ML20011D237

LER 89-009-00:on 891115,notification Received of Potential Failure Mechanism of Four 3-way Solenoid Operated Pilot Valves.Caused by Incorrect Mounting of Valves.Valves Remounted Vertically & Field Walkdown done.W/891215 Ltr

ML20011D237
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	12/15/1989
From:	Notaro J, Danni Smith LONG ISLAND LIGHTING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-009, LER-89-9, PM-89-219, NUDOCS 8912260028
Download: ML20011D237 (6)

Text

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ge LONG 18 LAND LIGHTING COM PANY t kN

.SHOREHAM NUCLEAR POWER STATION P.O. 00X 610. NORTH COUNTRY ROAD + WADING MlVER. N.Y.11792 ,

Direct Dial Numbers December 15, 1989 FM 89-219 l U.S. Nuclear Regulatory Commission  ;

Document Control' Desk  !

Washington, D.C. 20555 ,

Dear Sir:

In accordar.ce with 100FR50.73, enclosed is Shoreham Nuclear Power

. Station's-Licensee Event Report ?lR 09-003.

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cc s - William T. Russell, Regional Administrator Frank Crescenzo, Senior Resident Inspector i Institute of liuclear Power Operations, Records Center

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..cio,. n. ooc. , .u . u, ... a goreham Nuclear Ptwer Station Unit 1 0 ]6 l 0 t o 10 l 31719 1brlo15 Improper Installation of Solenoid Operated Valves i

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On November 15, 1980 at 3500, the Watch Engineer was notified of a  :

potential f ailure mcch.nism of four 3-stay solencid operated pilot i valves, 1T46*SOV-036A, 035B, 037A and 037B. These SOVs are the pilot valves for the Reactor Building Standby Ventilation System (RBSYS) inlet and outlet air operated isolation valves 1T46*AOV-035A, 035B. 037A and 037B. During an accident situation, a concurrent failure or malfunction of these SOVs could prevent or slow down the closing of the isolation valves and result in the ,

potential atmospheric release of effluent gas from the Reactor '

Building. The SOVs were mounted horizontally rather than vertically which was justified by their Engineering Design Basis but which may have contributed to operational reliability problems. This event was determined to be reportable per 10CFR50.72 (b) (2) (iii) (C) and the NRC was notified at 1532. This Licensee Event Report is being submitted per 10CFR50.73 (a) (2) (v). The SOVs are made by Automatic Switch Co.; their catalog numbers are HV206-832-6F,

.L206-380-6F and L206-832-6F. Corrective actions include remounting the four SOVs vertically, conducting a field walkdown of similar SOVs to verify their proper installation, modifications, and I continue to do frequent testing of the AOV's to monitor and reestablish reliability.

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Event Date: 11/15/89 Report Date: 12/15/89 CONDJT10HS_fB10B_IO._IBE_EYENT Reactor Defueled - All fuel sesembifes stored in the Spent Fuel Pool i

(Mode t Switch - Chutcown i RPV Pressure = 0 peig RPV Temperature : 84 Pogrees F POWER LEVEL - 0% 1 DESDBIEIION_DL':'UE_EYENI On November 15,1989 at 1500, tne Watch Engineer was notif$ed of a potential failure mechanism of four 3-way solenoid operated pilot valves (SOVs) in the Reactor Building Standby Ventilation System (RBSYS) [EH). These 4 SOVs hac' been mounted with their solenoids in  ;

o horizontal position rather than vertical and upright as per the manufacturer's preferred orientation. The valves had been the subject of recent investigations of Surveillance problems with their i essociated AOVs. This event was determined to be reportable per-10CFR50.72 (b) (2) (iii) (C). Plant management personnel were  ;

notified and the NRC was notified at 1532.

The SOVs (IT46*SOV-35A/B and 37A/B) are pilot valves for the' Reactor Building inlet and outlet air operated isolation valves, IT46*AOV-035A/B and IT46*AOV-37A/B. The SOVs are normally energized to allcw instrument air to hold open the isolation valves which permits outside air to be supplied to and exhausted from the Reactor Buildins. - In the event of a power fallure or other accident oenditions, these isolation valves are designed to close cutomatically.

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nIn 0 13 M 0 15 viu - .  % an.v nn This event was discovered while investigating the root cause of the periodic failures of the Reactor Building Automatic Isolation Valves IT46*AOV35A/B and IT46*ACV37A/B, to meet their 10 second closure times as required by Technical Specification Table 3.6.5.2-1. It is now believed that the horizontal mounting of the SOVs may have contributed to these periodic failures.

