ML18348A905

Submittal of LER 1980-008-00 Update of Valve Leakage

ML18348A905
Person / Time
Site:	Palisades
Issue date:	05/12/1980
From:	Hoffman D Consumers Power Co
To:	James Keppler NRC/RGN-III
References
LER 1980-008-00
Download: ML18348A905 (8)

Text

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Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

• Area Code 517 788-0550 May 12, 1980 Mr James G Keppler Office of Inspection & Enforcement Region III U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - UPDATE OF LICENSEE EVENT REPORT 80-008 - VALVE LEAKAGE Licensee Event Report (LER)80-008 was submitted to the NRC Region III office on April 29, 1980. An update to this LER is on the reverse side of this letter.

Also attached is a five page report which contains the actions taken with regard to this LER.

David P Hoffman*

Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Palisades Attachment (5 pages)

MAY 1 5 1S8D

. *.

UPDATE REP':. PREVIOUS REPORT DATf.,'-.04 29.'f30 PALISADES PLANT NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION 17*711 LICENSEE EVENT REPORT CONTROL BLOCK: I ,. 10 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 .e

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1 8 9 LICENSEE CODE 14 ,5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT Sil CON'T filTI8 =~~~~! L::J@l015101010 1215 15 K?)IO 1411 15f810 l@lo I sh 12 Isl al@

7 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@

[[II] I. The results of Type C containment leak tests indicated local leakage in

[]:II) I excess of the limit of TS 4.5.2B. Five penetrations had significant leak rates: Penet. 11 (Shield cooling surge tank fill) - 151,000 cc/min;

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£Irn 1 penet. 28 (Cont. air sample) - 52,000 cc/min; penetration 38 (heating *I

[]JI) I steam return) - 22,000 cc/min; penet 14 (CCW in) - 51~000 cc/min; penet.33!

~ I. (SI tank drain) - 1.32,000 cc/min: Limit is approx. 65,000 cc/min. In I

[]]!] I addition, penet 28 was designed such that one of the in-series :cont. isol.1.

7 8 9 valves is~sfiJ.wayscBRfn* CAUSE COMP. VALVE BO COOE CODE SUB CODE COMPONENT CO&lE SUBCODE SUBCODE

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~ LE RIRO CVENT YEAR REPORT NO. CODE TYPE NO.

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33 34 35 36 37 41 42 43 44 47 CAUSE DESCRIPTION ANO CORREC"flVE ACTIONS @ -

OJI] f In previous type C tests -the test methods did not always apply full. test; ITID 1pressure *differential across the boundary being tested;- *In *the -case of 1__

IT.DJ 1Penet 28, it is believed that valve stroking prior to testing caused leak-CIIIJ 1age to occur. Leakage has been reduced to T.S. limit Penet 28 has been EIJI] 1modified to provide double valve isolation.

7 8 9 80 FACILITY l:jQ\ METHOD OF

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. STATUS %POWER OTHERSTATUS ~ DISCOVERY DISCOVERY DESCRIPTION ~

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e. UPDATE IORT:.PRE~I~US REPORT DATE 04298 PALISADES PLANT

• NAC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION .

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LICENSEE EVENT REPORT CONTR"OL BLOCK:

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I J 0 !PLEASE PRINT OR TYl'E ALL REQUIRED INFOAMATIONI

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[]]]] I The results of Type C containment leak tests indicated local leakaqe in

[]]]]I excess of the limit of TS 4.5.2B. Five penetrations had significant leak rates: Penet. 11 (Shield cooling surge tank. fill) - 151,000 cc/min;

@:[!] '1--------~--~--------------~~--------------~----------------~----_.

@ID 1 penet. 28 (Cont. air sample) - 52,000 cc/min; penetration 38 (heating

@I[] I steam return) - 22,000 cc/min; penet 14 (CCW in) - 51.000 cc/min; penet.331

[IIIJ I {SI tank drain) - 1.32,000 cc/min: Limit is approx. 65 ,000 cc/min. In CII!J I addition, penet 28 was designed such that one of the in:_series. :cont. isol.J ..

.' a s valves is Ta 1 ways CAUSE

-S"?S *g ooen*. CAUSE COM,. VALVE ao CODE CODE SUBCODE COMPONENT CODE SUllCODE SUllCODE

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• 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE RE,ORT REVISION

/.":;\ LEAIRO .CVENTYEAR_ REPORT NO. CODE TY'E NO.

1,:.2 REPORT NUMBER 1a 1 a 1 2l l=1 10 Io I 8 I ~ I o 11 I Li l=1 l.!J 22 23 2* 26 27 is 29 JO ll J:Z ACi'ION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRa-. PRIME COM'. COMPONENT TAKEN ACTION ON PLANT _ METHOD

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!JI[] I In previous type C tests "the test methods did not always apply full test OJJJ 1pressure differential across the boundary being tested* In the -case of 1 __

o::I1J 1Penet 28, it is believed that valve stroking prior to testing caused leak-

[Ilil 1age to occur. Leakage has been reduced to T.S. limit Penet 28 has been o::I!J 1modified to provide double valve isolation.

7 8 9 . 80 FACILITY STATUS S 'OWER OTHER STATUS IJQ\

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METHOD OF DISCOVERY DISCOVERY DESCRll'TIDN A

ITTIJ L£.J@ 10 l 0 I OJ@l._......_N_A_____ LJ@I Test Results. ..

