ML19345C946
| ML19345C946 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/10/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Papay L SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 8012080650 | |
| Download: ML19345C946 (1) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3,
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j REGION V 1990 N. CALIFORNIA BOULEVARD
%,*,,,#,o*g SUITE 202. WALNUT CREEK PLAZA WALNUT CR EE K. CALIFORNIA 94608 iioveinber 10, 1980 y
Docket Nos..,s-206, 50-361, 50-362
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Soutnern California Edison Company Eso
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P. O. Box 800 e
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2244 Walnut Grove Avenue si Rosemead, Caiifornia 91770
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x Attention: Dr. L..T. Papay, Vice President Advanced Engineering Gentlemen:
This Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for possible applicability to their facilities. No specific action or rdsponse is requested at this time.
If further NRC evaluations so indicat' - an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you nave questions regarding tais matter, please contact tne Director of the appropriate NRC Regional Office.
Sincerely, I'
($. '. ngelken Director
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Enclosures:
1.
IE Information Notice No. 80-41 2.
Recently issued IE Information Notices cc w/ enclosures:
J. M. Curran, SCE R. Dieten, SCE T8012080 50
d SSINS No.: 6835 Accession No.:
8008220260
-UNITED STATES IN 80-41 t-NUCLEAR' REGULATORY COMMISSION CFFICE OF INSPECTION AND ENFORCEMENT:
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A WASHINGTON, D.C.
20555
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~4 CJ November 10, 1980
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IE Information-Notice No. 8u-41: FAILURE OF SWING CHECK VALVE IN.THE DECAY
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HEAT REMOVAL SYSTEM AT DAVIS-8 ESSE UNIT l
l NO. 1
'Descriotion of ' Circumstances:
l-On October 9,1980 the. resident inspector at the Davis-Besse facility was informed that the.ltcensee had performed leak rate tests and identified exces-3 sive leakage through Decay Heat Removal System check valve CF-30. Valve CF-30 l's the~ inboard one of two in-series check valves that is used to isolate the reactos coolant system from the low pressure decay heat removal systen. On further investigation the licensee found that the valve disc and ann had separated from the valve body and was lodged just under-the valve cover plate.
The two 2 5/8 x 5/8 inch bolts and locking mecnanism for the bolts that holds the arm to the valve body were missing and have not been located. The CF-30 l
valve is a 14-inch swing check valve manufactured by Velan Valve Corporation.
The cause of the failure has not been identified.
rhe test that was in-progress when-the failure was identified.was-being. con -
4 ducted in response to a ' letter from' Darrell G. Eisenhut, Office of Nuclear j
Reactor Regulations to all Light. Water Reactor Licensees, LWR Primary Coolant System Pressure Isolation Valves, February 23, 1980.
This IE Information Notice is provided as an early notification of a possibly 1
l significant matter that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to 1
L their facilities. No specif'c action or response is requested at this time.
- If HRC evaluations sa indicata, further licensee actions may be requested or required.
No written response to th!s IE Information' Notice is required.
If you lave any questions regarding this matter, please contact the Director of the j
appropriate NRC Regional Office.
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o IN 80-41 November-10, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information
-Date of Notice No.
Subiect Issue Issued to 80-40 Failure Of Swing Check 11/10/80 All power facilities Valve In The Decay Heat with and OL or CP Removal Systen At Davis-Besse Unit No.1 80-39 Malfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding Valcar Engineering Corporation power reactor OLs or cps 80-38' Cracking In Charging Pump 10/30/80 All PWR facilities Casing Cladding with an OL.or CP 80-37 Containment cooler leaks 10/24/80 All nuclear power and reactor cavity facilities holding flooding at Indian Point power reactor OLs Unit 2 or cps 80-36 Failure of Steam 10/10/80 All nuclear power Generator Support Bolting reactor facilities holding power reactor OLs or cps 80-3a Leaking and dislodged 10/10/80 All categories G and Iodine-124 implant seeds G1 medical licensees 80-34 Baron dilution of reactor 9/26/80 All pressurized water coolant during steam reactor facilities generator decontamination holding power reactor OLs 80-33 Determination of teletherapy 9/15/80 All teletherapy t4-er accuracy (G3) licensees 80-32 Clarification of certain 8/12/80 All NRC and agreement recuirements for Exclu-state licensees sive-use shipments of radioactive materials 80-31 Maloperation of Gould-8/27/80 All light water reactor Brown Boveri Type 480 facilities holding OLs volt type K-6005 and or cps K-CON 6005 circuit breakers t
- Operating Licenses or Construction Permits
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