ML022590644

Draft - Section C Operating

ML022590644
Person / Time
Site:	Millstone
Issue date:	08/12/2002
From:	Wilson M Dominion Nuclear Connecticut
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
05000423/02-301 05000423/02-301
Download: ML022590644 (253)

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{{#Wiki_filter:MILLSTONE POWER STATION 4I, NRC SIMULATOR EXAM GUIDE APPROVAL SHEET Exam

Title:

ATWS with Faulted S/G Revision: 0 ID Number: 2K2 NRC-001 This document is the property of Millstone Power Station, which controls its distribution. Further transfer, copying, and modification of this document are strictly prohibited without the written consent of Millstone Power Station. _2 / 3/ 0 Submitted by: 2D1a302t Technicl Reop er Date Validated by: 6D//7Aa Technical Reviewer Date Approved by: Operation Manager (Optional) Date Approved by: IX Training Supervisor / Date A% selected,, AT-AR" X P01

SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1. Cover Page

2. Table of Contents

3. Exam Overview

4. Evaluation Guide

5. Scenario Initial Conditions Sheet

6. Scenario Validation Checklists

7. Reference and Task Tracking

8. Scenario Attributes Checklist Attachments

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SECTION 3 EXAM OVERVIEW

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Exam Brief:

1. The plant is at 50% power, EOL steady state operations with all control systems in automatic. The "A" PORV is out of service due to an electrical short in the control circuitry.

The crew is directed to hold power at 50% and to Pump the Containment Drains Transfer Tank in accordance with OP 3335A, Reactor Plant Gaseous Drains, section 4.4. After the CDTT has been pumped a partial Loss of RCP B Cooling Water Supply will occur. The following alarms will actuate as their setpoints are reached: RCP B THERMAL BARRIER FLOW LOW (MB4B, 3-4A), RCP B COOLER SPLY PRES LOW (MB4B, 3-4B). The crew will primarily use MB4B, 3-4B to respond to this condition. Thrust bearing temperatures will remain <1950 so a rapid downpower and reactor trip will not be implemented. After the partial Loss of RCP B Cooling Water has been addressed, a Loss of Instrument Bus VIAC-3 will occur. The crew will respond using AOP 3564, Loss of One Protective System Channel. Once the US has referred to Tech Specs (step 6), the next event will occur. The A Main Feed Regulating valve will fail closed over 1 minute. The BOP operator should attempt to take manual control of the valve but that will be ineffective. Once the crew realizes that S/G lo-lo is inevitable they should decide to trip the reactor in anticipation. The reactor trip will not occur automatically, MB4 nor MB7 trip switches will work, and 32N will not be able to be de-energized. The crew will enter FR-S.1, Response to Nuclear Power Generation/ATWS. When attempting to align a boration flowpath the normal charging flow control valve will not open requiring the use of the safety grade boration. At step 6 the PEO will successfully open the reactor breakers locally. When E-0 steps 1-14 are checked, the RO will discover that the SIH (HPSI) components did not actuate and will have to be manually started or aligned [Critical Task]. During the initial ATWS transient a Main Steam Line D Rupture Inside CTMT occurs. MSI Fails to Auto Actuate and will have to be manually actuated by the crew at least by step 13 of FR-S.1 path [Critical Task]. The crew will proceed through FR-S.1 to completion and then transition to E-0 step 15 (SI verification done within FR-S.1) and then to E-2, Faulted Steam Generator Isolation, at E-0 [Critical Task], step 24. Conditions may require performing FR-Z.1. The scenario will end when the crew decides to make the transition to E-1.

2. The SM should classify this event as a Site Area Emergency- Charlie Two due to FR-S.1 being entered directly from E-0 (ES1).

3. Plant/Simulator differences that may affect the scenario are: NONE

4. Duration of Exam: 60 minutes

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 I. Summary: Facility: Millstone 3 PWR: Scenario No: 2K2NRC-001 Op-Test No: 2K2 Examiners: Operators: Initial Conditions: IC-22; 50% power, end of life The "A" PORV is out of service due to an electrical short in the control circuitry Event Malf. Event Event Description No: No. Type

• 1 N(US) Pump the Containment Drains Transfer Tank 2 CC03B C(RO) Partial Loss of RCP B Cooling water Supply 3 ED08C C(ALL) Loss of Instrument Bus VIAC-3 4 FW08A I(BOP) A S/G Feed Reg Valve Failure 5 I/Os 32N M(ALL) ATWS; 32N Fails to De-energize RP09A/B RP10A/B 6 CV18 C(RO) Charging Flow Control Failure 7 RP11E C(RO) SIH Fails to Align on SIS 8 MS01 D M(ALL) Main Steam Line D Rupture Inside CTMT 9 RP08 I(US/ MSI Fails to Auto Actuate I__ I_ BOP) I
• ( N) omal ( R ) eactivity ( I ) nstrument ( C ) omponent ( M) ajor Section 7 Page 1 of 1

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Exam

Title:

ATWS with Faulted SIG ID Number: 2K2 NRC-001 Revision: 0 Assessor: Steve Jackson QUALITATIVE ATTRIBUTES _Y_1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events. _Y_2. The scenario consists mostly of related events. _Y_3. Each event description consists of:

           -       the point in the scenario when it is to be initiated
           -       the malfunctions(s) that are entered to initiate the event
           -       the symptoms/cues that will be visible to the crew
           -       the expected operator actions (by shift position)
           -       the event termination point (if applicable)

_Y_4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. _Y_5. The events are valid with regard to physics and thermodynamics. _Y_6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. _N/A_7. If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. _Y_8. The simulator modeling is not altered. _Y_9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure functional fidelity is maintained while running the scenario. _Y__10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section D.4 of ES301 _Y_11. All individual operator competencies can be evaluated, as verified using form ES-301-6. _Y__12. Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5. (Form submitted with simulator scenarios). _Y__13. Level of difficulty is appropriate to support licensing decisions for each crew position. Section 8 Page 1 of 2

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Lesson

Title:

ATWS ID Number: 2K2 NRC-001 Revision: 0 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.

01. Total Malfunctions (TM) - Include EM's- 5 to 8 required Total: 7 Loss of RCP B Cooling water Supply, Charging Flow Control Failure, MSI Fails to Auto Actuate, Main Steam Line D Rupture Inside CTMT, Loss of Instrument Bus VIAC-3, A S/G Feed Reg Valve Failure, SIH Fails to Align on SIS

02. Malf's after EOP entry (EM's)- 1 to 2 required Total: 2 SIH Fails to Align on SIS, MSI Fails to Auto Actuate,

03. Abnormal Events (AE)-2 to 4 required Total: 3 Loss of RCP B Cooling water Supply, Loss of Instrument Bus VIAC-3, A S/G Feed Reg Valve Failure

04. Major Transients (MT)-1 to 2 required Total: 2 ATWS/32N Fails to De-energize, Main Steam Line D Rupture Inside CTMT

05. EOP's (EU) entered/requiring substantive actions 1 to 2 required Total: 2 E-O, E-2

06. EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to Total: 2 2 required FR-S.1, FR-Z.1

07. Critical Task (CT) - 2 to 3 required Total: 3 E-0-J: Establish flow from at least one SI pump before completion of the check of E-0, steps 1-14 in FR-S. 1.

E-0-P: Manually actuate MSI or close MSIV's before completion of FR-S. 1 step 10. E-2-A: Isolate the faulted SIG before transition out of E-2

08. Approximate Scenario Run Time: 45 to 60 min. (One scenario may Total: 70 min approach 90 minutes)

09. EOP run time: Total: 40 min

10. Technical Specifications are exercised during the scenario. (Y/N)_Y_

NOTES: Reactivity Manipulation: None Section 8 Page 2 of 2

SECTION 4 EVALUATION GUIDE

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 All Control Room Conduct, Operations and Communications shall be in accordance with MP-14-MMM.

      "Review the Simulator Operating Limits(design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

Section 4 Page 1 of 52

SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide. Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:

1. Place the simulator in FREEZE if possible.

2. Announce to the Crew that there is a simulator problem.

3. Request that the Crew leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).

4. Deal with the problem (reboot, call STSB, etc.)

5. After the Instructors believe the simulator is restored to service, the Crew should be told how the exam will continue. If it is possible and felt to be acceptable to the evaluators, the examination can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.

6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.

7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.

Section 4 Page 2 of 52

(( (r SECTION 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Simulator Setup Instructions:

1. HANG Exam Placards on the simulator doors.

2. START the Sun Workstation.

a. IF the Sun Workstation is running THEN go to SIM ACTIVE.

3. PLACE Recorder Power to ON.

4. VERIFY that the current approved training load is loaded.

5. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.

6. RESET to IC 89: TEMP IC 2K2NRC-LOUT-002 (based on IC 22)

7. ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.

8. PLACE Simulator to RUN.

9. RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.

10. ENSURE Simulator fidelity items cleared.

a. CHECK the STEP COUNTERS at correct position for plant conditions.

b. PLACE 5 tiles under the DEMINS IN SERVICE lamacord label on MB6.

c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.

d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.

e. CLEAR DCS alarms on MB7 and BOP console.

f. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT.

Section 4 Page 3 of 52

( ~(( SECTION 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

g. ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.

1. See laminated directions on clipboard in Sim booth.

2. RESET Computer Terminals to At Power displays if 100% power IC.

a. MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F132 (40-120), CHS-L1 12 (40-80), CHS-F121 (40-80), RCS-L461 (40-80)

b. MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL-T412*, (585-588)

c. MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4

d. BOP Console (AY5A), BOP Picture 26, Circ Water

e. STA Console, (AY3), NSSS Picture 15, RCP Seals

13. RESET Rad Monitor Screen to Status Grid.

14. OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report hanging near instructor booth door).

15. IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment OOS."

16. LOCK the Simulator Room front door.

17. HANG a Caution Tag on 3RCS*MV8000A stating, "Caution Tag 3RCS*MV8000A Closed and de-energized IAW Tech Spec 3.4.4, action b" Section 4 Page 4 of 52

( SECTIuN 4 ( Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K2NRC EXAM EQUIPMENT I Ensure CDTT Level Raised (-1000 gallons) to allow pumping during NORMAL Evolution Initial Malfunctions 1/0 (RC) 3RCS*PCV455A A PORV OPEN - OFF 1/0 (RC) 3RCS*PCV455A A PORV GREEN - OFF 1/0 (RC) 3RCS*PCV455A A PORV RED - OFF 1/0 (RC) 3RCS*MV8000A A PORV Block Valve GREEN - FALSE 1/0 (RC) 3RCS*MV8000A A PORV Block Valve RED - FALSE I/O (ED) 1-3NJSACB-BF TRIP - OFF 32N Fails to Trip I/O (ED) 1-3NNSACB-BF TRIP - OFF 32N High Side Fails to Trip MALF RP09A Reactor Fails to Manually Trip from MB4 MALF RP09B Reactor Fails to Manually Trip from MB7 MALF RP10A 'A' Train Reactor Fails to Auto Trip MALF RP1OB 'B' Train Reactor Fails to Auto Trip MALF RP11E Auto Actuation Failure: HPSI MALF CV18 Charging Flow Control Failure 0% BT13 MALF RP08A MSI Train A Fails to Auto Actuate MALF RP08B MSI Train B Fails to Auto Actuate MALF MS01 D Main Steam Line D Rupture Inside CTMT 20% 60 second ramp BT1 Section 4 Page 5 of 52

( SECTiuN 4 Lesson

Title:

ATWS with Faultec ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Event Malfunctions MALF CC03B Loss of RCP B Cooling water Supply 40% ramp 30 seconds RSCU I MALF ED08C Loss of Instrument Bus VIAC-3 RSCU 2 MALF FW08A A S/G FRV Failure 0% ramp 60 seconds RSCU 3 Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew. Section 4 Page 6 of 52

( ( SECTION 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assicn Expected Action Standard Exoected Action Standard T+1 EVENT 1: Pump the Containment Drains Transfer Tank OP3335A Reactor Plant Gaseous Drains, Rev. 7 [Normal Evolution] WDR01 When directed as PEO use Remote to RO IF CDTT is being pumped to the boron OP 3335A open 3DGS-V949. Delay 3 minutes recovery tanks, UNLOCK and OPEN Step 4.4.1 before reporting back. 3DGS-V949, gaseous drains to boron recovery isolation. RO OPEN the following: OP 3335A Step 4.4.2

• 3GSN*CTV105, "N2 TO PRT"
• 3GSN*CV8033, "N2 TO PRT" RO IF CDTT is being pumped to the OP 3335A radioactive gaseous waste degasifier, Step 4.4.3 PEFORM the following:

a. SELECT "DRAINS DEGAS" on the degasifier function selector switch (MB3).

b. Go To step 4.4.4.

Section 4 Page 7 of 52

( t (( SECTION 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO START one containment drains OP 3335A transfer pump (MB1) Step 4.4.4

• 3DGS-PlA, "CTMT DRAINS PPS""A"l
• 3DGS-Pl B, "CTMT DRAINS PPS""B" RO IF the low pressure N2 regulator is OP 3335A bypassed, CYCLE one of the following Step 4.4.5 as necessary to maintain pressure between 16 and 21 psia, as read on DGS-PI29 (MB1).
• 3GSN*CTV105, "N2 TO PRT"
• 3GSN*CV8033, "N2 TO PRT" RO WHEN CDTT level is less than 300 OP 3335A gallons, STOP the containment drains Step 4.4.6 transfer pump (MB1)
• 3DGS-P1A, "CTMT DRAINS PPS "A"
• 3DGS-PlB, "CTMT DRAINS PPS'"'B" Section 4 Page 8 of 52

( K, SECTIuN 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO IF CDTT was being pumped to the OP 3335A radioactive waste degasifier, SELECT Step 4.4.7 "LETDOWN DEGAS" on the degasifier function selector switch (MB3). RO CLOSE 3GSN*CTV105 and OP 3335A 3GSN*CV8033, "N2 TO PRT". Step 4.4.8 RO IF CDTT was being pumped to the OP 3335A boron recovery tanks, CLOSE and Step 4.4.9 LOCK 3DGS-V949, gaseous drains to boron recovery- isolation. T= normal MALIF EVENT 2: Partial Loss of RCP B evolution CC03B Cooling Water Supply complete 40% NOTE: Modify MALF to about 55% ramp 30 after annunciator received and as seconds necessary to maintain RCP bearing temperatures less than 1950 F. ARP P3353.MB4B, 3-4BSRev. 004 US IF a loss of RPCCW has occured, Go OP3353.MB RCP BCOOLER SUPPLY PRES LO To AOP 3561, "Loss of Reactor Plant 4B, 3-4B Component Cooling Water" Step 1 Section 4 Page 9 of 52

I' SECtiuN 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO CHECK the following parameters OP3353.MB (MBI1): 4B, 3-4B

• 3CCP-FI 15B, RPCCW containment Step 2 supply flow, 600 to 1000 gpm
• 3CCP*MOV45B, Train B RPCCW supply containment isolation, open
• 3CCP*AOV179A, Train A RPCCW header division valve, closed
• 3CCP*AOV179B, Train B RPCCW header division valve, closed
• 3CCP*AOV180A, Train A RPCCW header division valve, closed
• 3CCP*AOV180B, Train B RPCCW header division valve, closed Section 4 Page 10 of 52

( SECTION 4 ( Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Exoected Action Standard Stn nd3rrl RO MONITOR the following RCP B thrust OP3353.MB bearing and radial bearing temperature 4B, 3-4B computer points ("RCP Status," NSSS, picture 15) Step 3

• RCS-T480A, RCP B upper thrust bearing
• RCS-T484A, RCP B upper radial bearing
• RCS-T480B, RCP B lower thrust bearing
• RCS-T484B, RCP B lower radial bearing Section 4 Page 11 of 52

( ( SECTION 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Standard T= Step 4 MODIFY NOTE: To Instructor, for this RO IF at any time any RCP B thrust OP3353.MB MALF malfunction, as "valve" increases bearing or radial bearing temperature 4B, 3-44B CC03B severity of malfunction decreases. computer point is greater than 195 0F, PERFORM the following: Step 4 to 55% IF reactor power is greater than P-8 RSCU I (37%) PERFORM the following: Modify, as 1. TRIP the reactor necessary to keep 2. STOP RCP B thrust 3. Go To E-0, "Reactor Trip or Safety bearing Injection" temps less than Refer to AOP 3554, "RCP Trip or 1950 F Stopping an RCP at Power", and REMOVE RCP B from service. Refer to Technical Specifications, and OP3353.MB DETERMINE Limiting Condition for 4B, 3-4B Operation Step 5 T= RCP MALF EVENT 3: Loss of Instrument Bus Tech Specs ED08C VIAC-3 addressed RSCU 2 Section 4 Page 12 of 52

(I ( SECTIuN 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard AOP 3564, Loss of One Protective US Loss of VIAC-1 (2) results in diesel AOP 3564 System Channel, Rev. 8 generator sequencer A(B) being de- Step 1 energized. If an ESF actuation takes CAUTION place during this condition, the following items will not occur automatically. RO Determine Plant Status AOP 3564 Step 1 Check reactor status - TRIPPED AOP 3564 Step la Proceed to Step 2 AOP 3564 Step la RNO CREW Check the Following Control AOP 3564 Systems: Step 2

• Verify rod control - OPERATING NORMALLY IN AUTO
• Verify SG level - OPERATING NORMALLY IN AUTO
• Verify PZR level - OPERATING NORMALLY INAUTO
• Verify PZR pressure - OPERATING NORMALLY IN AUTO Section 4 Page 13 of 52

( ( SECTiuN 4 Lesson

Title:

ATWS with Faulted ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Perform the following: AOP 3564 Step 2 RNO

a. Place the affected controller in MANUAL.

b. Stabilize plant parameters.

c. Defeat the failed channel input.

d. Return the affected controller to AUTO.

RO Verify Normal Letdown - IN SERVICE AOP 3564 Step 3 RO Verify Cold Overpressure Protection AOP 3564 System - BLOCKED Step 4 Block the affected Train of Cold AOP 3564 Overpressure Protection System Step 4 RNO RO Verify VCT Level (3CHS*LT112) AOP 3564 Using Computer Point 3CHS-L 112 - Step 5 CONTROLLING NORMALLY [Tech Specs] US Refer to the Following Technical AOP 3564 Specifications for Applicable Step 6 Actions: Section 4 Page 14 of 52

(' ( SECTION 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

• If in Mode 2 and LESS THAN 10.10 IR amps, 3.3.1 Reactor Trip System Instrumentation:

Action 4 (FU 6.a) Action 8 (FU 17.a)

• 3.3.1 Reactor Trip System Instrumentation Action 8 (FU 17.b) 3.3.2 Action 17, the operable channel
• 3.3.2 ESF Actuation System is placed in the bypass condition Instrumentation:

Action 16 (FU 7.d) Action 17 (FU 2.c & 3.b.3) Action 18 (FU 7.e) Action 20 (FU 8.a & 8.b)*

                                                                               *entry into TIS 3.0.3 required

• If in Mode 5 or 6, 3.3.2 ESF Actuation System Instrumentation Action 26 (FU 3.c)
• If in Modes 4, 5 or 6, 3.4.9.3 Overpressure Protection Systems 3.8.3.1.e Action b, re-energize the AC
• 3.8.3.1 and 3.8.3.2, Onsite Power vital bus within 2 hours or be in HOT Distribution STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

Section 4 Page 15 of 52

( ( SECTION 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard NOTE: If PEO and/or Maintenance are RO Check All Vital 120 VAC Instrument AOP 3564 dispatched to investigate VIAC they will Buses - ENERGIZED Step 6 find it de-energized and Maintenance will find the 150A input fuse blown. Report that they will begin procurement and replacement procedures. (Found on EE-11BA) T= VIAC MALF EVENT 4: Feed Reg Valve Failure Tech Specs FWO08A NOTE: Loss of control at the Feed addressed 0% 60 sec Station will require an anticipatory ramp reactor trip IRSCU 3 T= AOP MALF EVENT 5: ATWS; 32N Fails to 3571, Att. B I/Os 32N De-energize step 4 RP09A/B RP10A/B FR-S.1, Response to Nuclear US

• If RHR is in service, all references EOP 35 Power Generation/ATWS, Rev. 16 to AFW are NOT applicable. FR-S. 1 Step 1
• Immediate Boration (step 4, 5 and NOTE

6) may be performed in parallel with steps 1*, 2*, or 3, provided that efforts to initiate Immediate Boration do not preclude or delay completion of steps 1*, 2*, or 3.

Section 4 Page 16 of 52

( ( SECI ioN 4 Lesson

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify Reactor Trip EOP 35 FR-S. 1 Step 1*

• Check reactor trip and bypass breakers - OPEN
• Check rod bottom lights - LIT
• Check neutron flux - DECREASING RO TRIP the reactor. EOP 35 FR-S.1 Step 1*

RNO IF the reactor will NOT trip, THEN Drive rods in (AUTO or MANUAL). BOP Verify Turbine Trip EOP 35 FR-S. 1 Step 2* Check all turbine stop valves - EOP 35 CLOSED FR-S. 1 Step 2.a BOP Verify AFW Pumps Running EOP 35 FR-S.1 Step 3 Section 4 Page 17 of 52

SEC iiON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

• Check MD pumps - RUNNING START pumps EOP 35 FR-S.1 Step 3 RNO
• Check TD pump - RUNNING, IF NECESSARY OPEN steam supply valves EOP 35 FR-S.1 Step 3 RNO T= t MALF EVENT 6: Charging Flow Control RO Initiate Immediate Boration of RCS EOP 35 FR-reactor trip CV18 Failure S.1 Step4 Check SI - NOT ACTUATED EOP 35 FR-S. 1 Step 4.a Check one charging pump - RUNNING EOP 35 FR-S. 1 Step 4.b START one charging pump. EOP 35 FR-S. I Step 4.b RNO Section 4 Page 18 of 52

SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Align boration path: EOP 35 FR-S.1 Step 4.c

1) START at least one boric acid transfer pump

2) OPEN emergency boration valve (3CHS*MV81 04)

Check normal charging flow path EOP 35 aligned: FR-S. 1 Step 4.d

1. Charging flow control valve - OPEN OR THROTTLED AND CAPABLE OF BEING THROTTLED

2) Charging header loop isolation valve (3CHS*AV8146 or 3CHS*AV8147) - OPEN

3. Charging header isolation valves -

OPEN

• 3CHS*MV8106
• 3CHS*MV8105 Section 4 Page 19 of 52

( (, SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Position valves as required. EOP 35 FR-S.1 Step 4.d RNO NOTE: Proceed To step 5 IF a controllable normal charging flow path can NOT be established, THEN Proceed to step 5. RO Align Safety Grade Boration Path EOP 35 FR-S.1 Step 5 Check busses 34C and 34D - BOTH EOP 35 ENERGIZED FR-S. 1 Step 5.a OPEN charging header flow control EOP 35 valve (3CHS*HCV190A) FR-S.1 Step 5.b open CHARGING HEADER BYPASS EOP 35 ISOLATION (3CHS*MV8116) FR-S. 1 Step 5.c CLOSE charging flow control outlet EOP 35 isolation (3CHS*MV8106) FR-S.1 Step 5.d Section 4 Page 20 of 52

( ( SEC i ION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T= FR-S.1 REMOVE NOTE: Call back as PEO as report Proceed to step 6 EOP 35 step 5 RP09A/B reactor trip breakers open. FR-S. 1 complete RP1OA/B Step 5.e INSERT RP02A/B T= FR-S.1 MALF EVENT 7: Main Steam Line D RO Verify Boration Flow EOP 35 step 6 MS01D, Rupture Inside CTMT FR-S.1 20%, 60 Step 6 second ramp T= Initial MALF EVENT 8: MSI Fails to Auto RP08 Actuate Check PZR pressure - LESS THAN EOP 35 2350 psia FR-S. 1 Step 6.a Check normal charging flow path - EOP 35 ALIGNED FR-S.1 Step 6.b Section 4 Page 21 of 52

(. SE.,iION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Perform the applicable action: EOP 35

• IF Si actuated, THEN Proceed FR-S.1 to step 7. Step 6.b RNO
• IF a safety grade boration flow path is established, THEN

1. Using GA-14, Establish reactor vessel head vent letdown to the PRT.

2. Proceed to step 7.

US Check the Following Has Occurred EOP 35 FR-S.1 Step 7 Verify reactor trip breakers - OPEN EOP 35 FR-S.1 Step 7.a Verify turbine trip EOP 35 FR-S. 1 Step 7.b RO Check If Si Is Actuated EOP 35 FR-S. 1 Step 8 Verify SAFETY INJECTION EOP 35 ACTUATION annunciator (MB4D 1-6 FR-S. 1 or MB2B 5-9) - LIT Step 8.a. Section 4 Page 22 of 52

( i' SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard [Critical Task] Verify steps 1-14 of E-0, Reactor Trip EOP 35 and Safety Injection FR-S.1 Establish flow from at least one SI Step 8.b. pump before completion of the check of E-0, steps 1-14 in FR-S.1. Manually actuate MSI or close MSIV's before completion of FR-S.1 step 13. NOTE: Crew should notice MSI is required and actuate when reviewing Step 10 of E-0. BOP Check AFW Suction Source EOP 35 FR-S.1 Step 9 Check DWST level - LESS THAN EOP 35 80,000 gal FR-S.1 Step 9.a Proceed to step 10 and, EOP 35 FR-S. 1 IF DWST level decreases to LESS Step 9.a, THAN 80,000 gal, RNO THEN Perform step 9.b BOP Check SG Levels EOP 35 FR-S. 1 Step 10 Section 4 Page 23 of 52

( ( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Verify NR level in at least one SG - EOP 35 GREATER THAN 8% (42% ADVERSE FR-S.1 CTMT) Step 10.a Perform the following: EOP 35

1. Verify total feed flow is GREATER Step 10.a THAN 1150 gpm RNO IFthe flow is LESS THAN 1150 gpm THEN START pumps and Align valves as necessary.

2. Maintain total feed flow GREATER THAN 1150 gpm until NR level is GREATER THAN 8% (42%

ADVERSE CTMT) in at least one SG. Control feed flow to maintain NR level EOP 35 between 8% and 50% (42% and 50% FR-S.1 ADVERSE CTMT) Step 10.b High Radiation Area Key and Locked EOP 35 Valve Key are required for FR-S.1 performance of some local actions in Step 11 the following step. NOTE Section 4 Page 24 of 52

( SEC i ION 4 l Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign ExDected Action Standard RO/US/ Verify All Dilution Paths Isolated EOP 35 PEO FR-S.1 Step 11

• Check primary makeup water to blender (3CHS*FCV11 1A) -

CLOSED NOTE: As US request wait 3 minutes and report chemical mix tank outlet

• Locally check chemical mix tank isolation valve (3CHS*V317) - outlet isolation valve (3CHS*V317)

CLOSED and manual dilution valve -CLOSED (3CHS*V305) - CLOSED

• Locally check manual dilution valve (3CHS*V305) - CLOSED
• Check BTRS - OFF AND BYPASSED CREW Check for Reactivity Insertion From EOP 35 Uncontrolled RCS Cooldown. FR-S.1 Step 12
• RCS temperature - DECREASING IN AN UNCONTROLLED MANNER OR
• Any SG pressure - DECREASING IN AN UNCONTROLLED MANNER Section 4 Page 25 of 52

SEC., iON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard [Critical Task] Manually actuate MSI BOP Check MSIVs and MSIV Bypass EOP 35 or close MSIV's before completion of Valves - CLOSED FR-S.1 FR-S.1 step 13. Step 13 CLOSE valves. EOP 35 FR-S. 1 Step 13 RNO BOP Identify Faulted SGs EOP 35 FR-S.1 Step 14 Check pressures in all SGs: EOP 35 FR-S.1 Step 14.a

• ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR
• ANY SG COMPLETELY DEPRESSURIZED US
• At least one SG must be EOP 35 maintained available for RCS FR-S.1 cooldown. Step 15 CAUTION Section 4 Page 26 of 52

Y SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

• If all SGs are faulted, at least 100 gpm feed flow should be maintained to each SG.
• If the TD AFW pump is the only available source for feed flow, a steam supply to the TD AFW pump must be maintained from at least one SG.

