Text

Initial Exam 2009-301 Draft Simulator Scenarios
	ML092870796
Person / Time
Site:	Browns Ferry
Issue date:	10/14/2009
From:	; Division of Reactor Safety II
To:	;
References
	50-259/09/301, 50-260/09/301, 50-296/09/301
	Download: ML092870796 (416)
	v • d • e

Appendix D 0 Scenario Outline '~. Form ES-D-1 ES-O-1 Facility:

Facility: Browns Ferry NPP Scenario No. : 3-09 Op-Test No. : HLT 0801 SRO: SROU-1 Examiners: .Operators: . ATe:

ATC: SROI-1 BOP: RO-1 Initial Unit 3 is at 95% power following turbine valve testing testing.. One loop of RHRSW is Conditions: tagged for repair of FCV 23-3423-34,, 3A RHR Hx SW OUTLET VLV; which is inoperable. 38 CRD pump is tagged for breaker maintenance.

Turnover: Units 1 and 2 are at 100%. On Unit 3, turbine valve testing has just been completed . Raise power to 100% with Recirc@ 10 MWe/min. Support maintenance on RHRSW valve which is expected to be repaired in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Thunderstorm warnings are in effect for Limestone County for the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . hours.

Event Event No. Malf. No. Type*

Type* Event Description R-ATC 1 ------ Raise power N-SRO reduction,,

RFP 3A failure/trip AOI-3-1 response and power reduction 2 fw13a C-ALL Restores tripped RFP per 3-01-3 N-ATC Start raising power per RCP, adjust 2-190 valve and generator 3 n/a N-SRO transfer volts N-80P I-ATC 4 rd25 RPIS failure on Control Rod 14-35 TS-SRO C-80P 3C Condenser waterbox develops a tube leak requiring isolation 5 mc01e 4 C-SRO of the waterbox 6 th233 M-ALL Fuel Failure 7 th35a 8 M-ALL MSL leak with failure to auto-isolate

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

~r.: "~

.;1 ~

ANTICIPATED EAL: 1.1-5-1 1.1-S SITE AREA

Appendix D 0 Scenario Outline Form ES-D-1 ES-O-1 Facility: Browns Ferry NPP No. :

Scenario No.: 3-09 (2) Op-Test No.:

No. : HLT 0801 r--~. ~--~-------------------' - .."

~aininers:

SRO: " SROI-2 Examiners: Operators: ATe: SROI-3 BOP: RO-2 Facility:

Facility: Browns Ferry NPP Scenario No.:

No. : 3-09 (3) Op-Test No.:

No.: HLT 0801 r

~-- --" -

SRO: " SROI-4 Examiners: ," Operators: ATe:

ATC: SROI-5 BOP: RO-3 ANTICIPATED EAL: 1.1-S SITE AREA

Scenario Narrative

Unit three is at 95% power following turbine valve testing. One loop of RHRSW is tagged for repair of FCV 23-34.

The crew will raise power with Recirc.

3A RFP will receive an inadvertent trip. The crew will reduce power per AOI-3-1 to within the capacity of the running RFPs << 5050 rpm) and return the pump to service per 3-01-3.

The Crew will raise power with Recirc after the return of 3A RFP.

A control rod reed switch will fail and the crew will reposition the rod to restore tech spec compliance.

The 3C NS Condenser waterbox develops a tube leak and the Crew will respond per 3-AOI-3-1 and 3-01-27 Foreign material and conductivity in the vessel causes fuel failure. A subsequent Main Steam Line Break and Group 1 isolation signal occurs. The MSIVs fail to auto-close and must be manually closed.

When SRVs are cycled to maintain reactor pressure, PCV 1-179 will stick open

resulting in decreasing RPV inventory and pressure. When an attempt to use HPCI is made a power failure occurs, resulting in HPCI system failure. When RCIC is operated, it will trip locally and area radiation levels will preclude immediate restoration. The 3A CRD pump trips. SLC should be aligned to the test tank.

The scenario is terminated when the RPV level is depressurized due to inability to maintain level above - 180".

ANTICIPATED EAL: 1.1-5 SITE AREA

Appendix D Scenario Outline Form ES-D-1 Facility: Browns Ferry NPP Scenario No. : 3-09 Op-Test No. : HLT 0801 r

. SRO:

$RO: SROU-1 EXaminerS:

Examiners: . Operators: ATe: . SROI-1

~

~... .

BOP: RO-1 Initial Unit 3 is at 95% power following turbine valve testing.

testing . One loop of RHRSW is Conditions: tagged for repair of FCV 23-34, 3A RHR Hx SW OUTLET VLV; VLV; which is inoperable. 38 CRD pump is tagged for breaker maintenance.

maintenance.

Turnover: Units 1 and 2 are at 100%. On Unit 3, 3, turbine valve testing has just been completed . Raise power to 100% with Recirc@ 10 MWe/min. MWe/min. Support maintenance on RHRSW valve which is expected to be repaired in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . hours.

Thunderstorm warnings are in effect for Limestone County for the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . hours.

Event Event No. Malf.

Malt. No. Type* Event Description R-ATC 1 ------ Raise power R-SRO I-ATC 2 th30v 0 RPS level instrument failure TS-SRO RFP 3A failure/trip - AOI response and power reduction, 3 fw13a C-ALL Restores tripped RFP per 3-01-3 N-ATC 4 n/a Start raising power per RCP N-SRO I-ATC 5 rd25 RPIS failure on Control Rod 14-35 I-SRO 6 th233 M-ALL Fuel Failure 7 th35a 8 M-ALL MSL leak with failure to auto-isolate

"** (N)ormal, (R)eactivity, (R)eactivity, (I )nstrument,

)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 1.1-S SITE AREA

Appendix 0 Scenario Outline Form ES-D-1 ES-O-1 Facility: Browns Ferry NPP No.::

Scenario No. 3-09 (2) No. :

Op-Test No.: HLT 0801 I SRO: **** SROI-2

. Examiners: Operators:

Operators: ATC: SROI-3

. BOP:

RO-2 RO*2 JI Facility: Browns Ferry NPP Scenario No. : 3-09 (3) Op-Test No.:

No.: HLT 0801

. .. , SRO: .

I[

IIi dperato~:

.. SROI-4 III Examiners:

Examiners:

I Operators: ATC:

BOP:

. SROI-5 RO-3 ANTICIPATED EAL: 1.1-5 SITE AREA

Scenario Narrative

Unit three is at 95% power following turbine valve testing. One loop of RHRSW is tagged for repair of FCV 23-34.

The crew will raise power with Recirc.

An inadvertent half scram will occur due to an instrument failure. The crew will respond per ARPs and Tech. Specs.

3A RFP will receive an inadvertent trip. The crew will reduce power per AOI-3-1 to within the capacity of the running RFPs << 5050 rpm) and return the pump to service per 3-01-3.

The Crew will raise power with Recirc after the return of 3A RFP.

A control rod reed switch will fail and the crew will reposition the rod to restore Tech Spec compliance.

Foreign material in the vessel causes fuel failure. A subsequent Main Steam Line Break and Group 1 isolation signal occurs. The MSIVs fail to auto-close and must be manually closed.

When SRVs are cycled to maintain reactor pressure, PCV 1-179 will stick open

resulting in decreasing RPV inventory and pressure. When an attempt to use HPCI is made a power failure occurs, resulting in HPCI system failure. When RCIC is operated, it will trip locally and area radiation levels will preclude immediate restoration. The 3A CRD pump trips. SLC should be aligned to the test tank.

The scenario is terminated when the RPV level is depressurized due to inability to maintain level above - 180".

ANTICIPATED EAL: 1.1-5 SITE AREA

HLTS-3-09 Rev 0 Page 1 of 52

SIMULATOR EVALUATION GUIDE TITLE: RAISE POWER WITH RECIRC, RFP FAILURE, RPIS FAILURE FOR A ROD, CONDENSER TUBE LEAK, FUEL FAILURE, MAIN STEAM LEAK, MSRV FAILS OPEN, HPCIINVERTER FAILURE, RCIC TRIP, CRD PUMP FAILURE, CONTINGENCY C1, EMERGENCY DEPRESSURIZE BEFORE LEVEL REACHES -180" REVISION: 0 DATE: Jan. 16,2009 PROGRAM: BFN Operator Training - Hot License Rep required (95% - 100% w/Recirc flow @ 10MWe/min) - Provide marked up copy of 3-GOI-100-12 signed thru step 5.0[6.2] and with steps 5.0[7] thru 5.0[19] marked N/A

An RPHP is required for re-starting tripped RFP (attached) and for raising power after RFP returned to service (also attached)

PREPARED: \

(Operations Instructor) Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HL TS-3-09 Rev 0 Page 2 of 52

Revision Number Description of Changes ChanlJes Nuclear Training Revision/Usage Log Date Pages Affected Revised 0 Initial 01/16/09 All csf

HL TS-3-09 Rev 0 Page 3 of 52 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

RAISE POWER WITH RECIRC, RFP FAILURE, RPIS FAILURE FOR A ROD, CONDENSER TUBE LEAK, FUEL FAILURE, MAIN STEAM LEAK, MSRV FAILS OPEN, HPCI INVERTER FAILURE, RCIC TRIP, CRD PUMP FAILURE, CONTINGENCY C1, EMERGENCY DEPRESSURIZE BEFORE LEVEL REACHES

-180" IV. Length of Scenario - 1 to 1 ~ hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment / unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HLTS-3-09 Rev 0 Page 4 of 52

B. Enabling Objectives:

1. The operating crew will raise power with recirc lAW GOI-100-12.

2. The operating crew will respond to a failure of RFP 3A per 3-AOI 1.

3. The operating crew will respond to a control rod reed switch failure and move the rod to a position with an operable detector per technical specifications.

4. The operating crew will respond to a Condenser tube leak per 3-AOI-3-1 and 3-01-27.

5. The operating crew will recognize and respond to fuel failure in accordance with ARPs.

6. The operating crew will recognize and respond to a Main Steam line break and failure of MSIVs to auto isolate per EOI-3.

7. The operating crew will recognize and respond to a stuck open SRV in accordance with AOI-1-1 and EOI-2.

8. The operating crew will respond to RPV low water level due to HPCI, RCIC and CRD pump failure in accordance with EOI-1, RC/L C1, and C2.

HLTS-3-09 Rev 0 Page 5 of 52 VI.

References:

The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

HLTS-3-09 Rev 0 Page 6 of 52 Console Operator Instructions

VIII.

A. Scenario File Summary

1. File: bat hlts-3-09 MF/RF/OR# Description 1) 11 trg e1 MODESW Set trigger

2) trg e2 HPCI Set trigger

3) trg e3 1-179 Set trigger

4) trg e4 RCIC Set trigger

5) imf rd01a (e1 0) Trip CRD pump 3A

6) imffw13c (e1 0) Trip RFW pump 3C

7) imffw13b (e1 0) Trip RFW pump 38

8) mmf th23 10 (e1 0) 1:00 Fuel failure

9) imf hp07 (e2 0) HPCI 120v power failure

10) imf ad01m ad01 m 100 (e3 0) SRV 1-179 fail open

11) imf rc03 (e4 0) RCIC trip on low suction

12) imfsw03a Tag RHRSW A 1 pump

13) imf sw03b Tag RHRSW A2 pump

14) ior zlohs231 a[1] off RHRSW A 1 green light off

15) ior ypobkrrhrswpa1 fail ccoil RHRSW A1 bkr

16) 17) 18) 19) 20) ior zlohs235a[1] off y~obkrrhrswpa2 fail ccoil ior ypobkrrhrswpa2 ior zlozi2331 off ior ypovfcv2334 fail _power ior zaopi234 0 RHRSW A2 green light off RHRSW A2 bkr RHRSW 23-31 red light off RHRSW FCV-23-34 breaker RHRSW A pressure = 0 psig

21) ior zdihs7117a null Null RCIC torus suction valve HS

22) imfrp15a MSIV ch A group 1 isolation fail

23) imf rp15b MSIV ch 8 group 1 isolation fail

24) imf rd01b Tag 38 CRD pump

25) ior zlohs852a[1] off pum~reen 38 CRD pump green light off

26) ior an:xa553a27 alarm off Disable Main Steam line RAD HI HI ann

27) ior zaori9020a .02 Override RI

HLTS-3-09 Rev 0 Page 7 of 52

IX. Console Operators Instructions HLTS 3-09 ELAP TIME DESCRIPTIONIACTION Simulator Setup Reset to IC 242 -95% power manual rst 242 PW =david Simulator Setup Main batch file - see summary bat hlts-3-09 Simulator Setup Place H.O. card on 38 CRD pump, A 1 & A2 RHRSW pumps and FCV-manual 23-34 imffw13a trips 3A RFW pump 4 minutes after Power returned to And After it Trips 100% or when directed by lead dmffw13a evaluator ....

Removes trip ROLE PLAY: If sent to investigate 3A RFW pump trip, report Radcon performing a survey in the 3A RFW pump room accidentally tripped the pump When RFP is recovered or when imf rd25 directed by lead evaluator. .... Loss of RPIS on rod 14-35 ROLE PLAY: If dispatched as 1M's to check individual circuit cards in panel 9-27, report card is fine, must be a reed switch failure ROLE PLAY: If contacted as Reactor Engineer, recommend notch insert control rod 14-35 one notch and see if rod indicates position 46, if so, leave at position 46. (Provide RCP and shove sheet) 5 minutes after the rod is imf mc01e 4 5:00 repositioned or when directed by the Condenser tube leak 3A SS lead evaluator. ...

ROLE PLAY: 5 minutes after requested, Chemistry reports Conductivity of "C" Hotwell is highest

HLTS-3-09 Rev 0 Page 8 of 52 If directed to close FCV-27-70 to sev mcvfcv2770 0.2 20% Throttle 3C NS outlet If directed to close FCV-27-78 to sev mcvfcv2778 0.2 20% Throttle 3C SS outlet ROLE PLAY: Report 3-FCV-27-46 (38) isfare throttled 5 minutes after the rod is imf th23 3 10:00 repositioned or when directed by the and fuel failure lead evaluator. ......

imf th35a (none 6:00) 8 6:00 Steam line A steam leak in steam tunnel After scram

ROLEPLAY: If sent to investigate trip of 3A CRD pump, report breaker appears to be damaged and Elec Maint has been contacted to repair ROLE PLAY: If sent to investigate trip of 38 and 3C RFW pumps, report nothing unusual noted in either pump room mrf ad01 m out When requested to open breaker Opens breaker for PCV 1-179 for PCV 1-179, wait 3 minutes ..... ,

When requested to close breaker mrf ad01m in for PCV 1-179 ... Closes breaker for PCV 1-179 mrf og09 shutdown If requested to shutdown HWC ........ Removes HWC from service ROLE PLAY: If asked to check RWCU temp ATU's in Aux Inst rm, report 68-835 A-D reading 90°F to 92 of

ROLE PLAY: When asked to check on HPCI, the fuse was replaced and blew again immediately. It smells like there is a burned transformer in the inverter. A FINN team member is here and thinks they can replace the inverter in 30 -45 minutes if there is one in the warehouse

HLTS-3-09 Rev 0 Page 9 of 52 (Updates on status may be provided as requested with progress toward success indicated)

ROLE PLAY: As the RB AUO, when directed to investigate RCIC, wait 1 minute then report back that your alarming dosimeter went off and you saw a CAM in alarm when you entered the building. I am currently trying to get Radcon to put me on an RWP to get to the RCIC room NOTE: monitor FW flow. If imf fw18 100 condensate injection is observed Rupture the RFW header prior to ED ...

