05000255/LER-1980-008-01, Test Results of Type C Containment Leak Tests Indicated Local Leakage in Excess of Tech Specs.Caused by Deterioration of Valve Internals

Test Results of Type C Containment Leak Tests Indicated Local Leakage in Excess of Tech Specs.Caused by Deterioration of Valve Internals

ML18044A889
Person / Time
Site:	Palisades
Issue date:	05/12/1980
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML18044A885	List: 05000255/LER-1980-008, Forwards Updated LER 80-008/01X-1 05000255/LER-1980-008-01, Test Results of Type C Containment Leak Tests Indicated Local Leakage in Excess of Tech Specs.Caused by Deterioration of Valve Internals
References
LER-80-008-01X, LER-80-8-1X, NUDOCS 8005160411
Download: ML18044A889 (6)

LER-1980-008, Test Results of Type C Containment Leak Tests Indicated Local Leakage in Excess of Tech Specs.Caused by Deterioration of Valve Internals

Event date:
Report date:
2551980008R01 - NRC Website

text

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UPDATE Rf PORT:. PREVIOUS "'REPORT I)ATE 0,4 2980

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PALISADES PLANT NRC FORM 366

!7*771 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT

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!PLEASE PRINT OR TYPE ALL REQUIRED INFOR~ATIONI

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LICENSEE CODE 14

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60 61 DOCKET.NUMBER 68 69 EVENT DATE 74 75 REPORT CATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

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

[))TI I excess of the limH. 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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[QJIJ 1 penet~. 28 {Cont. air sample) - 52,000 cc/min; penetration 38 (heating [QJ)) I steam return) 22,000 cc/min; penet 14 (CCW in). - 51,000 cc/min; penet.331

• IIITJ r. (SI tank drain) -

1.32, 000 cc/min:

Limit is approx. 65,000 cc/min~ In

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

1 a s. valves iR5 a 1 ways on en.

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CAUSE

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SUPPLIER ACTION FUTURE EFFECT SHUTDOWN

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COMPONENT MANUFACTURER*

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CAUSE DESCRIPTION AND CORREC"rlVE ACTIONS @

44 47 D:::m I In previous type C tests. -the test methods did not always apply full test DJ)) I pressure *differential *across the bounda~y being tested;-

In the -case of 1 __ -**

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

[!))] 1age to occur.

Leakage has been reduced to T.S. limit Penet 18 has been ITTIJ 1modified to provide double valve isolation.

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• e 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 leakage 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 leakage 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 pressiire (55 psig) across the penetration boundary (for example, in the case of the* -

condensate makeup to the shield cooling system, the system pressu~e 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" leakage was determined to be 442,260 cc/min; tpe post maintenance leakage was 29,429 cc/min. - The Technical Specification -limit for.. local leak testing is 65,"200 cc/min.

Evaluation. Although the basic 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 dete.rioration.. 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 leakage could be eJtpected, in most cases, to be considerably* less than this measured leakage.

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 c,ontainment 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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This drawing depicts the containment isolation boundary for penetration 28, but does not include all valves.and components.

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"'* ' PENETRATION DESCRIPTION Purge Air Supply Purge Air Exhaust Purge.Exhaust Bypass Service. Air Cond to *shld Clg Surge Tank CCW In CCW Out Cont. HP Switch CWRT Vent N2 to Quench Tank ILRT Fill Line Cont. Air Sample Line Safety Injection Tank Drain Letdown to Purification I Ex Primary Syst Drain Pump Disch Cont Building Htg Stm Return Cont Building Htg Stm Supply Pressurizer Deadweight Tester Sample Tube From Decay Coils*

Degasifier Pump Disch Demin Water To Quench Tank PCS Bleed Off Containment.Vent Header Primary System Drain I f Cont. HP Switch *

• CWRT Circulation Line Containment Sump Drain Reactor Cavity Fill and Recycle ILRT Instrument Line

• CWRT Pump Discharge Air Supply to Air Room

• CWRT Reactor Cavity Drain and Recycle Escape Lock (From S0-4)

Personnel Lock (From S0-4)

Equipment Hatch

• Nort.h *Elec. Pen South Elec. Pen e

AS FOUND LEAKAGE (cc/min) 2,740.2 3,354.7 12.9 0.9 151,393~

51,301 36.5 37.5

• 186.4 74.o 52,233 132,000.

57.1 2,296.

22,151 368.1 48.0 221.5 2,081.4 4.1 81.8 -.

190*.

2,452 404.6 a

927.6 3.3 570 1,850.2 3,871.3 4.4 AFTER MAINTENANCE LEAKAGE (cc/min) 5.3 11.0*

201.6 29.7 0

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. 195. 7 2,414 0

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'3*,153.6 804.9

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• .PENETRATION DESCRIPTION Transfer Winch Cable "A" SG-Sec Manway -

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"-A" sG Sec Miµiway -: s "B II SG Sec Manway - N "B" SG Sec Manway - s

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AS FOUND LEAKAGE (cc/min)

AFTER MAINTENANCE.

LEAKAGE (cc/min) 649.9 2.4 488.4 2;358.8*

1,122.5 "AS FOUND" 442,260 201.0 AFTER MAINTENANCE 29,492

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