ML20030B469
| ML20030B469 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 07/31/1981 |
| From: | Russell J Neely Research Reactor, ATLANTA, GA |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20030B467 | List: |
| References | |
| NUDOCS 8108180153 | |
| Download: ML20030B469 (35) | |
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GEORGI A INSTITUTE OF TECHNOLOGY SCHOOL OF* NUCLEAR ENGINEE5tlNh' ATLANT A, GEORGI A 30332 dl AUC 4 ' A 9 : 5J Flr AN K H. N E E LY NUCLE AR RESE ARCH CENTER T E L E PH ON E T (404)894 3600 July 31, 1981 U. S. Nuclear Regulatory Commisrion, Region II 101 Marietta Street, N.W. Suite 3100 Atlanta, Georgia 30303
Reference:
Report No. 50-160/81-01 Gentlemen:
This letter is in response to the referenced report / inspection of the Georgia Tech Research Reactor. The three reported items are discussed in detail below.
A.
Surveillance accomplished greather than plus or minus 25% of the required interval.
We acknowledge that on the two occasions noted in the report, portions of our ECCS monthly surveillance were not accomplished within the required limits. We believe the reason was due, in part, to the fact that the status of the reactor was changed from Mode 2 (ECCS required) to the Mode 1 (ECCS not required) and back to Mode 2.
Additionally, the plus or minus 25% interval is not explicitly noted on our surveillance documents leading, we believe, to the limit being inadvertantly exceeded.
We propose to strengthen our surveillance program by the following:
1.
Where possible, all surveillances will ha scheduled for the first Monday of the month due.
In addition, specific plus and minus 25% dates will be noted on the document. We expect these steps to be incorporated beginning with the surveillance k
documents for September, 1981.
2.
We are currently exploring ti.e use of a recently available computer for use as a back-up tickler system for the surveil-lance program.
If the reliability of the computer can be demonstrated, we expect to utilize it as a backup to the existing system.
8108180153 81080E PDR ADOCK 05000160 Q
U. S. Nuclear Regulatory Commission, Region II Page 2 July 31, 1981 B.
Written surveillance procedures Because the surveillance documents we had been using were not individually and explicitely approved by the Nuclear Safeguards Committee, we have written twenty-three (23) Instrumentation and Sr"veillance Procedures and inccrporated them into the Procedure System for the Georgia Tech Research Reactor.
The new procedures were reviewed by the Nuclear Safeguards Committee and approved on July 17, 1981. Enclosed with this letter are copies of these procedures. We believe we are now in full compliance.
C.
Operator Requalification Program The failure of two Senior Operators to complete the miminum number of reactivity manipulations and to adequately document the perfor-mance and competency of some of the staff was due in part to a mis-understanding of the requirements and to a change in responsibility for the Requalification Program.
We propose to add the reactivity manipulations requirement to our surveillance progran as a quarterly requirement and the performance and competency documentation as an annual requirement. This has been completed.
Additionally, performance and competency documen-tation for the individuals noted in the report has been initiated and will be completed by August 15, 1981.
I believe the above material answers the questions in the referenced report.
If you should need additional clarification or information, please do not hesitate to call.
Sincerely yours, l
/
s
/
L. Russell, Jr., Director 6 clear Research Center JLR:1rm
Enclosures:
Procedures as stated cc: Members, Nuclear Safeguards Committee File:
Docket 50-160-1981
'b c bd mcLe b Notary Put!!c, Georg!a, State At Large th Coremission bpares h*sy 24,198)
1 4
GEORGIA TECH RESEARCH REACTOR Chapter 9 Procedure 7200 Instrumention Approved 7-17-81 and Laters Rev.7-17-81 d
Surveillance Radionuclide Analysis Page 1 of 2 I.
GENERAL REQUIREMDIT A.
Frequency Monthly B.
Technical Specification or other reference See 4.4 c.
II.
PREREQUISITES Before sampling, the reactor should be at a power level of 1 MW and have operated for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at 1 MW.
III. PROCEDURAL INSTRUCTIONS A.
Adjust primary coolant sampling valves to permit recirculation of~
D 0 through the sample line for a miminum of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2 B.
Observe proper health physics techniques and take a 10 mi sample of D 0.
Secure sampling valves.
2 C.
Make a gamma ray spectrographic analysis of the sample using the instruction set (set up, calibration, program and analyzer operation cards) for the Ge(Li) detecter system.
D.
Log the results on the data sheet for this procedure IV.
ACCEPTANCE CRITERIA Notify Reactor Supervisor if fission product peaks are detected in the spectrum.
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GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7200 Instrumention Approved 7-17-81 and Lates t Rev. 7-17-81 Surveillance Radionuclide Analysis Page 2 of 2 Radionuclide Analysis - Data Sheet Report for month of Done on
/
/
By Calibration m=
b=
By Peak energy = m " peak channel + b Sample size 10 m1 taken with a 10 ml pipet Counting time (live time)
- 1) 15 min. after sampling sec.
- 2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> sec.
24 Hours sec.
t.
