GO2-86-943, Forwards Info in Response to IE Bulletin 85-003, Motor- Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Items a-e,per Util 860528 & BWR Owners Group s

Forwards Info in Response to IE Bulletin 85-003, Motor- Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Items a-e,per Util 860528 & BWR Owners Group s

ML20211C202
Person / Time
Site:	Columbia
Issue date:	10/01/1986
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
GO2-86-943, IEB-85-003, IEB-85-3, NUDOCS 8610210296
Download: ML20211C202 (8)

Text

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Washington Public Power Supply System . g.,,

3000 George Washington Way P.O. Box 968 Richland, Washington 993524968 (50bf372-5q00 NII?:,

October 1,1986 ?gc,.

Docket No. 50-397 G02-86-943 M %y Mr. J. B. Martin, Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596

Subject:

NUCLEAR PLANT NO. 2 RESPONSE TO IEB 85-03

Reference:

1) IEB 85-03 " Motor Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings", dated November 5,1985

2) Letter, G02-86-503, G.C. Sorensen (SS) to J.B. Martin (NRC), same subject, dated May 28, 1986

3) Letter BWR0G-8645, T.S. Pickens (BWR0G) to J.M. Taylor (NRC I&E), Boiling Water Reactor Owner's Group Report NEDC-31322 "BVR Owner's Group Report on the Operational Design Basis of Selected Safety-Related Motor-0perated Valves", dated Septebmer 2,1986 however The due toReference the subject 1) IE Bulletin matter the BWRrequested Owner's Groupresponse (BWROG by May)14,1986, requested and obtained deferral of the response in order to perform a generic review of the issue. Reference 2) notified your staff that the Supply System would participate with the BWROG in addressing the bulletin and would provide further submittals upon completion of the BWROG report tenta-tively scheduled for September 1986. Accordingly, with issuance of Reference 3), the BWROG report the Supply System hereby provides the attached information satisfying items a through e of the subject bulletin.

Should you have any further questions, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.

Very truly yours, C avn G. C. Sorensen, Manager Regulatory Programs 8610210296 861001 PDR ADOCK 05000397 PLP/bk G Attachment PDR cc: J0 Bradfute - NRC l NS Reynolds - BLCP&R  !

E Revell - BPA l Document Control Desk NRC Site Inspector I 1 \

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NUCLEAR PLANT N0. 2 RESPONSE TO IEB 85-03

a. Review and document the design basis....

This task was completed by Reference 3) and documented by Report NEDC-31322, "BWR Owner's Group Report on Operational Design Basis of Selected Safety-Related Motor-Operated Valves." This report was reviewed by the Supply System and -the WNP-2 plant specific values are delineated on the enclosure. (This task is considered com-plete). It should be noted that even though portions of the WNP-2 RCIC system are no longer considered safety-related, the system is still included in this response for infc,rmation purposes. The overall RCIC system, except for the isolation valves, is not safety related.

b. Using the results frcm item a. above, establish the correct switch settings....

Presently, torque switches at WNP-2 are set between the minimum and maximum specified by the valve manufacturer. Valve-operator inspec-tions were conducted during the first refueling outage (April-May 1986) in response to concerns raised by various valve related IE Bulletins including 85-03 and 86-03. These switch settings are tabulated in the enclosure. At WNP-2, safety related valves which have to open, have the open torque switch jumpered (hard-wired) and the opening circuit provided with' a series limit switch to stop travel at 100% open. For valves that have to close, the torque switch is bypassed by a geared limit switch which remains closed throughout most of the valve's stroke (98%) and opens just before the valve reaches the fully closed (seated) position. Furthermore, WNP-2 is in the process of obtaining a motor-operated valve (M0V) diagnostic / test equipment program for integration into the WNP-2 plant maintenance program. Technical direction for incorporation of this program, maintenance procedure changes and data gathering will be accomplished accordingly.

c. Individual valve settings shall be changed, as appropriate, to tlose established in itan b. above. Whether the valve setting is changed or not, the valve will be denonstrated to be operable.. ..

The valves listed on the Valve Data Summary are periodically checked for proper operation by Surveillance Procedures 7.4.5.1.11, HPCS System Operability Test, and 7.4.3.3, RCIC Operability Test. The main purpose of the valve cycling is to record the opening and closing times. The calculated opening and closing differential pressures along with the approximate differential pressures to which these valves are subjected during surveillance testing, are listed on the enclosure, Valve Data Summary. Since the valve differential pressures encountered during surveillance testing do not approach the calculated values, it is the Supply System's intent to utilize the diagnostic / test equipment program for deter-mining and verifying the valve thrust requirements at the differen-tial pressures listed in the enclosure.

d. Prepare or revise procedures....

