Text

June 50-269/2003-301 Final JPMs & Outlines
	ML032480909
Person / Time
Site:	Oconee
Issue date:	08/11/2003
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Rosalyn Jones; Duke Energy Corp
Shared Package
ML032521014	List: IR 05000269/2003301; ML032020259; ML032471475; ML032471483; ML032471531; ML032480791; ML032480796; ML032480798; ML032480800;
References
	50-269/03-301, 50-270/03-301, 50-287/03-301, ES-D-1, NUREG-1021, Rev 9 50-269/03-301, 50-270/03-301, 50-287/03-301
	Download: ML032480909 (486)
	v • d • e

Final Submittal

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OCONEE JUNE 2003 EXAM 50-269/2O03-30 1

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JUNE 16 27,2003 Administrative Questions/JPMs In-plant JPMs Control Room JPMs (simulator JPMs)

OCONEE Initial Exam June 16,2003 Final Submittal

Appendix D Scenario Outline Form ES-D-1 Facility: Oconee Scenario No.: 1, Fnl Op-Test No.:

Examiners: Operators:

Initial Conditions:

75% Reactor Power EOL, per disp; 3r request (Snap -217)

Turnover:

Unit 1 TD EFDW Pump 00s to repair oil leak, expected returned this shift SASS in MANUAL for I&E testing AMSAClDSS bypassed for I&E testing Keowee Unit 1 generating to the grid Diamond in MANUAL for I&E test Chemistry has requested that the RCS be De-Lithiation with the Normal deborating Demineralizer for 5 minutes. OP/l103/004 Encl. 4.26 completed up to step B Letdown Filter isolated due to leak

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2 MP1121, 100 I, BOP, SRO PZR LVL #1 Transmitter Fails HIGH 3 MCR021 C, OATC, SRO Drop CR Group 2 Rod 6, (TS)

Override Diamond blocked from AUTO operation 4 MPS440 (40- C, BOP, SRO IA, RCP High Vibration (secure RCP)

mob)

I MP1281 I I, OATC, SRO I AT,fails HIGH when RCP secured

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6 ~ I MCR022 I C, OATC, SRO I Second dropped control rod, requiring a manual reactor trio I I I 7 1 MELO90 1 MALL 1 ATWS I I 1 CT-1 Lockout (Loss of Power)

8 MELl80 M, ALL Keowee Unit 1 Emergency Lockout (blackout, P W NUREG-I 021, Draft Revision 9 Page 1 of 14

Appendix D Scenario Outline Form ES-D-1

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3p-Test No.: __ Scenario No.: 1 Event No.: 1 Page 1 of 1 Event Description: De-Lithiation with the deborating Demineralizer (N, BOP)

Position Applicants Actions or Behavior BOP Refer to OP/1/A/1103/004 (Soluble Poison Control) Enclosure 4.26 (Step 2.6) to begin de-lithiatio Perform OP/1/A/1103/004, Soluble Poison Control, Enclosure 4.26 Place Deborating IX in service:

Review Limits and Precautions Verify closed ICs-32 & 37 (SPARE DEBOR IX INLET &

OUTLET)

Close 1CS-26 (Letdown to RC Bleed)

Open ICs-27 (Debor IX Inlet)

Open IHP-16 (LDST Makeup Isolation)

Verify IHP-15 (LDST Makeup Control) in MANUAL and open Position IHP-14 (LDST Bypass) to BLEED Record letdown pressure (contact NEO, Cue: 115 psig)

Wait 5 minutes Restore system per O P I I I ~103/004, I Soluble Poison Control, Enclosure 4.26:

Place IHP-14 (LDST Bypass) in NORMAL Close IHP-16 (LDST Makeup Isolation)

Reset IHP-15 Moore Controller for Normal Operation(LDST Makeup Control)

Close ICs-27 (Debor IX Inlet)

Open 1CS-26 (Letdown to RC Bleed)

Complete OP/1/A/1103/004, Soluble Poison Control, Enclosure 4.26 When de-lithiation is complete or when directed by the lead evaluator this event is completed.

NUREG-1021, Draft Revision 9 Page 2 of 14

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: - Scenario No.: 1 Event No.: 2 Page 1 of 1 Event Description: PZR Level # Transmitter I Fails HIGH: (I,BOP)

Position Applicants Actions or Behavior Plant response:

StataIarms ISA-ZC-3, RC Pressurizer Level HighlLow ISA-ZC-4, RC Pressurizer Level Emerg. HighlLow Front board (1UBI) indications:

PZR Level 1 indicates 400 IHP-120 (RC Volume Control) throttles closed Makeup flow decreases to = 0 gp Crew response:

BOP Refer to ARG:

rn Check alternate PZR level indications (IUBI and OAC) and determine that PZR level 1 has failed hig Check for proper MakeupILetdown flows and adjust to restore proper leve SROIBOP SRO should direct the BOP to take actions to restore normal PZR leve SROIBOP SRO should refer to PT/600/001 (Periodic Instrument Surveillance) SASS Manual Operation and have the BOP select an alternate PZR level channel on 1UB When an alternate PZR level channel has been selected or when directed by the lead evaluator this event is completed.

NUREG-1021, Draft Revision 9 Page 3 of 14

Appendix D Scenario Outline Form ES-D-1 3p-Test No.: - Scenario No.: 1 Event No.: 3 Page 1 of 2

vent Description: Dropped Control Rod: (C, OATCISRO) (TS)

When directed by the Lead Examiner Group 2, rod #6 drops into the Applicant's Actions or Behavior Plant response:

Statalarms 1SA-2/B-10, CRD Position Error Position Indicating Panel API indication of dropped rod on individual meter In limit (zero %) green light on respective dropped ro Loss of respective dropped rod out limit (100%) red ligh Amber 7" asymmetric lights on the dropped rod and the entire grou Diamond Panel indications 9 asymmetric lam Group In Limit (green) lamp on respective grou Crew will use "Plant Transient Response" process to stabilize the plan OATC Acknowledge and verbalize to the SRO the most important Statalarm received for the failur Verbalize to the SRO reactor power level and direction of movemen Recognize that a valid runback should be occurring but is not BOP because the ICs is in manua Refer to ARG for 1SA-2/B-10, CRD Position Error Inform SRO entry into AP/015, Dropped Control Rods is reauire The SRO should use the OAC to monitor unit statu SRO Enter AP/l/NI 700/15, Dropped Control Rods NUREG-1021, Draft Revision 9 Page 4 of 14

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: - Scenario No.: 1 Event No.: 3 Page 2 of Z Event Description: Dropped Control Rod: (C, OATCISRO) (TS)

Position Applicant's Actions or Behavior SRO Direct actions per AP1015, Dropped Control Rod . Verify 5 one dropped control rod or misaligned 9 (6%) from group averag OATC 2. Verify Reactor is critical 3. Verify runback to 55% FP in progres OATC should determine that a runback is not in progress due to ICs in manual and initiate a manual runback as directed by the SR . Initiate Enclosure 5.1 (Control of Plant Equipment During BOP Shutdown)

Notify WCC SRO to make notifications Ensure 1A and 1B MSRH DRN PUMP stopped Place 1FDW-53 and 1FDW-65 (MFDWP Recircs) in MANUAL and closed Place IHD-37 and IHD-52 in DUM Start the 1A and 1B MFDW Pump's Seal Injection and Aux oil pump . Notify I&E (SPOC) to perform the following:

SRO Investigate cause of dropped rod Prepare to reduce RPS FluxIFlow-Imbalance and RPS High Flux setpoint . Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify > 1% SDM with the allowance for inoperable control rod@)by performing PT/I/A/I 103/15, Reactivity Balance Calculation . Refer to TS 3.2.3 Quadrant Power Tilt (QPT) and 3.1.4 Control Group Alignment Limit Verify QPT within COLR limit 3. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , ensure reactor power is less than 60% of the allowable power per the RCP combinatio dote: The crew may elect to place the Diamond in Auto to let he unit runback. However going to Auto is blocked by a nalfunction of the auto/manual pushbutto OATC 3. Begin reducing reactor power to less than 60% (55% OP limit)

with the ICs in manua When power is being reduced with the ICs in manual this went is completed.

NUREG-I 021, Draft Revision 9 Page 5 of 14

Appendix D Scenario Outline Form ES-D-1 3p-Test No.: ___ Scenario No.: 1 Event No.: 4 Page 1 of 1 Event Description: IA, RCP High Vibration: (C, BOPISRO)

-Time Position Applicant's Actions or Behavior

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BOP Statalarm 1SA-9/D-2 (RC PUMP VIBRATION HIGH) will alar . The BOP should refer to the ARG 2. Verify RCP vibration conditions by using RCP OAC Display Group RCP 3. Refer to AP/016, Abnormal Reactor Coolant Pump Operatio SRO Determine RCP immediate trip criteria are not met by referring to Enclosure 5.1 (RCP Immediate Trip Criteria).

Since immediate trip criteria is not met then notify the OSM and request an evaluation of the RCP vibration condition by the RCP Component Enginee Statalarm 1SA-9/E2 (RCP VIBRATION EMERG HIGH) will actuat BOP 1. The BOP should determine that the immediate trip criteria are now met based on Enclosure 5.1 (RCP Immediate Trip Criteria)

and inform the SR . The SRO should direct the BOP to:

SRO Verify Reactor power 5 70%

Verify four RCPs operating Trip the 1Al RC . Trip the 1Al RC BOP When crew has tripped the RCP this event is completed.

u NUREG-1021, Draft Revision 9 Page 6 of 14

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: __ Scenario No.: 1 Event No.: 5 Page 1 of 1 Event Description: AT,fails HIGH: (I, OATC)

Time When the IA, RCP is secured ATcfails HIGH Statalarm ISA-OZB-5 (RC Cold Leg Diff. Temperature High)

will actuat FDW flow will ratio based on the failure A FDW flow will increase causing A loop Tc to decreas B FDW flow will decrease causing Bloop Tc to increas This will cause actual ATcto increase OATC Diagnose the ATcfailure by observing the ATcmeter on 1UB1. It should return to zero but is staying a + 3.5 degree Take the Feedwater Masters to MANUAL and re-ratio feedwater using the loop Tc meters to return actual ATc to near zer SRO May refer to AP/28 (ICs Instrument Failures)

When the OATC has re-ratioed FDW and returned Tc to near zero or when directed by the lead examiner this event is completed.

NUREG-1021, Draft Revision 9 Page 7 of 14

Appendix D Scenario Outline Form ES-D-1 3p-Test No.: - Scenario No.: 1 Event No.: 6 Page 1 of 1 Event Description: Second dropped Control Rod (Manual Reactor Trip): (M, OATCISRO)

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Time Position Applicants Actions or Behavior After reactor power has been reduced and when directed by the lead examiner a second control rod will dro Plant response:

Statalarm 1SA-2/D-10 (CRD Continuous Boron Dilute Permit) actuates CRD PI Panel API indication of dropped rod on individual meter In limit (zero %) green light on respective dropped ro Amber 7 asymmetric lights on the dropped rod and the entire grou Crew response:

OATC The OATC should determine that a second control rod has dropped into the core by observing the CRD PI Panel and MANUALLY TRIP THE REACTOR. OATC will attempt to trip the reactor by depressing the reactor trip pushbutto Note: The reactor will NOT trip when the button is depresse SRO SRO should ENSURE that a manual reactor trip is performe SRO enters EOP IMAs After the reactor pushbutton has been depressed this event is completed.

d NUREG-1021, Draft Revision 9 Page 8 of 14

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Appendix D Scenario Outline Form ES-D-1 Op-Test No.: - Scenario No.: 1 Event No.: 7 Page 1 of 4 Event Description: CT-1 Lockout and an ATWS: (C, ALL)

When the manual reactor trip push button is depressed, the reactor will not trip and an ATWS will occur. When reactor power is less than 5% the turbine will be tripped and CT-1 (startup transformer) will lockout, which will result in a loss of power. Power will be restored from Keowee Unit 1 in approximately 35 seconds via the underground Dath and CT ~ ~ ~

Time Position Applicant's Actions or Behavior

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OATC Recognize that the Reactor should have tripped and begin performing Immediate Manual Action BOP Adjust FDW to match reactor power and maintain Tave near setpoint.

NUREG-I 021, Draft Revision 9 Page 9 of 14

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: __ Scenario No.: 1 Event No.: 7 Page 2 of 4 Event Description: CT-1 Lockout and an ATWS: (C, ALL)

When the manual reactor trip push button is depressed, the reactor will not trip and an ATWS will occur. When reactor power is less than 5% the turbine will be tripped and CT-1 (startup transformer) will lockout, which will result in a loss of power. Power will be rest, ed from Keowee Unit 1 in approximately 35 seconds via the underground path ar CT- Time Position AoDlicant's Actions or Behavior SRO Transfer to the UNPP tab from IMAs and direct the following actions:

Announce plant conditions Ensure Rule 1 is in progress or complet Verify Main FDW availabl IAAT A power range Nls are ~ 5 % FP, THEN ensure the turbine-generator is trippe Note: This action will result in a unit loss of power f o r - 35 seconds due to CT-1 lockou Verify A wide range Nls 21% F Maximize letdow Verify Main FDW availabl Adjust Main FDW flow as necessary to control RCS temperatur Verify overcooling NOT in progres Ensure makeup to the LDST is secure WHEN Nls are < I % FP, AND decreasing, THEN continue in this ta Note: Due to sequence of events all steps may not be completed.

LJ NUREG-1021, Draft Revision 9 Page 10 of 14

Appendix D Scenarlooutline Form ES-D-1 Op-Test No.: __ Scenario No.: 1 Event No.: 7 Page 3 of 4 Event Description: CT-1 Lockout and an ATWS: (C, ALL)

When the manual reactor trip push button is depressed, the reactor will not trip and an ATWS will occur. When reactor power is less than 5% the turbine will trip and CT-1 (startui :ransformer)will lockout, which will result in a loss of power. Power will be restore from Keowee Unit 1 in approximately 35 seconds via the underground path

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and C l Time Position Applicant's Actions or Behavior BOP Perform symptoms check and when asked report no other symptom When power is regained on the Main Feeder Buses perform AP/I 1, Recovery from Loss of Powe m IAAT Pzr level > 8 0 [180" acc],

THEN ensure Pzr heaters in AUTO Verify load shed is complete as indicated by LOAD SHED COMPLETE on ~JY ES Module (Channel 1 or 2).

Dispatch an operator to perform Encl 5.2 (Restoring Loads Outside the Control Room).

Dispatch an operator to perform Encl 5.4 (Actions to Restore ESV System to Normal Operation).

Verify condenser vacuum maintaine Verify IA header pressures 2 90 psig:

OATC Determine the Main Feedwater Pumps have tripped as a result of the loss of power and perform RULE 3 (Loss of Main or Emergency FDW).

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Ensure any EFDWP operating Initiate Enclosure 5.9 (Extended EFDW Operation)

9 Throttle Motor Driven EFDW as necessary to prevent overcooling.

NUREG-1021, Draft Revision 9 Page 11 of 14

Appendix D Scenario Outline Form ES-D-1 3p-Test No.: __ Scenario No.: 1 Event No.: 7 Page 4 of 4 Event Description: CT-1 Lockout and an ATWS: (C, ALL)

When the manual reactor trip push button is depressed, the reactor will not trip and an ATWS will occur. When reactor power is less than 5% the turbine will trip and CT-1

[startup transformer) will lockout, which will result in a loss of power. Power will be restored from Keowee Unit 1 in approximately 35 seconds via the underground path and CT- Position Applicant's Actions or Behavior SRO When the turbine is tripped and power is lost:

Two possible paths GO TO the "Blackout" tab per parallel actions page In the blackout tab, the crew will: verify power restored, initiate AP/11(Recovery from Loss of Power) and transfer to Subsequent Action OR If power is restored prior to transferring to blackout tab, SRO will complete UNPP ta When power is regained to the 4160-switchgear use a

"Parallel Actions" transfer from the yellow page to initiate APll1(Recovery from Loss of Power).

Determine that reactor power is s 1%.

Direct an RO to throttle HPI per Rule 6 and adjust Letdown if neede . Transfer to Subsequent Actions Verify all control rods are inserted Verify Main FDW is not operating and ensure SG level are approaching 2 4 0 XSU Verify all 4160V switchgear (ITC, ITD, ITE) energize This event is completed when EOP Encl. 5.9 (Extended EFDW Operation) is initiated or when directed by the lead examiner.

NUREG-1021, Draft Revision 9 Page 12 of 14

Appendix D Scenario Outline Form ES-D-1 3p-Test No.: __ Scenario No.: 1 Event No.: 8 Page 1 of 2

vent Description: Keowee Unit 1 Emergency Lockout, Unit Blackout: (M,ALL)

Uote: When directed by the lead examiner Keowee Unit 1 Emergency Lockout will 3ccu Position Applicant's Actions or Behavior Keowee Unit 1 Emergency Lockout will result in a Unit Blackou SRO 1. 'Determine that CC and HPI are lost and initiate AP/25 (SSF Emergency Operating Procedure)

The SRO will make a "Parallel Actions" transfer to the Blackout ta Close IHP-31 (RCP Seal Flow Control) and IHP-21 (RCP Seal Return).

Determine SGs are not being feed and dispatch operators to the Atmospheric Dump Valve Note: Since the TD EFDW Pump is 0 0 s no source of FDW is available t o the SGs until power is restored from CT- Notify SSF operators that feeding with SSF ASW is require Initiate Enclosure 5.38 (Restoration of Power)

Note: If RCS pressure reached 2300 psig the crew will initiate Rule 4 (Initiation of HPI Forced Cooling). Because no power is BOP available to the HPI pumps the rule will be exite Perform Enclosure 5.38 (Restoration of Power) (CT-8)

1. Verify MFBI and MFB2 de-energized 2. Determine CT-1 has no voltage 3. Verify both Standby Buses de-energized 4. Verify all Keowee Units operating Note: Keowee 1 emergency locked out, Keowee 2 operatin . Notify Keowee operator to give Oconee Control for Keowee 2 6. Close ACB-4 (Unit 2 MER FDR)

7. Verify CT-4 voltage 4160 8. Place CT-4 Bus 1 and 2 AUTO/MAN switches in MANUAL 9. Place STBY BUS Iand 2 SYNCHRONIZING switch in ON.

NUREG-1021, Draft Revision 9 Page 13 of 14

Appendix D Scenario Outline Form ES-D-1

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3p-Test No.: __ Scenario No.: 1 Event No.: 8 Page 2 of 2 Event Description: Keowee Unit 1 Emergency Lockout, Unit Blackout: (M, ALL)

Position ADDlicant's Actions or Behavior BOP I O . Close SKI and SK2 11. Place STBY BUS 1 and 2 SYNCHRONIZING switch in OF . Verify Standby Bus # I energize . Notify SRO Standby Bus # I is energize . Place the following switches in MANUAL:

MFBI AUTOIMAN MFB2 AUTOIMAN STANDBY 1 AUTOIMAN STANDBY 2 AUTOIMAN 15. Ensure the following breakers open:

N1 andN2 E l and E2 16. Close S I and S2 Note: This will power the Main Feeder Buse . Verify any of the following energized:

ITC, ITD, I T E 18. Notify SRO of status of 4160V SWGR 19. Use RULE 3 to establish EFDW flow to SG This event and the exam are complete when plant is in a safe configuration i.e. EFW is restored or when directed by the ~

Lead Examiner.

ii NUREG-1021, Draft Revision 9 Page 14 of 14

Appendix D Scenario Outline Form ES-D-1

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Facility: Oconee Scenario No.: 2, fnl Op-Test No.:

Examiners: Operators:

Initial Conditions:

100% Reactor Power (IC-41)

Turnover:

AMSAClDSS bvuassed for I&E testina-SASS in manuaifor I&E testina LII Condensate Booster PumpOOS, breaker to be replaced sowee Unit 2 00s for unplanned reasons Event N _ Oa Ob Pre-Insert NI-9 00s MN1082

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oc Pre-Insert AAFlS circuit disabled AOR B AFlS circuit disabled Od Pre-Insert MEL180 1 1 Keowee Unit 2 Emergency Lockout

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Oe Pre-Insert ES Channels 7 and 8 fail to automatically actuate la Override N. BOP, SRO Low ACFT Pressure (N2makeup)

Ib Override C, BOP, SRO IN-298 (N2 Fill CFT I A ) fails OPEN

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2 MPSO9O C, OATC, SRO IHP-120 (RC Volume Control) Fails closed 3 MCS004 I, OATC. SRO Controllina Tave fails HIGH

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- 5 MPS020 C, ALL 1 1B SG Tube leak 5 gpm (TS)

6 MPS020 I 1B SG Tube leak increases to rupture of 100 gpm

- 7 1 R. O A K . SRO 1 Unit Shutdown 8 MSS360,50 1 M,ALL 1A Main Steam line break in RB

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(N)orn (R)eactivity, (I)nstrument, (C)omponent, (M)ajor i/

NUREG-1021, Draft Revision 9 Page 1 of 11

Appendix D Scenario Outline Form ES-D-1 3p-Test No.: __ Scenario No.: 2 Event No.:

Event Description: Low A CFT pressure (N2 makeup) (N,BOP/SRO)

T-Position Plant response:

1SA-08/A-1lI CF TANK A PRESS HlGHlLOW will actuat Crew response:

1. The crew should refer to the AR . Refer to OP/1104/001, Enclosure 4.7 (Pressure Makeup To CFTs Using Nitrogen) to adjust CFT pressur Direct an NE0 to open IN-I 37 (CFTs Supply)

F Cue: Time compression used to open IN-137. This is used to speed the opening of the valve. It would take time for the NE0 to travel from work control to the Auxiliary Buildin Open IN-298 (N2 Fill CFT IA)

i/

NUREG-1021, Draft Revision 9 Page2of 11

Appendix D Scenario Outline Form ES-D-1 lp-Test No.: __ Scenario No.: 2 Event No.: 2 Page 1 of 1 ii Ivent Description: IN-298 (N2 Fill CFT IA) fails OPEN (C, BOPISRO)

Time Position Applicant's Actions or Behavior Plant response:

1. Determine 1N-298 has failed to close:

Red "open" light lit BOP CFT pressure continues to increase 2. Inform the SR . Direct the NE0 to close IN-I37 (CFTs Supply).

Note: If IN-I37 is not closed the CFT pressure will continue to increase, possibly outside of TS limit . Verify 1A CFT pressure is stabl When CFT pressurization is stopped or when directed by the lead examiner this event is completed.

ii u

NUREG-I 021, Draft Revision 9 Page 3 of 11

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: __ Scenario No.: 2 Event No.: 2 Page 1 of 1 Event Description: 1HP-120 (RC Volume Control) Fails closed (C, OATCISRO)

Time 1. Diagnose 1HP-120 (RC Volume Control) failed closed:

RCS makeup flow goes to zer PZR level begins to decreas LDST level begins to increas Valve position demand for IHP-120 begins to increase to the 100% demand value and valve position indication will indicate closed (green light).

SRO 2. Refer to APll4 (Loss of Normal Makeuo and/or RCP Seal Injection).

Determine Seal Injection is not lost Determine loss of suction to HPI pumps has not occurred and GO TO Step Verify HPI pump operatin Verify RCP seal injection flow exist Verify RCP seal injection or HPI makeup line leak is not indicated and GO TO Step 4.1 Verify all RCPs seal return temperatures are < 240° Verify IHP-120 has failed and GO TO Step 4.18 Perform the following as necessary to maintain Pzr level >

200:

= Close IHP-6 (Letdown Orifice Stop)

Throttle IHP-7 (Letdown Control)

1 Throttle IHP-26 ( I A HP Injection)

SRO Ensure IHP-120 to HAND and close 3. Contact SPOC to repair IHP-12 Note: IHP-120 will remain failed for the duration of the or when directed NUREG-1021, Draft Revision 9 Page 4 of 11

Appendix D Scenario Outline Form ES-D-1 Ip-Test No.: __ Scenario No.: 2 Event No.: 3 Page 1 of 1

vent Description: Controlling Tave fails HIGH (I, OATCISRO)

When directed by the lead examiner controlling Tave will fail hig Time Position Applicant's Actions or Behavior

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Plant response:

1. ISA-OZA-12, ICs Tracking, will actuate due to neutron and feedwater cross-limit . Controlling Tave will indicate = 596.4" . Actual loop A & B Tave will decrease until operator stops transien . RCS pressure and temperature will decreas Crew response:

1, When the ICs TRACKING alarm is received, the candidates OATC should utilize the "Plant Transient Response" process to stabilize the plant and recognize that the controlling Tave has failed. RX will trip on variable low pressure with no operator actio . Verbalize to the SRO reactor power level and direction of movemen . Place the FDW Masters in manual and stabilize the plant. Use control rods and FDW to stabilize the plant SRO 4. The SRO should:

Refer to AP/28, ICs Instrument Failures Contact SPOC to repair controlling Tav Note: The ICs will remain in manual for the remainder of the scenari When the plant is stable or when directed by the lead examiner this event is completed.

NUREG-I 021, Draft Revision 9 Page 5 of 11

Appendix D Scenario Outline Form ES-D-1

)p-Test No.: __ Scenario No.: 2 Event No.: 4 Page 1 of 1

vent Description: Seismic event (PRA)

1A RBCU rupture (C, BOPISRO) (TS)

Position Applicant's Actions or Behavior 1, 1SA-9/B-9, LPSW RBCU A Cooler Rupture will actuate and RB normal sump level will increas The BOP should refer to ARG for 1SA-9/B-9 BOP Verify alarm is valid by checking RBCU 1A Inlet Flow and RBCU 1A delta flo Verify ILPSW-18 (RBCU 1A Oultlet) open Verify adequate LPSW flow is available; check LPSW pump operation Monitor RBNS Level for any unexplained increase (Notify Chemistry to sample RBNS for boron to determine if a cooler rupture has occurred).

Diagnose a Cooler Rupture is indicated and Isolate the 1A RBCU Coole SRO 2. The SRO should determine that isolation of LPSW to a RBCU places the Unit in Tech Spec 3.6.5 Condition B (7 day completion Time) and refer to SLC 16.9.12 (Additional LPSW And SSW System operability Requirements).

Note: The control room will receive a phone call from security that indicates that a tremor has been felt but no damage has been note SRO 3. The SRO may refer to AP/05, Earthquak Dispatch operators to perform plant inspections Note: No damage will be reporte 'Notify SPOC to develop the Strong Motion Accelerometer tap ,*Verify NO fuel handling activities in progres * These items may not be completed depending on how soon the next event is starte Note: Team may decide at this time to begin a unit shutdow Refer to event When the RBCU has been isolated, or at the direction of the Lead Examiner this event is completed.

NUREG-1021, Draft Revision 9 Page 6 of 11

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Appendix D Scenario

_ Outline

_ Form ES-D-1 3p-Test No.: __ Scenario No.: 2 Event No.: 5 Page 1 of 2 Event Description: 1B SG Tube leak (5 gpm) (C, ALL) (TS)

16 SG tube leak occurs following RBCU isolation or when directed by tl lead evaluato Position Applicant's Actions or Behavior Plant response:

1. The following alarms actuate:

1SA-8/B-9, RM PROCESS MONITOR RADIATION HIGH ISA-8/D-10, RM CSAE EXHAUST RADIATION HIGH 2. PZR level will decreas Crew response:

ALL 1. Diagnose and take actions for a Tube leak in the 1B SG:

BOP 2. Refer to the ARG for the following alarms:

1SA-8/B-9, RM PROCESS MONITOR RADIATION HIGH ISA-8/D-10, RM CSAE EXHAUST RADIATION HIGH SRO 3. Refer to AP131 (Primary to Secondary Leakage)

BOP Monitor primary parameters; PZR Level and LDST level to SRO determine that gross leakage exist and transfer to step 4.7 Path 1 (crew determines that leakage is gross)

Using an RCS inventory balance, determine OTSG tube BOP leak size is less than 25 gp SRO Path 2 (crew determines that leakage is NOT gross)

Notify RP and Chemistry Determine leak rate using the OAC is 2 100 gp Common path Greater than 25 gpm will require entering the EO Log RIA readings (a rough log is adequate)

Initiate a Unit shutdown to met requirements of Encl. (Unit Shutdown Requirements). (Per Enclosure 5.1 reduce power < 50% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and TS 3.4.13 appllies).

9 Initiate a unit shutdown using OP/l/NI 102/004 (Operation At Power)

Note: A shutdown with the ICs in manual is require When the SRO has directed a manual Unit shutdown or when directed by the Lead Examiner the event is completed.

NUREG-1021, Draft Revision 9 Page 7 of 11

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: - Scenario No.: 2 Event No.: 7 Page 1 of 1 Event Description: Unit Shutdown (R,OATC)

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Time Position Applicant's Actions or Behavior 3ATClSRO The OATC will use the FDW Masters and the Diamond to reduce power while monitoring Reactor Power, Tave, and other plant parameter If the reactor trips automatically the team must return to IMA The BOP will utilize Enclosure 5.19 (Control of Plant Equipment During Shutdown for SGTR).

1. Notify WCC SRO to make notifications 2. Stop 1A and 1B MSRH Drain Pump 3. Place 1FDW-53 and 1FDW-65 in manual and closed. (Located on 1VB3)

4. Place IHD-37 and IHD-52 in DUM . Start the both FDWPs Seal Injection and Auxiliary Oil Pump . When Reactor power is 5 80%, stop 1El and 1E2 Heater Drain Pump . Transfer electrical auxiliaries Place I T A AUTO/MAN transfer switch in MAN Place I T B AUTOlMAN transfer switch in MAN Close ITA SU 6.9 KV FDR Close I T B SU 6.9 KV FDR Place MFBI AUTOlMAN transfer switches in MAN Place MFB2 AUTOlMAN transfer switches in MAN Close Ell MFBI STARTUP FDR 4. Close E21MFB2 STARTUP FDR Note: the team may manually trip the reactor if PZR level cannot be maintainedwith full HPI. This may occur because of the tube leak and RCS cooldow Note: If the reactor is manually tripped activate event When a unit shutdown of > 5% has occurred or when directed by the lead examiner this event is concluded.

NUREG-I 021, Draft Revision 9 Page 9 of 11

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: __ Scenario No.: 2 Event No.: 8 Page 1 of 2 Event Description: 1A Main Steam line break in RB (M, ALL)

1A main steam line break will occur following - event 7 as directed by the rd examine Time Position Applicants Actions or Behavior ALL Plant response:

1, Statalarm 1SA-OZA-9, MS Press High/Low, actuates 2. Aand B main steam (MS) pressure decreases 3. Reactor trip B MS line pressure stops decreasing A MS line pressure continues to decrease RCS may saturate Crew response:

1. The OATC will perform and verify IMA Depress REACTOR TRIP pushbutton SRO Verify reactor power < 5% FP and decreasing Depress TURBINE TRIP pushbutton Verify all turbine stop valves closed OATC Verify RCP seal injection available 2. The BOP will perform a symptoms chec . The Crew should respond to the MSLB in the IA SG BOP 4. The BOP will perform Rule #5 (Main Steam Line Break) after receiving concurrence from the SRO. (CT-17)

Stop 1A MDEFDW Pump OATC Initiate both trains of MSLB isolation Ensure both Main FDW pumps tripped Steam 1B SG to maintain CETCs constant 5. If SCM = 0°F then the OATC will perform Rule #2 (Loss of SCM)

after receiving concurrence from the SRO. (CT-1, CT-2)

Trip ALL RCPs within 2 minutes Ensure open 1HP-24 and 1HP-25 Ensure ALL HPI pumps operating Ensure open 1HP-26 and 1HP-27 Verify required HPI flow per header NUREG-I 021, Draft Revision 9 PageIOof11

Appendix D Scenario Outline Form ES-D-1 3p-Test No.: __ Scenario No.: 2 Event No.: 8 Page 2 of 2

vent Description: 1A Main Steam line break in RB (M, ALL)

Position Applicants Actions or Behavior BOP Verify TBVs available Feed all intact SGs Control EFDW as required to raise level to intact SGs to proper setpoint per RULE 7 (SG Feed Control)

Trip both Main FDWPs Place FDW block valve switches (1FDW-33, 31,42,40) in CLOSE:

Maintain SG pressure < RCS pressure SRO 6. The SRO will Parallel Action to transfer to the Excessive Heat Transfer (EHT) tab and direct the Crews actions as follows:

BOP 7. Enclosure 5.1 (ES Actuation) will be performe Diagnose that ES Channels 7 and 8 have not actuate Depress the ES Channels 7 and 8 trip pushbutton on 1UB Note: ES Channel 8 pushbuttonwill not work. This will require the operator to manually start the 1B RBS pump from the ES RZ modul . Excessive Heat Transfer (EHT) tab will:

Verify excessive heat transfer stopped Throttle HPI to stabilize RCS pressure and maintain PZR level > 8 0 (180 acc)

Feed and steam all intact SGs to stabilize RCS P/T. (CT-11)

Minimize SCM using the following methods as necessary:

(CT-7)

k De-energizing all PZR heaters 9 Using PZR spray 9 Throttling HPI Initiate Enclose 5.16 (SG Tube-to-Shell A T Control)

GO TO Steam Generator Tube Rupture (SGTR) ta When the SRO has transferred to the SGTR tab or when directed by the Lead Examiner the event and scenario is completed.

NUREG-1021, Draft Revision 9 Page 11 of 11

Appendix D Scenario Outline Form ES-D-1 Facility: Oconee Scenario No.: 3, fnl Op-Test No.:

Examiners: Operators:

Initial Conditions:

25% Reactor Power (IC-45), startup in progress Turnover:

Unit 1 TD EFDW Pump 00s to repair oil leak NI-9 OOS, to be replaced next outage Keowee Unit 2 00s for unplanned reasons Keowee Unit 1 aligned to underground Operability test of Keowee Unit 1 is to be performe. 2er PT/620/0 (Keowee Hydro Operation) after turnover and before startup continues. ONS to pf rm remote Keowee star Oa 1 Pre-Insert 1 TD EFDW Pump Fails to Start MSS330 Ob Pre-Insert SASS in manual Updater OC I Pre-Insert Uodater I I AMSAC DSS bypassed Pre-Insert MELISO

~ .. .

I Keowee Unit 2 Emergency Lockout 1 MEL020 N, BOP, SRO Operability test Unit 1 Override c, BOP, SRO Keowee Unit IGen Field Flashing Breaker fails to OPEN automaticallv MPS460 Override C. OATC, SRO I A HPI Pump sheared shaft and standby HPI pump fails to start (TS)

3 MN1032 I, OATC, SRO Controlling NI fails LOW 4 MSS310 C, BOP, SRO Loss of Instrument Air 5 MP129O Main FDW Pump Trips C, OATC, SRO Main Turbine Fails to trip (Lockout EHC Pumps)

6 MSS280,lOO M, ALL ATBVs fail open Override 1MS-17 (A TBV Block) fails to close 7 MPSOIO M, ALL A SG Tube Rupture (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-I 021, Draft Revision 9 Page 1 of 11

Appendix D Operator Actions Form ES-D-2 3p-Test No.: - Scenario No.: 3 Event No.: 1 Page 1 of 1

vent Description: Operability test Keowee Unit 1 (N, BOPERO)

H >weeUnit 1 Gen Field Flashing Breaker fails to OPEN omatically (C, BOPERO)

Position Applicant's Actions or Behavior SRO Direct BOP to perform PT/620/009 (Keowee Hydro Operation) to operability test unit 1 Keowee undergroun Use OP/l106/019 (Keowee Hydro At Oconee) to perform an BOP

"Automatic Startup" of Keowee Unit 1 Initial Conditions 1. Verify applicable Statalarms and breaker positions 2. Notify Keowee operator to give Oconee control of Keowee # . Review Limits and Precautions Procedure 1, Place UNIT 1 LOCAL MASTER switch to "START" AND hold until Keowee Unit start . Verify the following:

GEN 1 FIELD BREAKER closes GEN 1 SUPPLY BREAKER closes GEN 1 FIELD FLASHING BREAKER closes 3. Ensure GEN 1 FIELD FLASHING BREAKER trip Candidate should diagnose that the breaker did not open automatically and should open the breaker manually and initiate a work request or contact SPO SRO SRO should direct the BOP to continue with the startu Note: GEN FIELD FLASHING BREAKER automatically trips 5 45 seconds after receiving close signal. Failure of breaker to trip automatically does NOT make the KHU inoperable. Startup procedure may continu BOP 4. Determines KHU # I is operable when test complete 5. Verify ACB-1, Keowee 1 Generator Breaker, close . Verify Unit 1 EMER FDR ACB 3 closed 7. Verify m 4.16 KV on CT4 Volts (2AB3)

8. Close SKI and SK2 (CT4 STBY BUS 1/2 FEEDER)

9. Shutdown Keowee # Event is complete when operability test is complete or when directed bv the lead examiner.

NUREG-1021, Draft Revision 9 Page 2 of 11

p-Test No.: - Scenario No.: 3 Event No.: 2 Page 1 of 2 vent Description: A HPI Pump sheared shaft and the standby HPI pump fails to auto start: (C, OATC)

Position Applicants Actions or Behavior Plant response:

Statalarms:

ISA-2/8-2 (HP RCP Seal Injection Flow HighlLow)

ISA-2/C-2 (HP Injection Pump Disch. Header Pressure HighlLow)

Board indications:

RC Makeup Flow = 0 gpm 1A HPI Pump = 0 amps PZR level will begin to decrease and LDST level will begin to increas Crew response:

OATC 1. Refer to ARG for above Statalarms 2. SRO should refer to AP/014 (Loss of Normal Makeup andlor SRO RCP Seal Injection)

Verify no HPI pump operating OATC Close 1HP-5 (Letdown Isolation)

Ensure IHP-120 (RC Volume Control) in HAND and closed Place 1HP-31 (RCP Seal Flow Control) in HAND and closed Start standby HPI pump (1B HPI pump)

Slowly open IHP-31 in small increments until = 8 gpm/RCP i:

achieve Re-establish normal makeup through 1HPI 2 Reduce IHP-7 demand to 0%.

Close 1HP-6 Ensure the following open:

9 IHP-1 9 IHP-2 9 IHP-3 9 IHP-4 Open IHP-5 Throttle open 1HP-7 for = 20 gpm letdown flo Open IHP-6 Adjust 1HP-7 for desired letdown flo Place IHP-31 in auto.

NUREG-1021, Draft Revision 9 Page3of11

Op-Test No.: __ Scenario No.: 3 Event No.: 2 Page 2 of 2 Event Description: "A" HPI Pump sheared shaft and the standby HPI pump fails to auto start: (C, OATC)

Time Position Applicant's Actions or Behavior

=

SRO 3. Refer to Tech Spec 3.5.2High Pressure Injection Condition "A" Required Action: Restore HPI pump to OPERABLE status Completion Time: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Note: Due to sequence of events, SRO may not review the TS during the scenario. Follow-up questions may be required to ensure knowledge of this competenc ivent is complete when normal makeup and letdown is stablished or when directed by the lead examiner.

NUREG-1021,Draft Revision 9 Page 4 of 11

lp-Test No.: __ Scenario No.: 3 Event No.: 3 Page 1 of 1

-

ivent D criution:

- I Controlling NI fails LOW: (I, OATC) (TS)

Time Position Applicant's Actions or Behavior

-

__

Plant response:

Statalarm ISA-2/A-12 (ICs Tracking)

Diamond will transfer to MANUAL, because indicated reactor power is < 1.5%.

Tave will increase and actual reactor power will decreas Crew response:

OATC 1, Crew should use "Plant Transient Response" to stabilize the plant by placing both FDW Masters in MANUA . Adjust CR and FDW as required to stabilize the plan . SRO should refer to AP/028 (ICs Instrument Failures) and SRO PT/600/001 (Periodic Instrument Surveillance).

4. SRO should refer to TS 3.3.1 (RPS Instrumentation)

Note: ICs will remain in MANUAL for the reminder of the scenari Event is complete when plant is stable or when directed by the lead examiner.

ii NUREG-1021, Draft Revision 9 Page5of 11

3p-Test No.: __ Scenario No.: 3 Event No.: 4 Page 1 of 1

vent Description: Loss of Instrument Air (C, BOP)

Time Position Applicant's Actions or Behavior

-

Plant response:

Statalarm 1SA-4/C-5 (Aux Bldg Air HDR PR Low) activates IA pressure decreasing on Aux and Turb Building gauges located on 1UB Crew response:

BOP 1. Refer to ARG for 1SA-4/C- Send NE0 to start all backup IA compressor Send operators to check fro IA line ruptures or open valve Refer to AP/22 (Loss of Instrument Air)

Start Primary IA Compressor Using paging system, request that plant personnel stop using service and I SRO 2. AP/22 (Loss of Instrument Air)

BOP Direct Unit 2 to dispatch an operator to start the Diesel Air Compresso IAAT Feedwater flow cannot be controlled, trip Reactor and all Main FDW pump IAAT two or more CRD temperatures are > 180°F, trip Reacto Using paging system, request that plant personnel stop using service and I IAAT Aux IA press 5 88 psig dispatch operator to verify Unit 1 Aux IA Compressor is operatin IAAT IA header pressure is < 80 psig and letdown is desired:

Place 1HP-14 (LDST Bypass) to NORMAL Open 1HP-13 (Purification IX Bypass)

Verify Letdown Filter available Open IHP-17 ( I A Letdown Filter Inlet)

Open IHP-6 (Letdown Orifice Stop)

Adjust IHP-7 to obtain desired letdown flo Note: If reactor trips, continue to next even Note: IA leak will be repaired after letdown is aligne Event is complete when AP/22 actions are being performed or when directed by the lead examiner.

NUREG-1021, Draft Revision 9 Page6of 11

lp-Test No.: __ Scenario No.: 3 Event No.: 5 Page 1 of 1 Ivent Description: Main FDW Pump trips and the turbine Fails to trip (C, OATC)

Time Position Applicant's Actions or Behavior Plant response:

1A Main FDW pump trips resulting in a reactor tri The Main Turbine should trip but does not. This will result in a reduction steam pressure in both SG until actions are taken to trip the turbine. The will result in RCS overcooling until trippe Crew response:

SRO 1. SRO will enter the EO . OATC will perform Immediate Manual Actions OATC Depress REACTOR TRIP pushbutton Verify reactor power < 5% FP and decreasing Depress turbine TRIP pushbutto BOP Verify all turbine stop valves closed Note: The OATC should diagnose that the turbine diL .lot trip and then perform the RNO step which will stop both EHC pumps. This will cause the turbine to tri Verify RCP seal injection availabl . BOP will perform a symptom chec Event is complete when EHC pumps have been tripped or when directed by the lead examiner.

NUREG-1021, Draft Revision 9 Page7of 11

3p-Test No.: - Scenario No.: 3 Event No.: 6 Page 1 of 2

vent Description: A TBVs fails open and IMS-17 (A TBV Block) fails to close:

(M, OATC)

-Time Position Applicants Actions or Behavior Note: The A TBVs will fail open at the same time as the turbine tri Plant response:

The ATBVs will indicate full open. The B TBVs will be throttle The RCS will begin to slowly cool off A Main Steam line will begin to depressurize Crew response:

1. The crew may diagnose the TBVs failed open and with SRO guidance try to control SG pressure by taking the TBVs to manual. (This will not work)

2. After trying to control pressure with the TBVs in manual, the SRO may direct them to close IMS-17 (ATBV Block) but it will not clos . An RO should initiate Rule 5 (Main Steam Line Break). (CT-17)

Select OFF on the A MDEFDW Ensure both Min FDWPTs are tripped Close IFDW-315 Close 1FDW-33 and 1FDW-3 . Adjust 1B SG to maintain CETCs constan Ensure Rule 3 (Loss Of Main or Emergency FDW) in progres Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is in progress or complet When notified by the SRO, exit rule.

NUREG-1021. Draft Revision 9 Page8of11

Op-Test No.: - Scenario No.: 3 Event No.: 6 Page 2 of 2 Event Description: A TBVs fails open and IMS-17 (A TBV Block) fails to close:

- . OATC)

Time Position Applicants Actions or Behavior 4. The SRO should make a Parallel Actions transfer to the Excessive Heat Transfer ta . Excessive Heat Transfer tab will:

If any SG pressure < 550 psig ensure Rule 5 (Main Steam Line Break) in progress or complet Verify excessive heat transfer stoppe Verify level in both SGs 96% Throttle HPI to stabilize RCS pressure and maintain Pzr level

> 10 Verify letdown in servic Verify B SG has an intact secondary boundary (intact SG).

Ensure open 1FDW-382 and 1FDW36 Ensure 1B MDEFDWP operatin Feed and Steam B SG to stabilize RCS P/T. (CT-11)

Event is complete when Rule 5 is complete and Excessive Heat Transfer tab is in progress or when directed by the lead examiner.

u NUREG-1021, Draft Revision 9 Page 9 of 11

Op-Test No.: __ Scenario No.: 3 Event No.: 7 Page 1 of 2

~

Event [ scription: SG Tube Rupture: (M, ALL)

Time Position Applicants Actions or Behavior

-

Plant response:

Statalarms:

1SA-8/A-9 (RM Area Monitor Radiation High)

1SA-8/B-9 (RM Process Monitor Radiation High)

1SA-8/D-10 (RM CSAE Exhuast Radiation High)

Board indications:

PRZ level and RCS pressure will decreas Crew response:

SRO should remain in Excessive Heat Transfer Tab and perform the following:

1. Verify initiating Rule 8 (Pressurized Thermal Shock PTS)) is not require . Verify aux steam header being supplied from another uni . OpenAS-8 4. Close ISSH-1, 1SSH-3, and 1SSH- . Notify Chemistry to determine RCS Boron concentratio . Notify RP and Secondary Chemistry to check for indications of a SGT . IAAT the following conditions exist:

ES Bypass Permit satisfied All SCMs > 0°F RCS pressure controllable THEN Bypass ES as required 8. While maintaining RCP NPSH and Pzr level minimize SCM using the following methods as necessary: (CT-7)

De-energizing all Pzr heaters Using Pzr spray Throttling HPI Using PORV NUREG-1021, Draft Revision 9 Page 1Oof 11

Op-Test No.: __ Scenario No.: 3 Event No.: 7 Page 2 of 2 Event Description: A SG Tube Rupture: (M, ALL)

Time Position Applicants Actions or Behavior

=

9. Initiate Encl. 5116 (SG Tube-to-Shell AT Control)

IAAT any SG tube-to-Shell AT approaches either limit THEN take appropriate actio I O . GO TO SGTR ta SGTR tab will:

1. Verify Reactor is tripped and Initiate Encl. 5.5 (Pzr and LDST Level Control)

2. Start A and B Outside Air Booster Fans on Unit 1&2 and Unit (CT-27)

3. Dispatch operator to open TBS pump breakers.

,

Event is complete when TBS pump breakers have been opened or when directed by the lead examiner.

ii

NUREG-1021, Draft Revision 9 Page 11 of 11

Appendix D Scenario Outline Form ES-D-1 L/

Facility: Oconee Scenario No.: SPARE, fnl Op-Test No.: -

Examiners: Operators:

Initial Conditions:

50% Reactor Power, shutdown in progress (IC-44)

Turnover:

AMSAClDSS bypassed for I&E testing NI-9 OOS, to be replaced next outage Event N I Malf. N I Event Type* Event Description AMSAClDSS bypassed Ob oc I1 Pre-Insert MN1082 Pre-Insert I NI-9 00s 1HP-26 Failed CLOSED Od I Pre-insert 1FDW-316 Failed OPEN 1 1 MP1171, 100 1 I, OATC, SRO Th Fails HIGH (repair return to auto)

1 MP1500, 100 1 1 1 C, BOP, SRO

~~ ~

2 MPS290 IA cc Pump trips (I B cc Pump fails to auto 1 Override start)

3 1 MPS110 1 C. BOP, SRO . . .. - Fails IHP-5 -. -- - -

. -. .- clnsed closed 4 I MPS405 I C, BOP, SRO Unidentified RCS leak in RB (20 gpm) (TS)

Inability for CRD insertion in automatic during C, OATC, SRO shutdow Manual CRD power decrease SBLOCA (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9 Page 1 of 11

Appendix D Operator Actions Form ES-D-2 lp-Test No.: __ Scenario No.: SPARE Event No.: 1 Page 1 of 1 ii

vent Description: Tho,fails HIGH: (I, OATC)

Position Applicant's Actions or Behavior Plant response:

Loop A Thot Dixson meter reading goes to 62OoF Thot recorder ~612°F Tave recorder and digital meter increases to 683°F Loop A Delta T meter increases to =65"F Loop A Tave meter increases to ~588OF Statalarm ISA-21B-3, RC Hot Leg Temp High, alarms Crew response:

OATC The crew should use Plant Transient Response to stabilize the uni .

Depending on when ICs is taken to manual, FDW flow may be ii greater than 100%. If this is true, taking ICs to hand will allow NI Power to begin to increase to match FDW flow. When this occurs, the OATC will be required to decrease FDW flows to stop the power increas SRO should refer to AP128 (ICs Instrument Failures).

