W3P85-0337, Final Significant Const Deficiency Rept SCD-80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply shut-off Valves.Pneumatic Operators for Valves 2MS-V611A & V612 Replaced w/D-C Motors

Final Significant Const Deficiency Rept SCD-80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply shut-off Valves.Pneumatic Operators for Valves 2MS-V611A & V612 Replaced w/D-C Motors

ML20107N110
Person / Time
Site:	Waterford
Issue date:	02/22/1985
From:	Cook K LOUISIANA POWER & LIGHT CO.
To:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
SCD-80, W3P85-0337, W3P85-337, NUDOCS 8503060229
Download: ML20107N110 (2)

Text

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POWER & LIGHT / NEW ORLEANS LOUSLANA 70174-8008 . (504)308-234S MIDDLE SOUTH UDUDES SYSTEM February 22, 1985 W3P85-0337 Q-3-A35.07.80 3-A1.01.04 A4.05 Mr. Robert D. Martin Regional Administrator, Region IV U.S. Nuclear Regulatory Commission

$h$h@h 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 f

! FEB 2 51985

Dear Mr. Martin:

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Subject:

Waterford 3 SES Docket No. 50-382 SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 80

" Unsatisfactory Stroking of EFW Pump Turbine Steam Supply Shut-off Valves" Final Report

Reference:

LP&L letter W3K84-2962 dated October 31, 1984 The referenced letter provided an interim report on SCD-80 with the Justification for Interim Operation. It stated that the final report would be submitted upon the completion of response time testing.

In accordance with the requirements of 10CFR50.55(e)(3), enclosed are two copies of the Final Report of SCD-80.

Very truly yours,

/

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K.W. Cook Nuclear Support & Licensing Manager KWC:GEW:sms cc: NRC, Director, Office of I&E G.W. Knighton, NRC-NRR D.M. Crutchfield, NRC-NRR NRC Pssident Inspectors Office INPO Records Center (D.L. Gillispie)

E.L. Blake gg W.M. Stevenson 8503060229 850222 PDR S

ADOCK 05000382 PDR M-Dm#

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W3P85-0337 3

FINAL REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 80

" UNSATISFACTORY STROKING OF EFW PUMP TURBINE STEAM

, ,4 SHUT OFF VALVES" t

INTRODUCTION T'his report is . submitted pursuant to 10CFR 50.55(e). This report describes a deficiency in the automatic operation of valves 2MS-V611A and 2MS-V612B in the Main Steam System. This problem is considered reportable under the requirements of 10CFR50.55(e).-

To th'e.best of our knowledge this deficiency,hassnot been reported to the USNRC pursuant to 10CFR21.

- IiESCRIPTION During hot functional testing, automatic operation of valves 2MS-V611A and 2MS-V612B - were found to be unsatisfactory. Stroking of the valves was not

-smooth, and excessive force was needed to open the ; valves. The vendor representative was called in to look into the problem.- With new springs and proper lubrication to overcome the friction, the valves were stroked several times before completion of the hot functional testing, h'owever. the stroking was still deemed unsatisfactory due to the hesitation experienced in opening of the'

(. valves..

\[s SAFETY IMPLICATIONS

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These valves are located in the steam supply line to the emergency feedwater pump turbine. This steam supply is a diverse power source used to ensure that the Emergency Feedwater System (EFS) is capable of performing its function with complete loss of AC power. The function of the EFS is to ensure a sufficient supply _ of cooling ' water to the steam generators following a main steam or

- feedwater line break' or loss of normal feedwater to provide cooldown of the Reactor Coolant System to the temperature and pressure at which the Shutdown Cooling System can be placed into operation. Therefore, failure of the above valves to open would adversely affect the safe shutdown of the plant if left uncorrected. A4 t

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CORRECTIVE ACTION' 'r The pneumatic operators for the valves 2MS-V611A and 2MS-V612B have been replaced . with D-C motors. . The valves have been t'sted during cold conditions and hot. functional testing and in all instances o g rated satisfactory. Dur'.ng hot functional testing the valves opened in 8.01 and 9.23 seconds, respectively.

These valves are required to fully open within 25 seconds in order to support the minimum Emergency Feedwater Control "lo-lo" setpoint analyses. 4 Problems which occur during routine eighteen month surveillance tests will be s handled ini .accordance with administrative procedures and technical specifications.

SCD 80/PVG.y- y T

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