Because a verbal report to the NRC was made per 10CFR50.72 and because of the submission of this Licensee Event Report per 10CFR50.73(a)(2)(v)(C), LILCO considers this report to fulfill any reporting requirements that may be required by 10CFR21.

CAUSE QE_IBE_EYENI The SOVs were installed with solenoidt mounted horizontally. '.'h i s is contrary to the preferred configuration which states that the SOVs should be mounted with their soienoida verticsl and upright.

The fact that the SOVr were mounted in an Orientation 90 deg/ees off of the vertical was previously approved. The air-operated isolation valves (AOVs) supplied by Fisher Controls came with ASCO SOVs premounted. When these AOVs were ir, stalled the SOVs ended up horizontal. Thir was noted during the Torrey-Pines Independent Review of the Shorobam Nuclear Power Station (September 30, 1982).

It was also noted during the Environmental Qualification Status Report verification walkdown perf ormed n.id-1983. Because the generic qualification testing performed by ASCO for the HV206-832-6F SOVs did not meet the more stringent seismic test requirements for Shoreham, ASCO was requested to perform additional seismic >

qualification testing of tho.SOVs when mounted horizontal 1r. The test results are documellted in ASCO's Test Report No. AQR-67594, dated Jan. 8, 1985. The horizontnl mounting of the SOVs was accepted based upon the following items: 1) ASCO,s Test Report No.

AQR-67594, 2) the architect engineer's seismic calculation which verified SOV operability when mounted horizontally, and 3) the fact that the associated air-operated isolation valves met their closure time requirements.

The mounting of the SOVs was not changed in 1988 when the four SOVs were replaced with models L206-380-6F and L206-832-6F at the end of their environmentally qua]ified life. The modification design process used for this work took credit for the original installation design basis; therefore the work only involved replacing SOVs with similar ones, go. .u w oi m o m m m

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nl n n la " oI5 m, oa ,.,. e a .,., nama ec o anw nn The Plant had experienced reliability problems with the AOVs to which the SOVs may have contributed. Continuing investigation of these problems led to issuance of LILCO Deficiency Report 89-189.

Upon dispositioning of the LDR a reportability determination was initiated for a potential mounting discrepancy with the Environmental Qualification Documentation Package. This problem was reported per 50.72(b)(2)(iii)(C).

The Nuclear Engineering Department also began reviewing the design basis of the valves. The engineering design basis review determined that the valves would fulfill their design basis safety function in their original configuration. Due to the physical construction of the SOVs, the horizontally mounted SOVs may be more sus'eptible c to problems due to mechanical friction. The valves have been oriented in the vertical penition to alleviate this ocncern.

ANALEIS_ MIL 1HE_E71HI The two Reactor Building Ventilation m:.pply velvas, IT4 6

• AOV-036A and B, and the two exhaust valv m 1T46*AOV-037A and B are arranged in series so thar, the SOVs f or both supply or i'or both exhaust isolation valves would have to malfunction concurrent with an accident to allow a potential release path. But, because all SOVs were mounted in the same configuration this double isolation valve arrangement may be susceptible to the same failure mechanism.

Daring the pe riod coveu-d by this event, the rcactor accumulated slightly ov9r 2 effective l'ull power de.ys of operation. This was accumulated while operating under a license that J imited reactor thermal power to 5% of rata 6.

COREECIIYE ACTIONS

1. The SOVs were mounted in the vertical position. The Reactor Building supply and isolation valves were tested per SP 24.418.02, HVAC Reactor Building - Secondary Containment Isolation Valves Operability Test, with satisfactory results.

2. During the investigation it was noted that an Environmental Qualification Engineers approval was not always required for all safety related modifications. To address this concern Nuclear Engineering Department (NED) Procedure 3.11, Control of LILCO Engineering Change Reports for Modification of Shoreham Design Documents, has been revised to require a review of safety-related Engineering Change Reports by an Environmental Qualification Engineer. NED Procedure 3.10, Preparation, Review and Approval of L-Series E&.DCRs will be revised with the same intent.

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3. To ensure that other SOVs are mounted acceptably a field walkdown of other appropriate SOVs was completed with no other discrepancies noted.

4. The AOVs will continue to be monitored through frequent testing of the valves. This frequency is greater than required by Technical Specifications. Testing will be performed until it is established that their' reliability is adequate.

ADDlil0NAL_lHFORMATIQB

a. Manufacturer _and_mndeknumber_QL failed _comnenent_.Lal: None

b. LER numbern_of prey 1oun_nimilar_eyenta: None r.

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