ML082690661

May 05000369, 370/2008301 Exam Draft Simulator Scenarios & Outlines

ML082690661
Person / Time
Site:	Mcguire, McGuire
Issue date:	03/17/2008
From:	- No Known Affiliation
To:	NRC/RGN-II
References
Download: ML082690661 (262)

Text

Draft Submittal (Pink Paper)

SIMULATOR SCENARIOS

~AUJRE. MAY 2008 EXAM 369 370/2008-301

>~ijSIMULATOR SCENARIOS

i ati Scenarios McGuire Nuclear Station 45-day Submittal March 17, 2008

PROGRAM: McGuire Operations Training MODULE: Initial License Operator Training Class 24 TOPIC: NRC Simulator Exam Scenario N08-1-1

REFERENCES:

1. OP/0/A/64501011, "Control Area Ventilation/ Chilled Water System."

2. OP/1/A/6200/001 B, "Chemical and Volume Control System Charging."

3. OP/1/A/61 00101 OE, "Annunciator Response For PaneI1AD-4."

4. AP/1/A/5500/006, "S/G Feedwater Malfunction."

5. OP/1/A/61 00/01 OG, "Annunciator Response For PaneI1AD-6."

6. OP/1/A/61 00101 OH, "Annunciator Response For PaneI1AD-7."

7. McGuire Technical Specifications

8. AP/1/A/5500/010, "NV Leakage Within Capacity of Charging Pumps."

9. AP/1/A/5500/004, "Rapid Downpower."

1O. AP/1/A/5500/14, "Rod Control Malfunction."

11. EP/1/A/5000/E-0, "Reactor Trip or Safety Injection."

12. EP/1/A/5000/FR-Z.1, "Response to High Containment Pressure."

13. EP/1/A/5000/E-2, "Faulted Steam Generator Isolation."

14. EP/1/A/5000/E-3, "Steam Generator Tube Rupture."

15. RP/0/A/5700/000, "Classification of Emergencies."

Author:

Facility Review:

January 21,2008 Rev. 0 Scenario Event Description NRC Scenario 1 Facility: McGuire Scenario No.: 1 Op Test No.: N08-1 Examiners: Operators: (SRO)

---

~I (OATC)

(BOP)

Initial Conditions: The Plant is at 75% power (MOL), following an unplanned load reduction four days ago to complete corrective maintenance on the 18 CF Pump. The maintenance was completed and the pump restarted, and power level raised to the present power level two days ago. The present plan is to observe operation of the 18 CF Pump at this power level, and then raise power to 1000/0 within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 1A NV was started last shift to support maintenance observation.

Turnover: The following equipment is Out-Of-Service: A CA Pump (Expected back in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />),

OEMF 43A, Control Room Air Intake Radiation Monitor, failed last shift (IAE is investigating) and Enclosure 4.14, "Response When EMF43A or 438 In Trip 2 or Inoperable," of OP/O/A/64501011 , "Control Area Ventilationl Chilled Water System," has been completed. MC8 Annunciator 1AD-8, 8-6, "GLAND STM COND HI DIP," has alarmed spuriously several times over the last hour (IAE is investigating). It is expected to swap back to the 18 NV Pump on the upcoming shift. The previous shift has performed the flush and vent of the 18 NV Pump and the operator will commence the procedure starting at Step 3.3.4 of Enclosure 4.2 of OP/1/A/62001001 8, "Chemical and Volume Control System Charging." An NLO (John) is standing by locally to support the pump swap, and there are no R&Rs that will impact this activity.

Event Malf. Event Type* Event No. No. Description 1 NA N-BOP Swap NV Pumps N-SRO XMT 2 I-RO Steam Flow Channel fails low SMOO7:

I-SRO XMT 3 I-BOP Pzr Level Channel fails high ILEOO1 I(TS)-SRO 4 SGOO1B C-RO Steam Generator Tube LeakiDownpower C-BOP C(TS)-SRO S IREOO3A C-RO Uncontrolled Inward Rod Motion C-SRO 4

6 SMOO7C M-RO Inadvertent MSIV Closure/Faulted SG SMOO6C M-BOP M-SRO 7 ISEOOSAI NA Failure of Containment Spray to auto actuate B

8 CAOO9B NA B CA Pump Trip

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 1 McGuire 2008 NRC Scenario #1 The Plant is at 75% power (MOL), following an unplanned load reduction four days ago to complete corrective maintenance on the 1B CF Pump. The maintenance was completed and the pump restarted, and power level raised to the present power level two days ago. The present plan is to observe operation of the 1B CF Pump at this power level, and then raise power to 100°k> within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 1A NV was started last shift to support maintenance observation.

The following equipment is Out-Of-Service: A CA Pump (Expected back in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />), OEMF 43A, Control Room Air Intake Radiation Monitor, failed last shift (IAE is investigating) and Enclosure 4.14, "Response When EMF43A or 43B In Trip 2 or Inoperable," of OP/OIAl64501011, "Control Area Ventilationl Chilled Water System," has been completed. MCB Annunciator 1AD-8, B-6, "GLAND STM COND HI DIP," has alarmed spuriously several times over the last hour (IAE is investigating). It is expected to swap back to the 1B NV Pump for on the upcoming shift.

The previous shift has performed the flush and vent of the 1B NV Pump and the operator will commence the procedure starting at Step 3.3.4 of Enclosure 4.2 of OP/11A162001001 B, "Chemical and Volume Control System Charging." An NLO (John) is standing by locally to support the pump swap, and there are no R&Rs that will impact this activity.

Shortly after taking the watch, the operator will shift from 1A NV Pump to 1B NV Pump in accordance with section 3.3 of Enclosure 4.2, "NV Pump Operation," of OP/11A162001001 B, "Chemical and Volume Control System Charging." When the procedure is complete the 1B NV Pump will be operating and the 1A NV Pump will be shutdown.

Following this, the controlling Steam Flow Transmitter (FSM-5030) on the B Steam Generator will slowly fail low causing the Feed Regulating Valve to move in the closed direction, and a Steam Generator B Steam Flow Mismatch alarm. The operator will respond by implementing AP-6, "S/G Feedwater Malfunction," recognize the failure and select an operating Steam Flow channel.

After this, the controlling Pzr Level Transmitter (LNC-5160) will slowly fail high causing charging flow to lower. The operator will respond in accordance with 1AD-6/C-7, "Pzr Hi Level DEV Control," determine that a failed instrument has occurred and swap to an operable channel.

The operator will address Technical Specification 3.3.1, "RTS Instrumentation," 3.3.3, "Post-Accident Monitoring Instrumentation," and 3.3.4, "Remote Shutdown System."

Subsequently, a 10 gpm Steam Generator Tube Leak will develop on the B Steam Generator.

The Operator will respond by implementing AP-10, "NC System Leakage Within the Capacity of Both NV Pumps." The operator will address Technical Specification 3.4.13, "RCS Operational Leakage," and 3.7.16, "Secondary Specific Activity." The operator will reduce load to be in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in accordance with AP4, "Rapid Downpower."

During the downpower, uncontrolled inward rod motion will occur with Rod Control in automatic.

The operator will respond in accordance with AP14, "Rod Control Malfunction," and take manual control of the control rods. (The rods will remain in manual control throughout the remainder of the scenario).

Shortly afterwards, the C MSIV inadvertently closes causing a major Steam Line Rupture to occur on the C Steam Generator inside the Containment. A Reactor Trip/Safety Injection will occur and the operator will enter E-O, "Reactor Trip or Safety Injection." The Containment Spray (NS) bistable will fail to energize, and require manual operator action. The SGTL in the B SG Scenario Event Description NRC Scenario 1 will degrade to about 75 gpm over the next 15 minutes due to the plant transient. Additionally, the B CA Pump will auto start but trip on overcurrent. This will leave the CATD Pump as the only source of CA to the intact Steam Generators.

Upon completion of E-O, an Orange Path on Containment will require a transition to FR-Z.1, "Response to High Containment Pressure." Upon completion of FR-Z.1, the operator will transition to E-2, "Faulted Steam Generator Isolation," and isolate the C Steam Generator.

Upon Steam Generator isolation the steam supply for the CATD Pump will be provided from the B Steam Generator which has high radiation due to the on-going 75 gpm Steam Generator Tube Leak. After isolating the C Steam Generator, the operator will transition to E-3, "Steam Generator Tube Rupture," based on high radiation in the B Steam Generator.

The scenario will terminate at Step 1 of E-3, after the crew has isolated the B Steam Generator with the exception of the Steam Supply to the CATD Pump.

Critical Tasks:

E-O E Manually actuate the minimum required compliment of Containment Cooling Equipment (NS) before transitioning out of E-O.

E-2 A Isolate the Faulted Steam Generator before transitioning out of E-2.

Scenario Event Description NRC Scenario 1 SIMULATOR OPERATOR INSTRUCTIONS D Sim. Setup IC -103

• 7So/0 Power

• 1A CA Pump OOS

• OEMF 43 A OOS (Ene. 4.14 of OP/O/Al64S0/011 complete)

• ISEOOSAIB NS Failure of NS to Auto Actuate o RUN o Update Status Board, See Shift Turnover Information Setup OAC Setup ICCM, Turbine Displays, & Trend Recorders.

Check Rod Step Counters agree with rod positions o Freeze.

o Update Fresh Tech.

Spec. Log.

n Fill out the NLO*s Available section of Shift Turnover Info.

o Prior to Crew Briefing RUN o Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Handout OP/1/A16200/001 B w/Enclosure 4.2 marked up through Step 3.3.3.

4. Direct the erew to Review the Control Boards taking note of present conditions, alarms.

o T-O Begin Familiarization Period o At direction of NLO Local Actions Swap NV Pumps examiner Scenario Event Description NRC Scenario 1 0 At direction of (XMT) SM007 Steam Flow Channel fails low examiner Severity 0 Ramp 60 seconds Trigger 1 At direction of (XMT) ILE001 Pzr Level Channel fails high examiner Set 100 Ramp 120 Trigger 3 0 At direction of (MALF) SG0018 Steam Generator Tube LeakiDownpower examiner Set =10 gpm Ramp 60 Trigger 5 0 At direction of (MALF) IRE003A Uncontrolled Inward Rod Motion.

examiner Trigger 7 0 At direction of (OVR) SM012D Inadvertent MSIV Closure/Faulted SG/ Failure of examiner Containment Spray to auto actuate/ B CA Pump Trip (MALF) SM007C (Ramp

=60 Seconds)

(MALF) CA0098 NOTE: When Trigger #9 is operated MALF SG001 B must be changed to 75 gpm over a 900 second ramp, Trigger 9 o Terminate the scenario upon direction of Chief Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 1 Event # _ _ _ _ _ _ Page 7 of _4_3__

n Event

Description:

Swap Charging Pumps Position A licant's Actions or Behavior Shortly after taking the watch, the operator will shift from 1A NV Pump to 1B NV Pump in accordance with section 3.3 of Enclosure 4.2, "NV Pump Operation," of OP/1/A/62001001B, "Chemical and Volume Control System Charging." When the procedure is complete the 1B NV Pump will be operating and the 1A NV Pump will be shutdown.

Booth Operator Instructions: NLO (John) is standing by locally to support NV Pump swap.

Indications Available: NA OP/1/Al6200/001B, CHEMICAL AND VOLUME CONTROL SYSTEM CHARGING ENCLOSURE 4.2 BOP (Step 3.3.4) Start 1NV Lube Oil Pump 1B.

NOTE: A Plant Announcement is expected to be made prior to the start of the pump.

SRO may ask U2 Operator to make announcement.

BOP (Step 3.3.5) IF this is a routine start of the 1B NV Pump, do NOT continue until 1B NV Lube Oil Pump has run for 1 minute.

BOP (Step 3.3.6) Start 1B NV Pump.

BOP (Step 3.3.7) Place in "AUTO" 1B NV Lube Oil Pump.

BOP (Step 3.3.8) Depress "STP" for 1B NV Lube Oil Pump.

Booth Operator: As NLO (John) report "Pump status is Good."

BOP (Step 3.3.9) Check "START" pushbutton released AND "OFF" lit for 1B NV Lube Oil Pump.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ _ _ _ _ _ Page 8 of _4_3__

n Event

Description:

Swap Charging Pumps Time ~ Position II Applicant's Actions or Behavior BOP (Step 3.3.10) Calculate DP between Seal Balance Line Pressure and Suction Pressure for 1B NV pump:

Booth Operator: When called as NLO (John) report "Seal Balance Line Pressure

= 51 psig, and Suction Pressure = 31.2 psig."

BOP (Step 3.3.11) IF DP between Seal Balance Line Pressure and Suction Pressure greater than 50 psid, notify System Engineer.

BOP (Step 3.3.12) Stop 1A NV Pump.

BOP (Step 3.3.13) Adjust charging flow and seal flow as needed.

BOP (Step 3.3.14) Evaluate back leakage through 1A NV Pump as follows:

• WHEN Pzr level stable at setpoint, check 1NV-238 (Charging Line Flow Control) demand position.

• IF 1NV-238 demand position greater than 74%, notify System Engineering for guidance.

At the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 2 _ _ _ _ _ Page 9 of _4_3_~1 Event

Description:

Steam Flow Channel fails low Ti A licant's Actions or Behavior Following this, the controlling Steam Flow Transmitter (FSM-5030) on the B Steam Generator will slowly fail low causing the Feed Regulating Valve to move in the closed direction, and a Steam Generator B Steam Flow Mismatch alarm. The operator will respond by implementing AP-6, "S/G Feedwater Malfunction," recognize the failure and select an operating Steam Flow channel.

Booth Operator Instructions: Operate Trigger #1 (XMT-SM007 (0>>

Indications Available:

• Annunciator 1AD-4/A2, "S/G B Flow Mismatch Lo Stm Flow."

• Annunciator 1AD-4/C2, "S/G B Flow Mismatch Lo CF Flow."

• B FCV moves in closed direction.

• B CF flow decreases.

• B NR Level decreases.

OP/1/A16100/010E, ANNUNCIATOR RESPONSE FOR PANEL 1AD-4 A2, S/G B FLOW MISMATCH LO STM FLOW SRO (fA Step 1) IF Channel in Test, no further NOTE: Crew may NOT action required. address ARP, but enter AP6 directly.

SRO (IA Step 2) IF loss of feedwater, go to AP/1/A/5500/006 (SG Feedwater Malfunction).

AP/1/A15500/06, S/G FEEDWATER MALFUNCTION NOTE: Crew will carry out Immediate Actions of AP6, prior to the SRO addressing the AP.

RO (Step 1) IF CF control valve OR bypass valve has failed, THEN perform the following:

• Place affected valve in manual.

• Restore S/G level to program.

Appendix D Operator Action Form ES-D-2 Op Test No.: NOB-1 Scenario # Event # _ 2 _ _ _ _ _ Page 10 of 43 Event

Description:

Steam Flow Channel fails low Time A Iicant's Actions or Behavior RO (Step 2) IF CF pump speed control has failed, THEN perform the following:

RO (Step 3) On each S/G, check the following NOTE: Channel I Steam Flow channels - INDICATING the SAME: has failed low on B SG.

• Steam flow RO (Step 3 RNO) Select an operable channel on NOTE: operator will select the affected S/G(s). Channel lion Steam Flow, Feed Flow and NR level.

RO (Step 4) Check unit status as follows:

• Reactor trip breakers - CLOSED

• Pzr pressure - GREATER THAN P-11 (1955 PSIG).

RO (Step 5) IF AT ANY TIME S/G NR level approaches 17% OR 830/0, THEN perform the following:

• Trip reactor.

• GO TO EP/1/A/5000/E-O (Reactor Trip or Safety Injection).

SRO (Step 6) Announce occurrence on page. NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 7) Check reactor power - GREATER THAN 3%.

RO (Step 8) Check CM/CF - PRESENTLY FEEDING S/Gs.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 1 Event # _ 2 _ _ _ _ _ Page 11 of _4_3_---41 Event

Description:

Steam Flow Channel fails low Time " Position ~ Applicant's Actions or Behavior RO (Step 9) Check S/G levels - STABLE OR NOTE: By this time NR level TRENDING TO PROGRAM LEVEL. should be at or trending to programmed level.

RO (Step 10) Check NC temperatures as follows:

• IF any NC pump on, THEN check NC NOTE: NC Tavg should be T-Avg - STABLE OR TRENDING TO stable.

DESIRED TEMPERATURE.

RO (Step 11) Check all S/G CF control valves - NOTE: 1B CF Control Valve IN AUTO. will be in MANUAL.

(Step 11 RNO) WHEN the following NOTE: operator will place 1B conditions met, THEN place affected CF CF Control Valve back in control valve in automatic: AUTO.

• Automatic control - DESIRED

• Affected S/G level(s) - AT PROGRAM LEVEL

• Selected control channels - INDICATE CORRECTLY ON CHART RECORDER:

• Feed flow

• Steam flow

• S/G level RO (Step 12) Check all S/G CF control bypass valves - IN MANUAL AND FULL OPEN.

RO (Step 13) Check both CF pumps - IN AUTO.

RO (Step 14) Check all CA pumps - OFF.

NOTE: SRO will likely conduct a Focus Brief.

At the discretion of the Lead Examiner move to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 2 Page 12 of 43

---n Event

Description:

Steam Flow Channel fails low Time ~ Position II Applicant's Actions or Behavior

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _3 _ _ _ _ _ Page 13 of 43

--~I Event

Description:

Pzr Level Channel fails high Time II Position ~ Applicant's Actions or Behavior After this, the controlling Pzr Level Transmitter (LNC-5160) will slowly fail high causing charging flow to lower. The operator will respond in accordance with 1AD-6/C-7, "Pzr Hi Level DEV Control," determine that a failed instrument has occurred and swap to an operable channel. The operator will address Technical Specification 3.3.1, "RTS Instrumentation," 3.3.3, "Post-Accident Monitoring Instrumentation," and 3.3.4, "Remote Shutdown System."

Booth Operator Instructions: Operate Trigger #3 (XMT-ILE001 (100>>

Indications Available:

• Annunciator 1AD-6/C7, 'Pzr Hi Level Dev Control."

• Annunciator 1AD-7/F2, "Charging Line Demand Lo Flow."

• Charging flow decreases

• Actual Pzr Level decreases OP/1/Al61 00/01 OG, ANNUNCIATOR RESPONSE FOR PANEL 1AD-6 C7, PZR HI LEVEL DEV CONTROL BOP (IA Step 1) Check backup heaters are on and charging flow is decreasing.

BOP (IA Step 2) IF instrument malfunction, manually control charging flow at the appropriate man/auto station:

• Pzr Level Master Cntrl

• 1NV-238 (Charging Line Flow Control) NOTE: operator will place 1NV-238 in MANUAL to control Charging flow.

• PD Pump Speed BOP (IA Step 3) IF instrument malfunction, place NOTE: operator will select "Pzr Level Cntrl Select" to unaffected position 3-2 on Pzr Level channels. Control.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 3 _ _ _ _ _ Page 14 of 43

--~I Event

Description:

Pzr Level Channel fails high Time II Position I Applicant's Actions or Behavior SRO (SA Step 1) IF required to control NOTE: Operator may isolate Letdown/Charging, go to OP/1/A/6200/001 A Letdown. If so, Enter AP12 to (Chemical and Volume Control System re-establish Letdown.

Letdown) or OP/1/A/6200/001 B (Chemical and Volume Control System Charging).

SRO (SA Step 2) Refer to Tech Specs for NOTE: SRO will likely conduct minimum instrumentation requirements. a Focus Brief.

TECHNICAL SPECIFICATION 3.3.1, RTS INSTRUMENTATION SRO Reactor Trip System (RTS) Instrumentation Examiner NOTE: Addressing TS takes 8-10 minutes. May want to address after scenario.

SRO LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1-1. (9. Pressurizer Water level- HIGH)

ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Enter the Immediately more Condition functions referenced with one or in Table more 3.3.1-1 for required the channels channel(s).

inoperable.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 3 Page 15 of 43

---II Event

Description:

Pzr Level Channel fails high A licant's Actions or Behavior M. One M.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel channel in trip.

inoperable.

OR M.2 Reduce THERMAL 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> POWER to <

P-7.

TECHNICAL SPECIFICATION 3.3.3, PAM INSTRUMENTATION SRO Post Accident Monitoring (PAM)

Instrumentation SRO LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE. (11 -

Pressurizer Level)

APPLICABILITY:

MODES 1, 2, and 3.

CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Enter the Immediately more Condition Functions referenced with one or in Table more 3.3.3-1 for required the channel.

channels inoperable.

B. One or B.1 Restore 30 days more required Functions channel to with one OPERABLE required status.

channel inoperable.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 3 _ _ _ _ _ Page 16 of 43

---II Event

Description:

Pzr Level Channel fails high Time II Position ~ Applicant's Actions or Behavior TECHNICAL SPECIFICATION 3.3.4, REMOTE SHUTDOWN SYSTEM SRO 3.3.4 Remote Shutdown System SRO LCO 3.3.4 The Remote Shutdown System Functions in Table 3.3.4-1 shall be OPERABLE (4 RCS Inventory control a. Pressurizer Level).

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Restore 30 days more required required Function to Functions OPERABLE inoperable. status.

At the discretion of the Lead Examiner move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 1 Event # _ 4 _ _ _ _ Page 17 of _4_3----11 Event

Description:

Steam Generator Tube LeaklDownpower A licant's Actions or Behavior Subsequently, a 10 gpm Steam Generator Tube Leak will develop on the B Steam Generator. The Operator will respond by implementing AP-10, "NC System Leakage Within the Capacity of Both NV Pumps." The operator will address Technical Specification 3.4.13, "RCS Operational Leakage," and 3.7.16, "Secondary Specific Activity." The operator will reduce load to be in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in accordance with AP4, "Rapid Downpower."

Booth Operator Instructions: Operate Trigger #5 (MALF SG001B (10 gpm>>

Indications Available:

• Annunciator 1RA-1/B1, "1 EMF 33 Cond Air Eject Exh Hi Rad."

• Annunciator 1RA-1/C1, "1 EMF 71 S/G A Leakage Hi Rad."

• Annunciator 1RA-1/D1, "1 EMF 72 S/G B Leakage Hi Rad."

• Annunciator 1RA-1/D2, "1 EMF 73 S/G C Leakage Hi Rad."

• Annunciator 1RA-1/D3, "1 EMF 74 S/G D Leakage Hi Rad."

• 1 EMF 72 S/G B Leakage Hi Rad indicates higher than other SGs.

AP/1/AJ5500/10, NC SYSTEM LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS CASE I -- STEAM GENERATOR TUBE LEAKAGE BOP (Step 1) Check Pzr level - STABLE OR GOING UP.

BOP (Step 1 RNO) Perform the following as required to maintain level:

• Maintain charging flow less than 200 GPM at all times in subsequent steps.

• Ensure 1NV-238 (Charging Line Flow control) opening.

• Open 1NV-241 (Seal lnj Flow control) NOTE: Operator may open while maintaining NC pump seal flow 1NV-241 to maintain 6 gpm greater than 6 GPM. Seal Supply flow.

• Reduce or isolate letdown. NOTE: Operator will decide NOT to reduce Letdown due to the small size of the leak.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 1 Event # _ 4 _ _ _ _ Page 18 of _4_3_-41 Event

Description:

Steam Generator Tube LeaklDownpower Time II Position I Applicant's Actions or Behavior

• Start additional NV pump. NOTE: Operator will elect to NOT start a second NV Pump due to the small size of Leak.

BOP (Step 2) IF AT ANY TIME Pzr level goes NOTE: This is a Continuous down in an uncontrolled manner OR cannot Action. The SRO will make be maintained greater than 4%, THEN both board operators aware.

perform Step 1.

NOTE: The SRO may direct two NLOs to standby with Enclosure 3 of AP10 to isolate the 1B SG.

If so, Booth Instructor: Set LOA-SA003 = 0, (1 SA-2/78)

BOP (Step 3) Identify affected S/G:

• Any S/G N/R level - GOING UP IN AN UNCONTROLLED MANNER.

OR

• Check any of the following EMFs-ABOVE NORMAL:

• 1EMF-24 (SG/A Steamline Hi Rad)

• 1EMF-25 (SG B Steamline Hi Rad) NOTE: 1EMF-25 will be at Trip 1 set point.

• 1EMF-26 (S/G C Steam line Hi Rad)

• 1EMF-27 (S/G D Steam line Hi Rad)

• 1EMF 71 (S/G A Leakage Hi Rad)

• 1EMF 72 (S/G B Leakage Hi Rad) NOTE: 1EMF-72 will be at Trip 2 set point, and higher than other SGs.

• 1EMF 73 (S/G C Leakage Hi Rad)

• 1EMF 74 (S/G D Leakage Hi Rad)

OR

• Check CF Flow - LOWER IN ANY S/G COMPARED TO ALL.

OR

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 4 _ _ _ _ _ Page 19 of 43

--....(1 Event

Description:

Steam Generator Tube LeaklDownpower Time II Position ~ Applicant's Actions or Behavior

• Secondary Chemistry or RP has NOTE: SRO and Crew will determined affected S/G by sampling or identify 1B SG as leaking SG.

evaluation of available EMF data.

SRO (Step 4) Announce occurrence on page. NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

SRO (Step 5) REFER TO RP/0/A/5700/000 NOTE: SRO may ask OSM to (Classification of Emergency). address.

If so, Floor Instructor acknowledge as OSM.

SRO (Step 6) IF AT ANY TIME NC leakage NOTE: SRO and Crew will exceeds Tech Spec limits, THEN: acknowledge that leak exceeds TS limit.

• Ensure Outside Air Pressure Filter train NOTE: SRO may ask U2 in service PER OP/0/A6450/011 (Control BOP to address.

Area Ventilation/Chilled Water System),

If so, Floor Instructor Enclosure 4.4 (Control Room acknowledge as U2 BOP.

Atmosphere Pressurization During Abnormal Conditions).

• Have another SRO evaluate if leakage NOTE: SRO may call WCC to exceeds SLC 16.9.7 condition C limits address.

and immediately notify security if SSF is If so, Booth Instructor inoperable.

acknowledge as WCC.

BOP (Step 7) Check if unit shutdown or reactor trip required:

• Check VCT makeup - IN PROGRESS BOP (Step 7a RNO) GO TO Step 7c.

BOP (Step 7c) check S/G tube leak size - LESS NOTE: SRO and Crew will THAN 90 GPM. determine that leak is :::::10 gpm.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 4 _ _ _ _ _ Page 20 of _4_3_-.041 Event

Description:

Steam Generator Tube LeaklDownpower Time II Position ~ Applicant's Actions or Behavior SRO * (Step 7d) Leakage in one S/G -

GREATER THAN 125 GPO (GALLON PER OAY).

• (Step 7e) Observe the following limits while reducing load in Step 8:

• Ensure reactor power is less than 500/0 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of exceeding 125 GPO.

• Be in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of exceeding 125 GPO.

SRO (Step 8) Reduce load PER one of the Floor Instructor: Allow SRO following, while continuing with this AP as to determine which procedure time allows beginning at Step 9. to use to conduct shutdown.

!1 SRO chooses to conduct shutdown using OP, as Station Management, prompt crew to Shutdown plant to Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using AP04.

• AP/1/A/5500/04 OR

• OP/1/A/61 00/003 (Controlling Procedure For Unit Operation), Enclosure 4.2 (Power Reduction).

AP/1/Al5500/4, RAPID DOWNPOWER SRO (Step 1) Monitor Foldout page.

SRO (Step 2) Announce occurrence on page. NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 3) Check turbine control- IN AUTO.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # Event # _ 4 _ _ _ _ _ Page 21 of 43 N08-1

---II Event

Description:

Steam Generator Tube LeaklDownpower Time I Position I Applicant's Actions or Behavior RO (Step 4) Check "MW LOOP" - IN SERVICE.

SRO (Step 5) Check shutdown to Mode 3 -

DESIRED.

SRO (Step 6) Check if "Shutdown Via Reactor NOTE: Trip from 15% will be Trip from 150/0 Power - DESIRED. desired.

• Shutdown Via Reactor Trip from 150/0 Power - DESIRED

• At least two CA pumps - OPERABLE NOTE: One MD CA Pump is OOS (A). Still two pumps available (1B MD and 1TD CA Pumps).

RO (Step 7) Enter target load of 180 MWE in turbine control panel.

SRO (Step 8) Determine the required power NOTE: SRO will determine reduction rate (MW/min). 60% load reduction.

RO (Step 9) Check control rods - IN AUTO.

BOP (Step 10) Notify SOC of load reduction (red Booth Instructor:

dispatcher phone). Acknowledge as SOC.

RO (Step 11) Initiate turbine load reduction to NOTE: RO will start load desired load at desired rate. reduction.

BOP (Step 12) Borate NC System as follows:

• Energize all backup Pzr heaters.

• Determine boration amount based on the following:

• Power Reduction Rate (MW/min)

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 4 _ _ _ _ _ Page 22 of _4_3_-41 Event

Description:

Steam Generator Tube LeaklDownpower Time ~ Position ~ Applicant's Actions or Behavior

• Present NC System Boron concentration (ppm)

• Total Power Change (0/0).

• Record calculated boration amount: NOTE: BOP will determine 600 gallons.

• Perform boration in 4 equal additions during load reduction PER OP/1IAl61501009 (Boron concentration Control), Enclosure 4.7 (Boration Using 1NV-265B (Boric Acid To NV Pumps)).

RO (Step 13) Check control rods -- MOVING IN NOTE: RO will observe AS REQUIRED TO MAINTAIN T-AVE AT Control Rods stepping in.

T-REF.

RO (Step 14) Display rod Insertion Limits on OAC by entering turn on code "RIL".

ROI (Step 15) IF AT ANY TIME "CONTROL NOTE: This is a Continuous BOP ROD BANK LO LO LIMIT" alarm (1AD-2, Action. The SRO will make B-9) is lit, THEN perform one of the both board operators aware.

following to comply with Tech Spec 3.1.6 (Control Bank Insertion Limits):

• Ensure alarm clears within one hour as Xenon builds in.

OR

• Initiate boration as necessary within one hour to restore control rods above insertion limits.

RO (Step 16) IF AT ANY TIME during this procedure C-7A is received, THEN ensure Transient Monitor freeze is triggered.

RO (Step 17) Check turbine impulse pressure --

GREATER THAN 260 PSIG.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 4 _ _ _ _ _ Page 23 of _4_3__

11 Event

Description:

Steam Generator Tube LeaklDownpower Time II Position II Applicant's Actions or Behavior SRO (Step 18) REFER TO the following: NOTE: SRO may ask OSM to address.

If so, Floor Instructor acknowledge as OSM.

• RP/0/A/5700/000 (Classification of Emergency)

• RP/0/A/5700/010 (NRC Immediate Notification Requirements).

SRO (Step 19) Notify Reactor Group Duty NOTE: SRO may call wee to Engineer of load reduction. address.

If so, Booth Instructor acknowledge as weco SRO (Step 20) Check target load - LESS THAN 1000 MW.

Ro (Step 21) Check Unit 2 - AVAILABLE TO Floor Instructor: As U2 RO SUPPLY AUX STEAM (AS) HEADER. report "Yes."

SRO (Step 22) Dispatch operator to ensure the following valves are open:

• 1AS-74 (Unit 1 and Unit 2 AS Hdr Crosstie) service bldg, 739+12, room 202, R-27, over B RL Pump)

• Unit 2 valve 2AS-74 (Unit 2 AS Hdr IsoI)

(service bldg, 739+14, room 202, S-27, above RL strainer)

• 1AS-253 (Unit 1 AS Hdr Isol) (service NOTE: SRO will dispatch bldg, 739+ 15, P-28, room 202, above NLOs.

overhead door to Unit 1 turbine bldg).

Floor Instructor: After 3-4 minutes, as NLO report "Valves are Open."

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 4 _ _ _ _ _ Page 24 of 43

--~I Event

Description:

Steam Generator Tube LeaklDownpower Position A Iicant's Actions or Behavior NOTE: SRO will likely conduct a Focus Brief.

After the Brief the SRO may continue in AP1 0, while the plant is shutting down.

TECHNICAL SPECIFICATION 3.4.13, RCS OPERATIONAL LEAKAGE SRO 3.4.13 RCS Operational LEAKAGE Examiner NOTE: The SRO most likely will NOT address TS while maneuvering the plant. May want to address after scenario.

SRO LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

• 135 gallons per day primary to secondary LEAKAGE through anyone steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. RCS A.1 Reduce 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Operational LEAKAGE LWEAKAGE to within not within limits.

limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _4 _ _ _ _ _ Page 25 of 43 Event

Description:

Steam Generator Tube LeaklDownpower Time II Position ~ Applicant's Actions or Behavior TECHNICAL SPECIFICATION 3.7.16, SECONDARY SPECIFIC ACTIVITY SRO 3.7.16 Secondary Specific Activity SRO LCO 3.7.16 The specific activity of the secondary coolant shall be ~ 0.10 IJCi/gm DOSE EQUIVALENT 1..131.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. Specific A.1 Be in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> activity not MODE 3.

within limit.

AND A.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> At the discretion of the Lead Examiner move to Event #5.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _5 _ _ _ _ _ Page 26 of 43 Event

Description:

Uncontrolled Inward Rod Motion Time II Position ~ Applicant's Actions or Behavior During the downpower, uncontrolled inward rod motion will occur with Rod Control in automatic.

The operator will respond in accordance with AP14, "Rod Control Malfunction," and take manual control of the control rods. (The rods will remain in manual control throughout the remainder of the scenario).

Booth Operator Instructions: Operate Trigger #7 (MALF-IREOO3A)

Indications Available:

• Continuous inward rod motion with Tave-Tref matched or negative .

Examiner NOTE: This event may take 3-5 minutes to diagnose with the plant maneuvering.

AP/1/Al5500/14, ROD CONTROL MALFUNCTION NOTE: Crew will carry out Immediate Actions of AP14, prior to the SRO addressing the AP.

RO (Step 1) IF more than one rod dropped, THEN:

• Trip reactor.

• GO TO EP/1/A/5000/E-O (Reactor Trip or Safety Injection).

RO (Step 2) Place control rods in manual.

RO (Step 3) Check rod movement - STOPPED.

RO (Step 4) Check all rods - ALIGNED WITH ASSOCIATED BANK.

RO (Step 5) Check "ROD CONTROL URGENT FAILURE" alarm (1AD-2, A-10) - DARK.

RO (Step 6) Check the following reactor control instruments - NORMAL:

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 5 _ _ _ _ _ Page 27 of 43 Event

Description:

Uncontrolled Inward Rod Motion Time II Position I Applicant's Actions or Behavior

• "1A NC LOOP T-AVG"

• "1B NC LOOP T-AVG"

• "1C NC LOOP T-AVG"

• "10 NC LOOP T-AVG"

• "TURB IMP PRESS CH 1"

• T-Ref indication.

RO (Step 7) Check Nuclear Power P/R Channels

-NORMAL.

SRO (Step 9) IF this AP entered due to NOTE: The SRO will address unwarranted rod insertion or withdrawal, Enclosure 4.

THEN GO TO Enclosure 4 (Response To The load decrease may be Continuous rod Movement).

stopped to stabilize the plant.

AP/1/Al5500/14, ROD CONTROL MALFUNCTION ENCLOSURE 4, RESPONSE TO CONTINUOUS ROD MOVEMENT SRO (Step 1) Announce occurrence on paging NOTE: SRO may ask U2 RO system. to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 2) Evaluate the following prior to any control rod withdrawal:

• Ensure no inadvertent mode change will occur.

• Ensure control rods are withdrawn in a deliberate manner, while closely monitoring the reactor's response.

RO (Step 3) Check the following - NORMAL:

• "TURB IMP PRESS CH 1"

• T-Ref indication.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # _ 5 _ _ _ _ _ Page 28 of 43 Event

Description:

Uncontrolled Inward Rod Motion Time II Position ~ Applicant's Actions or Behavior RO (Step 4) Check the following channels -

NORMAL:

• "1A NC LOOP T-AVG"

• "1B NC LOOPT-AVG"

• "1C NC LOOP T-AVG"

• "1D NC LOOP T-AVG" SRO (Step 5) Check if failed channel - HAS BEEN IDENTIFIED.

RO / (Step 5 RNO) Perform the following:

BOP

• Notify rod control system qualified IAE NOTE: SRO may call WCC personnel to investigate problem with (IAE) to address.

Rod Control System.

If so, Booth Instructor acknowledge as WCC (IAE).

• Maintain T-Ave within 1°F of programmed T-Ref as follows:

• Adjust Turbine load OR

• Borate/dilute NC System.

At the discretion of the Lead Examiner move to Events # 6 - 8.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time II Position I Applicant's Actions or Behavior Shortly afterwards, the C MSIV inadvertently closes causing a major Steam Line Rupture to occur on the C Steam Generator inside the Containment. A Reactor Trip/Safety Injection will occur and the operator will enter E-O, "Reactor Trip or Safety Injection." The Containment Spray (NS) bistable will fail to energize, and require manual operator action. The SGTL in the B SG will degrade to about 75 gpm over the next 15 minutes due to the plant transient. Additionally, the B CA Pump will auto start but trip on overcurrent within 30 seconds of pump start. This will leave the CATD Pump as the only source of CA to the intact Steam Generators. Upon completion of E-O, an Orange Path on Containment will require a transition to FR-Z.1, "Response to High Containment Pressure." Upon completion of FR-Z.1, the operator will transition to E-2, "Faulted Steam Generator Isolation," and isolate the C Steam Generator. Upon Steam Generator isolation the steam supply for the CATD Pump will be provided from the B Steam Generator which has high radiation due to the on-going 75 gpm Steam Generator Tube Leak. After isolating the C Steam Generator, the operator will transition to E-3, "Steam Generator Tube Rupture," based on high radiation in the B Steam Generator. The scenario will terminate at Step 1 of E-3, after the crew has isolated the B Steam Generator with the exception of the Steam Supply to the CATD Pump.

Booth Operator Instructions: Operate Trigger #9 (OVR-SM012D, SM007C)

Change MALF SG001B to 75 gpm (900 Second Ramp)

Indications Available:

• C MSIV Closes

• C SG Pressure increases, then decreases below SGs A, B, and D.

• Containment Pressure increases NOTE: Crew will carry out Immediate Actions of E-O, prior to the SRO addressing the EP.

