ML023100238

Draft - Section C Operating

ML023100238
Person / Time
Site:	Limerick
Issue date:	10/04/2002
From:	Wasong A Exelon Nuclear
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-352/02-302, 50-353/02-302
Download: ML023100238 (15)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick Scenario No.: A Op-Test No.:

Examiners: Operators:

Initial Conditions: Unit 1 is at 100% Power, with "IM" SRV leaking. Unit 2 is in OPCON 5 for refueling.

Turnover: "IM" SRV is leaking. Pilot temperature for the "1M" SRV is 520 deg. F. and stable. RT-6-041-490-1(SUPPRESSION POOL GROSS INPUT LEAK RATE DETERMINATION) actions and monitoring are being performed by other operations and engineering personnel. The crew is directed to place "IA" RHR Loop in Suppression Pool Cooling. RHRSW is in service for the "IA" RHR heat exchanger using the "OA" RHRSW pump per S12.1 .A, and the RHR pump and breaker have been verified ready for a start. An Equipment Operator is standing by at the pump. A 90% Reactor Maneuvering Shutdown Instruction has been provided for this shift.

Event Malf. Event Event No. No. Type* Description 1 N/A N (CRS) Place Suppression Pool Cooling in Service (PRO) 2 MHP451B I (CRS) HPCI Inadvertent Isolation - Tech Spec (PRO) 3 MFW046B I (ALL) "1B"FW Steam Flow Transmitter Fails Low 4 MFH522A C (ALL) Loss of Feedwater Heating MFH516A 4 N/A R (ALL) Power Reduction with Rods and Recirc to 85%

5 MAD148B C (ALL) "IM" SRV fails open and will not close MAD1 48C 6 MRP029C M (ALL) ATWS (Electrical)

MRP407C 6 MSL196D C (CRS) SLC Failure prevents SLC Injection (PRO)

"t -J)ormal, tk)eactivity, (i)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8

Appendix D Operator Action Form ES-D-2 Scenario No. A Event No.: 1 Op-Test No.

Event

Description:

Place "IA" RHR loop in suppression pool cooling Time Position Applicant's Actions or Behavior CRS Direct the PRO to place the "IA" RHR loop in suppression pool cooling per $51.8.A PRO Start "IA" RHR pump PRO Establish 8000 to 8500 gpm flow through HV51 -1F024A I I

Appendix D Operator Action Form ES-D-2 Op-Test No. Scenario No. A Event No.: 2 Event

Description:

HPCI Inadvertent Isolation Time Position Applicant's Actions or Behavior PRO Recognize HPCI isolation PRO Reference ARC for HPCI OUT OF SERVICE alarm, and inform CRS to reference Technical Specification 3.5.1.

CREW Recognize no actual HPCI isolation signals exist RO/PRO Request WWM / I&C / Floor Supervisor investigate inadvertent HPCI isolation CRS Determine HPCI inoperable, and Unit 1 is in a 14 day action statement per T.S. 3.5.1 action C.1.

Appendix D Operator Action Form ES-D-2 Op-Test No. Scenario No. A Event No.: 3 Event

Description:

"IB" FWLC Steam Flow Transmitter Fails Low Time Position Applicant's Actions or Behavior RO Recognize lowering RPV level PRO Reduce power using recirc per OT-100 immediate operator actions CRS Enter OT-1 00, Reactor Low Level RO Recognize "1B" FWLC Steam Flow Transmitter failed downscale RO Reference ARC for alarm H-2 on 107 REACTOR (REACTOR HI/LO LEVEL)

CRS Direct RO swap FWLC to single element per S06.0.E RO Swap FWLC to single element per S06.0.E

Form ES-D-2 t-pPJu, U Li e-r

. A........tion Scenario No. A Event No.: 4 Op-Test No.

