ML20135D282

1996 Annual Rept for Ga Institute of Technology Research Reactor

ML20135D282
Person / Time
Site:	Neely Research Reactor
Issue date:	12/31/1996
From:	Karam R Neely Research Reactor, ATLANTA, GA
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 9703050170
Download: ML20135D282 (18)

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f474>."ee?.'ser "sexic4o41.e c=a February 26, 1997 U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Atlanta, GA 30323

Reference:

Annual Report Docket 50-1C3; License R-97 Gentlemen:

Pursuant to Section 6.7.a of the Technical Specifications for the Georgia Institute of Technology Research Reactor (License R-97) ,

the following annual report is submitted. The reporting period is January 1, 1996, through December 31, 1996 (calendar year 1996).

The designation of the sections below follow the title and order of Section 6.7.a of our Technical Specifications.

1. OPERATIONS

SUMMARY

a. Chances in Facility Desian /

There was one f acility design change during calendar year N 1996. The change was approved by the Nuclear Safeguards Committee. The design change is described in Appendix A.

b. Performance Characteristics During the reporting period, the reactor was not operated at anytime. The reactor was shutdown November 17, 1995 and all the irradiated fuel was shipped to the Savannah River site in preparation for the Olympics. Spare unirradiated fuel was shipped to DOE at Oak Ridge National Laboratories. Currently we have no fuel on hand for the reactor.

9703050170 961231 PDR ADOCK 05000160 R PDR UbUUlb 5.EEElElU]EEE.EE A Unr.of the Universty System of Georgta An Equal Education and Employment Opportunity Institution

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, 4- i f: .U.S. Nuclear Regulatory Commission - Annual Report ,

February 26, 1997 l Page 2  ;

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c. Chances in ODeratina Procedures ,

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The list of new and/or revised procedures which were ~ ,

approved by the Nuclear Safeguard Committee' during j calendar year 1996 were as follows t

i Proc. # Title l

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1501 Lower Top Shield Plug Removal From Irradiated -

i Fuel Elements  :

[ 1502 Fuel Handling in the Core ,

3600 Special Nuclear Materials Inventory i

l 3801 Storage Pool Water Circulation l t

9019 Water Sample Analysis ' For Tritiwa l r

l 9037 Tritium Determination in Urine i

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l- . 9162 Calibration Procedure for the LND Ionization  ;

l' Chamber 1 Probe  :

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l 9250 Facilities Contamination Surveys 1

! i L 9290 Radioactive Waste Management / Disposal j i  !

9304 Routine Facility Radiation Surveys i 1 ,

9708 Airborne Radioactivity Surveys 9510 Radioactive Material Shipment H400 Reporting of Defects and Noncompliance for Hot Cell Operations There was one procedure that was canceled:

. 9014 Vibrating Rrud Electrometer Calibration for Tritium 1

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U.S. Nuclear Regulatory Commission - Annual Report l February 26, 1997 l

Page 3

d. Results of Surveillance Tests and Insoections l

The surveillance tests and inspection of the facility required by the Technical Specifications were performed.

Documentation of each of the test ' and inspections are j available at the site for review.

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e. Chances. Test and Exoeriments Acoroved by USNRC There were no changes, tests or experiments that required j the approval of the USNRC pursuant to 10 CFR 50.59(a). l

f. Current Staf f and Nuclear Safeauards Committee Membershin l Dr. R. A. Karam, Director, Nuclear Research Center and j l Reactor Engineer j l Dr. Rodney Ice, Manager, Office of Radiation Safety  ;

l Mr. Billy Statham, Reactor Supervisor (part-time)  !

! Mr. Peter Newby, Assistant Reactor Supervisor i

! Mr. Dwayne Blay]ci,4, Senior Reactor Operator Mr. Johannes Stlyck m, Senior Safety Engineering Assistant l Mr. Edgar Jawdeh, Health Physics Mrs. Debbie McGeorge, Administrative Coordinator i Mrs. Arlene R. Smith, Administrative Secretary l

! In addition, the NNRC employed the following graduate I l students on part time basis during portions of the l reporting period:

Peter Newby, Senior Reactor Operator Jeremy Sweezy, Senior Reactor Operator Dwayne Blaylock, Senior Reactor Operator Chris Comfort, Reactor Operator Ralph Demeglio, Reactor Operator

Nick Jenkins, Reactor Operator l

Shane Klima, Reactor Operator Katherin Norton, Reactor Operator Tina Weatherman, Reactor Operator Trainee