SRO After the instrument is repaired the SRO should direct the crew from AP128 (ICs Instrument Failures) to return the ICs to aut When the ICs has been returned to auto this event is complete NUREG-1021, Draft Revision 9 Page 2 of 11

lp-Test No.: - Scenario No.: SPARE Event No.: 2 Page 1 of 1 Ivent Description: I A CC Pump trips: (C, BOP)

Time Position Applicant's Actions or Behavior

-

Plant response:

1. Statalarms:

ISA-S/B-l, CC CRD RETURN FLOW LOW ISA-S/C-l, CC COMP COOLING RETURN FLOW LOW ISA-21C-1, LETDOWN TEMPERATURE HIGH 2. Control Board indications:

IHP-5 will close due to high letdown temperature Crew Response:

BOP 1. Refer to ARGs 2. Initiate AP/020 (Loss of Component Cooling)

IAAT both of the following are lost:

P CCtoRCPs P RCP seal injection THEN perform the following:

P Trip RX P Stop all RCPs P Initiate AP/25 (SSF EOP)

SRO IAAT 2 two CRD stator temperatures 2 180"F, BOP THEN trip Open ICC-7 and ICC-8 Verify CC Surge Tank level 2 1 2 .

Manually start the Standby CC Pump SRO 3. Close 1HP- . Initiate AP1032 (Loss of Letdown)

This event is complete when the Standby CC pump is started or when directed by the lead examiner.

u NUREG-1021, Draft Revision 9 Page 3 of 11

3p-Test No.: - Scenario No.: SPARE Event No.: 3 Page 1 of 1 Event Description: 1HP-5 Fails closed: (C, BOP)

Position Applicant's Actions or Behavior SRO 1. AP/032 (Loss of Letdown)

BOP Ensure IHP-120 in HAND and closed Notifv chemist RCS Born samDle needed and normal letdown line is isolate Verify CC in operation Position the standby HPI pump switch to OF Throttle IHP-31 to establish 12-15 gpm SEAL INLE HDR FLO Close IHP-6 Close IHP-7 Ensure the following open P IHP-1 9 IHP-2 9 IHP-3 9 IHP-4 Verify letdown temperature 135°F Open IHP-13 Ensure 1HP-8 and 1HP-9&11 closed Select LETDOWN HI TEMP INTLK BYP switch to BYPAS Ensure IHP-5 is open Note: IHP-5 will not open from the control room or locall SRO GO TO step 4.1 1 Verify 1HP-5 closed Close IHP-6 Close 1HP-7 Dispatch an operator in continuous communication with Control Room to manually open IHP-5 (LETDOWN ISOLATION) (Tech Spec 3.6.3)

When an operator has been dispatched to open IHP-5 or when directed by the lead examiner this event is complete.

ii NUREG-1021, Draft Revision 9 Page 4 of 11

Op-Test No.: - Scenario No.: SPARE Event No.: 4 Page 1 of 1 Event Description: Unidentified RCS leak in RB (20 gpm): (C, BOP) (TS)

Position Applicant's Actions or Behavior Plant response:

1. Statalarms:

1SA-9/A-6, RB Reactor Bldg Norm Sump Level HighlLow 1SA-8/B-9, Process Radiation Monitor High 2. Control board indications:

RBNS level increases Pzr level will decrease very slowly due to the leak and IHP-5 being close Crew response:

BOP I.Refer to ARG for fSA-9/A-6, REI Reactor Bldg Norm Sump Level HighlLow SRO 2. Refer to AP/002, Excessive RCS Leakage I

Initiate Encl. 5.1 (Leak Rate Determination)

Bop Ensure OSM, STA, RP are notified Monitor trend of "T6 AP02 for increases (OAC)

Verify NO leakage through PORVand close IRC-4 Identify leak is in the RB and GO TO Step 4.20 Place standby CC pump switch to OF Close ICC-I/IHP-I and 1CC-2/1HP-2 Verify leakage has stopped (will not)

Verify re-establishing LD is desired (it is not due to IHP-5 failing shut)

Ensure RB isolation valves are close Verify unit shutdown is desired by Station Management SRO should determine unit SD is required due to RCS leak greater than TS limi Ensure unit shut down has been initiated in accordance with one of the following:

9 AP/29 (Rapid Unit Shutdown)

9 OP/1/PJ1102/004 (Operation At Power)

> 0Pl1lA/1102/010 (Controlling Procedure For Unit Shutdown)

Note: OP/1/A/1102/004 (Operation At Power) should be use Event is complete when a unit shutdown is directed by the SRO or when directed by the Lead Examiner.

NUREG-1021, Draft Revision 9 Page 5 of 11

3p-Test No.: __ Scenario No.: SPARE Event No.: 5 Page 1 of 1 Ivent Description: Inability for CRD insertion in automatic during shutdown:

Time Position Applicant's Actions or Behavior

-

SRO Unit shutdown per OP/l/Nl102/004 (Operation At Power) Encl. 3.2, Power Reduction 1. Review Limits and Precautions 2. Notify OSM to contact NRC if require . Start l N l B MFDW pump Seal Injection Pump OATC 4. Select HOLD 5. Select desired shutdown rate 6. Select desired rate of power reduction of RATE SET 7. Select CTPD SET power level 8. Release hold Note: Control Rods will not insert in aut Plant response:

1, Neutron Error goes negative 2. Tave increases 3. When Neutron Error reaches -5, unit will go to track and Statalarm 1SA-2/A-12 (ICs Tracking) will actuat Crew response:

OATC 1. OATC should determine that control rods are not insertin . SRO should determine that a manual unit shutdown is required SRO and direct the OATC to place the ICs in manual and continue the unit shutdow OATC 3. OATC should place Diamond in Manua Note: Crew may decide to place FDW Masters in manual for the power reductio Event is complete when ICs has been taken to manual or when directed by the Lead Examiner.

u NUREG-1021, Draft Revision 9 Page 6 of 11

Op-Test No.: - Scenario No.: SPARE Event No.: 6 Page 1 of 1 Event Description: Manual CRD power decrease (R, OATC)

enclosure of the Operation At Power procedur I I I Event is complete when reactor power has been reduced 5% or when directed by the Lead Examiner.

ii NUREG-1021, Draft Revision 9 Page 7 of 11

Op-Test No.: - Scenario No.: SPARE Event No.: 7 Page 1 of 4 Event Description: Small Break LOCA (M, ALL)

Position Applicant's Actions or Behavior Plant response:

RCS pressure will decrease resulting in a reactor tri ES 1&2 will actuate on low RCS pressure, ES 3-6 will actuate on high RB pressur RCS will saturat Crew response:

SRO 1. SRO should direct the OATC to perform Immediate Manual Actions and the BOP to perform a symptoms chec . Once the SRO completes the Immediate Manual Actions he should transfer to Subsequent Actions and ask the BOP to report any noted symptom BOP 3. When the RCS saturates, the BOP should inform the SRO that the RCS has saturated and obtain SRO concurrence to perform Rule #2, Loss of SC Verify that reactor power is < 1%.

Trip RCPs within 2 min of LOSCM (CT-1)

Verify that HPI is performing as required. (CT-2)

> Open IHP-410 Note: BOP should determine that 1HP-26 has failed to open and open 1HP-41 Verify that LPI flow in any header is 1000 gp Verify that TBVs are availabl Disable AFlS in non-actuated channel Establish EFDW to the OTSGs to feed to LOSCM SP per Rule 7 (SG Feed Control).

Verify both MDEFDWPs operatin Ensure TDEFDWP is in PULL TO LOC Trip both MFDWPs and close the FDW block valve Notify SRO of SG feed statu Maintain SG pressure < RCS pressur Ensure Rules 3 & 8 done or in progress Note: BOP should determine that IFDW-316 has failed open and use Rule 3 (Loss of Main and Emergency FDW) and End. 5.27 (Alternate Methods for Controlling EFDW Flow) to mitigate.

NUREG-I 021, Draft Revision 9 Page 8 of 11

Op-Test No.: __ Scenario No.: SPARE Event No.: 7 Page 2 of 4 Event Description: Small Break LOCA (M, ALL)

Time Position Applicants Actions or Behavior BOP e Attempt to control IFDW-316 by placing in manual. (will not control)

e Notify SRO that Encl. 5.27 (Alternate Methods for Controlling EFDW Flow) is being initiate e Stop B MDEFDW Pump e Place 1FDW-44 controller in HAND and clos e Close 1FDW-42 and 1FDW-382 Open 1FDW-384 Close 1FDW-45 e Verify 1FDW-47 e Verify 1FDW-45, 1FDW-44, and 1FDW-42 close e Verify 1FDW-382 closed e Verify 1FDW-384 ope Start 1B MBEFDWP e Throttle 1 FDW-44 to obtain desired floe rate and/or SG level per Rule 7 (SG Feed Control) (CT-10)

SRO 4. The SRO should GO TO the LOSCM Tab per the Parallel Actions page of the EOP Subsequent Actions section. LOSCM Tab will:

Ensure that Rule #2 is in progress or complet Verify that station ASW is not feeding any S Verify that the LOSCM is not caused by excessive heat transfe e Open 1AS-40 while closing 1MS-4 s Verify all the following conditions exist::

> NO RCPs are operating 9 HPI flow exists in both HPI headers P Adequate Total HPI flow per figure 1 (Total Required HPI Flow).

NUREG-1021, Draft Revision 9 Page 9 of 11

Op-Test No.: - Scenario No.: SPARE Event No.: 7 Page 3 of 4 Event Description: Small Break LOCA (M, ALL)

Position AppkantS Actions or Behavior SRO Control steaming and feed rates on all intact SGs to maintain cooldown rate within Tech Spec limits:

P Tc 2 280°F 5 50°F/% hour P Tc < 280°F 5 25F/ % hour GO TO Step 7 Close 1RC-4 Close the following:

P IHP-1 P IHP-2 P IRC-3 P IGWD-17 5. GO TO LOCA CD ta . When ES Channels 1 and 2 actuate, an operator should inform the SRO that ES Channels 1 and 2 have actuated. The SRO should initiate EOP Encl. 5.1, ES Actuation per the parallel actions page of Subsequent Actions section or of the LOSCM Tab. When running Encl. 5.1, the operator will:

OATC Determine which ES channels should have actuated and verify all Blue Lights and White Lightslare lighted for the appropriate channel Place HPI in Manua Verify SCMs > 0°F and proceed to the HPI flow check when he determines that the RCS has saturate The operator should determine HPI flo Open IBS-1 and IBS-2 Place LPI pumps in manual contro At SRO direction secure LPI pump Ensure A and B and 3A and 3B Outside Air Booster Fans are operating. (CT-27)

Dispatch an operator to perform Encl. 5.2 (Placing RB Hydrogen Analyzers In Service)

Notify Chemistry to prepare for caustic additio The operator must get CR SRO approval to exit this enclosure.

NUREG-f021, Draft Revision 9 Page 10 of 11

Dp-Test No.: - Scenario No.: SPARE Event No.: 7 Page 4 of 4 i/ Event Description: Small Break LOCA (M, ALL)

Position Applicant's Actions or Behavior SRO LOCA CD tab will:

0 IAAT BWST level 5 19 feet transfer ECCS suctions to the RBE Verify ES is actuate Ensure all RBCUs in low speed and LPSW flow 2 1400 gpm to each RBC Initiate Encl. 5.35, Containment Isolation 0 Ensure all RB Aux fans are operating 0 Ensure all RCPs are stoppe Dispatch operator to isolate both OTSG Close ICF-1 and ICF-2 0 Initiate End. 5.36, Equipment Alignment for Plant Shutdow WHEN CETCs are 5 400°F THEN continue in this procedure.

'ii Event and exam is complete when the SRO has transferred to LOCA CD or when directed by the Lead Examine NUREG-1021, Draft Revision 9 Page 11 of 11

ES-301 Administrative Topics Outline Form ES-301-1

inial Submittal Facility: Oconee Date of Examination: June 16, 2003 Examination Level (circle one): RO / SRO Operating Test Number:

Administrative Topic Describe activity to be performed Conduct of Operations CRO-203, Calculate Final SFP Boron Concentration GEN 2.1.23 (3.9/4.0) OP/l&2/A/I 104/006 C (SFP Makeup), Enclosure 4.9 (SFP Makeup With DW) (group activity) (new) ( I O min)

Conduct of Operations CRO-043, Perform Manual RCS Leakage Calculation; PT/0600/010 (RO Only) (group activity) (18 min)

GEN 2.1.7 (3.7/4.4)

CRO-204, Perform weekly surveillance test to Equipment Control determine RIA40 setpoint GEN 2.2.12 (3.013.4) PT/230/001 Encl. 13.10 (Operation of RIA-40)

(new) (20 min)

CRO - 205, Calculate the Maximum Permissible Stay Radiation Control Time Within Emergency Dose Limits (group activity)

GEN 2.3.4 (2273.1) (new) (20 min)

Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are require NUREG-1021. Draft Revision 9

S-301 Administrative Topics Outline Form ES-301-1 inial Submittal Facility: Oconee Date of Examination: June 16,2003 Examination Level (circle one): RO / SRO Operating Test Number:

Administrative Topic Conduct of Operations CRO-203, Calculate Final SFP Boron Concentration GEN 2.1.23 (3.9/4.0) OP/l&2/A/I 104/006 C (SFP Makeup), Enclosure 4.9 (SFP Makeup With DW) (group activity) (new) (IO min)

Conduct of Operations JPM-003, Evaluate Overtime Eligibility GEN 2.1.3 (3.013.4) OMP 2-01 Attachment "C",NSD 200 (SRO only)

(25 min)

CRO-204, Perform weekly surveillance test to Equipment Control determine R I A 4 0 setpoint GEN 2.2.12 (3.0/3.4) PT/230/001 Encl. 13.10 (Operation of RIA-40)

(new) (20 min)

Radiation Control CRO - 205, Calculate the Maximum Permissible Stay GEN 2.3.4 (2.Y3.1) Time Within Emergency Dose Limits (new)

(20 min)

SRO-206, Determine Emergency Classification and Emergency Plan Protective Action Recommendations (SRO only)

GEN 2.4.38 (2.2/4.0) (group activity) (new)

(20 min)

Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are require NUREG-1021, Draft Revision 9

CRO-203 fnl/Admin Page 1 of 8

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Calculate Final SFP Boron Concentration CANDIDATE u EXAMINER

CRO-203 fnl/Admin Page 2 of 8

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

-

Task:

Calculate Final SFP Boron Concentration Alternate Path:

NO Facility JPM #:

New KIA Ratin&):

Gen 2.1.23 3.9/ Task Standard:

Calculate Final SFP Boron Concentration within f 10 ppm Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Perform 1 Simulate -

ii References:

OP/l&2/All104/006 C (SFP Makeup), Enclosure 4.9 (SFP Makeup With DW)

OP/l108/001 (Curves and General Information), Enclosure 3.26 (Miscellaneous Data)

Validation Time: 10 rni Time Critical: NO

________________________________________-----__---~--------

_________________--______________________--~~~~-----------

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT -UNSAT - Performance Time -

Examiner: /

NAME SIGNATURE DATE

CRO-203 fnl/Admin Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS:

NONE i/

CRO-203 fnl/Admin Page 4 of 8 ToolslEquipmenffProcedures Needed:

OP/l&2/A/1104/006 C (SFP Makeup), Enclosure 4.9 (SFP Makeup With DW)

i/

READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

Unit 1 & 2 Spent Fuel Pool (SFP) level = 0.0 ft 0 Unit 1 & 2 SFP Boron = 2545 ppm SF-1 and SF-2 are closed In preparation for refueling operations, the Unit 1 & 2 SFP level will be increased to + 0.6 ft using D INITIATING CUE:

u The SRO directs to determine the final SFP Boron concentratio ~

CRO-203 fnl/Admin Page 5 of 8 START TIME:

L STEP: Determine and locate appropriate procedure for DW makeup to the SF STANDARD: Candidate locates Enclosure 4.9 (SFP Makeup With DW) of -SAT OP/l&2/NI 104/006 C (SFP Makeup).

Candidate may refer to OP/1108/001 (Curves and General Information)

End. 3.26 (Miscellaneous Data)

-UNSAT COMMENTS:

2- Determine volume of water required to raise SFP from 0.0 ft to + 0.6 f STANDARD: Refer to Enclosure 4.9 (SFP Makeup With DW) step 2.2 and determine that there is 13,080 GallFoot in the SFP and then calculate the total -SAT gallons required to raise level to + 0.6 f .6 fl x 13,080 gal/ft = 7848 gallons-UNSAT Calculate the total gallons required to raise level to + 0.6 f&using OP/I 108/001 (Curves and General Information) Encl. 3.26 (Miscellaneous Dat L 0.6 f& x 1512 gal/O. 1ft = 9072 gallons COMMENTS:

CRO-203 fnl/Admin Page 6 of 8

3- Determine finial SFP Boron concentratio CRITICAL STEP STANDARD: Refer to Enclosure 4.9 (SFP Makeup With DW) step SAT c

SFP final ppm = JSFP present opm) (SFP present vol)

(SFP final vol) -UNSAT SFP final ppm = j2545 ppm) 646.000 Cia11 (553, 848 gal)

SFP final pprn = 2508.9 (210 ppm)

Note: SFP final vol = 546,000 gal + (13,080 gallft X 0.6 ft)

= 553,848 gal Calculate finial SFP Boron concentration using OP/1108/001 (Curves and General Information) Encl. 3.26 (Miscellaneous Dat SFP final pprn = 12545 pprnj (544, 000 aau (553, 072 gal)

SFP final pprn = 2503.3 (& I O ppm)

Note: The SFP data given in the two procedures is different. A procedure problem report will be written to determine which numbers are correct after the NRC exam is complete.

L COMMENTS:

END OF TASK TIME STOP:

CRO-203 fnllAdmin Page 7 of 8 CRITICAL STEP EXPLANATIONS:

ii STEP # Explanation 3 Required to determine final SFP Boron concentratio CRO-203 fnl/Admin Page a of a CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

u INITIAL CONDITIONS:

Unit 1 & 2 Spent Fuel Pool (SFP) level = 0.0 ft Unit 1 & 2 SFP Boron = 2545 ppm SF-1 and SF-2 are closed In preparation for refueling operations, the Unit 1 & 2 SFP level will be increased to + 0.6 ft using D INITIATING CUE:

The SRO directs to determine the final SFP Boron concentratio Enclosure OP/1&2/A/I 104/006 C SFP Makeup With DW { 6 ) Page 1 of 2 W 1. Initial Conditions

- U1 B W S T W i n purificatio __ U2 B W S T W in purificatio .3 Review Limits and Precautions 2. Procedure

- - Review Section 3 (SFP Makeup With DW Information).

SRO

__ Calculate final SFP boron:

SFP volume at zero level = 546,000 ga GalFoot = 13,080 SFP final ppm = {SFP present Dum) (SFP present vol)

(SFP final vol)

final boron PPm final lvl ft

__ Ensure DW makeup to all units USTs stopped to provide adequate DW pressure.

ii Align valves: (A-2-SF Clr Rm)

- Unlock and Open DW-112 (SF Cooling Supply)

__ Open SF-53 (SF Pump Suction Hdr Blk) WHEN desired level reached, perfonn the following: (A-2-SF Clr Rm)

__ __ Lock Closed DW-112 (SF Cooling Supply)

- __ Close SF-53 (SF Pump Suction Hdr Blk)

- Request SFP boron sample. [ 1 J

Enclosure OPI~&2IAIl1041006C SFP Makeup With DW {6] Page 2 of 2 W 3. SFP Makeup With DW Information Makeup flow is dependent on number and configuration of SF Pumps in operatio Makeup flow enters via SF purification loop to SF Pump discharge pipin Best makeup flow is seen with one SF Pump in operation (A or B SF Pump).

Lower makeup flow is seen if both A and B SF Pumps are operatin Worst makeup flow is seen if C SF Pump is operatin CRO-43 fnl/Admin Page 1 of 11

REGION II

INIT1AL LI CENSE EXAMINAT10N JOB PERFORMANCE MEASURE CRO-43/Admin PERFORM MANUAL RCS LEAKAGE CALCULATION u CANDIDATE EXAMINER

CRO-43 fnl/Admin Page 2 of 11

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

PERFORM MANUAL RCS LEAKAGE CALCULATION Alternate Path:

No Facility JPM #:

CRO-43 KIA Ratinqb):

Gen 2. .71 Task Standard:

RCS Leakage is correctly calculated within .01 gpm of attached ke Preferred Evaluation Location: Preferred Evaluation Method:

Simulator -In-Plant X Perform Simulate -

References:

i/

PT/OIA10600/001A, Loss Of Computer PT/1/~600/10,Reactor Coolant Leakage Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT -UNSAT ~ Performance Time ~

Examiner: I NAME SIGNATURE DATE

CRO-43 fnlIAdmin Page 3 of 11 SIMULATOR OPERATOR INSTRUCTIONS:

NONE ii

CRO-43 fnl/Admin Page 4 of 11 ToolslEciui~menffProceduresNeeded:

Enclosure 13.3 of PT/I/A/600/10 ii READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

Unit 1 computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PT/O/A/0600/001A, Loss Of Computer, is in progress, however an RCS Leakage Calculation has not been performed during this shif INITIATING CUES:

The Control Room SRO directs you to perform a manual RCS leakage per PT/I/A/600/10 (Reactor Coolant Leakage). The initial data given was collected one hour previously. Use the final set of leakage data and manually calculate the RCS leakage rate. Enclosure 13.3 of PT/I/A/600/10 (Reactor Coolant Leakage) is complete up to step CRO-43 fnl/Admin Page 5 of 11 STARTTIME:

~

Note: Data cues are only applicable if JPM is performed in the control roo SAT STEP: Step After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Record final set of data in Table # UNSAT STANDARD: Student enters final set of data into Table # I of Enclosure 13.3 (Manual Leakage Calculation Data Sheet).

CUE: Present student with attachment of final data reading OR Student locates Pzr level gauge on UBI and enters value on data shee CUE: Pzr Level 219.0 inches Student locates Quench Tank level on AB1 and enters value on data shee CUE: Quench Tank Level 84.9 inches Student locates LDST level gauge on UBI and enters value on data shee CUE: LDST Level 74.0 inches L Student locates Tave meter on UBI and enters value on data shee CUE: Tave Indication 579.0F Student locates Power meters on UBI and enters value on data she1 CUE: Power Range NI indicates 100.1%

Student locates RCS NR Pressure chart on UBI and enters value on data shee CUE: RCS NR Pressure chart 2150 psig Student locates Group 7 Control Rod Position on the Computer and enters value on data shee CUE: Group 7 Control Rod Position is 93.6%

COMMENTS:

CRO-43 fnl/Admin Page 6 of 11 L STEP: Step Calculate and record Change values in Table # I of Enclosure 1 (Manual Leakage Calculation Data Sheet).

-SAT STANDARD: Student performs calculation and records Change values in Table #I of Enclosure 13.3 (Manual Leakage Calculation Data Sheet).

-UNSAT COMMENTS:

3- Step Calculated Corrected PZR Level Change:

-SAT STANDARD: (- 6.831 inches/ F X F) + -1inches = inches-UNSAT COMMENTS:

L STEP: Step Convert Corrected PZR Level Change to gallons:

-SAT STANDARD: - 3169 inches x 14.364 gallonshnch = - 4.552 gallons-UNSAT COMMENTS:

CRO-43 fnl/Admin Page 7 of 11 L Step Convert QT Level Change to gallons:

-SAT STANDARD: -

.3 inches X 34.94 gallonslinch = 10.482 gallons-UNSAT COMMENTS:

STEP: Step Convert LDST Level Change to gallons:

-SAT STANDARD: -

inches X 30.956 gallons/inch = 9.287 gallons-UNSAT COMMENTS:

L STEP: Step Calculated Total Volume Change:

-SAT STANDARD:

- 4.552 gallons + 10.482 gallons + I- 9.287 nallons) = - 3.357 gallons -UNSAT COMMENTS:

CRO-43 fnl/Admin PageEof11 L Step CRITICAL TASK Calculate RCS Leakage Rate:

-SAT STANDARD: - 3.357 gallons -

minutes = ,056 gpm (k .01-UNSAT COMMENTS:

END TASK STOP TIME:

CRO-43 fnl/Admin Page9of11 CRITICAL STEP EXPLANATIONS:

ii STEP # Explanation 8 Necessary data calculation to properly determine manual RCS leakage rat CRO-43 fnl/Admin Page 10 of 11 Manual RCS Leakage Final Data Parameter Final Pzr level 219.0 inches Quench Tank Level 84.9 inches LDST Level 74.0 inches Tave Indication 579.0"F

- NI Power Range 100.1%

I RCS NR Pressure I

12150 Dsia

. -

I I

Group 7 Control Rod Position 193.6%

CRO-43 fnl/Admin Page 11 of 11 CANDIDATE CUE SHEET C' (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PT/O/N0600/001A, Loss Of Computer, is in progress, however an RCS Leakage Calculation has not been performed during this shif INITIATING CUES:

The Control Room SRO directs you to perform a manual RCS leakage per PT/l/A/600/10 (Reactor Coolant Leakage). The initial data given was collected one hour previously. Use the final set of leakage data and manually calculate the RCS leakage rate. Enclosure 13.3 of PT/I/N600/10 (Reactor Coolant Leakage) is complete up to step Enclosure 1 PT/1/.4/0600/010 ~ . .: :,.:

Manual RCS Leakage Calculation Data Sheet Page. 1 of 2 1. Initial Conditions Non . Procedure J Record initial datajn "Table#l".

__ After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , record final data in "Table #1" NOTE: If RCS NR Pressure is off-scale, RCS WR Pressure range may be use If T,,, is off-scale, Tcoldmay be use Table # 1 Value Initial Duration time (1) minutes Pzr Level inches inches (2) inches W

QT Level inches (3) inches LDST Level q inches inches (4) inches Rx Power RCS NR or WR Pressure I '

Rod Position NOTE: Change = Final - Initial Negative sign (-) should be included with values as appropriat __ Calculate and record Change values in "Table # 1" ii

Enclosure 1 PT/1/N0600/010 . ~ -

Manual RCS Leakage Calculation Data Sheet Page 2 of 2 "

~~~ ~ ~~~

NOTE: Conversion Factor (-6.831 inchesl"F) must be negative (-) value. (7)

-2.4' Calculated Corrected PZR Level Change:

(-6.831 incheslOFx O F ) + inches = inches ( 5 ) Tave or Tcold Change (2) PZR Level Change Corrected PZR Level Change Convert Corrected PZR Level Change to gallons:

inchesx14.364 gallonslinch = gallons Corrected PZR Level Change Conversion corrected to 68°F Final PZR Change

__ Convert QT Level Change to gallons: ( 4 )

inclzesx 34.94 gallons/ inch = gallons ( 3 ) QT Level Change Conversion corrected to 68'F Final QT Change Convert LDST Level Change to gallons:

inchesx30.956 gallonslinch = gallons i/ ( 4 ) LDST Level Change Conversion corrected to 68°F Final LDST Change

- Calculate Total Volume Change:

gallons + gallons + gallons = gallons Final PZR Change Final QT Change Final LDST Change Total Change

__ Calculate RCS Leakage Rate:

gallons + Minutes = gPm Tolal Change (1) Duration RCS Leakage Rate

Enclosure 1 PT/1/A/0600/010 :

~,.:

Manual RCS Leakage Calculation Data Sheet Page. 1 of 2 1. Initial Conditions Non ,.

2. Procedure J ' Record initial datain." "Table#l". After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , record final data in !'Table #1".

NOTE: If RCS NR Pressure is off-scale, RCS WR Pressure range may be use If T,,, is off-scale, Tcoldmay be use Value Duration minutes 00 1 5 time (=J,rj time (1) Go Pzr Level QT Level LDST Level Tax or Tcoid Rx Power RCS NR or WR Pressure Control Rod Position NOTE: Change = Final Initial

~

I Negative sign (-) should be included with values as appropriat .3 Calculate and record Change values in "Table # 1".

Enclosure 1 PT/1/M0600/010 . Manual RCS Leakage Calculation Data Sheet Page 2 of 2 -

W NOTE: Conversion Factor (-6.831 inches/'F) must be negative (-) value. (7)

a3 2.4- Calculated Corrected PZR Level Change:

(-6.831 iizches/"Fx -.1 O F ) + - iizches = - ,31d9 inches ( 5 ) Tave or Tcold Change (2) PZR Level Cltange Corrected PZR Level Change-ST Convert Corrected PZR Level Change to gallons:

- .316$ inchesx14.364 gallonslinch = - s 5.2gallons Corrected PZR Level Clzaizge Conversion corrected to 68°F Final PZR Change Convert QT Level Change to gallons: ( 4 )

'3 inchesx 34.94 gailonilirzclz = +

I b . 6a gallons ( 3 ) QT Level Change Conversion corrected to 68'F Final QT Change 2 Convert LDST Level Change to gallons:

u

- ?

.3 inchesx 30.956 gallonslinch = - 9* 2 83 gallons ( 4 ) LDST Level Change Conversion corrected to 68°F Final LDST Change E Calculate Total Voluiiie Change:

- ~*!S.SZgallons + 1 gallons + - 7.a~7 gallons = - 3.35 3 gallons Final PZR Change Final QT Change Final LDST Change Total Cliarzge E Calculate RCS Leakage Rate: \

- 3 *'35 7 galloits + 60 Minutes = -o ~ Ggpni Total Change (1) Duration RCS Leakage Rate

CRO-204 fnl/Admin Page 1 of 9

REGION II

INITlAL LICENSE EXAMINATlON JOB PERFORMANCE MEASURE CRO-204/Admin Perform weekly surveillance test to determine RIA-40 setpoint CANDIDATE EXAMINER

CRO-204 fnl1Admin Page 2 of 9

REGION II

<d INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform weekly surveillance test to determine RIA-40 setpoint Alternate Path:

No Facilitv JPM #

New KIA Ratinqfs):

Gen 2.2.12 3.01 Task Standard:

Correctly determine new RIA-40 setpoint within f 5 cpm by procedur Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant - Perform Simulate -

i/ References:

PT/O/A/230/01, Encl. 13.10 (Operation of RIA-40)

Validation Time: 20 minutes Time Critical: No Candidate: Time Start:

NAME Time Finish:

Performance Ratinq: SAT -UNSAT - Performance Time -

Examiner: 1 NAME SIGNATURE DATE COMMENTS

CRO-204 fnllAdmin Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS:

None ii

CRO-204 fnl/Admin Page 4 of 9 ToolslEauiDmenff Procedures Needed:

PT/O/N230/01, Encl. 13.10 (Operation of RIA-40)

u READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

The unit has been continuouslyoperating at 100% for 9 month AP/31 (Primary to Secondary Leakage) not in effect The weekly performance of PT/O/A/230/01 (Radiation Monitor Check) is in progres CSAE offgas Xe 133 MCilml concentration is greater than MDA (Minimum Detectable Activity)

CURRENT DATA RCS Xe 133 activity = 7.189 E-3 pcilml c RCS Xe 133 activity eq = .4734 E-3 pcilml CSAE Off Gas Xe activity = 4.431 E-8 pcilml CSAE Off Gas Xe activity eq = 3.515 E-6 pcilml CSAE Off Gas Flow = 13 scfm 1RIA40 = 120 cpm INITIATING CUES:

The SRO directs you to perform PT/O/N230/01, Encl. 13.10 (Operation of RIA-40) to determine RIA-40 setpoint CRO-204 fnl/Admin Page 5 of 9 START TIME:

L STEP: Step IF all of the following conditions exist,

. Reactor power 15%

AP/l,2,3/A/1700/031 (Primary To Secondary Leakage) is NOT in effect-SAT reactor has been at steady state power operation > 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months CSAE offgas Xe 133 pCi/ml concentration is greater than MDA -UNSAT (Minimum Detectable Activity)

THEN set RIA-40 setpoints as follows:

STANDARD: Determine the above conditions are met and proceed to Step . COMMENTS:

STEP: Step .I Obtain the CSAE flow rat IF any CSAE flow meter(s) are o f f scale, refer to OP/O/A/1106/031 -SAT (Primary to Secondary Leak Rate Monitoring and Instrumentation) to determine the CSAE flow rat Candidate should obtain the CSAE flow rate (13 cfm) from the cue-UNSAT L STANDARD:

shee COMMENTS:

CRO-204 fnl/Admin Page 6 of 9 STEP: Step 1. CRITICAL STEP L NOTE: -SAT Xe 133 activity (NOT equivalent) is required for this calculatio The RCS and the CSAE Offgas samples should be taken at approximately the same time (ideally within 15 minutes). The RIA40 reading may be obtained from historical dat UNSAT Perform the following equations:

High Setpoint = [30 aallday) (RCS Xe 133 pCi/ml) (6.9 E-4 davlrnin) (RIA-40 c m )

(7.48 gallft3) (CSAE Flow ft3lmin) (CSAE offgas Xe 133 pCilml)

High Setpoint = RCS Xe 133 Ci/ml) (RIA40 corn) (2.77 E-3 ft3/mln)

M m i n ) (CSAE offgas Xe 133 pCi/rnl)

High Setpoint = ( )-pCi/ml(RCS) X ( ) cpm X 2.77 E-3 ft3/min = -cpm ( ) ft3/min ( ) pCi/ml(CSAE)

STANDARD: Calculate High Setpoint using data from Cue Sheet:

High Setpoint = (7.189 E-3)uCi/ml(RCS) X (120)cpm X 2.77 E-3 ft3/min = 4148.4 cpm ( 13 ) ft3/min (4.431 E-8) pCi/ml(CSAE)

(-+5 cpm)

L COMMENTS:

CRO-204 fnVAdmin Page 7 of 9 STEP: Step 1. I .2 (cont) CRITICAL STEP L -SAT Alert Setpoint = [5 aal/dav) (RCS Xe 133 pCi/ml) (6.9 E-4 dav/min) (RIA-40 cDm)

(7.48 gal/ft') (CSAE Flow f13/min) (CSAE offgas Xe 133 pCi/ml)

Alert Setpoint = (RCS Xe 133yCi/ml) (RIA-40 cpm) f2.77 E-3 f13/min) -UNSAT (CSAE flow fl /min) (CSAE offgas Xe 133 pCi/ml)

Alert Setpoint = ( )-pCi/ml(RCS) X ( )-cpm X 4.61 E-4 ft3/min = -cpm ( ) ft3/min ( ) pCi/ml(CSAE)

STANDARD: Calculate Alert Setpoint using data from Cue Sheet:

Alert Setpoint = (7.189 E-3)uCi/ml(RCS) X (120)cpm X 4.61 E-4 ft3/min = 690.4 cpm ( 13 ) f13/min (4.431 E-8) pCi/ml(CSAE)

(+ 5 cpm)

COMMENTS:

L END TASK STOP TIME:

CRO-204 fnl/Adrnin Page 8 of 9 CRITICAL STEP EXPLANAT10 NS:

ii STEP # Explanation 3 This step required to calculate High Setpoin This step required to calculate Alert Setpoin CRO-204 fnl/Admin Page 9 of 9 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

L INITIAL CONDITIONS:

The unit has been continuously operating at 100% for 9 month AP/31 (Primary to Secondary Leakage) not in effect The weekly performance of PT/O/N230/01 (Radiation Monitor Check) is in progres CSAE offgas Xe 133 pCi/ml concentration is greater than MDA (Minimum Detectable Activity).

CURRENT DATA RCS Xe 133 activity = 7.189 E-3 mclml RCS Xe 133 activity eq = ,4734 E-3 mclml RIA-40 Xe activity = 4.431 E-8 mclml RIA-40 Xe activity eq = 3.515 E-6 mclml CSAE Off Gas Flow = 13 scfm 1RIA40 = 120 cpm INITIATING CUES:

The SRO directs you to perform PTIO/N230/01, Encl. 13.10 (Operation of RIA-40) to determine RIA-40 setpoint c Enclosure 13.1 PT/o/A/0230/001 Operation Of RIA-40 Page 1 of 11 u

1. Determine RIA-40 setpoints as follows:

I I NOTE: .. "Steady state power operation > 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months " is defined as maintaining a constant power level & 2%) for at least 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Step 4 is perforged in addition to Step 1.1 when the weekly RJA-40 setpoint calculation is being perfor&e __ _-

IF all of the following conditions exist, e Reactor power 2 15%

e AF'/1,2,3/A/1700/031 (Primary To Secondary Leakage) is in effect reactor has been at "steady state power operation > 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months " 0 CSAE offgas Xe 133 pCi/ml concentration is greater than MDA (Minimum Detectable Activity) ( 7 )

THEN set RIA-40 setpoints as follows:

L '

1. ' Obtain the CSAE flow rat __ any CSAE flow meter(s) are off scale, refer to OP/O/AI1106/031 (Primary to Secondary Leak Rate Monitoring and Instrumentation) to determine the CSAE flow rat Enclosure 13.10 PT/o/A/0230/001 Operation Of RIA-40 Page 2 of 11 L/

__ 1. Perform the following equations:

NOTE: Xe 133 activity (NOT equivalent) is required for this calculatio The RCS and the CSAE Offgas samples should be taken at approximately the same time (ideally within 15 minutes). The RIA-40 reading may be obtained from historical dat High Setpoint = (30 eal/dav) (RCS Xe 133 uCi/ml) (6.9 E 4 day/min) (RIA40 cpm)

(7.48 gaUft3)(CSAE Flow ft3/min)(CSAE offgas Xe 133 pCdml)

High Setpoint = (RCS Xe 133 UCilml) (RIA40 cpm) (2.77 E-3 ft3/min)

(CSAE flow ft3/min)(CSAE offgas Xe 133 pCdml)

High Setpoint = -( )-ma) xA )- 2.77 E-3 ft3/min= CPm ( ) ft3/min ( ) PCdml,CSA!G Alert Setpoint = (5 gal/dav) (RCS Xe 133 uCi/ml) (6.9 E 4 dav/min) (RIA40 CPm)

b (7.48 gaUft) (CSAE How ft3/min)(CSAE offgas Xe 133 ~ C d m l )

Alert Setpoint = (RCS Xe 133 uCYml) (RIA40 cDm) (4.61 E 4 ft3/min)

(CSAE flow ft3/min)(CSAE offgas Xe 133 @did)

Alert Setpoint = -( ) uCi/mlma) -( )- 4.61 E 4 ft3/min= CPm ( ) ft3/min ( ) PCdd(CSA)

-1. SG primary to secondary leak rate is needed, THEN GO TO Step 4 to calculate leak rat . Record which Unit, procedure was performed on, in Remarks section on coversheet. (eg. Unit 1,Unit 2, or Unit 3)

Enclosure 13.10 PT/o/A/0230/00 1 Operation Of RIA-40 Page 3 of 11 Unit 1 Unit 2 , 3

< 55 cpm c 75 cpm THEN set RIA-40 setpoints at the following values:

Setpoints unit 1 Unit 2,3

'd Alert 115 cpm 135 cpm High 115 cpm 135 cpm

__ 1. SG primary to secondary leak rate is needed, THEN GO TO Step 3 to calculate leak rat . Record which Unit, procedure was performed on, in Remarks section on coversheet. (eg. Unit 1, Unit 2, or Unit 3)

Enclosure 13.10 PT/o/A/0230/001 Operation Of RIA-40 Page 4 of I 1 . .

NOTE: "Steady state power operation > 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months " is defined as maintaining a constant power ii e

level 2%) for at least 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Experience has shown that it may be desirable to calculate setpoints prior to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of steady state power operation if a startup from an outage (refueling or forced) is in progress. If a small amount of tube leakage exists when the unit is in the startup mode (on the order of 1 to 2 gpd), the alert and high setpoints may be exceeded prior to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of steady state power operatio __ 1.3 --

IF all of the following conditions exist, Reactor power 2 15%

AP/1,2,3/A/1700/031 (Primary To Secondary Leakage) is in effect reactor has NOT been at "steady state power operation > 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months " current RIA-40 reading:

Unit 1 Unit 2, 3

-> 55 cpm -

> 75 cpm W THEN GO TO Step 2 to calculate W - 4 0 setpoint __ & of l the following conditions exist, Unit 1 unit 2 , 3

-> 55 cpm . -> 75 cpm THEN GO TO Step 2 to calculate RZA-40 setpoint Enclosure 13.10 PT/o/A/0230/00 I Operation Of RIA-40 Page 5 of 11 W __ of the following conditions exist, reactor is critical Reactor power < 15%

AP/1,2,3/A/1700/031 (Primary To Secondary Leakage) is NOT in effect 0 current RIA-40 reading:

unit 1 .- Unit 2 , 3

< 55 cpm < 75 cpm Setpoints Unit 1 Unit 2,3 Alert 115 cpm 135 cpm hgh 115 cpm 135 cpm

__ 1. Record which Unit, procedure was performed on, in Remarks section on coversheet. (eg. Unit 1, Unit 2, or Unit 3)

1. . Exit this enclosur __ 1.6 IF both of the following conditions exist, reactor is critical AP/1,2,3/A/1700/031 (Primary To Secondary Leakage) is in effect THEN GO TO Step 5 to reset RIA-40 AIert/High setpoints as specified in AP/1,2,3/A/1700/031 (Primary To Secondary Leakage).

Enclosure 13.10 PT/o/A/0230/00 1 Operation Of RIA-40 Page6of 11

'u

__ 1.7 IF both of the following conditions exist, reactor is subcritical current RIA-40 reading:

Unit 1 Unit 2, 3 THEN GO TO Step 2 calculate RIA-40 setpoint __ 1.8 IF both of the following conditions exist, reactor is subcritical current RIA40 reading:

I Unit 1 I Unit 2, 3 I

< 100 cpm < 120 cpm THEN set RIA-40 setpoints at the following values:

Setpoints Unit 1 Unit 2,3 Alert 115 cpm 135 cpm figh 115 cpm 135 cpm

__ 1. Record which Unit, procedure was performed on, in Remarks section on coversheet. (eg. Unit 1, Unit 2, or Unit 3)

-1. Exit this enclosur Enclosure 13.10 PT/o/A/0230/001 Operation Of RIA-40 Page 7 of 11

, 2. Calculate RIA-40 setpoints as follows:

W

- Obtain the CSAE flow rat __ 2. any CSAE flow meter(s) are off scale, refer to OP/O/A/1106/031 (Primary to Secondary Leak Rate Monitoring and Instrumentation) to determine the CSAE flow rat __ Perform the following equations:

NOTE: Xe 133 equivalent activity is required for this calculatio The RCS and the CSAE Offgas samples should be taken at approximately the same time (ideally within 15 minutes). The RIA-40 reading may be obtained from historical dat High Setpoint = (30 gaYdav) (RCS Xe 133 eq ~ C i m l( ) E 4 dadmin) (RL4-40corn)

(7.48 gavft) (CSAE Flow ft/min) (CSAE offgas Xe 133 eq pCi/ml)

High Setpoint = (RCS Xe 133 eq ~ C i l m l(RIA40

) corn) (2.77 E-3 ft3/min)

(CSAE flow ft3/min)(CSAE offgas Xe eq 133 pCiml)

High Setpoint = -( )Uci/ml@CS,) x -( )- 2.17 E-3 ft3/min= CPm v ( ) ft3/min ( PCiml(CSAEC4I)

Alert Setpoint = (5 gayday) (RCS Xe 133 eq ~ ~ C i m( l ) E 4 davlmin) (RLA-40 Cum1 (7.48 gauft) (CSAE Flow ftlmin) (CSAE offgas Xe 133 eq pCUd)

Alert Setpoint = (RCS Xe 133 ea ~Cdml)(RL4-40 cum) (4.61 E-4 ft3/min)

(CSAE flow ft3/min) (CSAE offgas Xe 133 eq pCi/ml)

Alert Setpoint = -( u C i m l ( ~ ~ ~-( ~ , ) a 4.61 E4 ft3/min= CPm ( ) ft3/min ( ) PCid(CSAE,)

- E Reactor power is 2 15%,

THEN GO TO Step 3 to calculate the SG primary to secondary leak rat .4 E Reactor power is iIS%,

=record which Unit, procedure was performed on, in Remarks section on coversheet (eg. Unit 1, Unit 2, or Unit 3) Exit this enclosure.

v -

Enclosure 13.10 PT/o/A/0230/00 1 Operation Of RIA-40 Page 8 of 11 NOTE: SG primary to secondary leak rate calculation is NOT valid when CSAES &e NOT in servic ._ Calculation using Xe 133 Equivalent Activity should be used whenever reactor has NOT been at steady state power operation > 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Calculation of SG primary to secondary leak rate using Xe 133 Equivalent Activit __ Obtain the CSAE flow rat __ 3. any CSAE flow meter(s) are off scale, refer to OP/0/~1106/031(Primary to Secondary Leak Rate Monitoring and Instrumentation) to determine the CSAE flow rat __ Perform the following equation:

NOTE: Xe 133 equivalent activity is required for this calculatio The RCS and the CSAE Offgas samples should be taken at approximately the same time W (ideally within 15 minutes).

-

Leak Rate = (7.48 gaYft) (CSAE Flow ft3/min)(CSAE offgas Xe 133 eq LLci/d)

(RCS Xe 133 eq pCiml) (6.94E3-4daylnlin) Record the leak rate in the Unit Lo .4 Record which Unit, procedure was performed on, in Remarks section on covershee (eg. Unit 1, Unit 2, or Unit 3) Exit this enclosure.

W

Enclosure 13.10 PT/o/A/0230/00 1 Operation Of RIA-40 Page 9 of 11

~

NOTE: SG primary to secondary leak rate calculation is NOT valid when CSAEs are NOT in servic .. Calculation using X e 133 Activity should be used whenever reactor has been at steady state power operation z 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ~ ~~

4. Calculation of SG primary to secondary leak rate using Xe 133 Activit (1) Obtain the CSAE flow rat __ 4. E any CSAE?flow meter(s) are off scale, refer to OP/OIM1106/031 (Primary to Secondary Leak Rate Monitoring and Instrumentation) to determine the CSAE flow rat .2 Perform the following equation:

NOTE: Xe 133 activity (NOT equivalent) is required for this calculatio The RCS and the CSAE Offgas samples should be taken at approximately the same time (ideally within 15 minutes).

Leak Rate = (7.48 paVft3) (CSAE Flow fthn) (CSAE offgas Xe 133 lLCi/d)

(RCS Xe 133 kCi/ml) (6.94E-4 day/min)

Leak Rate = (CSAE flow ft3/min) (CSAE offgas Xe 133 ~ ~ C i m l l ( 10,800 gal mini (RCS Xe 133 pCiml) ft3 day Leak Rate = -( )- x -( ) ~ C i m l , 110.800~ ~ ~ pal~ min) = i3d ( 1 pciml(Rcs, ft3 day

__ Record the leak rate in the Unit Lo __ Record which Unit, procedure was performed on, in Remarks section on coversheet (eg. Unit 1, Unit 2, or Unit 3)

- Exit this enclosure.

v

Enclosure 13.10 PT/o/A/0230/001 Operation Of RIA-40 Page 10 of 11

..

v 5. Resetting MA-40 AIertIHigh aIarm setpoints and entering the Total Pri To Sec Leakrate Admin Limit in the OAC as specified in AP/1,2,3/A/1700/031. (8)

NOTE: . Xe 133 equivalent activity is required for this calculatio .1 Obtain the CSAE flow rat . any CSAE flow meter(s) are off scale, refer to OP/O/A/1106/031 (Primary to Secondary Leak Rate Monitoring and Instrumentatlon) to determine the CSAE flow rat .2 Perform the following equations:

High Setpoint = (AFV31 RIA40 Hizh stDt md) (RCS Xe133 ea bCi/ml) (6.9E-4 davlmin)

(7.48 gaVft3) (CSAE Flow ft3/min) (3.4 E-8 pCdmVcpni)

High Setpoint = (AP/31 RIA40 High stpt md) (RCS Xe133 ea ~ C i m l(2.71 ) E+3 ft dav cpm)

(CSAE Flow ft3/min) gal min p C i d W

High Setpoint = -( md -( )uci/mlrncscq) x (2.71 E+3 ft3 dav cum) = CPm ( )ft3/min gal min pCiml Alert Setpoint = (AP/31 RIA-40 Alert stpt md) (RCS Xe133 eq tlCiml) (6.9E-4davlminl (7.48 gaYft3) (CSAE Flow ft3/min) (3.4 E-8 pCdmVcpm)

Alert Setpoint =(AP/31 RIA-40 Alert stut md) (RCS Xe133 eq ~ ~ C i m(2.71 l ) E+3 ft3 dav CPml (CSAE Flow ft3/min) gal min p C i d Alert Setpoint = -(-)-& -( )msRaeq) x [2.71 E+3 ft3 dav cpm) = CPm ( )ft/min gal min & C d d

___ Enter the new RIA40 Alert and High Setpoints in the RIA View Nod Enclosure 13.10 PT/o/A/0230/001 Operation Of RIA-40 Page 11 of.11 5.4 Perform the following on the OAC to enter the Unit's new "Total Pri To Sec Leakrate Admin:

W Limit" as specified by AP/1,2,3/A/1700/031 (Primary To Secondary Leakage):

-5. Select "Main" from the menu ba . Select "Utilities" from the drop down men . Select "Manual Value Update" from the drop down men . Select "Pri-Leak Primary To Secondary Leakage Manual Inputs".

-5. Select "Update".

-5. Select the respective Unit's "Total Pri To Sec Leakrate Admn Limit" computer point ID from the following tabl Unit 1 Unit 2 Unit 3 01K1430 02K1430 03K1430-5. Tab or use the mouse to place the c.ursor in the "New Value" fiel __ 5. Enter the Unit's new "Total Pri To Sec Leakrate Admin Limit" as specified in v , ' AP/1,2,3/A/1700/031 (Primary To Secondary Leakage).

__ 5. Tab or use the mouse to.place the cursor in the "Modified By" fiel .4.10 Enter your LAN identificatio __ 5.4.11 Tab or use the mouse to place the cursor in the "Reason" fiel .4.12 Enter the reason for the change (ex. PT/O/A/O230/001).

-5.4.13 Select "Save".

__ 5.4.14 Select "okay" on the pop-up men .4.15 Select "Cancel" to exit "Manual Value Update PID Update Display" scree .4.16 Select "Cancel" to exit "Manual Value Update Croup Selection Display" scree __ 5.5 Record which Unit, procedure was performed on, in Remarks section on coversheet (eg. Unit 1, Unit 2, or Unit 3)

__ 5.6 Exit this enclosure.

v

CRO-205 fnl/Adrnin Page 1 of 8

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE CRO-205/Admin Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits (EDL)

CANDIDATE EXAMINER

CRO-205 fnl1Admin Page 2 of 8

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits Alternate Path:

NIA Facilitv JPM #:

NIA KIA Ratinds):

Gen 2. .51 Task Standard:

Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits (* 5 minutes).

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __ In-Plant X Perform X Simulate -

L--References:

NSD-507, Radiation Protection OMP 1-18, Implementation Standard During Abnormal And Emergency Events Candidate: Time Start:

NAME Time Finish:

Performance Ratina: SAT -UNSAT - Performance Time -

CRO-205 fnllAdmin Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS:

NONE i/

CRO-205 fnllAdmin Page 4 of 8 ToolslEquipmenff Procedures Needed:

None ii READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

1, Steam Generator Tube Rupture has occurred on Unit 3 Emergency Dose Limits are in effect NE0 A has received 1.46 R TEDE this year The following tasks are required to be performed:

I I Closinq 3 ~ - 5 7 3 12 min 6.55 Whr I 2 I Ooen3FDW-313 I 4 min I 21.45 Whr I 3 Open all Unit 3s ADVs 2.88 Whr INITIATING CUE:

Refer to the above information, NE0 A has completed tasks 1 and 2 in the time required. How long does he have to complete task 3 without exceeding his Emergency Dose Limits?

CRO-205 fnl/Admin Page 5 of 8 START TIME:

Note: Candidate may perform these steps in a different order however the calculated stay time should be

~ correc Note: Candidate should understand the following:

1. EDL is 5 R per event (LOCA or SGTR).

2. Current exposure for the year is not counted toward the Emergency Dose Limit (EDL).

STEP: Determine dose received while performing task SAT STANDARD: Determine dose received while performing task .55 Whr X lhr/60 min X 12 min = 1.31 R-UNSAT COMMENTS:

~~ ~ ~ ~~

2- Determine dose received while performing task SAT STANDARD: Determine dose received while performing task .45 Whr X 1hr/60 min X 4 min = 1.43 R-UNSAT L

COMMENTS:

STEP: Determine dose remaining from EDL SAT STANDARD: Determine dose remaining from EDL R- 1.31R - 1.43R = 2.26 R-UNSAT COMMENTS:

CRO-205 fnl/Admin

4- Determine time available for the NE0 to complete task 3 without CRITICAL STEP exceeding ED SAT L STANDARD: Stay time is calculated to be:

Available Dose = a = ,785 hr x = 47.1 min-UNSAT Dose Rate 2.88 Rlhr 1hr (* 5 minutes)

COMMENTS:

END OF TASK TIME STOP:

CRO-205 fnl/Admin Page 7 of 8 CRITICAL STEP EXPLANATIONS:

u STEP # Explanation 4 Required to calculate stay tim # I TASK TIME REQUIRED DOSE RATE I I Closina 3 ~ - 5 7 3 12 min 6.55 Whr 2 Open 3FDW-313 4 min 21.45 Rlhr 3 I Open all Unit 3's ADVS 2.88 Whr Note: Assume no dose received while traveling between tasks.

INITIATING CUE:

Refer to the above information. NE0 "A" has completed tasks 1 and 2 in the time required. How long does he have to complete task 3 without exceeding his Emergency Dose Limits?

JPM-003 fnl/Admin Page 1 of 7

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM-O03/Admin Evaluate Overtime Eligibility i/

CANDIDATE EXAMINER

JPM-003 fnllAdmin Page 2 of 7

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Evaluate Overtime Eligibility Alternate Path:

NO Facilitv JPM #:

New KIA Ratin&):

Gen 2. .01 Task Standard:

Evaluate overtime eligibility and determine at least 4 out of 5 violation Preferred Evaluation Location: Preferred Evaluation Method:

Simulator -In-Plant X Perform X Simulate -

i/

References:

OMP 2-01 Attachment "C",Work Schedules NSD 200, Overtime Control Validation Time: 25 mi Time Critical: NO

_______________________----~---_______--------_______---------

______-_________--------------------

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT- UNSAT - Performance Time -

~

~~~ ~

JPM-003 fnl/Admin Page 3 of 7 SIMULATOR OPERATOR INSTRUCTIONS:

NONE i/

JPM-003 fnl/Admin Page 4 of 7 TooIslEquipmenffProcedures Needed:

OMP 2-01 Attachment "C",Work Schedules i/ NSD 200, Overtime Control READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

The following is the schedule of two (2) operators for a seven-day perio INITIATING CUE:

Using the information in the following table, determine whether overtime guidelines have been violated, listing ALL of the violations (if any). Consider each case separatel NOTE: For the purposes of this JPM, shift turnover time should not be considered in your ii determinatio Operator #I Operator #2 Monday 0700 - 1900 0800 - 2000 (Came in late, stayed to makeup time)

Tuesday 0700 - 1900 0500 - 2200 (Called in early)

Wednesday 0700 - 2200 0700 - 1900 (Held over; relief called in sick)

Thursday OFF 0700 - 1900 Friday 1900 - 0100 OFF (Went home sick)

Saturday 1900 - 0700 0700 - 1900 ii Sunday 1400 - 0200 0700 - 1200 (Called in early)

JPM-003 fnl/Admin Page 5 of 7 START TIME:

c STEP: Obtain a copy of OMP 2-01 Attachment Cand NSD-200 (Overtime Control).

