ML19354D916

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LER 89-041-00:on 891122,unit Entered Tech Spec 3.0.3 When RCIC & HPCS Sys Inoperable Simultaneously for 37 Minutes. Chiller Condensing Unit Tripped Due to Low Refrigerant Pressure.Refrigerant in Chiller recharged.W/900117 Ltr
ML19354D916
Person / Time
Site: Clinton Constellation icon.png
Issue date: 01/17/1990
From: Holtzscher D, Morris D
ILLINOIS POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-041, LER-89-41, U-601585, NUDOCS 9001250005
Download: ML19354D916 (6)
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. 2C.220 f ILLINol8 POWER COMPANY IP CLINTON POntR STATION, P.O. BOX 678. CLINTON, ILLINOi$ 61727 l l

'l January 17, 1990 l i

10CFR50.73 -

l Docket No. 50-461 I

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Subj ect: Clinton Power Station' Unit 1 Licensee Event Renort No. 89-041-00 l I

Dear Sir:

f Please find enclosed Licensee Event Report No. 89 041 00: '

Leakane of Refrigerant from Chiller Results in Inonerable High Pressure' -l Core Sorav System While Reactor Core Isolation Coolina System was i

- Inocerable. This report is being submitted in accordance with the {

requirements of 10CFR50.73.  !

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Sincerely yours, j

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D.'L. Holt'zscher '

Acting Manager . -

Licensing and Safety DAS/krm ,  ;

Enclosure-i cc: NRC Resident Office  !

NRC Region III, Regional' Administrator  ;

INPO Records Center Illinois Department of Nuclear Safety- l NRC Clinton Licensing Project Manager ..

I 9001250005 900117 PDR ADOCK 05000461

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On December 18, 1989, Clinton Power Station management determined that an event reportable pursuant to 10CFR50.73(a)(2)(1)(B) had occurred on November 22, 1989, when the plant entered 'Iechnical Specification (TS) 3.0.3 for approximately 37 minutes, llowever, due to a procedural deficiency, the Shift Supervisor did not recognize that entry into TS 3.0.3 was a reportable event. The entry into TS 3.0.3 was required because the Reactor Core Isolation Cooling (RCIC) system and the liigh Presnure Core Spray (llPCS) system were inoperable simultaneously. The RCIC system was inoperable for planned maintenance. The llPCS system became inoperable because a chiller condensing unit on the Division III Essential Switchgear lleat Removal System became inoperable. The chiller condensing unit tripped during chiller performance monitoring as a result of low refrigerant prec sure. Following the trip, the chiller was recharged with refrigerant, then started and declared operable. The cause of tha low refrigerant pressure is believed to be a result of leakage from the system. Corrective actions include developing and impicmenting a plan to investigate and correct the refrigerant leakage, briefing Shift Supervisors and training licensed operations personnel so they recognize that entry into TS 3.0.3 is a reportable event, and revising the deficient procedure.

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DESCR Z ION OF EVENT On December 18, 1989, Clinton Power Station management determined that an event reportable pursuant to 10CFR50.73(a)(2)(1)(B) had occurred on November 22, 1989.

At 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br /> on November 21, 1989, the plant was in Mode 1 (POWER OPERATION) at approximately sixty one percent reactor [RCT) power. At 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />, the Reactor Core Isolation Cooling (RCIC) system [BN) was declared inoperable in order to perform planned maintenance. At approximately 1019 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.877295e-4 months <br /> on November 22, 1989, the Division III safety.

related essential switchgear [SWCR) heat removal system (VX) chiller condensing unit [CDU) IVXO6CC was started to monitor chiller performance in accordance with Clinton Power Station (CPS) Procedure 2604.01,

" Chiller Performance". However, after starting, the chiller condensing unit tripped due to low refrigerant pressure. At 1023 hours0.0118 days <br />0.284 hours <br />0.00169 weeks <br />3.892515e-4 months <br />, the chiller condensing unit was declared inoperable.

