W3P86-0076, Responds to IE Bulletin 85-003,Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Setting. Switch Settings for Valve Opening & Closing Will Be Reviewed & Revised as Necessary

Responds to IE Bulletin 85-003,Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Setting. Switch Settings for Valve Opening & Closing Will Be Reviewed & Revised as Necessary

ML20197H328
Person / Time
Site:	Waterford
Issue date:	05/14/1986
From:	Cook K LOUISIANA POWER & LIGHT CO.
To:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
IEB-85-003, IEB-85-3, W3P86-0076, W3P86-76, NUDOCS 8605190138
Download: ML20197H328 (9)

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LOUISI ANA / 317BARONNESTREET P. C. BOX 60340 POWER & L1GHT NEW ORLEANS, LOUISIANA 70160 + (504) 595-3100 UlrTON s*vsY$

May 14, 1986 W3P86-0076 A4.05 QA Mr. Robert D. Martin Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

Subject:

Waterford SES Unit 3 Docket No. 50-382 IE Bulletin 85-03

Dear Mr. Martin:

Through IE Bulletin 85-03, " Motor-Operated Valve Common Mode Failures During Plant Transients Due To Improper Switch Settings", the NRC requested certain information for motor-operated valves (MOVs) in the high pressure safety injection (HPSI) and emergency feedwater (EFW) systems.

In accordance with Item (a) of the Bulletin, LP&L has reviewed the design basis for operation of each MOV in the HPSI and EFW systems of Waterford 3.

The review results are documented in Attachments 1 and 2.

Included in the documentation is the maximum differential pressure expected during opening and closing of the valves for both normal and abnormal events, to the extent that these valve operations and events are present in the existing, approved design basis for Waterford 3.

Using the results of Attachments 1 and 2, LP&L intends to do the following:

1.

Switch settings (e.g. torque, torque bypass, etc.) for valve opening and closing will be reviewed and revised, as necessary.

This activity will include a program to review the methods for selecting and setting the switches. During the course of this project, should it be determined that a valve is inoperable, LP&L will document appropriate justification for continued operation in accordance with the applicable technical specification.

2.

Individual val're settings will be changed, as appropriate, to those established in item 1, above. Each valve identified in

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Attachments 1 and 2 will be demonstrated to be operable either by, a.

testing the valve at the maximum differential pressure established in Attachments 1 and 2 (with the exception of testing a valve under simulated line break conditions), or 8605190138 860514 PDR ADOCK 05000382 e' @ 1 \\

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"AN EQUAL OPPORTUNITY EMPLOYER"

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R.D. Martin W3P86-0076 Page 2 b.

providing appropriate justification for cases where testing under maximum differential pressure is not practicable.

Each valve will be stroke tested, to the extent practical, to verify that the switch settings have been properly implemented.

3.

Procedures will be revised, or newly prepered as necessary, to ensure that correct switch settings are determined and maintained. Applicable industry recommendations will be considered.

Items 1-3 above will be completed by November 15, 1987.

It is anticipated that valve testing will be primarily conducted during the first refueling outage for Waterford 3, tentatively scheduled to begin in December, 1986.

A written report will be provided to the NRC discussing the items suggested in IE Bulletin 85-03 following completion of the program.

As requested in IE Bulletin 85-03, this transmittal is made under affidavit pursuant to Section 182a, Atomic Energy Act of 1954, as amended. Should you have any questions or comments on this matter please contact Mike Meisner at (504) 595-2832.

Yours very truly,

'o K.

Cook Nuclear Support & Licensing Manager KWC/MJM/ssf Attachments

?NREMSuinent Control Desk? Washington,;D;C; 2(origin 51$

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NRC, Dire'5tidr70ffice 'of II&E"~" ~~""' ""

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G.W. Knighton, NRC-NRR J.H. Wilson, NRC-NRR NRC Resident Inspectors Office B.W. Churchill W.M. Stevenson

W3P86-0076 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the matter of

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Louisiana Power & Light Company

) Docket No. 50-382

-t._ ford 3 Steam Electric Station

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AFFIDAVIT R.M. Nelson, being duly sworn, hereby deposes and says that he.is Licensing Manager of Louisiana Power & Light Company; that he is duly authorized to sign and act on behalf of K.W. Cook, Nuclear Support & Licensing Manager and file with the Nuclear Regulatory Commission the attached responses to IE Bulletin 85-03; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.