Peak Peak Counts Counts Peak Comments No.
Channel Energy at Peak in Area Ident.
GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7201 Instrumention Approved 7-17-81 Cooling Tower Tritium Sampling Latest Rev.7-17-81 and Page 1 of 1 Surveillance I.
GENERAL REQUIREMENT A.
Frequency Monthly B.
Technical Specification or other references See 3.Sa (2) and 4.4d.
II.
PREREQUISITES None III.
PROCEDURAL INSTRUCTIONS A.
Use a clean vial and take a 5 ml sample of the water in the basin of the reactor cooling tower.
B.
Analyze the sample per Health r:4y=Ir= procedure 9019, " Cooling Tower Tritium Analysis" IV.
ACCEPTANCE CRITERIA If calculated concentration is 4.0 X 10-pCi per cc or greater, take a second sample.
If confirmed, notify Reactor Supervisor, I
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I GEORGIA TECH RESEARCH REACTOR Chapter 9 Procedure 7202 Instrumention Approved 7-17-81 Latest Rev.
7-17-81 Control Rod Drop-Time Surveillance Page l of 2 I.
GENERAL REQUIREMENT A.
Frequency Monthly B.
Technical Specification or other reference See 3.2c., and 4.2c.
II.
PREREQUISITES A.
Reactor shutdown B.
A licensed reactor operator to perform the rod withdrawls C.
Containment Integrity operable (see Tech. Spec. definition 1.26).
III. PROCEDURAL INSTRUCTIONS A.
Reset all control interlocks B.
Drive the Regulating Rod from IN to OUT and record the following times (in seconds) or positions (in inches) on the data card in the Control Room files.
1.
DOWN limit switch position 2.
Time to drive to the UP limit 3.
UP limit switch position 4.
Time to drive to the DOWN limit C.
Set up initial conditions for the Universal Counter as described on the Instruction card in the Control Room files.
D.
Select a shim blade. Drive from DOWN limit to UP limit (determine Aux.
Switch setting).
Reset counter and press MANUAL SCRAM Switch.
Record values for the following positions and times.
1.
DOWN limit switch position 2.
Auxiliary DOWN limit switch position 3.
UP limit switch position 4.
Drive time to UP limit 5.
Two drop times in milliseconds, as determined by the Universal Counter E.
Repeat D 1-5 for the remaining shim blades
O 4
GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7202 Instrumention Approved 7-17-81 and Latest Rev.
7-17-81 Surveillaine Control Rod Drop-Time Page 2 of 2
IV.
ACCEPTANCE CRITERIA A.
Regulating Rod 1.
Limit switch positions Down limit between 0.0 and 0.2 inch UP limit between 11.8 and 12.0 inch 2.
Drive time Between 45.5 and 48.5 secands B.
Shim Blades 1.
Limit switch position UP limit between 54 and 57 degrees 2.
Drive time Between 330 and 345 seconds 3.
Drop time Between 430 and 500 milliseconds and time is not + 20 msec different from previous months time.
C.
Advise Reactor Supervisor if any acceptance criteria are not met.
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1 GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7203 Instrumention Approved 7-17-81 and ECCS-Monthly Surveillance Latest Rev.7-17-81 Surveillance Pagel of1 I.
GENERAL REQUIREMENT A.
Frequency Monthly 4
B.
Technical Specification or other reference See 3.7a, 5.4a, and 4.5d II.
PREREQUISITES A.
Reactor shutdown B.
Cooldown requirements met III. PROCEDURAL INSTRUCTIONS A.
Verify primary coolant pump and purification pump are OFF.
B.
Verify TD-2 tank level is at overflow and block valve 94 OPEN C.
OPEN valve 8 and begin draining reactor vessel to storage tank TD-1.
Allow level to decrease until a Reactor Tank Low alarm is received.
j CLOSE valve 8.
D.
Confirm that the following actions occurs:
1.
Reactor Isolation Valves CLOSE 2.
TD-2 Spray Valves OPEN f
3.
FLOW from TD-2 is initiated l
E.
Simultaneous with III.D.2, begin timing for ECCS flow rate measurement.
Measure time for TD-2 level to drop to 1-inch.
F.
Start primary coolant pump and purification pump.
Restore reactor vessel and TD-2 to normal levels.
(
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In the High Bay Area, operate ECCS pump MEC-1 for a minimum of 5 minutes.
IV.
ACCEPTANCE CRITERIA A.
Reactor Isolation valves CLOSE on Reactor Low Level B.
TD-2 Spray Valves OPEN on Reactor Low Level I
C.
Time for TD-2 level to drop from overflow to 1 inch is between 30 and 36 minutes.
D.
Standby pump KEf operates normally.
.~.
GEORGIA TECH RESEARCH REACTOR Chapter 9 Procedure 7220 Instrumention Approved 7-17-81 and Latest Rev. 7-17-81 Surveillance Building Isolation Test Page 1 of 1 I.
GENERAL REQUIREMENT A.
Frequency Semi Annual B.
Technical Specificat;on or other reference See 4.3a.
l II.
