05000267/LER-1982-004, Forwards LER 82-004/01T-0.Detailed Event Analysis Encl

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Forwards LER 82-004/01T-0.Detailed Event Analysis Encl
ML20041A983
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 02/16/1982
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20041A984 List:
References
P-82043, NUDOCS 8202230123
Download: ML20041A983 (8)
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LER-1982-004, Forwards LER 82-004/01T-0.Detailed Event Analysis Encl
Event date:
Report date:
2671982004R00 - NRC Website
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text

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public servlee company otP cdorade 0

Road 19 1/2, Platteville, Colorado 80651-9298 O) 8 gCEWN February 16, 1982

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Fort St. Vrain eT-

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FEB 181982 Mr. John T. Collins, Regional Administrator Region IV

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611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Reference:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Collins:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/82-004, Final, submitted per the requirements of Technical Specification AC 7.5.2(a)2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/82-004.

l Very truly yours, l

Mon LdweJooq

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Don Warembourg Manager, Nuclear Production DW/cls c

Enclosure cc: Director, MIPC l

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8202230123 820216 PDR ADOCK 05000267 S

PDR'

REPORT DATE:

February 16, 1982 REPORTABLE OCCURRENCE 82-004 ISSUE O OCCURRENCE DATE:

February 2, 1982 Page 1 of 7 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/82-004/01-T-0 Final IDENTIFICATION OF OCCURRENCE:

In the early morning of February 2,1982, while the plant was shutdown for a modification outage, an improper valve position allowed an unauthorized radioactive liquid waste release to occur.

Since the source of the liquid waste had not been sampled, a violation of LCO 4.8.2, Part (c) occurred.

Upon subsequent investigation, the level of gross beta gamma in the liquid waste source had also exceeded the limit of LCO 4.8.2(c). This event is reportable per Fort St. Vrain Technical Specification AC 7.5.2(a)2.

CONDITIONS PRIOR TO OCCURRENCE:

Cold Shutdown THE MAJOR PLANT PARAMETERS AT THE TIME OF THE EVENT WERE AS FOLLOWS:

The reactor plant wTs in a shutdown, cooled down condition at the time of this event.

Plant parameters had no effect on this occurrence.

DESCRIPTION OF OCCURRENCE:

l On Tuesday, February 2,1982, at approximately 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, with the l

plant' shutdown for design modifications to the circulator auxiliary

systems, it was discovered that an unauthorized radioactive liquid l

waste release-had occurred. The release occurred while transferring l

radioactive liquid waste from the "IA" liquid waste receiver to the l

monitor tank. The release was due to an improper valve lineup.

.The total volume of the release is estimated to be 250 gallons. Analysis t

of the 1A receiver contents indicates the gross beta gamma level to have been 1.24 E-5 microcuries per milliliter, which is in excess of the 2.0 E-6 microcuries per milliliter limit of LCO 4.8.2, Part (c).

This level is the undiluted liquid waste prior to dilution in the cooling tower blowdown system.

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l

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1 REPORTABLE OCCURRENCE 32-004 ISSUE O t

Page 2 of 7 APPARENT CAUSE OF OCCURRENCE:

While performing the valve lineup for transferring the contents of the 1A liquid waste receiver to the monitor tank, the valve which allows the discharge.of the transfer pump to go to the cooling tower blowdown (V-6297) was inadvertently left in the open position.

Upon transferring the contents, approximately 250 gallons were discharged to the coolirig tower blowdown line.

ANALYSIS OF OCCURRENCE:

During the late hours of February 1,1982, an authorized radioactive liquid waste release (#518) and subsequent system flush was performed.

Following this release, the system was re-aligned, and a transfer of contents from 1A receiver to the monitor tank began.

Figure 1 shows a simplified schematic of this lineup. However, following the release and flush mentioned above, manual valve V-6297 was left in the open position. This configuration allowed a portion of the contents of IA liquid waste receiver to be discharged to the cooling tower blowdown system (see Figure 2).