BOP Isolate Each Faulted SG EOP 35 FR-S. 1 Step 15

• Isolate main feedline
• Isolate AFW flow
• CLOSE steam supply isolation valve to TD AFW pump
• Verify SG atmospheric dump valve

                                                                           - CLOSED

• Verify SG atmospheric dump bypass valve - CLOSED US/RO Check Core Exit TCs - LESS THAN EOP 35 1200OF FR-S. 1 Step 16 Section 4 Page 27 of 52

( ( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assian ExDected Action Standard Sta ndrrI RO Verify Reactor Subcritical EOP 35 FR-S.1 Step 17

• Check power range channels -

LESS THAN 5%

• Check intermediate range channels

                                                                           - NEGATIVE STARTUP RATE US      Verify No Fuel Damage                       EOP 35 FR-S.1 Step 18 Request Chemistry obtain RCS                EOP 35 samples                                     FR-S.1 Step 18.a Request the ADTS obtain samples             EOP 35 using any means possible.                   FR-S. 1 Step 18.a RNO Using MP-26-EPI-FAP06,                      EOP 35 "Classification and PARs," Evaluate for     FR-S.1 incident classification                     Step 18.b US      Verify Security Has Checked SLCRS           EOP 35 Doors - CLOSED                              FR-S.1 Step 19 Section 4 Page 28 of 52

( ( SEC iION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Request status of SLCRS doors from EOP 35 Security. FR-S.1 Step 19 RNO US Boration shall continue during EOP 35 subsequent actions until adequate FR-S.11 shutdown margin is obtained. Step 20 CAUTION US Go to Procedure and Step in Effect EOP 35 and Initiate Monitoring of the CSF FR-S.1 Status Trees Step 20 E-0, Reactor Trip or Safety Injection, Rev. 21 RO Determine If ADVERSE CTMT E-0, Step 15 Conditions Exist

• Ctmt temperature GREATER THAN 1800 F OR
• Ctmt radiation GREATER THAN 1O5 R/hr CREW DO NOT use ADVERSE CTMT E-0, parameters. Step 15, RNO Section 4 Page 29 of 52

( SEC, iiON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify ECCS Flow E-0, Step 16 Check charging pumps - E-0, Step 16.a FLOW INDICATED RO START pumps and Align valves. E-0, Step 16.a, RNO RO Check RCS pressure - GREATER E-0, THAN 1650 psia (1950 psia Step 16.b ADVERSE CTMT) US Proceed to Step 16.d E-0, Step 16.b, RNO CREW should perform a short brief Proceed to step 17. E-0, and come out of "Master Silence" at Step 16.c the completion of Step 16. Check SI pumps - FLOW INDICATED E-0, Step 16.d START pumps and Align valves. E-0, Step 16.d RNO Check RCS pressure - LESS THAN E-0, 300 psia (500 psia ADVERSE CTMT) Step 16.e Section 4 Page 30 of 52

i SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Standard Proceed to step 17. E-0, Step 16.e RNO Check RHR pumps - FLOW E-0, INDICATED. Step 16.f START pumps and Align valves. E-0, Step 16.f RNO BOP Verify Adequate Heat Sink E-0, Step 17 Check NR level in at least one SG - E-0, GREATER THAN 8% (42% ADVERSE Step 17.a CTMT) US Proceed to Step 17.d. E-0, Step 17.a, RNO BOP Control feed flow to maintain NR level E-0,

                                                                      - BETWEEN 8% and 50% (42% and              Step 17.b 50% ADVERSE CTMT)

US Proceed to Step 18. E-0, Step 17.c BOP Verify Total AFW Flow - GREATER E-0, THAN 530 gpm Step 17.d Section 4 Page 31 of 52

SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Standard BOP START pumps and Align valves as E-0, necessary. Step 17.d, RNO US IF AFW Flow GREATER THAN 530 gpm can NOT be established, THEN Initiate monitoring of CSF Status Trees and Go to FR-H.1, Response to Loss of Secondary Heat Sink. BOP Verify AFW Valve Alignment - E-0, Step 18 PROPER EMERGENCY ALIGNMENT Align valves E-0, Step 18, RNO RO Verify ECCS Valve Alignment - E-0, Step 19 PROPER EMERGENCY ALIGNMENT Align valves E-0, Step 19, RNO US Check Plant Status E-0, Step 20 BOOTH NOTE When asked, REPORT that "all Verify SLCRS doors - CLOSED E-0, INST SLCRS doors indicate closed." Step 20.a Section 4 Page 32 of 52

( SEC jION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US Request Security Close all SLCRS E-0, doors. Step 20.a, RNO RO Check CONTROL BUILDING E-0, ISOLATION annunciator (MB4D 3-6) - Step 20.b LIT RO Check if CBI is required E-0, Step 20.b, RNO RO

• Ctmt pressure GREATER THAN 18 psia OR RO
• Control Building radiation monitor in alarm OR
• SI manually actuated RO IF CBI required, THEN Initiate CBI.

Section 4 Page 33 of 52

( SEC, iON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 RRevision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US IF CBI is NOT required, THEN Proceed to Step 21. RO Verify ESF Group 2 CBI lights - LIT E-0, Step 20.c RO Align HVAC components as necessary E-0, for minimum safety function. Step 20.c, RNO BOP Verify control building purge supply E-0, fan and purge exhaust fan - NOT Step 20.d RUNNING BOP Perform the following: E-0, Step 20.d, RNO

• Stop purge supply fan.
• Stop purge exhaust fan.
• Locally Close instrument air isolations
• 31AS-V725 (CB 47' IRR stairwell)
• 31AS-V726 (CB 47' IRR stairwell)

Section 4 Page 34 of 52

(. SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

• 31AS-V644 (CB 66' west wall)
• Locally Close instrument air isolation valve for 3HVC-AOD134 BOP Control building air bank isolation E-0, valves - OPEN (after 60 seconds) Step 20.e BOP OPEN valves E-0, Step 20.e, RNO BOP IF at least one air bank isolation valve can NOT be opened, THEN Locally throttle Open at least one pair of air bank isolation bypass valves to maintain 0.125 inches water at Control Building AP indicator on VP1.
• 3HVC*V750 and 3HVC*V751
• 3HVC*V758 and 3HVC*V759 BOP STOP kitchen exhaust fan E-0, Step 20.f Section 4 Page 35 of 52

SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assian Expected Action Standard Exoected Action StRnd ni BOOTH NOTE When called, WAIT 3 - 5 min, Then PEO Close and Dog (as applicable) Control E-0, INST REPORT "All Control Building Building pressure boundary doors. Step 20.g pressure boundary doors are Closed and Dogged." RO Check RCS Temperature E-0, Step 21 Verify RCS cold leg WR temperature - E-0, BETWEEN 5500 F and 5600 F Step 21.a US Perform the applicable action: E-0, Step 21.a, RNO

• IF temperature is GREATER THAN 5500F AND 5600F, THEN

1) Dump steam to the condenser, if available OR Dump steam to atmosphere.

US 2) Proceed to Step 22.

• IF the temperature is LESS THAN 5500 THEN Proceed to Step 21 c.

Section 4 Page 36 of 52

( SEC i ION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US Proceed to Step 22 E-0, Step 21.b BOP Maintain total feed flow BETWEEN E-0, 530 and 600 gpm until NR level is Step 21.c GREATER THAN 8% (42% ADVERSE CTMT) in at least one SG BOP CLOSE SG atmospheric dump and E-0, dump bypass valves Step 21.d BOP Check the following valves - CLOSED E-0, Step 21.e

• MSIVs
• MSIV bypass valves US Perform the following: E-0, Step 21.e, RNO BOP 1. Place both condenser steam dump interlock selector switches to OFF.

BOP 2. IF unexpected cooldown continues, THEN CLOSE the MSIVs and MSIV bypass valves. RO Check PZR Valves E-0, Step 22 Section 4 Page 37 of 52

( SEC iiON 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Verify PORVs - CLOSED E-0, Step 22.a RO IF PZR pressure LESS THAN 2350 E-0, psia, THEN CLOSE PORVs. Step 22.a, RNO RO IF any PORV can NOT be closed, THEN CLOSE its block valve. RO IF block valve can NOT be closed, THEN Initiate monitoring of CSF Status Trees and Go to E-1, Loss of Reactor or Secondary Coolant. RO Verify normal PZR spray valves - E-0, CLOSED Step 22.b RO IF PZR pressure LESS THAN 2270 E-0, psia THEN CLOSE valves. Step22.b, RNO RO IF valves can NOT be closed, THEN STOP RCPs 1 and 2 RO Verify PZR safety valves - CLOSED E-0, Step 22.c Section 4 Page 38 of 52

( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Exoected Action Standard US IF PZR pressure decreasing in an E-0, uncontrolled manner, THEN initiate Step 22.c, monitoring of CSF Status Trees and RNO Go to E-1, Loss of Reactor or Secondary Coolant Check PORV block valves - OPEN E-0, Step 22.d OPEN energized block valves. E-0, Step 22.d, RNO CREW To prevent damage to the RCP E-0, seal(s), seal injection flow should be Step 23, maintained to all RCPs. CAUTION RO Check If RCPs Should Be Stopped E-0, Step 23 Verify RCPs - ANY RUNNING E-0, Step 23.a Proceed to step 24. E-0, Step 23.a, RNO. RO Verify RCS pressure - LESS THAN EOP 35 E-1500 psia (1800 psia ADVERSE 0, Step 23.b CTMT) Section 4 Page 39 of 52

f SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian Expected Action Standard Stndird US Proceed to Step 24 E-0, Step 23.b, RNO RO Verify charging or SI pumps - AT E-0, LEAST ONE RUNNING Step 23.c US Proceed to Step 24 E-0, Step 23.c RNO RO STOP all RCPs E-0, Step 23.d BOP/RO Check If SG Secondary Boundaries E-0, Step 24 Are Intact Check pressure in all SGs E-0, Step 24.a

• NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
• NO SG COMPLETELY DEPRESSURIZED US Initiate monitoring of CSF Status E-0, Trees and Go to E-2, Faulted Steam Step 24.a Generator Isolation. RNO Section 4 Page 40 of 52

SEC i ION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard E-2, Faulted Steam Generator Us At least one SG must be maintained E-2 CAUTION Isolation, Rev. 8 available for RCS cooldown. US Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown or sampling is required. US If RWST level decreases to LESS THAN 520,000 gal, Go to ES-1.3, Transfer to Cold Leg Recirculation, to align the ECCS system. BOP Check Main Steam Isolation And E-2, Step 1 US Bypass Valves - CLOSED US Check at least one SG boundary E-2, step 2 intact. RO/ BOP Check pressures in all SGs - AT LEAST E-2, step 2.a ONE STABLE OR INCREASING US Identify Faulted SGS E-2, Step 3 RO/ BOP Check pressure in all SGs E-2, Step 3.a ANY SG PRESS DECREASING IN AN UNCONTROLLED MANNER OR Section 4 Page 41 of 52

II (. SEC i iON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard ANY SG COMPLETELY DEPRESSURIZED High radiation Area Key and Locked E-2, Step 4 Valve Key are required for performance NOTE of some local actions in the following step. [Critical Task] Isolate the faulted RO/BOP Isolate each faulted SG. E-2, step 4 S/G before transition out of E-2 RO/BOP

• Isolate main steam line
• Isolate main feed line
• TRIP TD FW pumps
• Place MD FW pump in PULL-TO-LOCK
• Isolate AFW flow path
• CLOSE steam supply isolation valve to TD AFW pump
• Verify SG atmospheric dump and bypass valves - CLOSED
• CLOSE SG blowdown isolation valve
• CLOSE SG blowdown sample isolation valve
• Verify main steam line drains Section 4 Page 42 of 52

I SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard upstream of MSIVs and TD AFW pump-CLOSED SG A SG B SG C SG D 3DTM*AOV29A 3DTM*AOV29B 3DTM*AOV29C 3DTM*AOV29D 3DTM*AOV61A 3DTM*AOV61 B 3DTM*AOV61C 3DTM*AOV61D 3DTM*AOV63A 3DTM*AOV63B 3DTM*AOV63D 3DTM*AOV64A 3DTM*AOV64B 3DTM*AOV64D RO/ BOP/ Close valve(s) or isolation valve(s). E-2 Step 4 US IF flow path(s) can NOT be isolated, RNO THEN Dispatch an operator to locally Close valve(s) using Attachment A for guidance US Check SG Code Safety Valves Closed. E-2, step 5

• Flow switched (MB5) - NOT LIT BOP
• Locally (MSVB Roof) - BY OBSERVATION PEO BOP Check DWST level - GREATER THAN E-2, step 6 80,000 gallons.

RO Check If SG Tubes Are Intact E-2, step 7 Section 4 Page 43 of 52

( (' SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian Exnected Action Sta~ndrdnr Exnected Atinn 5t2nrI2 rrl RO Verify trend history and alarm status of E-2, step 7.a radiation monitors:

• Main steam line - NORMAL
• Condenser air ejector - NORMAL
• SG blowdown - NORMAL BOP Check steam generator levels - NO SG E-2, step 7.b LEVEL INCREASING IN AN UNCONTROLLED MANNER NOTE: Acknowledge request as RO Align all SGs for activity sample. E-2, step 7.c Chemistry.

1. RESET SG blowdown sample NOTE: sampling is to ensure a isolation primary to secondary leak does not exist in any S/G. 2) OPEN SG blowdown sample isolation valve(s)

WOG BKGD for E-2. SM/ US Request Chemistry provide activity E-2, step 7.d samples using HP coverage CREW Go to E-1, Loss of Reactor or E-2, step 8 Secondary Coolant. Section 4 Page 44 of 52

( I SEC;i ION 4 I. Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assign Expected Action Standard FR-Z.1, Response to CTMT High US/RO Verify CIA (ESF Group 2 Status FR-Z.1, Pressure, Rev. 10 columns 2 Through 10) Step 1 NOTE: If the crew anticipates high RO Initiate CIA OR reposition valves for FR-Z.1, CTMT pressure they may not be minimum safety function. Step 1 directed to perform FR-Z.1 RNO US Verify CIB FR-Z.1, Step 2 RO Check RPCCW Ctmt supply and return FR-Z.1, header isolation valves - CLOSED Step 2.a RO CLOSE valves. FR-Z.1, Step 2.a, RNO RO Check RPCCW pumps - STOPPED FR-Z.1, Step 2.b RO STOP pumps. FR-Z.1, Step 2.b, RNO RO STOP all RCPs FR-Z.1, Step 2.c If ECA-1.1, Loss of Emergency FR-Z.1, Coolant Recirculation, is in progress, Step 3 Ctmt spray should be operated as CAUTION directed in ECA-1.1 rather than steps 3, 4, and 7 Section 4 Page 45 of 52

( (' SECS ION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H. 1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US Verify Quench Spray System FR-Z.1, Operation Step 3 RO Check RWST level - GREATER THAN FR-Z.1, 100,000 gal (annunciator RWST Step 3.a EMPTY QSS PP OFF on MB2A 5-2 not lit) RO Verify quench spray pumps - FR-Z.1, RUNNING Step 3.b [Critical Task] RO START pumps. FR-Z.1, Step3.b, RNO RO Verify quench spray pump discharge FR-Z.1, valves (3QSS*MOV34A and Step 3.c 3QSS*MOV34B) - OPEN [Critical Task] RO OPEN valves. FR-Z.1, Step 3.c, RNO RO Check quench spray system - FLOW FR-Z.1, EXISTS IN AT LEAST ONE TRAIN Step 3.d US Proceed to step 5. FR-Z.1, Step 3.e BOP STOP All Main Circulating Water FR-Z.1, Pumps Step 5 BOP Check Containment Ventilation FR-Z.1, Step 6 Section 4 Page 46 of 52

EVALUATION GUIDE

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

• Verify CAR fans - STOPPED
• Verify CRDM fans - STOPPED BOP STOP fans. FR-Z. 1, Step 6, RNO US Verify Recirculation Spray System FR-Z.1, Operation Step 7 RO Check CDA signal - PRESENT AFTER FR-Z. 1, 11 minutes (annunciator CTMT Step 7.a RECIRC PUMP AUTO START SIGNAL on MB2B 1-8 lit)

US Proceed to step 8 and, WHEN 11 FR-Z.1, minutes have elapsed since CDA Step 7.a, initiation, THEN Perform steps 7b RNO through 7e. RO Verify recirculation spray pumps - FR-Z. 1, RUNNING Step 7.b RO WHEN Ctmt WR sump level is FR-Z.1, GREATER THAN 1.5 feed THEN Step 7.b, START pumps. RNO RO Verify recirculation spray pump suction FR-Z. 1, isolation valves - OPEN Step 7.c RO OPEN valves. FR-Z.1, Step 7.c, RNO Section 4 Page 47 of 52

( (. EVALUATION GUIDE

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instr uctor Information/Activity Assion Expected Actions Standard

                                                           ,As.    - n RO      Verify recirculation spray pump        FR-Z.1, discharge isolation valves - OPEN      Step7.d RO      OPEN valves.                           FR-Z.1, Step 7.d, RNO RO      Verify recirculation spray - FLOW      FR-Z.1, EXISTS IN AT LEAST ONE TRAIN           Step 7.e RO      Verify ESF Status Panel Group 4        FR-Z.1, Lights - LIT                           Step 8 CREW    Operate components as necessary for    FR-Z.1, minimum safety function.               Step 8, RNO US/ BOP Verify Main Steam Line Isolation       FR-Z.1, Step 9

• Check MSIVs and MSIV bypass valves - CLOSED
• Check ESF Status Group 3 lights -

LIT BOP Initiate MSI. FR-Z.1, Step 9, RNO BOP/RO Verify Main Feedwater Isolation FR-Z.1, Step 10

• Verify MD AND TD FW pumps -

TRIPPED Section 4 Page 48 of 52

( ( EVALUA l ION GUIDE

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

• Verify FW isolation trip valves -

CLOSED

• Verify SG feed regulating valves -

CLOSED

• Verify SG feed regulating bypass valves - CLOSED
• At least one SG must be FR-Z.1, maintained available for RCS Step 11, cooldown. CAUTION
• If all SGs are faulted, at least 100 FR-Z. 1, gpm feed flow should be Step 11, maintained to each SG. CAUTION US Check If Auxiliary Feedwater Flow FR-Z.1, Should Continue To All SGs Step 11 BOP/RO Check pressure in all SGs FR-Z. 1, Step 11.a
• NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
• NO SG COMPLETELY DEPRESSURIZED US Check Hydrogen Concentration FR-Z. 1, Step 12 Section 4 Page 49 of 52

I' EVALUAi iON GUIDE

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard PEO Using OP 3313A, "Hydrogen FR-Z.1, Recombiners and Recombiner Building Step 12.a Ventilation," Start the hydrogen monitoring system US Verify hydrogen concentration - LESS FR-Z.1, THAN 5% Step 12.b US Proceed to step 13. FR-Z.1, Step 12.b, RNO Us Notify ADTS of Hydrogen FR-Z. 1, Concentration Inside Containment Step 13 US Periodically Monitor Hydrogen FR-Z.1, Concentration (every 8 hours) Step 14 Us Go to Procedure and Step In Effect FR-Z.1, Step 15 TERMINATE UPON TRANSITION TO E-1, Loss of Reactor or Secondary Coolant. Section 4 Page 50 of 52

SECTION 4 ID Number: 2K2 NRC-001 Revision: 0 EVALUATION GUIDE I.

SUMMARY

The following Critical Tasks are covered in this exam: TASK DESCRIPTION TASK # K/A >I= 3.0 BASIS FOR SELECTION Establish flow from at least E-0-J 007 EA2.02 Failure to manually start at one Si pump before 4.3/4.6 least one intermediate - completion of the check of head ECCS pump under E-0, steps 1-14 in FR-S.1. the postulated conditions constitutes "mis-operation or incorrect crew performance which leads to degraded ECCS capacity." Manually actuate MSI or E-0-P 040 AA2.04 Failure to close the MSIVs close MSIV's before 4.5/4.7 challenges the CSFs completion of FR-S.1 step beyond those irreparably

13. introduced by the postulated conditions and constitutes a "demonstrated inability by the crew to recognize a failure of the auto actuation of an ESF system."

Isolate the faulted S/G E-2-A 040 AA1.04 Failure to isolate a faulted before transition out of E-2 4.34.3 SG that can be isolated causes challenges to CSFs beyond those irreparably introduced by the postulated conditions. Note: r] Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide. Section 4 Page 51 of 52

SECTION 4

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 EVALUATION GUIDE Section 4 Page 52 of 52

SECTION 5 SCENARIO INITIAL CONDITIONS ID Number: 2K2 NRC-001 REwvision: 0 Reactor Power: 50%, steady state Xenon Operating History: 450 days on line RCS Boron: 300 ppm Core Burnup: 18,600 MWD/MTU Condensate Demins: 5 demins in service Evolutions in Progress: NONE Major Equipment OOS: "A" PORV is inoperable due to ain electrical short in the control circuitry. It has been outI of service for 8 hours. Electrical maintenance estimate s that the valve will be returned to service within 24 hotirs. The following Tech Specs are ai pplicable: Tech Spec 3.4.4, action b 3TRM 7.4.1 action a.1 and a.3 fior both the A PORV and the block valve 3RCS*MV8000A Crew Instructions: The unit downpowered in response to a severe weather threat. The next shift will begin the power increase. Maintain the plant at 50% power. Intake conditions are now Green. The crew is directed to Pump the Containment Drains Transfer Tank in accordance with OP 3335A, Reactor Plant Gaseous Drains, section 4.4. Plant/Simulator Differences:

• Real Time and Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.
• Auto-log terminals need to be refreshed after entry is made.
• If not using the speed dial option on the phone system, the operator must dial either #3333 or #3334 to reach the person/department they desire.
• The following PPC programs do not function on the simulator:
• Samarium Follow
• Xenon Follow
• Sequence of Events Section 7 Page 1 of 1

SECTION 6 VALIDATION CHECKLIST

Title:

ATWS with Faulted S/G ID Number: 2K2 NRC-001 Revision: 0 Remote functions: All remote functions contained in the guide are certified. Malfunctions: All malfunctions contained in the guide are certified. Initial Conditions: The initial condition(s) contained in the guide are certified or have been developed from certified IC's in accordance with NSEM-4.02. Simulator Operating Limits: The simulator guide has been evaluated for operating limits and/or anomalous response. Test Run: The scenario contained in the guide has been test run and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected. Examination Scenario Review The dynamic examination review checklist is complete. (This is not required unless the exam will be used as an Annual Exam, then NUREG 1021 requirements apply.) 6/10/02 Technical Reviewer Date Section 7 Page 1 of 1

SECTION 7 REFERENCE AND TASK TRACKING

Title:

ATWS with Faulted SIG ID Number: 2K2 NRC-001 Revision: 0 I.

References:

OP3335A Reactor Plant Gaseous Drains ARP MB4B, 3-4B RCP B Cooler Supply Pressure Low AOP*3564 Loss of One Protective System Channel EOP*E-0 Reactor Trip or Safety Injection EOP*E-2 Faulted Steam Generator Isolation EOP*FR-S. 1 Response to Nuclear Power Generation / ATWS EOP*ERGEXE Westinghouse Owners Group Executive Document EOP* Step DOC MP3 step deviation Document EOP*ERGHP Westinghouse Owners Group Background Document FAP06*01 Event Assessment, Classification and Reportability NUREG*1021 rev 8 Examiners Standards Section 7 Page 1 of 1

MILLSTONE POWER STATION A NRC SIMULATOR EXAM GUIDE APPROVAL SHEET Exam

Title:

SGTR WITHOUT PZR PRESSURE CONTROL Revision: 0 ID Number: 2K2 NRC-002 This document is the property of Millstone Power Station, which controls its distribution. Further transfer, copying, and modification of this document are strictly prohibited without the written consent of Millstone Power Station. A A. A, ffl'K AM,

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SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1. Cover Page

2. Table of Contents

3. Exam Overview

4. Evaluation Guide

5. Scenario Initial Conditions Sheet

6. Scenario Validation Checklists

7. Reference and Task Tracking

8. Scenario Attributes Checklist Attachments

    -    NUTIMS Module Report A
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SECTION 3 EXAM OVERVIEW

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Exam Brief:

1. The plant is at 100% power, EOL steady state operations with all control systems in automatic. The "A" PORV is out of service due to an electrical short in the control circuitry.

The crew is initially directed to reduce CTMT pressure to 13.80 psia using OP 3313E, Containment Vacuum, section 4.2. After the evolution has commenced, the Digital Rod Position Indication system will experience a Data A failure on rod D12. AOP 3552, Malfunction of the Rod Drive System with Attachment C will direct the crew's actions. Tech Specs should be reviewed for this malfunction. After Tech Specs have been reviewed, a tube leak will occur on the "C" S/G. A small increase in charging flow and radiation alarms on ARC21, Air Ejector Rad Monitor, and N-16 alarms will indicate the problem to the crew. The crew may use the guidance in AOP 3573, Radiation Monitor Response, or may go directly to AOP 3555, Reactor Coolant System Leak. AOP 3555 and the N-16 ARP will direct the crew to AOP 3576, Steam Generator Tube Leak. Conditions are present to require a power reduction to be in MODE 3 within 6 hours (AOP 3576 step 9.j). When the decision to reduce power has been made a Rod Bank CB-D Continuous Rod Insertion will occur. The crew should place the control rod bank SEL switch in MAN and when this does not stop rod motion, trip the reactor and go to E-0, Reactor Trip or Safety Injection. At the time of the reactor trip the S/G leak will worsen into a SGTR [Critical Task - 2: Isolate Steam and Isolate Feed] and a loss of Offsite power will occur. The EDGs will both start and provide power to the emergency buses but offsite power will not return during the scenario. The B Service Water pump will trip at the reactor trip and the D SWP will not automatically start. Manual action will be required to start the D Service Water pump [Critical Task]. The crew should proceed through E-0 and transition to E-3, Steam Generator Tube Rupture. At step 3.i of E-3 the "C" MSIV will not close and the RNO will be implemented. Time compression techniques are used to complete Attachment A referenced in the step 3.1. At step 18 of E-3 the crew will be unable to depressurize the RCS due to one PORV out of service (initial condition), one PORV failing to open, and auxiliary spray unavailable due to the CTMT Instrument Header isolation valve, 31AS*MV72, failing to open. This will require the crew to transition to ECA-3.3, SGTR Without Pressure Control. The scenario will end when the crew has completed step 8 of ECA-3.3.