PREREQUISITES Reactor shutdown or operating at a power level of 100 KW or less.
III. PROCEDURAL INSTRUCTIONS l
A.
Reset all building isolation circuits and select a channel to be tested.
i B.
Initiate an isolation trip from the selected channel and verify:
1.
Trip point setting correct for the selected channel.
2.
All containment building isolation valves CLOSED. Check by physical inspection.
a.
Inboard and Outboard Inlet valves b.
Inboard and Outboard Outlet valves H15 and H16 flight and air supply valves-containment side 4
c.
d.
H15 and H16 flight and air supply valves-laboratory side.
Complete steps A and B above for the following channels c.
1.
Kanne i
2.
MAP-1 1
3.
Gas Monitor 4.
Filter Bank Monitor 5.
D 0 Leak Channel 2
IV.
ACCEPTANCE CRITERIA l
1 Each channel causes a complete building isolation to occur at its correct trip point setting.
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GEORGIA TECH RESEARCH REACTOR Chapter 9
Instrumention Procedure 7221 and Approved 7-17-81 Ourveillance Airlock Doors-Pressure Switch Check Latest Rev.
7-17-81 Page lof 1 I.
GENERAL REQUIREMDIT A.
Frequency Semi-Annual B.
Technical Specification or other reference See 3.2a II.
PREREQUISITES A.
Reactor Shutdown, Cooldown requirements met B.
No core reactivity changes in progress III. PROCEDURAL INSTRUCTIONS A.
Use the Heise gauge test assembly and check the trip setting of the Mercoid pressure switches at each airlock and the truck door.
Set point is 20 psig.
E.
Lubricate cabi. hinges and lever operating mechanism C.
Check adjustment of panel and ratchet interlock for proper functioning D.
Thoroughly clean the metal gasket seat and the rubber gasket.
Lubricate rubber gasket lightly with talcum powder or silicone oil.
Do not use a mineral base oil.
IV.
ACCEPTANCE CRITERIA Each pressure switch functions at 20 psig + 1 psi.
GEORGIA TECH RESEARCH REACTOR Chapter Procedure 7222 Instrumention Approved 7-17-81 and Surveillance ECCS Semi-Annual and Annual Surveillance p,"
- 1 e
f2 I.
GENERAL REQUIREMENT A.
Frequency Semi-Annual and Annual B.
Technical Specification or other reference See 3.7a., 4.5b., and 4.5c.
II.
PREREQUISITES A.
Reactor shutdown i
B.
Cooldown requirements met III.
PROCEDURAL INSTRUCTIONS A.
Semi-Annual Test of Individual Fuel Element Flow 1.
Shutdown primary coolant and purification pumps if running 2.
CLOSE manual ECCS valve 94 3.
Mark recorder trace TR-1, Individual Fuel Element temperatures.
Verify all points printing.
4 Initiate MANUAL ECCS and OPEN spray block valve 94 5.
Observe a temperature drop on all fuel elements with functioning thermocouples.
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6.
CLOSE block valve 94 l
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7.
For those fuel elements w~thout functioning thermocouples, use procedure 1502 to selectively remove a fuel element and, using special mirror and viewing telescope, visually observe ECCS flow to those elements by OPENING valve 94.
8.
Restore all systems to normal.
B.
Annual Test of Light Water Addition System.
1.
Procure two 1 inch Flexitallic gaskets and an RWP 2.
Install blind flange to prevent H 0 from entering TD-2, use suitable 7
5 3:11on container at test point to receive the light water.
3.
Establish communication with operator at light water addition station.
e GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7222 Instrumention Approved 7-17-81 Latest Rev. 7-17-91 and Surveillance ECCS 9emi-Annual and Annual Surveillance Page 2 of 2 4.
Connect special jumper hose on ECCS addition line in pipe tunnel 5.
OPEN valves 690 and 691 6.
Open valve 688 to set flow of light water (from city water line) to 10 gpm.
When steady flow of water in reported at ECCS tank, secure flow by closing valves 688, 690, and 691.
8.
Remove jumper hose 9.
Drain the ECCS light water addition line by using valve at laboratory side of containment shell. Sample water for tritium before disposal.
10.
Sample water at TD-2 tank for tritium before disposal.
11.
Remove blind flange and re-install in normal position.
Use new gaskets.
IV.
ACCEPTANCE CRITERIA A.
Semi-Annual Test Demonstrate that ECCS water is supplied to each fuel element by thermocouple response or visual observation B.
Annual Light Water Addition Test Demonstrate that light water can be supplied from the laboratory building to the test flange at TD-2.
~
GEORGIA TECH RESEARCH REACTOR Chapcer 9
Procedure 7223 Instrumenti'1n Approved 7-17-81 and Latest Rev. 7-17-81 Surreillance ECCS-Tank Level Calibration Check Page 1 of 2 I.
GENERAL REQUIREMENT I.
Frequency Semi-Annual B.
Technical Specification or other reference
.See 4.5e.
II.
PREREQUISITES A.
Reactor shutdown B.
