ML20085M560

LER 75/025:on 751114,during Cold Shutdown,Helium Circulator C-2103 Tripped.Caused by Loop 2 Bearing Water Sys Perturbation.No Explanation Found.Circulator Restarted & Continued to Self Turbine

ML20085M560
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1975
From:	Franek W, Swart F PUBLIC SERVICE CO. OF COLORADO
To:	Howard E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
LER-75-025, LER-75-25, P-75046, NUDOCS 8311090006
Download: ML20085M560 (6)

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• • *- 1 UNLP EVENTS AND ABNOR'i/ f, OCCURRENCE RF. PORTS ^TitiT>tTIONS w -

Numb;r of Copiss San Francisco Operations Office .

ERDA 1333 Broadway Oakland, California 94612 Atta: Manager - - - - - - - - - - - - - - - - - - - - - - - - - - 2*

Californir. Patect Group - - - - - - - - - - - - - - - - - - - 1*

Division of Reactor Research and Development ERDA Washington, D.C. 20545 Atta: Director --------------------------1*

Asst. Dir. for Cas Cooled Reactor Projects - - - - - - - - - 2*

Asst. Dir. for Engrg and Technology - - - - - - - - - - - - 1*

As s t . Dir. fo r Reac t o r Sa f e ty - - - - - - - - - - - - - - - - 1*

ERDA-S CRPO- S D - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1

• P. O. Box 81325 San Diego, California 92138 Project Engineer ---------------------------1* .

ERDA - SCRPO P. O. Box 1446 Canoga Park, California 91304 Address +++ Director -------------------------------1 Letter ERDA - SCRPO T3 P. O. Box 1446 Canoga Park, California 91304 Technical Information Center - - - - - - - - - - - - - - - - - ----3*

ERDA 1h 0. Box 62 Oak Ridge, Tennessee 37830 t .

Address -+++ Mr. E. Morris Howard, Director - - - - - - - - - - - - - - - - --- 1 (copy of Licensee Event P Lecter Region IV. Report)

TJ Office of_ Inspection & Enforcement

• Nucicar Regulatcry Cocsission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Director of Nuclear Reactor Regulation - - - - - - - - - - - - ----1 (copy of Howard's letter and Attn: Mr. Roger S. Boyd, Acting Director mailogra:i)

Division of Reactor Licensing U. S. Nuclear Regulatory Cocsission Washington, D.C. 20555 . .

Address +++ Office of Information & Program Control - - - - - - - - - - - - - - - - 1 (Original of LER)

P Letter U. S. Nuclear Regulatory Conctission To Washington, D.C. 20555 Address +++ John M. Waage. Project Manager - - - - - - - - - - - - - - - - - - - - 10*

FPLG General Atomic Company I4tter P. O. Box 81608 T2 San Diego, California 92138 Secretary, NFSC, Belleview - - - - - - - - - - - - - - - - - - ----1 .

Vice President, Engineering & Planning 39th Avenue Engineering - - - - 1 Manager af Production (Chairran, NFSC), Belleview - - - - - - - - - - - 1 Direc tor , Quality Assurance - - - - - - - - - - - - - - - - - - - - - - 1 Technical Services Supervisor - - - - - - - - - - - - - - - - - - - - - 1 Superintendent, Nuclear Production - - - - - - - -- - - - - - ----1 Superintendent, Operations - - - - - - - - - - - - - '-'- - - - ----1 Training coordinator -------------------------1

• PORC Cocnittee ---------------------------1 Technical Services Files -----------------------1 Train ing Review - - - - - - - - - - -- - - - - - - - - - - - - - - - - 6

• Indicates a zerox cony of the, letter to the Director ERDA-SCRPO, is sent with the copies of the report.