NOTE: The SRO may direct two NLOs standing by with

° Enclosure 3 of AP1 to isolate the 1B SG.

If so, Booth Instructor: Set

=

LOA-SA003 0, (1 SA-2/78).

NOTE: If so, this action will be undone at a later time or all CA flow will be lost when the 1C SG is isolated in E-2.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Position A licant's Actions or Behavior E-O, REACTOR TRIP OR SAFETY INJECTION SRO (Step 1) Monitor Foldout page.

RO (Step 2) check Reactor Trip:

• All rod bottom lights - LIT

• Reactor trip and bypass breakers -

OPEN

• I/R amps - GOING DOWN.

BOP (Step 3) Check Turbine Trip:

• All throttle valves - CLOSED.

BOP (Step 4) Check 1ETA and 1ETB-ENERGIZED.

RO I (Step 5) Check if SII is actuated:

BOP

• "SAFETY INJECTION ACTUATED" status light (1SI-18) - LIT.

• Both LOCA Sequencer Actuated status lights (1SI-14) - LIT.

SRO (Step 6) Announce "Unit 1 Safety Injection". NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 7) Check ESF Monitor Light Panel on energized train(s):

• Groups 1,2,5 - DARK.

• Group 3 - LIT.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time ~ Position ~ Applicant's Actions or Behavior

• OAC - IN SERVICE.

• Group 4, Rows A through F - LIT AS NOTE: BOP may recognize REQUIRED. that Containment Spray did NOT actuate and actuate CS manually.

SRO

• GO TO Step 8.

RO / (Step 8) Check proper CA pump status:

BOP

• MD CA pumps - ON. NOTE: Neither MD CA Pump will be running at this time.

The only source of CA flow is the TD CA Pump.

RO / (Step 8a RNO) Start pumps. NOTE: The SRO will verify BOP that the TD CA is running.

BOP (Step 9) Check all KC pumps - ON.

BOP Check both RN pumps - ON.

SRO (Step 11) Notify Unit 2 to start 2A RN pump. Floor Instructor: As U2 RO report "2A RN Pump is running."

RO (Step 12) Check all S/G pressures - NOTE: 1C SG Pressure is GREATER THAN 775 psig. decreasing uncontrollably.

Ro (Step 12 RNO) Perform the following:

• Check the following closed:

• All MSIVs

• All MSIV bypass valves

• All SM PORVs.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Position A licant's Actions or Behavior BOP (Step 13) Check Containment Pressure - NOTE: Containment Pressure HAS REMAINED LESS THAN 3 PSIG. is > 3 psig.

BOP (Step 13 RNO) perform the following:

• Record approximate time of reactor trip. NOTE: RO will report time of Rx Trip.

• Check Monitor Light Group 4, Row G, lit.

• IF any Row G window is dark on energized train(s), THEN perform the following:

• Initiate Phase B and Containment Spray signal.

Critical Task: (E-O E) Manually actuate the minimum required compliment of Containment Cooling Equipment (NS) (At least one Train) before transitioning out of E-O.

• Stop all NC pumps while maintaining seal injection flow.

• Ensure all RV pumps are in manual and off.

• Energize H2 Igniters by depressing "ON" and OVERRIDE".

SRO

• Dispatch operator to stop all Unit 1 NF NOTE: SRO will dispatch AHUs (control panels located in 750 and NLO.

733 electrical penetration rooms).

Booth Instructor: As NLO, report in 5 minutes that all Unit 1 NF AHUs are stopped.

Appendix 0 operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time II Position Applicant's Actions or Behavior

• When time allows, THEN check Phase B NOTE: The SRO may assign HVAC equipment PER Enclosure 2 the BOP to perform this action.

(Phase B HVAC Equipment).

If so, BOP Examiner follow actions of Enclosure 2.

The SRO may ask U2 BOP to perform this action.

If so, Floor Instructor:

Acknowledge as U2 BOP.

E-O, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 2, Phase B HVAC Equipment BOP (Step 1) Check VE System in Operation as Examiner NOTE: Follow the Follows: actions associated with Enclosure 2 if BOP is assigned by SRO to perform.

• VE Fans - On.

• Ensure all damper mode select switches in AUTO.

• 1AVS-D-7 Mode Select.

• 1AVS-D-8 Mode Select.

• 1AVS-D-2 Mode Select.

• 1AVS-D-3 Mode Select.

• Annulus pressure being maintained -

NEGATIVE BOP (Step 2) Check VX System in Operation as Follows:

• Time since Phase B actuation -

GREATER THAN 10 MINUTES.

• Check the following - OPEN.

• 1RAF-D-4 (1B Cont Air Ret Fan To Lwr Cont Test A).

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, & 8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time II Position II Applicant's Actions or Behavior

• 1VX-2B (1B H2 Skimmer Fan Isol Test A).

• 1RAF-D-2 (1A Cant Air Ret Fan To Lwr Cant Test A).

• 1VX-1A (1A H2 Skimmer Fan Isol Test A)

• Check Containment Air Return Fans -

ON.

• Check H2 Skimmer Fans - ON.

E-O, REACTOR TRIP OR SAFETY INJECTION BOPI (Step 14) Check SII flow:

RO

• Check "NV PMPS TO COLD LEG FLOW" gauge -INDICATING FLOW.

• Check NC pressures - LESS THAN 1600 PSIG.

BOPI (Step 14b RNO) Perform the following:

RO

• Ensure ND pump miniflow valve on running pump(s) open:

• 1ND-68A (1A ND Pump & Hx Mini Flow lsol)

• 1ND-67B (1B ND Pump & Hx Mini Flow Isol).

• IF valve(s) open on all running ND pumps, THEN GO TO Step 15.

SRO (Step 15) Notify OSM or other SRO to NOTE: SRO may ask OSM to perform EP/1/N5000/G-1 (Generic address.

Enclosures), Enclosure 22 (OSM actions If so, Floor Instructor Following an S/I) within 10 minutes.

acknowledge as OSM.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time II Position ~ Applicant's Actions or Behavior RO / (Step 16) Check CA flow:

BOP

• Total CA flow - GREATER THAN 450 GPM.

• Check VI header pressure - GREATER THAN 60 PSIG.

• Check VI header pressure - GREATER THAN 60 PSIG.

• WHEN N/R level in any S/G greater than NOTE: Adverse Containment 11% (32% ACC), THEN control CA flow Numbers will be used.

to maintain N/R levels between 11%

(320/0 ACC) and 50%.

RO (Step 17) Check NC temperatures:

• IF all NC pumps off, THEN check NC T- NOTE: All NC Pumps will be Cold - STABLE OR TRENDING TO OFF.

557°F RO (Step 17 RNO) Perform the following based NOTE: The SRO may assign on plant conditions: the RO to perform this action.

If so, RO Examiner follow actions of Enclosure 3.

• IF temperature less than 557°F AND going down, THEN attempt to stop cooldown PER Enclosure 3 (Uncontrolled NC System Cooldown).

E-O, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 3, UNCONTROLLED NC SYSTEM COOLDOWN RO (Step 1) Check steam dump valves - Examiner NOTE: Follow the CLOSED. actions associated with Enclosure 3 if RO is assigned by SRO to perform.

RO (Step 2) Check all SM PORVs - CLOSED.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time II Position ~ Applicant's Actions or Behavior RO (Step 3) Check MSR "RESET" light - LIT.

RO (Step 4) Check any NC pump - ON.

RO (Step 4 RNO) Perform the following:

• IF any NC T-Cold is still going down, THEN GO TO Step 6.

RO (Step 6) Control feed flow as follows:

• IF S/G N/R level is less than 11% (32%

ACC) in all S/Gs, THEN throttle feed flow to achieve the following:

• Minimize cooldown

• Maintain total feed flow greater than 450 GPM.

• WHEN N/R level is greater than 11%

(32% ACC) in at least one S/G, THEN throttle feed flow further to:

• Minimize cooldown

• Maintain at least one S/G N/R level greater than 11% (32% ACC).

RO (Step 7) Check MSIVs - ANY OPEN.

RO (Step 7 RNO) Perform the following:

• Close MSIV bypass valves.

• Exit this enclosure.

E-O, REACTOR TRIP OR SAFETY INJECTION BOP (Step 18) Check Pzr PORV and spray valves:

• All Pzr PORVs - CLOSED.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, & 8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time II Position ~ Applicant's Actions or Behavior

• Normal Pzr spray valves - CLOSED.

BOP (Step 19) Check NC subcooling based on core exit TICs - GREATER THAN OaF.

RO (Step 20) Check if main steam lines intact:

• All S/G pressure - STABLE OR GOING UP

• All S/Gs - PRESSURIZED.

SRO (Step 20 RNO) IF any S/G is faulted, THEN:

• IF fault is outside containment, THEN:

• Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/E-2 (Faulted Steam Generator Isolation).

• IF AT ANY TIME both of the following conditions exist, THEN start one train of VX PER Enclosure 4 (VX Manual Start).

• Containment pressure is between 1 PSIG and 3 PSIG.

• Containment pressure has remained less than 3 PSIG.

Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/E-2 (Faulted Steam NOTE: Upon transition to E-2, Generator Isolation). an ORANGE Path will exist on Containment.

The SRO will transition to FR-Z.1, rather than E-2.

FR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, & 8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time II Position ~ Applicant's Actions or Behavior FR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE SRO (Step 1) IF loss of emergency coolant recirc NOTE: Loss of Emergency has occurred, THEN this procedure may be Coolant Recirc has NOT completed as time allows. occurred.

SRO (Step 2) Monitor Foldout Page.

RO / (Step 3) Stop all NC pumps. NOTE: All NC Pumps are BOP stopped.

BOP (Step 4) ensure all RV pumps are in manual and off.

SRO (Step 5) Dispatch operator to remove white NOTE: SRO will dispatch tags and close the following breakers: NLO.

Floor/Booth Instructor:

Acknowledge as appropriate.

• 1EMXA-R2A (1A ND To A&B Cold Legs Cont Outside Isol Motor (1 NI-173A)) (aux bldg, 750, FF-54, FF-55).

• 1EMXB1-6B (1 B ND To C&D NC Cold Booth Instructor: Wait 5 Leg Cont Outside Isol Motor (1 NI-178B)) minutes, Insert LOA:

(aux bldg, 733, GG-55, GG-56).

NI024 = Racked In NI025 = Racked In And then, report as NLO that breakers are closed.

BOP (Step 6) Check containment pressure -

LESS THAN 15 PSIG.

BOP (Step 7) Check any NS pump - ON. NOTE: By this time both NS Pumps should be ON.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 1 Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Position A licant's Actions or Behavior SRO (Step 8) Perform the remainder of this EP as NOTE: SRO will transition to time allows. E-2.

E-2, FAULTED STEAM GENERATOR ISOLATION SRO (Step 1) Monitor Foldout page.

SRO (Step 2) Maintain at least one S/G available NOTE: Both 1A/1 D SGs are for NC System cooldown in subsequent available for cooldown. The steps. 1B SG has a SGTL.

SRO (Step 3) Maintain any faulted S/G or secondary break isolated during subsequent recovery actions unless needed for NC System cooldown.

RO (Step 4) Check the following - CLOSED:

• All MSIVs

• All MSIV bypass valves.

RO (Step 5) check at least one S/G pressure - NOTE: Both 1A/1 D SGs STABLE OR GOING UP. pressures are increasing. The 1B SG pressure is also increasing, but has a SGTL.

RO (Step 6) Identify faulted S/G(s):

• Any S/G pressure - GOING DOWN IN NOTE: The 1C SG is faulted.

AN UNCONTROLLED MANNER OR

• Any S/G - DEPRESSURIZED.

RO (Step 7) Check faulted S/G(s) SM PORV -

CLOSED.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, &8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time " Position ~ Applicant's Actions or Behavior RO (Step 8) Reset CA modulating valves.

RO / (Step 9) IF TD CA pump is the only source of NOTE: The TD CA Pump is BOP feedwater, THEN maintain steam flow to it the only source of feed, and its from at least one S/G. steam source must be maintained from 1B SG.

If the steam was previously isolated from the 1B SG to the TD CA Pump, the SRO will most likely unisolate 1B SG at this time.

!! necessary, Booth Instructor:

LOA-SA003 =1.0 Then, report actions as NLO.

RO / (Step 10) Isolate faulted S/G(s) as follows:

BOP

• For 1C S/G:

• Check "SG C FDW ISOLATED" status light (1 SI-4) - LIT.

• Close 1CA-50B (U1 TD CA Pump Disch To 1C S/G Isol).

• Close 1CA-46B (1B CA Pump Disch To 1C S/G Isol).

• Dispatch operator to unlock and NOTE: The SRO will dispatch close: an NLO to close 1SA-1 and 77.

Floor/Booth Instructor:

Acknowledge as appropriate.

• 1SA-1 (1 C S/G SM Supply to Unit 1 TD CA Pump Turb Maint Isol) (Unit 1 interior doghouse, 767 + 10, FF-53, above ladder)

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, & 8 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time II Position ~ Applicant's Actions or Behavior

• 1SA-77 (1C S/G SM Supply to Booth Instructor: Set LOA-Unit 1 TD CA Pump Turb Loop SA002 = 0, (1SA-1/77).

Seal Isol) (Unit 1 interior Wait 2 minutes and report as doghouse, 767+10, FF-53).

NLO that 1SA-1 and 77 are CLOSED.

• Check BB valves - CLOSED:

• 1BB-3B (1C S/G Blowdown Cont Outside Isol Control)

• 1BB-7A (C S/G BB Cont Inside Isol).

• Close 1SM-95 (C SM Line Drain Isol).

Critical Task: (E-2 A) Isolate the Faulted Steam Generator before transitioning out of E-2.

RO (Step 11) Close 1AS-12 (Main Steam To Aux Steam).

BOP (Step 12) CHECK if S/G tubes intact:

• Check steam line EMF's - NORMAL:

• 1EMF-24 (S/G A)

• 1EMF-25 (S/G B) NOTE: 1B SG was previously identified as leaking. 1EMF-25 is NOT Normal.

• 1EMF-26 (S/G C)

• 1EMF-27 (S/G D).

(Step 12a RNO) GO TO EP/1 A/5000/E-3 NOTE: The SRO will (Steam Generator Tube Rupture). transition to E-3.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # Event # 6,7, & 8 Page ~ of _4_3__

11 Event

Description:

Inadvertent MSIV Closure/Faulted SG - Auto Failure of NS/B CA Pump Trip Time " Position " Applicant's Actions or Behavior (Step 12b) IF any S/G has previously been identified as ruptured, THEN GO TO EP/1/A/5000/E-3 (Steam Generator Tube Rupture).

At the discretion of the Lead Examiner terminate the exam.

UNIT 1 STATUS:

Power Level: 75% NCS [B] 1136 ppm Pzr [8]: 1133 ppm Xe: Per OAC Power History: At 750/0 power (MOL), following an Core Burnup: 250.2 EFPDs unplanned load reduction four days ago to complete corrective maintenance on the 1B CF Pump.

The maintenance was completed and the pump restarted, and power level raised to the present power level two days ago. The present plan is to observe operation of the 1B CF Pump at this power level, and then raise power to 1000/0 within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

CONTROLLING PROCEDURE: OP/1/A/61 00/03 Controlling Procedure for Unit Operation OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

• The 1A NV was started last shift to support maintenance observation.

• A CA Pump (Expected back in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />).

• OEMF 43A, Control Room Air Intake Radiation Monitor, failed last shift (IAE is investigating) and Enclosure 4.14, "Response When EMF43A or 43B In Trip 2 or Inoperable," of OP/O/A/64501011 ,

"Control Area Ventilationl Chilled Water System."

• MCB Annunciator 1AD-8, B-6, "GLAND STM COND HI DIP," has alarmed spuriously several times over the last hour (IAE is investigating).

• It is expected to swap back to the 1B NV Pump on the upcoming shift. The previous shift has performed the flush and vent of the 1B NV Pump and the operator will commence the procedure starting at Step 3.3.4 of Enclosure 4.2 of OP/1/A/62001001 B, "Chemical and Volume Control System Charging." An NLO (John) is standing by locally to support the pump swap, and there are no R&Rs that will impact this activity.

Work Control SROIOffsite Communicator Jim Plant SRO Joe NLO*s AVAILABLE Aux Bldg. John Aux Bldg. Chris Turb Bldg. Bob Turb Bldg. Mike 5t h Rounds. Carol Extra NLOs: Bill Ed Wayne Tanya

PROGRAM: McGuire Operations Training MODULE: Initial License Operator Training Class 24 TOPIC: NRC Simulator Exam Scenario N08-1-2

REFERENCES:

1. PT/1/A/43S0/002B, "Diesel Generator Operability Test."

2. OP/1/A/6100/010G, "Annunciator Response For PaneI1AD-6."

3. AP/1/A/SSOO/014, "Rod Control Malfunction."

4. McGuire Technical Specifications S. OP/1/A/61 00/01 OH, "Annunciator Response For PaneI1AD-7."

6. AP/1/A/SSOO/012, "Loss of Letdown, Charging or Seal Injection."

7. OAC Alarm Response for M1A0689, "U1 Gland Steam Seal Header Pressure."

8. OAC Alarm Response for M1 P138S, "U1 Reactor Thermal Power, Best."

9. OP/1/A/61 00/01 OF, "Annunciator Response For PaneI1AD-S."

1O. McGuire Control Room Expectations Manual

11. OP/1/A/61 00/01 OC, "Annunciator Response For PaneI1AD-2."

12. EP/1/A/SOOO/E-0, "Reactor Trip or Safety Injection."

13. EP/1/A/SOOO/FR-Z-1, "Response to High Containment Pressure."

14. EP/1/A/SOOO/E-1, "Loss of Reactor or Secondary Coolant."

1S. EP/1/A/SOOO/ES-1.2, "Post-LOCA Cooldown and Depressurization."

16. EP/1/A/5000/ES-1.3, "Transfer to Cold Leg Recirculation."

17. RP/0/A/S700/000, "Classification of Emergencies."

Author: tern Technical Services, Inc.

Facility Review:

th March 4 , 2008 Rev. 2 Appendix D Scenario Outline Form ES-D-1 Facility: McGuire Scenario No.: 2 Op Test No.: N08-1 Examiners: Operators: (SRO)

---

i1 (OATC)

(BOP)

Initial Conditions: The Plant is at 100% power Steady-State (BOL), and has been for the last 12 days following Refueling Outage. The Diesel Generator 1B Operability Test is in progress and the Diesel has operated for 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per System Engineer request. It is presently loaded at 3800 KW and is ready to be shutdown in accordance with PT/1/A/4350/002B. The operation of the 1B DG was a Slow Start and conducted from the Control Room at the request of Maintenance.

Turnover: The following equipment is Out-Of-Service: 1B NI Pump (Expected back in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />), 1NV-265B, Boric Acid to NV Pumps, out for Limit Switch replacement (Expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />), PNV-5230, NCP 1A #1 Seal Differential Pressure indicator, failed last shift (IAE is investigating) and MCB Annunciator 1AD-12, C-2, "KR Storage Tank Low Level," has failed (IAE is investigating). An NLO (Wayne) is standing by at the 1B DG to assist in the shutdown. OTG is expected to be conducting some testing inside the TDCA Panel for about an hour early in the shift.

Event Malt. Event Type* Event No. No. Description 1 NA N-BOP Shutdown 1B DG N-SRO XMT 2 I-RO Thot Instrument fails high NC099 I(TS)-SRO 3 NV030 I-BOP Letdown Pressure Transmitter Failure/Letdown Relief Sticks open NV023A I-SRO 4 SM010 C-RO Steam Seal Pressure Regulator Failure C-SRO OVR 5 C-BOP Inadvertent Start of the TD CA Pump CA022 C(TS)-SRO 6 IRE006 C-RO Sequential Dropped Rods C-SRO 7 NC014A M-RO Pzr Steam Space LOCA M-BOP M-SRO 8 NI001A NA A NI Pump fails to Auto Start

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 2 McGuire 2008 NRC Scenario #2 The Plant is at 1000/0 power Steady-State (BOL), and has been for the last 12 days following Refueling Outage. The Diesel Generator 1B Operability Test is in progress and the Diesel has operated for 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per System Engineer request. It is presently loaded at 3800 KW and is ready to be shutdown in accordance with PT/1/A/4350/002B. The operation of the 1B DG was a Slow Start and conducted from the Control Room at the request of Maintenance.

The following equipment is Out-Of-Service: 1B NI Pump (Expected back in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />), 1NV-265B, Boric Acid to NV Pumps, out for Limit Switch replacement (Expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />),

PNV-5230, NCP 1A #1 Seal Differential Pressure indicator, failed last shift (IAE is investigating) and MCB Annunciator 1AD-12, C-2, "KR Storage Tank Low Level," has failed (IAE is investigating). An NLO (Wayne) is standing by at the 1B DG to assist in the shutdown. OTG is expected to be conducting some testing inside the TDCA Panel for about an hour early in the shift.

Shortly after taking the watch, the operator will shutdown the 1B Diesel Generator in accordance with step 2.52 of Enclosure 13.1, "1 B D/G Slow Start," of PT/1/A/4350/002B, "Diesel Generator Operability Test." The operator will adjust load to 2800-3000 KW and establish a 5 minute wait period.

During this five minute wait period, the Loop B Thot (TNC-8170) will fail high causing a Tavg-Tef mismatch and controls rods to insert. The operator will respond in accordance with ARP1 AD-6/A-10, "Auct Hi T-AVG, B-10, "T-REFIT-AUCT Abnormal," and D-10, "Loop T-AVG Deviation."

The operator will implement AP-14, "Rod Control Malfunction," and defeat the failed channel.

The operator will address Technical Specifications 3.3.1, "RTS Instrumentation," and 3.3.2, "ESFAS Instrumentation."

After this or during this time, the operator will continue the shutdown on the 1B Diesel Generator (Time compression will be used to satisfy cooldown requirements) in accordance with Enclosure 13.1, "1 B D/G Slow Start," of PT/1/A/4350/002B, "Diesel Generator Operability Test."

Subsequently, the Letdown line Pressure Transmitter will fail low causing NV-124 to close in an attempt to maintain setpoint pressure. With letdown flow closed off, actual Letdown line pressure will increase lifting the Letdown Line Relief Valve NV-6. Upon initial lift of this valve, NV-6 will fail in the open position. The operator will respond in accordance with ARP1AD-7/1-14, "Letdn Relief Hi Temp," and then implement AP-12, "Loss of Letdown, Charging or Seal Injection," due to the loss of Letdown flow. The operator will isolate normal Letdown and establish Excess Letdown.

Following this, the Steam Seal Header Pressure Control Valve, 1TL-6, will fail closed. The operator will respond to OAC alarm M1 A0689, "U1 Gland Steam Seal Header Pressure," and restore Main Turbine and CFPT Sealing Steam Pressure before a low Main Condenser Vacuum condition develops.

Shortly afterwards, the TDCA Pump will inadvertently start due an OTG error while working inside the TDGA Panel. The operator will respond to OAC alarm M1 P1385, "U1 Reactor Thermal Power, Best," and ARP1 AD-5/F-2, "TD CA Pump Lo Suct Flow." The operator will respond in accordance with the Control Room Expectations Manual for the condition in which CA operation occurs above 10% power. The stated expectation is that CA flow should be throttled/isolated as soon as practical. The operator will address Technical Specification 3.7.5, "Auxiliary Feedwater System," and SLC 16.9.7, "Standby Shutdown System."

Scenario Event Description NRC Scenario 2 After this, one Control Bank D Control Rod will drop into the core. The operator will respond in accordance with ARP1AD-2/D-9, "RPI at Bottom Rod Drop" and will implement AP-14, "Rod Control Malfunction." Shortly afterwards, a second rod will drop requiring that the operator manually trip the reactor. The operator will enter E-O, Reactor Trip or Safety Injection."

Upon the reactor trip a small break LOCA will occur in the Pressurizer Steam Space, and Safety Injection will be actuated. Upon the actuation of Safety Injection, the 1A NI Pump will fail to auto start and must be manually started. Upon completion of E-O, the operator will transition to E-1, "Loss of Reactor or Secondary Coolant," and the Reactor Coolant Pumps (NCPs) will be required to be manually tripped upon reaching the established NCP trip criteria. On the transition, an Orange Path will exist on the Containment Critical Safety Function, and the transition will be made to FR-Z.1, Response to High Containment Pressure," prior to E-1. Upon completion of FR-Z.1 the operator will transition to E-1.

The scenario will terminate at Step 14 of E-1, after the crew has determined to transition to ES-1.2, Post-LOCA Cooldown and Depressurization or upon a decision to transition to ES-1.3, "Transfer to Cold Leg Recirculation," based on E-1 Foldout Page criteria.

Critical Tasks:

SS Trip the reactor within 30 seconds of the second dropped rod (4600/113/E13.19)

SS (E1C)

Trip NC Pumps within 5 minutes of loss of SCM (4600/113/E13.1)

EOJ Establish flow from at least one Intermediate Head ECCS Pump before transition out of E-O.

Scenario Event Description NRC Scenario 2 SIMULATOR OPERATOR INSTRUCTIONS o Sima Setup Rod Step On o IC - 106 (May, 2008) o RUN o Update Status Board,

• 100 % Steady-State BOL Setup OAC

• MALF N1001B, 1B NI Pump OOS Setup ICCM, Turbine

• OVR-NV102A =OFF, OVR-NV102C = OFF (1 NV-265 Displays, & Trend OOS)

Recorders.

• XMT-NV004::= 0, PNV-5230 OOS Check Rod Step Counters agree with rod

• ANN-AD12-C02 = ON, AD-12/C2 Failed ON positions Check Make-up Control Switch in "ARMED."

Ensure DRPI Screen is Re-zeroed.

o (MALF) NI001A 1A NI Pump fails to Auto Start o Freeze.

o Update Fresh Tech.

Spec. Log.

o Fill out the NLO*s Available section of Shift Turnover Info.

o Prior to Crew Briefing RUN Scenario Event Description NRC Scenario 2 o Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Provide SRO with copy of PT/1/A/4350/002B, "Diesel Generator Operability Test," with Enclosure 13.1, marked up for placekeeping through Step 2.52.1 .4.

4. Provide SRO with Complex Plan associated with maintenance activities on 1NV-265B.

5. Direct the crew to Review the Control Boards taking note of present conditions, alarms.

o T-O Begin Familiarization Period o At direction of examiner NLO (Wayne) respond to assist in 1B OG Shutdown 1B DG Shutdown.

o At direction of examiner (XMT) NC099 Thot Instrument fails high Severity 650 Trigger 1 0 At direction of (MALF) NV030 Letdown Pressure Transmitter Failure/Letdown Relief examiner Sticks open Set 0 (MALF) NV023A Set OPEN Trigger 3 0 At direction of (MALF) SM010 Steam Seal Pressure Regulator Failure examiner Set 0 Trigger 5 0 At direction of (OVR) CA022 Inadvertent Start of the TD CA Pump examiner SetON Trigger 7 o At direction of examiner (MALF) IRE006 - M12 Sequential Dropped Rods Trigger 9 (MALF) IRE006 - 04 Trigger 11 Scenario Event Description NRC Scenario 2 o At direction of examiner (MALF) NC014A Pzr Steam Space LOCA Set 100 Trigger 13 NOTE: Trigger #13 set to jpplp4(1) (Rx Trip)

(Conditional: Rx Trip) n Terminate the scenario upon direction of Chief Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ Page 8 of _5_6----11 Event

Description:

Shutdown 1B DG Time II Position II Applicant's Actions or Behavior Shortly after taking the watch, the operator will shutdown the 1B Diesel Generator in accordance with step 2.52 of Enclosure 13.1, "1 B DIG Slow Start," of PT/1/A/43501002B, "Diesel Generator Operability Test." The operator will adjust load to 2800-3000 KW and establish a 5 minute wait period. After Event 2 or during this time, the operator will continue the shutdown on the 1B Diesel Generator (Time compression will be used to satisfy cooldown requirements) in accordance with Enclosure 13.1, "1 B DIG Slow Start,"

of PT/1/A/43501002B, "Diesel Generator Operability Test."

Booth Operator Instructions: An NLO (Wayne) is standing by at the 1B DG to assist in the shutdown.

Indications Available: NA PT/1/A14350/002B, DIESEL GENERATOR OPERABILITY TEST ENCLOSURE 13.1, 1B DIG SLOW START BOP (Step 2.52.2) Lower DIG load to 2800-3000 KW using "1B DIG Gov Cntrl."

BOP (Step 2.52.3) Maintain power factor 0.90 -

0.92 lagging using "1B DIG Volt Adjust" When BOP has established a 5 minute wait period, move to Event #2.

(Return after Event #2, starting with Step 2.53 below)

BOP (Step 2.53) WHEN DIG has operated at NOTE: By this time, the 1B 2800-3000 KW for at least 5 minutes, DIG has been operating at perform the following: 2800-3000 KW in excess of 5 minutes.

• Lower DIG load to 1800 - 2000 KW using "1B DIG Gov Cntrl"

• Maintain power factor 0.90 - 0.92 lagging using "1B DIG Volt Adjust"

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 9 of 56

---II Event

Description:

Shutdown 1B DG Time II Position ~ Applicant's Actions or Behavior BOP (Step 2.54) WHEN DIG has operated at 1800 NOTE: After BOP adjusts

- 2000 KW for 10 minutes, perform the load on 1B DIG to 1800-2000 following: KW, Floor Instructor: Report 10 minutes has elapsed (Time Compression).

• Lower DIG load to 800 - 1000 KW using "1 B DIG Gov Cntrl"

• Maintain power factor 0.90 - 0.92 lagging using "1B DIG Volt Adjust" BOP (Step 2.55) WHEN DIG has operated at 800 NOTE: After BOP adjusts

- 1000 KW for 10 minutes, perform the load on 1B DIG to 800-1 000 following: KW, Floor Instructor: Report 10 minutes has elapsed (Time Compression).

• Check "1ETB Normal Breaker" or "1 ETB Stdby Breaker" closed.

• Lower DIG load to less than 200 KW using "1B DIG Gov Cntrl".

• Open "1ETB Emerg Breaker".

BOP (Step 2.56) IF performing a routine monthly NOTE: Not in RN Fouling 1B DIG Operability Test during the RN Season.

Fouling Season (August, September, If contacted, Booth October), contact Engineering to determine if Instructor: Report No Super a Super Flush required.

Flush required.

BOP (Step 2.58) Allow DIG to idle unloaded for 15 NOTE: The remainder of the minutes. 1B DIG shutdown will be performed locally by the NLO (Wayne).

At the discretion of the Lead Examiner move to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 2 _ _ _ _ Page 10 of _5_6.....-011 Event

Description:

That Instrument fails high Time II Position ~ Applicant's Actions or Behavior During this five minute wait period (Event 1), the Loop B Thot (TNC-8170) will fail high causing a Tavg-Tef mismatch and controls rods to insert. The operator will respond in accordance with ARP1AD-6/A-10, "Auct Hi T-AVG, B-10, "T-REFIT-AUCT Abnormal,"

and D-10, "Loop T-AVG Deviation." The operator will implement AP-14, "Rod Control Malfunction," and defeat the failed channel. The operator will address Technical Specifications 3.3.1, "RTS Instrumentation," and 3.3.2, "ESFAS Instrumentation."

Booth Operator Instructions: Operate Trigger #1 (XMT-NC099 (650>>

Indications Available:

• 1AD-6/A10, "Auct Hi T-avg"

• 1AD-6/B 10, "T-refIT-auct Abnormal"

• 1AD-6/D10, "Loop T-avg Deviation"

• 1AD-6/E10, "Loop DIT Deviation"

• 1AD-6/F7, "OTDT Protection Alert"

• 1AD-6/F8, "OPDT Protection Alert"

• Rods move in Auto OP/1/Al61 00/01OG, ANNUNCIATOR RESPONSE FOR PANEL 1AD-6 A10, AUCT HI TAVG SRO (IA Step 1) IF channel in test, no further NOTE: Crew may NOT action required. address ARP, but enter AP14 directly.

SRO (IA Step 2) IF Control Rod malfunction, go to AP/1Al55001014 (Rod Control Malfunction)

RO (IA Step 3) IF at power, place "CRD Bank Selector" in "MAN" RO (IA Step 4) IF load rejection, go to AP/1/A/55001003 (Load Rejection).

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _2 _ _ _ _ _ Page 11 of _5_6_-.041 Event

Description:

Thot Instrument fails high Time ~ Position ~ Applicant's Actions or Behavior SRO (SA Step 1) IF instrument failure, refer to Tech Specs for minimum instrumentation requirements.

SRO (SA Step 2) IF in Mode 1 or 2, notify SWM to ensure transient monitor freeze triggered.

{PIP M-98-4253}

AP/1/Al5500/14, ROD CONTROL MALFUNCTION NOTE: Crew will carry out Immediate Actions of AP14, prior to the SRO addressing the AP.

RO (Step 1) IF more than one rod dropped, THEN:

• Trip reactor.

• GO TO EP/1/A/5000/E-O (Reactor Trip or Safety injection).

RO (Step 2) Place control rods in manual. NOTE: RO has previously placed Control Rods in MANUAL.

RO (Step 3) Check rod movement - STOPPED.

RO (Step 4) Check all rods - ALIGNED WITH ASSOCIATED BANK.

RO (Step 5) Check "ROD CONTROL URGENT FAILURE" alarm (1AD-2, A-10) - DARK.

RO (Step 6) Check the following reactor control instruments - NORMAL:

• "1A NC LOOP T-AVG"

• "1B NC LOOP T-AVG" NOTE: Loop 1B Tavg has failed.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 2 _ _ _ _ _ Page 12 of 56

--~I Event

Description:

That Instrument fails high Time II Position ~ Applicant's Actions or Behavior

• "1C NC LOOP T-AVG"

• "10 NC LOOPT-AVG"

• "TURB IMP PRESS CH"

• T-Ref indication.

ROJ (Step 6 RNO) IF "NC LOOP T-AVE channel failed, THEN:

BOP

• Place "OfT DEFEAT" switch to failed loop.

• Place "T-AVE DEFEAT" switch to failed loop.

• Monitor CF pump speed control response.

• Monitor SJG NR levels.

• IF AT ANY TIME CF pumps speed NOTE: This is a Continuous control fails to respond properly, THEN Action. The SRO will make take manual control of CF pump(s) as both board operators aware.

necessary to stabilize.

SRO GO TO Enclosure 4 (Response To NOTE: BOP may need to take Continuous Rod Movement). manual control of 1NV-238 and manually adjust Charging Flow.

AP/1/Al5500/14, ROD CONTROL MALFUNCTION ENCLOSURE 4, RESPONSE TO CONTINUOUS ROD MOVEMENT SRO (Step 1) Announce occurrence on paging NOTE: SRO may ask U2 RO system. to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 2) Evaluate the following prior to any control rod withdrawal:

• Ensure no inadvertent mode change will occur.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _2 _ _ _ _ _ Page 13 of 56

--"""'II Event

Description:

That Instrument fails high Time II Position II Applicant's Actions or Behavior

• Ensure control rods are withdrawn in a deliberate manner, while closely monitoring the reactor's response.

RO (Step 3) Check the following - NORMAL:

• "TURB IMP PRESS CH 1"

• T-Ref indication.

RO/ (Step 4) check the following channels -

NORMAL:

BOP

• "1A NC LOOP T-AVG"

• "18 NC LOOPT-AVG" NOTE: Loop 18 Tavg has failed.

• "1C NC LOOP T-AVG"

• "1D NC LOOP T-AVG" RO/ (Step 4 RNO) Perform the following:

BOP

• Perform any of the following as NOTE: Rods may have necessary to maintain T-Ave at T-Ref: stepped in as many as 10 steps.

RO will withdraw rods to original position, and may take 5-10 minutes to restore rods to original position.

• Position control rods in manual.

OR

• Borate/dilute NC System OR

• Adjust Turbine load.

RO

• WHEN T-Ave at T-Ref +/-1°F, AND auto NOTE: RO will place Rods in rod control is desired, THEN return rod AUTO upon restoring rods to control to auto. their original position.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 2 Page 14 of 56

--~I Event

Description:

That Instrument fails high Time A Iicant's Actions or Behavior RO

• Ensure P-12 interlock is in required state for existing unit conditions (Tech Spec 3.3.2.8.c).

SRO

• Instruct IAE to trip bistables associated NOTE: SRO may call with failed loop within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of failure WCC/IAE to address.

PER IP/O/A/30901014 (Tripping If so, Booth Instructor Inoperable Protection Channels):

acknowledge as WCC/IAE as appropriate.

• OPDT (Tech Spec 3.3.1.7)

• OTDT (Tech Spec 3.3.1.6)

• Low T-Ave (Tech Spec 3.3.2.5.d).

SRO

• WHEN problem is repaired, THEN perform the following:

• Instruct IAE to place the following bistables for failed loop back in service:

• Place the following switches to "OFF".

• Exit this procedure. NOTE: SRO will likely conduct a Focus Brief.

NOTE: Crew may need prompt to return to 1B DIG Shutdown.

If so, Booth Instructor as NLO (Wayne) ask SRO/BOP about 1B DIG Shutdown.

TECHNICAL SPECIFICATION 3.3.1, RTS INSTRUMENTATION SRO 3.3.1 Reactor Trip System (RTS) Examiner NOTE: Addressing Instrumentation TS takes 8-10 minutes. May want to address after scenario, or may occur will BOP continues with shutdown of 1B DIG.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 2 Page 15 of 56

---II Event

Description:

That Instrument fails high Time II Position ~ Applicant's Actions or Behavior SRO LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

SRO APPLICABILITY:

According to Table 3.3.1-1.6 - Over temperature ilT 7 - Overpower ilT.

SRO Actions CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Enter the Immediately more Condition Functions referenced with one or in Table more 3.3.1-1 for required the channels channel(s).

inoperable.

E. One E.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel channel in inoperable. trip.

OR E.2 Be in MODE 3.

TECHNICAL SPECIFICATION 3.3.1, ESFAS INSTRUMENTATION SRO 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation SRO LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

SRO APPLICABILITY:

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 2 Page 16 of 56

--""""II Event

Description:

That Instrument fails high Time II Position II Applicant's Actions or Behavior According to Table 3.3.2-1 5.b.4 Feedwater IsolationfTavg low; 8.c ESFAS InterlockslTavg low-low P-12.