-SAT STANDARD: A copy of OMP 2-01 Attachment C and NSDZOO (Overtime Control) is obtaine COMMENTS: -UNSAT

~~ ~

STEP: Evaluate Operator 1 *CRITICAL STEP STANDARD: Determine Operator # I overtime guidelines exceeded:

1. < 8 hr break (Sat - Sun) -SAT 2. > 16 hrs (Sat - Sun)

COMMENTS:

-UNSAT STEP: Evaluate Operator 2 *CRITICAL STEP L STANDARD: Determine Operator #2 overtime guidelines exceeded:

1. >16in24hrs(Mon-Tues) -SAT 2. > 16 straight (Tues)

3. > 28 in 48 hrs (Mon -Wed)

-UNSAT COMMENTS:

END OF TASK TIME STOP:

4 out of 5 violations must be identified to be satisfactor JPM-003 fnllAdmin Page 6 of 7 CRITICAL STEP EXPLANATIONS:

i/

STEP # Explanation 2 Operator # 1 must be evaluated and overtime guideline violations identifie Operator # 2 must be evaluated and overtime guideline violations identifie Note: There are a total of 5 overtime guideline violations. 4 out of the 5 must be identified for the candidate to be graded as satisfactor JPM-003 fnl/Admin Page 7 of 7 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The following is the schedule of two (2) operators for a seven-day perio INITIATING CUE:

Using the information in the following table, determine whether overtime guidelines have been violated, listing ALL of the violations (if any). Consider each case separatel NOTE: For the purposes of this JPM, shift turnover time should not be considered in your determinatio Operator #I Operator #2 Monday 0700 - 1900 0800 - 2000 (Came in late, stayed to makeup time)

Tuesday 0700 - 1900 0500 - 2200 (Called in early)

Wednesday 0700 - 2200 0700 - 1900 i/ (Held over; relief called in sick)

Thursday OFF 0700 - 1900 Friday 1900 - 0100 OFF (Went home sick)

Saturday 1900 - 0700 0700 - 1900 Sunday 1400 - 0200 0700 - 1200 (Called in early)

Attachment C OMP 2-01 Work Schedules Page 1 of I ii All operators are normally scheduled to work on 12-hour intervals. If overtime is required, the responsible supervisor shall control the use of overtime and limit employees to the following:

Adhere to the limits of NSD 200, Overtime Control. On rare occasions when these limits must be-exceeded, the guidance set forth in NSD 200 shall be followed including the completion of Appendix A, Request For Work Hours Extension, prior to exceeding any limits. These limits also apply to all employee The maximum time at the control board is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months straight excluding shift turnover time and time changes between standard time and daylight savings tim A maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of non-productive time (e.g., vacation and holidays) will not count toward the limitation set forth for overtim During selected critical activities (e.g., pulling control rods for criticality, involved testing),

shift turnover may cause delays that might not be conservative. For these activities, operations management may allow a maximum deviation of one hour to the work schedule. The Shift Operations Manager or the on-coming off-going OSM shall approve this deviatio If an operator is required to work in excess of 12 continuous hours, hidher duties shall be carefully selected to prevent assignment to activities in which fatigue may cause significant problems. Assignments that affect core reactivity or endanger safe operation of the plant or personnel should be avoide The responsible supervisor or designee shall review the time sheets of non-exempt operators to ii ensure that overtime requirements are not exceeded without proper authorization. Approval of the time sheet documents this revie J L 43 VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE

//5 /

hF /

ii TECHNICAL SPECIFICATION RELATED Duke

@Power, A Duke Ennu Company NUCLEAR POLICY MANUAL

. .

Nuclear System Directive: 20 Overtime Control . . , . . .

Process/Piogram Owner: .' Human Resource Managers BEST REVISION NUMBER ISSUE DATE 0 07/01/92 1 11/01/92 2 02/28/94

.. 3 03/30/95

. . .

12/12/96 06/16/98 03/31/99 10/19/00 03/22/01 W

CATAWBA I MCG RE I OCONEE Approved BylDate Approved BylDate Approved BylDate P.M. Grobuskv/03-05-01 W.B. Jackson/03-07-01 .. A. Rose/03-07-01 Human Resource Manager Human Resource Manager .:.: Human Resource Manager Effective Date: Effective Date: . , Effective Date:

.. . ..

04/16/01 04116/01 04/16/01 ssued By: C. J. Thomas Manager, Nuclear Regulatory & Industry Affairs VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE

VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE Nuclear Policy Manual - Volume 2 NSD 200 DOCUMENT REVISION DESCRIPTION REVISION N PAGES or SECTIONS REVISED AND DESCRIPTION

. o Initial Issue 1 Revised to reflect tech. spec. requirement Revised Section 200.5.1 to reflect procedure chang Revised Section 200.5,"Implementation"(Paragraph 2), to add clarificatio Changed 'Human Resource to 'Organization Effectiveness' in Section 200.5.1 and added clarification for the review proces Revised Appendix A, "Request For Work Hours Extension" toadd clarificatio .2, "Purpose" Added a sentence regarding employees working overtime and requirements

~

for FFD concern .5, "Implementation"- Added information contained on the Appendix A form and instructions for why and how to fill out the form. In addition, changed the responsibility for

. . initiating a PIP from the OE group to the work group failing to have overtime approved in advance. Added definition for Routine Deviatio .5.1, "Review" - Clarified OEs responsibility in reviewing information on the Appendix A -

Overtime Control Forms and defined discrepancies vs. violations as it relates to the reports generated by O Appendix A, "Request For Work Hours Extension" Section 1 - Added instructions to fill out all columns. Added columns DepartmenUVendor and Assigned SupvLlD Section 3 - Added spaces for UserID and Time, as well as a footnote stating Supervisor should not assess himself/herself for FFD concern Section 4 - Added correct Tech Spec for ONS, spaces for UserID and Time, as well as a footnote stating that Supervisor and Station ManagerlDesignee should not be the same perso Section 5 - Added new section to document PIP #and comment .2, "Purpose" -Deleted "hands on".

200.3.1, "Safety-Related W o r k - Changed definition for safety-related work. Added examples of'safety-related wor .4, "Applicability"-Changed statement to clarify to whom and when policy applie Deleted "hands on".

200.4.1, "Requirements" - Added Oconee to the 28 in any 48-hour period limi .5, "Implementation"- Changed "overtime" throughout this Section to clarify information requested on the Appendix A form. Changed "should" to shall to indicate policy requirements and not choices. Added list of positions authorized to sign as Station Managerldesigne Changed "employee's assigned crew" to Dept. ID,Changed "Organization Effectiveness" to Human Resources. Added statement: "Within approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to assure timely FFD assessments are being performed" to sentence referencing when the Assessment should be performe .5.1, "Review" - Changed "Organization Effectiveness" to Human Resources. Changed

"overtime" to clarify information required on the Appendix A form. Changed "should" to shall iii VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE

VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE Nuclear Policy Manual -Volume 2 NSD 200 c

W Table Of Contents 20 OVERTIME CONTROL ................................................................................................................................ 1

............................................. I 20 PURPOSE............. ....................................................... 1

....................................................

200. REQUIREMENTS .........

20 IMPLEMENTATION ....................................................................................... ...................... 2 200.5 1 REVIEW ................................................................................................

APPENDIX . .REQUESTFOR WORK HOURS EXTENSION ............................................................ 5 ii .. ~

V VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE

VERIFY HARD C O P Y AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE Nuclear Policy Manual - Volume 2 NSD 200 APPENDIX A.200. REQUEST FOR WORK HOURS EXTENSION Permission is requested for the individuals listed below to exceed the guidelines of Tech Spec 5.2.2 for hours that will be worked on the date shown. (Fill out ALL columns including: Full name, actual date work hour extension will occur, the letter(s) of the limit($ that will be exceeded, estimated hours that will be worked beyond guidelines, Emp. ID, department or vendor name and assigned supervisor's name.)

(Print First, MI &Last Name) Working more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time) Working more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period (excluding shift turnover time) Working more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months for MNS and ONS) in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period (excluding shift turnover time) Working more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in any 7 day period (excluding shift turnover time) Less than 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break between scheduled work periods (excluding callouts, but including shift turnover time).

Note: Call-outs are not considered scheduled work periods and d o not require an Appendix A form unless limit(s) a, b, c, d is exceeded due to the call-out. FFD and Management Procedures provisions apply to call-outs).

2 Specific reasons describing the need for exceeding the work hour guidelines. (Brief description of work to be performed and why specific individuals are needed to complete tas . I have assessed the fitness for continued duty of the above named individual(s). The assessment included an evaluation of the working conditions, and the individual(s) mental and physical ability to complete the task safely. I find the individual(s) fitness satisfactory to safely complete the assignment. I will I periodically re-assess their status as appropriate to determine their ability to continue. NOTE The FFD assessment must be done within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to.the beginning of the task datdtime the work hour extension begin Signed: Supv. ID: Date: Time:

SupervisoriTemp. SupervisorDesignee of employee(s)/vendor(s)*

22 MAR 2001 5 VERIFY HARD COPY AGAINST WEB SlTE IMMEDIATELY P R I O R TO EACH USE

VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR T O EACH USE

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Nuclear Policy Manual Volume 2 NSD 200 ii 200. OVERTIME CONTROL 200.1 INTRODUCTION A Policy Statement is necessary to provide the basis for the manner in which business is conducted and to address the department's, or company's position on such issues as they arise in the nuclear industry or as Duke experience indicates a need for a more definitive statement of polic .2 PURPOSE The objective of this policy statement is to provide administrative guidance to limit the working hours of people working at the site who perform safety related functions. It is recognized that excessive working hours can impact an employee's fitness for duty (FFD). Therefore, employees working excessive hours,will be assessed for, FFD each day a limit is exceede .3 DEFINITIONS 200. SAFETY-RELATED WORK Safety-related work is the performance or independent verification of an 'A' procedure (QAI procedures).

Examples: Assemblingldisassembling components, trains or systems; Performing, reviewing or approving QAI drawing, evaluations, procedures, specifications, et Non-safety related work must be counted towards work hour totals if that person routinely performs safety related wor .4 APPLICABILITY The provisions outlined in this policy statement are applicable to all Company employees and vendorslcontractors when performing or immediately supervising the performance of safety related work ('A'procedures).

200. REQUIREMENTS The objective shall be to have employees perform their duties without working excessive hour AI1 work hours must be considered when calculating overtime. There is no provision for separating non-safety related and safety related work. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed: An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time; An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 (28 for McGuire and Oconee) hours in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time and an allowance for time changes between standard time and daylight saving time (the 7-day period is any 7 day period); A break of at least 8, hours should be allowed between work periods, including shift turnover time; and 22 MAR 2001 1 VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE

VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR T O EACH USE Nuclear Policy Manual -Volume 2 NSD 200 ii Designee" form, and approval by the Site VF' or Station Manager prior to this individual authorizing the Appendix A,, Request for Work Hours Extension for Site Vice President, Station Manager, Site Engineering Manager, Operations Manager, Maintenance Superintendent, Radiation Protection Manager, Chemistry Manager, Work Control Manager, On Duty Operations Shift Manager, On Duty Shift Work Manager, On Duty Emergency Coordinator, On Duty Outage Manager, On Duty Outage Window Sponsor, Innage Manager and Human Resources Manage A periodic report will be compiled for site management Routine deviation from the above guidelines is not authorized. Routine deviation shall be defined as 'repetitive tasks with a duration of less than 14 days!

200. REVIEW A monthly review of authorized work hour extension forms shall be performed by the Station Managerldesignee (Human Resources Manager), to assure that overtime hours are not excessive, they have received proper authorization by the Station Manager or designee and have been documented in advance of the work hour extension (This is a requirement in the Catawba, McGuire, and Oconee Technical Specifications Sections 5.2.2; however, Oconee's Tech Specs require a periodic review of authorized work hour extension forms).

All employee's names and dates worked shall be clearly listed, with all blocks in Section 1, Appendix A complete Reasons for the work hour extension shall be clearly and specifically noted in Section 2, Appendix This review is also to assure that adequate employeelwork assessments are being conducted for excessive work hours on the actual shift or day the work hour extension occurred. Therefore, only one day shall be used per Appendix A form. In addition, an employeelsupervisor shall not assess himselflherself for fitness for duty concerns, Section '

W Any failure to authorize work hour extensions in advance shall be documented in a PIP. The PIP shall be initiated by the work group failing to have the work hour extension approved in advanc All Appendix A forms not completed in full or as stated in Section "Implementation" will be considered as discrepancies on the periodic report to management. Those forms which are not authorized in advance by the Station Managerldesignee in Section 4 shall have supporting PIP information in Section 5 before being routed to the Human Resources Manage MAR 2001 3 VERIFY HARD COPY AGAINST WEE SITE IMMEDIATELY PRIOR T O EACH USE

SRO-206 fnl/Adrnin Page 1 of 9

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Determine Emergency Classification and Protective Action Recommendations CANDIDATE EXAMINER

SRO-206 fnl1Admin Page 2 of 9

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Determine Emergency Classification and Protective Action Recommendations Alternate Path:

NO Facility JPM #:

New KIA Ratinds):

Gen 2.4.38 2.2/4.0 Task Standard:

Appropriate classification is determined and associated Protective Action Recommendations are made Preferred Evaluation Location: Preferred Evaluation Method:

Simulator 1 In-Plant X Perform -Simulate Examiner: 1 NAME SIGNATURE DATE

SRO-206 fnllAdmin Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS:

NONE W

SRO-206 fnllAdmin Page 4 of 9 ToolslEquipmenffProcedures Needed:

RPIOIBII OOOIOI RPIOIBIIOOOI02 BASIS Document (Volume A , Section D of the Emergency Plan)

READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

0800: Civil demonstration occurring at the intersection of Highway 183 and 130 by anti-nuke activist : Security reports to the OSM that, one or more persons has been observed cutting their way through the double security fences. RPIOIBII OOOI007 (Security Event) is being i/ used in conjunction with the Emergency Pla : Intruders have been seen entering Unit 3 Control Room. Security has isolated the area around Unit 3 s Control Roo : Security reports that an explosion has occurred on the Keowee Dam and that water is beginning to leak through the dam in several places. Keowee Dam failure is imminen : Security reports that no additional bombs were found and that no additional intruders have been locate Note: All three Oconee Units remain in MODE 1 at 100% power during this even INITIATING CUE:

You are to perform the required actions of the Emergency Coordinator by referring to RPIOIBIIOOOIOI , Emergency Classification and determining the emergency classification and any Protective Action Recommendation Note: Do not use Emergency Coordinators judgment while classifying the event. When ii required, an operator will maintain the Emergency Coordinators Log and assume the duties of the Control Room Offsite Communicato ~

SRO-206 fnl/Admin Page 5 of 9 START TIME:

STEP: Classify the Event CRITICAL STEP STANDARD: Refer to RP/O/B/1000/01 (Emergency Classification) Enclosure (FireslExplosions and Security Actions). -SAT Classify the event as a "General Emergency" due to following:

"Loss of physical control of the control room due to security event" -UNSAT COMMENTS:

~ ~

STEP: Determine Protective Action Recommendations STANDARD: Refer to RP/O/B/lOOO/OO2 (Control Room Emergency Coordinator -SAT Procedure) and GO TO Enclosure 4.1 (General Emergency)

COMMENTS:

-UNSAT

3- Step IF It has been determined that an Emergency Action Level for an Initiating Conditions has been met, THEN Declare a General Emergency -SAT Time of Declaration: -

STANDARD: Determine Initiating Conditions have been met and Declare a General Emergency due to: -UNSAT

"Loss of physical control of the control room due to security event" Determine Time of Declaration is present tim COMMENTS:

STEP: Step ADDOint a Derson to maintain the Emeraencv Coordinator Loa OR I , -

m'iintain the log yoursel SAT STANDARD: A person is appointed to maintain the Emergency Coordinator Log or indicate that you will maintain the lo COMMENTS: -UNSAT

SRO-206 fnl/Admin Page 6 of 9 STEP: Step Appoint Control Room Offsite Communicator(s).

i STANDARD: A Control Room Offsite Communicator is appointe SAT COMMENTS:

-UNSAT STEP: Step CRITICAL STEP Provide the Protective Action Recommendationsfor use by the Offsite Communicator to complete the Emergency Notification For SAT STANDARD: Determine from chart that the following Protective Action Recommendations should be given:

-UNSAT Evacuate sectors: Pickens County - AO, AI, BI, C1; Oconee County - AO, D I , E l , F1

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Shelter sectors: Pickens County A2, 82, C2; Oconee County- D2. E2, F2 COMMENTS:

L STEP: Step 1. IF Conditions A, Imminent or Actual Dam Failure (Keowee or Jocassee)

exist, -SAT THEN REFER TO Enclosure 4.7, (Condition NCondition B Response Actions), Step 1.O, for additional Protective Action Recommendation UNSAT STANDARD: Candidate should refer to Enclosure 4.7, (Condition NCondition B Response Actions).

COMMENTS:

SRO-206 fnllAdmin Page 7 of 9 STEP: Step CRITICAL STEP IF Conditions A, Imminent or Actual Dam Failure (Keowee or Jocassee)

exists, L -SAT THEN Perform the following actions:

Provide the following protective action recommendations to Oconee County and Pickens County for imminentlactual Dam Failur UNSAT 1. Provide the following recommendation for Emergency Notification Form Section 15 (B) Evacuate:

Move residents living downstream of the Keowee Hydro Project dams to higher groun . Provide the following recommendation for Emergency Notification Form Section 15 (D) Other:

Prohibit traffic flow across bridges identified on your inundation maps until the danger has passe STANDARD: Enclosure 4.7, (Condition A I Condition B Response Action) is used to determine that the following protective action recommendations are given to Oconee and Pickens County:

1. Provide the following recommendation for Emergency Notification Form Section 15 (B) Evacuate:

Move residents living downstream of the Keowee Hydro Project dams to higher groun . Provide the following recommendation for Emergency Notification c Form Section 15 (D) Other:

Prohibit traffic flow across bridges identified on your inundation maps until the danger has passe COMMENTS END OF TASK rlME STOP:

SRO-206 fnl/Admin Page 8 of 9 CRITICAL STEP EXPLANATIONS:

L STEP # Explanation 1 The candidate needs to be able to utilize the procedure and determine that a General Emergency should be declare The candidate must be able to make recommendations to the local agencies as the actions necessary to protect the health and safety of the publi The candidate must be able to make recommendations to the local agencies as the actions necessary to protect the health and safety of the publi SRO-206 fnllAdmin Page 9 of 9 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

L INITIAL CONDITIONS:

0800: Civil demonstration occurring at the intersection of Highway 183 and 130 by anti-nuke activist : Security reports to the OSM that, one or more persons has been observed cutting their way through the double security fences. RP/O/B/l000/007 (Security Event) is being used in conjunction with the Emergency Pla : Intruders have been seen entering Unit 3 Control Room. Security has isolated the area around Unit 3s Control Roo : Security reports that an explosion has occurred on the Keowee Dam and that water is beginning to leak through the dam in several places. Keowee Dam failure is imminen : Security reports that no additional bombs were found and that no additional intruders have been located.

i/ Note: All three Oconee Units remain in MODE 1 at 100% power during this even INITIATING CUE:

You are to perform the required actions of the Emergency Coordinator by referring to RPIOIBII000101, Emergency Classification and determining the emergency classification and any Protective Action Recommendation Note: Do not use Emergency Coordinators judgment while classifying the event. When required, an operator will maintain the Emergency Coordinators Log and assume the duties of the Control Room Offsite Communicato Duke Power Company

. 1mTION PROCEDURE PROCESS RECORD

' (1)IDNo ~ / 0 ~ / 1 0 0 0 / ~ 1 R ~ V ~ S INO O~ J ONLY W lEPARATION (2) Station OCONEE NUCLEAR STATION (3) Procedure Title Emergency Classification (4) Prepared By Mike Thome (Signature) ma& Date 01/27/03 Requires NSD 228 Applicability Determination?

'#

(5)

Yes (New procedure or revision with major changes)

No (Revision with minor changes)

No (To incorporate previously approved changes)

(6) ReviewedBy (QR) Date 37 b Cross-Disciplinary Re (QRWAhd-Date Reactivity Mgmt Review By (QR)NA&Date Mgmt Involvement Review By (Ops Supt) N A d D a t e (7) Additional Reviews Reviewed By Date Reviewed By Date (8) Temporary Approval (if necessary)

BY (OSWQR) Date i/ BY (QR) Date (9) Approved By Date $ Z / ( ) ld-2 PERFORMANCE (Compare &Icontrol copy every 14 calendar days while work is beingperformed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WOW COMPLETION (12) Procedure Completion Verification:

0 Unit 0 0 Unit 1 0Unit 2 0Unit 3 Procedure performed on what unit?

0 Yes 0 NA Check lists andor blanks initialed, signed, dated, or filled in NA, as appropriate?

0 Yes 0 NA Required enclosures attached?

0 Yes 0 NA Data sheets attached, completed, dated, and signed?

0 Yes 0 NA Charts, graphs, etc. attached, dated, identified, and marked?

0 Yes 0 NA Procedure requirements met?

Verified By Date

-,Procedure Completion Approved Date W

,..) Remarks (Attach addiliomlpages)

- Procedure N Duke Power Company u Oconee Nuclear Site RP/018/1000/001 Revision N Emergency Classification 013 Electronic Reference N Reference Use oxoo2wos

..

RP/O/B/lOOO/OO1 Page 2 of 5 Emergency Classification ii NOTE: This procedure is an implementing procedure to the Oconee Nuclear Site Emergency plan and must be forwarded io Emergency Planning w i h n seven (7)worhng days of approval 1. Symptoms This procedure describes the immediate actions to be taken to recognize and classify an emergency conditio .2 This procedure identifies the four emergency classifications and their corresponding Emergency Action Levels (E&). This procedure provides reporting requirements for non-emergency abnormal event .4 The following guidance is to be used by the Emergency CoordinatorhZOFDirector in assessing emergency conditions:

1. The Emergency CoordinatorEOF Director shall review all applicable initiating events to ensure proper classificatio . The BASIS Document (Volume A, Section D of the Emergency Plan) is available for review if any questions arise over proper classificatio . IF An event occurs on more than one unit concurrently, T The event with the higher classification will be classified on the Emergency Notification For A. Jnformation relating to the problem(s) on the other unit(s) will be captured on the Emergency Notification Form as shown in RP/OIB/1000/015A, (Offsite Communications From The Control Room),

RP/OIB/1000/015B, (Offsite Communications From The Technical Support Center) or RP/OIB/1000/015C, (Offsite Communications From The Emergency Operations Facility).

1. An event occurs,

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AND A lower or higher plant operating mode is reached before the Classification can be made, T The classification shall be based on the mode that existed at the time the event occurre RP/0IB/1000/001 Page 3 of 5 1. The Fission Product Barrier Matrix is applicable only to those eveAts that occur at Hot Shutdown or highe A. An event that is recognized at Cold Shutdown or lower shall not be classified using the Fission Product Bamer Matri . Reference should be made to the additional enclosures that provide Emergency Action Levels for specific events (e.& Severe Weather, Fire, Security). IF A transient event should occur, T Review the following guidance:

1. IF An Emergency Action Level (EAL) identifies a specific duration

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AND The Emergency CoordinatorlEOFDirector assessment concludes that the specified duration is exceeded or will be exceeded, (i.e.;

condition cannot be reasonably corrected before the duration elapses),

T Classify the even . E A plant condition exceeding EAL criteria is corrected before the specified duration time is exceeded, T The event is NOT classified by that EA A. Review lower severity EALs for possible applicability in these cases.

NOTE: Reporting under lOCFR50.72 may be required for the following step. Such a condition could occur, for example, if a follow up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believe . IF A plant condition exceeding EAL criteria is not recognized at the time of occurrence, but is identified well after the condition has occurred (e.g.; as a result of routine log or record review)

AND The condition no longer exists, T An emergency shall NOT be declare RP/O/l3/1000/001 Page 4 of 5 1. An emergency classification was warranted, but the plant condition has been corrected prior to declaration and notification, The Emergency Coordinator must consider the potential that the initiating condition (e.g.; Failure of Reactor Protection System)

may have caused plant damage that warrants augmenting the on shift personnel through activation of the Emergency Response Organizatio IF An Unusual Event condition exists, T Make the classification as require . The event may be terminated in the same notification or as a separate termination notificatio An Alert, Site Area Emergency, or General Emergency condition exists, T Make the classification as required,

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AND Activate the Emergency Response Organizatio .6 Emergency conditions shall be classified as soon as the Emergency CoordinatorEOF Director assessment determines that the Emergency Action Levels for the Initiating Condition have been exceeded.

2. Immediate Actions 2.1 Determine the operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response to the even .2 E The unit is at Hot Shutdown or higher AND The conditiodevent affects fission product barriers, T GO TO Enclosure 4.1, (Fission Product Barrier Matrix).

2. Review the criteria listed in Enclosure 4.1, (Fission Product Banier Matrix)

and make the determination if the event should be classifie FwoIB/ 1ooo/oo1 Page 5 of 5 Review the listing of enclosures to determine if the event is applicable to one of the Ll categories show . IF One or more categories are applicable to the event,

. 2. Refer to the associated enclosure . Review the EALs and determine if the event should be classifie ,An EAL is applicable to the event, T" Classify the event as required The condition requires an emergency classification, T" GO TO RP/O/B/1000/002, (Control Room Emergency Coordinator Procedure) Subsequent Action .5 Continue to review the emergency conditions to assure the current classification continues to be applicabl . Enclosures Enclosures Page Number i/ Fission Product Barrier Matrix 6 System Malfunctions I Abnormal Rad LevelslRadiological Effluents 9 Loss Of Shutdown Functions 11 Loss of Power 13 FireslExplosions And Security Actions 14 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety 15 Radiation Monitor Readings For Emergency Classification 18 UnexpectedKJnplanned Increase In Area Monitor Readings 19 4.10 Definitions 20 4.11 Operating Modes Defined In Improved Technical Specifications 24

'4 4.12 Instructions For Using Enclosure I I

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Enclosure 4.10 RP/O/B/1000/00 1 Definitions/Acrony ms Page 1 of 4 1. List of Definitions and Acronyms ii NOTE: Definitions are italicized throughout procedure for easy recognitio .1 ALERT - Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure level .2 BOMB - A fused.explosivedevice CONDITION A - Failure is Imminent or Has Occurred - A failure at the dam has occurred or is about to occur and minutes to days may be allowed to respond dependent upon the proximity to the da .4 CONDITION B - Potentially Hazardous Situation is Developing - A situation where failure may develop, but preplanned actions taken during certain events (such as major floods, earthquakes, evidence of piping) may prevent or mitigate failur .5 CIVIL DISTURBANCE - A group of ten (10) or more people violently protesting station operations or activities at the sit .6 CREDIBLE THREAT - The.detennination of what is a credible threat to the site will be the responsibility of Security Manageddesignee in consultation with the OSM. The determination of "credible" is made through use of information found in the Oconee Nuclear Station Safeguards Contingency Plan and Security implementing procedure .7 EXPLOSION - A rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components. A sudden failure of a pressurized pipe/line could fit this definition. This definition includes MS line rupture and F W line rupture .8 EXTORTION :An attempt to cause an action at the station by threat of forc . . FIRE - Combustion characterized by heat and light. Sources of smoke, such as slipping drive belts or overheated electrical equipment, do NOT constitutefires. Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observe .10 GENERAL EMERGENCY - Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guidelines exposure levels outside the Exclusion Area Boundar Enclosure 4.10 RPIOIBIl OOO/OO I Definitions/Acronyms Page 2 of 4 1.11 HOSTAGE - A person or object held as leverage against the station to ensure demands will be met by the station.

1.12 INTRUSIONDNTRUDER - Suspected hostile individual present in a Protected Area without authorization.

1.13 INABILITY TO DIRECTLY MONITOR - Operational Aid Computer data points are unavailable or gaugedpanel indications are NOT readily available to the operator.

1.14 LOSS OF POWER - EmergencyAction Levels (EALs) apply to the ability of electrical energy to perform its intended function, reach its intended equipment. Ex. -If both m s ,

are energized but all 4160v switchgear is not available, the electrical energy can not reach the motors intended. The result to the plant is the same as if both MElBs were de-energized.

1.15 PROTECTED AREA - Encompasses all Owner Controlled Areas within the security perimeter fence.

1.16 REACTOR COOLANT SYSTEM (RCS) LEAKAGE - RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13:

RCS leakage includes leakage from connected systems up to and including the second normally closed valve for systems which do not penetrate containment and the outermost isolation valve for systems which penetrate containmen Identified LEAKAGE LEAKAGE to the containment from specifically known and located sources, hut does not include pressure boundary LEAKAGE or controlled reactor coolant pump (RCP) seal leakoff (a normal function not considered LEAKAGE).

LEAKAGE, such as that from pump seals, gaskets, or valve packing (except RCP seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank, LEAKAGE through a steam generator (SG) to the Secondary System: Primary to secondary LEAKAGE must be included in the total calculated for identified LEAKAG B. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE Pressure Boundarv LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

1.17 RUPTURED (As relates to Steam Generator) - Existence of Primary to Secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.

1.18 SABOTAGE - Deliberate damage, mis-alignment, or mis-operation of plant equipment with the intent to render the equipment unavailabl Enclosure 4.10 RP/OIB/1000/001 Definitions/Acronyms Page 3 of 4 1.19 SAFETY-RELATEDSYSTEMS AREA - Any area within the Protected area which contains equipment, systems, components, or material, the falure, destructlon, or release of i/

which could directly or indirectly endanger the public health and safety by exposure to radiatio .20 SIGNIFICANT PLANT TRANSIENT - An unplanned event involving one or more of the following:

(1) Automatic turbine runbacb25% thermal reactorpower (2) Electrical load rejection >25% full electrical load ( 3 ) Reactor Trip (4) Safety Injection System Activation 1.21 SITE AREA EMERGENCY - Events are in process or have occurred which involve actual or likely major failures of plant functions needed for the protection of the public. Any releases are NOT expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels outside the Exclusion Area Boundar .22 SELECTED LICENSEE COMiViITMENT (SLC) -Chapter 16 of the FSAR 1.23 SITE BOUNDARY - That area, including the Prorected Area, in which DPC has the authority to control all activities including exclusion or removal of personnel and property (1 mile radius from the center of Unit 2).

W 1.24 TOXIC GAS - A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g.; Chlorine).

1.25 UNCONTROLLED - Event is not the result of planned actions by the plant staf .26 UNPLANNED - An event or action is UNPLANNED if it is not the expected result of normal operations, testing, or maintenance. Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNE .27 UNUSUAL EVENT - Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occur ,

1.28 VALID - An indication or report or condition is considered to be VALID when it is conclusively verified by: (1) an instrument channel check; or, (2) indications on related or redundant instrumentation; or, (3) by direct observation by plant personnel such that doubt related to the instruments operability, the conditions existence, or the reports accuracy is removed. Implicit with this definition is the need for timely assessmen .29 VIOLENT - Force has been used in an attempt to injure site personnel or damage plant propert ii LL

, Enclosure 4.10 RP/OIB/1000/001 DefinitiondAcronyms Page 4 of 4 1.30 VISIBLE DAMAGE -Damage to equipment or structure that is readily observable without.

W measurements, testing, or analyses. Damage is sufficient to cause concern regarding the continued operability or reliability of affected safety structure, system, or componen Example damage: deformation due to heat or impact, denting, penetration, ruptur Enclosure 4.11 RP/O/B/l ooo/oo1 Operating Modes Defined In Improved Page 1 of 1 Technical Specifications MODES REACTIVITY % RATED AVERAGE CONDITION THERMAL REACTOR COOLANT MODE TITLE POWER (a) TEMPERATURE (Kerf) (F)

1 Power Operation 20.99 >5 NA 2 Startup ->0.99 -<5 NA 3 Hot Standby 4.99 NA ->250 4 Hot Shutdown (b) < 0.99 NA 250 > T > 200 5 Cold Shutdown (b) < 0.99 NA -

< 200 6 Refueling (c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensione Enclosure 4.12 RP/o/B/lOOO/OO1 Instructions For Using Enclosure Page 1 of 2 1. Instructions For Using Enclosure 4.1 -Fission Product Barrier Matrix ii

& If the unit was at Hot S / D or above, (Modes 1,2,3, or 4) and one or more fiss'ion product barriers have been affected, refer to Enclosure 4.1, (Fission Product Barrier Matrix) and review the criteria listed to determine if the event should be classifie . For each Fission Product Barrier, review the associated EALs to determine if there is a Loss or Potential Loss of that barrier. Circle any that appl NOTE: An event with multiple events could occur which would result in the conclusion that exceeding the loss or potential loss thresholds is imminent (Le. within 1-3 hours). In this situation, use judgement and classify as if the thresholds are exceede .2 Three possible outcomes exist for each barrier. No challenge, potential loss, or los Use the worst case for each banier and the classification table at the bottom of the page to determine appropriate classificatio .3 The numbers in parentheses out beside the label for each column can be used to assist in determining the classification. If no EAL is met for a given barrier, that barrier will have 0 points. The points for the columns are as follows:

1. To determine the classification, add the highest point value for each barrier to determine a total for all barriers. Compare this total point value with the numbers in parentheses beside each classification to see which one applie . Finally as a verification of your decision, look below the Emergency Classification you selected. The loss andor potential loss EALs selected for each barrier should be described by one of the bullet statement ., Enclosure 4.12 RP/OIB/1000/001 Instructions For Using Enclosure Page 2 of 2 EXAMPLE: Failure to properly isolate a 'B' MS Line Rupture outside containment, results in W extremely severe overcoolin PTS entry conditions were satisfie Stresses on the 'B' S/G resulted in failure of multiple S/G tubes RCS leakage through the S/G exceeds available makeup capacity as indicated by loss of subcooling margi RCS SGTR >Makeup capacity of one HPI pump in Potential Loss 4 normal makeup mode with letdown isolated Entry into PTS operating range Potential Loss 4 RCS leak rate > available makeup capacity as Loss 5 indicated by a loss of subcooling Fuel Clad No EALs met and no justification for No 0 classification on judgment Containment Failure of secondary side of SG results in a W direct ouening. to the environment