Event

Description:

High FW Heater Level, LP FW Heater String Isolation Time Position [ Applicant's Actions or Behavior RO/PRO Reference ARCs for high level alarms for "2A" and "3A" FW heaters RO/PRO Recognize "2A" FW heater drain and dump valves are both closed PRO Request Equipment Operator check FW heater levels locally RO/PRO Reference ARC for "FW HTRS 1&2 HI-HI LEVEL LP HTR STRING ISOLATION" alarm RO/PRO Recognize isolation of "A" LP FW heater string RO Recognize power increase due to loss of feedwater heating PRO Reduce reactor recirculation flow to reduce power below initial pre transient power level per OT-1 04 immediate operator actions CRS Enter OT-1 04, UNEXPECTED/UNEXPLAINED POSITIVE OR NEGATIVE REACTIVITY ADDITION.

CRS Direct power reduction to 85% or below PRO Reduce power using recirc flow to 90% power RO Reduce power using control rods to 85% power or less

Attachment to Form ES-D-2 Op-Test No. Scenario No. A Event No.: 5 Event

Description:

"1M" SRV Fails Open Time Position Applicant's Actions or Behavior RO/PRO Recognize "1M" SRV open RO/PRO Reference ARC for "SAFETY RELIEF VALVE OPEN" alarm CRS Enter OT-1 14, INADVERTENT OPENING OF A RELIEF VALVE PRO Place the "1B" loop of suppression pool cooling in service CRS Direct the RO to reduce turbine inlet pressure to 900 psig RO Reduce turbine inlet pressure to 900 psig CRS Direct pulling of fuses for "IM" SRV per OT-114 CRS Recognize "1M" SRV still open after turbine inlet pressure reduced to 900 psig CRS Direct rapid plant shutdown per GP-4, RAPID PLANT SHUTDOWN TO HOT SHUTDOWN PRO Transfer house loads to startup buses per S91.6.B PRO Runback both reactor recirc pumps to minimum speed RO Manually scram the reactor at 50% core flow

_ _I __ _ _ _ _I

Attachment to Form ES-D-2 Op-Test No. Scenario No. A Event No.: 6 Event

Description:

ATWS (Scram Failure)

Time Position Applicant's Actions or Behavior RO Recognize no control rod motion, and report to the CRS CRS Enter T-1 01, RPV CONTROL due to scram condition with power above 4%

RO Place reactor mode switch in "SHUTDOWN" RO Insert SRMs/IRMs CRS Direct RRCS initiation RO Manually initiate RRCS CRS Direct trip of both recirc pumps PRO Trip both recirc pumps CRS Direct the RO to manually insert control rods RO Insert control rods manually CRS Direct performance of T-214, ARI Initiation from AER CRS Direct performance of T-215, Scram Fuse Removal CT CRS Direct performance of T-216, Vent Scram Air Header PRO Recognize SLC is not injecting to the RPV CRS Direct performance of T-212 to inject SLC CRS Enter T-1 17, LEVEL/POWER CONTROL CRS Direct auto ADS inhibited PRO Inhibit auto ADS CRS Direct performance of T-221 to maintain MSIVs open CRS Direct performance of T-270 to terminate and prevent injection to reduce RPV level to below -50 inches PRO Perform T-270 to terminate and prevent HPCI, RHR, and Core Spray injection RO Perform T-270 to terminate and prevent condensate/feedwater injection CRS Provide direction to the RO to reinject as necessary to maintain RPV level in a band that is above -129 and at or below -50 inches

Attachment to Form ES-D-2]

Op-Test No. Scenario No. A Event No.: 6 Event

Description:

ATWS (Scram Failure)

Time Position Applicant's Actions or Behavior RO Reinject with condensate/feedwater to maintain RPV level in band as directed by CRS PRO Recognize suppression pool temperature at or above 110 deg. F.

CRS Direct performance of T-270 to terminate and prevent injection CT PRO/RO Perform T-270 to terminate and prevent HPCI, RHR, Core Spray injection (PRO) and Condensate/Feedwater (RO)

CRS Direct RO to reinject when RPV level is below -161, or SRV is closed and DW pressure is <1.68 psig, or power is <4%, or SP temperature is less than 110 deg F.

