ML19324C178

LER 89-023-00:on 891005,outboard MSIV Ac Solenoid Pilot Valves de-energized,resulting in Expected Closure of Outboard MSIV D & Automatic Reactor Scram.Caused by Incomplete Guidance.Procedure revised.W/891106 Ltr

ML19324C178
Person / Time
Site:	Peach Bottom
Issue date:	11/06/1989
From:	Cribbe T, Danni Smith PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-023-01, LER-89-23-1, NUDOCS 8911150135
Download: ML19324C178 (6)

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SUBJECT:

Licensee Event Report Peach Bottom Atomic Power Station - Unit 2 This LER concerns a closure of a Main Steam isolation Valve during testing which resulted in a reactor scram from full power.

Reference:

Docket No. 50-277 Report Number: 2-89-023 Revision Number: 00 Event Date: 10/05/89 Report Date: 11/06/89 Facility: Peach Bottom Atomic Power Station RD 1, Box 208A, Delta, PA 17314 This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(iv). 1 Sincerely,/ - h, ' i cc: J. J. Lyash, USNRC Senior Resident Ir.spector W. T. Russell, USNRC, Region I l l l 8911150135 e91106 M l PDR ADOCK0500g7 , g l s , I

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Requirement. for the Report This report is required pursuant to 10 CFR 50.73(a)(2)(iv) due to an Engineering Safeguard feature actuation (i.e., scram). Unit Status at Time of Event Unit 2 was in the Run Mode at 99.5% thermal power in steady state operation. There were no structures, systems or components that were known to be inoperable that contributed to this event. Description of Event At 1806 hours on 10/5/89 with Unit 2 at 95.5% thermal power, ST 1.3A-2 "PCIS Group 1 Logic System functional Test" was inprogress (performed on a six month frequency per Technical Specifications). The inboard Main Steam ltolation Valves (MSIVs) (EIIS:ISV) portion of the test had already been completed. When the outboard MSIV AC solenoid pilot valves (E!!S:PSV) were de-energized as part of the testing procedure, the "0" outboard MSIV unexpectedly closed. This caused a rapid increase in indicated reactor pressure to approximately 1001 psi. The pressure increase caused steam voids to collapse, thus inserting positive reactivity causing reactor power to increase to approximately 115% and an automatic scram at 1806 hours due to an APRM high flux signal. Within five seconds of the scram, reactor water level dropped to an indicated narrow range level of +1" (just aN ve the bottom of steam separator shroud) causing the "C" Primary Containment Isolation System (PCIS) (Ells:JM) channel to trip (setpoint of 0" reactorlevel). However, a full Group I1/111 isolation did not occur. Reactor water level rapidly increased until the "A", "B" and "C" Reactor feed Pump Turbines (RFPTs) (EIIS:JK) were manually tripped just prior to the automatic main turbine trip on high reactor water level (+45"). The bypass valves were observed to be full open shortly after the scram (exact time i unknown) which caused an indicated reactor water level decrease to +8" and a subsequent swell to +70" following the RFPT trip. Additionally, a Reactor Water Cleanup (RWCU) (Ells:CE) isolation on low RWCU System flow occurred (exact time  ; unknown), which is also attributed to the opening of the bypass valves and the resultant drop in reactor pressure and indicated level. The EHC pumps were shutdown l l in order to close the bypass valves. Main Steam Line Drains, Turbine Sealing Steam, and Turbine Stop/ Control Valve Lead ' Drains were used to control pressure below 960 psig until the "A" EHC pump was started. The "A" and "B" EHC pressure regulators "In Control" lights were observed L , to be swapping between the "A" and "B" regulators. After attempts to bias the "B"  ; l regulator in control were unsuccessful, the "A" pressure transmitter was valved out i of service and vented in order to successfully place the "B" pressure regulator in E control. ! Post scram investigation revealed that the DC Solenoid Pilot Valve (AVCo model 6910-l 020) on the "0" outboard MSIV was mechanically binding in the vented position. The

solenoid valve was replaced, the MSIVs were verified to remain in the open position t

