ML18219D943
| ML18219D943 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/25/1976 |
| From: | Jurgensen R American Electric Power, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co) |
| To: | James Keppler NRC/IE, NRC/RGN-III |
| References | |
| Download: ML18219D943 (7) | |
Text
NI1C FOAM 106
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U,S. NUCLEAR REOULaTORV C ISSION NRC DISTRIBUTION ron PART 50 DOCKET MATERIAL OOCKET NUMIIEA cp-3t Q FILL: NUMBER TO:
MR J G KEPPLER FROM'NDIANA a MICHIGAN POWER CO MIDGMAN, MICH R W JURGENSON DATE or. OocUMENT OATE RECEIVED
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August 25; 1976 AUG3pp~~
g Mr. J.G.
Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 700 Dnorghvgh]t oosd Glen Ellyn, IL 60137
Dear Mr. Keppler:
Operating License DPR-58 Docket No. 50-315 AEO 50-315/76-05
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On August 20,
- 1976, we reported to you an event which occurred at the Donald C.
Cook Nuclear Plant Unit ffl on August 19, 1976.
In that report we stated that a liquid release was made without a gamma spectrum analysis made on the sample prior to the release in violation of.
Technical Specification Appendix B, Section 2.4.2.b.
After normal recirculation, the south waste evaporator condensate tank was sampled prior to release.
Analysis yie',9ed the following results:
Tr itium Unidentified gross beta Boron 2.78 x 10 2 yCi/ml 3.31 x 10 4 yCi/ml 164 ppm Because neither Ge(Li) gamma spectrum analysis unit was operating, the Chemical Technician suggested that the gamma analysis of a release granted earlier that day be used until the complete analysis of this release could be performed.
The Chemical Foreman was called and gave his permission and at 2330 the Radiation Protection Supervisor was called and he also gave his permission.
The analysis of the previous release had yielded essentially the same gross beta while tritium and boron were greater in the previous release than in the subjec't release.
The source of water was the same for both releases, but it was believed that the waste evaporator was performing better for.the second release than for the first due to the much lower boron results in the second tank.
For these reasons, it was believed by all concerned that the gamma spectrum would be similar and would not yield greater concentrations than the previous analysis and would, therefore, be conservative.
At 0130 on the 19th, the SOE gave permission for the release to be made which was done starting at 0140 and terminating at 0229.
The alarm point on R-18, the effluent monitor, was set at less than 194,301 CPM (lower than
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Mr. J.G.
Keppler
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August 25, 1976 Page 2
the previous release) and did not alarm.
The. release flow rate was 23 gpm with a dilution flow of 690,000 gpm for a dilution factor of 3 x 104.
- Thus, even from the standpoint of using the unidentified beta
- results, the final release concentration was still a factor of ten lower than the unidentified MPCW.
The gamma analysis was completed at 1413 on the 19th.
All concentrations
. were lower than the previous analysis used for the estimates.
The attached table shows the data for both releases.
The requirement for complete analysis of each batch of liquid to be released has been explained to all Chemistry and Radiation Protection personnel as well as operating personnel in or der to prevent a recurrence of this type of violation.
The radioactive liquid release form has also been revised to assure compliance with the Technical Specifications.
Sincerely, R.W. J gen Plant anager
/bab CC:
R.S.
Hunter J.E.
Dolan G.E. Lien R. Kilburn R.J. Voll;.n BPI R.C. Callen MPSC K.R. Baker RO:III P.W. Steketee, Esq.
R. Walsh, Esq.
G. Charnoff, Esq.
G. Olson J.M Hennigan PNSRC R.S.
Keith D.C. Palmer Dir., IE (20 copies)
Dir., MIPC (2 copies) directorate-of-Licensing (1 copy)Q
Mr. J.G.
Keppler t
August 25, 1976 Attachment No. l Release No.
Sample No.
Sample Date Sample Time H-3 Beta Boron I-131 C&-136 Cs-134 Cs-137 Nb-95 Co-58 Mn-54 Co-60 Sr-85 334 26787H August 18, 1976 0345 3.2 x 10
~ pCi/ml 3.12 x 10"" pCi/ml 456 ppm 2.9 x 10 s pCi/ml 2.4 x 10 s pCi/ml 1.7 x 10 " pCi/ml 2.6 x 10 " pCi/ml 2.08 x 10 s pCi/ml 1.5 x 10 4 pCi/ml 6.7 x 10"s pCi/ml 6.5 x 10 s pCi/ml 3.7 x 10 s pCi/ml 335 26820H August 18, 1976 1725 2.78 x 10
~ pCi/ml 3.31 x 10 4 pCi/ml 164 ppm 1.39 x 10 pCi/ml 2.39 x 10 pCi/ml 1.04 x 10 " pCi/ml
- 1. 58 x 10 " p Ci/ml 1.30 x 10
~ pCi/ml 1.11 x 10 4 pCi/ml 5.30 x 10 s pCi/ml 4.96 x 10 's pCi/ml Non Detected
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