AECM-86-0291, Submits Final Responses to IE Bulletin 85-003, Motor- Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Response Consistent W/ NEDC-DRF-E12-00100-75, BWR Owners Group Rept on ..

Submits Final Responses to IE Bulletin 85-003, Motor- Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Response Consistent W/ NEDC-DRF-E12-00100-75, BWR Owners Group Rept on ..

ML20215J411
Person / Time
Site:	Grand Gulf
Issue date:	10/03/1986
From:	Kingsley O MISSISSIPPI POWER & LIGHT CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
AECM-86-0291, AECM-86-291, IEB-85-003, IEB-85-3, NUDOCS 8610240432
Download: ML20215J411 (11)

Text

e IV MISSISSIPPI POWER & LIGHT COMPANY

]

EullMiddiddE Helping Build Mississippi P. O. B O X 164 0, J A C K S O N, MIS SIS SIP PI 39215-1640 SB 007 7 A9: 50 O. D. KINGSLEY, JR.

VICE PREllDENT NUCLE AR OPERATION $

U. S. Nuclear Regulatory Commission Region II 101 Marietta St. , N. W. , Suite 2900 Atlanta, Georgia 30323 Attention: Dr. J. Nelson Grace, Regional Administrator

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/L-830.0 IE Bulletin 85-03, Motor Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings AECM-86/0291

Reference:

AECM-86/0135 AECM-86/0161 In the referenced letters, Mississippi Power and Light Company (MP&L) responded to IE Bulletin No. 85-03, " Motor Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings." Reference 1 provided an overview for the implementation of bulletin Items b through d while Reference 2 provided " rough estimate" maximum differential pressure values of the affected high pressure ECCS valves in response to Item a.

MP&L has participated in the BWR Owners' Group (BWR0G) project to develop the scope systems, range of events, and a set of assumptions to form a sound technical basis and uniform application for BWR plant response to the bulletin. The results of this project are contained in BWROG document NEDC-DRF-E12-00100-75 "BWR Owners' Group Report on the Operational Design Basis of Selected Safety-Related Motor-0perated Valves." MP&L has used guidelines set forth in this report to finalize its response to IE Bulletin 85-03. A summary of the IEB 85-03 items and the finalized MP&L responses are as follows:

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AECM-86/0291 Page 2 Item a) Review and document-the design basis for the operation of each valve.

Response: MP&L has completed its review of the design basis of all motor operated valves in the High Pressure Core Spray (HPCS)-and Reactor Core Isolation Cooling (RCIC) systems subject to testing for operational readiness in accordance with 10 CFR 50.55a(g).

This review is consistent.with the basis, assumptions, and findings of the BWROG report NEDC-31322. Based on this review, maximum differential pressure values were calculated and are provided in Attachment I in the format suggested by the bulletin.

Item b) Using the results from Item a above, establish correct switch settings. This shall include a program to review and revise, as necessary, the methods for selecting and setting all switches for each valve operation.

Response: The GGNS Preventive Maintenance (PM) program requires a verification of torque switch settings on a 3-year basis.

Currently, MP&L uses vendor-supplied torque switch settings.

The PM program ensures that the valve PM data sheets reflect the vendor-supplied settings. -MP&L will re-verify these torque switch settings based on the design basis peak differential pressures expected. The switch settings will be changed to proper values if the vendor specifications are found to be non-conservative. Accessible valves which require switch setting changes may be adjusted whenever practical as plant conditions permit; however, these adjustments will be completed prior to completion of the second refueling outage.

Inaccessible valves will be adjusted during the second refueling outage but prior to startup. The work scheduled for the second refueling outage will be accomplished on a basis not to affect the critical path. If problems arise with this work, the NRC will be notified.

Item c) Individual valve settings shall be changed, as appropriate, to those established in Item b, above. The valves will be demonstrated to be operable by testing at the maximum differential pressure determined in Item a above, with the exception that testing M0V's under conditions simulating a break in the line containing the valve is not required.

Otherwise, justification should be provided for any cases where testing with the maximum differential pressure cannot be performed.

Response: As stated in Item b above, switch settings found to be non-conservative will be changed to the proper value. Accessible valves which require switch setting changes may be adjusted whenever practical as plant conditions permit; however, these adjustments will be completed prior to completion of the second refueling outage. Inaccessible valves will be adjusted during the second refueling outage but prior to startup. The work J16AECM86100101 - 2

AECM-86/0291 Page 3

- scheduled for the second refueling outage will be accomplished on a basis not to affect the critical path. If problems arise with this work, the NRC will be notified. MP&L will test the associated valves using methods sufficient to demonstrate valve operability in order to meet the requirements of Item c. MP&L is currently planning to establish a separate valve testing program to ensure proper tracking and execution of Bulletin requirements. Actual differential pressure testing will be performed when practical while other testing methods will be used when actual differential pressure testing is not practical or could possibly damage equipment. Alternate methods are being evaluated by MP&L to determine which, if any, will best meet testing needs. The valves to be tested using actual differential pressures will be determined by evaluating the results from Item a and the plant conditions required to perform the testing. It is MP&L's intent to have HPCS and RCIC valve testing completed prior to startup following the second refueling outage. However, any valve testing being performed during the second refueling outage will not be considered a critical path item or a startup restraint.

