ML20196D632

Provides Current Status of Commitments in Re NRC Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings

ML20196D632
Person / Time
Site:	Sequoyah
Issue date:	02/12/1988
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
IEB-85-003, IEB-85-3, NUDOCS 8802170333
Download: ML20196D632 (13)

Text

{{#Wiki_filter:;) L / -w TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 374ot SN 157B Lookout Place FEB 121988 U.S. Nuclear Regulatory Comission ATTN: Document Control Desk Washington, D.C. 20555 -Gentlemen: In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - 0FFICE OF INSPECTION AND DiFORCEMENT (IE) BULLETIN 85 MOTOR-OPERATED VALVE (MOV) COMMON MODE FAILURES DURING PLANT TRANSIENTS BECAUSE OF IMPROPER SWITCH SETTINGS

References:

1. NRC IE Culletin 85-03 dated November 15, 1985, "Motor-Operated Valve com,n Mode Failures During Plant Transients Due To Improper Switch Settings" 2. TVA letter to NRC dated May 12, 1986, "Office of Inspection and Enforcement Bulletin 85 Motor-Operated Valve Comon Mode Failures During Plant Transients Due To Improper Switch Settings - Sequoyah kuclear Plant" This letter provides a current status of -SQN's MOV program to address IE Bulletin 85-03. of SQN's initial response (reference 2) listed nine comitment items wita scheduled completion dates. SQN has now implemented and completed each of the nine comitment items with the exception of items 6 and 8 given below. Item 6 Stroke test 1 MOV in each of the test categories 4 and 5 (reference attachment 1 of SQN's May 1986 submittal) under full-flow differential pressure 'DP) conditions (total of 2 MOVs) during turbine-driven auxiliary feedwatar pump surveillance testing af ter returning SQN unit 2 to service from its current outage. Item _8 After issuing a design output document (item 7), revist, plant procedures to incorporate these requirements before startup from the unit 2 cycle 3 refueling outage but no later than November 1987. Item 6 is presently scheduled durinz unit 2 restart, although the actual comitment states that testing will be performed af ter returning SQN unit 2 to service. Item 8 has been rescheduled for completion by March 31, 1988. This extension is needed for consolidation of other needed changes to Maintenance Instruction (MI) 10.43 for the purpose of incorporating all changes under one revision. Thir will ensure that valve operability (proper tongue switch settings) is maintained. }, h!bbo K 7 I O l An Equal Opportunity Employer

e U.S. Nuclear Regulatory Commission FEB 121988 contains a description of each of SQN's seven completed commitments. Attachment A contains a MOV Data Summary Table that lists as-found and as-left torque switch settings for determination of as-found valve operability. restates commitment item 6 and revises the scheduled completion date for item 8. Upon completion of these items, SQN will submit a final report to NRC within the required 60 days (item F of IE Bulletin 85-03) to document full completion. If you have any questions, please telephone M. R. Harding at (615) 870-6422. Very truly yours, TENNESSEE VALL AUTHORITY / R. Gridley, Dire or Nuclear Licensing and Regulatory Affairs Enclosures cc (Enclosures): Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division Office of Special Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. G. G. Zech, Assistant Director for Projects TVA Projects Division Office of Special Projects U.S. Nuclear Regulatory Commission Mail Stop 7E23 7920 Norfolk Avenue 3ethesda, Maryland 20814 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 ,n . -.,,. -.. -. ~..

