ML20064E573
| ML20064E573 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Brunswick |
| Issue date: | 10/06/1978 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20064E577 | List: |
| References | |
| FOIA-82-389 NUDOCS 7811200399 | |
| Download: ML20064E573 (3) | |
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OCT 6 gg MEMORAfiDUM FOR:
G. Knighton, Chief, Environmental Evaluation Branch, DDR FROM:
J. T. Collins, Chief, Effiucnt Treatment Systems Branch, DSE
SUBJECT:
TAC 7762, REVIEW OF BRUi Sh'lCK 1 LICEf SEE EVENT REPORT i; UMBER l-78-051 Ori A RADI0 ACTIVE RELEASE In response to your. request dated August 3, 1978, we have completed a re-view of the events and remedial action reported by the Brunswick Steam Electric Plant in LER No. 1-78-051. The event concerned an onsite radio-active release of approximately 20 to 50 gallons of evaporator bottoms with approximately 0.26 to 0.65 millicuries of mixed radionuclides occurred on April 26, 1978.
In our review, we calculated that an individual dose.of <70 mrem /yr re-sulted from the release which was well below the 1500 mrem /yr corresponding to the limit of 10 CFR Part 20 at the unrestricted area boundary-(0.91 miles, NE) and out over Cape Fear River.
For this determination, we assumed that:
Wind Direction = NE at 10 to 15 mph for 15 minute release time.
X/Q (average) = 9.4 x 10-7 sec m-3 (ground release)
D/Q (average) = 1.7 x 10-8 m-2 (ground release)
For the nuclides Mn-54 and Co-60 identified in the LER:
Inhalation Dose Factors i(Mn-54)=2.5xlb4 mrem /yrperuCi/m3 P
Pj (Co-60) - 3.2 x 104 mrem /yr per uCi/m3 i
Food and Ground Dose Factors P-(Mn-54)~=1.1xlb9m2.(mrem /yr)peruCi/sec j
2 9 m -(mrem /yr) per uCi/sec Pj (Co-60) = 4.6 x 10 0.65mCifl03 uCi/ mci).
O " TS minutes (60 sec/ min) = 0.72 uti/sec (assumed) e v
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e G. I:nighton OCT 6 STd f [Pg (X/Q) + Pj (D/Q)]Q Dose
=[(2.5+3.2)(10)(9.4)(10-7)+(1.1+4.5)(10)(1.7)(10-8)]0.72 4
9 s
= 70 mrem /yr (assuming that the total release was airborne)
Since cost of the released fluid rettled near the loading dock, this is a conservative calculation.
The on' site and offsite sampiing program to assess any possible environmental inpact did not produce any reportable concentrations in soil, water and vegetation, and no individual offsite was exposed to concettrations in excess of 00 CFR Part 20.
The LER l-78-051 does not follow the guidelines of NUREG-0161, "Instruc-tions for Preparation of Data Entry Sheets for LER File, July 1977.
The root cause of the event wss the malfunction of the concentrated waste tank heaters due to corrosion that had been out-of-service for about 11 nonths.
The LER reports subsequent events that resulted in the release, action taken to correct the contributing problems and personnel error, but does not address remedial action on the root cause.
He recomend that the licensee provide this additional information by amendment to the LER, Enclosed is a list of our recomendations to reduce personnel error-- - -
often leading to unplanned radioactive releases.
ORIGINAL SIGED BY JOHN T.. COLLINS I
John T. Collins, Chief f
Effluent Tyeatment Systems Branch Division of Site Safety and Environmental Analysis cc:
D. Mullei-
- 8. Grimes D. Eisenhut DISTRIBUTION:
R. Vollmer Central File L. liigginbotham ETSB Reading File L. Barrett ETSB Subject File 20.3 JTCollins L. Cunningham J. Donohew F. Congel
.W. Burke' J. Boegli c,
l ETSB/d&1 EISB/DJE R.DSE Q B/D JSoec b WEf$rY onoel b lins'
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