ML18139A383
| ML18139A383 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 05/29/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8007010239 | |
| Download: ML18139A383 (4) | |
Text
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c,\\.f>-R REG<,(.,
e UNITED STATES 1~:~1 NUCLEAR REGULATORY COMMISSION REGION II i
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~o 101 MARIETIA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 MAY 29 1980 In Reply Refer To:
RII:JPO 50-338, 50-339 50-404, 50-~
~280, 50-~>
Virginia Electric and Power Company Attn:
J. H. Ferguson Executive Vice President-Power P.O. Box 26666 Richmond, VA 23261 Gentlemen:
This Information Notice is forwarded for information.
No written response to this Information Notice is required. If you have any questions related to this matter, please contact this office.
Enclosures:
- 1.
IE Information Notice No. 80-23
- 2.
List of Recently Issued IE Information Notices
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Sincerely~*.
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e Virgin.ia Electric fowe.J;' Company cc w/encl:
W. R. Cartwr.igh.t, Station Manager P.O. Box 402 Mineral, Virginia 23261 P. G. Perry Senior Resident Engineer Post Office Box 38 Mineral, Virginia 23117 J. L. Wilson, Manager Post Office Box 315 Surry, Virginia 23883
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.
20555 May 29, 1980 SSINS No. :
6835 Accession No.:
8005050061 IE Information Notice No. 80-23 LOSS OF SUCTION TO EMERGENCY FEEDWATER PUMPS Description of Circumstances:
On April 7, 1980, Arkansas Nuclear One, Unit 2, suffered.a loss of offsite *pb~er due to tornado damage to 500 kv transmission towers.
The unit tripped from 98%
power; the diesel generators started and supplied vital loads; natural circula=*
tion in the reactor coolant system was established; and the emergency feedwater (EFW) pumps supplied feedwater to the steam generators.
The *suction of the EFW pumps was,aligned to the Condensate Storage Tanks (CST) and to the Startup and Blowdown Demineralizer effluent in parallel. Approxi-mately 15 minutes after the unit tripped, both EFW pumps lost suction.
Prompt operator action was taken to isolate the EFW pump suction from the Startup and Blowdown Demineralizer and to vent the EFW pumps.
EFW flow was reestablished within one minute.
Investigation revealed that the EFW pump suction loss was caused by flashing in the main feedwater train forcing hot water through the Startup and Blowdown Demineralizers to the EFW pump suction where it flashed to steam.
The steam caused cavitation of the EFW pumps, and the pressure in the EFW suction header prevented flow from the CST.
The licensee has submitted Licensee Event Report No. 50-368/80-18/031-0, dated May 5, 1980, describing this event. Action to prevent recurrence included revising the EFW system operating procedure and the Plant Startup Procedure to require shutting the EFW suction valve from the Startup and Blowdown.Demineralizers during plant startup at about 5% full power after the steam generator feedwater source has been shifted to a main feedwater pump.
In addition, the EFW suction valve from the Startup and Blowdown Demineralizers will be verified closed once per shift during Mode 1 operation.
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 fo.r 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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IE Information Notice No. 80-23 May 29, 1980 Information Notice No. 80-23 80-22 80-21 80-20 80-19 80-18 80-17 80-16 80-15 RECENTLY ISSUED IE INFORMATION NOTICES Subject Date Issued Loss of Suction to Emergency 5/29/80 Feedwater Pumps Breakdown In Contamination 5/28/80 Control Programs Anchorage and Support of 5/16/80 Safety-Related Electrical Equipment Loss of Decay Heat Removal 5/8/80
- Capability at Davis-~esse Unit 1 While in a Refueling Mode NIOSH Recall of Recircu-
"5/6/80 lating-Mode (Closed-Circuit)
Self-Contained Breathing Apparatus (Rebreathers)
Possible Weapons Smuggling 5/5/80 Pouch Potential Hazards Associated 5/5/80 With Interchangable Parts On Radiographic Equipment Shaft Seal Packing 4/29/80 Causes Binding In Main Steam Swing Check And Isolation Valves Axial (Longitudinal) 4/21/80 Oriented Cracking In Piping e
Enclosure Issued To All power reactor facilities with ~n-, !'
OL or CP All power reactor OLs and near term CPs All power reactor facilities with an 01 or CP All light water reactor facilities holding power reactor OLs or CPs All holders of a power reactor OL, Research Reactor License, Fuel Cycle Facility License and Priority I Material License All power reactor facilities with an OL, fuel fabrication and processing facilities and Materials Priority I licensees (processors and distributors)
All radiography Licenses All power reactor facilities in your Region with an OL or CP All Light Water Reactor Facilities holding power reactor OLs or CPs