The function of chiller condensing unit IVXO6CC is to provide adequate heat removal to maintain required temperatures in the Division III safety-related switchgear area and the Division III battery.[BTRY) room following a loss of the non safety related cooling coil cabinet. As L

such, IVXO6CC provides support for the operability of the equipment in these areas. As a result of IVXO6CC becoming inoperable, the Division III battery charger [BYC) and other equipment served by this system were declared inoperable. Action "b" of Technical Specification 3.8.2.1, "DC Sources Operating", requires that, with the Division III battery and/or charger inoperable, the High Pressure Core Spray (HPCS) system [BC) be declared inoperable. Technical Specification 3.5.1, " Emergency Core Cooling System Operating", and Technical Specification 3.7.3, ' Reactor Core Isolation Cooling", do not address having the RCIC and HPCS systems inoperable simultaneously. Therefore, this condition resulted in entry into Technical Specification 3.0.3. -Entry into Technical Specification 3.0.3 constitutes a condition prohibited by the plant's Technical Specifications and is therefore reportable pursuant to 10CFR50.73(a)(2)(1)(B) (as discussed in the " Questions and Answers from the LER Workshops" section of NUREC-1022 " Licensee Event Report System",

Supplement 1).

Following recharging of the refrigerant in chiller condensing unit IVXO6CC, the chiller condensing unit was restarted. At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on November 22, 1989, IVXO6CC was declared operable and Technical Specification 3.0.3 was exited.

At the time of this event, the Shift Supervisor did not recognize that entry into Technical Specification 3.0.3 constituted operation prohibited by the plant's Technical Specifications and hence, was reportable pursuant to 10CFR50.73(a)(2)(1)(B). As a result of determining that M'oa* ** ..... cro, i m . m . m , m n i

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entry into Technical Specification 3.0.3 on November 29, 1989 was ]

reportable (see LER 89 037 00), a review was conducted to determine whether there were previous entries into Technical Specification 3.0.3.

On December 18, 1989 CPS management determined that an entry into  !

Technical Specification 3.0.3 had occurred on November 22, 1989. l' Therefore, this event is being reported within 30 days of this determination on December 18, 1989.

1 No automatic or manually initiated safety system responses were necessary  !

.to place the plant in a safe and stable condition. No other equipment or 'l components were inoperable at the start of this. event such.that their inoperable condition contributed to this event.

1 CAUSE OF EVENT i

Inoperability of IVX06CC resulted in declaring the HPCS system )

inoperable. Since this condition occurred while.the RCIC system was  ;

inoperable for planned maintenance, it required entry into Technical j Specification 3.0.3. The cause of the inoperability of chiller condensing unit IVXO6CC was low refrigerant pressure believed to be a ,

result of leakage of the refrigerant from the system. l At the time of this event, the Shift Supervisor did not recognize that ,

entry into Technical Specification 3.0.3 constituted operation prohibited j by the plant's Technical Specifications and was therefore reportable-pursuant to 10CFR50.73(a)(2)(1)(B). The cause of this aspect of the 1 event has been attributed to a deficient procedure. Administrative procedure 1016.04, "Clinton Power Station Licensee Event Reports (LER)"

does not identify that entry into Technical Specification 3.0.3 is a reportable event. .

CORRECTIVE ACTIONS J 5

Chiller condensing unit IVX06CC was recharged with refrigerant and I restored to OPERABLE status at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on November 22, 1989, i Illinois Power has developed a plan to investigate and correct the loss of refrigerant problem and any other equipment problems which may affect 3 the operability of the VX system. -]

1 In accordance with this plan, a leak check will be performed on each i division of the VX system by January 31, 1990. System leaks will be i corrected on a priority basis consistent with parts availability and as l permitted by plant conditions.