The BWROG Report NEDC-31322 identifies several valves which have no active safety function during the FSAR design basis events based on the BWR design basis assumptions made in the report.

MP&L shall evaluate the need for testing these valves in order to meet the requirement of Item c and will provide adequate justification if these valves are not tested.

Item d) Prepare or revise procedures to ensure that correct switch settings are determined and maintained throughout the life of the plant. Ensure that applicable industry recommendations are considered.

Response: Procedures will be revised as necessary to incorporate any changes in accordance with the schedules discussed in items b and c above. The GGNS PM program currently includes vendor-recommended preventive maintenance practices. MP&L is continually re-evaluating these procedures based on current industry experience. As a result of the recent activities related to motor operated valves, many more refined techniques of M0V testing and setup are being developed. MP&L will continue to evaluate this information for possible incorporation into the current Preventive Maintenance Program as it becomes available. Any deficiencies identified or enhancements noted from testing conducted in accordance with Item c of the bulletin will be reviewed for inclusion into the Preventive Maintenance Program.

Item e) Within 180 days of the date of this bulletin, submit a written report to the NRC that: (1) reports the results of Item a and (2) contains the program to accomplish Items b through d above including a schedule for completion of these items.

J16AECM86100101 - 3

' AECM-86/0291 Page.4 Response: (1) The results of Item are are included in Attachment I.

(2) Programs to accomplish Items b through d have been

- addressed in the responses above, with the current GGNS PM program discussed in Items b and d.

Yours ruly, ODK:bms Attachment cc: (See Next Page)

I J16AECM86100101 - 4

- = ,.

1 . .

I AECM-86/0291 Page 5 cc: Mr. T. H. Cloninger (w/a)

Mr. R. B. McGehee (w/a) ,

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. R. C. Butcher (w/a)

Mr. James M. Taylor, Director (w/a)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555

. Document Control Desk (w/a)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 a

I 1

3 4

J16AECM86100101 - 5

Switch Settings Final Switch Maximum Prior to Adjust- Settings in Expected ments as a Result Response to l DP (psid) Test DP (psid) of Bulletin Bulletin j Valve Valve Operator Valve Function Open/Close Open/Close Open/Close Open/Close Q1E51F010 Limitorque Isolation Valve 22/21 Wm Powell SMB-000-2 for RCIC Suction l

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Switch Settings Final Switch Maximum Prior to Adjust- Settings in Expected ments as a Result Response to DP (psid) Te:t DP (psid) of Bulletin Bulletin Valve Valve Operator Valve Function Open/Close Open/Close Open/Close Open/Close Q1E51F063 Limitorque RCIC Turbine 0/1177 Wm Powell 58-1-40 Inlet Stm. from 10"-900# Nuclear Boiler Flex System Ctmt.

Wedge Isolation Valve Gate Q1E51F064 Limitorque RCIC Turbine 0/1177 Wm Powell SB-1-40 Inle' Stm. from 10"-900# Nuclear Boiler Flex. System Ctmt.

Wedge Isolation Valve Gate Q1E51F068 Limitorque RCIC Turbine 0/15 Wm Powell SMB-0-15 Exhaust Isola-20"-150# tion Valve Flex.

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.DP (psid) Test DP (psid) of Bulletin Bulletin Valve Valve Operator Valve Function Open/Close Open/Close Open/Close Open/Close Q1E51F077 Limitorque RCIC Turbine 0/30 Wm Powell SMB-00-2 Exhaust Vacuum 2 1/2"-150# Breaker Line Flex. Isolation Valve Wedge Gate Q1E51F078 Limitorque RCIC Turbine 0/30 Yarway SMB-00-10 Exhaust Vacuum 1 1/2"-1500# Breaker Line Isolation Valve

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Switch Settings Final Switch Maximum Prior to Adjust- Settings in Expected ments as a Result Response to DP (psid) Test DP (psid) of Bulletin Bulletin Valva Valve Operator Valve Function Open/Close Open/Close Open/Close Open/Close Q1E22F001 Limitorque HPCS Pump 24/18 Anchor- SMB-00-15 Suction Isola-Darling tion Valve 18"-150#

Gate Value Q1E22F004 Limitorque HPCS Injection / 1425/1463 Anchor- SB-3-100 Ctmt. Isolation Darling Valve 12"-655#

Gate Valve Q1E22F010 Limitorque HPCS Recirc. to 1409/1425 Anchor- SMB-4-200 CST Line Isola-Darling tion Valve 10"-900# i l

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Switch Settings Final Switch Maximum Prior to Adjust- Settings in Expected ments as a Result Response to DP (psid) Test DP (psid) of Bulletin Bulletin Valve Valve Operator Valve Function Open/Close Open/Close Open/Close Open/Close Q1E22F012 Limitorque PPCS Pump Min- 1449/1437 Anchor- SB-0-25 Flow Bypass Darling Line Isolation 4"-900# Valve Gate Valve Q1E22F015 Limitorque HPCS Pump Suc- 104/19 Anchor- SB-1-40 tion from Sup-Darling pression Pool 24"-150# Line Isolation Gate Valve Valve Q1E22F023 Limitorque HPCS Pump Test 1409/1417 Anchor- SMB-4-150 Return Line Darling Isolation Valve 12"-900#

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