ENCLOSURE 1 Upon receipt of the Office of Inspection and Enforcement (IE) Bulletin 85-03, Sequoyah Nuclear Plant (SQN) began evaluating and implementing a. program to ensure that valve operator switches are set and maintained properly. It should be noted that SQN was in the middle of an extended outage and well into a major motor-operated valve (MOV) modification and testing effort for 10 CFR 50.49 environmental qualification. of SQN's May 1986 submittal outlined nine activities that SQN would take to address th.e subject bulletin. The following provides a summary of each of the nine commitment items. Items 1 and 4 1. Determination / verification of correct switch settings for 21 MOVs on each unit in attachment 1 by August 31, 1986. 4. Stroke test the 21 MOVs on each unit in attachment i under non-differential pressure (DP) conditions by August 31, 1986, for verification of correct switch settings as determined for item (b). SQN Effort Commitment items 1 and 4 were not completed by August 31, 1986, because of problems in obtaining maximum allowable thrust data from Crane-Alloy Company (Walworth) for valves 1, 2-FCV-1-15, -16. -17, and -18. By way of a TVA letter to NRC dated September 11, 1986, SQN extended the commitment due date on items 1 and 4 to October 18, 1986. Because of a failure of Crane-Alloy to perform their contract with IVA, it was determined that TVA's Division of Nuclear Engineering (DNE) would evaluate the data available for Walworth valves and would e',tablish by engintering evaluation / judgment that the actual thrust being seen in the field for these valves is acceptable. DNE's evaluation allowed SQN to meet the October 18, 1986 commitment date with one exception: 1-FCV-63-40. During initial testing, this valve had a higher thrust value than its identical sister valve, FCV-63-39. By way of a TVA letter to NRC dated October 31, 1986, commitment items 1 and 4 were considered complete; and an additional commitment was made to investigate and complete resolution of 1-FCV-63-40 by November 30, 1986. SQN completed resolution of 1-FCV-63-40 on November 28, 1986. Although no obvious causes were found, it is believed that wadge orientation was the probable root cause, based on vendor comments and final test results. Attachment A of this enclosure (MOV Data Summary Table) provides the final results of SQN's commitment items 1 and 4. l Item 2 Test the overload protection devices on 1, 2-FCV-1-17 and -18 by August 31, 1986, t I l

.. SON Effort SQN has included the subject valves in preventive maintenance,(PM) instructions 1634-001, 1635-001, 1636-001, and 1637-001 to ensure that the overload protection devices are properly tested, sized, and maintained. This was completed as required by August 31, 1986. Item 3 Review, revise, and prepare (as necessary) procedures for overload protection devices on the 21 MOVs before startup from the unit 2 cycle 3 refueling outage but no later than November 1987. SQN Effort SQN nerformed a review of two existing surveillance instructions (SI) (SI-251.1 and -251.2) to ensure that the overload protection devices for the remainder of the 21 MOVs (those not included under commitment item 2) were properly tested, sized, and maintained. This action was completed July 21, 1986. Item 5 Stroke test 1 MOV in each of the test categories 1, 2, and 3 (attachment A) under full-flow DP conditions (total of 3 MOVs) by August 31, 1986. SQN Effort Full-flow DP testing was performed on the following MOVs: Valve Number Test Date 2-FCV-62-91 July 16, 1986 1-FCV-63-22 August 14, 1986 1-FCV-63-40 August 14, 1986 Note: 1-FCV-63-39 (sister valve to 1-FCV-63-40) was also tested under full-flow DP conditions on August 23, 1986. The design and test DPs for these valves are provided in the MOV Data Summary Table (attachment A). Item 6 Stroke test 1 MOV in each of the test categories 4 and 5 (attachment A) under full-flow DP conditions (total of 2 MOVs) during turbine-driven (TD) auxiliary feedwater (AFW) pump surveillance testing after returning SQN unit 2 to service from its current outage. l SQN Effort l l This item will be completed during unit 2'startup. f i l l 1 -..n

