ML20134B624

Event Tracking & Follow Up Assignment Sheet of 950802 Event Re Ue Declaration Resulting from Two Stages of Reactor Rc Pump Seal Failures w/2 Gpm Identified Leakage

ML20134B624
Person / Time
Site:	Saint Lucie
Issue date:	08/09/1995
From:	Thomas Koshy NRC
To:
Shared Package
ML20134B255	List: L-93-112, Forwards Safeguards Event Log Entries for Jan-Mar 1993.Encl Withheld (Ref 10CFR73.21) L-93-181, Forwards Safeguards Event Log Entries for Period of Apr-June 1993.Entries Withheld (Ref 10CFR73.21) L-93-265, Forwards Safeguards Event Log Entries for Period Jul-Sept 1993.Log Withheld L-94-095, Forwards Safeguards Event Log Entries for Period Jan-Mar 1994.Log Entries Withheld,Per 10CFR73.21 L-94-186, Forwards Safeguards Event Log Entries for Period Apr-June 1994.Encl Withheld L-94-269, Forwards Safeguards Event Log Entries for Period Jul-Sept 1994.Encl Does Not Contain Safeguards Info Per 10CFR73.21 L-95-121, Forwards Safeguards Event Log Entries for Period of Jan-Mar 1995,per 10CFR73.71(c)(2) L-96-296, LER 96-S02-00:on 961011,failed to Terminate Access of Temporary Licensee Employee.Caused by Cognitive Personnel Error.Security Unassigned Card Key & Plant Administrative Procedure 0010509 Revised ML20134B253 ML20134B260 ML20134B469 ML20134B502 ML20134B509 ML20134B516 ML20134B520 ML20134B535 ML20134B538 ML20134B541 ML20134B549 ML20134B561 ML20134B566 ML20134B624 ML20134B629 ML20134B742 ML20134B796 ML20134B826 ML20134E919 ML20134H152 ML20134K088
References
FOIA-96-485 29153, NUDOCS 9508300278
Download: ML20134B624 (3)

Text

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CEAB EVENT TRACKING SHEET EWE r >= 29153 & Event Ntaber <= 29153 l

l Plant! SAINT LUCIE Unit: Engineer: KOSHY T.

l l EvCnt: 08/02/95 Morning Report: Briefing:

50.72# 29153 LER#: 050000009500000 PN#:

1 Othcr Notification:

System: Component:

OPERATING NODE SIGNIFICANCE

- Operation A - Reactor Protection System 2 Startup B - Safety-Related Cooling System Hot Stan@y C - fuel Cladding 4 - Hot Shutdown @-ReactorCoolantPressureBoundary 5 Cold Shutdown E Containment 6 - Refueling F - Plant Power 7 - Other G Unexpected Plant Performance H - Other:

CAUSE EVENT E 25 h Equipment Failure $1G - Significant Event 2 Design or Installation Error EDI - Event of Interest 3 - Operating Error TBD - To Be Determined 4 - Maintenance Error 5 External h other 6 - Other POTENTIAL AO: Criterion:

Preptsed By: roswy T.

Engineer -

3h Apprcved: f # 5 Section Leader A. Chaffee Branch Chief {

EVENTS ASSESSMENT PANEL First Screening:

/(s16 significance

Description:

UE declaration resulting from two stages of Reactor coolant ptmp seat feitures with 2gpm identified leakage.

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Page:1 08/09/95 ETS 02 F~' ' t B!!B COPY A

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EVENT FOLLOW-UP ASSIGNMENT SMEET I

PSE - _ YES _x NO l I  !

ASSIGNMENT DATE: 8-2-95 l ASSIGNED T0: T Koshy 4 PLANT & UNIT: Saint Lucie l 2

EVENT DATE: 8-2-95 l 50.72 REPORT NO: 29153 i MR NO: .

OTHER REPORT: l SPECIALTY CODE:

EVENT

SUMMARY

1 UE declaration resulting from two stages of Reactor coolant pump seal failures 4 with 2gpm identified leaktge.

l SPECIFIC F0LLOW-UP ASSIGNMENT

]

DETERMINE DETAILS, EVALUATE SAFETY SIGNIFICANCE AND GENERIC IMPLICATIONS. IN j ADDITION, ADDRESS THE FOLLOWING SPECIFIC CONCERNS:

e ASSIGNMENT OPTIONS

• IDENTIFY DISCREPANCIES FROM INITIAL EVENT INFORMATION: _ YES _ N0 _ N/A

• PERFORM RISK ASSESSMENT: _ YES _ NO _ N/A i

ESTIMATE CONDITIONAL CORE DAMAGE PROBABILITY: _ YES _ NO _ N/A

• COMPARE WITH PREVIOUS SIMILAR EVENTS: _ YES _ N0 _ N/A PREVIOUS SIMILAR EVENTS:

• RELATE TO ENFORCEMENT ACTIONS: _ YES _ NO _ N/A j 1

• RELATE TO USI GSI (NUREG-0933): _ YES _ NO _ N/A RELEVANT USI GSI:

PREPARE TO BRIEF: _ YES _ NO

• TARGET CLOSE00T SCHEDULE:

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• INITIAL SCREENING PANEL '

EVENT / CONDITION SAFETY SIGNIFICANCE: _ OTH _ E0I _ SIG _ A0 i

• REMAINING OR ADDITIONAL FOLLOW-UP ITEMS:

1 l

• FINAL PANEL ASSESSMENT EVENT / CONDITION SAFETY SIGNIFICANCE: _ OTH _ E01 _ SIG _ A0 i

• BASIS: _ RISK _ PROGRAMMATIC _ MARGIN _ N/A

• GENERIC FOLLOW-UP ACTION RECOMMENDED: _ YES _ N0 _ PRIORITY (1,2,3,4)'

_ IN _ BUL _ GL CLOSE0VT During the plant restart following the hurricane warning, the operator noticed the first stage seal failure. The licensee attempted to " restage the seal" using a previously successful method. The process involved transfering the full pressure to stage two and relieving pressure in stage 3.

The attempt was not successful this time and it is believed to have caused the second stage of RCP seal failure. Such " restaging seal" was not attempted when the plant conditions were 370F and 530 psi. The higher temperature and pressure could be the cause for the second stage seal failure. The licensee plans to perform further failure analysis.

The station black out analysis assumes 25gpm. The failures were within the analyzed bases. No further follow up is required. Classified as other.

FILE: G:\T Wr 4 %'r s s c_

BRIEF #

GENERIC RESPONSE: IN # BUL # GL #

1. Priority endnote:

PRIORITY 1: Innediate assignment of resources (e.g., for highly risk-significant saf ety concerns)

PRIORITY 2: Wear -term action (e.g., significant safety issues not warranting inmediate action)

PRIORITY 3: Long-term action (e.g., issues of moderate to low safety significance)

PRIORITY 4: Resource dependent action (e.g., items that can be deferred)

_ _ _,