Text

Pulstar Annual Rept to NRC for Jul 1990 to June 1991
	ML20082H817
Person / Time
Site:	North Carolina State University
Issue date:	06/30/1991
From:	Bilyj S; North Carolina State University, RALEIGH, NC
To:	;
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ML20082H816	List: ML20082H812; ML20082H817; ML20082H821;
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$ i PULSTAR ANNUAL Rl! PORT TO i UNITED STATES NUCLEAR REGULATORY COMMISSION f f

i for the !

I Period 01 Jul 90 30 Jun 91

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Submitted by Stephen J, ll!!yj -

PULSTAR Reactor Operations Manager i Acting Associate Director j i

NCSU NUCLEAR REACTOR PROGRAM i

Reference:

PULSTAR Technical Specifications !

Section 6.7.5 :

Docket No. 50 297 ;

7 Department of Nuclear Engineering !

North Carolina State University ;

Raleigh, North Carolina 27607 21 Aug 91 i 1

l b 9108260288 910821 I PDR ADOCK 05000297 i R PDR >

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DiiPAllTMENT OF NUCl.IIAlt liNGINiilittlNG PULSTAll itI!ACTOlt ANNUAL,11!!POltT For the Period: 01 Jul 90 30 Jun 91 The following report is submitted in accordance with Section 6.7.5 of the PUI. stall Technleal Specifications:

6.7.5.a .D.IklSlinunaIy (1) Reattor Ooeratini! ihnc.tiente:

The NCSU l'UI.STAlt Iteactor has been utilized for the following:

a. Teaching and Short Courses 144.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

b. Graduate Itescarch 470.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

c. hotope Production 31.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

d. Neutron Activation Analysis 1,900.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

c. Nuclear Training (Utilitles) 576.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

f. PUlJSTAlt iteactor Training 48.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months

g. Iteactor Cal /Mer,surements & Surveillance 16.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months

h. lleactor llealth Physics Surveillance 4.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

1. l(eactor Sharing 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months TOTAL. 3,190.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Same reporting period 1989 1990 2,625.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months A cross section of experiments performed in the reactor:

a. Neutron Activation Analysis of filters, animal tissue, bone, proteins, hair, sediments / soil, rain / river water, vegetation, fibers, resins, coal, fly ash, asbestos, graphite, quartz, etc.

b. Itenctor thermal power measurements for teaching laboratories.

c. Isotope Production

d. Thermal neutron depth profiling of boron implanted silicon.

c. Nc6 tron diffusion length measurements in graphite, f, Neutron Itadiography.

(2) .ClRDECS..lal'.CIfuntli1TA _CJMilticlial[CS.Eclated _to lleaetor Sa(cly:

None

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(3) Enulb_DLSutYrillance In%nntLinsectiutu:

The teactor sutveillance program has sevealed no significant nor unexpzeted trends in r: actor systems performance during this report period.

6.7.5.b IuntLEntla10nittul:

1,017.5 hiegawatt hours 42.4 hiegawatt days j'Lils.cd2ncin1101n:

None ReittluLERLClijkal:

1,321.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months

.Citiantallrr TulaUlttcIntoutputaince_lajiiaLCriticality:

16,846.6 hiegawatt hours 701.9 hiegawatt days 6.7.5.c Eutuhttellitncigello' 1uuLUnshtdule d3hutdowns:

.Unsiteduisd2hutdurns - 3 total (1) Loss of commercial power (2) Sample basket stuck in irradiation facility (3) llubbles formed in primary coolant after ammonia was added for pil control lundYr.Ltc31LSCHAhh 17 total (4) Operator error - 13 (5) Spuriom. signals - 4 lixplanation of (1) above:

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1(cactor safety systems are designed to be fail. safe and will cause a SCl(Ahi for any momentary loss of electrical power.

Explanation of (2) above:

At the completion of the irradiation, the sample could not be removed from the facility adjacent to the core. The reactor was shut down to prevent over frradiating the samples.

Explanation of (3) above:

Ammonia was added to the primary coolant for pil control per section 5.3.2 of the PULSTAlt Operations hianual. Apprmimately 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after reaching 95% power, babbles were observed rising from the core area. Several small !

I power changes (all within the capability of the automatic control channel) were noted hp the operator. The reactor was shut down by driving rods in. l(outine !

operations were resumed after the w(ekend without any sign of bubbles In the primary coolant. Standing Order #52 was issued limiting the amount of ammonia that can be adt',d to the coolant to 500 ml. Additionally, the reactor

- must remain shut down for at least 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after any chemleal additions.. i Explanation of (4) above:

Improper operation of the linear level power channel range switch by Nuclear Power Plant trainees (NT) and PULSTAll lleactor trainees (PitT).

Explanation of (5) above:

Spurious manual SCl(Ahls were received while at various power levels. A contact cleaning solution was sprayed on the manual SCl(Ahi switch and the problem has not recurred.

6.7.5.d' Ainjaflinintemutte_Oncrattorin None 6.7.5.e ChaDges in Facillly. ProcedurrilcituuldEsperiments:

1. Design Changes - Nonc

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@t Mi % . tu )L'N el l 2. Procedure Changes (a) 1(evision 6 was made to the PUl51' Alt Opciations hianual to document minor procedural changes and remove typographical and figure errors.