+ Fuel 0-- + Containment 3= Total 3

~~~~ ~

RCS 5

--

A. Even though two Potential Loss EALs and one Loss EAL are met for the RCS barrier, credit is only taken for the worst case (highest point value) EAL, so the points from this bamer equal B. No EAL is satisfied for the Fuel Clad Barrier so the points for this barrier equal C. One Loss EAL is met for the Containment Barrier so the points for this barrier equal D. When the total points are calculated the result is 8, therefore the classification would be a Site Area Emergenc E. Look in the box below "Site Area Emergency". You have identified a loss of two barriers. This agrees with one of the bullet statement The classification is correc ean P:SD 703 @04-01) J- Q5W)

~ u k Power e company (1) NO RP/O/B/1000/002

' JWOWTION$ ; PROCEDURE PROCESS RECORD 010

-

RensionNo

' M Y EPARATION (2) Station OCONEE NUCLEAR STATION (3) Procedure Title Control Room Emergency Coordinator Procedure (4) Prepared By Rodney Brown (Signature) IZL-M L Date 08/27/2002 (5) Requires NSD 228 Applicability Determination?

Yes (New procedure or revision with major changes)

(6) Reviewed By fhp L---

q/ g/bL Reactivity Mgmt Review By (QR)NA- Date Mgmt Involvement Review By (Ops Supt) NA- Date (7) Additional Reviews Reviewed By Date Reviewed By Date Temporary Approval (ifnecessary)

BY (OSWQR) Date BY (QR) Date (9) Approved By &

f g+- Date &&9/@7 PERFORMANCE (Compare w& control copy every 14 calendar akys while work is bekgpeflomed.)

(IO) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification:

Unit 0 0 Unit 1 0 Unit 2 0 Unit 3 Procedure performed on what unit?

0 Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in N A as appropriate?

0Yes 0 NA Required enclosures attached?

0 Yes 0 NA Data sheets attached, completed, dated, and signed?

0Yes 0 NA Charts, graphs, etc. attached, dated, identified, and marked?

0 Yes NA Procedure requirements met?

Verified By Date

,-

ii

, Procedure Completion Approved Date (14) Remarks (Attnch addilionalpases)

Duke Power Company Procedure N Oconee Nuclear Site RP/O/B/10oo/oo2 Revision No.

Control Room Emergency Coordinator Procedure 010 Electronic Reference N Reference Use OX002WOT

RP/0/B/1000/002 Page 2 of 8 Control Room Emergency Coordinator Procedure :

NOTE: This procedure is an implemenling procedure to the Oconee Nuclear Site Emergency Plan and must be forwarded to Emergency Planmng witiun three (3) working days of approva . Symptoms Events are in process or have occurred which require activation of the Oconee Nuclear Site Emergency Pla . Immediate Actions The Operations Shift ManagerEmergency Coordinator shall use this procedure until relieved by the Station ManagerlAltematein the Technical Support Center.

~~ ~~ ___

NOTE: Place Keeping Aids: cl at left of steps may be used for procedure place keeping. (0)

0 IF General Emergency conditions are met, T" GO TO Enclosure 4.1 (General Emergency).

0 IF Site Area Emergency conditions are met, GO TO Enclosure 4.2 (Site Area Emergency).

0 IF Alert conditions are met, T" GO TO Enclosure 4.3 (Alert).

cl IF Unusual Event conditions are met,

= GO TO Enclosure 4.4 (Unusual Event).

0 IF An Emergency Classification does NOT exist and ERO Activation is desired, T" GO TO Step 1.6 of Enclosure 4.4 (Unusual Event).

3. Subsequent Actions NOTE: Actions are NOT required to be followed in any particular sequenc .1 A SBLOCA or Steam Generator Tube Leak exist, Implement Step 5.4, Emergency Worker Exposure Limits, of OM' 1-18, (Implementation Standard During Abnormal And Emergency Events).

RP/0/B/1000/002 Page 3 of 8 0 E RJA 46 is on scale, T" Use Enclosure 4.3 of RP/O/B/1000/001, (Emergency Classification), to determine if the emergency classification should be upgraded to a Site Area Emergency or General Emergency based on radiation activit .2.1 Instruct RP to perform an Offsite Dose Calculation and determine any additional Protective Action Recommendation .3 E 1 , 3 RIA 57 reads 2 1.0 FUhr; 2 RIA 57 reads 11.6 R/hr, or 1,2,3 RIA 58 reads 11.0 Rfh T" Use Enclosure 4.1 or 4.8 of RP/OIB/1000/001, (Emergency Classification),to determine if the emergency classification should be upgraded to a Site Area Emergency or General Emergency based on radiation activit .4 RIA 16 or 17 are/were in AIea or High Alarm (22.5 mR/hr),

T" Instruct RP to perform an Offsite Dose Calculation using the RIA value .4.1 Use Enclosure 4.3 of RP/O/B/1000/001, (Emergency Classification), and the Offsite Dose Calculation results to determine if the emergency classification should be upgraded to a Site Area Emergency or General Emergency based on dose projection at the site boundar .4.2 Determine any additional Protective Action Recommendations.

W 0 E A large scale fire or flood damage has occurred or is occurring, T" Use RP/O/B/1000/022, (Procedure For Site Fire Damage Assessment And Repair) and /or RP/OIB/1000/29, (Fire Brigade Response) to determine additional actions that may be require .6 E A Security Event is in progress, T" Use RP/O/B/1000/007, (Security Event), to determine additional actions that may be required 0 A hazardous substance has been released, T" Use RP/O/B/1000/017, (Spill Response), to determine additional actions that may be require I RP/0IB/1000/002 Page 4 of 8 NOTE: Priority should be placed on providing treatment for the most life-threatening event (i.e.,

medical vs radiation exposure - OSC procedure RP/O/B/1000/011, (Planned Emergency

. Exposure). The Emergency Coordinator may authorize (either verbal or signature)

exposures greater than 25 rem TEDE (Total Effective Dose Equivalent) for lifesaving mission .8 A medical response is required, THEN Use RP/0/1000/016, (Medical Response).

0 3. Document verbal approval of Planned Emergency Exposures required for lifesaving missions in the Control Room Emergency Coordinator Lo .9 Changing plant conditions require an emergency classification upgrade, THEN GO TO the applicable enclosure, designated in the Immediate Actions section of this procedure, required for the appropriate emergency classificatio .10 Announce over the Plant Public address System the following information:

0 3.1 The current emergency classification level and plant status UE/Alert/SAE/GE W

0 3.1 If appropriate, the status of contamination and how people are to handle themselves:

Plant personnel should assume they are contammated until surveyed by RP or until they have frisked themselve NO eating, drinking, or smoking until the area is cleared by RP Identify areas of contamination to plant personnel:

Fw0/B/1000/002 Page 5 of 8 WARNING: Use of the Outside Air Booster Fans during a Security Event may introduce incapacitating agents into the Control Roo NOTE: The Outside Air Booster Fans (Control Room Ventilation System - CRVS) are used to provide positive pressure in the Control Room to prevent smoke, toxic gases, or radioactivity from entering the area as required by NuReg 073 Chlorine Monitor Alarm will either stop the Air Booster Fans or will not allow them to star .11 E There is an indication that smoke or toxic gases from the Turbine Building may enter the Control Roo T" Instruct Control Room personnel to turn on the Outside Air Booster Fan Fans On - Time: -

0 3.12 RIA-39 is in ALARM, T" Follow AP/1/2/3/1700/018, (Abnormal Release Of Radioactivity).

W Fans On __ Time: -

0 Secure fans if back-up sample by RP shows RIA-39 is in erro Isolate source of airborne contamination to the Control Room if sample from RP shows RIA alarm is vali Secure fans if dose levels in CR/TSC/OSC are increased by the addition of outside filtered ai Fans Off - Time: __

RP/0IB/1000/002 Page 6 of 8 NOTE: IOCFR50.54(q) allows for reasonable actions that depart from a License Condition or Technical Specification to be performed in an emergency when this action is immediately needed to protect the health and safety of the public and no action consistent with the License Condition or Technical Specification that can provide adequate or equivalent protection is immediately apparen lOCFR50.54 (y) requires approval of any IOCFR50.54(x) actions by a Licensed Senior Operator Implementation of Oconee Severe Accident Guidelines (OSAG) requires the use of lOCFR50.54 (x) and (y) provision .13 Plant conditions require a decision to implement 10CFR50.54(x),

Perform the following steps:

3.1 Document decision and actions taken in the affected units lo .1 Document decision and actions taken in the CR Emergency Coordinator Lo NOTE: NRC must be notified of any lOCFR50.54(~)decisions and actions within one (1) hour.

ii 0 3.1 Request CR NRC Communicator to report decision and actions taken to the NR NOTE: 10CFR50.72 requires NRC notification for specific plant condition .14 IF Plant conditions require NRC notification under 10CFR50.72, T Request the CR NRC Communicator to provide this notification using the guidance in OMP 1-14, (Notifications).

.3.15 TheEmergency Response Organization was activated and a security event involving an intrusiodattempted intrusion does not exist, 141 Provide turnover to the Technical Support Center using Enclosure 4.5 of this procedur Technical Support Center Activated __ Tlme: __

A. Turn over all emergency response procedures in use to the TS RP/0/B/1000/002 Page 7 of 8 L

NOTE: After normal working hours, emergency response personnel will not report to the TSC or OSC until after the security threat has been neutralize The EOF Director will notify the Control Room Emergency Coordinator once the EOF is Operational and initiate turnove .16 The Emergency Response Organization was activated after normal working hours a security event involving an intrusioxdattempted intrusion does exist, THEN Provide turnover to the EOF Director using the following guidanc {4}

3.1 Obtain the current copy of the Emergency Notification Form and plant statu A. Verify the following information being provided by the EOF Director to the Control Room Emergency Coordinato Present Emergency Classification Time of Classification -

Initial Emergency Classification Time of Classification __

Initiating Condition/Unit(s) Affected Present status of affected unit(s), including significant equipment out of servic Plant Condition: Improving - Stable - Degrading -

Status of affected unit(s):

Unit 1 shutdown at or at % Power Unit 2 shutdown at or at % Power Unit 3 shutdown at or at % Power Equipment out of service:

0 Emergency Releases:

None - Potential - Is Occurring __ Has Occurred -

0 Protective Action Recommendations:

None __

Oconee County:

Pickens County:

0 Last Message Number - Next Message due at (time):

RpI0IB/1000/002 Page 8 of 8 3.1 Control Room Emergency Coordinator turnover to EOF Director completed, EOF Activated Time

.n 3.1 Direct NRC Communicator to notify the NRC Operations Center that the EOF is activate .17 An Unusual Event classification is being terminated, T" RFFER TO Enclosure 4.6, (Emergency Classification Termination Criteria),

of this procedure for termination guidanc .1 Verify that the Offsite Communicator has provided termination message to the offsite agencie NOTE: The EP Section shall develop a written report, for signature by the Site Vice President, to the State Emergency Preparedness Agency, Oconee County EPD, and Pickens County EPD within 24 working hours of the event termination.

~~ ~

0 3.1 Notify Emergency Planning Section (Emergency Planning Duty person after hours) that the Unusual Event has been terminate .1 Emergency Planning shall hold a critique following termination of any actual Unusual Event.

4. Enclosures General Emergency Site Area Emergency Alert Unusual Event Operations Shift Manager to TSC Emergency Coordinator Turnover Sheet Emergency Classification Termination Criteria Condition NCondition B Response Actions ERO Pager Activation By Security References

Enclosure Fw0/B/1000/002 General Emergency Page 1 of 4 1. Immediate Actions NOTE: State and County Agencies must be notified of event classification within 15 minutes of Emergency Declaratio Provide Offsite Communicator with declaration tim CI It has been determined that an Emergency Action Level for an Initiating Condition has been met, Declare a General Emergenc Time of Declaration:

0 Appoint a person to maintain the Emergency Coordinator Log maintain the log yoursel NOTE: Remind the Control Room Offsite Communicator that Follow Up notifications (updates)

are required at least every 60 Minutes for this classificatio Condition A, Dam Failure (Keowee or Jocassee), Condition B also requires notification of the Georgia Emergency Management Agency and National Weather Service. Rekind the Control Room Offsite Communicator to notify these agencies in addition to and after SC State, Oconee County, and Pickens Count .3 Appoint Control Room Offsite Communicator(s).

0 Provide the following Protective Action Recommendations for use by the Offsite Communicator to complete the Emergency Notification Form.

I PROTECTIVE ACTION I PICKENS COUNTY I OCONEE COUNTY 1 RECOMMENDATION 1. IF Condition A, Imminent or Actual Dam Failure (Keowee or Jocassee)

exists, REFER TO Enclosure 4.7, (Condition NCondition B Response Actions), Step 1.0, for additional Protective Action Recommendation Enclosure RpI0/B/1000/002 General Emergency Page 2 of 4 -

u NOTE: Steps 1.6 - 1.13 may be startedcompleted while the Emergency Notification Form is being prepared by the Offsite Communicato .5 Review and approve completed Emergency Notification For . Sign Emergency Notification For NOTE: Activate the Alternate TSC and OSC in the Oconee Office Building, Rooms 316 and 316A, if a fire in the Turbine Building, flooding conditions, security events (except those involving intrusiodattempted intrusion), or onsite/offsite hazardous materials spill have occurred or are occumn (41 0 Activate the Emergency Response Organization (ERO) by completing the following action . Activate ERO Pagers as follows:

NOTE: Flooding/dam failure/earthquake conditions assume bridges may be impassable to reach emergency facilities. Provide the code below for these condition O E ERO activation for an Emergency (Blue Echo) is required, THEN Press ERO Pager Activation Panel Button 1.

W O E ERO activation for an Emergency affecting bridges (Blue Echo Bridges) is required, Press ERO Pager Activation Panel Button CI E ERO activation for a Drill (Eke Delta) is required, THEN Press ERO Pager Activation Panel Button O E ERO activation for a Dnll affecting bridges (Blue Delta Bridges)

is required, Press ERO Pager Activation Panel Button WARNING: Activating the Alternate TSC and OSC during security events involving an intrusiod attempted intrusion into the site is not recommende (41 U E Alternate TSC/OSC will be used, THEN Press ERO Pager Activation Panel Button U E A Security Event is in progress, Press ERO Pager Activation Panel Button 6.

U 1. Wait one minute and repeat step 1. Enclosure RP/o/B/1ooo/oo2 General Emergency Page3of4 ' ' ,,

ii 0 Monitor ERO Pager and verify that message :en provided to the ER . Repeat steps 1.6.1 - 1.6.3 if message is not displayed on ERO Page A. REFER TO Enclosure 4.8, (ERO Pager Activation By Security), if the ERO Pager is not activated by the completion of Steps 1.6.1 - 1. . IF ERO activation is after normal working hours, THEN Contact Security at extension 3636 or 230 Security Officer Name A. Request Security Officer to activate the CAN call lis WARMNG: Conducting Site Assembly during a Security Event may not be pruden .7 Contact the Security Shift Superviso . Inform the Security Shift Supervisor that the ERO has been' activate . Discuss the need to conduct Site Assembly.

v 0 A Security'Event does NOT exist,

-

OR A Security Event does exist and the Security Shift Supervisor agrees, Conduct Site Assembly per RP/O/B/1000/009, (Procedure For Site Assembly),

. .

Enclosure 4.1 and 4.3.. .

(7 Area Radiation Monitors are in ALARM,

-

OR Steam Line Bredk has occurred, Contact shift RF' and dispatch onsite monitoring team NOTE: Remind the NRC Communicator to complete the NRC Event Notification Worksheet and Plant Status Sheet from OM? 1-14 (Notifications).

An open line to the NRC may be require .10 Appoint a SRO to notify the NRC immediately after notification'of the Offsite Agencies but not later than one (1) hour after declaration of the emergenc .1 NRC Communicator (SRO) Name

Enclosure General Emergency Page 4 of 4 i/

NOTE: The NRC Communicator is responsible for activating ERD .1 Start the Emergency Response Data System (ERDS) for unit(s) involved within one (1) hour of the emergency classificatio A. REFER TO RFVO/J3/1000/003A, (ERDS Operation).

1.11 Evacuate all non-essential personnel from the site after personnel accountability has been reache .1 REFER TO ,RP/O/B/1000/010. (Procedure For Emergency Evacuation/

Relocation Of Site Personnel).

1.12 Condition A, Imminent or Actual Dam Failure (Keowee or Jocassee),

-

OR Condition B (Keowee) exists, THEN REFER TO Enclosure 4.7, (Condition A/Condition B Response Actions),

Step 2.0 or 3.0, for additional response action .13 Return to Step 3.0, (Subsequent Actions), of this procedur Enclosure RP/0/B/1000/002 Site Area Emergency Page 1 of 4 -

ii 1. Immediate Actions NOTE: State and County Agencies must be notified of event classification within 15 minutes of Emergency Declaratio Provide Offsite Communicator with declaration tim .1 It has been determined that an Emergency Action Level for an Initiating Condition has been met, T

E J Declare a Site Area Emergenc Time of Declaration:

0 Appoint a person to maintain the Emergency Coordinator Log maintain the log yoursel NOTE: Remind the Control Room Offsite Communicator that Follow Up notifications (updates)

are required at least every 60 Minutes for this classificatio Condition A, Dam Failure (Keowee or Jocassee), Condition B also requires notification of the Georgia Emergency Management Agency and National Weather ii Service. Remind the Control Room Offsite Communicator to notify these agencies in addition to and after SC State, Oconee County, and Pickens Count .3 Appoint Control Room Offsite Communicator(s).

0 Condition A, Imminent or Actual Dam Failure (Keowee or Jocassee), exists, REFER TO Enclosure 4.7, (Condition NCondition B Response Actions),

Step 1.0, and provide Protective Action Recommendations to the Offsite Communicato t5)

NOTE: Steps 1.6 - 1.12 may be startedcompleted while the Emergency Notification Form is being prepared by the Offsite Communicato .5 Review and approve completed Emergency Notification For . Sign Emergency Notification For Enclosure RPl0n311000/002 Site Area Emergency Page 2 of 4 L NOTE: Activate the Alternate TSC and OSC in the Oconee Office Building, Rooms 316 and 316.4, if a fire in the Turbine Building, flooding conditions, security events (except those involving intrusiodattempted intrusion), or onsite/offsite hazardous materials spill have occurred or are occurrin (4)

0 Activate the Emergency Response Organization (ERO) by completing the following action . Activate ERO Pagers as follows:

NOTE: Flooding/dam failure/earthquakeconditions assume bridges may be impassable to reach emergency facilities. Provide the code below for these condition U E ERO activation for an Emergency (Blue Echo) is required, THEN Press ERO Pager Activation Panel Button U E ERO activation for an Emergency affecting bridges (Blue Echo Bridges) is required, Press ERO Pager Activation Panel Button o ERO activation for a Drill (Blue Delta) is required, Press ERO Pager Activation Panel Button O E ERO activation for a Drill affecting bridges (Blue Delta Bridges)

is required, Press ERO Pager Activation Panel Button WARNING: Activating the Alternate TSC and OSC during security events involving an intrusion/

attempted intrusion into the site is not recommende W

Enclosure RpIoIB/1000/002 Site Area Emergency Page 3 of 4 1. IF ERO activation is after normal working hours, Contact Security at extension 3636 or 230 Security Officer Name A. Request Security Officer to activate the CAN call lis WARNING: Conducting Site Assembly during a Security Event may not be pruden I 0 Contact the Security Shift Superviso . Inform the Security Shift Supervisor that the ERO has been activate . Discuss the need to conduct Site Assembl .8 -

IF A Security Event does NOT exist,

-

OR A Security Event does exist and the Security Shift Supervisor agrees, Conduct Site Assembly per RP/OIB/1000/009, (Procedure For Site Assembly),

Enclosure 4.1 and 4.3.

ii 0 IF Area Radiation Monitors are in ALARM,

-

OR Steam Line Break has occurred, THEN Contact shift RP and dispatch onsite monitoring team NOTE: Remind the NRC Communicator to complete the NRC Event Notification Worksheet and Plant Status Sheet from OMP 1-14 (Notifications).

An open line to the NRC may be require .10 Appoint an SRO to notify the NRC immediately after notification of the Offsite Agencies but not later than one (1) hour after declaration of the emergenc .1 NRC Communicator (SRO) Name NOTE: The NRC Communicator is responsible for activating ERD .

1.1 Start the Emergency Response Data System (ERDS) for unit(s) involved within one (1) hour of the emergency classificatio A. REFER TO W/O/B/1000/003A, (ERDS Operation).

Enclosure RPf0/B/1000/002 Site Area Emergency Page 4 of 4 W 0 1.11 E Condition A, Imminent or Actual Dam Failure (Keowee or Jocassee),

-

OR Condition B (Keowee) exists, REFER TO Enclosure 4.7, (Condition NCondition B Response Actions),

Step 2.0 or 3.0, for additional response action .12 Return to Step 3.0, (Subsequent Actions), of this procedure

.W

.

Enclosure Fw0/B/1000/002 Alert Page 1 of 4 ii 1. Immediate Actions NOTE: State and County Agencies must be notified of event classification within 15 minutes of Emergency Declaratio Provide Offsite Communicator with declaration tim .1 E It has been determined that an Emergency Action Level for an Initiating Condition has been met, Declare an Aler Time of Declaration: Appoint a person to maintain the Emergency Coordinator Log maintain the log yoursel NOTE Remind the Control Room Offsite Communicator that Follow Up notifications (updates)

are required at least every 60 minutes for this classificatio Condition B for Keowee Hydro Project DamsDikes also requires notification of the Georgia Emergency Management Agency and National Weather Service. Remind the Control Room Offsite Communicator to notify these agencies in addition to and after SC State, Oconee County, and Pickens Count .3 Appoint Control Room Offsite Communicator(s).

~~~ ~~~~~ ~~~~ ~ ~ ~

NOTE: Steps 1.5 - 1.1 1 may be startedcompleted while the Emergency Notification Form is being prepared by the Offsite Communicato .4 Review and approve completed Emergency Notification For . Sign Emergency Notification For .

Enclosure Fw0/B/1000/002 Alert Page 2 of 4 v NOTE: Activate the Alternate TSC and OSC in the Oconee Office Building, Rooms 316 and 316A, if a fire in the Turbine Building, flooding conditions, security events (except those involving intrusionlattempted intrusion), or onsite/offsite hazardous materials spill have occurred or are occurrin I41 0 Actwate the Emergency Response Organization P R O ) by completing the following action . Activate ERO Pagers as follows:

NOTE: Flooding/dam failure/earthquakeconditions assume bridges may be impassable to reach emergency facilities. Provide the code below for these condition O E ERO activation for an Emergency (Blue Echo) is required,

-

THEN Press ERO Pager Activation Panel Button O E ERO activation for an Emergency affecting bridges (Blue Echo Bridges) is required, THEN Press ERO Pager Activation Panel Button oc. E ERO activation for a Drill (Blue Delta) is required, W THEN Press ERO Pager Activation Panel Button O ERO activation for a Drill affecting bridges (Blue Delta Bridges)

is required, THEN Press ERO Pager Activation Panel Button WARNING: Activating the Alternate TSC and OSC during security events involving an intrusion/

attempted intrusion into the site is not recommende I41 D Alternate TSC/OSC will be used, Press ERO Pager Activation Panel Button O E A Security Event is in progress, ,

THEN Press ERO Pager Activation Panel Button . Wait one minute and repeat step 1. . Monitor ERO Pager and verify that message has been provided to the ER . Repeat steps 1.5.1 - 1.5.3 if message is not displayed on ERO Pager.

ii A. REFER TO Enclosure 4.8, (ERO Pager Activation By Security), if the ERO Pager is not activated by the completion of Steps 1.5.1 - 1. Enclosure RP/0/B/1000/002 Alert Page 3 of 4 W 0 1. ERO activation is after normal working hours, Contact Security at extension 3636 or 230 Security Officer Name A. Request Security Officer to activate the CAN call lis I WARNING:

--

Conducting Site Assembly during a Security Event may not be pruden I Contact the Security Shift Superviso . Inform the Security Shift Supervisor that the ERO has been activate . Discuss the need to conduct Site Assembl .7 A Security Event does exist,

-

OR A Security Event does exist and the Security Shift Supervisor agrees, THEN Conduct Site Assembly per RP/O/B/1000/009, (Procedure For Site Assembly),

Enclosure 4.1 and 4.3.

W Area Radiation Monitors are in ALARM,

-OR Steam Line Break has occurred, Contact shift RP and dispatch onsite monitoring teams NOTE: Remind the NRC Communicator to complete the NRC EventNotification Worksheet and Plant Status Sheet from OMP 1-14 (Notifications).

An open line to the NRC may be require .9 Appoint an SRO to notify the NRC immediately after notification of the Offsite Agencies but not later than one (1) hour after declaration of the emergenc ,

1. NRC Communicator (SRO) Name W

W NOTE: The NRC Communicator is responsible for activating ERD . Start the Emergency Response Data System (ERDS)for unit@)involved within one (1) hour of the emergency classificatio A. REFER TO FWO/B/1000/003A, (ERDS Operation).

1.10 E Condition B at Keowee exists, REFER TO Enclosure 4.7, (Condition NCondition B Response Actions),

Step 3.0, for additional response action .11 Return to Step 3.0, (Subsequent Actions), of this procedur Enclosure RP/0/B/1000/002 Unusual Event Page 1 of 4 v 1. Immediate Actions NOTE: State and County Agencies must be notified of event classification within 15 minutes of Emergency Declaratio Provide Offsite Communicator with declaration tim .1 It has been determined that an Emergency Action Level for an Initiating Condition has been met, Declare an Unusual Even Time of Declaration: Appoint a person to maintain the Emergency Coordinator Log maintain the log yoursel NOTE: Remind the Control Room Offsite Communicator that an Initial Message and a Termination Message gre required for this classification. No Follow Up Notifications (updates) are required unless requested by the Offsite Agencie Condition B for Keowee Hydro Project DamsDikes also requires notification of the Georgia Emergency Management Agency and National Weather Service. Remind the Control Room Offsite Communicator to notify these agencies in addition to and after SC State, Oconee County, and Pickens Count .3 Appoint Control Room Offsite Communicator(s).

NOTE: Steps 1.5 - 1.11 may be startedhompleted while the Emergency Notification Form is being prepared by the Offsite Communicato .4 Review and approve completed Emergency Notification For . Sign Emergency Notification For ,

1.5 IF Condition B at Keowee exists, REFER TO Enclosure 4.7, (Condition NCondition B Response Actions),

Step 3.0, for additional response action Enclosure RP/0/B/1000/002 Unusual Event Page 2 of 4 W NOTE: Activation of the ERO is NOT required for an Unusual Event Classificatio Activate the Alternate TSC and OSC in the Oconee Office Building, Rooms 316 and 316A, if a fire in the Turbine Building, flooding conditions, security events (except those involving intrusiodattempted intrusion), or onsite/offsite hazardous materials spills have occurred or are occumn {41 0 E Emergency Response Organization (ERO) activation is desired, Complete the following action . Activate ERO Pagers as follows:

NOTE Flooding/dam failure/earthqu&e conditions assume bridges may be impassable to reach emergency facilities. Provide the code below for these condition U E ERO activation for an Emergency (Blue Echo) is require Press ERO Pager Activation Panel Button O ERO activation for an Emergency affecting bridges (Blue Echo Bridges) is required, W

THEN Press ERO Pager Activation Panel Button oc. E ERO activation for a Drill (Blue Delta) is required, THEN Press ERO Pager Activation Panel Button O E ERO activation for a Drill affecting bridges (Blue Delta Bridges)

is required, Press ERO Pager Activation Panel Button WARNING: Activating the Alternate TSC and OSC during security events involving an intrusion/

attempted intrusion into the site is not recommende O E Alternate TSC/OSC will be used, THEN Press ERO Pager Activation Panel Button O E A Security Event is in progress, THEN Press ERO Pager Activation Panel Button . Wait one minute and repeat step 1.6.1.

v 0 1. Monitor ERO Pager and verify that message has been provided to the ER Enclosure RP/0/s/1000/002 Unusual Event Page 3 of 4 W 1. Repeat steps 1.6.1 - 1.6.3 if message is not displayed on ERO Page A. REFER TO Enclosure 4.8, (ERO Pager Activation By Security), if the ERO Pager is not activated by the completion of Steps 1.6.1 - 1. . IF ERO activation is after normal working hours, Contact Security at extension 3636 or 230 Security Officer Name A. Request Security Officer to activate the CAN call lis I WARNING: Conducting Site Assembly during a Security Event may not be pruden .7 Contact the Security Shift Superviso . Inform the Security Shift Supervisor that the ERO has been activate . Discuss the need to conduct Site Assembl NOTE: Consider conducting a Site Assembly if a Hazardous Materials spill affecting personnel W safety is involved; or,if personnel safety is a concer .9 Area Radiation Monitors are in ALARM,

-OR Steam Line Break has occurred, THEN Contact shift RP and dispatch onsite monitoring team Enclosure RP/0/s/lO00/002 Unusual Event Page 4 of 4

-

W NOTE: Remind the NRC Communicator to complete the NRC Event Notification Worksheet and Plant Status Sheet from OMP 1-14 (Notifications).

An open line to the NRC may be require .10 Appoint an SRO to notify the NRC immediately after notification of the Offsite Agencies but not later than one (1) hour after declaration of the emergenc .1 NRC Communicator (SRO) Name 0 1.11 Return to Step 3.0, (Subsequent Actions), of this procedur Enclosure RP/0B/1000/002 Operations Shift Manager To TSC Emergency Page 1 of 2 Coordinator Turnover Sheet W

EMERGENCY CLASSIFICATION TlME DECLARED DESCRIPTION OF EVENT Unit One Status:

Reactor Power RCS Pressure RCS Temperature Auxiliaries Being Supplied Power From ES Channels Actuated MAJOR EQUIPMENT OUT OF SERVICE JOBS IN PROGRESS Unit Two Status:

Reactor Power RCS Pressure RCS Temperature Auxiliaries Being Supplied Power From ES Channels Actuated W

MAJOR EQUIPMENT OUT OF SERVICE JOBS IN PROGRESS Unit Three Status:

Reactor Power RCS Pressure RCS Temperature Auxiliaries Being Supplied Power From ES Channels Actuated MAJOR EQUIPMENT OUT OF SERVICE JOBS IN PROGRESS

Enclosure RP/0/B/1000/002 Operations Shift Manager To TSC Emergency Page 2 of 2 Coordinator Turnover Sheet W

Classification Procedure in Use:

RP/0/B/1000/002 (Control Room Emergency Coordinator Procedure)

Is RP/O/B/1000/03A, (EmsOperation) in use? Yes __ No __ If Yes, Unit No. -

Step No. -

Is RP/O/B/1000/007, (Security) in use? . Yes __ No - If Yes, Step N Is RP/O~/1000/016,(Medical) in use? Yes __ No __ If Yes, Step No. -

Is RP/O/B/1000/017, (Spill Response) in use? Yes __ No __ If Yes, Step No. -

Is RP/O/B/1000/022, (FireFlood) in use? Yes-No- If Yes, Step No. -

Is RP/O/B/1000/029, (Fire Brigade) in use? Yes __ No __ If Yes, Step No. __

Is Step 5.4 of OM 1-18 (Implementation Standard During Abnormal And Emergency Events) in use? * Yes __ No __

If yes, implementation of emergency worker exposure limits must be announced over Public Address Syste (1)

E Condition A, Dam Failure, has been declared for Keowee Hydro Project, T Provide the following information to the TSC Emergency Coordinator:

+ Status of Offsite Agency Notifications t Recommendations made to offsite agencies t Status of relocation of site personnel What is the status of Site Assembly? (This question is only applicable for those times that the Emergency Response Organization is activated after hours, holidays, or weekends.)

Next message due to Offsite Agencies at Time:

W Operations Shift Manager/CR Time:

Emergency CoordinatorRSC Time:

Enclosure RFv0/s/1000/002 Emergency Classification Termination Page 1 of 1 -

Criteria v

-

IF The following guidelines applicable to the present emergency condition have been met or addressed,

-

THEN An emergency condition may be considered resolved when:

-1. Existing conditions no longer meet the existing emergency classification criteria and it appears unlikely that conditions will deteriorate furthe __ 2. Radiation levels in affected in-plant areas are stable or decreasing to below acceptable level . Releases of radioactive material to the environment greater than Technical Specifications are under control or have cease . The potential for an uncontrolled release of radioactive material is at an acceptably low leve . Containment pressure is within Technical Specification requirements 6. Long-term core cooling is availabl . The shutdown margin for the core has been verified.

d 8. A fire, flood, earthquake, or similar emergency condition is controlled or has cease . Offsite power is available per Technical Specification requirement . All emergency action level notifications have been complete . Hydro Central has been notified of termination of Condition B for Keowee Hydro Projec (2)

4 REFER TO Section 6 of the Emergency Telephone Directory, (Keowee Hydro Project DamDike Notification).

__ 12. The Regulatory Compliance Section has evaluated plant status with respect to Technical Specifications and recommends Emergency classification terminatio Datmme

__

Initial 13. Emergency terminated. Request the Control Room Offsite Communicator to complete an Emergency Notification Form for a Termination Message using guidance in RP/0/1000/015A, (Offsite Communications From The Contrbl Room), and provide information to offsite agencie + Return to Step 3.1 Enclosure Rp/0/B/1000/002 Condition MCondition B Response Actions Page 1 of 3 W 1. Condition A Response - Immediate Actions 17 Condition A, Imminent or Actual Dam Failure (Keowee or Jocassee) exists, Perform the following actions:

0 1. Provide the following protective action recommendations to Oconee County and Pickens County for imminent/actual dam failur A. Provide the following recommendation for Emergency Notification Form Section 15 (B) Evacuate:

1. Move residents living downstream of the Keowee Hydro Project dams to higher groun B. Provide the following recommendation for Emergency Notification Form Section 15 (D) Other:

1. Prohibit traffic flow across bridges identified on your inundation maps until the danger has passe .2 Return to applicable Enclosure (4.1 or 4.2).

ii 0 1. E A General Emergency has been declared, GO TO Step 1.5 of Enclosure 4.1, (General Emergency).

0 1. E A Site Area Emergency has been declared, GO TO Step 1.5 of Enclosure 4.2, (Site Area Emergency).

-

2. Condition A Response Subsequent Actions Notify Hydro Central and provide information related to the even . REFER TO Section 6 of the Emergency Telephone Directory, (Keowee Hydro Project DamlDike Notification). I21

0 Relocate Keowee personnel to the Operational Support Center (OSC) if events occur where their safety could be affecte i IF Keowee personnel are relocated to the OSC; Notify Hydro Centra REFER TO Section 6 of the Emergency Telephone Directory, (Keowee Hydro Project DamlDike Notification). I21

Enclosure RP/0/B/1000/002 Condition MCondition B Response Actions Page 2 of 3 NOTE: A loss of offsite communications capabilities (Selective Signaling and the Wi.de Area Network - WAN) could occur within 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after Keowee Hydro Dam failur Rerouting of the Fiber Optic Network through Bad Creek should be started as soon as possibl .3 Notify Telecommunications Group in Charlotte to begin rerouting the Oconee Fiber Optic Networ . REFER T O Selective Signaling Section of the Emergency Telephone Directory (page 9).

0 Request Security to alert personnel at the Security TracWFiring Range and Building 8055 (Warehouse #5) to relocate to work areas inside the plant.

NOTE: Plant access road to the Oconee Complex could be impassable within 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months if the Keowee Hydro Dam fails. A loss of the Little River Dam (Newry Dam) or Dikes A-D will take longer to affect this roa PA Announcements can be made by the Control Room using the Office Page Ovemde feature or Securit .5 Make a PA Announcement to relocate personnel at the following locations to the World Of Energy/Operations Training Cente Oconee Complex Oconee Garage Oconee Maintenance Training Facility Dispatch operators to the SSF and establish communication .7 Return to applicable Enclosure (4.1 or 4.2).

0 2. IF A General Emergency has been declared, THEN GO T O Step 1.13 of Enclosure 4.1, (General Emergency).

17 2. A Site Area Emergency has been declared, .

THEN GO TO Step 1.12 of Enclosure 4.2, (Site Area Emergency).

, I '

Enclosure RP/O/B/ 1000/002 Condition NCondition B Response Actions Page 3 of 3 W -

3. Condition B Response Immediate Actions E Condition B at Keowee exists, Notify Hydro Centra . REFER TO Section 6 of the Emergency Telephone Directow, (Keowee Hydro Project Dam/Dike Notification).

0 Return to applicable Enclosure (4.1, or 4.2, or 4.3, or 4.4).

0 3. IF A General Emergency has been declared, THEN GO TO Step 1.13 of Enclosure 4.1, (General Emergency).

0 3. A Site Area Emergency has been declared, GO TO Step 1.12 of Enclosure 4.2, (Site AreaEmergency).

3. E An Alert has been declared, THEN GO TO Step 1.11 of Enclosure 4.3, (Alert).

0 3. An Unusual Event has been declared, L THEN GO TO Step 1.6 of Enclosure 4.4, (Unusual Event).

Enclosure Fw0/B/l000/002 ERO Pager Activation By Security Page 1 of 2 1. Symptoms Activation of the ERO Pagers using the ERO Pager Activation Panel in the TSC was unsuccessfu . Immediate Actions Activate the Emergency Response Organization (Technical Support Center, Operational Support Center, and Emergency Operations Facility) by completing the following actions.:

2. Contact Securit A. Dial 3636 (Dial 2309 if no response is received).

Security Officer Name 2. Read the following information to the Security Officer:

A. The Emergency Response Organization (Technical Support Center, Operational Support Center, and Emergency Response Facility) is being activated for an emergency relating to Unit # -.

B. This is a Blue Delta (Drill) activation, !3J This is a Blue Echo (Emergency) activation NOTE: Flooding/dam failurdearthquake conditions assume bridges maybe impassable to reach emergency facilities. Provide the code below for these condition I C. Thisisa Blue Delta Bridges (Drill) activation, !3J This is a Blue Echo Bridges (Emergency) activation NOTE: Activate the Alternate TSC and OSC in the Oconee Office Building, Rooms 316 and 316A, if a fire in the Turbine Building, flooding conditions, security events (except thod involving intrusiodattempted intrusion), or onsite/offsite hazardous materials spills have occurred or are occumn {4}