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\ pubite sendee company *e odlemde P. O. Box 361, Platteville, Co18rado 80651 December 31, 1975 Fort St. Vrain Unit No. 1 P-75046 . s (Q C3 g ( 'Q <

Mr. E. Morris Howard, Director 2 '

Nucicar Regulatory Commission  : d4Ng /3/ __

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V' 0.g,,,h Region IV Office of Inspection and Enforcement

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Suite 1000 Arlington, Texas 76012 gj

[Ap Ref: Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Howard:

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

75/25, Final, submitted per the requirements of the Technical Specifi-cations.

Also, please find enclosed one copy of the Licensee Event Report for Abnormal Occurrence Report No. 50-267/75/25.

Very truly yours, C::=se W Frederic E. : Swart Superintendent, Nuclear Production Fort St. Vrain Nuclear Generating Station FES/alk cc: Mr. Roger S. Boyd 177-n y b f G- O "

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U REPORT DATE: December 31, 1975 ABNORMAL OCCURRENCE 75/25 Page 1 of 3 OCCURRENCE DATE: December 22, 1975 FORT ST. VRAIN NUCLEAR CENERATINC STATION PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/75/25

' Final IDENTIFICATION OF - i OCCURRENCE:

Helium circulator C-2103 tripped. This is identified as an abnormal occurrence per' Section 2.1, paragraph (F), of the Fort St. Vrain Technical Specifications.

This problem occurred November 14, 1975, and in discussion with the Nuclear Regulatory Commission on December 22, 1975, it was agreed to report this inci-dent as an; abnormal occurrence. .

CONDITIONS PRIOR TO OCCURRENCE: Steady State Power. Routine Shutdown Hot Shutdown Routine Load Change X Cold Shutdown Other (specify')

Refueling Shutdown Routine Startup The major plant parameters at the time of the event were as follows: -

Power RTR 0 MWth ELECT

• O MWe Secondary Coolant Pressure 1,333 psid Temperature 214 *F -

Flow 49,000 f/hr.

Primary Coolant Pressure 333 psig 4

Temperature 214 'F' Core Inlet 207 'F Core Outlet Flow N/A* f/hr.

• Loop 2 circulators, C-2103 and C-2104, 'self-turbinina. .

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' ABNORMAL OCCURRENCE 75/25 Page 2 o f 3 DESCRIPTION OF OCCURRENCE: Design Unusual Service Cond.

Including Environment Manufacture Component Failure Installation /Const. X - Other (specify)

Operator Bearing water pressure change.

Procedure Cause unknown.

ANALYSIS OF OCCURRENCE:

Helium circulators, C-2103 and C-2104, were scif-turbining when C-2103 tripped with an alarm indication of " loss of bearing water." The standby bearing water pump in the af fected loop started which indicates the loop bearing water pressure to the circulators decreased. This eliminates the possibility that the trip signal was caused by the plant protective system. The circulator was restarted and no' further problems were encountered.

A check of the latest bearing water switch calibrations did not indicate any reason why C-2103 would trip and C-2104 would not.

The trip is considered spurious and could not be caused to repeat. No explanation for this occurrence could be found. .

CORRECTIVE ACTION:

The circulator was restarted and continued to self-turbine. The other circulator

-in the. loop was operated up to near 3,000 RPM and continued to function normally. .

No further corrective action is planned ~at this time.

FAILURE DATA /SIMILAR REPORTED OCCURRENCES:

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Unusual: Event Report No. 50-267/75/16, dated October 17, 1975, describes the same circulator: tripping due to "high pressure separator-level".. No reason for this trip could be:found.

PROGRAMMATIC' IMPACT: .

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i ' ABNORR\L OCCURRENCE 73/25 s

Page 3 of 3 .

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Submitted by:

H. W. Hilfyard, Jr(

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3 Technical Services Supervisor ,

1 Reviewed by: N. W b1 /t H. Larry Brey

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Superintendent, Operations i

Approved by: Ar2u - '

Q Frederic E. Swart' Superintendent, Nuclear Production j

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