(b) PC 4 90 was a minor resision to llcalth Physics procedure used when preparing filters for proportional counting.

(c) I'C 5 90 was made to update the format of all current surveillance procedures and to correct typographical errors.

6.7.5.f Endimittirtfffhient L{guld Waste (summarized by quarters)

1. l(adioactivity released during the reporting period:

(a) (b) (c) (d) (e)

No. of Total Tot. Vol. Diluent Tritium Period llatches uCi 1.iters 1.iters pCi 4

01 Jul 30 Sep 90 4 18.11 1.37 x 10 3.16 x 10' 13.33 01 Oct 31 Dec 90 4 11.05 1.37 x loi 1.39 x 10' 8.65 01 Jan - 31 hiar 91 8 517.91 2.73 x 10' 1.27 x 10 475.39 01 Apr 30 Jun 91 12 120.92 4.10 x 10-' 2.61 x 10' 82.12 (f) 667.99 pCi total activity released during this reporting period.

(g) 582.49 pCi of tritium were released during this reporting period.

2. Identification of Fission and Activation Products:

The gross al less than 4 x 10pha beta pCl/ml (the gamma maximum activity specific activity of the given hatches in llealth in (a) above were Physics Procedure llP 20-2). An isotopic analysis of these batches indicated only background activity.

3. Disposition of liquid effluent not releasable to Sanitary Sewer System:

All batches of 1(a) above when diluted by campus water (2.54 x 10

liters; the maximum daily campus release) resulted in activity considerably

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3 less than 4 x 10 pCi/ml (10 CI'R 20 limit). Therefore, all batches were released to the sanitary sewer system Gaseous Waste (summarized monthly)

1. Radioactivity discharged during the reporting period (in Curies) for:

(a) _

Gases:

l Total Time

.Ynt ... Pedod ht.1]nuti. Quies 1990 28 Jun 27 Jul 704.50 0.474 27 Jul 27 Aug 735.00 0.949 ,

27 Aug 26 Sep 720,20 0.499 26 Sep 24 Oct 704.00 0.622 _

24 Oct 25 Nov 774.30 0.521 25 Nov - 28 Dec 778.00 0.574 i

1991 28 Dec 28 Jan 720.00 0.736 -

28 Jan 26 Feb - 711.50 0.348 26 Feb 28 Mar 715.00 0.710 28 Mar 26 Apr 706.50 0.410 26 Apr - 27 May 743.00 0.285 27 May - 25 Jun 728.00 0.529 Totals 8,740.00 6.657-i (b) Particulates with a half /!fe of greater than eight days:

Filters from_the particulate monitoring channel were analyzed-upon removal and again the following week. There was no particulate activity ((b) above) indicated on any filter during this -

reporting period.

2. Gases and particulates discharged during this reporting period:

(a) Oases:

The yearly average concentration of argon 41 released from the i

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PULSTAll reactor facility exhaust stack during this period was 2.24 x 108 pCi/ml.

(b) Particulates:

See gaseous waste 1(b) above.

i Spild Waste from Reactor :

3

1. Total volume of solid waste 0.2 m

2. Total activity of soild waste < 5 pCl

3. Dates of shipments and disposal: ,

28 Mar 1991 Chem Nuclear Systems Inc. (CNSI) e i-b I

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6.7.5.g l'ersonitellhidiatint1Lpnane.llepjan' IInculty and Staff Total thpnuar_(Lem)

ARMISTO, Antonio C. 0.020 tilDDY, Oscar D. 0.020 lllLYJ, Stephen J. 0.060 DAYlS. Glenda l'. 0.030 DOSTElt, J. Michael . 0.020 DUDZIAK Donald J.2 0.230 DUFOUlt, Laurence it. 0.000 ELLEMAN. Thomas S. 0.050 GAllDNiilt, Itobin P. 0.010 GILLIGAN, John G. 0.010 llANKINS, Orlando E. 0 010 KINKAID, Kerry L. 0.020 LODGE, Phillip S. 0.030 MANI, Kolam V. 0.010 MAYO, Charles W. 0.010 MAYO, Itobert M. 0.010 MILLElt, Garry D. 0.010 MUNN,11. Ilugh 0.020 MUllTY, K. Linga 0.010 PEltEZ, Pedro 11. 0.020 PLAVNEY, Christopher 0.020 REllAltKElt, Warren A. 0.000 TUltlNSKY, Paul J. 0.010 VERGilESE, Kuruvilla 0.030 WEAVElt, Jack N. 0.030

.Other:

Approximately 25 film badges wera issued monthly to graduate students and temporary staff; Approximately 175 film badges were issued for short courses; Approximately 360 film badges were issued for visitors.

No significant radiation exposures were reported; the majority of these exposures were in the "no measureable exposure" range.

' Compiled and prepared by the Radiation Protection offico. '

2 Exposure is duo primarily to internally administered radio-pharmaceutical treatment during October 1990.

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6.7.5.h Summ:HyJJLRadialintunLCmumninniton survsydithhuhe Facility i Neither the radiation nor the contamination surveys indice.ted any trend or shift of data from past experience or . surveys.

1 6.7.5.1 Descripion of linvironmental Sunenfutsle of the_Entility See Attachment A l

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ML20082H817

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