I WARNING: Activating the Alternate TSC and OSC during security events involving an intrusion/

~~~~

attempted intrusion into the site is not recommende ~ ~ ~ ~~

I41 I The Alternate TSC/OSC will be used

Il .

Enclosure RP/0/B/1000/002 ERO Pager Activation By Security Page 2 of 2 u NOTE: The following step is only applicable during security event A.Security Event is in progres .j

-~

ES-301 Control Room/ln-Plant Outline Form ES-301-2

inial Submittal Facility: Oconee Date of Examination:

Exam Level (circle one): RO I SRO(I) / SRO(U) Operating Test No.:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title

& CRO-200, Makeup to the LDST I Type Code* Safety Function OP/1103/004 (Soluble Poison Control) N,S 1

[KA: 004 A4.13 (3.3/2.9)] (new) (15 min)

AP132 (Loss of Letdown) M, A, S 2

[KA: 004 A2.07 (3.4/3.7)] (IO min)

0 CRO- 066, Perform Required Action's for RCS Pressure 5 550 psig EOP End. 5.1 (ES Actuation)

D, A, S

[KA: EPEOI 1 EA1. I 3 (4.1/4.2)] (15 min)

CRO-013, Align MDEFDWP Suction to the Hotwell and Feed the SGs D,L,FL" 4s EOP Encl. 5.9 [KA: APE054 AA1.01 (4.5/4.4)] (IO min)

' CRO-201, Restart RCP EOP, Encl. 5.6 [KA: 003 A4.06 (2.9*/2.9)] (new) (20 min) N, S 4P 6 CRO-009, Following a Keowee Emergency Start Transfer from CT-4 to CT-5 D. L, S 6 OP/O/A/I 106/019 Encl. 4.12

[KA: 062 A4.01 (3.3/3.1)] (IO min)

g. CRO-202, Reset RIA40 setpoints and enter the OAC Pri to Sec Admin Limit N, S 7 PT/230/001 Encl. 13.10 (Operation of RIA-40)

[KA: 073 A4.02 (3.7/3.7)] (new) (IO min)

67 CRO-IIA, Align Intake Canal For Recirc On Dam Failure APll3 (Dam Failure), [KA: 075 A2.01 (3.0/3.2)] (15 min) D, L, A, S 8 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

NLO-022, Station ASW Pump Alignment EOP End. 5.10 [KA: APE054 AA1.01 (4.514.4)l (last exam) (12 min)

4s D, R, L CRO-47, Emergency start SSF Diesel Generator and supply power to the SSF ASW and SSF RCMU pumps

, AP/25, [KA: 062 A211 (3.7/4.1)] ( I O min)

W NLO-007, Start Diesel Air Compressor And Align To I Service Air Header AP/32, Encl. "Emergehcy Start of the Diesel Air Compressor",

[KA: APE-065 AA1.04 (3.5*/3.4*)] (10 min)

D I

I

"Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room,

(S)imulator, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9

ES-301 Control Roomlln-Plant Outline Form ES-301-2

inial Submittal Facility: Oconee Date of Examination:

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System I JPM Title CRO-200, Makeup to the LDST I Code*

Type I Function Safety OP/1103/004 (Soluble Poison Control) N, S 1

[KA: 004 A4.13 (3.3/2.9)] (new)

@ CRO- 083, Re-establish RCS letdown flow AP132 (Loss of Letdown) M. A. S 2

[KA: 004 A2.07 (3.4/3.7)]

(5CRO- 066, Perform Required Actions for RCS Pressure S 550 psig EOP End. 5.1 (ES Actuation)

D, A, S

[KA: EPEOTI EA1.13 (4.1/4.2)]

d. CRO-013, Align MDEFDWP Suction to the Hotwell and &

Feed the SGs D. L, 8 4s EOP End. 5.9 [KA: APE054 AA1.01 (4.5/4.4)]

e. CRO-201, Restart RCP EOP, End. 5.6 [KA: 003 A4.06 (2.9*/2.9)] (new)

FF) CRO-202, Reset RIA40 setpoints and enter the OAC Pri to

\ - Sec Admin Limit N, S 7 PT/230/001 End. 13.10 (Operation of RIA-40)

[KA: 073 A4.02 (3.7/3.7)] (new)

CRO-IIA, Align Intake Canal For Recirc On Dam Failure APll3 (Dam Failure), [KA: 075 A2.01 (3.0/3.2)]

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

6 NLO-022, Station ASW Pump Alignment EOP End. 5.10 [KA: APE054 AA1.01 (4.514.411 D, R, L 4s (last exam)

( CRO-47, Emergency start SSF Diesel Generator and supply power to the SSF ASW and SSF RCMU pumps M, A, L 6 AP/25, [KA: 062 A2.11 (3.7/4.1)]

NLO-007, Start Diesel Air Compressor And Align To Service Air Header D 8 AP132, End. "Emergency Start of the Diesel Air Compressor",

[KA: APE-065 AA1.04 (3.5*/3.4')]

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9

ES-301 Control Room/ln-Plant Outline Form ES-301-2 inial Submittal Facility: Oconee Date of Examination:

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Safety Code* Function

@ CRO- 083, Re-establish RCS letdown flow AP/32 (Loss of Letdown) M , A, S 2

[KA: 004 A2.07 (3.4/3.7)]

@ CRO- 066, Perform Required Actions for RCS 3 Pressure 5 550 psig EOP End. 5.1 (ES Actuation) D, A, S

[KA: EPEOll EA1.13 (4.1/4.2)]

q?CRO-202, Reset RIA40 setpoints and enter the OAC Pri to Sec Admin Limit N, S 7 PT/230/001 End. 13.10 (Operation of RIA-40)

[KA: 073 A4.02 (3.7/3.7)] (new)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

@) NLO-022, Station ASW Pump Alignment

@

EOP Encl. 5.10 [KA: APE054 AA1.01 (4.5/4.4)]

(last exam)

NLO-007, Start Diesel Air Compressor And Align To Service Air Header

D, R, L D 8 AP/32, Encl. Emergency Start of the Diesel Air Compressor, [KA: APE-065 AA1.04 (3.5*/3.4*)]

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9

CRO-200 fnl Page 1 of 10

REGION II

INIT1AL LICENSE EXAMI NATION JOB PERFORMANCE MEASURE CRO-200 Makeup to LDST i/ CANDIDATE:

EXAM1NER:

CRO-200 fnl Page 2 of 10

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Makeup to the LDST Alternate Path:

No Facilitv JPM #:

New KIA Ratin&):

System: 004 WA: A4.13 Rating: 3.3/2.9 Task Standard:

Makeup to the LDST from 1A and 1B BHUT is performed correctly per procedure.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator 2In-Plant - Perform Simulate -

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT -UNSAT - Performance Time: -

COMMENTS

CRO-200 fnl Page 3 of 10 SIMULATOR OPERATOR INSTRUCTIONS:

1. Recall Snap 207 ii 2. Place simulator in RUN

CRO-200 fnl Page 4 of 10 ToolslEquiomentIProceduresNeeded:

OP/I/AJl 103/004, Encl. 4.5 (RCS Inventory Control)

ii READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

Unit 1 is at 100% powe LDST level = 80 inches A batch addition to the LDST is desired INITIATING CUES:

The SRO directs you to use OP/l/~1103/004,Encl. 4.5 (RCS Inventory Control) beginning at step 3.2 to add the following to the LDST:

50 gallons from 1A BHUT i/

10 gallons from 1B BHUT

CRO-200 fnl Page 5 of 10 START TIME:

STEP: Step 3.2 c Ensure 1HP-15 Moore Controller reset for Normal Operatio SAT STANDARD: Locate 1HP-15 Moore Controller on 1UBI and ensure the following:

Mode selector in MANUAL Display selector to P -UNSAT Valve position: 100% open Start-stop to START COMMENTS:

STEP: Step IF two Letdown Filters are available, position the following:

IHP-17 ( I A LETDOWN FILTER INLET) switch to OPEN -SAT IHP-18 (1B LETDOWN FILTER INLET) switch to OPEN STANDARD: Place a second Letdown Filter in service by locating IHP-18 (1B -UNSAT LETDOWN FILTER INLET) switch on 1UB1 and placing it in the OPEN position. Valve is verified open by red light illuminated.

L COMMENTS:

STEP: Step CRITICAL STEP Ensure open IHP-16 (LDST MAKEUP ISOLATION)

-SAT STANDARD: Locate 1HP-16 on 1UBI and open the valve by rotating the switch to the open position. The red light will illuminate and the green light will go of UNSAT COMMENTS:

CRO-200 fnl Page 6 of 10 STEP: Step CRITICAL STEP IF required makeup from 1A BHUT as follows:

c -SAT Step 3. IF required, makeup with 1HP-15 in auto as follows:

Select " S on 1HP-15 Moore Controlle Enter batch size on 1HP-15 Moore Controlle UNSAT Place 1HP-15 Moore Controller in "AUT Ensure " P on 1HP-15 Moore Controlle Ensure 1HP-14 (LDST BYPASS) to "NORMAL".

STANDARD: Locate 1HP-15 Moore Controller on 1UBI and perform the following:

Select " S on 1HP-15 Moore Controlle Enter batch size of 50 gallons on 1HP-15 Moore Controlle . Place 1HP-15 Moore Controller in "AUT Ensure " P on 1HP-15 Moore Controlle Ensure 1HP-14 (LDST BYPASS) to "NORMAL".

Cue: If asked, inform candidate that it is desired to perform the makeup with IHP-15 in aut COMMENTS:

L STEP: Step 3. CRITICAL STEP Start 1A BLEED TRANSFER PUMP-SAT NOTE:

Normal make-up flow rate should be > 55 gp UNSAT STANDARD: Locate the switch for 1A BLEED TRANSFER PUMP on I A B I and start the pump by rotating the switch to the START position. The red light will illuminate and the green light will go of COMMENTS:

CRO-200 fnl Page 7 of 10 STEP: Step 3. CRITICAL STEP Open ICs-46 ( I A RC BLEED XFER PUMP DISCH)

-SAT NOTE:

1HP-15 may require throttling if only one Letdown Filter is in service and AP is hig UNSAT STANDARD: Locate ICs-46 ( I A RC BLEED XFER PUMP DISCH) valve on I A B I and open the valve by rotating the switch to the OPEN position. The red light will illuminate and the green light will go off.

COMMENTS:

STEP: Step 3. IF required, throttle 1HP-15 as follows:

Ensure 1HP-15 Moore Controller in "MANUAL" -SAT Throttle 1HP-15 to control make-up flow to LDST STANDARD: Determine throttling IHP-15 is not required when two Letdown Filters are in servic UNSAT COMMENTS:

STEP: Step 3. IF required, lower LDST level per Section 4 "Reducing RCS Inventory".

-SAT STANDARD: Determine lowering LDST level is not required.

COMMENTS: -UNSAT STEP: Step 3. WHEN required, stop 1A BLEED TRANSFER PUMP-SAT STANDARD: When the addition is completed the candidate should stop the 1A BLEED TRANSFER PUMP (located on IABI).

-UNSAT COMMENTS:

CRO-200 fnl Page 8 of 10 STEP I O : Step 3. WHEN required:

L Close ICs-46 (IA RC BLEED XFER PUMP DISCH) -SAT STANDARD: When the addition is completed the candidate should:

Close ICs-46 ( I A RC BLEED XFER PUMP DISCH) by rotating the -UNSAT switch to the CLOSE position. Valve is verified closed by red light off and green light illuminated. (located on I A B I )

COMMENTS:

STEP 11: Step 3. Reset IHP-15 Moore Controller for Normal Operatio SAT STANDARD: Locate IHP-15 Moore Controller on 1UB1 and ensure the following:

Mode selector in "MANUAL" Display selector to " P -UNSAT Valve position: 100% open Start-stop to "START" L Cue: Another operator will complete this addition to the LDS COMMENTS:

END TASK STOP TIME:

CRO-200 fnl Page 9 of 10 CRITICAL STEP EXPLANATIONS:

i/

STEP # Explanation 3 Step required to establish flow path to LDS Step required to properly setting up 1HP-15 for additio Step required to pump water to LDS Step required to establish flow path to LDS CRO-200 fnl Page 10 of 10 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

'U INITIAL CONDITIONS:

Unit 1 is at 100% powe LDST level = 80 inches A batch addition to the LDST is desired INlTlATlNG CUES:

The SRO directs you to use OPIIIAII 103I004, Encl. 4.5 (RCS Inventory Control) beginning at step 3.2 to add the following to the LDST:

50 gallons from 1A BHUT 10 gallons from 1B BHUT

Enclosure OP/l/A/I 103/004 RCS Inventory Control Page 1 of 7 . Initial Conditions None 2. Procedure NOTE: This enclosure affects reactivity management by changing RCS boro .1 Perform the following for RCS inventory control:

E requxed, makeup to RCS per Section 3 "RCS Normal Makeup" required, lower LDST level per Section 4 "Reducing RCS inventory"

Enclosure OP/l/A/I 103/004 RCS Inventory Control Page 2 of 7 c

3. RCS Normal Makeup

__ Determine amount and source RCS makeu E two Letdown Filters are available review component boron log and make appropriate adjustments to makeup volumes. ( 15)

__ Ensue 1HP-IS Moore Controller reset for Normal Operatio NOTE: Both filters may be used for RCS makeup and, as a result, may contain different boron concentrations. ( 11 )

Placing an idle Letdown Filter in service can affect reactivity management by adding different concentration of boron to RCS. ( 11 ]

One Letdown Filter holds = 60 gals. ( 1 1 ) ( 15)

~ 3.3 E two Letdown Filters are available, position the following:

1HP-17 (1A LETDOWN FILTER INLET) switch to "OPEN" L' 0 1HP-I 8 (1B LETDOWN FETER INLET) switch to "OPEN'

__ Ensure Open IHP-16 (LDST MAKEUP ISOLATION)

Enclosure OP/1/A/1103/004 RCS Inventory Control Page 3 of 7 ii 3.5 Erequired makeup from 1A BHUT as follows:

3. Erequired, makeup with 1HP-15 in auto as follows:

A. Select "S" on 1HP-15 Moore Controlle B. Enter batch size on 1HP-I 5 Moore Controlle C. Place 1HP-15 Moore Controller in "AUTO".

D. Ensure "P" on 1HP-15 Moore Controlle E. Ensure 1HP-14 (LDST BYPASS) to "NORMAL'

3. Start 1A BLEED TRANSFER PUM ~~~~ ~~~ ~

NOTE: Normal make-up flow rate should be > 55 gpm. (22)

__ 3. Open 1CS-46 (1A RC BLEED XFER PUMP DISCH).

NOTE: 1HP-15 may require throttling if only one Letdown Filter is in service and AP is high.

W 3. Erequired, throttle 1HP-15 as follows: (20)

0 Ensure 1HP- 15 Moore Controller in "MANUAL 0 Throttle 1HP-I 5 to control makeup flow to LDST

__ 3. required, lower LDST level per Section 4 "Reducing RCS Inventory".

__ 3. WHEN required, stop 1A BLEED TRANSFER PUM . Close 1CS-46 (1A RC BLEED XFER PUMP DISCH).

~ 3. Reset 1HP-I5 Moore Controller for Normal Operation

Enclosure OP/1/A/1103/004 RCS Inventory Control Page 4 of 7 ii E required makeup from 1B BHUT as follows:

3. Erequired, makeup with 1HP-15 in auto as follows:

~ A. Select "S" on 1HP- 15 Moore Controlle ~ B. Enter batch size on 1HP-15 Moore Controlle ~ C. Place 1HP-15 Moore Controller in "AUTO".

__ D. Ensure "P" on 1HP- 15 Moore Controlle E. Ensure 1HP-14 (LDST BYPASS) to "NORMAL'

-3. Start 1B BLEED TRANSFER PUM NOTE: Norinal make-up flow rate should be > 55 gpm. (22)

-3. Open 1CS-56 (1B RC BLEED XFER PUMP DISCH)

NOTE: IHP-15 may require throttling if only one Letdown Filter is in service and AP is hig . Erequired, throttle 1HP-15 as follows: I201 0 Ensure 1HP-15 Moore Controller in "MANUAL Throttle 1HP- 15 to control makeup flow to LDST

~ 3. required, lower LDST level per Section 4 "Reducing RCS hiventoiy".

~ 3. WHEN required, stop 1B BLEED TRANSFER PUMP 3. Close ICs-56 (1B RC BLEED XFERPUMP DISCH).

~ 3. Reset 1HP-15 Moore Controller for Normal Operatio Enclosure OP/1/A/1103/004 RCS Inventory Control Page 5 of 7 W

- Position IHP-I6 (LDST MAKEUP ISOLATION) switch to "CLOSE'.

3.8 Check 1HP-16 position per one of the follow~ng:

~ 3. Verify 1HP-I 6 closed by indication (closed lamp illuminated and open lamp extinguished).

-

Or 3. Check 1HP-I 6 position by flow check as follows:

~ A. Start 1A BLEED TRANSFER PUM B. Open 1 CS-46 (1A RC BLEED XFER PUMP DISCH).

NOTE: Any flow past 1HP-16 could affect core reactivity by changing RCS boron-IF 1A BLEED TRANSFER PUMP flow or 1HP-15 Moore Controller does indicate flow, 1HP- 16 is close C. Check the following for flow:

W I3 1A BLEED TRANSFER PUMP 0 1HP- 15 Moore Controller D. Stop 1A BLEED TRANSFER PUMP E. Close ICs-46 (1A RC BLEED XFER PUMP DISCH).

__ A BLEED TRANSFER PUMP flow or 1HP-15 Moore Controller indicates flow, notify SRO IHP-16 is NOT close __ required, reset 1HP-15 Moore Controller for Normal Operation Enclosure OP/1/A/1103/004 RCS Inventory Control Page 6 of 7 ii

__ required, request RCS sample for boro __ 3.10 Record RCS batch volumes in Unit Lo .1 1 E required, place one Letdown Filter in service as follows:

-3.1 Verify > 10 minutes since LDST makeup was secured. [ I 1 ]

___ 3.1 Position of the following:

1HP-17 (1A LETDOWN FILTER INLET) switch to "CLOSE"

-

Or 0 1HP-18 (1B LETDOWN FILTER INLET) switch to "CLOSE"

-3.12 E two Letdown Filters were used, make appropriate entries for Letdown Filters in component boron log. [ 15 ]

Enclosure OP/l/A/I 103/004 RCS Inventory Control Page 7 of 7 ii 4. Reducing RCS inventory NOTE: If make-up is in progress, make-up flow can be diverted from LDST to BHUT while cycling 1HP-14 (10-15 second stroke time). (21) required, reduce RCS inventory as follows:

4. Check the following:

___ Ensure open ICs-26 (LETDOWN TO RC BHUT)

- Ensure open 1CS-41 (1A RC BHUT INLET)

-4. Position 1HP-14 (LDST BYPASS) to "BLEED".

-4. WHEN required, position 1HP-14 (LDST BYPASS) to "NORMA CRO-083 fnl Page 1 of 15

REGION II

INITIAL LICENSE EXAMINAT10N JOB PERFORMANCE MEASURE CRO-083 Reestablish RCS Letdown Flow i/ CANDIDATE:

EXAMINER:

CRO-083 fnl Page 2 of 15

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Reestablish RCS letdown flow Alternate Path:

Yes Facility JPM #:

CRO-083 KIA Ratinds):

System: 004 WA A2.07 Rating: 3.4/3.7 Task Standard:

RCS Letdown flow is restored correctly using AP/32 (Loss of Letdown)

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant __ Perform Simulate -

References:

AP/32 (Loss of Letdown)

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT -UNSAT - Performance Time: -

CRO-083 fnl Page 3 of 15 SIMULATOR OPERATOR INSTRUCTIONS:

1. Recall Snap 201 ii 2. Place simulator in RUN

CRO-083 fnl Page4of15 ToolslEquipmentlProcedures Needed:

AP/32 (Loss of Letdown)

i/

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

Unit # I is at 100% powe ICC-8 (CC RETURN OUTSIDE BLOCK) was inadvertently closed during ES testin Letdown flow has been los Component cooling flow has been restore INITIATING CUES:

The SRO directs you initiate AP132 (Loss of Letdown)

CRO-083 fnl Page 5 of 15 START TIME:

STEP: Step Ensure in HAND and reduce demand to zer SAT STANDARD: IHP-120 (located on I U B I ) is taken to HAND by depressing the HAND button and reducing demand using the toggle switc UNSAT COMMENTS:

STEP: Step Initiate makeup to LDST with boron concentration 2 RCS boron concentration as require SAT STANDARD: Determine makeup to LDST is not required at this tim UNSAT COMMENTS:

STEP: Step IAAT additional makeup flow is desired AND 1A Bleed Transfer Pump is operating, -SAT THEN dispatch an operator to close ICs-48 ( I A BHUT RECIRC)

STANDARD: Determine additional makeup flow is not required at this tim UNSAT COMMENTS:

4- Step Notify chemist of the following:

Current RCS boron sample is needed for possible unit shutdow SAT Normal letdown line is isolate STANDARD: Chemistry is notified of the need for an RCS sample and the normal -UNSAT letdown line is isolate ZOMMENTS:

CRO-083 fnl Page 6 of 15

5- Step IAAT Pzr level 2 260" AND letdown CANNOT be established,

-SAT THEN initiate unit shutdown at 20%/min per AP/29 (Rapid Unit Shutdown)

-UNSAT STANDARD: Determine unit shutdown is not required COMMENTS:

STEP: Step IAAT Pzr level 2 3 7 5 THEN trip R SAT STANDARD: Determine tripping the reactor is not require UNSAT COMMENTS:

-7 Step Verify CC system in operatio SAT STANDARD: Verify proper operation of the CC system by observing 1A CC pump operating with normal CC system flows and pressure UNSAT COMMENTS:

8- Step Position the standby HPI pump switch to OF SAT STANDARD: Locate the standby HPI pump switch (located on I U B I ) and place in OF UNSAT COMMENTS:

CRO-083 fnl Page 7 of 15 STEP: Step Throttle IHP-31 to establish 12 -15 gpm SEAL INLET HDR FLO SAT STANDARD: Locate IHP-31 (on I U B I ) and use the setpoint knob to adjust SEAL INLET HDR FLOW to 12 -15 gp UNSAT COMMENTS:

STEP 10: Step 4.10 Verify loss of letdown is due to letdown valve or interlock failur SAT STANDARD: Determine that the loss of letdown in not due to letdown valve or interlock failur GO TO Step 4.29 -UNSAT Cue: If ask as the SRO, inform candidate that the loss of letdown was not due to letdown valve or interlock failure.

COMMENTS:

STEP 11: Step 4.29 WHEN letdown can be re-established, THEN ensure proper operation of the CC syste SAT STANDARD: Verify proper operation of the CC system by observing 1A CC pump operating with normal CC system flows and pressure UNSAT COMMENTS:

CRO-083 fnl Page 8 of 15 STEP 12: Step 4.30 Close IHP-6 (LETDOWN ORIFICE STOP)

-SAT STANDARD: IHP-6 (LETDOWN ORIFICE STOP) switch on I U B I is placed in the CLOSE positio UNSAT The green CLOSED light illuminates and the red OPEN light extinguishes.

Note: Candidate may use OAC indication to verify valve position.

COMMENTS:

STEP 13: Step 4.31 Close IHP-7 (LETDOWN CONTROL) -SAT STANDARD: IHP-7 (LETDOWN CONTROL) is located on I U B I and the manual controller is rotated counter-clockwise until the position demand needle -UNSAT indicates 0%.

COMMENTS:

STEP 14: Step 4.32 Ensure the following are open: -SAT IHP-1 ( I A LETDOWN COOLER INLET)

IHP-2 ( I B LETDOWN COOLER INLET)

IHP-3 ( I A LETDOWN COOLER OUTLET) -UNSAT 1HP-4 (1B LETDOWN COOLER OUTLET)

STANDARD: The above valves are located on 1UBI and verified open by observing the red OPEN light lit and green CLOSED light off.

Note: Candidate may use OAC indication to verify valve position.

COMMENTS:

CRO-083 fnl Page 9 of 15 STEP 15: Step 4.33 Verify letdown temperature c 135O SAT STANDARD: Locate LETDOWN TEMP meter on I U B I and determine that letdown temperature is greater than 135° UNSAT Perform RNO steps COMMENTS:

STEP 16: Step 4.33 RNO 1 Open IHP-13 (PURIFICATION IX BYPASS)

-SAT STANDARD: IHP-13 (PURIFICATION IX BYPASS) control switch is located on I U B I ,

and the switch is rotated to the OPEN position. Red OPEN light illuminates, and green CLOSE light extinguishe UNSAT Note: Candidate may use OAC indication to verify valve position.

COMMENTS:

STEP 17: Step 4.33 RNO 2 Ensure the following are closed:

IHP-8 (PURIFICATION IX INLET) -SAT 1HP-9&11 (SPARE PURIF IX INLET AND OUTLET)

STANDARD: IHP-8 (PURIFICATION IX INLET) control switch is located on I U B I and -UNSAT the switch is rotated to the CLOSED position. Green CLOSE light illuminates. Red OPEN light extinguishe HP-9&11 on 1UBI verified closed by Green CLOSE light lit.

Note: Candidate may use OAC indication to verify valve position.

COMMENTS:

CRO-083 fnl Page 10 of 15 STEP 18: Step 4.33 RNO 3 IF any deborating IX in service, THEN perform the following...

-SAT STANDARD: Determine that no deborating IXs are in service by verifying ICs-27 (Debor IX Inlet) (IABI) and ICs-32 & 37 (Spare Debor IX Inlet & Outlet)

(IABI) are closed. Continue with restoring letdow UNSAT Cue: If asked, inform candidate that no deborating IXs are in service.

COMMENTS:

STEP 19: Step 4.33 RNO 4 CRITICAL STEP Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.

STANDARD: LETDOWN HI TEMP INTLK BYPASS control switch is located on 1UBI, -SAT switch is rotated to the BYPASS positio The switch will backlight amber, and statalarm ISA-21E-4 HP LETDOWN FLOW INTERLOCK BYPASSED is actuate UNSAT COMMENTS:

STEP 20: Step 4.34 CRITICAL STEP Ensure IHP-5 (LETDOWN ISOLATION) is open.

STANDARD: 1HP-5 (LETDOWN ISOLATION) control switch is located on 1UBI and -SAT the switch is rotated to the OPEN positio Red OPEN light illuminates, and green CLOSE light extinguishe UNSAT Note: Candidate may use OAC indication to verify valve position.

COMMENTS:

CRO-083 fnl Page 11 of 15 STEP 21: Step 4.35 CRITICAL STEP Throttle open IHP-7 (LETDOWN CONTROL) to establish = 20 gpm.

ii STANDARD: IHP-7 (LETDOWN CONTROL) is throttled Open to establish = 20 gpm -SAT letdown flow as indicated on LETDOWN FLOW meter on 1UB COMMENTS:

-UNSAT STEP 22: Step 4.36 WHEN letdown temperature is c 130°F, THEN ensure LETDOWN HI TEMP INTLK BYP switch in NORMAL-SAT STANDARD: Statalarm lSA-2/C-1, HP-LETDOWN TEMP HI, is located by the student, and verified to be clear, and/or LETDOWN TEMP meter is used to verify letdown temperature is <13O" UNSAT LETDOWN HI TEMP INTLK BYP control switch is located on 1UB1 and switch is rotated to the NORM positio Amber backlight goes out, and statalarm ISA-2/E-4, HP LETDOWN FLOW INTERLOCK BYPASSED, clear COMMENTS:

ii STEP 23: Step 4.37 Open IHP-6 (LETDOWN ORIFICE STOP).

STANDARD: IHP-6 (LETDOWN ORIFICE STOP) is placed in the OPEN positio SAT Red OPEN light illuminates, and green CLOSED light extinguishe Note: Candidate may use OAC indication to verify valve positio UNSAT COMMENTS:

CRO-083 fnl Page 12 of 15 STEP 24: Step 4.38 Adjust 1HP-7 (LETDOWN CONTROL) to control desired letdown flow.

ii STANDARD: IHP-7, (LETDOWN CONTROL) station is located by student and the -SAT manual controller is slowly rotated clockwise, until 70 GPM is indicated on the LETDOWN FLOW mete UNSAT Cue: SRO desires 70-gpm letdown flo COMMENTS:

END TASK STOP TIME:

CRO-083 fnl Page 13of 15 CRITICAL STEP EXPLANATIONS:

ii STEP # Explanation 19 Bypassing interlock required to re-open 1HP-5 to reestablish letdown flo Aligns flow path to reestablish letdown flo Aligns flow path to reestablish letdown flo CRO-083 fnl Page 14 of 15 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

u INITIAL CONDITIONS:

Unit #is I at 100% powe CC-8 (CC RETURN OUTSIDE BLOCK) was inadvertently closed during ES testing Letdown flow has been los Component cooling flow has been restore INITIATING CUES:

The SRO directs you initiate AP132 (Loss of Letdown)

CRO-083 fnl Page 150f 15

-r---J RevisionNo 002 i/

PREPARATION (2) Station (3) Procedure Title Loss of Letdown (4) Prepared By., David P. Garland (Signature) 3 ~ 4 J

Date 11/20/02 (5) Requires NSD 228 Applicability Determination?

Yes (New procedure or revision with major changes)

No (Revision with minor (QR) Date /2-03- 07-Cross-Disciplinary Revi (QR)NA- Date 1z)l~lDZ (QWN.4- Date /?.-a+-or (Ops Supt) N W (7) Additional Reviews Reviewed By Date Reviewed By Date (8) Temporary Approval (@necessary)

BY (OSWQR) Date BY (QR) Date (9) Approved By 4)& Date \?-Iloit,-,

PEF@ORMANCE (Compare with control copy every 14 calendar days while work is bebagperformcd.)

(IO) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date

' (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure

,

.. .

Completion Verification:

0 Unit 0 Unit 1 0 Unit 2 Unit 3 Procedure performed on what unit?

Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

0 Yes 0 NA Required enclosures attached?

0 Yes NA Data sheets attached, completed, dated, and signed?

Yes 0 NA Charts, graphs, etc. attached, dated, identified, and marked?

0 Yes 0 NA Procedure requirements met?

Verified By (13) Procedure Completion Approved L (14) Remarks (Attach udditional pages, ifneccssary)

Loss of Letdown AP/1/A/ 1700/032 Carryover Steps Page 1 of 1 IF AT AM7TIME:

W .

(4.3) additional makeup flow is desired AND 1A Bleed Transfer Pump is operating ...

(dispatch an operator to close lCS-48)

(4.5) Pzr level 2 260" and letdown CANNOT be established ... (initiate unit shutdown)

(4.6) Pzr level 2 375" ... (trip Rx)

AP/l/A/1700/032 Page 1 of 11 1. Entry Conditions v Unintentional loss of letdown flow 2. Automatic Systems Actions Possible ES Channel 1 and 2 actuation 1"-24 and 1HP-25 will open at 40" LDST level decreasing 1HP-14 swaps fromBBED to NORMAL at 40"LDST level decreasing

3. Immediate Manual Actions None

AP/1/A/I 700/032 Page 3 of 11 .-.

W 4. Subsequent Actions ACTION/EXPECTED RESPONSE RESPONSE KOT OBTAINTD

.. Ensure 1Hp-120 in HAM, and reduce

~~ ~~~~~~~~~

demand to zer ~ ~~ ~~~~~~~ Initiate makeup to LDST with boron concentration 2 RCSboron .

concentration as require .3 - IAAT additional makeup flow is desired, AND 1A Bleed Transfer Pump is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT RECIRC)

(A-1-107. Unit 1 RC Bleed Transfer Pump Rm). Notify Chemistry of the following:

- Current R13S boron sample is needed W for possible unit shutdow Normal letdown line is isolate NOTE Tech Spec 3.4.9 applies when indicated Pzr level 2 260" (corrected value for 285"). IAAT Pzr level 2 260",

AND letdown CANNOT be established, THEN initiate unit shutdown at

= 20%/min per AP/29 (Rapid Unit

' . Shutdown). JAAT Pzr level 2 375".

THEN trip R .1 - Verify CC system in operatio GO TO Step 4.1 .8 - Position the standby HPI pump switch Throttle 1"-31 to establish 12 - 15 gpm SEAL INLET HDR Fm (2)

ii 4.10 - Verify loss of letdown is due to - GO TO Step 4.2 letdown valve or interlock failur AP/l/A/1700/032 ,

Page 5 of 11

-.

-

ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 1 4.1 1 - Verify 1HP-5 close .- Notify SPOC to initiate repairs on failed equipmen . - GO TO Step 4.2 .12 - Close 1HP- ..

4.13 - Close 1HP- .14 - Open 1HP- Dispatch an operator in continuous communication with Control Room to manually open 1"-5 (LETDOWN ISOLATION) (East Pen Rm).

(Tech Spec 3.6.3)

4.15 - WHEN 1HP-5 is open, THEN ensure CC System in operatio .16 - Verify letdown temperature < 135° .- Open 1HP-1 .Ensure the following are closed

- 1HP-8

- lHP-9&11 3.- IF any deborating M in service, THEN perform the following:

A.- Select 1"-14 to NORMP B.- Close 1"-1 . - Select LETDOWN HI TEW INTLK BYP switch to BYPAS .17 - Throttle open 1HP-7 to establish

= 20 gp .18 - WHEN letdown temperature < 130° THEN ensure LETDOWN HI TEW INTLK BYP switch in NORMA .19 - Open 1"- .20 - Adjust 1HP-7 to control desired letdown flo .21 - Re-establish normal makeup through 1HP-12 ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.22 - Venfy 2purification M in servic IF purification M operation is desired,

.. THEN initiate OP/l/A/1103/004 (Soluble Poison Control) to establish desired M operatio .23 - Notify SPOC to initiate repairs on 1"- .24 - Venfy SEAL INLET HDR %OW - GO TO Step 4.2 gp .25 - Re-establish normal RCP seal injection flo .26 - Position the standby HFI pump switch to AUT .27 - W K E N repairs are complete on 1HP-5 (LETDOWN ISOLATION)

(East Pen Rm),

THEN locally turn 1HP-5 handwheel

'd' fully clockwis .28 - EXIT this procedur AP/l/A/1700/032 Page 9 of 11 W

I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 4.29 - WHEN letdown can be re-established, I THEN ensure proper operation of the CC Syste .30 - Close 1"- .31 - Close 1"- .4 4.32 Ensure the following are open:

- 1HP-1

- 1HP-2

- 1HP-3

- lHP-4 4.33 - Verify letdowntemperature < 135O .- Open 1Hp-1 . Ensure the following are closed

- 1HP-8

- lHp-9&11 3.- IF any deborating M in service, THEN perform the following:

A.- Select 1"-14 to NORMA B.- Close 1"-1 .- Select LETDOWN HI TEMP INTLK BYP switch to BYPAS .34 - Ensure 1HP-5 is ope ~ GO TO Step 4.1 .35 - Throttle open 1"-7 to establish

= 20 gp .36 - WHEN letdown temperature < 130"F, THEN ensure LETDOWN HI TEW INTLK BYP switch in NORMA .37 - ODen 1"- ~~ ~

4.38 - Adjust 1HP-7 to control desired letdown flo .39 - Re-establish normal makeup through 1Hp-12 AP/1/.4/1700/032 Page 11 of 11

-

ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.40 - Verify SEAL INLET HDR FLOW - GO TO Step 4.4 .. 12 - 15 gp .41 - Re-establish normal RCP seal injection flo .42 - Position the standbyEE1 pbmp switch to AUTO.

~~

4.43 - Verify purification I X in service. - IF purification M operation is desired, THEN initiate OP/1/PJ1103/004 (Soluble Poison Control) to establish desired IX operatio .44 - EXIT this procedur DIRECTIONS TO SIMULATOR CONSOLE INSTRUCTOR JPM NO.: CRO-83 Directions with SNAP: Recall: SNAP: $O\

2. Unfreeze Simulator, acknowledge alarms and Freeze Simulator Directions without SNAP:

1. Initialize simulator to 100% FULL POWER IC Increase letdown flow with 1HP-7 to trip 1HP-5 closed on high temperature i/ Return 1HP-7 to original position and freeze simulator 4. Acknowledge alarms and Freeze Simulator

CRO-066 fnl Page 1 of 15

REGION II

I NITIAL LIC ENSE EXAMINAT10N JOB PERFORMANCE MEASURE CRO-066 PERFORM REQUIRED ACTIONS FOR RCS PRESSURE I550 PSlG L

CANDIDATE:

EXAMINER:

CRO-066 fnl Page2of15 REGION I1 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Perform required actions for RCS pressure s 550 PSlG Alternate Path:

Yes Facility JPM #:

CRO-066 WA Ratinds):

System: EPEOl1 KIA: EA1.13 Rating: 4.V Task Standard:

Proper ES conditions are verified, using the appropriate procedures; 1B LPI pump is started and LPI Header flows are throttled to between 3000 gpm (Procedural High Flow Limit) and 2800 gpm (LPI Pump Flow Low Statalarm Setpoint).

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant __ Perform X Simulate -

ii References:

EOP End. 5.1 (ES Actuation)

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT __ UNSAT- PerformanceTime: __

CRO-066 fnl Page 3 of 15 SIMULATOR OPERATOR INSTRUCTIONS:

1. Recall Snap 202 i/

2. Import CRO-066 simulator files 3. Place simulator in RUN

CRO-066 fnl Page4of15 ToolslEquiDmentlProcedures Needed:

EOP Encl. 5.1 (ES Actuation)

ii READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

Large break LOCA in progress RCS saturated and RCPs are of ES channels 1 and 2 actuated on Low RCS Pressure and EP/1/A!1800/001 Enclosure 5.1, ES Actuation, has been completed up to Step 1 Additional ES channels have just actuate HPI flow has been verifie INITIATING CUES:

i/ The Procedure Director directs you to continue with Enclosure 5.1 (ES Actuation) at Step 1 CRO-066 fnl Page 5 of 15 START TIME:

Step 1 IAAT either of the following conditions exists: -SAT An ES channel is NOT bypassed, AND RCS pressure reaches actuation setpoint RB pressure reaches actuation setpoint -UNSAT Actuation Setpoint (psig)

1 Associated ES Channel I 1600 (RCS) 1&2 THEN perform Step STANDARD: Candidate checks outstanding IAAT steps and determines that Step 1 applie ES channels 3,4, 5, 6, 7, and 8 have actuated, so candidate goes to Step COMMENTS STEP: Step 2 Verify ail ES channels associated with actuation setpoint have actuated -SAT All Blue ES AUTO lights on All White ES POSITION lights on-UNSAT STANDARD: Candidate goes to RZ module and checks that the Blue ON lights and White POSITION lights for each component on the affected channels are illuminate Candidate should determine that the White light for 1B LPI pump is not lit and then should perform the RNO. Verify digital channel 4 has actuated by observing Tripped light on 1UB Return to SteD 1 COMMENTS:

CRO-066 fnl Page 6 of 15 Step 14-SAT i IAAT flow in 9 LPI Header > 3000 gpm, THEN perform Steps 15 and 1 UNSAT STANDARD: Monitors LPI Flow Train A and B gauges located on 1UB2. Should recognize that flow in A Header is > 3000 gpm and continue to the next ste Continue to Step 15 CUE: LPI Flow Train A will be greater than 3000 gp COMMENTS:

STEP: Step 15 CRITICAL STEP Throttle ILP-17 to maximize header flow 5 3000 gpmlpum SAT STANDARD: Locates ILP-17 on F Z module on 1VB2 and depresses the MANUAL pushbutton for local control of ILP-17.

L NOTE: Candidate may also take MANUAL control of ILP-18 at this tim UNSAT Throttle ILP-17 control switch in the CLOSE direction to obtain 53000 gpmlpum Continue to Step 16 COMMENTS:

CRO-066 fnl Page 7 of 15 I STEP5: Step 16 Throttle 1LP-18 to maximize header flow 5 3000 gpmlpum SAT STANDARD: Candidate:

Observes there is no flow in this heade UNSAT NOTE: 1B LPlP has failed to auto star Continue to Step 17 COMMENTS:

STEP 6: Step 17 Open the following: -SAT IBS-1 IBS-2 -UNSAT STANDARD: Verifies valves 1BS-I and 1BS-2 are OPEN at RZ module Continue to Step 18 COMMENTS:

STEP 7: Step 18 IAAT ES Channels 7& 8 are actuated, -SAT THEN perform Step 1 STANDARD: Verifies Channels 7 & 8 are actuated by observing Statalarms ISA-I/C-I 1, D - I 1 ES CHANNEL 7 (8) TRIP or by the ES digital -UNSAT

"tripped" lights on 1UB Continue to Step 19 COMMENTS:

CRO-066 fnl Page 8 of 15 I-STEP 8: Step 19 Throttle the following to maximize RBS header flow < 1500 gpm for each ooerating header: -SAT IBS-I IBS-2-UNSAT STANDARD: At RZ modules the candidate throttles 16s-1 and 16s-2 as required to maximize RBS header flo The candidate will place 16s-I and 16s-2 to manual at the RZ module by depressing the MANUAL pushbutton. 16 s - I and 1BS-2 will be throttled to adjust RBS flow to between 1500 and 1300 gpm (Procedural High Flow Limit) and (RBS Pump Low Flow Statalarm) by depressing the CLOSE pushbutton on the Rz modul Continue to Step 20 COMMENTS:

STEP: Step 20 IAAT ES Channels 3&4 are actuated, -SAT THEN GO TO Step 2 STANDARD: Verifies Channels 3 & 4 are actuated c.-;erving Statalarms I S A -

-UNSAT 1/C-10, D-10 ES CHANNEL 3 (4) TRIP or by the ES digital tripped lights on 1UB GO TO Step 21 COMMENTS:

CRO-066 fnl Page 9 of 15 STEP IO: Step 21 L Place the following in manual control: -SAT IALPIpump IBLPIpump -UNSAT ILP-17 ILP-18 STANDARD: Components are located on RZ modules on 1VB2 and the MANUAL pushbuttons are depressed for each of the following:

IALPIpump IBLPIpump ILP-17 0 ILP-18 Continue to Step 22 COMMENTS:

L STEP 11: Step 22 Verify one of the following conditions exists: -SAT ILP-17 open 1LP-17 throttled to control flow -UNSAT STANDARD: Recognizes that ILP-17 has been throttled to control flo Continue to Step 23 COMMENTS:

CRO-066 fnl Page 10 of 15 STEP 12: Step 23 Verify= of the following conditions exists:

-SAT ILP-18 open ILP-18 throttled to control flow-UNSAT STANDARD: Verifies ILP-18 OPEN at RZ modul Continue to Step 24 COMMENTS:

STEP 13: Step 24 IAAT w LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pump SAT STANDARD: Verifies RCS pressure is < LPI pump shutoff hea Continue to Step 25 -UNSAT COMMENTS:

STEP 14: Step 25 IAAT RCS pressure is C LPI pump shutoff head, AND 9of the following conditions exist: -SAT power on 1LP-12 power on ILP-17 -UNSAT 1LP-17 locally throttled THEN perform Step 26.

STANDARD: Recognizes that ILP-12 and ILP-17 have power by observing light indication Continue to Step 26 COMMENTS:

CRO-066 fnl Page 11 of 15 STEP 15: Step 26 Verify 1A LPI Pump operating.

L-SAT STANDARD: Observes 1A LPI Pump control switch has red RUN indication and pump amp Continue to Step 27 -UNSAT COMMENTS:

STEP 16: Step 27 IAAT RCS pressure is < LPI pump shutoff head, AND of the following conditions exist: -SAT power on 1LP-14 power on 1LP-18 -UNSAT 1LP-18 locally throttled THEN perform Step 2 STANDARD: Observes control switches for ILP-14 and ILP-18 for red or green light Continue to Step 28 L

COMMENTS:

CRO-066 fnl Page 12 of 15 STEP 17: Step 28 CRITICAL STEP Verify 1B LPI Pump operatin RNO: Attempt to start 1B LPI Pump-SAT STANDARD: Observes 1B LPI Pump control switch has white OFF indication and NO pump amp Locates tHe control switch for 1B LPI pump on 1UB2 and rotates it to the -UNSAT START position. The red RUN lights come on; the white OFF light goes Of The candidate monitors LPI Flow Train A and B gauges located on 1UB2, to ensure flow is less thanlequal to 3000 gpmlpum Candidate will realize that IAAT Step 14 applies (IAAT flow in any LPI header is > 3000 gpm).

Go to Step 14 COMMENTS

~ ~ ~ ~

STEP 18: Step 14 IAAT flow in any LPI header is > 3000 gpm, THEN perform Steps 15 and 16 -SAT STANDARD: Candidate verifies that flow in the "B" LPI header is > 3000 gpm Continue to Step 15 -UNSAT COMMENTS:

STEP 19: Step 15 Throttle ILP-17 to maximize header flow 5 3000 gpdpum SAT STANDARD: Candidate verifies that "A" LPI header flow is < 3000 gprnlpump Continue to Step 16-UNSAT COMMENTS:

CRO-066 fnl Page 130f 15 CRITICAL STEP STEP 20: Step 16 L Throttle 1LP-18 to maximize header flow 5 3000 gpmlpum STANDARD: Locates ILP-18 on RZ module on 1VB2 and depresses the MANUAL -SAT pushbutton for local control of ILP-1 NOTE: This may have been performed earlier in Step Throttle ILP-18 control switch in the CLOSE direction to obtain 5 3000 gPm/Pum UNSAT Return to Step 28 COMMENTS:

END TASK STOP TIME:

CRO-066 fnl Page 14 of 15 CRITICAL STEP EXPLANATIONS:

ii STEP # Explanation 4 This step is necessary to prevent the running out of the LPI pump and causing a loss of DHR capabilit This step starts the idle pump, ensuring adequate flow to the cor This step is necessary to prevent the running out of the LPI pump and causing a loss of DHR capabilit CRO-066 fnl Page 150f 15 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

i/

INITIAL CONDITIONS:

Large break LOCA in progres RCS saturated and RCPs are of ES channels 1 and 2 actuated on Low RCS Pressure and EP/l/N1800/001 Enclosure 5.1, ES Actuation, has been completed up to Step 1 Additional ES channels have just actuate HPI flow has been verifie INITIATING CUES:

The Procedure Director directs you to continue with Enclosure 5.1 (ES Actuation) at Step 1 Enclosure EP/1IA/1800/001 ES Actuation Page 1 of 19 ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 1. -1AAT either of the following conditions exists:

an ES channel is NOT bypassed, AND RCS pressure reaches actuation setpoint RB pressure reaches actuation setpoint Actuation Setpoint Associated ES Channel 550 (RCS) 3&4 3 (RBI 1 , 2 , 3 , 4 , 5 ,& 6 10 (RBI 7&8 2. Verify all ES channels associated with - Ensure affected ES digital channels are actuation setpoint have actuated actuate _ All Blue ES AUTO lights on

-_ All White ES POSITION lights on 3. -Place HPI in manual control.

4. -Verify RCP operatin GO TO Step 6.

5. Ensure the following are open:

-1HP-20-1HP-21 6. -IAAT RCP is operating, - GO TO Step AND ES Channels 5 and 6 actuate, THEN uerform Stem 7 and 8.

7. Ensure the following are open:

-ICC-7

- 1CC-8

- 1LPSW-15

- 1LPSW-6 8. -Ensure 1A 1B Component Cooling Pump is operatin Enclosure EP/1/A/1800/001 ES Actuation Page 2 of 19 IF AT AM! TIME: .. L (1) an ES channel is NOT bypassed RCS pressure reaches actuation setpoint OR RB pressure reaches actuation setpoint.. . (verify associated channels have actuated)

(6) RCP is operating AND ES Channels 5 and 6 actuate.. . (ensure CC and LPSW to RCPs)

Enclosure EP/1/A/1800/001 ES Actuation Pase 3 of 19 L/ ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 9. -Verify all SCMs > 0° GO TO Step 1 . Ensure the following are open: L. - IF both BWST suction valves

- 1HP-24 (IHP-24 and 1HP-25) afe closed,

- 1HP-25 THEN perform the following:

A. Ensure the following are open: (231

- 1LP-6

- 1LP-7

- ILP-9

- 1LP-10

- ILP-15

- 1LP-16 B. - Start 1A or 1B LPI Pum C . -Dispatch an operator to open 1HP-363 (LETDOWN LINE TO LPI P U M P SUCTION BLOCK)

(A-1-119. U1 LPI Hatch Rm, N end).

-.- IF only one BWST suction valve

)

("-24 or 1HP-25)is open, THEN perform the following:

A. -Ensure only two HPI pumps are operatin B. - GO TO Step 1 . -Ensure at least two KPI pumps are operatin . Ensure the following are open:

- 1HP-26

- 1"-27

Enciosure EP/lIA/I SOO/OO 1 ES Actuation Page 4 of 19 IF AT ANY TIME: i/

(1) an ES channel is NOT bypassed & RCS pressure reaches actuation setpoint OR RB pressure reaches actuation setpoint.. . (verify associated channels have actuated)

(6) RCP is operating AND ES Channels 5 and 6 actuate.. . (ensure CC and LPSW to RCPs)

Enclosure EP/1/A/1800/001 ES Actuation Page 5 of 19 ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAIA'ED 13. -1AAT at least two HPI pumps are operating, AND HPI flow in ~IJ header is in the Unacceptable Region of Figure 1, THEN open the following.in the affected header:

Figure 1 Required HPI Flow Per Header 0 100 200 300 400 500 600 Required " IFlmPer Header (gpm)

Enclosure EPI1IN1SOOIOO 1 ES Actuation Page 6 of 19 IF AT ANY TIME: .. L (1) an ES channel is NOT bypassed RCS pressure reaches actuation setpoint OR RB pressure reaches actuation setpoint.. . (verify associated channels have actuated)

(6) RCP is operating AND ES Channels 5 and 6 actuate.. . (ensure CC and LPSW to RCPs)

(13) at least two HPI pumps are operating AND HPI flow in any header is in the Unacceptable Region of Figure 1... (open 1Hp-410 and/or 409)

I - Enclosure EP/1/A/1800/00 1 ES Actuation Page 7 of 19 i/

I ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 14. -IAAT flow in a LPI header is - GO TO Step 1 > 3000 gpm, THEN perform Steps 15 and 1 . -Throttle 1LP-17 to maximize header ._ Throttle 1LP-12to maximize header flow flow I 3000 gpdpum I3000 gpdpum ._ IF 1LP-12 CANNOT be throttled, THEN perform the following:

A. -Stop 1A LPI pum B. Dispatch an operator to perform the following 1. - Close 1LP-17 (IA LP INJECTION) (A-4-402, E Pen Rm) .

2. - Throttle 1LP-17 sixteen turns ope . -Throttle 1LP-18 to maximize header .- Throttle 1LP-14 to maximize header flow W flow I 3 0 0 0 gpdpum I3000 gpdpum . _ IF 1LP-14 CANNOT be throttled, THEN perform the following:

A. -Stop 1B LPI pum B. Dispatch an operator to perform the following 1. - Close 1LP-18 (1ALP INJECTION) (A-4-409, W Pen Rm).

2. - Throttle ILP-18 sixteen turns ope . Open the following: Dispatch an operator to open the affected valve 20 turns:

- 1BS-1

- 1BS-2 - lBS-l(lA RBS HEADER ISOLATION)

(A-4-402, E Pen Rm)

- 1BS-2 (1B RBS HEADER ISOLATION)

(A-4-409, W Pen Rm)

Enclosure EP/l/A/I 800/001 ES Actuation Page 8 of 19 IF AT ANY TIME: b (1) an ES channel is NOT bypassed and RCS pressure reaches actuation setpoint OR RB pressure reaches actuation setpoint... (verify associated channels have actuated)

(6) RCP is operating AND ES Channels 5 and 6 actuate.. . (ensure CC and LPSW to RCPs)

(13) at least two HPI pumps are operating AND HPI flow in any header is in the Unacceptable Region of Figure 1.. . (open 1HP-410 andor 409)

(14) flow in LPI header is > 3000 gpm... (throttle flow)

Enclosure EP/1/A/1800/00 1 ES Actuation Page 9 of 19 ii ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED 1 18. -1AAT ES Channels 7 & 8 are actuated, - GO TO Step 2 TJZEN perform Step 1 . Throttle the following to maximize RBS 1.- IF 1BS-1 CANNOT be throttled header flow I 1500 gpm for operating S 1500 gpm, header: THEN stop 1A RBS Pum BS-1 l. - IF 1BS-2 CANNOT be throttled

- 1BS-2 5 1500 gpm, THEN stOD 1B RBS Pum . -IAAT ES Channels 3 & 4 are actuated, - GO TO Step 5 THEN GO TO Step 2 . Place the following in manual control:

- 1A LPI Pump

- 1B LPI Pump

- 1LP-17

- 1LP-18 ~

22. Verify one of the following conditions 1.- IF power is available to 1LP-12, W exists: THEN dispatch an operator to open

- 1LP-17 open 1LP-17 (1A LP INJECTION) (A-4402,

- 1LP-17 throttled to control flow E Pen Rm).

2.- IF power is NOT available to 1LP-12, THEN dispatch an operator to perform the following:

A. -Close 1LP-17 (1A LP NECTION)

(A-4402, E Pen Rm).

B. -Throttle 1LP-17 sixteen turns ope . Verify one of the following conditions 1.- IF power is available to 1LP-14, exists: THEN dispatch an operator to open

- 1LP-18 open 1LP-18 (1B LP INJECTION) (A-4409,

- 1LP-18 throttled to control flow W Pen Rm).

2. - IF power is NOT available to 1LP-14, THEN dispatch an operator to perform the following:

A. -Close 1LP-18 (1B LP INJECT101 (A-4-409, W Pen Rm).

B. -Throttle 1LP-18 sixteen turns ope Enclosure EP/l/A/I 800/00 1 ES Actuation Page 10 of 19 IF AT AM' TIME: L (1) an ES channel is NOT bypassed RCS pressure reaches actuation setpoint OR RB pressure reaches actuation setpoint.. . (verify associated channels have actuated)

(6) RCP is operating AND ES Channels 5 and 6 actuate.. . (ensure CC and LPSW to RCPs)

(13) at least two HFI' pumps are operating AND HPI flow in any header is in the Unacceptable Region of Figure 1.. . (open 1HP-410 andor 409)

(14) flow in LPI header is > 3000 gpm.. . (throttle flow)

(18) ES Channels 7 & 8 are actuated... (throttle RBS)

Enclosure EP/l/A/l 800/00I ES Actuation Page 11 of 19 L

ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAIhTD I

I CAUTION I24. -IAAT g y LPI pump is operating against LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head. (61 I

a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps. {6,&

25. -IAAT RCS pressure is c LPI pump - GO TO Step 2 shutoff head, AND a of the following conditions exist:

- power on 1LP-12

- power on 1LP-17

- 1LP-17 locally throttled THEN perform Step 2 . -Verify 1A LPI Pump operatin Attempt to start 1A LPI Pum . -IAAT RCS pressure is <: LPI pump - GO TO Step 29.

W shutoff head, AND gg of the following conditions exist:

- power on 1LP-14

- power on ILP-18

- 1LP-18 locally throttled THEN perform Step 2 . -Verify 1B LPI Pump operatin Attempt to start 1B LPI Pum Enclosure EP/1/A/1800/001 ES Actuation Page 12 of 19 IF AT ANY Tim: L (1) an ES channel is NOT bypassed RCS pressure reaches actuation setpoint OR RB pressure reaches actuation setpoint.. . (verify associated channels have actuated)

(6) RCP is operating AND ES Channels 5 and 6 actuate. .. (ensure CC and LPSW to RCPs)

(13) at least two HPI pumps are operating AND HPI flow in any header is in the Unacceptable Region of Figure 1... (open 1Hp-410 andor 409)

(14) flow in a LPI header is > 3000 gpm.. . (throttle flow)

(18) ES Channels 7 & 8 are actuated... (throttle RES)

(24) LPI pump is operating against a shutoff head.. . (at CR SROs discretion, stop affected LPI pumps)

(25) RCS pressure is < LPI pump shutoff head AND power on lLP-12,1LP-17 or 1Lp-17 throttled.. . (verify 1A LPI pump operating)

(27) RCS pressure is < LPI pump shutoff head AND power on lLP-14,1LP-18 or 1LP-18 throttled ... (verify 1B LPI pump operating)

Enclosure EP/1/A/1800/001 ES Actuation Page 13 of 19 ACTIONEXPECTED RESPOKSE RESPONSE XOT OBT.4IKED 29. -1AAT of,the following conditions - G O T 0 Step3 exist:

-. an LPI Pump (1A andlor 1B) fails to start

- an LPI Pump (1A and/or 1B) fails during operation, AND the following conditions exists:

- RCS pressure < LPI pump shutoff head

- 1LP-19 closed

- 1LP-20 closed

- 1BS-1 open OR throttled open

- 1BS-2 open OR throttled open TMSN perform Steps 30 through 3 . -Verify LPI pump operatin IF 1C LPI Pump is available, THEN perform the following:

A. Ensure the following are open on the desired header to provide suction to IC LPI Pump:.

1LP-21 1LP-22 1LP-7 B. - Start IC LPI Pum . Open the following:

- 1LP-9

- 1LP-10 If 1LP-17/18 have NOT been locally throttled, header flow is m at has NOT been locally W

Enclosure EP/~/A11800/001 ES Actuation Page 14 of 19 IF AT ANY TIME: L (1) an ES channel is NOT bypassed RCS pressure reaches actuation setpoint OR RB pressure reaches actuation setpoint.. . (verify associated channels have actuated)

(6) m RCP is operating AND ES Channels 5 and 6 actuate. .. (ensure CC and LPSW to RCPs)

(13) at least two HpI pumps are operating AND HPI flow in any header is in the Unacceptable Region of Figure l... (open 1Hp-410 and/or 409)

(14) flow in LPI header is > 3000 gpm. .. (throttle flow)

(18) ES Channels 7 & 8 are actuated... (throttle RBS)

(24) m LPI pump is operating against a shutoff head. .. (at CR SRO's discretion, stop affected LPI pumps)

(25) RCS pressure is < LPI pump shutoff head AND power on 1LP-12,1LP-17 or 1LP-17 throttled... (verify 1A LPI pump operating)

(27) RCS pressure is c LPI pump shutoff head AM) power on lLP-14,1LP-18 or 1LP-18 throttled ... (verify 1B LPI pump operating)

(29) an LPI Pump (1A andor 1B) fails to start or fails during operation AND RCS pressure is < LPI pump shutoff head AND 1LP-19 closed AND 1LP-20 closed AM) 1BS-1 & 2 are open or throttled open ... (cross-tie or line up and start 1C LPI Pump)

Enclosure EP/1/A/1800/001 ES Actuation Page 15 of 19 ii ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 33. Ensure the following are operating:

-A Outside Air Booster Fan-B Outside Air Booster Fan-3A Outside Air Booster Fan-3B Outside Air BoosterFan 34. - XAAT ES Channels 5 & 6 have actuated, THEN dispatch an operator to establish

= 1000 cfm flow in each PRVS filter train using the following flow controllers (A-6-602, Vent Equip Rm, N wall):

- 1PR-13 (Controller) (Filter 1A)

- 1PR-17 (Controller) (Filter 1B)

35. -Verify

-

RCS pressure is 2 550 psi GO TO Step 3 . Ensure the following are open:

W

- 1CC-7

- 1cc-8

- 1LPSW-15

- 1LPSW-6 37. -Ensure 1A 1B Component Cooling Pump is operatin . -Verify 1CF-1 and 1CF-2 being open is - GO TO Step 4 desire . Ensure the following are open:

- lCF-1

- 1CF-2 40. -Verify IHP-410 close Ensure 1"-120 in manual and close Enclosure EP/~/A/1800/001 ES Actuation Page 16 of 19 IF AT ANY TIME: L (1) an ES channel is NOT bypassed and RCS pressure reaches actuation setpoint OR RB pressure

. reaches actuation setpoint.. . (verify associated channels have actuated)

(6) RCP is operating AND ES Channels 5 and 6 actuate.. . (ensure CC and LPSW to RCPs)

(13) at least two W I pumps are operating AND PI flow in any header is in the Unacceptable Region of Figure l... (open 1Hp-410 and/or 409)

(14) flow in LPI header is > 3000 gpm.. . (throttle flow)

(18) ES Channels 7 & 8 are actuated.. . (throttle RBS)

(24) LPI pump is operating against a shutoff head. .. (at CR SRO's discretion, stop affected LPI pumps)

(25) RCS pressure is < LPI pump shutoff head AND power on lLP-12,1LP-17 or 1LP-17 throttled.. . (verify 1A LPI pump operating)

(27) RCS pressure is < LPI pump shutoff head AM) power on 1LP-14, 1LP-18 or 1LP-18 throttled.. . (verify 1B LPI pump operating)

(29) an LF'I Pump (1A and/or 1B) fails to start or fails during operation AM) RCS pressure is < LPI pump shutoff head AND 1LP-19 closed AND 1LP-20 closed AND 1BS-1& 2 are open or throttled open ... (cross-tie or line up and start 1C LPI Pump)

(34) ES Channels 5 & 6 have actuated.. . (establish PRVS flow)

Enclosure 5.1 EP/ 1/A/1800/001 ES Actuation Page 17 of 19 41. -Dispatch an operator to perform Encl (Placing RB Hydrogen Analyzers In Service). (PS)

42. -Ensure Chemistry has been notified to prepare for caustic addition per CP/1&2/A/2002/005 post Accident Caustic Injection Into LPI System).

43. -Ensure makeup to the LDST is secure . -Ensure ES channel 1 through 4 components that can be operated from the Control Room are in desired positio . Place the following in manual control:

- 1A LPI Pump

' B LPI Pump 46. -Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON.

u 47. -WHEN ES channels 5 & 6 have actuated, THEN ensure ES Channel 5 & 6 components that can be operated from the Control Room are in desired positio . -WHEN ES channels 7 & 8 have actuated, THEN ensure ES Channel 7 & 8 components that can be operated from the Control Room are in the desired positio . -WHEN CR SRO approves, THEN EXIT this enclosur Enclosure EP/l/A/l 800/001 ES Actuation Page 18 of 19 IF AT ANY TIME: .. L (1) an ES channel is NOT bypassed RCS pressure reaches actuation setpoint OR RB pressure reaches actuation setpoint.. . (verify associated channels have actuated)

(6) RCP is operating AND ES Channels 5 and 6 actuate.. . (ensure CC and LPSW to RCPs)

(13) at least two PI pumps are operating AND PI flow in i n y header is in the Unacceptable Region of Figure l... (open 1Hp-410 andor 409)

(14) flow in LPI header is > 3000 gpm.. . (throttle flow)

(18) ES Channels 7 & 8 are actuated... (throttle RBS)

(20) ES Channels 3 & 4 are actuated.. . (GO TO path for proper LPI actuation)

.

Enclosure EP/1/,4/1800/001 ES Actuation Page 19 of 19

\-

ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAIhXD 50. Start the following:

-A Outside Air Booster Fan-B Outside Air Booster Fa . Notify Unit 3 to start the following:

-3A Outside Air Booster Fan-3B Outside Air Booster Fan 52. -Verify 1CF-1 and 1CF-2 being open is - GO TO Step 5 desire . Ensure the following are open:

-1CF-1-1CF-2 .

54. -Verify 1HP-410 close Ensure IKP-120 in manual and closed.

W 55. -Dispatch an operator to perform Encl (Placing R B Hydrogen Analyzers In Service). (PS)

56. -Notify Chemistry to prepare for caustic addition per CP/1&2/,4/2002/005 (Post Accident Caustic Injection Into LPI System).

57. -Ensure makeup to the LDST is secure . -Ensure ES channel 1 & 2 components that can be operated from the Control Room are in desired positio . -WHEN CR SRO approves, THEN EXIT this enclosur CRO-013 fnl Page 1 of 12

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE CRO-013 ALIGN MDEFDWP SUCTION TO THE HOTWELL AND FEED THE STEAM GENERATORS i/ CANDIDATE:

EXAMINER:

CRO-013 fnl Page 2 of 12

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Align MDEFDWP suction to the hotwell and feed the steam generators.

Alternate Path:

No Facility JPM #

CRO-013 KIA Ratinak):

System: APE054 KIA: AA1.01 Rating: 4.514.4 Task Standard:

The MDEFDWPs are aligned to the hotwell and providing flow to the SG's within limits correctly per procedure.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant - Perform Simulate -

References:

EOP Enclosure 5.9 (Extended EFDW Operation)

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT -UNSAT - Performance Time: -

CRO-013 fnl Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS:

1. Recall Snap 203 L./

2. Import CRO-013 files 3. Place simulator in RUN

CRO-013 fnl Page 4 of 12 ToolslEquiDmentlProcedures Needed:

EOP Enclosure 5.9 (Extended EFDW Operation)

u READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

Unit 2 reactor has tripped due to a loss of Main FDW Main FDW is not expected back for several hour The TDEFDWP is unavailabl UST makeup flow capability has been los Actions of the EOP have been complete Enclosure 5.9, Extended EFDW Operation has been completed up to Step 5 Steps 1, 2, and 3 of Enclosure 5.24, Operation of the ADVs are complet INITIATING CUES:

i/ The Procedure Director directs you to align the MDEFDWP suction from the Hotwell using EOP Enclosure (Extended EFDW Operation) beginning at Step 5 CRO-013 fnl Page 5 of 12 START TIME:

Note: Cues are provided for conducting JPM in the plant control roo STEP: Step 51 CRITICAL STEP WHEN UST level is c 3 feet, -SAT THEN ensure all CBPs stopped STANDARD: Monitors UST level by one or more of the following ways and determines that level is less than three feet: -UNSAT OAC UST B LEVEL meter on 2AB-1 UST A LEVEL meter on 2AB-3 UST LEVEL chart recorder on 2VB-1 Locates Condensate Booster Pumps A, B, and C switches on 2AB1 Stops fl Condensate Booster Pumps by rotating the switches to the OFF positio Booster Pump red run light goes off and white stop light comes on for pumps secure Cue: Indicate UST level is 2.8 feet UST A/B LEVEL meter on ?AB-?.

Cue: Indicate any pumps in auto start when CBPs are stoppe COMMENTS:

STEP: Step 52 CRITICAL STEP Ensure fl HWPs stopped-SAT STANDARD: Locates Hotwell Pump A, B, and C switches on 2AB1 Stops fl Hotwell Pumps by rotating the switches to the OFF positio UNSAT Hotwell Pump red run light goes off and white stop light comes on for pumps secure Cue: Indicate Hotwell Pump A, B, and C are off by red run lights of Cue: Indicate anypumps in auto start when HWPs are stopped.

COMMENTS:

CRO-013 fnl Page 6 of 12 1-3: Step 53 i Dispatch an operator with a safety harness to 2C-573 (MD EFDWPS -SAT SUCTION FROM UST) to standby until further notic STANDARD: Dispatches NE0 to 2C-57 UNSAT Cue: Indicate N E 0 has been dispatched to 2C-57 COMMENTS:

STEP: Step 54 CRITICAL STEP Open 2V-186 (VACUUM BREAKER)

-SAT STANDARD: Locates 2V-186 on 2AB1 and rotates the switch in the open directio The red open light comes on and the green closed light goes of UNSAT Cue: Indicate 2V-186 is open by red open light illuminate COMMENTS:

L STEP: Step 55 Stop main vacuum pumps -SAT STANDARD: Locates main vacuum pump switches on 2AB3 and verifies all three pumps indicate OF UNSAT Cue: Indicate dl Main Vacuum Pumps OFF by green "off"1ights illuminate COMMENTS:

CRO-013 fnl Page 7 of 12 1-6: Step 56 L Close the following: -SAT 2MS-47 (MS to CSAEs)

2AS-40 (CSAE AUX STEAM SUPPLY)

-UNSAT STANDARD: Locates 2MS-47 on 2AB1 and rotates the switch in the closed directio The green closed light comes on and the red open light goes of Locates 2AS-40 on 2AB1 and verifies the green closed light on and the red open light of Cue: Indicate 2MS-47 and 2AS-40 are closed by green c1osedlights illuminate COMMENTS:

-7: Step 57 CRITICAL STEP IAAT UST level < I foot, AND IC-573 is open, -SAT THEN stop all EFDW pumps L

STANDARD: Monitors UST level and if UST level is < I foot both MDEFDW -UNSAT Pumps if 2C-573 is open by rotating pump switch to the off position and verifying red run light goes off and white stop light comes o Cue: Indicate UST level is .8 feet U S T A B LEVEL meter on 2AB-I and when candidate stops both MDEFDW Pumps indicate they are off by red run light of COMMENTS:

CRO-013 fnl Page 8 of 12 Step 58 CRITICAL STEP i WHEN vacuum is broken, THEN locally close 2C-573 (MD EFDWP Suction from UST) -SAT NOTE: MDEFWP flow is limited to < 440 gpmlpump when suction is aligned to the hotwell-UNSAT STANDARD: Observes vacuum gauge on 2UB2 and determines that vacuum is broken and then contacts an NE0 to close 2C-57 Ensures MDEFDWP flow c 440 qpm/pumD by observing MDEFDWP flow gauges on 2UB CUE: Inform student that 2C-573 is close CUE: Inform student that MDEFDWP flow gauges on 2UB1 indicate 200 gpm/pum COMMENTS:

L :9- Step 59 CRITICAL STEP Restart MDEFWPs that were stopped due to UST level < I foo SAT STANDARD: Pumps are started if required. Step is N/A if the pumps were not secure UNSAT Cue: When candidate starts both MDEFDW Pumps indicate that red run lights are illuminate COMMENTS:

CRO-013 fnl Page 9 of 12 I STEPIO: Step 60 Ensure TDEFDWP is NOT operating.

i -SAT STANDARD: Determine the TDEFDWP is not availabl UNSAT Note: The TDEFDWP is 00 COMMENTS:

STEP 11: Step 61 Locally close 26-157 (TD EFDWP Suction from UST). -SAT STANDARD: Dispatches an NE0 to close 2C-15 UNSAT CUE: Inform student that 2 6 1 5 7 is close COMMENTS:

L STEP 12: Step 62 OPEN 2C-391 (TDEFDWP Suction from Hotwell) -SAT STANDARD: Locates the control for 2C-391 on 2VB3 and rotates the switch in the OPEN direction. Red open light comes on, green closed light goes off. -UNSAT Continue to Step 63 Cue: Indicate Red open light comes on, green closed light goes of COMMENTS:

CRO-013 fnl Page 10 of 12 I STEP 13: Step 63 IAAT TDEFDWP operation is desired, -SAT AND hotwell level is >I",

THEN start TDEFDW UNSAT STANDARD: Determine the TDEFDWP is not availabl Note: The TDEFDWP is 00 COMMENTS:

STEP 14: Step 64 Dispatch an operator to open 2C-188 (HOTWELL Emergency Makeup #I -SAT Control Bypass).

STANDARD: Dispatches an NE0 to open 2C-188-UNSAT CUE: Inform student that 2C-188 is ope COMMENTS:

STEP 15: Step 65 Notify TSC to evaluate methods to maintain secondary inventor STANDARD: Notifies TSC to evaluate methods to maintain secondary inventor UNSAT CUE: Inform candidate that the TSC will evaluate methods to maintain secondary inventor COMMENTS:

END TASK STOP TIME:

CRO-013 fnl Page 11 of 12 CRITICAL STEP EXPLANATIONS:

i/

STEP # Explanation 1 STOP all CBPs to prevent damage to the MDEFDWP by decreasing NPS STOP all HWPs to prevent damage to the MDEFDWP by decreasing NPS Condenser vacuum must be broken thus increasing the NPSH to the EFDWPs This prevents EFDWP damage due to not meeting suction head requirements when Hotwell level is < If Stopping Emergency Feedwater Pumps prevents possible air introduction into the pumps suction, thus preventing pump cavitation and possible pump damag Closing 2C-573 prevents air introduction into the pumps suction, thus preventing pump cavitation and possible pump damag Restart of MDEFWPs is essential regaining feed to the SGs if feed had been secure CRO-013 fnl Page 12 of 12 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

u INITIAL CONDITIONS:

Unit 2 reactor has tripped due to a loss of Main FDW Main FDW is not expected back for several hour The TDEFDWP is unavailabl UST makeup flow capability has been los Actions of the EOP have been complete Enclosure 5.9, Extended EFDW Operation has been completed up to Step 51 Steps 1,2, and 3 of Enclosure 5.24, Operation of the ADVs are complet INITIATING CUES:

The Procedure Director directs you to align the MDEFDWP suction from the Hotwell using EOP Enclosure (Extended EFDW Operation) beginning at Step 5 Enclosure EP/2/N1 800/001 Extended EFDW Operation Page 1 of 17 C%

326

'E+* GGl i/

ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED 1. - Monitor EFDW parameters on EFW graphic displa . - IAAT UST level is < 4',

THEN GO TO Step 4 . - IAAT feeding both SGs with one - GO TO Step MDEFDWP is desired, THEN perform Steps 4 - . Ensure EFDW control valve on SG with NO EFDW flow is in MANUAL. and closed

.'.

5. Locally open the following:

- . 2FDW-313 (2A JZDW LINE DISCH TO 2A S/G X-CONN)

v (T-l,5'N Of M-39, 12' UP)

-2FDW-314 (2B EFDW LINE DISCH TO 2B S/G X-CONN)

(T-l,2'N of M-31,6' UP)

6. - Ensure a MDEFDWP is operatin . Throttle EFDW control valve on SG with NO EFDW flow to establish appropriate level per Rule 7 (SG Feed Control):

8. Perform the following as required to maintain UST level > 7':

- Makeup with demin wate Ensure CST pumps are in AUT Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 2 of 17 IF AT ANY TIME:

(2) UST level is < 4'... (prepare to swap EFDW suction to hotwell)

(3) feeding both SGs with one MDEFDWP is desired ... (cross-tie)

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 3 of 17 I ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAIhXD 9. - IAAT the following conditions exist:

-Rapid cooldown NOT in progress-MDEFDWP operating for each available SG-EFDW flow in &e header

< 600 gpm THEN place TDEFDWP switch in PULL TO LOC . ~~ Verify TDEFDW Pump operatin GO TO Step 13.

_

11. - Ensuie 2LPSW-137 is ope _ _ I _ _ _

12. - Ensure EMER FDWPT BRNG OIL COOLING PUMP is operatin __-

13. - IAAT UST level CANNOT be maintained > 7',

THEN dispatch an operator to close 2C-186 (HOTWELL EMERGENCY MAKEUP #1 CONTROL INLET)

(T-1, S of E-31). _-

14. - Verify HWP operatin GO TO SteD 2 . - Verify CBP operatin GO TO Step 3 . - Verify 2C CBP operating+z) 1.- Ensure only one CBP is operating 2.- GO TO Step 1 . Ensure the following stopped 112)

- 2A CBP

- 2B CBP 18. - Ensure only one HWP is operatin . - GO TO Step 3 Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 4 of 17 IF AT ANY TIME:

(2) UST level is < 4'. .. (prepare to swap EFDW suction to hotwell)

(3) feeding both SGs with one MDEFDWP is desired.. . (cross-tie)

(9) rapid cooldown NOT in progress AND MDEFDWP operating for each available SG AND EFDW flow in header is < 600 gpm.. . (place TDEFDWP in PULL TO LOCK)

(13) UST level CANNOT be maintained > 7'... (dispatch an operator to close 2C-186)

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 5 of 17 following is met:

An engineering evaluation is performed EFDW is NOT available and secondan, uumi are needed to restore feed to a SG. (17)

20. - Verify & condensate l flow has NOT 1.- IF Engineering approves starting a HWP been lost for > 25 minute OR secondary pumps are needed to immediately restore SG feed, THEN GO TO Step 2 . - Notify CR SRO to evaluate starting Main Vacuum Pumps per AP127 (Loss of Condenser Vacuum).

3.- GO TO Step 6 . - Place HWP control switches in OFF.

W 22. - Place all CBP control switches in OF . - Dispatch an operator to start &l CBP Aux Oil Pumps. (T-1/J-33)

24. Close the following:

- 2FDw-4

- 2FDW-9 25. Ensure Main FDWP Aux Oil Pumps operating:

- 2A FDWP AUXILJARY OIL PUMP

- 2B FDWP AUXlLIARY OIL PUMP 26. Place the following in MANUAL close:

-2FDW-53-2FDW-65 2 ~ Ensure 2C-10 is close . - Using a plant page, clear TB Basement and TB third floor of non-essential personne . -WHEN notified that &l CBP Aux Oil pumps are operating, THEN continu Enclosure EP12IA/1800/001 Extended EFDW Operation Page 6 of 17 IF TANYTIME: i-(2) UST level is e 4'. .. (prepare to swap EFDW suction to hotwell)

(3) feeding both SGs with one MDEFDWP is desired.. . (cross-tie)

(9) rapid cooldown NOT in progress AND MDEFDWP operating for each available SG AND EFDW flow in each header is < 600 gp . (place TDEFDWP in PULL TO LOCK)

(13) UST level CAhWOT be maintained > 7'... (dispatch an operator to close 2C-186)

'.

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 7 of 17 L

ACTlONlEXPECTED RESPONSE RESPONSE NOT OBTAINED 31. - Throttle 2C-10 controller 10% ope . - WHEN FWP SUCT HDR PRESS (2VJ33) is 2 100 psig,

~ ~~

THEN ouen 2C-1 . Establish 1000-1200 gpm total recirc flow with one of the following:

-2FDW-53-2FDW-65

'. 34. - WHEN five mnutes has elapsed, THEN GO TO Step 3 _- -

-35. - Ensure tWO H W P s operatin __

36. - Start the 2C CBP.{IZ) - Start one available CB . - Stop one operating HWP.____ -

u 38. - Ensure control switch for one idle HWP is in AUTO. -

39. - Ensure control switch for one idle CBP is in AUT . Ensure the following in MANUA FDW-53-T

-~-

-2FDW-65 41. Establish 2 2300 gpm total recirc flow with

-

one of the following:

-2FDW-53 2FDW-65 42. - IAAT UST level CANNOT be maintained > 8',

THEN locally open 2C-209 (SEAL WATER SUPPLY HEADER)

(T-I, E Of 5-32, 12' UP).

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 8 of 17 IF AT ANY TIME:

(2) UST level is < 4'. .. (prepare to swap EFDW suction to hotwell)

(3) feeding both SGs with one MDEFDWP is desired ... (cross-tie)

(9) rapid cooldown NOT in progress AND MDEFDWP operating for each available SG AND EFDW flow in &header is < 600 gpm.. . (place TDEFDWP in PULL TO LOCK)

(13) UST level CANNOT be maintained > 7'. .. (dispatch an operator to close 2C-186)

(42) UST level CANNOT be maintained > 8'. .. (locally open 2C-209)

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 9 of 17

._ ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAIKED 43. - IAAT UST level increases > l l ' ,

THEN perform the following as required:

-Throttle demin water-Locally throttle 2C-188 (HOTWELL EMERG MAKEW #1 CONTROL BYPASS) (T-1, between E-31 and F-3 1)

44. Verify the following are closed - GO TO Step 4 FDw-4

- 2FDW-9 45. Ensure the following are closed with the switches in CLOSE:

- 2FDW-33

- 2FDW-31

- 2FDw-42 W

- 2FDw-40 _-

46. Locally open the following:

- 2FDW-5 (2A FDWP DISCHARGE BYPASS) (T-1, 1 0 N of 2A FDW Pump, 15' up, above SGFDW Panel 2SGFP)

- 2FDW-10 (2B FDWP DISCHARGE BYPASS) (T-l,5' N Of D-30, 15' Up)

47. - WHEN FWP DISCH HDR PRESS (2VB3) is approximately equal to either of the following:

02A1014 (FDWP 2A DISCHARGE PRESS)

02A1391 (FDWP 2B DISCHARGE PRESS)

THEN open the following:

-2FDW -4

-

-2FDW-9 ___-

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 10 of 17 IF AT ANY TIME:

(2) UST level is < 4'... (prepare to swap EFDW suction to hotwell)

(3) feeding both SGs with one IvlDEFDWP is desired.. . (cross-tie)

(9) rapid cooldown NOT in progress AND MDEFDWP operating for each available SG AND a

EFDW flow in headers is < 600 gp . (place TDEFDWP in PULL TO LOCK)

(13) UST level CANNOT be maintained > 7'. .. (dispatch an operator to close 2C-186)

(42) UST level CANNOT be maintained > 8'. .. (locally open 2C-209)

i (43) UST level increases > 11'... (locally throttle 2C-188 as required)

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 11 of 17 i/

ACTIONRXPECTED RESPONSE RESPONSE NOT OBTAINED 1 48. Locally close the following:

- 2FDW-5 (2A FDWP DISCHARGE BYPASS) (T-1,lO' N of 2A FDW Pump, 15' up, above SGFDW Panel 2SGFp)

- 2FDW-10 (2B FDWP DISCHARGE BYPASS) (T-l,5' N Of D-30, 15' UP)

49. - WHEN UST level is < 4',

THEN dispatch two operators to perform Encl 5.24 (Operation of the ADVs) in preparation for loss of vacuum. (PS)

50. - Verify power available to 2V-18 Dispatch an operator with a safety harness to 2V-186 (VACUUM BREAKER)

(T-3, catwalk at 2C2 waterbox).

-

51. - WHEN UST level is < 3',

THEN ensure CBPs stopped.

L.,

52. - Ensure &l HWPs stoppe . - Dispatch an operator with a safety harness to 2C-573 (MD EFDWPS SUCTION FROM UST)

(T-1, W of 2-31, 8' above floor).

54. - Open 2V-18 Notify operator to open 2V-186 (MAIN CONDENSER VACUUM BREAKER)

(T-3, catwalk at 2C2 waterbox).

55. - Stop &main l vacuum pump . Close the following: Dispatch an operator to close the following:

- 2MS-47 - 2MS-49 (2A CSAE STEAM SUPPLY)

- 2AS-40 (T-3, F-29)

- 2MS-58 (2B CSAE STEAM SUPPly)

(T-3, G-29)

- 2MS-67 (2C CSAE STEAM SUPPLY)

(T-3, N of H-29)

57. - IAAT UST level is < l',

L/ A h 4 2C-573 (MD EFDWPS SUCTION FROM UST) is open, THEN stop &l EFDW

___- - pump ..-

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 12 of 17 IF AT ANY TIME:

(3) feeding both SGs with one MDEFDWP is desired.. . (cross-tie)

(9) rapid cooldown NOT in progress AND MDEFDWP operating for each available SG AND EFDW flow in &header is < 600 gpm ... (place TDEFDWP in PULL TO LOCK)

,

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 13 of 17

\_

RESPONSE NOT OBTAINED h4DEFDW flow is limited to < 440 gpdpump when suction is aligned to the hotwell (2C-573 closed).

I 58. - WHEN vacuum is broken, THEN locally close 2C-573 (MD EFDWPS SUCTION FROM UST).

59. - Restart & h4DEFDWPs that were stopped due to UST level < 1'.

60. ~ Ensure TDEFDWP is NOT ooeratin ' 61. - Locally close 2C-157 (TD EFDWP SUCTION FXOM UST)

(T-I, N of C-36).

62. - Open2C-391 - Locally open 2C-391 (TD EFDWP SUCTION FROM HOTWELL)

(T-l/C-36).

63. - IAAT TDEFDWP operation is desired, AND hotwell level is > I",

THEN start TDEFDW . - Dispatch an operator to open 2C-188 (HOTWELL EMERG MAKEUP #1 CONTROL BYPASS)

(T-1. W Of E-31). (181 65. - Notify TSC to evaluate methods to maintain secondan) inventor . - IAAT hotwell level is 5 l",

THEN stop & EFDWP . - WHEN directed by CR SRO, THEN EXIT this enclosur Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 14 of 17 IF AT ANY TIME:

(3) feeding both SGs with one MDEFDWP is desired.. . (cross-tie)

(9) rapid cooldown NOT in progress AND MDEFDWP operating for each available SG AND EFDW flow in header is 600 gpm.. . (place TDEFDWP in PULL TO LOCK)

Enclosure EP/2/AJ1800/001 Extended EFDW Operation Page 15 of 17

..

ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED 1 68. - WHEN UST level is < 4, THEN dispatch two operators to perform Encl5.24 (Operation of the ADVs) in preparation for loss of vacuum. (PS)

69. - Verify power available to 2V-18 Dispatch an opeFator with a safety harness to 2V-186 (VACUUM BREAKER)

(T-3, catwalk at 2C2 waterbox).

-.__-

70. - WHEN UST level is < 3',

THEN ensure CBPs stoppe ,

-71. - Ensure HWPs stoppe . - Dispatch an operator with a safety harness to 2C-573 (MD EFDWPS SUCTION FROM UST)

(T-1, W of E-31, 8' above floor).

73. - Open 2V-18 Notify operator to open 2V-186 (MAIN L CONDENSER VACUUM BREAKER)

(T-3, catwalk at 2C2 waterbox).-

74. - Stop & l vacuum pump main 75. Close the following: Dispatch an operator to close the following:

- 2MS-47 - 2MS-49 (2A CSAE STEAM SUPPLY)

- 2AS-40 (T-3/F-29)

- 2MS-58 (2B CSAE STEAM SUPPly)

(T-3/G-29)

- 2MS-67 (2C CSAE STEAM SUPPLY)

(T-3, N of H-29)

76. - IAAT UST level is < l',

AND 2C-573 (h4D EFDWPS SUCTION FROM UST) is open, THEN stop & l EFDW pump MDEFDWF' flow is limited to e 440 gpdpump when suction is aligned to the hotwell (2C-573 L

THEN locally close 2C-573 (MD EFDWPS SUCTION FROM UST).

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 16 of 17 IF AT ANY TIME:

(3) feeding both SGs with one MDEFDWP is desired.. . (cross-tie)

(9) rapid cooldown NOT in progress AM> MDEFDWP operating for each available SG AND EFDW flow in header is < 600 gpm.. . (place TDEFDWP in PULL TO LOCK)

Enclosure EP/2/A/1800/001 Extended EFDW Operation Page 17 of 17 L

ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAIAXD 78. - Restart & l h4DEFDWPs that were stopped due to UST level < . - Ensure TDEFDWF is NOT operatin . - Locally close 22-157 (TD EFDWF SUCTION FROM UST)

(T-1, N of C-36).

81. - Open 22-391 - Locally open 2C-391 (TD EFDWP SUCTION FROM HOTWELL)

(T-1/C-36).

8 IAAT TDEFDWP operation is desired, AND hotwell level is > l, THEN start TDEFDW . - Dispatch an operator to open 2C-188 (HOTWELL EMERG MAKEUP #1 CONTROL BYPASS)

(T-1. W Of E-31). i i x l ii 8 Notify TSC to evaluate methods to maintain secondary inventor . - IAAT hotwell level is 2 l, THEN stop gJl EFDWF . - WHEN directed by CR SRO, THEN EXIT this enclosur CRO-201 fnl Page 1 of 16

REGION II

INITIAL LICENSE EXAMINATION PERFORMANCE MEASURE CRO-201 Restart RCP CANDIDATE:

EXAMINER:

CRO-201 fnl Page 2 of 16

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE u Task:

Restart RCP Alternate Path:

No Facilitv JPM #

New KIA Ratinds):

System: 003 K/A: A4.06 Rating: 2.9*/ Task Standard:

1 A l RCP is started correctly per procedur Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant - Perform Simulate -

i/ References:

EOP Enclosure 5.6 (RCP Restart)

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT -UNSAT - Performance Time: ___

~

CRO-201 fnl Page 3 of 16 SIMULATOR OPERATOR INSTRUCTIONS:

1. Recall Snap 206

-' 2. Place simulator in RUN

CRO-201 fnl Page 4 of 16 ToolslEquiDmentlProcedures Needed:

EOP Enclosure 5.6 (RCP Restart)

L READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

Reactor tripped from 100% power I T A and 1TB did not auto transfer to CT-1 on the trip resulting in tripping of all RCPs Power has been restored to I T A and 1TB EOP Subsequent Action in progress at Step 4.46 INITIATING CUES:

SRO directs you to initiate EOP Enclosure 5.6 (RCP Restart) to start 1Al RCP.

i/

CRO-201 fnl Page 5 of 16 START TIME:

STEP: Step 1 Verify ICC tab NOT in progres SAT STANDARD: Determine ICC tab NOT in progres UNSAT Cue: If asked, inform candidate that the ICC tab NOT in progress, COMMENTS:

2- Step 2 Verify NO RCPs operatin SAT STANDARD: Verify NO RCPs operating by observing RCP red run light off and " 0 amps indicated on I A B I . -UNSAT COMMENTS:

STEP: Step 3 Verify all the following: -SAT Boiler condenser cooling has NOT occurred 0 Nat Circ cooling exists in at least one RCS loop-UNSAT STANDARD: Candidate should determine that Boiler condenser cooling has NOT occurre Candidate should determine that Nat Circ cooling exists in at least one RCS loop by observing any of the following: SG pressure, core AT, CETCs, feeding SGs.and TBV positio Cue: If asked, indicate that Boiler condenser cooling has NOT occurre COMMENTS:

CRO-201 fnl Page 6 of 16 STEP: Step 4 Ensure all SCMs are > 0° SAT STANDARD: Determine all SCMs are > 0°F by observing SCM on the ICCM located on 1UB UNSAT COMMENTS:

STEP: Step 5 Ensure adequate RCP NPSH per Encl 5.18 (PiT Curves). -SAT STANDARD: Obtain EOP Encl 5.18 (PiT Curves) and determine that adequate RCP NPSH exist UNSAT COMMENTS:

STEP: Step 6 Verify any of the following exist: -SAT Either hot leg level < 597" Either train of vessel head level < 171" RVLlS indications NOT available AND NO RCPs operating STANDARD: Determine step not met. Both hot leg levels > 597" and both trains of vessel head level indicate > 171". RVLIS indications are availabl Continue to Step 6 RNO COMMENTS:

CRO-201 fnl Page 7 of 16-7: Step 6 RNO Ensure Pzr level > 100: [ I 8 0 acc]. -SAT GO TO Step 8 STANDARD: Monitor Pzr level on 1UB1 and determine level is > 100"

-UNSAT Continue to Step 8 COMMENTS:

STEP: Step 8 Verify HPI CD tab NOT in progres SAT STANDARD: Determine HPI CD tab NOT in progres UNSAT Cue: If asked, inform candidate that the UP/CD tab NOTin progress.

COMMENTS:

m: Step 9 Ensure the following are closed: -SAT IRC-155 IRC-156 IRC-157 -UNSAT IRC-158 IRC-159 IRC-160 STANDARD: Determine the above valves are all closed by observing their light indications on 1UB2 are de-energized. This indicates that they have not been opened.

Cue: If asked, valves have not been opened.

>OMMENTS:

CRO-201 fnl Page 8 of 16 STEP I O : Step 10 Verify Pzr level is < 375: [340 acc]. -SAT STANDARD: Monitor Pzr level on 1UB1 and determine level is < 37 UNSAT COMMENTS:

STEP 11: Step 11 Verify 1RC-4 is NOT closed to isolate leakage past POR SAT STANDARD: Observe 1RC-4 position indication on 1UBI and determine 1RC-4 is open by red light illuminate UNSAT COMMENTS:

STEP 12: Step 12 Ensure 1RC-4 is ope SAT STANDARD: Observe 1RC-4 position indication on 1UBI and determine 1RC-4 is open by red light illuminate UNSAT COMMENTS:

STEP 13: Step 13 Ensure IRC-1 is in manual and close SAT STANDARD: Locate 1RC-1 on 1UBI and press close. Verify the blue AUTO light goes out and the white close light illuminate UNSAT COMMENTS:

CRO-201 fnl Page 9 of 16 STEP 14: Step 14 Ensure the following are open: -SAT ILPSW-6 ILPSW-15-UNSAT STANDARD: Verify 1LPSW-6 and 1LPSW-15 are open on the RZ modules located on 1VB2.

COMMENTS:

STEP 15: Step 15 Ensure the following are open for each RCP to be started using OAC I CRITICALSTEP 1 graphic LPSO2:

1LPSW-7&8 (1Al)

-UNSAT STANDARD: Open 1LPSW-7&8 by rotating the switch in the open direction and verify they both are open on the OAC by calling up graphic LPSO2.

COMMENTS:

STEP 16: Step 16 Ensure = 8 gpm seal injection for each RCP to be starte SAT 1Al STANDARD: Ensure 8 gpm seal injection for 1Al RCP by observing seal injection -UNSAT flow meter on 1VB3.

COMMENTS:

CRO-201 fnl Page 10 of 16 STEP 17: Step 17 L

Ensure the following are open for each RCP to be started: -SAT IHP-228 (1Al)

STANDARD: Verify 1HP-228 open by observing red open light illuminated on 1VB UNSAT COMMENTS:

STEP 18: Step 18 Ensure the following are open: -SAT IHP-20 IHP-21-UNSAT STANDARD: Verify 1HP-20 open by observing indication on the RZ module located on 1VB2. Verify IHP-21 open by observing red open light illuminated on 1UB COMMENTS:

'ii

~

STEP 19: Step 19 Verify CC TOTAL FLOW 575 gp SAT STANDARD: Verify CC TOTAL FLOW ? 575 gpm by observing gauge located on 1AB UNSAT COMMENTS:

CRO-201 fnl Page 11 of 16 STEP 20: Step 20 L Verify HPI CD tab is NOT in progres SAT STANDARD: Determine HPI CD tab is NOT in progres UNSAT Cue: If asked, inform candidate that the HPI CD tab NOT in progress, COMMENTS:

STEP 21 : Step 21 Verify ICC tab is NOT in progress -SAT STANDARD: Determine ICC tab is NOT in progress-UNSAT Cue: If asked, inform candidate that the ICC tab NOT in progres COMMENTS:

L STEP 22: Step 22 IAAT any SCM is = 0°F due to RCP restart, -SAT THEN ensure full HPI flow per Rule 6 (HPI).

STANDARD: Candidate should indicate that if any SCM is = 0°F due to RCP restart, -UNSAT then they would ensure full HPI flow per Rule 6 (HPI).

ZOMMENTS:

CRO-201 fnl Page 12 of 16 STEP 23: Step 23 c IAAT any SCM is = 0°F for ? 2 minutes following RCP restart, -SAT THEN GO TO LOSCM ta STANDARD: Candidate should indicate if any SCM is = 0°F for 7 2 minutes following -UNSAT RCP restart they would inform the SRO to go to the LOSCM ta COMMENTS:

CRITICAL STEP STEP 24: Step 24 Start AC or DC lift oil pump for an RCP to be starte SAT STANDARD: Start AC or DC lift oil pump for the 1Al RCP by locating switch on I A B I and placing the switch in the start position. The red light should come on and the white light should go of UNSAT COMMENTS:

b STEP 25: Step 25 CRITICAL STEP WHEN computer alarm for low lifl oil pump discharge pressure clears for RCP to be started,

-SAT THEN start RC STANDARD:

-UNSAT Monitor computer alarms on the OAC Alarm screen located on 1UB2 and when low lifl oil pump discharge pressure alarm clears, start the 1Al RCP by rotating the switch located on l A B l clockwise. The red light should illuminate and the green light should go off. Monitor RCP amps to ensure they return to norma COMMENTS:

CRO-201 fnl Page 13 of 16 STEP 26: Step 26 c Stabilize RCS P SAT STANDARD: Monitor RCS PR on 1UB1 and the OAC to determine it is stable-UNSAT COMMENTS:

STEP 27: Step 27 WHEN RCP motor current stabilizes, -SAT THEN stop respective RCP lift oil pum STANDARD: Monitor RCP motor current by observing amp gauge on I A B I and when -UNSAT it stabilizes stop the 1Al lift pump previously started by placing the switch on I A B I in the trip position. Observe the red light goes off and the green light illuminate COMMENTS:

L STEP 28: Step 28 Verify starting another RCP is NOT desire SAT STANDARD: Determine that starting another RCP is not desire UNSAT Cue: I f asked, inform candidate that starting another RCP is not desired at this tim COMMENTS:

CRO-201 fnl Page 14 of 16 STEP 29: Step 29 c Monitor OAC graphic RCPMPALL to analyze operating RCP parameter SAT STANDARD: Display OAC graphic RCPMPALL and analyze 1Al RCP parameter UNSAT COMMENTS:

STEP 30: Step 30 Return the following components to their desired position: -SAT IRC-1 Pzr heaters-UNSAT STANDARD: Return 1RC-1 and Pzr heaters to AUTO by depressing the AUTO pushbuttons located on 1UB1 for IRC-1 and Pzr heater Cue: If asked, inform candidate that it is desired to return IRC-I and Pzr heaters to AUTO.

u COMMENTS:

STEP 31: Step 31 EXIT this enclosur SAT STANDARD: Candidate should indicate that they would exit this enclosur UNSAT COMMENTS:

END TASK STOP TIME:

CRO-201 fnl Page 15of 16 CRITICAL STEP EXPLANATIONS:

ii STEP # Explanation 15 This step aligns cooling water to the RC This step required for the RCP to satisfy RCP start interlock requirement This step required to start the RC CRO-201 fnl Page 160f 16 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON C MPLETION OFT i/

INITIAL CONDITIONS:

Reactor tripped from 100% power ITA and 1TB did not auto transfer to CT-1 on the trip resulting in tripping of all RCPs Power has been restored to ITA and 1TB EOP Subsequent Action in progress at Step 4.46 INITIATING CUES:

SRO directs you to initiate EOP Enclosure 5.6 (RCP Restart) to start 1Al RC Enclosure EP/1/N1800/00 1 RCP Restart Page 1 of 9

'W ACTIONIEXI'ECTED RESPONSE RESPONSE NOT OBTAINED 1'

1. -Verify ICC tab NOT in progres G O T 0 Step 1 . --Verify NO RCPs operatin GO TO Step __ Verify the following: 1.- Obtain TSC concurrence to perform RCP

- Boiler condenser cooling has NOT restar occurred 2.- IF TSC does NOT concur with RCP

- Nat Circ cooling exists in at least one restart, RCS lo00 THEN EXIT this enclosur . -Ensure dl SCMs are > 0° . -Ensure adequate RCP NPSH per Encl5.18 (PR Curves). Verify of the following exist: 1.- EnsurePzr level is 2 100" [180"acc].

-Either hot leg level < 597" 2.- GO TO Step Either train of vessel head level < 171"

-RVLIS indications NOT available AND NO RCPs operating 7. -Ensure Pzr level > 200" 1235 acc . -Verify HPI CD tab NOT in progres GO TO Step 1 I Ensure the following are closed

- 1RC-155

- 1RC-156

- 1RC- 157

- IRC- 158 -

- 1RC- 159

- 1RC-160 __

io. -Verify Pzr level is < 375" [340" acc].

-______ ~ .___

- Reduce RCS

- pressure to < 2000 psi _-__

11. - Verify 1RC-4 is NOT closed to isolate - GO TO Step 1 leakage past POR . -Ensure 1RC-4 is ope . -Ensure IRC-1 is in manual and close . Ensure the following are open:

- 1LPSW-6 ii - 1LPS w- 15

. .. .. . . . .. . . . .. ... .. .-

Enclosure EP/1/A/I800/001 RCP Restart Page 2 of 9

.. u I

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L/

..

Enclosure RCP Restart i/'

.:. : . . .. . ,.. .... . ... ... . . .'C ACTIONlEXPECTED RESPONSE ' ~ ~ P O N NOT S E OBTAINED

. . . .. . . . .. ..

,. ., . . ' . ...' .. .., i ..,, ;.,

15. Ensure the following are open for each RCP

~

to be started using OAC graphic LPSO2:

- 1LPSW-7&8 (1Al)

- lLPSW-13&14 (1A2)

- ILPSW-9&10 (1B1)

- lLPSW-11&12 (1B2)

16. Ensure = 8 gpm seal injection for each RCP to be starte Al

- 1A2

- 1B1

- 1B2 17. Ensure the following are open for each RCP to be started

- 1"-228 (1Al)

- 1"-226 (1A2)

W

- 1"-232 (1B1)

- 1"-230 (1B2)

18. Ensure the following are open:

- 1m-20

____-1 m - 2 1 19. -Venfy CC TOTAL FLOW 2 575 gp Open the following as necessary to obtain 2 575 gpm total CC flow: -

- 1m-1

- 1Hp-2 -

20. -Verify HPI CD tab is NOT in progres GO TO Step 3 . verify ICC tab is NOT in progres GO TO Step 41. _._____

____--

Enclosure EP/1/A/1800/001 RCP Restart Page 4 of 9

_... .. .. .. ..,

.%%, :.:

.. Y-

. . .. .

..**I ,

.

. . I .

. .

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Enclosure EP/1/N1800/00 1 RCP Restart Page 5 of 9 v ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED

. . . . . ..* .. . . . . . .

NOTE If SCM is lost due to RCP restart, performance of Rule 2 (Loss of SCM) may be delayed for up to 2 minutes to allow SCM to recove I 22. -IAAT SCM is = O'F due to RCP restart, THEN ensure full HPI flow per Rule 6 (HPI).

__---

23. - IAAT any SCM is = 0°F for z 2 minutes following RCP restart, THEN GO TO LOSCM ta . -Start AC DC lift oil pump for an RCP to be starte c 25. -WHEN computer alarm for low lift oil pump discharge pressure clears for RCP to be started, THEN start RC W 26. -Stabilize RCS Pn . -WHEN RCP motor current stabilizes, THEN stop respective RCP lift oil Pum . -Verify starting another RCP is NOT - GO TO Step 2 desire _____

29. -Monitor OAC graphic RCPMPALL to analyze operating RCP parameter ........ ~.. -

30. Return the following components to their desired position:

. _ IRC-1-Pzr heaters__ -~.......

3 I. -EXIT this enclosur Enclosure EP/1/A/1800/00 1 RCP Restart Page 6 of 9

. .

I I

THIS PAGE INTENTIONALLY BLANK

~~ I

,

Enclosure EP/l/A/I 800/00 1 RCP Restart Page I of 9 d

!

~ L ....

i 4 .

,:&-.

. . .

..

-..I

. ,I

'

. " ..

! Unit Status :

!

! HPI CD tab is in progres :

!

~~ ~~

NOTE If SCM is lost due to RCP restart, performance of Rule 2 (Loss of SCM) may be delayed for up to 2 minutes to allow SCM to recove Transition to LOSCM tab is NOT required if SCM is lost during RCP restart in HPI CD ta . -IAAT SCM is = 0°F due to RCP restart, THEN ensure full HPI flow per Rule 6 WI).

33. -Start AC DC lift oil pump for an RCP to be starte c

-_

34. -WHEN computer alarm for low lift oil pump discharge pressure clears for RCP to be started, THEN start RCP.

W 35. -Stabilize RCS P/ . -WHEN RCP motor current stabilizes, THEN stop respective RCP lift oil pum . -Verify starting another RCP is NOT desire I - Go To Step 3 . -Monitor OAC graphic RCPMPALL to analyze operating RCP parameter I 39. Return the following components to their desired position:

- 1RC-1-Pzr heaters 4 EXIT this enclosur I

Enclosure EP/1/N1800/00 1 RCP Restart Page 8 of 9

. . .....*'. .

v

. . . : :,e.,: ~

.. .. . ..

. . . . .... - .

..

Enclosure EP/1/Af1800/001 RCP Restart Page 9 of 9 ii I I I

L ICC tab inr.progres I I

41. -Start AC DC lift oil pump for an RCP to be starte . -WHEN computer alaim for low lift oil pump discharge pressure clears for RCP to be started, THEN start RC . -IAAT RCP motor current stabilizes, THEN stop respective RCP lift oil pum . -Verify starting another.RCP is NOT desire GOTOStep41. ..

~ ~

45. -Monitor OAC graphic RCPMPALL to analyze operating RCP parameter . Return the following components to their ii desired position:

- 1RC- 1-Pzr heaters -

47. -EXIT this enclosur CRO-009 fnl Page 1 of 8

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE CRO-009 Following a Keowee Emergency Start Transfer from CT-4 to CT-5 ii CANDIDATE:

EXAMINER:

CRO-009 fnl Page 2 of 8 REGION I1 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Following a Keowee Emergency Start Transfer from CT-4 to CT-5 Alternate Path:

No Facilitv JPM #

CRO-009 KIA Ratinds):

System: 062 KIA: A4.01 Rating: 3.31 Task Standard:

Auxiliary power is correctly swapped from CT-4 to CT-5 by procedur Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant - Perform Simulate -

ii References:

OPIO1AI1 106119 Encl. 4.12 Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT -UNSAT - performance Time: __

COMMENTS

CRO-009 fnl Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS:

Recall Snap 204 ii . Import CRO-009 file . Place simulator in RUN

CRO-009 fnl Page 4 of 8 ToolslEauivmenffProcedures Needed:

ii OP/O/N1106/19, Encl. 4.12 READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

CT-1 is out of service for repair A Switchyard Isolation has resulted in a reactor trip and Unit 1's Main Feeder Busses are being supplied from CT-4 via the Standby Busse CT-5 has been energized from a Lee Gas Turbine and the dedicated path, bypassing the Central switchyard, has been establishe Keowee personnel have requested that the Keowee units be shutdow OP/O/NI 106/19, Keowee Hydro at Oconee, Enclosure 4.12 has been completed up to step 2. INITIATING CUES:

-' The Control Room SRO directs you to utilize Enclosure 4.12 of OP/O/N1106/19, Keowee Hydro at Oconee, to transfer MFB power from CT-4 to CT-5 starting at step 2. CRO-009 fnl Page 5 of 8 START TIME:

L :1- Step 2. CRITICAL STEP Place the following transfer switches in MANUAL: -SAT CT-4 BUS 1 AUTOJMAN CT-4 BUS 2 AUTOlMAN CT-5 BUS 1 AUTOlMAN -UNSAT CT-5 BUS 2 AUTOlMAN STANDARD: The following transfer switches are placed in the MANUAL position:

CT-4 BUS 1 AUTO/MAN CT-4 BUS 2 AUTOlMAN CT-5 BUS 1 AUTOlMAN Not Critical CT-5 BUS 2 AUTOlMAN Not Critical COMMENTS:

2- Step 2. CRITICAL STEP Open SKI (CT-4 Stby Bus 1 Feeder).

L -SAT STANDARD: SK1 (CT-4 Stby Bus 1 Feeder) is OPENED by placing the switch in the trip position on 2AB COMMENTS: -UNSAT

CRO-009 fnl Page 6 of 8 CRITICAL STEP L

NOTE: The time period between opening SK2 and closing SL1 should be > 3 secondsand~20second SAT Step 2. Energize the STBY BUSES from CT-5 by performing the following: -UNSAT Open SK2 (CT-4 STBY BUS 2 FEEDER)

Close SL1 (CT-5 STBY BUS 1 FEEDER)

Close SL2 (CT-5 STBY BUS 2 FEEDER)

STANDARD: The following breakers located on 2AB3 are operated in the listed sequence:

. Open SK2 (CT-4 STBY BUS 2 FEEDER)

Close SL1 (CT-5 STBY BUS 1 FEEDER)

Close SL2 (CT-5 STBY BUS 2 FEEDER)

COMMENTS:

STEP: Step 2.1.7 L Return the following transfer switches to AUTO: -SAT CT-4 BUS 1 AUTOIMAN CT-4 BUS 2 AUTOIMAN CT-5 BUS 1 AUTOIMAN CT-5 BUS 2 AUTOIMAN -UNSAT STANDARD: The following transfer switches located on 2AB3 are placed in the AUTO position:

CT-4 BUS 1 AUTOIMAN CT-4 BUS 2 AUTOIMAN CT-5 BUS 1 AUTOIMAN CT-5 BUS 2 AUTOlMAN NOTE: Recovery of lost loads is not required for this JP COMMENTS:

END TASK STOP TIME:

ii

CRO-009 fnl Page 7 of 8 CRlTlCAL STEP EXPLANAT10NS :

i/

STEP # Explanation 1 Breakers required in manual to allow operation 2 Breaker required to be open to remove power from CT-4 allowing power restored from CT-5 3 Proper breaker alignment to transfer power from CT-4 to CT-5

CRO-009 fnl Page 8 of 8 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

v INITIAL CONDITIONS:

CT-1 is odt of serv:ce for repair A Switchyard Isolation has resulteo in a reactor trip and Unit 1's Main Feeder Busses are being supplied from CT-4 v:a the Standby Busse CT-5 has been energized from a Lee Gas Turbine and the dedicated path, bypassing the Central switchyard, has been establishe Keowee personnel have requested that the Keowee units be shutdow OP/O/N1106/19. Keowee Hydro at Oconee, Enclosure 4.12 has been completed up to step 2. INITIATING CUES:

The Control Room SRO directs you to utilize Enclosure 4.12 of OP/O/AI1106/19, Keowee Hydro at Oconee, to transfer MFB power from CT-4 to CT-5 starting at step 2. Enclosure 4.12 OPIO/AI1106/019 Transfer Of MFB Power Supply Page 1 of 4 From CT 4 To CT 5 1. Initial Conditions

- KKos have been started by emergency actuation =it is desired to shut down the KHU __ It is desired to supply power from CT .3 Review Limits and Precaution . Procedure Perform a Dead Bus transfer to CT5 from CT4 while CT4 is supplvine,Unit 1,2,

-

OR 3 MFB by:

- -2.1.1 Ensure CT 5 is energized U r e a d y to power auxiliary loads 2. Prior to performing Dead Bus transfer, notify the following:

__ SecurityForce

__ ChemistryDepartment W

__ GroupHeads

__ KeoweeOperator

__ 2. Ensure reset MFB Monitor Panel for any Oconee Units receiving power from the STBY Buse . Place the following transfer switches in "MAN":

-- CT 4 BUS 1 AUTOMAN

-__ CT 4 BUS 2 AUTOMAN

-- 9 CT 5 BUS 1 AUTOMAN

-- CT 5 BUS 2 AUTOMAN

- -2. Open SK 1 CT 4 STANDBY BUS 1 FEEDE v CAUTION: Transfer should be made in > 3 but < 20 seconds to prevent picking up MFB Monitor Panel actuation which will cause a Load Shed, Keowee Emergency start and possibIe EPSL actuation. Undervoltage relays will cause a loss of most non-safety load *

2. Energize STBY BUSES from CT 5 by performing the following:

- - Open SK 2 CT 4 STBY BUS 2 FEEDE Close SL-1 C T 5 STBY BUS 1 FEEDE ~- C. Close SL-2 CT 5 STBY BUS 2 FEEDE . Return the following Transfer Switches to "AUTO":

-- CT4 BUS 1 AUTOMAN

-- CT4 BUS 2 AUTOMAN

~~

CT5 BUS 1 AUTOMAN

-- CT5 BUS 2 AUTOMAN

__ 2. Recover any loads lost in transfer.

c

' Enclosure 4.12 OP/O/A/1106/019 Transfer Of MFB Power Supply Page 3 of 4 v

From C T 4 To C T 5 NOTE: KHU(s) are generating with Overhead ACB closed prior to an Emergency Start Actuation, that KHU(s) will shutdown when ES Channel has been reset unless ACB is currently close .2 When all three Units no longer require an energized Underground Power Path m a Normal Lockout does m e x i s t on either KHU supplying power to an Oconee Unit, completelyshut down the KHU tied to the Underground by:

2. ES 1 2 has actuated, either reset ES 1 2 channels press

"MANUAL" on the following ES 1 AND 2 modules:

-- Keowee Emer Start Ch A

-- Keowee Emer Start Ch B

-- Load Shed and STBY Bkr 1

-- Load Shed and STBY Bkr 2 2. IF a manual Keowee Emergency start has been performed from any Oconee Unit, return both Keowee Emergency Start Channel switches on the affected Unit to " O W positio Keowee Emergency Staa Channel A

- - Keowee Emergency Start Channel B

~- 2. Ensure reset Main Feeder Bus Monitor Panel . Reset External Grid Trouble Protection System by depressing the followhg buttons. (Unit 112):

-__ GRID TROUBLE PROTECTIVE SYSTEM U.V. CHANNEL 1 RESET

-__ GRID TROUBLE PROTECTIVE SYSTEM U.V. CHANNEL 2 RESET

-___ GRID TROUBLE PROTECTIVE SYSTEM U.F. CHANNEL 1 RESET

-- GRID TROUBLE PROTECTIVE SYSTEM U.F. CHANNEL2 RESET

Enclosure 4.12 OP/O/A/1106/019 Transfer Of MFB Power Supply Page 4 of 4 From CT 4 To CT 5 2. Ensure External Grid Trouble Protection has been reset. (Unit 112):

___ SA-15, A-2 Channel #1 Underfrequency

- SA-15, A-4 Channel #2 Underfrequency

__ SA-15, C-1 Channel #1 Undervoltage

__ SA-15, C-3 Channel #2 Undervoltage NOTE: External Grid Trouble Protection System actuates Keowee Emergency Start from Oconee Unit 1circuitr . Depress Keowee "PUSH TO RET TO NORMAL AFT ES RESET" pushbutton on Oconee UNts which have generated a Keowee Emergency Start signal:

A. Unit1

-- KEOWEE LOGIC RESET CHANNEL 1

-- KEOWEE LOGIC RESET CHANNEL 2 B. Unit2

-- KEOWEE LOGIC RESET CHANNEL I

-- KEOWEE LOGIC RESET CHANNEL 2 unit3

-__ KE0WEEESCHANNE KEOWEE ES CHANNEL B

__ 2. Notify Keowee Operator to shutdown the KHU(s) per OP/O/A/2000/041 (KHS

- Modes of Operation).

CRO-202 fnl Page 1 of 8

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE CRO-202 Reset RIA-40 setpoints and enter the OAC Pri to Sec Admin Limit CANDIDATE EXAMINER

CRO-202 fnl Page 2 of 8 REGION I1 i/ INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Reset RIA-40 setpoints and enter the OAC Pri to Sec Admin Limit Alternate Path:

No Facility JPM #:

New WA Ratinds):

System: 073 WA: A4.02 Rating: 3.71 Task Standard:

Correctly adjust 1RIA-40 alarm setpoints for the RIA and OAC per AP/31, Primary to Secondary Leakage Preferred Evaluation Location: Preferred Evaluation Method:

i/ Simulator In-Plant - Perform &Simulate -

References:

AP131, Primary to Secondary Leakage Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT -UNSAT - Performance Time ___

Examiner: I NAME SIGNATURE DATE COMMENTS

CRO-202 fnl Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS:

1, Recall IC-41 i/

2. Place simulator in RUN

CRO-202 fnl Page 4 of 8 ToolslEauivmenUProceduresNeeded:

AP131, Primary to Secondary Leakage u AP131 (Primary to Secondary Leakage) Encl. 5.7 (Resetting IRIA-40 and OAC Setpoints) completed thru step READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

The unit has been continuouslyoperatingat 100% for 9 months with a small SG tube leak in the 1B S SG tube leakage in the 1B SG has increased and new leakage is calculated to equal 17 gp AP/31, Primary to Secondary Leaklage is in progress and completed up to step 4.4 INITIATING CUES:

b The SRO directs you to complete step 4.40 of AP/31, Primary to Secondary Leakage

CRO-202 fnl Page 5 of 8 START TIME:

L STEP: Step 4.40 Perform Enclosure 5.7 (Resetting 1RIA-40 and OAC Setpoints) to set the-SAT following setpoints:

1RIA-40 High - 75 gpd 1 RIA-40 Alert - 30 gpd -UNSAT OAC point 0 1K1430 (Total PRI To Sec Leakrate Admin Limit) - 30 gpd STANDARD: Locate Enclosure 5.7 (Resetting 1RIA-40 and OAC Setpoints)

Cue: Give candidate the partially completed copy of Enclosure 5.7. Inform candidate that the enclosure is complete up to step COMMENTS:

STEP: Step 6 CRITICAL STEP Enter the new 1RIA-40 Alert and High setpoints in the RIA View Node-SAT STANDARD:

c Locate the RIA View Node on 1VB2, perform the following:

-UNSAT From the U1 Radiation Monitor display page, select 1RIA-40 by placing the cursor on 1 RIA-40 "hot link" then depress the lefl mouse ke From the Channel Summary display page, select Enable Controls by placing the cursor on the ENABLE CONTROLS "hot link" and depressing the left mouse ke From the ENABLE CONTROLS display page, type in the new ALERT setpoint (3602 cpm) in the ALERT window and depress enter (or left mouse key).

From the ENABLE CONTROLS display page, type in the new HIGH setpoint (9006 cpm) in the HIGH window and depress enter (or left mouse key).

"Verify the new ALERT (Yellow bar) and HIGH (Red bar) setpoints increase to the new elevated values on the Channel Summary display page.*

NOTE: * Not critical COMMENTS:

c

CRO-202 fnl Page 6 of 8

3- Step 7 CRITICAL STEP Enter the new OAC TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT by L performing the following: -SAT Enter MVU Select PRI-LEAK PRIMARY TO SECONDARY LEAKAGE MANUAL INPUT UNSAT Select UPDATE Select 01K1430 (TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT)

Enter the new TOTAL PRI TO SEC LEAKRATE ADMIN LIMI Enter your LAN identification and reason for chang Select SAVE STANDARD: Using one of the OAC terminals located on 1UBI or 1UB2 the candidate should perform the following:

Enter MVU Select PRI-LEAK PRIMARY TO SECONDARY LEAKAGE MANUAL INPUT Select UPDATE Select 01K1430 (TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT)

Enter 30 gpd as the new TOTAL PRI TO SEC LEAKRATE ADMIN LIMI *Enter their LAN identification and reason for chang Select SAVE L *Note: Reason for change can be either AP131 guidance or increase in SG Leakrat Step not critical COMMENTS:

END OF TASK STOP TIME:

CRO-202 fnl Page 7 of 8 CRITICAL STEP EXPLANATIONS:

d STEP # Explanation 2 Setpoint adjustment for the RIA View Node 1RIA-40 High and Alert alarm setpoints 3 Setpoint adjustment OAC TOTAL PRI TO SEC LEAKRATE ADMlN LIMIT

CRO-202 fnl Page 8 of 8 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

W INITIAL CONDITIONS:

The unit has been continuously operating at 100% for 9 months with a small SG tube leak in the 1B S SG tube leakage in the 16 SG has increased and new leakage is calculated to equal 17 gp AP/31, Primary to Secondary Leakage is in progress and completed up to step 4.4 INITIATING CUES:

The SRO directs you to complete step 4.40 of AP131, Primary to Secondary Leakage

/I 3 PREPARATION L J bp (2) Station OCONEE (3) Procedure Title Primary to Secondary Leakage I

(4) Prepared By David P. Garland (signature) v ~ j Date 10/23/02

/

.

@) .. Requires NSD 228 Applicabitity Determination?

" (XI Yes (New procedure or revision with major changes)

11-I - b a (QR)

(QW Date

Mgmt Involvement Review By (Ops Supt) N (7) Additional Reviews Reviewed By Date I

Reviewed By Date (8) Temporary Approval [ifnecessury)

ii BY (OSWQR) Date BY (QR) Date (9) Approved By - R U Date \\\%\b?.-

PERFORMANCE [Compare wiih control copy every 14 calendar d a s h & work is beingperformed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification:

Unit 0 0 Unit 1 0 Unit 2 0 Unit 3 Procedure performed on what unit?

Yes NA, Check lists andor blanks initialed, signed, dated, or filled in NA, as appr Yes NA Required enclosures attached?

0 Yes NA Data sheets attached, completed, dated, and signed?

0 Yes 0 NA Charts, graphs, etc. attached, dated, identified, and marked?

0 Yes 0 NA Procedure requirements met?

Verified By b 13) Procedure Completion Approved (14) Remarks [Aaach addifionalpuges, ifnecessaryj

Procedure N Duke Power Company Oconee Nuclear Station AP/1/A/1700/031 Revision N Primary to Secondary Leakage Electronic Reference N OP0095ZI

~~ilt~/i~oota31 Page 1 of 35 1. Entry Conditions c Any actual or suspected primary to secondary leakage 2 5 gpd and < 25 gp . Automatic Systems Actions None 3. Immediate Manual Actions None

AP/l/A/1700/031 Page 2 of 35

... L