2. The SM should classify this event as a Alert - Charlie One due to Loss of RCS Barrier (RCB4).

3. Plant/Simulator differences that may affect the scenario are: NONE

4. Duration of Exam: 60 minutes

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0

1. Summary:

Facility: Millstone 3 PWR: Scenario No: 2K2NRC-002 Op-Test No: 2K2 Examiners: Operators:_ Initial Conditions: IC-21; 100% power, end of life The "A" PORV is out of service due to an electrical short in the control circuitry Event Malf. Event Event Description No: No. Type

• I N(ALL) Reduce CTMT Pressure 2 RD10- C(RO) Control Rod Position Data A Failure 59 3 SG03C C(ALL) Steam Generator "C" Tube Leak 4 RD021 C(RO) Rod Bank CB-D Continuous Rod Insertion 5 SG01C M(ALL) Steam Generator "C" Tube Rupture ED01 Loss of Offsite Power 6 SWO1 B C(RO) B SWP Trips SW02D D SWP Fails to Auto Start 7 MS12C C(BOP) MSIV on Ruptured S/G Fails to Close 8 I/Os: M(ALL) Inability to De-pressurize RCS PCV455 PCV456 IAS*V72
• ( N ) ormal ( R ) eactivity ( I ) nstrument ( C ) omponent ( M) ajor Section 7 Page 1 of 1

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Exam

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Assessor: Steve Jackson QUALITATIVE ATTRIBUTES _Y_1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events. _Y_2. The scenario consists mostly of related events. _Y_3. Each event description consists of:

            -       the  point in the scenario when it is to be initiated
            -       the  malfunctions(s) that are entered to initiate the event
            -       the  symptoms/cues that will be visible to the crew
            -       the  expected operator actions (by shift position)
            -       the  event termination point (ifapplicable)

Y 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. _Y_5. The events are valid with regard to physics and thermodynamics. _Y_6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. Y 7. If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. _Y_8. The simulator modeling is not altered. _Y_9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure functional fidelity is maintained while running the scenario. __Y10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered IAW Section D.4 of ES301 _Y_11. All individual operator competencies can be evaluated, as verified using form ES-301-6. _Y_12. Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5. (Form submitted with simulator scenarios). _Y_13. Level of difficulty is appropriate to support licensing decisions for each crew position. Section 8 Page 1 of 2

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Lesson

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.

01. Total Malfunctions (TM) - Include EM's- 5 to 8 required Total: 8 PORV failed closed, CTMT IAS valve will not open, S/G Tube Leak / Rupture, DPRI Data A Failure, Continuous Rod Insertion, Service Water Pumps Fail to Auto Start, Loss of Offsite Power, MSIV Fails Closed

02. Malfs after EOP entry (EM's)- 1 to 2 required Total: 2 PORV failed closed, MSIV Fails Closed

03. Abnormal Events (AE)-2 to 4 required Total: 4 Service Water Pumps Fail to Auto Start, S/G Tube Leak, DPRI Data A Failure, Continuous Rod Insertion

04. Major Transients (MT)-1 to 2 required Total: 2 S/G Tube Rupture / Loss of Offsite Power

05. EOP's (EU) entered/requiring substantive actions 1 to 2 required Total: 2 E-0, E-3

06. EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to Total: 1 2 required ECA-3.3

07. Critical Task (CT) - 2 to 3 required Total: 3 E-3-A: Isolate feedwater flow to and steam flow from ruptured S/G before a transition to ECA-3.1 occurs at step 3 of E-3. (MSIV fails)

E-3-C: Identify and Isolate ruptured S/G before narrow range level reaches 29%. ECA-O.O--F: Manually start the B Train Service Water Pump before transitioning from E-0.

08. Approximate Scenario Run Time: 45 to 60 min. (One scenario may Total: 60 min approach 90 minutes)

09. EOP run time: Total: 30 min

10. Technical Specifications are exercised during the scenario. (Y/N)_Y_

NOTES: Reactivity Manipulation: None Section 8 Page 2 of 2

SECTION 4 EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 All Control Room Conduct. Operations and Communications shall be in accordance with MP-14-MMM.

      "Review the Simulator Operating Limits(design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

Section 4 Page 1 of 61

SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide. Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:

1. Place the simulator in FREEZE if possible.

2. Announce to the Crew that there is a simulator problem.

3. Request that the Crew leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).

4. Deal with the problem (reboot, call STSB, etc.)

5. After the Instructors believe the simulator is restored to service, the Crew should be told how the exam will continue. If it is possible and felt to be acceptable to the evaluators, the examination can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.

6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.

7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.

Section 4 Page 2 of 61

EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Simulator Setup Instructions:

1. HANG Exam Placards on the simulator doors.

2. START the Sun Workstation.

a. IF the Sun Workstation is running THEN go to SIM ACTIVE.

3. PLACE Recorder Power to ON.

4. VERIFY that the current approved training load is loaded.

5. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.

6. RESET to IC 90: TEMP IC 2K2NRC-LOUT-002 (based on IC 21)

7. ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.

8. PLACE Simulator to RUN.

9. ADJUST MWt using Turbine Load Set to 3411, (+)0, (-)3 IF using 100% power IC.

10. RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT' and "F6" simultaneously.

11. ENSURE Simulator fidelity items cleared.

a. CHECK the STEP COUNTERS at correct position for plant conditions.

b. PLACE 7 tiles under the DEMINS IN SERVICE lamacord label on MB6.

c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.

d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.

e. CLEAR DCS alarms on MB7 and BOP console.

f. VERIFY annunciator, "COMPUTER FAILURE' (MB4C, 1-1 1), is NOT LIT.

Section 4 Page 3 of 61

( ( ( EVALUAI ION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

g. ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.

1) See laminated directions on clipboard in Sim booth.

12. RESET Computer Terminals to At Power displays if 100% power IC.

a. MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F132 (40-120), CHS-L1 12 (40-80), CHS-F121 (40-80), RCS-L461 (40-80)

b. MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL-T412*, (585-588)

c. MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4

d. BOP Console (AY5A), BOP Picture 26, Circ Water

e. STA Console, (AY3), NSSS Picture 15, RCP Seals

13. RESET Rad Monitor Screen to Status Grid.

14. OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report hanging near instructor booth door).

15. IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment OOS."

16. LOCK the Simulator Room front door.

17. HANG a Caution Tag on 3RCS*MV8000A stating, "Caution Tag 3RCS*MV8000A Closed and de-energized IAW Tech Spec 3.4.4, action b"

18. HANG DRPI Console picture/diagram (A+B switch position) on Main Board Door directly behind MB4.

19. IF Necessary, insert correct page 18 & 19 of 39 of E-3 (E-3, step 17)

Section 4 Page 4 of 61

( EVALUAN iON GUIDE (

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K2NRC EXAM EQUIPMENT Initial Malfunctions 1/0 (RC) 3RCS*PCV455A A PORV OPEN - FALSE 1/0 (RC) 3RCS*PCV455A A PORV GREEN - FALSE 1/0 (RC) 3RCS*PCV455A A PORV RED- FALSE 1/0 (RC) 3RCS*PCV456 B PORV OPEN - FALSE 1/0 (RC) 3RCS*MV8000 A PORV Block Valve GREEN - FALSE 1/0 (RC) 3RCS*MV8000 A PORV Block Valve RED - FALSE MALF SG01C Steam Generator "C" Tube Rupture 50% 30 second ramp BT1 MALF ED01 Loss of Offsite Power BT1 I/O (IA) 31AS*MOV72 IAS CTMT Isolation OPEN - FALSE BT1 MALF MS12C MSIV "C" Stuck Open MALF SWO1 D Service Water Pump D Trips BT1 MALF SW02B Service Water Pump B Fails to Auto Start Section 4 Page 5 of 61

( ( EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Fynzreted Anftinns .Qftnnnrirrl 5tn rIrA Event Malfunctions MALF RD1 0-59 Control Rod Position Failure Data A - Rod D12 RSCU I MALF SG03C Steam Generator "C" Tube Leak 100% (46 gpm) 60 second ramp RSCU 2 MALF RD021 (eye) Rod Bank CB-D Continuous Rod Insertion RSCU 3 Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew. Section 4 Page 6 of 61

EVALUATION GUIDE (

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Standard T+1 EVENT 1: Reduce CTMT Pressure OP3313E CTMT Vacuum, Rev. 8 US Do not reduce containment pressure below OP331 3E 13.75 psia if a CTMT entry is anticipated Step 4.2.1 CAUTION US One CTMT vacuum pump is operated OP331 3E periodically to maintain 3LMS*PI24A and Step 4.2.1 3LMS*PI24B containment pressure 13.7 to NOTE 13.9 psia, (MB2) RO IF using 3CVS-P1A, containment vacuum OP331 3E pump A, PERFORM the following: Step 4.2.1 RO OPEN 3CVS*CTV20A, "CTMT VAC PP" OP331 3E (MBI) Step 4.2.1.a RO OPEN 3CVS*CTV21 A, "CTMT VAC PP" OP331 3E (MB1) Step 4.2.1.b RO START 3CVS*PlA, "CTMT VAC PP'S" OP331 3E "1A" (MB2) Step 4.2.1.c T= normal MALF EVENT 2: Control Rod Position RO evolution RD1 0-59 Failure Data A - Rod D12 commenced RSCU #1 AOP 3552 Rev. 3 CREW Stabilize Plant Conditions AOP 3552 MALFUNCTION OF THE ROD Step 1 DRIVE SYSTEM Section 4 Page 7 of 61

( ( EVALUAI iON GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Place control rod bank SEL switch in MAN AOP 3552 Step 1.a RO Verify - NO RODS MOVING AOP 3552 Step 1.b CREW Stop any power increase or decrease AOP 3552 evolutions in progress. Step 1.c US Verify Tavg - Tref deviation - LESS THAN AOP 3552 OR EQUAL TO 1.50F Step 1.d US Verify TURB LOAD REJECTION ARM C-7 AOP 3552 (MB4D 6-6) annunciator - NOT LIT Step 1.e Borate or Dilute as necessary to maintain AOP 3552 Tavg within 1.50F of Tref Step 1.f US Check No Rod Dropped AOP 3552 Step 2 US Verify RPI URGENT FAILURE (MB4C 4- AOP 3552

10) annunciator - NOT LIT Step 2.a RO Check rod bottom lights - NONE LIT AOP 3552 Step 2.b US Check No Rod Position Indication AOP 3552 Malfunctions Step 3 Verify DRPI power available AOP 3552 Step 3.a

• Any DRPI display light lit Section 4 Page 8 of 61

( ( EVALUAI iUN GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Verify status of following annunciators: AOP 3552 Step 3.b NOTE: Annunciator IS LIT

• RPI NON URGENT FAILURE (MB4C 3-10) annunciator - NOT LIT
• RPI URGENT FAILURE (MB4C 4-

10) annunciator - NOT LIT NOTE: US will most likely US Determine rod position indication AOP 3552 transition to the Attachment at this malfunction using Attachment C. Step 3, RNO step Verify status of DRPI display alarms: AOP 3552 Step 3.c

• URGENT ALARM - NOT FLASHING NOTE: DATA A IS Flashing
• DATA A FAILURE - NOT FLASHING
• DATA B FAILURE - NOT FLASHING
• Rod GW - NONE FLASHING
• CENTRAL CONTROL FAILURE lights - NONE LIT US Determine rod position indication AOP 3552 malfunction using Attachment C. Step 3, RNO Section 4 Page 9 of 61

f EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Exoected Actions Standard AOP 3552, ATTACHMENT C Check DRPI Power Supply AOP 3552 Att C Step 1 RO Verify DRPI display lights - NONE LIT AOP 3552 Aft C Step 1.a US Proceed to Step 2. AOP 3552 Att C Step 1.a, RNO RO A DRPI URGENT ALARM indicates one of AOP 3552 the following: Attachment C Step 2, Note

• Error in both data A AND data B from detector/encoder cards.
• Codes from data A and data B differ by GREATER THAN 1 bit
• The binary sum of data A and data B data exceeds 38.

RO Check For DRPI Urgent Alarm AOP 3552 Att C Step 2 Verify DRPI display URGENT ALARM AOP 3552 Att lights - FLASHING C Step 2.a US Proceed to NOTE prior to Step 3 AOP 3552 AttC Step 2.a, RNO Section 4 Page 10 of 61

( ( EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Standard US

• Loss of Data A will result in DRPI AOP 3552 Att half-accuracy of +10 and -4 steps C Step 3, for affected rods. Note US
• Loss of Data B will result in DRPI AOP 3552 Att half-accuracy of +4 and -10 steps C Step 3, for affected rods. Note US Check For DRPI Non-Urgent Alarm AOP 3552 Att C Step 3 RO Verify RPI NON URGENT FAILURE AOP 3552 Att (MB4C 3-10) annunciator - LIT C Step 3.a RO Verify DRPI Display DATA A FAILURE OR AOP 3552 Att DATA B FAILURE lights - FLASHING C Step 3.b NOTE: If asked or if board RO Verify ACCURACY MODE selector switch AOP 3552 Att operator is sent to DRPI cabinet, (back of DRPI cabinet) - A + B POSITION C Step 3.c "ACCURACY MODE switch is in A+Byl RO Identify affected rod(s) as follows: AOP 3552 Att C Step 3.d
• General Warning (GW) light flashing RO Verify affected rod(s) indicates within +/- 12 AOP 3552 Att steps of associated group Step counter C Step 3.e demand height Section 4 Page 11 of 61

( EVALUAI iON GUIDE (

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard NOTE: When requested RO Perform the applicable action: AOP 3552 Aft acknowledge direction and after 1 C Step 3.e, minute REPORT that the

• IF DRPI display DATA A FAILURE RNO ACCURACY MODE switch is in B lights flashing, THEN ONLY position 1) Place ACCURACY MODE selector switch (back of DRPI cabinet) in B ONLY position.

2) Proceed to Step 3.g RO Verify affected rod(s) indicated within +/- 12 AOP 3552 Att steps of associated group Step counter C Step 3.g demand height NOTE: Proceed to Event 3 Notify I & C AOP 3552 Att C Step 3.h US A Central Control Card failure does not AOP 3552 Att impair system operation since the three C Step 4, cards are redundant, handling both data A Note and data B.

US Check For Central Control Card Failure AOP 3552 AUt C Step 4 RO Verify DRPI display any CENTRAL AOP 3552 Att CONTROL FAILURE 1 2 3 light - LIT C Step 4.a US Proceed to NOTE prior to Step 5. AOP 3552 AUt C Step 4.a, RNO Section 4 Page 12 of 61

EVALUkI iON GUIDE (

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US In "half accuracy" operation, the affected AOP 3552 Att rod position will be indicated by every other C Step 5, LED as the rod is raised or lowered. Note US Perform Follow-up actions AOP 3552 Aft C Step 5 T= MALF EVENT 3: Steam Generator "C" complete SG03C Tube Leak step 3 of 100% NOTE: Crew can enter AOP 3573, AOP AOP 3555 (pg. 14), orAOP 3576 3552, Att. (pg. 15) based on MALF C indications. AOP 3573, Radiation Monitor US If alarms are actuated on both area and AOP 3573, Alarm Response, Rev. 12 process monitors, the applicable steps in Step 1, this procedure for each alarm may be NOTE performed concurrently. RO Check Initiating Monitor - AN AREA AOP 3573, MONITOR Step 1 US Proceed to step 3. AOP 3573, Step 1 RNO US Identify Affected Process Using AOP 3573, Attachment A Step 3 RO Check initiating process monitor - IN AOP 3573, ALARM Step 3.a Section 4 Page 13 of 61

EVALUATION GUIDE (

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign ExDected Actions Standa~qrd Stndrd RO Verify automatic actuations stated in AOP 3573, Attachment A - OCCURRED Step)3.b Monitor Sample Stream/Possible Automatic/ Subsequent Actions ARC21-1 Condenser air ejector discharge to Monitor radioactive gaseous waste. radiation monitors Possible indication of primary to MSS75 - secondary leakage. MSS79 and SSR08 for possible 10 to 20 leak. Take appropriate action using AOP 3555, Reactor Coolant __ Leak. AOP 3555, Reactor Coolant RO Check PZR Level - DECREASING AOP 3555 System Leak, Rev. 14 Step 1 Proceed to NOTE prior to step 7 AOP 3555 Step 1 RNO Section 4 Page 14 of 61

( I ( EVALUATION GUIDE

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions  ; Standard I Standard CREW Steps 7 through 17 may be performed in AOP 3555 any order. Step 7, NOTE US Determine Leak Rate Using One Or AOP 3555 More Of the Following: Step 7

• Computer program 3J3
• Inventory balance
• VCT level trend US Check If SG Tubes Are Intact AOP 3555 Step 8 US Verify trend history and alarm status of AOP 3555 radiation monitors: Step 8.a
• Main steamline - NORMAL
• Condenser air ejector - NORMAL
• SG blowdown - NORMAL RO Go to AOP 3576, Steam Generator Tube AOP 3555 Leak. Step 8 RNO AOP 3576: Steam Generator US Foldout Page must be open. 3576 Step 1 Tube Leak, Rev. 001 NOTE RO Verify PZR Level 3576 Step 1 Check PZR Level - DECREASING 3576 Step 1.a Section 4 Page 15 of 61

    !'                                                                                                                I' EVALUAI ION GUIDE

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Proceed to step 2. 3576 Step 1.a RNO US Notify Chemistry 3576 Step 2 US Request Chemistry perform SP 3861, 3576 "Primary to Secondary Leak Rate Step 2.a Determination," to:

1. Determine the presence of primary to secondary leakage.

2. Determine the leak rate.

3. Identify the leaking SG.

Note: There are 2/5 conditions US SG tube leakage can be interpreted as 3576 Step 3 which satisfies the step action. "verified" when any two of the bulleted NOTE Crew should proceed substeps of step 3 are satisfied. US/RO Verify Primary To Secondary Leakage 3576 Step 3 Note: This condition exists

• Check trend history and alarm status of 3576 Step 3 condenser air ejector radiation monitor

                                                                             - NOT NORMAL

• Check trend history and alarm status of steam generator blowdown radiation monitor - NOT NORMAL Section 4 Page 16 of 61

EVALUAi iON GUIDE (

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assign Expected Actions Standard Note: This condition exists

• Check trend history and alarm status of main steam line radiation monitors -

NOT NORMAL

• Check Chemistry grab sample -

INDICATESPRESENCE OF PRIMARY TO SECONDARY LEAKAGE

• Check trend history and alarm status of N16 monitors - NOT NORMAL RO Perfom Monitoring of N16 Monitor 3576 Step 4 Trends Initiate monitoring of N16 monitor trends 3576 Step 4.a RO Verify SG Blowdown Status 3576 Step 4 Check if blowdown should be isolated 3576 Step 5.a Condenser air ejector radiation monitor -

IN ALERT OR ALARM OR Steam generator blowdown radiation monitor - IN ALARM OR Section 4 Page 17 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv

                                          -     - -- -         Asirin J...9 PEnnetaed Artinne QCtnA~orA
                                                                                                                     %VJL2I1Iou M  U Chemistry grab sample indicates primary to secondary leakage - GREATER THAN OR EQUAL TO 75 gpd OR N16 monitor in ALERT or HIGH RO               Check SG blowdown isolation valves -    3576 CLOSED                                  Step 5.b

• 3BDG-CTV22A
• 3BDG-CTV22B
• 3BDG-CTV22C
• 3BDG-CTV22D RO CLOSE valves. 3576 Step 5.b RNO US Proceed to step 6. 3576 Step 5.c US Limit Effects Of Secondary 3576 Step 5 Contamination BOP Check auxiliary steam - SUPPLIED FROM 3576 MAIN STEAM Step 6.a Section 4 Page 18 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign ExDected Actions Standard Standard REMOTE NOTE: When directed as PEO, US/PEO Using OP 3331A, "Auxiliary Boiler, Steam 3576 MSR01 use REMOTE MSR01 To start and Condensate" Perform the following: Step 6.b Aux Boiler.

1. Startup of auxiliary boiler A (B)

2. Shift auxiliary steam from main steam to auxiliary boiler system.

US/PEO Locally Close the condenser level control 3576 valve outlet isolation (3CNS-V12) Step 6.c US Request HP determine if personnel should 3576 be evacuated from affected areas Step 6.d

• Turbine Bldg (north end)
• Secondary sample sink
• CPE
• MS Valve Bldg Evacuate personnel from affected areas 3576 Step 6.e NOTE: Not desired to implement US Refer to C OP 200.11, "Operation of a 3576 C OP 200.11. INFORM US that Cross Contaminated System," and Step 6.f STA will perform and notify US of Perform any required actions any required actions.

US Check If Unit Shutdown Should Be 3576 Step 7 Initiated Section 4 Page 19 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Check any of the following: 3576 Step 7.a Note: This condition exists RO

• Condenser air ejector radiation monitor

                                                                           - IN ALERT OR ALARM OR

• Chemistry grab sample indicates primary to secondary leakage in any SG - GREATER THAN OR EQUAL TO 75 gpd OR
• Condenser air ejector radiation monitor correlation to leak rate (gpd) indicates primary to secondary leakage -

GREATER THAN OR EQUAL TO 75 gpd OR

• N16 monitor in ALARM US Evaluate event using MP-26-EPI-FAP06- 3576 003, Unit 3 Emergency Action Levels Step 7.b (Barrier Failure)

US Check plant status - MODE 1 OR 2 3576 Step 7.c Section 4 Page 20 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Proceed to step 9. 3576 Step 7.d US

• The shutdown times provided are EPRI 3576 Step 9 recommendations and should not be NOTE achieved at the cost of plant stability or intentional reactor trip.
• If a unit shutdown is initiated based on a condenser air ejector or N16 monitor ALERT or ALARM condition and subsequent Chemistry calculations indicate actual leakage does not meet or exceed a shutdown criterion, then the shutdown may be suspended.
• The rate of increase limit does not apply to leak rate spikes followed by decreasing leak rates.
• Plant shutdown may be accomplished using AOP 3575, "Rapid Downpower,"

or appropriate General Operating Procedures as determined necessary. Section 4 Page 21 of 61

EVALUATION GUIDE (

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign ExDected Actions Staqndlard

                                                                                            -        --------                     r

[Tech Specs] US Perform Unit Shutdown 3576 Step 9 NOTE TO EVALUATOR: IF Tech Specs are not reviewed at this point, follow-up with US at end of scenario (procedure does not specifically direct Tech Spec review). LCO 3.4.6.2.b & c, action b Verify a leakage rate of increase limit met: 3576 Step 9.a NOTE: The leak is about 40 gpm.

• Check leakage increased in any SG by This should be obvious to the - GREATER THAN OR EQUAL TO 15 crew and they should answer yes gpd IN A 30 min PERIOD at this step and continue to step 9.b..IF they pause at this step REPORT as Chemistry that initial indications are that the leak is > 20 gpm.

OR

• Check condenser air ejector radiation monitor RATE OF CHANGE ALARM -

IN ALARM FOR 30 min OR Section 4 Page 22 of 61

EVALUATION GUIDE (

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assiqn Expected Actions Standard

• Check N16 S/G Leak Detection Status (PPC) HIGH RATE (75 GPD & 15 GPD RISE IN 30 MIN) - IN ALARM Proceed to step 9.d 3576 Step 9.b RO Check power level - GREATER THAN 3576 50% Step 9.d US Initiate power reduction to be LESS THAN 3576 50% within 1 hour (downpower rate of Step 9.e 3%°/min or 5%/o/min recommended)

CREW Return to step 9.d 3576 Step 9.f T= power MALF EVENT 4: Rod Bank CB-D reduction RD021 Continuous Rod Insertion decision AOP 3552 MALFUNCTION OF CREW Stabilize Plant Conditions AOP 3552 THE ROD DRIVE SYSTEM, Rev. Step 1 3 RO Place control rod bank SEL switch in MAN AOP 3552 Step 1.a RO Verify - NO RODS MOVING AOP 3552 Step 1.b Section 4 Page 23 of 61

EVALUAI iON GUIDE (

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard CREW TRIP the reactor and Go to E-O, Reactor AOP 3552 Trip or Safety Injection. Step 1.b RNO MALF EVENT 5: SGTR with Loss of SGO1C Offsite Power 50% ED01 E-O, Reactor Trip or Safety Crew Go to E-O, Reactor Trip or Safety Injection. Injection, Rev. 21

• Foldout page must be open E-0, Step 1, NOTE
• ADVERSE CTMT defined as GREATER THAN 180 0F or GREATER THAN 105 R/hr in containment.
• The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

RO Verify Reactor Trip E-0, Step 1

• Check reactor trip and bypass breakers - OPEN
• Check rod bottom lights - LIT
• Check neutron flux - DECREASING Section 4 Page 24 of 61

EVALUAI iON GUIDE A'

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard BOP Verify Turbine Trip E-0, Step 2 Check all turbine stop valves - CLOSED E-0, Step 2.a BOP Verify Power to AC Emergency Busses E-0, Step 3 BOP Check busses 34C and 34D - E-0, Step 3.a BOTH ENERGIZED US Check If SI Is Actuated E-0, Step 4 RO Verify SAFETY INJECTION ACTUATION EOP 35 E-0, annunciator - (MB4D 1-6 or MB2B 5-9) - Step 4.a LIT US Check if SI is required E-0, Step 4, RNO

• CTMT pressure GREATER THAN 18 psia OR
• RCS pressure LESS THAN 1890 psia OR
• PZR level LESS THAN 16%

OR

• RCS subcooling LESS THAN 32 0F OR Section 4 Page 25 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian ExDected Actions Standard Standard

• SG pressure LESS THAN 660 psig IF Si is required, THEN initiate Si and Proceed to step 5 MALF EVENT 6: Service Water RO Verify Service Water Pumps - AT LEAST E-0, Step 5 SWO1 B Pumps Fail to Auto Start ONE PER TRAIN RUNNING SW02D

[Critical Task] Manually start the RO START pumps E-0, Step 5 B Train Service Water Pump RNO before transitioning from E-0. NOTE: If the B SWP does not start RO Verify Two RPCCW Pumps - ONE PER E-0, Step 6 on the first time REPORT as PEO TRAIN RUNNING or Maintenance, if requested, and recommend a second attempt. RO Verify ECCS Pumps Running E-0, Step 7

• Check SI pumps - RUNNING
• Check RHR pumps - RUNNING
• Check two charging pumps -

RUNNING Section 4 Page 26 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Maif Instructor Information/Activity Assian Exnertpd Actions- .qtnnxiarr Asian

                                                                   *                     -r      d IAr-ti I- - n NOTE: Crew may identify ruptured       BOP          Verify AFW Pumps Running                 E-0, Step 8 S/G early and take critical task action in advance of procedural direction.

