W3P84-2962, Interim Rept of Significant Const Deficiency 80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply Shutoff Valves.Motor Operators Installed. Retesting of Valves Planned.Next Rept by Dec

Interim Rept of Significant Const Deficiency 80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply Shutoff Valves.Motor Operators Installed. Retesting of Valves Planned.Next Rept by Dec

ML20107M256
Person / Time
Site:	Waterford
Issue date:	10/31/1984
From:	Cook K LOUISIANA POWER & LIGHT CO.
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
80, W3P84-2962, NUDOCS 8411140085
Download: ML20107M256 (3)

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LOUIStANA 70174-800. . (504)386-.345 MIDDLE SOUTH '

UTluTIES SYSTEM October 31, 1984 W3P84-2962 Q-3-A35.07.80 3-A1.01.04 Mr. John T. Collins Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Sm 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 g g g RV/ 6 W

Dear Mr. Collins:

NOV - l 1984

Subject:

Waterford 3 SES ..

Docket No. 50-382 SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 80

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

Reference:

LP&L letter W3K84-2105 dated September 5, 1984 The referenced letter indicated that closure of the subject deficiency was contingent on completion of Post Core Hot Functional Testing. In accordance with the requirements of 10CFR50.55(e)(3). closed is an interim report on SCD-80 with the Justification for Inter Operation. A final report will be submitted upon the completion of response time testing during Post Core Hot Functionals which is currently planned for early December and prior to initial criticality.

Very truly yours, caJ del K.W. Cook Nuclear Support & Licensing Manager KWC.GEW:sms cc: NRC, Director, Office of I&E NRC, Director, Office of Management E.L. Blake W.M. Stavenson W.A. Cross INP0 Records Centet- (D.L. Gillispie)

G.W. Knighton, NRC-NRR -

8411140085 841031 M27

{DRADOCK 05000382 i PDR ' \

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. INTERIM REPORT W3P84-2962 L 0F OfGNIFICANT CONSTRUCTION DEFICIENCY NO. 80

" UNSATISFACTORY STROKING OF EFW PUMP TURBINE STEAM SHUT OFF VALVES" 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 knowladge this deficiency has not been reported to the USNRC pursuant to 10CFR21.

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 (mooth and excessive force was needed to open the valves. The vendor representative was called in to look into tha 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. ,

SAFETY IMPLICATIONS 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 abova valves to open could adversely affect the safe shutdown of the plant if left uncorrected.

CORRECTIVE ACTION TAKEN NCR W3-6115 was initiated to track and document ,this deficiency. Anchor-Darling, the supplier of the above valves, concluded their site evaluation on these valves and submitted a report on April 29, 1983. In summary, the vendor stated that it was his opinion that the existing valves and operators would function properly .

and were adequate for their intended service.

However, reworking the valves (i.e. Replace springs, lapping of seat surfaces etc.)

3 per the vendors recommendation proved to be unsatisfactory during hot functional testing.

It had been previously determined by Ebasco Engineering that; if, after re-testing, per the vendor's recomnendation, the valve's operation was still deemed unsatis-factory, an alternate solution, such as changing from pneumatic to motor operators, would be implemented for Correct'.ve Action.

e 1,

. SCI-80 .

. W3P84-2962

• _Pcg3 2 A test on a prototype valve was conducted during September 1983, at Crosby Valve test facility to assure its operability under simulated operating conditions. The test was conducted as outlined in " Emergency Feedwater Pump Turbine Steam Isolation Valves Test Outline", Rev. 2 dated July 30, 1983. This~ test was conducted in two steps.

First using a pneumatic operated valve assembly and then using a motor operated valve assembly. The results of the test showed that the valve operation using the

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pneumatic operator was not satisfactory. However, with the motor operator, the valve operation was satisfactory and consistent. DCN MP-853 was issued on 10/10/83 to install .

motor operators instead of air operators on these valves. These motor operators are DC powered to ensure operability under complete loss of AC power conditions. The FSAR has been approp.riately revised in the Amendment 34.

JUSTIFICATION FOR INTERIM OPERATION The remaining corrective actions require response time testing of valves 2MS-V611A and 2MS-V611B during post core hot functionals when steam is available to operate EFW pump A/B. This retesting will include operation of the valves under differential pressure at temperature and cold quick starcing of the pump to retest the governor control system.

Waterford 3 Draft Technical Specification 3.7.1.2 requires at least three independent steam generator emergency feedwater pumps and associated flow paths be "0PERABLE" in

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Modes 1, 2 and 3 with (a) two feedwater pumps, each capable' of being powered from reparate "0PERA3LE" emergency buses, and (b) one feedwater pump capable of being powered from an "0PERABLE" steam supply system.

Surveillance Requirements 4.7.1.2.a and c s~ tate that the provisions of Specification 4.0.4 are not applicable for entry into Mode 3 for the turbine driven pump, thus allowing for operability testing of the turbine driven pump after entering Mode 3.

. r If the operability of the turbine driven emergency feedwater pump cannot be demonstrated during post core hot functional retesting, LCO Adtion Statement 3.7.1.2.a will be compiled with.

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