ML20155A357
| ML20155A357 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1986 |
| From: | Barr K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Lees E GENERAL ELECTRIC CO. |
| References | |
| IEIN-86-017, IEIN-86-17, NUDOCS 8604080379 | |
| Download: ML20155A357 (1) | |
Text
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MAR 311986 General Electric Company ATTN: Mr. Eugene A. Lees, General Manager Nuclear Fuel and Component Manufacturing P. O. Box 780 Wilmington, NC 28402 Gentlemen:
SUBJECT:
IE INFORMATION NOTICE NO. 86-17: UPDATE OF FAILURE OF AUTOMATIC SPRINKLER SYSTEM VALVES TO OPERATE Enclosed is a copy of IE Information Notice No. 86-17: Update of Failure of Automatic Sprinkler System Valves to Operate. This notice is provided to inform you of the continuing problems of the operational failure of 6-inch deluge and pre-action fire protection water control valves. As stated in the notice, this information is provided for information purposes only and no specific action or written response is required.
Sincerely, Kenneth P. Barr, Chief Nuclear Materials Safety and Safeguards Branch Division of Radiation Safety and Safeguards
Enclosure:
IE Information Notice No. 86-17 cc w/ encl:
T. Preston Winslow, Manager Licensing and Nuclear Materials Management bec w/o encl:
Document Control Desk License Fee Management Branch State of North Carolina RII RII
- vdh EM ne 03/3y86 03/3/ /86 l 8604080379 860331
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e l ' SINS No.: 6835 IN 86-17 N
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
- WASHINGTON, DC 20555 March 24, 1986 IE INFORMATION NOTICE NO. 86-17: UPDATE OF FAILURE OF AUTOMATIC SPRINK SYSTEM VALVES TO OPERATE Addressees:
All nuclear power reactor f acilities holding an operating license (OL) or a construction permit (CP).
Purpose:
This is a notice of the continuing problems of the operational failure of 6-inch '~
deluge and pre-action fire protection water control valves, identified as Model C, manufactured by Automatic Sprinkler Corporation of America (ASCOA) of Cleveland, Ohio. This notice supplemerts information contained in Information Notice (IN) 84-16, issued on March 2,1984.
It is expected that recipients will review the information for applicability to their facilities and consider actions, if appropriate, to preclude similar
,preblems from occurring at their facilities. However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Description of Circumstances:
The NRC received a copy of a notification from ASCOA in January of 1986 stat.tng that previous instructions issued to customers in late 1984 or early 1985 concerning maintenance to the 6-inch Model C deluge and pre-action valve was inadequate to prevent the failure-to-actuate problems that had been experienced.
In September of 1983, Mississippi Power and Light reported the failure of one of these valves to actuate during a fire in the emergency diesel / generator and the failures of two other identical valves to actuate during tests. These events and subsequent licensee findings are detailed in IN 84-16. That information notice stated that ASCOA was evaluating the failures.
In June of 1984, ASCOA concluded in a letter to NRC that the Grand Gulf events were plant unique. In November of 1984, ASCOA informed the NRC that three separate reports of tne 6-inch Model C valve failing to actuate under certain circumstances had caused them to re-evaluate their previous conclusion. They provided NRC with an advanced copy of instructions to customers on the nature of the problem, identification of affected systems, and a recommended course of action to be taken to correct the problem. ASCOA stated this notification would be sent to all their nuclear customers.
p?/YO Y
1 I IN 86-17
,, March 24, 1986 Page 2 of 2 l 1
The most recent ASCOA instructions (circa January 1986) supersede the previous instructions and state that the previously recommended maintenance procedure is inadequate. These instructions provide what is termed a " temporary solution."
A tentative date for availability of a permanent solution, additional information for identification of affected valves, and a course of action described by ASCOA as " required" for the elimination of the problem are also given. However, it is not clear that this notification has been sent to all nuclear customers.
Licensees who have not received this communication from ASCOA are encouraged to contact their ASC0A represe'ntative for this important information.
No specific action or written response is required by this notice. If you have any questions about this matter, please contact the Regional Acministrator of the appropriate regional office or this office.
Edward L. Jordan, Director ..
Division of Emergency Preparedness ,
and Engineering Response Office of Inspection and Enforcement Technical
Contact:
Mary S. Wegner, IE 301-492-4511
Attachment:
List of Recently Issued IE Information Notices
I Attach cnt 1 y IN 86-17 March 24, 1986 LIST OF RECENTLY ISSUED
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IE INFORMATION NOTICES Information Date of Notice No. Subject Issue Issued to 86-16 Failures To Identify Contain- 3/11/86 All power reactor ment Leakage Due To Inadecuate facilities holding Local Testing of BWR Vacuum an OL or CP Relief System Valves 86-15 Loss Of Offsite Power Caused 3/10/86 All power reactor By Problems In Fiber Optics facilities holding Systems an OL or CP 86-14 PWR Auxiliary Feedwater Pump 3/10/86 All power reactor Turbine Control Proelems facilities holding an OL or CP 86-13 Standby Liquid Control 2/21/86 All BWR facilities System Squib Valves Failure holding an OL or CP To Fire 86-12 Target Rock Two-Stage SRV 2/25/86 All power reactor Setpoint Orift facilities holding an OL or CP 86-11 Inadequate Service Water 2/25/86 All power reactor Protection Against Core Melt facilities holding Frecuency an OL or CP 84-69 Operation Of Emergency Diesel 2/24/86 All power reactor Sup. 1 Generators facilities holding an OL or CP 86-10 Safety Parameter Cisplay 2/13/86 All power reactor System Malfunctions facilities holding an OL or CP 86-09 Failure Of Check And Stop 2/3/86 All rower reactor Check Valves Subjected To facilities holding Low Flow Conditions an OL or CP 86-08 Licensee Event Report (LER) 2/3/86 All power reactor Format Modification facilities holding an OL or CP OL = Operating License CP = Construction Permit
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