ML20085M445

LER 76/004:on760206,during Weekly Surveillance on 1A Standby generator,1B Engine Partially Declutched Under Load.Caused by Clutch Engaging Pressure Not within Acceptable Tolerance

ML20085M445
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/13/1976
From:	Franek W, Swart F PUBLIC SERVICE CO. OF COLORADO
To:	Howard E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
LER-76-004, LER-76-4, P-76044, NUDOCS 8311080578
Download: ML20085M445 (6)

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Division of Reactor Rescatch and Development ERDA Washington, D.C. 20545 Attn: Director --------------------------1* - - - - - - 2*

Asst. Dir. for cas Cooled Reactor Projects - - -

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

z Asst. Dir. for Reactor Saf ety - - - - - - - - - - - - - - - - 1*

ERDA- SCRPO- SD - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1

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

ERDA - SCRPO i P. O. Box 1446 Canoga Park, California 91304 Address +++ Director ---------------------+---------1 Letter ERDA - SCRPO Ta P. O. Box 1446

• Canoga Park, California 91304

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Technical Information Center ERDA P. O. Box 62 04k Ridge Tennessee 37810 ' .

Hr. E. Ibtris Howard, Director - - - - - - - - - - - - - ----- -1 (copy of Licensee Event Afdrese +++

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P Letter Region IV.

• Ta Office of Inspeccion & Enforcement Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Director of Nuclear Reactor Regulation - - - - - - - - - ------1 (copy of Howard's letter, Attu: Mr. Roger S. Boyd. Director. mailogramr and Licensee Division of Project Management Event Report)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Office of informatioc & Program Control - - - - - - - - - - - - - - - - 1 (Original of 1 Licensee Address +++

Event Report)

P Letter U. S. Nuclear Regulatory- Commission Ta Washington, D.C. 20555

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Address +++ John M. Vaage, Project Manager FPLC General Atomic Company Letter P. O. Box 81608 Ta ' San Diego, California 92138 ,

Secretary, NFSC, Belleview ----------------------1 Vice President, Engineering & Planning, 39th Avenue Engineering - - - -

Manager of Production (Chairman, NFSC), Belleview - - - - - - - - - - - 1  ;

Director. Quality As surance - - - - - - - - - - - - - - - - - - - - - - 1 Technical Services Supervisor - - - - - - - - - - - - - - - - - - - - - 1 Superintendent, Nuclear Production - - - - - - - - - - - -------1 Superintendent, Operations --------------------- ,

l Training Coordinator -------------------------1 PORC Committee ----------------------------1 Technical Services Files -------------.---------1 Training Review - - - - - - - - - - --- - - - - - - - - - - - - - - - - 6 .

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'puhuc service company oe conende P.O. Box 361, Platteville; Colorado 80651 February 13, 1976 Fort St. Vrain g.; ,.,

Unit No. , ,p - . , , - "

P-76044 s ~

p Mr. E. Morris Howard, Director Q#% O g/j';.,

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Nuclear Regulatory Commission O Region IV f# %g f /

l Office of Inspection and Enforcement \ s l Suite 1000 'k/ / f . . hj'@3 Arlington, Texas 76012 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/

J6/04,_ Preliminary, submitted per the requirements of the Technical Specifications.

Also, please find enclosed one copy of the Licensee Event Report for Abnormal Occurrence Report No. 50-267/76/04.

Very truly yours, n' s' 'I

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/ Frederic E. Swart Superintendent, Nuclear Production Fort St. Vrain Nuclear Generating Station FES/dme ec: Mr. Roger S. Boyd

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REPORT DATE February 13, 1976 . ABNOR&u,OCCURP2NCE 76/04 Page 1 of 3 OCCURRENCE DATE February 6, 1976 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P.O. BOX 361 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/76/04 Preliminary IDENTIFICATION OF OCCURRENCE:

The clutch on "B" engine 1A Standby Generator moved in the declutch direction under load. This is identified as an abnormal occurrence per Section 2.1, paragraph (f) of the Fort St. Vrain Technical Specifications.

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 paraceters at the time of the event were as follows: ,

Power RTR 0 MWth ELECT 0 MWe Secondary Coolant. Pressure 15. _

psig Temperature 70 *F -

Flow 75000 I/hr.

Primary Coolant Pressure 159 psig Temperature 86 *F Core Inlet 86 *F Core Outlet Flow 0 #/hr.

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ABNORMAL OCCURRENCE 76/04 Page 2 of 3 DESCRIPTION OF OCCURRENCE:

The 1A Standby Diesel generator diesel engines had been locally started and the generator loaded to 50% per the weekly surveillance procedure. The standby generator set continued in operation for approximately one hour when a Standy Cenerator Trouble alarm was r ceived in the main control room. The operator went to the standby generator roomand discovered the clutch arm had moved slightly in the declutch direction and actuated the switch. Load was reduced to 25% and the engine was declutched and the test was complete.

APPARENT CAUSE OF OCCURRENCE: Design Unusual Service Cond.

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

Operator Procedure The force required to engage the clutch was out of tolerance.

ANALYSIS OF OCCURRENCE:

In this instance, the clutch was engaged and later disengaged under load. A check of the clutch engaging force was made and found to be in excess of 225 pounds. It should have been bet.veen 155 and 204 pounds. The clutch mechanism force had been adjusted on January 12, 1976, per PM 92.10 quarterly inspection.. This was the first operation of the diesel generators under load since that inspection. It has not yet been determined why the engaging force was excessive. The surveillance procedure 5.6.1d-M (Diesel Engine Exhaust Temperature Functional Test) was com-pleted before the 50% load test. This procedure requires the clutch to be operated and the low temperature declutch verified.

CORRECTIVE ACTION:

The solenoid valve was cleaned and checked for leakage and reinstalled. The clutch pressure has been readjusted to 190 pounds engaging force. The clutch mechanism will be disassembled and thoroughly examined for any possible mechanical problems.

FAILURE DATA /SIMILAR REPORTED OCCURRENCES:

Abnormal Occurrence 50-267/74/23 concerning Engine 1A. Similar occurrence but different cause.

PROGRAMMATIC IMPACT:

• None e

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O OABNORMALOCCURRENCE76/04

. . Pagn 3 of 3 CODE IMPACT:

None ,

Submitted by- .

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IW.'liillygd, Jr. /

Technical Servi::es Supervisor

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• Reviewed by: W2u.4v 7- t pu, _

Duane Lambert Supervisor, Plant Electricians l .

Reviewed by: S b' Frank M. Mathie

,, Superintendent, Maintenance 7

Approved by , ag ag$ , j [ . d ov-o,v Ffederic E. Swart Superintendent. Nuclear Production f

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