ML20041C513

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Submits Status of NUREG-0737,Item II.F.1.2, Iodine/ Particulate Sampling. Grab Sampling Equipment Installed. Final Hookup of Sampling Line in Stack Scheduled During Upcoming Planned Outage
ML20041C513
Person / Time
Site: Oyster Creek
Issue date: 02/23/1982
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8203020133
Download: ML20041C513 (6)
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Text

{{#Wiki_filter:N O 4 9 RECEIVED % T pu Nuci.ar /:* %0 b -1 100 Interpace Parkway QQ gf gk P rs ppa Jew Jersey 07054 f TELEX 136-482 Writer's Direct Dial Number g hf g { February 23, 1982 g 3j AcJ:.s.M -c- &L~'f,,'/ &n/cl j%. etM pt-c< / / Mr. Darrell G. Eisenhut, Directcr / Division of Licensing pcgU / _am /.a g-y 2 Office of Nuclear Reactor Regulation U.S. Nucicar Regulatory Commission gj /[d, w... W6shington, D. C. 20555

Dear Sir:

g g, f

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 NUREG 0737

Reference:

(a) 1. R. Finfrock (JCP&L) letter of Januar y 6, 1981 to Mr. Darrell G. Eisenhut (NRC) The purpose of this letter is to transmit to you our present status of NUREG item II.F.1.2 " lodine / Particulate Sampling." The status of this item is as follows. In our correspondence of January 6, 1981, we stated that we were instalIing an on-1ine system for monitoring lodine and particulate in the exhaust up to levels of 10 uCi/cc. Additionally, we stated that provisions would be provided f or oh,taining a grab sample that can be analyzed on site for concentrations up to 10 'uCi/cc as required by NUREG 0737 criteria. This equipment has been installed. Finai hookup of the sampling line in the stack is scheduled during an upcoming planned outage. Attached, as discussed by telephone between your staf f and my staf f, is further documentation supporting our position. This documentation was supplied by Science App lications, Inc. who we contracted to perform the calculations for t h i s NUREG i terr, if you should have any further questions on this issue, please contact Mr. James Knubel, Mardger, BWR Licensing at (201) 299-2264 Very truly yours, Pl. B. F ied I erad bh 8203020133 820223 &i l PDR ADOCK 05000219 Vice President k P PDR 3g1 Ir GPU Nuclear is a part of tre General Puchc UMiies System

cc: Mr. Ibnald C. Haynes U.S. Nuclear Regulatory Comnission Region I 631 Park Avenue King of Prussia, PA 19406 a

a/ Science Apphcetions. Inc. August 24, 1981 e Mr. Satish Gera GPU Nuclear Oyster Creek Project 99 Cherry liill Road 1arsippany, New Jersey 07054

Dear Satish:

I have reviewed the highest concentrations of airborne iodine expected at thii monitor sampling station at the Oyster Creek stack under a loss-of-coolant accident. The assumptions made in the review were the conservative ones listed in Reg. Guide 1.3, namely: "1. 254 of the-core iodine inventory becomes airborne in the drywell. 2. The drywell leaks to the atmosphere of the reactor building at the -- ratie of 0.1% per day. 3. The reactor building is exhausted through the stand-by gas treat-ment system at 2500 CFM to the stack. 4. The stand-by gas treatment system charcoal filter adsorbs 90% of the airborno iodine. 5. All other ventilation fans feeding the stack are off. 6. Radioactivo decay of the iodine activitics is occurring in all stages. W e results of these calculations are shown in Figure 1 as a function of ti..e after shutdown. For the first 30 hours, the dominant iodine activity is I331 After that time, 131I dominates. As can be seen, the maximum acti-i t vity concentration in the stack under these conditions is only slightly high-er than 10-1 t.Ci/cc. The results of another calculation assuming a very high leak rate of 11 are shown in Figure 2. Here, the maximum concentration would te'lcss than 2 LCi/cc. Nuclear Environmental Services, a division of Science Applications, Inc. 3 Choke Cherry Rd., Rockville, Md. 20850, (301) 977 4480 '- 3 4' 6" < -s 4, v. s.., ~,.. 4,,, 4,3,,, 3, n o,,,,,,,,,,,,,,,,,, e n ; c,,, n o o,,,,,,, t,,,,,,, t o,,,,,,,, p,,,,i,o. s.,te e s,e.< e. s wanvv ei...a J Tocion. ~ .w* p 4 -W-kN-s W ye* W 9-45*

Mr. Satish Gera August' 24, 1981 These assumptions are very conservative. They do not consider realistic desposition of iodine on surfaces, particularly in the drywell where the acti-l vity has a long contact time. At TMI we have scen -3 cvidence of substantial iodine deposition that would reduce predicted levels of airborne iodine by at least another factor of 100. - 'Sisce ely, .\\ 4)/? James E. Cline JECapfc L*. closure _

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~~~ - - - 1. I Studies at TMI Unit 2. J. E. Cline, P. G. Voillequd, C. A. Pelletier and C. D. Thomas, Jr., EPRI-1389, April 1980. 2. Measurements of I and Radioactive Particulate Concentrations in the TMI-2 Contain::.cnt Atmoc1>here During and Af ter the Venting. J. E. Cline, P. A. Roy, Jr., J. W. Hollcroft, J. Ilobaugh, Jr., T. L. McVey, C. D. Thorus, Jr., C. A. Polletier and P. G. Voillequd, SAI-139-80-573-LJ, Septerrber 1980. 3. Iodine-131 P,chavior During the TMI Accident, NSAC Report, C. A. Pelletier g and C. D. Thomas, Jr., July 1981. I 4 t h I ki 1 i ? I 2 l a 0 F I k ? -w .-,y 7 m..m.,,em,- ,-p e,en. ,, o e --,m.e... 4 n., n

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