[Critical Task] Identify ruptured S/G and Isolate AFW before narrow range level reaches 29%. Check MD pumps - RUNNING E-0, Step 8.a Check turbine - driven pump - RUNNING, E-0, IF NECESSARY Step 8.b BOP Verify FW Isolation E-0, Step 9

• Check SG feed regulating valves -

CLOSED

• Check SG feed regulating bypass valves - CLOSED
• Check FW isolation trip valves -

CLOSED

• Check MD FW pump - STOPPED
• Check TD FW pumps - TRIPPED
• Check SG blowdown isolation valves -

CLOSED Section 4 Page 27 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

• Check SG blowdown sample isolation valves - CLOSED
• Check SG chemical feed isolation valves - CLOSED BOP Check If Main Steam Lines Should Be E-0, Step 10 Isolated Check Ctmt pressure GREATER THAN 18 E-0, psia Step 10.a OR Any SG pressure LESS THAN 660 psig Proceed to Step 11 E-0, Step 10.a, RNO RO Check if CDA Required E-0, Step 11 Check Ctmt pressure is GREATER THAN E-0, 23 psia Step 11.a OR Ctmt spray is initiated US Proceed to Step 12. E-0, Stepl 1,a, RNO Section 4 Page 28 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard BOP Verify CAR Fans Operating In E-0, Step 12 Emergency Mode BOP Check CAR fan status: E-0, Step 12.a

• CAR fans A and B - RUNNING
• CAR fan C - STOPPED BOP START/STOP CAR fans as necessary. E-0, Step 12.a, RNO RO Verify RPCCW Ctmt supply and return E-0, header isolations - OPEN Step 12.b RO Verify Train A and B RPCCW supply and E-0, return to chill water valves - OPEN Step 12.c RO Verify CIA E-0, Step 13 RO Check ESF Group 2 status columns 2 E-0, through 10 - LIT Step 13.a RO Verify Proper ESF Status Panel E-0, Step 14 Indication
• Verify ESF Group 1 lights - OFF
• Verify ESF Group 2 lights - LIT Section 4 Page 29 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO/BOP Align component(s) as necessary for E-0, minimum safety function. Step 14, RNO RO Determine If ADVERSE CTMT E-0, Step 15 Conditions Exist

• Ctmt temperature GREATER THAN 1800 F OR
• Ctmt radiation GREATER THAN 105 R/hr CREW DO NOT use ADVERSE CTMT E-0, parameters. Step 15, RNO RO Verify ECCS Flow E-0, Step 16 Check charging pumps - E-0, Step 16.a FLOW INDICATED RO Check RCS pressure - GREATER THAN E-0, 1650 psia (1950 psia ADVERSE CTMT) Step 16.b US Proceed to Step 16.d E-0, Step 16.b, RNO Proceed to step 17. E-0, Step 16.c Section 4 Page 30 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign ExDected Actions Standard ExDected Actions Standard Check SI pumps - FLOW INDICATED E-0, Step 16.d START pumps and Align valves. E-0, Step 16.d RNO Check RCS pressure - LESS THAN 300 E-0, psia (500 psia ADVERSE CTMT) Step 16.e Check RHR pumps - FLOW INDICATED. E-0, Step 16.f BOP Verify Adequate Heat Sink E-0, Step 17 Check NR level in at least one SG - E-0, GREATER THAN 8% (42% ADVERSE Step 17.a CTMT) US Proceed to Step 17.d. E-0, Step 17.a, RNO BOP Control feed flow to maintain NR level - E-0, BETWEEN 8% and 50% (42% and 50% Step 17.b ADVERSE CTMT) US Proceed to Step 18. E-0, Step 17.c BOP Verify Total AFW Flow - GREATER THAN E-0, 530 gpm Step 17.d BOP Verify AFW Valve Alignment - PROPER E-0, Step 18 EMERGENCY ALIGNMENT Section 4 Page 31 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Verify ECCS Valve Alignment - PROPER E-0, Step 19 EMERGENCY ALIGNMENT US Check Plant Status E-0, Step 20 BOOTH NOTE When asked, REPORT that "all Verify SLCRS doors - CLOSED E-0, INST SLCRS doors indicate closed." Step 20.a RO Check CONTROL BUILDING ISOLATION E-0, annunciator (MB4D 3-6) - LIT Step 20.b RO Check if CBI is required E-0, Step 20.b, RNO RO

• Ctmt pressure GREATER THAN 18 psia OR RO
• Control Building radiation monitor in alarm OR
• SI manually actuated RO IF CBI required, THEN initiate CBI.

US IF CBI is NOT required, THEN proceed to Step 21. RO Verify ESF Group 2 CBI lights - LIT E-0, Step 20.c Section 4 Page 32 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Align HVAC components as necessary E-0, for minimum safety function. Step 20.c, RNO BOP Verify control building purge supply fan E-0, and purge exhaust fan - NOT RUNNING Step 20.d BOP Control building air bank isolation valves E-0,

                                                                           - OPEN (after 60 seconds)                  Step 20.e BOP           STOP kitchen exhaust fan                   E-0, Step 20.f BOOTH       NOTE        When called, WAIT 3 - 5 min,          PEO           Close and Dog (as applicable) Control      E-0, INST                    Then REPORT "All Control                            Building pressure boundary doors.          Step 20.g Building pressure boundary doors are Closed and Dogged."

RO Check RCS Temperature E-0, Step 21 Verify RCS cold leg WR temperature - E-0, BETWEEN 5501F and 5601F Step 21.a Us Perform the applicable action: E-0, Step 21.a, RNO

• IF temperature is GREATER THAN 550 0F AND 5600F, THEN Section 4 Page 33 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Standard

1) Dump steam to the condenser, if available OR Dump steam to atmosphere.

US 2) Proceed to Step 22. IF the temperature is LESS THAN 550°, THEN proceed to Step 21c. US Proceed to Step 22 E-0, Step 21.b BOP Maintain total feed flow BETWEEN 530 E-0, and 600 gpm until NR level is GREATER Step 21.c THAN 8% (42% ADVERSE CTMT) in at least one SG BOP CLOSE SG atmospheric dump and dump E-0, bypass valves Step 21.d BOP Check the following valves - CLOSED E-0, Step 21.e

• 5s
• MSIV bypass valves US Perform the following: E-0, Step 21.e, RNO BOP Place both condenser steam dump E-0, interlock selector switches to OFF. Step 21.e.1, RNO Section 4 Page34 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard BOP IF unexpected cooldown continues, THEN E-0, CLOSE the MSIVs and MSIV bypass Step 21.e.2, valves. RNO RO Check PZR Valves E-0, Step 22 Verify PORVs - CLOSED E-0, Step 22.a RO Verify normal PZR spray valves - CLOSED E-0, Step 22.b RO Verify PZR safety valves - CLOSED E-0, Step 22.c RO Check PORV block valves - OPEN E-0, Step 22.d CREW To prevent damage to the RCP seal(s), E-0, seal injection flow should be maintained to Step 23, all RCPs. CAUTION RO Check If RCPs Should Be Stopped E-0, Step 23 Verify RCPs - ANY RUNNING E-0, Step 23.a Proceed to step 24. E-0, Step 23.a, RNO. Section 4 Page 35 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Verify RCS pressure LESS THAN 1500 RO Verify RCS pressure - LESS THAN 1500 E-0, psia (1800 psia ADVERSE CTMT) Step 23.b US Proceed to Step 24 E-0, Step 23.b, RNO. RO Verify charging or SI pumps - AT LEAST E-0, ONE RUNNING Step 23.c US Proceed to Step 24 E-0, Step 23.c, RNO RO STOP all RCPs E-0, Step 23.d BOP/RO Check If SG Secondary Boundaries Are E-0, Step 24 Intact Check pressure in all SGs E-0, Step 24.a

• NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
• NO SG COMPLETELY DEPRESSURIZED BOP Check If SG Tubes Are Intact E-0, Step 25 Section 4 Page 36 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Sample all SGs for activity E-0, Step 25.a

1. RESET SG blowdown sample isolation

2. OPEN SG blowdown sample isolation valve(s)

3. Request Chemistry obtain activity samples using HP coverage BOP Check steam generator levels - NO SG E-0, LEVEL INCREASING IN AN Step 25.b UNCONTROLLED MANNER US Initiate monitoring of CSF Status Trees E-0, and Go to E-3, Steam Generator Tube Step 25.b, Rupture. RNO Verify trend history and alarm status of E-0, radiation monitors Step 25.c

• Main steam line - NORMAL
• Condenser air ejector - NORMAL
• SG blowdown - NORMAL Initiate monitoring of CSF Status Trees E-0, and Go to E-3, Steam Generator Tube Step 25.c Rupture RNO Section 4 Page 37 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Verify trend history and alarm status of radiation monitors MALF E-3: Steam Generator Tube US To prevent damage to the RCP seal(s), E-3 Step 1 SGOIC Rupture, Rev. 17 seal injection flow should be CAUTION maintained to all RCPs. US

• Foldout page must be open E-3, Step 1, NOTE
• The RCP trip criteria is only applicable until a controlled cooldown is initiated in step 6.

RO Check If RCPs Should Be Stopped E-3, Step 1 Check RCPs - ANY RUNNING E-3, Step 1.a Proceed to step 2. E-3, Step 1.a, RNO Verify RCS pressure - LESS THAN 1500 E-3, psia (1800 psia ADVERSE CTMT) Step 1.b Proceed to step 2. E-3, Step 1.b, RNO Verify charging or safety injection pumps - E-3, AT LEAST ONE RUNNING Step 1.c STOP all RCPs E-3, Step 1.d Section 4 Page 38 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assiqn Expected Actions Standard ExDected Actions Standard [Critical Task] Identify ruptured BOP Identify Ruptured SGs E-3, Step 2 S/G and Isolate AFW before narrow range level reaches 29%.

• Unexpected increase in any SG level OR
• High radiation from any SG steam line as indicated by the trend history or alarm status OR
• High radiation from any SG sample US
• If the TD AFW pump is the only E-3, Step 3, available source for feed flow, CAUTION steam supply to the TD AFW pump must be maintained from at least one SG.
• At least one SG must be maintained available for RCS cooldown.

BOP Isolate Flow From Each Ruptured SG E-3, Step 3 Verify each ruptured SG atmospheric E-3, Step dump valve controller - IN AUTO AT 1125 3.a psig RO Check each ruptured SG atmospheric E-3, dump valve - CLOSED Step 3.b Section 4 Page 39 of 61

EVALUAI ION GUIDE

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Check each ruptured SG atmospheric E-3, dump bypass valve - CLOSED. Step 3.c CLOSE each ruptured SG steam supply E-3, Step isolation valve to TD AFW pump. 3.d

• 3MSS*MOV17A
• 3MSS*MOV17B
• 3MSS*MOV17D Verify each ruptured SG blowdown E-3, isolation valve - CLOSED Step 3.e CLOSE valves. E-3, Step 3.e, RNO Verify each ruptured SG blowdown sample E-3, Step isolation valve - CLOSED 3.f CLOSE valves E-3, Step 3.f, RNO Verify each ruptured SG chemical feed E-3, isolation valve - CLOSED Step 3.g CLOSE valves E-3, Step 3.g, RNO Section 4 Page 40 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Using table, CLOSE the main steam line E-3, drains upstream of MSIVs and TD AFW Step 3.h pump for the ruptured SG(s) SGA I SG B 1 SG C SG D 3DTM*AOV29A 3DTM*AOV29B 3DTM*AOV29C 3DTM*AOV29D 3DTM*AOV61A 3DTM*AOV61 B 3DTM*AOV61 C 3DTM*AOV61 D 3DTM*AOV63A 3DTM*AOV63B 3DTM*AOV63D 3DTM*AOV64A 3DTM*AOV64B 3DTM*AOV64D EVENT 7: MSIV on Ruptured S/G BOP CLOSE each ruptured SG MSIV and MSIV E-3, Fails to Close bypass valve. Step 3.i Perform the following: E-3, Step [Critical Task] Isolate steam flow from 3.i RNO

1. CLOSE all remaining SG MSIVs and ruptured S/G before a transition to ECA- MSIV bypass valves.

3.1 occurs at step 3 of E-3 (MSIV failed).

2. Close all valves listed on Attachment A.

NOTE: Perform this step when directed

3. Use the intact SG atmospheric dump as PEO and Report when the crew valves to dump steam, for RCS reaches Step 5 Caution. (This is a Time temperature control or cooldown.

Compression technique to support procedure flow). IF any ruptured SG can NOT be isolated from at least one intact SG, THEN Go to ECA-3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery Desired. Section 4 Page 41 of 61

EVALUATION GUIDE (

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US If any ruptured SG is faulted, feed flow E-3, Step 4, to that SG should remain isolated CAUTION during subsequent recovery actions unless the SG is needed for RCS cooldown. BOP Check Ruptured SG Level E-3, step 4 Verify one of the following is satisfied: E-3, Step 4.a

• Ruptured SG WR level - GREATER THAN 67% (95% ADVERSE CTMT)

OR

• Ruptured SG NR level - GREATER THAN 8% (42% ADVERSE CTMT)

Isolate feed flow to ruptured SGs. E-3, Step 4.b NOTE: When the Crew reaches this step Steps 3.d and 3.i for isolating the ruptured E-3, Step 5, report as the PEO that the step is SG must be completed prior to continuing CAUTION complete (This is a Time Compression to step 5. technique to support procedure flow). BOP Check Ruptured SGs Pressure - E-3, step 5 GREATER THAN 530 psig Section 4 Page 42 of 61

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SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign ExDected Actions Standard I Standard US If RCPs are NOT running, the following E-3, Step 6 steps may cause a false entry into the CAUTION INTEGRITY Status Tree for the affected loop. Disregard the affected loop Tc indication until after performance of step 27. US

• To allow steam dump operation to E-3, Step 6 continue during a controlled cooldown, NOTE ensure the Low-Low Tavg interlock is bypassed at 553 0F.
• Ensure Low Steam Line Pressure SI is blocked when pressurizer pressure is LESS THAN 2000 psia.
• After the Low Steam Line Pressure SI signal is blocked, MSI will occur if the high steam pressure rate setpoint is exceeded.

US/RO/ Initiate RCS Cooldown E-3, Step 6 PEO Check RCPs -ANY RUNNING E-3, Step 6.a Proceed to step 6.c. E-3, Step 6.a, RNO Section 4 Page 43 of 61

( i. EVALUAi iON GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Locally, Place the eight RCP overcurrent E-3, trip switches (43PP and 43PB) in the Step 6.b COLD position using CO key Locker Key

                                                                       #7 Determine required core exit temperature         E-3, without internolatina (use lower   nremiire)/
                                                                                                     -F.r-I           Sten
                                                                                                                        --    Anc
                                                                                                                               -{a\

Lowest Ruptured SG Core Exit Temperature Pressure (psig) (OF) NORMAL ADVERSE 1285 537 513 1185 526 502 1085 515 489 985 502 475 885 488 459 785 474 443 685 457 423 585 449 426 530 435 410 Dump steam to condenser from intact SGs at E-3, Step 6.d maximum rate Section 4 Page 44 of 61

EVALUAi iON GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

1. Verify the following:

• Intact SG MSIVs - OPEN
• Annunciator "CONDENSER AVAIL FOR STM DUMP C-9" (MB4D 5-6) -

LIT

2. Adjust steam pressure controller to obtain zero output in MANUAL

3. Transfer condenser steam dumps to Steam Pressure Mode

4. Place both condenser steam dump interlock selectors - ON

5. Adjust steam pressure controller to dump steam to condenser Dump steam to atmosphere from intact E-3, SGs at maximum rate using SG Step 6.d atmospheric dump valves. RNO Verify core exit TCs - LESS THAN E-3, REQUIRED TEMPERATURE Step 6.e Section 4 Page 45 of 61

( ': EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian Expected Actions Standard Stndrd Proceed to NOTE prior to step 7 and, E-3, Step 6.e WHEN RNO Core exit TCs less than required temperature, THEN Perform steps 6.f and 6.g Stop RCS cooldown E-3, Step 6.f Maintain core exit TCs - LESS THAN E-3, REQUIRED TEMPERATURE Step 6.g To aid in identifying previously undetected E-3, Step 7, steam generator tube failures, the wide NOTE range SG level indication should be used if the narrow range level is off scale. BOP Check Intact SG Levels E-3, step 7 Verify NR level - GREATER THAN 8% E-3, (42% ADVERSE CTMT) Step 7.a Maintain total feed flow GREATER THAN E-3, 530 gpm until NR level is GREATER Step 7.a, THAN 8% (42% ADVERSE CTMT) in at RNO least one SG. Control feed flow to maintain NR level E-3, between 8% and 50% (42% and 50% Step 7.b ADVERSE CTMT) Section 4 Page 46 of 61

EVALUATION GUIDE (

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assigin ExDected Actions Standard 8, E-3, Step Standard US If any PZR PORV opens because of high E-3, Step 8, PZR pressure, step 8.a should be CAUTION repeated when pressure decreases to LESS THAN 2350 psia. RO Check PZR PORVs And Block Valves E-3, Step 8 Verify PORVs - CLOSED E-3, Step 8.a Verify PORV block valves - AT LEAST E-3, ONE OPEN Step 8.b

• If offsite power is lost after SI reset, E-3, Step 9 manual action to restart safeguards CAUTION equipment may be required.
• DO NOT reset CDA if recirculation spray pumps are required and have not automatically started.

RO RESET ESF Actuation Signals If E-3, Step 9 Required

• SI
• CDA
• CIA
• CIB
• LOP Section 4 Page 47 of 61

(' f EVALUA) ION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Maif Instructor Information/Activity Assign Expected Actions Standard RO Establish Instrument Air to Ctmt E-3, Step 10 Check instrument air compressors - AT E-3, LEAST ONE RUNNING Step 10.a START one instrument air compressor E-3, Step 10.a, RNO NOTE: RO will be unable to OPEN instrument air Ctmt isolation valves E-3, complete this step Step 10.b US/PEO RESTORE MCC 32-3T E-3, Step 11 Check Emergency Bus 34C ENERGIZED E-3, Step 11a Proceed to the caution prior to step 12 E-3, and, Step 11a RNO WHEN Power restored to emergency bus 34C THEN perform step 1 b T+ 5 EDR1 8 Resets 32-3T and Using GA-1, Energize MCC32-3T E-3, minutes of Step 11.b request EDR44 clears inverter 6 alarms Section 4 Page 48 of 61

EVALUAI iON GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US To provide adequate ECCS flow, RCS E-3, pressure should be monitored to Step 12, ensure that the RHR pumps are CAUTION manually restarted if pressure decreases to LESS THAN 300 psia (500 psia ADVERSE CTMT). RO Check If RHR Pumps Should Be E-3, Step 12 Stopped Verify RCS pressure - GREATER THAN E-3, 300 psia (500 psia ADVERSE CTMT) Step 12.a Proceed to CAUTION prior to step 13. E-3, Step 12.a, RNO STOP RHR pumps and Place in AUTO E-3, Step 12.b US Check If Cooldown Should Be Stopped E-3, Step 13 Check Cooldown - IN PROGRESS E-3, Step 13.a Proceed to step 13.d E-3, Step 13.a, RNO Maintain core exit TCs - LESS THAN E-3, REQUIRED TEMPERATURE Step 13.d Section 4 Page 49 of 61

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( ( EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard 1/0 EVENT 8: Inability to De- RO Depressurize RCS Using PZR PORV to E-3, Step 17 3RCS* pressurize RCS Minimize Break Flow And Refill PZR PCV456 OPEN - FALSE Check PZR PORVs - AT LEAST ONE E-3, AVAILABLE Step 17.a Proceed to step 17.e. E-3, Step 17.a, RNO Establish auxiliary spray: E-3, Step 17.e

1. Verify at least one Si pump - RUNNING E-3, Step 17.e.1

2. Verify at least one charging pump - E-3, RUNNING Step 17.e.2

3. CLOSE charging header loop isolation E-3, valves (3CHS*AV8146 and Step 17.e.3 3CHS*AV8147)

4. Fully OPEN charging line flow control E-3, valve Step 17.e.4

5. OPEN charging header isolation valves E-3, (3CHS*MV8106 and 3CHS*MV8105) Step 17.e.5 Section 4 Page 51 of 61

( ( EVALUAi iON GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

6. Unlock and OPEN auxiliary spray valve E-3, (3RCS*AV8145) Step 17.e.6

7. CLOSE both charging pump cold leg E-3, injection valves Step 17.e.7

8. Verify Auxiliary Spray - ESTABLISHED E-3, Step 17.e.8

• Charging header flow
• PZR Pressure - DECREASING Perform the following: E-3, Step 17.e.8 RNO a) OPEN both charging pump cold leg injection valves.

b) CLOSE auxiliary spray valve. c) CLOSE charging header isolation valves. d) Go to ECA - 3.3, SGTR Without Pressurizer Pressure Control. ECA-3.3: SGTR WITHOUT US Foldout page must be open. EOP 35 PRESSURE CONTROL, Rev. 12 ECA-3.3 Step 1, Note Section 4 Page 52 of 61

( EVALUAM iON GUIDE (

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Check Ruptured SG(s) Level EOP 35 ECA-3.3 Step 1 Check Ruptured SGs Narrow Range Level - EOP 35 LESS THAN 80% (54% ADVERSE CTMT) ECA-3.3 Step 1.a US RCPs should be operated in the following EOP 35 order of priority to ensure optimum PZR ECA-3.3 spray flow: Step 2, Note First: RCP 2 Second: RCP 1 and one other RCP RO Try To Establish Normal PZR Spray EOP 35 ECA-3.3 Step 2 Check RCP status - AT LEAST ONE EOP 35 RUNNING IN EITHER LOOP 1 OR LOOP 2 ECA-3.3 Step 2.a Using GA-6, START the preferred RCP(s) EOP 35 ECA-3.3 IF the preferred RCP(s) can NOT be started, Step 2.a, THEN RNO Proceed to step 3. Section 4 Page 53 of 61

A: ( EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assiqn Expected Actions Standard Standard RO Try To Restore PZR PORV EOP 35 ECA-3.3 Step 3 Establish conditions for opening a PZR EOP 35 PORV: ECA-3.3 Step 3.a Check PZR PORV power available EOP 35 ECA-3.3 Step 3.a.1 Check PZR PORV block valve open EOP 35 ECA-3.3 Step 3.a.2 Check PZR PORV - AT LEAST ONE EOP 35 AVAILABLE ECA-3.3 Step 3.a.3 Proceed to step 4. EOP 35 ECA-3.3 Step 3.a, RNO RO Try To Establish Auxiliary Spray EOP 35 ECA-3.3 Step 4 Verify SI pumps - BOTH RUNNING EOP 35 ECA-3.3 Step 4.a Section 4 Page 54 of 61

(  ! ( EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian En~ritzed Antinns- .<::nnr1nrH4

                                                                                -                                        '41   II.A~4 M Verify charging pumps - AT LEAST ONE        EOP 35 RUNNING                                    ECA-3.3 Step 4.b NOTE: These steps were                               Establish auxiliary spray:                 EOP 35 attempted in E-3. It is expected                                                                ECA-3.3 that the crew will not attempt them                                                             Step 4.c again without a change in conditions.

Proceed to step 5. EOP 35 ECA-3.3 Step 4.c, RNO CLOSE charging header loop isolation valves EOP 35 (3CHS*AV8146 and 3CHS*AV8147) ECA-3.3 Step 4.cl CLOSE charging line flow control valve EOP 35 ECA-3.3 Step 4.c.2 OPEN charging header isolation valves EOP 35 (3CHS*MV8106 and 3CHS*MV8105) ECA-3.3 Step 4.c.3 Unlock and OPEN auxiliary spray valve EOP 35 (3RCS*AV8145) ECA-3.3 Step 4.c.4 Section 4 Page 55 of 61

( ( EVALUA1 ION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian Exnected Actions, Standrdnr Exoected Actions 5tnr1rd Slowly Open charging line flow control valve EOP 35 to establish auxiliary spray flow ECA-3.3 Step 4.c.5 CLOSE both charging pump cold leg injection EOP 35 valves ECA-3.3 Step 4.c 6 Go to E-3, Steam Generator Tube Rupture, EOP 35 step 17.b ECA-3.3 Step 4.d BOP Check Intact SG Levels EOP 35 ECA-3.3 Step 5 Verify NR level - GREATER THAN 8% (42% EOP 35 ADVERSE CTMT) ECA-3.3 Step 5.a Maintain total feed flow GREATER THAN EOP 35 530 gpm until NR level is GREATER THAN ECA-3.3 8% (42% ADVERSE CTMT) in at least one Step 5.a, SG. RNO Control feed flow to maintain NR level - EOP 35 BETWEEN 8% and 50% (42% and 50% ECA-3.3 ADVERSE CTMT) Step 5.b IF NR level in any intact SG continues to EOP 35 increase in an uncontrolled manner, THEN ECA-3.3 Go to E-3, Steam Generator Tube Rupture. Step 5.b, RNO Section 4 Page 56 of 61

EVALUAi iON GUIDE (

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian Expected Actions S;tandrdnr ExDected Actions tindird RO Check PZR Level - GREATER THAN 16% EOP 35 (50% ADVERSE CTMT) ECA-3.3 Step 6 US/RO Check If ECCS Flow Can Be Terminated EOP 35 ECA-3.3 Step 7 Verify RCS subcooling based on core exit EOP 35 TCs - GREATER THAN 320F (11 50F ECA-3.3 ADVERSE CTMT) Step 7.a Verify secondary heat sink EOP 35 ECA-3.3 Step 7.b

• Total feed flow to SGs - GREATER THAN 530 gpm AVAILABLE OR
• NR level in at least one intact SG -

GREATER THAN 8% (42% ADVERSE CTMT) Check RVLMS plenum level - GREATER EOP 35 THAN OR EQUAL TO 19% ECA-3.3 Step 7.c Check ruptured SGs NR level - EOP 35 ECA-3.3 INCREASING IN AN UNCONTROLLED Step 7.d MANNER Section 4 Page 57 of 61

I ( EVALUATION GUIDE

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assion FxyntmrdP Antinne QftnAnr.4r Ak NICI ..... aV. u'.11 U OR OFF-SCALE HIGH RO Stop ECCS Pumps EOP 35 ECA-3.3 Step 8

• STOP Si pumps and Place in AUTO
• STOP all but one charging pump and Place in AUTO TERMINATE UPON COMPLETION OF STEP 8 OF ECA-3.3. Verify ECCS Flow Not Required.

Section 4 Page 58 of 61

SECTION 4 ID Number: 2K2 NRC-002 Revision: 0 EVALUATION GUIDE I.

SUMMARY

The following Critical Tasks are covered in this exam: TASK DESCRIPTION TASK# K/A >/= 3.0 BASIS FOR SELECTION Isolate steam flow from E-3-A 038 EA1.32 Failure to isolate the ruptured S/G before a 4.614.7 ruptured SG causes a loss transition to ECA-3.1 occurs of differential pressure at step 3 of E-3 (MSIV between the ruptured SG failed). and the intact SGs and the crew must transition to a contingency procedure that

                                                                         "...necessitates the crew taking compensating action which complicates the event mitigation strategy...."