CT RO Reinject with condensate/feedwater to maintain RPV level in band as directed by the CRS CREW Recognize "1 M" SRV is closed RO Recognize control rods inserted following performance of T-216 CRS Exit T-1 17, LEVEL/POWER CONTROL CRS Re-enter T-1 01, RPV CONTROL, RC/L leg CRS Give RO a level band above the top of active fuel (>-161 inches)

RO Restore RPV level above -161 inches I I -

Termination Point:

The scenario will be terminated when the following criteria are met:

1. All control rods are fully inserted

2. RPV level is being maintained above the top of active fuel

Appendix D Scenario Outline Form ES-D-1 Facility: Limerick Scenario No.: B Op-Test No.:

Examiners: Operators:

Initial Conditions: Unit 1 is at 90% power, with N2 makeup in progress to the Unit 1 drywell. Unit 2 is in OPCON 5 for refueling.

Turnover: Secure from drywell N2 makeup. After N2 makeup is secured, raise power to 100% per GP-5, Attachment 1. An 85% Reactor Maneuvering Shutdown Instruction has been provided for this shift.

Event Malf. Event Event No. No. Type* Description 1 N/A N (CRS) Secure from N2 Makeup (PRO) 2 MFLCPR = C (CRS) Power Ascension I Thermal Limit Violation 1.003 (RO) Tech Spec 2 N/A R (ALL) Power Reduction to correct thermal limit violation 3 MCW483C I (CRS) "IA" RECW pump trips, "l B" RECW fails to (PRO) start 4 MRR433A C (ALL) Both "IA" RRP Seals Fail MRR434A 4 HS43-FO31A C (CRS) "IA" RRP Discharge Valve Fails Open (PRO) 5 MRR440A M (ALL) Reactor Coolant Leak 5 MRH528C C (CRS) "IA" Drywell Spray Valve Fails to Open

-(PRO) 5 MRH171B I (CRS) "lB" RHR Pump Fails to Start (PRO)

I- +

.1- 4 F

.1. I I I __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8

Appendix D Operator Action Form ES-D-2 Op-Test No. Scenario No. B Event No.: 1 Event

Description:

Secure N2 makeup flow to the drywell Time Position Applicant's Actions or Behavior CRS Direct the PRO to secure N2 flow per $57.3.B PRO Secure N2 flow per $57.3.B PRO Request an Equipment Operator to open 57-1088 valve locally

Appendix D Operator Action Form ES-D-2 Op-Test No. Scenario No. B Event No.: 2 Event

Description:

Power increase, Thermal Limit violation Time Position Applicant's Actions or Behavior CRS Direct PRO to increase power using recirc flow per GP-5, Attachment 1 CRS Direct RO/PRO to generate a P-1 edit RO/PRO Recognize MFLCPR is greater than 1.000, and MCPR is less than the limit (1.350) and notify CRS CRS Enter GP-14, Resolution of Thermal Limit Violations CRS Notify Reactor Engineering of thermal limit violation CRS Reference Tech Spec 3.2.3 for MCPR limit, recognize corrective action must be initiated within 15 minutes, and MCPR must be restored to greater than the MCPR limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

CRS Within 15 minutes direct power reduction until all thermal limits are less than 1.000 PRO Reduce power with recirc. per RMSI to 85% power RO Reduce power with control rods per RMSI until MFLCPR is less than 1.000

Operator Action Form ES-D-2 Appendix D Scenario No. B Event No.: 3 Op-Test No.

Event

Description:

"IA" RECW pump trip and "I B" RECW pump fails to auto start Time Position Applicant's Actions or Behavior PRO Recognize trip of "IA" RECW pump and failure of "I B" pump to start PRO Reference ARC for annunciator 118 SERVICES, window H-1 CRS Enter ON-1 13, Loss of RECW RO Request EO/Floor supervisor investigate the trip of the "IA" RECW pump and the failure of the "I B" RECW pump to auto start PRO Reference ARCs for 111 RECIRC window A-3, 112 CLEANUP window A-3, and 111 RECIRC window G-3 CRS Direct the Equipment Operator to attempt to start the "I B" RECW pump from the breaker PRO Recognize "IB" RECW pump is running

Attachment to Form ES-D-2 Op-Test No. Scenario No. B Event No.: 4 Event

Description:

Failure of both seals on "IA" Reactor Recirculation pump/Reactor Coolant System Leak Time Position Applicant's Actions or Behavior RO/PRO Reference ARCs for 111 RECIRC window A-1 RO/PRO Recognize failure of the #1 seal on the "IA" RRP, and notify CRS RO/PRO Reference ARC for 111 RECIRC window A-2 RO/PRO Recognize failure of the #2 seal on the "IA" RRP, and notify CRS RO Recognize drywell pressure is rising CRS Enter OT-1 01, High Drywell Pressure CRS Direct PRO to maximize drywell cooling PRO Ensure drywell cooling is maximized CRS Direct PRO to perform section 3.4 of OT-101 PRO Trip "IA" RRP PRO Close "IA" RRP discharge, seal purge, and suction valves PRO Recognize "IA" RRP discharge valve has failed to close RO/PRO Request EO/Floor Supervisor investigate failure of "IA" RRP discharge valve

Attachment to Form ES-D-2 Op-Test No. Scenario No. B Event No.: 5 Event

Description:

Failure of both seals on "IA" Reactor Recirculation pump/Reactor Coolant System Leak CRS Before drywell pressure reaches 1.68 psig, order rapid plant shutdown per GP-4, Rapid Plant Shutdown to Hot Shutdown PRO Transfer house loads to startup buses per S91.6.B PRO Runback "1B" recirc pump to minimum speed RO Manually scram the reactor at 50% core flow CRS Enter T-1 01, RPV CONTROL, on low RPV level RO Report all control rods fully inserted RO Place reactor mode switch in SHUTDOWN RO Insert SRMs/IRMs CRS Direct trip of the main turbine PRO Trip the main turbine CRS Direct the RO to maintain RPV level 12.5 to 54 inches using feedwater RO Align feedwater for startup level control per S06.1 .D, POST SCRAM LEVEL CONTROL, and maintain 12.5 to 54 inches CREW Recognize drywell pressure greater than 1.68 psig CRS Enter T-102, PRIMARY CONTAINMENT CONTROL, and re-enter T-101 PRO Recognize HPCI start and notify CRS CRS Direct PRO to minimize HPCI injection PRO Place HPCI controller to MANUAL, and reduce HPCI speed to terminate HPCI injection CRS Direct PRO place one loop of suppression pool spray in service PRO Place one loop of RHR in suppression pool spray per T-225, STARTUP AND SHUTDOWN OF SUPPRESSION POOL AND DRYWELL SPRAY OPERATION CRS When drywell temperature is above 145 deg. F., direct the PRO to maximize drywell cooling, bypassing isolations per GP-8 as necessary

Attachment to Form ES-D-2]

Op-Test No. Scenario No. B Event No.: 5 Event

Description:

Failure of both seals on "IA" Reactor Recirculation pump/Reactor Coolant System Leak CRS Evaluate Drywell Spray Initiation Limit Curve on T-102 CRS Evaluate Pressure Suppression Pressure Limit Curve on T-102 CT CRS When plant conditions cannot be maintained on the safe side of the Pressure Supression Pressure Curve, then enter T-1 12, EMERGENCY BLOWDOWN CRS Direct 5 ADS/SRVs opened PRO Open 5 ADS/SRVs CREW Recognize LOCA signal imminent CREW Perform SE-1 0, LOCA following LOCA signal PRO Control ECCS injection to prevent flooding Main Steam Lines (maintain RPV level below +118 inches)

CRS Direct H2/02 analyzers bypassed and restored per GP-8.5 PRO Bypass and restore H2/02 analyzers per GP-8.5 CRS Recognize conditions on SAFE side of Drywell Spray Initiation Limit Curve CRS Direct drywell sprays per T-225 PRO Recognize HV51-1 F021A valve will not open RO/PRO Request EO/Floor Supervisor investigate failure of HV51-1F021A PRO Recognize "1 B" RHR pump will not start RO/PRO Request EO/Floor Supervisor investigate failure of the "IB" RHR pump to start CRS Direct drywell spray using RHRSW or Fire Water CT PRO/RO Spray drywell per T-225 using RHRSW or Fire Water Termination Point:

The scenario will be terminated when the following criteria are met:

1. Drywell spray has been initiated with RHRSW or Fire Water per T-225