At about 450 psig prior to ED. dmf ad01m Leave open if ED is initiated earlier Closes PCV 1-179 If requested to perform App 7B, wait batapp07b 25 minutes Align SLC to test tank Terminate the scenario when the following conditions are satisfied or upon request of instructor:

1) MSIV's closed

2) Emergency Depressurization completed

3) RPV water level restored to +2 to +51 (Lead evaluator may desire to terminate when satisfactory progress to achieve this standard is observed)

HLTS-3-09 Rev 0 Page 10 of 52 Scenario Summary:

x.

Unit three is at 95% power following turbine valve testing. One loop of RHRSW is tagged for repair of FCV 23-34.

The crew will raise power with Recirc.

3A RFP will receive an inadvertent trip. The crew will reduce power per AOI-3-1 to within the capacity of the running RFPs << 5050 rpm) and return the pump to service per 3-01-3.

The Crew will raise power with Recirc after the return of 3A RFP.

A control rod reed switch will fail and the crew will reposition the rod to restore tech spec compliance.

The 3C NS Condenser waterbox develops a tube leak and the Crew will respond per 3-AOI-3-1 and 3-01-27 Foreign material and conductivity in the vessel causes fuel failure. A subsequent Main Steam Line Break and Group 1 isolation signal occurs. The MSIVs fail to auto-close and must be manually closed.

When SRVs are cycled to maintain reactor pressure, PCV 1-179 will stick open resulting in decreasing RPV inventory and pressure. When an attempt to use HPCI is made a power failure occurs, resulting in HPCI system failure. When RCIC is operated, it will trip locally and area radiation levels will preclude immediate restoration. The 3A CRD pump trips. SLC should be aligned to the test tank.

The scenario is terminated when the RPV level is depressurized due to inability to maintain level above - 180".

HL TS-3-09 Rev 0 Page 11 of 52 XI. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. SRO: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. MSIV's closed

2. Emergency Depressurization completed

3. RPV level being maintained + 2 to + 51 " or recovering

HL TS-3-09 Rev 0 Page 12 of 52 XII. Simulator Event Guide:

Event 1: Raise Power With Recirc Position Expected Actions Time/Comments SRO Notify ODS of power increase Direct return of U3 to Full Power using Recirc Flow per 3-GOI-1 00-12 step 5[17] and 3-01-68 ATC Raises Power w/Recirc using 3-GOI-100-12 and 3-01-68, section 6.2

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(158)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-17A(178)(17C),

push-buttons, to achieve balanced jet pump flows.

AND/OR ADJUST Recirc Pump speed 38 using, RAISE SLOW (MEDIUM), 3-HS-96-16A(168)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-18A(188)(18C),

push-buttons, to achieve balanced jet pump flows

[2] WHEN desired to control Recirc Pumps 3A and/or 38 speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 38 using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 80P Provides peer check for Recirc adjustment adlustment Continue to monitor 80P (transfer volts, condensate flow, etc)

HLTS-3-09 Rev 0 Page 13 of 52

XII. Simulator Event Guide:

Event #2: RFP 3A Failure Position Expected Actions Time/Comments ATC Announces "RFPT A Abnormal" alarm and trip of RFPT 'A'.

SRO Directs Entry into 3-AOI-3-1 Directs Reactor Power lowered as needed to maintain operating RFP's speed < 5050 rpm ATC Reduces reactor power as necessary to maintain Rx level or verifies Recirc run backs Reduces reactor power as necessary to maintain RFP speed < 5050 rpm as directed by SRO BOP Refers to ARP, 3-AOI-3-1 and/or 3-01-3 and takes required actions.

SRO Dispatches AUO to RFP to determine cause of trip ATC Verifies unit stable, Power, Level, Pressure

HLTS-3-09 Rev 0 Page 14 of 52 XII. Simulator Event Guide:

Event #2: RFP 3A Failure (continued)

Position Expected Actions Time/Comments SRO Directs RFP returned to service after report of spurious trip per 3-01-3, section 8.1 I 5.7 BOP Returns RFP to service per 3-01-3, section 8.1 I 5.7 8.1 RFPT Trip Recovery

[1] VERIFY complete actions of Alarm Response RFPT TRIPPED, 3-XA-55-6C Window 29

[2] CHECK CLOSED RFP 3A(3B)(3C) DISCH TESTABLE CHECK VLV, 3-FCV-3-94(93)(92), by one of the following:

Observe RFP discharge flow indicator

Locally listening to check valve slam A. IF testable check valve did NOT close, THEN CLOSE tripped RFP discharge and suction valves

[3] IF desired to place alternate RFP/RFPT in service AND another RFPT is available, THEN PERFORM applicable action: (Otherwise N/A)

IF no RFP/RFPT in service, THEN REFER TO Section 5.5

IF any RFP/RFPT in service, THEN REFER TO Section 5.7 A. WHEN either Section 5.5 or 5.7 is complete, THEN GO TO Step 8.1 [1]

HL TS-3-09 Rev 0 Page 15 of 52 XII. Simulator Event Guide:

Event #2: RFP 3A Failure (continued)

Position Expected Actions Time/Comments BOP [4] IF cause of RFPT trip is already corrected AND tripped RFPT will be returned to service, THEN PERFORM applicable action: (Otherwise N/A)

IF no RFP/RFPT in service, THEN GO TO Section 5.5

IF any RFP/RFPT in service, THEN GO TO Section 5.7 3-01-3, section 5.7 5.7 Placing the Second and Third RFP/RFPT In Service

[1] BEFORE placing a RFPT in service:

[1.1] NOTIFY Radiation Protection that an RPHP is in effect for the impending action to place RFPT 3A(3B)(3C) in service. RECORD time Radiation Protection notified in NOMS Narrative Log [BFN PER 126211]

[1.2] VERIFY appropriate data and signatures recorded on Appendix A per Appendix A instructions [Tech Spec 5.7] [BFN PER 126211]

Evaluator Note: Provide signed RPHP to SRO

HLTS-3-09 Rev 0 Page 16 of 52

XII. Simulator Event Guide:

Event #2: RFP 3A Failure (continued)

Position Expected Actions Time/Comments BOP [2] IF RFP/RFPT is NOT warmed, reset and rolling, THEN PERFORM the following: (Otherwise N/A)

N/A

[3] VERIFY RFP 3A(3B)(3C) MIN FLOW VALVE, 3-HS-3-20(13)(6), in OPEN position

CHECK OPEN MIN FLOW VALVE, 3-FCV-3-20(13)(6)

[4] SLOWLY RAISE speed of RFPT using RFPT 3A(3B)(3C) SPEED CO NT RAISE/LOWER, 3-HS-46-8A(9A)( 1OA), to establish flow and maintain level in vessel

[5] WHEN RFPT discharge pressure is within 250 psig of reactor pressure, THEN VERIFY OPEN RFP 3A(3B)(3C) DISCHARGE VALVE, 3-FCV-3-19(12)(5)

[6] SLOWLY RAISE RFPT speed using RFPT 3A(3B)(3C) SPEED CO NT RAISE/LOWER switch, 3-HS-46-8A(9A)(10A), to slowly raise RFP discharge pressure and flow on the following indications (Panel 3-9-6):

RFP Discharge Pressure - RFP 3A(3B)(3C),

3-PI-3-16A(9A)(2A)

RFP Discharge Flow - RFP 3A(3B)(3C), 3-FI-3-20(13)(6)

HLTS-3-09 Rev 0 Page 17 of 52

XII. Simulator Event Guide:

Event #2: RFP 3A Failure (continued)

Position Expected Actions Time/Comments 80P [7] WHEN sufficient flow is established to maintain RFP 3A(38)(3C) MIN FLOW VALVE, 3-FCV 20(13)(6), in CLOSED position (approximately 2 x 106Ibm/hr), THEN PLACE RFP 3A(38)(3C) MIN FLOW VALVE, 3-HS-3-20(13)(6), in AUTO

[8] OBSERVE lowering in speed and discharge flows of other operating RFPs

[9] IF transferring RFPT from MANUAL GOVERNOR to individual RFPT Speed Control PDS, THEN PERFORM the following: (Otherwise N/A)

[9.1] PULL RFPT 3A(38)(3C) SPEED CONT RAISE/LOWER switch, 3-HS-46-8A(9A)(10A),

to FEEDWATER CONTROL position

[9.2] VERIFY amber light at switch extinguished above RFPT 3A(38)(3C) SPEED CO NT RAISE/LOWER switch, 3-HS-46-8A(9A)(10A)

[9.3] PERFORM the following on RFPT 3A(38)(3C) SPEED CONTROL(PDS), 3-SIC-46-8(9)(10) (Panel 3-9-5):

[9.3.1] SELECT Column 3

[9.3.2] VERIFY PDS in MANUAL

[10] IF transferring control of RFPT from individual RFPT Speed Control PDS to "AUTO" control using REACTOR WATER LEVEL CONTROL PDS, 3-LlC-46-5, THEN PERFORM the following:

(Otherwise N/A)

[10.1] VERIFY REACTOR WATER LEVEL CONTROL (PDS), 3-LlC-46-5 is functioning properly and ready to control second or third RFP

[10.2] SLOWLY RAISE RFP discharge flow and pressure by raising RFP speed

[10.3] WHEN RFP speed is approximately equal to operating RFP(s) speed, THEN PERFORM the following on RFPT 3A(38)(3C) SPEED CONTROL (PDS), 3-SIC-46-8(9)(10):

[10.3.1] PLACE PDS in AUTO

[10.3.2] VERIFY Column 3 selected

HLTS-3-09 Rev 0 Page 18 of 52 XII. Simulator Event Guide:

Event #2: RFP 3A Failure (continued)

Position Expected Actions Time/Comments BOP [11] WHEN RFP in automatic mode on REACTOR WATER LEVEL CONTROL, (PDS) 3-LlC-46-5, THEN CLOSE the following valves:

RFPT 3A(3B)(3C) LP STOP VL V ABOVE SEAT DR, 3-FCV-6-120(125)(130)

RFPT 3A(3B)(3C) LP STOP VLV BELOW SEAT DR, 3-FCV-6-121(126)(131)

RFPT 3A(3B)(3C) HP STOP VLV ABOVE SEAT DR, 3-FCV-6-122(127)(132)

RFPT 3A(3B)(3C) HP STOP VLV BELOW SEAT DR, 3-FCV-6-123(128)(133)

RFPT 3A(3B)(3C) FIRST STAGE DRAIN VLV,3-FCV-6-124(129)(134)

RFPT A(B)(C) HP STEAM SHUTOFF ABOVE SEAT DRAIN, 3-FCV-006-0153(0155)(0157) (local control)

RFPT A(B)(C) LP STEAM SHUTOFF ABOVE SEAT DRAIN, 3-FCV-006-0154(0156)(0158) (local control)

[12] VERIFY CLOSED the following valves on first RFP started in Section 5.5:

RFPT 3A(3B)(3C) LP STOP VLV ABOVE SEAT DR, 3-FCV-6-120(125)(130)

RFPT 3A(3B)(3C) LP STOP VLV BELOW SEAT DR, 3-FCV-6-121(126)(131)

RFPT A(B)(C) LP STEAM SHUTOFF ABOVE SEAT DR, 3-FCV-006-0154(0156)(0158) (local control)

HLTS-3-09 Rev 0 Page 19 of 52 XII. Simulator Event Guide:

Event #2: RFP 3A Failure (continued)

Position Expected Actions Time/Comments BOP [13] VERIFY both RFPT Main Oil Pumps running

[14] IF desired to stop Turning Gear for in service RFPT, THEN PLACE appropriate handswitch in STOP and RETURN to AUTO:

RFPT 3A TURNING GEAR MOTOR, 3-HS-3-101A

RFPT 3B TURNING GEAR MOTOR, 3-HS-3-127A

RFPT 3C TURNING GEAR MOTOR, 3-HS-3-152A

[15] REFER TO Section 6.0.

CONTROL and MONITOR RFW system operation Notify SRO that 3A RFP is returned to service

HL TS-3-09 Rev 0 Page 20 of 52 XII. Simulator Event Guide:

Event #3: Raise Power Position Expected Actions Time/Comments SRO Contact Reactor Engineer for RCP Notify ODS of power increase Direct return of U3 to Full Power using Recirc Flow per 3-GOI-100-12 step 5[17] and 3-01-68 ATC Raises Power w/Recirc using 3-GOI-1 00-12 and 3-01-68, section 6.2

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-17A(17B)(17C),

push-buttons, to achieve balanced jet pump flows.

AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS-96-16A(16B)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-18A(18B)(18C),

push-buttons, to achieve balanced jet pump flows

[2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 BOP Provides peer check for Recirc adjustment Continue to monitor BOP (transfer volts, condensate flow, etc)

HLTS-3-09 Rev 0 Page 21 of 52 XII. Simulator Event Guide:

Event #4: Rod Position Failure Position Expected Actions Time/Comments Crew Announces alarm 9-5A window 28, CONTROL ROD DRIFT ATC A. DETERMINE which rod is drifting from Full Core Display Identifies rod 14-35 has no position indication on full core and 4-rod display B. IF rod drifting in, THEN REFER TO 3-AOI-85-5 C. IF rod drifting out, THEN REFER TO 3-AOI-85-6 D. REFER TO Tech Spec Section 3.1.3,3.10.8 SRO Determines rod is not drifting but RPIS indication has failed Enters LCO 3.1.3 and notes that insertion of the rod to an operable position indication (46) is

ATC allowed Directs entry into 3-AOI-85-4, Loss of RPIS 4.1 Immediate Actions

[1]

[1] STOP all control rod movement 4.2 Subsequent Actions

[1] CHECK with Operations Superintendent and Reactor Engineer for actions to be taken in a timely manner

HLTS-3-09 Rev 0 Page 22 of 52 XII. Simulator Event Guide:

Event #4: Rod Position Failure (continued)

Position Expected Actions Time/Comments ATC [2] CHECK withTechnical Support to help determine the extent of loss of RPIS

[3] IF control rod was in motion when RPIS failed and position of that control rod can NOT be determined, THEN CONSIDER that Control Rod Inoperable. REFER TO Tech. Spec. 3.1.3 N/A

[4] IF control rod movement is required with a total loss of RPIS, THEN MANUALLY SCRAM reactor N/A

[5] REFER TO EPIP-1 SRO SRO verifies the EPIP's do not apply ATC [6] VERIFY ON Breaker 612, PANEL 3-9-27 ROD POSITION INFO SYS FEED FROM UNIT PREFERRED 120VAC, at Panel 3-9-9 Cabinet 6

Evaluator Note:

ATC When Operator goes around back to check bkr 612, report that breaker is closed

[7] IF half or all control rod position indications on Full Core Display are off, THEN PERFORM the following: N/A

HL TS-3-09 Rev 0 Page 23 of 52 XII. Simulator Event Guide:

Event #4: Rod Position Failure (continued)

Position Expected Actions Time/Comments ATC [8] IF an individual control rod position indication is off on Full Core Display or 4-Rod Display, THEN CHECK individual circuit cards in Panel 3-9-27 for proper operation

[9] IF an individual reed switch position indicator is out-of-service on Full Core Display or 4-Rod Display, THEN RECORD control rod coordinates and position in Unit Operators Log N/A

[10] [NER/C] IF unable to restore position indication for an individual control rod or rods, THEN CHECK with Reactor Engineer and DETERMINE additional corrective action 4.4 Alternate Methods of Determining Control Rod Position of A Single Control Rod

[1] IF the "TENS" Digit for an individual reed switch position indicator is out-of-service on Full Core Display and 4-Rod Display for the Control Rod, THEN VERIFY the following:

The Associated Control Rod was NOT being moved when the loss of reed switch Position for the "TENS" Digit occurred

No Drift Alarm is present for the associated Control Rod

The "ONES" Digit is at its original expected position

HLTS-3-09 Rev 0 Page 24 of 52 XII. Simulator Event Guide:

Event #4: Rod Position Failure (continued)

Position Expected Actions Time/Comments ATC [1.1] IF all three of the bullets in 4.4[1] are satisfied, THEN The associated Control Rod can be assured it is in its required/intended position N/A

[1 .2] IF any of the three bullets in 4.4[1] cannot be met, THEN Control Rods may be moved to an Operable Position Indication as a means of position verification (Refer to Tech Spec Bases SR 3.1.3.1) (bullets 2 & 3 cannot be met)

[2] IF the "ONES" Digit for an individual reed switch position indicator is out-of-service on Full Core Display and 4-Rod Display for the Control Rod, THEN Control Rods may be moved to an Operable Position Indication as a means of position verification (Refer to Tech Spec Bases SR 3.1.3.1)

SRO When provided the RCP for the rod movement, direct rod 14-35 inserted to position 46 to see if RPIS indications return ATC Notches rod 14-35 to position 46 and verifies that the RPIS indications have returned Reports RPIS restored on rod 14-35 to SRO SRO Directs rod 14-35 to remain in position 46 Notifies Reactor Engineer Directs initiation of WO

HL TS-3-09 Rev 0 Page 25 of 52 XII. Simulator Event Guide:

Event #5: Condenser Tube Leak Position Expected Actions Time/Comments Crew Reports alarm 9-6B window 6, Condensate Demin Abnormal BOP A. CHECK system flow conductivity, and system DP, on Panel 3-9-6 for abnormalities.

