ML20137C486

Special Rept:On 850816,0911,12 & 16 During Startup Testing, RCIC Sys Actuations & Injections Into RCS Occurred.Incidents Part of Startup Testing.No Corrective Actions Required

ML20137C486
Person / Time
Site:	Limerick
Issue date:	11/14/1985
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8511260514
Download: ML20137C486 (4)

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 0699 PHILADELPHIA. PA.19101 1215)841-4000 November 14, 1985 Docket No. 50-352 Dr. Thomas E. Murley, Administrator U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

SUBJECT:

Special Report - Reactor Coro 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. Murlays This Special Report in being submitted pursuant to the requirements of Limerick Generating Station Technical Specification 3.7.3.b which states that, In the ovant the RCIC system is actuated and injects water into the reactor coolant system, a Special Report shall be prepared and submitted to the Commission purnuant to Specification 6.9.2 within 90 days doncribing the circumstances of the actuation and the total accumulated actuation cycles to dato", and Technical Specification 6.9.2 which states that, "Special Reports shall bo submitted to the Regional Administrator of the Regional Of fice of the NRC within the timo period speci f led for each report. "

This report concerna the occurrence of six Roactor Core b

emA Inolation Cooling (RCIC) system actuations and injections into the reactor coolant syntom during ntartup testing U8' conditions 1 and 2 of Unit No. I beginning with an August g@ 16, 1985 injoction. The night injoctionn which occurrod a)o prior to August 16, 1985 woro doncribed in a nimilar special g report dated July 10, 1985.

no 00 AlI but one of the nix subnoquent injoctionn woro 7 anticipated under the purview of the startup tent program Og and directed by Startup Test Proceduros. Sinco those g injectionn woro donigned into the ntartup test program, thorn woro no adverso of facts on the reactor vensol or the I $

RCIC system an a result of thono injoctionn. The remaininq injection was the renuit of a valid low roactor water lovel ,D 7 h

, Dr. Thomac E. Murlcy Nov;mber 14, 1985 o

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signal, following an unexpected reactor scram. There were no adverse ef fects on the reactor vessel or the RCIC system as a result of this injection since reactor parameters remained within the applicable design criteria.

Below is a description of each of the RCIC system actuation and injection events during test conditions one and two.

On August 16, 1985 Startup Test Proceduro (STP) 14.9-1,

" Loss of AC Power", was performed. The test involved two intentional RCIC injections into the reactor vessel. Both injections were achieved by pushing the manual initiation pushbutton, resulting in an automatic quick start to an injection flowrato of 600 gpm.

Reactor parameters for both injections were as follows:

reactor thermal power approximately 625 MWt, dome pressure 910 psig, and moderator temperature 510 degrees F. RCIC pump suction for both injections was lined up to the Condensate Storngo Tank (CST) and pump dischargo pressure was approximately 980 psig to achiovo 600 gpm. Those two injections represent the ninth and tenth RCIC actuation cycles to dato.

On September 11, 1985 the reactor scrammed on low reactor water lovel as a result of a low suction pressure trip of two foodwater pumps. Reactor water level dropped further to the RCIC initiation sotpoint. RCIC injected automatically and ran for approximately fifteen minutos before it was minually secured. The reactor was operating at approximately 28% of rated power prior to the scram.

Reactor paramotors for this injection woro as follows:

reactor thermal power 922 MWt, domo prosauro 940 psig, and moderator temperature 525 degrees F. RCIC pump suction was lined up to the Condonnato Storage Tank. This represents the oloventh RCIC actuation cycle to date.

On September 11, 1985 STP-20.2-1, " Reactor Cooldown Demonstration", was performed. The test is designed to demonstrate that the Ronctor can be coolod f rom hot 'o cold shutdown from outsido the Control Poom. The test involves uning safety relief valvos to depronsurize the reactor from 150 psig and maintaining roactor water lovel using RCIC.

Reactor paramotors for this injection worn as follows:

reactor thermal power 0 MWt, domo prennuro 210 poig, and moderator temporaturo 390 degroon F. With RCIC pump suction linod up to the CST, a nlow start in manual was performed with the flowrato adjunted to maintain reactor water lovel.

This reprosonts the twelf th RCIC actuation cyclo to dato.

On September 12, 1985 STP-28.1-1, "Roactor Shutdown to llot Standby Domonstration", wan performed. Thin test in designed to demonntrato that the roactor can be shutdown to hot standby from outsido the Control Room. The tent involven using nafety relief valvos to doprannurzio the

.. pr. Thomac E. Muricy Novc=ber 14, 1985 l .** ** Pcgo 3 i

l reactor to hot standby and maintaining reactor water level l using RCIC.

Reactor parameters for this injection were as follows:

l reactor thermal power 556 MWt, dome pressure 928 psig, and l moderator temperature 515 degrees F. With RCIC pump suction l lined up to the CST, a slow start in manual was performed with the flowrate adjusted to maintain reactor water level.

This represents the thirteenth RCIC actuation cycle to date.

On September 16, 1985 STP-31.1-1, " Loss of Turbine-Generator and Of fsite Power", was performed. The test involved tripping of f the main turbine and of fsite power source simultaneously and ensuring the plant safety systems responded accordingly. An expected scram followed the loss of of fsite power and as reactor water level remained low, RCIC was manually initiated.

Reactor parameters, prior to the loss of of fsite power were as follows: reactor thermal power 686 MWt, dome pressure 931 psig, and moderator temperature 522 degrees F.

With RCIC pump suction lined up to the CST, flow was adjusted to maintain reactor water level. This represents the fourteenth RCIC actuation cycle to date.

Since five of these injections were expected and planned for in the Startup Test Program and the remaining injection was the result of a legitimate low reactor water level signal, no corrective action is to be taken.

Should you require additional information, please do not hesitate to contact us.

Very truly yours,

};*f [ck'? & Y W. T. Ullrich

- Supe rintendent Nuclear Generation Division cc E. M. Molly, Senior Resident Inspector See Attached Service List

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• I cc Troy B. Conner, Jr., Esq.

Ann P. Hodgdon, Esq. ;l Mr. Frank R. Romano  :

Mr. Robert L. Anthony 8

'Ms. Phyllis Zitser

Charles W. Elliott, Esq. .

Eori G. Ferkin, Esq. .i 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. Gutierres, Esq.

Atomic Safety & Licensing Appeal Board '

Atomic Safety & Licensing Board Panel ,

Docket & Service Section (3 Copies) i E. M. Kelly Tisothy R. S. Campbell

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September, 1985 l

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