ML20154G068

Special Rept:On 851105 & 09,two HPCI Sys Actuations & Injections Into RCS Occurred During Startup Testing.No Adverse Effects Noted.No Corrective Actions Necessary

ML20154G068
Person / Time
Site:	Limerick
Issue date:	01/31/1986
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
CON-#186-090, CON-#186-90 OL, NUDOCS 8603070577
Download: ML20154G068 (2)

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PHILADELPHIA ELECTRIC COMPANY 23ol MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.191o1 12151841 4000 January 31, 1986 Docket No. 50-352 i

Dr. Thomas E. Murley, Regional Administrator U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

SUBJECT:

Special Report - liigh Pressure Coolant Injection (HPCI) System Actuations and Injections - Limerick Generating Station - Unit 1

REFERENCE:

Technical Specifications 3.5.1.f and 6.9.2 l

Dear Dr. Murley:

This Special Report is being submitted pursuant to the requirements of Limerick Generating Station Technical i Specification 3.5.1. f and 6.9.2. Speci fication 3.5.1. f states, "In the event an ECCS system is actuated and injects water into  !

the reactor coolant system, a Special Report shall be prepared ,

and submitted to the Commission 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 factor for each affected safety injection nozzle shall be provided in this Special Report whenever its  ;

value exceeds 0.70". Technical Speci fication 6.9.2 states that,  ;

"Special Reports shall be submitted to the Regional Administrator l of the Regional Of fice of the NRC within the time period specified for each report". l i'

This report concerns the occurrence of two liigh 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 IIPCI system actuation  !

and injection events.

l' On November 5, 1985, Startup Test Procedure (STP) 15.5, "HP CI Cold-Quick Start At Rated Pressure CST to RPV", was performed.

This test involved one injection into the vessel at a flowrate of 9603070577 B60131 3 PDH ADOCK 05000352 ;k/

g PDH -

Dr. Thomas E. Murley Jcnuary 31, 1986 Page 2 5,600 gpm for 64 minutes. Reactor parameters for the injection were na follows:

reactor thermal power 2052 MWt done pressare 962 psig coolant temperature 525 degrees Fahrenheit i

t This injection was the second HPCI injection to date.

I On November 9, 1985 Startup Test Procedure (STP) 15.5 i

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:

i i reactor thermal power 2192 MWt I dome pressure 963 psig i

coolant pressure 527 degrees Fahrenheit This injection was the third HPCI injection to date.

The total usage factor for these two events for each l affected safety injection nozzle is 1.18 N4 for the feedwater nozzles and 1.18 N2 for the core spray nozzles. The projected usage f actor for each aff ected safety injection nozzle, based on

, the ef fect of all design transients occurring over the 40 year i 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 nozzols and therefore is less than 0.70.

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 factor 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.

If you have any questions, do not hesitate to contact us.

Very truly yours, 1

7tt J W. T. Ullrich Supe rintendent t

Nuclear Generation Division cc: E. M. Kelly, Senior Resident Inspector See Attached Service List