Cooldown requirements met III. PROCEDURAL INSTRUCTIONS A.
Shutdown primary and purification pumps if running B.
Record data on the attached Data Sheet (page 2 of 2)
C.
Initiate manual ECCS D.
Take simulatanecus level readings of ECCS tank from the Barton differential pressure indicator LIA-D2, and the column indicater LC-D2 from tank over-flow to 5-inches. Take data at approximately 2-inch intervals.
E.
Note and record actuation of Low Level alarm for TD-2 IV.
ACCEPTANCE CRITEFJA A.
Tank level data should agree to within + 2 inches with the column in-dicator LC-D2 considered correct.
B.
Low level alarm should actuate between 24 and 25 inches.
C.
It criterion IV. A. is not met, calibrate the Barton differential pressure indicator following manufacturers instructions. Complete a data sheet following calibration.
GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7223 Instrumentation Approved 7-17-81 Latest Rev.7-17-81 and ECCS-Tank Level Calibration Check Page 2 of 2 Surveillance DATA SHEET Operator Date LC-D2 LIA-D2 COMMENT COLUMN IPDICATOR DIFF. PRESS. IND.
)
Low Level Alarm actuates at inches (Read LC-D2) l O
n,.
GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7224 Instrumention Approved 7-17-81 and Latest Rev. 7-17-81 Surveillance D 0 Leak Detection System Surveillance Pagel of 1 2
I.
GENERAL REQUIREMENT A.
Frequency Semi-Annual B.
Technical Specification or other reference See 3.2a.
II.
PREREQUISITES Reactor shutdown for a minimum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> III. PROCEDURAL INSTRUCTIONS A.
Verify building isolation circuitry is operable, building not isolated.
B.
Verify "D0 NOT ENTER" and "AFTER HOURS" alarms are not activated.
C.
Select one of the D 0 leak collection cups and add a small (5 ml) 2 amount of distilled H 0.
2 D.
Verify the following 1.
Building isolation with alarm plate 2.
DO NOT ENTER alarm activates 3.
AFTER HOURS alarm activates i
E.
Remove water from cup and replace salt-impregnated paper.
1 L
F.
Verify all alarms reset G.
Check all collection cups for:
1.
Presence of salt impregnated paper l
l 2.
Correct position to receive any D 0 leakage 2
H.
At the D 0 Leak Detection control panel in the Process Equipment Room, 2
activate each circuit using the test buttom.
I.
Restore system to normal l
IV.
ACCEPTANCE CRITERIA Any selected leak detection position will'cause the action specified in lllD.
GEORGIA TECH RESEARCH REACTOR Chapter g
Procedure 7225 Instr umention Approved 7-17-81 Latest Rev. 7-17-81 and Primary Coolant System-Mechanical Surveillanc e Page 1 of 1 Sur/eillance I.
GENERAL REQUIREMENT A.
Freqeuecy Semi-Annual B.
Technical Specification or other reference See 6.4b. (5) and Question No. 5, Letter to NRC dated 6-23-72 II.
PREREQUISTES Reactor shutdown III. PROCEDURAL INSTRUCTIONS A.
Visually check all primary coolant piping and system components including welds, flanges, valves, pumps and heat exchangers for any indication of leakage, deterioration or fault.
B.
Lubricate pump motors.
C.
Lubricate valve stems, check each valve for ease of operation.
D.
Check MD-2A seal for excessive leakage. Start and stop pump to make this check.
E.
With all systems operating normally at nominal flow rates, check for unusual vibration.
F.
Check operation of reflector drain valves SA and 5B including solenoid function.
IV.
ACCEPTANCE CRITERIA No excessive vibration, leakage or other fault indication should be apparent.
A GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7226 Instrumention Approved 7-17-81 and Latest Rev. 7-17-81 Surveillance Scram Insertion Delay Time Measurement Page 1 of1 I.
GENERAL REQUIREMENT A.
Frequency Semi-Annual Technical Specification or other reference L;e 3.2d.
II.
PREREQUISITES A.
Reactor Shutdown B.
Licensed reactor operator at console III. PROCEDURAL INSTRUCTIONS A.
Set up Universal Counter as described on the Instruction card in the Control Room files.
B.
Remove "B" input to Universal Counter from Log Count Rate channel a.id connect cable identified as "Stop Signal For Scram Delay Insert" to B input.
C.
Verify other end of signal cable in attached to the BNC connector on relay K15 (Shim blade #4 UP LIMIT).
J D.
Raise shim shafety blade #4 to UP limit, reset counter and PRESS MANUAL SCRAM switch.
E.
Record time in milliseconds on Control Room data card.
F.
Repeat steps D. and E.
i IV.
ACCEPTANCE CRITERIA A.
The times must be less than 100 msec.
B.
The average delay time should not be more than 15 msec different from average of previous last two measurements.
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GEORGIA TECH RESEARCH REACTOR Chapter g Procedure 7240 Approved 7-17-81 Instrumention and Reflector Drain Valve Solenoid Maintenance Latest Rev. 7-17-81 Page 1 of 1 Surveillance I.