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0l2 l 3 - 0l0 01 5 1mu . - c - mi with the "AC" solenoid pilot valves de-energized. Additionally. ST 1.3A-2 was performed satisfactorily. Unit 2 was returned to service on 10/9/89. Cause of Event The proximate cause of this event was closure of the "D" outboard MSIV resulting from a component failure of the associated DC solenoid valve. The root cause of the component failure was incomplete technical information supplied to PECo by the valve manuf acturer. Automatic Valve Company (AVCo). Examination of the solenoid valve removed from the *0" outboard MSIV revealed that the plunger spring was slightly tapered. Because removal of the solenoid valve fi'om the MSIV requires that the valve be disassembled, the as found spring position is unknown. Bench testing of the solenoid valve was performed with the plunger spring in each of the two possible positions. With the spring installed with the smaller end toward the solenoid coil, testing showed that the plunger would bind sporadically when the solenoid was energized (the frequency of the binding increased with operating temperature). However, in none of these tests did the valve fail to return to the vented position (de-energized state). With the spring installed in the reverse direction (largc end of spring toward solenoid coil), the valve operated correctly each time the solenoid was energized. The manufacturer indicated that this is the correct position. Conversations between PECo and AVCo following this discovery revealed that AVCo had changed the design of the plunger spring fro:a cylindrical to tapered to enhance the retention of the Spring on the plunger shaft during assembly. Vendor information supplied by AVCo to PECo on these valves did not reference this change and therefore did not include guidance relative to the spring orientation, it is believed that the orientation of the spring was inadvertently reversed during , the installation of the solenoid valve on the MSIV. Because site maintenance engineering personnel were unaware of the change to the plunger spring by AVCo. the 1 i installation procedure for these valves did not indicate the correct spring  ! crientation. Additionally, the slight taper of the spring is not readily noticeable l !~ upon observation. l The cause of the bypass valves remaining full open and the subsequent control problems have been attributed to the "A" EHC pressure transducer. A physical  ! inspection of the "A" pressure transducer revealed some water damage. Testing of the ,

            'A" EHC pressure regulator circuitry indicated the.t the circuitry was sluggish in l            responding to changes in input pressure. After the reactor scram, the "A" pressure regulator circuitry was slow to respond to the decreasing reactor pressure, and thus, continued to produce an 'open' signal to the bypass valves.

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u wucu m ioutu oavco==isma= l 4 LICENSEE EVENT REPORT (LER) TEXT CINTINUATION uexovio owe wo mo-cios imnis. swas  ; f ACitity a>404 666 pong, wonego g3 } PZch Bottom Atomic Power ' Station vs.m %gp,*6 g tl11t 2 0 l6 l0 l0 l0 l2 l 7l 7 81 9 - 0]2l3 - 01 0 0l 4 of ol5 ! miv . % <* ace mr.wi Analysis of the Event l No safety consequences occurred as a result of this event.  ! TheReactorProtectionSystem(RPS)operatedproperlythroughoutthistransient. Other safety systems operated as designed. Since the installation of the solenoid pilot valve plunger spring in the reverse direction causes the valve to remain in the vented (safe) condition, automatic t closure of the "D" MSly was at no time inhibited. Therefore, the primary containment ' pressure boundry was not comprimised.  ! 1 Because the other three outboard MSIVs remained open during this transient and during  ! post scram testing, it is believed that their associated 'DC' pilot solenoid valves , are properly assembled. Additionally, previously in test, the inboard MSIVs were ' tested satisfactorily. An 'AC' solenoid pilot valve of the same type and model as the ones used on the MSIVs was tested in the same manner as the 'DC' solenoid. Spring orientation did not affect the proper operation of the "AC" valve. Tais is apparently the result of the greater solenoid thrust force since the AC solenoid valves have higher operating current. Therefore, the 'AC' solenoids are not believed to be susceptible to this problem.  ; t The Main Steam Safety Relief Valves utilire a similar type of solenoid valve. Incorrect plunger spring orientation on these valves has been determined not to be a {

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concern because these valves are replaced as a unit and are not disassembled during i installation at the plant and the manufacturer is aware of preferential orientation i of the spring during assembly. Additionally, the valves are tested by the manufacturer prior to being shipped. . l Corrective Actions , The "D" outboard MSIV DC pilot solenoid valve was replaced and verified operable prior to returning Unit 2 to service. Additionally, ST 1.3A-2 was completed satisfactorily prior to returning Unit 2 to service. l The manufacturer of the solenoid valve has been involved in the investigation of this problem. Both the "A" and "B" EHC pressure transducers were replaced with recently , refurbished transducers. The following corrective actions are planned:

1. The maintenance procedure for the installation of both AC and DC solenoid pilot valves on the MSIVs (M-1.5) will be revised to specify the correct orientation of the plunger spring.

2. The Unit 3 MSIV pilot solenoid valves will be inspected to ensure the plunger springs are installed correctly and any discrepancies will be corrected prior to the restart of Unit 3 from its current outage. The solenoid valves are normally replaced every refuel outage as part of the Preventive Maintenance Program

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3. A preventive maintenance task will be developed to refurbish the EHC pressure transducers on a frequency determined appropriate to improve the reliability of these transducers.

Previous Similar Events There were no previous similar LERs in that a scram resulted from incomplete installation information provided by the manufacturer. There have been 3 previous similar LERs involving scrams resulting from loss of AC power with DC solenoid valve already inoperable (open circuit coil failures) (LERs 3-85-18,2-86-03,3-86-16). The corrective actions in these LERs were electrical in nature (replacement of the inoperable electrical coil) and therefore would not have been expected to prevent this event. 4

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