SRO Actions CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Enter the Immediately more Conditio Functions n with one or referenc more ed in required Table channels or 3.3.2-1 trains for the inoperable. channel(

s) or train(s).

J. One J.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel channel inoperable. in trip.

OR J.2 Be in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> MODE 3.

Q. One Q.1 Verify 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> channel interlock inoperable. is in required state for existing unit condition OR Q.2.1 Be in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> MODE 3.

AND 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> Q.2.2 Be in MODE 4.

At the discretion of the Lead Examiner, Return to Event #1 to complete the remaining portions on Page 8.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _3 _ _ _ _ Page 17 of _5_6---11 Event

Description:

Letdown Pressure Transmitter Failure/Letdown Relief Sticks Open Time II Position II Applicant's Actions or Behavior Subsequently, the Letdown line Pressure Transmitter will fail low causing NV-124 to close in an attempt to maintain setpoint pressure. With letdown flow closed off, actual Letdown line pressure will increase lifting the Letdown Line Relief Valve NV-6. Upon initial lift of this valve, NV-6 will fail in the open position. The operator will respond in accordance with ARP1AD-7/1-4, "Letdn Relief Hi Temp," and then implement AP-12, "Loss of Letdown, Charging or Seal Injection," due to the loss of Letdown flow. The operator will isolate normal Letdown and establish Excess Letdown.

Booth Operator Instructions: Operate Trigger #3 (MALF-NV030(O)/NV023A (OPEN>>

Indications Available:

• 1AD-7/14, "Letdn Relief Hi Temp."

• Letdown Pressure lowers to bottom of scale

• Letdown flow lowers

• If prolonged PRT Level/Temperature rise OP/1/Al61 00/01 OH, ANNUNCIATOR RESPONSE FOR PANEL 1AD-7 14, LETDN RELIEF HI TEMP RO (IA Step 1) Monitor letdown pressure and NOTE: Crew may NOT correct if necessary. address ARP, but enter AP12 directly.

RO (SA Step 1) Monitor VCT and PRT. NOTE: The crew will manually isolate Letdown due to the leak and enter AP12.

If the crew enters AP10 instead, the leak will be isolated when Letdown is isolated and excess. Letdown will need to be established in accordance with AP12 for inventory control.

AP/1/Al5500/12, LOSS OF LETDOWN, CHARGING OR SEAL INJECTION

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 3 _ _ _ _ Page 18 of 56

---

ll Event

Description:

Letdown Pressure Transmitter Failure/Letdown Relief Sticks Open Time II Position ~ Applicant's Actions or Behavior BOP (Step 1) IF a loss of charging through the Regenerative HX has occurred, THEN ensure the following are closed:

• 1NV-458A (75 GPM UD Orifice Outlet Cant Isol)

• 1 NV-457A (45 GPM UD Orifice Outlet Cant Isol)

• 1NV-35A (Variable UD Orifice Outlet Cant Isol).

BOP (Step 2) Check Pzr level - LESS THAN 96%.

BOP (Step 3) IF AT ANT TIME "REGEN HX LETDN HI TEMP" alarms (1AD-7, 1-2),

THEN close the following valves:

• 1NV-1A (NC UD Isol To Regen Hx) NOTE: These valves are most likely already closed.

• 1NV-2A (NC UD Isol To Regen Hx).

SRO (Step 4) Stop any power or temperature changes in progress.

SRO (Step 5) Announce occurrence on paging NOTE: SRO may ask U2 RO system. to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

SRO (Step 6) IF this AP entered due to loss of letdown only, THEN GO TO Step 36.

BOP (Step 36) Ensure the following are closed:

• 1NV-458A (75 GPM UD Orifice Outlet Cant Isol)

• 1NV-475A (45 GPM UD Orifice Outlet Cant Isol)

Appendix D Operator Action Form ES-D-2 Op Test No.: N08*1 Scenario # 2 Event # 3 Page 19 of 56

---

ll Event

Description:

Letdown Pressure Transmitter Failure/Letdown Relief Sticks Open Time II Position ~ Applicant's Actions or Behavior

• 1NV-35A (Variable UD Orifice Outlet Cont Isol).

BOP (Step 37) "NC SYS M/U CONTROLLER" in "AUTO".

BOP (Step 38) Ensure charging flow going down to maintain Pzr at program level.

BOP (Step 39) Check "LETDN RELIEF HI TEMP" alarm (1AD-7, 1-4) - HAS REMAINED DARK.

BOP (Step 39 RNO) Evaluate if low failure of letdown pressure instrument caused loss of letdown.

BOP (Step 40) Check 1NV-21A (NV Spray To PZR Isol) - CLOSED.

BOP (Step 41) Operate Pzr heaters as follows:

• Check all Pzr heater group supply breakers - CLOSED.

• Check normal Pzr spray - AVAILABLE.

• Place the following Pzr heater groups in manual and "ON" to maximize spray flow:

• A

• B

• D.

BOP (Step 42) check the following valves - NOTE: These valves have OPEN: been previously closed.

• 1NV-1A (NC UD Isol To Regen Hx)

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 3 _ _ _ _ _ Page 20 of 56

---ll Event

Description:

Letdown Pressure Transmitter Failure/Letdown Relief Sticks Open Time II Position II Applicant's Actions or Behavior

• 1NV-2A (NC LID Isol To Regen Hx).

SRO (Step 42 RNO) IF normal letdown known to NOTE: Normal Letdown is be unavailable, THEN GO TO Step 49. unavailable because it was isolated to stop the Leak.

BOP (Step 49) Establish excess letdown:

• Adjust charging to minimum while maintaining the following:

• NC pump seal injection flow greater than 6 GPM

• Pzr level at program level.

• IF AT ANY TIME excess letdown cannot be established, THEN observe Note prior to Step 50 and GO TO Step 50 to establish letdown using Rx Vessel Head Vents.

• Open the following:

• 1KC-315B (Excess LID Hx Ret Hdr Cont Otsd Isol).

• 1KC-305B (Excess UD Hx Sup Hdr Cont Otsd Isol).

• Ensure 1NV-27B (Excess UD Hx Otlt 3-Way Cntrl) selected to "VCT" position.

• Open 1NV-26 (Excess UD Hx Outlet Cntrl).

• Wait 2 minutes.

• Close 1NV-26 (Excess UD Hx Outlet Cntrl).

• Check the following valves - OPEN:

• 1NV-94AC (NC Pumps Seal Ret Cont Inside Iso I)

• 1NV-95B (NC Pumps Seal Ret Cont Outside Isol).

• Open 1NV-24B (C NC Loop To Exs LID Hx Isol).

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 3 _ _ _ _ _ Page 21 of 56

--"""'II Event

Description:

Letdown Pressure Transmitter Failure/Letdown Relief Sticks Open Time II Position II Applicant's Actions or Behavior

• Open 1NV-25B (C NC Loop To Exs UD Hx Isol).

• Check the following:

RO

• Reactor - CRITICAL BOP

• 1NV-27B - ALIGNED TO VCT

• Closely monitor reactor response once excess letdown is in service.

• Slowly open 1NV-26 while maintaining NOTE: BOP will fully open excess letdown HX temperature less 1NV-26 over time, in order to than 200°F. control inventory.

SRO

• GO TO Step 49.r.

• Notify Primary Chemistry that excess NOTE: SRO may call letdown is in service. Chemistry to address.

If so, Booth Instructor acknowledge as Chemistry.

BOP

• Adjust charging flow as desired while maintaining:

• NC pump seal injection flow greater than 6 GPM

• Pzr level at program level.

• Operate Pzr heaters as desired.

SRO

• WHEN time allows, THEN notify NOTE: SRO may call WCC to engineering to document the following address.

transients:

If so, Booth Instructor acknowledge as WCC.

• Letdown isolation

• Potential charging nozzle transient

• IF NV Aux Spray was in service, NOTE: NV Aux Spray has THEN spray nozzle transient. NOT been used.

BOP

• Check 1NV-27B (Excess LID Hx Otlt 3-Way Cntrl) - ALIGNED TO "VCT".

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 3 _ _ _ _ _ Page 22 of 56

---II Event

Description:

Letdown Pressure Transmitter Failure/Letdown Relief Sticks Open Time ~ Position I Applicant's Actions or Behavior

• IF AT ANY TIME VCT level needs to be NOTE: This is a Continuous lowered AND NCDT is available to pump Action. The SRO will make water outside containment, THEN both board operators aware.

perform the following:

• Place 1NV-27B to "NCDT".

• Adjust 1NV-26 (Excess UD Hx Outlet Cntrl) as necessary to maintain NCDT pressure less than 8 PSIG.

• WHEN VCT at desired level, THEN return 1NV-27B to "VCT".

SRO

• WHEN normal letdown available, THEN establish normal letdown PER Steps 42 through 48.

SROI

• WHEN desired to isolate excess BOP letdown, THEN perform the following:

• Close 1NV-26 (Excess UD Hx Outlet Cntrl).

• Close 1NV-24B (C NC Loop To Exs UD Hx Isol).

• Close 1NV-25B (C NC Loop To Exs UD Hx losl).

• Close 1KC-305B (Excess LID Hx Sup Hdr Cant Otsd Isol).

• Close 1KC-315B (Excess LID Hx Ret Hdr Cont Otsd Isol).

SRO

• RETURN TO procedure and step in NOTE: SRO may call WCC to effect. address.

If so, Booth Instructor acknowledge as WCC.

NOTE: SRO may address AP10 to deal with Relief Valve Leak into PRT.

At the discretion of the Lead Examiner move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 4 _ _ _ _ Page 23 of _5_6----41 Event

Description:

Steam Seal Pressure Regulator Failure Position A licant's Actions or Behavior Following this, the Steam Seal Header Pressure Control Valve, 1TL-6, will fail closed.

The operator will respond to GAC alarm M1A0689, "U1 Gland Steam Seal Header Pressure," and restore Main Turbine and CFPT Sealing Steam Pressure before a low Main Condenser Vacuum condition develops.

Booth Operator Instructions: Operate Trigger #5 (MALF- SM010 (0>>

Indications Available:

• OAC Alarm M1 A0689, "U1 Gland Steam Seal Header Pressure."

• OAC Alarm M1 A0801, "1 A & 1B CFPT Sealing Steam Pressure."

• If prolonged, Main Condenser vacuum starts to lower.

M1 A0689, U1 GLAND STEAM SEAL HEADER PRESSURE RO (Step 1) throttle open 1TL-8 (HP STEAM NOTE: RO will throttle open SEAL BYPASS VALVE) to maintain "STM 1TL-8.

SEAL HEADER PRESS" between 90 to 120 psig.

SRO (Step 2) Notify Maintenance to troubleshoot NOTE: SRO may call WCC to 1TL-6 (STEAM SEAL HDR PRESSURE address.

CONTROL VALVE).

If so, Booth Instructor acknowledge as WCC.

RO (Step 3) If "STM SEAL HEADER PRESS" NOTE: SRO may dispatch cannot be maintained at least 90 psig, NLO to locally investigate.

dispatch an operator to look for steam leaks If so, Booth Instructor and verify valve alignment per acknowledge as NLO, and OP/1/S/63001005 (Steam Seal System).

report parameters as expected.

M1A0801, 1A & 1B CFPT SEALING STEAM PRESSURE

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 4 Page 24 of 56

---II Event

Description:

Steam Seal Pressure Regulator Failure Time ~ Position I Applicant's Actions or Behavior ROJ (Step 1) Ensure valve 1TF-2 (GF PUMP NOTE: If the RO corrects the NLO TURB STEAM SEAL GTRL) working Gland Steam Seal Header properly to maintain steam seal pressure Pressure by throttling 1TL-8, between 1 to 4 psig. the Steam Seal concern with the GFPTs will be corrected as well.

RO / If necessary, open 1TF-4 (GF PUMP TURB NLO STEAM SEAL GTRL BYP) to maintain steam seal pressure between 1 to 4 psig.

At the discretion of the Lead Examiner move to Event #5.

~ Alarn} Response II

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 5 _ _ _ _ Page 25 of 56 Event

Description:

Inadvertent Start of the TO CA Pump Time Position Applicant's Actions or Behavior Shortly afterwards, the TOCA Pump will inadvertently start due to an OTG error while working inside the TOCA Panel. The operator will respond to OAC alarm M1 P1385, "U1 Reactor Thermal Power, Best," and ARP1AO-5/F-2, "TO CA Pump Lo Suct Flow." The operator will respond in accordance with the Control Room Expectations Manual for the condition in which CA operation occurs above 10% power. The stated expectation is that CA flow should be throttled/isolated as soon as practical. The operator will address Technical Specification 3.7.5, "Auxiliary Feedwater System," and SLC 16.9.7, "Standby Shutdown System."

Booth Operator Instructions: Operate Trigger #7 (OVR- CA022 (ON>>

Indications Available:

• OAC Alarm M1 P1385, "U1 Reactor Thermal Power, Best."

• 1AO-5/F2, "TO CA Pump Lo Suct Flow."

• CA Flow indicated to all four Steam Generators

• Valve position indicators for 1SA-48ABC and 1SA-49AB have red status lights lit.

• TO CA Pump at 3800 RPM.

M1P1385, REACTOR THERMAL POWER, BEST RO (Step 1) HI HI IF "FAILED" or "BAD NOTE: Crew mayor may NOT QUALITY" status, refer to PT/1/A/4600/021 A refer to alarm response.

(LOSS OF OPERATOR AID COMPUTER Regardless, Thermal Power WHILE IN MODE 1). will need to be reduced.

RO (Step 2) Ensure reactor power is reduced to less than or equal to 100 % (3411 MWT).

Simulator Instructor: 2 minutes after Pump start call Control Room as IAE and report that you inadvertently started the TO CA Pump while working inside the TD CA Control Panel.

RO (Step 3) Check the following have not been exceeded:

• M1P2372 (U1 THERMAL POWER 15 MINUTE RUNNING AVERAGE)

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 5 _ _ _ _ _ Page 26 of 56 Event

Description:

Inadvertent Start of the TO CA Pump Time ~ Position ~ Applicant's Actions or Behavior

• M1 P0856 (U1 AVG RATED THERMAL POWER, HOURLY)

• M1 P0779 (U1 THERMAL POWER OUTPUT, 4 HOUR AVG)

• M1 P0965 (U1 THERMAL POWER 12 HOUR RUNNING AVERAGE)

SRO (Step 4) Refer to TS 3.4.1.

SRO (Step 5) Refer to SOMP 01-02 (REACTIVITY MANAGEMENT).

RO (Step 6) Perform the following for swings of unknown origin.

• Type "TABLOG" in OAC input window.

• Depress "F3" to access dialog box "ENTER LOG NAME FOR ACTIVATION".

• Type "TPBE" in dialog box.

• Click "OK".

• Check TPBE ACTIVATED" in status column.

• Contact Reactor Duty Engineer with the time "TPBE" was activated.

SRO (Step 7) Initiate a PIP for reactor power NOTE: The SRO will probably exceeding 101.50/0. call Security to implement Comp Measures for the inoperability of the SSF (10 minute Action required by SLC 16.9.7)0

~ Alarm Response II Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 5 _ _ _ _ _ Page 27 of 56 Event

Description:

Inadvertent Start of the TO CA Pump TimA I Position ~ Applicant's Actions or Behavior OP/1/Al61 00/01 OF, ANNUNCIATOR RESPONSE FOR PANEL 1 AO-5 F2, TO CA PUMP LO SUCT FLOW BOP (Step IA) IF recirculation control does NOT establish minimum flow of 360 - 720 gpm suction flow:

• Ensure open:

.. 1CA-231 (#1 TO CA Pump Mini Flow 2 nd Isol)

.. 1CA-255 (#1 TO CA Pump Mini Flow 1 st Isol)

CONTROL ROOM EXPECTATIONS MANUAL SRO CA Operation above 10% power.

SRO CA flow should be throttled/isolated as soon as practical. This will make the effected CA pumps inoperable due to the control valve not being fully open above 10% as required by the CA SR.

SRO Feeding SGs with CA pumps results in feeding slightly oxygenated water from the CASTs. This could result in exceeding Action Level 2 limits for SG oxygen.

BOP Close the following valves: NOTE: The SRO will direct that the Flow Control Valves from the TO CA Pump be closed, which will render the TO CA Pump inoperable.

.. 1CA-64 (TO CA Pump to S/G A)

• 1CA-52 (TD CA Pump to S/G B)

• 1CA-48 (TO CA Pump to S/G C)

Appendix D operator Action Form ES-D-2 Op Test No.: NOB-1 Scenario # 2 Event # 5 Page 28 of 56 Event

Description:

Inadvertent Start of the TO CA Pump Time II Position ~ Applicant's Actions or Behavior

• 1CA-36 (TD CA Pump to S/G D)

TECHNICAL SPECIFICATION 3.7.5, AUXILIARY FEEDWATER SYSTEM SRO LCO 3.7.5 Three AFW trains shall be Examiner NOTE: Addressing OPERABLE. TS takes 8-10 minutes. May want to address after scenario.

SRO APPLICABILITY:

MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

SRO ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME B. OneAFW B.1 Restore 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> train AFW train inoperable to AND in MODE 1, OPERABLE 10 days from 2 or 3 for status. discovery of reasons failure to other than meet the Condition LCO A.

SELECTED LICENSEE COMMITMENT 16.9.7, STANDBY SHUTDOWN SYSTEM SRO COMMITMENT The Standby shutdown System (SSS) shall be operable.

SRO APPLICABILITY MDOES 1, 2, and 3.

SRO REMEDIAL ACTIONS

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 5 Page 29 of 56 Event

Description:

Inadvertent Start of the TO CA Pump Time " Position " Applicant's Actions or Behavior The SRO should ensure that security is notified 10 minutes prior to declaring the SSS inoperable. Immediately upon discovery of the SSS inoperability, Security must be notified to implement compensatory measures within 10 minutes of the discovery.

CONDITION REQUIRED COMPLETION ACTION TIME A. One or A. 1Verify the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> more OPERABILITY required of fire SSS detection and components suppression identified in systems in the Table associated 16.9.7-1 areas inoperable. identified in Table 16.9.7-1.

AND A.2 Restore the 7 days component to OPERABLE status.

At the discretion of the Lead Examiner move to Event #6.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event #

6 Page 30 of 56 Event

Description:

Sequential Dropped Rods Time II Position ~ Applicant's Actions or Behavior After this, one Control Bank D Control Rod will drop into the core. The operator will respond in accordance with ARP1 AD-2/D-9, "RPI at Bottom Rod Drop" and will implement AP-14, "Rod Control Malfunction." Shortly afterwards, a second rod will drop requiring that the operator manually trip the reactor. The operator will enter E-O, Reactor Trip or Safety Injection."

Booth Operator Instructions: Operate Trigger #9 (MALF- IRE006 - M12)

Indications Available:

• 1AD-2/D9, "RPI At Bottom Rod Drop."

• 1AD-2/A10, "Rod Control Urgent Failure."

• 1AD-2/01 0, "RPI Urgent Failure."

• 1AD-2/B1, "P/R Lower Det Hi Flux Devor Auto Defeat."

• 1AD-2/B2, "P/R Upper Det Hi Flux Devor Auto Defeat."

• 1AD-2/B3, "P/R Channel Deviation."

• 1AD-2/A8, "OTOT RunbackiRod Stop Alert."

• 1AD-2/B8, "OPOT RunbackiRod Stop Alert."

• NC Temperature drops (Tavg < Tref)

OP/1/Al6100/010C, ANNUNCIATOR RESPONSE FOR PANEL 1AD-2 09, RPI At BOTTOM ROD DROP SRO (IA Step 1) Go to AP/1/A/5500/014 (Rod NOTE: Crew may NOT Control Malfunction). address ARP, but enter AP14 directly.

SRO (SA Step 1) IF desired to have Engineering evaluation as to cause for alarm, freeze the Transient Monitor.

SRO (SA Step 2) Refer to Tech Specs.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ 6 _ _ _ _ _ Page 31 of 56 Event

Description:

Sequential Dropped Rods Time II Position ~ Applicant's Actions or Behavior AP/1/Al5500/14, ROD CONTROL MALFUNCTION NOTE: Crew will carry out Immediate Actions of AP14, prior to the SRO addressing the AP.

RO (Step 1) IF more than one rod dropped, NOTE: Only ONE Rod has THEN: dropped.

• T rip reacto r.

• GO TO EP/1/A/SOOO/E-O (Reactor Trip or Safety Injection).

RO (Step 2) Place control rods in manual. NOTE: RO has previously placed Control Rods in MANUAL.

RO (Step 3) Check rod movement - STOPPED.

RO (Step 4) Check all rods - ALIGNED WITH ASSOCIATED BANK.

RO (Step 4 RNO) Perform the following:

• IF T-Ave has gone down, THEN lower NOTE: Tave has decreased, Turbine load as necessary to restore and RO will drop Turbine T-Ave to T-Ref. Load.

• IF two or more rods are misaligned NOTE: This is a Continuous greater than 24 steps, THEN: Action. The SRO will make both board operators aware.

• Trip reactor.

• GO TO EP/1/A/SOOO/E-O (Reactor Trip or Safety Injection).

• IF any rod is dropped AND another rod is NOTE: This is a Continuous misaligned, THEN: Action. The SRO will make both board operators aware,

• Trip reactor.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 6 of 56 Event

Description:

Sequential Dropped Rods Time II Position  ! Applicant's Actions or Behavior

• GO TO EP/1/N5000/E-O (Reactor Trip or Safety Injection).

SRO

• IF one rod dropped, THEN GO TO NOTE: The SRO will address Enclosure 1 (Response To A Dropped Enclosure 1.

Rod).

AP/1/Al5500/14, ROD CONTROL MALFUNCTION ENCLOSURE 1, RESPONSE TO A DROPPED ROD SRO (Step 1) Announce occurrence on paging NOTE: SRO may ask U2 RO system. to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

SRO (Step 2) Dispatch rod control system NOTE: SRO may call qualified IAE to correct cause of dropped rod. WCC/IAE to address.

If so, Booth Instructor acknowledge as WCC/IAE as appropriate.

SRO (Step 3) Check "ROD CONTROL URGENT FAILURE" alarm (1AD-2, A-10) - DARK.

RO (Step 3 RNO) Perform the following:

• Do not move control rods while the "ROD CONTROL URGENT FAILURE" alarm is lit, unless instructed by IAE.

• IF AT ANY TIME IAE desires to reset NOTE: This is a Continuous

'ROD CONTROL URGENT FAILURE" Action. The SRO will make alarm, THEN depress the 'ROD both board operators aware.

CONTROL ALARM RESET" pushbutton.

SRO

• IF AT ANY TIME while in this procedure NOTE: This is a Continuous a runback occurs AND no rods will Action. The SRO will make move, THEN perform the following: both board operators aware.

• Trip Reactor.

• GO TO EP/1/N5000/E-O (Reactor Trip or Safety Injection).

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 6 Page 33 of 56 Event

Description:

Sequential Dropped Rods Time II Position I Applicant's Actions or Behavior RO (Step 4) Use OAC point MP1385 (Reactor Thermal Power, Best Estimate), to determine reactor power in subsequent steps.

SROI (Step 5) Check AFD (Tech Spec 3.2.3) -

RO WITHIN TECH SPEC LIMITS.

SRO (Step 6) Check QPTR (Tech Spec 3.2.4) - NOTE: When SRO checks WITHIN TECH SPEC LIMITS. QPTR, the OAC shows 1.14.

The power reduction must be 3% for everyone % over 1.02, or :::::36%.

RO (Step 6 RNO) Reduce reactor power as required by Tech Specs as follows:

• Do not move rods until IAE determines rod movement is available.

BOP

• Borate as required during power reduction to maintain T-Ave at T-Ref.

RO

• Monitor AFD during load reduction.

SRO

• IF AT ANY TIME AFD reaches Tech NOTE: This is a Continuous Spec limit AND reactor power is greater Action. The SRO will make than 50%, THEN: both board operators aware.

• Trip Reactor.

• GO TO EP/1/A/5000/E-0 (Reactor Trip or Safety Injection).

ROI

• Reduce load PER one of the following NOTE: RO or BOP will start procedures: the load decrease:

BOP

• OP/1/A/61001003 (Controlling Procedure For Unit Operation),

Enclosure 4.2 (Power Reduction)

OR

• AP/1/A/5500104 (Rapid Downpower).

Booth Operator Instructions: Operate Trigger #11 (MALF- IRE006 - 04)

Appendix D operator Action Form ES-D-2 Op Test No.: NOB-1 Scenario # 2 Event # 6 of 56 Event

Description:

Sequential Dropped Rods Time ~ Position I Applicant's Actions or Behavior NOTE: SRO recognizes that conditions have changed and that AP14 must be restarted from the beginning.

RO (Step 1) IF more than one rod dropped, NOTE: Two rods have THEN: dropped.

• Trip reactor.

• GO TO EP/1/A/5000/E-O (Reactor Trip or Safety Injection).

Critical Task: (55 - 4600/113/E13.19) Trip the reactor within 30 seconds of the second dropped rod.

Move to Events #7 & 8.

Appendix 0 operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event #

7&8 Page 35 of 56 Event

Description:

Pzr Steam Space LOCAl A NI Pump fails to Auto Start Time II Position ~ Applicant's Actions or Behavior Upon the reactor trip a small break LOCA will occur in the Pressurizer Steam Space, and Safety Injection will be actuated. Upon the actuation of Safety Injection, the 1A NI Pump will fail to auto start and must be manually started. Upon completion of E-O, the operator will transition to E-1, "Loss of Reactor or Secondary Coolant," and the Reactor Coolant Pumps (NCPs) will be required to be manually tripped upon reaching the established NCP trip criteria. On the transition, an Orange Path will exist on the Containment Critical Safety Function, and the transition will be made to FR-Z.1, Response to High Containment Pressure," prior to E-1. Upon completion of FR-Z.1 the operator will transition to E-1. The scenario will terminate at Step 14 of E-1, after the crew has determined to transition to ES-1.2, Post-LOCA Cooldown and Depressurization or upon a decision to transition to ES-1.3, "Transfer to Cold Leg Recirculation," based on E-1 Foldout Page criteria.

Booth Operator Instructions: NA - Trigger #13 is Conditional on Rx Trip (MALF-NC014A (100>>

Indications Available:

• All Rods on the bottom

• Neutron Flux decreasing

• NC Pressure dropping rapidly

• Pzr Level remains abnormally high for plant conditions

• Many MCB Annunciators NOTE: Crew will carry out Immediate Actions of E-O, prior to the SRO addressing the EP.

EP/1/A15000/E-0, REACTOR TRIP OR SAFETY INJECTION SRO (Step 1) Monitor Foldout page. Examiner NOTE: NC Subcooling is lost immediately on the LOCA, and although neither NI Pump is running, Both NV Pumps are operating.

The five minute Clock to stop the NC Pumps should start here.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ Page 7&8 36 of 56 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Time II Position ~ Applicant's Actions or Behavior RO (Step 2) Check Reactor Trip:

• All rod bottom lights -- LIT

• Reactor trip and bypass breakers --

OPEN

• IIR amps -- GOING DOWN.

RO (Step 3) Check turbine Trip:

• All throttle valves -- CLOSED.

BOP (Step 4) Check 1ETA and 1ETB--

ENERGIZED.

RO I (Step 5) Check if SII is actuated:

BOP

• "SAFETY INJECTION ACTUATED" status light (1SI-18) -- LIT.

• Both LOCA Sequencer Actuated status lights (1SI-14) -- LIT.

SRO (Step 6) Announce "Unit 1 Safety Injection". NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 7) Check ESF Monitor Light Panel on energized train(s):

• Groups 1, 2, 5 -- DARK.

• Group 3 - LIT.

• GAC -- IN SERVICE.

BOP

• Group 4, Rows A through F -- LIT AS NOTE: The 1B NI Pump is REQUIRED. OOS, and the 1A NI Pump does NOT Auto start.

The BOP may recognize this and manually start the 1A NI Pump.

Appendix D operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # Page

-7&8 of 56 N08-1 37 Event

Description:

Pzr Steam Space LOCAl A NI Pump fails to Auto Start Time II Position I Applicant's Actions or Behavior BOP (Step 7.d RNO) Perform the following:

• Ensure both trains Phase A Isolation are initiated.

• Align or start SII and Phase A components with individual windows in Group 4 as required.

• GO TO Step 7.f.

BOP

• Check LOCA Sequencer Actuated status light (1SI-14) on energized train(s) - LIT.

• Check the following windows on Monitor Light Panel Group 4 - LIT:

• C-3 "CONT ISOL PHASE A TRN A VLVS ALIGNED"

• C-6 "CONT ISOL PHASE A TRN B VLVS ALIGNED"

• F-4 "SAFETY INEJCTION TRAIN A COMPONENTS ALIGNED"

• F-5 "SAFETY INEJCTION TRAIN B COMPONENTS ALIGNED".

BOP (Step 8) Check proper CA pump status:

• MD CA pumps - ON

• N/R level in at least 3 SIGs - GREATER THAN 17%.

BOP (Step 9) Check all KC pumps - ON BOP (Step 10) Check both RN pumps - ON.

SRO (Step 11) Notify Unit 2 to start 2A RN pump. Floor Instructor: As U2 RO report "2A RN Pump is running."

Appendix D Operator Action Form ES-D-2 Scenario # 2 Event # Page of Op Test No.:

-7&8 56 N08-1 38 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Time II Position I Applicant's Actions or Behavior RO (Step 12) Check all S/G pressures -

GREATER THAN 775 PSIG.

BOP (Step 13) Check Containment Pressure - NOTE: Containment pressure HAS REMAINED LESS THAN 3 PSIG. is ~5 psig due to the LOCA.

BOP (Step 13 RNO) Perform the following:

• Record approximate time of reactor trip. NOTE: RO will report time of Rx Trip.

• Check Monitor Light Group 4, Row G, lit.

• IF any row G window is dark on energized train(s), THEN perform the following:

• Initiate Phase B and Containment Spray signal.

• Stop all NC pumps while maintaining seal injection flow.

Critical Task: (E-1 C/SS-4600/113/E13.1) Trip NC Pumps within 5 minutes of loss of SCM.

• Ensure all RV pumps are in manual and off.

• Energize H2 Igniters by depressing "ON" and "OVERRIDE".

SRO

• Dispatch operator to stop all Unit 1 NF NOTE: SRO will dispatch AHUs (Control panels located in 750 and NLO.

733 electrical penetration rooms).

Booth Instructor: As NLO, report in 5 minutes that all Unit 1 NF AHUs are stopped.

Appendix D Operator Action Form ES-D-2 Scenario # 2 Event # Page of Op Test No.:

-7&8 56 N08-1 39 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Time I Position I Applicant's Actions or Behavior

• WHEN time allows, THEN check Phase NOTE: The SRO may assign B HVAC equipment PER Enclosure 2 the BOP to perform this action.

(Phase B HVAC Equipment).

If so, BOP Examiner follow actions of Enclosure 2.

The SRO may ask U2 BOP to perform this action.

If so, Floor Instructor:

Acknowledge as U2 BOP.

E-O, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 2, Phase B HVAC Equipment BOP (Step 1) Check VE System in Operation as Examiner NOTE: Follow the Follows: actions associated with Enclosure 2 if BOP is assigned by SRO to perform.

• VE Fans - On.

• Ensure all damper mode select switches in AUTO.

• 1AVS ..D..7 Mode Select.

• 1AVS..D..8 Mode Select.

• 1AVS..D..2 Mode Select.

• 1AVS..D..3 Mode Select.

• Annulus pressure being maintained -

NEGATIVE BOP (Step 2) Check VX System in Operation as Follows:

• Time since Phase B actuation -

GREATER THAN 10 MINUTES.

• Check the following - OPEN.

• 1RAF..D-4 (1 B Cont Air Ret Fan To Lwr Cont Test A).

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 7&8 40 of 56 Event

Description:

Pzr Steam Space LOCAl A NI Pump fails to Auto Start Time " Position " Applicant's Actions or Behavior 4& 1VX-2B (1 B H2 Skimmer Fan Isol Test A).

4& 1RAF-D-2 (1A Cant Air Ret Fan To Lwr Cant Test A).

4& 1VX-1A (1 A H2 Skimmer Fan Isol Test A) 4& Check Containment Air Return Fans -

ON.

4& Check H2 Skimmer Fans - ON.

E-O, REACTOR TRIP OR SAFETY INJECTION ROI (Step 14) Check SII flow: NOTE: If the 1A NI Pump has NOT been previously manually BOP started, it will be started here.

4& Check "NV PMPS TO COLD LEG FLOW" gauge -INDICATING FLOW.

4& Check NC pressures - LESS THAN 1600 PSIG.

4& Check NI pumps -INDICATING FLOW.

4& Check NC pressure - LESS THAN 286 PSIG Critical Task: (E-a J) Establish flow from at least one Intermediate Head ECCS Pump before transition out of E-O.

ROI (Step 14.d RNa) Perform the following:

BOP 4& Ensure ND pump miniflow valve on running pump(s) open:

4& 1ND-68A (1A ND Pump & Hx Mini Flow Isol) 4& 1ND-67B (1B ND Pump & Hx Mini Flow Isol).

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

-7&8 of 56 N08-1 41 Event

Description:

Pzr Steam Space LOCAl A NI Pump fails to Auto Start Time " Position I Applicant's Actions or Behavior

• If valve(s) open on all running ND pumps, THEN GO TO Step 15.

SRO (Step 15) Notify OSM or other SRO to NOTE: SRO may ask OSM to perform EP/1/N5000/G-1 (Generic address.

Enclosures), Enclosure 22 (OSM Actions If so, Floor Instructor Following an S/I) within 10 minutes.

acknowledge as OSM.

RO 1 (Step 16) Check CA flow:

BOP

• Total CA flow - GREATER THAN 450 GPM.

BOP

• BOP Check VI header pressure -

GREATER THAN 60 PSIG.

RO

• WHEN N/R level in any S/G greater than NOTE: Adverse Containment 11% (32% ACC), THEN control CA flow Numbers will be used.

to maintain N/R levels between 11%

(32% ACC) and 50%.

RO (Step 17) Check NC temperatures;

• IF all NC pumps off, THEN check NC T- NOTE: All NC Pumps will be Colds - STABLE OR TRENDING TO OFF.

557°F.

RO (Step 17 RNO) Perform the following based NOTE: The SRO may assign on plant conditions: the RO to perform this action.

If so, RO Examiner follow actions of Enclosure 3.

• IF temperature less than 557°F AND going down, THEN attempt to stop cooldown PER Enclosure 3 (Uncontrolled NC System Cooldown).

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # Page of

-7&8 56 N08-1 42 Event

Description:

Pzr Steam Space LOCAl A NI Pump fails to Auto Start Time II Position ~ Applicant's Actions or Behavior EP/1/A15000/E-O, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 3, UNCONTROLLED NC SYSTEM COOLDOWN RO (Step 1) Check steam dump valves - Examiner NOTE: Follow the CLOSED. actions associated with Enclosure 3 if RO is assigned by SRO to perform.

RO (Step 2) Check all SM PORVs - CLOSED.

RO (Step 3) Check MSR "RESET" light - LIT.

RO (Step 4) check any NC pump - ON.

RO (Step 4 RNO) perform the following:

• IF any NC T-Cold is still going down, THENGO TO Step 6.

• IF cooldown stopped, THEN exit this enclosure.

RO (Step 6) Control feed flow as follows:

• IF S/G N/R level is less than 11% (32%

ACC) in all S/Gs, THEN throttle feed flow to achieve the following:

• Minimize cooldown

• Maintain total feed flow greater than 450 GPM.

• WHEN N/R level is greater than 11%

(32% ACC) in at least one S/G, THEN throttle feed flow further to:

• Minimize cooldown

• Maintain at least one S/G N/R level greater than 11% (32% ACC).

Appendix 0 Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # Page of N08-1

-7&8 ---- 43 56 Event

Description:

Pzr Steam Space LOCAl A Nt Pump fails to Auto Start Position A licant's Actions or Behavior RO (Step 7) Check MSIVs - ANY OPEN.

nd RO (Step 8) Close 1SM-15 (U1 SM to MSR 2 Stg Tube Bundles Isol).

RO (Step 9) Check any NC pump - ON.

RO (Step 9 RNO) Perform the following:

• IF any NC T-Cold is still going down, THEN GO TO Step 11.

RO (Step 11) Notify Control Room SRO that cooldown is continuing.

SRO I IF cooldown continues, THEN close:

RO

• All MSIVs

• All MSIV bypass valves.

EP/1/A15000/E-O, REACTOR TRIP OR SAFETY INJECTION BOP (Step 18) Check Pzr PORV and spray valves:

• All PZR PORVs - CLOSED.

• Normal Pzr spray valves - CLOSED.

BOP (Step 19) Check NC subcooling based on core exit TIC - GREATER THAN O°F.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ Page 7&8 44 of 56 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Position A licant's Actions or Behavior BOP (Step 19 RNO) IF at least one NV OR NI Examiner NOTE: Stopping pump on, THEN stop all NC pumps while the NC Pumps on low NC maintaining seal injection flow. Subcooling is a Critical Task, and is most likely completed.

If NOT, the NC Pumps will be stopped here.

Critical Task: (E-1 C/SS-4600/113/E13.1) Trip NC Pumps within 5 minutes of loss of SCM.

RO (Step 20) check if main steamlines intact:

• All S/G pressures - STABLE OR GOING UP

• All S/Gs - PRESSURIZED.

BOP (Step 21) Check if S/G tubes intact:

• The following secondary EMFs-NORMAL:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-34(L) (S/G Sample (Lo Range))

• 1EMF-24 (S/G A)

• 1EMF-25 (S/G B)

• 1EMF-26 (S/G C)

• 1EMF-27 (S/G D)

RO

• S/G levels - STABLE OR GOING UP IN A CONTROLLED MANNER.

BOP (Step 22) Check if NC System intact:

• Check containment EMFs - NORMAL: NOTE: 1EMF-38L is in TRIP 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 7&8 45 of 56 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Time ~ Position I Applicant's Actions or Behavior BOP (Step 22 RNO) Perform the following:

• IF H2 Igniters are off, THEN perform the NOTE: The H2 Igniters are following: ON.