B. DISPATCH personnel to determine problem with condensate demineralizers.

C. IF High Conductivity exists, THEN REFER TO 3-AOI-2-1.

SRO After AUO report of high conductivity, directs entry into 3-AOI-2-1, Reactor Coolant High Conductivity BOP 4.2 Subsequent Actions

[1] LOWER reactor power, as necessary, to maintain radiation levels in main steam lines below the "Main Steam Line Radiation High-High" (3-XA-55-3A, Window 27) setpoint. REFER TO 3-GOI-100-12A.

[2] MONITOR reactor vessel water conductivity on REACTOR WATER CLEANUP BEFORE DEMIN (CONDUCTIVITY), 3-CR-43-11 A, on Panel 3-9-4.

[3] NOTIFY Chemistry to sample reactor water.

REFER TO 3-SI-4.6.B.1-4.

[4] IF condenser hotwell inleakage is suspected, THEN PERFORM the following:

[4.1] ISOLATE and DRAIN the condenser water boxes (one at a time). REFER TO 3-01-27

[4.1.1] OBSERVE reactor water conductivity and off gas flow rate. (After the leaking water box is isolated and drained, Reactor water conductivity should begin to lower within 30-45 minutes. OFF-GAS flow rate could raise.)

HLTS-3-09 Rev 0 Page 26 of 52 XII. Simulator Event Guide:

Event #5: Condenser Tube Leak (continued)

Position Expected Actions Time/Comments SRO When Chemistry calls and reports conductivity highest in 3C condenser, directs isolating and draining 3S CCW waterboxes per 3-01-27 BOP Starts removing waterboxes per 3-01-27 section 8.17 8.17 Removing a Waterbox from Service for Leak Check

[1] IF time permits, THEN COLLECT the Amertap System balls and SHUT DOWN the Amertap System from the waterboxes to be removed. REFER TO 3-01-278. N/A

[2] IF the waterbox being removed from service is 3A 1(SS), THEN SHUT DOWN Debris Filter REFER TO Section 7.2 N/A

[3] CLOSE the CNDR 3A1(3A2)(3B1 )(3B2)(3C1 )(3C2), OFFGAS SHUTOFF VALVE to the waterbox to be removed from service using 3-HS-66-A(3A)(4A)(5A)(6A)(7A) on Panel 3-9-8

[4] CLOSE the CNDR 3A(3B)(3C) CCW OUTLET SO VALVE (on the waterbox to be removed) to approximately 20% open as follows:

[4.1] WHILE performing the following steps, MONITOR condenser vacuum closely

[4.2] PLACE handswitch CNDR 3A(B)(C)

NS(SS) CCW OUTL SHUTOFF VLV 2-HS-027-38( 46,54,62,70, 78)A (3-PNLA-009-0020) in CLOSE and release to close valve to ==5% open

HlTS-3-09 Rev 0 Page 27 of 52 XII. Simulator Event Guide:

Event #5: Condenser Tube leak (continued)

Position Expected Actions Time/Comments 80P [4.3] AS necessary to maintain Condenser Vacuum greater than 25 inches Hg, SLOWLY THROTTLE OPEN the remaining CNOR 3A(38)(3C) CCW OUTLET SHUTOFF VALVEs by using the following OPEN/CLOSE/STOP pushbutton on Panel 25-116

CNOR 3A NS CCW OUTl SHUTOFF VlV, 3-HS-027 -00380

CNOR 3A SS CCW OUTl SHUTOFF Vl V, 3-HS-027-00460

CNOR 38 NS CCW OUTl SHUTOFF Vl V, 3-HS-027 -00540

CNOR 38 SS CCW OUTl SHUTOFF Vl V, 3-HS-027 -00620

CNOR 3C NS CCW OUTl SHUTOFF VlV,

3-HS-027 -00700

CNOR 3C SS CCW OUTl SHUTOFF Vl V, 3-HS-027 -00780

[4.4] IF necessary, THEN REDUCE LOAD and MAINTAIN condenser vacuum greater than 25 inches Hg to get the CNOR 3A(38)(3C) CCW OUTLET SHUTOFF VALVE NS(SS) (on the waterbox to be removed) to approximately 20 percent open

HLTS-3-09 Rev 0 Page 28 of 52 XII. Simulator Event Guide:

Event #5: Condenser Tube Leak (continued)

Position Expected Actions Time/Comments 80P [5] CLOSE the CNDR 3A(38)(3C) CCW INLET SHUTOFF VALVE for the waterbox to be removed from service using the appropriate switch on Panel 3-9-20:

CNDR 3A NS CCW INLET SHUTOFF VLV, 3-HS-27-31A

CNDR 3A SS CCW INLET SHUTOFF VLV, 3-HS-27 -39A

CNDR 38 NS CCW INLET SHUTOFF VLV, 3-HS-27-47A

CNDR 38 SS CCW INLET SHUTOFF VLV, 3-HS-27 -55A

CNDR 3C NS CCW INLET SHUTOFF VLV, 3-HS-27 -63A

CNDR 3C SS CCW INLET SHUTOFF VLV, 3-HS-27-71A Notices Conductivity lowering after 3C NS waterbox inlet valve

[6] IF DESIRED CLOSE NASH valves step 8.3[11.2] and drain the waterbox step 8.3[18].

(otherwise N/A)

.(otherwise

[7] ADJUST the position the remaining CNDR CCW OUTLET SHUTOFF VALVES to optimize CCW System performance by performing Section 6.1 SRO Checks Tech Specs 3.4.6 and TRM 3.4.1 and determine neither apply unless conductivity exceeded 2 I-Imho/cm (then 3.4.1 would apply)

HLTS-3-09 Rev 0 Page 29 of 52 XII. Simulator Event Guide:

Event #6: Fuel Damage/MSL Leak Position Expected Actions Time/Comments BOP Announces alarm 9-3A window 5, OG Pre Treatment Radiation High. Responds per ARP A. VERIFY high radiation on following:

1. OFFGAS PRETREATMENT RADIATION recorder, 3-RR-90-157 on Panel 3-9-2

2. OFFGAS RADIATION recorder, 3-RR-90-160 on Panel 3-9-2

3. OG PRETREATMENT RAD MON RTMR, 3-RM-90-157 on Panel 3-9-10

4. OFFGAS RAD MON RTMR, 3-RM-90-160 on Panel 3-9-10 B. CHECK off-gas flow normal C. CHECK following radiation recorders and associated radiation monitors:

1. MAIN STEAM LINE RADIATION, 3-RR 135 on Panel 3-9-2

2. OFFGAS POST-TREATMENT RADIATION, 3-RR-90-265 on Panel 3-9-2

3. STACK GAS/CO NT RM RADIATION FROM STACK GAS, 0-RR-90-147 on Panel 1-9-2 D. NOTIFY RADCON E. REQUEST Chemistry perform radiochemical analysis to determine source

HLTS-3-09 Rev 0 Page 30 of 52 XII. Simulator Event Guide:

Event #6: Fuel Damage/MSL Leak (continued)

Position Expected Actions Time/Comments BOP F. IF Offgas System Isolation Valve, 3-FCV-66-28 is manually restrained in the OPEN position and it has been determined that this is a valid alarm, THEN UNRESTRAIN Offgas System Isolation Valve, 3-FCV-66-28 G. REFER TO 0-SI-4.8.B.1.a.1 and 1(2)(3)-SR-3.4.6.1 (A) for ODCM compliance and to determine if power level reduction is required H. IF directed by Unit Supervisor, THEN REDUCE reactor power to maintain off-gas radiation within ODCM limits I. IF ODCM limits are exceeded, THEN REFER TO EPIP-1 SRO Notifies Chem Lab to Sample Declares NOUE (1.4-U)

BOP Announces alarm 9-3A window 5, TURBINE BLDG AREA RADIATION HIGH A. DETERMINE area with high radiation level on Panel 3-9-11. (Alarm on Panel 3-9-11 will automatically reset if radiation level lowers below setpoint.)

B. IF the TSC is NOT manned, THEN USE public address system to evacuate area where high airborne conditions exist.

C. IF the TSC is manned, THEN REQUEST the TSC to evacuate non-essential personnel from affected areas.

HLTS-3-09 Rev 0 Page 31 of 52 XII. Simulator Event Guide:

Event #6: Fuel Damage/MSL Leak (continued)

Position Expected Actions Time/Comments BOP D. NOTIFY RADCON.

E. MONITOR other parameters providing input to this annunciator frequently as these parameters will be masked from alarming while this alarm is sealed in.

F. IF alarm is due to sensor malfunction, THEN REFER TO 0-01-55.

Check instruments and reports increase in radiation RR-90-157 (OG Pretrt) RR-90-135 (MSL Rad)

Evacuates Turbine Building per ARP SRO Notifies Rad Con BOP Announces alarm 9-3A window 22, RX BLDG AREA RADIATION HIGH

A. DETERMINE area with high radiation level on Panel 3-9-11. (Alarm on Panel 3-9-11 will automatically reset if radiation level lowers below setpoint.)

B. IF the alarm is from the HPCI Room while Flow testing is being performed, THEN REQUEST personnel at the HPCI Quad to validate conditions.

C. NOTIFY RADCON

HLTS-3-09 Rev 0 Page 32 of 52 XII. Simulator Event Guide:

Event #6: Fuel Damage/MSL Leak (continued)

Position Expected Actions Time/Comments BOP D. IF the TSC is NOT manned and a "VALID" radiological condition exists., THEN USE public address system to evacuate area where high airborne conditions exist E. IF the TSC is manned and a "VALID" radiological condition exists, THEN REQUEST the TSC to evacuate non-essential personnel from affected areas.

F. MONITOR other parameters providing input to this annunciator frequently as these parameters will be masked from alarming while this alarm is sealed in.

G. IF a CREV initiation is received, THEN

1. VERIFY CREV A(B) Flow is ~ 2700 CFM, and::::; 3300 CFM as indicated on 0-FI-031-7214(7213) within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of the CREV initiation. [BFPER 03-017922]

2. IF CREV A(B) Flow is NOT ~ 2700 CFM, and

3300 CFM as indicated on O-FI-031-7214(7213) THEN PERFORM the following

(Otherwise N/A) [BFPER 03-017922]

a. STOP the operating CREV per 0-01-31.

b. START the standby CREV per 0-01-31.

HLTS-3-09 Rev 0 Page 33 of 52 XII. Simulator Event Guide:

Event #6: Fuel Damage/MSL Leak (continued)

Position Expected Actions Time/Comments BOP H. IF alarm is due to malfunction, THEN REFER TO 0-01-55.

I. ENTER 3-EOI-3 Flowchart.

J. REFER TO 3-AOI-79-1 or 3-A01-79-2 if applicable.

Checks RB instruments to determine affected areas Evacuates Reactor Building per ARP SRO Notifies Rad Con Enters 3-EOI-3 (may direct power reduction with recirc flow)

HL TS-3-09 Rev 0 Page 34 of 52 XII. Simulator Event Guide:

Event #6: Fuel Oamage/MSL Leak (continued)

Position Expected Actions Time/Comments 80P Recognize and announce Group 6 isolation on high radiation Reports alarm 9-30 window 24, MAIN STEAM LINE LEAK DETECTION TEMP HIGH and verifies on T11-60A A. CHECK the following temperature indications:

MN STEAM TUNNEL TEMP temperature indicator, 3-TIS-1-60A on Panel 3-9-3

Temperature Switches 3-TS-1-608, -60C, or -600 window(s) on Panel 3-9-21

RWCU Piping in the Main Steam Tunnel temperature indicators, 3-TIS 834A(8)(C)(0), Auxiliary Instrument Room Panels 9-83(84)(85)(86) OR ICS 'HPTUR8' mimic.

8. CHECK the following flow indications:

MAIN STEAM LINE FLOW A(8)(C)(0), 3-FI-46-1 (2)(3)(4) on Panel 3-9-5

RFW FLOW LINE A(8), 3-FI-3-78A(788) on Panel 3-9-5

RFP 3A(38)3C) flow indicators, 3-FI 20(13)(6) on Panel 3-9-6

HL TS-3-09 Rev 0 Page 35 of 52 XII. Simulator Event Guide:

Event #6: Fuel Oamage/MSL Leak (continued)

Position Expected Actions Time/Comments BOP C. IF RCIC is NOT in service AND 3-FI-71-1A(B),

RCIC STEAM FLOW indicates flow, THEN ISOLATE RCIC and VERIFY Temperatures lowering.

O. CHECK for elevated RAO Levels on the following Instruments:

3-RM-90-20, CRO-HCU West

3-RM-90-29, Suppression Pool E. IF HPCI is injecting with elevated Suppression Pool Temperature, THEN CONSIDER securing HPCI to determine if it is the source of the leak.

F. IF Rx Bldg main steam tunnel temperature is above 160°F on 3-TIS-1-60A on Panel 3-9-3, THEN PERFORM the following:

1. ENTER 3-EOI-3 Flowchart

2. VERIFY Rx Zone fans, 3-HS-64-11 A at Panel 3-9-25, in fast speed

3. VERIFY Steam Vault Exhaust Booster Fan in service. REFER TO 3-01-30B G. IF turbine building main steam tunnel temperature is above 160°F on 3-TS-1-60B, -60C, or -600 on Panel 3-9-21 , THEN DISPATCH personnel to 480V AC Turb Bldg Vent Bd 3A (TB, EI 617') to verify TB fans and the Mechanical Spaces Exhaust Fan running

HLTS-3-09 Rev 0 Page 36 of 52 XII. Simulator Event Guide:

Event #6: Fuel Damage/MSL Leak (continued)

Position Expected Actions Time/Comments SRO Directs Core Flow Runback Renters 3-EOI-3 Enters EOI-1 and Directs manual scram ATC Manually scrams and verifies all rods inserted SRO Directs ATC to carry out actions of 3-AOI-100-1 ATC Carries out 3-AOI-100-1 actions Mode switch in SID Gives scram report Trips main turbine Verify Recirc pumps at minimum Crew Verifies Group 2, 3, 6 and 8 isolations

HLTS-3-09 Rev 0 Page 37 of 52 XII. Simulator Event Guide:

Event 6: Fuel Oamage/MSL Leak (continued)

Position Expected Actions Time/Comments BOP Closes MSIVs prior to isolation Or Reports MSIVs not closed on MSL high temp (189°F) on panel 9-30 alarms SRO Directs MSIV closure, if not already directed BOP Closes MSIVs SRO Directs pressure control 800 to 1000 psig using SRV's, Appendix-11A Directs level control + 2" to + 51" using RCIC, Appendix-5C or HPCI, Appendix-50 BOP Controls pressure as directed using SRVs, Appendix-11A

1. IF ..... Orywell Control Air is NOT available,

THEN ... EXECUTE EOI Appendix 8G, CROSSTIE CAD TO ORYWELL CONTROL AIR, CONCURRENTL Y with this procedure.

