05000267/LER-1976-013, Handwritten LER 76-013:on 760607,circulators Tripped Due to Trouble Shooting.Caused by Pulled Module Interlock Circulator Isolation Relays.Modules inserted.W/760617 Ltr

Handwritten LER 76-013:on 760607,circulators Tripped Due to Trouble Shooting.Caused by Pulled Module Interlock Circulator Isolation Relays.Modules inserted.W/760617 Ltr

ML20086A013
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/17/1976
From:	Hillyard H, Swart F PUBLIC SERVICE CO. OF COLORADO
To:	Howard E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20086A000	List: 05000267/LER-1976-013, Handwritten LER 76-013:on 760607,circulators Tripped Due to Trouble Shooting.Caused by Pulled Module Interlock Circulator Isolation Relays.Modules inserted.W/760617 Ltr
References
LER-76-013-01, LER-76-13-1, P-76136, NUDOCS 8311110201
Download: ML20086A013 (6)

LER-2076-013, Handwritten LER 76-013:on 760607,circulators Tripped Due to Trouble Shooting.Caused by Pulled Module Interlock Circulator Isolation Relays.Modules inserted.W/760617 Ltr

Event date:
Report date:
2672076013R00 - NRC Website

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E.MORRISHOWAND .0 JUNE 15, 1976 REGION IV, REGULATORY OPERATION a f, \k NUCLEAR REGULATORY CO}cf1SSION 611 RYAN PLAZA DRIVE, SUITE 1000 Y' k' p\-g ARLINGTON, TEXAS 76012 THIS CONFIRMS OUR TELEPHONE CONVERSATION OF 6/15/76 CONCERNING THE FOLLOWING ABNORMAL OCCURRENCES:

DURING RUNNING OF SR 5.4.1.3.7.a-R ON 6/7/76 PROBLEMS WERE EXPERIENCED ASSOCIATED WITH THE PLANT PROTECTIVE SYSTEM OUTPUT TRIP FUNCTIONS. SUBSEQUENT TROUBLE SHOOTING RESULTED IN AN UNANTICIPATED TRIP SIGNAL TO C AND D HELIUM CIRCULATORS.

INVESTIGATION OF THE INCIDENT REVEALED THAT VARIOUS CONTROLLING ADMINISTRATIVE PROCEDURES WERE NOT FOLLOWED. (70LLOWING THE PROCEDURE WOULD NOT NECESSARILY HAVE PREVENTED THE HELIUM CIRCULATOR TRIPS.) THIS IS IDENTIFIED AS ABNORMAL OCCURRENCE 76/13 PER THE FORT ST. VRAIN TECHNICAL SPECIFICATIONS, SECTION 2.1 PARAGRAPH F.

ON 6/11/76 B HELIUM CIRCULATOR TRIPPED DUE TO AN APPARENT LOSS OF BEARING WATER.

THIS IS IDENTIFIED AS ABNORMAL OCCURRENCE 76/14 PER THE FORT ST. VRAIN TECHNICAL SPECIFICATIONS, SECTION 2.1, PARAGRAPH F.

FROM: F. E. SWART FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 550 FIFTEENTH STREET, DENVER, COLORADO 80202

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. Ja 'M June 17, 1976 Fort St. Vrain Unit No. 1 P-76136 n, s Mr. E. Norria Howard, Director # D Nuclear Regulatory Co:mnission S h go[0 [__

Region IV p* j* od ;

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Office of Inspection and Enforcement Suite 1000 9- o

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Arlington, Texas 76012 g 43 Ref: Facil N ing License No. DPR-34 Docket No. A 2.67 _

Dear Mr. Howard:

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

76/13, Prelimi2ary, Submitted per the requirements of the Technical Specifications.

Also, please find enclosed one copy of the Licensee Event Report for Abnormal Occurrence Report No. 50-267/76/13.

Very truly yours, *

• $w Frederic E. Swart Superintendent, Nuclear Production Fort St. Vrain Nuclear Generating Station FES/dme l cc: Mr. Roger S. Boyd -

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g Jure 17, 1976 REPORT DATE: ABNORMAL OCCURRENCE 76/13 I Page 1 of 3 l OCCURRENCE DATE: June 7, 1976 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P.O. Box 361 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/76/13 Preliminary IDENTIFICATION OF O_CCURRENCE:

During rurning of SR 5.4.1.3.7.a-R on June 7,1976, problems were experienced associated with the plant protective system output trip functions. Subsequent trouble shooting resulted in an unanticipated trip signal to 1C and 1D helium circulators. Investigation of the incident revealed that various controlling administrative procedure were not followed. (Following the procedure would not necessarily have prevented the helium circulator trips). This was identif-ied as an abnornal occurrence per the Fort St. Vrain Technical Specifications, Section 2.1, paragraph f.

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 Wth ELECT 0 We Secondary Coolant Pressure 1000 psig l

Temperature 180 *F 1

l Flow 244000 f/hr. -

i Primary Coolant Pressure Nl .0 psig l

Temperature _ _150 *F Core Inlec 150 *F Core Outlet Flow 0 f/hr.

. All 4 helium circulators were self-turbining.

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l NORMAL OCCURRENCE 76/13 i

Page 2 of 3 DESCRIPTION OF OCCURRENCE:

Results and Operations personnel were attempting to complete SR 5.4.1.3.7.a-R.

This test includes an " Auto Water Turbine Start" of the helium circulators through the operation of the plant protective system (PPS). Due to various interlocks, certain PPS modules had to be removed to obtain the desired initial conditions required by the test, however the necessary initial condit-ions could not be obtained. Resulte personnel began trouble shooting the problem which included pulling and inserting certain PPS modules. This action resulted in a " loss of bearing water" trip signal being initiated but due to the pulled PPS modules the circulator auxiliaries could not be properly con-trolled or isolated. The action resulted in an increase in the primary coolant moisture and nitrogen content. (Nitrogen source is the bearing water accumulator).

APPARENT CAUSE OF OCCURRENCE: Design Unusual Service Cond.

Including Environment Manufacture Component Failure Installation / Cons t. Other (specify)

X Operator X Procedure ANALYSIS OF OCCURRENCE:

The " auto water turbine start" portion of procedure 5.4.1.3.7.a-R does not properly address the conditions or trips the will be present when the reactor is scrammed and the ISS is in the " power" position.

There were several violations of established procedures but following procedures probably would not have prevented this occurrence.

CORRECTIVE ACTION:

Impurities in the primary coolant are being removed by the helium purification system.

Further investigation into the sequence of events is continuing and will be submitted in a future report along with appropriate corrective actions.

FAILURE DATA /SIMILAR REPORTED OCCURRENCES:

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NORMAL OCCURRENCE 76/13 age 3 of 3 PROGRAMMATIC IMPACT:

! None CODE IMPACT:

None Submitted by: 2,

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H.W. Killyard//Jr.

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Technical Serfices Supervisor Reviewed by: '

H. Larry Brey Superintendent, Operations Approved by: o ,, g ma pedericE. Swart _

Superintendent, Nuclear Production 1

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