05000267/LER-1980-075, Forwards LER 80-075/03L-0

Forwards LER 80-075/03L-0

ML19341A005
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/14/1981
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19341A006	List: 05000267/LER-1980-075, Forwards LER 80-075/03L-0 05000267/LER-1980-075-03, /03L-0:on 801215-31,plant Operated W/Total Primary Coolant Oxidants Greater than 10 Ppm & Average Core Outlet Temp Greater than 1200 F on Seven Occasions.Caused by High Moisture in Helium Storage Tanks.Tanks Purged
References
P-81014, NUDOCS 8101210406
Download: ML19341A005 (8)

LER-1980-075, Forwards LER 80-075/03L-0

Event date:
Report date:
2671980075R00 - NRC Website

text

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Ed @1 pubuc Sendee Company f Cdondo

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16805 ROAD 19%

b:i J PLATTEVILLE, COLOR ADO 80651 a

January 14, 1981 Fort St. Vrain Uni No. 1 P-81014 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Co= mission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Ref er ence:

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

Dear Mr. Seyfrit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/

80-075, 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. 50-267/80-075.

Very truly yours, 40~ 1%J9 Don Warembourg Manager, Nuclear Production DW/cls Enclosure l

cc: Director, MIPC 6Y e:w n Joe s

b REPORT DATE:

Januarv 14, 1931 REPORTABLE OCCURRENCE 80-075 ISSUE O OCCURRENCE DATE:

December 15, 1980 Page 1 of 7 FCRT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD CCUNTY ROAD 191/2 PLITTEVILLE, COLORADO 80651 REPORT NO. 50-267/30-075/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

1 During the period from December 15, 1980, through December 31, 1980, the 4

plant was operated with total primary coolant oxidants (the sum of carbon monoxide, carbon dioxide, and water) greater than 10 parts per million and average core outlet temperature greater than 1200*F on seven separate oc-casions.

These events constitute operation in a degraded mo.le of LCO 4.2.10 and are reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

~

DESCRIPTION

From December 15, 1980, through December 31, 1980, the plant was operated in a degraded mode of LCO 4.2.10 on seven separate occasions as described below:

1.

(Ref er to Figure 1.)

On December 14, the plant power level was being varied as part of a test (RT-500H). Upon completion of the test, power level was increased on the 15th and primary coolant oxidants also in-cr eased. The reason was not clear, and to verify that no steam gener-ator tube leakage was present, the plant power level was reduced and the steam generators were sequentially dumped and checked. This was conveyed to the Nuclear Regulatory Commission via a Significant Event Notification. No leakage was f ound, and the plant was returned to power.

2.

(See Figure 2.)

This incident is a continuation of' incident #1.

The return to power caused the oxidants to increase arxi resulted in total oxidants greater than 10 ppa.

3.

(See Figure 3.) Following the decrease of oxidants af ter event #2, the plant continued at power levels of about 6C until December 24, 1980, when oxidants again increased. The oxidants gradually decreased again until 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on December 25, when the total oxidants were 9.9 ppm.

)

REPORTABLE OCCURRENCE 80-075 ISSUE O Page 2 of 7 EVENT

DESCRIPTION

(Cont'd) 4.

(See Figure 4.)

On December 24, at midnight, the total oxidants again exceeded 10 ppm f or one reading. Shortly thereaf ter, the plant was taken off line to repair a leak at a steam generator f eedwater trim valve.

5.

(See Figure 4.5 On the return to power following the trim valve repair, the total oxid ants again followed power and exceeded 10 ppa. b'hile the oxidants were still increasing, the turbine and Loop 2 tripped due to a control problem with Loop 2 helium circulator steam bypass vcive, PV-2244, 6.

The repair to PV-2244 was completed and the plant returned to power.

The oxidants again followed the power increase and exceeded 10 ppm.

7.

This continued until December 31, 1980, when the power was reduced to repair a valve.

CAUSE

DESCRIPTION:

The primary coolant oxidants experienced during these seven periods is being attributed to high moisture in the helium storage tanks. This is introduced into the primary coolant as the stored helium is used as makeup helium.

CCRRECTIVE ACTION:

The original corrective action was to take the plant off line and sequentially dump the steam generators to verify there was no steam generator tube laak.

k' hen this was established, sources of makeup helium were investigated and high. moisture found-in the storage tank. The storage tank was purged and dry helium obtained.

No further corrective action is anticipated or required.

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MS Asa B. Reed Technica?. Services Technician REVIEWED BY:

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Frank M. Mathie Operations Manager APPROVED BY:

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Manager, Nuclear Production i

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