2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE MSRVs and CONTROL RPV pressure using other options.

3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

a.1 3-PCV-1-179 MN STM LINE A RELIEF VALVE

b. 2 3-PCV-1-180 MN STM LINE 0 RELIEF VALVE

c. 3 3-PCV-1-4 MN STM LINE A RELIEF VALVE

d. 4 3-PCV-1-31 MN STM LINE C RELIEF VALVE

e. 5 3-PCV-1-23 MN STM LINE B RELIEF VALVE

f. 6 3-PCV-1-42 MN STM LINE 0 RELIEF VALVE

g. 7 3-PCV-1-30 MN STM LINE C RELIEF VALVE

h. 8 3-PCV-1-19 MN STM LINE B RELIEF VALVE

i. 9 3-PCV-1-5 MN STM LINE A RELIEF VALVE

j. 10 3-PCV-1-41 MN STM LINE 0 RELIEF VALVE

k. 11 3-PCV-1-22 MN STM LINE B RELIEF VALVE I. 12 3-PCV-1-18 MN STM LINE B RELIEF VALVE

m. 13 3-PCV-1-34 MN STM LINE C RELIEF

VALVE

HLTS-3-09 Rev 0 Page 38 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCI/RCIC/CRD Failure Position Expected Actions Time/Comments BOP Attempts to control level as directed using HPCI, Appendix-5D and RCIC, Appendix-5C Reports HPCI failure (120V Power Alarm)

Reports RCIC TRIP and failure to reset SRO Dispatches AUO to reset RCIC Dispatches OS-US to troubleshoot I replace HPCI power supply fuses BOP Reports PCV 1-179 failure to close after use SRO Directs entry into 3-AOI-1-1 BOP Enters 3-AOI-1-1, Relief Valve Stuck Open and performs immediate operator actions 4.1 Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 3-FMT 4, on Panel 3-9-3, OR

MSRV DISCHARGE TAILPIPE TEMPERATURE, 3-TR-1-1 on Panel 3-9-47

HLTS-3-09 Rev 0 Page 39 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCIIRCIC/CRD Failure Position Expected Actions Time/Comments BOP [2] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch several times as required:

CLOSE to OPEN to CLOSE positions

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A) N/A SRO Directs actions to close PCV 1-179 per 3-AOI-1-1 outside control room BOP 4.2.1 Attempt to close valve from Panel 9-3:

[1] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the OFF position

[2] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON position

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A) N/A

[4] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT, 3-XS-1-202 in INHIBIT:

[5] IF relief valve closes, THEN OPEN breaker or PULL fuses as necessary using Attachment 1 (Unit 3 SRV Solenoid Power Breaker/Fuse Table)

HLTS-3-09 Rev 0 Page 40 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCIIRCIC/CRD Failure Position Expected Actions Time/Comments BOP [6] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT 3-XS-1-202, in AUTO Uses table at step 7 to determine which step to proceed to (4.2.2[12])

[12] IF 3-PCV-1-179 is NOT closed, THEN PERFORM the following: (Otherwise N/A this section.)

[12.1] REMOVE the power from 3-PCV-1-179 by performing one of the following: (Otherwise N/A):

A. OPEN the following breaker: (Preferred method)

3B 250V RMOV, Compartment 8C2 OR B. In 3-LPNL-925-0658, (EI 593' 3B Electric Board Room, South Wall)

PULL the following fuses as necessary:

Fuse 3-FU1-001-0179A

Fuse 3-FU1-001-0179B

HLTS-3-09 Rev 0 Page 41 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCI/RCIC/CRD Failure Position Expected Actions Time/Comments BOP [12.2] IF the valve does NOT close, THEN CLOSE breaker or REINSTALL fuses removed in Step 4.2.2[12.1].

[12.3] CONTINUE at Step 4.2.3 4.2.3 Other Actions and Documentation

[1] IF ANY EOI entry condition is met, THEN ENTER the appropriate EOI(s)

[2] REFER TO Technical Specifications Sections 3.5.1 and 3.4.3 for Automatic Depressurization System and relief valve operability requirements

[3] INITIATE suppression pool cooling as necessary to maintain suppression pool temperature less than 95°F

[4] IF the relief valve can NOT be closed AND suppression pool temperature Can NOT be maintained less than or equal to 95°F, THEN

PLACE the reactor Modeo4 in accordance with 3-GOI-100-12A

[5] DOCUMENT actions taken and INITIATE Work Order for the valve Reports PCV 1-179 does not close SRO Directs RHR placed in Suppression Pool cooling per 3-01-74 Reviews Tech Specs 3.5.1 and 3.4.3 and determined no active LCO exists

HLTS-3-09 Rev 0 Page 42 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCIIRCIC/CRD Failure (continued)

Position Expected Actions Time/Comments SRO Enters EOI-2 at 95°F suppression pool temperature Directs all available RHR placed in Suppression Pool Cooling per Appendix-17A BOP Places all available Suppression Pool Cooling in service per Appendix-17A

1. IF .............. Adequate core cooling is assured, OR Directed to cool the Suppression Pool irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS.

2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

c. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

HLTS-3-09 Rev 0 Page 43 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCI/RCIC/CRD Failure (continued)

Position Expected Actions Time/Comments BOP d. IF ............. Directed by SRO, THEN ....... PLACE 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD in MANUAL OVERRIDE.

e. IF ............. LPCIINITIATION Signal exists, THEN ....... MOMENTARILY PLACE 3-XS 121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT in SELECT.

f. IF ............. 3-FCV-74-53(67), RHR SYS 1(11) LPCI INBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV-74-52(66),

RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

g. OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBRIPOOL ISOL VLV.

h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating.

i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11)

SUPPR POOL CLGITEST VL V, to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR SYS 1(11) FLOW:

Between 7000 and 10000 gpm for one-pump operation. OR

At or below 13000 gpm for two-pump operation.

j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

k. MONITOR RHR Pump NPSH using Attachment 1.

I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

m. IF ............. Additional Suppression Pool Cooling flow is necessary, THEN ....... PLACE additional RHR and RHRSW pumps in service using Steps 2.b through 2.1.

HLTS-3-09 Rev 0 Page 44 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCI/RCIC/CRD Failure (continued)

Position Expected Actions Time/Comments SRO Directs Alternate RPV Injection System Lineup SLC System, Appendix-7B ATC Performs Appendix-7B by injecting with SLC from the Boron tank or dispatching AUO to align SLC suction to the test tank Verifies recirc pumps trip at -45" SRO Directs preventing flooding vessel via Condensate system by closing RFP discharge valves ATC Closes RFP discharge valves SRO Enters C1, Directs ADS inhibited BOP Inhibits ADS Reports DG starts Dispatches AUO to monitor D/G's

HL TS-3-09 Rev 0 Page 45 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCI/RCIC/CRD Failure (continued)

Position Expected Actions Time/Comments SRO When level decreases to T AF determines/verifies that sufficient injection sources are available to not enter steam cooling and enters C2. i.e. Will Emergency Depressurize somewhere between -

162 and -180" Directs RHR be realigned from Suppression Pool Cooling to injection BOP Secures Suppression Pool Cooling and aligns RHR for injection SRO Directs opening 6 ADS valves BOP Opens 6 ADS valves as directed SRO Directs BOP to inject with ECCS until level is above -122" then secure systems to not exceed to maintain + 51"; Directs restoration of Suppression Pool Cooling after RWL control is established BOP Operates and secures ECCS injection as directed /

reestablishes Suppression Pool Cooling as directed

HLTS-3-09 Rev 0 Page 46 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCIIRCIC/CRD Failure (continued)

Position Expected Actions Time/Comments SRO Directs restoring level + 2" to + 51" with Core Spray, Appendix-6D(E)

BOP Recover level with CS Loop I, 3-EOI Appendix-6D

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VL V

3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VL V

3-FCV-75-23, CORE SPRAY SYS I OUTBD INJECT VALVE

2. VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALVE

3. VERIFY CS Pump 3A and/or 3C RUNNING

4. WHEN ... RPV pressure is below 450 pSig, THEN ... THROTTLE 3-FCV-75-25, CORE SPRAY SYS IINBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pump

5. MONITOR Core Spray Pump NPSH using Attachment 1

HLTS-3-09 Rev 0 Page 47 of 52 XII. Simulator Event Guide:

Event #7: Stuck Open SRV, HPCIIRCIC/CRO Failure (continued)

Position Expected Actions Time/Comments BOP Recover level with CS Loop II, 3-EOI Appendix-6E

1. VERIFY OPEN the following valves:

3-FCV-75-30, CORE SPRAY PUMP 3B SUPPR POOL SUCT VL V

3-FCV-75-39, CORE SPRAY PUMP 3D SUPPR POOL SUCT VL V

3-FCV-75-51, CORE SPRAY SYS II OUTBO INJECT VALVE

2. VERIFY CLOSED 3-FCV-75-50, CORE SPRAY SYS II TEST VALVE

3. VERIFY CS Pump 3B and/or 3D RUNNING

4. WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-53, CORE SPRAY SYS IIINBO INJECT VALVE, as necessary to control injection at or below 4000 gpm per pump

5. MONITOR Core Spray Pump NPSH using Attachment 1 SRO Classifies event as Site Area Emergency (1.1-S 1)

HLTS-3-09 Rev 0 Page 48 of 52 XIII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Isolates MSIVs prior to 2 3-EOI-3 Area Radiations /

Temperatures reaching Max Safe

2) Prevent Automatic Depressurization

3) Emergency Depressurizes when below TAF and before level drops to -180"

4) If SRO directs 2/3 core height override then the SRO will verify that the RHR system is fully realigned for injection when required (contingent - if directed)

HLTS-3-09 Rev 0 Page 49 of 52 XV. SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-09

~ Total Malfunctions Inserted: List (4-8)

1) RFP failure

2) RPIS failure

3) Condenser Waterbox Tube Leak

4) Fuel Failure

5) MSL Leak with MSIV Auto Close Failure

6) Stuck Open SRV

7) HPCI failure

8) RCIC trip

9) CRD Pump 3A trip

~ Malfunctions that occur after EOI entry: List (1-4)

1) MSL Leak with MSIV Auto Close Failure

2) Stuck Open SRV

3) HPCI failure

4) RCIC trip

5) CRD Pump 3A trip 4 Abnormal Events: List (1-3)

1) RFP failure

2) Condenser Waterbox Tube Leak

3) Fuel Failure

4) Stuck Open SRV 2 Major Transients: List (1-2)

1) Fuel Failure

2) MSL Leak

~ EOI's used: List (1-3)

1) EOI-1

2) EOI-2

3) EOI-3

.-L EOI Contingencies used: List (0-3)

1) C1

2) C2

~ Run Time (minutes)

~ EOI Run Time (minutes): 46 % of Scenario Run Time

3-4 Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

FCV 23-34 repair underway, clearance has 3A RHR Hx inop for containment cooling. Out of service 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , expected back in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 30 day LCO entered per T.S. 3.7.1,3.6.2.3, 3.6.2.4, 3.6.2.5. All Appendix R T.S. LCO's have been addressed. 38 CRD pump is tagged for breaker maintenance.

Operations/Maintenance for the Shift:

Raise Unit 3 to 100% power at 10MWe/min. Support maintenance on RHRSW valve. Power

was reduced for turbine valve testing which has been completed. Units 1 and 2 are at 100%

power Unusual Conditions/Problem Areas:

Thunderstorm warning in effect next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in Limestone County

Appendix A (Page 2 of 2)

Name Of Radiation Protection Person Notified: _ _--=J.=.o=e....:...N.:...::e=u=tr.=.o.:....:.n_ _ _ _ _ __

Date: _----'T:.....:::o;..:;d=a~y_ _ _ Time: _ _...:...N=o;.,:.;w'--_ _

Step# 5[16] Procedure: 3-GOI-100-12 (if not this procedure) Rev: Current RPHP Required by Ol? _(V) ~(N) RPHP Required For GOI? ~(Y) _(N)

RCI-17 Controls Necessary? ~(Y) _ _(N)

Radiation Protection Supervisor Signature for Release

_ _~=-I-')o..."e"-'-N"""'e:..:...l.{::;.::t"-yO"""V'-':....:..-_ _ _ _ Date: _----'T:.....:::o;..:;d=a~y_ _ _ Time: _ _-,-N=o~w-=--_ _

Comments: For returning Rx Power to 100% after RFP recovery Name Of Radiation Protection Person Notified:

Date: _ _ _ _ _ _ _ _ Time: _ _ _ _ _ __

Step#_ _ _ _ Procedure: _ _ _ _ _ _ (if not this procedure) Rev: _ _ __

RPHP Required by Ol? _(V) _ _(N) RPHP Required For GOI? _ _(V) _(N)

RCI-17 Controls Necessary? _(V) _ _(N)

Radiation Protection Supervisor Signature for Release

_ _ _ _ _ _ _ _ _ _ _ _ Date: _ _ _ _ _ _ _ Time: _ _ _ _ _ __

Comments:

FORWARD copies of completed Appendix pages to Radiation Protection Supervisor.

Name Of Radiation Protection Person Notified: _ _

Appendix A (Page 2 of 2)

_--=J..::::,o=e..!..N.:..=e=u:..:.:.tr..::::,o.:..:.n

--=-Jo=e::...:...:N.=e=ut:.:...;ro=n-=--_ _ ____ __ ____

Date: _---=T'

__ T:...,:o=d=a:..Ly

-=o:;..::d=a' -'-y_ _ _ Time: _ _...:....N:..=o' ..:....;N=o.,:.:w_ __

-'-'w'---_ _

Step# 5.7[1] Procedure: _--=-3-..,;:0:...:,.1--=3'---_

__3=--..,; :0;. :. 1-.. .=;3__ (if not this procedure) Rev: Current RPHP Required by Ol? _(V) ~(N) RPHP Required For GOI? ~(Y) _(N)

RCI-17 Controls Necessary? ~(Y) _ __ _(N)

Radiation Protection Supervisor Signature for Release

_ --==~)o;;.:.:e:....,:N--'

_---.",,=,1-';)

o"-"e"-'--N"-'=e:..::...u:;.;:;t"-vD"'

-'='.e.::....::u=tY-' -'o'V'-'v-V"""'v-'-'-_

____ Date: _~T:....::o=d=a~y

_---=T'-=o:;..::d=a'-'-y___

_ _ _ Time: _ ___-=-N~o~w-=--

. :. .;N:.;: .o. :. .:.w__

Comments: For returning 3A RFP to service

Name Of Radiation Protection Person Notified: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date: _ _ _ _ _ _ _ _ Time:

Date: Time: _ _ _ _ _ __

Step#____

_ _ _ _ Procedure: _ _ _ _ _ _ (if not this procedure) Rev: ______ _ _ __

RPHP Required by Ol? _(V) _ __ _(N) RPHP Required For GOI? _ ___(V) _(N)

RCI-17 Controls Necessary? _(V) _ __ _(N)

Radiation Protection Supervisor Signature for Release

_ _ _ _ _ _ _ _ _ _ _ _ Date: ___________ _ _ _ _ _ _ _ Time: ________ _ _ _ _ _ ___ _

Comments:

FORWARD copies of completed Appendix pages to Radiation Protection Supervisor.