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l U.S. Nuclear Regulatory Commission - Annual Report t February 26,-1997 Page 4 The current membership of the Nuclear Safeguards Committee is:

(1) Mr. Emsley Cobb, Chairman Discipline: Reactor Operation and Reactor Safety ,

, (2) Dr. Bernd Kahn '

! Discipline: Radiation Protection and Environmental j Measurements j (3) Dr. Robert Braga l Discipline: Chemistry l (4) Dr. Prateen V. Desai, Secretary Discipline: Thermal Hydraulics, Mechanical Systems

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l (5) Dr. Billy R. Livesay, Member Discipline: Material Science, Physics i l (6) Mr. Jack Vickery, Member Discipline: Security 1

(7) Dr. Thomas G. Tornabene, Member ,

l Discipline: Biology and Biochemistry l

(8) Dr. S. M. Ghiaasiaan, Member i Discipline: Nuclear Engineering 1

(9) Mr. Len Gucwa, Member j l Discipline

Reactor Safety i i

l (10) Mr. Steve Ewald, Member  !

Discipline: Health Physics 4

(11) Dr. Peggy Girard, Member Discipline: Biology and Biochemistry l (12) Mr. James O'Hara, Member l

Discipline: Health Physics l

2. POWER GENERATION There was no reactor operation during this reporting period.

3. SHUTDOWNS l There was no reactor operation during this reporting period.

. l U.S. Nuclear Regulatory Commission - Annual Report February 26, 1997 Page 5

4. UNSCHEDULED MAINTENANCE ON SAFETY RELATED SYSTEMS AND COMPONENTS There were five minor repairs performed on safety-related systems and components. Records of maintenance performed on components are available at NNRC offices for inspection.

5. CHANGES. TESTS AND EXPERIMENTS During 1996, there were no experiments which used the GTRR.

6. RADIOACTIVE EFFLUENT RELEASES

a. Technical Specification 6.7. (6) (a) - Gaseous Ef fluents -

Summation of All Releases Via Stack, i.e., ground level release.

1 (1) FISSION AND ACTIVATION GASES Tritium Released (gaseous)

None Measurable '

Argon-41 Released: None (Reactor Shutdown)  ;

(2) IODINES RELEASED None released (Reactor Shutdown) l (3) PARTICULATES None release (Reactor Shutdown)

Lower Limit of Detection gross beta / gamma = <5.32 E-06 pCi Lower Limit of Detection gross alpha = <3.45 E-06 pCi l l

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L U.S. Nuclear Regulatory Commission - Annual Report  !

i February 26, 1997 Page 6 j

b. Liquid Effluents I

(1) TOTAL GROSS RADIOACTIVITY ( / gamma)  !

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Total Average Maximum  % Tech Release Release Rate

• Conc. heleased Specs l l.

Ci (pCi/cc) (yCi/cc) l 1st QTR 5.01 E-06 1.45 E-11 1.76 E-07 5.9%  ;

2nd QTR 2.14 E-06 6.21 E-12 4.81 E-08 1.6% -

3rd QTR 8.45 E-07 2.45 E-12 1.70 E-08 < 1% r l

l 4th QTR 1.09 E-06 3.17 E-12 8.61 E-08 2.9% '

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! Annual 9.09 E-06 6.58 E-12 1.76 E-07 5.9%

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• Average. release' rate values are based on a Georgia Tech  ;

campus water discharge rate of 3.447*10 11 ml/ quarter.

(2) TOTAL GROSS RADIOACTIVITY (Alpha) i Total Average Maximum  % Tech  ;

Release Release Rateb Conc. Released Specs Ci (pCi/cc) ( Ci/cc) l 1st QTR 3.38 E-07 9.82 E-13 1.89 E-08 < 1%

2nd CTR 2.49 E-07 7.22 E-13 1.40 E-08 < 1%

, 3rd QTR 1.02 E-07 2.96 E-13 4.58 E-09 < 1%

4th QTR 1.59 E-07 4.60 E-13 1.'05 E-08 < 1%

Annual 8.48 E-07 6.15 E-13 1.89 E-08 < 1%

b. Average release rate values are based on a Georgia Tech campus water discharge rate of 3.44 7 *1011 ml/ quarter.

! (3) FISSION AND ACTIVATION PRODUCTS i

! Cobalt-60 is the only activation product released via the liquid pathway from the reactor facility.

The Co-60 does not result from reactor operations, but is attributable to material stored in storage i' pool that is part of the State of Georgia 4

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l U,S. Nuclear Regulatory Commission - Annual Report February 26, 1997 l

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Radioactive Materials License No. 147-1-SNM. No l l fission products are released via the liquid l effluent pathway.