GENERAL REQUIREMENT A.
Frequu..cy Annual B.
Technical Specification or other reference None II.
PREREQUISITES A.
Reactor shutdown B.
Top reflector drained C.
Drain valves 5A and 5B OPEN D.
DO NOT OPERATE Tag on Drain Valve control switches III. PROCEDURAL INSTRUCTIONS A.
Valve off air supply to solenoid valves; remove air fitting connection at solenoid.
B.
Remove cylinder exhaust fittings from each solenoid.
C.
Loosen retaining nut at bottom of each solenoid.
CAUTION:
Do not allow any pieces to drop into TD-1 pit D.
Remove solenoid coil and valve body E.
Take entire unit to workbench, dissemble and clean all parts.
Lubricate with a light silicon oil. CAUTION:
Do not use a mineral base oil.
l F.
Replace 0-rings and gaskets if required.
G.
Reassemble and replace solenoid unit on the valve; remove tag from control switches IV.
ACCEPTANCE CRITERIA With personnel in the centrol room and at the valve location, operate the valves five (5) times. Verify both valves open and close fully each time they are operated.
GEORGIA TECH RESEARCH REACTOR Chapter 9
Precedure 7241 Approved 7-17-81 Instrumention and Peactor Tank Level Maintenance and Latest Rev.7 81 Surveillance Calibration Check Page 1 of 2 I.
GENERAL REQUIREMENT A.
Frequency Annual B.
Technical Specification or other reference See 3.2A.
II.
PREREQUISITES A.
Reactor shutdown B.
Cooldown requirements met
(
C.
Licensed reactor operator in control room III. PROCEDURAL INSTRUCTIONS A.
Inspect transmitter and receiver for evidence of air or D 0 leakage.
2 B.
Turn off air supply; remove restriction screw and clean C.
Remove air filter; clean or replace Carefully vent D 0 (high-pressure) side of cell into suitable container D.
2 to remove any liquid D 0.
2 Carefully drain He (low pressure) side of cell into suitable container E.
to remove any liquid D 0.
2 F.
Reestablish air supply.
Record calibration check data on the attached Data Sheet (page 2 of 2).
G.
Open level column drain valve and allow column level to decrease about H.
2 inches. Close valve and take column level and control room indication readings.
I.
Repeat step H until column indicates 25-inches.
Compare the data; if L1-D1 is more than + 1-inch from LC-D1 value, calibrate J.
the transmitter following manufacturers instructions. Complete a data sheet following calibration.
K.
Restore level system to normal configuration of all valves.
IV.
ACCEPTANCE CRITERIA L1-D1 value to be no more than + 1 inch from LC-D1 value
GEORGIA TECH RESEARCH REACTOR Chapter 9 Procedure 7241 Instrumentation Approved 7-17-81 Reactor Tank Level Maintenance and Latest Rev.7-17-81 and Page 2 of 2 Surveillance Calibration Check g
Data Sheet Operator Date l
Comment LC-D1 LI-D1 Column Ind.
Control Reem
=4
%am vAM hm-ma seNo + enc w = ag,w4stdu M9 9tP %8&
""*"9**"**'WM*'8
- N" " " *'
4 4
GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7242 Instrumention Approved 7-17-81 Reactor Control System-Interlock Latest Rev.7-17-81 and System Maintenance Page 1 of 1 Surveillance I.
GENERAL RFQUIREMENT A.
Frequency Annual B.
Technical Specification or other reference See 6.4 b. (5)
II.
PREREQUISITES A.
Reactor Shutdown B.
Cooldown requirements met C.
Licensed reactor operator in control room III. PROCEDURAL INSTRUCTIONS i
A.
Visually check all relays for any indication of loose or broken parts.
l
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B.
Spray all relay contacts with suitable contact cleaner.
C.
Using an insulated screwdriver and a great deal of care, check that all screws on the terminal boards behind the panels are tight.
IV.
ACCEPTANCE CRITERIA No apparent problems F
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GEORGIA TECH RESEARCH REACTOR Chapter 9 Procedure 7243 Instrumention Approved 7-17-81 Latest Rev. 7-17-81 and Reactor Controls -- Regulating Rod Drive Surveillence Maintenance Page 1 Of 1 I.
GENERAL REQUIREMENT A.
Frequency Annual B.
Technical Specification or other reference See 4.la.
II.
PREREQUISITES A.
Reactor shutdown B.
Cooldown requirements met C.
Licensed reactor operator in control roo~
III. PROCEDURAL INSTRUCTIONS A.
Remove Lead Cover Plate and Upper Top Shield to gain access to the regulating rod.
B.
Verify Regulating Rod is on the DOWN limit.
C.
Following instruction on maintenance card, dissassemble drive shaft, inspect and lubricate the ball-nut drive mechanism.
D.
Reassemble mechanism E.
Verify both UP and DOWN limit switch positions F.
Operate Regulating Rod, verify time to drive UP and DOWN within limits.
G.
Lubricate external (reactor-face) drive gear system with Shell Tellus
- 29 or equivalent.
