IR 05000267/1985021

Insp Rept 50-267/85-21 on 850721-31.No Violation or Deviation Noted.Major Areas Inspected:Operational Safety Verification

ML20135H569
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/30/1985
From:	Ireland R, Jaudon J, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20135H565	List: IR 05000267/1985021 ML20135H564
References
50-267-85-21, NUDOCS 8509240020
Download: ML20135H569 (3)

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APPENDIX

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U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-267/85-21 License: DPR-34

. Docket: 50-267 Licensee:

Public Service Company of Colorado

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P. O. Box 840 Denver, Colorado 80201 Facility Name: Fort St.'Vrain Nuclear Station (FSV)

Inspection At: Platteville, Colorado Inspection Conducted: July 21-1, 19 Inspector :-

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7kow Pfoject Inspector.

Date Pr ecLS tion A,-Reactor Projects Branch s

Y$. Ob/wY W/2 9 h5 R. E. Ireland, Chief, Engineering Section D&te

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Reactor Safety Branch

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Approved:

. Jo ns /Jaudfn, Chief, Project Section A Date ct6r P{ojects Branch R

Inspection Summary Inspection Conducted July 21-31, 1985 (Report 50-267/85-21)

Areas Inspected: Routine, unannounced inspection of operational safety verification. The inspection involved 50 inspector-hours onsite by two NRC inspectors.

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Results: Within the areas inspected, no violations or deviations were identified.

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DETAILS 1.

Persons Contacted J. C. Gahm, Manager, Nuclear Power Operations

• C. Fuller, Station Manager F. Novachek, Technical / Administrative Services Manager

• F. Borst, Support Services Manager

• Denotes those present at exit interview 2.

Operational Safety Verification The NRC inspectors observed control room activities, control room panels, toured the plant observing general conditions and plant status. During this inspection period, the reactor was started up for the first time in over 1 year. Because of-the extended shutdown and the nature of the maintenance activities permitting moisture to become absorbed in the primary systems, a slow rise to power was anticipated. This period would permit the removal of the excess moisture.

An automatic reactor shutdown occurred a few days after startup due to high moisture just after midnight, the morning of July 24, 1985. Human factors engineering appears.to have contributed to the shutdown. A valve in the bearing water drain from the "A" circulator was inadvertently operated in closed direction vice the open direction. This action forced water past the circulator seals into the reactor coolant. The notation on the control switch previously read "open" or " closed." The revised notation read "INCR" or "DECR" differential pressure. Based on discussions with plant personnel, the revised notation was intended to reduce operator thought processes.

It appears that increased thought process as well as-misinterpretation of "INCR" and "DECR" took place.

Plant personnel stated the operator knew that he wanted the valve to move in the open direction, but could not remember which switch position would cause the desired valve movement. The "Open" and "Close" notation was subsequently added to the switch position labels.

In addition, other similarly labeled switches have also had the "open" and "close" notation added. The labeling aspects of this event were discussed with the staff of the Human Factors Engineering Branch of NRR.

No violations or deviations were noted.

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Exit Interview An exit interview was held on July 19, 1985, with Mr. Fuller and Mr. Borst.. At ~the meeting, the scope of the inspection was summarized.

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An additional exit was held on July 22, 1985', by Mr. Ireland with Mr. Fuller and Mr. Borst.

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