ML19332F296

LER 89-009-01:on 890820,eight RCIC Sys Injections Into RCS Occurred Under Purview of Facility start-up Test Program. Caused by Abnormal Plant Conditions Requiring Safety Sys Actuations.Rcic & HPCI Sys Tests completed.W/891129 Ltr

ML19332F296
Person / Time
Site:	Limerick
Issue date:	11/29/1989
From:	Endriss C, Mccormick M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-009-01, LER-89-9-1, NUDOCS 8912140234
Download: ML19332F296 (8)

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TS 6.9.2 i 4 8 '

PHILADELPHIA ELECTRIC COMPANY LIMERICK GENER ATING ST ATION P. O. BOX A SAN ATOG A. PENNSYLV ANI A 19464 trio n 7 iroc e=,. toco November 29, 1989 M. J. M c C O ft M IC et. J... PL ux . ../O".' .".".'.'.".. . . Docket No. 50-353 .

License No. NPF-85 U.S. Nuclear Regulatory Commission Attn Document Control Desk Washington, DC 20555

SUBJECT:

Special Report Limerick Generating Station - Unit 2 This Special Report concerns' preplanned Reactor Core Isolation Cooling system and High Pressure Coolant Injection ,

system injections into the Reactor Pressure Vessel (RPV) during the Unit 2 Start-Up Test Program.

Reference:

Docket No. 50-353 Report Number 2-89-009 Revision Number: 01 Event Date: August 20, 1989 i Report Date: November 29, 1989 Facility: Limerick Generating Station P.O. Box A, Sanatoga, PA 19464 This revised Special Report is being submitted pursuant to '

Technical Specifications Reporting Requirement 6.9.2, as required '

by Technical Spe71fication Actions 3.7.3.b and 3.5.1.f. Changes are identified by revision bar markers in the righthand margin, Very truly yours,

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T. J. Kenny, USNRC Senior Resident Inspector, LGS

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"'*This special Report identifies eight Reactor Core 1. solation Ccolino svsten iniections andt three Mich Dressure coolant Injection system injections.

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i ur . .ct ,4 . . . .e .....-...-..-,-o.3 l l l Between August 20, 1989 and September 25,'1989, eight Reactor Core Isolation Cooling (RCIC) system injectiots into the Reactor Coolant System (RCS). occurred under the purviee of the Unit 2 Start-Up Test Program. Between October 23, 1989 and October 26, 1989, three High Pressure Coolant Injection (HPC!) system injections into the RCS occurred under the purview of the Unit 2 Start-Up Test Program. These RCIC and HPCI system tests were completed satisfactorily during Unit 2 Test Conditions 1, 2 and

3. This Special Report is being submitted pursuant to Technical Specifications (TS) Reporting Requ7tement 6.9.2, as required by TS Actions 3.7.3.b and 3.5.1.f. These are the only RCIC system and'UPCI injections planned to be performed during the Unit 2 Start-Up Test Program.

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1 TDET fr suuwe spe.e 4 soeweed. ese .se.ome r MC ser= Jap s# (17e Reporting Requirements:

Technical Specifications (TS) 3/4.7.3, Reactor Core Isolation Cooling System, Limiting Conditions for Operation Action ,

3.7.3.b  !

In the event the RCIC system is actuated and injects water into the Reactor Coolant System, a Special Report shall tue 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 Specifications (TS) 3/4.5.1, Emergency Core Cooling Systems, Limiting Conditions for Operation Action 3.5.1.f In the event the 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.

Special Reports 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

Description of Events:

The following events are associated with eight Reactor Core Isolation Cooling (RCIC) system and three High Pressure Coolant Injection (HPCI) system injections into the Reactor Coolant System (RCS). These injections were anticipated and performed under the purview of the Unit 2 Start-Up Test Program and conducted in accordance with Start-Up Test Procedures. These events were not the result of abnormal plant conditions requiring safety system actuations. These are the only RCIC system and ECCS injections planned to be performed during the Unit 2 Start-Up. Test Program.

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" Controller Optimization During Injection at Rated Pressure -

Subtest 14.4," was performed with the reactor in Test Condition 1 (Heatup). The test involved two preplanned RCIC system injections into the RCS.

