05000325/LER-1982-108, Updated LER 82-108/03L-1:on 821010 & 14,while Performing Automatic Depressurization Sys Valve Operability Test,Valves 1-B21-F013J & 1-B21-F013D & E Failed to Reclose.Caused by Faulty Spring.Valves Replaced

Updated LER 82-108/03L-1:on 821010 & 14,while Performing Automatic Depressurization Sys Valve Operability Test,Valves 1-B21-F013J & 1-B21-F013D & E Failed to Reclose.Caused by Faulty Spring.Valves Replaced

ML20091A101
Person / Time
Site:	Brunswick
Issue date:	05/18/1984
From:	Dietz C, Pastva J CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
BSEP-84-1168, LER-82-108-03L, LER-82-108-3L, NUDOCS 8405290274
Download: ML20091A101 (3)

LER-2082-108, Updated LER 82-108/03L-1:on 821010 & 14,while Performing Automatic Depressurization Sys Valve Operability Test,Valves 1-B21-F013J & 1-B21-F013D & E Failed to Reclose.Caused by Faulty Spring.Valves Replaced

Event date:
Report date:
3252082108R00 - NRC Website

text

NRC FORM 366 U. S. NUCLEA3 REZ ULATIGY COMMISSION (7-77) . UPDATE REPORT:

• LICENSEE EVENT REPORT PREVIOUS REPORT DATE: 11-12-82 (PLEASE PRINT CR TYPE ALL RECUlRED INFIRMATl!N)

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DATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h lTITI l While performing ADS Valve Operability Test, PT-11.1.2, at 200 psig reactor pressure l 10 l 3 l l on 10-10-82, S/RV valve 1-B21-F013J failed to reclose until 55-100 psig reactor pres- l l0l4; l sure. Performance of this PT on 10-13-82 revealed S/RV valves 1-B21-F013D and E l

[Tl f] l would not open at 200 psig reactor pressure. However, while performing this PT on j iO le l l 10-14-82, S/RV F013E was manually opened, but responded slowly. In each case, the unitj 6

l C l 7 l l was then placed into cold shutdown. Neither event affected the health and safety of [

o,ggg the public. Technical Specifications 4.5.2b, 6.9.1.9b l E CODE $ BC E COMPON ENT CODE SLB ODE SU E lT[9"l 5 l Cl Jl@ W@ lB l@ lV lA lL lV l0 lP l@ W@ y @ 18 19 20 7 8 9 10 11 12 13 REVISION *

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CAUSE DESC' IPTION AND CORRECTIVE ACTIONS h l i l a l l F013J failed to reclose because its solenoid valve failed to close, attributed to I t i l n faulty spring within the solenoid valve. The defective solenoid valve was replaced l The problems l g l along with the valve pilot assembly and F013J was tested satisfactorily.

ITT'n I frecting F013D and E were not determined. Both valves were replaced in their l i 4 l entirety and tested satisfactorily. l 7 8 3 80

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t Facility: BSEP Unit.1 ' ; q- r, T. vent Date: October 10, 1982 t , ,

s s. . s While performing 'the ADS (Syr.cm Valve Opersbility Test, PT-11.1.2, during

< Unit I startup-at a reactor pressurh of 300'pilg, S/RV 1-B21-F013J failed to reclose until reactor piessurs was '50-100 psig. 'The reactor was then placed in cold shutdown. . On October 13, 982, whfle' performing this PT, S/RV valves Following

' 1-B21-F013DandE(failedtoopenatareacjorpressureof200psig.

s this event, the'uait waa jgain placed into cold shutdown.

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,An inspection of the F013J, Model No. 7567F', revealed the F013J solenoid valve opened with noninterruptible instxtymnt air still exhausting through the solenoid valve outlet port. When 1.he solenoid valve air supply was isolated, the solenoid valve closed. The F013J' solenoid valve was then removed and bench tested satisfactorily. An in'vestigation of this problem by an on-site representative of the valve vendor concluded the unusual valve operation was caused by a faulty spring within the solenoid valve. The valve vendor, Target Rock Corporation, acknowled; a that solenoid valve spring relaxation is a design problem, and comequently, they have developed a more reliable replacement sprias. - Qe design modification changed the material from the original 302SS 'to Incpel-718. This modification was completed for the solenoid valves in Unit 2 during the Unit 2 1982 refueling outage. The remaining Unit' I solenaid valves were modified during the Unit 1 1983 refueling,outam.

The problem solenoid valve on S/RV F013J was modified with the improved spring material. As a preventive measure, the valve pilot assembly was also replaced. During suosequent performance of PT-11.1.2 on October 13, 1982, F013J tested satisfactorily.

Followin's the discovery of problems affecting the opening capabilities of S/RV F013D and E, an inspection of both valves was performed. This inspection, which was conducted with the assistance of the valve vendor representative, was unsuccessful in determining what problems affected both valves. Both valves were replaced in their entirety and were tested satisfactorily. Also, the solenoid valves for these valves were modified with the improved spring material. It is felt the incurred F013D and E failures each resulted from one or both of the following identified two-stage S/RV generic problems:

1. High friction in the valve labyrinth seal guide area associated with a clearance less than minimum required by design.

2. Corrosion at the valve pilot valve seat-disc interface which results in sticking of the S/RV disc-to-seat assembly.

The BWR Owners' Group has concluded that the frequency of S/RV setpoint drift problems can be adequately controlled by improved maintenance practices during valve refurbishment / maintenance. Wyle Laboratory, which tests the setpoints of two-stage S/RVs, is currently revising their procedures as required to reflect the BWR Owners' Group recommendations. In addition, General Electric Company plans to issue a service /information letter regarding the suggested changes to S/RV procedures.

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g'd.ca'.ouna Power.:&. Light Company Q n u+ .. . /- :w Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 May 18, 1984 FILE: B09-13510C SERIAL: BSEP/84-1168 Mr. James P. O'Reilly, Administrator U. S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N.W.

Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 SUPPLEMENT TO LICENSEE EVENT REPORT 1-82-108

Dear Mr. O'Reilly:

In accordance with Section 6.9.1.9b of the Technical Specifications for Brunswick Steam Electric Plant, Unit 1, the enclosed supplemental Licensee Event Report is submitted. The original report fulfilled the requirement for a written report within thirty (30) days of a reportable occurrence and both are in accordance with the format set forth in NUREG-0161, July 1977.

Very truly yours, d(g C. R. Dietz, General Manager Brunswick Steam Electric Plant RMP/pms/LETPS1 Enclosure cc: Mr. R. C. DeYoung NRC Document Control Desk OITICI AL col'.Y

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