• IF AT ANY TIME both of the following NOTE: Neither condition conditions exist, THEN start one train of exists.

VX PER ENCLOSURE 4 (VX Manual Start).

• Containment pressure is between 1 PSIG and 3 PSIG.

• Containment pressure has remained less than 3 PSIG.

SRO

• Implant EP/1/A/5000/F-O (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/E-1 (Loss of NOTE: Upon transition to E-1, Reactor Or Secondary Coolant). an ORANGE Path will exist on Containment.

The SRO will transition to FR-Z.1, rather than E-1.

EP/1IAl5000/FR-Z. 1, RESPONSE TO HIGH CONTAINMENT PRESSURE SRO (Step 1) IF loss of emergency coolant recirc NOTE: Loss of Emergency has occurred, THEN this procedure may be Coolant Recirc has NOT completed as time allows. occurred.

SRO (Step 2) Monitor Foldout Page.

BOP (Step 3) Stop all NC pumps. NOTE: All NC Pumps are stopped.

BOP (Step 4) Ensure all RV pumps are in manual and off.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 7&8 46 of 56 Event

Description:

pzr Steam Space LOCAl A Nt Pump fails to Auto Start Tim A licant's Actions or Behavior SRO (Step 5) Dispatch operator to remove white NOTE: SRO will dispatch tags and close the following breakers: NLO.

Floor/Booth Instructor:

Acknowledge as appropriate.

• 1EMXA-R2A (1A ND To A&B Cold Legs Cont Outside Isol Motor (1NI-173A)) (aux bldg, 750, FF-54, FF-55)

• 1EMXB1-6B (1B ND To C&D Cold Legs Booth Instructor: Wait 5 Cont Outside Isol Motor (1 NI-178B)) (aux minutes, Insert LOA:

bldg, 733, GG-55, GG-56)

NI024 =Racked In NI025 =Racked In And then, report as NLO that breakers are closed.

BOP (Step 6) Check containment pressure - NOTE: Containment pressure LESS THAN 15 PSIG. is =5 psig due to the LOCA.

BOP (Step 7) Check any NS pump - ON.

SRO (Step 8) Perform the remainder of this EP as NOTE: SRO may continue time allows. with FR-Z.1 or Transition to E-1.

If Transition is made here, moved forward to Page 49.

BOP (Step 9) Check containment isolation:

• Check OAC - IN SERVICE.

• Check the following windows on Group 4 of ESF Monitor light Panel - LIT.

• C-3 "CONT ISOL PHASE A TRN A VLVS ALIGNED"

• C-6 "CONT ISOL PHASE A TRN B VLVS ALIGNED"

• G-4 "CONT ISOL PHASE B TRN A VLVS ALIGNED"

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 7&8 47 of 56 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start e II Position I Applicant's Actions or Behavior

• G-5 "CONT ISOL PHASE B TRN B VLVS ALIGNED".

BOP (Step 10) Check NS System in operation as follows:

• Check EP/1/A/5000/ECA-1.1 (Loss of NOTE: Loss of Emergency Emergency Coolant Recirc) - IN Coolant Recirc is NOT in EFFECT. effect.

SRO (Step 10a RNO) GO TO Step 10.d.

BOP

• Check NS suction - ALIGNED TO FWST AS FOLLOWS:

• Check 1NS-18A (A NS Pump Suct From Cont Sump) - CLOSED

• Check 1NS-20A (A NS Pump Suct From FWST) - OPEN

• Check 1NS-1B (B NS Pump Suct From Cont Sump) - CLOSED

• Check 1NS-3B (B NS Pump Suct From FWST) - OPEN

• Check containment pressure - NOTE: Containment pressure GREATER THAN 3 PSIG. is ~5 psig due to the LOCA.

• Check NS pump discharge valves -

OPEN:

• 1NS-32A (A NS Pump Disch Cont Outside Isol)

• 1NS-29A (A NS Pump Disch Cont Outside Isol)

• 1NS-12B (B NS Pump Disch Cont Outside Isol)

• 1NS-15B (B NS Pump Disch Cont Outside Isol).

• Check NS pumps - ON.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 7&8 48 of 56 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Position A licant's Actions or Behavior SRO (Step 11) check Phase B HVAC equipment NOTE: The SRO may assign PER Enclosure 3 (Phase B HVAC the BOP to perform this action.

Equipment).

If so, BOP Examiner follow actions of BOP previously performed as Enclosure 2 of E-O.

The SRO may ask U2 BOP to perform this action.

If so, Floor Instructor:

Acknowledge as U2 BOP.

RO (Step 12) Check the following - CLOSED:

• All MSIVs

• All MSIV bypass valves.

RO (Step 13) Check steamlines intact:

• All S/G pressures - STABLE OR GOING UP

• All S/Gs - PRESSURIZED.

BOP (Step 14) Check if one or two trains of ND aux spray should be aligned:

• Any ND Train - OPERATING IN COLD LEG RECIRC MODE.

SRO (Step 14a RNO) Perform the following:

• WHEN EP/1/N5000/ES-1.3 (Transfer To Cold Leg Recirc), is completed, THEN perform Step 14 to determine if one or two trains of ND aux spray should be aligned.

• GO TO Step 15.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event #

7&8 Page 49 of 56 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Time Position J Applicant's Actions or Behavior BOP (Step 15) Check containment H2 NOTE: The H2 Analyzers are concentration: NOT in service.

• Ensure operator dispatched to stop Unit 1 NF AHUs.

• Check H2 analyzers -IN SERVICE.

SRO (Step 15 RNa) Perform the following: NOTE: SRO will dispatch NLO.

Floor/Booth Instructor:

Acknowledge as appropriate.

• Dispatch operator to place H2 analyzers in service PER EP/1/N5000/G-1 (Generic Enclosures), Enclosure 5 (Placing H2 Analyzers In Service).

• WHEN H2 analyzers in service, THEN Booth Instructor: Wait 15 complete Steps 15.c through 15.1. minutes, Insert LOA:

VX009 =In Service/Enabled VX010 = In Service/Enabled And then, report as NLO that H2 Analyzers are in service.

• GO TO Step 16.

SRO (Step 16) RETURN TO procedure and step NOTE: SRO will transition to in effect. E-1.

NOTE: SRO will likely conduct a Focus Brief.

EP/1/Al5000/E-1, LOSS OF REACTOR OR SECONDARY COOLANT SRO (Step 1) Monitor Foldout page.

RO (Step 2) Check NC subcooling based on core NOTE: There should be no exit TICs - GREATER THAN OaF. NC Subcooling due to the LOCA.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 7&8 of 56 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Time II Position ~ Applicant's Actions or Behavior (Step 2 RNO) IF at least one NV OR NI NOTE: The NC Pumps should pump on, THEN stop all NC pumps while be stopped by this time.

maintaining seal injection flow.

RO (Step 3) Check if main steam lines intact:

• All S/G pressures - STABLE OR GOING UP

• All S/Gs - PRESSURIZED.

RO (Step 4) Control intact S/G levels:

• Check N/R level in any intact S/G - NOTE: Adverse Containment GREATER THAN 11% (32% ACC). Numbers will be used.

BOP

• Check VI header pressure - GREATER THAN 60 PSIG.

RO /

• Throttle feed flow to maintain all intact NOTE: Adverse Containment BOP S/G N/R levels between 11% (32% ACC) Numbers will be used.

and 50%.

BOP (Step 5) Check secondary EMFs -

NORMAL:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-34(L) (S/G Sample (Lo Range))

• 1EMF-24 (S/G A)

• 1EMF-25 (S/G B)

• 1EMF-26 (S/G C)

• 1EMF-27 (S/G D).

BOP (Step 6) Check Pzr PORVs and isolation valves:

• Power to all Pzr PORV isolation valves -

AVAILABLE.

• All Pzr PORVs - CLOSED.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 7&8 51 of 56 Event

Description:

Pzr Steam Space LOCAl A NI Pump fails to Auto Start Position A licant's Actions or Behavior

• At least one Pzr PORV isolation valve -

OPEN.

• IF AT ANY TIME any Pzr PORV opens due to high pressure, THEN after pressure goes below 2315 PSIG, ensure PORV closes or is isolated.

RO (Step 7) Check SII termination criteria:

• NC subcooling based on core exit TICs -

GREATER THAN O°F.

SRO (Step 7a RNO) GO TO Step 7.f ROI IF AT ANY TIME while in this procedure SII NOTE: This is a Continuous SRO termination criteria is met, THEN RETURN Action. The SRO will make TO Step 7. both board operators aware.

BOP (Step 8) Check if NS pump should be stopped:

• Any NS pump - ON.

• Containment pressure - LESS THAN 2 PSIG.

SRO (Step 8b RNO) Perform the following:

• IF NS pump suction has been aligned for NOTE: Neither NS Pump has Cold Leg Recirc, THEN GO TO Step 9. been aligned for Cold Leg Recirc.

• IF AT ANY TIME containment pressure is NOTE: This is a Continuous less than 2 PSIG, AND NS pump suction Action. The SRO will make is still aligned to FWST, THEN perform both board operators aware.

Step 8.

• GO TO Step 9.

BOP (Step 9) check if ND pumps should be stopped:

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 7&8 52 of 56 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Position A licant's Actions or Behavior

• NC pressure - GREATER THAN 286 PSIG.

• NC pressure - STABLE OR GOING UP.

SRO (Step 9b RNO) GO TO Step 10.

RO I (Step 10) Check NC and S/G pressures:

BOP

• All S/G pressures - STABLE OR GOING UP.

• NC pressure - STABLE OR GOING DOWN.

BOP (Step 11) Check if DIGs should be stopped:

• Check any DIG - ON. NOTE: Both DIGs are ON, and should be stopped.

• Check 1 ETA and 1 ETB - ENERGIZED BY OFFSITE POWER.

• Reset the following:

• S/I.

• Sequencers.

• IF AT ANY TIME a BIO signal occurs, NOTE: This is a Continuous THEN restart SII equipment previously Action. The SRO will make on. both board operators aware.

SRO

• Dispatch operator to stop any unloaded NOTE: SRO will dispatch D/G(s) and place ins standby readiness NLO.

PER OP/1/A/63501002 (Diesel Floor/Booth Instructor:

Generator):

Acknowledge as appropriate.

• Enclosure 4.3 (1 A DIG Shutdown)

• Enclosure 4.4 (1B DIG Shutdown). Booth Instructor: Wait 5 minutes, Insert LOA:

DG003 =Stop D/G DG004 = Stop DIG And then, report as NLO that Both DIGs are stopped.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # _ _ _ _ _ _ Page 7&8 53 of 56 Event

Description:

Pzr Steam Space LOCAl A NI Pump fails to Auto Start Time II Position ~ Applicant's Actions or Behavior BOP (Step 12) Check containment H2 concentration:

• Ensure Operator dispatched to stop Unit 1 NF AHUs.

• Check H2 analyzers - IN SERVICE. NOTE: The H2 Analyzers are NOT in service.

SRO (Step 12b RNa) perform the following:

• Dispatch operator to place H2 analyzers NOTE: The SRO has most in service PER EP/1/A/5000/G-1 likely previously dispatched (Generic Enclosures), Enclosure 5 NLO.

(Placing H2 Analyzers In Service).

If contacted, Booth Instructor: Report action still in progress.

• WHEN H2 analyzers in service, THEN NOTE: This is a Continuous complete Steps 12.c through 12.e. Action. The SRO will make both board operators aware.

• GO TO Step 13.

BOP (Step 13) Initiate evaluation of plant status:

• Check Cold Leg Recirc capability:

• Any ND pump - AVAILABLE.

• Power to following valves -

AVAILABLE:

• 1NO-19A (A ND Pump Suct From FWST or NC)

• 1NI-185A (RB Sump To Train A ND & NS)

• 1NO-58A (Train A ND To NV &

NI Pumps)

• 1NO-4B (B ND Pump Suct From FWST or NC)

BOP

• 1NI-184B (RB Sump To Train B ND & NS)

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 2 Event # 7&8 Page 54 of 56 Event

Description:

Pzr Steam Space LOCAl A NI Pump fails to Auto Start Time II Position II Applicant's Actions or Behavior

• 1NI-1368 (8 NI Pump Suction Fr40m ND)

• 1NI-332A (NV & NI Pumps Suction X-Over)

• 1NI-3338 (NV & NI Pumps Suction X-Over.

• 1NI-3348 (NV & NI Pumps Suct X-Over Blk)

• 1NI-147A (NI Pumps Miniflow Hdr Isol)

• 1NI-1158 (A Nt Pump Miniflow)

• 1NI-1448 (8 NI Pump Miniflow).

• "8 LATCHED" on following switches

- LIT:

• 1NI-1848 control permissive for recirc mode

• 1NI-185A control permissive for recirc mode.

• Check aux bldg radiation:

• All area monitor EMFs - NORMAL

• EMF-41 (Aux 81dg Ventilation) -

NORMAL.

SRO WHEN the TSC is staffed, THEN request NOTE: Any attempts to reach TSC to evaluate obtaining samples. the TSC fail (The TSC is NOT yet staffed).

Consult station management to start Floor/Booth Instructor (As additional plant equipment to assist in Appropriate): report as recovery as necessary. Station Management that the TSC is about to be manned and they will call when it is up and ready.

BOP (Step 14) Check if NC System cooldown and depressurization is required:

• NC pressure - GREATER THAN 286 P8IG.

Appendix D operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # Page of 56

-7&8 N08-1 55 Event

Description:

pzr Steam Space LOCAl A NI Pump fails to Auto Start Tim A licant's Actions or Behavior SRO

• GO TO EP/1/A/5000/ES-1.2 (Post LOCA NOTE: The SRO will transition Cooldown And Depressurization). to ES-1.2.

At the discretion of the Lead Examiner terminate the exam.

UNIT 1 STATUS:

Power Level: 100% NCS [B] 1314 ppm Pzr [B]: 1312 ppm Xe: Per OAC Power History: At this power since startup Core Burnup: 12.1 EFPDs CONTROLLING PROCEDURE: OP/1/N61 00/03 Controlling Procedure for Unit Operation OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

• The Plant is at 100 % power Steady-State (BOL), and been for the last 12 days following Refueling Outage.

• The Diesel Generator 1B Operability Test is in progress and the Diesel has operated for 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per System Engineer request. It is presently loaded at 3800 KW and is ready to be shutdown in accordance with PT/1/N4350/002B. The operation of the 1B DG was a Slow Start and conducted from the Control Room at the request of Maintenance. An NLO (Wayne) is standing by at the 1B DG to assist in the shutdown.

• OTG is expected to be conducting some testing inside the TDCA Panel for about an hour early in the shift.

The following equipment is Out-Of-Service:

• 1B NI Pump (Expected back in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />).

• 1NV-265B, Boric Acid to NV Pumps, out for Limit Switch replacement (Expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).

• PNV-5230, NCP 1A #1 Seal Differential Pressure indicator, failed last shift (IAE is investigating) .

• MCB Annunciator 1AD-12, C-2, "KR Storage Tank Low Level," has failed (IAE is investigating) .

Work Control SROIOffsite Communicator Jim Plant SRO Joe NLO*s AVAILABLE Aux Bldg. John Aux Bldg. Chris Turb Bldg. Bob Turb Bldg. Mike s'" Rounds. Carol Extra(s) Bill Ed Wayne Tanya

PROGRAM: McGuire Operations Training MODULE: Initial License Operator Training Class 24 TOPIC: NRC Simulator Exam Scenario N08-1-3

REFERENCES:

1. OP/1/A/61 001003, "Controlling Procedure for Unit Operations."

2. OP/1/A6300/001, "Turbine-Generator Startup/Shutdown."

3. OP/1/A/6150/009, "Boron Concentration Control."

4. OP/1/A/61 00/01 OG, "Annunciator Response For Panel 1AD-6."

5. AP/1/A/55001011, "Pressurizer Pressure Anomalies."

6. McGuire Technical Specifications

7. OP/1/A/61 00101 OR, "Annunciator Response For Panel 1RAD-2."

8. AP/1/A/55001018, "High Activity in Reactor Coolant"

9. AP/1/A/5500/AP1, "Steam Leak."

10. AP/1/A/5500/AP2, "Turbine Generator Trip."

11. EP/1/A/5000/E-0, "Reactor Trip or Safety Injection."

12. EP/1/A/5000/E-2, "Faulted Steam Generator Isolation."

13. EP/1/A/5000/ECA-2.1, "Uncontrolled Depressurization of All Steam Generators."

14. RP/O/A/5700/000, "Classification of Emergencies."

Author: David Lazarony, W.estern Technical Services, Inc.

Facility Review:

March s", 2008 Rev. 2 Appendix D Scenario Outline Form ES-D-1 Facility: McGuire Scenario No.: 3 Op Test No.: N08-1 Examiners: Operators: (SRO)

---

11 (OATC)

(BOP)

Initial Conditions: The Plant is at 290/0 power (SOL) in a Chemistry Hold, during plant startup. It is expected to raise power on the upcoming shift.

Turnover: The following equipment is Out-Of-Service: 1B CA Pump (Expected back in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), PSM-5170, D Steam Generator Pressure (ChanneI1), failed last shift (Channel has been defeated and IAE is investigating) and MCB Annunciator 1AD-5, G-3, "CACST Not Full," has been in constant alarm over the last hour (IAE is investigating) .

Event Malf. Event Type* Event No. No. Description 1 NA R-RO Raise Power N-BOP N-SRO 2 NC012B C-BOP PORV Leakage C(TS)-SRO 3 CHOO1 C-BOP Crud Burst/High Activity C(TS)-SRO 4 SMOO1A C-RO A SG PORV failure C-SRO 5 DEHOO1 C-RO Turbine Generator Trip C-SRO XMT 6 M-RO Inadvertent MSI SM025 M-BOP M-SRO 7 SMOO5 NA SM Safety Valves fail A-D 8 NIOO9A/B NA N1-9/1 0 fail to open

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 3 McGuire 2008 NRC Scenario #3 The Plant is at 29% power (BOL) in a Chemistry Hold, during plant startup. It is expected to raise power on the upcoming shift.

The following equipment is Out-Of-Service: 1B CA Pump (Expected back in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), PSM-5170, D Steam Generator Pressure (ChanneI1), failed last shift (Channel has been defeated and IAE is investigating) and MCB Annunciator 1AD-5, G-3, "CACST Not Full," has been in constant alarm over the last hour (IAE is investigating).

Shortly after taking the watch, the operator will raise power in accordance with Step 3.21 of .1, "Power Increase," of OP/1/A/6100/003, "Controlling Procedure for Unit Operations." The RO will control the Turbine Generator in accordance with Enclosure 4.1, "Turbine-Generator Load Change," of OP/1/A6300/001, "Turbine-Generator Startup/Shutdown,"

and the BOP will conduct an NC System Boron dilution in accordance with Enclosure 4.4, "Alternate Dilute," of OP/1/A/6150/009, "Boron Concentration Control."

During the up-power seat leakage will develop on the Pzr PORV, 1NC-34A. The operator will respond in accordance with ARP1 AD-6/F-5, "NC1, 2, or 3 Flo Detected," and implement AP11 ,

"Pressurizer Pressure Anomalies." The operator will recognize the failure and close the associated PORV Block Valve. The operator will address Technical Specifications 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits," 3.4.11, "Power Operated Relief Valves," and 3.4.13, "RCS Operational Leakage."

Following this, a Crud Burst will occur and 1EMF48, "Reactor Coolant Water Radiation Monitor,"

will alarm. The operator will respond in accordance with ARP1 RAD-2/C-3, "1 EMF 48 Reactor Coolant Hi Had," and implement AP18, "High Activity in Reactor Coolant." The operator will raise Letdown flow at the request of Chemistry and address Technical Specification 3.4.16, RCS Specific Activity."

Subsequently, the A Steam Generator PORV will fail such that the valve fails fully open. The operator will respond in accordance with OP/1/A/5500/AP1, "Steam Leak."

After this, the Main Turbine will trip inadvertently. The Operator will respond by implementing AP2, "Turbine Generator Trip." The operator will stabilize reactor power at 12-15% with control rods in manual.

Shortly afterwards, PSM-5190, D Steam Generator Pressure (Channel 4) will fail low completing the logic for an MSI actuation and all four MSIVs will go closed. On the trip the low set Safety Valve on each Steam Generator will lift and fail to re-close. Additionally, upon Safety Injection actuation, NI-9/10, the NV to Cold Leg Isolation Valves, will fail to automatically open and need to be opened manually. The operator will enter E-O, "Reactor Trip or Safety Injection," and transition to E-2, "Faulted Steam Generator Isolation."

Upon entry into E-2, the operator will recognize that all four Steam Generators are depressurizing and transition to ECA-2.1, "Uncontrolled Depressurization of All Steam Generators." The operator will throttle CA flow to each Steam Generator to maintain a minimum of 25 gpm to each Steam Generator.

The scenario will terminate at Step 5 of ECA-2.1, after the crew has throttled CA flow as required.

Scenario Event Description NRC Scenario 3 Critical Tasks:

E-O I Establish flow from at least one high-head ECCS Pump before transition out of E-O.

ECA-2.1 A Control the CA Flowrate to not exceed < 25 gpm per SG in order to minimize the NC Cooldown rate before a severe challenge (Orange Path) develops to the integrity CSF.

Scenario Event Description NRC Scenario 3 SIMULATOR OPERATOR INSTRUCTIONS o Sim. Setup Rod Step On o IC - 113 o RUN o Update Status Board, See Shift Turnover Information Setup OAC Setup ICCM, Turbine Displays, & Trend Recorders.

Check Rod Step Counters agree with rod positions o (LOA) CA009 Rackout breaker for "1B" Auxiliary Feedwater Pump o (XMT) SM0023 PSM-5170, D Steam Generator Pressure (ChanneI1),

failed Set = 0 Swap to Channel #2.

o (ANN) AD05-G03 =ON MCB Annunciator AD-5, G-3, "CACST Not Full," in constant alarm o (MALF) NI009A Failure of automatic opening of NI-9/1 0.

(MALF) NI0098 o (MALF) SM005A-D SM Safety Valves fail Set: A = 100

=

8 50 C =20 0=20 Conditional Trigger 11 (RTB Open) o Freeze.

o Update Fresh Tech.

Spec. Log.

Scenario Event Description NRC Scenario 3 o At direction of examiner (XMT) SM025 Inadvertent MSI Set =0 Conditional Trigger #11 (Rx Trip)

Trigger 9 SM Safety Valves fail (T=0)

Failure of automatic opening of NI-9/1 0 (T=0) o Terminate the scenario upon direction of Lead Examiner Scenario Event Description NRC Scenario 3 n Fill out the NLO*s Available section of Shift Turnover Info.

o Prior to Crew Briefing RUN o Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Provide Enclosure 4.1 of OP/1/A/6100/003 marked up from 3.20.18 - 3.20.23.1 and 3.20.23.4 checked off. 3.20.17 should be blank. 3.20.23.2-3 should be NA.

4. Provide OP/1/A6300/001, "Turbine-Generator Startup/Shutdown," and OP/1/A/6150/009, "Boron Concentration Control," with Enclosure 4.4 marked up through Step 3.5.

5. Provide a Reactivity Plan W/Pwr ascension Guidelines

6. Direct the crew to Review the Control Boards taking note of present conditions, alarms.

n T-O Begin Familiarization Period 0 At direction of Raise Power examiner 0 At direction of (MALF) NC012B PORV Leakage examiner Severity 20 Trigger 1 0 At direction of (MALF) CH001 Crud BursVHigh Activity examiner Trigger 3 At direction of (MALF) SM001A A SG PORV failure examiner Severity 100 Trigger 5 0 At direction of (MALF) DEH001 Turbine Generator Trip examiner Trigger 7 Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ _ _ _ _ Page 8 of _4_4--l 1

Event

Description:

Raise Power Time I Position I Applicant's Actions or Behavior Shortly after taking the watch, the operator will raise power in accordance with Step 3.21 of Enclosure 4.1, "Power Increase," of OP/1/A/61 001003, "Controlling Procedure for Unit Operations." The RO will control the Turbine Generator in accordance with Enclosure 4.1, "Turbine-Generator Load Change," of OP/1I A63001001 A, Turbine-Generator Load Change," and the BOP will conduct an NC System Boron dilution in accordance with .4, "Alternate Dilute," of OP/1/A/61501009, "Boron Concentration Control."

Booth Operator Instructions: NA Indications Available: NA OP/1/Al61 00/003, CONTROLLING PROCEDURE FOR UNIT OPERATIONS ENCLOSURE 4.1, POWER INCREASE SRO (Step 3.21) Increase power to 45% RTP as follows:

RO (Step 3.21.1) Maintain control rods within insertion and withdrawal limits per COLR.

RO (Step 3.21.2) Maintain AFD within target band per OP/1/N61 00/022 (Unit 1 Data Book), Enclosure 4.3, Graph(s) 1.1.

RO (Step 3.21.3) IF initial startup following refueling outage, check Bank D Control Rods greater than or equal to 200 steps withdrawn.

SRO (Step 3.21.4) Notify IAE to stand by for NOTE: SRO may contact periodic adjustments of Power Range NI wce or IAE.

channels If so, Booth Instructor:

acknowledge appropriately.

RO (Step 3.21.5) IF "Power Mismatch o/ >>

(ExcorelThermal Power Mismatch) indicates greater than 4% during power increase, perform the following: .

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ _ _ _ _ _ Page 9 of _4_4_~

Event

Description:

Raise Power Time I Position I Applicant's Actions or Behavior RO (Step 3.21.6) Begin power increase to 45%

RTP.

OP/1/Al6150/009, BORON CONCENTRATION CONTROL ENCLOSURE 4.4, ALTERNATE DILUTE BOP (Step 3.6) Ensure Boric Acid Flow Counter reset to zero.

BOP (Step 3.7) Set Total Make Up Flow Counter to value determined in Step 3.5. (R.M.)

BOP (Step 3.8) WHEN Total Make Up Flow Counter cover closed, check counter at desired value. (R.M.)

BOP (Step 3.9) Select "ALTERNATE DILUTE" on "NC Sys M/U Controller".

BOP (Step 3.10) If desired to makeup only through 1NV-175A (BA Blender to VCT Outlet),

select CLOSED on 1NV-171A (BA Blender to VCT Inlet).

BOP (Step 3.11) IF desired to adjust reactor makeup water flow using the "BA Blend Discharge Cntrl" potentiometer, adjust "BA Blend Discharge Cntrl" potentiometer setpoint to achieve desired flowrate.

BOP (Step 3.12) If desired to manually adjust reactor makeup water flow, perform the following:

• Place "BA Blend Disch Cntrl" in manual.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ _ _ _ _ _ Page 10 of 44

--~I Event

Description:

Raise Power Time I Position I Applicant's Actions or Behavior

• Adjust "BA Blend Disch Cntrl" output to control reactor makeup water flowrate.

OP/1/AJ6300/001A, TURBINE-GENERATOR STARTUP/SHUTDOWN ENCLOSURE 4.1, TURBINE-GENERATOR LOAD CHANGE RO (Step 3.5) Changing Turbine Load

• IF Turbine in "OPERATOR AUTO",

perform the following:

• Ensure desired change within "Calculated Capability Curve".

• IF turbine load will increase or decrease more than 10 MWs, notify Dispatcher of expected load change.

• Depress "LOAD RATE".

• Enter desired load rate in "VARIABLE DISPLAY".

• Depress "ENTER".

• Depress "REFERENCE".

• Enter desired load in "VARIABLE DISPLAY".

• Depress "ENTER".

• Depress "GO" Check load changes at selected rate.

OP/1/AJ6100/003, CONTROLLING PROCEDURE FOR UNIT OPERATIONS ENCLOSURE 4.1, POWER INCREASE RO (Step 3.21.7) Maintain one pen selected to PR channel on "Nuclear Power (0/0) recorder.

(1ENBCR9450)

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ _ _ _ _ _ Page 11 of 44

---4\

Event

Description:

Raise Power Time I Position I Applicant's Actions or Behavior RO (Step 3.21.8) Maintain other pen as desired on "Nuclear Power (%)" recorder.

(1ENBCR9450)

After 15-25 MWe increase, OR at the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 2 _ _ _ _ Page 12 of _4_4----(1 Event

Description:

PORV Leakage Time I Position I Applicant's Actions or Behavior During the up-power seat leakage will develop on the Pzr PORV, 1NC-34A. The operator will respond in accordance with ARP1AD-6/F-5, "NC1, 2, or 3 Flo Detected,"

and implement AP11 , "Pressurizer Pressure Anomalies." The operator will recognize the failure and close the associated PORV Block Valve. The operator will address Technical Specifications 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits," 3.4.11, "Power Operated Relief Valves," and 3.4.13, "RCS Operational Leakage."

Booth Operator Instructions: Operate Trigger #1 (NC012B (20>>

Indications Available:

• 1AD-6/F5, "NC 1, 2, OR 3 Flo Detected."

• 1AD-6/B9, 'Pzr PORV Disch Hi Temp."

• 1AD-6/Bl0, "Tret/Tauct Abnormal."

• Dual indication on PORV 1NC-34A.

• Pzr Pressure decreasing.

OP/1/Al61 00/01 OG, "ANNUNCIATOR RESPONSE FOR PANEL 1AD-6" F-5, NC 1, 2,OR 3 FLO DETECTED BOP (IA) Check pressurizer pressure is less than NOTE: Crew may NOT safety relief setpoint (2485 psig). address ARP, but enter AP11 directly.

BOP (SA Step 1) Monitor outlet temperature of 1NC-1, 1NC-2, and 1NC-3 to determine which safety relief valve is leaking.

SRO (SA Step 2) Notify OSM.

SRO (SA Step 3) Refer to Tech Specs for primary system leakage.

SRO (SA Step 4) IF in Mode 1, 2, or 3, ensure transient monitor freeze triggered.

{PIP M-98-4253}

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 2 _ _ _ _ Page 13 of _4_4__

11 Event

Description:

PORV Leakage Time I Position I Applicant's Actions or Behavior OP/1/Al6100/010G, "ANNUNCIATOR RESPONSE FOR PANEL 1AD..6" B..

9, PZR PORV DISCH TEMP HI SRO (IA Step 1) IF excessive leakage, go to NOTE: Crew may NOT AP111N550010 10 (NC System Leakage address ARP, but enter AP11 Within Capacity of Both NV Pumps). directly.

SRO (IA Step 2) IF Pzr pressure decreasing, go to AP/1/N55001011 (Pressurizer Pressure Anomalies).

BOP (SA Step 1) Monitor PRT temperature, pressure, and level.

SRO (SA Step 2) Refer to Tech Specs for leakage limiting conditions for operation.

AP/1/Al5500/11, PRESSURIZER PRESSURE ANOMALIES NOTE: Crew will carry out Immediate Actions of AP11, prior to the SRO addressing the AP.

BOP (Step 1) Check actual Pzr pressure - HAS GONE DOWN.

BOP (Step 2) Check all Pzr pressure channels -

INDICATING THE SAME.

BOP (Step 3) Check Pzr PORVs - CLOSED.

BOP (Step 3 RNO) Perform the following:

• Close PORVs.

• IF PORV will not close, THEN close PORV isolation valve.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 2 _ _ _ _ _ Page 14 of 44

---41 Event

Description:

PORV Leakage Time I Position  ! Applicant's Actions or Behavior BOP (Step 4) Check Pzr spray valves - CLOSED. NOTE: Crew may stop load increase and place Control Rods in AUTO, while investigating PORV leakage.

BOP (Step 5) Check Pzr PORVs - CLOSED.

BOP (Step 5 RNO) Perform the following:

• IF associated PORV isolation valve will not close AND pressure going down rapidly, THEN:

• Close associated PORV inlet drain valve as follows:

• IF 1NC-34A (PZR PORV) failed, NOTE: BOP will close 1NC-THEN close 1NC-270 (PZR. PORV 270.

Drn Isol For 1NC-34A).

BOP (Step 6) Check PZR spray valves - NOTE: SRO may recoqnize CLOSED. that Step 6 was written to address Spray Valves that have failed. Because this is NOT the case, the SRO may elect to not take the action of Step 6 RNO.

If OSM concurrence is sought, Floor Instructor, as OSM, concur.

SRO (Step 7) GO TO Step 9.

SRO (Step 9) Announce occurrence on page. NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 2 _ _ _ _ Page 15 of _4_4---41 Event

Description:

PORV Leakage Time ~ Position I Applicant's Actions or Behavior BOP (Step 10) Check 1NV-21A (NV Spray To PZR Isol) - CLOSED.

BOP (Step 11) Check the following Pzr heaters -

ON:

• 1A

• 1B

• 1D BOP (Step 12) Check 1C Pzr heaters - ON.

BOP (Step 12 RNa) IF NC pressure below desired pressure, THEN:

• Place "PZR PRESS MASTER" in manual.

• Control pressure.

• WHEN Pzr pressure returns to normal AND automatic Pzr pressure control desired, THEN place "PZR PRESS MASTER" in auto.

BOP (Step 13) check Pzr pressure - GOING UP TO DESIRED PRESSURE.

BOP (Step 14) Check "1NC-27 PRESSURIZER SPRAY EMERGENCY CLOSE" switch -

SELECTED TO "NORMAL".

BOP (Step 15) Check "1NC-29 PRESSURIZER SPRAY EMERGENCY CLOSE" switch -

SELECTED TO "NORMAL".

SRO (Step 16) GO TO Step 24.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 2 _ _ _ _ _ Page 16 of 44

--'"""ll Event

Description:

PORV Leakage Time I Position ~ Applicant's Actions or Behavior BOP (Step 24) Ensure "PZR PRESS REC NOTE: SRO will likely conduct SELECT" is on operable channel. a Focus Brief.

NOTE: SRO may contact Station Management regarding continued load increase.

If so, Booth Instructor: as Station Management direct SRO to hold at present power level temporarily.

TECHNICAL SPECIFICATION 3.4.11, PRESSURIZER POWER OPERATED RELIEF VALVES (PORVs)

SRO 3.4.11 Pressurizer Power Operated Relief Examiner NOTE: Addressing Valves (PORVs) TS takes 8-10 minutes. May want to address after scenario.

SRO LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

SRO APPLICABILITY: MODES 1, 2, and 3.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 2 Page 17 of 44

---II Event

Description:

PORV Leakage Time I Position I Applicant's Actions or Behavior SRO ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME B. One or two B.1 Close 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> PORVs associated inoperable block and not valves.

capable of being AND manually B.2 Remove cycled. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> power from associated block valves.

AND B.3 Restore one 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> PORV to OPERABLE status if two PORVs are inoperable.

TECHNICAL SPECIFICATION 3.4.1, RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS SRO 3.4.1 ReS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified in Table 3.4.1-1.

APPLICABILITY: MODE 1.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 2 Page 18 of 44

--~I Event

Description:

PORV Leakage Time ~ Position I Applicant's Actions or Behavior CONDITION REQUIRED COMPLETION ACTION TIME A. Pressurizer A.1 Restore DNB 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

pressure or parameter(s)

RCS to within limit.

average temperature DNB parameters not within limits.

At the discretion of the Lead Examiner move to Event #3.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 3 _ _ _ _ Page 19 of _4_4---41 Event

Description:

Crud Burst/High Activity Time I Position I Applicant's Actions or Behavior Following this, a Crud Burst will occur and 1EMF48, "Reactor Coolant Water Radiation Monitor," will alarm. The operator will respond in accordance with ARP1 RAD-2/C-3, "1 EMF 48 Reactor Coolant Hi Rad," and implement AP18, "High Activity in Reactor Coolant." The operator will raise Letdown flow at the request of Chemistry and address Technical Specification 3.4.16, RCS Specific Activity."

Booth Operator Instructions: Operate Trigger #3 (CH001)

Indications Available:

• 1RAD-2/C-3, "1EMF 48 Reactor Coolant Hi Rad."

• 1RAD-3/D-3, "1 EMF 18 Reactor Coolant Filter 1A."

• 1RAD-1/E-2, "1EMF 38 Containment Particulate."

OP/1/Al61 00/01OR, "ANNUNCIATOR RESPONSE FOR PANEL 1RAD-2" C-3, 1 EMF 48 REACTOR COOLANT HI RAD SRO (SA Step 1) Go to AP/1/A/5500/018 (High NOTE: SRO will enter Activity in Reactor Coolant). AP/1/A/5500/18.

SRO (SA Step 2) Notify chemistry. NOTE: SRO may contact Chemistry.

If so, Booth Instructor:

acknowledge as Chemistry.

SRO (SA Step 3) Notify RP. NOTE: SRO may contact RP.

If so, Booth Instructor:

acknowledge as RP.

AP/1/Al5500/18, HIGH ACTIVITY IN REACTOR COOLANT BOP (Step 1) Check 1NV-127A (UD Hx Outlet 3-Way Temp Cntrl) - ALIGNED TO DEMIN.

SRO (Step 2) Determine cause of high activity:

Appendix 0 operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _3 _ _ _ _ _ Page 20 of 44 Event

Description:

Crud Burst/High Activity Time ~ Position Applicant's Actions or Behavior

• Request Chemistry to check NOTE: SRO will contact decontamination factor of mixed bed Chemistry.

demineralizer.

If so, Booth Instructor:

acknowledge as Chemistry.

• Notify Chemistry to perform an NC System isotopic analysis to determine if high activity is from a crud burst or failed fuel.

Booth Instructor: as Chemistry (Time Compression) report that you suspect a Crud Burst, but DEI is 1.2 IJc/ml.

BOP (Step 3) IF AT ANY TIME it is determined that high activity is from crud burst, THEN raise letdown flow to 120 GPM.

• Slowly adjust 1NV-459 open. NOTE: This activity is within the tasks identified as "Skill of the Craft" within SOMP 04-02, Section 12, and therefore is NOT governed by a specific procedure.

• Monitor letdown flow Increase.

• Maintain LD pressure 350 psig (may place controller in manual).

• Monitor increase in Chg flow.

• Set-up OAC to monitor Pzr level.

• Adjust 1NV-241 as Chg flow increases.

SRO IF AT ANY TIME it is determined that high NOTE: This is a Continuous activity is from failed fuel, THEN: Action. The SRO will make both board operators aware.

• Ensure mixed bed demineralizer in service.