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ATTACHMENT TO LER 80-08, Rev.l CONSUMERS POWER COMPANY PALISADES*PLANT DOCKET*50..:.255 Discussion. Containment local leak rate testing is performed in accordance with Palisades Technical Specifications and 10CFR50 Appendix J in order to determine the magnitude of leak.age through containment penetrations.

Acceptance criteria established by 10CFR50 Appendix J permit detection of degradation in penetration boundaries (eg, gaskets, seals, valve seats, valve packings) prior to leak.age rates reaching the allowable containment leak rate.

During the current refueling outage a program to systematically review all Technical Specification surveillance tests was undertaken to assure, among other items, adequacy of test methods and compliance with requirements of basis documents. Review of the local leak rate test program revealed a number of deficiencies which were not apparent when the program was first established. Among these deficiencies were failure to test all penetrations and failure, in some cases, to apply the containment design pressure (55 psig) across the penetration boundary (for example, in the case of the- -

condensate makeup to the shield cooling system, the .system pressure exceeded

• • the test pressure -- .in previous tests,.the test .procedure (R0-32) did not require compensating for this pressure difference). The procedure, which has been extensively revised now includes all testable penetrations and requires 55 psid to be applied across containment per-etration boundaries.

Test Results. Results of leakage measurement prior to and following maintenance are tabulated in Table 1. In summary, the "as found 11 leakage was determined to be 442,260 cc/min; the post maintenance leakage was 29,429 cc/min. - The Technical Specification -limit for *local leak testing is 65 ;200 cc /min.

Evaluation. Although the basi.c cause of the leakage _was_primarily* deterior-ation of valve internals, the inadequacies in the previous version of test procedure R0-32 prevented timely detection of valve deterioration. Accord-ingly, the abnormally high leak rate detected during this outage Would not be expected during the next test. It should be noted that because most local leak tests are performed by pressurizing between two valves in series, the measured leakage is in fact the sum of the individual leakage of the two valves. Therefore, the actual leak.age could be e;{pected, in most cases, to be considerably less than this measured leak.age.

Refer to Figure 1 for the following discussion. Regarding penetration 28 (containment air sample) the design of the handswitch which operates the solenoid valves is such that one of the solenoid valves (2402-L,M,N, or E) is .always energized (open). As a result, a single valve boundary existed between containment atmosphere and the containment hydrogen vent line.

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This penetration has been modified by the addition of two manual valves which provide containment isolation. Additionally, valve SV-2402-L was previously oriented such that.it provided an essentially leak-tight boundary for flow from the hydrogen exhaust line but not in the reverse direction. The valve orientation has been reversed such that leakage through the valve should not occur during containment sampling operations.

Corrective Action. Corrective action to reduce leakage has consisted of valve repair, valve replacement, packing adjustment, valve reorientation, and in the case of penetrations which are no longer used, installation of blank flanges to "eliminate" those penetrations.

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. I AS BUILT AFTER MODIFICATION FIGURE 1 NOTE: This drawing depicts the containment isolation boundary for penetration 28, but does not include all valves.and components.

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PENETRATION DESCRIPTION

.

• AS FOUND LEAKAGE (cc/min). AFTER MAINTENANCE LEAKAGE (cc/min)

Purge Air Supply 2,-740.2 5.3 Purge Air EXhaust 3,354.7 11.0

" *. Purge Exhaust Bypass 12.9 201.6.

Service Air 0.9 Cond to Shld Clg Surge Tank 151,393. 29.7 CCW In 51,301 0 CCW Out 36.5 Cont. HP Switch * ,, 0 CWRT Vent 37*.5

• *N2 to Quench* Tank 186.4 ILRT Fill Line 74.o Cont. Air Sample Line 52,233' 0 Safety Injection Tank Drain 132,000. 195-7 Letdown to Purification I Ex 57.1 Primary Syst Drain Pump Disch 2,296.

Cont Building Htg Stm Return 22,151 Cont Building Htg Stm Supply 368.1 Pressurizer Deadweight Tester* 48 .* o 0 Sample Tube From Decay Coils 221.5 Degasifier Pump Disch 2,081.4 Demin Water To Quench Tank 165.

PCS Bleed Off 0

.Containment.Vent Header 4.1 Primary System Drain 81.8 .

Cont. HP Switch 0 CWRT Circulation Line 190 Containment Sump Drain 2,452.

Reactor Cavity Fill and* Recycle ILRT Instrument Line 404.6 CWRT Pump Discharge 0 57.4 Air Supply to Air Room

• 927.6 CWRT 3.3 Reactor Cavity Drain and Recycle 570 Escape Lock (From S0-4) 1,850.2 Personnel Lock (From S0-4) 3,871.3 Equipment Hatch 4.4 Nort.h *Elec. Pen *3-,153.6 South Elec. Pen 804.9

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PENETRATION DESCRIPTION AS.FOUND LEAKAGE (cc/min) AFTER MAINTENANCE U!AKAGE (cc/min)

Transfer Winch Cable 649.9 201~0 "A" SG Sec Manway - N 2o4 "A" SG Sec Manway - s 488.4 "B II SG Sec Manway - N 2,358.8 "B" SG Sec Manway - s 1,12205 "AS FOUND" AFTER MAINTENANCE TOTALS 442,260 29 ,492*