ML20071J771

Interim Significant Deficiency Rept 80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Shutoff Valves.Initially Reported on 830420.Vendor Rept Submitted on 830429 & Springs Replaced.Next Rept by 830729

ML20071J771
Person / Time
Site:	Waterford
Issue date:	05/20/1983
From:	Drummond F LOUISIANA POWER & LIGHT CO.
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, 80, SCD-80, W3I83-0178, W3I83-178, NUDOCS 8305270138
Download: ML20071J771 (2)

Text

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.o 142 OELARONDE STREET POWER & LIGHT P O BOX 6008 . NEW ORLEANS. LOUISIANA 70174 . (504) 366-2345

{$PuSN sysSEN May 20, 1983 W3I83-0178 Q-3-A35.07.80 Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission ' '

l 611 Ryan Plaza Drive, Suite 1000 j,)) $- j Arlington, Texas 76012 [I M 2 A mes

SUBJECT:

Waterford SES Unit No. 3 JU Docket No. 50-382 d gM%,u I

Significant Construction Deficiency No. 80

" Unsatisfactory Stroking of EFW Pump Turbine Steam Shut Off Valves" First Interim Report

REFERENCE:

Telecon dated April 20, 1983 to W. A. Crossman from M. A. Livesay

Dear Mr. Collins:

In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Interim Report of Significant Construction Deficiency No. 80,

" Unsatisfactory Stroking of EFW Pump Turbine Steam Shut Off Valves". This item was previously identified as PRD 113.

If you have any questions, please advise.

Very truly yours,

- '?

mm F. J. Drummond Project Support Manager - Nuclear FJD/ MAL:keh Attachment cc: 1) Director 3) Mr. E. L. Blake Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555

2) Director 4) Mr. W. M. Stevenson Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 8305270138 830520 PDR ADOCK 05000382 S

.L E -]7 PDR

. ___-_ _ _ _ ____________ _ _ _______ - ____________ - A

INTERIM REPORT

-OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 80

- " UNSATISFACTORY STROKING OF EW PUMP TURBINE STEAM SHUT OFF VALVES" i

a INTRODUCTION ,

This report-is submitted pursuant to 10CFR50.55(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 the best of our knowledge this deficiency has not been reported to the USNRC pursuant to 10CFR21. j

]

DESCRIPTION During Hot Functional Testing, automatic operation of valves 2MS-611A 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, however, the stroking was still deemed unsatisfactory due to the hesitation experienced in opening of the valves.

I SAFETY IMPLICATIONS These valves are located in the steam supply line to the' emergency feedwater l

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 could adversely affect the safe shutdown of the plant if lef t uncorrected.

} CORRECTIVE ACTION TAKEN 3

i NCR W3-6115 has been initiated to track.and document'this deficiency.

t Anchor-Darling, the supplier of the above valves, concluded their site evaluation on these valves and submitted a report on April 29, 1983. In sunmary, the vendor states that it is his opinion that the existing valves and operators will function properly and are adequate for their intended 4

service. Some of the corrective action such as replacing the springs and lapping the seating surfaces to minimize binding, have been completed.

The evaluation of this condition is continuing and an update or final report will be submitted on or before July 29, 1983.

J 4

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