IV.
ACCEPTANCE CRITERIA A.
No apparent mechanical faults B.
DOWN limit between 0.0 and 0.2 inch C.
UP limit between 11.8 and 12.0 inches D.
Drive time between 45.5 and 48.5 seconds
GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7244 a
Instrumention Approved 7-17-81 and Reactor Controls - Shim Safety Latest Rev7-17-81 Surveillance Blade Drive Maintenance Page 1 of 1 I.
GENERAL REQUIREMENT A.
Frequency Annual B.
Technical Specification or other reference See 4.1.a II.
PREREQUISI?ZS A.
Reactor shutdown B.
Cooldown "equirements met C.
Licensed reactor operator in control room III.
PROCEDURAL INSTRUCTIONS A.
Visually observe operation of each shim blade drive mechanism from 0 to 20 degrees including clutch release. Check for bind-ing, mis-alignment, clutch slippage or cther mechanical faults.
Use manufacturers instructions to adjust any faults.
B.
Check dash pot oil level C.
Oil ball-nut mechanism, needle bearing and thrust ball bearing with Shell Tellus #29 or equivalent CAUTION: Do not allow any oil, grease, spray or other lubricant to get on the clutch surfaces.
l D.
Clean mechanism l
E.
Request control room operator to OPEN AU and AV switches F.
Using an insulated screwdriver, check all screws tight on the terminal strip l
NOTE: AU and AV do NOT remove all power to the terminal strip IV.
ACCEPTANCE CRITERIA No apparent mechanical faults u
~m,-
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GEORGIA TECH RESEARCH REACTOR Chapter g Procedure 7245 Instrumention Approved 7-17-81 and Reactor Shutdown Margin Determination Latest Rev.7-17-81 Surveillance Page 1 of 1 I.
GENERAL REQUIREMENT A.
Frequency Annual (but see Technical Specification 4.la. )
B.
Technical Specification or other reference See 3.la. and 4 la.
II.
PREREQUISITES A.
Applicable startup checklist complete B.
Licensed senicm reactor operator and reactor operator on duty III. PROCEDURAL INSTRUCTIONS A.
Reactor Shutdown Margin Determination 1.
Startup reactor, stabilize pcwer at approximately 1 KW with shim blades bankes within h degree 2.
Adjust recorder output potentiometer from one of the linear picoa= meter channels so that recorder trace is approximately 100% on recorder scale. Put chart speed switch on EAST.
3.
Down-range the selected picoammeter a factor of 10, causing chart pen to drive to full up-scale position.
4 Manually scram the reactor 5.
Collect recorder trace data for 3 minutes, then return chart speed switch to SLOW.
6.
Remove the applicable chart section and deliver to reactor manage-ment personnel for analysis.
IV.
ACCEPTANCE CRITERIA l
l A.
The shutdown margin relative to the cold, Xenon free, critical con-dition shall be at least 0.01 AK/K with the mest reactive shim-safety i
blade and the regulating rod fully withdrawn.
B.
The reactor shall be subcritical by more than 0.0275 AK/K during load-ing changes.
]
4 G ORGIA TECH RESEARCH REACTOR Chapter 9
A Proved 7-17-81 P
i Instrumention l
Latest Rev.7-17-81 and Surveillance Control Element Reactivity Worth Measurement Page 1 of 2 l
GENERAL REQUIREMENT A.
Frequency i
Annual (but see Technical Specification 4.la.)
B.
Technical Specification or other reference See 3.la and 4.la.
II.
PREREQUISITES I
A.
Applicable startup checklist complete B.
Licensed senior reactor operator and reactor operator on duty III. PROCEDURAL INSTRUC" IONS i
A.
Reactivity Calibration of Regulating Rod 1.
Startup and maintain reactor at minimum critical power; regulating rod on manual control at DOWN limit.
2.
Wait at least 15 min. then withdraw regulating rod to 3.0 inches and allow reactor power to increase.
3.
Take doubling-time data until repetitive values indicate that a stable asymtotic period has been achieved.
4.
Quickly reduce reactor power with shim blades to value in step III.
A.1., Regulating rod remains at 3.0 inches.
5.
Repeat step 2 through 4 for ragulcting rod movements of 3 to 6 inches, 6 to 9 inches and 9 to 12 ir ches.
6.
Using GTRR inhour curve, determine reactivity value associated with each regulating rod movement.
Submit data to reactor management for evaluation and analysis.
B.
Reactivity Calibration of Shim-Safety Blades 1.
Maintain a primary coolant temperatur s of 75 F + 3 F throughout this phase er the calibration.
l 2.
Position selected shim-safety blade at DOWN limit (0.0 degrees) l l
Position Regulating Rod at UP limit (12.0 Inches) i 3.
Maintain reactor at a low ( c 1 KW if possible) pcwer using remaininp; three shim-safety blades.
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GEORGIA TECH RESEARCH REACTOR Chapter 9
Procedure 7246 Instrumention Approved 7-17-81 I
and Latest Rev. 7-17-81 i
Surveillance Control Element Reactivity Worth Measuremt Page 2 of 2
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B.