Identify ruptured SIG and E 038 EA1.01 Failure to stop reactor Isolate AFW before narrow C(1) 4.5/4.4 coolant leakage into a range level reaches 29%. ruptured SG by depressurizing the RCS needlessly complicates mitigation of the event and constitutes a "significant reduction of safety margin beyond that irreparably introduced by the scenario." Section 4 Page 59 of 61

TASK DESCRIPTION TASK # K/A >/= 3.0 BASIS FOR SELECTION Manually start the B Train ECA-0.0- Failure to manually start Service Water Pump before -F the SW pump under the transitioning from E-0. postulated plant conditions means that the EDG is running without SW cooling leading to a high-temperature condition that can result in EDG failure due to damage caused by engine overheating. Under the postulated plant conditions, the running EDG is the only operable EDG. Thus, failure to perform the critical task constitutes "mis-operation or incorrect crew performance that leads to degraded emergency power capacity." Note: [*] Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide. Section 4 Page 60 of 61

SECTION 4

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 EVALUATION GUIDE Section 4 Page 61 of 61

SECTION 5 SCENARIO INITIAL CONDITIONS ID Number: 2K2 NRC-002 Revision: 0 Reactor Power: 100% Operating History: 450 days on line RCS Boron: 50 ppm Core Burnup: 18,600 MWD/MTU Condensate Demins: 7 demins in service Evolutions in Progress: NONE, A Train Protected, Intake Condition: GREEN Major Equipment OOS: "A" PORV is inoperable due to an electrical short in the control circuitry. It has been out of service for 8 hours. Electrical maintenance estimates that the valve will be returned to service within 24 hours. The following Tech Specs are applicable: Tech Spec 3.4.4, action b 3TRM 7.4.1 action a.1 and a.3 for both the A PORV and the block valve 3RCS*MV8000A Crew Instructions: The crew is initially directed to reduce CTMT pressure to 13.80 psia by starting CTMT vacuum pump 3CVS-P1A using OP 3313E, Containment Vacuum, section 4.2. Plant/Simulator Differences:

• Real Time and Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.
• Auto-log terminals need to be refreshed after entry is made.
• If not using the speed dial option on the phone system, the operator must dial either #3333 or #3334 to reach the person/department they desire.
• The following PPC programs do not function on the simulator:
• Samarium Follow
• Xenon Follow
• Sequence of Events Section 7 Page 1 of 1

SECTION 6 VALIDATION CHECKLIST

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 Remote functions: All remote functions contained in the guide are certified. Malfunctions: All malfunctions contained in the guide are certified. Initial Conditions: The initial condition(s) contained in the guide are certified or have been developed from certified IC's in accordance with NSEM-4.02. Simulator Operating Limits: The simulator guide has been evaluated for operating limits and/or anomalous response. Test Run: The scenario contained in the guide has been test run and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected. Examination Scenario Review The dynamic examination review checklist is complete. (This is not required unless the exam will be used as an Annual Exam, then NUREG 1021 requirements apply.) 6110/02 Technical Reviewer Date Section 7 Page 1 of 1

SECTION 7 REFERENCE AND TASK TRACKING

Title:

SGTR WITHOUT PZR PRESSURE CONTROL ID Number: 2K2 NRC-002 Revision: 0 I.

References:

OP3313E Containment Vacuum AOP 3552 Malfunction of the Rod Control System AOP*3555 Reactor Coolant System Leak AOP*3576 Steam Generator Tube Leak EOP*E-0 Reactor Trip or Safety Injection EOP*E-3 Steam Generator Tube Rupture EOP*ECA-3.3 SGTR Without Pressure Control EOP*ERGEXE Westinghouse Owners Group Executive Document EOP* Step DOC MP3 step deviation Document EOP*ERGHP Westinghouse Owners Group Background Document FAP06*01 Event Assessment, Classification and Reportability NUREG*1021 rev 8 Examiners Standards Section 7 Page 1 of 1

MILLSTONE NUCLEAR POWER STATION I1 LOIT NRC SIMULATOR EXAM GUIDE APPROVAL SHEET Exam

Title:

STEAM LINE BREAK AND FR-H.1 Revision: 0 ID Number: 2K2 NRC-003 This document is the property of Millstone Power Station, which controls its distribution. Further transfer, copying, and modification of this document are strictly prohibited without the written consent of Millstone Power Station. O4w Cn

SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1. Cover Page

2. Table of Contents

3. Exam Overview

4. Evaluation Guide

5. Scenario Initial Conditions Sheet

6. Scenario Validation Checklists

7. Reference and Task Tracking

8. Scenario Attributes Checklist Attachments

    -    NUTIMS Module Report
                                 ..    ,,*WkB,        A.

SECTION 3 EXAM OVERVIEW

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Exam Brief:

1. The plant is at 100% power, EOL, steady state operations with all control systems in automatic. The 'A" PORV is out of service due to an electrical short in the control circuitry.

After turnover CONVEX will direct the crew to begin an "Emergency Load Reduction" decreasing unit electrical output by 300 MwE. The crew will use AOP 3575, Rapid Downpower to accomplish this down power. The emergency boration valve, 3CHS*MV8104, will fail to open and the RO will have to use the RNO steps to achieve boration flow. Once the downpower is commenced, it will become evident that the Impulse Pressure Instrument, PT-505,is failed "as-is" (100% power value). Abnormal Rod motion will be one evidence of this failure. The crew should respond using AOP 3571, Instrument Failure Response, to defeat the failed channel input and address Tech Specs. The US may or may not choose to halt the downpower while dealing with this malfunction After discovery and mitigation of the PT-505 failure the B CCP pump will spuriously trip and will not restart. The crew will use AOP 3561, Loss of RPCCW, to verify alignment and start the C CCP pump on the B Train. After CCP flow is restored, the GEN Core Monitor Level Hi, MB7C, 4-5, will alarm. Annunciator response procedures will direct the crew to Trip the reactor and Go To E-0. At the time of the reactor trip a Main Steamline break will occur on the "B" S/G upstream of the MSIV and inside CTMT. When the Safety Injection actuation occurs, the B MDAFW Pump will fail to start but will start manually and the Turbine Driven AFW pump will not start. The A MDAFW pump will start but it's discharge valve is inadvertently shut. A PEO, if dispatched, will be able to find and open this valve. With initially only the B MDAFW pump running and Adverse CTMT, the crew will transition to FR-H.1, Loss of Heat Sink until it is determined that AFW flow is adequate. When the procedure calls for the RCPs to be tripped, the C RCP will not trip from MB4. The steam break is large enough that a Containment Depressurization Actuation (CDA) will eventually be required but will not automatically occur. The crew should recognize this and should manually initiate CDA [Critical Task]. The crew should carry out the actions of E-0 through step 17, transition to FR-H.1 and establish feedwater flow to at least one S/G [Critical Task], and eventually transition to E-2, Faulted Steam Generator Isolation. When CTMT Pressure is greater than 23 psia the crew should transition to FR-Z.1, Response to CTMT High Pressure, after FR-H.1 is addressed. The scenario will end when the crew has completed E-2 and made the decision to transition to E-1, Loss of Reactor or Secondary Coolant.

2. The SM should classify this event as a General Interest Event - Echo due Safety Injection in the Vessel but may achieve an Alert - C-1 if AFW is not restored within 15 minutes.

3. Plant/Simulator differences that may affect the scenario are: NONE

4. Duration of Exam: 60 minutes

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 I. Summary: Facility: Millstone 3 PWR: Scenario No: 2K2NRC-003 Op-Test No: 2K2 Examiners: Operators: Initial Conditions: IC-21; 100% power, end of life Event Malf. No. Event Type Event Description No: T N/A R(ALL) AOP 3575, Rapid Downpower 2 I/O 3CHS* C(RO) Emergency Boration Valve Fails to Open MV8104 3 RX16A I(RO / BOP) Pimp (PT-505) Instrument failed as-is 4 CC01B C(RO) B CCP Pump Trips 5 ANN I/O C(BOP) Generator Core Monitor Level Hi MB7C, 4-5 6 MS01 B M(ALL) Trip and Steam Break 7 FW21A C(BOP) AFW Pumps Fail to Provide Adequate Flow FW20B FW19 8 RP06A C(RO) CDA Fails to Automatically Actuate RP06B _ 3RCS* P1C C(RO) RCP Fails to Trip

• ( N ) ormal ( R ) eactivity ( I ) nstrument ( C ) omponent ( M ) ajor Section 7 Page 1 of 1

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Exam

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Assessor: Steve Jackson QUALITATIVE ATTRIBUTES Y__1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events. Y__2. The scenario consists mostly of related events. Y__3. Each event description consists of:

            -       the  point in the scenario when it is to be initiated
            -       the  malfunctions(s) that are entered to initiate the event
            -       the  symptoms/cues that will be visible to the crew
            -       the  expected operator actions (by shift position)
            -       the  event termination point (if applicable)

_Y_4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. _Y_5. The events are valid with regard to physics and thermodynamics. _Y_6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. _N/A_7. If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. _Y_8. The simulator modeling is not altered. _Y_9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure functional fidelity is maintained while running the scenario. _Y__10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered IAW Section D.4 of ES301 _Y_11. All individual operator competencies can be evaluated, as verified using form ES-301-6. _Y__12. Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5. (Form submitted with simulator scenarios). _Y__13. Level of difficulty is appropriate to support licensing decisions for each crew position. Section 8 Page 1 of 2

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.

01. Total Malfunctions (TM) - Include EM's- 5 to 8 required Total: 8 Main Generator Overheating, PT-505 failed 'as-is", 3CHS*MV8104 Fails to Open, "B" CCP Pump Trips, Main Steam Break, AFW Malfunctions (AFW Pump B Fail to auto start, AFW Pump A discharge valve shut, Terry Turbine Trip), CDA Auto Actuation Failure, RCP Fails to Trip from MB4

02. Malfs after EOP entry (EM's)- 1 to 2 required Total: 2 CDA Auto Actuation Failure, RCP Fails to Trip from MB4

03. Abnormal Events (AE)-2 to 4 required Total: 4 Rapid Downpower,, Main Generator Overheating, Instrument Failure Response (PT-505), AFW Malfunctions

04. Major Transients (MT)-1 to 2 required Total: 2 Main Steam Break, Loss of Auxiliary Feed

05. EOP's (EU) entered/requiring substantive actions 1 to 2 required Total: 1 E-0

06. EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to Total: 2 2 required FR-H.1, FR-Z.1

07. Critical Task (CT) - 2 to 3 required Total: 2 FR-H.1--E: Establish 530 gpm AFW flow to the SGs before bleed and feed is required.

E-O-E: Manually actuate CDA or start at least one Quench Spray Pump before transition out of E-0 to FR-H.1.

08. Approximate Scenario Run Time: 45 to 60 min. (One scenario may Total: 60 min approach 90 minutes)

09. EOP run time: Total: 30 min

10. Technical Specifications are exercised during the scenario. (YIN)-Y NOTES: Reactivity Manipulation: Downpower directed by Main Gen. ARP Section 8 Page 2 of 2

SECTION 4 EVALUATION GUIDE

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 All Control Room Conduct, Operations and Communications shall be in accordance with MP-14-MMM.

      "Review the Simulator Operating Limits(design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

Section 4 Page 1 of 49

SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide. Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:

1. Place the simulator in FREEZE if possible.

2. Announce to the Crew that there is a simulator problem.

3. Request that the Crew leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).

4. Deal with the problem (reboot, call STSB, etc.)

6. After the Instructors believe the simulator is restored to service, the Crew should be told how the exam will continue. If it is possible and felt to be acceptable to the evaluators, the examination can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.

6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.

7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.

Section 4 Page 2 of 49

    !'                                                            (                                                               ('

SECTIvN 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Simulator Setup Instructions:

1. HANG Exam Placards on the simulator doors.

2. START the Sun Workstation.

a. IF the Sun Workstation is running THEN go to SIM ACTIVE.

3. PLACE Recorder Power to ON.

4. VERIFY that the current approved training load is loaded.

5. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.

6. RESET to IC 91: TEMP IC 2K2NRC-LOUT-003 (based on IC 21)

7. ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.

8. PLACE Simulator to RUN.

9. ADJUST MWt using Turbine Load Set to 3411, (+)0, (-)3 IF using 100% power IC.

10. RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.

11. ENSURE Simulator fidelity items cleared.

a. CHECK the STEP COUNTERS at correct position for plant conditions.

b. PLACE 7 tiles under the DEMINS IN SERVICE lamacord label on MB6.

c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.

d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.

e. CLEAR DCS alarms on MB7 and BOP console.

Section 4 Page 3 of 49

(l ( SECTIuN 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

f. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-1 1), is NOT LIT.

g. ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.

1) See laminated directions on clipboard in Sim booth.

12. RESET Computer Terminals to At Power displays if 100% power IC.

a. MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F132 (40-120), CHS-L1 12 (40-80), CHS-F121 (40-80), RCS-L461 (40-80)

b. MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL-T412*, (585-588)

c. MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4

d. BOP Console (AY5A), BOP Picture 26, Circ Water

e. STA Console, (AY3), NSSS Picture 15, RCP Seals

13. RESET Rad Monitor Screen to Status Grid.

14. OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report hanging near instructor booth door).

15. IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under

     'Equipment OOS."

16. LOCK the Simulator Room front door.

17. HANG a Caution Tag on 3RCS*MV8000A stating, "Caution Tag 3RCS*MV8000A Closed and de-eneraized IAW Tech Spec 3.4.4, action b" Section 4 Page 4 of 49

( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K2NRC EXAM EQUIPMENT Initial Malfunctions 1/0 (RC) 3RCS*PCV455A A PORV OPEN - FALSE 1/0 (RC) 3RCS*PCV455A A PORV GREEN - FALSE 1/0 (RC) 3RCS*PCV455A A PORV RED - FALSE 1/0 (RC) 3RCS*MV8000 A PORV Block Valve GREEN - FALSE 1/0 (RC) 3RCS*MV8000 A PORV Block Valve RED - FALSE 1/0 (CV) 3CHS*MV8104 Emergency Boration Valve OPEN - FALSE I/O (RC) 3RCS* P1C RCP "C" STOP - FALSE MALF FW21A AFW Pump PlA Discharge Valve, V4, Closed MALF FW20B AFW Pump P1 B Fails to Auto Start MALF FW1 9 AFW Pump P2, Terry Turbine, Trips BTI MALF RP06A CDA Fails to Auto Actuate Train A MALF RP06B CDA Fails to Auto Actuate Train B MALF RX16A Turbine First Stage Pressure PT-505 Failure 78.7% "as-is" failure Section 4 Page 5 of 49

( (. SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Infoirmation/Activity Assign Expected Action Standard Event Malfunctions MALF CC01 B B CCP Pump Trips ACTIVE RSCU 2 ANN I/O MB7C, D5 Generator Core Monitor Level I High ON RSCU 3 ANN I/O MB7C, A3 H2 & Stator Cooling Sys Trouble ON RSCU 3 MALF MS01 B Main Steam Line "B" RuF)ture Inside Containment 100% 30 second ramp RSCU 4 Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew. Section 4 Page 6 of 49

l; ( SECTIkN 4 Lesson

Title:

STEAM LINE BREAK AND FR-H. 1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard EVENT 1: CONVEX ordered turnover + downpower 1 minute NOTE: Call as CONVEX and order Millstone Unit 3 to perform an "Emergency Load Reduction" of 300 MwE in the next 15 minutes due to Grid Instabilities. AOP 3575, Rapid Downpower, Rev. 7

• A CONVEX requested AOP 3575 emergency generation reduction Step 1 Action if crew chooses to increase should be completed within 15 NOTE power reduction rate due to perceived minutes of notification.

degrading conditions.

• If a unit shutdown is required, the

[Reactivity Manipulation] target power level should be between 20% and 25% reactor power.

• If at any time ROD CONTROL BANKS LIMIT LO - LO (MB4C 4

                                                                             - 9 ) annunciator is received, DO NOT go to AOP 3566, Immediate Boration. Immediately perform step 9.

CREW Determine Power Reduction Rate AOP 3575 (%/min). Step 1 Section 4 Page 7 of 49

( SECTiuN 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assign Expected Action Standard US Check desired power reduction rate - AOP 3575 LESS THAN OR EQUAL TO Step 1.a 5%/min. US Check power reduction CONVEX AOP 3575 REQUESTED Step 1.b CREW Perform load reduction at 5%/min AOP 3575 and Proceed to step 2 Step 1.c US Check Rod Control In AUTO. AOP 3575 Step 2 CREW Align EHC Panel AOP 3575 Step 3 US Check turbine OPERATING MODE - AOP 3575 MANUAL Step 3.a US Check LOAD LIMIT LIMITING light - AOP 3575 LIT Step 3.b BOP Intermittently Press DECREASE AOP 3575 LOAD pushbutton until LOAD LIMIT Step 3.c LIMITING light - NOT LIT BOP Rotate LOAD LIMIT SET adjust knob AOP 3575 at least one full turn in raise direction Step 3.d Select DECREASE LOADING RATE AOP 3575 to ON Step 3.e Section 4 Page 8 of 49

( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 RRevision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP Select LOAD RATE LIMIT % MIN to AOP 3575 required power reduction rate (% Step 3.f min) If at any time the power reduction AOP 3575 rate or target power level must be Step 4 changed, Return to step 1. NOTE US/RO Verify Power Reduction Rate AOP 3575 Step 4 RO Check power reduction rate 5% MIN AOP 3575 Step 4.a Check power reduction - REQUIRED AOP 3575 TO STABILIZE PLANT Step 4.b Proceed to Step 5 AOP 3575 Step 4.b RNO Initiate Rapid Boration AOP 3575 Step 5 Verify RCS makeup system in - AOP 3575 AUTO Step 5.a START one boric acid transfer pump AOP 3575 Step 5.b Section 4 Page 9 of 49

( SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T = initial 1/0 EVENT 2: Emergency Boration OPEN emergency boration valve AOP 3575 MALF Valve Fails to Open (3CHS*MV8104). Step 5.c 3CHS* MV8104, OPEN - FALSE RO Verify direct boric acid flow (3CHS-FI AOP 3575 183A) - INDICATED. Step 5.d Perform the following to initiate AOP 3575 gravity boration: Step 5.d RNO

1. Place the charging line flow control valve in MAN.

2. OPEN at least one gravity feed boration valve.

3. CLOSE at least one VCT outlet isolation valve.

4. Limit net charging flow to the RCS to LESS THAN 75 gpm (charging +

seal injection - RCP seal return).

5. Adjust charging line flow control valve as required.

6. Proceed to step 5.f.

Section 4 Page 10 of 49

( ( SEC ION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assign ExDected Action Standard Record time boration started AOP 3575 Step 5.f Time Energize all PZR heaters AOP 3575 Step 5.g Determine required boric acid AOP 3575 addition by multiplying total power Step 5.h change (A%) by 15(gal/%) = gal. Determine required time to borate by AOP 3575 dividing required gallons of boric acid Step 5.i by the direct boric acid flowrate (net charging flow rate if using gravity boration) min Check turbine load decrease - IN AOP 3575 PROGRESS OR COMPLETED Step 5.j Proceed to NOTE prior to Step 7 AOP 3575 Step 5.j RNO RO If a unit shutdown is being AOP 3575 performed, the final Mwe load should Step 7 be approximately 230 Mwe. NOTE Section 4 Page 11 of 49

( SEC fi ON 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US/BOP Initiate Load Reduction. AOP 3575 Step 7 BOP Check turbine OPERATING MODE - AOP 3575 MANUAL Step 7.a BOP Check rapid or gravity boration - IN AOP 3575 PROGRESS Step 7.b BOP Proceed to step 7.d. AOP 3575 Step 7.b RNO BOP Check LOAD RATE LIMIT % MIN set AOP 3575 at - 3% OR 5%.LIMITING light - LIT. Step 7.c BOP Utilizing DECREASE LOAD AOP 3575 pushbutton, Adjust LOAD SET to Step 7.d desired final Mwe (target power level) BOP Check power reduction - CONVEX AOP 3575 REQUESTED. Step 7.e US Inform CONVEX of load reduction AOP 3575 rate (Mwe/min) and final Mwe level. Step 7.e RNO BOP Maintain initial MVAR loading during AOP 3575 power reduction, unless directed Step 7.f otherwise. Section 4 Page 12 of 49

SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US/RO Check boration - IN PROGRESS AOP 3575 Step 7.g BOP The following step places one TD AOP 3575 FW pump in manual while allowing Step 8 the other TD FW pump to NOTE automatically unload during the downpower. US/BOP Align One Feedwater Pump For AOP 3575 Automatic Unloading Step 8 T = When EVENT 3: Pimp Failure "As-Is" US Do not leave the rod selector switch in AOP 3571 discovered AUTO while diagnosing a related Step 1 AOP 3571, Instrument Failure instrument failure unless the reason for CAUTION Response rod movement is a turbine runback. MALF NOTE: If the PT-505 "as-is" has not If a reactor trip occurs, immediately go AOP 3571 Step RX16A been discovered by the normal to E-0, Reactor Trip or Safety Injection. 1 NOTE 78.7% downpower due to the slow rate, MODIFY the malfunction to make it more identifiable. CREW Determine the initiating parameter AOP 3571 and place the affected controller in Step 1 MANUAL. CREW Stabilize the plant parameters. AOP 3571 Step 2 Section 4 Page 13 of 49

!' (' ( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US It is desired that l&C personnel trip the AOP 3571 bistables specified in this procedure. Step 3 If, during off-hours, I&C personnel are NOTE not able to trip the necessary bistables within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure. US Perform corrective actions using AOP 3571 appropriate attachment. Step 3 Instrument Failure Attachment Turbine Impulse Pressure Channel G Failure AOP 3571 Attachment G Rev. 7 US Turbine Impulse Pressure Channel Failure The following annunciators are symptoms of a PT-505 or 506 failure: HI T ERROR TAVE - TREF - MB4C 2-8 AMSAC NOT ARMED - MB4C 1-6 Section 4 Page 14 of 49

( SEC iiON 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Stadar TREF/AUCT TAVE DEVIAITON - MB4C 6-5 LO POWER AUTO ROD INTERLOCK C MB4D 6-4 TURB LOAD REJECTION ARM C MB4D 6-6 LO T ERROR TAVE - TREF - MB4D 4-1 TURBINE IMPULSE PRES > P MB4G 1, 2-2 BOP Defeat the failed channel by AOP 3571 selecting the alternate channel on Attachment first stage steam pressure channel G Step 1 selector switch (3MSS-PS505Z). BOP If C-7 is actuated, select RESET on AOP 3571 the steam dump mode selector. Attachment G Step 2 BOP Set steam generator pressure AOP 3571 controller (3MSS-PK507) to 1092 Attachment psig. G Step 3 BOP Place one condenser interlock AOP 3571 selector switch to OFF. Attachment G Step 4 Section 4 Page 15 of 49

( (. SEC- I ON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP Place the steam dump mode AOP 3571 selector in the STEAM PRESSURE Attachment mode. G Step 5 BOP Place both condenser interlock AOP 3571 selector switches to ON. Attachment G Step 6 RO Restore TAVE - TREF error to within IF AOP 3571 and Place rod control in AUTO. Attachment G Step 7 ANN I/O US Using OP 3350, "ATWS Mitigation AOP 3571 MB4C, System Actuation Circuitry," Place Attachment F8 AMSAC in Bypass. G Step 8 US Refer To 3TRM-7.2, Additional AOP 3571 Requirement, AMSAC. Attachment G Step 9 CREW When conditions have stabilized, AOP 3571 Observe MB annunciators and Attachment parameters. Immediately report any G Step 10 unexpected or unexplained conditions to the Shift Manager. US If the interlock (permissive annunciator AOP 3571 window) is in the required state for the Attachment existing plant conditions, no further G Step 11, actions are required (e.g., tripping of NOTE bistables). Section 4 Page 16 of 49

SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Us Within one hour, Perform the AOP 3571 following: Attachment G Step 11 Determine (by observation of the AOP 3571 associated permissive annunciator Attachment windows) if the interlock is in the G Step 1a required state for the existing plant conditions.

• RX OR TURBINE NOT AT POWER P-7 (MB4D 5-3)
• TURBINE NOT AT POWER P-13 (MB4D 6-3).

[Tech Specs] Refer to Technical Specification 3.3.1, AOP 3571 Action 8. Attachment 3.3.1, Functional Unit 17.b, Action 8 G Step 11 b TRM 7.2, Action 1 US Request l&C Department perform AOP 3571 corrective maintenance on failed Attachment instrument. G Step 12

• Check SG blowdown isolation valves - CLOSED
• Check SG blowdown sample isolation valves - CLOSED Section 4 Page 17 of 49

(. SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

• Check SG chemical feed isolation valves - CLOSED T+ AOP MALF EVENT 4: B RPCCW Pump Trips The Foldout Page must be open. AOP 3561 3575 Step 1, Reactivity CC01 B NOTE Manipulation Complete RO Verify RPCCW System Alignment. AOP 3561 Step 1 RO Check RPCCW pumps - AT LEAST ONE AOP 3561 RUNNING Step 1.a RO Check RPCCW pumps - ONLY ONE AOP 3561 RUNNING. Step 1.b RO Check the standby RPCCW pump - AOP 3561 ALIGNED TO THE AFFECTED TRAIN Step 1.c US Proceed to Attachment A. AOP 3561 Step 1.c, RNO RO START the standby RPCCW pump AOP 3561 Step 1.d RO Verify RPCCW heat exchanger SW inlet AOP 3561 isolation valves (3SWP*MOV50A or Step 1.e 3SWP*MOV50B) to the affected Train -

OPEN RO Check the CDS chiller on affected train - AOP 3561 Section 4 Page 18 of 49

SEC ION 4 K, Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard AUTO STARTED Step 1.g RO Check RPCCW containment supply and AOP 3561 return header isolation valves - OPEN Step 1.h RO Check RPCCW containment header AOP 3561 cross-connect valves - CLOSED Step 1.1 3CCP*AOV179A 3CCP*AOV179B 3CCP*AOV180A 3CCP*AOV1 80B CLOSE valves AOP 3561 Step 1.1, RNO RO Check Service Water to RPCCW Heat AOP 3561 Exchangers Step 2 Verify RPCCW heat exchanger SW inlet AOP 3561 isolation valves (3SWP*MOV50A and Step 2.a 3SWP*MOV50B) - OPEN. Section 4 Page 19 of 49

( SEC i iON 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T+ AOP ANN 1/0 EVENT 5: Generator Core Monitor 3561 STEP I actions MB7C, Level Hi addressed 4-5, ON MB7C, 1-3, ON RSCU #3 OP 3353 MB Annunciators, Rev. 6 Setpoint: Less than 50% MB7C, 4-5 NOTE: If the PEO is dispatched to the US Send operator to core monitor unit to OP H2 and Stator Cooling System panel, confirm alarm 3353.MB7C, 4-5, Step 1 DELETE MB7C, 1-3 and report a "Core Monitor" alarm on the Hydrogen Control Panel (TB 14') When "simulating" operating the core monitor re-enter MB7C, 1-3 & 4-5 (if previously cleared) NOTE: Report as the PEO that "When BOP MONITOR main generator temperatures OP the 'filter' pushbutton was depressed, 3353.MB7C, 4-the monitor trace returned to normal." 5, Step 2 Section 4 Page 20 of 49

( ( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assian Exnected Action Standard St n

                                                                                         -r US       IF monitor trace returns above alarm     OP setpoint while "FILTER" button is        3353.MB7C, 4-pressed PERFORM the following:           5, Step 1

1. NOTIFY ISO New England that the reactor will be tripped

2. TRIP reactor

3. Go To E-0, "Reactor Trip or Safety Injection" T = Manual MALF EVENT 6: Trip and Steam Break RO TRIP the reactor decision to MS01 B trip based on ARP RSCU #4 direction E-0, Reactor Trip or Safety Crew Go to E-0, Reactor Trip or Safety Injection, Rev. 21 Injection.

• Foldout page must be open E-0, Step 1, NOTE
• ADVERSE CTMT defined as GREATER THAN 180 0F or GREATER THAN 105 R/hr in containment.