(i) CO 60 RELEASE l

i Total Average Maximum  % Tech

! Release Release Rateh Conc. Specs

! Ci (pCi/cc) Released

! (gCi/cc) ist QTR 3.45 E-06 1.00 E-11 3.40 E-07 1.1%

l 2nd QTR <MDA* <MDA* <MDA* < 1%

3rd QTR 7.23 E-06 2.10 E-11 4.23 E-07 1.4%

4th QTR <MDA* <MDA* <MDA* < 1%

Annual 1.07 E-05 7.75 E-12 4.23 E-07 1.4%

a. Lower than minimum detectable activity l b. Average release rate values are based on a Georgia Tech campus water discharge rate of 3.447*10 2 ml/ quarter.

Co' Lower Limit of Detection = < 1.44 E-7 uCi/cc.

(ii) TRITIUM l

l Total Average Maximum l Release Release Rate

• Conc, Released %10CFR20"

! Ci (yCi/cc) (gCi/cc) 1st QTR 1.57 E-02 4.55 E-08 6.22 E-04 6.2%

? l 2nd QTR 1.72 E-02 4.98 E-08 5.84 E-04 5.8%

3rd QTR 4.40 E-02 1.28 E-07 6.79 E-04 6.8%

4th QTR 3.74 E-03 1.09 E-08 8.56 E-05 < 1% j l \

l Annual 8.06 E-02 5.84 E-08 6.79 E-04 6.8% l l

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• Average release rate values are based on a Georgia Tech campus water discharge rate of 3.447*10 22 ml/ quarter.

• • As percent of Tech Specs, the listed values would be a factor of 10 less.

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e U.S. Nuclear Regulatory Commission - Annual Report February 26, 1997 Page 8 (4) TOTAL VOLUME OF LIOUID WASTE RELEASED 1st QTR . . . 9.46 E+07 ml 2nd QTR . . . 9.43 E+07 ml 3rd QTR . . . 1.29 E+08 ml 4th QTR . . . 5.32 E+07 ml ANNUAL . . . 3.71 E+08 ml (5) GEORGIA TECH VOLUME OF DILUTION WATER USED 1st QTR . . . 3.447 E+11 ml 2nd QTR . . . 3.447 E+11 ml 3rd QTR . . . 3.447 E+11 ml 4th QTR , . . 3.447 E+11 ml ANNUAL . . . 1.379 E+12 ml

7. ENVIRONMENTAL MONITORING: (Tech. Spec. 6.7.a(7))

a. Thirty sites are monitored for environmental radiation.

The parameter monitored for Georgia Tech Research Reactor (GTRR) operations is that of direct radiation from the facility and from emitted gaseous effluents (predominantly Ar-41). The location of the sites relative to the reactor are shown in Figure 1,

" Environmental Monitoring Stations" The sites are predominantly around the reactor perimeter fence or down-wind from the reactor. An updated wind rose is given in Figure 2.

b. Total assays = 30 sites X 4 quarters = 120 assays. The results are reported in the Environmental Radiation Surveillance table (attached). The letter M was used to designate any reading which was less than the minimum detectable limit.

c. Monitors are Landauer "X9" aluminum oxide thermoluminescent dosimeters (TLD). The dosimeters meet ANSI standards. None of the thirty monitored sites show

, levels significantly above background.

i U S. Nuclear Regulatory Commission - Annual Report February 26, 1997 Page 9 The reactor was not operated during 1996. During the period Jan 1 - March. 31 the GTRR fuel was shipped to SRS and ORNL. Exposures represent normal variance in background radiation.

Thermoluminescent dosimeter (TLD #9) is located on the perimeter fence near the Georgia Tech Short-Term Radioactive Waste storage and preparation facility licensed by the State of Georgia. Radioactive waste was not stored in rad waste barn during the year -- but in ,

containment vessel. ,

Thermoluminescent dosimeters (TLD's 17 through 24) are closely positioned to a granite wall. We attribute the majority of exposure to these dosimeters to natural radioactivity in the granite.

