05000312/LER-1988-001, :on 880114,radiation Protection Discovered That Alpha Analysis Results for Reactor Bldg Purge 87-47 on 871226 Missing.Cause Unknown.Chemistry Personnel Conducted Thorough Search of Area
| ML20196C990 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/10/1988 |
| From: | Andognini G, Crunk S SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GCA-88-011, GCA-88-11, LER-88-001, LER-88-1, NUDOCS 8802160304 | |
| Download: ML20196C990 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(i) |
| 3121988001R00 - NRC Website | |
text
I NRC Fe<m 364 U s. NUCLEAM LE1ULATO;tY COMMisslON APPLOVED oms NO. 3150C104 LICENSEE EVENT REPORT (LER)
E XPIRES; 8/31/80 l
FACILITY NAME 111 OOCKE T NUMBER (2)
PAGEsh Rancho Seco Nuclear Generatina Station o Is l 010 l 0 l31 l 2 i lorl 0 l3 1
TlYLE 141 Lost Air Filter Sample EVENT DATE 131 LER NUM8E R 161 REPORT DATE (7)
OTHER F ACILITIES INVOLVED (4)
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On December 26, 1987, a particulate filter and charcoal cartridge sample was taken of the Reactor Building (RB) effluent during RB purge 87-47.
The samp;e log in the Chemistry Hot Lab shows that the filter was received in the lab on December 26, 1987.
The sample was analyzed for gamma radiation.
The results of that analysis were less than the lower limit of detection (LLD) of both the Technical Specifications and the equipment.
Following the gamma analysis, the filter was placed in a labeled envelope.
The envelope was placed in an interim storage location (sample rack) awaiting analysis for gross alpha activity.
During an administrative review on January 14, 1988, Radiation Protection discovered that the alpha analysis results for RB purge 87-47 were missing.
Chemistry personnel conducted a thorough search of the Hot Lab; however, the filter was not found.
The failure to perform a gross alpha analysis of the air sample taken during RB purge 87-47 is a violation of Technical Specification Table 4.22-1.
This Technical Specification violation is reportable in accordance with 10 CFR 50.73(a)(2)(1)(b).
A program defining accountabilities and responsibilities for Technical Specification i
required samples will be established by February 15, 1988.
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_ 0l0 0l2 op mw--. e e,.,* <,,,, m ec w manm Descriotion of Event On December 26, 1987, a particulate filter and charcoal cartridge sample was taken of the Reactor Building (RB) effluent during RB purge 87-47.
The sample log in the Chemistry Hot Lab shows that the filter was received in the lab on December 26, 1987.
The sample was analyzed for gamma radiation.
The results of that analysis were less
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than the lower limit of detection (LLD) of both the Technical Specification and the equipment.
Following the gamma analysis, the filter was placed in a labeled envelope.
The envelope was placed in an interim storage location (sample rack) awaiting analysis for gross alpha activity.
Typically, there is a five to seven day wait between gamma analysis and alpha analysis.
This delay allows the alpha activity from the naturally occurring radon gas to decay.
On January 8, 1988, alpha analyses were performed for several samples.
The results were forwarded to Radiation Protection for tracking. On January 14, 1988, Radiation Protection notified Chemistry personnel that they had not received gross alpha analysis results for the sample taken during RB purge 87-47.
Chemistry personnel conducted a thorough search of the Hot Lab; however, the sample was not found.
Technical Soecifica. tion Reauirements Technical Specification 4.22 "Gaseous Effluents" states that the analysis for radioactive materials in gaseous effluents shall be performed in accordance with Table 4.22-1.
Table 4.22-1 requires that the continuous air samples taken during an RB purge be analyzed for gross alpha, Sr-89, and Sr-90 activity.
The failure to perform these analyses for the air sample taken during RB purge 87-47 is a violation of Technical Specification Table 4.22-1.
This Technical Specification violation is reportable in accordance with 10 CFR 50.73(a)(2)(i)(b).
Method of Discovery
During an administrative review on January 14, 1988, Radiation Protection discovered that the alpha analysis results for RB purge 87-47 were missing.
Plant Ooeratina Condition The plant has been in continuous cold shutdown since December 29, 1985.
Cause of Event
It has not been determined how the sample was lost, nor has the sample been found, g*= =
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Corrective Actions
Immediate corrective actions:
Chemistry personnel conducted a thorough search of the area.
Chemistry instituted a sign-in/ check-out log for Technical Specification required samples.
Long term corrective actions:
In 1986, the Independent Investigation / Review Group (IIRG) investigated a loss of analysis results reported in LER 86-?7.
As corrective actions, the applicable recommendations from the IIRG investigation (Root Cause Investigation 86-29) will be incorporated into procedures by February 15, 1988.
A program defining the accountabilities and responsibilities of Chemistry and Radiation Protection personnel for Technical Specification required samples will be established by February 15, 1988.
i Safety Conseauences This event had no impact on the health and safety of the public or District employees.
Alpha analyses are not incorporated into any calculation to determine dose to the public.
The alpha activity is reported in the Semiannual Radioactive Effluent Release Report.
This missing Sr-89 and Sr-90 analyses will also be discussed in the Semiannual Radioactive Effluent Release Report.
Previous Similar Events
LER 86-27 1
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SACRAMENTO MUNICIPAL UTIUTY DISTRICT O 6201 S Street, P.O. Box 15830, Sacramento CA 958521830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA l
GCA 88-011 FEB 101938 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk i
Hashington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 LICENSEE EVENT REPORT 88-01:
LOST AIR FILTER SAMPLE 4
Dear Sirs:
In accordance with the requirements of 10 CFR Part 50.73(a)(2)(i) the Sacramento Municipal Utility District hereby submits Licensee Event Report Number 88-01.
Please contact me if you have any questions.
Members of your staff with questions requiring additional information or clarification may contact Mr. Paul Lavely at (916) 452-3211, extension 4674.
Sincerely, 1
G r
n Chief Executive Officer, Nuclear i
Attachment cc w/atch:
G. Kalman, NRC, 8ethesda (2)
A. D'Angelo, NRC, Rancho Seco
/]k J. B. Hartin (2)
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INPO RANCHO SECO NUCLEAR GENERATING STATloN D 1444o Twin Cities Road, Herald, CA 95638 9799;(2o9) 333 2935