ML18054A470

LER 88-022-00:on 881202,foreign Matl on Valve Seat Resulted in Inoperable Isolation Valve.Valve CV-1037 Disassembled, Inspected & Repair & Procedures Re Cleanliness Control upgraded.W/881228 Ltr

ML18054A470
Person / Time
Site:	Palisades
Issue date:	12/28/1988
From:	Johnson B, Kozup C CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-022, LER-88-22, NUDOCS 8901030435
Download: ML18054A470 (5)

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• * *1111111*1 I0.731111211HO *.7Jlall21f*I LICINllE CONT ACT ,Dll THll Liii 1121 TELEPHONE NUMIER AlllA CDOI CSKozup_,. Technical Engineer, Palisades 6116 71614 l-181'.11113 COMl'LITI ONE LINI FOii IACH COMl'ONENT ,AILUlll OllClllllO IN TH* lll_POllT 1131 CAUIE S'l'ITIM COMPONENT X WID I II S IV Ml 112 I 0 NO I I I I I I I I I I I I I I I I I I I I I IU"LIMINTAL lllPOllT IXPICTED IHI MONTH DAY '!'~All EXPECTED n ~

IUIMISllON DATE 1151 YES llf ,.... _,_.,. llXHCTllO SU.II/SS/ON OATlll NO I I I Abstract During the performance of Technical Specification (TS) Surveillance Test Q0-11, "Containment Isolation Check Valve Test 11 on December 2, 1988, inner containment isolation valve CV-1037 [WD;ISV] was discovered to be leaking by in excess of allowed TS limit, however, integrity of the outer containment isolation check valve CK-CRW408 was maintained. TS 4.5.2 requires that the total leakage from all penetrations and isolation valves remain under 0.60La* At 2216 when this condition was identified, the reactor was critical° with the Plant operating at 35.2 percent of rated power.

In attempting to identify the root cause of CV-1037's failure, it was flushed and cycled several times. During this evolution, the valves stem was observed to be traveling further closed upon each cycle. At this time mechanical binding of valve inte~nals was the suspected cause.

However, when the valve was disassembled, a small unidentifiable hardened green plastic object was found adhered to the valve's plug.

This plastic appeared to have been chipped away by cycling the valve such that_ acceptable seating was achieved prior to valve repair.

NllC'"-* Lr.I:\ OOULL-LlUJ.19-431

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'.ll-631

• A U.I. NUCLEAll lllEGULATOlllY COMMIDI~

LICENSEE EVENT REPORT (LERI TEXT CONTINUATION Al'l'ROVEO OMB NO 3150--0104 EXPIRES. 8/31185 FACILITY NAME 111 OOCKET NU. . ER 121 LEiii N~Ell 111 ~AGE Ill Palisades Nuclear Plant 0 15 I 0 I 0 I 0 I 2 I s Is 8 18 - o I2 12 - o p o I 2 oF o I 4 TEXT I,,,,.,,,._..;,, ,.,,.,nd, - - N l f C Fotm .m.4'111171 Description During the performance of Technical Specification (TS) Surveillance Test Q0-11, "Containment Isolation Check Valve Test" on December 2, 1988, inner containment isolation valve CV-1037 [WD;ISV] was discovered to be leaking by in excess of allowed TS limit, however, integrity of the outer containment isolation check valve CK-CRW408-was maintained. TS 4.5.2 requires that the total leakage from all penetrations and isolation valves remain under 0.60La* At 2216 when this condition was identified, the reactor was critical with the Plant operating at 35.2 percent of rated power.

TS Surveillance Test Q0-11 is performed at three month intervals in accordance with TS 4.5_.2.d.2. This test verifies the ability of containment isolation check valves to close in order to achieve their required safety position per ASME Section XI. During test performance, a reverse pressure is applied across the check valve seat and flow is verified'to be secured by monitoring test pressure decay rates.

Containment isolation valve CV-1037 is associated with containment penetration 67* which services the clean waste receiver tank pump P-70

[WD;P] recirculation line. Penetration 67 is classified as a Palisades Final Safety Analysis Report (FSAR) class C2 penetration. Penetrations in this class include systems that are not connected to either the containment atmosphere or to the primary coolant system and are normally

. open or may be opened during power operation. *Pipe lines passing through the containment, associated with FSAR class C2 penetrations are required to have two automatic isolation valves in series. Check valves are considered to be automatic. Penetration 67 meets this requirement via CV-1037 and CK-CRW408 being in series, with CV-1037 receiving an automatic close signal upon actuation of the containment isolation system.