k ./ / \\ ATTACHMENT A .y MOV DATA

SUMMARY

TABLE SEQUOYAH NUCLEAR PLANT IE BULLETIN 85-03 NOTES i ( 1; SQN agraed to test 1 MOV in each of the test categories 1, 2, and 3 under full-flow DP conditions (total of 3 MOVs). Reference commitment itam 5 of SQN's Hay 12, 1986 submittal. 2. Torque switch settings in the open direction havelbeen deleted for all 21 MOVs as discussed in SQN's May 12, 1986 submittal. For this reason, all torque switch settings and thrust values are given in the closing direction. 3. Valve Operability Designations: Acceptable as-found closing thrust did not excled tha twquired closing thrust. Indeterminate - as-found data was unavailable. At the tin;e SQN began s to implement IE Bulletin 85-03 SQN was'in the middle of an extended outage and well into a majlc MOV modification and testing effort for 10 CFR 50.49 cnvironmental qualification. By the time the Electrical Maintenance Section began testing valves for the bulletin, the actual as-found condition had s not been recorded and therefore was indeterminate. Unacceptable - as-found closing thrust exceeded the req'u' red closing i thrus t. 4. Valve 2-FCV-63-22 has a required seating thrust of 11,870 pounds;' however, the as-found closing thrust was 8,030 pounds, which is unacceptable. Because this valve is required by SQN technical specifications to remain in the open position with power removed (modes 1, 2, and 3) the unacceptable as-found closing thrust would not have prevented this valve from performing its safety function to remain open. 5. At the time of test 2-PCV-63-25 had a required seating thrust of 14,190 podnds. The as-found total' closing thrust was,found to be 14,115 pounds. This difference (75' pounds) is less than 1 percent of the total required thrust. The additional seating action provided by this small dif ference is considered to be inconsequential f or valve closure and operability. SQN considers this valve to be acceptsble, s 4 8 m -M

-4. ,s ,[- Item ~/' Issue a design output.pocument that spe cifies and controls switch settings for the 21 MOVs in attactment A before startup from the unit 2 cycle 3 refueling ,i outage but no later than November 1987,. 30N Effort SQN has issued the design output document (Drawing Series 47A940) that defines x the design basis DP, the Tequ! red thrust, and the maximum allowable thrust for '+ach of the 21 MOVs. "This com'mitment was completed as required on November 27, 1987. Item 8 Af ter issuing a design cutput document (item 7), revise plant procedures to incorporate these regairements before startup from the unit 2 cycle 3 refuelingoutageyrnolaterthanNovember1987. SON Effort j This item is rescheduled for completion by March 71, 1988. SQN's present procedure (MI-10.43) contains censervative requir tt thrust values. This will ensure that valve operability (proper torque swit, settings) ir maintained. Item 9 Delete the opening torque / torque bypass switches on 1, 2-FCV-1-17 -18 and -51 by August 31, 1936. SON Effort SQN performed modifications to delete the opening torque / torque bypass switches on the subject valves. This action was complete on April 16, 1986. Conclusion The data contained in the MOV Data Summary Table (attachment A) provides 1 assurance that thece valves would have performed their safety function under ( the as-found switch settings. It should be noted that all as-found data was not available as requested by part E of the bulletin. At the time SQN developed its_MOV test program and began to implement IE Bulletin 85-03, SQN was already in the middle of an extended outage and well into a major MOV modification and testing effort for 10 CFR 50.49 environmental qualif! cation. By the time the Electrical Maintenance Section began testing for IE Bulletin 85-03, an actual as-found condition was not determinable. Attachment A identifies those valves not having as-found conditions. Upon completion of the remaining commitment items 6 and 8. SQN will submit a fin 21 report to NRC within the required 60 days (reference item F of IE Bulletin 85-03) to document completion of these two items.

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1 ENCLOSURE 2 SQN's two remaining commitments for final resolution of IE Bulletin 85-03 are items 6 and 8, contained in TVA's May 12, 1986 response. Item 6 has been restated to indicate that testing would be performed during unit 2 restart rather than after unit 2 restart. Item 8 contains a revised completion date of March 31, 1988. 6. Stroke test 1 MOV in each of the ttst categories 4 and 5 (reference attachment 1 of-SQN's May 12, 1986 response) under full-flow DP conditions (total of 2 MOVs) during TD ATW pump surveillance testing during unit 2 restart. j I 8. After issuing a design output document (item 7), revise plant procedures to incorporate these requirements before startup from the unit 2 cycle 3 refueling outage but no later than March 31, 1988. h S .}}