ML20029D994

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LER 94-006-00: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.W/940511 Ltr
ML20029D994
Person / Time
Site: Waterford Entergy icon.png
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)


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Operations - u ma le ' . 6;3tPO D. F. Packer G.' r,.vce rA, mor nan, m..a ox G'.if e t f' WL13 W3F1-94-0058 A4.05 PR fiay 11, 1994 U.S. Nuc1 ear Regulatcry Commission Attn: 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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D.F. Packer General flanager Plant Operations DFP/RWP/ssf Attachment cc: 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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uError (nRCSMassBalanceEquation EVEtJT DATE (5) LER NUMBER (6' REPORT NUMBER (7) OTHER FACILITIES itJVOLVED (8) atiA , mon f AM ( NAW M I NUMut,H

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11 03 92 L 94 006 00 05 11 94 t1/A 05000 OPERATING THIS REPORT IS SUBMITTED PURSUAtJT TO THE REQUIREMEtJTS OF 10 CFR 1: (Check one or more) (11)

MODE (9) 5 20 402(b) 20 405(c, so.73(a)(2)0v) 73.73 (n)

POWER 20 405(aH1)W 50.36(cH 1) 50 73(a)(2)(v) 73 71(c)

LEVEL (10) 0 20 405faH1Hid X 50 30(::H2) So.73(a)(2)lvu) OTHER 20 405(aHI)0n) X 50 73(aH2'(0l 50.73(a)(2Hviii)(A) W/

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LICENSEE COf1 TACT FOR THIS LER (12) m vs - tuu m Nuve rw4,..cm D.W. Vinci,_0perations Superintendent (504) 464-3178 COMPLETE ONE ilNE FOR EACH COMPONEfJT FAILURE DESCRIBED IN THIS RLPORT (13) cemt m ri u m uacNtNr uANor scTuna E R E

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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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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMS NO. 3150-0104 m et EXPJRES 5/31/95 .

ESilMATED BURDEN PE R RESPON1E TO COMU WTH TH:$

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TEXT CONTINUATlON $$j'aSO8e$'*$$'"'w%10*%"*ccS'l34$"UETe" u a10 THE PAPERWORa( REDUCTCN PRCAJECT Q150 0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 29603 F ACILITV N AME p) DOCH ET NUMBLR (2) LER NUMBE R H) PAGE (3)

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NUMBER Waterford Steam Electric Station 05000 382 ~ ~

02cF 04 Unit 3 94 006 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 l

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 l Major Equipment Out of Service l'

Specific to this Event lione l l

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MC FORM 3M4 it 92)

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b NHC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROYED BY OMB HO. 3150-0104 li p sr, . EXPIRc3 2,/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY MTH Tws INFORMAT'CN COLLECTON REQUEST, 50 0 HRS. F054WA40 LICENSEE EVENT REPORT (LER) COuuE.c. REauoNG suROEN cSTiuAfs TO TmE i-Oavnou

'AN REC A S MANA EMENT BRANCH (uNes nuh U B NMAR TEXT CONTINUATION PEGULATORY COMM'S$ ON. W ASHINGTON. DC 20555 0001, AND TO THE PAPERWomet NEDUCTCN PROJECT (31500104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20SC1 l P ACit KY NAMF 0) DOCRET NUMBf A (2) LIR NUMBEM (4) PAGE (3)

LEQUE NT AL RE asioN NUMBER NUMBER i Waterford Steam Electric Station 05000 382 -

03 OF 04 '

Unit 3 94 - 006 00 i

'iimm ,,., , ,, ..,,,,.w. m ,6., o ww,m> v n EVENT SEQUENCE On April 11, 1994, during Refuel 6 while attempting to use Attachment 10.4 l 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 Ta vg is <540*F, used in l 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 rcs. The investigation determined that this equation was revised by l

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 1 compliance review check be conducted of previous RCS leak rate calculations {

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

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

.l OP-903-024. l

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TiFi6)ORM M6A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 315(H)104 c5 ea . EXPIRES 5/31/95 ESTMATED BURDEN PER RESPONSE To COMPLY WTH TH1$

INFOFWATON COLLECTION REQUEST. 50 0 HRS. FORWARD LICENSEE EVENT REPORT (LER) CouuevTs REauoNo BURotN EsTuaTE To THE woRMATcN AND RECORD 3 MANAGEMENT ORANCH (MNB8 771dL U S. NUCLEAR TEXT CONTINUATION Recut 4Tosu CoMutssroN. wAsMiNoToN, oc resss-ooo1 ANa To THE PAPERW1DR< REDUCTON PROJECT (31504104, # OFFICE 08 MANAGEMENT AND BUDGET. WASHINGTON DC 20503.

7 ACILITY N A ME p ) I DOCF ET NUMBER (2) LE.*l NUMBE R l8) P AGE 13)

Si;QUENTIAL hEV1LON ygg NUMBER NUMBER Waterford Steam Electric Station 05000 382 ~ -

04 & 04 006 00 u unit 3 94

, 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 )

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