Additionally, VX system equipment history will be reviewed to identify system problems. Maintenance personnel will provide input on problems identified. For problems which are not associated with leakage of 801C p@ies pesa 'U.S. Gros 190 9-5 20- 589 > 90010 C 43)

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Further, a preventive maintenance task has been generated to run the condensing units of the three divisions on a weekly basis. During these runs, operating data will be obtained and then trended. The frequency of running the condensing units will be reassessed and revised accordingly after sufficient weekly runs have been completed.

Shift Supervisors will be briefed so they recognize that entry into Technical Specification 3.0,.3 constitutes operation prohibited by the plant's Technical Specifications and hence, is reportable pursuant to 10CFR50.73(a)(2)(1)(B). This briefing is scheduled to be completed by January 31, 1990.

Procedure 1016.04 will be revised to identify that entry into Technical Specification 3.0.3 is an event reportable under the provisions of 10CFR50.73(a)(2)(1)(B). This revision is scheduled to be completed by April 30, 1990.

Additionally, reportability of plant entry into Technical Specification 3.0.3 will be reviewed with licensed operations personnel during requalification training for 1990. This training is scheduled to be completed by June 4, 1990.

ANALYSIS OF EVENT Upon failure of the RCIC and HPCS systems to function properly following a small break loss of coolant accident, the automatic depressurization system (ADS) automatically causes depressurization of the reactor so that flow from the low pressure Emergency Core Cooling Systems (ECCS) can enter the core in time to limit fuel cladding temperature to less than 2200 degrees F. At the time of this event, the ADS, as well as the four low pressure ECCS trains were operable.

Each division of the switchgear heat removal system consists of two -

independent switchgear heat removal coil cabinets connected to a common supply duct [ DUCT) system. Each switchgear heat removal coil cabinet (CAB) consists of a filter [FLT), cooling coil [CCL), and fan [ FAN). One switchgear heat removal coil cabinet is non safety related and has a chilled water coil fed from the plant chilled water system [KM). This i non-safety related coil cabinet is utilized for cooling during normal station operating conditions. The other switchgear heat removal coil cabinet is safety related and has a refrigerant evaporator coil fed from a water cooled condensing unit located within the switchgear room. The condenser heat is removed by shutdown service water'[BI) or plant service' water [KG)'. This safety related coil is aligned in standby and is utilized during abnormal operating conditions or upon failure of the non-g ,.... ~

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safety related coil cabinet. Under normal. operating conditions, makeup  !

air to the VX system is provided by the auxiliary' building HVAC supply system [VF). Under abnormal operating conditions, provision is made for  !

outside air to be inducted to the switchgear room to make up for the j battery room exhaust requirements. Therefore, cooling to the areas l served by IVXO6CC was not lost during this event. ]

Additionally, the low refrigerant pressure condition ~of IVXO6CC was - I discovered during the routine chiller performance of CPS Procedure {

2604.01. Therefore, this condition would not have gone undetected. Upon _;

identification of this condition, the appropriate Technical Specification  !

Actions were entered. Once identified, had this condition persisted for i longer than allowed by the Technical Specifications, action would have  !'

'oeen taken to place the plant in the shutdown condition, thereby mitigating the consequences of this event. Based upon the above assessment, this event is not considered to be nuclear safety significant.  ;

-l The VX and HPCS systems were inoperable from 1023 hours0.0118 days <br />0.284 hours <br />0.00169 weeks <br />3.892515e-4 months <br /> to 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on' -

November 22, 1989. The RCIC system was inoperable from 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br /> on.

November 21, 1989 until 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> on November 22, 1989.

ADDITIONAL INFORMATION  ;

The chiller condensing unit IVX06CC which failed is a Model SF40 >

manufactured by Carrier Corporation. l No events have been previously reported which' identified entry into Technical Specification 3.0.3 as a result of the failure of the essential l switchgear heat removal system.

For further information regarding this event, contact D. R. Morris, Director - Plant Operations at (217) 935 8881, extension 3205.

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