• Notify Chemistry to consult with Reactor Group and RP to determine if the caution bed demineralizer should be placed in service.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 3 _ _ _ _ _ Page 21 of _4_4_~,

Event

Description:

Crud Burst/High Activity Time ~ Position ~ Applicant's Actions or Behavior

• IF AT ANY TIME Chemistry requests cation bed demineralizer be placed in service, THEN place in service PER OP/1/N6200/001 D (Chemical and Volume Control System Demineralizers),

Enclosure 4.3 (Removing/Returning the Cation Bed Demineralizer from/to Service.

• REFER TO RP/O/N5700/000 (Classification of Emergency).

• Notify Reactor Group to perform OP/O/N6550/017 (Estimate of Failed Fuel Based on lodine-131 Concentration) .

SRO Notify Radwaste to ensure VCT H2 purge NOTE: SRO will contact flow is established. Radwaste.

If so, Booth Instructor:

acknowledge as Radwaste.

SRO REFER TO Tech Spec 3.4.16 (RCS Specific Activity).

TECHNICAL SPECIFICATION 3.4.16, RCS SPECIFIC ACTIVITY SRO 3.4.16 RCS Specific Activity Examiner NOTE: Addressing TS may take several minutes.

May want to address after scenario.

SRO LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

SRO APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) ~

500°F.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 3 Page 22 of 44, Event

Description:

Crud Burst/High Activity Time ~ Position I Applicant's Actions or Behavior CONDITION REQUIRED COMPLETION ACTION TIME A. DOSE A.1 Verify Once per 4 EQUIVALENT Dose hours 1-131 > Equivalent 1.0~Ci/gm. 1-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Dose Equivalent 1-131 to within limit.

At the discretion of the Lead Examiner move to Event #4.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 4 _ _ _ _ Page 23 of _4_4_~,

Event

Description:

A SG PORV failure Time I Position ~ Applicant's Actions or Behavior Subsequently, the A Steam Generator PORV will fail such that the valve fails fully open.

The operator will respond in accordance with OP/1/N5500/AP1, "Steam Leak."

Booth Operator Instructions: Operate Trigger #5 (SM001 A (100>>

Indications Available:

• 1AO-6/C-6, 'Pzr Lo Press Control."

• 1A SG PORV Red Status Light is LIT.

If malfunction is NOT diagnosed within 2 Minutes of insertion, Booth Instructor:

call Control Room as NLO and report that Steam is coming out of exterior Doghouse.

AP/1/Al5500/01, STEAM LEAK SRO (Step 1) Monitor Foldout page.

RO (Step 2) Reduce turbine load to maintain the following:

• Excore NI's - LESS THAN OR EQUAL TO 100%.

• NC Loop OfT's - LESS THAN 60°F OfT

• T-ave - AT T-REF.

SRO (Step 3) Check containment entry - IN PROGRESS.

SRO (Step 3 RNO) GO TO Step 5.

RO (Step 5) Check Pzr pressure prior to event -

GREATER THAN P-11 (1955 PSIG).

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _4 _ _ _ _ _ Page 24 of _4_4__

11 Event

Description:

A SG PORV failure Time I Position ~ Applicant's Actions or Behavior BOP (Step 6) Check Pzr level - STABLE OR GOING UP.

BOP (Step 6 RNO) Perform the following as required to maintain level:

• Maintain charging flow less than 200 GPM at all times in subsequent steps.

• Ensure 1NV-238 (Charging Line Flow Control) opening.

• Open 1NV-241 (Seallnj Flow Control) while maintaining NC pump seal flow greater than 5 GPM.

• Reduce or isolate letdown.

• Start additional NV pump.

• IF Pzr level going down with maximum charging flow, THEN GO TO Step 9.

BOP (Step 7) IF AT ANY TIME while in this procedure Pzr level cannot be maintained stable, THEN RETURN TO Step 6.

SRO (Step 8) GO TO Step 12.

SRO (Step 12) Announce occurrence on paging NOTE: SRO may ask U2 RO system. to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 13) Identify and isolate leak on Unit 1:

• Check SM PORVs - CLOSED. NOTE: The 1A SG PORV is Open.

RO (Step 13 RNO) IF S/G pressure is less than 1092 PSIG, THEN perform the following:

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 4 _ _ _ _ _ Page 25 of 44

---II Event

Description:

A SG PORV failure Time ~ Position I Applicant's Actions or Behavior

• Close affected S/G SM PORV manual loader.

• IF 8M PORV is still open, THEN: Close NOTE: The 1A SG PORV SM PORV isolation valve. Isolation Valve will need to be closed.

At the discretion of the Lead Examiner move to Event #5.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 5 _ _ _ _ _ Page 26 of 44 Event

Description:

Turbine Generator Trip Time I Position I Applicant's Actions or Behavior After this, the Main Turbine will trip inadvertently. The Operator will respond by implementing AP2, "Turbine Generator Trip." The operator will stabilize reactor power at 12-15% with control rods in manual.

Booth Operator Instructions: Operate Trigger #7 (DEH001)

Indications Available:

• 1AD-6/C-6, "Pzr Lo Press Control."

• Many MCB Annunciators go into alarm.

• MWe goes to "0."

• Control Rods drive inward in Automatic.

AP/1/A15500/02, TURBINE GENERATOR TRIP RO (Step 1) Check Turbine Trip:

• All throttle valves - CLOSED.

RO (Step 2) Check P/R meters - LESS THAN NOTE: By the time power level 20%. stabilizes, power level may be

< 200/0. If so, move forward to Step 3.

RO (Step 2 RNO) Perform the following:

• Ensure control rods moving in to reduce T-Ave. . r

• Designate an operator to continuously monitor reactor power.

• WHEN reactor power is less than 200/0, THEN:

• Place control rods in manual.

• Perform Step 3 to stabilize reactor power.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 5 _ _ _ _ _ Page 27 of 44 Event

Description:

Turbine Generator Trip Time ~ Position I Applicant's Actions or Behavior RO (Step 3) Stabilize reactor power as follows:

• Place control rods in manual. NOTE: The RO will place Control Rods in MANUAL.

• Check P/R meters - GREATER THAN 50/0.

• Stabilize reactor power, as indicated on PJR meters, between 12% - 15% with control rods in manual.

• WHEN reactor power is stabilized between 12% - 150/0, THEN maintain IIR startup rate at "0" to ensure a constant power level.

RO (Step 4) IF AT ANY TIME reactor power NOTE: Power level should goes below 5%, THEN: remain> 5%.

• Do not pull control rods.

• Insert control rods as necessary to maintain negative SUR on IIR startup rate meters.

BOP (Step 5) Check "C-9 COND AVAILABLE FOR STEAM DUMP" status light (1SI-18) -

LIT.

ROJ (Step 6) Check any CF pump - IN SERVICE. NOTE: The 1 A CF Pump is in BOP service.

RO (Step 7) Check both generator breakers - NOTE: Both Main Generator OPEN. Breakers are Open.

RO (Step 8) Check "EXCITATION" - OFF.

ROJ (Step 9) IF AT ANY TIME T-Ave is less than NOTE: This is a Continuous BOP 551°F AND going down, THEN perform the Action. The SRO will make following: both board operators aware.

• Trip reactor.

Appendix 0 operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # _ 5 _ _ _ _ Page 28 of 44 Event

Description:

Turbine Generator Trip Time I Position I Applicant's Actions or Behavior

• GO TO EP/1/N5000/E-0 (Reactor Trip or Safety Injection).

RO (Step 10) Check all control rods - ALIGNED WITH ASSOICATED BANK.

RO (Step 11) Check MSR "RESET" light - LIT.

SRO (Step 12) Announce "UNIT 1 TURBINE NOTE: SRO may ask U2 RO TRIP, NON-ESSENTIAL PERSONNEL to make Plant Announcement.

STAY OUT OF UNIT 1 TURBINE BLDG".

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 13) Check S/G CF control bypass NOTE: The S/G CF control valves - IN MANUAL AND FULL OPEN. bypass valves will be closed.

SRO (Step 13 RNa) GO TO Step 16.

RO (Step 16) Check condenser dump valves -

MODULATING OPEN.

BOP (Step 17) Check Pzr pressure control response:

• Ensure Pzr heaters are in auto.

• Ensure Pzr spray control valves are in auto.

• Check Pzr PORVs - CLOSED.

BOP (Step 17 RNO) WHEN Pzr pressure is less than 2315 PSIG, THEN perform the following:

• Ensure Pzr PORVs are closed. NOTE: 1NC-34A NOT closed from previous malfunction.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 5 Page 29 of 44 Event

Description:

Turbine Generator Trip Time ~ Position ~ Applicant's Actions or Behavior

• IF any PORV cannot be closed, THEN close its isolation and inlet drain valve as follows:

• IF 1NC-34A (PZR PORV) failed, NOTE: 1NC-34A PORV THEN close: isolation will be closed from previous malfunction.

• 1NC-33A (PZR PORV Isol).

• 1NC-270 (PZR PORV Drn Isol For 1NC-34A).

BOP * (Step 17d) Check Pzr spray control valves - CLOSED.

• (Step 17d RNO) IF AT ANYTIME Pzr pressure is less than 2100 PSIG, THEN perform the following:

• Ensure spray valves closed.

• IF any spray valve cannot be closed AND uncontrolled depressurization occurs, THEN REFER TO AP/1/N5500/11 (Pressurizer Pressure Anomalies).

BOP (Step 18) Check Pzr level- TRENDING TO PROGRAM.

RO (Step 19) Ensure Bearing Lift pump in "AUTO".

RO (Step 20) WHEN bearing oil pressure goes down to 11-12 PSIG, THEN ensure AC Bearing Oil pump starts.

At the discretion of the Lead Examiner move to Events #6-8.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 5 Page 30 of 44 Event

Description:

Turbine Generator Trip Time A licant's Actions or Behavior

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSII SM Safety Valves fail/ NI-9/10 fail to open Time I Position i Applicant's Actions or Behavior Shortly afterwards, PSM-5190, 0 Steam Generator Pressure (Channel 4) will fail low completing the logic for an MSI actuation and all four MSIVs will go closed. On the trip the low set Safety Valve on each Steam Generator will lift and fail to re-close.

Additionally, upon Safety Injection actuation, NI-9/10, the NV to Cold Leg Isolation Valves, will fail to automatically open and need to be opened manually. The operator will enter E-O, "Reactor Trip or Safety Injection," and transition to E-2, "Faulted Steam Generator Isolation." Upon entry into E-2, the operator will recognize that all four Steam Generators are depressurizing and transition to ECA-2.1 , "Uncontrolled Depressurization of All Steam Generators." The operator will throttle CA flow to each Steam Generator to maintain a minimum of 25 gpm to each Steam Generator. The scenario will terminate at Step 5 of ECA-2.1, after the crew has throttled CA flow as required.

Booth Operator Instructions: Operate Trigger #9 (XMTSM025 (0>>

Trigger #11 is Conditional on Rx Trip (MALF-SM005A (100), SM005B (50), SM005C (20) and SM005D (20>>

Indications Available:

• All MSIVs close

• Steam Flow decreases

• CF Pumps stop NOTE: Crew will carry out Immediate Actions of E-O, prior to the SRO addressing the EP.

E-O, REACTOR TRIP OR SAFETY INJECTION SRO (Step 1) Monitor Foldout page.

RO (Step 2) Check Reactor Trip:

• All rod bottom lights - LIT

• Reactor trip and bypass breakers -

OPEN

• IIR amps - GOING DOWN.

RO (Step 3) Check Turbine Trip:

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSII SM Safety Valves fail! NI-9!1 0 fail to open Time ~ Position ~ Applicant's Actions or Behavior

• All throttle valves - CLOSED BOP (Step 4) Check 1ETA and 1ETB-ENERGIZED.

RO 1 (Step 5) Check if SII is actuated: NOTE: Crew will most likely BOP manually actuate SI based on lowering Pzr Pressure.

• "SAFETY INJECTION ACTUATED" status light (1SI-18) - LIT.

• Both LOCA Sequencer Actuated status lights (1SI-14) - LIT.

SRO (Step 6) Announce "UNIT 1 SAFETY NOTE: SRO may ask U2 RO INJECTION". to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 7) Check ESF Monitor Light Panel on energized train(s):

• Groups 1, 2, 5 - DARK.

• Group 3 - LIT.

• OAC - IN SERVICE.

• Group 4, Rows A through F - LIT AS NOTE: 1NV-9/10 lights will REQUIRED. NOT be LIT due to failure of auto Open.

BOP (Step 7.d RNO) Perform the following:

• Ensure both trains Phase A Isolation are initiated.

• Align or start SII and Phase A components with individual windows in Group 4 as required.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSII SM Safety Valves fail! NI-9!10 fail to open Time I Position I Applicant's Actions or Behavior Critical Task: (E-a I) Establish flow from at least one high-head ECCS Pump before transition out of E-O.

• GO TO Step 7.1.

BOP

• Check LOCA Sequencer Actuated status light (1SI-14) on energized train(s) - LIT.

• Check the following windows on Monitor Light Panel Group 4 - LIT:

• C-3 "CaNT ISOL PHASE A TRN A VLVS ALIGNED"

• C-6 "CaNT ISOL PHASE A TRN B VLVS ALIGNED"

• F-4 "SAFETY INEJCTION TRAIN A COMPONENTS ALIGNED"

• F-5 "SAFETY INEJCTION TRAIN B COMPONENTS ALIGNED" RO / (Step 8) Check proper CA pump status:

BOP

• MD CA pumps - ON. NOTE: The 1B MD CA Pump is OOS. The 1A MD Pump is running.

RO / (Step 8a RNO) Start pumps.

BOP RO / (Step 8b) Check proper CA pump status:

BOP

• N/R level in at least 3 S/Gs - GREATER THAN 17%.

RO / (Step 8b RNO) Ensure TD CA pump on. NOTE: The SRO will verify BOP that the TD CA is running.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSII SM Safety Valves faill NI-9/1 0 fail to open Time I Position I Applicant's Actions or Behavior BOP (Step 9) Check all KC pumps - ON.

BOP (Step 10) Check both RN pumps - ON.

SRO (Step 11) Notify Unit 2 to start 2A RN pump. Floor Instructor: As U2 RO report "2A RN Pump is running."

RO (Step 12) Check all SIG pressures - NOTE: All SG Pressures are GREATER THAN 775 PSIG. decreasing uncontrollably at varying rates.

RO (Step 12 RNa) Perform the following:

• Check the following closed:

• All MSIVs

• All MSIV bypass valves

• All SM PORVs. NOTE: 1A SG PORV has failed open due to a previous malfunction. It should be isolated.

• IF any valve open, THEN:

• Initiate Main Steam Isolation signal. NOTE: MSI will be actuated manually, however it was previously inadvertently actuated.

• IF any valve still open, THEN close valve.

BOP (Step 13) Check Containment Pressure - NOTE: Containment Pressure HAS REMAINED LESS THAN 3 PSIG. is normal.

BOP (Step 14) Check SII flow:

• Check "NV PMPS TO COLD LEG FLOW" gauge -INDICATING FLOW.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSI! SM Safety Valves fail! NI-9!10 fail to open Time I Position I Applicant's Actions or Behavior

• Check NC pressure - LESS THAN 1600 PSIG.

• Check NI pumps -INDICATING FLOW.

• Check NC pressure - LESS THAN 286 PSIG.

BOP (Step 14d RNO) Perform the following:

• Ensure NO pump miniflow valve on running pump(s) open:

• 1ND-68A (1A NO Pump & HX Mini Flow Isol)

• 1ND-67B (1B NO Pump & Hx Mini Flow Isol).

• IF valve(s) open on all running NO pumps, THEN GO TO Step 15.

SRO (Step 15) Notify OSM or other SRO to NOTE: SRO may ask OSM to perform EP/1/A/5000/G-1 (Generic address.

enclosures), Enclosure 22 (OSM Actions If so, Floor Instructor Following an S/I) within 10 minutes.

acknowledge as OSM.

RO I (Step 16) Check ~CA flow:

BOP

• Total CA flow - GREATER THAN 450 GPM.

• Check VI header pressure - GREATER THAN 60 PSIG.

• WHEN N/R level in any S/G greater than 11% (320/0 ACC), THEN control CA flow to maintain N/R levels between 110/0 (320/0 ACC) and 500~.

RO I (Step 17) Check NC temperatures:

BOP

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSII SM Safety Valves fail! NI-9!10 fail to open Time I Position I Applicant's Actions or Behavior

• IF any NC pump on, THEN check NC T-avg - STABLE OR TRENDING TO 557°F.

RO / (Step 17 RNO) Perform the following based BOP on plant conditions:

• IF temperature less than 557°F and NOTE: The SRO may assign going down, THEN attempt to stop the RO to perform this action.

cooldown PER Enclosure 3 If so, RO Examiner follow (Uncontrolled NC System Cooldown).

actions of Enclosure 3.

E-O, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 3, UNCONTROLLED NC SYSTEM COOLDOWN RO (Step 1) Check steam dump valves - Examiner NOTE: Follow the CLOSED. actions associated with Enclosure 3 if RO is assigned by SRO to perform.

RO (Step 2) Check all SM PORVs - CLOSED. NOTE: 1A SG PORV is OPEN, but isolated.

RO (Step 2 RNO) Perform the following:

• Close affected SM PORV manual loader.

• IF SM PORV can not be closed, THEN:

• Close SM PORV isolation valve.

RO (Step 3) Check MSR "RESET" light - LIT.

RO (Step 4) Check any NC pump - ON.

RO (Step 5) Check NC T-avg - GOING DOWN.

RO (Step 6) Control feed flow as follows:

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSII SM Safety Valves fail! NI-9!10 fail to open Time I Position I Applicant's Actions or Behavior

• IF S/G N/R level is less than 11% (320/0 ACC) in all S/Gs, THEN throttle feed flow to achieve the following:

• Minimize cooldown.

• Maintain total feed flow greater than 450 GPM.

• WHEN N/R level is greater than 110/0 (320/0 ACC) in at least one S/G, THEN throttle feed flow further to:

• Minimize cooldown

• Maintain at least one S/G N/R level greater than 11% (320/0 ACC).

RO (Step 7) Check MSIVs - ANY OPEN.

RO (Step 7 RNO) Perform the following:

• Close MSIV bypass valves.

• Exit this enclosure.

E-O, REACTOR TRIP OR SAFETY INJECTION BOP (Step 18) Check Pzr PORV and spray valves:

• All Pzr PORVs - CLOSED. NOTE: 1NC-34A NOT closed from previous malfunction.

BOP (Step 18 RNO) IF Pzr pressure less than 2315 PSIG, THEN perform the following:

• Close Pzr PORV(s).

• IF any Pzr PORV can not be closed, THEN:

• IF 1NC-34A (PZR PORV) failed, NOTE: 1NC-34A PORV THEN close 1NC-270 (PZR PORV isolation will be closed from Drn Isol For 1NC-34A). previous malfunction.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSI/ SM Safety Valves faill NI-9/10 fail to open Time I Position I Applicant's Actions or Behavior BOP (Step 18b) Normal Pzr spray valves - NOTE: Pzr Spray Valves will CLOSED. be Closed.

RO (Step 19) Check NC subcooling based on NOTE: NC System core exit TICs - GREATER THAN O°F. Subcooling will be ~1 OO°F.

RO (Step 20) Check if main steamlines intact: Booth Instructor: as Security report that you see large amounts of Steam Flow from the top of both Doghouses.

SRO (Step 20 RNO) IF any S/G is faulted, THEN:

• IF fault is outside containment, THEN:

• Implement EP/1/A/5000/F-O (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/E-2 (Faulted NOTE: The SRO will transition Steam Generator Isolation). to E-2.

E-2, FAULTED STEAM GENERATOR ISOLATION SRO (Step 1) Monitor Foldout page.

SRO (Step 2) Maintain at least one S/G available for NC System cooldown in subsequent steps.

SRO Maintain any faulted S/G or secondary break isolated during subsequent recovery actions unless needed for NC System cooldown.

RO (Step 4) Check the following - CLOSED:

• All MSIVs

• All MSIV bypass valves.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSI/ SM Safety Valves fail/ NI-9/10 fail to open Time I Position I Applicant's Actions or Behavior RO (Step 5) Check at least one S/G pressure - NOTE: All 5G Pressures will STABLE OR GOING UP. be decreasing.

SRO (Step 5 RNO) IF all S/Gs faulted, THEN GO TO EP/1/A/5000/ECA-2.1 (Uncontrolled Depressurization of All Steam Generators).

ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS SRO (Step 1) Monitor Foldout page.

SRO (Step 2) IF TD CA pump is the only source of NOTE: 1A MD CA Pump is feedwater, THEN maintain steam flow to it running. The SRO will keep from at least one S/G. TD CA Pump running as long as possible.

RO (Step 3) check secondary pressure boundary:

• For1AS/G:

• Check the following - CLOSED:

• MSIV

• MSIV bypass valve.

• Check SM PORV - CLOSED.

RO (Step 3a2 RNO) Perform the following:

• Close SM PORV.

• IF PORV can not be closed; THEN close NOTE: 1A SG PORV has SM PORV isolation valve. failed open due to a previous malfunction. It should be isolated.

RO * (Step 3a3) Check "S/G A FDW ISOLATED" status light (1 SI-4) - LIT.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSI/ SM Safety Valves faiV NI-9/1 0 fail to open Time I Position I Applicant's Actions or Behavior

• MSIV

• MSIV bypass valve.

• Check SM PORV - CLOSED.

• Check "S/G C FDW ISOLATED" status light (1SI-4) - LIT.

• Check 88 Valves - CLOSED:

• 1BB-3B (1C S/G Blowdown Cont Outside 1501 Control)

• 1BB-7A (C S/G BB Cont Inside 1501).

• Close 1SM-95 (C SM Line Drain 1501).

• Dispatch operator to unlock and NOTE: SRO will dispatch close: NLO.

Floor/Booth Instructor:

Acknowledge as appropriate.

• 1SA-1 (SM 1C to TD CA Pump Manual 1501) (Unit 1 interior doghouse 767+10, FF-53, above ladder) 1SA-77 (SM 1C to TO CA Loop Booth Instructor: Wait 2 Seal 1501) (Unit 1 interior minutes, Insert LOA:

doghouse, 767+1 0, FF-53).

SA002 =0 And then, report as NLO that Valves are closed.

• For 10 S/G:

• Check the following - CLOSED:

• MSIV

• MSIV bypass valve.

RO

• Check SM PORV - CLOSED.

• Check "S/G 0 FDW ISOLATED" status light (1SI-4) - LIT.

• Check 8B valves - CLOSED:

• 1BB-4B (1 0 S/G Blowdown Cont Outside 1501 Control)

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, & 8 Event

Description:

Inadvertent MSII SM Safety Valves faill NI-9/10 fail to open Time I Position I Applicant's Actions or Behavior

• 1BB-8A (D S/G BB Cont Inside Isol).

• Close 1SM-101 (0 SM Line Drain Isol).

SRO (Step 4) Monitor shutdown margin during cooldown as follows:

WHEN the TSC is staffed, THEN request NOTE: Any attempts to reach TSC to evaluate obtaining samples. the TSC fail (The TSC is NOT yet staffed).

• WHEN each NC boron sample obtained, NOTE: This is a Continuous THEN: Action. The SRO will make both board operators aware.

• Perform shutdown margin calculation for Cold Shutdown Per OP/OIN61001006 (Reactivity Balance Calculation).

• Check shutdown margin -

ADEQUATE.

RO I (Step 5) Control feed flow as follows:

BOP

• Check all S/G N/R levels - GREATER THAN 11% (32% ACC).

RO I (Step 5a RNO) Maintain a minimum feed BOP flow of 25 GPM to any S/G with a N/R level less than 11% (320/0 ACC).

RO I * (Step 5b) Check cooldown rate in NC T-BOP Colds - LESS THAN 100°F IN AN HOUR.

RO I (Step 5b RNO) Perform the following:

BOP

• Reduce feed flow to 25 GPM to each S/G.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 3 Event # 6,7, &8 Event

Description:

Inadvertent MSII SM Safety Valves fail/ NI-9/10 fail to open Time I Position I Applicant's Actions or Behavior Critical Task: (ECA-2.1 A) Control the CA Flowrate to not exceed < 25 gpm per SG in order to minimize the NC Cooldown rate before a severe challenge (Orange Path) develops to the integrity CSF.

At the discretion of the Lead Examiner terminate the exam.

UNIT 1 STATUS:

Power Level: 290/0 NCS [B] 1816 ppm Pzr [B]: 1821 ppm Xe: Per OAC Power History: At this power 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for Chemistry Core Burnup: 12 EFPDs hold.

CONTROLLING PROCEDURE: OP/1/A/61001003 Controlling Procedure for Unit Operation (See Reactivity Plan with Power Ascension Guidelines)

OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

The Plant is at 290/0 power (BOL) in a Chemistry Hold, during plant startup. It is expected to raise power on the upcoming shift.

The fuel maneuvering limits are as follows:

• 30°A,/hour s 50%

• 200/0/hour ~ 90%

• 3% / h o u r > 90%

Use of Alternate Dilute during power ascension in accordance with Enclosure 4.4, "Alternate Dilute," of OP/1/A/61501009, "Boron Concentration Control," has been approved.

A Train in service.

The following equipment is Out-Of-Service:

• 1B CA Pump (Expected back in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).

• PSM-5170, D Steam Generator Pressure (ChanneI1), failed last shift (Channel has been defeated and IAE is investigating).

• MCB Annunciator 1AD-5, G-3, "CACST Not Full," has been in constant alarm over the last hour (IAE is investigating).

Work Control SROIOffsite Communicator Jim Plant SRO Joe NLO*s AVAILABLE Aux Bldg. John Aux Bldg. Chris Turb Bldg. Bob Turb Bldg. Mike s" Rounds. Carol Extra(s) Bill Ed Wayne Tanya

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PROGRAM: McGuire Operations Training MODULE: Initial License Operator Training Class 24 TOPIC: NRC Simulator Exam Scenario N08-1-4

REFERENCES:

1. PT/0/A/4150/041, "RCCA Bank Repositioning."

2. PT/1/A/4600/001, "RCCA Withdrawal Test."

3. OP/1/A/61 00/01 OC, "Annunciator Response For PaneI1AD-2."

4. McGuire Technical Specifications.

5. OP/1/A/61 00/01 OG, "Annunciator Response For PaneI1AD-6."

6. AP/1/A/5500/11, "Pressurizer Pressure Anomalies."

7. OP/1/A/61 00/01 OH, "Annunciator Response For PaneI1AD-7."

8. AP/1/A/5500/012, "Loss of Letdown, Charging or Seal Injection."

9. AP/1/A/5500/005, "Generator Voltage and Electrical Grid Disturbances."

10. AP/1/A/5500/04, "Rapid Downpower."

11. EP/1/A/5000/E-0, "Reactor Trip or Safety Injection."

12. EP/1/A/5000/FR-F'.1, "Response to Imminent Pressurized thermal Shock Condition."

13. EP/1/A/5000/FR-Z.1, "Response to High Containment Pressure."

14. EP/1/A/5000/E-1, "Loss of Reactor or Secondary Coolant."

15. EP/1/A/5000/ES-1.3, "Transfer to Cold Leg Recirc."

16. EP/1/A/5000/F-0, "Critical Safety Function Status Trees."

17. RP/0/A/5700/000, "Classification of Emergencies."

Author: David Lazarony, Western Technical Services, Inc.

Facility Review:

th March 6 , 2008 Rev. 2 Appendix 0 Scenario Outline Form ES-D-1 Facility: McGuire Scenario No.: 4 Op Test No.: N08-1 Examiners: Operators: (SRO)

---

11 (OATC)

(BOP)

Initial Conditions: The Plant is at 1000/0 power Steady-State (EOl), and been for the last 485 days.

An RCCA Movement Test is in progress in accordance with PT/0/A/4150/041, "RCCA Bank Repositioning," and it is expected to be continued starting with Control Bank D on the upcoming shift.

Turnover: The following equipment is Out-Of-Service: 1A NV Pump (Expected back in 24-36 hours), 1FW-5020, FWST level, failed last shift (IAE is investigating) and MCB Annunciator AD-12, E-5, "FWST Lo-Lo Temp," has alarmed spuriously several times over the last hour (IAE is investigating).

Event Malt. Event Type* Event No. No. Description 1 EDA349 I-RO RCCA Withdrawal TestlDRPI Failure I(TS)-SRO 2 IlEOO3B C-BOP Spray Valve fails open C(TS)-SRO 3 NV029B C-BOP NV Pump B trips/loss of Charging C(TS)-SRO 4 PlP-014 C-RO Electrical Grid Disturbances C-SRO 5 NA R-BOP Rapid Downpower N-RO N-SRO (ANN) 6 NA Seismic Event AD13E07 7 NC008B M-RO large Break lOCA M-BOP M-SRO 8 ND001A NA 1A/1 B ND Pumps fail to auto start ND001B

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 4 McGuire 2008 NRC Scenario #4 The Plant is at 100 % power Steady-State (EOL), and been for the last 485 days. An RCCA Movement Test is in progress in accordance with PT/0/A/4150/041, "RCCA Bank Repositioning," and it is expected to be continued starting with Control Bank D on the upcoming shift.

The following equipment is Out-Of-Service: 1A NV Pump (Expected back in 24-36 hours),

1FW-5020, FWST Level, failed last shift (lAE is investigating) and MCB Annunciator AD-12, E-5, "FWST Lo-Lo Temp," has alarmed spuriously several times over the last hour (IAE is investigating).

Shortly after taking the watch, the operator will perform the RCCA Movement Test on Control Bank D in accordance with PT/0/A/4150/041, "RCCA Bank Repositioning." After Control Bank D has been inserted 10 steps into the core, the DRPI for Control Rod D-4 will fail when the operator attempts to withdrawal the Control Bank D rods back to their original position. The operator will respond in accordance with 1AD-2/D-10, "RPI Urgent Failure," and address Technical Specification 3.1.7, "Rod Position Indication."

Following this, the controller for Pressurizer Spray Valve 1NC-29 will fail causing the Spray Valve to open, causing Pressurizer pressure to drop. The operator will respond in accordance with ARP1AD-6/C-6, "PZR Lo Press Control," and implement AP/1/A/5500/11, "Pressurizer Pressure Anomalies." The operator will address Technical Specification 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits."

After this, the 1B NV Pump will trip causing a Charging Line abnormal flow alarm. The operator will respond in accordance with 1AD-7/G-2, "Charging Line Abnormal Flow," and implement AP/1/A/5500/12, "Loss of Letdown, Charging or Seal Injection." The operator will start the NV PD Pump to maintain Seal Injection flow. With two NV Pumps OOS the operator will address Technical Specification 3.5.2, "ECCS-Operating," and enter Technical Specification 3.0.3.

A short time later, SOC notifies McGuire Nuclear Station that sporadic grid voltage disturbances have been experienced in the region and that these may affect MNS operation. Over the next several minutes, grid voltage cycles between 216-231 KV. The operator will respond in accordance with AP/1/A/5500/05, "Generator Voltage and Electrical Grid Disturbances," and make adjustments of Main Generator voltage.

Due to the degraded Charging (NV) System and the grid voltage fluctuations station management will direct a shutdown using AP/1/A/5500/04, "Rapid Downpower."

During the shutdown, the O.B.E. Exceeded alarm comes in, indicating that an earthquake has occurred. Within seconds a Large Break LOCA will occur on Loop B, and a Reactor Trip/Safety Injection will occur. The operator will enter E-O, "Reactor Trip or Safety Injection." On the Safety Injection, the 1A and 1B ND pumps fail to start automatically and will require manual action to start the pumps.

Upon completion of E-O, the operator will transition to E-1, "Loss of Reactor or Secondary Coolant." However, upon transition an Orange Path will exist on both the Integrity and Containment Critical Safety Functions. The operator will first address FR-P.i, "Response to Imminent Pressurized thermal Shock Condition," and then transition to FR-Z.1, "Response to High Containment Pressure." If these procedures are completed the operator will transition to E-1, "Loss of Reactor or Secondary Coolant" however, it is more likely that Cold Leg Scenario Event Description NRC Scenario 4 Recirculation transition criteria will be met during the performance of the two Functional Recovery Procedures. If so, the operator will transition to ES-1.3, "Transfer to Cold Leg Recirc,"

on low FWST level.

The operator will place Cold Leg Recirculation in service in accordance with ES-1.3. The scenario will terminate at Step 8 of ES-1.3 when the operator is directed to check if NS should be aligned for Recirc.

Critical Tasks:

SS (4600/113/E13.19)

Close the Spray Valve within 1 minute to avoid a reactor trip.

E-O H Manually start at least one NO Pump before transition out of E-O.

SS (4600/113/E13.81.b)

Align ECCS such that FW-27 A is closed by 195 seconds after FWST Lo Level alarm, and NO-58A1NI-136 B are opened by 355 seconds after FWST Lo Level alarm.

Scenario Event Description NRC Scenario 4 SIMULATOR OPERATOR INSTRUCTIONS o Sim. Setup Rod Step On n IC - 112 o RUN o Update Status Board, See Shift Turnover Information Setup OAC Setup ICCM, Turbine Displays, & Trend Recorders.

Check Rod Step Counters agree with rod positions o (LOA) NV046 1A NV Pump OOS Set = Racked Out o (XMT) FW006 1FW-5020, FWST Level Failed Low Set =0 o (MALF) ND001 A 1N1 B NO Pumps fail to auto start (MALF) ND001 B o Freeze.

o Update Fresh Tech.

Spec. Log.

o Fill out the NLO*s Available section of Shift Turnover Info.

o Prior to Crew Briefing RUN o Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Provide SRO with marked up copy of PT/0/A/4150/041 (marked up through section 12.1.7.5 with all repositioned Banks left at 226 Steps). Also provide Enclosure 13.1 of PT/1/N4600/001 marked up through each Shutdown Banko

4. Direct the crew to Review the Control Boards taking note of present conditions, alarms.

Scenario Event Description NRC Scenario 4 0 T-O Begin Familiarization Period 0 At direction of (MALF) EDA349 RCCA Withdrawal Test/DRPI Failure examiner Set = INSERT Trigger 1 0 At direction of (MALF) ILE003B Spray Valve fails open examiner Severity 100 Ramp 10 Trigger 3 0 At direction of (MALF) NV029B NV Pump B trips/Loss of Charging examiner Set = INSERT Trigger 5 0 At direction of PLP-014 Electrical Grid Disturbances examiner Set = 216 Ramp = 120 seconds Trigger 7 After Adjustment:

Set = 231 Ramp = 120 seconds At direction of NA Rapid Downpower examiner 0 At direction of (ANN) AD13E07 Seismic Event examiner Set = ON Trigger 9 0 At direction of (MALF) NC008B Large Break LOCA examiner Set = INSERT Trigger 9 (45 Seconds T=O; 1N1B ND Pumps fail to auto start Delayed) o Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ _ _ _ _ Page 7 of _5_2---11 Event

Description:

RCCA Withdrawal TestlDRPI Failure Time II Position ~ Applicant's Actions or Behavior Shortly after taking the watch, the operator will perform the RCCA Movement Test on Control Bank D in accordance with PT/0/A/4150/041, "RCCA Bank Repositioning." After Control Bank D has been inserted 10 steps into the core, the DRPI for Control Rod D-4 will fail when the operator attempts to withdrawal the Control Bank D rods back to their original position. The operator will respond in accordance with 1AD-2/D-1 0, "RPI Urgent Failure," and address Technical Specification 3.1.7, "Rod Position Indication."

Booth Operator Instructions: NA Indications Available: NA PT/0/Al4150/041 , RCCA BANK REPOSITIONING RO (Step 12.1.7.6) Control Bank D (CBD):

• Select "CBD" with "CRD Bank Select".

• Check "GRP SELECT" light B on the NOTE: RO will contact IAE to Power Cabinets 1BD and is illuminated determine.

2BD If so, Booth Instructor report Both lights are LIT.

• Insert CBD 10 steps.

Booth Operator Instructions: At the START of Rod Withdrawal Operate Trigger #1 (EOA349).

Indications Available:

• 1AD-2/D-1 0, "RPI Urgent Failure."

• 1AD-2/D-9, "RPI at Bottom Rod Drop."

• 1AD-2/E-1 0, "RPI Non-Urgent Failure."

• Rod Bottom Light.

• No accompanying NCS Temperature Change. (However Rods have been inserted 10 steps)

OP/1/A161 00/01 OC, ANNUNCIATOR RESPONSE FOR PANEL 1AO..2 010, RPI URGENT FAILURE

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ _ _ _ _ _ Page 8 of _5_2_-l Event

Description:

RCCA Withdrawal Test/CRPI Failure Time ~ Position ~ Applicant's Actions or Behavior RO (IA Step 1) Check to see which rod(s) is NOTE: Rod D-4 is affected.

affected.

SRO (IA Step 2) IF Unit is in Mode 2 (pulling rods NOTE: Unit is in Mode 1, SRO toward criticality), 3, 4, or 5, move rods to recognizes NOT applicable.

ensure OAC DRPI application is updating.

SRO (IA Step 3) IF actual rod misalignment exists NOTE: Actual Rod or rod control system malfunctions, go to Misalignment does NOT exist.

AP/1/A/55001014 (Rod Control Malfunction).

Examiner NOTE: If the crew misdiagnoses and goes to AP14, allow crew time to determine that they do NOT have a Dropped Rod.

If crew goes to AP14, when RE asked to conduct Flux Map, Booth Instructor: report as RE, that a Rod has NOT dropped.

SRO (lA Step 4) IF in Mode 1-2:

• IF failure on only one Data train (either Data A or Data B) AND does NOT clear:

• Using the keypad control, page to the

"(A or B) DATA ONLY" page (DATA ONLY that is NOT in alarm)

• Compare DATA ONLY data to Rod Demand Step Counter for Tech Spec rod alignment.

• Refer to Tech Specs. NOTE: SRO will refer to TS 3.1.7.

• Contact System Engineering. NOTE: SRO may call WCC/SE to address.

If so, Booth Instructor acknowledge as WCC/SE as appropriate.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ _ _ _ _ _ Page 9 of _5_2_-41 Event

Description:

RCCA Withdrawal TestlDRPI Failure Time I Position I Applicant's Actions or Behavior SRO (IA Step 5) IF both channels of DRPI and OAC Rods indication lost, refer to ITS 3.1.7.