The first injection was achieved by a manual startup of the RCIC system with the flow controller in the manual mode (i.e. operator flow control required), resulting in an injection flow rate of 600 gpm into the RCS. The second RCIC system injection into the RCS was achieved by a manual startup with the flow controller in the automatic mode (i.e. no operator flow control required) to demonstrate system response and stability.

In both RCIC system injections, the pump suction was lined up to the Condensate Storage Tank (CST). The reactor parameters for both injections were as follows:

Reactor Thermal Power 97.4 MWT/2.95% Rated ,

Reactor Vessel Dome Pressure: 920 PSIG Core Moderator Temperature 520 Deg. F Core Flow: 37.0 Mlbm/Hr.

Feedwater Flow: 0.4 Mlbm/Hr.

Feedwater Temperature: 95 Deg. F These two injections represent the first and second RCIC system actuation cycles. ,

Event 2:

On August 28, 1989, the Unit 2 STP, "RCIC Cold Quick Start at Rated Pressure CST to Reactor Pressure Vessel - Subtest 14.6,"

was performed with the reactor in Test Condition 1. This first performance of STP Subtest 14.6 was to demonstrate the operation of the RCIC system under anticipated operational conditions of a manual quick start with discharge to the RCS at rated temperature and pressure.

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"""~~'""*~TW"AUTU'"$y'*sfe:E" Injection was achieved by a stinual startup with the flow controller in the automatic mode. This action resulted in an injection flow rate of 600 gpm into the RCS.

The reactor parameters for the injection were as follows:

Reactor Thermal Power: 317 MWT/9.6% Rated Reactor Vessel Dome Pressure 921 PSIG Core Moderator Temperature 524 Deg. F.

Core Flows 37.0 M1bm/Hr.

Feedwater Flow: 0.4 Mlbm/Hr.

Feedwater Temperature: 95 Deg. F This injection represents the third RCIC system actuation cycle. ,

Event 3:

On September 4, 1989, the Unit 2 STP Subtest 14.6 was performed a second tiine in conjunction with STP Subtest 14.8, "RCIC Endurance Run," with the reactor in Test Condition 2. These two tests were, performed to demonstrate RCIC system operation, establish the high steam flow isolation setpoint, and verify that the system can operate for extended periods of time.

Performance of STP Subtest 14.6 was initiated by a manual startup resulting in an injection into the RCS at a flow rate of 600 gpm.

Following this injection, the RCIC system was realigned to discharge back into the CST and run for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with an average flow of 600 gpm.

The reactor parameters for the injection were as follows:

Reactor Thermal Power: 755 MWT/23% Rated Reactor Vessel Dome Pressure: 925 PSIG ,

Core Moderate Temperature: 515 Deg. F Core Flow: 44.7 Mlbm/Hr.

Feedwater Flow 2.68 Mlbm/Hr.

Feedwater Temperature: 293 Deg. F This injection represents the fourth RCIC system ac'tuation cycle.

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• kr f.VO.E o p le lc lc l 3]S; 3 q9 0;GlP 0;l 0l5 op 0l7 e m ,, . . .- : a.c a-- m on On September 10, 1989, and September 11, 1989, the Unit 2 STP Subtest 14.9, " Loss of AC Power," was performed with the reactor in Test Condition 2. This subtest demonstrated the ability of the RCIC system to start and run for an extended period of tirae with a loss of AC power.

The RCIC system was initiated per STP Subtest 14.9 on September 10, 1989, and September 11, 1989. During these two separate manual startups, the RCIC system injected into the RCS as required by the procedure and served to demonstrate the ability of the system to start without the aid of AC power (with the ,

exception of the RCIC DC/AC inverters). The RCIC system was then secured in accordance with STP Subtest 14.9. The average RCIC system flow was approximately 600 gpm.

The reactor parameters for these two injections were as followst Reactor Thermal Power 895.5 MhT/27.2% Rated Reactor Vessel Dome Pressure 928 PSIG

- Core Moderator Temperature: 520 Deg. F .

Core Flow: 44.5 M1bm/lir .

