ML20050B248

Forwards LER 82-006/03L-0.Detailed Event Analysis Encl

ML20050B248
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/19/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20050B249	List: ML20050B248 ML20050B254
References
P-82084, NUDOCS 8204050142
Download: ML20050B248 (4)

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Public Service Company Cf Ochada

,' 16805 Road 19 1/2, Platteville, Colorado 80651-9298 l

March 19, 1982 Fort St. Vrain Unit No. 1 P-82084 Mr. John T. Collins, Regional Administrator Region IV Nuclear Regulatory Commission 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. 50-267/82-06, 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. 50-267/82-0#.

Very truly yours, Oon L.0a<embw y .& */&vi$

Don Warembourg l

Manager, Nuclear Production DW/lsb Enclosure e A cc: Director, MIPC #  %

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REPORT DATE: March 19. 1982 REPORTABLE OCCURRENCE 82-006 i ISSUE O OCCURRENCE DATE: February 18, 1982 Page 1 of 3 FCRT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE CCMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/82-006/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During normal startup and low power operations, the primary coolant moisture, measured by dewpoint, exceeded tne limits of Figure 4.2.11-1, on four separate occasions. These events are reportable as a degraded mode of LCO 4.2.11 per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT DESCRIPTION:

Event 1: During the system modification outage, the primary coolant became contaminated with moisture. During a subsequent reactor startup, with the purification system in operation, the moisture level measured by dewpoint increased past the ,

limit of LCO 4.2.11. This event occurred from 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, February 18, 1982, to 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> en February 19, 1982. ,

Event 2: With the reactor critical at approximately 1% power, moisture again exceeded LCO 4.2.11 limits. This event occurred from 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> (last acceptable reading),

February 19, 1982 to 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> (next acceptable reading),

February 19, 1982.

Event 3: Again while maintaining the reactor critical at approximately 1% power, moisture exceeded the limits of LCO 4.2.11. This event occurred from 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> (last i acceptable reading), February 21, 1982, to 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />'(next

acceptable reading), February 21, 1982.

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Event 4: With the reactor sub-critical with scme control rod groups withdrawn, the LCO 4.2.11 limits were exceeded. The event began at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on February 21, 1982. The moisture level would not have decreased below the limits of LCO 4.2.11 within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> grace period, and the reactor was manually scrammed at 2148 hours, j

Februa ry 22, 1982, in compliance with the Technical Specifications.

, CAUSE 4

DESCRIPTION:

i The reactor plant had been in a cold shutdown condition over a three month period for a major system modification outage. During this outage, the PCRV had been at subatmospheric pressure several times for maintenance and fuel handling activities. There were also many primary coolant systems physically opened during the modification.

4 For maintenance reasons, the purification train flow was terminated on several occasions. All of these conditions allowed for a gradual buildup of moisture which exceeded the limits of Figure 4.2.11-1 upon reactor operation.

CORRECTIVE ACTION:

The purification train was operated to remove the impurities from the primary coolant for events one through four. However, moisture would

. not have been lowered below the limits of LCO 4.2.11 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for event number four; therefore, the reactor was manually scrammed in accordance with the Technical Specifications.

The reactor has remained shutdown while efforts continue to reduce the impurity levels to acceptable operating levels. No additional corrective action is anticipated or required.

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REPORTABLE CCCURRENCE S2-006  :

ISSUE O Page 3 of 3 Prepared By: W (.

Owen J. G yton Technical services sechnician Reviewed By: L p[

Charles Fuller Technical Services Engineering Supervisor Reviewed By: 2S '1. 0 2m inhl u Ecwin D. H141 Station Manager Approved By:

Don Waremoourg Manager, Nuclear Production s

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