Maintenance PPM 10.25.4, Testing Motor Operated Valve Motors and Controls, and PPM 10.25.74, Adjustment of Geared Limit Switches in Motor Operated Valves, will be revised by Plant Maintenance to In-clude the diagnostic equipment and procedures once this information.

has been obtained.

e. Within 180 days of the date of this bulletin, subnit a written report to the NRC that: (1) reports the results of item a and (2) contains the program to accmplish itens b. through d. above including a schedule for ocmpletion of these items.

The following schedule is provided:

December 1986 Finalize procurement of the M0V diagnostic /

test equipment system.

March 1987 Revise Maintenance Procedures, as required to include the diagnostic / test equipment.

April 1987 Train Personnel in the use of the M0V' diagnostic /

test equipment.

April-May 1987 Gather valve baseline, signature data on safety related valves during WNP-2's second refueling outage.

October 1987 Final closecut of open items from IE Bulletin

, 85-03.

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STATE OF WASHINGTON )

Subject:

IEB 85-03

)

County of Benton )

I, G. C. SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.

DATE /d ~ / ,1986

'ZCW

/ G. C. Sorphsen, Manager Regulatory Programs On this day personally appeared before me G. C. Sorensen to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned.

GIVEN under my hand and seal this / dayof()(/shX ,1986 y

fiA n 0

. (/tmed Notary Public in and for the State of Washington Residing at ownow w h)4

i /

Page 4 ENCLOSURE VALVE DATA

SUMMARY

NOTES

1. Valve designations as they appear in Report No: NEDC-31322, BWR Owner's Group Report on the Operational Design Basis of Selected Safety-Related Motor Operated Valves, dated September 1986.

2. Note Deleted

3. Opening torque switch is jumpered throughout travel. Closing torque switch is bypassed by Limit Switch No. 7* until the valve is approximately 95%-99% closed.

4. Opening torque switch is jumpered throughout travel . Closing torque switch is bypassed by Limit Switch No.16* until valve is approximately

95%-99% closed.

5. Opening torque switch is jumpered throughout travel . Closing torque switch is bypassed by Limit Switch No.1* until the valve is approximately 5% closed.

6. Opening torque switch is bypassed by Limit Switch No. 5* until the valve is approximately 5% open. Closing torque switch is bypassed by Limit Switch No. 7* until the valve is approximately 95%-99% closed.

7. Opening torque switch is bypassed by Limit Switch No. 5* until the valve is approximately 5% open. Closing torque switch is bypassed by Limit Switch No. '16* until the valve is approximately 95%-99% closed.

• Switch designation per Limitorque Standard Valve Operator Wiring Diagram.

8. Valve capable of 2160 PSID actually supplied by the valve vendor.

9. Turbine Trip and Throttle Valve not included in the analysis because the valve does not have a safety function and is spring-loaded to close.

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P' ENCLOSURE VALVE DATA SifMARY Page 1 NROG Diff Press Diff Press Torque SW .

Destgn Spec Test V:1ve No WNP-2 Valve Oper Opening Closing Settings Limit SW Pressure Pressure (Note 1) Valve No. Size / Type Manfacturer Model Valve Description ( PSID) (PSID) Open/Close Setting (PSID) (PSIG) 3 HPCS-V-1 14*/ GATE Anchor Darling SMB-000-25 HPCS-P-1 Suction --

15.0 1.5/1.5 (Note 3) 150 <15 Supply from Condensate Storage Tank (CST)-

1 HPCS-V-4 12"/ GATE Anchor Darling SMB-4-200 HPCS-P-1 Discharge 1450.0 1500.0 1.25/1.0 (Note 3) 1500 <200 to Reactor Vessel 5 HPCS-V-10 10*/ GLOBE Anchor Darling SMB-3-150 Test bypass from -

1468.0 1.5/1.0 (Note 6) 1500 >200 HPCS-P-1 to *

. (Note 8)

Condensate Storage Tank 6 HPCS-V-11 10*/ GLOBE Anchor Darling SMB-3-150 Test bypass from -