Feedwater Flows 3.27 Mlbm/11r .

Feedwater Temperature 303 Deg. P -

These two injections represent the fifth and sixth RCIC actuation cycles.

Event 5:

On September 21, 1989, the Unit 2 STP Subtest 14.5, " Stability Check CST to RPV at 150 psig," was performed with the reactor in Test Condition 2. As directed by the procedure, a manual startup with the RCIC flow controller in the automatic mode was performed followed by flow demand step changes to demonstrate system response.

The RCIC system injected into the RCS with a flow rate of 300 gpm.

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""""IT17i~e*a*ctoE pay $5ters for the injection were as follows:

Reactor Thermal Power 46 MWT/1.4%, Rated Reactor Vessel Dome Pressure: 149 PSIG Core Moderator Temperature: 365 Deg. P Core Flow: 42 M1bm/Hr.

Feedwater Flow: 0.3 Mlbm/Hr.

Feedwater Temperature: 120 Deg. F  ;

This injection represents the seventh RCIC system actuation cycle.

Event 6:

On-September 25, 1989, the Unit 2 STP Subtest 28.1, " Reactor Shutdown to Hot Standby Demonstration," was performed with the reactor in Test Condition 2. This subtest demonstrates that the -

reactor can be safely shutdown and maintained in a Hot Standby Condition from outside the Main Control Room (MCR). During the performance of this subtest, the RCIC system injected into the RCS to aid in a controlled depressurization/cooldown of the reactor. The average RCIC system flow was approximately 450 gpm.

The reactor parameters for the injection were as follows:

Reactor Thermal Power 0.0 MWT/0.0 Rated Reactor Vessel Dome Pressure: 920 PSIG Core Moderator Temperature: 521 Deg. F.

Core Flows 35.4 Mlbm/Hr.

Feedwater Flow: 0.0 M1bm/Hr.

Feedwater Temperature: 116 Deg. F. i This injection represents the eighth RCIC system actuation cycle to date.

Event 7:

On October 23, 1989, the Unit 2 STP 15.4, " Controller Optimization During Injection at Rated Pressure," was performed with the reactor in Test Condition 3. The test involved two preplanned HPCI system injections into the RCS with the HPCI pump lined up to take suction from the condensate storage tank (CST). i The first injection was achieved by a manual startup of the HPCI system with the flow controller in the manual mode (i.e.,

operator flow control required), resulting in an injection flow rate of 5650 gpm into the RCS for approximately three minutes.

The-second HPCI system injection into the RCS lasted three minutes and was achieved by a manual startup with the flow contr51'lba'in~th'e' automatic mode (i.e. no operator flow control required) to demonstrate system response and stability.

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The reactor parameters for the injection were as follows:

Reactor Thermal Power 2350 MWT/74.1% Rated Reactor Vessel Dome Pressure 953 PSIG Core Moderator Temperature 526 Deg. F.

Core Flow: 98.5 Mlbm/Hr.

Feedwater Flow: 8.7 Mlbm/Hr. ~

Feedwater Temperature 380 Deg. F.

These injections represent the first and second HPCI system actuation cycles with a safety injection nozzle usage factor less than 0.7.

Event 8:

On October 26, 1989, the Unit 2 STP Subtest 15.5, " Cold Quickstart at Rated Pressure - CST to RPV," was performed with the reactor in Test Condition 3. As directed by the procedure, a j manual startup of the HPCI system with the flow controller in the automatic mode was performed followed by flow demand step changes

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to demonstrate system response.

The HPCI system injected into the RCS with a flow rate of 5600 gpm for approximately ten minutes and was then reduced by 600 gpm increments each minute for an additional 10 minutes.

The reactor parameters for the injection were as follows:

Reactor Thermal Power 2192 MWT/66.6% Rated Reactor Vessel Dome Pressure: 950 PSIG Core Moderator Temperature: 528 Deg. F.

Core Flow: 99.8 Mlbm/Hr.

Feedwater Flow: 8.8 Mlbm/Hr.

Feedwater Temperature: 384 Deg. F.

This injection represents the third HPCI system octuation cycle I with a safety injection nozzle usage factor less than 0.7.

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