At approximately 90 minutes into the transfer (0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> on February 2,1982), V-6297 was found open, and immediately closed.

The Nuclear Regulatory Commission was notified of the "significant event" per 10CFR50.72, item #8.

Water samples at appropriate locations were taken for radiochemistry analysis. None of the analysis, except for IA liquid waste receiver, resulted in activities that were above MPC limits.

An "after release" sample for release #518 was taken at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> which was during the unauthorized release. The results of these samples are listed in Table 1.

The sample of the 1A receiver tank indicated a beta gamma level in excess of permissible per LCO 4.8.2, Part (c). Since it was an unauthorized radioactive liquid waste retease, the event is reportable per Fort St.

Vrain Technical Specification AC 7.5.2(a)2.

CORRECTIVE ACTION:

The event was thoroughly reviewed with the operating staff involved.

The valve lineup error, and the significance of his operating responsibilities, was discussed at length with the operator responsible.

No further corrective action is anticipated or required.

FAILURE DATA /SIMILAR REPORTED OCCURRENCES:

None

REPORTABLE OCCURRENCE 82-004 ISSUE O Page 3 of 7 PROGRAMMATIC IMPACT:

None CODE IMPACT:

None l

f

REPORTABLE OCCURRENCE 82-004 ISSUE O Page 4 of 7 TABLE 1 All Samples Taken on February 2, 1982 Sample Time: 0010 Hours Location: Cooling Tower Blowdown Reason: Completed Authorized Release #518 Results: Beta-Gamma - 3.29 E-7 pCi/ml Alpha

- 7.36 E-8 pCi/ml Tritium
- 1.42 E-6 pCi/ml hSampleTime:

0115 Hours Location: Cooling Tower Blowdown Reason: Unauthorized Release Results: Beta-Gamma - 6.42 E-8 pC1/ml Alpha

- 2.94 E-8 pCi/mi Tritium
- 2.63 E-6 pC1/ml hSampleTime:

0215 Hours Location: Cooling Tower Blowdown Reason: Unauthorized Release Results: Beta-Gamma - 1.21 E-7 pCi/mi Alpha

- 2.45 E-8 pCi/ml Tritium
- 8.54 E-7 pCi/mi hSampieTime:

0225 Hours Location: Downstream Platte River Reason: Unauthorized Release Results: Beta-Gamma -

7.90 E-8 pCi/ml 2.53 E-8 pCi/mi Alpha Tritium

- < 5.68 E-7 uC1/ml Sample Time: 0950 Hours Location:

1A Liquid Waste Receiver (T-6202)

Reason: Source of Unauthorized Release Results: Beta-Gamma - 1.24 E-5 uCi/ml Alpha

- 9.85 E-9 pCi/mi Tritium
- 7.80 E-2 pCi/ml I

_.-_,........---s.~+..~

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FIGURE 1 es V-6242 m

V-6243 V-6244 5

V-6233 E

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1.egend IClosed Valve

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i V-6230 V-6275 V-6297 A

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I V-62202 255 Valve V-6219

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P-6202 O@

o Sample Transfer Pump 1A 5

(See Table 1)

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To cooling tower s

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blowdown Be2 i

O F1GURE 2 REPORTABLE OCCURRENCE 82-004 ISSUE O Page 6 of 7 O Sample (See Table 1) h venion

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\\j Cooling Tower Blowdown (Exits with minimum A

1100 gpm dilution)

REPORTABLE OCCURRENCE 82-004 ISSUE O Page 7 of 7 houw k. NN[LW Prepared By:

Owen J. OT)yton ej Technical'5ervices Technician Reviewed By:

b a. b / o Charles Fuller Technical. Services Engineering Supervisor Reviewed By:

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Edwin D. Hill

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Station Manager Approved By:

Om. r.s-. L.- A t>x//<me a Don Warerabourg '

Manager, Nuclear Production J

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