1468.0 1.5/1.0 (Note 6) 1500 >200 HPCS-P-1 to CST (Note 8) 2 HPCS-V-12 4*/ GATE Anchor Darling SB-0-25 HPCS-P-1 mininum 1500.0 1540.0 1.5/1.5 (Note 3) 1500 <200 flow valve 4 HPCS-V-15 18"/ GATE Anchor Darifng SMB-2-60 HPCS-P-1 Suction 50.0 50.0 1.75/1.75 (Note 3) 150 <10 Supply from Suppression Pool 7 HPCS-V-23 12"/ GLOBE Anchor Darling SMB-4-150 Test bypass from --

1485.0 4.0/2.75 (Note 6) 1500 > 200 HPCS-P-1 to (Note 8)

Suppression Pool

ENCLOSURE VALVE DATA SISetARY Page 2 INROG Diff Press Diff Press Torque SW Design Spec Test Valve No WNP-2 Valve Oper Opening Closing Settings Limit SW Pressure Pressure (Note 1) Valve No. Size / Type Manfacturer Model Valve Description ( PSID) (PSID) Open/Close Setting ( PSID) ( PSIG)

III RCIC-V-8 4*/ GATE Borg-Warner SMB-00-7.5 Outboard Contain- 1150.0 1150.0 1.0/1.0 (Note 4) 1337 0 ment Isolation on Steam Supply to RCIC turbine 3 RCIC-V-10 8"/ GATE Velan SMB-00-15 RCIC Pump Suction --

63.5 1.0/1.0 (Note 4) 125 < 20 Supply from Con- '

densate Storage Tank (CST) 1 RCIC-Y-13 6*/ GATE Velan SMB-0-40 RCIC Pump Discharge 1325.0 1325.0 2.5/2.5 '(Note 4)# 1350 0 to Reactor Vessel 2 RCIC-V-19 2"/ GLOBE Borg-Warner SMB-00-10 RCIC-P-1 Minimum 1325.0 1325.0 2.0/2.0 (Note 4) 1500 >1020-Flow Valve 5 RCIC-V-22 6*/ GLOBE Anchor Darling 588-2-60 Test bypass from 1325.0 1325.0 1.5/1.5 (Note 4) 1325 >1020 RCIC Pump (Note 8)

(RCIC-P-1) to CST 4 RCIC-V-31 8"/ GATE Borg-Warner SMB-00-15 Pump RCIC-P-1 51.5 51.5 1.5/1.5 (Note 4) 125 < 10 Suction Supply from Suppression Pool .

I RCIC-V-45 4*/ GLOBE Anchor Darling SMB-0-15 RCIC Turbine Steam 1150.0 1150.0 4.25/4.25 (Note 5) 920-1020 920-1020 Supply Admission Yalve 9 RCIC-Y-46 2"/ GLOBE Borg-Warner SMB-000- 5 RCIC lube oil 1325.0 1325.0 1.0/1.75 (Note 5) 1500 > 1020 cooler-cooling water supply valve 6 RCIC-V-59 6*/ GATE Velan SMB-0-40 Test bypass from 1325.0 1325.0 2.0/2.0 (Note 7) 1300. O RCIC-P-1 to CST

/

ENCLOSURE i VALVE DATA StBMARY - ,

Page 3 BIROG Diff Press Diff Press Torque SW Destgn Spec Test Valve No WNP-2 Valve Oper Opening Closing Settings Limit SW Pressure Pressure i (Note 1) Valve No. Size / Type Manfacturer Model Valve Description (PSID) (PSID) Open/Close Setting (PSID) (PSIG)

II RCIC-V-63 10*/ GATE Velan SMB-2-60 Inboard Containment 1150.0 1150.0 1.5/2.0 (Note 4) 1377 0 Isolation on Steam Supply to RCIC Turbine VI RCIC-V-68 10"/ GATE Velan SMB-0-15 RCIC Turbine 28.0 43.0 1.5/2.0 (Note 4) 45 0 Exhaust to Suppression Pool 7 RCIC-V-69 1-1/2"/ GATE Borg-Warner SMB-000-5 RCIC Vacuum Pump - 45.0 3.0/2.0 (Note 4) - 0 RCIC-P-2 Discharge -

to Suppression Pool IV RCIC-Y-76 1*/ GLOBE Borg-Warner SMB-000-5 RCIC Turbine Steam 1150.0 1150.0 3.0/3.0 (Note 4) 1250 920-1020 Supply Line '

Warm-up Valve X RCIC-V-1 3"/ GATE Schutte-Koerting SMB-000-5 RCIC-Turbine Steam (Note 9) (Note 9) 1.0/3.0 (Note 5) 1250 0 Trip-Throttle

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