Building Gas - NaI(TI) Scintillation 2 x 2' crystal Range:

1.48 E-06 to 1.20 E-04 pCi/cc 10 4 Flow Rates:

3 Stack = 5000 ft / min 3

Ch 1 = 7.0 ft / min (7.5 cfm indicated)

Ch 2 = 4.2 scfm (310 scfh indicated)

Ch 3 = 6.0 scfm (275 scfh indicated)

Ch 4, 6 = 5.2 scfm (355 scfh indicated) 29.

IDENTIFY ALL AUTOMATIC SCRAM CONDITIONS OTilER TilAN Tile REACTOR SAFETY CilANNELS' LISTED IN TABLE V, SAR, PAGE 100.

ANS:

a) Period Scram + < 3 second period (optional see 30 j) b) EP #4 Cave Door + automatic scram when cave door is opened while reactor is positioned within 18" of the beam port.

c) Power switch on Temperature Recorder + if turned off will initiate an automatic scram.

d) Bridge Unlocked + unlocking bridge will initiate an automatic scram.

e) Bridge Interlock - see 30 h).

30.

LIST ALL PARAMETERS TIIAT ARE ALARMED IN TIIE CONTROL ROOM AND SPECIFY ALARM TRIP SETTINCS.

ANS: a) Bridge Unlocked - Spring loaded microswitch actrated when lock removed.

b) Safety Amp Scram - 115% of licensed power of 1 MW on both #1 and #2 safeties.

c)

Fuel Temperature Scram - 975 F (525 C) switch located on Fuel Temp recorder.

d) Manual Scram - Manual switches on control console, and bridge, e) Period Scram - Any reactor period < 3 seconds (optional see 30 j) f) Experiment Scram - Manual switches on east face of stall, irradiation cell, 2 locations on wall on lower research level.

g) Linear Recorder off Scale - 150% of reactor power for any given scale selected *

'icoammeter switch.

h) Bridge Interlock - When reactor rolled more than 8' away from stall the bridge interlock must be disconnected resulting in an alarm on the console.

1) Servo Fault - Adjustable - normally set to alarm at 2 5%.

either side of null position.

j) Period Scram Bypass - No alarm trip setting - used to override period scram setting.

Will receive alarm on console when switch is placed in bypass.

k) Reg Rod Shimming Required - < 8 cm's (20% of travel) or

> 32 cm's (80% of travel)

1) Building Pressure System Failure - Adjustable.

Normally set at

.05" of water (actuates LED at pressure less than that).

m)

Facility Air Monitor - Any FAM monitoring alarm will trip this alarm including a low level alarm on Channel 1.

n) Cell Door Open - Manual actuation by switch mounted on cell wall and actuated by the cell door.

o)

Emergency Shutdown Air IIandling System - Manual switch on console.

p) Pool Level Alarm - Pool water level decreasing to approximately 90% of normal level.

Actuated by float switch.

Auxiliary Panel a) Primary Pump Failure - Motor starter relay switch.

b) Secondary Pump Failure - Motor starter relay switch.

c) Secondary Flow - Flapper valve actuated switch.

d) Diffuser Pump Failure - Motor starter contacts.

e) Facility Air Lo Pressure - Pressure switch actuated during low pressure condition.

f)

Beam Port #5 Door Open - Manually actuated switch nounted on BP door.

g)

Beam Port #1 Door Open - Manually actuated switch mounted on BP door, h) Beam Port #2 Door Open - Manually actuated switch mounted on BP door.

1) Beam Port #4, C-2 Cave Door - Manually actuated switch mounted on BP door.

j)

Beam Port #4, C-2 Sample Prep Room - Manually actuated switch mounted on BP door.

k) Fuel Storage Room Door Open - Marually actuated switch mounted on Fuel Storage Room Door.

1) Boneyard Gate Open - Manually actuated switch mounted on gate.

m) Lab Bui ding Rear Door

- Manually actuated switch mounted on Door.

n) Tunnel Door Open - Manual actuation by switch mounted on door.

o) Gate - Light comes on anytime voltage applied to gate either to open or close it.

p)

Irradiation Cell C-2 Control Room Door Open - Manual actuation by switch mounted on control room door.

q)

Irradiation Cell C-2 Upper Level Door Open - Manual actuation by switch mounted on door going from Upper Research Level to hall.

r)

Irradiation Cell C-2 Up Ramp Door Open - Manual actuation by switch mounted on door, s)

Beam Port #4, C-2 Down Ramp Door - Manual actuation by switch mounted on door.

t)

Beam Port #4, C-2 Stairwell Door - Ranual actuation by switch mounted on stairwell door when (C-2) switch in control room is in outer.