.' .. '- 'f.

Appendix D 0 Scenario Outline \" l ":' \ j,;:

Form ES-D-1 ES-O-1 Facility: Browns Ferry NPP Scenario No.: 3-10 Op-Test No. : HLT 0801 SRO: SROI-1

.Examiners: Operators: . ATC: SROI-2 BOP: RO-4 Jj Initial Unit 3 is at approximately 95% power with 3B Stator Cooling Water Pump tagged Conditions: for bearing replacement and RHR Loop I in Suppression Pool Cooling following HPCI Testing.

Turnover: Units 1 and 2 are at 100%. On Unit 3, secure RHR Loop I from Suppression Pool Cooling.

Cooling . Raise power to 100% with Recirc@ 10 MWe/min. MWe/min. Support maintenance on 3A CRD Pump and 3B Stator Cooling Water Pump. Pump.

Event Event No. Malt. No. Type* Event Description N-BOP 1 ------ Secure RHR Loop I from Suppression Pool Cooling N-SRO R-ATC Raise power with Recirc flow, adjusts 2-190 valve and generator 2 ------ N-SRO transfer volts N-BOP 3 ed27d TS-SRO Evaluate Technical Specifications on loss of HPCI (B Logic)

C-ATC RPS Level instrument failure (blown fuse), fuse) , reset % scram after 4 th30v 0 fuse replaced C-SRO C-BOP FPCP 3A failure/trip - AOI response and restores cooling per 3-5 sw10a C-SRO AOI-78-1 Loss of RBCCW - AOI response and attempted recovery, power 6 multiple C-ALL reduction and Manual SCRAM 7 fw18100 fw18 100 M-ALL RFW Line Rupture in Turbine Building 8 th211.5 th211 .5 M-ALL Recirculation line break in Drywell

(N)ormal, (R)eactivity, (R)eactivity, (I)nstrument, (I )nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 1.1-S SITE AREA 57u/:?J 57;2-//::>)

Appendix 0 Scenario Outline Form ES-O-1 Facility: Browns Ferry NPP No.:

Scenario No.: 3-10 (2) Op-Test No.: HLT 0801 SRO: SROI-3 Examiners: Operators: ATC:

~~~------~~------~

SROI-4

' - ' - - -. _ ._ _ .. _ BOP:

_ _ _ _ __ __ _ RO-5

"'---"--=-______ --I

~"--------~----------------~

~C

~. , ------~------------------~

Facility: Browns Ferry NPP No. :

Scenario No.: 3-10 (3) Op-Test No.:

No.: HLT 0801 I SRO: SROI-5 Examiners: operato~:

IOperators: ATC: RO-1 BOP:

._- _. RO-6

~--------~------------------~

f') ;:

.t:!:1::-.. ::'-- i.:

ANTICIPATED EAL: 1.1-S SITE AREA

Scenario Narrative

The Crew will remove RHR Loop I from Suppression Pool Cooling and return it to standby readiness per 01-74.

With the Unit initially at - 95% power, the operating crew will return Reactor Power to 100%

per Reactor Engineer's instructions and the RCP.

The operating crew will respond to a HPCI "8" logic power failure per ARPs and Technical Specifications and declare HPCI inoperable.

The Crew will respond to an RPS level instrument failure (blown fuse) and reset % scram after fuse is replaced.

The crew will respond to an FPCP trip and will place the 38 FPCP in service.

An earthquake occurs causing damage to various systems.

The crew will recognize and respond to a R8CCW leak inside the drywell. The crew will respond per AOI-70-1 and AOI-64-1.

A feedwater line ruptures in the turbine building causing a loss of feedwater and subsequent scram on low RPV water level (If manual scram not already inserted due to loss of R8CCW and small DW leak). The dryweilleak increases forcing the crew to spray

the suppression chamber and the drywell.

RPV water level drops to TAF as the leak increases forcing the crew to stop spraying containment and to emergency depressurize. The crew will restore water level +2" to +51" and resume drywell sprays.

Additionally, the '3D' DG fails to automatically start but can be manually started. RHR pumps 38 and 3D fail to start and Core Spray injection valve 75-53 fails to open. Core Spray Loop I and RHR Loop I injection valves must be manually opened.

ANTICIPATED EAL: 1.1-5 SITE AREA

Appendix D Scenario Outline Form ES-D-1 Facility: Browns Ferry NPP Scenario No.: 3-10 Op-Test No.: HLT 0801 SRO: . SROI-1 Examiners: Operators: ATC:<:

ATC: SROI-2

,. BOP: RO-4 i Initial Unit 3 is at approximately 90% power with 3B Stator Cooling Water Pump tagged Conditions: for bearing replacement and RHR Loop I in Suppression Pool Cooling following HPCI Testing.

Turnover: Units 1 and 2 are at 100%. On Unit 3, 3, secure RHR Loop I from Suppression Pool Cooling. Raise power to 100% with Recirc@ 10 MWe/min. Support maintenance on 3A CRD Pump and 3B Stator Cooling Water Pump.

Event Event No. Malt. No. Type* Event Description N-BOP 1 ------ N-SRO Secure RHR Loop I from Suppression Pool Cooling R-ATC 2 ------ Raise power R-SRO 3 ed27d TS-SRO Evaluate Technical Specifications on loss of HPCI C-BOP FPCP 3A failure/trip - AOI response and restores cooling per 3-4 sw10a C-SRO AOI-78-1 N-ATC Swap CRD pumps per 3-01-85 (Remove 3B pump and place 3A 5 ------

N-SRO pump in service)

Loss of RBCCW - AOI response and attempted recovery, power 6 multiple C-ALL reduction and Manual SCRAM 7 fw18100 M-ALL RFW Line Rupture in Turbine Building 8 th21 1.5 M-ALL Recirculation line break in Drywell Orywell

(N)ormal, (R)eactivity, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 1.1-5 SITE AREA

Appendix D 0 Scenario Outline Form ES-D-1 ES-O-1 Facility: Browns Ferry NPP Scenario No.: 3-10 (2) Op-Test No.: HLT 0801 F~e~: I---

Fe~: __

I------------t I

I II! SRO: SROI-3

t Operators: ATC: SROI-4 eOp; "

BOP; RO-5 Facility:

Facility: Browns Ferry NPP Scenario No.:

No. : 3-10 (3) Op-Test No.

No.:: HLT 0801 I

II SRO: SROI-5 Examiners: " Operators: ATC: ' RO-1

~--------~

~." ... _ _----'L..-_ _ _ _ _ _ _ _---' BOP: RO-6

.---~~--------~

ANTICIPATED EAL: 1.1-S SITE AREA

Scenario Narrative

The Crew will remove RHR Loop I from Suppression Pool Cooling and return it to standby readiness per 01-74.

With the Unit initially at - 90% power, the operating crew will return Reactor Power to 100%

per Reactor Engineer's instructions and the RCP.

The operating crew will respond to a HPCllogic power failure per ARPs and Technical Specifications and dec/are HPCI inoperable.

The crew will respond to an FPCP trip and will place the 38 FPCP in service.

The Crew will swap CRO pumps per 3-01-85 and contact Maintenance for PMT.

An earthquake occurs causing damage to various systems.

The crew will recognize and respond to a R8CCW leak inside the drywell. The crew will respond per AOI-70-1 and AOI-64-1.

A feedwater line ruptures in the turbine building causing a loss of feedwater and subsequent scram on low RPV water level (If manual scram not already inserted due to loss of RBCCW and small OW leak). The drywelileak increases forcing the crew to spray the suppression chamber and the drywell.

RPV water level drops to TAF as the leak increases forcing the crew to stop spraying containment and to emergency depressurize. The crew will restore water level +2" to +51" and resume drywell sprays.

Additionally, the '3~' OG fails to automatically start but can be manually started. RHR pumps 38 and 3D fail to start and Core Spray injection valve 75-53 fails to open. Core Spray Loop I and RHR Loop I injection valves must be manually opened.

ANTICIPATED EAL: 1.1-5 SITE AREA

HLTS-3-1 0 Rev 0 Page 1 of 66

SIMULATOR EVALUATION GUIDE TITLE: SECURE RHR FROM SUPPRESSION POOL COOLING, HPCI LOGIC FAILURE, RPS LEVEL INSTRUMENT FAILURE, FUEL POOL COOLANT PUMP TRIP, RBCCW LEAK IN DRYWELL, FEEDWATER LINE RUPTURE IN TURBINE BUILDING, RECIRC LINE BREAK REVISION: 0 DATE: Mar. 23, 2009 PROGRAM: BFN Operator Training - Hot License Rep required (95% - 100% w/Recirc flow @ 10MWe/min)

An RPHP is required for raising power (attached)

PREPARED:

(Operations Instructor)

\

Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HLTS-3-1 0 Rev 0 Page 2 of 66

Revision Number Description of Changes Nuclear Training Revision/Usage Log Date Pages Affected Revised 0 Initial 03/23/09 All csf

HL TS-3-1 0 Rev 0 Page 3 of 66 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

SECURE RHR FROM SUPPRESSION POOL COOLING, HPCI LOGIC FAILURE, RPS LEVEL INSTRUMENT FAILURE, FUEL POOL COOLANT PUMP TRIP, RBCCW LEAK IN DRYWELL, FEEDWATER LINE RUPTURE IN TURBINE BUILDING, RECIRC LINE BREAK IV. Length of Scenario - 1 to 1 % hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment / unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HLTS-3-1 0 Rev 0 Page 4 of 66

B. Enabling Objectives:

1. The operating crew will secure RHR from Suppression Pool cooling per 3-01-74.

2. The operating crew will recognize and respond to a HPCI Logic Failure per ARPs and Tech Specs.

3. The operating crew will recognize and respond to an inadvertent half scram due to instrument failure in accordance with ARPs and Technical Specifications.

4. The operating crew will recognize and respond to a Fuel Pool Coolant pump trip per 3-AOI-78-1.

5. The operating crew will recognize and respond to a RBCCW leak in the drywell per ARPs, 3-AOI-64-1, and 3-AOI-70-1.

6. The operating crew will recognize and respond to a Feedwater Line Break in the Turbine Building per 3-EOI-1 and 3-AOI-100-1.

7. The operating crew will recognize and respond to a LOCA per 3-EOI-2 and C1.

8. The operating crew will Emergency depressurize per C2.

HLTS-3-1 0 Rev 0 Page 5 of 66 VI.

References:

The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

HLTS-3-1 0 Rev 0 Page 6 of 66 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat hlts-3-10 MF/RF/OR# Description

1) imfdg01d DG '3D' auto start failure

2) trg e1 MODESW Set trigger

3) imf th21 (el 0) 1.520:00 1.5 20:00 LOCA

4) imf rh01b RHR pump 3B and 3D fails to start

5) imf rh01d

6) imf cs02a CS spray loop I & II inboard

7) imf cs02b injection valve auto opening failure

8) ior ypovfcv7553 fail now Valve 75-53 fails

9) ior zlohs7553a[1] on Override green light on

10) ior zlohs 3536a[1]

3536a[1} off

11) ior zdihs 3536a ptl 3B Stator Cooling Water Pump tagout 1~

12) ior zlohs 3536a[2] off

13) imf rh05b FCV 74-53 auto open failure

2. File: bat hlts-3-1 0-1

1) 2)

3)

MF/RF/OR#

imf sw08 10020:00 imf th22 2.5 2:00 imf sw02a (none 18:00)

Small Drywell leak Trip RBCCW pump 3A Description RBCCW leak in the drywell

4) imf sw02b (none 20:00) Trip RBCCW pump 3B

3. File: bat app07b MF/RF/OR# Descri tion mrf s1 01 ali n SLC to Test Tank

4. File: bat app08e MF/RF/OR# Description

1) I mrf rp14a byp Bypasses Group 6 isolation to Reactor Building

2) I mrf rp14b byp Ventilation

HL TS-3-10 TS-3-1 0 Rev 0 Page 7 of 66 IX. Console Operators Instructions HLTS-3-10 ELAPTIME DESCRIPTION/ACTION

-95% power, MOC Simulator Setup Manual rst IC 234 [david]

Simulator Setup r,f See Scenario Summary bat hlts-3-10 Verify RHR Loop I is in Suppression Pool Cooling (3A RHR pump and A2 Simulator Setup Manual RHRSW pump)

Place Hold Order Tags on 38 Stator Simulator Setup Manual Cooling Water pump.

....* :.:.:"'!'"!'_H......

r,r

~_.

When Power is being Loss of HPCI 8 Logic raised (imf ed27d)

ROLE PLAY: Report breaker 1101, on 3A 250v RMOV bd has tripped and will not reset (HPCI "B" Logic) 2 min after Tech Specs fails LlS-3-2038 downscale addressed for HPCI (imf th30v 0)

ROLE PLAY: When sent to Aux Inst room to investigate, wait 2 minutes and report LlS-3-203B reading about 0 inches in Aux Inst room and that fuse 3-FU1-3-203BA was found blown If requested to replace Replaces fuse blown fuse (dmf th30v)

ROLE PLAY: If directed to replace fuse - Report 3-FU1-3-203BA (5A-F6B) replaced in panel 9-17 5 minutes after Tech t""''' 'MWA

t

,- <~ - ".',', ".'., .,

,.,~

.,~. ,

"- Trips 3A FPCP j

Specs addressed on (imf sw10a) 2038 or when directed by I

\

lead evaluator ...

HLTS-3-1 0 Rev 0 Page 8 of 66 ROLE PLAY: When sent to investigate the trip of 3A FPCP, report that everything at the pump looks normal but the breaker shows an overcurrent trip

"'"' ' ~',.,,...,

"' ~

~

If requested to locally throttle Open 3-FCV [ Throttles valve Open (tum on Red light)

(ior zlohs7865a[2] on) 65 t -~.-:- ~ oo

_~Cooo .......:;:'.__-- - *, '

If requested to locally Throttles valve Closed (tum off Red throttle Closed 3-FCV ~ light) (dor zlohs7865a[2])

65 l * ° After FPCP swapped to 38 (takes a while to ramp in)

,1\

~

-- .,~~", ,-~-~ ....

--I-I R8CCW leak in DW leak (bat hlts-3-10-1)

OW and small DW OW ROLE PLAY: U1 Operator reports "Seismic Trigger A, B, C" is in alarm.

ROLE PLAY: AUO in Rx Bldg reports piping movement.

ROLE PLAY: Respond to other Earthquake calls when received.

. - - - - - - - - - - ----,---,:-0---=-'"""" -- ,.----"",

0" 0---;'-:;;::" .-':-'-.-r----:-:-:-----=-=-=::-:-::-:-- ----:---:-:---:-:-::---

If requested to align spare Aligns spare R8CCW pump to Unit 3 R8CCW pump to Unit 3 ,i' j

(mrf sw02 align)

Wait 3 minutes ROLE PLAY: Call and report Spare RBCCW pump aligned to Unit 3 ROLE PLAY: When requested to check level in surge tank, wait 3 minutes and report no level in sight glass and manual by-pass valve is wide open.

ROLE PLAY: RE Recommends (if called) core flow runback and inserting all rods on emergency shove sheet.

If asked to start S8GT , (

'-or"""""

.~

Starts A S8GT

!,,~ (mrf pc01 a start)

ROLE PLAY: As Unit 1 RO, call and report A SBGT train in service

? -. .A

-,-.,..,~ ",_. , ". _._.V -- --

3 minutes after rods are !fi~ Feedwater break in Turbine bldg being inserted or at scram (imf fw18 1005:00)

(imffw18 100 5:00)

HLTS-3-1 0 Rev 0 Page 9 of 66

, . . .. ~ ** M If requested to perform Align SLC to Test Tank Appendix-7B, wait 25 i (bat app07b) minutes ROLE PLAY: Call and report SLC aligned to test tank

,f""* - ...*

If requested to perform Bypass Group Isolations and allows

~7""

~ > h " __

_ _A

~

Appendix-8E, wait 3 minutes i~

!~ l"I restart of ventilation (bat app08e)

ROLE PLAY: Call and report Appendix-8E completed.

-. '" "'~ -"

After ED and DW sprays Lowers leak rate are needed, (mmfth21 (mmf th21 0.7)

Terminate the scenario when the following conditions are satisfied or when requested by Chief Examiner:

1. RPV Emergency Depressurization completed

2. Reactor Water level restored between +2 to +51"

3. Drywell Sprayed

HLTS-3-1 0 Rev 0 Page 10 of 66 Scenario Summary:

x.

The Crew will remove RHR Loop I from Suppression Pool Cooling and return it to standby readiness per 01-74.

With the Unit initially at - 95% power, the operating crew will return Reactor Power to 100% per Reactor Engineer's instructions and the RCP.

The operating crew will respond to a HPCllogic power failure per ARPs and Technical Specifications and declare HPCI inoperable.

An inadvertent half scram will occur due to an instrument failure. The crew will respond per ARPs and Tech. Specs.

The crew will respond to an FPCP trip and will place the 38 FPCP in service.

An earthquake occurs causing damage to various systems.

The crew will recognize and respond to a R8CCW leak inside the drywell. The crew will respond per AOI-70-1 and AOI-64-1.

A feedwater line ruptures in the turbine building causing a loss of feedwater and subsequent scram on low RPV water level (If manual scram not already inserted due to loss of R8CCW and small OW leak). The drywell leak increases forcing the crew to spray the suppression chamber and the drywell.

RPV water level drops to T AF as the leak increases forcing the crew to stop spraying containment and to emergency depressurize. The crew will restore water level +2" to

+51" and resume drywell sprays.

Additionally, the '3~' OG fails to automatically start but can be manually started. RHR pumps 38 and 3D fail to start and Core Spray injection valve 75-53 fails to open. Core Spray Loop I and RHR Loop I injection valves must be manually opened.

HLTS-3-1 0 Rev 0 Page 11 of 66 XI. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. SRO: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide SRO with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. ED completed

2. RPV level restored to 2" to 51" (or recovering)

3. DW sprayed

HLTS-3-1 0 Rev 0 Page 12 of 66 XII. Simulator Event Guide:

Event # 1: Secure RHR Loop I from Suppression Pool Cooling Position Expected Actions Time/Comments SRO Directs RHR Loop I returned to standby readiness per 3-01-74 section 8.6 BOP Removes RHR Loop I from Suppression Pool Cooling per 3-01-74, section 8.6 8.6 Shutdown of Loop 1(11) Suppression Pool Cooling

[1] VERIFY Suppression Pool Cooling in operation.

REFER TO Section 8.5.

[2] REVIEW the precautions and limitations in Section 3.0.

[3] NOTIFY Radiation Protection of Suppression Pool Cooling loop removed from service.

RECORD name and time of Radiation Protection representative notified in NOMS narrative log.

CAUTIONS

1) To prevent draining an RHR Loop, at least one of the RHR System test valves must be closed before stopping RHR Pumps in the associated loop.

2) To prevent excessive vibration, RHR pumps should not be allowed to operate for more than 3 minutes at minimum flow.

3) When closing throttle valve 3-FCV-74-59 and 3-FCV-74-73 RHR SYS 1(11) SUPPR POOL CLGITEST VLV, from the control room, the handswitch should be held in the close position for approximately 6 seconds after the red light extinguishes. Failure to completely close these valves could provide a leak path to the suppression pool from the RHR discharge piping.

HLTS-3-1 0 Rev 0 Page 13 of 66 XII. Simulator Event Guide:

Event # 1: Secure RHR Loop I from Suppression Pool Cooling (continued)

Position Expected Actions Time/Comments BOP [4] IF both Loop 1(11) RHR Pumps are in operation AND one pump is to be removed from service due to reduced heat load, THEN:

NIA - ONL Y 3A RHR is in service.

[5] CLOSE RHR SYS 1(11) SUPPR POOL CLGITEST VLV, 3-FCV-74-59(73).

[6] STOP RHR PUMP(s) 3A(3B) and/or 3C(3D) 3-HS-74-16A(39A).

using 3-HS-74-5A(28A) andlor 3-HS-74-16A(39AJ

[7] CLOSE RHR SYS 1(11) SUPPR CHBRIPOOL ISOL VL V, 3-FCV-74-57(71).

[8] CLOSE RHR HX(s) 3A(3B) and 3C(3D)

RHRSW OUTLET VLV(s), 3-FCV-23-34(46) and 3-FCV-23-40(52).

[9] IF RHRSW for RHR Heat Exchanger(s) A(B) and C(D) is NOT required to support other unit operations, THEN STOP RHRSW Pump(s) for the heat exchanger(s) removed from service.

[10] CHECK RHR System discharge header pressure> 48 psig, as indicated on 3-PI-74-51, RHR SYS I DISCH PRESS, and> 35 psig, as indicated on 3-PI-74-65, RHR SYS II DISCH PRESS.

NOTE RHR Room Cooling Fans automatically shut off when area temperature is < 95°F.

[11] WHEN 3-TI-74-136A and B, AlC and BID RHR PUMP ROOM TEMP indicators at Panel 3-9-3 indicate < 95°F, THEN RETURN EECW to its normal operating configuration, if desired. REFER TO 0-01-67.

HL TS-3-1 0 Rev 0 Page 14 of 66 XII. Simulator Event Guide:

Event # 2: Raise Power Position Expected Actions Time/Comments SRO Notify ODS of power increase Direct retum of U3 to Full Power using Recirc Flow per 3-GOI-1 00-12 step 5[17] and 3-01-68 ATC Raises Power w/Recirc using 3-GOI-1 00-12 and 3-01-68 3-GOI-1 00 5.0 INSTRUCTION STEPS

[6.3] WHEN desired to raise power after testing is complete, THEN PERFORM the following as directed by Unit Supervisor. (N/A Steps 5.0[7]

through 5.0[19].

RAISE Recirculation flow. REFER TO 3 68.

MAINTAIN Reactor thermal power within the limits shown on ICS and 0-TI-248, Station Reactor Engineer, as appropriate.

3-01 6.2 Adjusting Recirc Flow

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(158)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-17A(178)(17C),

push-buttons, to achieve balanced jet pump flows.

AND/OR ADJUST Recirc Pump speed 38 using, RAISE SLOW (MEDIUM), 3-HS-96-16A(168)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-18A(188)(18C),

push-buttons, to achieve balanced jet jet pump flows.

HLTS-3-1 0 Rev 0 Page 15 of 66 XII. Simulator Event Guide:

Event # 2: Raise Power (continued)

Position Expected Actions Time/Comments ATC [2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 BOP Provides peer p_eer check for Recirc adjustment Continue to monitor BOP (transfer volts, condensate flow, etc)

HL TS-3-1 0 Rev 0 Page 16 of 66 XII. Simulator Event Guide:

Event # 3: HPCI Logic Failure Position Expected Actions Time/Comments BOP Announces alarm "HPCI Logic Power Failure",

Consults ARP.

SRO Dispatches outside SRO to Aux. Instrument Room Panel 2-9-39 to check fuses and 3A RMOV Bd.

Bkr. 11 D1.

Refers to Tech Spec 3.5.1.C, 3.3.5.1.B, and 3.3.6.1.B, 14 days on HPCI, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to restore isolation capability, or isolate flowpath within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 3.5.1 BFN-UNIT 2 3.5-2 Amendment No. 253, 269 March 12, 2001ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. HPCI System inoperable.

