ML20084N806
| ML20084N806 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 12/09/1971 |
| From: | Cindy Montgomery SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20084N783 | List: |
| References | |
| NUDOCS 8306090080 | |
| Download: ML20084N806 (2) | |
Text
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SAxTON NUCl.EAlt EXPER,IMENTAL CORPORATION m
UTILITO everca G
ERAL P U D LIC iNEC d
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u TaorouTAN roisoN courANv P. O. tox 542, Rcoding, Pa.
19603 Telephone: Area 215 929 3631
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- O2 G Saxton, Pa.
December 9, 1971
- r. 1cter A. Morris, Director
- .:.-:41on of Reactor Licensing t.5. Ato:Ic Energy Commission Vr.hington, D.C.
20545 Dc.ir Dr. Morris:
In accordance with Paragraph 3.E. (1)(b) of License DPR-4, Saxton herewith reports the accidental release of a'small quantity of radioactive gases.
Th i t, occurrence was reported by telephone to Mr. R. L. Spassard, Region I, Division of Compliance, on December 1,'1971.
The accidental release of radioactive gases occu ed on November 29, 1971, while operating personnel were making a primary coolant boron dilution. While the dilution was in progress, radioactive gases leaked out of the purificatign system pipian through the stem packing of a Is-inch valve and escaped into the charging purp roo= of the C&A Building. The gases were then picked up by the building ventilatin; system and exhausted to the environs via the plant stack.
Using the stack' monitor recorder (RIC-3) as a basis for estimating the activity released, we estimate 80.2 curies of gaseous activity were released to the environs over a 7-hour period. The maximum concentration of gaseous activity
,3 5
in the stack, excluding I-131, when averaged over a 15-minute period, is estimated 3.52 x 10-3 uCi/cc, which exceeds the 1 x 10-3 uCi/cc set forth in the Technical at Specifications.
The activity was predominately Xe-133 and Xe-135. The Iodine activity associated with ' this release was negligible.
Based on the activity cbtained from the stack gas Iodine sampler, we calculate 4.3 uCi of I-131 were released from the stack during the 7-day sample period.11/24/71 - 12/1/71. The particulate activity associated with this release was also negligible.
We calculate 0.75 uCi of particulate activity were released from the stack during the
,7-day sat:ple period, 11/24/71 - 12/1/71.
There were no over exposures to on-site personnel.
F9r a release of 80.2 curies of gaseous activity from the stack and using a value of 2.3 x 10-4 sec/ 3 for the short term atmospheric dilution factor and 1 Mev for Y we calculate the of f-site whole body dose to be 4.23 x 10-3 rem.
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The above calculations confirm that this accidental release of radioactivity does not constitute a possible unsafe condition relative to the operation of the f.icility or to tima lieulth and safety of the public; nor does it involve an unreviewed l
safety question. We have reviewed the events and' equipment, associated with this release and have taken the necessary action to prevent a recurrence.
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Very trdly yours, s
--x C. R. Mont.gomery
. President ec:
G. F. Trowbridge, Esquire R. L. Spessard, Region I, Division o.f Compliance
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