ML20055H083

Advises That Amend 9 to SAR Will Be Revised,Per Encl Calculations & Results in Response to Request for Addl Info

ML20055H083
Person / Time
Site:	North Carolina State University
Issue date:	07/18/1990
From:	Monteith L North Carolina State University, RALEIGH, NC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9007250179
Download: ML20055H083 (4)

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cD gJ North Carolina State University -

Office of the Chancellor Bom 7001 July 18, 1990 Haldgh 27(n%7001 (919) 737-2191 Document Control Desk

-Attention: Alexander Adams, Jr.

U.S. Nuclear Regulatory Ccunission Washington, D.C. 20555 Re: License No. R-120 Docket No. 50-297

Dear Sir:

In accordance with the transmittal dated April 18,1990, frcan Mr. Alexander Adams, Jr., project manager, Non-Power Reactor, Deccmnissioning and Environmental Project Directorate, the attached question / answer cmpilation is officially suhuitted.

As a result of the attached revised calculations and results, certain sections of the PULSTAR Safety Analysis Report (An.ndment 9) shall be revised and subnitted in a separate transmittal within the next nonth.

If there are any questions on this matter, contact Mr. Garry D.

Miller Associate Director, Nuclear Reactor Program eat (919) 737-2321.

Sincerely, w

A%

Lar K. Monteith

1. Chancellor cc:. Dr. Donald Dudziak, Head, Nuclear Engineering Department Garry D. Miller, Associate Director

'Ihcmas C. Bray, Reactor Operations Manager William D. Morgan, Radiation Protection Officer Richard McWat, Chairman, Radiation Protection Council Hayne Palmour, Chairman, Reactor Safeguards Advisory Group E.J. McAlpine Division of Radiation Safety and Safeguards j 8 U.S. Nuclear Regulatory Ccxmtission Region II 101 Marietta Street, N.W., Suite 3100 g/

Atlanta, Georgia 30303 9007250179 900710 - O- l W ADOCK 0500 7 pg gDR Ccmvission Imp. 7/1/91 l North Carolina State University is a land grant university and a coratituent institution of T\e University of North Carolina.

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North Carolina State University Nuclear Reactor Program PULSTAR Reactor License # R 120 Docket # 50-297 Response to Request for AdditionalInformation July 18,1990 The following responses correlate to the itemized questions on the April 18,1990 transmittal from Mr. Alexander Adams, Jr, requesting additional :nformation.

1. In regards to AR-41 doses for the " nearest permanent housing" and the maximum ground location", the calculations have been revised using NUREG 0851, Nomograms for Evaluation of Doses from Finite Noble Gas Clouds (1983). As a result of NUREG 0851 only treating releases at ground elevation,80 meters and 100 meters, whereas our stack is 30 meters high, we used the meandering plume model for a ground release to calculate doses. This assumption results in conservative estimates for the Ar-41 doses. In addition the nearest permanent housing at 240 meters is approximated by the 250 meter value available with the nomograms. The revised values are as follows:

Beta Gamma Location mrad / year mrad / year Nearest Permanent Housing 0.0271 0.0268 Maximum Ground Location 0.0183 0.0169

2. (a.) In regards to fuel pin clad failure doses for the " nearest permanent housing" and the maximum ground location", the calculations have been revised using NUREG 0851, Nomograms for Evaluation of Doses from Finite Noble Gas Clouds (1983) As a result of NUREG 0851 only treating releases at ground elevation,80 meters and 100 meters, whereas our stack is 30 meters high, we again used the meandering plume model for a ground release to calculate doses. NUREG 0851 was specifically used to calculate Kr-88, Xe-133, and Xe 138 doses. The methodology described in Introduction to Nuclear Engineering by John R. Lamar3h was used to revise calculations for I 133, I-134, Br-83 and Br 84. Earlier thyroid calculations were based on inhalation factors given in Table E-7 of Reg Guide 1.109. The revised results of the fuel pin clad failure scenario are as follows:

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LOCATION - Nearest Permanent Housing:

Total Body Total Noble Gas Total Thyroid  ;

Dose (mrem)

Isotone Beta Dose (mrad) Dose (mrem)

Kr-188 ' 2.268 x 10-5 2.23 x 10 5 Xe 133 3.766 x 104- 2.22 x 10 4

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Xe-138 6.693 x 10 ' 8.15 x 104  :!'

' I-131 3.78 x 104 8.66 x 10'8

. 1133 6.76 x 104 2.83 x 10-5 Br 83 4.37 x 104 i Br-84 3.11 x 10*

LOCATION . Maximum Off-site Ground location Total Body Total Noble Gas Total Thyroid l Isotone Dose (mrem) Beta Dose (mrad) Dose (mrem)

Kr-188 - 1.587 x 10-3 1.436 x 10-5 4

Xc-133 2.71 x 10 3.25 x 10-5 Xe-138 4.462 x 104 4.85 x 104

- I-131 6.68 x 10* 1.56 x 10d I133 1.67 x 10 7 6.98 x 10 5 Br-83 7.1 x 104 Br-84 4.83 x 10*

(b.) Off. cite thyroid dose calculations have been revised with results as detailed under item 2.(a) above. Earlier calculations lacked a 1/A term in the results. In addition, thyroid doses to personnel within the Reactor Pay have been reanalyzed with revised results as follows:

I-131 Thyroid Dose = 1469 mrem .

1-133 Thyroid Dose = 480 mrem .

These values assume continuous occupancy in the Reactor Bay for the duration of the fission gas release.

4 (c.) (1) There was a typographical error in the earlier submittal. The correct Fraction for Xe-138 is 8.15 x 104.

(2) ' Using ANSI /ANS 5.41982, the fractional releases were re-calculated and compare to our original SAR subm'ttal as 1 follows:

PUISI'AR SAR ANS 5.4 Isotone Fraction Fraction Kr-88 2.55 x 10'8 1.210 x 10

d Xe-133 1.97 x 10 0.820 x 104 Xe-138 8.15 x 104 3.870 x 104 I131 2.11 x 104~ 1.017 x 10 4

I-133 1.21 x 104 0.332 x 104 Br-83 2.70 x 10-3 0.355 x 10 d  !

Br-84 1.28 x 10-5 0.525 x 10-8 Cs 137 2.94 x 10-8 1.400 x 10~'

Cs-138 1.11 x 10-5 0.526 x 105 Cs-139 4.87 x lod 0.268 x 10-5 4.83 x 10d Sr-89 2.625 x 10" 9 Sr-90 2.61 x 10-8 1.400 x 10

Sr-91 1.49 x 10-5 1.206 x 10-5 Note that the general equation in ANS 5.4 for calculating long lived (i.e., greater than one year half-life) Cs-137 and Sr-90 produced a very low fraction compared to our previous ,

submittal.

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