(Continued) 4.
Wait at least 15 minutes to establish equiliorium.
5.
Simultaneously withdraw the selected shim-safety blade and insert the Regulating Rod to compensate.
6.
When the Regulating Rod is at or near its DOWN limit, stabilize reactor power and record both selected shim-safety blade position 4
i and Regulating rod position.
7.
Withdraw Regclating Rod to UP linit, compensating with +he three remaining shim-safety blades.
8.
Continue step 5, 6 and 7 until the selected shim-safety blade is fully withdrawn.
9.
Adjust shim-safety blades so the next selected blade is on its DOWN limit and the Regulating Rod is at its UP limit.
10.
Repeat steps 5 through 9 to complete calibration of all shim-safety blades.
4 11.
Shutdown reactor, submit data to reactor management for evaluation and analysis.
IV.
ACCEPTANCE CRITERIA Compare calculated values of control element worths to previous values l
to determine if significant changt.a have occurred.
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i GEORGIA TECH RESEARCH REACTOR Chapter 11 Procedure 9015 Health Physics Approved 7-17-81 Operations Cooling Water Gamma Monitor - Response Latest Rev. 7 '.7-81 Check Page l of 1 I.
PURPOSE The purpose of this procedure is to perform a source response check of the Cooling Water Gamma Monitor (CWGM)
II.
HATERIAL REQUIRED 1 mci ha-226 sealed source i
II
I. PROCEDURE
A.
Place 1 mci Ra-226 source against the center of the lead shield on the point marked with an X.
B.
The 1 mci Ra-226 source should cause a response of > 200,000 cpm on the ratemeter in the control room.
C.
Check that ratemeter alarm is received and "H O High Radiation" alarm 2
is activated.
D.
Remove source, clear alarms and verify normal reading on ratemeter.
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CEORCIA TECH RESEARCH REACTOR Chapter 11 Procedure 9016 Approved 7-17-81 Health Phy.31cs atest ev. 81 Operations Filter Bank Monitor - Rasponse Check p,
g 7
I.
PRUPOSE The purpose of this procedure is to perform a source response check of the Filter Bank Monitor System.
1 II.
MATERIAL REQUIRED i
10 mci Ra-226 sealed source.
II
I. PROCEDURE
A.
Place 10 mci Ra-226 source on the Filter Bank duct at the center of the position marked with an X.
t B.
The 10 mC1 Ra-226 source should cause a response of > 200,000 cpm on the rate meter in the control room.
C.
Check that the following occurs:
1.
Ratemeter alarm received 2.
" Radiation High Vent. Duct" alarm t
3.
" Vent System Low Flow" alarm 4
Building isolation is initiated 2.
Remove source, clear alarm, open building ventilation valves, start vant duct blower are verify Filter Bank Monitor returns to normal reading.
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GEORGIA TECH RESEARCH REACTOR Chapter 11 Procedure 9017 Approved.7-17-81 Health Physics Latest Rev. 7-17-81 Operations Stack Grab Sample Analysis Page 1 of 1 I.
PURPOSE The purpose of this procedure is to describe basically how to perform a Stack Crab Sample Analysis. This procedure is used to identify gamma emitting isotopes in the GTRR stack effluent.
II.
MATERIALS REQUIRED A.
Plastic bag for sample (5 gallon bag)
B.
NaI (TI) Solid Scintillation Detector C.
Multichannel Analyzer (MCA)
D.
Polaroid Camera E.
Known Co-60 Standard II
I. PROCEDURE
A.
Climb stack to sample door elevation and obtain bag sample of stack gas.
i B.
Place stack grab sample on NaI (T1) detector and set count time to 6 X 10 seconds. Acquire data in first half of memory cf the Multichannel Analyzer.
Deadtime should not exceed 7%.
C.
After spectrum is accumulated, place Co-60 standard on detectcr and accumu-3 seconds in second half at memory.
late spectrum for 6 X 10 D.
Set Multichannel Analyzer memory switch to compare and take a photograph of the MCA screen.
(See instruction for taking photos of the MCA).
~
E.
Place picture on Form RS-50 and analyze stack grab sample VS the known Co-60 spectrum.
T.
Calculate energy of all peaks sample and determine radioisotopes present.
G.
Record all information in Grab Sample Notebook for later inspection.
NOTE: SEE ATTACHED TORM RS-50 ANC CALCULATION MODEL.
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FORM RS-50 (12-78) w -~ _-
-2 c aan e W as - s.=n MULTICHANNEL ANALYZER SAMPLE ANALYSIS Dato Analysed:
Channel 2 Time:
sample physical forc Channel 1 esmple physical fort (Type of Analysis)
CHANNEL 1:
a.
Collect time b.
Dead time c.
Center channel i d.
Center channel counts e.
Integral counts f.
Integral area start stop CHANNEL 2:
a.
Collect time b.
Dead time c.
Center channel #
d.
Center channel counts a.
Integral counts f.