SRO (SA Step 1) Have Engineering determine and NOTE: SRO may call correct problem. WCC/SE to address.

If so, Booth Instructor acknowledge as WCC/SE as appropriate.

SRO (SA Step 2) Check proper VL and RV alignment per OP/1/A/64501001 (Containment Ventilation System) to maintain desired lower containment temperature.

SRO (SA Step 3) Have Reactor Group run NOTE: SRO may call OP/O/A/6150/012 (Non-Indicating RCCA WCC/RG to address.

Position Determination) as necessary per If so, Booth Instructor ITS 3.1.7.

acknowledge as WCC/RG as appropriate.

Booth Instructor: Delete Malf-EDA349 As IAE report that DRPI problem has been fixed, and that they should verify this.

PT/OIAJ4150/041 , RCCA BANK REPOSITIONING RO * (Step 12.1.7.6) Withdraw 10 steps. NOTE: The SRO have the RO restore rods to desired position (226).

• Ensure both group demand counters are on the same step.

TECHNICAL SPECIFICATION 3.1.7, ROD POSITION INDICATION

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # Page 10 of 52

---II Event

Description:

RCCA Withdrawal TestlDRPI Failure Ti I!====

A licant's Actions or Behavior SRO 3.1.7 Rod Position Indication SRO LCO 3.1.7 The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System shall be OPERABLE.

SRO APPLCIABILITY: MODES 1 and 2.

SRO ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One DRPI A.1 Verify the Once per 8 per group position of hours inoperable the rods for one or with in-more operable groups. position indicators by using movable incore detectors.

OR 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> A.2 Reduce THERMAL POWER to

50%

RTP.

At the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _2 _ _ _ _ Page 11 of _5_2~,

Event

Description:

Spray Valve fails open Time " Position " Applicant's Actions or Behavior Following this, the controller for Pressurizer Spray Valve 1NC-29 will fail causing the Spray Valve to open, causing Pressurizer pressure to drop. The operator will respond in accordance with ARP1AD-6/C-6, "PZR Lo Press Control," and implement AP/1/A/5500/11, "Pressurizer Pressure Anomalies." The operator will address Technical Specification 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits."

Booth Operator Instructions: Operate Trigger #3 (ILE003B (100>>.

Indications Available:

• Increasing output on Controller for 1NC-29.

• 1AD-6, C-6, 'Pzr Lo Press Control."

• Pzr pressure decreases (to approximately 2160 psig).

OP/1/Al61 00/01 OG, ANNUNCIATOR RESPONSE FOR PANEL 1AD-6 C-6, PZR LO PRESS CONTROL SRO (IA) IF Pzr pressure decreasing, go to NOTE: Crew may NOT AP/1/A/55001011 (Pressurizer Pressure address ARP, but enter AP11 Anomalies). directly.

SRO (SA) Refer to Tech Specs for minimum instrumentation requirements.

AP/1/Al5500/11, PRESSURIZER PRESSURE ANOMALIES BOP (Step 1) Check actual Pzr pressure - HAS NOTE: Crew will carry out GONE DOWN. Immediate Actions of AP11 ,

prior to the SRO addressing the AP.

BOP (Step 2) Check all Pzr pressure channels -

INDICATING THE SAME.

BOP (Step 3) Check Pzr PORVs - CLOSED.

Appendix 0 operator Action Form ES-D-2 Op Test No.: NOB-1 Scenario # 4 Event # _ 2 _ _ _ _ Page 12 of _5_2__

11 Event

Description:

Spray Valve fails open Position A licant's Actions or Behavior BOP (Step 4) Check Pzr spray valves - CLOSED. NOTE: 1NC-29 will be OPEN.

(Step 4 RNO) Perform the following:

• Close Pzr spray valve(s). NOTE: The BOP will take manual control of and close 1NC-29.

• IF AT ANY TIME a reactor trip occurs NOTE: This is a Continuous AND spray valve still open, THEN stop Action. The SRO will make 1A and 1B NC pumps. both board operators aware.

Critical Task: (SS-4600/113/E13.19) Close the Spray Valve within 1 minute to avoid a reactor trip.

BOP (Step 5) Check Pzr PORVs - CLOSED.

BOP (Step 6) Check Pzr spray valves - CLOSED. NOTE: Both Spray Valves will be CLOSED.

SRO (Step 7) GO TO Step 9.

SRO (Step 9) Announce occurrence on page. NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 10) Check 1NV-21 A (NV Spray To PZR Isol) - CLOSED.

BOP (Step 11) Check the following Pzr heaters -

ON:

• 1A

• 18

• 1D

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 2 Page 13 of 52

---

----II Event

Description:

Spray Valve fails open Time II Position II Applicant's Actions or Behavior BOP (Step 12) Check 1C Pzr heaters - ON.

BOP (Step 13) Check Pzr pressure - GOING UP TO DESIRED PRESSURE.

BOP (Step 14) Check "1NC-27 PRESSURIZER SPRAY EMERGENCY CLOSE" switch -

SELECTED TO "NORMAL".

BOP (Step 15) Check "1NC-29 PRESSURIZER NOTE: 1NC-29 Switch will be SPRAY EMERGENCY CLOSE" switch - selected to CLOSE.

SELECTED TO "NORMAL".

SRO (Step 15 RNO) Notify station management to NOTE: SRO may call WCC to ensure switch restored to "NORMAL" once address.

spray valve is repaired.

If so, Booth Instructor acknowledge as WCC.

SRO (Step 16) GO TO Step 24.

BOP (Step 24) Ensure "PZR PRESS REC SELECT" IS ON OPERABLE CHANNEL.

TECHNICAL SPECIFICATION 3.4.1, RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS SRO 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits SRO LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified in Table 3.4.1-1.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 2 Page 14 of 52

---41 Event

Description:

Spray Valve fails open Time ~ Position ~ Applicant's Actions or Behavior SRO APPLICABILITY: MODE 1.

SRO CONDITION REQUIRED COMPLETION ACTION TIME A. Pressurizer A.1 Restore 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

pressure or DNB RCS parameter(s) average to within temperatur limit.

e DNB parameters not within limits.

At the discretion of the Lead Examiner move to Event #3.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 3 _ _ _ _ Page 15 of _5_2__

u Event

Description:

NV Pump B Tripsl Loss of Charging Time II Position I Applicant's Actions or Behavior After this, the 1B NV Pump will trip causing a Charging Line abnormal flow alarm. The operator will respond in accordance with 1AD-7/G-2, "Charging Line Abnormal Flow,"

and implement AP/1/A/5500/12, "Loss of Letdown, Charging or Seal Injection." The operator will start the NV PD Pump to maintain Seal Injection flow. With two NV Pumps OOS the operator will address Technical Specification 3.5.2, "ECCS-Operating," and enter Technical Specification 3.0.3.

Booth Operator Instructions: Operate Trigger #5 (NV029B).

Indications Available:

• 1AO-7, G-2, "Charging Line Abnormal Flow."

• 1AO-7, J-1, "NC Pump Seallnj La Flow."

OP/1/AJ6100/010H, ANNUNCIATOR RESPONSE FOR PANEL 1AD-7 G-2, CHARGING LINE ABNORMAL FLOW SRO/ (IA Step 1) IF High flow: NOTE: Crew may NOT RO address ARP, but enter AP12 directly.

SRO (IA Step 2) IF Low flow:

• IF 1A(1B) NV pump trips, go to AP/1/A/55001012 (Loss of Letdown, Charging or Seal Injection).

• IF failure of "PO Pump Speed Cntrl" or 1NV-238 (Charging Line Flow control),

place controller in "MAN" and establish normal charging flow.

AP/1/AJ5500/12, LOSS OF LETDOWN, CHARGING OR SEAL INJECTION NOTE: Crew will carry out Immediate Actions of AP12, prior to the SRO addressing the AP.

BOP (Step 1) IF a loss of charging through the Regenerative HX has occurred, THEN ensure the following are closed:

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _3 _ _ _ _ _ Page 16 of 52

---41 Event

Description:

NV Pump B Tripsl Loss of Charging Time II Position ~ Applicant's Actions or Behavior

• 1NV-458A (75 GPM UD Orifice Outlet Cont Isol)

• 1NV-457A (45 GPM UD Orifice Outlet Cont Isol)

• 1NV-35A (Variable UD Orifice Outlet NOTE: Normal Letdown will Cont Isol). be isolated.

BOP (Step 2) check Pzr level - LESS THAN 96%.

BOP (Step 3) IF AT ANY TIME "REGEN HX NOTE: This is a Continuous LETDN HI TEMP" alarms (1AD-7, 1-2), THEN Action. The SRO will make close the following valves: both board operators aware.

• 1NV-1A (NC UD Isol To Regen Hx)

• 1NV-2A (NC UD Isol To Regen Hx).

RO (Step 4) Stop any power or temperature changes in progress.

SRO (Step 5) Announce occurrence on paging NOTE: SRO may ask U2 RO system. to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

NOTE: SRO may call WCC to address and/or dispatch NLO to check out pump.

If so, Booth Instructor acknowledge as wec, Floor Instructor acknowledge as NLO.

SRO (Step 6) IF this AP entered due to loss of NOTE: AP entered due to letdown only, THEN GO TO Step 36. Loss of Charging; continue.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event #

3 Page 17 of

---4\

52 Event

Description:

NV Pump B Tripsl Loss of Charging Time II Position II Applicant's Actions or Behavior BOP (Step 7) Check any of the following charging NOTE: Both 1A and 1B NV pumps - ON. are OFF.

SRO (Step 7 RNO) IF all pumps off, THEN GO TO Step 11.

BOP (Step 11) Monitor NC pump parameters:

• Lower bearing temperature - LESS THAN 225°F

• Number 1 seal outlet temperature -

LESS THAN 235°F

• "NC PUMP HI-HI VIBRATION" alarm (1AD-6, F-11) - DARK.

BOP (Step 12) IF AT ANY TIME NC pump NOTE: This is a Continuous temperature(s) reach trip criteria, OR Action. The SRO will make continuous HI-HI vibration alarm occurs, both board operators aware.

THEN trip associated NC pump(s) as follows:

• Close spray valve on affected NC pump(s).

• Stop any dilution in progress.

• IFin Mode 1 or 2, THEN:

• Trip reactor.

• Stop affected NC pump(s).

• GO TO EP/1/A/5000/E-O (Reactor Trip or Safety Injection) while continuing with this procedure as time allows.

• Stop affected NC pump(s).

BOP (Step 13) Check NC pump thermal barriers as follows:

• Check the following valves - OPEN:

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # _ 3 _ _ _ _ _ Page of N08-1 18

---II 52 Event

Description:

NV Pump B Tripsl Loss of Charging I Time II Position ~ Applicant's Actions or Behavior

• 1KC-394A (A NC Pump Therm Bar Otlt)

• 1KC-345A (C NC Pump Therm Bar Otlt)

• 1KC-364B (B NC Pump Therm Bar Otlt)

• 1KC-413B (D NC Pump Therm Bar Otlt).

SRO

• Contact station management to evaluate NOTE: SRO may call WCC to the following: address.

If so, Booth Instructor acknowledge as WCC.

• Evaluate lowering KC temperature to improve thermal barrier cooling.

BOP (Step 14) Check "SEAL WATER INJ FILTER HI DIP" alarm (1AD-7, L-4) - DARK.

BOP (Step 15) align NV pump to available suction source:

• Check VCT - AVAILABLE AS SUCTION SOURCE.

• Ensure the following valves are open:

• 1NV-141 A (VCT Outlet Isol)

• 1NV-142B (VCT Outlet Isol).

SRO (Step 16) Check if gas binding of NV pumps NOTE: Gas Binding is NOT

- SUSPECTED: suspected.

Booth Instructor As NLO report back Overcurrent Relay (51) has operated for 1B NV Pump.

SRO (Step 16 RND) GO TO Step 20.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 3 _ _ _ _ Page 19 of _5_2 11 Event

Description:

NV Pump B Tripsl Loss of Charging Time " Position " Applicant's Actions or Behavior BOP (Step 20) Check any of the following NOTE: No NV Pumps are charging pumps - ON: ON.

• 1A NV pump OR

• 1B NV pump OR

• PD pump.

BOP (Step 20 RNO) IF all pumps off, THEN perform the following:

• Fully open 1NV-241 (Seal Inj Flow Control).

• Close 1NV-238 (Charging Line Flow Control).

BOP (Step 21) Check both of the following -

OPEN:

• 1NV-244A (Charging Line Cont Outside Isol)

• 1NV-245B (Charging Line Cant Outside Isol).

BOP (Step 22) Check one of the following -

OPEN:

• 1NV-13B (NV Supply To A NC Loop Isol)

OR

• 1NV-16A (NV Supply To D NC Loop Isol).

BOP (Step 23) Check all NC pumps - ON. NOTE: All NC Pumps are ON.

BOP (Step 24) Check any of the following NOTE: No NV Pumps are charging pumps - ON: ON.

• 1A NV pump

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 3 _ _ _ _ _ Page 20 of _5_2_..-041 Event

Description:

NV Pump 8 Tripsl Loss of Charging Time ~ Position ~ Applicant's Actions or Behavior OR

• 1B NV pump OR

• PO pump.

SRO (Step 24 RNO) IF all pumps off, THEN GO TO Step 26.

BOP (Step 26) Start 1A or 1B NV pump as follows: NOTE: 1A NV is OOS.

• Start associated NV Lube Oil pump.

• Start 1A or 1B NV pump.

BOP (Step 26 RNO) IF PO pump is available, NOTE: PO Pump will be THEN start PO pump as follows: started.

• IF SI has occurred OR 1ETA is deenergized, THEN GO TO Step 27.

• Ensure 1RN-42A (AB Non Ess Supply Isol) is open.

• Open the following valves:

• 1RN-64A (AB Non Ess Return Isol)

• 1RN-63B (AB Non Ess Return Isol).

• Place PO pump speed control in manual and set for minimum speed.

• Open 1NV-1047A (PO Pump Recirculation).

• Start the PO pump.

• Ensure 1NV-1047A closes after 2 minutes.

BOP * (Step 26c) Place associated NV Lube Oil pump in "AUTO".

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 3 Page 21 of 52

---

----II Event

Description:

NV Pump B Tripsl Loss of Charging Ti Position A licant's Actions or Behavior BOP (Step 27) Check any of the following charging pumps - ON.

• PD pump.

BOP (Step 28) Check seal injection flow to any NC pump - LESS THAN 6 GPM.

BOP (Step 29) Slowly restore seal injection flow to limit cooldown of NC pump lower bearing temperature to 1°F per minute by performing the following steps concurrently:

• Monitor NC pump lower bearing temperatures.

• Slowly establish charging flow by performing one of the following:

• Throttle open 1NV-238 (Charging Line Flow Control)

OR

• WHEN 1NV-1047A (PD Pump Recirculation) is closed, THEN raise PD pump speed control in manual.

• Slowly raise seal injection flow by throttling close 1NV-241 (Seal Inj Flow Control).

BOP (Step 30) Check seal injection flow -

ESTABLISHED.

SRO (Step 31) GO TO Step 33.

BOP (Step 33) Check Unit 1 Standby Makeup pump-OFF.

BOP (Step 34) Check normal or excess letdown - NOTE: Normal Letdown is IN SERVICE. NOT in service.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 3 _ _ _ _ _ Page 22 of _5_2--41 Event

Description:

NV Pump B Tripsl Loss of Charging Time ~ Position " Applicant's Actions or Behavior SRO (Step 34 RNO) GO TO Step 36.

BOP (Step 36) Ensure the following are closed:

• 1NV-458A (75 GPM UD Orifice Outlet cant Isol)

• 1NV-457A (45 GPM UD Orifice Outlet Cant losl)

• 1NV-35A (Variable UD Orifice Outlet Cant Isol).

BOP (Step 37) Ensure "NC SYS M/U CONTROLLER" in "AUTO".

BOP (Step 38) Ensure charging flow going down to maintain Pzr at program level.

BOP (Step 39) Check "LETDN RELIEF HI TEMP" alarm (1AD-7, 1-4) - HAS REMAINED DARK.

BOP (Step 40) Check 1NV-21A (NV Spray To PZR Isol) - CLOSED.

BOP (Step 41) Operate Pzr heaters as follows:

• Check all Pzr heater group supply breakers - CLOSED.

• Check normal Pzr spray - AVAILABLE. NOTE: One Spray Valve is available, the other is isolated due to a previous malfunction.

• Place the following Pzr heater groups in manual and "ON" to maximize spray flow:

• A

• B

• D.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 3 _ _ _ _ _ Page 23 of _5_2__

41 Event

Description:

NV Pump B Tripsl Loss of Charging Time ~ Position ~ Applicant's Actions or Behavior BOP (Step 42) Check the following valves -

OPEN:

• 1NV-1A (NC UD Isol To Regen Hx)

• 1NV-2A (NC UD Isol To Regen Hx).

SRO (Step 43) GO TO Step 48.

BOP (Step 48) Establish normal letdown:

• Ensure 1NV-459 (Variable UD Orifice Outlet Flow Cntrl) is closed.

• Place 1NV-124 (Letdown Pressure Control) in manual between 10- 20 0/0 open.

• Check the following - OPEN:

• 1NV-1A (NC UD Isol To Regen Hx)

• 1NV-2A (NC UD Isol To Regen Hx).

• Establish cooling to Regenerative HX by performing the following concurrently:

BOP

• Establish at least 65 GPM charging flow by throttling open 1NV-238 (Charging Line Flow Control) or raising PD pump speed.

• Throttle 1NV-241 (Seal Inj Flow Control) to establish approximately 8 GPM seal injection flow to each NC pump.

• Open letdown line isolation valves:

• 1NV-7B (Letdown Cont Outside Isol).

• 1NV-1A (NC UD Isol To Regen Hx).

• 1NV-2A (NC UD Isol To Regen Hx).

• 1NV-235A (Variable UD Orifice Outlet Cont Isol).

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _3 _ _ _ _ _ Page 24 of _5_2_-41 Event

Description:

NV Pump B Trips! Loss of Charging Time II Position ~ Applicant's Actions or Behavior BOP

• Establish desired letdown flow (normally 75 GPM) by completing the following concurrently:

• Slowly throttle open 1NV-459 (Variable UD Orifice Outlet Flow Cntrl) to achieve desired letdown flow.

• As letdown pressure rises, adjust 1NV-124 (Letdown Pressure Control) to maintain letdown pressure between 250 PSIG and 350 PSIG.

• Adjust charging flow as desired while maintaining:

• NC pump seal injection flow greater than 6 GPM

• Regenerative HX letdown temperature less than 380°F

• Pzr level at program level.

• IF more letdown flow required OR a different letdown orifice is desired, THEN REFER TO:

• OP/1/A/62001001 A (Chemical and Volume Control System Letdown),

Enclosure 4.5 (Establishing Maximum Normal Letdown)

OR

• OP/1/A/62001001 A (Chemical and Volume Control System Letdown),

Enclosure 4.3 (Swapping Letdown Orifices).

• Check 1NV-124 (letdown Pressure Control) -IN MANUAL.

• Check potentiometer setting for 1NV-124 (Letdown Pressure Control) set at -

APPROXIMATELY 5.8.

s Manually adjust 1NV-124 to obtain letdown pressure of 350 PSIG.

• Place 1NV-124 in "AUTO".

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 3 _ _ _ _ _ Page 25 of 52

---

ll Event

Description:

NV Pump B Tripsl Loss of Charging Time ~ Position ~ Applicant's Actions or Behavior BOP

• Ensure letdown pressure controlled at 350 PSIG.

• Check 1A or 1B NV pump- NOTE: PD Pump is supplying SUPPL YING NORMAL CHARGING. Charging flow.

• IF #1 PD pump is supplying normal charging, THEN GO TO 48.p.

• Notify Chemistry that normal letdown is NOTE: BOP may call in service. Chemistry.

If so, Booth Instructor acknowledge as Chemistry.

• Check position of 1NV-127A (UD Hx Outlet 3-Way Temp Cntrl) - ALIGNED TO "DEMIN".

• Operate Pzr heaters as desired.

• WHEN time allows, THEN notify NOTE: SRO may call WCC to engineering to document the following address.

transients:

If so, Booth Instructor acknowledge as WCC.

• Letdown isolation

• Potential charging nozzle transient

• IF NV Aux Spray was in service, THEN spray nozzle transient.

• Check excess letdown -ISOLATED.

SRO

• RETURN TO procedure and step in NOTE: SRO will likely conduct effect. a Focus Brief.

Booth Instructor: Call as SOC and report that there have been sporadic Grid Voltage Disturbances that may affect MNS.

(This will set up Event 4).

TECHNICAL SPECIFICATION 3.5.2, ECCS-OPERATING

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 3 Page 26 of 52

---41 Event

Description:

NV Pump B Tripsl Loss of Charging Time " Position Applicant's Actions or Behavior SRO 3.5.2 ECCS - Operating SRO LCO 3.5.2 Two ECCS trains shall be OPERABLE.

SRO APPLICABILITY: MODES 1, 2, and 3.

SRO ACTIONS SRO CONDITION REQUIRED COMPLETION ACTION TIME A. One or more A.1 Restore 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> trains train(s) to inoperable. OPERABLE status.

AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.

SRO Enter T.S. 3.0.3 based on two NV Pumps NOTE: Operator mayor may inoperable. not start downpower at this time.

Examiner NOTE: Before any downpower is started move to Event #4.

At the discretion of the Lead Examiner move to Event #4.

Appendix 0 operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 4 Page 27 of 52

---

----41 Event

Description:

Electrical Grid Disturbances Time II Position ~ Applicant's Actions or Behavior A short time later, SOC notifies McGuire Nuclear Station that sporadic grid voltage disturbances have been experienced in the region and that these may affect MNS operation. Over the next several minutes, grid voltage cycles between 216-231 KV. The operator will respond in accordance with AP/1/A/5500/05, "Generator Voltage and Electrical Grid Disturbances," and make adjustments of Main Generator voltage.

Booth Operator Instructions: Operate Trigger #7 (PLP-014 (216>>.

Indications Available:

• GAC Alarm M1A0960 Line Voltage Up/Down

• MVARs outside Main Generator Capability Curve on OAC.

AP/1/AJ5500/05, GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES SRO (Step 1) Announce occurrence on page. NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

SRO (Step 2) GO TO appropriate enclosure:

• Enclosure 1 (Abnormal Generator or Grid Voltage)

AP/1/AJ5500/05, GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES ENCLOSURE 1, ABNORMAL GENERATOR OR GRID VOLTAGE RO (Step 1) Check Generator - TIED TO GRID.

RO (Step 2) Monitor Generator capability Curve as follows:

• IF generator voltage less than 24KV, THEN REFER TO Enclosure 4 (Generator Capability Curve - 22.8 KV)

OR

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-.1 Scenario # 4 Event # _ 4 _ _ _ _ _ Page 28 of _5_2_-4\

Event

Description:

Electrical Grid Disturbances Time II Position ~ Applicant's Actions or Behavior

• IF generator voltage greater than or equal to 24KV, THEN REFER TO Enclosure 5 (Generator Capability Curve - 24 KV).

RO (Step 3) Check Generator MVARs -

EXCEED GENERATOR CAPABILITY CURVE.

RO (Step 4) Adjust MVARs to within the capability curve by performing one of the following:

• Depress "LOWER" on the "VOLTAGE ADJUST" to reduce lagging MVARs OR

• Depress "RAISE" on the "VOLTAGE ADJUST" to reduce leading MVARs.

RO (Step 5) Check Generator MVARs - WITHIN NOTE: After the adjustment LIMITS OF GENERATOR CAPABILITY MVARS will be within CURVE. Capability Curve.

Booth Operator Instructions: Change PLP-014 to 231 over 120 Second Ramp.

NOTE: This will require a second MVAR adjustment by RO.

RO (Step 4) Adjust MVARs to within the capability curve by performing one of the following:

• Depress "LOWER" on the "VOLTAGE ADJUST" to reduce lagging MVARs OR

• Depress "RAISE" on the "VOLTAGE ADJUST" to reduce leading MVARs.

Appendix D Operator Action Form ES-D-2 Scenario # 4 4 of Op Test No.: N08-1 Event # Page 29

---II 52 Event

Description:

Electrical Grid Disturbances Time ~ Position ~ Applicant's Actions or Behavior RO (Step 5) Check Generator MVARs - WITHIN NOTE: After the adjustment LIMITS OF GENERATOR CAPABILITY MVARS will be within CURVE. Capability Curve.

RO (Step 6) Determine status of voltage regulator as follows:

• Check status of voltage regulator on OAC using turn on code "MAINGEN".

• Dispatch operator to check for alarms on NOTE: SRO may dispatch Unit 1 local panel. NLO from Control Room.

If so, Floor Instructor acknowledge. Wait 5 minutes and then report that there are NO alarms on the Unit 1 Local Panel.

• Contact dispatcher to determine if NOTE: SRO may NOT generator voltage problem is due to contact Dispatcher since SOC disturbances on the grid. has notified them of possible Grid Disturbances.

If SRO does contact SOC, Booth Instructor acknowledge, and report that they may continue. The source is unknown.

SRO (Step 7) Evaluate the following:

• Stopping any ongoing surveillance testing.

• Stopping any ongoing maintenance activities.

• Returning systems to normal/functional.

SRO (Step 8) Contact the following personnel for NOTE: SRO may call wce to guidance: address.

If so, Booth Instructor acknowledge as weco

• System Engineering

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 4 _ _ _ _ _ Page 30 of 52

---ll Event

Description:

Electrical Grid Disturbances Time A licant's Actions or Behavior

• Maintenance Technical Support.

SRO (Step 9) IF AT ANY TIME System NOTE: This is a Continuous Engineering or Maintenance Technical Action. The SRO will make Support request operation of the voltage both board operators aware.

regulator from the local panel, THEN dispatch licensed operator to perform applicable section(s) of OP/1/A/6300/001 (Turbine Generator Startup/Shutdown),

Enclosure 4.10 (Voltage Regulator Operation From U1 Gen Voltage Reg Local Control Panel).

At the discretion of the Lead Examiner move to Event #5.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 5 _ _ _ _ _ Page 31 of 52 Event

Description:

Rapid Downpower Time ~ Position II Applicant's Actions or Behavior Due to the degraded Charging (NV) System and the grid voltage fluctuations station management will direct a shutdown using AP/1/A/5500/04, "Rapid Downpower."

Floor Instructor: As OSM, because of TS 3.0.3 and Grid Voltage Fluctuations, direct that the Unit be taken off line within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in accordance with AP4, Rapid Downpower.

Indications Available: NA AP/1/Al5500/04, RAPID DOWNPOWER SRO (Step 1) Monitor Foldout page.

SRO (Step 2) Announce occurrence on page. NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 3) Check Turbine control - IN AUTO.

RO (Step 4) Check "MW LOOP" -IN SERVICE.

RO (Step 4 RNO) Depress "MW IN/MW OUT" pushbutton.

SRO (Step 5) Check shutdown to Mode 3 -

DESIRED.

SRO (Step 6) Check if "Shutdown Via Reactor Trip NOTE: Trip from 15% will be form 150/0 Power" appropriate: desired.

• Shutdown Via Reactor Trip from 15%

Power - DESIRED

• At least two CA pumps - OPERABLE.

Appendix D operator Action Form ES-D-2 Op Test No.: NOB-1 Scenario # 4 Event # 5 Page 32 of 52 Event

Description:

Rapid Downpower Ti A licant's Actions or Behavior

!k====

RO (Step 7) Enter target load of 180 MWE in turbine control panel.

SRO (Step 8) Determine the required power NOTE: SRO will determine reduction rate (MW/min). 85% load reduction.

RO (Step 9) Check control rods - IN AUTO.

RO (Step 9 RNO) Perform the following:

• IF auto control available, THEN place NOTE: If NOT in AUTO, RO control rods in auto. will place Rods in AUTO.

SRO (Step 10) Notify SOC of load reduction (red Booth Instructor:

dispatcher phone). Acknowledge as SOC.

RO (Step 11) Initiate turbine load reduction to NOTE: RO will start load desired load at desired rate. reduction.

BOP (Step 12) Borate NC System as follows:

• Energize all backup Pzr heaters.

• Determine boration amount based on the following:

• Power Reduction Rate (MW/min)

• Present NC System Boron concentration (ppm)

• Total Power change (o~).

• Record calculated boration amount: NOTE: BOP will determine 600 gallons.

• Perform boration in 4 equal additions during load reduction PER OP/1/A/6150/009 (Boron Concentration Control), Enclosure 4.7 {Boration Using 1NV-265B (Boric Acid to NV Pumps)).

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # _ 5 _ _ _ _ _ Page 33 of 52 Event

Description:

Rapid Downpower Time ~ Position ~ Applicant's Actions or Behavior RO (Step 13) check control rods - MOVING IN NOTE: RO will observe AS REQURIED TO MAINTAIN T-AVE AT Control Rods stepping in.

T-REF.

RO (Step 14) Display rod Insertion Limits on OAC by entering turn on code "RIL".

ROI (Step 15) IF AT ANYTIME "CONTROL ROD NOTE: This is a Continuous BOP BANK LO LO LIMIT" alarm (1AD-2, B-9) is lit, Action. The SRO will make THEN perform one of the following to comply both board operators aware.

with Tech Spec 3.1.6 (Control Bank Insertion Limits):

• Ensure alarm clears within one hour as Xenon builds in.

OR

• Initiate boration as necessary within one hour to restore control rods above insertion limits.

RO (Step 16) IF AT ANY TIME during this procedure C-7A is received, THEN ensure Transient Monitor freeze is triggered.

After Emergency Borate Valve 1NV-265B is closed, OR at the discretion of the Lead Examiner move to Events #6-8.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time " Position ~ Applicant's Actions or Behavior During the shutdown, the G.B.E. Exceeded alarm comes in, indicating that an earthquake has occurred. Within seconds a Large Break LOCA will occur on Loop B, and a Reactor Trip/Safety Injection will occur. The operator will enter E-O, "Reactor Trip or Safety Injection." On the Safety Injection, the 1A and 1B NO pumps fail to start automatically and will require manual action to start the pumps. Upon completion of E-O, the operator will transition to E-1, "Loss of Reactor or Secondary Coolant." However, upon transition an Orange Path will exist on both the Integrity and Containment Critical Safety Functions. The operator will first address FR-P.1, "Response to Imminent Pressurized thermal Shock Condition," and then transition to FR-Z.1 , "Response to High Containment Pressure." If these procedures are completed the operator will transition to E-1, "Loss of Reactor or Secondary Coolant" however, it is more likely that Cold Leg Recirculation transition criteria will be met during the performance of the two Functional Recovery Procedures. If so, the operator will transition to ES-1.3, "Transfer to Cold Leg Recirc," on low FWST level. The operator will place Cold Leg Recirculation in service in accordance with ES-1.3. The scenario will terminate at Step 8 of ES-1.3 when the operator is directed to check if NS should be aligned for Recirc.

Booth Operator Instructions: Operate Trigger #9 (ANN-AD13E07, NC008B (45 Seconds Delayed>>.

Indications Available:

• 1AD-13, E-7, "O.B.E. Exceeded."

• Reactor Trip/Safety Injection.

• NC System Pressure goes down.

• Containment Pressure Increases NOTE: Crew will carry out Immediate Actions of E-O, prior to the SRO addressing the EP.

E-O, REACTOR TRIP OR SAFETY INJECTION SRO (Step 1) Monitor Foldout page.

RO (Step 2) Check Reactor Trip:

• All rod bottom lights - LIT

• Reactor trip and bypass breakers -

OPEN

• IIR amps - GOING DOWN.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time II Position ~ Applicant's Actions or Behavior RO (Step 3) Check Turbine Trip:

• All throttle valves - CLOSED.

BOP (Step 4) Check 1ETA and 1ETB-ENERGIZED.

RO / (Step 5) Check if S/I is actuated:

BOP

• "SAFETY INJECTION ACTUATED" status light (1SI-18) - LIT.

• Both LOCA Sequencer Actuated status lights (1SI-14) - LIT.

SRO (Step 6) Announce "Unit 1 Safety Injection". NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 7) Check ESF Monitor Light Panel on energized train(s):

• Groups 1, 2, 5 - DARK.

• Group 3 - LIT.

• OAC - IN SERVICE.

• Group 4, Rows A through F - LIT AS NOTE: BOP may recognize REQUIRED. that neither ND Pump started automatically and manually start both.

BOP (Step 7d RNO) Perform the following

• Ensure both trains Phase A Isolation are initiated.

• Align or start S/I and Phase A components with individual windows in Group 4 as required.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time ~ Position ~ Applicant's Actions or Behavior

• GO TO Step 7f.

BOP * (Step 7f) Check LOCA Sequencer Actuated status light (1 SI-14) on energized train(s) - LIT.

• Check the following windows on Monitor Light Panel Group 4 - LIT:

• C-3, "CONT ISOL PHASE A TRN A VLVS ALIGNED"

• C-6 "CONT ISOL PHASE A TRN B VLVS ALIGNED"

• F-4 "SAFETY INJECTION TRAIN A COMPONENTS ALIGNED"

• F-5 "SAFETY INJECTION TRAIN B COMPONENTS ALIGNED".

BOP (Step 8) Check proper CA pump status:

• MD CA pumps - ON.

• (Step 8b) N/R level in at least 3 S/Gs -

GREATER THAN 17%.

BOP (Step 9) Check all KC pumps - ON.

BOP (Step 10) Check both RN pumps - ON.

SRO (Step 11) Notify Unit 2 to start 2A RN pump. Floor Instructor: As U2 RO report "2A RN Pump is running."

RO (Step 12) Check all S/G pressures -

GREATER THAN 775 PSIG.

BOP (Step 13) Check Containment Pressure - NOTE: Containment Pressure HAS REMAINED LESS THAN 3 PSIG. is > 3 psig.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time ~ Position ~ Applicant's Actions or Behavior BOP (Step 13 RNO) Perform the following:

• Record approximate time of reactor trip. NOTE: RO will report time of Rx Trip.

• Check Monitor Light Group 4, Row G, lit.

• IF any Row G window is dark on energized train(s), THEN perform the following:

• Initiate Phase B and Containment Spray signal.

• IF Row G window is still dark, THEN:

• Check OAC Monitor Light Program ("MONL") for Phase B, and align valves.

• IF OAC is out of service, THEN ensure Phase B valves closed PER EP/1/N5000/G-1 (Generic Enclosures), Enclosure 12 (Phase B Valve Checklist), while continuing in this EP.

• Stop all NC pumps while maintaining seal injection flow.

• Ensure all RV pumps are in manual and off.

• Energize H2 Igniters by depressing "ON" and "OVERRIDE".

• Dispatch operator to stop all Unit 1 NF NOTE: SRO will dispatch AHUs (control panels located in 750 and NLO.

733 electrical penetration rooms).

Booth Instructor: As NLO, report in 5 minutes that all Unit 1 NF AHUs are stopped.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, &8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time ~ Position ~ Applicant's Actions or Behavior

• WHEN time allows, THEN check Phase NOTE: The SRO may assign B HVAC equipment PER Enclosure 2 the BOP to perform this action.

(Phase B HVAC Equipment).

If so, BOP Examiner follow actions of Enclosure 2.

The SRO may ask U2 BOP to perform this action.

If so, Floor Instructor:

Acknowledge as U2 BOP.

E-O, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 2, Phase B HVAC Equipment BOP (Step 1) Check VE System in Operation as Examiner NOTE: Follow the Follows: actions associated with Enclosure 2 if BOP is assigned by SRO to perform.

• VE Fans - On.

• Ensure all damper mode select switches in AUTO.

• 1AVS-D-7 Mode Select.

• 1AVS-D-8 Mode Select.

• 1AVS-D-2 Mode Select.

• 1AVS-D-3 Mode Select.

• Annulus pressure being maintained -

NEGATIVE BOP (Step 2) Check VX System in Operation as Follows:

• Time since Phase B actuation -

GREATER THAN 10 MINUTES.

.. Check the following - OPEN.

• 1RAF-D-4 (1 B Cont Air Ret Fan To Lwr Cont Test A).

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, &8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time II Position I Applicant's Actions or Behavior

• 1VX-2B (1 B H2 Skimmer Fan Isol Test A).

• 1RAF-D-2 (1A Cont Air Ret Fan To Lwr Cont Test A).

• 1VX-1 A (1A H2 Skimmer Fan Isol Test A)

• Check Containment Air Return Fans -

ON.

• Check H2 Skimmer Fans - ON.

E-O, REACTOR TRIP OR SAFETY INJECTION ROI (Step 14) Check SII flow:

BOP

• Check "NV PMPS TO COLD LEG NOTE: Neither 1A or 1B NV FLOW" gauge -INDICATING FLOW. Pump is running.

• Check NC pressure - LESS THAN 1600 PSIG.

• Check NI pumps - INDICATING FLOW.

• Check NC pressure - LESS THAN 286 NOTE: BOP may recognize PSIG. that neither NO Pump started automatically and manually start both.

• Check NO pumps -INDICATING FLOW TO COLD LEGS.

• Start NO pumps and align valves.

Critical Task: (E-O H) Manually start at least one NO Pump before transition out of E-O.

SRO (Step 15) Notify OSM or other SRO to NOTE: SRO may ask OSM to perform EP/1IA/5000/G-1 (Generic address.

Enclosures), Enclosure 22 (OSM Actions If so, Floor Instructor Following an S/I) within 10 minutes ...

acknowledge as OSM.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, &8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time II Position ~ Applicant's Actions or Behavior RO (Step 16) Check CA flow:

• Total CA flow - GREATER THAN 450 GPM.

• Check VI header pressure - GREATER THAN 60 PSIG.

• WHEN N/R level in any S/G greater than NOTE: Adverse Containment 11% (320/0 ACC), THEN control CA flow Numbers will be used.

to maintain N/R levels between 11o (32% ACC) and 50%.

RO (Step 17) Check NC temperatures:

• IF all NC pumps off, THEN check NC NOTE: All NC Pumps will be T-Colds - STABLE OR TRENDING TO OFF.

557°F.

RO (Step 17 RNO) Perform the following based NOTE: The SRO may assign on plant conditions: the RO to perform this action.