31.

Il0W DOES Tile REACTOR OPERATOR DETERMINE Tile CAUSE(S) 0F EACil SCRAM? WHAT ARE TiiE PROCEDURES FOR RESTART FOLIDWING A SCRAM?

ANS: The annunciator panel on the reactor console will identify each scram.

Reactor startup following an unscheduled shutdown will be performed as per SOP II-C-6 and NSC Form 539 - Recovery From Un-scheduled Scram will be used as a review of the scram (see attachment).

32.

WilAT IS MEANT BY Ti!E TERM " JAM CONDITION" IN RELATION TO CONTROL ROD POSITION INDICATION? CAN Ti!E CONTROL RODS STILL FALL FREELY INTO THE CORE UNDER TiiE CIRCUMSTANCE?

ANS: A jam condition results in the control rod drive mechanism lead screw moving upward approximately '" due to either the extension rod or control rod jamming while being driven in.

Whether the rod can still fall freely depends upon whether the binding occurred above or below the armature magnet.

33.

IT IS ESSENTIAL TO liAVE Tile ANALYSIS AND REPORT OF YOUR 1976 FUEL ELEMENT DAMAGE INCIDENT.

IN ADDITION, WilAT ARE Tile CURRENT PLANS FOR PULSING A MIXED OR FLIP CORE?

ANS:

The fuel element damage report is enclosed. The earliest plan for pulsing a FLIP core is approximately one year away.

There are no plans to pulse a mixed core.

34 PROVIDE A REFERENCE FOR Tile STATED FISSION PRODUCT RELEASE FRACTION OF

2. 6 x 10- 5, ANS: General Atomic report Gulf-EES-A10801, " Summary of TRIGA Fuel Fission Product Release Experiments", F. C. Foushee, R.11. Peters, September 1971.

35.

WlIAT CRITERION OR GUIDANCE WAS USED IN TliE SELECTION OF Tile DESIGN BASIS ACCIDENT AND Tile OTi!ER ACCIDENTS CONSIDERED?

ANS:

Guidance for the Design Basis Accident and other accidents described in the SAR was provided by General Atomics. Their experience with TRIGA fuel safety evaluations and access to numerous computer codes was the source of our information. Several calculations were per-formed by the NSC using Exterminator-2 computer code.

Comparisons were made with G. A. to verify the accuracy of.the Exterminator-2 code. SAR's for the Oregon State University and the Puerto Rico Nuclear Center reactors were useful in the description and study of accidents.

36.

WilAT ARE Ti!E LIMITATIONS ON TIIE POSSIBLE POSITIONS OF Tile TRANSIENT ROD IN A MIXED CORE?

ANS: Mounting of the transient pulse rod assembly for operational mixed cores is restricted to one of twelve grid positions that have been modified to accept control rods with followers. The pulse operation of mixed TRIGA cores requires the use of an air followed pulse control rod to reduce flux peaking in the FLIP fuel region of the core. The available positions are shown in Figure 3-1 of the SAR, p. 13.

The limitation becomes one of physically mounting the transient rod assembly for operation in these locations.

37.

FOR A RANGE OF MIXED CORES SPECIFY:

a)

TllE MAXIMUM RATIO OF POWER PRODUCED IN Tile MAXIMUM POWER STANDARD ELEMENT TO Tile POWER PRODUCED IN Tile INSTRUMENTED (TilERM0 COUPLE)

ELEMENT.

ANS: Mixed core loadings of 35 FLIP and 59 FLIP elements have been operated. Only the 35 FLIP mixed core was pulsed.

Both core loadings contained 98 total elements.

Mixed Core Peak Thercal Neutron Peak Thermal Neutron PSTD ELEM.

Loading Flux in Max. STD Elem Flux in I.F. Elem.

)1.F.ELEM.

7 6

35 FLIP 1.33 x 10 / Watt 7.45 x 10 / Watt 1.78 6

7 59 FLIP 8.06 x 10 / Watt 1.59 x 10 / Watt 0.51

b)

TiiE MAXIMUM RATIO OF Tile PEAK AT IN A STANDARD ELEMENT TO Ti!E AT AT TiiE TilERM0 COUPLE.