~~~~

THIS PAGE INTENTIONALLY BLANK

-/

AP111AJ17001031 Page 3 of 35 4. Subsequent Actions -

u ACTIONBXPECTED RESPONSE RESPONSE NOT OBTAINED 4.1 +._IAAT the SGTR tab of EPll POP) is entered, THEN EXIT this procedur .2 - IAAT either of the fo!lowing

-. exists - GO TO Step for 1FSA-54:

- is in alarm

- inoperable THEN perform Steps 4.3 - I L

4.3 Dispatch an operator to open and white NOTE The white tags can be created and hung after the TBS pump breakers are opene (1)

I tag the following:

w

- 1XD-R3C (1A TURBINE BUILDING L-S U M P PUMP BKR)

W - 1XE-R3D (1B TURBINE BUILDING S U M P PUMP BKR) Notify Secondary Chemistry to perform the following:

- Obtain a TBS sampl Recommend TBS release pat .5 - IAAT gross tube leakage is indicated by an increase in normal RC makeup flow, THEN GO TO Step 4.7 .6 - IAAT a tritium sample indicates 2 75 gpd primary to secondary leakage, THEN GO T O Step 4.7 AP/1/A/1700/03 1 Page 4 of 35 IF AT ANY TIME:

L (4.1) the SGTR tab of EP/1 (EOP) is entered.. . (EXIT this procedure)

(4.2) 1RL4-54in alarm inoperable ... (open TBS pump breakers)

...