C.1 Verify by administrative means RCIC System is OPERABLE. (Immediately)

AND C.2 Restore HPCI System to OPERABLE status.

(14 days)

HL TS-3-1 0 Rev 0 Page 17 of 66 XII. Simulator Event Guide:

Event # 3: HPCI Logic Failure (continued)

Position Expected Actions Time/Comments SRO ECCS 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

B.1 -------------NOTES-----------

1. Only applicable in MODES 1, 2, and 3.

2. Only applicable for Functions 1.a, 1.b, 2.a, and 2.b.

Declare supported ECCS feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

(1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of initiation capability for features in both divisions)

AND B.2 --------------NOTE------------

Only applicable for Functions 3.a and 3.b.

Declare High Pressure Coolant Injection (HPCI)

System inoperable.

(1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of HPCI initiation Capability)

AND B.3 Place channel in trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SRO Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with isolation capability not maintained.

B.1 Restore isolation capability.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Function 1.d when normal ventilation is not available

HLTS-3-10 Rev 0 Page 18 of 66 XII. Simulator Event Guide:

Event # 3: HPCI Logic Failure (continued)

SRO Directs investigation on tripped breaker Declares HPCI inoperable, Inform crew of 14 day LCO and 7 day Appendix R LCO ATC Announces half scram Reports half scram due to level from 3-XA-55-4A-2 Verifies RPV level normal Refers to 3-9-4 ARP 3-ARP-9-4A Operator Action:

A. VERIFY alarm by multiple indications.

B. IF level is ~2.0" AND reactor has NOT scrammed, THEN MANUALLY SCRAM the reactor. ENTER 3-EOI-1 FLOWCHART.

D. IF alarm is NOT valid or initiating condition is corrected, THEN with SRO permission, RESET Half Scram. REFER TO 3-01-99.

SRO C. DISPATCH personnel to 3-LlS-3-203 A, B, C and D to check for abnormal condition.

Determines 3-203-BA, 5A-F6B in pnl 9-17 is fuse to trip inst Consults Tech Specs, 3.3.1.1,3.3.6.1, 3.3.6.2, 3.3.7.1 determines Required actions are to place in trip in 12 hrs. which is met at this time Directs fuse replaced after report that fuse 3-203-BA was found blown Directs ~ scram reset after fuse replaced

HLTS-3-1 0 Rev 0 Page 19 of 66 XII. Simulator Event Guide:

Event # 4: RPS Level Instrument Failure (continued)

Position Expected Actions Time/Comments ATC 3-01 6.1 Reset of One RPS Trip Logic Channel

[1] VERIFY Reactor Protection System in prestartup/standby readiness alignment in accordance with Section 4.0.

[2] REVIEW all Precautions and Limitations in Section 3.0.

[3] VERIFY RPS Bus for tripped channel energized.

[4] CHECK trip signals NOT present.

[5] MOMENTARILY PLACE SCRAM RESET, 3-HS-99-5A/S5, as follows:

A. RESET FIRST B. RESET SECOND C. NORMAL

HL TS-3-1 0 Rev 0 Page 20 of 66 XII. Simulator Event Guide:

Event # 4: RPS Level Instrument Failure (continued)

Position Expected Actions Time/Comments ATC [6] CHECK the following conditions:

A. All eight SCRAM SOLENOID GROUP Al8 LOGIC RESET lights illuminated.

B. The following four lights illuminated:

SYSTEM A 8ACKUP SCRAM VALVE, 3-1 L-99-5A1A8

SYSTEM 8 8ACKUP SCRAM VALVE, 3-1 L-99-5A1CD C. Scram Discharge Volume vent and drain valves indicate open.

D. Points SOE033(Channel A3 manual scram) and SOE035 (Channels A1&A2 Auto Scram) on ICS computer or on the First Out Printer reads "NOT TRIP" for RPS "A".

E. Points SOE034 (Channel 83 manual scram) and SOE036 (Channels 81&82 Auto Scram) on ICS computer or on the First Out Printer reads "NOT TRIP" for RPS "8".

Resets annunciator(s)

HLTS-3-1 0 Rev 0 Page 21 of 66 XII. Simulator Event Guide:

Event #5: FPCP Trip Position Expected Actions Time/Comments ATC Announces alarm 3-9-4C win 1 Fuel Pool System Abnormal Reports trip of 3A Fuel Pool Cooling pump SRO Directs Entry into 3-AOI-78-1 ATC Verifies unit stable, Power, Level, Pressure BOP Refers to ARP, 3-AOI-78-1 and takes required actions.

3-AOI-78 4.2 Subsequent Actions

[1] VERIFY automatic actions have occurred.

[2] IF Fuel Pool Cooling System failure is due to a loss of SFSP level, THEN: (Otherwise N/A)

NIA - NO loss of level

[3] IF fuel pool cooling system failure is from loss of

cooling, THEN:

PERFORM the following:

[3.1] START idle FUEL POOL COOLING PUMP 3B(3A).

[3.2] ATTEMPT to re-start the tripped FUEL POOL COOLING PUMP 3A(3B).

[3.3] VERIFY RBCCW System is operating.

REFER TO 3-01-70.

[3.4] IF Fuel Pool Cooling flow cannot be established such that Fuel Pool Cooling temperature input 3-TE-78-20 on 3-TR-74-80 is available, THEN:

NOTIFY MIG to install a temporary Fuel Pool temperature monitoring device to determine Fuel Pool temperature. (Otherwise N/A)

NIA - STBYpump starts

HLTS-3-10 Rev 0 Page 22 of 66 XII. Simulator Event Guide:

Event #5: FPCP Trip (continued)

Position Expected Actions Time/Comments BOP [3.5] BYPASS fuel pool filter demineralizer to raise flow by performing the following:

THROTTLE OPEN FPC F/D BYPASS ISOL VALVE A(B), 3-FCV-078-0066(0065), using local control switch 3-HS-078-0066B(0065B) to maintain pump discharge pressure greater than 130 psig as indicated on FPC PUMP 3A(3B)

DISCH PRESS LOW, 3-PIS-078-0011(0016), on 3-LPNL-925-0016.

[3.6] IF Fuel Pool/Reactor Cavity gates are removed, THEN:

NIA - Gates instal/ed

[3.7] DIRECT the STA to ESTIMATE the time for the fuel pool temperature to rise to 125F and 150F, using the heat-up rates as provided on Attachment 1, Table 1 at least once per shift UNTIL Fuel Pool cooling is restored:

NIA - Pump restored

[3.8] PLACE RHR supplemental fuel pool cooling mode in operation, NIA - Pump restored

HLTS-3-10 Rev 0 Page 23 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Drywell Position Expected Actions Time/Comments SRO [3.9] EVALUATE Technical Specification Section 3.7.6, Spent Fuel Pool Water Level; Technical Requirements Manual 3.9.2, Spent Fuel Pool Water Temperature; and TRM 3.9.3, Spent Fuel Pool Water Chemistry.

No actions - flow restored BOP [3.10] NOTIFY RADCON NIA - Flow restored

[3.11] IF Dry Cask Storage activities are in progress, THEN:

NIA - NOT in operation SRO Dispatches AUO to FPCP and breaker to determine cause of trip Directs FPCP 3B placed in service after report of breaker problem on 3A pump SRO Informs crew that annunciation "Strong Motion Accelerograph and Seismic Trigger" received on Unit 1 Begins executing 0-AOI-100-5 EPIP-3 Alert, EAL 7.1-A

HL TS-3-1 0 Rev 0 Page 24 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Drywell Position Expected Actions Time/Comments SRO 0-AOI-100 4.2 Subsequent Actions

[1] VERIFY annunciations by noticeable building movement or some damage to nonseismic structures.

[2] CALL the National Earthquake Information Service at 1-303-273-8502 or 1-303-273-8500 and PERFORM the following:

[2.1] INFORM the Information Service of indication that an earthquake has taken place.

[2.2] REQUEST verification of an earthquake.

[3] IF the National Earthquake Information Service has verified an earthquake has occurred AND one or more of SEISMIC SWITCH A(B)(C) RX BLDG 519, 1-XA-55-22C, Window 6(7)(8) has alarmed, THEN COMMENCE a controlled shut down of all reactors. REFER TO 1, 2 and 3-GOI-100-12A.

(Otherwise N/A)

HLTS-3-1 0 Rev 0 Page 25 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Drywell Position Expected Actions Time/Comments SRO [4] IF START OF STRONG MOTION ACCELEROGRAPH (1-XA-55-22C, Window 5) OR one or more of SEISMIC SWITCH A(B)(C) RX BLDG 519, [1-XA-55-22C, Window 6(7)(8)] has alarmed, THEN DIRECT IMs to download information from the three digital accelerographs.

2.5.5.3. (Otherwise N/A)

REFER TO FSAR Section 2.5.5.3.iOtherwise

[13] DISPATCH personnel to all units Reactor Bldg elevation 519' to check torus area and corner rooms for flooding. [NRC Commitment LER 86-021]

[14] REFER TO EPIP-3, Alert, and MAKE appropriate notifications.

EAL 7.1-A Any of the following annunciations in the Unit 1 Control Room, Panel 1-XA-55-22C:

Window 6, SEISMIC SWITCH A

Window 7, SEISMIC SWITCH B

Window 8, SEISMIC SWITCH C AND Assessment by Unit 1 and 2 Control Room personnel that an earthquake has occurred.

OPERATING CONDITION:

ALL

HLTS-3-1 0 Rev 0 Page 26 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Drywell (continued)

Position Expected Actions Time/Comments BOP Reports alarm "RBCCW Surge Tank Level Low".

Consults ARP.

3-ARP-9-4C - Window 13 Operator Action:

A. ADD water to the RBCCW Surge Tank for approximately one minute or until low level alarm resets using the following:

RBCCW SYS SURGE TANK FILL VLV, 3-FCV-70-1 (Panel 3-9-4) OR

FCV-70-1 BYPASS VLV, 3-BYV-002-1369 (locally)

B. IF alarm does NOT reset, THEN CHECK tank locally.

C. IF unable to maintain RBCCW Surge Tank level, THEN REFER TO 3-AOI-70-1.

Reports alarm "RBCCW pump Discharge Header Pressure Low" Consults ARP 3-ARP-9-4C - Window 12 A. VERIFY 3-FCV-70-48 CLOSING/CLOSED.

B. VERIFY RBCCW pumps A and B in service.

C. VERIFY RBCCW surge tank low level alarm is reset.

D. DISPATCH personnel to check the following:

RBCCW surge tank level locally.

RBCCW pumps for proper operation E. REFER TO 3-AOI-70-1 for RBCCW System failure and 3-01-70 for starting spare pump.

HL TS-3-10 Rev 0 Page 27 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Drywell (continued)

Position Expected Actions Time/Comments SRO Directs removal of RWCU Determines RBCCW leak by low level alarm, low pressure, RWCU isolation.

BOP Reports loss of RWCU due to isolation. (If not previously removed)

Calls Rx Engineer to adjust heat balance Sends AUO to check out level locally in the surge tank and to look for leaks.

ATC/BOP Monitors containment parameters Reports alarm "OW to Suppression Chamber Differential Pressure Abnormal" 3-ARP-9-3B - Window 26 Automatic Action:

A. VERIFY alarm by checking Drywell to Suppression Chamber DP.

B. REFER TO 3-01-64.

C. REFER TO Tech Spec Section 3.6.2.6.

SRO Refers to 3-AOI-70-1, 3-AOI-64-1.

Directs venting per 3-AOI-64-1 Recognizes shutdown required due to earthquake

HLTS-3-1 0 Rev 0 Page 28 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Drywell (continued)

Position Expected Actions Time/Comments BOP Checks RBCCW pump suction temperature.

D~ell Pressure is High 3-AOI-64 4.2.2 Drywell

[1] CHECK Drywell pressure using multiple indications.

[2] ALIGN and START additional Drywell coolers and fans as necessary. REFER TO 3-01-64.

None necessary WARNING Stack release rates exceeding 1.4 X 107 IJci/sec, or a SI-4.8.B.1.a.1 release fraction above one will result in ODCM release limits being exceeded.

[3] VENT Drywell as follows:

[3.1] CLOSE SUPPR CHBR INBD ISOLATION VL V 3-FCV-64-34 (Panel 3-9-3).

[3.2] VERIFY OPEN, DRYWELL INBD ISOLATION VLV, 3-FCV-64-31 (Panel 3-9-3).

(PaneI3-9-3).

[3.3] VERIFY 3-FIC-84-20 is in AUTO and SET at 100 scfm (Panel 3-9-55).

[3.4] VERIFY Running, required Standby Gas Treatment Fan(s} SGTS Train(s} A, B, C (Panel 3-9-25).

HL TS-3-1 0 Rev 0 Page 29 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Drywell (continued)

Position Expected Actions Time/Comments BOP [3.5] IF required, THEN REQUEST Unit 1 Operator to START Standby Gas Treatment Fan(s) SGTS Train(s) A, B. (Otherwise N/A)

NOTE If 3-FCV-84-20 closes after placing 3-HS-64-35 to open, the valve's closure signal must be reset and 3-HS-64-35 must be returned to the OPEN position in order for 3-FCV-84-20 to RE-OPEN

[3.6] IF required, THEN RECORD venting data in 3-SI-4.7.A.2.a (Otherwise N/A)

[3.7] PLACE 3-FCV-84-20 CONTROL DW/SUPPR CHBR VENT, 3-HS-64-35, in OPEN (Panel 3-9-3).

CAUTION Stack release rates exceeding 1.4 X 107 cilsec, or a SI-4.8.B.1.a.1 release fraction above one will result in ODCM release limits being exceeded

[3.8] MONITOR stack release rates to prevent exceeding ODCM limits Directs Log AUO to monitor stack release rates Crew Reports alarm "OW Floor Drain Sump Level Abnormal" and both sump pumps running.

Notifies Chem. Lab on loss of RWCU.

HLTS-3-1 0 Rev 0 Page 30 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Drywell (continued)

Position Expected Actions Time/Comments SRO Directs beginning load reduction based on AOI 1 for loss of RBCCW or AOI-64-1 for rising drywell pressure and temperature.

Directs Core Flow runback, manual scram, trip Recirc pumps and start cooldown Directs all available OW cooling placed in service ATC 3-AOI-64 4.2.3 High Drywell Temperature

[1] IF Reactor is at power AND Drywell cooling is lost and can NOT be immediately restored, THEN PERFORM the following:

[1.1] IF core flow is above 60%, THEN REDUCE core flow to between 50-60%.

[1 .2] MANUALLY SCRAM the reactor and REFER TO 3-AOI-100-1.

3-AOI-100 4.1 Immediate Actions

[1] DEPRESS REACTOR SCRAM A and B, 3-HS-99-5A/S3A and 3-HS-99-5A/S3B, on Panel 3-9-5.

[2] IF scram is due to a loss of RPS, THEN NIA - Manual Scram inserted

[3] PLACE REACTOR MODE SWITCH, 3-HS 5A-S1, in REFUEL, THEN

[3.1] CHECK REFUEL MODE ONE ROD PERMISSIVE light, 3-XI-85-46, illuminates.

[3.2] IF REFUEL MODE ONE ROD PERMISSIVE light, 3-XI-85-46, is NOT illuminated, THEN (Otherwise N/A)

CHECK all control rod positions at Full-In Overtravel, or Full-In.

[4] PLACE REACTOR MODE SWITCH, 3-HS 5A-S1, in the SHUTDOWN position.

HLTS-3-10 Rev 0 Page 31 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Orywell (continued)

Position Expected Actions Time/Comments ATC [5] IF all control rods CAN NOT be verified fully inserted, THEN NIA - ALL Rods inserted

[6] REPORT the following status to the US:

"All rods in" or "rods out"

Power level

Mode Switch is in Shutdown

Reactor pressure

MSIV position

Reactor Level is recovering recovering or lowering.

SRO [7] US REPEAT back status to UO, eye contact is not necessary.

ATC/BOP 3-AOI-64 4.2.3 High Orywell Temperature

[1.3] INITIATE a 90°F/hr cooldown rate.

REFER TO 3-AOI-100-1.

[2] CHECK Orywell temperature using multiple

indications.

[3] ALIGN and START additional Orywell coolers and fans as necessary. REFER TO 3-01-64.

3-01 5.2 Startup of Orywell Atmospheric Cooling Coils

[1] REVIEW all Precautions and Limitations in Section 3.0.

[2] VERIFY all Prestartup/Standby Readiness requirements in Section 4.0 are satisfied.

[3] IF personnel are present in the Orywell, NIA

HLTS-3-1 0 Rev 0 Page 32 of 66 XII. Simulator Event Guide:

Event #6: RBCCW Leak In Orywell (continued)

Position Expected Actions Time/Comments BOP [4] OPEN the associated Orywell Cooler valve and damper, THEN START the associated Orywell Cooler Blower (Panel 3-9-25). Component Blower Hand-switch Associated Valve and Damper Hand-switch OW CLG UNIT 3A1 BLOWER 3-HS-70-37A 3-HS-70-16A OW CLG UNIT 3A2 BLOWER 3-HS-70-38A 3-HS-70-18A OW CLG UNIT 3A3 BLOWER 3-HS-70-39A 3-HS-70-20A OW CLG UNIT 3A4 BLOWER 3-HS-70-40A 3-HS-70-22A OW CLG UNIT 3A5 BLOWER 3-HS-70-41A 3-HS-70-24A OW CLG UNIT 3B1 BLOWER 3-HS-70-42A 3-HS-70-26A OW CLG UNIT 3B2 BLOWER 3-HS-70-43A 3-HS-70-28A OW CLG UNIT 3B3 BLOWER 3-HS-70-44A 3-HS-70-30A OW CLG UNIT 3B4 BLOWER 3-HS-70-45A 3-HS-70-32A OW CLG UNIT 3B5 BLOWER 3-HS-70-46A 3-HS-70-34A

[5] PLACE OW CLR RBCCW OUTLET TEMP SEL, 3-XS-70-36, to a position corresponding to an operating cooling unit to monitor RBCCW outlet temperature (Panel 3-9-25).

[6] IF personnel are present in the Orywell, THEN NIA ATC Trips Recirc pumps

HLTS-3-1 0 Rev 0 Page 33 of 66 XII. Simulator Event Guide:

Event #7: RFW Line Rupture In Turbine Building Position Expected Actions Time/Comments ATC/BOP Reports alarms "Hotwell A(B)(C) Level Abnormal" and level in hotwell decreasing SRO Directs manual scram. (If not already done)

ATC Manually scrams reactor. (If not already scrammed) scrammedl Verifies all rods in via:

- One rod permissive

-ICS

- Green backgrounds Reference previous excerpt on AOI-100-1 actions BOP Verifies Group Isolations (Gp 2, 3, 6, & 8) (Group 1 possible if leak not isolated prior to isolation)

SRO Enters EOI-1 on low RPV level Directs RFP discharge valves Closed Directs RCIC run for level control per Appendix-5C BOP Closes RFP discharge valves Starts RCIC perper 3-EOI APPENDIX-5C

1. IF ..... BOTH of the following exist:

RPV Pressure is at or below 50 psig, AND Bypass of RCIC low RPV pressure isolation interlocks is necessary, THEN ... EXECUTE EOI Appendix 16A concurrently with this procedure.

NIA

2. IF ..... BOTH of the following exist:

High temperature exists in the RCIC area, AND SRO directs bypass of RCIC High Temperature Isolation interlocks, THEN ... PERFORM the following:

a. EXECUTE EOI Appendix 16K concurrently with this procedure.

b. RESET auto isolation logic using RCIC AUTO-ISOL LOGIC A(B) RESET 3-XS

51 A(B )pushbuttons.

NIA

HLTS-3-10 Rev 0 Page 34 of 66 XII. Simulator Event Guide:

Event #7: RFW Line Rupture In Turbine Building (continued)

Position Expected Actions Time/Comments BOP 3. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPfTHROT VALVE RESET

4. VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL,controlier in AUTO with setpoint at 600 gpm

5. OPEN the following valves:

3-FCV-71-39, RCIC PUMP INJECTION VALVE

3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

3-FCV-71-25, RCIC LUBE OIL COOLING WTRVLV

6. PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START

7. OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPL Y VL V, to start RCIC Turbine

8. CHECK proper RCIC operation by observing the following:

a. RCIC Turbine speed accelerates above 2100 rpm.

b. RCIC flow to RPV stabilizes and is controlled automatically at 600 gpm.

c. 3-FCV-71-40, RCIC Testable Check Vlv, opens by observing 3-ZI-71-40A, DISC POSITION, red light illuminated.

d. 3-FCV-71-34, RCIC PUMP MIN FLOW VAL VE, closes as flow rises above 120 gpm

HLTS-3-10 Rev 0 Page 35 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization Position Expected Actions Time/Comments BOP 9. IF ..... BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN ... VERIFY OPEN 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

10. ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller as necessary to control injection.

Reports OW press >2.45 psig Reports all DG started except '3D', starts "3D' DG Dispatches AUO to monitor DIG's SRO Enters EOI-2 Directs venting per Appendix-12 and H2 02 analyzers in service

BOP 3-EOI APPENDIX-12

1. VERIFY at least one SGTS train in service.

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOL VLV,

3-FCV-64-29, DRYWELL VENT INBD ISOL VLV,

3-FCV-64-34, SUPPR CHBR INBOARD ISOL VLV,

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VLV

