ML19257D442

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LER 80-003/03L-0:on 800106,during Surveillance Testing of torus-to-drywell Vacuum Breakers,Torus Water Level Decreased Approx 1 Inch Below Tech Spec Limit.Caused by Testing of Breakers,Allowing Torus Water to Fill Downcomer Pipes
ML19257D442
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 01/29/1980
From: W. Verne Childs
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19257D441 List:
References
LER-80-003-03L, LER-80-3-3L, NUDOCS 8002040412
Download: ML19257D442 (2)


Text

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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l During surveillance ~ testing of torus to drywell vacuum breakers, the l o 3 g torus water level decreased to a point approximately one inch below l o yj l the limi t of T.S. 3.7. A.1 as a resul t of the vacuum breaker t'esting. I o s ; Since the volume of water in the torus did not change, no significant I o c, l hazard was present. l I O 7 l See attachment for details. l 0 8 l BC 7 8 9 SY ST E *.1 CAUSE C At,50 CGt' P . VALVE CODE CCCE SUBCOCE COMFCNENT CODE SUBCOCE SUCCODE 7

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POWER AUTHORITY OF THE STATE OF NEW YORK

- JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 80-003/03L-0 Page 1 of I During normal operation, while conducting Operations Surveillance Test F-ST-15A titled " Pressure Suppression Chamber-Drywell Vacuum Breakers Opening and Closing Test," torus water level decreased to approximately 1" below the limits of Technical Speci fications Appendix A, Paragraph 3.7.A.I. The decreased torus level was a di rect result of the surveillance testing being conducted which requires that the drywell to torus differential pressure be decreased to "0" psi. Elimination of the drywell to torus di f ferential pressure allows the vent header downcomers to be reflooded with water resulting in a lower water level in the torus. Since the volune of water contained in the torus did not change, and the surveillance testing was being conducted to satisfy Technical Speci fication requi rements ,

the event did not represent any signi ficant hazard to the public health and safety.

Reestablishment of the drywell to torus dif ferential pressure approx-imately one hour later restored torus water level to within the limits of Technical Specifications. In addition, a Technical Speci fication amendment request has been submitted to NRC:NRR to allow torus water level changes beyond the current Techni cal Speci ficat ion nimits during required surveil-lance testing.

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