(4.5) goss tube leakage is indicated by an increase in noma1 RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicat& 2 75 gpd primary to secondary leakage.. .

(GO TO shutdown guidance)

ACTIONBXE'ECTED RESPONSE RESPONSE NOT OBTAIMED d Notify RP to perform the,.1.following:

- Use a portable monitor to identify leaking SG. ,2)

- Obtain CSAE off-gas sampl Expect contact from Primary Chemistry to coordinate CSAE off-gas and RCS sample times within 15 minute .8 Notify Primary Chemistry to perform the following:

- Obtain an RCS sample for use in calculating SG tube leakage rat Contact RP to coordinate CSAE ii off-gas and RCS sample times within 15 minute .9 - Verify OAC primary to secondary leak - GO TO Step 4.1 rate calculation available (including 1RzA-40 operable).

'-4:lO - Determine primary to secondary leakage rate using OAC point 01P1599 (ESTTOTALPRITO SEC LEAKRATE).

4.11 - GO TO Step 4.14.

c

AP/llAl1700/031 Page 6 of 35

-.

IF AT A M TIME:

(4.1) the SGTR tab of EP/I (EOP) is entered. .. (EXIT this procedure)

(4.2) >RIA-54 in alarm inoperable . . . (open TBS pump breakers)

(4.5) gross tube Ieakage is indicated by an increase in normal RC makeup flow. ..

(GO TO shutdown guidance)

B (4.6) tritium sample indicates 2 75 gpd primary to secondary leakage...

(GO TO shutdown guidance)

,

AP/1/N1700/03 1 Page 7 of 35 i/

ACTIONRZXPECTED RESPONSE RESPONSE NOT O B T A W D 4.12 - Verify 1RIA-40 operabl .- IF CSAE off-gas sample indicates

._

. primary to secondary leakage z 60 gpd (0.04164 gpm),

AND leak rate was unstable/increasing at the time 1RIA-40 became inoperable, THEN perform the following:

A. -Stop any power increase in progres B. -GO TO Step 4.7 . - IF CSAE off-gas sample indicates primary to secondary leakage 2 5 gpd (0.003472 gpm),

THEN perform the following:

A. - Stop any power increase in progres B. -GO TO Step 4.2 .- EXIT this procedure.

'4 4.13 - PERFORM Encl 5.5 (Calculation of Primary to Secondary Leak Rate using 1RIA-40). 131 4.14 - Verify primary to secondary leak rate NOTE

< 25 gpm (36,000 gpd). ff the EOP is NOT already in progress, entry will be directly to the SGTR ta GO T O EP/1 (EOP).

4.15 - Verify primary to secondary leak rate 1. - IF primary to secondary leak rate is eithe < 75 gpd (0.05205 gpm). of the following:

-2 75 gpd for at least one hour-2 100 gpd (0.0694 gpm)

THEN GO T O Step 4.7 . - GO T O Step 4.4 .16 - Verify primary to secondary leak rate - GO T O Step 4.4 < 30 gpd (0.02082 gpm).

4.17 - Verify primary to secondary leak rate - GO T O Step 4.2 < 5 gpd (0.003472 gprn).

A P / l / A / 1700/03 1 Page 8 of 35 IF A T ANY TIME:

(4.1) the SGTR tab of EP/1 POP) is entered.. . (EXIT this procedure)

(4.2) 1RIA-54 in alarm inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow.. .

(GO TO shutdown guidance)

(4.6) tritium sample indica& 2 75 gpd primary to secondary leakage.. .

(GO TO shutdown guidance)

A P / l / A /1700/031 Page 9 of 35 4.18 - W E E N CSAE off-gas and RCS samples are available,

.'THEN PERFORM Encl (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples) to confirm rat .19 - Verify primary to secondary leak rate - GO TO Step 4.2 confirmed < 5 gpd (0.003472 gpm). __-

4.20 Notify the following to take a second sample (within 15 minutes of each other, 1-if possible):

Group Primary Chemistry Sample RCS 4.21 - WHEN second CSAE off-gas and RCS samples are available, W

THEN PERFORM Encl (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples) to confirm rat .22 - Verify primary to secondary leak rate - GO TO Step 4.2 confirmed < 5 gpd (0.003472 gpm).

4.23 - Verify 1RJA-40 operabl GO TO Step 4.2 .24 Jnitiate Encl5.7 (Resetting lRX-40 and OAC Setpoints) to ensure the following alarm setpoints: (7 J

- 1RIA-40 High - 30 g d

- 1RIA-40 Alert - 5 gpd

- OAC point 01K1430 (TOTAL PRI TO SEC LEAKRATE ADMIN LIMIT)- 5 Qd

Apll/A/1700/03 1 Page 10 of 35 IF AT ANY TIME: L (4.1) the SGTR tab of EPll (EOP) is entered.. . (EXIT this procedure)

(4.2) IRIA-54 in alarm inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flo (GO TO shutdown guidance)

(4.6) tritium sample indica& 2 75 gpd primary to secondary leakage.. .

(GO TO shutdown guidance)

AP/l/A/1700/031 Page 11 of 35 b I ACTION/EXFECTED RESPONSE RESPONSE NOT OBTAINED 1 4.25 Notify Secondary Chemistry of the following:

-_

- Primary to secondary leak rate has been confirmed < 5 gpd and this procedure will be exite .s

- To recommend TBS release pat .26 Notify the following that primary to secondary leak rate has been confirmed

< 5 gpd and this procedure will be exited

- RP

- Primary Chemistry

- Personnel previously notified per O W 1-14 (Notifications)

4.27 - EXIT this procedur AP/1/.4/17001031 Page 12 of 35

- IF AT AM' TLME:

L

...

' (4.1) the SGTR tab of EP/1 (EOP) is entered ... (EXIT this procedure)

(4.2) 1FU-54in alann inoperable ... (open TBS pump breakers)

..

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow...

(GO TO shutdown guidance)

(4.6) tritium sample indica& 2 75 gpd primary to secondary leakage...

(GO TO shutdown guidance)

AP/1/A/1700/031 Page I3 of 35 ACTIONEXPECTED RESPONSE RESPONSE NOT OUTAIhTD J 4.28 - IAAT primary to secondary leak rate increases to 2 30 gpd (0.02082 gpm),

-THEN GO TO Step 4.4 .29 - Verify 1RIA-40 operabl .- Monitor the following at least twice per shift for indications of an increasing leak rate: (4)

1RIA-16 1RIA-17

!, - GO TO Step 4.3 .30 - h4onitor the following at least once pel shift for indications of an increasing leakrate: ( 4 )

. 1RIA-16 1RIA-17 1RL4-40 W 4.31 - Make notifications of primary to secondary leakage per Oh@ 1-14 (Notifications).

4.32 - Maintain the Primary to Secondary Leak Log to include the following:

1RX-16, 17, and 40 readings RCS activity levels Calculated leak sizes (including those based on 1RIA-40 readings)

4.33 - Issue a priority work request for any 00s SG tube leak monitoring equipmen =f 1FUA-40 Frequency (hr)

Operable 24 Inoperable 4

AP/~/A/1700/031 Page 14 of 35 IF AT ANY TIME:

,... L (4.1) the SGTR tab of EP/I POP) is entered ... (EXIT this procedure)

(4.2) IRIA-54 in alarm inoperable ... (open TBS pump breakers)

,,

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow.. .

(GO TO shutdown guidance)

""

(4.6) tritium sample indicates 2 75 gpd.primary to secondary leakage.. .

(GO TO shutdown guidance)

(4.28) primary to secondary leak rate increases to 2 30 gpd.. . (GO TO guidance to increase monitoring)

AP/1/A/1700/031 Page 15 of 35 i/

[ ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED 1 4.35 - IAAT CSAE off-gas sample and RCS - GO TO Step 4.3 sample results become available, THEN perform Steps 4.36 - 4.3 .36 - PERFORM Encl 5.4 (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and R%S Samules).

4.37 - Log leak rate calculation results in Primarv to Secondam Leak Lo ~ ~

4.38 Notify the following to enter leak rate calculation results in the Excel leakage spreadsheet:

- Ops Mods Supervisor

- Ops Work Process Manager Administrative Specialist 4.39 - IAAT 1RL4-40 is operable, - GO TO Step 4.4 THEN perform Steps 4.40 - 4.42.

ii 4.40 PERFORM Encl 5.7 (Resetting 1RIA-40 and OAC Setpoints) to set the following alarm setpoints: (7)

- IRL4-40 High - 75 gpd

- IRIA-40 Alert - 30 gpd

- OAC point 01K1430 (TOTAL PRI TO SEC LEAKRATE ADMTN LIMIT) - 30 md 4.41 - Record OAC and 1RIA-40 High and Alert setpoints on turnover shee .42 - Verify CSAE off-gas and RCS - Notify Rp and Primary Chemistry to samples are being performed on a perform CSAE off-gas and RCS samples 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months frequenc on a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months frequenc .43 - Notify OSM to include most recent primary to secondary leak rate (determined by CSAE off-gas sample or 1RIA-40) on the OSM turnover sheet. 181

AP/1/A/1700/031 Page 16 of 35

-

'L (4.1) the SGTR tab of EP/1 (EOP) is entered.. . (EXIT this procedure)

inoperable ... (open TBS pump breakers)

(4.7.)

-1RIA-54 in alarm (4.5) gross tube leakage is indicated by an increase in normal RC makeup flow.. .

(GO TO shutdown guidance)

(4.6) tritium sample indicags 2 75 gpd primary to secondary leakage,. .

(GO TO shutdown guidance)

(4.28) primary to secondary leak rate increases to 2 30 gpd.. . (GO TO guidance to increase monitoring)

(4.35) CSAE off-gas sample and RCS sample results become available. .. (calculate and record primary to secondary leak rate)

(4.39) 1RL4-40 is operable.. . (reset OAC and 1RIA-40'setpoints and record new setpoints)

,

AP/1/N1700/031 Page 17 of 35 ii 4.44 - IAAT CSAE off-gas sample indicates primary to secondary leak rate

'.c5 gpd (0.003472 gpm),

THEN perform the following:

A. Notify the following to take another sample (&thin 15 minutes of each other, if possible):

Group Sample B. - GO TO Step 4.2 .45:- WHEN in MODE 5, THEN EXIT this procedur AF'/1/A/1700/031 Page 18 of 35 IF AT ANY TIME: -

L (4.1) the SGTR tab of EP/1 (EOP) is entered. .. (EXIT this procedure)

(4.2) 1RL4-54 in alarm 3 inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow.. .

(GO TO shutdown guidance)

(4.6) tritium sample indicafes 2 75 gpd. primary to secondary leakag (GO TO shutdown guidance)

AP/1/.4/1700/031 i Page 19 of 35

..^

ACTIONEXPECTED RESPONSE RESPONSE KOT OBTAIMD 4.46 - IAAT the following conditions

..exist:

- 1RIA-40 inoperable

- primary to secondary leak rate

> 60 gpd (0.04164 gpm)

'-4

- leak unstable/increasing at time 1RIA-40 became inoperable THEN GO TO Step 4.73.

4.47 - IAAT primary to secondary leak rate increases to of the following:

'

- 2 75 gpd (0.05205 gpm) for at least one hour

- 2 100 gpd (0.0694 gpm)

THEN GO TO Step 4.73.

4.48 - Make notifications of primary to secondary leakage per OMP 1-14 (Notifications).

4.49 - Monitor the following every

.15 minutes for indications of increasing leak rate: p l 1RIA-16 1RIA-17 1RIA-40 4.50 - IAAT leak rate is stable (< 10%

change in a one hour time period),

THEN reduce monitoring frequency of the following to every two hours:

IRIA-16 1RIA-17 1RIA-40

AP/1/.4/1700/031 Page 20 of 35 IF AT ANI TIME:

_..

(4.1) the SGTR tab of EP/1 (EOP) is entered ... (EXIT this procedure)

(4.2) IRIA-54 in alarm inoperable ... (open TBS pump breakers)

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow ...

(GO TO shutdown guidance)

(4.6) tritium sample indicates 2 75 gpd primary to secondary leakage ...

(GO TO shutdown guidance)

(4.46) 1RIA-40 is inoperable AND primary to secondary leak rate > 60 gpd AND leak unstabldincreasing at time 1-40 became inoperable.. . (GO TO shutdown guidance)

(4.47) primary to secondary leak rate increases to 2 75 gpd for at least one hour OR 2 100 gpd...

(GO TO shutdown guidance)

(4.50) leak rate is stable (< 10%change in a one hour time period). .. (reduce monitoring frequency of RIAs to every two hours)

AP/1/A/1700/031 Page 21 of 35 L

I ACTIOKEXFECTED RESPONSE RESPONSE NOT OBTAINED 4.51 - Maintain the Pnmary to Secondary Leak Log to include the following:

5 .

1RL4-16, 17, and 40 readings RCS actjvity levels Calculated leak sizes (including those based on 1RJA-40 readings)

4.52 - Verify affected SG identifie (21 Attempt to identify affected SG by a of the following methods:

- 1RL4-16/17 readings

- Local RP surveys of MS lines 4.53 - Issue a priority work request for any I 2% 0 0 s SG tube leak monitonng equipmen .54 - HAT the OSM desires, THEN initiate Encl5.2 (Reduction of W Secondary Leakage and Cross-Unit Contamination). (10)

4.55 Notify Rp and Primary Chemistry to perform CSAE off-gas and RCS samples based on 1 U 4 0 operability: { 5 ) ( 6 )

..

&3 1U-40 I Frequency (hr)

I Operable I 12 1 Inoperable I 4 4.56 - IAAT CSAE off-gas sample and RCS - GO TO Step 4.6 sample results become available, THEN Derform Stem 4.57 - 4.5 ~~~

4.57 - PERFORM Encl5.4 (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples).

4.58 - Log leak rate calculation results in Primary to Secondary Leak Lo AF'/1/A/1700/031 Page 22 of 35 IF AT ANY TIME: -

.. L (4.1) the SGTR tab of EP/1 (EOP) is entered ... (EXIT this procedure)

(4.2) 1RIA-54 in alam 3 inoperable ... (open TBS pump breakers)

(4.5) ~ O S tube S leakage is indicated by an increase in normal RC makeup flow.. .

(GO TO shutdown guidance)

(4.6) tritium sample indica& 2 75 gpd primary to secondary leakage.. .

(GO TO shutdown guidance)

(4.46) 1RL4-40 is inoperable AND primary to secondary leak rate > 60 gpd AND leak unstable/increasing at time 1RIA-40 became inoperable.. . (GO TO shutdown guidance)

(4.47) primary to secondary leak rate increases to 2 75 gpd for at least one hour OR 2 100 gpd.. .

(GO TO shutdown guidance)

(4.50) leak rate is stable (< 10% change in'a one hour time.period). .. (reduce monitoring frequency of-RIAs to every two hours)

(4.54) OSM desires ... (initiate Encl5.2 to reduce secondary leakage and cross-unit contamination)

(4.56) CSAE off-gas and RCS sample results become available... (calculate and record primary to secondary leak rate)

AP/1/A/1700/03 1 Page 23 of 35

~.

i/

L A C l iGN/EXPECTED RESPONSE RESPONSE NOT OBTAIWD .59 Notify the following to enter leak rate calculation results in the Excel leakage spreadsheet: Ops Mods Supervisor

- Ops Work Process Manager Administrative SDecialist 4.60 - IAAT 1RIA-40 is operable, . ' - GO TO Step 4.6 AND primary to secondary leak rate is unstable (210% change in a two hour period),

T H E N perform Steps 4.61- 4.6 .61. PERFORM Encl5.7 (Resetting IRIA-40 and OAC Setpoints) to set the following

.,. .alm.setpoints: (7)

....

- 1RIA-40 High - 75 s d

- 1RIA-40 Alert - 75 gpd

- OAC point 01K1430 (TOTAL PRI W . TO SEC LEAKRATE ADMIN

'

-,, i.,

'.' .' L m )- 75 gpd 4.62 - Record OAC and 1RIA-40 High and Alert setpoints on turnover shee .. . 4.63 - Verify CSAE off-gas and RCS - Notify RP and Primary Chemistry to Samples are being performed on a 24 perform CSAE off-gas and RCS samples hour freauenc?. . . on a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months frequenc .64 - IAAT 1RIA-40 is operable, - GO T O Step 4.6 AND primary to secondary leak rate is stable (c 10% change in a two hour period),

THEN DeIfOrm SkDS 4.65- 4.6 .-

AP/1/A/1700/03 I Page 24 of 35 IF AT ANY TIME:

(4.1) the SGTR tab of EP/l (EOP) is entered... (EXIT this procedure)

(4.2) 1RIA-54 in alarm inoperable ... (open TBS pump breakers)

~

(4.5) gross tube leakage is indicated by an increase in normal RC makeup flow.. .

(GO TO shutdown guidance)

(4.6) tritium sample indica& 2 75 gpd.primary to secondary leakage...

(GO TO shutdown guidance)

(4.46) 1RIA-40 is inoperable and primary to secondary leak rate > 60 gpd AND leak unstable/increasing at time lRIA-40 became inoperable.. . (GO TO shutdown guidance)

(4.47) primary to secondary leak rate increases to 2 75 gpd for at least one hour OR 2 100 gpd.. .

(GO TO shutdown guidance)

(4.50) leak rate is stable (< 10% change in a one hour time period).. . (reduce monitoring frequency of RIAs to every two hours)

(4.54) OSM desires ... (initiate Encl 5.2 to reduce secondary leakage and cross-unit contamination)

(4.56) CSAE off-gas and RCS sample results become available.. . (calculate and record primary to secondary leak rate)

(4.60) 1RIA-40 is operable AND primary to secondary leak rate is unstable. .. (set OAC and 1RJA-40 setpoints to 75 gpd)

(4.64) 1RJA-40 is operable AND primary to secondary leak rate is stable. .. (set OAC and 1RJA-40 setpoints to 75 gpd and 30 gpd above current reading)

AP/1/A/1700/031 Page 25 of 35 v ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.66 - Record OAC and 1RIA-40 High and Alert setpoints on turnover shee .67 - Verify CSAE off-gas and RCS - Notify W and Primary Chemistry to Samples are being performed on a 24 perform CSAE off-gas and RCS samples hour frequenc on a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months frequenc .68 - Notify OSM to include most recent primary to secondary leak rate i/

(determined by CSAE off-gas sample or 1RIA-40) on the OSM turnover sheet. 18)

4.69 - Prepare for response to primary to secondary leakage 2 75 gpd by reviewing Steps 4.73 - 4.9 .70 - WHEN in MODE 5, THEN EXIT this procedur AP/l/A/1700/031 Page 26 of 35 IF AT ANI TME:

(4.1) the SGTR tab of EP/1 F O P ) is entered ... (EXIT this procedure)

(4.2) 1RIA-54 in alarm 3 inoperable ._.(open TBS pump breakers)

.. . .

J

AP/llA/1700/03 1 Page 27 of 35 ii ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.71 - Verify gross leak rate determination is - GO TO Step 4.73, desire .72 Determine primary to secondary leak rate:

LR=-+-

Mu SI LD "'.TSR LR= ZPm Where:

LR = LeakRate MU= MakeupFlow SI = Seal Inlet Header Flow LD = Letdown TSR = Total Seal Return NOTE If the EOP is NOT already in progress, entry will be directly to the SGTR tab.

W 4.73 - IAAT primary to secondary leak rate is 2 25 gpm (36,000 gpd),

THEN GO TO EP/1 (EOP).

4.74 - Make notifications of primary to secondary leakage per OMP 1-14 (Notifications).

4.75 - Log readings from the following every 15 minutes in the Primary to Secondary LeakLog: ( 9 )

1RIA-16 1RIA-17 1RIA-40

AP/1/N1700/03 1 Page 28 of 35 IF AT ANY TIME:

(4.1) the SGTR tab of EP/1 (EOP) is entered.. . (EXIT this procedure)

(4.2) IRIA-54 in alarm inoperable ... (open TBS pump breakers)

(4.73) primary to secondary leak rate is 2 25 gpm.. . (GO T O EP/l POP))

AP/l/N1700/031 Page 29 of 35 ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAbTD 1 4.76 - Initiate a unit shutdown using the

-.following as necessary to meet requirements of Encl5.1 (Unit Shutdown Requirements):

OP/l/A/1102/004 (Operation at

r

Power)

OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown)

4.77 - IAAT primary to secondary leakase increases, THEN modify shutdown as required by Encl5.1 (Unit Shutdown Requirements).

4.78 - Notify Radwaste to stop liquid releases in progress until sample results assure release rates within limits.

4.79 - Stop & l gaseous releases in progress until sample results assure release rates within limits.

4.80 - Make up to the UST only as necessary to maintain UST level > 7'.

4.81 Notify the following that a shutdown is in progess due to primary to secondary leakage:

- Rp

- Primary Chemistry

- Secondary Chemistry 4.82 - Initiate Encl5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination). (10)

4.83 - Verify affected SG identifie (2) Attempt to identify affected SG by of the following methods:

- 1RIA-16/17readings

- Local RP surveys of MS lines

AP/1/A/1700/031 Page 30 of 35 IF AT ANY TIME: ,.

L

..'

(4.1) the SGTR tab of EP/1 F O P ) is entered.. . (EXIT this procedure)

(4.2) !RIA-54 in alarm inoperable ... (open TBS pump breakers)

(4.73) primary to secondary leak rate is 2 25 gpm ... (GO TO EP/1 (EOP))

(4.77) primary to secondary leakage increases.. . (modify shutdown as required by End 5.1)

A.P/~/A11700/031 Page 3 1 of 35

.-

L ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 1 4.84 Verify entry into this procedure was due to - GO TO Step 4.8 one of the following:

.. .

- gross tube leakage indicated by an increase In normal RC makeup flow

- tritium sample indicating 2 75 gpd primary to seconda$feak 4.85 - GO TO Step 4.9 ~~

4.86 - Verify CSAE off-gas sample and RCS Notify the following to take another sample sample have been requested to verify (within 15 minutes of each other, if possible):

leak rat Group I Sample I

RP

- .~ II CSAE I Primary Chemistry 1 RCS 4.87 - WHEN CSAE off-gas and RCS sample results become available, THEN PERFORM Encl5.4 W (Calculation of Primary to Secondary Leak Rate using CSAE Off-gas and RCS Samples).

4.88 - Log leak rate calculation results in Primary to Secondary Leak Lo .89 Notify the following to enter leak rate calculation results in the Excel leakage spreadsheet:

- Ops Mods Supervisor

- Ops Work Process Manager Administrative Specialist

AP/1/N1700/031 Pase 32 of 35 IF AT ANY TIME: -I L

(4.1) the SGTR tab of EP/1 (EOP) is entered. .. (EXIT this procedure)

(4.2) 1.RIA-54 in alam or inoperable ... (open TBS pump breakers)

(4.73) primary to secondary leak rate is 2 25 gpm. .. (GO TO EP/1 (EOP))

(4.77) primary to secondary leakage increases.. . (modify shutdown as required by Encl 5.1)

P9/1/A/1700/03 1 Page 33 of 35 c

W ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED 1 4.90 - Ensure unit shutdown is in progress to meet the shutdown requirements of

--Encl5.1 (Unit Shutdown Requirements).

4.9 1 - WHEN in MODE 3, THEN continu &

'I 4.92 - Verify leak rate calculation (Step 4.87) 1.- IF OSM desires, confirms shutdown to MODE 5 is THEN stop unit shutdow required due to leakage exceeding 2. - IF unit shutdown is stopped, limits of Encl 5.1 (Unit Shutdown AND only one confirmation of leak rate Requirements).

(per Step 4.87) has been made, THEN perform the following:

A. Notify the following to take a second sample (within 15 minutes of each other, if possible):

Group Sample B. -GO TO Step 4.8 . - IF unit shutdown is stopped, THEN'GO TO Step 4.1 . - GO TO Step 4.9 .93 - WHEN LPI is providing DHR, THEN dispatch an operator to perform Encl5.3 (Local SO Isolation)

to isolate affected SGs. 112) -

.

AP/1/A/1700/031 Page 34 of 35 IF AT ANY TIME:

L (4.1) the SGTR tab of EP/1 (EOP) is entered ... (EXIT this procedure)

(4.2) lRI.4-54 in a l a r m s inoperable .. . (open TBS pump breakers)

(4.73) primary to secondary leak rate is 2 25 gm... (GO TO EP/l (EOP))

(4.77) primary to secondary leakage increases.. . (modify shutdown as required by Encl5.1)

.'

Ap/1/A/1700/03 1 Page 35 of 35

-

I I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.94 Close the following on affected SGs: (12)

1 IFDW-31 llFDW-40 W

llSD-419 11SD-421

~

4.95 - WHEN condenser vacuum is broken, OR in MODE 5, THEN notify W to stop taking CSAE off-gas sample .96 - Notify Primary Chemistry to stop taking non-routine samples as part of their primary to secondary leak rate monitoring proga .97 - EXIT this procedur Enclosure AF'/l/A/1700/031 Resetting 1RTA-40 and OAC Setpoints Page 1 of 3 L

NOTE Xe 133 equivalent activity is required for this calculatio . L Verify CSAE flow rate is on-scal l- PERFORRl Encl5.6 (CSAE Flow Rate Determination).

3. L Obtain CSAE flow rat I ft3/min 4. Determine 1RIA-40 High setpoint from the following formulas:

5. Determine 1RIA-40 Alert setpoint from the following formulas:

Alert RCS (Xe 133eq) activity ( C d m l ) 2.71E+3 (ft')(day)(cpm)

1RIA-40 Alert Setpoint (cpm)= Setpoint X X CSAEflow (fi3/min) (gal)(min)(pCci/ml)

(@d)

6. -Enter the new 1RIA-40 Alert &High Setpoints in the RIA View Nod Enclosure AP/1/A/1700/031 Resetting 1RI.4-40 and OAC Setpoints Page 2 of 3 I THIS PAGE INTENTIONALLY BLANK I

Enclosure AP/ 1/A/1700/03 1 Resetting 1RIA-40 and OAC Setpoints Page 3 of 3 L ACTIONEXPECTED RESPONSE RESPONSE NOT OBTALNED

CRO-O11A fnl Page 1 of 15

REGION II

INITlAL LICENSE EXAMINATlON JOB PERFORMANCE MEASURE CRO-O11A Align Intake Canal For Recirc On Dam Failure CANDIDATE:

L/

EXAMINER:

CRO-O11A fnl Page2of15

REGION II

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ii Task:

Align Intake Canal for Recirc on Dam Failure Alternate Path:

Yes Facility JPM #:

CRO-O11A KIA RatinqM:

System: 075 WA: A2.01 Rating: 3.0/ Task Standard:

Intake Canal ISaligned for recirculation correctly by procedure and an NE0 is dispatched to manually open CCW- Preferred Evaluation Location: Preferred Evaluation Method:

S i m u l a t o r X In-Plant - Perform X Simulate -

i/ References:

"CCW LAKE LEVEL LOW" statalarm (ISA-9, B-10)

AP/I/NI 700/13, Dam Failure Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT __ UNSAT __ Performance Time: __

Examiner: /

NAME SIGNATURE DATE COMMENTS

CRO-O11A fnl Page 3 of 15 SIMULATOR OPERATOR INSTRUCTIONS:

1. Recall Snap 205

'- 2. Import CRO-O11A files 3. Place simulator in RUN

CRO-011A fnl Page4of15 ToolsIEQuiDmentlProceduresNeeded:

AP111AJ1700113, Dam Failure i/ READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:

Dam failure has occurre Intake Canal is intac Unit has been manually trippe Subsequent Actions of AP/l/A/1700/13, Dam Failure have been completed up to step INITIATING CUES:

Control Room Supervisor directs you to align the CCW Intake Canal for recirc following a dam failure beginning at step 4.3 of AP/1/AIl700/13, Dam Failur CRO-O11Afnl Page 5 of 15 START TIME:

STEP: Step 4.3: CRITICAL STEP L

Depress the "CCW DAM FAILURE pushbutton -SAT STANDARD: The "CCW DAM FAILURE pushbutton is located by the candidate on 1AB3 and depresse UNSAT COMMENTS:

STEP: Step 4.4:

Dispatch an individual to the area of the dam failure to report damage to -SAT the Control Room STANDARD: The candidate contacts the Shift Work Manager, or calls the Work Control Center kitchen directly, and dispatches an individual to the area-UNSAT of the dam failure to report damage to the control roo Cue: N E 0 dispatched to the area of the dam failure to report damage to the Control Room COMMENTS:

L STEP: Step GO TO Step 4.45 -SAT STANDARD: The candidate proceeds to Step 4.45 in AP101 UNSAT COMMENTS:

CRO-O11Afnl Page 6 of 15 CRITICAL STEP STEP: Step 4.45:

Stop RCP SAT L

STANDARD: The control switches for RCPs I A l , 1A2, 1B1,l B2 are located by the candidate on I A B I and rotated to the TRIP positio UNSAT The candidate verifies by red run lights off and/or 0 amps indicated that the RCPs are trippe COMMENTS:

-5: Step 4.46:

Ensure all CCW pumps are stoppe SAT STANDARD: The candidate locates the CCW pump light indications on 1AB3 and verifies by red run lights off and/or 0 amps indicated that all CCW pumps are trippe UNSAT COMMENTS:

L STEP: Step 4.47:

Ensure ICCW 1-6 are ope SAT STANDARD: The candidate locates ICCW 1-6 (WATERBOX EMER DISCH) control switch and indications located on 1AB3. The red OPEN indication light-UNSAT is verified o COMMENTS:

CRO-O11A fnl Page 7 of 15

-7 Step 4.48:

Ensure all condenser outlet valves indicate closed (GD AP13): -SAT 01D0273 (ICCW-20 CONDENSER 1A OUTLET 1)

01D0275 (ICCW-21 CONDENSER 1A OUTLET 2)

01DO277 (1CCW-22 CONDENSER 1B OUTLET 1) -UNSAT 01D0279 (ICCW-23 CONDENSER 1B OUTLET 2)

01DO281 (1CCW-24 CONDENSER 1C OUTLET 1)

01DO283 (1CCW-25 CONDENSER 1C OUTLET 2)

STANDARD: The candidate displays OAC Graphics GD AP13 and verifies ICCW-20 through ICCW-25 indicate close The candidate may also display individual points by Point ID or a Group Display to determine ICCW-20 through 1CCCW-25 indicates close COMMENTS STEP: Step 4.49:

Verify CCW-8 is ope SAT STANDARD: CCW-8 switch and indication are located by the candidate on 2AB3 verifying red OPEN light illuminated and green CLOSED light extinguishe UNSAT COMMENTS:

STEP: Step 4.50:

Notify Unit 2 that emergency CCW siphon flow has been established on -SAT Unit STANDARD: The candidate notifies Unit 2 that emergency CCW siphon flow has been -UNSAT establishe COMMENTS:

CRO-O11A fni Page 8 of 15 STEP IO: Step 4.51:

Dispatch operators to perform Enci 5.2 (CCW Inventory Conservation) -SAT L

STANDARD: The candidate contacts the Shift Work Manager, or calls the Work Control Center kitchen directly, and dispatches operators to perform Encl -UNSAT 5.2 (CCW Inventory Conservation).

COMMENTS:

STEP 11: Step 4.52:

IAAT Unit 2 CR has directed Unit 1 to supply CCW recirculation, THEN perform Steps 4.53 - 4.6 SAT STANDARD: The candidate determines where or not Unit 2 has directed Unit 1 to supply CCW recirculatio UNSAT The candidate will proceed to Step 4.53 when informed that Unit 2 directs Unit 1 to supply CCW recirculatio CUE: When the candidate reaches Step 4.52 inform the candidate that Unit 2 directs that Unit I will supply CCW recirculation.

c COMMENTS:

STEP 12: Step 4.53:

Determine which CCW pump will be started-SAT STANDARD: The candidate determines which CCW pump to be starte UNSAT Cue: If asked as the SRO which CCWpump to start, inform candidate to start the I D CCWpum COMMENTS:

CRO-011A fni Page 9 of 15 STEP 13: Step 4.54:

Place CCW Pump switches in the trip position: -SAT L IACWPump I B C W Pump 1CCWPump-UNSAT 1DCWPump STANDARD: The candidate locates the CCW Pump controls on 1AB2 and rotates the I A , I B , I C , and I D CCW Pump control switches to the trip positio COMMENTS:

STEP 14: Step 4.55:

Verify 1A or 1B CCW Pump is to be starte SAT STANDARD: The candidate may ask the Procedure Director which CCW is desired to be starte UNSAT When instructed by the Procedure Director that 1D CCW Pump is to be started, the candidate should refer to the RNO column.

L Cue: Instruct the candidate that the SRO requests that I D CCW Pump be starte COMMENTS:

STEP 15: Step 4.55 RNO:

GO TO Step 4.57 -SAT STANDARD: The candidate should proceed to Step 4.5 UNSAT COMMENTS:

CRO-O11A fnl Page 10 of 15 STEP 16: Step 4.57:

Verify the I C or I D CCW Pump is to be starte SAT L

STANDARD: The candidate determines from the direction given by the Procedure Director that I D CCW Pump is to be starte UNSAT COMMENTS:

STEP 17: Step 4.58 Verify both of the following CCW pump discharge valves are closed: -SAT

. ICCW-12 ICCW-13-UNSAT STANDARD: The candidate verifies that ICCW-12 indicates closed by the green closed light indication on 1AB3 or by OAC indication The candidate verifies that ICCW-13 indicates open by the red open light indication on 1AB3 or by OAC indication The candidate proceeds to Step 5.58 RNO.

L COMMENTS:

CRO-O11A fnl Page 11 of 15 STEP 18: Step 4.58 RNO Dispatch an operator to close the discharge valves from the breaker -SAT i switch (Unit 1 Equipment rm):

Pump Valve Breaker IC ICCW-12 1XS3-2E -UNSAT ID 1CCW-13 1XS1-F3C STANDARD: The candidate dispatches an operator to Unit 1 Equipment Room to close ICCW-1 If the candidate directs the operator to close valves, ICCW-12 and ICCW-13, the operator will inform the candidate that ICCW-13 indicated closed when he arrived to close 1CCW-1 Simulator operator: After the candidate has dispatched an operator to Unit 1s Equipment Room, FIRE TIMER # I TO CLOSE ICCW-12; Cue: Inform the candidate that ICCW-12 and ICCW-13 both indicate closed from equipment roo COMMENTS:

L STEP 19: Step 4.59 CRITICAL STEP Start the selected CCW Pum SAT STANDARD: The candidate locates the control switch for I D CCW Pump on 1AB3 and rotates the control switch to the close positio UNSAT The candidate observes that the ICCW-13 starts to travel open and when approx 20% open, the I D CCW pump starts as indicated by red run light illuminated and amps indicate COMMENTS:

CRO-O11A fnl Page 12 of 15 STEP 20: Step 4.60 Verify the started CCW pump discharge valve opene SAT c

STANDARD: The candidate verifies that ICCW-13 indicates OPEN with a red light indication. The candidate may verify ICCW-13 open by OAC indications. -UNSAT COMMENTS:

STEP 21: Step 4.61 Verify CCWQ (EMERGENCY CCW DISCHARGE TO INTAKE) open -SAT STANDARD: The candidate locates CCW-9 switch and indication on 2AB3 determines that CCW-9 is closed by the red "OPEN" indication off and the green -UNSP

"CLOSED" indication o The candidate should proceed to step 4.61 RN NOTE: CCW-9 will be found CLOSED COMMENTS:

L

CRO-O11A fnl Page 13 of 15 STEP 22: Step 4.61 RNO CRITICAL STEP 1. Stop the operating CCW pump -SAT L Notify Security to meet an operator at the IRW gate to provide access to CCW-9 at the Southwest corner of the Protected Are . Dispatch an operator to perform the following: -UNSAT A. Obtain the CCW-9 IRW Gate Key from Security box in Unit 3 Control Room storage are B. Open CCW-9 (Emergency CCW Discharge to Intake) (between protected area fences).

C. Notify Unit 1 CR when CCW-9 is open D. WHEN notified that CW-9 is open, THEN GO TO Step 4.53 to restart a CCW pum ST m: Locate the control switch for the I D CCW Pump on 1AB2 and rotate the control switch to the trip positio Notify Security that access to CCW-9 (EMERGENCY CCW DISCHARGE TO INTAKE) is required Dispatch an operator to obtain the CCW-9 IRW Gate Key from the Security box in the Unit 3 Control Room Storage are The operator, along with Security, proceeds between the Protected Area fences in order to open CCW-9 Note: When an operator is dispatched to obtain the CCW-9 IRW Gate Key and is L instructed to open CCW-9, END TAS COMMENTS:

END TASK

TOP TIME

CRO-O11A fnl Page 14 of 15 CRITICAL STEP EXPLANATIONS:

i/ STEP# Explanation 1 Step (1) stops all CCW pumps, opens ICCW-1-6, and closes condenser outlet valve Step (4) reduces RCS heat load and prevents RCP damage from inadequate LPS Step (18) required for the start of I D CCW Pump for recirculation back to the intake cana Step (21) ensures the operating CCW pump is stopped and CCW-9 is opened manually to align CCW recirc flo CRO-O11Afnl Page15of15 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

i/ INITIAL CONDITIONS:

Dam failure has occurre Intake Canal is intac Unit has been manually trippe Subsequent Actions of AP/1/N1700/13, Dam Failure have been completed up to step INITIATING CUES:

Control Room Supervisor directs you to align the CCW Intake Canal for recirc following a dam failure beginning at step 4.3 of AP/I/Nl700/13, Dam Failur I -zk$zpP 7*

. NSD 703 (RO4-01) s;@7 -3 Duke Power Company ( I ) lDNo ~ / l l A / 1 7 0 0013

/

brief 440 PROCEDURE PROCESS RECORD Rcvlslon No Rev 18 NPC SR i/ KEPARATION (2) Station OCONEE NUCLEAR STATION (3) Procedure Title Dam Failure (4) Prepared By A.S. Hollingsworth (Signature) Aih,& A - f - b a k # d Date 10-16-02 (5) Requires NSD 228 Applicability Determination?

0 Yes (New procedure or revision with major changes)

Ix] No (Revision with minor changes)

0 No (To incorporate previously approved changes)

(6) Reviewed By (QR) Date lo[Zd~Z Cross-Disciplinary Review By (QR)NA-Date Reactivity Mgmt Review By (QR)NA=Date Mgmt Involvement Review By (Ops Supt) N A A D a t e (7) Additional Reviews Reviewed By Date Reviewed By Date (8) Temporary Approval (ifnecessary)

BY (OSWQR) Date BY (QR) Date (9) Approved By fa Date \Cl'L&Ipl PERFORMANCE (Compare with control copy every 14 c a s a r d a y while work is being performed.)

(IO) Compared with Control Copy Date Compared with Control Copy Date Compded with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification:

0 Unit 0 0 Unit 1 Cl Unit 2 0 Unit 3 Procedure performed on what unit?

0 Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in N 0 Yes 0 NA Required enclosures attached?

Yes 0 NA Data sheets attached, completed, dated, and signed?

0 Yes 0 NA Charts, graphs, etc. attached, dated, identified, and marked?

0 Yes 0 NA Procedure requirements met?

Verified By

'(I 3 ) Procedure Completion Approved 9

,14) Remarks (Attach additionalpages, ifnecessary)

Duke Power Company Procedure No.

b Oconee Nuclear Station AP/1/A/1700/0 13 Revision N Dam Failure 018 Electronic Reference N OXOOZRGO

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I.,.. t Page 1 of 31 1. Entry Conditions -

W of the following:

Loss of CCW Intake Canal CCW Intake Canal intact and dam failui :urs or is imminent 2. Automatic Systems Actions e Possible trip of Main Turbine and FDWP turbines on loss of vacuum e Possible anticipatory Rx trip 3. Immediate Manual Actions None

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AP/l/A/I 7001013 Page 3 of 31 4. Subsequent Actions .-

ii ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINZD Ensure

. Rx is trippe .2 - Verify CCW Intake Canal intac GO TO Step .3 Depress CCW'DAM FAILURE Dushbutto '

- Dispatch an individual to the area of I

the dam failure to report damage to the Control Room .5 - GO TO Step 4.4 .6 - Ensure only one CCW pump I

operatin CAUTION Continued operation of the RCPs will provide heat load with limit'ed cooling capacity and may result inRCP damage due to inadequate LPSW flow. RCP restart when directed by EP/1 POP)

.. should consider these factors. , ,

'4 Stop'aJRCP .8 Dispatch an operator to open the following valve(s) on aJ operable SSW headers:

- HPSW-900 (B HDR SIPHON SEAL WATER (SSW) SYSTEM CONN)

(T-1M-48, IO'S., 15' up)

- HPSW-901 (A HDR SIPHON SEAL WATER (SSW) SYSTEM CONN)

(T-1/J-26, SE, IO' Up)

NOTE CCW-8 must be de-energized prior to submersion by lake water. This should be accomplished within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of initiation of the even CCW Emergency Discharge Siphon Flow may have been established automatically as a result of loss of powe .9 - Verify CCW-8 is open., - GO TO Step 4.1 .10 - Verify lCCW 1-6 are close Ensure lCCW 1-6 throttle . 4.1 1 - Verify 2CCW-7 is close Ensure 2CCW-7 throttle ... . .... . .

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ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.12 - Verify 3CCW-93 is close Ensure 3CCW-93 throttle .13 Close CCW- .14 Ensure the following:

- ICCW 1-6 are close lCCW 1-6 switch in PULLTO, LOC .15 Notify Unit 2 to ensure the following:

- 2CCW-7 is close CCW-7 switch in PULL TO LOC .16 Notify Unit 3 to ensure the following:

- 3CCW-93 is close CCW-93 switch in PULLTO LOC .17 - Dispatch an operator to open I 1DP-FSC (CCW-8 BECR m G CCW DISCH TO TAILRACE))

v (T-3L24).

4.18 Stop glJ Unit 1ESV pumps:

- 1A ESV PUMP

- 1cESV PUMP

- 1B ESV PUMP NOTE The EWST will be used as CCWP sealing water and to cool the following:

HFI pump motor coolers TDEFDWPump

Operating CCWP motors 4.19 Place the following switches in OFF:

- A HPSW PUMP

~~ B HPSW PUMP

Page 6 of 31

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4.20 ' - IAAT of the following is full - GO TO Step 4.2 open:

HPSW-900 (B HDR SIPHON SEAL WATER (SSW) SYSTEM cow HPSW-901 (A HDR SPHON SEAL WATER (SSW) SYSTEM cow, THEN perform Steps 4.21 - 4.2 .21 - Ensure the Unit 1/2 STANDBY LPSW PUMP AUTO START CIRCUIT in DIS.ABL .22 Stop the following pumps:

- A LPSW PUMP

- B LPSW PUMP

-. 'CLPSW PUMP W NOTE The intent is to maintain adequate cooling water inventory while preventing loss through the EWST overflo AFV1/A/1700/013 Page 8 of 31 IF AT

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.. TIME: . .. .. .. .

. . L (4.20) HPSW-900 aHPSW-901 is full open ....(stop LF'SW pumps and cycle HPSW Jockey Pump as necessary) :.:. . . .

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AP/1/A/1700/013 Page 9 of 31 u ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAWED I

I NOTE I Similar instructions are provided in Unit 2 and 3 procedures. The same operator should be used for these task .25 - Ensure an operator has been dispatched to the CCW Intak .26 - Notify operator at CCW Intake to isolate SSW to & I stopped CCW pumps per Encl5.4 @LO Actions at CCW Intake). (PS)

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AP/1/A/1700/013 Page 10 of 31

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., .. L (4.20) . -.HPSW-900EHPSW-901 is full open .;. ,(stop LPSW pumps and cycle HPSW Jockey

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Pump as necessary)

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Page 11 of 31 L ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.27 - IAAT RCP seal injection is 1 THEN dispatch an operator to perform AFV25 (SSF EOP) to i the SSF RCMU syste .28 - MAT & the following exist: - GO TO

Step 4.3 Loss of power occurred on Power has been restored to Unit 1 Keowee Lake Level > 775' (6)

THEN perform Steps 4.29 - 4.36 to start one CCW pum .29 - Ensure Pressurizer Heaters are in AUT (4)

-

NOTE At least one CCW Pump discharge valve is required to remain open prior to establishing forced flo The adjacent CCW Pumps discharge valve must be closed to prevent excessive torque on the W starting pumps discharge valve. The 1A and 1B CCW Pumps are adjacent, and the 1C and 1D CCW Pumps are adjacen Similar instructions are provided in Unit 2 and 3 procedures. The same operator should be used for these task .. .

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AP/1/N1700/013

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Page 12 of 31 IF AT ANY TIME:

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.. .. L (4.20) HPSW-900 or HPSW-901 is full open ... (stop LPSW pumps and cycle HPSW Jockey Pump as necessary)

(4.27) RCP seal injection is lost ... (dispatch an operator to operate SSF RCMU)

(4.28) Loss of power occurred on Unit 1, power is restored, and Keowee Lake Level > 775' (6) ...

(restart a CCW pump)

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775' (6)...

(restart a CCW pump)

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APl~lA/1700/013 Page 15 of 31 L ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.36 - WHEN SSW is aligned to the pump, AND the discharge valves are closed, THEN start the CCW pum .37 - IAAT Keowee Lake Level 5 775' (6), - GO TO Step 4.4 AND CCW-8 Bkr is open, THEN perform Steps 4.38 - 4.4 .38 - Stop all CCW pump NOTE Similar instructions are provided in Unit 2 and 3 procedures. The same operator should be used for W

these task .40 - Notify the operator performing

.