Section 4 Page 21 of 49

( ( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assian Exnected Action Standard

• The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

RO Verify Reactor Trip E-0, Step 1

• Check reactor trip and bypass breakers - OPEN
• Check rod bottom lights - LIT
• Check neutron flux -

DECREASING BOP Verify Turbine Trip E-0, Step 2 Check all turbine stop valves - E-0, CLOSED Step 2.a BOP Verify Power to AC Emergency E-0, Step 3 Busses BOP Check busses 34C and 34D - AT E-0, LEAST ONE ENERGIZED Step 3.a BOP Check busses 34C and 34D - BOTH E-0, ENERGIZED Step 3.b US Check If Si Is Actuated E-0, Step 4 Section 4 Page 22 of 49

( SEC i iON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify Safety Injection Actuation EOP 35 E-0, annunciator - (MB4D 1-6 or MB2B 5-9) Step 4.a

                                                                          - LIT US      Check if Si is required                      E-0, Step 4, RNO

• CTMT pressure GREATER THAN 18 psia OR
• RCS pressure LESS THAN 1890 psia OR
• PZR level LESS THAN 16%

OR

• RCS subcooling LESS THAN 320F OR
• SG pressure LESS THAN 660 psig By observation of ESF Group 2 Status E-0, Panel lights, Verify both trains of Si - Step 4.b ACTUATED RO Verify Service Water Pumps - AT E-0, Step 5 LEAST ONE PER TRAIN RUNNING Section 4 Page 23 of 49

 !(                                                                                                           k.'

SEC , iON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify Two RPCCW Pumps - ONE E-0, Step 6 PER TRAIN RUNNING RO Verify ECCS Pumps Running E-0, Step 7

• Check SI pumps - RUNNING
• Check RHR pumps - RUNNING
• Check two charging pumps -

RUNNING EVENT 7: AFW Pumps Fail to BOP Verify AFW Pumps Running E-0, Step 8 Start NOTE: Terry Turbine has tripped, the Check MD pumps - RUNNING E-0, B AFW Pump has failed to Step 8.a automatically start, and the discharge valve on the A AFW Pump is closed. T = When DELETE [Critical Task] START pump(s) E-0, requested Step 8.a, as PEO MALF NOTE: If dispatched as PEO, RNO discover valve V4 on the A pump FW21A closed 5 minutes after dispatch. Call back and after receiving permission from US to open the valve AND crew has reached FR-H.1 step 3.h, remove the malfunction, FW21A. This will most likely be performed when in FR-H.1 Section 4 Page 24 of 49

SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assion Expected Action Standard Standard NOTE: B AFW Pump has failed to Check turbine - driven pump - E-0, automatically start. RUNNING, IF NECESSARY Step 8.b OPEN steam supply valves. E-0, Step 8.b, RNO BOP Verify FW Isolation E-0, Step 9

• Check SG feed regulating valves -

CLOSED

• Check SG feed regulating bypass valves - CLOSED
• Check FW isolation trip valves -

CLOSED

• Check MD FW pump - STOPPED
• Check TD FW pumps - TRIPPED
• Check SG blowdown isolation valves - CLOSED
• Check SG blowdown sample isolation valves - CLOSED
• Check SG chemical feed isolation valves - CLOSED NOTE: MSI should have occurred by BOP Check If Main Steam Lines Should E-0, Step 10 this point. Be Isolated Section 4 Page 25 of 49

( SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Check Ctmt pressure GREATER THAN E-0, 18 psia Step 10.a OR Any SG pressure LESS THAN 660 psig Proceed to Step 11 E-0, Step 10.a, RNO EVENT 8: Manually Actuate CDA RO Check if CDA Required E-0, Step 11 [Critical Task] Manually actuate CDA or start at least one Quench Spray Train before transition out of E-0, or at other appropriate procedural cues in the EOP network Check Ctmt pressure is GREATER E-0, THAN 23 psia Step 11.a OR Ctmt spray is initiated RO Verify quench spray initiated E-0, Step 11.b RO

• Check quench spray pumps -

RUNNING Section 4 Page 26 of 49

( SEC ION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H. 1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

• Check quench spray pump discharge valves (3QSS*MOV34A and 3QSS*MOV34B) - OPEN RO Initiate CDA. E-0, Step 11.b RNO RO IF CDA will NOT actuate, THEN RO 1. START quench spray pumps.

RO 2. OPEN quench spray pump discharge valves. Check RPCCW pumps - STOPPED E-0, Step 11.c RO STOP RPCCW pumps. E-0, Step 11.c, RNO BOP Check CAR fans - STOPPED E-0, Step 11.d BOP STOP CAR fans E-0, Step 11.d RNO BOP Check CRDM fans - STOPPED E-0, Step 11.e Section 4 Page 27 of 49

( SEC, iON 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP STOP CRDM fans E-0, Step 11.e, RNO T = Initial 1/0: EVENT 9: RCP Fails to Trip RO STOP all RCPs E-0, Malfunction 3RCS* Step 11.f Pic STOP - FALSE MALF NOTE: 3RCS* PlC will have to be RC09C tripped locally. when dispatched as PEO BOP STOP all main circulating water E-0, pumps Step 11.g US Verify ESF Group 4 lights - LIT E-0, Step 11.h Align component(s) as necessary for E-0, minimum safety function. Step 11.h RNO Proceed to step 13. E-0, Step 11.i RO Verify CIA E-0, Step 13 Section 4 Page 28 of 49

( ( SEC i iON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Check ESF Group 2 status columns 2 E-0, through 10 - LIT Step 13.a RO Verify Proper ESF Status Panel E-0, Step 14 Indication

• Verify ESF Group 1 lights - OFF
• Verify ESF Group 2 lights - LIT RO Determine If ADVERSE CTMT E-0, Step 15 Conditions Exist
• Ctmt temperature GREATER THAN 1800 F OR
• Ctmt radiation GREATER THAN 1 05 R/hr CREW DO NOT use ADVERSE CTMT E-0, parameters. Step 15, RNO RO Verify ECCS Flow E-0, Step 16 Check charging pumps - FLOW E-0, INDICATED Step 16.a RO Check RCS pressure - GREATER E-0, THAN 1650 psia (1950 psia ADVERSE Step 16.b CTMT)

Section 4 Page 29 of 49

/

A" SEC i iON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US Proceed to Step 16.d E-0, Step 16.b, RNO RO Check Si pumps - FLOW INDICATED E-0, Step 16.d RO Check RCS pressure - LESS THAN E-0, 300 psia (500 psia ADVERSE CTMT) Step 16.e Proceed to step 17. E-0, Step 16.e RNO BOP Verify Adequate Heat Sink E-0, Step 17 Check NR level in at least one SG - E-0, GREATER THAN 8% (42% ADVERSE Step 17.a CTMT) US Proceed to Step 17.d. E-0, Step 17.a, RNO BOP Control feed flow to maintain NR level - E-0, BETWEEN 8% and 50% (42% and Step 17.b 50% ADVERSE CTMT) US Proceed to Step 18. E-0, Step 17.c Section 4 Page 30 of 49

( ( ( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP Verify Total AFW Flow - GREATER E-0, THAN 530 gpm Step 17.d START pumps and Align valves as E-0, necessary Step 17.d IF AFW flow GREATER THAN 530 RNO gpm can NOT be established THEN Initiate monitoring of CSF Status Trees and Go To FR-H.1, Response to Loss of Secondary Heat Sink FR-H.1, Response to Loss of US If total feed flow is LESS THAN 530 FR-H.1 Secondary Heat Sink, Rev. 13 gpm due to operator action, DO NOT Step 1 PERFORM THIS PROCEDURE. CAUTION Feed flow must not be reestablished to any faulted SG if a non-faulted SG is available. BOP Check IF Secondary Heat Sink is FR-H.1 Required. Step 1 Verify RCS pressure - GREATER FR-H. 1 THAN ANY NON-FAULTED SG Step 1.a PRESSURE. Verify RCS hot leg W temperature - FR-H.1 GREATER THAN 3500 f. Step l.b Section 4 Page 31 of 49

SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Check Charging Pump Status - AT FR-H.1 LEAST ONE RUNNING. Step 2 US Steps 10. Through 14. (bleed and feed) FR-H.1 of this procedure must be immediately Step 3 initiated if either of the following occur: CAUTION W level in any 3 SGs is LESS THAN 29% (59% ADVERSE CTMT) OR PZR pressure is GREATER THAN OR EQUAL TO 2350 psia due to loss of secondary heat sink indicated by core exit TCs increasing. If offsite power is lost after SI reset, manual action to restart safeguards equipment may be required. If the recirculation spray pumps are required and have not started, DO NOT reset CDA. US Try to Establish AFW Flow to at FR-H.1 Least One SG. Step 3 RO Check SG blowdown isolation FR-H.1 Step 3.a RO

• Verify SG blowdown isolation valves - CLOSED Section 4 Page 32 of 49

( SECi iON 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO

• Verify SG blowdown sample isolation valves - CLOSED Verify AFW valve alignment - PROPER FR-H.1 EMERGENCY ALIGNMENT. Step 3.b DELETE [Critical Task] US/PEO Perform the following: FR-H. 1 FW21A Step 3.b NOTE: If dispatched as PEO, 1. Align valves as necessary to restore flow. RNO discover valve V4 on the A pump closed 5 minutes after dispatch. Call 2. Perform the applicable action:

back and after receiving permission

• IF flow is restored, THEN from US to open the valve remove the malfunction, FW21A but NOT before Proceed to Step 3.f.

step 3.h. BOP Verify DWST suction valves FR-H.1 (3FWA*AOV61A and 3FWA*AOV61 B) Step 3.c

                                                                          - OPEN.

BOP Verify DWST level - LESS THAN FR-H. 1 80,000 gal Step 3.d US Proceed to step 3.f and, IF DWST level FR-H. 1 decreases to LESS THAN 80,000 gal, Step 3.d THEN Perform step 3.e. RNO BOP Check MD pumps - RUNNING. FR-H. 1 Step 3.f Section 4 Page 33 of 49

( ( SEC; iON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP/US START pumps. FR-H.1 IF the pump(s) do NOT start, THEN Step 3.f RNO Restore power to the pumps (MB or locally). BOP Check turbine - driven pump - FR-H.1 RUNNING. Step 3.g OPEN steam supply valve(s). FR-H.1 IF the pump does NOT start, THEN Step 3.g RNO OPEN steam supply isolation valves: 3MSS*MOV1 7A 3MSS*MOV1 7B 3MSS*MOV1 7D DELETE [Critical Task] US Locally restore AFW flow using FR-H. 1 FW21A Attachment A, if required. Step 3.h NOTE: If dispatched as PEO, discover valve V4 on the A pump closed 5 minutes after dispatch. Call back and after receiving permission from US to open the valve remove the malfunction, FW21A Check total flow to SGs - GREATER FR-H. 1 THAN 530 gpm. Step 3.i Section 4 Page 34 of 49

(S (= SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US Perform the applicable action: FR-H.1

• IF no AFWflow is indicated, THEN Step 3.i RNO Proceed to Step 4.
• IF any AFW flow indicated, THEN Proceed to step 3.k.

Verify NR level in at least one SG is FR-H. 1 GREATER THAN 8% (42% Step 3.k ADVERSE CTMT). US Proceed to step 3.m. FR-H.1 Step 3.k RNO US Go to procedure and step in effect. FR-H.1 Step 3.1 BOP/RO Verify a secondary heat sink FR-H.1 established Step 3.m

• WR level in at least one SG -

INCREASING

• Core exit TCs - STABLE OR DECREASING BOP Maintain flow to restore NR level to FR-H. 1 GREATER THAN 8% (42% ADVERSE Step 3.n CTMT)

US Go to procedure and step in effect. FR-H.1 Step 3.o Section 4 Page 35 of 49

SECTION 4 ( Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assian Expected Action Standard St2ndz rd BOP Verify AFW Valve Alignment - E-0, Step 18 PROPER EMERGENCY ALIGNMENT RO Verify ECCS Valve Alignment - E-0, Step 19 PROPER EMERGENCY ALIGNMENT US Check Plant Status E-0, Step 20 NOTE: When asked, REPORT that Verify SLCRS doors - CLOSED E-0, "all SLCRS doors indicate closed." Step 20.a RO Check CONTROL BUILDING E-0, ISOLATION annunciator (MB4D 3-6) - Step 20.b LIT RO Check if CBI is required E-0, Step 20.b, RNO RO

• Ctmt pressure GREATER THAN 18 psia OR RO
• Control Building radiation monitor in alarm OR
• Si manually actuated RO IF CBI required, THEN initiate CBI.

Section 4 Page 36 of 49

SEC ION 4 I Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 RRevision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US IF CBI is NOT required, THEN proceed to Step 21. RO Verify ESF Group 2 CBI lights - LIT E-0, Step 20.c RO Align HVAC components as necessary E-0, for minimum safety function. Step 20.c, RNO BOP Verify control building purge supply E-0, fan and purge exhaust fan - NOT Step 20.d RUNNING BOP Perform the following: E-0, Step 20.d, RNO

• Stop purge supply fan.
• Stop purge exhaust fan.
• Locally Close instrument air isolations
• 31AS-V725 (CB 47' IRR stairwell)
• 31AS-V726 (CB 47' IRR stairwell)
• 31AS-V644 (CB 66'west wall)

Section 4 Page 37 of 49

C i' SEC iiON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

• Locally Close instrument air isolation valve for 3HVC-AOD134 BOP Control building air bank isolation E-0, valves - OPEN (after 60 seconds) Step 20.e BOP OPEN valves E-0, Step 20.e, RNO BOP IF at least one air bank isolation valve can NOT be opened, THEN Locally throttle Open at least one pair of air bank isolation bypass valves to maintain 0.125 inches water at Control Building AP indicator on VP1.
• 3HVC*V758 and 3HVC*V759 BOP STOP kitchen exhaust fan E-0, Step 20.f BOOTH NOTE When called, WAIT 3 - 5 min, Then PEO Close and Dog (as applicable) Control E-0, INST REPORT "All Control Building Building pressure boundary doors. Step 20.g pressure boundary doors are Closed and Dogged."

Section 4 Page 38 of 49

SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Check RCS Temperature E-0, Step 21 Verify RCS cold leg WR temperature - E-0, BETWEEN 5500 F and 5600 F Step 21.a US Perform the applicable action: E-0, Step 21.a, RNO

• IFtemperature is GREATER THAN 5500 F AND 5600F, THEN

1) Dump steam to the condenser, if available OR Dump steam to atmosphere.

US 2) Proceed to Step 22.

• IF the temperature is LESS THAN 550°, THEN proceed to Step 21c.

US Proceed to Step 22 E-0, Step 21.b BOP Maintain total feed flow BETWEEN 530 E-0, and 600 gpm until NR level is Step 21.c GREATER THAN 8% (42% ADVERSE CTMT) in at least one SG BOP CLOSE SG atmospheric dump and E-0, dump bypass valves Step 21.d Section 4 Page 39 of 49

( ( SECTION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Info rmation/Activitv Assign Expected Action Standard BOP Check the following valves - CLOSED E-0, Step 21.e

• MSIVs
• MSIV bypass valves US Perform the following: E-0, Step 21.e, RNO BOP Place both condenser steam dump E-0, interlock selector switches to OFF. Step 21.e.1, RNO BOP IF unexpected cooldown continues, E-0, THEN CLOSE the MSIVs and MSIV Step 21.e.2, bypass valves. RNO RO Check PZR Valves E-0, Step 22 Verify PORVs - CLOSED E-0, Step 22.a RO Verify normal PZR spray valves - E-0, CLOSED Step 22.b RO Verify PZR safety valves - CLOSED E-0, Step 22.c Check PORV block valves - OPEN E-0, Step 22.d Section 4 Page 40 of 49

( I (' SE i ION 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assign ExDected Action Standard Standard CREW To prevent damage to the RCP seal(s), E-0, seal injection flow should be Step 23, maintained to all RCPs. CAUTION RO Check If RCPs Should Be Stopped E-0, Step 23 RO Verify RCPs - ANY RUNNING E-0, Step 23.a US Proceed to Step 24 E-0, Step 23.a, RNO. BOP/RO Check If SG Secondary Boundaries E-0, Step 24 Are Intact Check pressure in all SGs E-0, Step 24.a

• NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
• NO SG COMPLETELY DEPRESSURIZED Ensure crew request activity samples BOP Initiate monitoring of CSF Status Trees E-0, with HP coverage and Go to E-2, Faulted Steam Step 24.a Generator Isolation RNO Section 4 Page 41 of 49

k SE6 iiON 4 Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assign Expected Action Standard TERMINATE UPON TRANSITION TO E-2, Faulted SIG Isolation FR-Z.1, Response to CTMT High US/RO Verify CIA (ESF Group 2 Status FR-Z.1, Pressure, Rev. 10 columns 2 Through 10) Step 1 [Critical Task] RO Initiate CIA OR reposition valves for FR-Z.1, NOTE: CDA has not automatically minimum safety function. Step 1 actuated. IF the crew has not RNO determined this prior to entering FR-Z.1, these RNOs should prompt them to actuate CDA. US Verify CIB FR-Z.1, Step 2 RO Check RPCCW Ctmt supply and return FR-Z.1, header isolation valves - CLOSED Step 2.a RO CLOSE valves. FR-Z.1, Step 2.a, RNO RO Check RPCCW pumps - STOPPED FR-Z.1, Step 2.b RO STOP pumps. FR-Z.1, Step 2.b, RNO Section 4 Page 42 of 49

( SECTION 4 (. Lesson

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Exoected Action Standard RO STOP all RCPs FR-Z.1, Step 2.c If ECA-1.1, Loss of Emergency FR-Z.1, Coolant Recirculation, is in progress, Step 3 Ctmt spray should be operated as CAUTION directed in ECA-1.1 rather than steps 3, 4, and 7 us Verify Quench Spray System FR-Z.1, Operation Step 3 RO Check RWST level - GREATER THAN FR-Z.1, 100,000 gal (annunciator RWST Step 3.a EMPTY QSS PP OFF on MB2A 5-2 not lit) RO Verify quench spray pumps - FR-Z.1, RUNNING Step 3.b [Critical Task] RO START pumps. FR-Z.1, Step3.b, RNO RO Verify quench spray pump discharge FR-Z.1, valves (3QSS*MOV34A and Step 3.c 3QSS*MOV34B) - OPEN [Critical Task] RO OPEN valves. FR-Z.1, Step 3.c, RNO Section 4 Page 43 of 49

( ( EVALUATION GUIDE (

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Check quench spray system - FLOW FR-Z. 1, EXISTS IN AT LEAST ONE TRAIN Step 3.d US Proceed to step 5. FR-Z.1, Step 3.e BOP STOP All Main Circulating Water FR-Z.1, Pumps Step 5 BOP Check Containment Ventilation FR-Z. 1, Step 6

• Verify CAR fans - STOPPED
• Verify CRDM fans - STOPPED BOP STOP fans. FR-Z.1, Step 6, RNO US Verify Recirculation Spray System FR-Z.1, Operation Step 7 RO Check CDA signal - PRESENT AFTER FR-Z.1, 11 minutes (annunciator CTMT Step 7.a RECIRC PUMP AUTO START SIGNAL on MB2B 1-8 lit)

US Proceed to step 8 and, WHEN 11 FR-Z.1, minutes have elapsed since CDA Step 7.a, initiation, THEN Perform steps 7b RNO through 7e. RO Verify recirculation spray pumps - FR-Z.1, RUNNING Step 7.b Section 4 Page 44 of 49

I EVALUAi iON GUIDE

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO WHEN Ctmt WR sump level is FR-Z.1, GREATER THAN 1.5 feed THEN Step 7.b, START pumps. RNO RO Verify recirculation spray pump suction FR-Z.1, isolation valves - OPEN Step 7.c RO OPEN valves. FR-Z.1, Step 7.c, RNO RO Verify recirculation spray pump FR-Z.1, discharge isolation valves - OPEN Step7.d RO OPEN valves. FR-Z.1, Step 7.d, RNO RO Verify recirculation spray - FLOW FR-Z.1, EXISTS IN AT LEAST ONE TRAIN Step 7.e RO Verify ESF Status Panel Group 4 FR-Z.1, Lights - LIT Step 8 CREW Operate components as necessary for FR-Z.1, minimum safety function. Step 8, RNO US/ BOP Verify Main Steam Line Isolation FR-Z.1, Step 9

• Check MSIVs and MSIV bypass valves - CLOSED Section 4 Page 45 of 49

EVALUA) iON GUIDE

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assiqn Expected Actions Standard

• Check ESF Status Group 3 lights -

LIT BOP Initiate MSI. FR-Z.1, Step 9, RNO BOP/RO Verify Main Feedwater Isolation FR-Z.1, Step 10

• Verify MD AND TD FW pumps -

TRIPPED

• Verify FW isolation trip valves -

CLOSED

• Verify SG feed regulating valves -

CLOSED

• Verify SG feed regulating bypass valves - CLOSED
• At least one SG must be FR-Z.1, maintained available for RCS Step 11, cooldown. CAUTION
• If all SGs are faulted, at least 100 FR-Z.1, gpm feed flow should be Step 11, maintained to each SG. CAUTION US Check If Auxiliary Feedwater Flow FR-Z.1, Should Continue To All SGs Step 11 BOP/RO Check pressure in all SGs FR-Z.1, Step 11.a Section 4 Page 46 of 49

(f ( 1: EVALUATION GUIDE

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

• NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
• NO SG COMPLETELY DEPRESSURIZED US Check Hydrogen Concentration FR-Z.1, Step 12 PEO Using OP 3313A, "Hydrogen FR-Z.1, Recombiners and Recombiner Building Step 12.a Ventilation," Start the hydrogen monitoring system US Verify hydrogen concentration - LESS FR-Z. 1, THAN 5% Step 12.b US Proceed to step 13. FR-Z.1, Step 12.b, RNO US Notify ADTS of Hydrogen FR-Z.1, Concentration Inside Containment Step 13 US Periodically Monitor Hydrogen FR-Z.1, Concentration (every 8 hours) Step 14 US Go to Procedure and Step In Effect FR-Z.1, Step 15 TERMINATE UPON TRANSITION TO E-2, Faulted SIG Isolation.

Section 4 Page 47 of 49

SECTION 4 ID Number: 2K2 NRC-003 Revision: 0 EVALUATION GUIDE I.

SUMMARY

The following Critical Tasks are covered in this exam: TASK DESCRIPTION TASK # K/A >/= 3.0 BASIS FOR SELECTION Manually actuate CDA or start E-0-E 026.A2.03 4.1/4.4 Failure to manually actuate at least one Quench Spray CDA or start at least one Pump before transition out of Quench Spray Train under E-0 to FR-H. 1. the postulated conditions constitutes a "demonstrated inability by the crew to recognize a failure/incorrect auto actuation of an ESF system or component." Establish 530 gpm AFW flow FR-H.1- 061.A3.01 4.2/4.2 Failure to establish the to the SGs before bleed and E minimum required feedwater feed is required. flow rate, under the postulated plant conditions, results in "adverse consequence(s) or a significant degradation in the mitigative capability of the plant" and represents a "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety. Note: ri Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide. Section 4 Page 48 of 49

SECTION 4

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 EVALUATION GUIDE Section 4 Page 49 of 49

SECTION 5 SCENARIO INITIAL CONDITIONS ID Number: 2K2 NRC-003 Revision: 0 Reactor Power: 100% Operating History: 450 days on line RCS Boron: 50 ppm Core Burnup: 18,600 MWD/MTU Condensate Demins: 7 demins in service Evolutions in Progress: NONE, A Train Protected, Intake Condition: GREEN Major Equipment OOS: "A" PORV is inoperable due to an electrical short in the control circuitry. It has been out of service for 8 hours. Electrical maintenance estimates that the valve will be returned to service within 24 hours. The following Tech Specs are applicable: Tech Spec 3.4.4, action b 3TRM 7.4.1 action a.1 and a.3 for both the A PORV and the block valve 3RCS*MV8000A Crew Instructions: Maintain present plant conditions Plant/Simulator Differences:

• Real Time and Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.
• Auto-log terminals need to be refreshed after entry is made.
• If not using the speed dial option on the phone system, the operator must dial either #3333 or #3334 to reach the person/department they desire.
• The following PPC programs do not function on the simulator:
• Samarium Follow
• Xenon Follow
• Sequence of Events Section 7 Page 1 of 1

SECTION 6 VALIDATION CHECKLIST

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 Remote functions: All remote functions contained in the guide are certified. Malfunctions: All malfunctions contained in the guide are certified. Initial Conditions: The initial condition(s) contained in the guide are certified or have been developed from certified IC's in accordance with NSEM-4.02. Simulator Operating Limits: The simulator guide has been evaluated for operating limits and/or anomalous response. Test Run: The scenario contained in the guide has been test run and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected. Examination Scenario Review The dynamic examination review checklist is complete. (This is not required unless the exam will be used as an Annual Exam, then NUREG 1021 requirements apply.) 6/10/02 Technical Reviewer Date Section 7 Page 1 of 1

SECTION 7 REFERENCE AND TASK TRACKING

Title:

STEAM LINE BREAK AND FR-H.1 ID Number: 2K2 NRC-003 Revision: 0 I.

References:

ARP MB7C, 3-7 Exciter Field Ground ARP MB7C, 4-5 Gen Core Monitor Level Hi AOP*3561 Loss of RPCCW AOP*3575 Rapid Downpower AOP*3571 Instrument Failure Response EOP*E-0 Reactor Trip or Safety Injection EOP*FR-H.1 Response to Loss of Secondary Heat Sink EOP*FR-Z.1 Response to CTMT Overpressure EOP*ERGEXE Westinghouse Owners Group Executive Document EOP* Step DOC MP3 step deviation Document EOP*ERG_HP Westinghouse Owners Group Background Document FAP06*01 Event Assessment, Classification and Reportability NUREG*1021 rev 8 Examiners Standards Section 7 Page 1 of 1

                                                                              .I-&

MILLSTONE NUCLEAR POWER STATION I LOIT NRC SIMULATOR EXAM GUIDE APPROVAL SHEET Exam

Title:

INTER-SYSTEM LOCA Revision: 0 ID Number: 2K2NRC-004 (SPARE) This document is the property of Millstone Power Station, which controls its distribution. Further transfer, copying, and modification of this document are strictly prohibited without the written consent of Millstone Power Station. MW N8'

SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER

1. Cover Page

2. Table of Contents

3. Exam Overview

4. Evaluation Guide

5. Scenario Initial Conditions Sheet

6. Scenario Validation Checklists

7. Reference and Task Tracking

8. Scenario Attributes Checklist Attachments

    -    NUTIMS Module Report I

I AM

                        'NA210 251'<"

F Il. 11 mI IMES -11 90 1111 MR pll '11%,

SECTION 3 EXAM OVERVIEW

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Exam Brief:

1. The plant is at 100% power, EOL steady state operations with all control systems in automatic. The "A" PORV is out of service due to an electrical short in the control circuitry.