_C R. @ing Manager - Nuclear n

N Licens STATE OF LOUISIANA

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) ss PARISH OF ORLEANS

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Subscribed and sworn to before me, a Notary Public and for the Parish and State above named this

/J fA day of 1986.

P otary PubliE My Commission expires I

Attachmtnt 1 W3P86-0076 Sheet 1 of 3 Waterford Unit 3 Design Bases for Operation of HPSIS MOVs Postulated Postulated Valve Upstream Downstream Valve Function Tag. No Condition Condition Notes

- ' Manually open from SI-121B High: HPSI pump Low: RWSP @ atmos. - HPSIP mini flow Control-Room SI-120B shutoff head pressure recirculation SI-120A line isolation ST-121A valves Manually Close SI-121B High: HPSI Pump Low: RWSP @ atmos.

on RAS SI-120B shutoff head pressure SI-120A SI-121A

' Manually open from SI-506A High: HPSI pump Low: RCS at atmos. -

Hot Leg Injection Control Room SI-506B shutoff head pressure isolation valves SI-502A SI-502B Manually close SI-506A High:HPSI pump Low: RCS at atmos.

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Following Hot Leg SI-506B shutoff head pressure Injection SI-502A SI-502B Manually open from SI-219A High: HPSI pump Low: RCS at atmos. -

HPSI Train

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Control Room SI-219B shutoff head pressure Isolation Valves 4

Manually close SI-219A High: HPSI pump Low: RCS at atmos.

from Control Room SI-219B shutoff head pressure to divert fraction I

of HPSI flow to hot leg Open on SIAS SI-225B High: HPSI pump Low: RCS at atmos.

HPSI isolation SI-225A shutoff head pressure valves SI-226B SI-226A SI-227B SI-227A SI-228B SI-228A Manually close SI-225B High: HPSI pump Low: RCS at atmos.

from Control SI-225A shutoff head pressure Room following SI-226B Shutdown or due SI-226A to inadvertent SI-227B opening SI-227A SI-228B SI-228A 1

Attachm:nt 1 W3P86-0076 Sheet 2 of 3 Waterford Unit 3 High Pressure Safety Injection System Design Basis Maximum Differential Pressure Valve Design Basis Design Basis Function Valve ID ddiP Open (psi)

JOLP Close (psi)

HPSIP Mini Flow SI-121B 1502 1502 Recirculation Line SI-120B 1502 1502 Isolation HPSIP Mini Flow SI-120A 1502 1502 Recirculation SI-121A 1502 1502 Hot Leg Injection SI-506A 1502 1502 Isolation S1-506B 1502 1502 SI-502A 1502 1502 SI-502B 1502 1502 HPSI Train SI-219A 1499 1499 Isolation SI-219B 1498 1498 HPSI Isolation SI-2253 1502 1502 SI-225A 1502 1502 SI-226B 1502 1502 s

SI-226A 1502 1502 SI-227B 1502 1502 SI-227A 1502 1502 SI-228B 1502 1502 SI-228A 1502 1502

3.

U3P86-0076 Sheet 3 of 3 Waterfoni Unit 3 HPSIS Schematic SI-502A SI-506A To Hot Le9 SI-121B SI-1208 i

HPSIP Recirc.

SI-225B SI-121A SI-120A To Cold Leg SI-219A

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From Refueling Water Storage Tank SI-226B d ll-l To Cold Leg

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SI-226A SI-219B gg, From Cont.

Sump To Cold Leg 7

l SI-2278 HPSI Pumps SI-228A To Cold Leg SI-228B To Not Leg SI-502B SI-5068

l Attcchment 2 W3P86-0076-Sheet 1 of 3 Waterford Unit 3 Design Bases for Operation of EFWS MOVs 1

Postulated Postulated Valve Upstream Downstream Valve Function Tag. No Condition Condition Notes 1

Manually open MS401A High: main steam Low:~ atmos. press. -

EFWP Turbine and close from MS401B pressure Driver isolation

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coutrol room, valves Opens on EFAS 4

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Attachmznt 2 W3P86-0076 j

Sheet 2 of 3

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1 Waterford Unit 3 Emergency Feedwater System Design Basis Maximum Differential Pressure l

Valve Design Basis Design Basis Function Valve ID AL P Open (psi)

AkP Close (psi)

EFWP Turbine MS-401A 1135~

1135 Driver Isolation MS-401B 1135 1135 2

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