Encl5.4 (NLO Actions at CCW Intake) to isolate SSW to a U N t 1 CCW pump .41 - Notify TSC to replenish Unit 2 CCW intake line .42 - Notify Emergency Coordinator to review Encl 5.5 @am Failure Considerations).

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4.43 - WHEN secondary heat removal systems are near depletion, THEN initiate AP125 (SSF EOP) in preparation for feeding the SGs with SSF AS .44 - WHEN conditions permit, THEN EXIT this procedure.

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AP/llA11700/013 Page 16 of 31

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AF'/1/A/1700/013 Page 17 of 31 L ACTIONlEXPECTED RESPONSE RESPONSE NOT O B T A N D I
CAUTION Continued operation of the RCPs will provide heat load with limited cooling capacity and may result in RCP damage
- due to inadequate LPSW flow. RCP restart when directed by EP/1 (EOP)
should consider these factor .45 - StopalJRCP .46 - Ensure & CCW l pumps are stoppe .47 - Ensure lCCW 1-6 are ope .48 Ensure & I condenser outlet valves indicate closed (GD AP13):
- OlD0273 (1CCW-20 CONDENSER 1A OUTLET 1)'
- OlD0275 (1CCW-21 CONDENSER 1A OUTLET 2)
.. .- - OlD0277 (1CCW-22 CONDENSER 1B OUTLET 1)
- OlD0279 (1CCW-23 CONDENSER W 1B OUTLET 2)
- 01D0281(1CCW-24 CONDENSER 1C OUTLET 1)
- 01130283 (1CCW-25 CONDENSER 1C OUTLET 2)
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AP/1/A/1700/0 13
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AP/1/A/17Oo/O13 Page 19 of 31 L
ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE CCW-8 shpuld open after the CCW DAM FAILURE pushbutton is pressed and the first Waterbox Emergency Discharge valve (ICCW-1-6) opens. If CCW-8 does not open, it should be left closed in preparation for CCW recirculatio .49 - Verify CCW-8 is ope . - IF emergency CCW siphon flow has NOT been established on Unit 1, THEN notify Unit 2 that emergency CCW siphon flow has NOT been established on Unit .- GO TO Step 4.5 .50 - Notify Unit 2 that emergency CCW siphon flow has been established on Unit NOTE i/ Unit 2 CR will decide which unit will establish CCW recirculation. Unit 1 will only supply CCW recirculation when directed by Unit .52 - IAAT Unit 2 CR has directed Unit 1 - GO TO Step 4.6 to supply CCW recirculation, THEN perform Steps 4.53 - 4.67 to start one CCW Pump andestablish recirculatio I -
NOTE At least one CCW Pump discharge valve \
is required to remain open prior to establishing forced flo The adjacent CCW Pumps discharge valve must be closed to prevent excessive torque on the starting pumps dischaige valve. The 1A and 1B CCW Pumps are adjacent, and the I C and 1D CCW Pumps are adjacen .53 - Determine which CCW Pump will be started.
W
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Page 21 of 31 I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAMIZD 1 4.54 - Place CCW Pump switches in the trip position:
4.55 - Verify the 1A or 1B CCW Pump is to - GO TO Step 4.5 be starte .56 - Verify both of the following CCW - Locally close the discharge valves from pump discharge valves are closed (5 the breaker switch (Unit 1 Equipment rm):
. .,.,
1B I I ICCW-1 ' .,. ,. ' , !$,
I l B I I ICCW-11 IlXS2-F2D I 4.57 - Verify the 1C or 1D CCW Pump is to - GO TO Step 4.5 be starte .58 - Verify both of the following CCW - Locally close the discharge valves from pump discharge valves are closed: (s the breaker switch (Unit 1 Equipment rm):
I l D I I 1ccw-13 I I l D I I 1ccw-13 Ilxsl-mc I
'4P/1IAI1700/013 Page 22 of 31
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APl1/A/1700/013 Page 23 of 3 1 I
NOTE I I CCW pump amps and temperatures will read higher than normal when started with this plant confieura&on. CCWP motor stator temDerature limit is 284° I 4.59 - Start the selected CCW Pum .60 - Verify the started CCW pump 1.- Stop the operating CCW pum discharge valve opene . - GO TO Step 4.54 to attempt to start a different CCW pum .61 - Verify CCW-9 is ope .- Stop the operating CCW pum . - Notify Security to meet an operator at the IRW gate to provide access to CCW-9 at the Southwest comer of the Protected Are . Dispatch an operator to perform the following:
A. -Obtain the CCW-9 IRW Gate Key from the security box in Unit 3 Control Room storage are B. -Open CCW-9 @MERGENCY CCW DISCHARGE TO INTAKE) (between protected area fences).
C. -Notify Unit 1 CR when CCW-9 is ope .- WHEN notified that CCW-9 is open, THEN GO TO Step 4.53 to restart a CCW pum AP/1/A/1700/0 13 Page 24 of 3 1
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AP/1/A/1700/013 Page 25 of 31
._I ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED J 4.62 - Verify CCW-8 is close .- Stop the operating CCW pum .- Dispatch an operator to open 1DP-F5C (CCW-8 BKR (EMERG CCW DISCH TO TAILRACE)) (T-3L-24).
3. - Dispatch two operators to close CCW-8 (EMERGENCY CCW DISCHARGE TO TAILRACE) (Beside tailrace 3' N of 8'
drain pipe under middle valve pit cover).
4.- WHEN CCW-8 is closed, THEN GO TO Step 4.53 to restart a CCW uum I .
1 I I
CCW-8 must be de-energized prior to submersion by lake water. This should be accomplished within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of initiation of the even .63 - Ensure an operator has been I
dispatched to open v IDP-F5C (CCW-8 BKR (EMERG CCW DISCH TO TALLRACE))
(T-3L-24).
4.64 Ensure the discharge valves on & stopped l
CCW pumps are closed:
4.65 - Notify Unit 2 and Unit 3 to ensure &I
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Unit 2 and Unit 3 CCW pump discharge valves are close .~
AP/l/A/ 1700/013 Page 26 of 31
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(4.52) Unit 1 is to supply CCW recirculation ... (start a CCW pump and align for recirculation) ....
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APll/A/1700/013 Page 27 of 3 1
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ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAIh'ED I
IThe purpose of the following steps is to force CCW NOTE inlet flow to the other two units through the I
CCW inlei cross-connects to establish > 7" vacuum for TBV operability. Unit 2 and Unit 3 personnel will provide information about the effects of the following actions on their condenser vacuu .66 - Throttle ICCW 1-6 as necessaxy to establish > 7" vacuum on Unit 2 and Unit .67 - WaEN condenser vacuum on three units is being maintained > 7" vacuum, TREN stop adjusting 1CCWl- NOTE CCW pump discharge valves act as throttle valves from the breaker switches unless the respective CCW pump switch is positioned to TRI .68 - IAAT another unit is to supply CCW recirculation, AND requests &Unit 1 CCW pump discharge valves closed, THEN perform the following:
A. Dispatch an operator to close the following valves from the breaker switches (Unit 1Equipment Rm):
I ICCW-13 I
I lXSI-F3C I B. - Monitor Unit 1 condenser vacuum while CCW recirculation is established on another uni C. - Communicate condenser vacuum changes to the unit supplying CCW recirculation flo ., .
. .. . ...,.,: AP/l/AJ1700/013
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(4.52) Unit 1 is to supply CCW ,recirculation ... (start a CCW pump and align for recirculation)
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on and requests all Unit 1CCV PUYP. .discharge.; , .
. I close
. . the valves, monitor vacuum)
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W GO TO Step 4.7 A MDEFDW VALVE switch in the BYPASS position (T-l/D-25,24'E, SG FDW
~
W NOTE EWST will be used to cool HPI Pump Motor Coolers and T!XFDW Pum I -
NOTE I The intent is to maintain adequate cooIing water inventory while preventing loss through the EWST overflo .74 - Maintain EWST level
>70,000 gallons and < OVEF@LOW by cycling HPSW JOCKEY PUMP as necessar AP/1/A/1700/013 Page 30 of 31 IFATA . . . . . . . . . . . . . . . . . . . ."
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(4.52) Unit 1 is to supply CCW recirculation ... (start a CCW pump. and ...
align for recirculation)
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and requests"aJUnit 1 CCW' pump discharge "
h an operator to'close
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API1IAI1700/0 13 Page 31 of 31 L ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.75 - IAAT operating IvJ?EFDWP motor stator temperatures > 21OoF, T m N consult Station Management for guidance about stopping MDEFDWP .76 - Notify Emergency Coordinator to review Eccl5J-(Dm Failure Considerations).
4.77 - Initiate Encl 5.1 (LPSW Recirc Lineup).
4.78 - WHEN conditions permit, THEN EXIT this procedur NLO-022 fnl Page 1 of 12
REGION II
INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE N LO-022 ALIGN AND START THE STATION AUXILIARY SERVICE WATER PUMP b
CANDIDATE EXAMINER
NLO-022 fnl Page 2 of 12
REGION II
INITIAL LICENSE EXAMINATION Ll JOB PERFORMANCE MEASURE Task:
Align and start the Station Auxiliary Service Water Pump Alternate Path:
No Facilitv JPM #:
NLO-022 KIA Ratinqb):
System: APE-054 WA: AA1.01 Rating: 4.5/ Task Standard:
Station Auxiliary Service Water Pump is aligned and started correctly by procedur Preferred Evaluation Location: Preferred Evaluation Method:
Simulator -In-Plant Perform -Simulate
'u References:
Enclosure 5.10, Station ASW Pump Alignment, of the EOP Candidate: Time Start:
NAME Time Finish:
Performance Rating: SAT -UNSAT - Performance Time -
-
NLO-022 fnl Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS:
NONE L
NLO-022 fnl Page 4 of 12 ToolslEquipmenffProcedures Needed:
Enclosure 5.10, Station ASW Pump Alignment, of the EOP ii READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:
1. A station blackout has occurre . No EFDW pumps are availabl . HPI forced cooling is not adequat . The SSF DIG failed to start rendering the SSF ASWP inoperable.
L, 5. Power has been restored to the standby buse . SG pressure is = atmospheri INITIATING CUES:
The BOP directs you perform Enclosure 5.10 (Station ASW Pump Alignment) of the EO NLO-022 fnl Page 5 of 12 START TIME:
ii 1:- Step 1 Obtain racking equipment and pipe wrench from EOP equipment locker U2AB1 (A-I, hallway near U2 elevator lobby). -SAT STANDARD: Candidate locates equipment locker and indicates they would open locker and obtain the racking equipment and pipe wrenc UNSAT Note: For this JPM the equipment locker should not be opene COMMENTS:
-2: Step 2 CRITICAL STEP Open CCW-99 (Aux. Service Water Pump Suction)
-SAT STANDARD: Candidate locates and opens CCW-99 (Aux. Service Water Pump Suction) by turning the hand wheel counter-clockwise until the valve indicator indicates ope UNSAT Cue: Indicate CCW-99 valve position indicator indicates, ope COMMENTS:
STEP: Step 3 CRITICAL STEP Open CCW-247 (Aux. Service Water Pump Recirc.).
STANDARD: Candidate locates and opens CCW-247 (Aux. Service Water Pump-SAT Discharge) by turning the valve hand wheel counter-clockwise until it reaches a hard sto UNSAT Cue: Indicate CCW-247 open (rising stem) and at the hard sto COMMENTS:
NLO-022 fnl Page 6 of 12 c STEP: Step 4 CRITICAL STEP Open CCW-308 (Aux. Service Water Pump Vent.)
-SAT STANDARD: Candidate locates and opens CCW-308 (Aux. Service Water Pump Vent).
Candidate should indicate they would use a wrench to remove the pipe -UNSAT Plu Cue: Indicate CCW-308 open with air and water coming out of the vent. If the candidate does not remove the plug indicate that nothing is coming out of the vent COMMENTS:
5- Step 5 CRITICAL STEP WHEN gJ air is vented from Station ASW Pump, THEN close CCW-30 SAT STANDARD: Candidate locates and closes CCW-308 (Aux. Service Water Pump Vent). -UNSAT b
Cue: Indicate that a solid stream of water is issuing out of the ven COMMENTS:
NLO-022 fnl Page 7 of 12 L STEP: Don protective equipment-SAT STANDARD: Candidate dons the appropriate personal protective equipment prior to operation of any electrical breaker rated 400 VAC and above:
Safety glasses -UNSAT Face shield Hard hat Rubber gloves with leather protectors Flame-resistant clothing Note: This step should be simulated and discussed, at the discretion of the examiner. This is the equipment obtained in step COMMENTS:
STEP: Step 6 CRITICAL STEP Rack in ASWS-6B (STATION ASW PUMP BKR) (ASW SWGR 600V LOAD CENTER Unit 6).
-SAT STANDARD: Candidate locates breaker and opens shutter door, inserts 600V rack out tool. and rotates tool clockwise to rack breaker in.
L-UNSAT Cue: After breaker is racked in, indicate to candidate that the AUX SERVICE WATER PUMP MOTOR breaker green open indicating light is ON and when the racking tool is removed the shutter drop COMMENTS:
NLO-022 fnl Page 8 of 12 L
Step 7 Ensure closed ASW SWGR FDR (ASW SWGR FDR FROM BIT-UNITIO) (ASW SWGR 600V LOAD CENTER Unit 5 ) -SAT STANDARD: Candidate locates the ASW SWGR FDR control switch and rotates it to the CLOSE directio UNSAT RED Closed lamp is observed to be illuminated OR Breaker position flag is observed to indicate Close UE: lndicate to candidate that the 4160V Feeder Breaker for the "AUX SER W R SWGR TRANSFORMER" red light is li :OMMENTS:
9- Step 8 CRITICAL STEP WHEN notified that Standby Bus # I is energized, THEN oerform the followina (ASW SWGR 600V LOAD CENTER Unit 5): -SAT Ensure closed ASW TkANSFORMER FDR (ASW SWITCHGEAR L
. TRANSFORMER FDR).
Start Station ASW Pump using the control switch STATION ASW PUMP S UNSAT
TANDARD

Candidate locates the ASW TRANSFORMER FDR (ASW SWITCHGEAR TRANSFORMER FDR) Breaker control switch and rotates it to the CLOSE directio RED Closed lamp is observed to be illuminated OR Breaker position flag is observed to indicate Close Candidate locates AUX SERVICE WATER PUMP MOTOR control switch and rotates switch to the CLOSE positio CUE: Indicate to candidate that Standby Bus #I is energize CUE: After control switch is rotated, indicate to candidate that the AUX SERVICE WATER PUMP MOTOR breaker red "closed" indicating light is ON and you can hear the pum COMMENTS:
NLO-022 fnl Page 9 of 12
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STEP 12: Step 9 CRITICAL STEP L
Close CCW-309 (Aux Service Water Pump Disch Drain) (12' West of ASW Pump). -SAT STANDARD: Candidate locates and closes CCW-309 (Aux. Service Water Pump Disch Drn) is manually closed by turning the valve clockwise until it -UNSAT reaches a hard sto Cue: Indicate CCW-309 closed and at the hard sto COMMENTS:
STEP 13: Step 10 CRITICAL STEP Open CCW-101 (Aux Service Water Pump Discharge),
-SAT STANDARD: Candidate locates and opens CCW-101 (Aux. Service Water Pump Discharge) by turning the valve hand wheel counter-clockwise until it reaches a hard sto UNSAT Cue: Indicate CCW-IO1 open (rising stem valve) and at a hard stop.
L COMMENTS:
STEP 14: Step 11 Verify Turbine Building flood is NOT in progres SAT STANDARD: Candidate determines that a Turbine Building flood is NOT in progress Cue: Indicate that a Turbine Building flood is NOT in progres UNSAT COMMENTS:
NLO-022 fnl Page 10 of 12 c STEP 15: Step 12 Notify CRO that Station ASW Pump is operatin SAT STANDARD: Using either the phone or a radio inform the CRO is that Station ASW Pump is operatin UNSAT COMMENTS:
END TASK STOP TIME:
NLO-022 fnl Page 11 of 12 CRITICAL STEP EXPLANATIONS:
ii STEP # Explanation 2 Step necessary to align pump suction 3 Step is necessary so that the pump can have the minimum flow that is necessary for pump protection until flow to the steam generators is establishe Step is necessary to prevent damage to the pump due to air bindin Step is necessary to prevent flooding of the Aux. Bldg when the Aux. Service Water Pump is starte Step is necessary to power the Aux. Service Water Pum Step is necessary to power the Aux. Service Water Pum Step is necessary to start the Aux. Service Water Pum Step is necessary to prevent flooding of the Aux. Bldg when flow is established to the SGs.
L/ 13 Step is necessary to provide a flow path of water to the necessary components, in this case the steam generator NLO-022 fnl Page 12 of 12 CANDIDATE CUE SHEET u (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
1. A station blackout has occurre . No EFDW pumps are availabl . HPI forced cooling is not adequat . The SSF D/G failed to start rendering the SSF ASWP inoperabl . Power has been restored to the standby buse . SG pressure is is atmospheri INITIATING CUES:
The BOP directs you perform Enclosure 5.10 (Station ASW Pump Alignment) of the EO Enclosure 5.10 EP/l/A/I 800/001 Station ASW Pump Alignment Page 1 of 3 CHG 3 m v
ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAIhTD
-
All equipment operated in the following st 8s is located in A-1-128, ASW PumpR I 1. - Obtain rackmg equipment and pipe wrench from EOP equipment locker U2AB1 (A-1, hallway near U2 elevator lobby).
2. -Open CCW-99 ( A m SERVICE WATER PUMP SUCTION).
3. -Open CCW-247 (AUX. SERVICE WATER PUMP RECIRC).
4. -Open CCW-308 ( A m . SERVICE WATER PUMP VENT).
5. -yITHEN & l is vented from Station air ASW Pump, THEN close CCW-30 . -Rack in ASWS-6B (STATION ASW PUMP BKR) (ASW SWGR 600V LOAD CENTER Unit 6).
7. -Ensure closed ASW SWGR FDR (ASW SWGR FDR FROM B 1T- UNIT 10)
(ASW SWGR 600V LOAD CENTER Umt 5 ) .
8. -WHEN notrfied that Standby Bus #1 is energized, THEN perform the following (ASW SWGR 600V LOAD CENTER Umt 5):
A. -Ensure closed ASW TRANSFORMER FDR (ASW SWITCHGEAR TRANSFORMER FDR).
B. -Start Station ASW Pump using the control switch STATION ASW PUMP s . -Close CCW-309 ( A m SERVICE L/ WATER PUMP DISCH DRAIN)
(12' West of ASW Pump).
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10. -Open CCW-101 (AUX SERVICE WATER P U " DISCHARGE).
11. -Verify Turbine Building flood is NOT in 1.- Notify &IControl Rooms that Station progres ASW Pump is operatin . - GO TO Step 1 ___
12. -Notify CRO that Station ASW Pump is operatin . -WHEN Station ASW Pump is no longer needed in Unit 1, THEN continue in this enclosur . Verify &Ithe following conditions exist: - GO TO Step 1 Station ASW Pump is NOT supplying SGs in other uni Station ASW Pump is NOT needed to supply HPI pump motor coolers in uni . -Stop Station ASW Pump using the control switch STATION ASW PUMP SW (ASW SWGR 600V LOAD CENTER Unit 5 ) .
16. Close the following:
- CCW-99 (AUX. SERVICE WATER PUMP SUCTION)
- CCW-101 (AUX. SERVICE WATER PUMP DISCHARGE)
- CCW-2.47 (AUX. SERVICE WATER PUMP RECIRC)
17. -Open CCW-309 (AUX SERVICE WATER PUMP DISCH DRAIN)
(12'West of ASW Pump).
~
18. -Rack out ASWS-6B (STATION ASW PUMP BKR) (ASW SWGR 600V LOAD CENTER Unit 6).
19. -EXIT this enclosur CRO-047 fnl Page 1 of 13
REGION II
INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE CRO-047 Emergency start SSF Diesel Generator and supply power to the SSF ASW and SSF RCMU pumps CANDIDATE:
EXAMINER:
CRO-047 fnl Page 2 of 13
REGION II
INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Emergency start SSF Diesel Generator and supply power to the SSF ASW and SSF RCMU pumps Alternate Path:
Yes Facility JPM #:
CRO-047 KIA Ratina(s):
System: 062 KIA: A2.11 Rating: 3.71 Task Standard:
SSF Diesel Generator is emergency started aligned to supply power to the SSF ASW and SSF RCMU pumps correctly by procedur Preferred Evaluation Location: Preferred Evaluation Method:
Simulator -In-Plant X Perform -Simulate u References:
APIOIA/1700125 (SSF EOP)
Validation Time: 10 minutes Time Critical: Yes Time Critical Time: 13 min. 29 sec
________________________________________------------------------
______-_________________________________------------------------
Candidate: Time Start:
NAME Time Finish:
Performance Rating: SAT -UNSAT - Performance Time: -
Examiner: I NAME SIGNATURE DATE COMMENTS
__
CRO-047 fnl Page 3 of 13 SIMULATOR OPERATOR INSTRUCTIONS:
None ii
CRO-047 fnl Page 4 of 13 ToolslEauiDrnenVProcedures Needed:
APIOINI 700I25 (SSF EOP)
ii READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:
Unit 2 was operating at 100% power, Unit 2 TD EFDWP is out of servic INITIATING CUES:
Unit 2 Reactor has just tripped and experienced a complete loss of AC power. During the performance of Immediate Manual Actions, the OATC notified the Control Room SRO that HPI seal injection and Component Cooling have been lost and that the SSF must be activated. The Control Room SRO directs you to utilize AP/O/A/1700/025 (SSF EOP) to activate the SSF. No Operators have been staged at the SS CRO-047 fnl Page 5 of 13 START TIME:
I STEP: Step SAT Determine which SSF Systems are required:
-UNSAT STANDARD: Recognizes the initial conditions determine that SSF RCMU Pump flow is required. With no source of FDW available SSF ASW flow is also require Continue to Step Cue: SSF ASW feed is required to SGs due to NO source of available FD COMMENTS:
STEP: Step SAT Ensure RCPs on affected Units are of UNSAT STANDARD: Determine that all RCPs are of Continue to Step CUE: If asked, inform candidate of the following:
All RCP white lights on All RCP red lights off COMMENTS:
CRO-047 fnl Page 6 of 13 STEP: Step SAT L Verify a Licensed Operator staged in SSF to perform AP/25 (SSF EOP). (PS)
-UNSAT STANDARD: Determine that SSF Operator has NOT been stage Continue to RNO for Step COMMENTS:
CRITICAL STEP
4- Step 4.3 RNO 1. Obtain the following items: -SAT Vital area access keyring Flashlight -UNSAT 2. Proceed to SSF HVAC Roo . GO TO Step 4.5 L
STANDARD: Candidate proceeds to supply room and identifies the location of the dedicated flashlight and the required keys to be carried to the SS Candidate proceeds to the SSF with the A GO TO Step CUE: When the flashlight and keys are located, inform the candidate that he/she is NOT required to actually carry them to the SSF for the purposes of this JP COMMENTS:
CRO-047 fnl Page 7 of 13 r
I- STEP 5: Step CRITICAL STEP Perform the following on the affected unit: -SAT Open 2XSF-F5A (3,2, IXSF NORM INCOMING FDR BKR FROM 2x8-58) and remove Kirk Key Using the Kirk Key, close 2XSF-F3A (2XSF ALTERNATE iNCOMlNG -UNSAl FDR BKR FROM OXSF-5A, 5B. or 5C)
STANDARD: NORMAL INCOMING FDR BKR is opened by rotating breaker switch to the OFF position and removing Kirk Ke Compartment 5A on the affected unit's XSF MCC:
2XSF ALTERNATE INCOMiNG FDR BKR is closed in by inserting Kirk Key and rotating breaker switch to the ON positio Compartment 3A on the affected unit's XSF MCC:
2XSF Continue to Step NOTE: Kirk Key must be rotated %turn to be remove CUE: As operator performs the key/breaker operation, indicate to operator the appropriate component position NOTE: Step 5 will power the SSF Systems from OXSF. Power supply for 600V MCC 2XSF, located in HVAC Roo COMMENTS:
6- Step CRITICAL STEP Press DIESEL EMERGENCY START pushbutton -SAT STANDARD: The SSF Control Room DiESEL EMERGENCY START pushbutton is presse UNSAT CUE: Allow - Continue to Step sec for the D/G to reach rated spee COMMENTS:
CRO-047 fnl Page 8 of 13
-7 Step SAT L Verify DIG frequency 59.8 - 60.2 H STANDARD: The DIG HERTZ meter is monitored to determine frequency is low. -UNSAT Continue to Step 4.7 RN CUE: Indicate D/G frequency is 57 Hertz on the SSF Control Room D/G HERTZ mete COMMENTS:
CRITICAL STEP STEP: Step 4.7 RNO Adjust GOVERNOR CONTROL to obtain DIG frequency 59.8 - 6 SAT STANDARD: The GOVERNOR CONTROL is used to raise DIG frequency to between 59.8 - 6 UNSAT Continue to Step 4.8.
L CUE: After candidate indicates the GOVERNOR CONTROL would be used to raise D/G frequency indicate D/G frequency is 60 Hertz on the SSF Control Room DIG HERTZ mete COMMENTS:
CRO-047 fnl Page 9 of 13
9-1 Step SAT Verify DIG voltage 4100 - 4200V.
L STANDARD: The DIG AC VOLTS meter is mor rmine voltage -UNSAT Continue to step CUE: Indicate D/G voltage is 4160 volts on the SSF Control Room D/G AC VOLTS mete COMMENTS:
STEP I O : Step SAT Verify SSF DIG operating STANDARD: Acknowledges successful completion of previous steps indicates SSF DIG is operatin UNSAT Continue to Step 4.10 L COMMENTS:
CRO-047 fnl Page 10 of 13 I STEPII: Step 4.10 CRITICAL STEP i Open breaker OTSI-1 (SSF NORMAL POWER SUPPLY BREAKER -SAT B2T).
STANDARD: TRIP pushbutton on the SSF OTSl-1 (SSF NORMAL POWER SUPPLY -UNSAT BREAKER B2T) control switch is presse Continue to Step 4.1 1 Cue: Inform student that the green light for OTSI-1 (SSF NORMAL POWER SUPPLY BREAKER B2T) is on and the red light is of Note: FOR UNIT 2 ONLY: On a loss of power to Unit 2,OTSl-1 would have already tripped ope Note: Steps 4.10 - 4.12 will Align the DIG to supply the SSF load COMMENTS:
STEP 12: Step 4.1 1 CRITICAL STEP WHEN 3 seconds have elapsed, -SAT THEN close breaker OTSI-4 (DIESEL GEN BREAKER),
L STANDARD: Three seconds after OTSl-1 is opened, the red CLOSE pushbutton on the SSF Control Room OTSI-4 (DIESEL GEN BREAKER) switch is-UNSAT presse Continue to Step 4.12 CUE: After student closes in diesel generator breaker, inform h i d h e r that red light is on and green light is of COMMENTS:
CRO-047 fnl Page 11 of 13 I T E P 13: Step 4.12 i Ensure the following breakers are closed:
-SAT OTSI-3 (SSF 600V OXSF FDR BKR CONTROL)
OXSF-4B (SSF LC OXSF 600V INC BKR)
-UNSAT STANDARD: Red CLOSE breaker position indicating light is observed to be ON at the SSF OTSl-3 (SSF 600V OXSF FDR BKR CONTROL) switc CUE: Inform student the red light is on and the green light is of Red CLOSE breaker position indicating light is observed to be ON at the (SSF OXSF-4B SSF LC OXSF 600V INC BKR) switc CUE: lnform student the red light is on and the green light is of COMMENTS:
END TASK STOP TIME:
ii
CRO-047 fnl Page 12 of 13 CRITICAL STEP EXPLANATIONS:
ii STEP # Explanation 4 Step is necessary to gain access to the SSF during a blackou Step must be performed to power the SSF from the DieseVGenerato Step must be performed to start the diesel and get power for the SS Step is necessary to ensure D/G frequency is correc Step is necessary to power the SSF load Step is necessary to power the SSF load CRO-047 fnl Page 13of 13 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Unit 2 was operating at 100% power.
Unit 2 TD EFDWP is out of service.
INITIATING CUES:
Unit 2 Reactor has just tripped and experienced a complete loss of AC power. During the performance of Immediate Manual Actions, the OATC notified the Control Room SRO that HPI seal injection and Component Cooling have been lost and that the SSF must be activated. The Control Room SRO directs you to utilize AP/O/AI1700/025 (SSF EOP) to activate the SSF. No Operators have been staged at the SS ~~~
mwv m s:fi n)
NSD 703 (RO4-01) &?. Duke Power Company (IIIDNo AP/O/A11700/025 (A rief PROC Revision No 025 I/$
KLP iREPARATION s6/=
(2) Station NRC (3) Procedure Title Standby Shutdown Facility Emergency Operating Procedure
~
(4) Prepared By Kevin McMurray (Signature) ,J&-mwmc Date 07/13/02 (5) Requires NSD 228 Applicability Determination?
Yes (New procedure or revision with major changes)
No (Revision with minor changes)
No (To incorporate pr (6) Reviewed By i
(QR) Date l(/tbL Cross-Disciplinary Review By (QR)NA&Date Reactivity Mgmt Review By (QR)NA M D a te Mgmt Involveinent Review By (Ops Supt) N A B D a t e (7) Additional Reviews Reviewed By Date Reviewed By Date (8) Temporary Approval (ifnccessuy)
J BY (OSWQR) Date BY (QR) Date (9) Approved By Wl02 PERFORMANCE (Compare with control c (IO) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification:
0Unit 0 0Unit 1 0 Unit 2 Unit 3 Procedure performed on what unit?
0 Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in Yes 0 NA Required enclosures attached?
0 Yes 0 NA Data sheets attached, completed, dated, and signed?
0 Yes NA Charts, graphs, etc. attached, dated, identified, and marked?
Yes ! I Procedure requirements met?
NA Verified By Date 13) Procedure Completion Approved Date 14) Remarks (Attach additional puges)
AP/O/A/1700/025 Revision 025 ChangeNo. -
Page 1 of 1 ii SUMMARY OF CHANGES: (DESCRIPTION AND REASON)
General Changes In Enclosure 5.4B (Unit 1 MS Line Valve Breaker Checklist), changed the following breaker locations: 2MS-17 to "2XGB-F1DB", 2MS-26 to "2XA-F5C", 2MS-76 to "2XA-F5AT, and 2MS-79 to "2XA-F6AT per NSM 2306 PCR Numbers Incorporated 2002-3479
Duke Power Company Procedure No.
d Oconee Nuclear Station APIOIA/17Q0/025 Revision N Standby Shutdown Facility Emergency Operating 025 Procedure Electronic Reference N OXOO2RG2
AP/o/A/1700/025 Page 1 of 15 1. Entry Conditions ii Directed by another A p or the EOP 10 CFX 50 Appendix R fire in any fire zone except West Pen Rms Security event 2. Automatic Systems Actions None 3. Immediate Manual Actions None
AP/o/A/ 1700/025 Page 2 of 15 THIS PAGE INTENTIONALLY BLANK b
AP/O/A/17001025 Page 3 of 15 4. Subsequent Actions W
I I NoTE SSF RCMU is required when CC and RCP seal injection are lost to the RCP I SW feed is required to SGs when NO source of FDW is availabl .1 Determine which SSF systems are ,
required:
SSF RCMU I SSFASWfeed Ensure RCPs on affected Units are off:
W B1
~ ~- Verify a Licensed Operator staged in 1.- Obtain the following items:
SSF to perform APl25 (SSF EOP).
Vital area access keyring PS)
Flashlight 2. - Proceed to SSF HVAC Room GO TO Step Step To continue this procedure at Step AP/O/N1700/025 Page 4 of 15
AP/o/AI1700/025 Page 5 of 15 L
ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINEB 1x8-5B) and remove &rk Ke Using Kirk Key, close 1XSF-F3A (1XSF ALTERNATE INCOMING FDR BKR FROM OXSF-5A)
Open 2XSF-F5A (2XSF NORM INCOMING FDR BKR FROM 2x8-5B) and remove Kirk Ke Using &rk Key, close 2XSF-BA (2XSF ALTERNATE INCOMING FDR BKR FROM OXSF-5B)
Open 3XSF-FSA (3XSF NORM INCOMING FDR BKR FROM 3x8-5B) and remove Kirk Ke Using Kirk Key, close 3XSF-F3A (3XSF ALTERNATE INCOMING FDR BKR FROM OXSF-5C) Press DIESEL EMERGENCY START push butto .1 - Verify D/G frequency 59.8 - 60.2 H Adjust GOVERNOR CONTROL to obtain D/G frequency 59.8 - 60.2 H .8 - Verify D/G voltage 4100 - 4200 Adjust VOLTAGE REGULATOR to obtain DIG voltage 4100 - 4200 .9 - Verify SSF D/G operatin .- PERFORM Encl5.6 (Powering SSF from Unit 2 MFB). (4)
2. - GO TO Step 4.1 .10 - Open breaker OTS1-1 (SSF NORMAL POWER SUPPLY BREAKER B2T).
4.11 - WHEN 3 seconds have elapsed, THEN close breaker OTS 1-4 (DIESEL GEN BREAKER).
AF'/o/A/1700/025 Page 6 of 15 THIS PAGE INTENTIONALLY BLANK
AP/o/A/1700/025 Page 7 of 15
- ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.12 Ensure the following breakers are closed
- . OTS1-3 (SSF 600V OXSFFDR BKR CONTROL)
- OXSF-4B (SSF LC OXSF 600V INC BKR)
4.13 - Ensure Diesel Engine Service Water Pump operatin .14 - StartSSFASWPUM .15 PERFORM the following enclosures on
-
all affected units:
- Encl 5.1A (Emergency Operation of SSF Systems Unit 1) (PS)
- Encl 5.1B (Emergency Operation of SSF Systems Unit 2) (PS)
. - Encl 5.1C (Emergency Operation of SSF Svstems Unit 3). (Ps)
<
~
. .
u I will NOT affect the power factor but will affect j 4.16 - Maintain D/G operation within the following limits as posted on the D/G control uanel:
4.17 -' Verify D/G SER WTR PMP FLOW - Dispatch an operator to throttle CCW-285
= 500 gp (SSF DIESEL SERVICE WATER PUMP DISCHARGE) to maintain 500 gpm through the Diesel Engine (SSF Pump Rm).
AP/O/A/1700/025 Page 8 of 15
.. L THIS PAGE INTENTIONALLY BLANK
APIO/A/1700/025 Page 9 of 15 v ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAlNED J 4.19 - Notify TSC to monitor SFP levels and makeup to SFps as soon as possible to minimize SFp area dose rate of initiation of the even .20 - IAAT 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 50 minutes have elapsed since the event causing activation of the SSF, THEN dispatch an operator to perform the following:
W A. - Open CCW-384 (JACKET COOLING WATER TO YARD DRAIN ISOLATION)
(SSF D/G Rm).
B. - Close CCW-286 (DIESEL COOLING JACKET RETURN)
(SSF Pump Rm).
C. - Throttle CCW-285 (SSF DIESEL SERVICE WATER PUMP DISCHARGE) to maintain 500 gpm through the Diesel Engine (SSF Pump Rm).
APIO/A/ 1700/025 Page 10 of 15 IF AT ANY TIME:
L (4.20) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 50 minutes have elapsed since the event ... (dispatch an operator)
ApIo/A/1700/025 Page 11 of 15 ii ACTIONlEXF'ECTED RESPONSE RESPONSE NOT OBTAINED 4.21 - LAAT SSF Control Room temperature exceeds 85"F, THEN perform one of the following:
- Notify TSC to install portable spot cooler OR
- Remove power from SSF Security Computer as follows:
A. - Notify Security that power will be removed from SSF Security Compute B. - Notify Local Information Technology (LJT) to remove power from SSF Security Computer to reduce heat loa .22 Notify CRO from each affected unit to perform the following as appropriate:
u
- Encl 5.3A (Unit 1 Control Room Enclosure)
- Encl 5.3B (Unit 2 Control Room Enclosure)
II
- Encl 5.3C (Unit 3 Control Room
~
Enclosure)
-
N1
&..
L Siphon flow will be lost when CCW piping integrity is violate M O / N1300/059 (Pump-Submersible-Emergency SSF Water Supply-Installation and Removal) as necessary to -the Dedicated Submersible Pump for installation in
AP/o/A/ 1700/025 Page 12 of 15 IF AT ANY TIME:
L (4.20) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 50 minutes have elapsed since the event ... (dispatch an operator)
(4.21) SSF Control Room temperature exceeds 85°F... (perfom one of the following)
AP/o/N1700/025 Page 13 of 15 W ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAIWD The Dedicated SubmersiblePump must be installed and started within 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of loss of both forced and gravity/siphon flow on the Unit 2 CCW Svste I I
4.24 - IAAT of the following are-lost - GO TO Step 4.2 on the Unit 2 CCW System:
- Forced Flow
- Gravity/Siphon Flow THEN perform Steps 4.25 - 4.2 .25 - Notify SPOC to perform AM/O/N1300/059 (Pump-Submersible-Emergency SSF Water Supply-Installation and Removal) as necessary to install the Dedicated Submersible Pump for Unit 2 CCW Syste ~
i/
4.26 - WHEN I&E and Maintenance have Notify TSC to provide makeup guidance to completed installation of the assure SSF ASW Pump suction based on Dedicated Submersible Pump, availability of Unit 2 CCW piping:
THEN dispatch an operator to place the pump in service as follows: Rack in &close OXSF-4D Intact Cross-connect with (SUBMERSIBLE PUMP BKR) Unit 1 or 3 with forced (SSF Electrical Equip Rm). Close CCW-R5-0010 Intact Encl5.5 (Supply of (SUBMERSIBLE PUMP Water to SSF)
REMOTE STARTER BKR)
Not Intact or Alternate method (Outside SSF CR).
Questionable determined by TSC Start the Dedicated Submersible Pump by the push button on the Remote Starter Breaker (Outside SSF CR).
AF'/o/A/1700/025 Page 14 of 15 IF AT ANY TIME:
(4.20) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 50 minutes have elapsed since the event ... (dispatch an operator)
(4.21) SSF Control Room temperature exceeds 85°F... (perform =of the following)
(4.24) loss of Unit 2 CCW System forced flow and gravity/siphon flow ...
(notify I&E and Maintenance to install Dedicated Submersible Pump)
--
AP/o/A/1700l025 Page 15 of 15 u
I ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED 4.27 - IAAT flooding has occurred in TB, AND actions affecting CCW System are performed, THEN dispatch an operator to monitor TB basement are .28 - IAAT Unit 2 CCW Condenser Inlet piping has been isolated (from Lake Keowee or from the other units),
THEN monitor level in CCW Condenser Inlet pipins as directed by TS .29 - Notify Operations Support Group or TSC to order fuel oil for SSF Diesel Generator as necessar ___--
4.30 - W H E N &inl progress enclosures of this procedure are complete, THEN EXIT this procedure.
L,
NLO-007 fnl Page 1 of 10
/
REGION II
INlTlA C ENSE EXAMIbAT10 JOB PERFORMANCE MEASURE NLO-007 START DIESEL AIR COMPRESSOR AND ALIGN TO SERVICE AIR HEADER i/
CANDIDATE:
EXAMINER:
NLO-007 fnl Page 2 of 10 REGION I1 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE
'W'
-
Task:
Start Diesel Air Compressor and Align to Service Air Header Alternate Path:
No Facilitv JPM #:
NLO-007 KIA Ratinds):
System: APE065 WA: AA1.04 Rating: 3.5*/3.4*
Task Standard:
Diesel Air Compressor started and aligned to the Service Air Header correctly per procedur Preferred Evaluation Location: Preferred Evaluation Method:
Simulator __ In-Plant 1 Perform __ Simulate Candidate: Time Start:
NAME Time Finish:
Performance Rating: SAT -UNSAT - Performance Time: -
Examiner: I NAME SIGNATURE DATE COMMENTS
NLO-007 fnl Page 3 of 10 SIMULATOR OPERATOR INSTRUCTIONS:
None L/
NLO-007 fnl Page 4 of 10 ToolslEquipmentlProceduresNeeded:
APR/AJ1700/22, Enclosure 5.4 (Emergency Start of the Diesel Air Compressor) prestaged at compressor.
~U READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided yo INITIAL CONDITIONS:
Units 1, 2, and 3 are operating at 100% powe The Unit 1 Control Room Operator receives the "INSTRUMENT AIR SYSTEM TROUBLE Statalarm and observes that Instrument Air pressure is decreasing on the Control Room IA pressure gaug INITIATING CUES:
The Unit 2 Control Room Operator directs you to obtain a copy of "Emergency Start of the Diesel Air Compressor" Enclosure of AP/2/~1700/22(Loss Of Instrument Air), start the diesel air compressor, and align it to the Service Air Header.
c
~
NLO-007 fnl Page 5 of 10 START TIME:
CRITICAL STEP
~
L NOTE The Low Water Level light should light for 4 seconds and then go of SAT 1:- Step 1 Position the POWER Toggle Switch to ON-UNSAT STANDARD: The POWER Toggle Switch is located and pushed up to the ON positio Cue: Indicate that the Low Water Level light is on for 4 seconds and then goes of COMMENTS:
STEP: Step 2 Press and HOLD the SAFETY CIRCUIT BYPASS button for 10 - 15 seconds) -SAT STANDARD: Operator locates and presses the SAFETY CIRCUIT BYPASS button, L holding it for 10 - 15 second UNSAT COMMENTS:
STEP: Step 3 CRITICAL STEP While holding the SAFETY CIRCUIT BYPASS button, depress the START button to start the engin SAT STANDARD: While continuing to hold the SAFETY CIRCUIT BYPASS button, the operator locates and presses the START butto UNSAT CUE: After the buttons are pressed, inform the candidate that the diesel has starte COMMENTS:
c
NLO-007 fnl Page 6 of 10 STEP: Step 4 WHEN engine starts,
'L THEN release the start button-SAT STANDARD: The candidate releases the START button when the engine start UNSAT CUE: Indicate to the operator that engine has starte COMMENTS:
STEP: Step 5 WHEN ENGINE OIL PRESSURE reaches 20 psig -SAT THEN release the SAFETY CIRCUIT BYPASS butto STANDARD: Candidate should determine that ENGINE OIL PRESSURE is 20 psig -UNSAT and then release the SAFETY CIRCUIT BYPASS butto CUE: Indicate to the operator that ENGINE OIL PRESSURE is 20 psi COMMENTS:
L m: Step 6 CRITICAL STEP Push the "SERVICE AIR PUSH AFTER WARM-UP button to allow the compressor to fully loa SAT STANDARD: The "SERVICE AIR PUSH AFTER WARM-UP button is LOCATED on the Control Panel, and is DEPRESSE UNSAT CUE: Inform operator that the "SERVICEAIR PUSH AFTER WARM-UP" button is depresse COMMENTS:
NLO-007 fnl Page 7 of 10 STEP: Step 7 CRITICAL STEP Open SA-2797 (SA BLOCK VALVE) (North side of compressor below the control panel)
-SAT STANDARD: Service Air Outlet Valve, located in front of the control panel, is OPENED by placing the valve operator lever PARALLEL with the service air lin UNSAT CUE: Inform operator that lever is parallel with service air lin COMMENTS:
-8: Step 8 CRITICAL STEP OPEN SA-339 (DIESEL AIR COMPRESSOR TIE) (T-3/FIG-56)
-SAT STANDARD: Compressor is aligned to Service Air Header by rotating SA-339 (Diesel Air Compressor Tie) T-handle until parallel with pipe.
CUE: Inform operator that lever is parallel with service air lin UNSAT COMMENTS:
STEP I O : Step 10 CRITICAL STEP OPEN SA443 (SA TO IA CONTROLLER BYPASS) (T-I/L-33. 15' E)
STANDARD: Valve is located and manually opened by rotating valve Counter-clockwise to the hard sto SAT Cue: After the operator indicates that he will open SA-143, inform operator that valve is at the hard sto UNSAT ZOMMENTS:
NLO-007 fnl Page 8 of 10 STEP 11: Notify Unit 2 CR that the Diesel Air Compressor is operating.
L STANDARD: Unit 2 CR is notified that the Diesel Air Compressor is operating using a -SAT phone or radi Cue: Inform candidafe that the Unit 2 CR has been notified that the Diesel Air -UNSAT Compressor is operatin COMMENTS:
END TASK STOP TIME:
NLO-007 fnl Page 9 of 10 CRITICAL STEP EXPLANATIONS:
u STEP # Explanation 1 Provides power to engine indications and control circuit Operator must press bypass and start buttons to crank engin Step is required to load the compresso Valve must be opened to allow the supply of air to leave the compresso Air is not supplied to the Service air Header until this valve is opene Allows SA to raise IA Header pressure above 85 psi NLO-007 fnl Page 10 of 10 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
ii INITIAL CONDITIONS:
Units 1, 2, and 3 are operating at 100% powe The Unit 1 Control Room Operator receives the "INSTRUMENT AIR SYSTEM TROUBLE Statalarm and observes that Instrument Air pressure is decreasing on the Control Room IA pressure gaug INITIATING CUES:
The Unit 2 Control Room Operator directs you to obtain a copy of "Emergency Start of the Diesel Air Compressor" Enclosure of AP/2/N1700/22 (Loss Of Instrument Air), start the diesel air compressor, and align it to the Service Air Heade Enclosure AP/2/A/1700/022 Emergency Start of the Diesel Air Compressor (3) Page 1 of 5 NOTE
.The "Low WaIer Level" light should light for 4 seconds and then go off
_- O L i
2. - Press and hold the SAFETY CIRCUIT I
__--
BYPASS button for 10-15 second . - While holding the SAFETY CIRCUIT I

I-- _-

BYPASS button, depress the START button to start the engine. - -+---I -
4. - WHEN engine starts, I THEN release the START butto I
5. - WHEN ENGINE OIL PRESSURE reaches 20 psig,
~
THEN release the SAFETY CIRCUIT i i BYPASS butto I -
. ~ __
6. - Push the SERVICE AIR PUSH AFTER WARM-UP button to allow the I I
compressor to fully loa ___
7. - Open SA-2797 (PORTABLE DIESEL AIR COMPRESSOR BLOCK) (North
__
i 1 side of the compressor below the control panel).
________--.
8 . - Open SA-339 (DIESEL AIR
.-- ii -
i COMPRESSOR TIE) (T-3fF/G-56). ~
~.
Enclosure Emergency Start of the Diesel Air Compressor Page 2 of 5 THIS PAGE INTENTIONALLYBLANK
Enclosure Emergency Start of the Diesel Air Compressor {3) Page 3 of 5
.4CTIONIEXPECTED RESPONSE RESPONSE No'r OBTAINED I
ISA-141 (SA TO IA CONTROLLER) automatically NOTE regulates IA header pressure to 85 psi Opening SA-143 will bypass SA-I41 and'allow the SA header to pressurize the LA header greater than 85 psi . - Open SA-143 (SERVICE AIR TO INSTRUMENT AIR CONTROLLER BYPASS) (T-1/L-33, 15' E).
10. - Notify Unit 2 CR that the Diesel Air Compressor is operatin . - Periodically monitor compressor parameters and associated lamps:
Parameter Range ENGINE qo Load = 1200 rpm TACHOMETER :ull Load = 1800 rpm ENGINE WATER Max 200°F TEMPERATURE W
DISCHARGE AIR Max 220'F TEMPERATURE COMPRESSOR Min 75 psig (with DISCHARGE compressor loaded)
PRESSURE ENGINE OIL Min 20 psig PRESSURE Normal = 35 - 60.usig
Enclosure Emergency Start of the Diesel Air Compressor (3) Page 4 of 5
'L THIS PAGE INTENTIONAJLY BLANK
Enclosure AP/2/A/1700/022 Emergency Start of the Diesel Air Compressor (3) Page 5 of 5 r ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED 1 12. - WHEN directed by CR to secure the Diesel Air Compressor, THEN perform the following:
A. -Close SA-143 (SERVICE AIR TO INSTRUMENT AIR CONTROLLER BYPASS)
(T-lL-33, 15'E).
B. -Close SA-339 DIESEL AIR COMPRESSOR TIE)
(T-3/F/G-56).
C. -Close SA-2797 (PORTABLE DIESEL AIR COMPRESSOR BLOCK) (North side of the compressor below the control panel).
D: ':-Allow engine to idle for 5 minute E. .-Position IGNITION toggle switch to u OF F. -Replenish operating fluids as require __ ______--_
13. - Notify Unit 2 CR that the Diesel Air Compressor is shutdow ___ _-
14. - EXIT this enclosure.

v t e Inspection Report - Oconee - 2003301 (Operator Exams)
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \|
2003 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 10(0) 7(0) 8(0) 9(0) 10(0) 11(1) 12(0) Security Operator Exams 301(0) 302(0) Emergency Planning Other

IR 05000269/2003301

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