During the performance of Q0-11, CK-CRW408 is tested by applying 80 psia of air pressure between it and CV-1037. A test fixture is attached at a test tap to monitor pressure decay. When this test was performed on December 2, 1988, the acceptance criteria of maintaining greater than 69.7 psia of air pressure for five minutes was not met. This determination was made at 2136. At 2216, it was determined that CV-1037 and not CK-CRW408 was leaking by. This was determined by opening an in-containment valve (CV-1018) upstream of CV-1037. When the valve was opened, the test pressure rapidly dropped *off, thus confirming CV-1037 was leaking by.

At this time, Operations personnel entered TS 3.0.3 and initiated a series of line flushes and valve cycling operations in attempting to get CV-1037 to seat properly. At 2316, it was determined that CV-1037 was functioning properly, so TS 3.0.3 was exited.

N"'C FORM 3e6.A 1e.eJ1 LER 88022-LIOl

NllC I .>. . .A U.I. NUCLEAll llEGULATOllY COMMIDION 19-631 LICENSE ENT REPORT (LERI TEXT CONTINUATION A'PROVEO OMS NO. 3150~104 EX,.llES: 8/31 '115 FACILITY NAME 111 DOCKET NU. . ER 121 Liii NU..Ell 111 Palisades Nuclear Plant 0 15 I 0 I 0 I 0 I 2 I 51 5 8 18 o I 21 2 01 0 0 I 3 OF 0 14 T£XT ( I f , _ _ io '9qVftd, - .-.W NltC Foml _.'*I 1171 Cause Of The Event In attempting to identify the root cause of CV-1037's failure, it was flushed and cycled several times. During this evolution, the valves stem was observed to be traveling further to closed upon each cycle. At this time mechanical binding of valve internals was the suspected cause.

However, when the valve was disassembled, a small unidentifiable harden.ed* green plastic object was found adhered to the valve's plug.

This plastic appeared to have been chipped away by cycling the valve such that acceptable seating was achieved prior to valve repair.

The source .of the hardened gree.n plastic object is not known, however, it is felt to be an i.solated occurrence resulting from maintenance activities.

Corrective Action CV-1037 was disassembled, inspected and repaired. During this repair, the valve packing was upgraded by installation of graphite packing to minimize mechanical binding. Valve operability was confirmed by the satisfactory performance of the Local Leak Rate Test R0-32-367.

During this event, Operations personnel noted that Q0-11 prescribed actions for test results not meeting a.cceptance criteria entailed retesting, initiating corrective action documents and initiating applicable local leak rate tests during the next cold shutdown condition. However, no reference was made to potentially applicable TS Limiting Conditions of Operation.

Therefore, actions prescribed within Q0-11 are being evaiuated to assure proper actions are taken to preclude potential TS violations regarding containment integrity.

Procedures regarding cleanliness control have recently been upgraded to aide in precluding foreign materials and tools from entering Plant system.

Analysis Of The Event During the one hour period when CV-1037 was declared inoperable, the integrity of the outer most containment isolation valve CV-CRW408 was maintained. Therefore, at no time was there leakage from the Containment Building in excess of Plant TS. TS 3.6 requires that containment integrity be maintained unless the reactor is in the cold shutdown condition. TS 1.4, as it applies to automatic isolation valves, is defined to exist when "all automatic containment isolation valves are operable or are locked closed". In that CV-1037 was not operable and was not locked closed, this event is being reported per 10CFRS0.73(a){2){ii) as an operational condition prohibited by Plant TS.

NlllC FORM 3e8A 19-1131 LER 88022-LIOl

NRC *****' . .A U.I. NUCLEAI! lliGULATOll'I' COMMlalON 19-831 LICENSEE ENT REPORT (LERI TEXT CONTINUATI A"ROVEO OMD NO. 3150~104 EX,IRES 81311115 FACILITY NAME (11 DOCKET N..,...EI! 121 , (I YEAfllt SEQUENTIAL .::::.<* llllEVrllON NUM Ell! * .*:-:*:* NUM 1!111

'Palisades Nuclear Plant OF 0 4 0500025 588-02 2-0 00 TEXT l / f - - * - - * - - N l t C -.-...*111171 Additional Information Containment isolation valve, CV-1037 is a Masoneilan Division model number 38-20571 control valve.

For additional information regarding inoperable containment isolation valves, reference Licensee Event Reports87-005, 87-026,85-029, 83-059,83-066 and 81-036.

NJllC FOllllM 38eA (9-!131 LER 88022-LIO 1

PDWERINli MICHlliAN'S PROGRESS General Offices: 1S45 West Parnell Road, Jack_son, Ml 49201 * (517) 788-0550 December 28, 1988 Nuclear-Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

LICENSEE EVENT- REPORT 88-022 - FOREIGN MATERIAL ON VALVE SEAT RESULTS IN-INOPERABLE ISOLATION VALVE Licensee Event Report (LER)88-022 (Foreign Material on Valve Seat Results in Inoperable Isolation Valve) is attached. This event is reportable to the NRG per 10CFR50.73(a)(2)(ii).

Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC1288-0248-NL04

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