ML20154K322

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Forwards Response to IE Bulletin 85-001, Steam Binding of Auxiliary Feedwater Pumps, Discussing Monitoring of Fluid Temp Conditions & Procedure for Restoring Pumps.Rept Re motor-driven Pump Concerns Will Be Submitted by 860314
ML20154K322
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/28/1986
From: Williams J
TOLEDO EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
1-622, IEB-85-001, IEB-85-1, NUDOCS 8603110286
Download: ML20154K322 (6)


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Docket No. 50-346 JOE VVLUAMS. Jn s va n a= s*c. ,

l419] P49 2Eo License No. NPF-3 Id"18dS 522' Serial No. 1-622 February 28, 1986 Mr. James G. Keppler, Regional Administrator United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr. Keppler:

The enclosed report is submitted in response to IE Bulletin 85-01:

Steam Binding of Auxiliary Feedwater Pumps (Log No. 1-1268). Toledo Edison has reviewed IE Bulletin 85-01 and evaluated the potential for steam binding of the auxiliary feedwater (AFW) pumps at the Davis-Besse Nuclear Power Station Unit No. 1. The enclosed report describes Toledo Edison's plans for monitoring fluid temperature conditions of the AFW pumps' discharge on a regular basis when the pumps are required to be operable. In addition, the report describes the procedural method for restoring a steam bound AFW pump.

Toledo Edison has also evaluated the potential for steam binding of the recently installed motor-driven feedwater pump (MDFP). Procedures are under development addressing monitoring of appropriate fluid temperature conditions of the MDFP discharge and the restoration of the MDFP should it become steam bound. The applicability of IE Bulletin 85-01 concerns to the MDFP has been identified by the NRC office of Nuclear Reactor Regulation (NRR) as an unresolved issue requiring resolution before restart authorization. Accordingly, Toledo Edison will submit a report describing the methods used to address these concerns to NRR by March 14, 1986.

As you are aware, Davis-Besse is currently in a shutdown condition.

As discussed with Mr. I. N. Jackiv of your staff on February 25, 1986, 86031102 Gee B60:NNB PDR ADOCK 05000346 Q PDR ThE TOLEDO EDISON COMPANY EDISON PLAZA 300 MAOISON AVENUE TOLEDO, OHIO 43052 //

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Serial No. 1-622 February 28, 1986 Page 2 approval of the procedure, associated training and procedure implemen-tation will be completed by Toledo Edison prior to placing the plant in Mode 3 from the current shutdown.

Very truly yours, J n tv % Jr- ) w _

JW:DRW:p1f Attachment cc: DB-1 NRC Resident Inspector J

ATOMIC ENERGY ACT OF 1954 SECTION 182a SUBMITTAL IN RESPONSE FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 FACILITY OPERATING LICENSE NO. NPF-3 This letter and enclosure is submitted in conformance with Atomic Energy Act of 1954 Section 182a, in response to IE Bulletin 85-01 (Log No.

1-1268). This response addresses steam binding of auxiliary feedwater pumps at the Davis-Besse Nuclear Power Station Unit No. 1.

By /% W %.-

Terry D. Murray G Assistant Vice President, Nuclear For J. Williams, Jr.

Senior Vice President, Nuclear Sworn to and subscribed before me this 28th day of February, 1986.

G - ^- a f bML Notary Public, Stdte of Ohio V My Commission Expires May 16, 1986

fl TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1

RESPONSE

TO IE BULLETIN 85-01

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STEAM BINDING OF AUXILIARY FEEDWATER PUMPS i

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RESPONSE TO STEAM BINDING OF AUXILIARY FEEDWATER PUMPS On October 29, 1985, the Nuclear Regulatory Commission Office of Inspection and Enforcement issued IE Bulletin 85-01: Steam Binding of Auxiliary Feedwater Pumps. Toledo Edison has reviewed IE Bulletin 85-01 and evaluated the potential for steam binding of the Davis-Besse auxiliary feedwater (AFW) pumps. The following briefly describes the AFW system and the procedure under development which will be implemented to address AFW pump steam binding.

AUXILIARY FEEDWATER SYSTEM DESCRIPTION The Davis-Besse AFW system consists of two safety-grade steam turbine-driven AFW pumps capable of being actuated and controlled by safety-grade signals. The pumps are capable of taking suction from the condensate storage tanks or the Class 1 service water system. The design of the AFW pump suction and discharge lines to the steam generators.

AFW pump turbine steam inlet lines, and associated power supplies ensure the AFW system is redundant and independent.

PROCEDURES Toledo Edison is proceduralizing the monitoring of AFW pump discharge fluid conditions on a regular basis during Modes 1 through 3 (when the system is required to be operational). System Procedure SP 1106.06, Revision 24, Auxiliary Feedwater System Procedure, will address AFW pump steam binding.

Under SP 1106.06 an Equipment Operator will monitor, by touching, the AFW pump discharge piping temperature to ensure that the piping fluid is at about ambient temperature. IE Bulletin 85-01 recognizes that elaborate monitoring instrumentation is not necessary and that monitoring the fluid temperature by touching the pipe is acceptable. As an alternative method of monitoring, the Reactor Operator may determine the acceptable temperature of the AFW pump piping discharge header via plant computer points. Under either of these methods, completion of the monitoring will be recorded.

When the plant is in Modes 1 through 3, monitoring will be performed on a frequency of at least twice a day at approximately twelve hour intervals. Should a high (hot) temperature be identified, the Equipment Operator or Reactor Operator will notify the Shift Supervisor. Should an AFW pump be identified as steam bound, SP 1106.06, will require that the normally open AFW pump discharge valve, AF599 or AF608, be closed to allow the steam to be vented from both the pump casing and discharge piping. This will also allow the pump caning and discharge piping to be filled with cool water. If an AFW pump has been steam bound, the frequency of monitoring will be increaned as specified in SP1106.06 until corrective action has been implemented.

IMPLEMENTATION SCHEDULE SP 1106.06, Revision 24, proceduralizing the above steps will be approved and implemented, and training completed, prior to placing the plant in Mode 3 from the current shutdown.

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