ANS:

Mixed Core Peak AT of Max AT at Thermocouple AT STD. Elem.

Loading Power STD. Elem.

(25 Mw-Sec Pulse)

AT (25 Mw-Sec Pulse) 35 FLIP 498 C 461 C 1.08 59 FLIP 300 C 335 C 0.89 38.

SPECIFY 110W Tile POSITION OF TiiE TRANSIENT ROD AFFECTS T!!E RATIOS DISCUSSED ABOVE FOR BOTil FLIP AND STANDARD ELEMENTS.

ANS: The position of the transient rod in a mixed core would not have a significant affect on the ratios presented in Question 37 provided the instrumented fuel element is not adjacent to the transient rod.

It would be a poor choice to position the I.F. element adjacent to the transient rod due to the various rod height requirements of the transient rod for pulsing and steady state operations.

39.

SPECIFY Tile REACTIVITY WORTil 0F EACll INDIVIDUAL CONTROL ROD OR WORTil RANGE UNDER DIFFERENT CORE CONFIGURATIONS.

ANS:

Rod worth data has been included for Cores IV-B and VII which are representative of a mixed core and full FLIP core both of which have been used at the Nuclear Science Center (see at tachment).

40.

REGARDING APPENDIX III, " SAFETY EVALUATION OF Tile IRRADIATION OF EXPLOSIVES IN NEUTRON RADIOGRAPilY FACILITY," TllE FOLLOWING INFORMATION IS DESIRED.

a.

ARE DEVICES SUCl! AS SATCllEL CilARCES, SilAPED CllARGES AND OTilER MILITARY DEVICES RADIOGRAPilED? IF SilAPED CilARGES ARE RADIOGRAPilED, Wily WASN'T Tile EFFECT OF " JETTING" CONSIDERED?

ANS:

If a shaped charge were to be radiographed the fccus of its blast would be directed away from the beam port.

Thus, it would present no additional hazard and was not discussed.

b.

WilAT IS Tile BASIS FOR PREDICTING A PEAK PRESSURE OF LESS TilAN 2 PSI IN Tile LOWER RESEARCli LEVEL FROM Tile DETONATION OF A 5-LB EXPLOSIVE CliARGE?

ANS:

The peak pressure is determined from empirical data presented in

" Baker, W.

E.,

(1978), ' Internal Blast Loading', a short course on Explosion llazards Evaluation', Southwest Research Institute, pp. 3-6 to 3-34.

The peak pressure is determined by the free volume of the lower research level and the total of 5 lbs. of explosives. Actually, the upper level is open to the lower level and the total free volume of the facility, 180,000 ft 5, could be used.

This results in a peak pressure of approximately b psi.

1

.c.

WHY IS THE POTENTIAL OF MISSILES WITH CREATER MOMENTUM THAN TilAT OF Tile.38 SPECIAL-BULLET DISCOUNTED?~

ANS:

The potential of a missile with greater momentum than.38 bullet is not discounted.

If it were generated and directed towards the end of the beam port it could cause pool leakage. Ref:

" Additional Information Concerning Texas A&M University, Nuclear Science Center Reactor Radiography of explosive Material Request for a Technical Specification Change", submitted 15 May 1979.

d.

WHAT IS THE MAXDIUM QUANTITY OF EXPLOSIVES (TNT EQUIVALENT) TilAT WILL -

BE ALLOWED IN Ti!E FACILITY AT ANY TIME?

ANS: The maximum quantity of explosives allowed in the facility containment-at any one time is 5 pounds.

41.

Tile PREVENTION OF PEAK CORE TEMPERATURE IN STANDARD CORES FROM EXCEEDING 950 C IS DISCUSSED AT TOP OF PAGE 137 (SAR).

SHOULD NOT TilIS NUMBER BE 800 C FOR STANDARD FUEL, TO BE CONSISTENT WIT!! ESTABLISiiED SAFETY MARGIN DESCRIBED ON PACE 132, " EVALUATION OF Tile LSSS"?

ANS:

In the discussion at the top of page 137 (SAR) the second sentence should read: (Thus, if a value of 667 C were chosen for the LSSS, it would prevent peak core temgeratures from exceeding 800 C in standard fuel elements and 950 C in FLIP fuel elements for all cores that comply with the Technical Specifications.)

42.

EXPLAIN Tile ORDINATE SCALE ON FIGURE 3, APPENDIX II.

