05000267/LER-1982-027, Forwards LER 82-027/03L-0.Detailed Event Analysis Encl

Forwards LER 82-027/03L-0.Detailed Event Analysis Encl

ML20063G713
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/22/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20063G719	List: 05000267/LER-1982-027, Forwards LER 82-027/03L-0.Detailed Event Analysis Encl
References
P-82264, NUDOCS 8207290196
Download: ML20063G713 (6)

LER-2082-027, Forwards LER 82-027/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2672082027R00 - NRC Website

text

t s >s public Service Company Cf OcEcIreldo Yn 16805 Road 19 1/2, Platteville, Colorado 80651-9298 July 22, 1982 Fort St. Vrain Unit No. 1 P-82264 - - - - -

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All 2 61982 .

Mr. John T. Collins, Regional Administrator :N

Region IV -

Nuclear Dagulatory 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. 50-267/82-027, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)1 and AC 7.5.2(b)3..

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/82-027.

Very truly yours, hn kwl*

Don Warembourg Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC A h

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8207290196 820722 PDRADOCK05000g

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REPORT DATE: July 22, 1982 REPORTABLE OCCURRENCE 82-027 ISSUE O CCCURRENCE DATE: June 28, 1982 Page 1 of 5

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FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/82-027/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

While performing a regularly scheduled Surveillance Test on primary coolant moisture monitor instrumentation sample flow alarm setpoints, an Instrument < Technician found 11 of the flow alarms were out of

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tolerance as specified by LCO 4.4.1, Table 4.4-1, note (t). This event is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)1 and AC 7.5.2(b)3.

EVENT j DESCRIPTION:

With the plant operating at 70% thermal power and 215 MW(e), plant Instrument Technicians performed the Primary Coolant Instrumentation Sample Flow Alarm Functional Test, SR 5.4.1.1.6e-M. This test

determines if the sample flow low and sample flow high alarm setpoints are correct and will alarm in the main Control Room.

Limiting Conditions of Operation 4.4.1, Table 4.4-1, note (t),

specifies that a dewpoint moisture monitor will not be considered operable unless the following conditions are met:

a) The fixed low-low sample flow alarms are set at 1 standard cubic centimeter per second.

b) The fixed high sample flow alarms are set at 75 standard cubic centimeters per second.

c) The variable low sample flow alarms are set at 1 to 50 standard cubic centimeters per second, depending on reactor power level.

i While performing the above mentioned Surveillance Test, one of the fixed low-low sample flow alarm setpoints was found below the 1 standard cubic centimeter per second limit, five of the fixed high sample flow alarm setpoints were found above the 75 standard cubic centimeters per second limit, and five of the variable low sample flow alarm setpoints were found below the 50 standard cubic centimeters per second limit as was specified for the reactor power level at the time the Surveillance Test was performed. The setpoints found for these flow alarms are listed in the attached tables, one through three.

REPORTABLE OCCURRENCE 82-027 ISSUE O Page 2 of 5 In reference to the attached tables, the fixed " low-low" sample flow alarm and the variable " low" sample flow alarms are actuated on decreasing voltage, and the fixed "high" sample flow alarms are actuated on increasing voltage.

Although the flow alarm setpoints were found out of tolerance, this did not prevent the fulfillment of the functional requirements of the dewpoint moisture monitors. The actual sample flows were verified to be above the minimum flow rates specified for 75% to 100% reactor power operation.

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e REPORTABLE OCCURRENCE 82-027 ISSUE 0 Page 3 of 5 TABLE 1 i

Low-Low Flow (1 sec/sec) l Moisture l Monitor l Acceptance l As l As l l Monitor I Loop 1 Criteria l Found I Left l I I I I i 1 l MM-1117 i Loop 1 1 0.08V - 0.13V I 0.006V l 0.108V l -

TABLE 2 High Flow (75 sec/sec) l Moisture l Monitor i Acceptance l As l As l l Monitor i Loop i Criteria l Found i Left [

l i I I i 1 l MM-1115 i High Level 1 4.06V - 4.16V l 5.11V I 4.15V l l l l l l 1 l MM-1116 i Looo 1 1 4.09V - 4.19V l 4.28V l 4.15V l l 1 I I I i l MM-1119 i High Level i 4.06V - 4.16V I 4.34V I 4.11V [

l i l I I I l MM-1120 i Loop 2 1 4.05V - 4.15V I 4.23V I 4.07V l l l l l l l l MM-1122 l Loop 2 1 4.06V - 4.16V I 4.30V I 4.07V l TABLE 3 Low Flow (50 sec/sec) l Moisture l Mur. tor l Acceptance l As l As l l Monitor I Loop 1 C9tteria l Found l Left l 1 I I I I -

l l MM-1115 i High Level i 2.99V - 3.09V I 2.02 V I 3.06V l l l l l 1 l l MM-1116 i Loco 1 l 2.93V - 3.03V I 0.897V l 3.01V l l 1 1 I I i l MM-1119 I Hioh Level i 2.96V - 3.06V I 0.805V l 3.03V l l l 1 1 I I l MM-1120 i Loop 2 1 2.92V - 3.02V I 0.87 V I 3.00V l l l 1 l l l l MM-1122 l Loco 2 1 2.86V - 2.96V l 0.98 V l 2.90V l 1

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REPORTABLE OCCURRENCE 82-027 ISSUE 0 Page 4 of 5 CAUSE DESCRIPTION:

The cause of this event, as far as the "high alarm setpoints are

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concerned, was instrument drift due to ambient conditions in that area of the Reactor Building.

Concerning the " low-low" and the variable " low" alarm setpoints, it has been determined there is a procedural inadequacy in the Overall Plant Operating Procedures, III and IV. The Reactor Operator was required only to verify correct moisture monitor sample flow without any verification of actual alarm setpoints.

CORRECTIVE ACTION:

The alarm set' points were re-adjusted to the correct values, and the Surveillance Test was completed satisfactorily.

The frequency of this test will be increased for a period of time until enough data can be gathered to verify a higher level of reliability. Also, a change will be ini+* ted to the Overall Plant Operating Procedures, Sections III and IV. Vs change will require that not only the actual sample flows be verified, but also the alarm setpoints have been reset by plant Instrument Technicians in accordance with reactor power level at that time.

As a precaution, the digital volt ~ meter used for the previous Surveillance Test of June 28, 1982, has been sent out for a calibration recheck. When results of this check have been received, action will be taken as required.

No further carrective action is anticipated or required.

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REPORTABLE OCCURRENCE 82-027 ISSUE O Page 5 of 5 Prepared By: //ent. . Io o .

Quane C.~Frye 47 Technical Services Technician Reviewed By: hAldr,L id Charles Fuller TechnicalServicsEngine 'ing Supervisor

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Reviewed By: /

StatibnMana}gerEdwin/DL(H14 A" Approved By: FwM Don Waremcourg (/

Manager, Nuclear Production