05000346/LER-1978-115-01, /01T-0:on 781127,noted That Station Procedures Failed to Specify Proper Actions in Event of Combined Steam & Feedwater Rupture Control Sys & Safety Features Actuation Sys Actuation

/01T-0:on 781127,noted That Station Procedures Failed to Specify Proper Actions in Event of Combined Steam & Feedwater Rupture Control Sys & Safety Features Actuation Sys Actuation

ML20027A523
Person / Time
Site:	Davis Besse
Issue date:	12/08/1978
From:	Lingenfelter J TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20027A522	List: 05000346/LER-1978-115, Forwards LER 78-115/01T-0 05000346/LER-1978-115-01, /01T-0:on 781127,noted That Station Procedures Failed to Specify Proper Actions in Event of Combined Steam & Feedwater Rupture Control Sys & Safety Features Actuation Sys Actuation
References
TASK-TF, TASK-TMR LER-78-115-01T, LER-78-115-1T, NP-32-78-12, TAC-11050, NUDOCS 7812140140
Download: ML20027A523 (3)

LER-1978-115, /01T-0:on 781127,noted That Station Procedures Failed to Specify Proper Actions in Event of Combined Steam & Feedwater Rupture Control Sys & Safety Features Actuation Sys Actuation

Event date:
Report date:
3461978115R01 - NRC Website

text

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during a meeting to discuss a proposed change to the steam generator levell 10121 l On 11/27/78, it was determined that station procedurc{s l setpoints for the Auxiliary Feedwater System, io l3 j d

g l f ailed to specify the proper actions for the event of a combined Steam and Fee water o,

i System (SFAS) actuation j o,,,, l Rupture Control System (SFRCS) and Saf ety Features Actuat on d as per Tech Spec 4

l 0 {6 l l This inadequacy of administative controls is being reporte The special 120 inch level setpoint is only required in the unlikely j

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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-32-78-12 DATE OF EVENT: November 27, 1978 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Procedure inadequacy if a small Reactor Coolant Sys-tem (RCS) leak occurred during a Steam and Feedwater Rupture Control System (SFRCS) actuation Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWI) = 2250, and Load (MWE) = 720.

Description of Occurrence: On November 27, 1978, Toledo Edison and Babcock and i

Wilcox personnel met to discuss a proposed change to the steam generator level setpoints for the Auxiliary Feedwater System, which provides feedwater when the SFRCS is actuated.

A steam generator level of about 35 inches was determined to be adequate in all cases of SFRCS actuation except when an RCS leak in the "small break" category An SFRCS actuation in conjunction with a small break requires a 120 inch occurs.

level setpoint.

With the present control configuration,120 inch steam generator level setpoint is automatically obtained in all cases of SFRCS actuation.

In order to minimize the effects of the cooldown following auxiliary feedwater injection, station emergency procedures direct the operator to take manual control of the auxiliary feedwater and maintain a lower level. The procedures do not tell the operator to leave the auxiliary feedwater in automatic (" Auto Essential") if a small RCS break occurs with the SFRCS actuation, or to return to automatic if a small break occurs af ter SFRCS

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actuation. Actuation of the Safety Fe'atures Actuation System (SFAS) Incident Level 2 is considered to be the indication of a small break.

Failure of the procedures to specify the proper actions for the event of a combined SFRCS and SFAS actuation is being reported as per Technical Specification 6.9.1.8(1).

Designation of Apparent Cause of Occurrence: The procedural inadequacy occurred because the unique requirement of a 120 inch steam generator level setpoint for a SFRCS and SFAS actuation was not recognized until the proposed change in setpoints was investigated.

e Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. The 120 inch steam generator level 'setpoint is only required

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in the unlikely event of an SFRCS actuation and a small RCS' break.

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LER #78-115 I

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TOLEDO EDISON COMPA!N DAVIS-BESSE NUCLEAR POWER STATION UNIT OI.E PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-32-78-12 Modifications to all station procedures related to SFRCS actua-

Corrective Action

Tha modifications will require the operator to leave tion are being prepared.

(or return) the auxiliary feedwater controls in automatic in the event of an SFAS Incident. Level 2 actuation occurring with an SFRCS actuation.

No previous discoveries of procedure errors due to unrecognized Failure Dcta:

safety analysis assumptions have been made.

LER #78-115

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