If so, RO Examiner follow actions of Enclosure 3.

• IF temperature less than 557°F AND going down, THEN attempt to stop cooldown PER Enclosure 3 (Uncontrolled NC System Cooldown).

E-O, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 3, UNCONTROLLED NC SYSTEM COOLDOWN RO (Step 1) Check steam dump valves - Examiner NOTE: Follow the CLOSED. actions associated with Enclosure 3 if RO is assigned by SRO to perform.

RO (Step 2) Check all SM PORVs - CLOSED.

RO (Step 3) Check MSR "RESET" light - LIT.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time ~ Position ~ Applicant's Actions or Behavior RO (Step 4) Check any NC pump - ON.

RO (Step 4 RNO) Perform the following:

• IF any NC T-Cold is still going down, THEN GO TO Step 6.

RO (Step 6) Control feed flow as follows:

• IF S/G N/R level is less than 11% (32%

ACC) in all S/Gs, THEN throttle feed flow to achieve the following:

• Minimize cooldown

• Maintain total feed flow greater than 450 GPM.

• WHEN N/R level is greater than 11%

(320/0 ACC) in at least one S/G, THEN throttle feed flow further to:

• Minimize cooldown

• Maintain at least one S/G N/R level greater than 11% (32% ACC).

RO (Step 7) Check MSIVs - ANY OPEN.

RO (Step 7 RNO) Perform the following:

• Close MSIV bypass valves.

• Exit this enclosure.

E-O, REACTOR TRIP OR SAFETY INJECTION BOP (Step 18) Check Pzr PORV and spray valves:

• All Pzr PORVs - CLOSED.

• Normal Pzr spray valves - CLOSED.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, &8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time ~ Position ~ Applicant's Actions or Behavior RO (Step 19) Check NC subcooling based on NOTE: There is NO NC core exit TICs -- GREATER THAN OaF. Subcooling.

(Step 19 RNO) IF at least one NV OR NI pump on, THEN stop all NC pumps while maintaining seal lnjectiontlow, RO (Step 20) Check if main steam lines intact:

• All S/G pressures -- STABLE OR GOING UP

• All S/Gs -- PRESSURIZED.

BOP (Step 21) check if S/G tubes intact:

• The following secondary EMFs --

NORMAL:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-34(L) (S/G Sample (Lo Range))

• 1EMF-24 (S/G A)

• 1EMF-25 (S/G B)

• 1EMF-26 (S/G c)

• 1EMF-27 (S/G D).

• S/G levels -- STABLE OR GOING UP IN A CONTROLLED MANNER.

BOP (Step 22) Check if NC System intact:

• Check containment EMFs -- NORMAL:

• 1EMF-38(L) (Containment NOTE: 1EMF-38(L) is in Trip Particulate (LR)) 2.

• 1EMF-39(L) (Containment Gas (Lo NOTE: 1EMF-39(L) is in Trip Range)) 2.

• 1EMF-40 (Containment Iodine)

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, &8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time II Position I Applicant's Actions or Behavior

• 1EMF-9 (Reactor Bldg Incore Inst Rm)

• 1EMF-16 (Containment Refueling Brdg).

BOP (Step 22 RNO) Perform the following:

• IF H2 Igniters are off, THEN perform the following:

• Energize H2 Igniters by depressing "ON" and "OVERRIDE".

• Dispatch operator to stop all Unit 1 NOTE: This action has been NF AHUs (control panels located in previously performed.

750 and 733 electrical penetration If not reported Booth rooms).

Instructor: As NLO, report that all Unit 1 NF AHUs are stopped.

• IF AT ANY TIME both of the following NOTE: Containment Pressure conditions exist, THEN start one train of has NOT remained < 3 psig.

VX PER Enclosure 4 (VX Manual Start).

• Containment pressure is between 1 PSIG and 3 PSIG.

• Containment pressure has remained less than 3 PSIG.

SRO

• Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/E-1 (Loss of NOTE: Upon transition to E-1, Reactor or Secondary Coolant). an ORANGE Path will exist on NC Integrity and Containment.

The SRO will transition to FR-P.1, rather than E-1.

FR-Pn1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION BOP (Step 1) Check NC pressure - GREATER NOTE: NC Pressure will be 5-THAN 286 PSIG. 10 psig.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time II Position ~ Applicant's Actions or Behavior SRO (Step 1 RNO) Perform the following:

• IF ND pump flow is greater than 500 NOTE: Both ND Pumps will be GPM, THEN RETURN TO procedure operating.

and step in effect.

The SRO will transition to FR..

Z.1, rather than E.. 1.

FR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE Examiner NOTE: If at any time during the performance of FR-Z.1 the FWST Lo Level Alarm comes in, the Crew will immediately transition to ES-1.3.

If this occurs, proceed to Page 48.

SRO (Step 1) IF loss of emergency coolant recirc NOTE: Loss of Emergency has occurred, THEN this procedure may be Coolant Recirc has NOT completed as time allows. occurred.

SRO (Step 2) Monitor Foldout Page.

BOP (Step 3) Stop all NC pumps. NOTE: All NC Pumps are stopped.

BOP (Step 4) Ensure all RV pumps are in manual and off.

SRO (Step 5) Dispatch operator to remove white NOTE: SRO will dispatch tags and close the following breakers: NLO.

Floor/Booth Instructor:

Acknowledge as appropriate.

.. 1EMXA..R2A (1 A NO To A&B Cold Legs Cont Outside Isol Motor (1 NI.. 173A)) (aux bldg, 750, FF..54, FF..55)

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, &8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time II Position ~ Applicant's Actions or Behavior

• 1EMXB1-6B (1 B ND To C&D NC Cold Booth Instructor: Wait 5 Leg Cont Outside Isol Motor (1NI-178B)) minutes, Insert LOA:

(aux bldg, 733, GG-55, GG-556).

NI024 =Racked In NI025 =Racked In And then, report as NLO that breakers are closed.

BOP (Step 6) Check containment pressure - NOTE: Containment pressure LESS THAN 15 PSIG. is ==5-10 psig due to the LOCA.

BOP (Step 7) Check any NS pump - ON.

SRO (Step 8) Perform the remainder of this EP as NOTE: SRO may continue time allows. with FR-Z.1 or Transition to E-1.

If Transition is made here, moved forward to Page 48 and await entry into ES-1.3.

BOP (Step 9) Check containment isolation:

• Check OAC - IN SERVICE.

• Check of the following windows on Group 4 of ESF Monitor light Panel -

LIT.

• C-3 "CaNT ISOL PHASE A TRN A VLVS ALIGNED"

• C-6 "CaNT ISOL PHASE A TRN B VLVS ALIGNED"

• G-4 "CaNT ISOL PHASE B TRN A VLVS ALIGNED"

• G-5 "CONT ISOL PHASE B TRN 8 VLVS ALIGNED".

BOP (Step 10) Check NS System in operation as follows:

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, &8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time II Position Applicant's Actions or Behavior

• Check EP/1/N5000/ECA-1.1 (Loss of NOTE: Loss of Emergency Emergency Coolant Recirc) -- IN Coolant Recirc is NOT in EFFECT. effect.

SRO (Step 10 RNO) GO TO Step 10d.

BOP * (Step 10d) Check NS suction --

ALIGNED TO FWST AS FOLLOWS:

• Check 1NS-18A (A NS Pump Suct From Cant Sump) -- CLOSED

• Check 1NS-20A (A NS Pump Suct From FWST) - OPEN

• Check 1NS-1 B (B NS Pump Suct From Cant Sump) -- CLOSED

• Check 1NS-3B (B NS Pump Suct From FWST) - OPEN

• Check containment pressure -- NOTE: Containment pressure GREATER THAN 3 PSIG. is ==5-10 psig due to the LOCA.

• Check NS pump discharge valves --

OPEN:

• 1NS-32A (A NS Pump Disch Cant Outside Isol)

• 1NS-29A (A NS Pump Disch Cant Outside Isol)

• 1NS-12B (B NS Pump Disch Cant Outside Isol)

• 1NS-15B (B NS Pump Disch Cant Outside Isol).

• Check NS pumps -- ON.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time ~ Position ~ Applicant's Actions or Behavior BOP (Step 11) Check Phase B HVAC equipment NOTE: The SRO may assign PER Enclosure 3 (Phase B HVAC the BOP to perform this action.

Equipment).

If so, BOP Examiner follow actions of BOP previously performed as Enclosure 2 of E-O.

The SRO may ask U2 BOP to perform this action.

If so, Floor Instructor:

Acknowledge as U2 BOP.

RO (Step 12) Check the following - CLOSED:

.. All MSIVs

.. All MSIV bypass valves.

RO (Step 13) steamlines intact:

.. All S/G pressures - STABLE OR GOING UP

.. All S/Gs - PRESSURIZED.

BOP (Step 14) Check if one or two trains of ND aux spray should be aligned:

.. Any ND Train - OPERATING IN COLD LEG RECIRC MODE.

.. Containment pressure - GREATER THAN 3 PSIG.

.. Check the following:

.. Time after reactor trip - GREATER THAN 50 MINUTES

• At least one of the following -

ENERGIZED:

.. 1NI-173A (Train A ND to A & B CL)

OR

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, &8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time ~ Position ~ Applicant's Actions or Behavior

• 1NI-178B (Train B NO to C & 0 CL).

• Check the following - CLOSED.

• 1NS-43A (A NO to NS Cant Outside Isol)

• 1NS-38B (B NO to NS Cant Outside Isol).

Examiner NOTE:

Mark Time of FWST La Level Alarm (To the Second):

ES-1.3, TRANSFER TO COLD LEG RECIRC SRO (Step 1) Have STA monitor Foldout Page. NOTE: SRO will address STA.

Floor Instructor:

Acknowledge as STA.

SRO (Step 2) Perform this EP without delay:

• CSF procedures should not be implemented until directed by this procedure.

• Double 3-way communication is not required.

BOP (Step 3) Check containment sump level by checking at least one of the following alarms - LIT:

• "CONT SUMP LEVEL GREATER THAN 3 FT" on 1AD LIT OR

• "CONT SUMP LEVEL GREATER THAN 3 FT" on 1AD LIT.

BOP (Step 4) Check KC flow to each NO heat exchanger - GREATER THAN 5000 GPM.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time I Position I Applicant's Actions or Behavior BOP (Step 5) Reset the following:

• S/I.

• Sequencers.

BOP (Step 6) Align NO System for recirc:

• Check 1NI-185A (RB Sump to Train A NO & NS) - OPEN.

• Check 1A NO pump - ON.

• Check 1NI-184B (RB Sump to Train B NO & NS) - OPEN.

• Check 1B NO pump - ON.

• Enable power disconnect and close Examiner NOTE:

1FW-27A (FWST Supply to NO).

Mark Time of 1FW-27A Closed (To the Second):

• Check any NO pump - ON.

BOP (Step 7) Align NV and NI Systems for recirc:

• Check NC pressure - LESS THAN 1600 PSIG.

• Close the following:

• 1NI-115B (A NI Pump Miniflow)

• 1NI-144B (B NI Pump Miniflow).

• Enable power disconnect and close 1NI-147A (NI Pumps Miniflow Hdr Isol).

• Close the following valves:

• 1ND-30A (Train A NO to Hot Leg lsoI)

• 1NO-15B (Train B NO to Hot Leg Isol).

• Check 1NI-334B (NV & NI Pumps Suct X-Over Blk) - OPEN.

Appendix D operator Action Form ES-D-2 Op Test No.: NOB-1 Scenario # 4 Event # 6,7, & 8 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time I Position I Applicant's Actions or Behavior

• Open the following:

• 1NI-332A (NV & NI Pumps Suction X-Over)

• 1NI-3338 (NV & NI Pumps Suction X-Over).

• Align NO discharge to suction of NI and NV pumps as follows:

• Open 1NO-S8A (Train A NO to NV &

NI Pumps)

• Open 1NI-1368 (8 NI Pump Suction Examiner NOTE:

From ND).

Mark Time of 1N1-1368 Opened (To the Second):

• Isolate FWST from NV and NI pumps:

• Enable power disconnect and close 1NI-1008 (FWST)

• Close the following

• 1NV-22A (NV Pumps Suct From FWST)

• 1NV-2228 (NV Pumps Suct From FWST).

Critical Task: (SS-4600/113/E13.81.b) Align ECCS such that FW-27A is closed by 195 seconds after FWST Lo Level alarm, and NO-58A1NI-136 B are opened by 355 seconds after FWST Lo Level alarm.

At the discretion of the Lead Examiner terminate the exam.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 4 Event # 6, 7, & 8 Page _51_ _ of _5_2_-11 Event

Description:

Seismic Event/Large Break LOCAl1 A and 1B NO Pumps Fail to Auto Start Time ~ Position Applicant's Actions or Behavior

UNIT 1 STATUS:

Power level: 100% NCS [B] 76 ppm pzr [B]: 76 ppm Xe: Per OAC Power History: At this power since startup Core Burnup: 485 EFPDs CONTROLLING PROCEDURE: OP/1/A/6100103 Controlling Procedure for Unit Operation PT/O/A/41501041 , "RCCA Bank Repositioning," in progress.

OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

• The Plant is at 100% power Steady-State (EOl), and been for the last 485 days.

• An RCCA Movement Test is in progress in accordance with PT/O/A/41501041 , "RCCA Bank Repositioning," and it is expected to be continued starting with Control Bank D on the upcoming shift, starting at step 12.1.7.6.

The following equipment is Out-Of-Service:

• 1A NV Pump (Expected back in 24-36 hours).

• 1FW-5020, FWST level, failed last shift (IAE is investigating).

• MCB Annunciator 1AD-12, E-5, "FWST Lo-Lo Temp," has alarmed spuriously several times over the last hour (IAE is investigating).

Work Control SRO/Offsite Communicator Jim Plant SRO Joe NLO*s AVAILABLE Aux Bldg. John Aux Bldg. Chris Turb Bldg. Bob Turb Bldg. Mike 5th Rounds. Carol Extra(s) Bill Ed Wayne Tanya

PROGRAM: McGuire Operations Training MODULE: Initial License Operator Training Class 24 TOPIC: NRC Simulator Exam Scenario N08-1-5

REFERENCES:

1. OP/1/A/61 00/003, "Controlling Procedure for Unit Operation."

2. OP/1/A/6300/001, "Turbine Generator Startup/Shutdown."

3. OP/1/A/6100/01OC, "Annunciator Response for Panel 1AD-2."

4. AP/1/A/5500/16, "Malfunction of Nuclear Instrumentation."

5. McGuire Technical Specifications

6. OAC Alarm Response M1A1104, "U1 VCT Level."

7. OP/1/A/61 00/01OG, "Annunciator Response for PaneI1AD-6."

8. OP/1/A/61 00/01OE, "Annunciator Response for PaneI1AD-4."

9. AP/1/A/5500/06, "S/G Feedwater Malfunction."

10. AP/1/A/5500/07, "Loss of Electrical Power."

11. EP/1/A/5000/E-0, "Reactor Trip or Safety Injection."

12. EP/1/A/5000/ES 1.1, "Safety Injection Termination."

13. Generic Enclosure 1, "Establishing Normal Letdown."

14. RP/O/A/5700/000, "Classification of Emergencies."

Author: David Lazarony, Western Technical Services, Inc.

Facility Review:

March r", 2008 Rev. 3 Scenario Event Description NRC Scenario 5 Facility: McGuire Scenario No.: 5 Op Test No.: N08~1 Examiners: Operators: (SRO)

---

11 (OATC)

(BOP)

Initial Conditions: Both units had been recently shutdown to Mode 3 due to a Hurricane, and now it has become necessary to restart both units. Unit 2 has been restarted and is presently holding at 30% power. The plant has limited personnel, however, station management has approved the start-up. Unit 1 is at 150/0 power in accordance with OP/1/A/61 00/003, "Controlling Procedure for Unit Operation," Enclosure 4.1, "Power Increase," and the Main Turbine is operating at 1800 RPM in accordance with Step 3.11 of Enclosure 4.1, "Startup with Turbine Control in "Operator Auto"," of OP/1/A/6300/001, "Turbine Generator Startup/Shutdown." It is expected that this shift will complete the startup of the main turbine and synchronize the main generator to the electrical grid.

Turnover: The following equipment is Out-Of-Service: 1NCP-5050, NC Loop B Flow, has failed (Channel has been defeated by IAE) and MCB Annunciator 1AD-8, C-6, "Hotwell Lo Level," has been in constant alarm over the last hour (IAE is investigating).

Event Malf. Event Type* Event No. No. Description 1 NA N-RO Prepare for Synchronization of the Main Generator N-SRO 2 EN8013C I-BOP Power Range Channel Failure I(TS)-SRO OVR 3 C-RO Failure of Main Generator Autosynch Circuit MG017A1 B C-SRO 4 XMT NVOO1 I-BOP VCT Level Failure I-SRO 5 XMT CF029 I-RO C SG Narrow Range Level Failure I(TS)-SRO 6 EP0098 C-BOP Blackout on 1ETB/1 B RN Pump & 1B1 KC Pump fails to Auto Start RN0038 C-SRO KC001C 7 ISE001C M-RO Spurious 81 M-BOP M-SRO 8 IPE001A1 NA Auto Reactor Trip fails/manual available 8

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 5 McGuire 2008 NRC Scenario #5 Both units had been recently shutdown to Mode 3 due to a Hurricane, and now it has become necessary to restart both units. Unit 2 has been restarted and is presently holding at 30%

power. The plant has limited personnel, however, station management has approved the start-up. Unit 1 is at 150/0 power in accordance with OP/1/A/6100/003, "Controlling Procedure for Unit Operation," Enclosure 4.1 , "Power Increase," and the Main Turbine is operating at 1800 RPM in accordance with Step 3.11 of Enclosure 4.1, "Startup with Turbine Control in "Operator Auto","

of OP/1/A/6300/001, "Turbine Generator Startup/Shutdown." It is expected that this shift will complete the startup of the main turbine and synchronize the main generator to the electrical grid.

The following equipment is Out-Of-Service: 1NCP-5050, NC Loop B Flow, has failed (Channel has been defeated by IAE) and MCB Annunciator AD-8, C-6, "Hotwell Lo Level," has been in constant alarm over the last hour (lAE is investigating).

Upon shift turnover, the operator will perform Step 3.13 of Enclosure 4.1, "Startup with Turbine Control in "Operator Auto," of OP/1/A/6300/001, "Turbine Generator Startup/Shutdown." The operator will place the Voltage Regulator in service and attempt to synchronize the Main Generator to the electrical grid.

Just prior to attempting to synchronize the Main Generator, Power Range N42 Upper Detector will fail low. The operator will respond in accordance with ARP1 AD-2/B-3, "P/R Channel Deviation," and implement AP/1/A/5500/16, "Malfunction of Nuclear Instrumentation." The operator will address Technical Specification 3.3.1, "RTS Instrumentation."

Following this, when the operator attempts to synchronize the Main Generator the autosynch circuit for the breaker that is attempted to be closed first, will fail. The operator will need to recognize the failure and attempt to close the other breaker in accordance with Step 3.15.4.7.B of Enclosure 4.1, "Startup with Turbine Control in "Operator Auto," of OP/1/A/6300/001, "Turbine Generator Startup/Shutdown."

At the time that the Main Turbine is stabilized at 25 MWe, VCT Level Transmitter NVLT-5760 will slowly fail to 40% causing a continual Auto Make-up to the VCT. The operator will perform a channel check of the two VCT Level instruments and recognize that actual VCT level is rising and take manual control of the NC System Makeup Controller. If no action is taken, OAC Alarm M1A1104, "U1 VCT Level," will alarm. If still no action is taken, auto makeup will continue indefinitely and 1NV-137 will divert to the Recycle Holdup Tank causing an increase in waste liquid.

Subsequently, the C SG Narrow Range Level transmitter (LCF-5570) will fail low. The operator will respond in accordance with ARP1 AD-4/B-3, "S/G C Level Deviation," and implement AP/1/A/5500106, "S/G Feedwater Malfunction." The operator will address Technical Specification 3.3.1, "RTS lnstrumentation," Technical Specification 3.3.2, "ESFAS lnstrumentatlon," and Technical Specification 3.3.3, "PAM lnstrumentation."

Shortly after this, the normal supply breaker for 1ETB will open causing a Blackout signal on Essential 4160V Bus 1ETB. The 1B DG will auto start and re-energize the bus, however, the 1B RN Pump and the 1B1 KC Pump will fail to start and need to be manually started. The operator will implement AP/1/A/5500/07, "Loss of Electrical Power."

Scenario Event Description NRC Scenario 5 During the recovery of 1ETB, Train A Safety Injection will spuriously actuate. The Reactor will fail to trip automatically and the operator will need to trip the Reactor manually. The operator will enter E-O, "Reactor Trip or Safety Injection," and then transition to step 10 of ES-1.1, Safety Injection Termination."

Upon entry into ES-1.1, the operator will stop NI and ND pumps, and restore Normal Letdown in accordance with Generic Enclosure 1, "Establishing Normal Letdown."

The scenario will terminate when normal letdown has been established.

Critical Tasks:

E-O A Manually trip the reactor prior to transition to FR-5.1, "Response to Nuclear Generation/ATW5."

55 (4600/113/E13.6)

Terminate 81 by closing NI-9/10 within 15 minutes of 51 actuation.

Scenario Event Description NRC Scenario 5 SIMULATOR OPERATOR INSTRUCTIONS o Sim. Setup Rod Step On o IC - 120 o RUN o Update Status Board, See Shift Turnover Information Setup OAC Setup ICCM, Turbine Displays, & Trend Recorders.

Check Rod Step Counters agree with rod positions o (XMT) NC015 1NCP-5050, NC Loop Flow OOS Set =0 o (ANN) ADOS-C06 MCB Annunciator AD-8, C-6, "Hotwell Lo Level" in continuous alarm Set = ON o (MALF) IPE001A Auto Reactor Trip fails/manual available (MALF) IPE0018 Set =TRUE o (OVR) MG017A Failure of Main Generator Autosynch Circuit (OVR) MG0178 Set =OFF o Freeze.

o Update Fresh Tech" Spec. log.

o Fill out the NLO's Available section of Shift Turnover Info.

Scenario Event Description NRC Scenario 5 o Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Provide Crew with appropriate handouts (OP/1/A/61 00/003, Enclosure 4.1 marked up through 3.26.6.3 and OP/1/A/6300/001, Enclosure 4.1 marked up through Step 3.12, with Steps 3.13.8, 10, 14 marked NA).

3. Review the Shift Turnover Information with the crew.

4. Direct the crew to Review the Control Boards taking note of present conditions, alarms.

o T-O Begin Familiarization Period Prepare for Synchronization of the Main Generator Power Range Channel Failure Failure of Main Generator Autosynch Circuit NOTE: After the first position is selected and fails, remove the other Override so that the second channel will work.

VCT Level Failure C SG Narrow Range Level Failure Scenario Event Description NRC Scenario 5 0 At direction of (MALF) EPOO98 Blackout on 1ETB/1 B RN Pump & 1B1 KC Pump fails to examiner Auto Start (MALF) RNOO38 (MALF) KC001C Trigger 7 0 At direction of (MALF) ISE001C Spurious SI (Train A) examiner Trigger #9 NOTE: Remove Malfunction at Step 6 of E-O (MALF) IPE001A Auto Reactor Trip fails/manual available (At T=0)

(MALF) IPE0018 Set =TRUE o Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ Page 8 of _5_1---11 Event

Description:

Prepare for Synchronization of the Main Generator Time I Position I Applicant's Actions or Behavior Upon shift turnover, the operator will perform Step 3.13 of Enclosure 4.1, "Startup with Turbine Control in "Operator Auto," of OP/1/A/6300/001, "Turbine Generator Startup/Shutdown." The operator will place the Voltage Regulator in service and attempt to synchronize the Main Generator to the electrical grid.

Booth Operator Instructions: NLO (Bill) is standing by at the Main Generator Voltage Regulator Panel.

Indications Available: NA OP/1/Al6300/001, TURBINE GENERATOR STARTUP/SHUTDOWN ENCLOSURE 4.1, STARTUP WITH TURBINE CONTROL IN "OPERATOR AUTO" RO (Step 3.13) Place Voltage Regulator in service as follows:

(Step 3.13.1) Check Turbine speed greater than 1710 rpm.

(Step 3.13.2) Locally check closed: NOTE: RO will contact NLO (Bill).

Booth Operator: As NLO (Bill) report "Disconnects are CLOSED."

• 1EGB-SC-Q701 (U1 Gen Voltage reg Ch 1 Discon)

• 1EGB-SX-Q702 (U1 Gen Voltage Reg Ch 2 Discon)

(Step 3.13.3) Check PMG voltage 120 - 140 VAC.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ _ Page 9 of 51

--~I Event

Description:

Prepare for Synchronization of the Main Generator Time I Position I Applicant's Actions or Behavior (Step 3.13.4) IF any Voltage Regulator NOTE: RO will contact NLO Alarms are present at Local control Panel. (Bill).

Booth Operator: As NLO (Bill) report "There are NO alarms at local panel."

(Step 3.13.5) Check Voltage Regulator aligned for control Room operation per one of the following:

• OAC Graphic "MAINGEN"

• U1 Gen Voltage Reg Local control Panel

• M102342 (1 Gen Volt Reg in Local Cabinet Control)

RO (Step 3.13.6) Check one of the following:

• M102348 (U1 Gen Voltage Regulator System) is normal OR

• Trouble alarms or faults have been reviewed on the following:

• U1 Gen Voltage Reg Local Control Panel

• U1 Gen Voltage Reg Ch 1 Panel

• U1 Gen Voltage Reg Ch 2 Panel RO (Step 3.13.7) Ensure Voltage Regulator in "MAN".

RO (Step 3.13.8) IF performing Generator / NOTE: This step has been Automatic Voltage Regulator (AVR) testing, identified as NA in procedure HOLD until Generator I AVR personnel are provided.

ready for Operations to continue with Unit 1 Turbine Generator startup.

RO (Step 3.13.9) Ensure Excitation "ON".

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ _ Page 10 of 51

---II Event

Description:

Prepare for Synchronization of the Main Generator Time ~ Position I Applicant's Actions or Behavior RO (Step 3.13.10) IF Generator / AVR personnel NOTE: This step has been are performing post Turbine OPC and identified as NA in procedure Mechanical Overspeed Trip Test turning, provided.

HOLD until notified that Unit 1 Turbine Generator startup may continue.

RO (Step 3.13.11) Check Generator Voltage 22.4 - 23.2 KV.

RO (Step 3.13.12) Check "READY" lit on Voltage Regulator.

RO (Step 13.3.13) IF auto Voltage Regulator operation is desired, perform the following:

.. Ensure Voltage Regulator in "AUTO".

.. Notify SOC that McGuire Unit 1 NOTE: RO will contact SOC.

Generator Voltage Regulator status is As SOC.

now in "AUTO" AND to update this status Booth Operator:

in the EMS System. acknowledge.

RO (Step 3.13.14) IF manual Voltage Regulator operation is desired RO (Step 3.13.15) Depress and hold "SYNC" on either "Generator Breaker 1A" or "Generator Breaker 1B".

RO (Step 3.13.16) Using "Voltage Adjust",

ensure "Station Run Volts" slightly higher than "Generator Incoming Volts".

RO (Step 3.13.17) Release "SYNC".

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ _ Page 11 of 51

---41 Event

Description:

Prepare for Synchronization of the Main Generator Time I Position I Applicant's Actions or Behavior RO (Step 3.13.18) Notify System engineer that NOTE: RO will contact Exciter field has been flashed. WCC/SE.

Booth Operator: As WCC/SE (Jim Allgood) acknowledge.

RO (Step 3.14) Close Generator MODs as follows:

RO (Step 3.14.1) Ensure Generator Frequency greater than or equal to 59.6 Hz.

RO (Step 3.14.2) IF Control Room operation of Generator Breaker MODs is desired, perform the following:

• Close:

• MODs for Generator Breaker 1 A

• MODs for Generator Breaker 1 B

• Dispatch operator to locally check: NOTE: RO will contact NLO (Bill).

Booth Operator: As NLO (Bill) report "MODs 1A and 1B CLOSED, no condensation in IPS Enclosures."

• MODs closed for Generator Breaker 1A

• MODs closed for Generator Breaker 1B

• No condensation in IPB enclosures through windows at MODs RO (Step 3.14.3) IF local operation of MODs is NOTE: This step has been required, perform Enclosure 4.5 (Local identified as NA in procedure Operation of Generator Breaker MODs). provided.

At the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 2 _ _ _ _ Page 12 of _5_1__

u Event

Description:

Power Range Channel Failure Time I Position I Applicant's Actions or Behavior Just prior to attempting to synchronize the Main Generator, Power Range N42 Upper Detector will fail low. The operator will respond in accordance with ARP1AD-2/B-3, "P/R Channel Deviation," and implement AP/1/A/5500/16, "Malfunction of Nuclear Instrumentation." The operator will address Technical Specification 3.3.1, "RTS Instrumentation."

Booth Operator Instructions: Operate Trigger #1 (ENB013C (0>>

Indications Available:

• 1AD-2/B-3, "P/R Channel Deviation."

• PR42 MCB indication low

• AFD MCB indication low

• N42 Drawer indication low

• N42 Upper Detector Current low OP/1/A16100/010C, ANNUNCIATOR RESPONSE FOR PANEL 1AD-2 B-3, P/R CHANNEL DEVIATION RO (IA Step 1) Check rod bottom lights, NOTE: Crew may NOT annunciator, and rod position indication. address ARP, but enter AP16 directly.

SRO I (IA Step 2) IF dropped rod exists, go to RO AP/1/A/55001014 (Rod Control Malfunction).

BOP I (IA Step 3) IF channel in test, place the SRO "Comparator Channel Defeat" switch to the channel in test.

SRO (IA Step 4) IF instrument failure, go to AP/1/A/55001016 (Malfunction of Nuclear Instrum entation).

SRO (SA Step 1) IF desired to have Engineering evaluation as to cause for alarm, freeze the Transient Monitor.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # 2 Page 13 of 51

---

----41 Event

Description:

Power Range Channel Failure Time I Position I Applicant's Actions or Behavior SRO (SA Step 2) IF deviation exists due to instrument drift, notify:

• IAE

• Engineering AP/1/Al5500/16, MALFUNCTION OF NUCLEAR INSTRUMENTATION CASE III, POWER RANGE MALFUNCTION NOTE: Crew will carry out Immediate Actions of AP16, prior to the SRO addressing the AP.

RO (Step 1) Place control rods in manual.

RO (Step 2) Check S/G levels - AT PROGRAMMED LEVEL.

SRO (Step 3) Announce occurrence on paging NOTE: SRO may ask U2 RO system. to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 4) Check P/R channels - ONLY ONE CHANNEL FAILED.

RO (Step 5) Position "PR TO S/G PROGRAM LEVEL CHANNEL DEFEAT" switch to defeat inoperable channel.

RO (Step 6) Secure any power increase in progress.

BOP I (Step 7) Check the following interlocks - IN RO REQURED STATE FOR EXISTING PLANT CONDITIONS:

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 2 _ _ _ _ _ Page 14 of _5_1_-41 Event

Description:

Power Range Channel Failure Time I Position I Applicant's Actions or Behavior

• P-7 Lo Power Rx Trips Blocked

• P-8 Hi Pwr Lo Flo Rx Trip Blocked

• P-10 Nuclear at Power.

BOP (Step 8) Perform the following actions at the "MISCELLANEOUS CONTROL AND INDICATION PANEL" drawer:

• Place the appropriate "ROD STOP BYPASS" switch to the failed channel position.

• Place the "POWER MISMATCH BYPASS" switch to the failed channel position.

BOP (Step 9) Perform the following actions at the "DETECTOR CURRENT COMPARATOR" drawer:

• Place the "UPPER SECTION" switch to the failed channel position.

• Check the "CHANNEL DEFEAT" LIGHT for the upper section - LIT.

• Place the "LOWER SECTION" switch to the failed channel position.

• Check the "CHANEL DEFEAT" light for the lower section - LIT.

BOP (Step 10) Perform the following actions at the "COMPARATOR AND RATE" drawer:

• Place the "COMPARATOR CHANNEL DEFEAT" switch to the failed channel position.

• Check the "COMPARATOR DEFEAT" light - LIT.

BOP (Step 11) Trip bistables of failed channel as follows:

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 2 _ _ _ _ Page 15 of _5_1 11 Event

Description:

Power Range Channel Failure Time I Position I Applicant's Actions or Behavior

• Remove Control Power fuses from NOTE: Three Additional MCB "POWER RANGE A" drawer for failed alarms will come in:

channel.

• 1AD-2/A-1

• 1AD-2/A-3

• 1AD-2/F-3

• IF Power Range Cabinet shows evidence of damage (i.e, visual smoke or abnormal smell), THEN remove Instrument Power fuses from "POWER RANGE B" drawer.

RO I (Step 12) Check the following status lights for BOP the failed channel - LIT:

• "NUC OVERPOWER ROD STOP CH I(II,III,IV) BYP" (1SI-19)

• "P/R HI FLUX LO STPT" (1SI-2)

• "P/R HI FLUX HI STPT" (1SI-2)

• "P/R HI FLUX RATE" (1SI-3).

RO I (Step 13) Check the following annunciator BOP lights - LIT:

• "P/R HI VOLTAGE FAILURE" (1AD-2, F-3)

• "P/R HI FLUX HI STPT ALERT" (1AD-2, A-3)

• "P/R HI FLUX RATE ALERT" (1AD-2, A-1).

BOP (Step 14) Check the following status lights on 1 SI LIT:

• g'P/R LO SETPOINT TRAIN A TRIP BLOCKED"

• "P/R LO SETPOINT TRAIN B TRIP BLOCKED".

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 2 _ _ _ _ _ Page 16 of _5_1_~

Event

Description:

Power Range Channel Failure Time I Position I Applicant's Actions or Behavior RO (Step 15) IF desired to control S/G levels in NOTE: CF Control Valve auto, THEN return affected S/G CF control Bypass Valves in AUTO, CF valves to auto. Control Valves in MANUAL due to power level.

RO (Step 16) Ensure operable P/R channel selected to record on NIS Recorder.

RO (Step 17) Adjust control rods to maintain T-avg at T-ref.

RO (Step 18) WH EN T-avg within 1of of T-ref, NOTE: Control Rods are in AND auto rod control desired, THEN return MANUAL due to plant power control rods to auto. level.

SRO (Step 19) Instruct IAE to trip the following NOTE: SRO may call bistables associated with failed P/R channel WCC/IAE to address.

within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of failure PER IP/1/A/30901014 If so, Booth Instructor (Tripping Inoperable Protection Channels):

acknowledge as WCC/IAE.

• OPDT

• OTDT NOTE: SRO will likely conduct a Focus Brief.

TECHNICAL SPECIFICATION 3.3.1, RTS INSTRUMENTATION SRO 3.3.1 Reactor Trip System (RTS)

Instrumentation Examiner NOTE: Addressing TS takes 3-5 minutes. May want to address after scenario.

SRO LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # 2 Page 17 of 51

---

41 Event

Description:

Power Range Channel Failure Time ~ Position I Applicant's Actions or Behavior SRO APPLCIABILITY: According to Table 3.3.1-1.

SRO ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Enter the Immediately more Condition Functions referenced with one or in Table more 3.3.1-1 for required the channels channel(s).

inoperable.

D. One 0.1.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel channel in inoperable. trip.

AND 0.1.2 Reduce 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> THERMAL POWER to s 750/0 RTP.

OR 0.2.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel in trip.

AND 0.2.2 Perform SR 3.2.4.2.

OR 0.3 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E. One E.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel channel in inoperable. trip.

OR E.2 Be in MODE 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # 2 Page 18 of 51

--...-011 Event

Description:

Power Range Channel Failure Time ~ Position I Applicant's Actions or Behavior

8. One or 8.1 Verify 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> more interlock is channel(s) in required inoperable. state for existing unit conditions.

OR 8.2 Be in MODE 3.

7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> T. One or T.1 Verify 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> more interlock is channels(s) in required inoperable. state for existing unit conditions.

OR T.2 Be in MODE 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 2.

At the discretion of the Lead Examiner move to Event #3.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _3 _ _ _ _ _ Page 19 of 51

--.-.011 Event

Description:

Failure of Main Generator Autosynch Circuit Time I Position I Applicant's Actions or Behavior Following this, when the operator attempts to synchronize the Main Generator the autosynch circuit for the breaker that is attempted to be closed first, will fail. The operator will need to recognize the failure and attempt to close the other breaker in accordance with Step 3.15.4.7.8 of Enclosure 4.1, "Startup with Turbine Control in "Operator Auto," of OP/1/A/6300/001, "Turbine Generator Startup/Shutdown."

Floor Instructor: As OSM, direct SRO to continue with synchronizing Main Generator to the electrical Grid. Report that SOC needs the power as soon as possible.

Booth Operator Instructions: After the first position is selected and fails, remove the other Override (OVR-MG017AlB) so that the second channel will work.

Indications Available: NA OP/1/Al6300/001, TURBINE GENERATOR STARTUP/SHUTDOWN ENCLOSURE 4.1, STARTUP WITH TURBINE CONTROL IN "OPERATOR AUTO" RO (Step 3.15) Synchronize Generator to grid as follows:

RO (Step 3.15.1) Notify SOC (System Operation NOTE: RO will contact SOC.

Center) unit to be paralleled.

Booth Operator: As SOC acknowledge.

RO (Step 3.15.2) Ensure "Valve Position Limit Display" lit.

RO (Step 3.15.3) Lower limit to 17% using "Valve Position Limit Lower".

RO (Step 3.15.4) IF auto sync of generator is desired, perform the following:

• Check Voltage Regulator in "AUTO".

• Depress and hold "SYNC" for breaker to be closed.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 3 _ _ _ _ _ Page 20 of 51

---II Event

Description:

Failure of Main Generator Autosynch Circuit Time I Position I Applicant's Actions or Behavior RO

• Using "Voltage Adjust", ensure "Station Run Voltage" is slightly higher than "Gen Incoming Voltage."

• Adjust Generator speed until Synchroscope hand moves smoothly and slowly in "FAST" direction.

RO

• Release "SYNC".