ANS:

The ordinate scale on Figure 3, Appendix II of the SAR should read:

(DECAY llEAT POWER, Watts /Kw OPERATION POWER.)

ATTACHMENTS I

I i

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'NSC Texas A&i4 University Form-316 NUCLEAR SCIENCE CENTER

~

Revised 9/79 WEEKLY ELECTHONIC MAINTENANCE Cl!ECKS EMEHUENCY AIR HANDLING CHECh Notify Senior Reactor Operator cn duty Notify Her.lth Physicist Announce Ventilation System Shutdown on Femco Place " Air Handling System Shutdown" switch located in the control room to the "0N" position.

Verify all air handling unit.s and chem lab exhaust hood

~

are chutdown and building closure damperc are closed Check zero reading on manometer at filter system station Cont rol Panel. Check Obtain supervluor's key Manual snutdown light

'ON' Place fj1ter syntam switch to- "!N" position -

Overrlde with supervisor's key anni ut, art all air handling units All air handling units light- 'ON' (green light)

Check manual outside air damper controln by moving control clockwise, then count.er-clockwine.

Preunure indica t,or-should increase, then decrease Place exhaust controls to " MANUAL" Check manual exhaust controls by moving control clockwise, then-counter-clockwise.

Preucure indicator should increase, then decrease Ret. urn exhaust controls to "AUTU" Filter System Ch"ck Filter Syctem dampers should.be in filter mode.of operation Record pressure across filter bank in inchen or oil _ac indicated on the manometer.

(Pully clogged filtern read 2 9 inches of oil)

Return System to Normal Operation Cut all air handling units off Return filter switch to "OUT" position and return key to Supervisor Return " Air Handling System Shutdown" switch located in control room to the "0FF" position Start all air handling units.

(Allow at leact two minutes for filter dampers to operate be fore nt. art ing e haunt ran)

Figure VI-B-1(a)

N, t,,4

-..(..

[. ),..

Set fresh-air dampers such that exhaust by-pass is controlling Alarm (high) channel 1, Facility Air Monitor Verify all air handling units are shutdown Reset channel 1 alarm Restart all air handling units Alarm channel 2 Facility Air Munitor

~

Verify all air handling units are shutdown Reset channel 2 alarm Restart all air handling units REACTOR SCRAM TESTS tiotify SRO and obtain the bridge lock key Raise a scrammable rod a few centimeters-Unlock the bridge.

The scrarmaable rod should drop.

This indicates the loss of magnet power Return the bridge lock key to the SRO Heset the magnet power and rai:m a scrammable rod a few centimeters Depress experlmenter scram buttun on lower research level north wall

- Veri fy that the scrammable rod drops Reset the magnet power-and again raise a.:crammable rod a few centimeters Depress experimenter scram button on lower research level south wall Verify that the.scrammable rod drops Inform the SRO that scram tests have been completed SCOTT AIR PAK CHECK Read gauge on neck of bottle Record pressure reading Cneck completed by Date SRO Signature Figure VI-B-llD) g g

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TRAINING PROGRAM OUTLINE FOR NON-IIEALTH PHYSICS STAFF Topic-Outline - approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in length I.

Introduction-II.

Facility Entry and Exit A.

Normal Working Hours B.

After Hours III.

Emergency Plan IV.

Radiation Effects V.. Instruction Concerning Prenatal Radiation Exposure (Regulatory Guide 8.13)

VI.

The Nuts and Bolts of Radiation Safety A.

Radioactivity and Radiation-B.

Radiation Dose C.

Units of Radioactivity D.

Behavior of Radiations E.

Principles of Protection I

+

--- =

~

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EXPOSURE

SUMMARY

FOR 1977-1981 NUCLEAR SCIENCE CENTER -- TAMU Estimated Whole Body Number of Individuals in Range Exposure Range (Rem) 1977 1978 1979 1980 1981 No Measurable Exposure 5

37 9

18 15 Measurable Exposure < 0.1 16 13 30 19 29 0.1 to 0.25 15 4

4 9

6 0.25 to 0.5 2

2 2

5 6

0.5 to 0.75 5

0 4

1 2

0.75 to 1.00 1

0 0

0 0

1.00 to 2.00 1

2 1

0 3

2.00 to 3.00 0

0 0

1 0

Greater Than 3.00 0

0 0

0 0

Total Number Reported 45 58 50 53 61

~

NSC.