After turnover the crew will shift running Charging Pumps as directed by the turnover per OP 3304A, Charging and Letdown, Section 4.4. After the normal evolution is complete, Power Range Nuclear Instrument (NI) Channel 42 Lower Detector will fail high. Inward rod motion will occur and the appropriate annunciators will alarm. Rod Control should be placed in manual and the crew should respond using AOP 3571, Instrument Failure Response. Once the failed channel has been defeated Tave will be restored by moving the rods if necessary before they are returned to automatic control. Once Tech Specs have been address for the failed NI channel, a leak will develop in the 6B Low Pressure Feedwater Heater. Feedwater Heater annunciators will alarm directing the crew to AOP 3567, Operation with one Feedwater Heater String Isolated. The B Heater Drain Pump will trip and the heater string will automatically isolate. The AOP response includes a plant downpower to 95% and verification of isolation of the heater string from the Control Room. Once the crew has confirmed isolation of the affected LP heater, a leak (tube failure) of Reactor Plant Component Cooling Water (CCP) into the Upper Oil Reservoir of the "B" RCP will occur. CCP Surge Tank level, though slight, will discernibly decrease and, after a few minutes of leakage, an Oil Reservoir high level alarm will sound. The crew should take action per the ARP and AOP 3554, RCP Trip or Stopping a RCP at Power to attempt to reduce reactor power and take the affected RCP out of service. The crew may judge that they cannot take the plant offline quickly enough to prevent RCP damage and elect to trip the plant. At the time of the trip, an Inter-System LOCA will occur. The crew should transition through E-0 to step 27 and then to ECA-11.2, LOCA Outside CTMT. At some point in the EOP network, depending on the speed of the crew, RCP trip criteria may be reached and should be implemented [Critical Task]. Si will actuate or be actuated normally except that ESF Building Ventilation (RHR area ACUs) will fail to start. When the SI cold leg injection valve (3SIH*MV8835) is closed, the break will be isolated [Critical Task]. The scenario will be terminated upon transition to E-1, Loss of Reactor or Secondary Coolant.

2. The SM should classify this event as a Site Area Emergency - Charlie Two due to a failure of two barriers (RCS & CTMT).

3. Plant/Simulator differences that may affect the scenario are: NONE

4. Duration of Exam: 60 minutes

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 Revision: 0

1. Summary:

Facility: Millstone 3 PWR: Scenario No: 2K2NRC-004 Op-Test No: 2K2 Examiners: Operators: Initial Conditions: IC-21; 100% power, end of life Event Malf. Event Event Description No: No. Type

• 1 None N(RO) Shift running CHS pumps using OP 3204A, Charging and Letdown, Section 4.4 2 N109B I(RO) or Power Range NI Channel 42 Lower Detector Fails High R(RO) 3 FW1 3N C(RO/ LP Feedwater 6B Heater Leak BOP)

R(ALL) 4 RC14B C(RO) RPCCW Leak into RCP B Upper Oil Reservoir R(ALL) Rapid Downpower per AOP 3575 5 S106A M(ALL) RCS to Si Inter-System LOCA S106B 6 RP11 D C(ALL) ESF Bldg Ventilation Fails to Automatically Actuate

• ( N ) ormal ( R ) eactivity ( I ) nstrument ( C) omponent ( M) ajor Section 7 Page 1 of I

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Assessor: Steve Jackson QUALITATIVE ATTRIBUTES Y__1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events. Y__2. The scenario consists mostly of related events. Y__3. Each event description consists of:

            -       the point in the scenario when it is to be initiated
            -       the malfunctions(s) that are entered to initiate the event
            -       the symptoms/cues that will be visible to the crew
            -       the expected operator actions (by shift position)
            -       the event termination point (if applicable)

Y__4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. Y__5. The events are valid with regard to physics and thermodynamics. _Y_6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. _N/A_7. If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. _Y_8. The simulator modeling is not altered. _Y_9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure functional fidelity is maintained while running the scenario. _Y__10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered IAW Section D.4 of ES301 _Y_11. All individual operator competencies can be evaluated, as verified using form ES-301-6. _Y__12. Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-5. (Form submitted with simulator scenarios). _Y__13. Level of difficulty is appropriate to support licensing decisions for each crew position. Section 8 Page 1 of 2

SECTION 8 MILLSTONE UNIT 3 SIMULATOR SCENARIO ATTRIBUTES CHECKLIST FORM ES-301-4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.

01. Total Malfunctions (TM) - Include EM's- 5 to 8 required Total: 5 Power Range NI Fails High, Leak in LP Feedwater Heater, RCP Hi Motor Temp (CCP Leak to Oil Reservoir), Inter-System LOCA,, ESF Auto Actuation Failure (ESF Bldg Ventilation)

02. Malf's after EOP entry (EM's)- 1 to 2 required Total: 2 ESF Auto Actuation Failure (ESF Bldg Ventilation), Inter-System LOCA

03. Abnormal Events (AE)-2 to 4 required Total: 4 Power Range NI Fails High, Operation with One Feedwater String Isolated, RCP Hi Motor Temp (CCP Leak to Oil Reservoir), ESF Auto Actuation Failure (ESF Bldg Ventilation)

04. Major Transients (MT)-1 to 2 required Total: 2 Rapid Downpower/Plant Trip, Inter-system LOCA

05. EOP's (EU) entered/requiring substantive actions 1 to 2 required Total: 1 E-O

06. EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to Total: 1 2 required ECA-1.2, LOCA Outside CTMT

07. Critical Task (CT) - 2 to 3 required Total: 2 ECA-1.2 -- A Isolate the LOCA outside containment before transition out of ECA-2.1 E.1-C Trip all RCPs before Orange Path

08. Approximate Scenario Run Time: 45 to 60 min. (One scenario may Total: 60 min approach 90 minutes)

09. EOP run time: Total: 30 min

10. Technical Specifications are exercised during the scenario. (Y/N)_Y_

NOTES: Reactivity Manipulation: Power Range High Failure/RCP High Temp Section 8 Page 2 of 2

SECTION 4 EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 All Control Room Conduct, Operations and Communications shall be in accordance with MP-14-MMM.

      "Review the Simulator Operating Limits(design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded." (NSEM 6.02)

Section 4 Page 1 of 55

SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a minimum negative impact on the Crew and the examinations we provide. Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator. As soon as the Instructors are aware of a simulator problem that will adversely affect the exam in progress (computer fault, etc.) the Instructor should:

1. Place the simulator in FREEZE if possible.

2. Announce to the Crew that there is a simulator problem.

3. Request that the Crew leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).

4. Deal with the problem (reboot, call STSB, etc.)

5. After the Instructors believe the simulator is restored to service, the Crew should be told how the exam will continue. If it is possible and felt to be acceptable to the evaluators, the examination can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If the examination will not begin where it left off, the crew should be told how and where the exam will begin again.

6. Once the Crew has been told how and where the exam will begin, have the crew conduct a brief so that the Instructor and evaluators can insure that the crew has all the necessary information to continue with the scenario.

7. Once all Crew members, Instructors and evaluators are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the evaluation session.

Section 4 Page 2 of 55

go(E ( SECTIUN 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Simulator Setup Instructions:

1. HANG Exam Placards on the simulator doors.

2. START the Sun Workstation.

a. IF the Sun Workstation is running THEN go to SIM ACTIVE.

3. PLACE Recorder Power to ON.

4. VERIFY that the current approved training load is loaded.

5. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.

6. RESET to IC-92: TEMP IC 2K2NRC-LOUT-004 (based on IC-21)

7. ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.

8. PLACE Simulator to RUN.

9. ADJUST MWt using Turbine Load Set to 3411, (+)0, (-)3 IF using 100% power IC.

10. RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.

11. ENSURE Simulator fidelity items cleared.

a. CHECK the STEP COUNTERS at correct position for plant conditions.

b. PLACE 7 tiles under the DEMINS IN SERVICE lamacord label on MB6.

c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.

d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.

e. CLEAR DCS alarms on MB7 and BOP console.

Section 4 Page 3 of 55

SECTIuN 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

f. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-1 1), is NOT LIT.

g. ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.

1) See laminated directions on clipboard in Sim booth.

12. RESET Computer Terminals to At Power displays if 100% power IC.

a. MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F132 (40-120), CHS-L1 12 (40-80), CHS-F121 (40-80), RCS-L461 (40-80)

b. MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL-T412*, (585-588)

c. MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4

d. BOP Console (AY5A), BOP Picture 26, Circ Water

e. STA Console, (AY3), NSSS Picture 15, RCP Seals

13. RESET Rad Monitor Screen to Status Grid.

14. OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report hanging near instructor booth door).

15. IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment OOS."

16. LOCK the Simulator Room front door.

Section 4 Page 4 of 55

SECTION 4 (, Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard 0 PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K2 NRC EXAM EQUIPMENT Initial Malfunctions 1/0 (RC) 3RCS*PCV455A A PORV OPEN - FALSE 1/0 (RC) 3RCS*PCV455A A PORV GREEN - FALSE 1/0 (RC) 3RCS*PCV455A A PORV RED - FALSE 1/0 (RC) 3RCS*MV8000A A PORV Block Valve GREEN - FALSE 1/0 (RC) 3RCS*MV8000A A PORV Block Valve RED - FALSE MP&LF S106A RCS to Inter-System LOCA 100% BT1 MAkLF S106B RCS to Inter-System LOCA (isolable) 100% BT1 MA1LF RP11 D Failure of Automatic Actuation of ESF Bldg. Ventilation Event Malfunctions MALLF N109B Power Range NI Channel 42 Lower Detector Fails High I 100% 15 second ramp RSCU #1 MAKLF FW13N Low Pressure Feedwater Heater E6 Leak 100% 15 second ramp RSCU #2 MAkLF RC14B RCP B Upper

                                    ,     Oil Reservoir
                                                    ,   Coolina Water

_ Leak 100% No ramp RSCU #3 Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew. Section 4 Page 5 of 55

SECTION 4 ( Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T=0 EVENT 1: Shifting Charging Starting/Shifting Charging Pumps OP 3304A, Pumps Step 4.4 OP 3304A, Charging and Letdown, This Section Contains EOP Related Rev. 28-01 Material [Normal Evolution] US A computer display, showing all data OP 3304A, relevant to the operation of the pump Step 4.4.1 being started, should be used. NOTE US IF the associated alternate minimum OP 3304A, flow relief valves (3CHS*RV851 OA or Step 4.4.1 3CHS*RV851OB) lift, REQUEST IST to perform required testing and inspections. (a Ref. 6.4.6) US/ RO/ IF starting or shifting to 3CHS*P3A, OP 3304A, PEO charging pump A, PERFORM the Step 4.4.4 following: a) Refer To OP 3330D, "Charging Pump Cooling," and VERIFY charging pump cooling water is in operation for 3CHS*P3A, charging pump A. Section 4 Page 6 of 55

( I SECTiON 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard NOTE: Throughout this procedure, PEO b) For 3CHS*P3A, charging pump A, when asked for local indications, all CHECK lube oil reservoir level is indications are normal as per between 1/3 and 2/3 full using procedure. 3CHS*LG1A, A lube oil reservoir site glass on pump (local). PEO c) PLACE 3CHS*P6A, charging pump A auxiliary lube oil pump in "AUTO," (local). d) To align charging pump minimum flow recirculation valves for 3CHS*P3A, charging pump A, OPEN the following (MB3): RO

• 3CHS*MV811 1A, "RECIRC DIS" RO
• 3CHS*MV8110, "RECIRC HDR ISOL" RO e) VERIFY a flow path from one of the following sources to the charging pumps:
• VCT
• RWST
• Boric acid tanks RO f START 3CHS*P3A, "CHG PP A,"

(MB3). Section 4 Page 7 of 55

g f ( SECTiuN 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO g) VERIFY minimum recirculation flow of 60 gpm as indicated on 3CHS-F75 (computer) or SHUTDOWN pump. US/ RO h) IF any of the following conditions occur during the operation of the pump, SHUTDOWN the charging pump:

• Pump operation changes from smooth to rough
• Oil temperature leaving the thrust bearing exceeds 1550F (local)
• Discharge pressure drops suddenly as indicated on 3CHS*PI 117 (local)
• Auxiliary lube oil pressure drops less than 15 psi (local)
• Pump running current exceeds 88 amps (MB3)

US/ PEO i) CHECK the following parameters (locally): Section 4 Page 8 of 55

SECTION 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDAIMalf Instructor Information/Activity Assign Expected Action Standard

1) WHEN oil discharge pressure is greater than 8 psig as indicated on 3CHS*PI 1023A, VERIFY appropriate auxiliary lube oil pump automatically stops.

2) CHECK 3CHS-TI 1021A, auxiliary lube oil bearing outlet temperatures, are less than 1550 F (local).

3) CHECK 3CHS-PI 1023A, auxiliary lube oil filter outlet pressure, between 15 psig and 18 psig.

4) CHECK differential pressure between 3CHS-PI 1024A, auxiliary lube oil filter (3CHS*FLT1 1A) inlet, and 3CHS-PI 1023A, auxiliary lube oil filter (3CHS*FLT1 1A) outlet, pressure indicators between 3 psid and 10 psid.

RO k) CHECK the following annunciators, not lit:

• MB3A 2-7, "CHARG PP A MOTOR TEMP Hi"
• MB3A 3-7, "CHARG PP A LUBE OIL PRESSURE LO" Section 4 Page 9 of 55

( ( SECTION 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDAIMalf Instructor Information/Activity Assign ExDected Action Standard

• MB3A 5-9, "CHARG PP AUTO TRIP/OVERCURRENT"
• MB3B 3-1, "CHARG PP A OIL COOLER FLOW LO"
• MB3B 4-1, "CHARG PP A OIL COOLER TEMP Hi" BOP I) VERIFY the following charging pump cubicle dampers positioned as required (VP1):

The ventilation supply lines to the OP 3304A, charging pump cubicles are isolated in Step 4.4.4.1 winter mode; no supply flow will occur NOTE when the inlet MODs are open.

• 3HVR*MOD50A, ventilation supply, opened
• 3HVR*MOD49A, ventilation exhaust, opened RO m) IF the charging pump was started for the purpose of shifting charging pumps, PERFORM the following:

RO 2) STOP the desired charging pump. RO 3) PLACE the applicable control switch to "AUTO." Section 4 Page 10 of 55

( ( SECTIuN 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard-RO 4) Refer To SP 3601 F.3," RCS Leakage-Controlled Leakage to RCP Seals," and PERFORM leakage determination. BOP n) WHEN the applicable pump is stopped, VERIFY the following applicable charging pump cubicle dampers positioned as required (VP1): us The ventilation supply lines to the OP 3304A, charging pump cubicles are isolated, Step 4.4.4.n therefore no supply flow will occur NOTE when the inlet MODs are open. BOP 1) IF charging pump 3CHS*P3B was stopped, VERIFY the following closed:

• 3HVR*MOD50B, ventilation supply
• 3HVR*MOD49B, ventilation exhaust US/ PEO o) For the charging pump stopped, VERIFY the appropriate auxiliary lube oil pump automatically started:

CHS PUMP LUBE OIL PUMP INDICATOR 3CHS*P3B 3CHS*P6B 3CHS*PI 1023B Section 4 Page 11 of 55

( ( SECTION 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Standard T=CHS MALF EVENT 2: PR NI 42 UPPER pump shift N109B DETECTOR FAILS HIGH complete 100% 15sec ramp RSCU #1 AOP 3571, Instrument Failure US Do not leave the rod selector switch in AOP 3571 Response, Rev.7 AUTO while diagnosing a related Step 1 instrument failure unless the reason for CAUTION rod movement is a runback. [Reactivity Manipulation - potential] US If a reactor trip occurs, immediately go to AOP 3571 E-0, Reactor Trip or Safety Injection. Step 1 NOTE or [instrument Malfunction - potential] RO Determine the initiating parameter AOP 3571 and place the affected controller in Step 1 MANUAL. CREW Stabilize the plant parameters. AOP 3571 Step 2 Section 4 Page 12 of 55

( I SECTION 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US It is desired that I&C personnel trip the AOP 3571 bistables specified in this procedure. If, Step 3 NOTE during off-hours, I&C personnel are not able to trip the necessary bistables within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure. US Perform corrective actions using AOP 3571 appropriate attachment. Step 3 Instrument Failure Attachment Power Range Nuclear Instrument D Channel Failure AOP 3571 Rev. 7 Attachment D US Power Range Nuclear Instrument Channel Failure The following annunciators are symptoms of a PZR pressure instrument failure: PRESSURIZER PRESSURE HI MB4A 3-4 PRESSURIZER PORV CHANNEL MB4A 4-3 PRESSURE HI Section 4 Page 13 of 55

SECtIuN 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard PRESSURIZER PRESSURE MB4A 4-4 DEVIATION PRESSURIZER PRESSURE LO MB4A 5-4 PZR RELIEF VALVE DIS TEMP HI MB4A 3-5 PRESSURIZER Si CHANNEL MB4A 5-3 PRESSURE LO PZR REL TK TEMP HI MB4A 2-2 PZR REL TK LEVEL HI-HI/HI/LO MB4A 2-3 PZR REL TK PRESSURE HI MB4A 2-4 PZR PRES LO MB4F 1,2,3,4-3 PZR PRES HI MB4F 1,2,3,4-4 LOOP 1,2,3,4 OVR TEMP AT MB4F 1,2,3,4-5 LOOP 1,2,3,4 OVR TEMP AT MB4F 1,2,3,4-7 PZR PORV PRES HI MB4F 1,2,3,4-13 PZR PRES LO MB2D 1,2,3,4-5 Section 4 Page 14 of 55

( ( SECTIUN 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard PZR PRES HI MB2D 1,2,3-6 Failure of two or more channels of PR AOP 3571 instrumentation may prevent P-10 from Attachment D resetting when power is reduced below Step 1 10%. If P-10 fails to reset, the following CAUTION automatic reactor trip signals are lost:

1. SR HIGH FLUX TRIP (105 CPS)

2. IR HIGH FLUX TRIP (25%)

3. PR HIGH FLUX LOW STPT TRIP (25%)

• The reactor operator must remain alert to any power increases which would necessitate a manual reactor trip.
• The Gamma Metrics Nuclear Instrumentation System shall be used during the reactor shutdown in lieu of the source range channels.

RO Defeat the failed channel input. AOP 3571 Attachment D Step 1 Section 4 Page 15 of 55

( ( SECTION 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian Exnected Action Standard_ I At the detector current comparator AOP 3571 drawer, Turn the following switches to Attachment D the failed channel: Step 1a Rod Stop Bypass Upper Section Lower Section Power Mismatch Bypass. At the comparator and rate drawer, Turn AOP 3571 the following switch to the failed channel: Attachment D Step 1b Comparator Channel Defeat. RO Restore TAVE - TREF error to within 1VF AOP 3571 and Place rod control in automatic. Attachment D Step 2 CREW When conditions have stabilized, AOP 3571 observe MB board annunciators and Attachment D parameters and immediately report Step 3 any unexpected or unexplained conditions to the Shift Manager. US Determine which Reactor Protection AOP 3571 System bistable (s) requires tripping: Attachment D Step 4 Place a check mark in the box above the AOP 3571 appropriate channel that requires tripping Attachment D on the last page of this Attachment. Step 4a Section 4 Page 16 of 55

SECTION 4 ( Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard [Tech Specs] Refer to Technical Specification 3.3.1 AOP 3571 and 4.2.4.2 and 4.2.1.1.1.b. Attachment D LCO 3.3.1 (FU2) Step 4b SURV 4.2.4.2 NOTE: 4.2.1.1.1.b. not required if the crew removes the affected channel from the AFD computer per AOP 3571, Att. D, steps 6 & 7 Check the existing bistable status to AOP 3571 ensure a reactor trip will not occur when Attachment D the failed channel is tripped. Step 4c Remove the appropriate control power AOP 3571 fuses for the affected channel. Attachment D Step 4d REMOTES NOTE: When requested act as l&C Request the l&C Department trip the AOP 3571 See Technician and trip bistables. appropriate bistables using Attachment Attachment D column 3 D and Attachment S. Step 4e REMOTES RXR107 Door Open RXR02 OTDT 421 C RXR06 OTDT 421 D RXR107 Door Closed Section 4 Page 17 of 55

( ( SECTiUN 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Verify the appropriate bistable status AOP 3571 lights are lit. Attachment D Step 4f NOTE: If at any time during the US Within one hour, Determine by AOP 3571 performance of this procedure, if observation of the associated Attachment D asked, as Reactor Engineering or Unit permissive annunciator window (s) Step 5 Management, advice that NI power that the following interlocks are in should be used to determine reactor their required state for the existing power. plant condition (Tech, Spec. 3.3.1, Action 8):

• Rx or turbine not at power P-7 (MB4D 5-3)
• Three loop permissive P-8 (MB4D 3-3)
• NIS power range P-9 permissive (MB4D 6-1)
• Reactor at power P-10 (MB4D 4-3).

US / Perform the following to remove the AOP 3571 CREW affected power range input to the AFD Attachment D computer (Program 3R5): Step 6 On the plant process computer, Select AOP 3571 the NSSS menu, page 2. Attachment D Step 6a Section 4 Page 18 of 55

( ( SECTIUN 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard At the NSSS menu, Select "Tilting AOP 3571 Factors" (F9). Attachment D Step 6b Press the key (F5 through F8) that AOP 3571 corresponds to the channel to be Attachment D removed. Step 6c US Within one hour, if step 6 has not AOP 3571 been performed, Refer to T/S Attachment D Surveillance Requirement 4.2.1.1.1.b. Step 7 US Request l&C Department perform AOP 3571 corrective maintenance on failed Attachment D instrument. Step 8 T=NI failure MALF EVENT #3: LP Feedwater Heater 6B complete and FW13N Leak reactivity manipulation RSCU #2 complete. AOP 3567, Operation With One CREW When removing a feedwater heater AOP3567 Feedwater Heater String Isolated, Rev from service during turbine operation, Step 1 4 closely monitor turbine vibration, CAUTION differential expansion, nuclear power, and feedwater heater temperatures and pressures. [Reactivity Manipulation] CREW Decrease Reactor Power To EQUAL AOP3567 TO OR LESS THAN 95% Step 1 Section 4 Page 19 of 55

( ( SECTION 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard NOTE: The leak is in LP Feedwater CREW Identify Faulted Feedwater Heater AOP3567 Heater E6B (6 th Point, B Train) String Step 2

• Check feedwater heater levels -

HIGH (with proper LCV operation) NOTE: If PEO dispatched, report

• Check feedwater heater - NOISE abnormal noise and vibration AND VIBRATION
• Check feedwater heater performance - DEGRADED BOP OPEN Feedwater Heater Bypass AOP3567 Valve For The Affected Feedwater Step 3 Heaters NOTE: This valve will be open For the low pressure heaters (3CNM-MOV88)

NOTE: This valve will be closed For the 1st point heaters (3FWS-MOV17) BOP Check 1st Point Feedwater Heater AOP3567 Bypass Valve (3FWS-MOVI 7) - Step 4 OPEN US Proceed to step 7. AOP3567 Step 4 RNO BOP Check LP Feedwater Heater Bypass AOP3567 Valve (3CNM-MOV88) - OPEN Step 7 Section 4 Page 20 of 55

SECTION 4 Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US Isolate Steam Supply and Drains For AOP3567 LP Feedwater Heaters Step 8 BOP Check affected low pressure feedwater AOP3567 heater string extraction steam supply Step 8.a valves - CLOSED For String A For String B For String C 3ESS-MOV29A (E2A) 3ESS-MOV29B (E2B) 3ESS-MOV29C (E2C) 3ESS-MOV38A (E3A) 3ESS-MOV38B (E3B) 3ESS-MOV38C (E3C) 3ESS-MOV47A (E4A) 3ESS-MOV47B (E4B) 3ESS-MOV47C (E4C) BOP CLOSE valves. AOP3567 Step 8.a RNO BOP Check affected low pressure feedwater AOP3567 heater string extraction steam drain Step 8.b valves - OPEN For String A For String B For String C 3DTM-AOV46A (E2A) 3DTM-AOV46B (E2B) 3DTM-AOV46C (E2C) 3DTM-AOV47A (E3A) 3DTM-AOV47B (E3B) 3DTM-AOV47C (E3C) Section 4 Page 21 of 55

a SECTI1uN 4 ( Lesson

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard ll 3DTM-AOV49A (E4A) I3DTM-AOV49B (E4B) I3DTM-AOV49C (E4C) BOP OPEN valves. AOP3567 Step 8.b RNO IF the low pressure feedwater heater string extraction steam drain valves will NOT open, THEN Open affected low pressure feedwater heater string extraction steam drain bypass valves using Attachment C. BOP Verify Affected SG Blowdown Flash AOP3567 Tank Vent - CLOSED Step 9 For heater E4A 3BDG-MOV21A For heater E4B 3BDG-MOV21 B For heater E4C 3BDG-MOV21 C BOP CLOSE valves. AOP3567 Step 9 RNO Section 4 Page 22 of 55

( SECTIUN 4 ( Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP If a heater drain tank pump is stopped AOP3567 with the Main Feed System in Step 10 operation, closely monitor the main NOTE feed pump suction pressure, discharge pressure, and flow rate for abnormalities. NOTE: See attached ARP MB6A, 5-7, BOP Verify Affected 4th Point Heater AOP3567 to direct PEO actions on Heater Drain Drain Pump - TRIPPED Step 10 Pump trip. BOP STOP pump. AOP3567 Step 10 RNO CREW Complete Isolation Of Feedwater AOP3567 Heater String Step 11 BOP Check affected heater outlet isolation AOP3567 valve - CLOSED Step 11.a For string A 3CNM-MOV70A BOP CLOSE valves. AOP3567 Step 11.a RNO BOP Check affected heater inlet isolation AOP3567 valve - CLOSED Step 11.b Section 4 Page 23 of 55

i SECTION 4 ( Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard For string A 3CNM-MOV49A BOP CLOSE valves. AOP3567 Step 11.b RNO NOTE: Objective of the procedure met. CREW Perform Local Isolation of Affected AOP3567 Consult with Lead Examiner and LP Feedwater Step 12 proceed ahead to Event 4. US Dispatch an operator to Perform the AOP3567 local actions to isolate the affected Step 12.a feedwater heater string using Attachment B US WHEN the local actions specified in AOP3567 Attachment B are complete, THEN Step 12.b Proceed to step 13 Following the performance of the AOP3567 proceeding steps, the affected Step 13 feedwater heater string is sufficiently NOTE isolated for continued power operation. CREW Verify MB Annunciators And AOP3567 Parameters - AS EXPECTED Step 13 Immediately notify the Shift Manager of AOP3567 any unexplained or unexpected Step 13 conditions. RNO Section 4 Page 24 of 55

( ( SECTION 4 Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard CREW Perform Follow-up Actions: AOP3567 Step 14 CREW If desired, increase reactor power to AOP3567 100% Step 14.a US Repair affected feedwater heater string AOP3567 Step 14.b CREW Restore the affected 1st point AOP3567 feedwater heater to service by Step 14.c performing the following: Using OP 3321, "Main Feedwater," AOP3567 Place the tube side of the affected HP Step 14.c 1) feedwater heater in service Using OP 3320, "Feedwater Heater AOP3567 Drains and Vents," Place the shell side Step 14.c 2) of the affected HP feedwater heater in service US Notify Plant Engineering (ISI Group) AOP3567 that the LP feedwater heater bypass Step 14.d line or the HP feedwater heater bypass line (MP3 Erosion/Corrosion Program low usage lines) has been placed in service Section 4 Page 25 of 55

SECTiuN 4 (' Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T= AOP 3567 MALF EVENT 4: RPCCW Leak into RCP substantially RC14B B Upper Oil Reservoir complete 100% AND Examiner's RSCU #3 Cue. NOTE: The reservoir high level alarm RO Check RCS-L477A, RCP C upper oil OP 3353.MB4B will sound after the malfunction has reservoir level computer point, to confirm Step 1 been in about 4 minutes. alarm. CREW MONITOR the following RCP C OP 3353.MB4B computer points: Step 2

• RCS-T481A, RCP C upper thrust bearing temperature
• RCS-T481 B, RCP C upper thrust bearing temperature
• RCS-T485A, RCP C upper thrust bearing temperature RO IF at any time RCP C thrust bearing or OP 3353.MB4B radial bearing temperature computer Step 3 point is greater than 1950 F PERFORM the following:
• TRIP reactor
• STOP RCPC Section 4 Page 26 of 55

( ( SECTIoN 4 Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard

• Go To E-0 US CHECK 3CCP-LI20B, RPCCW surge OP 3353.MB4B tank level, for indication of RPCCW Step 4 leakage.

