ML20084K272
| ML20084K272 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/24/1974 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084K274 | List: |
| References | |
| AO-50-254-74-21, NJK-74-173, NUDOCS 8305190246 | |
| Download: ML20084K272 (3) | |
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Cuad-Ci:il Anerating Station ty f'Q2V/.]'
,3 Post Othce'66x 216 Cordova. !!!inois 61242
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Telephone 309/654-2241 NJK-74-173 '
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- Mr. John F. 0 ' Leary,. Di rector
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_ Directorate 6f Licensing Regulation U. S. Atomic Energy Conynission Washington, D. C.
20545
Reference:
quad-Cities Nuclear Power Station Unit I Docket No. 50-254, DPR-29, Appendix A Sections 1.0.A.2, 3.7.D.1, 4.7.D.I.a and 6.6.B.I.a
Dear Mr. O ' Leary:
Enclosed please find Abnormal Occurrence Report No. A0 50-254/74-21 for Quad-Cities Nuclear Power Station. This was previously reported to Region
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to you and Kegion t il, Directorate of Mcgulatory Operations by telecopy also on July 15, 1974.
This report is submitted to you in accordance with the requirements of Technical Speci fication 6.6.B.I.a.
Very truly yours, COMM0lNEALTH EDISON COMPANY
' QUAD-CITIES NUCLEAR POWER STATION CM'JW [
j N. J. Kalivianakis Station Superintendent NJK/JLS/j ch l
l cc: Region iII, Directorate of Regulatory Operations
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'r REPORT NUMDER: A0 254/74-21 REPORT DATE: July 23, 1974 OCCURRENCE DATE: July 14, 1974 r
FACILITY: Quad-Cities Nuclear Power Station Cordova, Illinois 61242 IDENTIFICATION OF OCCURRENCE:
. Failure of recirculation pump seal pressure sensor 1-262-25A instrument line check valve.
CONDITIONS PRIOR TO OCCURRENCE:
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Unit I reactor in shutdown condition.
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Both Unit I recirculation pumps on.
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DESCRIPTION OF OCCURRENCE:
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While doing instrument Department refueling outage surveillance testing of the instru-ment sensing line high flow check valves for the Unit I reci rculat ion pump seals, 'Yt_
was discovered that flow check valve 1-262-25A would not check. The check valve was valved out by closing the instrument isolation valve 1-262-2-3A and tagged out-of-crv!:: for rep !r :nd rep!:::: nt.
A werk rcque t u:: !== d!:t !y in!!!:ted t: In '
vestigate and repair the malfunctioning check valve.
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DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
s The reason the excess flow check v'alve 1-262-25A did not check was' bebause the valve disk and popit were missing. The surveillance test on these valves is 'done once every refueling outage, and was last done on 11-11-71 during the initial startup test-7 "r
Ing of Unit 1.
At that time, the 25A valve passed the test satisfactorily, however, the 1-262-26A did not pass the test. Since having the 1-262-25A valve pass the test l
on 11-11-71 and fall the test on 7-14-74 because of missing parts is inconsistent, an l
crror must have been made during the testing on 11-11-71.
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lt is postulated that the error was made in recording the test results on Il-11-71.
l The 26A ' valve was reported as defective; i t is likely that it was the 25A valve that'
- was defective at that time. The 26A valve was repaired and tested satisfactorily in 1971. The 25A valve was not retested then because it had been satisfactory during the first test. When the valves were retested in 1974, the error showed up by indie' sting the 25A valve was still defective.
l ANALYSIS OF OCCURRENCE:
The purpose of this valve is to check the flow of water through the instrument line in case of a line rupture. The effect of not having this valve in the line is that if the instrument line severed downstream of the I;262-25A valve the flui of water s
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A0 264/74-21 Q Q July 23, 1974 into the Reactor Building through the i-inch instrument line would have been uncheck-cd. Reactor water and steam from the reactor would escape. The steam would condense to water ~ because the temperature in the Reactor Building is below the boiling point of tha steam. This condensate and reactor water. would be collected in the Reactor Build-ing floor drain sumps. Fission products gases might also be released, but they could i
ba handled by the Reactor Building Ventilation System.
Since this line is small, a l'arge inventory of reactor watch could not escape in a short period of time. The manual. isolation, valve 1-262-2-3A could also be closed to stop any leak. Because this situation is easily manageable, the consequences to public hanith and safety would be minimal.
t CORRECTIVE ACTION.:
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A new valve disk and popit were installed. There is no reason to take any further corrective action because the new valve passed the surveillance test and should operate without further problems.
P' F_AI LURE DATA :
The J.-262-26A valve was previously found defective during the Unit 1 pre-operational i
tests. "Flowever, as explained above, itcis felt that this was an error in recording the test results.
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Since it is felt that this is the same valve-that had been defective in 1971, there 1.. no cumuloiive ca,ciicnce iv i..di cots ca, $r...t l..uir.g p.2 b !ct.s.:! th th::: v:!ve:.
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