Date of-Scram Time of Scram Form.539 ~

5/76 E

1. 8" Texan ALM Univernity NUCL' EAR

.-S C !.E N C C CENTER Recovery from Unncheduled Scram I.

' PERSONNEL ON DUTY: SRO RO IIP II. -CONDITION OF REACTOR PRIOR TO SCPAM:

Mode Power Level Rod lleights:

1. 1

1. 2

1. 3

1. 4 Tr Reg

~

Experiments in Core III.

SUMMARY

OP OBSERVATIONS:

(Alarms, Tripped Meters, etc.)

Chart Traces:

fuel Log N Linear.

Temperature IV.

CONSIDERED CAUSE OF SCRAM,* COMMENTS:

• If a high fuel element temperature scram occurred,Section VII must be-completed and approved before reactor operation is resumed.

I

[t Figure II-B-10(a)

V.

Wi!AT WAS DONE PRIOR TO RESTART Of REACTOR TO ItiSURE SAFE AND P!:0Pl.R Ol'l: RAT 10?1 VI.

C0!IDIT10tl 0F REACTOR AFTER STARTUP Mode Power Level Rod II ights:

1. 1

1. 2

1. 3

1. 4 Tr Peg Experiments in Core Operator Sinnatuve SRO Signature VII.

TEMPERATURE SCRAM EVALUATI011 Instrumented Fuel Element #

TC#

Mode:

SS Pulse Description of events leading to scram Maximirn Temperature Observed:

Recorder F

Doric F

(0 value from Paactor Log ) x (max temp olmerved) =

F Evaluation:

LSSS was exceeded:

Yes

!!o Safety Limit was exceeded:

Ye si-

!!o Evaluation performed by

• If safety limit was exceeded refer to Tech Cree f3 Vill.

Scram review by Management Date d

,(

Figure II-B-10(b)

GRA

A B

C D

E F

l I

I 9-l3 LINEAR PULSE iia POWER.

A

'V' tii!::

8 liii 7

Maimieeieff2 Ca!E3iEO!E8l@)

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NSCR CORE IV-B

NSC Tons 576 Texas ACH University 11-76 NUCLEAR SCIENCE CENTER ANNUAL CONTROL ROD CALIDRATION AND SHUTDOWN HARGIN DETEPMINATION I.

Results of Control Rod Calibration control Rod Date Calibrated Control Rod Worth SS II 4/..? #

J '/8-SS 62

'/- 3 71

.J. */2

?

SS 63 VJ M

._3 J F SS 64

_ 4 J-14

'/. 4 9 Reg Rod

'/-J-?1 67 Transient Rod

~~

J Total Control Rod Worth

/3, d 7 II.

Detensination of Shutdown Margin A.

Determine Core Excess at 300 Watts:

300 Watt Excess Rod Nwaber Position Remaining SS 91

/?.O h'2S'0

/. 'l /

SS i2

/ 9. 0 (n.S'?. )

/ 29 SS 63

/ 'A (> b) J'2)

_ /-P / 6 9 SS 94

/'T C (JJ S*9.)

.'2. *l.L Reg Rod

/O 5' VL Transient Rod

~

Core Excess at 300 Watt

'7-)'$

B.

The highest worth non-secured experiment in its most reactive state is worth Al

• C.

Compute Shutdown Margin:

j Total Control Pod Worth

/ 3. '/'7 (Subtract) Core excess at 300 Watts

"? 2 f (Subtract) Highest worth exp o'

(Subtract) Most reactive rod worth

~ Y M9

-(Subtract) Peg rod worth 87 Shutdown Margin :

1. f, / 3 Control. Rod Calibration and Shutdown Margin reviewed by SRO

/ 6 k.._. _

d0l SS d's Peg Yod

0. $r'u fi Y$

Trancient Rod

//

._,_/i 2 ____

Core I:xcer.c at 300 Watt

[

B.

The highest porth non-r.ecured experiment in its moct reactive stato is uorth -

W. UA C.

Cc.npute Shutdown Marcin:

Total Control PoJ Worth

_b>

(Subtract) Core exceu;.it 300 Wattr.

d b '/'

(Subtract) Highest wor th exp W

( Subt ract ) Mor,t reac t i ve-tod worth

1. /. i (Subtract) Reg rod worth Shutdown Margin =,h[, [) f Cont rol Pod Calibration and Shutdown Margin reviewc.! by SFO

_ M A L ~. % !M l l' "

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-