Landauer reports that 21 dosimeter locations out of 30, averaged over the year, have radiation levels greater than local background and 9 dosimeters had radiation levels less than local background.

d. The highest, lowest and annual average levels of radiation for the sampling point (TLD #17) with the highest average radiation exposure with respect to the site, are Highest Annual Average Level -

36.6 mrem / year Lowest Annual Average Level -

19.6 mrem / year Average Annual Level -

28,2 mrem / year

e. The gross dose rate readings for all TLDs from all stations varied between 24 and 50 mrem per quarter. The control TLD station varied between 32 and 40 mrem per quarter. This range ]

of variation produced some net dose rate readings (gross )

reading minus control or background reading) that are negative. The negative readings are replaced by the letter M ,

in the Table. Statistically, no conclusions can be made about  !

the environmental dose attributed to the GTRR operation. l l

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d.S. Nuclear Rzgulatory Commission - Annual Report February 26, 1997 Paga 1,0 , NEELY NUCLEAR RESEARCH CENTER ENVIRONMENTAL RADIATION SURVEILLANCE

• 1996 A B C D E F Jan.1 - Apr.1 - July 1 - Oct.1 - 1996 Total Comments Mar. 31 June 30 Sept. 30 Dec. 31 Landauer 1 M M M M -15 In Stack 2 M M M M -25.4 Inner Ring 3 2.5 1.4 2.4 1.5 7.8 Inner Ring 4 4.8 1.9 1.1 M 7.4 Inner Ring .

5 4.1 4.1 M 1 7.8 Inner Ring 1

6 1.2 7.8 M 1 9.3 Inner Ring '

7 5.3 6.I M 2.5 12.7 Inner Ring l 1

8 6.6 8.5 M 3.6 17.8 inner Ring 9 11 6.7 1.7 2.1 21.5 Rad. Waste Barn 10 2.7 2.6 1.2 M 0.2 Inner Ring i 11 6.5 3.7 M 2.6 12.3 Inner Ring 12 2.7 10.3 5.9 1.1 20.1 Inner Ring l 13 12.5 Ab 0.2 7.2 19.8 Inner Ring

! 14 2 M M M -13.5 inner Ring )

15 5.3 1.7 M M -2.9 Inner Ring 16 9.1 5.8 0.6 4.3 19.7 Outer Ring 17 9.2 7.2 4.9 6.2 27.5 Granite Wall 18 3.8 4.9 M 1.4 8.8 Granite Wall 19 3.3 0.2 M 1.1 4.3 Granite Wall 20 4.9 1.1 1.5 2.7 10.2 Granite Wall 21 4.1 M 0.4 0.3 4 Granite Wall 22 8 M ,

2.2 4.2 12.1 Granite Wall 23 7.8 0.8 0 4.1 12.7 Granite Wall 24 7.1 4.4 M 4.4 15 Granite Wall 25 M M M M -11.4 Outer Ring 26 M M M 0 -9.3 Outer Ring 27 M 0.5 M M -4.8 Outer Ring 28 3 Ab 0.2 M 2.6 Outer Ring 29 M M M M -25 Outer Ring 30 M ,M M M -25 Outer Ring Workload MW-IIRS 0 0 0 0 0

• Sum of natural radiation, direct radia: ion from facility and gaseous radioactive efiluents monitored mth Al2O3 TLD's less control badge kept at GT Police Department. Badges processed by Landauer. The Lower Limit of Detection is 0.1 mrem. All negative readings are indicated by M. Absent = Ab ( TLD was lost ).

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b.S. Nuclear Regulatory Commission - Annual Report l February 26, 1997 i Page 11 i

8. OCCUPATIONAL PERSONNEL RADIATION EXPOSURE 1995: f i

Radiation workers of Georgia Institute of Technology are monitored through the use of film badges which are provided by .

a-NVLAP certified vendor and have a lower limit of detection

.of s 10 mrem. A monthly radiation dosimetry report is issued for the personnel of the-Neely Nuclear Research Reactor, a , _

j summary shown in Table 1. '

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l a. Summary of exposure for persons under 18 years of age ';

greater than mrem -

None r

b. Summary of occupational exposures greater than 500 mrem -

l None I 3

c. Person-Rem for the Neely Nuclear Research Center - R-97.

Person-Rem = Sum of occupational workers = 0.764 rem  ;

The highest, lowest and average levels of personnel i exposure due to reactor and hot cell operations:  !

Average annual level - 25 mrem  !

Highest annual level - 220 mrem Lowest annual level - < 10 mrem. ,

d. Category of exposure NNRC Radiation Workers Annual Deep Dose # Radiation workers

< 10 mrem 11 10 mrem - 49 mrem 16 50 mrem - 99 mrem 1 100 mrem - 149 mrem 0 I

150 mrem - 199 mrem 1 2 200 mrem 1 1

Total Workers 30/764 mrem total l

U,S. Nuclear Regulatory Commission - Annual Report February 26, 1997 Page 12 Should there be any questions concerning this report, please let us know.

