05000382/LER-1994-006, :on 940415,determined That on 921103, Unidentified RCS Leak Rate of Greater than 1 Gpm Occurred. Caused by Error in RCS Mass Balance Equation.Approved Temporary Change to Procedure OP-903-024

:on 940415,determined That on 921103, Unidentified RCS Leak Rate of Greater than 1 Gpm Occurred. Caused by Error in RCS Mass Balance Equation.Approved Temporary Change to Procedure OP-903-024

ML20029D994
Person / Time
Site:	Waterford
Issue date:	05/11/1994
From:	Packer D, Vinci D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-006, LER-94-6, W3F1-94-0058, W3F1-94-58, NUDOCS 9405130277
Download: ML20029D994 (6)

LER-1994-006, on 940415,determined That on 921103, Unidentified RCS Leak Rate of Greater than 1 Gpm Occurred. Caused by Error in RCS Mass Balance Equation.Approved Temporary Change to Procedure OP-903-024

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3821994006R00 - NRC Website

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Document Control Desk Washington, D.C.

20555

Subject:

Waterford 3 SES Docket No. 50-382 License flo. f4PF-38 Reporting of Licensee Event Report Gentlemen:

Attached is Licensee Event Report fiumber LER-94-006-00 for Waterford Steam Electric Station Unit 3.

This Licensee Event Report is submitted in accordance with the requirements of 10CFR50.73(a)(2)(i)(B) and 10CFR50.36(c)(2).

Very truly you s, CM

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L.J. Callan, NRC Region IV G.L. florreich J.T. Wheelock - INPC Records Center R.B. McGehee N.S. Reynolds f1RC Resident Inspectors Office y

Administrator - LRPD

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Waterford Steam Electric Station Unit 3 05000 382 10F 04 pru m -

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ADSTRACT (Lim,t to 1400 spaces. t e, a;; proximate:y 15 mngle spaced typeetten kne?) (16)

On April 15, 1994, Waterford SES Unit 3 was shutdown for refueling in Mode 5 while conducting a compliance review check of previous Reactor Coolant System (RCS) leak rate calculations that were based on Attachment 10.4 of Revision 8 to Operating Procedure OP-903-024.

At this time it was determined that on Noverrber 3,1992, during the previous refueling outage (Refuel 5), that an unidentified RCS leak rate of >l GPM had occurred during Mode 5 before entering Mode 4, which constituted noncompliance with Technical Specification (TS) 3.0.4.

The root cause of this event was inadequate technical review of a change made to the RCS mass balance equation in Attachment 10.4 of Revision 8 to OP-903-024.

Immediate corrective action included a tetrporary approved change to Attachment 10.4, correcting the equation.

Action to prevent recurrence will be to have Operations personnel review this event.

The event did not compromise the health and safety of the public.

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00 um,.,,. w.....n.a. -..m-. m...., ec o+ um p n REPORTABLE OCCURRENCE On flovember 3,1992, during the previous refueling outage (Refuel 5), an unidentified RCS (EIIS Identifier AB) leak rate of 1.4424 GPM had occurred.

Due to incorrect calculational methods, the unidentified RCS leak rate at the time, during Refuel 5, was calculated to be <1 GPM; therefore, no action was taken to prevent from proceeding to Mode 4.

TS 3.0.4 states that entry into an operational mode shall not be made unless the conditions of the LCO are met without reliance on provisions contained in the action requirements.

Also, TS 3.4.5.2 states that RCS leakage shall be limited to 1 GPM unidentified leakage for Modes 1, 2, 3 and 4.

Therefore, upon entry into Mode 4, a condition prohibited by the plant's Technical Specifications had occurred; and, per 10CFR50.73(a)(2)(i)(B) and 10CFR50.36(c)(2) the event is reportable as an LER.

I INIT_IAL_COND1TIONS Plant Power 0%

Plant Operating Mode Mode 5 Procedures Being Performed Specific to this Event OP-903-024 1

Technical Specification LCO's in

'l Effect Specific to this Event 3.4.b.2 Major Equipment Out of Service l

Specific to this Event lione l

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Waterford Steam Electric Station 05000 382 03 OF 04 Unit 3 94

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,6., o ww,m> v n EVENT SEQUENCE On April 11, 1994, during Refuel 6 while attempting to use Attachment 10.4 of OP-903-024 for an RCS leak rate calculation, it was realized that the i

results were ur, realistic for plant conditions that existel at the time.

On April 13, 1994, the results of an investigation revealed that the formula for the RCS mass balance equation (AGrcs), when T vg is <540*F, used in a

step 8.1.1.5 of Attachment 10.4 of OP-903-024 was in error.

The initial and final RCS inventories were reversed in the equation; i.e., the final I

inventory should have been subtracted from the initial inventory to obtain i

AG The investigation determined that this equation was revised by rcs.

Revision 8 to OP-903-024 on September 6, 1991.

The previous Revision 7 (dated February 13, 1990) equation was correct and the incorrect equation i

was introduced by Revision 8.

The investigation also recommended that a compliance review check be conducted of previous RCS leak rate calculations

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that were based on Attachment 10.4 of Revision 8 to OP-903-024.

On April 15, 1994, at 1637 hours0.0189 days <br />0.455 hours <br />0.00271 weeks <br />6.228785e-4 months <br />, Waterford 3 was shutdown for refueling in Made 5 while conducting the recommended compliance review check when it was determined that on November 3, 1992, that an unidentified RCS leak rate of

>l GPM had occurred during Mode 5 before entering Mode 4.

CAUSAL _ FACTORS i

The root cause of this event was inadequate technical review of a change I

l made to the RCS mass balance equation in Attachment 10.4 of Revision 8 to

.l OP-903-024.

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Si;QUENTIAL hEV1LON ygg NUMBER NUMBER Waterford Steam Electric Station 05000 382 04 & 04 unit 3 94

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, E a w n. n...u.n.a.... m -., n m xm o n IMMEDIATE CORRECTIVE MEASURES Immediate corrective action for this event was to make a temporary approved change to Attachment 10.4 of OP-903-024 correcting the mass balance equation.

ACIIONS TO PREVENT RECURRENCE Given that Waterford 3 believes that this was an isolated case, action to prevent recurrence will be to have Operations personnel review this event.

1 This will be completed by June 15, 1994.

l

SAFETY SIGNIFICANCE

This event did not compromise the health and safety of the public because RCS components and support systems designed to accommodate RCS leakage were not burdened during the time frame that the leakage could have occurred.

Also, when the surveillances were conducted upon exiting Refuel 5 during Modes 1 through 4, which were based on correct calculations in Attachment 10.1 of OP-903-024, RCS unidentified leakage was within LCO limits.

The l

incorrect methodology in Attachment 10.4 of Revision 8 to OP-903-024 was l

used only once to determine RCS leak rate, which was on November 3, 1992 j

involving this event.

SIMILAR EVENTS

None I

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