• Place "Gen Auto/Man Sync Select" to Booth/Floor Instructor:

"Auto 1A" or "Auto 18". Observe Gen Auto/Man Sync Select position, and take following action:

If placed in AUTO 1 A: Delete OVR-MG0178 If placed in AUTO 1B: Delete OVR-MG017A

• IF the selected generator breaker did NOT close immediately, perform the following:

• Depress "Auto Sync" on DEH panel.

• IF selected generator breaker fails to close within 5 minutes, perform Steps 3.15.4.6 - 3.15.4.7 for opposite breaker.

• IF selected generator breaker(s) NOTE: SRO will contact failed to close within 5 minutes, notify WCC/SE.

System Engineer.

Booth Operator: As WCC/SE (Jim Allgood) acknowledge, and recommend trying other Auto Circuit.

• Place "Gen Auto/Man Sync Select" in Man".

RO (Step 3.15.6) WHEN Generator paralleled to grid, load Generator as follows:

• Maintain Pwr Fact to 0.90 - 0.95 Lag using "Voltage Adjust".

• Depress "MW IN".

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # 3 Page 21 of 51 Event

Description:

Failure of Main Generator Autosynch Circuit Time I Position I Applicant's Actions or Behavior

• Ensure lit "Valve Position Limit Display".

• Raise limit to 120% using "Valve Position Limit Raise".

• Check "Demand" and "Reference" windows match actual load.

• Load Turbine to 25 MWE per OP/1/A/6300/001 A (Turbine-Generator Load Change).

RO (Step 3.15.7) Place other Generator Breaker in service as follows:

• Depress and hold "SYNC" for selected breaker.

• WHEN Synchroscope for selected breaker in 12 o'clock position, depress "CLOSE" for selected breaker until "CLSD" light is lit.

• Release "SYNC".

At the discretion of the Lead Examiner move to Event #4.

Appendix D operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 4 _ _ _ _ Page 22 of _5_1--11 Event

Description:

veT Level Failure Time I Position I Applicant's Actions or Behavior At the time that the Main Turbine is stabilized at 25 MWe, VCT Level Transmitter NVLT-5760 will slowly fail to 40% causing a continual Auto Make-up to the VCT. The operator will perform a channel check of the two VCT Level instruments and recognize that actual VCT level is rising and take manual control of the NC System Makeup Controller. If no action is taken, OAC Alarm M1A1104, "U1 VCT Level," will alarm. If still no action is taken, auto makeup will continue indefinitely and 1NV-137 will divert to the Recycle Holdup Tank causing an increase in waste liquid.

Booth Operator Instructions: Operate Trigger #3 (XMT-NV001 (40>>

Indications Available:

• VCT Channel deviation between board indications is 18%

• Auto Makeup occurs (Hear sound of makeup counters)

• OAC Trend VCT level shows prompt drop in VCT (1 NV-5760) with out corresponding indication in other channel.

OAC ALARM M1A1104, U1 VCT LEVEL BOP (Hi-Step 1) Ensure Makeup is secured. NOTE: BOP will take MU Switch to OFF.

BOP (Hi Step 2) Ensure 1NV-137 (NC Filters OTLT 3-way CTRL) is partially diverting letdown flow.

OP/1/Al61 00/01 OG, ANNUNCIATOR RESPONSE FOR PANEL 1AD-6 F-12, AUTO MAKEUP START BLOCKED BOP (IA Step 1) Ensure Boric Acid and total NOTE: The System cannot be makeup flow controllers are set for desired returned to AUTO with a failed flow, then place the "NC System M/U VeT Level instrument.

Controller" switch in "AUTO" and the "NC System Makeup" switch to "START7~.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 4 _ _ _ _ _ Page 23 of _5_1_---41 Event

Description:

veT Level Failure Time I Position I Applicant's Actions or Behavior BOP (IA Step 2) IF automatic makeup control NOTE: SRO should have BOP failure, refer to OP/1/A/6150/009 (Boron refer to OP/1/A/6150/009.

Concentration Control) for controlling makeup flow manually.

At the discretion of the Lead Examiner move to Event #5.

Appendix 0 Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 5 _ _ _ _ Page 24 of _5_1----11 Event

Description:

C SG Narrow Range Level Failure

Time I Position I Applicant's Actions or Behavior Subsequently, the C SG Narrow Range Level transmitter (LCF-5570) will fail low. The operator will respond in accordance with ARP1 AD-4/B-3, "S/G C Level Deviation," and implement AP/1/A/5500/06, "S/G Feedwater Malfunction." The operator will address Technical Specification 3.3.1, "RTS Instrumentation," Technical Specification 3.3.2, "ESFAS Instrumentation," and Technical Specification 3.3.3, "PAM Instrumentation."

Booth Operator Instructions: Operate Trigger #5 (XMT-CF029 (0>>

Indications Available:

• 1AD-4/B-3, "S/G C Level Deviation."

• 1AD-4/F-3, "S/G C Lo-Lo Level Alert."

• C S/G NR Level drops 10

• C S/G CF Control bypass valve opens

• C S/G Feed flow increases OP/1/A161 00/01 OE, ANNUNCIATOR RESPONSE FOR PANEL 1AD-4 B-3, S/G C LEVEL DEVIATION SRO (IA Step 1) IF loss of feedwater, go to NOTE: Crew may NOT AP/1/A/5500/006 (S/G Feedwater address ARP, but enter AP6 Malfunction). directly.

SRO (SA Step 1) Refer to Tech Specs.

AP/1/A15500/06, S/G FEEDWATER MALFUNCTION NOTE: Crew will carry out Immediate Actions of AP6, prior to the SRO addressing the AP.

RO (Step 1) IF CF control valve OR bypass valve has failed, THEN perform the following:

• Place affected valve in manual.

• Restore S/G level to program.

RO (Step 2) IF CF pump speed control has failed, THEN perform the following:

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 5 _ _ _ _ _ Page 25 of 51

---

41 Event

Description:

C SG Narrow Range Level Failure Time I Position I Applicant's Actions or Behavior RO (Step 3) On each S/G, check the following channels -INDICATING THE SAME:

• Feed flow

• Steam flow

• S/G level. NOTE: Channell NR Level has failed low on C SG.

RO (Step 3 RNO) Select an operable channel on NOTE: operator will select the affected S/G(s). Channell! on Steam Flow, Feed Flow and NR level.

RO (Step 4) Check unit status as follows:

• Reactor trip breakers - CLOSED

• Pzr pressure - GREATER THAN P-11 (1955 PSIG).

RO (Step 5) IF AT ANY TIME S/G N/R level approaches 17% OR 83%, THEN perform the following:

• Trip reactor.

• GO TO EP/1/A/5000/E-O (Reactor Trip or Safety Injection).

SRO (Step 6) Announce occurrence on page. NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 7) Check reactor power - GREATER THAN 3%.

RO (Step 8) Check CM/CF - PRESENTLY FEEDING S/Gs.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _5 _ _ _ _ _ Page 26 of 51 Event

Description:

C SG Narrow Range Level Failure Time I Position I Applicant's Actions or Behavior RO (Step 9) Check S/G levels - STABLE OR TRENDING TO PROGRAM LEVEL.

RO (Step 10) Check NC temperatures as follows:

• IF any NC pump on, THEN check NC T-avg - STABLE OR TRENDING TO DESIRED TEMPERATURE.

RO (Step 11) Check all S/G CF control valves - NOTE: The CF Control IN AUTO. Valves are in MANUAL due to plant power level.

RO (Step 11 RNO) WHEN the following NOTE: The CF Control conditions met, THEN place affected CF Valves will remain in MANUAL control valve in automatic: until power level has been raised.

• Automatic control - DESIRED

• Affected S/G level(s) - AT PROGRAM LEVEL

• Selected control channels - INDICATE CORRECTLY ON CHART RECORDER:

• Feed flow

• Steam flow

• S/G level.

RO (Step 12) Check all S/G CF control bypass NOTE: The 1C CF Control valves - IN MANUAL AND FULL OPEN. Bypass Valves is in MANUAL due to malfunction.

RO (Step 12 RNO) WHEN the following conditions met, THEN place affected CF control bypass valve in automatic:

• Automatic control - DESIRED

• Affected S/G level(s) - AT PROGRAM LEVEL

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 5 _ _ _ _ Page 27 of 51

---41 Event

Description:

C SG Narrow Range Level Failure Time I Position I Applicant's Actions or Behavior

• Selected S/G level control channel - NOTE: The 1C CF Control INDICATES CORRECTLY ON CHART Bypass Valve will be returned RECORDER. to AUTO.

RO (Step 13) Check both CF pumps -IN AUTO. NOTE: The CF Pumps are in MANUAL due to plant power level.

RO (Step 13 RNO) Perform the following:

• IF both CF pumps in manual AND it is desired to place CF pump in auto ....

• IF one CF pump in auto AND it is desired NOTE: The CF Pumps will to place second CF pump in auto .... remain in MANUAL until plant power level is higher.

RO (Step 14) Check all CA pumps - OFF.

NOTE: SRO will likely conduct a Focus Brief.

NOTE: SRO may call WCC to address.

If so, Booth Instructor acknowledge as WCC.

TECHNICAL SPECIFICATION 3.3.1, RTS INSTRUMENTATION SRO 3.3.1 Reactor Trip System (RTS) Examiner NOTE: Addressing Instrumentation TS takes 8-10 minutes. May want to address after scenario.

SRO LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

SRO APPLICABILITY: According to Table 3.3.1-1.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _5 _ _ _ _ _ Page 28 of 51

---n Event

Description:

C SG Narrow Range Level Failure Time I Position I Applicant's Actions or Behavior SRO ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Enter the Immediately more Condition Functions referenced with one or in Table more 3.3.1-1 for required the channels channel(s).

inoperable.

E. One E.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel channel in inoperable. trip.

OR E.2 Be in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> MODE 3.

TECHNICAL SPECIFICATION 3.3.2, ESFAS INSTRUMENTATION SRO 3.2.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation SRO LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

SRO APPLICABILITY: According to Table 3.3.2-1.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # 5 Page 29 of 51 Event

Description:

C SG Narrow Range Level Failure Time I Position I Applicant's Actions or Behavior SRO ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Enter the Immediately.

more Condition Functions referenced with one or in Table more 3.3.2-1 for required the channels or channel(s) trains or inoperable. trains(s).

D. One D.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel channel in inoperable. trip.

OR D.2.1 Be in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> MODE 3.

AND D.2.2 Be in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> MODE 4.

J. One J.1 Place 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel channel in inoperable. trip.

OR J.2 Be in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> MODE 3.

TECHNICAL SPECIFICATION 3.3.3, PAM INSTRUMENTATION SRO 3.3.3 Post Accident Monitoring (PAM)

Instrumentation SRO LCO 3.3. The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

SRO APPLICABILITY: MODES 1, 2, and 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # 5 Page 30 of 51

--~I Event

Description:

C SG Narrow Range Level Failure Time I Position I Applicant's Actions or Behavior SRO ACTIONS CONDITION REQUIRED COMPLETION ACTION TIME A. One or A.1 Enter the Immediately.

more Condition Functions referenced with one or in Table more 3.3.3-1 for required the channel.

channels inoperable.

B. One or B.1 Restore 30 days more required Functions channel to with one OPERABLE required status.

channel inoperable.

E. One or E.1 Restore one more channel to Functions OPERABLE with two status.

required channels inoperable.

At the dlscretlonot the Lead Examiner move to Event #6.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _6 _ _ _ _ Page _31_ of _5_1 11 Event

Description:

Blackout on 1ETB/1B RN Pump & 181 KC Pump fails to Auto Start Time I Position I Applicant's Actions or Behavior Shortly after this, the normal supply breaker for 1ETB will open causing a Blackout signal on Essential 4160V Bus 1ETB. The 1B DG will auto start and re-energize the bus, however, the 1B RN Pump and the 1B1 KC Pump will fail to start and need to be manually started. The operator will implement AP/1/A/5500/07, "Loss of Electrical Power."

Booth Operator Instructions: Operate Trigger #7 (EP009B, RN003B, KC001 C)

Indications Available:

• Blackout Seq Actuated Train B - Lit on 1SI-14

• 1B DG Starts

• Train B components start to sequence onto 1ETB AP/1/Al5500/07, LOSS OF ELECTRICAL POWER CASE II, LOSS OF NORMAL POWER TO EITHER 1ETA OR 1ETB BOP (Step 1) Check bus energized and sequencer applying loads.

SRO (Step 2) GO TO Step 33.

BOP (Step 33) Check 1A RN pump - ON. NOTE: The 1A RN Pump is NOT running, and need to be manually started.

BOP (Step 33 RNO) Perform the following:

• Start 1A RN pump.

SRO

• IF 1A RN pump is on, THEN GO TO Step 34.

BOP (Step 34) Check 1B DIG - ON. NOTE: The 1B DIG has automatically started and is powering 1ETB.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 6 _ _ _ _ _ Page ~ of _5_1__

11 Event

Description:

Blackout on 1ETB/1 B RN Pump & 1B1 KC Pump fails to Auto Start Time I Position I Applicant's Actions or Behavior BOP (Step 35) Check 1B RN pump - ON. NOTE: The 1B RN has failed to sequence on, and must be manually started.

BOP (Step 35 RNO) Perform the following:

• Start 1 B RN pump.

SRO

• IF 1B RN pump is on, THEN GO TO Step 36.

SRO * (Step 36a & b) Notify Unit 2 RO to start Floor Instructor: As U2 RO 2A RN pump report "2A RN Pump is runninq."

BOP

• Check any Unit 1 6900V Bus -

ENERGIZED.

BOP (Step 37) Check ND System status:

• ND System -IN RHR MODE AT TIME NOTE: The Unit is NOT in the OF BIO RHR Mode at the time of the BO.

SRO (Step 38 RNO) GO TO Step 38.

SRO (Step 38) Announce occurrence on paging NOTE: SRO may ask U2 RO system. to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 39) Check - SII HAS OCCURRED NOTE: SI has NOT occurred.

DURING THIS EVENT.

SRO (Step 39 RNO) Perform the following:

• Initiate EP/1/A/5000/G-1 (Generic NOTE: The SRO may ask the Enclosures), Enclosure 13 (VC and VA U2 BOP to perform.

System Operation) within 30 minutes of If so, Floor Instructor:

B/O.

Acknowledge as U2 BOP.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 6 _ _ _ _ _ Page ~ of _5_1_-41 Event

Description:

Blackout on 1ETB/1 B RN Pump & 181 KC Pump fails to Auto Start Time I Position I Applicant's Actions or Behavior SRO (Step 40) have available licensed operator NOTE: The SRO may ask the initiate Enclosure 7 (DC Bus Alignment) U2 BOP to perform.

within 30 minutes of B/O.

If so, Floor Instructor:

Acknowledge as U2 BOP.

BOP (Step 41) Check DIG on bus that was blacked out - ON.

BOP (Step 42) Check bus energized and sequencer applying loads.

BOP (Step 43) Check - SII HAS OCCURRED NOTE: SI has NOT occurred.

DURING THIS EVENT.

SRO (Step 43 RNa) GO TO Step 45.

RO (Step 45) Control CA flow:

• Check TD CA pump - ON. NOTE: TD CA Pump is ON.

• Check VI header pressure - GREATER THAN 60 PSIG.

• Control CA flow to maintain SIG N/R levels at program level.

• Check reactor power - GREATER THAN 100/0.

• IF AT ANY TIME CA control valves are NOTE: This is a Continuous throttled closed, THEN have available Action. The SRO will make operator perform the following both board operators aware.

• IF any TD CA pump control valve throttled closed, THEN immediately notify Security that SSF is inoperable.

• Declare associated CA pump inoperable.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _6 _ _ _ _ Page ~ of _5_1---41 Event

Description:

Blackout on 1ETB/1 B RN Pump & 1B1 KC Pump fails to Auto Start Time I Position I Applicant's Actions or Behavior BOP (Step 46) Place recirc valve control switch for running KC pumps in "AUTO":

• 1KC-51A (Train A Recirc 1501)

• 1KC-54B (Train B Recirc 1501).

BOP (Step 47) Place recirc valve control switch for KC pumps that are off to "CLOSE":

• 1KC-51A (Train A Recirc 1501)

• 1KC-54B (Train B Recirc 1501).

BOP (Step 48) Check DIG cooling water aligned as follows:

• 1A DIG - RUNNING. NOTE: The 1A DIG is NOT running.

SRO (Step 48a RNO) GO TO Step 48c.

BOP * (Step 48c & d) 1B DIG - RUNNING.

• 1RN-171B (B DIG Hx Inlet 1501) - OPEN.

OBP (Step 49) check the following status lights on 1SI DARK.

• "ELXA STD-BY BKR CLOSED"

• "ELXB STD-BY BKR CLOSED"

• "ELXC STD-BY BKR CLOSED"

• "ELXD STD-BY BKR CLOSED".

BOP (Step 50) Check 1ETA - ENERGIZED BY DIG.

SRO (Step 50 RNO) GO TO Step 52.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ 6 _ _ _ _ _ Page ~ of _5_1_---41 Event

Description:

Blackout on 1ETB/1 B RN Pump & 1B1 KC Pump fails to Auto Start Time I Position I Applicant's Actions or Behavior BOP (Step 52) Check 1ETB - ENERGIZED BY DIG.

BOP (Step 53) Ensure the following equipment loaded as required:

• 1ELXB Fdr Breaker - CLOSED.

• 1B NV pump - ON.

• EVCB Batt Charger - ON.

• EVCD Batt Charger - ON

• 1ELXD Fdr Breaker - CLOSED.

• 1B1 KC pump - ON. NOTE: The 1B1 KC Pump has failed to sequence on, and must be manually started.

• 1B2 KC pump - ON.

• 1B RN pump-ON.

• 1B CA pump - ONI

• Check SII HAS OCCURRED. NOTE: SI has NOT occurred.

SRO (Step 53j RNO) GO TO Step 54.

At the discretion of the Lead Examiner move to Events #7-8.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 5 Event # _ _ _ _ _ _ Page 7&8 36 N08-1 of

---II 51 Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior During the recovery of 1ETB, Train A Safety Injection will spuriously actuate. The Reactor will fail to trip automatically and the operator will need to trip the Reactor manually. The operator will enter E-O, "Reactor Trip or Safety Injection," and then transition to step 10 of ES-1.1, Safety Injection Termination." Upon entry into ES-1.1, the operator will stop NI and ND pumps, and restore Normal Letdown in accordance with Generic Enclosure 1, "Establishing Normal Letdown." The scenario will terminate when normal letdown has been established.

Booth Operator Instructions: Operate Trigger #9 (ISE001C)

Indications Available:

• Train A Safety Injection actuates.

• Reactor does not trip.

Examiner NOTE:

Mark Time of Train A SI Actuation (To the Minute):

NOTE: Crew will carry out Immediate Actions of E-G, prior to the SRO addressing the EP.

E-O, REACTOR TRIP OR SAFETY INJECTION SRO (Step 1) Monitor Foldout page.

RO (Step '2) Check Reactor Trip: NOTE: Reactor does not trip on SI Actuation as required, and will need to manually tripped.

• All rod bottom lights - LIT

• Reactor trip and bypass breakers -

OPEN

• I/R amps - GOING DOWN.

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 5 Event # Page of N08-1

-7&8---- 37 51

---

41 Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior RO (Step 2 RNO) Perform the following:

• Trip the reactor.

Critical Task: (E-O A) Manually trip the reactor prior to transition to FR-S.1, "Response to Nuclear Generation/ATWS."

BOP (Step 3) Check Turbine Trip:

• All throttle valves - CLOSED.

BOP (Step 4) Check 1ETA and 1ETB-ENERGIZED.

RO / (Step 5) Check if S/I is actuated:

BOP

• "SAFETY INJECTION ACTUATED" status light (1SI-18) - LIT.

• Both'LOCA Sequencer Actuated status lights (1SI-14) - LIT.

BOP (Step 5 RNO) Initiate S/1. NOTE: Train B of SI must be manually initiated.

SRO (Step 6) Announce "Unit 1 Safety Injection". NOTE: SRO may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

Booth Operator Instructions: Remove Malfunction ISE001 C at Step 6 of E-O BOP (Step 7) Check ESF Monitor Light Panel on energized train(s):

• Groups 1,2,5 - DARK.

• Group 3 - LIT.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event #

7&8 Page 38 of 51

---II Event

Description:

Spurious 51/ Auto Reactor Trip fails/manual available Time I Position I , Applicant's Actions or Behavior

• OAC - IN SERVICE.

• Group 4, Rows A through F - LIT AS REQUIRED.

SRO

• GO TO Step 8. Booth Operator: As IAE, Call Control Room and report that the Train A 51 Actuation was caused inadvertently during maintenance.

RO / (Step 8) Check proper CA pump status:

BOP

• MD CA pumps - ON.

• N/R level in at least 3 S/Gs - GREATER THAN 17%.

BOP (Step 9) Check all KC pumps - ON.

BOP (Step 10)Check both RN pumps - ON.

SRO (Step 11) Notify Unit 2 to start 2A RN pump. Floor Instructor: As U2 RO report "2A RN Pump is running."

RO (Step 12) Check all S/G pressures -

GREATER THAN 775 psig.

BOP (Step 13) Check Containment Pressure - NOTE: Containment Pressure HAS REMAINED LESS THAN 3 PSIG. is 0 psig.

BOP (Step 14) Check s/I flow:

• Check "NV PMPS TO COLD LEG NOTE: NV Flow is :::::320 gpm.

FLOW" gauge -INDICATING FLOW.

• Check NC pressures - LESS THAN 1600 PSIG.

Appendix D Operator Action Form ES-D-2 Scenario # 5 Event # Page of 51 Op Test No.: N08-1

-7&8

---

39

--...g Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior BOP (Step 14b RNO) Perform the following:

• Ensure NO pump miniflow valve on running pump(s) open:

• 1NO-68A (1A NO Pump & Hx Mini Flow Isol)

• 1NO-67B (1 B NO Pump & Hx Mini Flow Isol).

• IF valve(s) open on all running NO pumps, THEN GO TO Step 15.

SRO (Step 15) Notify OSM or other SRO to NOTE: SRO may ask OSM to perform EP/1/A/5000/G-1 (Generic address.

Enclosures), Enclosure 22 (OSM actions If so, Floor Instructor Following an S/I) within 10 minutes.

acknowledge as OSM.

RO I (Step 16) Check CA flow:

BOP

• Total CA flow - GREATER THAN 450 GPM.

• Check VI header pressure - GREATER THAN 60 PSIG.

• Check VI header pressure - GREATER THAN 60 PSIG.

• WHEN N/R level in any S/G greater than 11% (32% ACC), THEN control CA flow to maintain N/R levels between 11%

(320/0 ACC) and 500/0.

RO (Step 17) Check NC temperatures:

• IF any NC pump on, THEN check NC NOTE: All NC Pumps will be T-Avg - STABLE OR TRENDING TO ON.

557°F RO (Step 17 RNO) Perform the following based on plant conditions:

Appendix D Operator Action Form ES-D-2 Op Test No.: N08*1 Scenario # 5 Event # 7&8 of 51

--~I Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior

• IF temperature less than 557°F AND NOTE: The SRO may assign going down, THEN attempt to stop the RO to perform this action.

cooldown PER Enclosure 3 If so, RO Examiner follow (Uncontrolled NC System Cooldown).

actions of Enclosure 3.

EP/1/A/5000/E-O REACTOR TRIP OR SAFETY INEJCTION ENCLOSURE 3 UNCONTROLLED NC SYSTEM COOLDOWN RO (Step 1) Check steam dump valves - Examiner NOTE: Follow the CLOSED. actions associated with Enclosure 3 if RO is assigned by SRO to perform.

Ro (Step 1 RNO) Close steam dump valves as follows:

• Place "STEAM DUMP SELECT" in steam pressure mode.

• IF steam dumps still open, THEN place "STM PRESS CONTROLLER" in manual and close.

• IF steam dumps still open, THEN select "OFF RESET" on the following switches:

RO (Step 2) Check all SM PORVs - CLOSED.

RO (Step 3) Check MSR "RESET" light - LIT.

RO (Step 4) Check any NC pump - ON.

RO (Step 5) Check NC T-avg - GOING DOWN.

RO (Step 5 RNO) IF cooldown stopped, THEN exit this enclosure.

E-O, REACTOR TRIP OR SAFETY INJECTION

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ _ Page 7&8 41 of 51 Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior BOP (Step 18) Check Pzr PORV and spray valves:

• All Pzr PORVs - CLOSED.

• Normal Pzr spray valves - CLOSED.

(Step 18b RNO) IF Pzr pressure is less than 2100 PSIG, THEN perform the following:

BOP (Step 19) Check NC subcooling based on NOTE: NC System Subcooling core exit TICs - GREATER THAN OaF. will be 8S-90°F.

RO (Step 20) Check if main steamlines intact:

• All S/G pressure - STABLE OR GOING NOTE: All SG Pressures are UP ==1100psig.

• All S/Gs - PRESSURIZED.

BOP (Step 21) Check if S/G tubes intact: NOTE: All EMF instrumentation reads normal.

• The following secondary EMFs -

NORMAL:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-34(L) (S/G Sample (Lo Range))

• 1EMF-24 (S/G A)

• 1EMF-25 (S/G B)

• 1EMF-26 (S/G C)

• 1EMF-27 (S/G D)

• S/G levels - STABLE OR GOING UP IN A CONTROLLED MANNER.

BOP (Step 22) Check if NC System intact:

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 5 Event # Page of

-7&8 51 N08-1 42

---

---II Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior

., Check containment EMFs - NORMAL: NOTE: All EMF instrumentation reads normal .

., 1EMF-38(L) (Containment Particulate (LR))

., 1EMF-39(L) (Containment Gas (Lo Range))

., 1EMF-40 (Containment Gas (Lo Range))

., 1EMF-9 (Reactor Bldg Incore Inst Rm)

., 1EMF-16 (Containment Refueling Brdg) .

., IF offsite power available, THEN check "ICE COND LOWER INLET DOORS OPEN" alarm (1 AD-9, A-5) - DARK .

., Check containment pressure - LESS THAN 1 PSIG

., Check containment sump level -

NORMAL.

RO I (Step 23) Check SII termination criteria:

BOP

., NC subcooling based on core exit T/Cs-GREATER THAN O°F.

., Secondary heat sink:

., NIR level in at least one SIG -

GREATER THAN 11%

OR

., Total feed flow to SIGs - GREATER THAN 450 gpm .

., NC PRESSURE - stable or going up.

., Pzr level-GREATER THAN 11%.

Bop (Step 24) Reset the following:

., S/I

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ _ Page 7&8 43 of 51

---II Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior

• Sequencers.

BOP (Step 25) Stop all but one NV pump.

BOP (Step 26) Check NC pressure - STABLE OR GOING UP.

BOP (Step 27) Isolate NV S/I flowpath:

• Check NV pumps miniflow valves-OPEN:

• 1NV-150B (NV Pumps Recirculation)

• 1NV..151A (NV Pumps Recirculation).

• Close the following valves:

• 1NI..9A (NC Cold Leg Inj From NV)

• 1NI..10B (NC Cold Leg Inj From NV). Examiner NOTE:

Mark Time of 1NI-9A/1 OB Closure (To the Minute):

Critical Task: (55-4600/113/E13.6) Terminate 51 by closing NI-9/10 within 15 minutes of 51 actuation.

BOP (Step 28) Establish charging:

• Check VI header pressure - GREATER THAN 60 PSIG.

• Throttle 1NV..238 (Charging Line Flow Control) to maintain 6-10 GPM seal injection flow to each NC pump.

• Close 1NV-241 (U1 Seal Water Inj Flow Control).

• Open the following valves:

• 1NV-244A (Charging Line Cont Outside Isol)

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ _ Page 7&8 44 of 51

---n Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior

• 1NV-245B (Charging Line cont Outside Isol).

• IF AT ANY TIME charging flow is NOTE: This is a Continuous required to be controlled in subsequent Action. The SRO will make steps, THEN: both board operators aware.

• Slowly throttle 1NV-241.

• Throttle 1NV-238 while maintaining NC pump seal injection flow.

• Maintain charging flow less than 200 GPM.

BOP (Step 29) Control charging flow as required to maintain stable Pzr level.

BOP (Step 30) IF AT ANY TIME a BIO signal NOTE: This is a Continuous occurs, THEN restart SII equipment Action. The SRO will make previously on. both board operators aware.

BOP (Step 31) Reset the following:

• Phase A Isolation

• Phase B Isolation.

BOP (Step 32) Establish VI to containment:

• Check the following valves - OPEN:

• 1VI-129B (VI Supply to A Cont Ess VI Hdr Outside Isol)

• 1VI-160B (VI Supply to B Cont Ess VI Hdr Outside Isol)

• 1VI-150B (Lwr Cant Non-Ess Cant Outside Isol).

• Check VI header pressure - GREATER THAN 85 PSIG.

SRO (Step 33) Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 5 Event # Page of

-7&8 51 N08-1 45

---

-----41 Event

Description:

Spurious 51/ Auto Reactor Trip fails/manual available Time ~ Position I Applicant's Actions or Behavior SRO (Step 34) WHEN EP/1/A/5000/ES-1.1 (Safety Injection Termination) is implemented in next step, THEN monitor its Foldout page.

SRO (Step 35) GO TO Step 10 of NOTE: The SRO will transition EP/1/A/5000/ES-1.1 (Safety Injection to ES-1.1 Step 10.

Term ination).

ES-1.*1, SAFETY INJECTION TERMINATION BOP (Step 10) Check if NI pumps should be stopped:

• Check NC pressure -

• STABLE OR GOING UP

• GREATER THAN 1600 PSIG.

• Stop NI pumps.

SRO

• GO TO Step 11.

BOP (Step 11) Check if ND pumps should be stopped:

• Check any NO pump - ON.

• Check running NO pumps suction -

ALIGNED TO FWST.

• Stop NO pumps.

RO (Step 12) Check S/I flow not required:

• NC subcooling based on core exit TICs - NOTE: NC System Subcooling GREATER THAN O°F. will be 65-75°F.

BOP

• Pzr level- GREATER THAN 11% (29% NOTE: Pzr Level will be 60-ACC). 900/0

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ _ Page 7&8 46 of 51 Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior RO (Step 13) Check steam dumps as follows:

• Check condenser available:

• "C-9 COND AVAILABLE FOR STEAM DUMP" status light (1SI-18)

- LIT.

• MSIVs on intact S/Gs - OPEN.

• Perform the following to place steam dumps in steam pressure mode:

• Place "STM PRESS CONTROLLER" in manual.

• Adjust "STM PRESS CONTROLLER" output to equal "STEAM DUMP DEMAND" signal.

• Place "STEAM DUMP SELECT" in steam pressure mode.

• Check "P-12 LO-LO TAVG" status light (1SI-18) - DARK.

• Control steam dumps to maintain NC T-Hots - STABLE.

• IF AT ANY TIME "STEAM HEADER NOTE: This is a Continuous PRESSURE" is at 1092 PSIG AND auto Action. The SRO will make control desired, THEN perform the both board operators aware.

following:

• Ensure "STM PRESS CONTROLLER" setpoint at 1092 PSIG (pot setting of 8.4).

• Place "STM PRESS CONTROLER" in auto.

• Ensure steam dumps open as required to control "STEAM HEADER PRESSURE" between 1090 -1110 PSIG.

SRO

• GO TO Step 14.

RO (Step 14) Check NC T-Hots - STABLE.

Appendix D Operator Action Form ES-D-2 Op Test No.: N08-1 Scenario # 5 Event # _ _ _ _ _ _ Page 7&8 47 of 51 Event

Description:

Spurious SII Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior BOP (Step 15) Check letdown can be established:

• Pzr level- GREATER THAN 25% (500/0 ACC).

• Check NO pumps - OFF.

• Open the following:

• 1KC-1A (Trn A Aux Bldg Non Ess Ret Iso I)

• 1KC-2B (Trn B Aux Bldg Non Ess Ret Isol).

• Monitor the following while aligning KC to aux bldg non essential header:

• KC surge tank levels

• KC System flow.

• Place the following in "AUTO" for the operating KC train(s):

• 1KC-51A (Train A Recirc Isol)

• 1KC-54B (Train B Recirc Isol).

• Check 1KC-1A - OPEN.

• Perform the following concurrently:

• Close 1KC-56A (KC to A NO HX)

• As flow goes down, open 1KC-50A (Trn A Aux Bldg Non Ess Sup Isol).

• Check 1KC-2B - OPEN.

• Perform the following concurrently:

• Close 1KC-81 B (KC to B NO HX)

• As flow goes down, open 1KC-53B (Trn B Aux Bldg Non Ess Sup Isol).

• Reset modulating valves using reset buttons on RN control board.

BOP

• Check:

• 1EMF-51 A (Containment Train A (Hi Range)) - LESS THAN 25 R/HR

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # Event # Page of 5

-7&8 51 N08-1 48 Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior

• 1EMF-51 B (Containment Train B (Hi Range)) - LESS THAN 25R/HR.

SRO

• Establish letdown PER EP/1/A/5000/G-1 NOTE: SRO directs BOP to (Generic Enclosures), Enclosure 1 establish normal Letdown.

(Establishing Normal Letdown) while SRO and RO will continue in continuing in procedure.

ES-1.1 EP/1/A15000/G-1, GENERIC ENCLOSURES ENCLOSURE 1, ESTABLISHING NORMAL LETDOWN BOP (Step 1) Ensure 1NV-459 (U1 Variable UD Orifice Outlet flow Cntrl) is closed.

BOP (Step 2) Place 1NV-124 (Letdown Pressure Control) in manual between 10-200/0 open.

BOP (Step 3) Establish cooling to Regenerative Hx by performing the following concurrently:

• Throttle open 1NV-238 (Charging Line Flow Control) to establish at least 65 GPM charging flow.

• Throttle 1NV-241 (U1 Seal Water Inj Flow Control) to establish approximately 8 GPM seal injection flow to each NC pump.

BOP Open the following letdown line isolation valves:

• Open 1NV-7B (Letdown Cant Outside Isol).

• Open 1NV-1A (NC UD lsol To Regen Hx).

• Open 1NV-2A (NC UD Isol To Regen Hx).

• Open 1NV-35A (Variable LID Orifice Outlet Cant Isol).

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 5 Event # Page of

-7&8 51 N08-1 49 Event

Description:

Spurious SI/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior BOP (Step 5) Establish desired letdown flow rate (normally 75 GPM) by completing the following concurrently:

• Slowly throttle open 1NV-459 (U1 Variable UD Orifice Outlet Flow Cntrl) to desired flow rate.

• As letdown pressure rises, adjust 1NV-124 (Letdown Pressure Control) to maintain letdown pressure between 250 PSIG and 350 PSIG.

BOP (Step 6) Do not continue until desired flow rate is established.

BOP (Step 7) Adjust charging flow as desired while maintaining the following:

• NC pump seal injection flow greater than 6GPM

• Regenerative Hx letdown temperature less than 380°F.

BOP (Step 8) Return valves to normal as follows:

• IF pot setting for 1NV-124 (Letdown Pressure Control) is set at approximately 5.8, THEN perform the following:

• Manually adjust 1NV-124 to obtain letdown pressure of 350 PSIG.

• Place 1NV-124 in "AUTO".

• Ensure letdown pressure controlled at 350 PSIG.

• GO TO Step 9.

SRO (Step 9) IF more letdown flow is required, NOTE: Additional Letdown THEN raise flow PER OP/1/A/62001001 A flow will NOT be needed.

(Chemical and Volume Control System Letdown), Enclosure 4.5 (Establishing Maximum Normal Letdown).

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 5 Event # Page of

-7&8 51 N08-1 50

---

--"""'II Event

Description:

Spurious 51/ Auto Reactor Trip fails/manual available Time I Position I Applicant's Actions or Behavior SRO (Step 10) IF desire to swap letdown orifices, NOTE: Additional Letdown THEN swap PER OP/1/N6200/001 A flow will NOT be needed.

(Chemical and Volume Control System Letdown), Enclosure 4.3 (Swapping Letdown Orifices).

SRO (Step 11) Notify Chemistry that normal NOTE: BOP will contact letdown is in service. Chemistry.

Booth Operator: As Chemistry acknowledge.

SRO (Step 12) WHEN time allows, THEN notify NOTE: BOP will contact engineering to document transients on WCC/Engineering.

letdown and charging.

Booth Operator: As WCC/Engineering acknowledge.

At the discretion of the Lead Examiner terminate the exam.

UNIT 1 STATUS:

Power Level: 14% NCS [B] 1606 ppm Pzr [B]: 1610 ppm Xe: Per OAC Power History: Startup in progress Core Burnup: 250 EFPDs CONTROLLING PROCEDURE: OP/1/A/61 00/003, Enclosure 4.1, Controlling Procedure for Unit Operation.

OP/1/A/61 00/001, Enclosure 4.1, Continue with Startup of Turbine Generator starting at Step 3.13 OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:

• Both units had been recently shutdown to Mode 3 due to a Hurricane, and now it has become necessary to restart both units.

• Unit 2 has been restarted and is presently holding at 30% power.

• The plant has limited personnel, however, station management has approved the start-up.

• Unit 1 is at 14% power in accordance with OP/1/A/61 00/003, "Controlling Procedure for Unit Operation," Enclosure 4.1, "Power Increase," and the Main Turbine is operating at 1800 RPM in accordance with Step 3.11 of Enclosure 4.1, "Startup with Turbine Control in "Operator Auto"," of OP/1/A/6300/001, "Turbine Generator Startup/Shutdown."

• It is expected that this shift will complete the startup of the main turbine and synchronize the main generator to the electrical grid.

The following equipment is Out-Of-Service:

• 1NCP-5050, NC Loop B Flow, has failed (Channel has been defeated by IAE).

• MCB Annunciator 1AD-8, C-6, "Hotwell Lo Level," has been in constant alarm over the last hour (IAE is investigating).

• NLO (Bill) is standing by at the Main Generator Voltage Regulator Panel.

• Jim Allgood (SE) is available in the WCC (x4276).

Work Control SROIOffsite Communicator Jim Plant SRO Joe NLO's AVAILABLE Aux Bldg. John Aux Bldg. Chris Turb Bldg. Bob Turb Bldg. Mike 5th Rounds. Carol Extra(s) Bill Ed Wayne Tanya