ML18044A889
| 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: |
| References | |
| LER-80-008-01X, LER-80-8-1X, NUDOCS 8005160411 | |
| Download: ML18044A889 (6) | |
Text
~ ~0516 ~i/ll (" UPDATE Rf PORT:. PREVIOUS "'REPORT I)ATE 0,4 2980
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PALISADES PLANT NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION
!7*771 LICENSEE EVENT REPORT
'COf\ITROL BLOCK: I 1Q !PLEASE PRINT OR TYPE ALL REQUIRED INFOR~ATIONI 1 ~
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- ~~~~! ~Io 15 10 (o 10 12 15 15 K?)IO 14 11 15 I s 10 @lo. I s Ii I 2 I s I a I@
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 iR 5 a 1 ways on en. 80
- ; " Tc!S CAUSE CAUSE COMP. VALVE CODE CODE SU8CODE COMPONENT CODE SUBCOOE SUBCOOE
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- 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRQ CVENTYEAR REPORT NO. CODE TYPE NO.
@ REPORT NUMBER I8 I 0 I 1.=:::J JO Io I 8 I (/( Io 11 J EU.* l=I l!J 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTIOlll ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER*
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33 34 35 36 37 42 43 44 47 CAUSE DESCRIPTION AND CORREC"rlVE ACTIONS @ .
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.
l B 9 80 FACILITY tjQ\ METHOD OF ~
STATUS % POWER OTHER STATUS ~ DISCOVERY. DISCOVERY DESCRIPTION ~
[ill] l.£J@ 10 I O I O1@1--I_NA_____~ L_J~l.__T_e_s_t~R_e_s_u_lt_s~~~~~~~~~~--l 7 . 8 9 10 . 12 13 44 45 46 80 ACTIVITY CONTENT .t.:;::\
RELEASED OF RELEASE AM.:>UNT OF ACTIVITY~ LOCATION OF RE_LEASE @
~~@~@I NA I NA l 8 9 10 11 44 45 . so PERSONNEL EXPOSURES * ~
A OESCRIPFJ~N ElZJ I 0 I I 0 le;L::J@...._____________,______________,
NuMaEP Tz.PE l B 9 11 12 13 ~ 80 PERSONNEL INJURIES ('.;";'\
NUMBER DESCAtrTION~
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. NA 80 PUBLICITY C\_ C E 0 ISSUEDI'.:"::\ DESCRIPTION~ NA US NLV
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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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2 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 I
I, 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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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 e
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 a 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 2,414 Cont Building Htg Stm Supply 368.1 Pressurizer Deadweight Tester 48.0 0 Sample Tube From Decay Coils* 221.5 Degasifier Pump Disch 2,081.4 Demin Water To Quench Tank PCS Bleed Off 0 Containment.Vent Header 4.1 Primary System Drain 81.8 - .
!
f 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 a 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.
LEAKAGE (cc/min)
Transfer Winch Cable 649.9 201.0 "A" SG-Sec Manway - N 2.4
"-A" sG Sec Miµiway -: s 488.4 "B II SG Sec Manway - N 2;358.8*
"B" SG Sec Manway - s 1,122.5 "AS FOUND" AFTER MAINTENANCE
- . TOTALS 442,260 29,492