ML20155A189
| ML20155A189 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1986 |
| From: | Barr K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Loch E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| IEIN-86-017, IEIN-86-17, NUDOCS 8604080311 | |
| Download: ML20155A189 (1) | |
Text
r.
MAR 3i ses
- Westinghouse Electric Corporation ATTN: Mr. E. P. Loch, Manager Columbia Plant Nuclear Fuel Division Drawer R Columbia, SC .29250 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 l
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, f
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 l
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Document Control Desk License Fee Management Branch State of South Carolina RII RII J e:vdh 7MK EMcATpine 03 t/86 03/31/86 e6040001186,,PSNT PDR TOPRP E PDR C f
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- ATLANTA, GEORGI A 30323
'..... MAR 311986 Westinghouse Electric Corporation ATTN: Mr. E. P. Loch, Manager Columbia Plant Nuclear Fuel Division Drawer R Columbia, SC 29250 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, C
f s, KennethP.Barr,
, , r--
Chiel Nuclear Materials Safety and Safeguards Branch Division of Radiation Safety and Safeguards
Enclosure:
IE Information Notice No. 86-17 f6
SINS No.: 6435 '
IN 86-17 UNITED STATES NUCLEAR REGULATORY COMMISSION CFFICE OF INSPECTION AND ENFORCEMENT
.- WASHINGTON. DC 20555 Maren 24, 1986 IE INFORMATION NOTICE NO. 86-17: UPDATE OF FAILURE OF AUTOMATIC SPRINKLER 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 supplements 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
, problems 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 stating that previous instructiors 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 ceperienced.
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 ASC0A was evaluating the failures.
In June of 1984, ASC0A concluded in a letter to NRC that the Grand Gulf events j were plant unique. In November of 1984, ASCOA informed the NRC that three
! separate reports of the 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 l 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.
l
- IN 86-17
- March 24, 1986 Page 2 of 2 The mo.*, recent ASCOA instructions (circa January 1986) supersede the previous instructions and state that the previously recommended maintenance procedure is inadequate. These instructions provide wnat 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 ASC0A 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 commur.ication from ASCOA are encouraged to contact their ASCOA representative for this important information.
No specific action er written response is required by this notice. If you have any questions about this matter, please contact the Regional Administrator of the appropriate regional office or this office.
Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enfor:etent Technical
Contact:
Mary S. Wegner, IE 301-492-4511
Attachment:
List of Recently Issued IE Information Notices
I
. Att cheent 1
. . IN 86-17 March 24, 1986 LIST OF RECENTLY ISSUED 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 Inadeauate 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 Problems 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 Drift facilities holding an OL or CP 86-11 Inadequate Service Water 2/25/86 All power reactor Protection Against Core Melt facilities holding Frequency 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 Display 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 power 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 1
l OL = Operating License l CP = Construction Permit i
l i