05000267/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl

Forwards LER 83-003/03L-0.Detailed Event Analysis Encl

ML20064K762
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/03/1983
From:	Clayton O, Fuller C, Eva Hill, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20064K767	List: 05000267/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl 05000267/LER-1983-003-03, /03L-0:on 14 Separate Occasions,Total Primary Coolant Oxidants Exceeded Acceptable Limits.Oxidant Offgassing Caused by Increasing Temps During Normal Reactor Startup & Rise to Power.Oxidant Concentration Reduced
References
P-83046, NUDOCS 8302150001
Download: ML20064K762 (7)

LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671983003R00 - NRC Website

text

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Public Service Company *f OcDondo 16805 Road 19 1/2, Platteville, Colorado 80651-9298 i

February 3, 1983 Fort St. Vrain Unit No. 1 m '~7 0 f r (c'[i

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FEB ~ 71983 g Mr. John T. Collins, Regional Administrator bL Region IV

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d Nuclear Regulatory Commission 1

611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Reference:

Facility Operating 3.icense No. DPR-34 Docket No. 50-267

Dear Mr. Collins:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/83-003, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/83-003.

V trul yours,

/

Don Warembourg Manager, Nuclear Production i

DW/cis Enclosure cc:

Director, MIPC k@

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8302150001 830203 DR ADOCK 05000

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REPORTABLE OCCURRENG DISTRIBUTION Number of Copies De p a rtmen t o f Ene rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P I4tter)

San Frmeisco operations Office Atta California Patent Group 1333 Broadway Oakland, California 94612 De p a r t me n t o f En e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P IAtter)

Mr. Glen A. Newby, Chief HTR Branch Division of Nuclear Power Development Mail Station B-107 Washin gton, D.C.

20545 De p a r t men t o f En e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P 14tter)

Attn: Project Manager P. O. Box 81608 San Diego, California 92138

!!r. John T. Collins, Regional Administrator ------------------

1 (Original of P I4tter)

Region IV Nuclear Regulatory Conumission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011 M r. Ge o rge Kuzmy cz - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Intter)

Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20034 Di re c t o r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Intter)

Office of Management Information and Program Control Nuclear Regulatory Commission Washington, D.C.

20555 i

INFO Records Center 1 (P Letter)

Suite 1500 1100 circle 75 Parkway Atlanta, G4 30339 Mr. Richard Phelps, ' FSV, CA, Site Rep resentative - - - - - - - - - - - - - - - - 1 (P Letter)

General Atomic Conq)any 16864 Weld County Road 191/2 Platteville, Colorado 80651 1 (P 14tter)

NRC Resident Site Inspector l

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O REPORT DATE:

February 3, 1983 REPORTABLE OCCURRENCE 83-003 ISSUE O OCCURRENCE DATE:

January 5, 1983 Page 1 of 5 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/83-003/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During the period January 5, 1983, through January 18, 1983, the reactor plant was operated in a degraded mode of LCO 4.2.10 on 14 separate occasions.

These events are reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

At approximately 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on January 5, 1983, the concentration of total primary coolant oxidants (sum of water, carbon monoxide, and carbon dioxide) exceeded 10 parts per million (ppm) by volume. This impurity concentration increase occurred during a rise in power following a normal startup with the average core outlet temperature greater than 1200 degrees fahrenheit.

The concentration of total primary coolant oxidants returned to less than the 10 ppm limit of LCO 4.2.10 on January 7,1983, at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br /> as a result of primary coolant cleanup through the helium purification system, but continued to fluctuate about 10 ppm until 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on January 18, 1983.

A total of 14 events occurred in which the 10 ppm limit was exceeded.

l Each event is described in Table 1 and illustrated in Figure 1.

l

CAUSE

DESCRIPTION:

The reactor plant had been maintained in either a low power or shutdown condition for several months. During this period, several maintenance activities took place, including the isolation of a steam generator tube leak (Reportable Occurrence 82-049). As a result of this tube leak, feedwater entered the reactor vessel and became entrained in the primary coolant.

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j Following the steam generator tube maintenance, the primary coolant I

purification system was utilized to remove sufficient moisture to l

allow plant startup. However, due to the hygroscopic properties of the reactor core graphite and absorption in the vessel liner insulation, some of the moisture was retained.

REPORTABLE OCCURRENCE 83-003 ISSUE O Page 2 of 5 As the core temperature was increased, the retained moisture was released from the reactor vessel internal components and chemically reacted with the core graphite.

This process caused the total oxidant concentration to fluctuate about 10 ppm until all moisture had been removed.

CORRECTIVE ACTION:

In all 14 events, the total oxidant concentration was reduced below the LCO 4.2.10 limit by utilization of the helium purification system.

No further corrective actions are anticipated or required.

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REPORTABLE OCCURRENCE 83-003 ISSUE O Page 3 of 5 TABLE 1 Maximum Start End PPM Event No.

Date/ Time Date/ Time Attained 1

830105/0030 830107/0345 51.0 2

830107/0415 830108/0050 14.2 3

830108/0230 830108/1500 15.4 4

830108/1700 830108/2245 12.6 5

830109/0130 830109/0400 11.8 l

6 830109/0400 830109/1100 12.2 7

830109/1530 830109/1715 11.2 8

830109/1900 830109/2315 11.6 9

830110/0100 830111/1200 15.3 10 830111/1200 830112/0800 14.4 11 830112/0800 830112/1430 10.5 12 830112/1930 830113/0330 10.4 13 830114/2330 830115/0030 10.5 14 830118/0700 830118/0900 13.2 l

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REPORTABLE OCCURRENCE 83-003 ISSUE O Page 5 of 5 Prepared By:

Auw k. b who Owen J. CLayton O

Senior Technical Services Technician Reviewed By:

/b Charles Full'er Technical Services neering Supervisor r

Reviewed By:

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Station Man'll f' Edwin D. Hi ager Approved By:

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Don Warembourg

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Manager, Nuclear Pfoduction