ML19341A231

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Forwards LER 80-076/03L-0
ML19341A231
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 01/16/1981
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19341A232 List:
References
P-81015, NUDOCS 8101220413
Download: ML19341A231 (4)


Text

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~ T ~ '] public Service Company *f CoHondo i I

16805 ROAD 19%

. . _'Ad PLATTEVILLE, COLORADO 80651 January 16, 1981 Fort St. Vrain Unit No. 1 P-81015 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012

Reference:

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

Dear Mr. Seyfrit:

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

80-076 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. 50-267/80-076.

Very truly yours,

?Y Don Warembourg #

Manager, Nuclear Production DW/cis Enclosure ~~

0) cc: Director, MIPC 0

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81012205//3 g

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REPORT DATE: January 16, 1981 REPORTABLE OCCURRENCE 80-076 ISSUE O OCCURRENCE DATE: December 16, I980 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE C(EPANY OF COLORADO 16805 WELD COUNTY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-076/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

On Friday, December 19, 1980, t 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, it was determined that the results of the laboratory carbon sample analysis performed on the 1A reactor plant exhaust filter on December 16, 1980, showed an 86.75% radioactive methyl iodide removal capability, which is less than the 90% required by SR 5.5.3(a) . The 1B and 1C filters showed 90.81% and 92.69% removal capa-bilities respectively.

This event is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT DESCRIPTION:

On December 4,1980, methyl iodide penetration tests were perf ormed on reactor plant exhaust charcoal adsorbers 1A,13, and 1C (F-7301, F-7302, and F-7302S respectively). The tests were performed to demonstrate compli-ance with Surveillance Requirement 5.5.3(a) and Limiting Condition for Operation 4.5.1(b). The tests were performed by contract personnel and the results were conveyed to the licensee via Western Union Mailgram, which was received at Fort St. Vrain on December 16, 1980. The methyl iodide removal efficiencies for the reactor plant adsorbers were as follows: F-7301 -

86.75%; F-7302 - 90.81%; and F-7302S - 92.69%. The methyl iodide removal efficiency specified in Surveillance Requirement 5.5.3(a) is 90% or greater.

The methyl iodide removal efficiency for F-7301 did not satisfy the limit contained in Surveillance Requirement 5.5.3(a).

CAUSE DESCRIPTION:

The cause of this occurrence appears to be normal exhaustion of the acti-vated charcoal adsorber. The activated charcoal contained in F-7301, F-7302, and F-7302S was last changed out in January,1975. A trend analysis performed subsequent to receiving the methyl iodide removal results indi-cates a gradual decrease in removal efficiency since June,1979, f or all three adsorber beds.

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- l REPORTABLE OCCURRENCE 80-076 ISSUE O Page 2 of 3 CORRECTIVE ACTION:

Immediately upon receiving the methyl iodide removal results, IA reactor plant charcoal adsorber (F-7301) was removed from service via status tag

  1. 1579, issued at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on December 16, 1980. F-7302S was placed into service.

Plant Trouble Report 12-247, requesting change-out of F-7301, was written on December 16, 1980. Replacement activated charcoal adsorber is currently on site, and F-7301 will be changed out as soon as manpower becomes available.

No further corrective action is anticipated or r equired.

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. l REPORTABLE OCCURRENCE 80-076 ISSUE O Page 3 of 3

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a Prepared By: d/Afrh ['. M FMderick J. Bordt)

Senior Plant Engineer s

Reviewed By* _

. W. Gatin

/ Technical Services Supervisor Reviewed By:

Frank M. Mathie .

Operations Manager Approved By: ~ Mu; ,

Don Warembourg /

Manager, Nuclear Production

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