ML20155F246

Special Rept:On 860102 & 13,RCIC Sys Actuated & Injected to Reactor Pressure Vessel.Caused by Potential Low Water Level During Planned Turbine Trip & Decreasing Water Level, Respectively.Related Correspondence

ML20155F246
Person / Time
Site:	Limerick
Issue date:	03/05/1986
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
CON-#286-415 OL, NUDOCS 8604210430
Download: ML20155F246 (3)

Text

15?p; M/T LE1Altu CURRE.SPONDENCQ PHILADELPHIA ELECTRIC COMPANY l 2301 MARKET STREET 00CMETED P.O. BOX 8699 PHILADELPHIA. PA.191o1 msieu 4ooo

'86 MAR 17 31 :19 March 5, 1986 kMYT$G $ dry' BRANCH Docket No. 50-3 52 6G_.

Dr. Thomas E. Murley, Administrator U. S. Nuclear Regulatory Commission Region I

• 631 Park Avenue King of Prussia, PA 19406

SUBJECT:

Special Report - Reactor Core Isolation Cooling (RCIC) System Actuations and Injections - Limerick Generating Station - Unit 1

REFERENCE:

Technical Specifications 3.7. 3.b and 6.9. 2

Dear Dr. Murley:

This Special Report is being submitted pursuant to the requirements of Limerick Generating Station Technical Specification 3.7. 3.b and 6.9. 2. Specification 3.7.3.b states, "In the event the RCIC 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." Technical Specification 6.9.2 states, "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".

This report concerns the occurrence of three Reactor Core Isolation Cooling (RCIC) system actuations and injections into the reactor coolant system of Unit No.l.

Below is a description of each of the RCIC system actuation and injection events.

On January 2, 1986 the Reactor Core Isolation Cooling (RCIC) system actuated and injected to the reacior pressure vessel. The actuation occurred manually in response to potential low water level during a planned turbine trip under the purview of STP-27.4

" Turbine Trip at Test Condition 6".

8604210430 860305 PDR ADOCK 05000352

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I Dr. Thomas E. Murley March 5, 1986

l. Page 2

. Reactor parameters prior to the transient (test) were as follows: '

Reactor Power - 3259 MWt Reactor Coolant System Pressure i 1003 PSIG Moderator Temperature - 542 deg. F

• Core Flow - 98.9 Mlba/Hr.

Feedwater Flow - 14.1 Mlbm/Hr.

Feedwater Temperature - 426 deg. F .

RCIC injected twice for a total of approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

l The RCIC flow was directed to the reactor vessel until the pump i

tripped on high reacter water level. The pump was subsequently restarted with the flow directed to the condensate storage tank.*

Once the reactor water level. dropped to an acceptable level, the RCIC flow was again directed to the reactor vessel to control water level. Therefore, two actuations and injections occurred during the transient. These constitute the sixteenth and seventeenth RCIC actuations and injections to date.

On January 13, 1986 the Reactor Core Isolation Cooling (RCIC) system actuated and injected to the reactor pressure vessel. The actuation occurred manually in response to decreasing water level after a reactor trip to shut down to repair control valve #4.

I Reactor parameters prior to the transient were as follows:

Reactor Power - 930 MWt Reactor Coolant System Pressure - 931 PSIG Moderator Temperature - 522 deg. F Core Flow - 58.9 Mlbm/Hr.

Feedwater Flow - 3.59 Mlbm/Hr.

Feedwater Temperature - 322 deg. F Average RCIC flow was approximately 600 gpm which operated continously for approximately 17 minutes. This

• constitutes the eighteenth RCIC actuation and injection to date.

Since RCIC operated as designed to control level, no corrective action is to be taken.

Should you require additional information, please do not hesitate to contact us. I Very truly yours, NT W. T. Ullrich Superintendent Nuclear Generation Division cc: E. M. Kelly, Senior Resident Inspector See Attached Service List i

L_1-__ - _ _ _ - _ _ . _ _ _ - __ ._. ..

f. . . ,o .

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 Management Agency ,

Angus Love, Esq.

David Warsan, Esq.

Robert J. Sugarman, Esq.

Kathryn S. Lewis, Esq.

Spence W. Perry, Esq.

Jay M. Gutierrez, Esq. ,

': Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies)

E. M. Kelly

. Timothy R. S. Campbell i

t i

il

t February 4, 1986

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