ML18082A655
| ML18082A655 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/29/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 8007010300 | |
| Download: ML18082A655 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-272 50-311 Public Service El ectri*c and Gas Company ATIN:
Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Gentlemen:
May 29, 1980 The enclosed IE Information Notice No.* 80-23, 11Loss of Suction To Emergency Feedwater Pumps 11, is forwarded to you for information.
No written response is required. If you desire additional information regarding this matter, please* contact this office.
S.i nee rely,
Enclosures:
L IE Infarmati on Nati ce No. 80-23
- 2.
List of Recently Issued IE Information Notices CONTACT:
E. G. GrBenman (215-337-5267) cc w/encls:
F. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station soo70103oo
_,./~
I l)
ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF.INSPECTION AND ENFORCEMENT WASHINGTON, D. C.
20555 SSINS No.:
6835 Accession No. :
8005050061 IE Information Notice No. 80*23 Date:
May 29, 1980 Page lof l LOSS OF SUCTION TO EMERGENCY FEEDWATER PUMPS Description of Circumstances:
On April 7,.1980, Arkansas Nuclear One, Unit 2, suffered a loss of offsite power.
due to tornado damage to 500 kv transmission towers.
The unit tripped from 98%.
power; the diesel gene.rators started and supplied vital loads;. natural circula-tion in the reactor coolant system was established; and the emergency feedwater
( EFW) pumps supp 1 i ed feedwater to the steam generators..
The suctfon of the EFW pumps was aligned to the Condensate Storage Tanks (CST)
.and to the Startup and Slowdown 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.
Slowdown Demineralizer. and to vent the EFW pumps.* EFW flow was re-established 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 Slowdown 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. 50-368/80-18/03L-O, 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 Slowdown 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 s4ction valve from the Startup and Slowdown 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 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.
....._~-...........
Information Notice No. 80-15 80-16 80-17 80-18 80-19
~ 80-20 80-21 80-22
.ENCLOSURE 2 IE Information Notice No. 80-23 Date:
May 29, 1980 Page l of 1 RECENTLY ISSUED IE INFORMATION NOTICES Subject Date IS sued.
Axial (Longitudinal) 4/21/80 Oriented Cracking in Piping Shaft Seal Packing 5/5/80 Causes Binding in Main Steam. Swing Check and Isolation Valves Potential Hazards 5/5/80.
Associated With Interchangeable Parts On Radiogr.aphic Equipment Possible Weapons 5/5/80 Smuggling Pouch NIOSH Recall of Recir-5/6/80 culation-Mode (Closed-Circuit) Self-Contained Breathing Apparatus
( Rebreathe.rs)
Loss of Decay Heat Re-5/8/80 nioval Capability at Davis-Besse Unit 1 While in Refueling Mode Anchorage and Support 5/16/80 of Safety-Related Electrical Equipment Breakdown in Contamin-5/28/80 ation Control Systems Issued to All Power Reactor Facil-ities with an Operating License (OL) or Construc-tion Permit (CP)
All Power Reactor Facil-ities with an OL or CP All Radiographic Licensees.
All Power Reactor Faci-lities with an OL, fuel.
Fabrication and Processing Facilities and Materials Priority I Licensees All Power Reactors with an