Sincerely,

$'f R.A. Karam, Ph.D., Director Neely Nuclear Research Center RAK/ars cc: 1. Dr. Jean-Lou Chameau

2. Dr. John White

3. Members- Nuclear Safeguards Committee

4. Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

5. Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l

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II.S. Ndclear Regulatory Commission - Annual aeport February 26, 1997 Pege 14 ATLANTA 1984-89 January 1-December 31: Midnight-11 PM N

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'U.S.-Nuciser R:guletory Commincion - Annual Report Fabruary 26, 1.997 P:gs,15 - APPENDIX A Facility Modification i

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NEELY NUCLEAR RESEARCH CENTEm l' sinor Changa Procrdura 4200

• Revi'; ion 00

- Numoer Approved 04/28/89 By: CHANGES IN GTRR DESIGN Date: / / - Page 3 of 4 APPENDIX A 10 CFR 50.59 SAFETY EVALUATION QUESTIONNAIRE FACILITY MODIFICATION NO: hd-CD/

TITLE: ODIPlc AT/OA! CiJRIT'l blARM SY.STEQ

1. Will the probability of the occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.be increased? [yes/no) A O LEttl&T/l OC Tin-(c THa sEcueirY /]LAR.M' SYSTw/ lthu OPEDTf- I ITHGJT l)Tll ITY ACWLR. d\LL- 1% //vcR CA SG D Nb TNE

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,5TI SulE CAWMK A Dt LL Ct ER. ATE Ld e'l. .

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2. Will the poss ility for an accident or malfunction of a different type than evaluated previously 1,p the safety l analysis report be created? [yes/no] NO I l

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3. Will the margin of safety as defined in the basis fcr any technical specification be reduced? [yes/no) A0

4. Is the propopOed change an unreviewed safety question?

[yes/no] A NOTE: If additional space is needed to justify conclusion (s) please attach extra sheet (s).

PREPARED BY:

)

f flf ffd/A DATE:

2-27-I6

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APPROVALS: j Director NNRC: hj9- A-Ilk.0 A Nuclear Safeguards Committee: - // 9

• / I

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NEELY NUCLEAR RESEARCH CENTER

,' ' Minor Chang 3 Procndura 4200 l

~ Number: Revicion 00 1 By: CHANGES IN GTRR DESIGN Approvnd 04/28/89 i!

Date: / /

Page 4 of 4

(

FACILITY MODIFICATION DOCUhENTATION CHECKLIST i APPENDIX B FACILITY MODIFICATION NO: @d - CC / , ,

TITLE: OTNPic AT/o eJ % Tile 3ECJg.17 Y { wu1 '-T H DRAWINGS:

NUMBER TITLE REVISED BY DATE PROCEDURES:

NUMBER TITLE REVISED BY DATE Ob p 2 bECdbT'! Awpa 5 %TCov1 TEST / A/ 4 I A)n l'14AA)&th L)iEbED )

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Reviewed By: O hl414 Date: d /87,/9 2

~ ' .U.*S. Nuclear Regulatory Commission - Annual Report Fa6ruary 26, 1997 Pdge 18 i  :

. FACILITY MODIFICATION 96-001 l MODIFICATION TO THE SECURITY ', INTRUSION) ALARM SYSTEM

< l.0 PURPOSE The purpose of this facility modification is to connect the passive IR motion detection to the 12 Volt battery system that powers the remainder of the security alarm system and replace the vestibule camera with a 12 VDC model that will be powered from this same battery system.

2.0 SCOPE l

The proposal is to power the IR detector from existing 12 VDC l supply and replace the vestibule camera with a 12 VDC model. '

3.0 RESPONSIBILITY .

The approval f or this modification lies with the NNRC director with the concurrence of the Nuclear Safeguards Committee. ]

4.0 REFERENCES

i 4.1 Facility Modification number 94-001, Battery power for Instrusion Alarm.

5.0 SYSTEM DESCRIPTION 5.1 At present, the IR detector has its own battery backup that will supply power for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> without utility power. Connecting the IR detector to the main battery system will increase the operating time, without utility power, to at least 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

5.2 At present, the vestibule camera requires 115 VAC utility power to operate. This camera will be replaced with a camera that operates f rom 12 VDC. The new camera will be the type that will operate in low light (near total darkness) and will be equipped with an auto iris lens that adjust to existing light condition.