ML19345C697
| ML19345C697 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/10/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mcdonald R ALABAMA POWER CO. |
| References | |
| NUDOCS 8012080212 | |
| Download: ML19345C697 (1) | |
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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.I REGION il 101 MARIETTA ST., N.W., SUITE 3150 e%g* * * * *,o[
ATLANTA. GEORGIA 30303
.NOV 101980 m
In Reply Refer To:
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ATTN:
R. P. Mcdonald D
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P. O. Box 2641 Birmingham, AL 35291 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 response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely,
..- m James P. O'Reilly Director
Enclosures:
1.
IE Information Notice No. 80-41 2.
List of Recently Issued IE Information Notices cc w/ encl:
W. O. Whitt, Executive Vice President F. L. Clayton, Jr., Senior " ice President H. O. Thrash, Manager-Nuclear Generation O. D. Kingsley, Jr., Manager, Nuclear Engineering and Technical Services J. W. McGowan, Manager-Operations Quality Assurance W. G. Hairston, III, Plant Manager W. C. Petty, Manager-Quality Assurance (Design and Construction)
R. E. Hollands, Jr., QA Supervisor 801206U &
SSINS Ns.: 6835 t
Acccesien No.:
8008220260 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 10, 1980 IE Information Notice No. 80-41: FAILURE OF SWING CHECK VALVE IN THE DECAY HEAT REMOVAL SYSTEM AT DAVIS-BESSE UNIT NO. I Description of Circumstances:
On October 9,1980 the resident inspector at the Davis-Besse facility was informed that the licensee had performed leak rate tests and identified exces-sive leakage through Decay Heat Removal System check valve CF-30.
Valve CF-30 is the inboard one of two in-series check valves that is used to isolate the reactor coolant system from the low pressure decay heat removal system. On further investigation the licensee found that the valve disc and arm 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 mechanism for the bolts that h-Ids the arm to the valve body were missing and have not been located. The CF a0 valve is a 14-inch swing check valve manufactured by Veles '.alve Corporation.
The cause of the failure has not been identified.
The test that was in progress when the failure was identified was being con-ducted in response to a letter from Darrell G. Eisenhut, Office of Nuclear 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
.significant matter that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to their facilities. No specific action or response is requested at this time.
If NRC evaluations so indicate, further licensee actions may be requested or required.
No written response to this IE Information Notice is required.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
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y IN 80-41 N:vember 10, 1980 i
h RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 80-41 Failure to Swing Check Valve 11/10/80 All nuclear power reactor' in the Decay Heat Removal facilities with an OL System at Davie-Besse Unit or CP -
No. 1 80-40 Failure Of Swing Check 11/10/80 All power facilities Valve In The Decay Heat with and OL or CP Removal System At Davis-Besse Unit No. I 80-39 Malfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding Valcor Engineering Corporation power reactor OLs or C.;
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 80-3F Leaking and dislodged 10/10/80 All categories G and Iodine-124 implant seeds G1 medical licensees 80-34 Boron dilution of reactor 9/26/80 All pressurized water coolant during steam reactor faci.11 ties generator decontamination holding power reactor OLs 80-33, Determination of teletherapy. 9/15/80 All teletherapy timer accuracy (G3) licensees 80-32
. Clarification of certain 8/12/80 All NRC and agreement requirements for Exclu-state licensees sive-use shipments of radioactive materials-80-31 Maloperation'of Gould-8/27/80 All light water reactor Brewn Boveri Type 480 facilities holding OLs volt type K-600S and or cps K-DON 600S circuit breakers
- Operating Licenses or Construction Permits