US The following steps requires OP 3353.MB3B containment entry. ALARA Step 5 CREW IF directed by the SM/US CHECK for OP 3353.MB3B RPCCW to RCP C lube oil leak. Step 5 US Refer to Tech Specs and DETERMINE OP 3353.MB3B LCOs Step 6 AOP 3554, Stopping an RCP at RO Check RCP Status - ALL PUMPS AOP 3554 Power, Rev. 6 RUNNING. Step 1 RO Check Reactor Power. AOP 3554 Step 2 Verify THREE LOOP PERMISSIVE P-8 AOP 3554 annunciator (MB4D 3-3) - LIT. Step 2.a NOTE: The rate at which temperature Go to one of the following to reduce AOP 3554 is increasing should inspire the crew power: Step 2.a to use the Rapid Downpower RNO

l. AOP 3575, "Rapid Downpower

• OP 3204, "At Power Operation" Section 4 Page 27 of 55

( ( SECTION 4 Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard AOP 3575, Rapid Downpower, Rev.7

• A CONVEX requested AOP 3575 emergency generation reduction Step 1 should be completed within 15 NOTE minutes of notification.
• If a unit shutdown is required, the

[Reactivity Manipulation] target power level should be between 20% and 25% reactor power.

• If at any time ROD CONTROL BANKS LIMIT LO - LO (MB4C 4

                                                                        - 9 ) annunciator is received, DO NOT go to AOP 3566, Immediate Boration. Immediately perform step 9.

CREW Determine Power Reduction Rate AOP 3575 (%/min). Step 1 Us Check desired power reduction rate - AOP 3575 LESS THAN OR EQUAL TO Step 1.a 5%/min. US Check power reduction CONVEX AOP 3575 REQUESTED Step 1.b US Proceed to Step 1.d. AOP 3575 Step 1.b RNO Section 4 Page 28 of 55

( (. SECTIUN 4 Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard CREW Determine power reduction rate AOP 3575 using Table. Step 1.d Total Power Change (A%) 10% 20% 30% 40% 50% 60% 60/a 70% 70% 1 1- - 20% - 30% 40%

• 50% * +

15 1 3 3 3 5 5 5 30 0.5 1 1 3 3 3 3 45 0.5 0.5 1 1 3 3 3 60 0.5 0.5 1 1 1 3 Time to 75 0.5 0.5 1 1 1 1 Reduce 90 0.5 0.5 0.5 1 1 1 Power 105 0.5 0.5 0.5 0.5 1 1 (min) 120 0.5 0.5 0.5 0.5 1 135 0.5 0.5 0.5 0.5 1 150 0.5 0.5 0.5 0.5 0.5 160 16I. 0.5 0.5 0 505I. 0.5 0.5 0.5 US Check Rod Control In AUTO. AOP 3575 Step 2 Section 4 Page 29 of 55

SECTuJN 4 ( Exam

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard CREW Align EHC Panel AOP 3575 Step 3 US Check turbine OPERATING MODE - AOP 3575 MANUAL Step 3.a US Check LOAD LIMIT LIMITING light - AOP 3575 LIT Step 3.b BOP Intermittently Press DECREASE AOP 3575 LOAD pushbutton until LOAD LIMIT Step 3.c LIMITING light - NOT LIT BOP Rotate LOAD LIMIT SET adjust knob AOP 3575 at least one full turn in raise direction Step 3.d Select DECREASE LOADING RATE AOP 3575 to ON Step 3.e BOP Select LOAD RATE LIMIT % MIN to AOP 3575 required power reduction rate (% Step 3.f min) If at any time the power reduction AOP 3575 rate or target power level must be Step 4 changed, Return to step 1. NOTE US/RO Verify Power Reduction Rate AOP 3575 Step 4 RO Check power reduction rate 5% MIN AOP 3575 Step 4.a Section 4 Page 30 of 55

EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) FRevision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Check power reduction - REQUIRED AOP 3575 TO STABILIZE PLANT Step 4.b Proceed to step 5. AOP 3575 Step 4.b RNO RO Initiate Rapid Boration AOP 3575 Step 5 Verify RCS makeup system in - AOP 3575 AUTO Step 5.a START one boric acid transfer pump. AOP 3575 Step 5.b OPEN emergency boration valve AOP 3575 (3CHS*MV8104). Step 5.c RO Verify direct boric acid flow (3CHS-FI AOP 3575 183A) - INDICATED. Step 5.d OPEN charging line flow control AOP 3575 valve, to match boric acid flow Step 5.e (3CHS-FI 183A) RO Record time boration started AOP 3575 Step 5.f Time Energize all PZR heaters. AOP 3575 Step 5.g Section 4 Page 31 of 55

( ( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activitv Assian Expected Actions Standard Determine required boric acid AOP 3575 addition by multiplying total power Step 5.h change (A%) by 15 (gal/%) = gal. Determine required time to borate by AOP 3575 dividing required gallons of boric acid Step 5.i by the direct boric acid flowrate (net charging flow rate if using gravity boration) min. US Check turbine load decrease - IN AOP 3575 PROGRESS OR COMPLETED. Step 5.j US Proceed to NOTE prior to Step 8. AOP 3575 Step 5.k BOP The following step places one TD AOP 3575 FW pump in manual while allowing Step 8 the other TD FW pump to NOTE automatically unload during the downpower. NOTE: The degrading oil reservoir US/BOP Align One Feedwater Pump For AOP 3575 condition will eventually either impell the Automatic Unloading Step 8 Crew to manually trip the Reactor OR the RCP will seize and the Reactor will trip on RCP Low Speed. It is not expected that the crew will get much further than Step 8 of AOP 3575 before one of these conditions occurs. Section 4 Page 32 of 55

( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard BOP Verify removing a feedwater pump AOP 3575 from service during the downpower- Step 8.a DESIRED T= MALF EVENT 4: RPCCW Leak into RCP Downpower RC14B C Upper Oil Reservoir - Ongoing underway ongoing and reactivity manipulation complete if done here plus Examiner's Cue EVENT 5: Inter-System LOCA NOTE: US should go to "Master RO TRIP the reactor Silence" before ordering reactor trip. E-O, Reactor Trip or Safety Crew Go to E-0, Reactor Trip or Safety Injection, Rev. 21 Injection.

• Foldout page must be open E-0, Step 1, NOTE
• ADVERSE CTMT defined as GREATER THAN 180 0F or GREATER THAN 105 R/hr in containment.

Section 4 Page 33 of 55

( EVALUAI iON GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

• The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.

T= 3 mins Floor Prompt the SM to contact the back RO Verify Reactor Trip E-0, Step 1 of event instructor room for the Shift Tech. classifiable

• Check reactor trip and bypass breakers - OPEN
• Check rod bottom lights - LIT
• Check neutron flux -

DECREASING Verify Turbine Trip E-0, Step 2 Check all turbine stop valves - E-0, CLOSED Step 2.a BOP Verify Power to AC Emergency E-0, Step 3 Busses BOP Check busses 34C and 34D - E-0, Step 3.a BOTH ENERGIZED US Check If Sl Is Actuated E-0, Step 4 RO Verify SAFETY INJECTION EOP 35 E-ACTUATION annunciator - (MB4D 1-6 0, Step 4.a or MB2B 5-9) - LIT Section 4 Page 34 of 55

( ( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Check if SI is required E-0, Step 4.a, RNO

• CTMT pressure GREATER THAN 18 psia OR
• PZR pressure LESS THAN 1890 psia OR
• PZR level LESS THAN 16%

OR

• RCS subcooling LESS THAN 32 0F OR
• SG pressure LESS THAN 660 psig IF SI is required, THEN Initiate SI and Proceed to step 5.

Section 4 Page 35 of 55

( ( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign ExDected Actions Standard IStandard IF SI is NOT required, THEN Initiate monitoring of CSF Status Trees and Go to ES-0. 1, Reactor Trip Response. By observation of ESF Group 2 Status E-0, Panel lights, Verify both trains of SI - Step 4.b ACTUATED Manually Initiate SI. E-0, Step 4.b, RNO RO Verify Service Water Pumps - AT E-0, Step 5 LEAST ONE PER TRAIN RUNNING RO Verify Two RPCCW Pumps - ONE E-0, Step 6 PER TRAIN RUNNING RO Verify ECCS Pumps Running E-0, Step 7

• Check SI pumps - RUNNING
• Check RHR pumps - RUNNING
• Check two charging pumps -

RUNNING BOP Verify AFW Pumps Running E-0, Step 8 Section 4 Page 36 of 55

( ( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Check MD pumps - RUNNING E-0, Step 8.a Check turbine - driven pump - E-0, RUNNING, IF NECESSARY Step 8.b BOP Verify FW Isolation E-0, Step 9

• Check SG feed regulating valves -

CLOSED

• Check SG feed regulating bypass valves - CLOSED
• Check FW isolation trip valves -

CLOSED

• Check TD FW pump - TRIPPED
• Check MD FW pumps - STOPPED
• Check SG blowdown isolation valves - CLOSED
• Check SG blowdown sample isolation valves - CLOSED
• Check SG chemical feed isolation valves - CLOSED BOP Check If Main Steam Lines Should E-0, Step 10 Be Isolated Section 4 Page 37 of 55

EVALUA110N GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Check Ctmt pressure GREATER E-0, THAN 18 psia Step 10.a OR Any SG pressure LESS THAN 660 psig Verify MSIVs and MSIV bypass valves E-0,

                                                                   - CLOSED                               Step 10.b Check ESF Group 3 lights - LIT.        E-0, Step 10.c RO     Check if CDA Required                  E-0, Step 11 Check Ctmt pressure is GREATER         E-0, THAN 23 psia                           Step 11.a OR Ctmt spray - INITIATED US     Proceed to Step 12.                    E-0, Stepl 1,a, RNO BOP    Verify CAR Fans Operating In           E-0, Step 12 Emergency Mode BOP    Check CAR fan status:                  E-0, Step 12.a

• CAR fans A and B - RUNNING Section 4 Page 38 of 55

( ~(( EVALUATrON GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

• CAR fan C - STOPPED BOP START/STOP CAR fans as E-0, necessary. Step 12.a, RNO RO Verify RPCCW Ctmt supply and return E-0, header isolations - OPEN Step 12.b RO Verify Train A and B RPCCW supply E-0, and return to chill water valves - Step 12.c OPEN RO Verify CIA E-0, Step 13 RO Check ESF Group 2 status columns 2 E-0, through 10 - LIT Step 13.a RO Initiate CIA. E-0, IF ESF Group 2, columns 2 Step 13.a, through 10 are NOT lit, THEN Using Attachment A Reposition valves as necessary for minimum safety function RO Verify Proper ESF Status Panel E-0, Step 14 Indication
• Verify ESF Group 1 lights - OFF
• Verify ESF Group 2 lights - LIT Section 4 Page 39 of 55

(. EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assian Expected Actions Standard T= Initial MALF EVENT 6: ESF Building Ventilation Align components for minimum safety E-0, Step 14 MALF RP11D Fails to Auto Actuate function. RNO RO Determine If ADVERSE CTMT E-0, Step 15 Conditions Exist

• Ctmt temperature GREATER THAN 1800 F OR
• Ctmt radiation GREATER THAN 105 R/hr CREW DO NOT use ADVERSE CTMT E-0, parameters. Step 15, RNO RO Verify ECCS Flow E-0, Step 16 Check charging pumps - E-0, Step 16.a FLOW INDICATED RO START pumps and Align valves. E-0, Step 16.a, RNO RO Check RCS pressure - GREATER E-0, THAN 1650 psia (1950 psia Step 16.b ADVERSE CTMT)

Section 4 Page 40 of 55

( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Proceed to Step 16.d E-0, Step 16.b, RNO CREW should perform a short brief Proceed to step 17. E-0, and come out of "Master Silence" at Step 16.c the completion of Step 16. Check SI pumps - FLOW INDICATED E-0, Step 16.d START pumps and Align valves. E-0, Step 16.d RNO Check RCS pressure - LESS THAN E-0, 300 psia (500 psia ADVERSE CTMT) Step 16.e Proceed to step 17. E-0, Step 16.e RNO Check RHR pumps - FLOW E-0, INDICATED. Step 16.f START pumps and Align valves. E-0, Step 16.f RNO BOP Verify Adequate Heat Sink E-0, Step 17 Check NR level in at least one SG - E-0, GREATER THAN 8% (42% ADVERSE Step 17.a CTMT) Section 4 Page 41 of 55

( EVALUAI iON GUIDE (

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Proceed to Step 17.d. E-0, Step 17.a, RNO BOP Control feed flow to maintain NR level E-0,

                                                                    - BETWEEN 8% and 50% (42% and             Step 17.b 50% ADVERSE CTMT)

US Proceed to Step 18. E-0, Step 17.c BOP Verify Total AFW Flow - GREATER E-0, THAN 530 gpm Step 17.d BOP START pumps and Align valves as E-0, necessary. Step 17.d, RNO US IF AFW Flow GREATER THAN 530 gpm can NOT be established, THEN Initiate monitoring of CSF Status Trees and Go to FR-H.1, Response to Loss of Secondary Heat Sink. BOP Verify AFW Valve Alignment - E-0, Step 18 PROPER EMERGENCY ALIGNMENT Align valves E-0, Step 18, RNO Section 4 Page 42 of 55

( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard RO Verify ECCS Valve Alignment - E-0, Step 19 PROPER EMERGENCY ALIGNMENT Align valves E-0, Step 19, RNO US Check Plant Status E-0, Step 20 NOTE: When asked, REPORT that Verify SLCRS doors - CLOSED E-0, "all SLCRS doors indicate closed." Step 20.a US Request Security Close all SLCRS E-0, doors. Step 20.a, RNO RO Check CONTROL BUILDING E-0, ISOLATION annunciator (MB4D 3-6) - Step 20.b LIT RO Check if CBI is required E-0, Step 20.b, RNO RO

• Ctmt pressure GREATER THAN 18 psia OR RO
• Control Building radiation monitor in alarm OR Section 4 Page 43 of 55

( ~(( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

• SI manually actuated RO IF CBI required, THEN Initiate CBI.

US IF CBI is NOT required, THEN Proceed to Step 21. RO Verify ESF Group 2 CBI lights - LIT E-0, Step 20.c RO Align HVAC components as necessary E-0, for minimum safety function. Step 20.c, RNO BOP Verify control building purge supply E-0, fan and purge exhaust fan - NOT Step 20.d RUNNING BOP Perform the following: E-0, Step 20.d, RNO

• Stop purge supply fan.
• Stop purge exhaust fan.
• Locally Close instrument air isolations Section 4 Page 44 of 55

( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

• 31AS-V725 (CB 47' IRR stairwell)
• 31AS-V726 (CB47' IRR stairwell)
• 31AS-V644 (CB 66' west wall)

Locally Close instrument air isolation valve for 3HVC-AOD134 BOP Control building air bank isolation E-0, valves - OPEN (after 60 seconds) Step 20.e BOP OPEN valves E-0, Step 20.e, RNO BOP IF at least one air bank isolation valve can NOT be opened, THEN Locally throttle Open at least one pair of air bank isolation bypass valves to maintain 0.125 inches water at Control Building AP indicator on VP1.

• 3HVC*V750 and 3HVC*V751
• 3HVC*V758 and 3HVC*V759 Section 4 Page 45 of 55

( EVALUAI iON GUIDE (

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard BOP STOP kitchen exhaust fan E-0, Step 20.f NOTE: When called, WAIT 3 - 5 min, PEO Close and Dog (as applicable) Control E-0, Then REPORT "All Control Building Building pressure boundary doors. Step 20.g pressure boundary doors are Closed and Dogged." RO Check RCS Temperature E-0, Step 21 Verify RCS cold leg WR temperature - E-0, BETWEEN 5500 F and 5600F Step 21.a US Proceed to Step 22 E-0, Step 21.b RO Check PZR Valves E-0, Step 22 Verify PORVs - CLOSED E-0, Step 22.a RO IF PZR pressure LESS THAN 2350 E-0, psia, THEN CLOSE PORVs. Step 22.a, RNO RO Verify normal PZR spray valves - E-0, CLOSED Step 22.b RO Verify PZR safety valves - CLOSED E-0, Step 22.c Section 4 Page 46 of 55

EVALUATION GUIDE (

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard CREW To prevent damage to the RCP E-0, seal(s), seal injection flow should be Step 23, maintained to all RCPs. CAUTION [Critical Task] RO Check If RCPs Should Be Stopped E-0, Step 23 NOTE: Depending on the pace of the crew through the EOP network this step may be performed here or later as a continuous action. Verify RCPs - ANY RUNNING E-0, Step 23.a BOP/RO Check If SG Secondary Boundaries E-0, Step 24 Are Intact Check pressure in all SGs E-0, Step 24.a

• NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
• NO SG COMPLETELY DEPRESSURIZED Ensure crew request activity samples BOP Check If SG Tubes Are Intact E-0, Step 25 with HP coverage RO Sample all SGs for activity E-0, Step 25.a Section 4 Page 47 of 55

( ( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard

1. RESET SG blowdown sample isolation

2. OPEN SG blowdown sample isolation valve(s)

3. Request Chemistry obtain activity samples using HP coverage BOP Check steam generator levels - NO E-0, SG LEVEL INCREASING IN AN Step 25.b UNCONTROLLED MANNER US Initiate monitoring of CSF Status E-0, Trees and Go to E-3, Steam Step 25.b, Generator Tube Rupture. RNO Verify trend history and alarm status of E-0, radiation monitors Step 25.c

• Main steam line - NORMAL
• Condenser air ejector - NORMAL
• SG blowdown - NORMAL Initiate monitoring of CSF Status E-0, Trees and Go to E-3, Steam Step 25.c Generator Tube Rupture RNO RO Check If RCS Is Intact E-0, Step 26 Section 4 Page 48 of 55

( ( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assiqn Expected Actions Standard Standard

• Verify Ctmt radiation using 3CMS*RE22 (pre-trip) - NORMAL
• Verify Ctmt radiation using radiation monitoring group histogram (CTMT) - NORMAL
• Verify Ctmt pressure - NORMAL
• Verify Ctmt recirculation sump level - NORMAL RO Check for RCS Leakage Outside E-0, Step 27 CTMT Check Auxiliary Building and ESF E-0, Building radiation (radiation monitoring Step 27.a group histograms)

Verify Auxiliary Building (AUX) - NORMAL Verify ESF Building (ESF) - NORMAL Verify SLCRS Building (SLCRS) - NORMAL Section 4 Page 49 of 55

( ~( EVALUAl iON GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Check for Auxiliary Building or ESF E-0, Building flooding Step 27.b

1) Verify SUMP LEVEL Hi lights (MB1) - NOT LIT

• ESF PIPE TNL
• ECCS PIPE CUB
• ESF RHR CUB
• ESF RSS CUB

2) Verify Annunciator SAFEGUARDS AREA FLOODING (MB1C 2-8) -

NOT LIT IF the cause is a loss of RCS E-0, inventory outside containment, THEN Step 27.b Initiate monitoring of CSF Status Tress RNO and Go to ECA-1.2, LOCA Outside Containment ECA-1.2, LOCA Outside CTMT, US Determine Procedure Entry Point ECA 1.2, Rev. 7 And Perform The Applicable Action Step 1 US

• IF the LOCA is in the Auxiliary Building, THEN Proceed to Step 2.

US

• IF the LOCA is in the ESF Building, THEN Proceed to CAUTION prior to Step 3.

Section 4 Page 50 of 55

( ( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Consult with the ADTS prior to ECA 1.2, dispatching personnel to locally Step 3 operate RHR System valves. CAUTION US/RO Verify Proper Valve Alignment In ECA 1.2, ESF Building Step 3 CLOSE valves. ECA 1.2, Step 3 RNO IF the valves can NOT be closed, THEN Locally Close valves for minimum safety function. Verify RHR suction isolation valves - CLOSED. ECA 1.2, Step 3.a 3RHS*MV8701A 3RHS*MV8701 B 3RHS*MV8701 C 3RHS*MV8702A 3RHS*MV8702B 3RHS*MV8702C Verify RHR hot leg injection valve ECA 1.2, (3SIL*MV8840) - CLOSED. Step 3.b Verify Si pump hot leg injection valves ECA 1.2, (3SIH*MV8802A and 3SIH*MV8802B) Step 3.c

                                                                   - CLOSED.

Section 4 Page 51 of 55

( EVALUATION GUIDE (.

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard US Try To Identify And Isolate Break ECA 1.2, Step 4 Turn the power lockout switch to ON ECA 1.2, for the following valves (MB2R): Step 4.a

• RHR pump A cold leg injection valve (3SIL*MV8809A).
• RHR pump B cold leg injection valve (3S[L*MV8809B).
• SI cold leg injection valve (3SIH*MV8835).

CLOSE one of the following: ECA 1.2, Step 4.b

• RHR pump A cold leg injection valve (3S IL*MV8809A)
• RHR pump B cold leg injection valve (3S[L*MV8809B)

T= Begins to MALF [Critical Task]

• SI cold leg injection valve close 3SIH* (3SIH*MV8835)

MV8835 S106A Check RCS pressure - INCREASING ECA 1.2, Step 4.c Section 4 Page 52 of 55

( ( ( EVALUATION GUIDE

Title:

INTER-SYSTEM LOCA ID Number: 2K2 NRC-004 (SPARE) Revision: 0 Task Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard Perform the following: ECA 1.2, Step 4.c RNO

1. OPEN valve closed in step 4.b

2. IF all lines have been checked, THEN Proceed to step 4.d

3. Return to step 4.b Turn the power lockout switch to OFF ECA 1.2, for the following valves (MB2R): Step 4.d

• RHR pump A (3SI L*MV8809A)
• RHR pump B (3SIL*MV88809B)
• Si injection (3SIH*MV8835)

Check If Break Is Isolated ECA 1.2, Step 5 Check RCS pressure - INCREASING. ECA 1.2, Step 5.a Go to E-1, Loss of Reactor or ECA 1.2, Secondary Coolant. Step 5.b TERMINATE UPON TRANSITION TO E-1, Loss of Reactor or Secondary Coolant. Section 4 Page 53 of 55

SECTION 4 ID Number: 2K2NRC-004 Revision: 0 EVALUATION GUIDE I.

SUMMARY

The following Critical Tasks are covered in this exam: TASK DESCRIPTION TASK# K/A >/= 3.0 BASIS FOR SELECTION Trip all RCPs so that an E-1 -- C 002. K5.14 Failure to trip the RCPs under the Orange Path on Core Cooling 3.8/4.2 postulated plant conditions leads to based on core exit core uncovery and to fuel cladding thermocouples (718 F) does temperatures in excess of 2200 F, not occur when forced which is the limit specified in the circulation in the RCS stops ECCS acceptance criteria. Thus, (Small Break LOCA). failure to perform the task represents "mis-operation or incorrect crew performance which leads to degradation of.. .{the fuel cladding) ...barrier to fission product release" and to "violation of the facility license condition." Isolate the LOCA outside ECA-1.2 E04.EA1.3 Failure to isolate a LOCA outside

                                           -- A      3.8/4.0        containment (that can be isolated) containment before transition                                     degrades containment integrity out of ECA-1.2                                                    beyond the level of degradation irreparably introduced by the postulated conditions. It also constitutes "mis-operation or incorrect crew performance which leads to degradation of a barrier to fission product release" and eventually "to degraded ECCS... capacity."

Note: l] Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide. Section 4 Page 54 of 55

SECTION 4

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 Revision: 0 EVALUATION GUIDE Section 4 Page 55 of 55

SECTION 5 SCENARIO INITIAL CONDITIONS ID Number: 2K2NRC-004 Revision: 0 Reactor Power: 100% Operating History: 450 day on line RCS Boron: 50 ppm Core Burnup: 18,600 MWD/MTU Condensate Demins: 7 demins in service Evolutions in Progress: NONE, A Train Protected, Intake Condition: GREEN Major Equipment OOS: "A" PORV is inoperable due to an electrical short in the control circuitry. It has been out of service for 8 hours. Electrical maintenance estimates that the valve will be returned to service within 24 hours. The following Tech Specs are applicable: Tech Spec 3.4.4, action b 3TRM 7.4.1 action a.1 and a.3 for both the A PORV and the block valve 3RCS*MV8000A Crew Instructions: Shift running Charging Pumps to the "A" CHS pump running per OP 3304A, Charging and Letdown, Section 4.4. Plant/Simulator Differences:

• Real Time and Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.
• Auto-log terminals need to be refreshed after entry is made.

O If not using the speed dial option on the phone system, the operator must dial either

       #3333 or #3334 to reach the person/department they desire.

O The following PPC programs do not function on the simulator:

• Samarium Follow
• Xenon Follow
• Sequence of Events Section 7 Page 1 of 1

SECTION 6 VALIDATION CHECKLIST

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 Revision: 0 Remote functions: All remote functions contained in the guide are certified. Malfunctions: All malfunctions contained in the guide are certified. Initial Conditions: The initial condition(s) contained in the guide are certified or have been developed from certified IC's in accordance with NSEM-4.02. Simulator Operating Limits: The simulator guide has been evaluated for operating limits and/or anomalous response. Test Run: The scenario contained in the guide has been test run and validated (validation sheet completed, next page)on the simulator. Simulator response is reasonable and as expected. Examination Scenario Review The dynamic examination review checklist is complete. (This is not required unless the exam will be used as an Annual Exam, then NUREG 1021 requirements apply.) 6/10/02 Technical Reviewer Date Section 7 Page 1 of 1

SECTION 7 REFERENCE AND TASK TRACKING

Title:

INTER-SYSTEM LOCA ID Number: 2K2NRC-004 Revision: 0 I.

References:

AOP*3571 Instrument Failure Response AOP*3567 Operation with One Feedwater Heater String Isolated AOP*3575 Rapid Downpower AOP*3554 RCP Trip or Stopping an RCP at Power EOP*E-0 Reactor Trip or Safety Injection EOP*ECA-1.2 LOCA Outside CTMT EOP*ERGEXE Westinghouse Owners Group Executive Document EOP* Step DOC MP3 step deviation Document EOP*ERGHP Westinghouse Owners Group Background Document EPIP*EPIP 4400 Event Assessment, Classification and Reportability NUREG*1021 rev 8 Examiners Standards Section 7 Page 1 of 1}}