05000387/LER-1984-047, Forwards LER 84-047-00,originally Issued on 841130.LER Reissued Due to Apparent Distribution Problems

Forwards LER 84-047-00,originally Issued on 841130.LER Reissued Due to Apparent Distribution Problems

ML20102C090
Person / Time
Site:	Susquehanna
Issue date:	02/22/1985
From:	Piemontese A PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
PLAS-042, PLAS-42, NUDOCS 8503050218
Download: ML20102C090 (1)

LER-2084-047, Forwards LER 84-047-00,originally Issued on 841130.LER Reissued Due to Apparent Distribution Problems

Event date:
Report date:
3872084047R00 - NRC Website

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PPat P;nnsylvania Powcr & Light Company Two North Ninth Street

• Allentown, PA 18101

• 215/ 770 5151 February 22, 1985 U.S. Nuclear Regulatory Commission Document Control Desk Wash ing ton , DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE' EVENT REPORT 84-047-00 ER 100450 FILE 841-23 PLAS-042 Docket No. 50-387 License No. NPF-14 Attached is a copy of Licensee Event Report 84-047-00. This was originally issued November 30, 1984. Due to apparent distribution problems, this is being reissued.

A.P. Piemontese Compllance SJS/pjg Attachment cc: Dr. Thomas E. Murley Regional Administrator, Region i U.S. Nuclear Regulatory Commission 631 Park Avenuc King of Prussia, PA 19406 Mr. R.H. Jacobs Senior Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655 f

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Shortly before 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on November 2, 1984, Operations personnel were in the process of placing the ' A' Reactor Water Cleanup (RWCU) Filter Demineralizer in service in accordance with OP-161-001 " Reactor Water Cleanup" following backwash and precoat operations. During delsolation of the ' A' Fil ter Demineralizer, total RWCU system flow exceeded the system's high flow trip settings (approximately 415 gpm), causing system containment isolation valves 1F001 and IF004 to shut.

The cause of the system isolation was determined to be t he result of a surge in system flow created by excessive air in the ' A' Fil ter Demin-eralizer as the result of an extended period of precoat operation.

The System isolation valves were opened at 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br />.

As a result of this occurrance, RWCU system operating procedures are being revised to ensure the demineralizers are filled and verted prior to de-Isolation; precoat operations will be limited in time. This event will be reviewed with Operations personnel.

Isolation of the RWCU system is an Engineered Safety Feature (ESF) actuation p due to the closure of the system's containment isolation valves. The V occurrence of this event had no adverse ef fects on the heal th and saf ety g of the publIc. J

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0 l0 0 l2 OF 0 l2 rexr m .- -aac e m4mm Shortly before 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> dn November 2,1984, Operations personnel were in the process of placing the 'A' RWCU Filter Demineralizer in service in accordance with OP-161-001

" Reactor Water Clean Up" following backwash and precoat operations. The Filter Bypss valve was closed and RWCU System flow was reduced to approximately 210 pgm. During deisolation of the 'A' Filter Demineralizer, total RWCU system flow quickly increased to greater than 400 gpm, exceeding the system high flow trip settings causing valves IF001 and 1F004 to go shut, isolating the RWCU system from the plants reactor coolant system. The high flow trip settings for valves IF001 and IF004 are 415 gpm and 417 gpm respectively.

A Limiting Condition for Operation was entered at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> in accordance with T.S. 3.4.4 to sample Reactor Coolant once every four hours, but was cleared at 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br /> when it was learned that the cause for the occurrence was a surge in system flow created by excessive air in the 'A' Filter Demineralizer as the result of an extended period of precoat operation; the air was drawn into the Demineralizer during precoat operations from the precoat tank. The Demineralizer precoat cycle normally last eighteen minutes, but can be extended if Chemistry determines it needs to be.

As a result of this occurrence, OP-161-001 (Unit 1) and OP-261-001 (Unit 2) are being revised to ensure RWCU Filter Demineralizers are filled and vented prior to deisolation and opening of the demineralizer inlet valve. In addition, a precaution will be added to limit demineralizers precoat operating time. This event has been placed on the 9 Operations Supervisor's Training Agenda and will be reviewed with Operations personnel.

Isolation of the RWCU System is an Engineered Safety Feature (ESF) actuation due to the closure of the systems Containment 1 solation Valve. The occurrence of this event had no adverse effects on the health and safety of the public.

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PPaL SUSQUEHANNA STEAM ELECTRIC STATION PO B0X 467, BERWICK, PA 18603

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November 30, 1984 U.S. Nuclear Regulatory Commission Document Control Desk Wa sh i ng ton , DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 84-047-00 ER 100450 FILE 841-23 PLAS- 015 Docket No. 50-387 License No. NPF-14 Attached is Licer.see Event Report 84-047-00. This event was determined reportable per 10CFR50.73(a)(2)(iv), in that an unplanned Engineered Safety Feature (ESF) actuation occurred.

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V 1 M1 H. . Keiser Superintendent of Plant-Susquehanna BLW/pjg cc: Dr. Thomas E. Murley Regional Administrator, Region i U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. R.H. Jacobs Senior Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655

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