ML20140F127

Rev 1 to 860131 Special Rept:On 851109,HPCI Into Reactor Vessel Occurred.Rev Changes Reactor Parameter Entitled Coolant Pressure to Coolant Temp. Related Correspondence

ML20140F127
Person / Time
Site:	Limerick
Issue date:	02/28/1986
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
CON-#186-417 OL, NUDOCS 8603310063
Download: ML20140F127 (4)

Text

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0 03gpg PHILADELPHIA ELECTRIC COMPANY DOCKETED

~~~~~~,. USNRC' s 230' U ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 N - Y \9 , ,

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[ February 28, 1986 dh[N ..- ,

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Docket No. . 50-35286.- ._- .

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Dr. Thomas.E. Murley, Regional Administrator i U. S. Nuclear Regulatory Commission

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Region-I J 631 Park Avenue King of Prussia, PA 19406 .

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SUBJECT:

Special Report - High Pressure Coolant Injection (HPCI) System Actuations and Injections' - Limerick '.

Generating Station - Unit 1, Revision 1 '

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REFERENCE:

Technical Specifications 3.5.1.f and 6.9.2 E

Dear.Dr. Murley:

V This revised Special Report is being submitted to correct a  ;

typographical . error in the title of one of the reactor parameters L provided in the Special Report dated January 31, 1986 for a HPCI

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' injection into the reactor vessel which occurred on November 9, 1985 (which was-the third'HPCI injection at that point in time). .-

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The reactor parameter titled " coolant pressure" is being changed to " coolant' temperature" to correct a discrepancy between the l title and the units listed. This change is identified by-a ,

vertical bar'in the margin.

The original Special Report was submitted pursuant to the  ;

requirements of Limerick Generating Station Technical' Specification 3.5.1.f and 6.9.2. Specification 3.5.1.f states, "In the event an ECCS system is actuated and injects water into

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'the reactor coolant system, a Special Report shall be

• prepared and submitted to the Comreissien pursuant to Specification 6.9.2 within 90 days ' describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value- of the usage f actor for each af fected safety injection nozzle - shall' be provided in this Special Report whenever its value ~ exceeds 0.70". Technical Specification 6.9.2 states that, "Special Reports shall be submitted to the Regional Administrator of the Regional Of fice of the NRC within the time period specified .for each report".

B603310063 860228 PDR ADOCK 05000352 g PDR

2860009290 Dr. Thomas E. Murley February 28,-1986' Page 2 This report concerns the occurrence of two High Pressure Coolant Injection (HPCI) System actuations and injections into the reactor coolant system during startup testing of Unit No.1.

Below is a description of each of' the HPCI , system actuation and injection events. [ - ' -

On November 5, 1985, Startup Test Procedure (STP) 15.5, "HPCI .

Cold Quick Start At Rated Pressure CST to RPV", was performed.

This test involved one injection into the vessel at a flowrate of 5,600 gpm for 64 minutes. Reactor parameters for the injection-were as 'follows:

reactor _ thermal power 2052 MWt dome pressure 962.psig . ,

coolant temperature 525 degrees Fahrenheit

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This injection was the second HPCI injection to date. ,

On November 9, 1985 Startup Test Procedure (STP) 15.5 was performed a second time. This test involved one injection into the vessel at a flowrate 5,600 gpm for 62 minutes. Reactor parameters for the injection were as follows:

reactor thermal power 2192 MWt dome pressure 963 psig coolant temperature 527 degrees Fahrenheit l This injection was the third HPCI injection to date.

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The total usage factor for these two events for each af fected safety injection nozzle is 1. fB' N4 for the feedwater -

nozzles and 1.18 N2 for the core spray nozzles. The projected usage fa'ctor for each af fected safety injection nozzle, based on the ef fect of all design transients occurring over the 40 year life of the plant including the increase of each usage factor as a result of these two events, is 7.18 N4 for the feedwater nozzles and 6.07 N1 for the core spray nozzels and therefore is less than 0.70.

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There were no adverse effects as a result of this event, since the injections were part of the Startup Test Program and the projected usage f actor for each af fected safety injection nozzle is less than the Technical Specification limit of 0.70.

Consequently, no corrective actions are to be taken. <

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2860009290 Dr. Thomas E. Murley pebruary 28, 1986 Page 3 ,

. E If you have any questi'ons, do not hesitate to contact. ~

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- Very truly yours, ,

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~ W. T. Ullrich '

Superintendent Nuclear. Generation Division GHS:bic cc: E. M. Kelly, Senior Resident Inspector . ,

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See Attached. Service List

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cc: Troy B. Conner, Jr. , Esq.

Ann P. Hodgdon, Esq.

Mr. Frank R. Romano Mr. Robert L. Anthony Ms. Phyllis Zitzer Charles W. Elliott, Esq.

' Barry M. Hartman, Esq.

Mr. Thomas Gerusky Director,' Penna. Emergency Managetaent Agency Angus' Love, Esq.

David Wersan, Esq.

Robert J. Sugaman, Esq.

Kathryn S. Lewis, Esq. ~

Spence W. Perry, Esq.

Jay M.- Gutierrez, Esq.

Atomic Safety 4 Licensing Appeal Board Atomic 5?fety 4 Licensing Board Panel Docket 4 Service Section ,

E. M. Kelly Timothy R. S. Campbell 4

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