Integral area start stop (USE BACK FOR CGGVIATIONS)
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STACK GRAF SAMPLE ANALYSIS - CALCULATION MODEL Co-60 3*.andard:
Peak No. 1 = 1.1732 MeV Peak No. 2 = 1.3325 MeV 1.3325 MeV - 1.1732 MeV eV Per Gannel
=
CHANNEL S'*1MBER OF PEAK NO. 2 - CHANNEL NUMBER OF PEAK No.1 l
CHANNEL NUMBER OF UNKNOWN PEAK - CHANNEL NUMBER OF Co-60 PEAK NO.1 = 4 CHANNELS a CHANNELS X MeV PER CHANNEL = 4 MeV 1.1732 MeV + a MeV = CHARACTERISTIC GAMMA ENERGY OF UNKNOWN PEAK MeV Ar-41 HAS A KNOWN GA&!A ENERGY OF 1.2935 MeV i
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GEORGIA TECH RESEARCH REACTOR Chapter 11 Procedure 9018 Approved 7-17-81 Health Physics Latest Rev. 7-17-81 Operations Charcoal Cartridge Analysie Page 1 of 1 4
I.
PURPOSE 1
The purpose of this procedure is to describe basically how to ycrform a charcoal cartridge analysis.
This analysis is used to determine the 4
j activity of I-131 as a gaseous effluent emitted from the GTRR stack.
I II.
MATERIAL REQUIRED A.
Charcoal Filter Cartridge B.
NaI(T1) Solid Scintillation Detector C.
Multichannel Analyzer (MCA)
D.
Polaroid Camera E.
Known Cs-137 Standard 1
III. TROCEDURE
/
Change charctal filter cartridge B.
Place cartridge on NaI (T1) detector and collect spectra in first half 3 seconds.
of multichannel analyzer memory.
Set MCA acquire time to 6 X 10 Deadtime should not exceed 7%.
C.
Collect Cs-137 standard spectrum in second half of multichannel analyzer memory and acquire for 6 X 103 seconds.
D.
Set multichannel analyzer memory on compare and take a photograph of MCA screen.
(See instruction for taking photos of the MCA).
E.
Place picture on Form RS-50 and anclyze charcoal cartridge filter VS the known Cs-137 spectrum.
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F.
Calculate the activity and release rate of I-131 being emitted from the GTRR stack. Technical Specifications requires that the I-131 activity
-4 not exceed 8.3 X 10 pCi/sec.
i G.
Record all information in charcoal cartridge notebook for later inspection.
NOTE: SEE ATTACHED CALCULATIG; MODEL.
4
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Charcoal Cartridge Filter - Calculation Model I
Cs-137 Standard:
Primary Peak = 0.662 MeV CHANNEL NUMBER OF PRIMARY PEAK CHANNELS PER MeV
=
0.662 MeV I-131 has a characteristic gamma peak at 0.364 MeV 0.364 MeV X Channels Per MeV = Channel Number for 1-131 Peak i
NUMBER OF COUhTS = NUMBER OF COUNTS IN CHANNEL NUMBER FOR 0.364 MeV PEAK DETERMINE ACTIVITY OF Cs-13' STANDARD CORRECTED FOR DECAY:
9 A=Ae" A=
= 0.02297 A = Microcuries
=
9 1
l NUMBER OF COUNTS (I-131) X MICR0 CURIES (Co-137) g 337)
NUMBER OF COU"TS IN PEAK (Cs-137) 4 3 ml/L = 7.0 X 10 cc per minute.
FLOW RATE OF SAMPLER = 70 L/ Minute X 10 4
7.0 X 10 cc per minute X sample time = Total cc thru sampler "I"#
8
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Microcuries (I-131) per cc thru sa=pler
=
i 3 per cc per L i
Stack velocity CFM X 29.32 L per CF X 10
= cc per second stack ficw 60 seconds per minute Stack flow (cc per second) X microcuries (I-131) per cc = microcuries (I-131) per secor.1 i
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GEORGIA TECH RESEARCH REACTOR Chapter 11 Procedure 9019 Approved 7-17-81 Health Physics Latest Rev. 7-17-81 Operations Cooling Tower Tritium Analysis 1
Page 1 of 1 J
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PRUPOSE l
The purpose of this procedure is to determine the amount of tritium in cooling tower water.
II.
MATERIALS REQUIRED A.
Pipettes B.
Liquid scintillation vial + 10 cc liquid scintillation preparation C.
Liquid scintillation counter for H-3 i
II
I. PROCEDURE
I A.
Obtain water sample from cooling tower basin B.
Pipette 1 cc of sample into 10 cc of liquid scintillation preparation.
C.
Count sample for one minute 5 times and calculate the concentration (pCi/ml) of tritium in cooling tower water.
NOTE: See attached calculation model.
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t Cooling Tower Tritium - Calculational Model Counts per minute
, background
= disintegrations per minute counter efficiency Disintegrations per minute
= disintegrations per minute per cc Volume of counted sample (1 cc)
Disintegrations per minute per cc = microcuries per cc 2.22 X 106 d/m/microcuries 4
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