HL TS-3-10 Rev 0 Page 36 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization Position Expected Actions Time/Comments BOP 3. IF ... While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN. PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required

4. IF ... While executing this procedure, the desired vent path is lost or can not be established, THEN . PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.

5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4 OR G-9, is to begin, THEN. BEFORE CAD is initiated, PERFORM Step 13 to secure the vent path NOTE:

Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CaNT, OR 3-FIC-84-20, PATH A VENT FLOW CaNT NOTE:

Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented.

HL TS-3-1 0 Rev 0 Page 37 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 6. IF ... ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR Suppression Chamber can NOT be vented, OR SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:

Step 10 to vent the Drywell through 3-FCV-84-19, OR

Step 11 to vent the Drywell through 3-FCV-84-20.

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20.

HLTS-3-1 0 Rev 0 Page 38 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments

8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CO NT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3 54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3 55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12.

HL TS-3-1 0 Rev 0 Page 39 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 9. VENT the Suppression Chamber using 3-FIC-84-20, PATH A VENT FLOW CONT, as follows:

a. VERIFY OPEN 3-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 3-9-3).

b. PLACE keylock switch 3-HS-84-36, SUPPR CHBRlDW VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

c. VERIFY OPEN 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV (Panel 3-9-54).

d. VERIFY 3-FIC-84-20, PATH A VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

e. PLACE keylock switch 3-HS-84-20, 3-FCV-84-20 ISOLATION BYPASS, in BYPASS (Panel 3-9-55).

f. VERIFY 3-FIC-84-20, PATH A VENT FLOW CONT, is indicating approximately 100 scfm.

ste~ 12.

g. CONTINUE in this procedure at step

HLTS-3-1 0 Rev 0 Page 40 of 66

XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 10. VENT the Drywell using 3-FIC-84-19, PATH B VENT FLOW CaNT, as follows:

a. VERIFY CLOSED 3-FCV-64-141, DRYWELL DP CaMP BYPASS VALVE (Panel 3-9-3).

b. PLACE keylock switch 3-HS-84-36, SUPPR CHBRlDW VENT ISOL BYP SELECT, to DRYWELL position (Panel 3 54).

c. VERIFY OPEN 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE (Panel 3-9-54).

d. PLACE 3-FIC-84-19, PATH B VENT FLOW CaNT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

e. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3 *

55) .

f. VERIFY 3-FIC-84-19, PATH B VENT FLOW CaNT, is indicating approximately 100 scfm.

g.

Q. CONTINUE in this procedure at step 12 .

HL TS-3-1 0 Rev 0 Page 41 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 11. VENT the Drywell using 3-FIC-84-20, PATH A VENT FLOW CONT, as follows:

a. VERIFY CLOSED 3-FCV-64-141 ,

DRYWELL DP COMP BYPASS VALVE (Panel 3-9-3).

b. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to DRYWELL position (Panel 3 54).

c. VERIFY OPEN 3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV (Panel 3-9-54).

d. VERIFY 3-FIC-84-20, PATH A VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

e. PLACE keylock switch 3-HS-84-20, 3-FCV-84-20 ISOLATION BYPASS, in BYPASS (Panel 3-9-55).

f. VERIFY 3-FIC-84-20, PATH A VENT FLOW CONT, is indicating approximately 100 scfm.

HLTS-3-1 0 Rev 0 Page 42 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

Release rates as determined below:

i. IF ... PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress, THEN . .MAINTAIN release rates below those specified in Attachment 2.

ii. IF ... Severe Accident Management Guidelines are being executed, THEN . .MAINTAIN release rates below those specified by the TSC SAM Team.

iii. IF .. .venting for ANY other reason than items i or ii above, THEN . .MAINTAIN release rates below Stack release rate of 1.4 x 107 J,JCi/s AND 0-SI-4.8.8.1.a.1 release fraction of 1.

HL TS-3-1 0 Rev 0 Page 43 of 66 Simulator Event Guide:

XII.

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 13. WHEN ... ANY of the following exists:

Venting is no longer required, OR Pressure in the space being vented approaches zero, OR Directed by SRO, OR Directed by Step 3, 4, or 5, THEN ... SECURE venting as follows:

a. VERIFY the following keylock switches in OFF (Panel 3-9-54): 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT 3-HS-84-36, SUPPR CHBRlDW VENT ISOL BYP SELECT.

b. VERIFY keylock switch 3-HS-84-20, 3-FCV-84-20 ISOLATION BYPASS, in NORMAL (Panel 3-9-55).

c. VERIFY keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in CLOSE (Panel 3-9-55).

d. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54): 3-FCV-64-31, DRYWELL INBOARD ISOLATION VL V, 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV, 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

e. VERIFY CLOSED 3-FCV-64-141 ,

DRYWELL DP COMP BYPASS VALVE (Panel 3-9-3).

HLTS-3-1 0 Rev 0 Page 44 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments SRO Directs RHR Loop I & II in Suppression Pool Cooling per Appendix 17A BOP Places RHR Loop I & II in Suppression Pool Cooling per Append ix-17A 3-EOI APPENDIX-17 A

1. IF ..............Adequate core cooling is assured, OR Directed to cool the Suppression Pool irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VL V BYPASS SEL in BYPASS.

2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

c. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV

HL TS-3-1 0 Rev 0 Page 45 of 66 Simulator Event Guide:

XII.

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP d. IF ............. Directed by SRO, THEN ....... PLACE 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD in MANUAL OVERRIDE.

e. IF ............. LPCIINITIATION Signal exists, THEN ....... MOMENTARIL Y PLACE 3-XS-74-121 (129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT in SELECT.

f. IF ............. 3-FCV-74-53(67), RHR SYS 1(11) LPCIINBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV 52(66), RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

g. OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBRIPOOL ISOLVLV.

h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating.

i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11) SUPPR POOL CLGITEST VLV, to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR SYS 1(11)

FLOW:

Between 7000 and 10000 gpm for one-pump operation.

OR At or below 13000 gpm for two-pump operation.

HLTS-3-1 0 Rev 0 Page 46 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

k. MONITOR RHR Pump NPSH using Attachment 1 .

I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

m. IF ............. Additional Suppression Pool Cooling flow is necessary, THEN ....... PLACE additional RHR and RHRSW pumps in service using Steps 2.b through 2.1.

SRO Directs Appendix-5B (CRD)

ATC 3-EOI APPENDIX-5B

1. IF ..... Maximum injection flow is NOT required, NIA

2. IF ..... BOTH of the following exist:

CRD is NOT required for rod insertion, AND Maximum injection flow is required, THEN ... LINE UP ALL available CRD pumps to the RPV as follows:

a. IF ..... CRD Pump 3A is available, THEN ... VERIFY RUNNING CRD Pump 3A or 3B.

b. IF ..... CRD Pump 3B is available, THEN ... VERIFY RUNNING CRD Pump 3A or 3B.

HLTS-3-1 0 Rev 0 Page 47 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments ATC c. OPEN the following valves to increase CRD flow to the RPV:

0 3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VLV 0 3-PCV-85-27, CRD CLG WATER PRESS CONTROL VLV 0 3-FCV-85-50, CRD EXH RTN LINE SHUTOFF VALVE.

d. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, on Panel 9-5 to control injection WHILE maintaining 3-PI-85-13A, CRD ACCUM CHG WTR HDR PRESS, above 1450 psig, if possible.

e. IF ....... Additional flow is necessary to prevent or mitigate core damage, THEN

..... DISPATCH personnel to fully open the following valves as required:

0 3-THV-085-0527, CRD PUMP DISCH THROTTLING (RB NE, el 565')

0 3-BYV-085-0551, CRD PUMP TEST BYPASS (RB NE, eI565').

HL TS-3-1 0 Rev 0 Page 48 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments SRO Directs all available DW cooling Directs Suppression Chamber Sprays per Appendix-17C BOP 3-EOI APPENDIX-17C

1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in this procedure at Step 6.

2. IF .............. Adequate core cooling is assured, OR Directed to spray the Suppression Chamber irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS.

3. IF .............. Directed by SRO to spray the Suppression Chamber using Standby Coolant Supply, THEN ....... CONTINUE in this procedure at Step 7.

N/A

4. IF .............. Directed by SRO to spray the Suppression Chamber using Fire Protection, THEN ....... CONTINUE in this procedure at Step 8.

N/A

HLTS-3-1 0 Rev 0 Page 49 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

o . LPCI Initiation signal is NOT present, OR

o. Directed by SRO, THEN ....... PLACE keylock switch 3-XS 122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS 121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11) INBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV 52(66), RHR SYS 1(11) OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired RHR System 1(11) pump(s) for Suppression Chamber Spray.

f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBRIPOOL ISOL VLV.

HL TS-3-1 0 Rev 0 Page 50 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP g. OPEN 3-FCV-74-58(72), RHR SYS 1(11)

SUPPR CHBR SPRAY VALVE.

h. IF ............. RHR System 1(11) is operating ONL Y in Suppression Chamber Spray mode, THEN ....... CONTINUE in this procedure at Step 5.k.

k. MONITOR RHR Pump NPSH using Attachment 2.

I. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

m. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm flow:

o . 3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV o . 3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV o . 3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV o . 3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV.

n. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

HL TS-3-1 0 Rev 0 Page 51 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments SRO Directs Appendix-7B (SLC)

ATC 3-EOI APPENDIX-7B Performs Appendix-7B by injecting with SLC from the Boron tank or dispatching AUO to align SLC suction to the test tank

2. IF ..... RPV injection is needed immediately ONL Y to prevent or mitigate fuel damage, THEN ... CONTINUE at Step 10 to inject SLC Boron Tank to RPV.

10. UNLOCK and PLACE 3-HS-63-6A, SLC PUMP 3A13B, control switch in START PUMP 3A or START PUMP 3B (Panel 3-9-5).

11. CHECK SLC injection by observing the following:

Selected pump starts, as indicated by red light illuminated above pump control switch.

Squib valves fire, as indicated by SQUIB VALVE A and B CONTINUITY blue lights extinguished,

SLC SQUIB VALVE CONTINUITY LOST Annunciator in alarm (3-XA-55-5B, Window 20).

3-PI-63-7A, SLC PUMP DISCH PRESS, indicates above RPV pressure.

System flow, as indicated by 3-IL-63-11, SLC FLOW, red light illuminated,

SLC INJECTION FLOW TO REACTOR Annunciator in alarm (3-XA-55-5B, Window 14).

HL TS-3-1 0 Rev 0 Page 52 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments ATC 12. IF ..... Proper system operation CANNOT be verified, THEN ... RETURN TO Step 10 and START other SLC pump.

13. IF ..... SLC tank level drops to 0%,

THEN ... STOP SLC pumps.

14. DISPATCH personnel to Unit 3 SLC pump area to line up SLC Test Tank and isolate SLC Boron Tank as follows (RB NE, EI 639 ft):

SRO pirects shutting down OW blowers, recirc pumps, and

~praying the Drywell per Appendix-17B BOP 3-EOI APPENDIX-17B

1. BEFORE Drywell pressure drops below 0 psig, CONTINUE in this procedure at Step 7.

2. IF .............. Adequate core cooling is assured, OR Directed to spray the Drywell irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS.

3. VERIFY Recirc Pumps and Drywell Blowers shutdown.

4. IF .............. Directed by SRO to spray the Drywell using Standby Coolant NIA

5. IF .............. Directed by SRO to spray the Drywell using Fire Protection, NIA

HLTS-3-10 Rev 0 Page 53 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments

6. INITIATE Drywell Sprays as follows:

a. VERIFY at least one RHRSW pump sup~ying each EECW header.

supplying BOP b. IF ............. EITHER of the following exists:

. LPCI Initiation signal is NOT present, OR

Directed by SRO, THEN ....... PLACE keylock switch 3-XS 122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS 121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11) LPCIINBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV 52(66), RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired System 1(11) RHR pump(s) for Drywell Spray.

f. OPEN the following valves:

3-FCV-74-60(74), RHR SYS 1(11) DW SPRAY OUTBD VL V

3-FCV-74-61(75), RHR SYS 1(11) DW SPRAY INBD VLV.

HLTS-3-1 0 Rev 0 Page 54 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

h. IF ............. Additional Drywell Spray flow is necessary, THEN ....... PLACE the second System 1(11) RHR Pump in service.

i. MONITOR RHR Pump NPSH using Attachment 2.

j. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

k. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV.

I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

Reports drywell pressure and temperature decrease

HLTS-3-1 0 Rev 0 Page 55 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments SRO Directs ADS inhibited at < -120" and enters C1 BOP Inhibits ADS Monitors Level SRO At TAF (-162"), directs 6 ADS Valves open Directs RHR secured from sprays and re-aligned for injection until level is> -162" BOP 3-EOI APPENDIX-17B (DW Sprays) -Secure

7. WHEN ...... EITHER of the following exists:

Before drywell pressure drops below 0 psig, OR

Directed by SRO to stop Drywell Sprays, THEN ....... STOP Drywell Sprays as follows:

a. VERIFY CLOSED the following valves:

0 0

0 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE 3-FCV-74-60(74), RHR SYS 1(11) OW SPRAY OUTBD VL V 3-FCV-74-61(75), RHR SYS 1(11) OW SPRAY INBD VLV

b. VERIFY OPEN 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

c. IF ............. RHR operation is desired in ANY other mode, THEN ....... EXIT this EOI Appendix

HLTS-3-10 Rev 0 Page 56 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

BOP 3-EOI APPENDIX-17C (Supp Chmbr Sprays)-

Secure.

6. WHEN ...... EITHER of the following exists:

Before Suppression Pool pressure drops below 0 psig, OR

Directed by SRO to stop Suppression Chamber Sprays, THEN ....... STOP Suppression Chamber Sprays as follows:

a. CLOSE 3-FCV-74-58(72), RHR SYS 1(11)

SUPPR CHBR SPRAY VALVE.

b. VERIFY CLOSED 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE

c. IF ............. RHR operation is desired in ANY other mode, THEN ....... EXIT this EOI Appendix Opens 6 ADS Valves Reports all Core Spray pumps started

SRO Reports "3B" and "3D" RHR auto start failures (If not manually started)

Directs Reactor level restored +2" to +51" with Appendix-6D(6E) (CS) and Appendix-6B(6C)

(RHR), if needed

HLTS-3-1 0 Rev 0 Page 57 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 3-EOI APPENDIX-6D

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VL V

3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VL V

3-FCV-75-23, CORE SPRAY SYS IOUTBD INJECT VALVE.

2. VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALVE

3. VERIFY CS Pump 3A and/or 3C RUNNING.

Reports 3-FCV-75-25 did Not auto Open and Manually Opens 3-FCV-75-25

4. WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-25, CORE SPRAY SYS IINBD INJECT VALVE, as necessary to

control injection at or below 4000 gpm per pump.

5. MONITOR Core Spray Pump NPSH using Attachment 1 3-EOI APPENDIX-6E

1. VERIFY OPEN the following valves:

3-FCV-75-30, CORE SPRAY PUMP 3B SUPPR POOL SUCT VL V

3-FCV-75-39, CORE SPRAY PUMP 3D SUPPR POOL SUCT VL V

3-FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE.

2. VERIFY CLOSED 3-FCV-75-50, CORE SPRAY SYS II TEST VALVE.

HLTS-3-1 0 Rev 0 Page 58 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 3. VERIFY CS Pump 3B and/or 3D RUNNING.

4. WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-53, CORE SPRAY SYS IIINBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pump.

On Loop II Core Spray (App-6E) Reports to SRO that 3-FCV-75-53 did Not auto Open and will Not manually Open

5. MONITOR Core Spray Pump NPSH using Attachment 1 SRO Directs FCV-75-53 opened from the breaker BOP Restores Reactor Level +2" to +51" with RHR I per 3-EOI APPENDIX-6B

1. IF .............. Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN ....... PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL in BYPASS.

2. VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VLV

3. VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VLV

HLTS-3-1 0 Rev 0 Page 59 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 4. VERIFY CLOSED the following valves:

3-FCV-74-61, RHR SYS I DW SPRAY INBD VLV

3-FCV-74-60, RHR SYS I DW SPRAY OUTBD VLV

3-FCV-74-57, RHR SYS I SUPPR CHBRIPOOL ISOL VLV

3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE

3-FCV-74-59, RHR SYS I SUPPR POOL CLGITEST VL V

5. VERIFY RHR Pump 3A and/or 3C running.

6. WHEN ...... RPV pressure is below 450 pSig, THEN ...... .vERIFY OPEN 3-FCV-74-53, RHR SYS I LPCIINBD INJECT VALVE.

7. IF .............. RPV pressure is below 230 psig, THEN ....... VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE.

8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, as necessary to control injection.

HL TS-3-1 0 Rev 0 Page 60 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 9. MONITOR RHR Pump NPSH using Attachment 1.

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV.

11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV.

12. NOTIFY Chemistry that RHRSW is aligned to in-service RHR heat exchangers.

END6B Restores Reactor Level +2" to +51" with RHR " per 3-EOI APPENDIX-6C

1. IF .............. Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN ....... PLACE 3-HS-74-155B, LPCI SYS "

OUTBD INJ VLV BYPASS SEL in BYPASS.

2. VERIFY OPEN 3-FCV-74-24, RHR PUMP 3B SUPPR POOL SUCT VL V.

3. VERIFY OPEN 3-FCV-74-35, RHR PUMP 3D SUPPR POOL SUCT VL V.

HLTS-3-1 0 Rev 0 Page 61 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 4. VERIFY CLOSED the following valves:

3-FCV-74-75, RHR SYS II OW SPRAY INBD VLV

3-FCV-74-74, RHR SYS II OW SPRAY OUTBD VLV

3-FCV-74-71, RHR SYS II SUPPR CHBRIPOOL ISOL VLV

3-FCV-74-72, RHR SYS II SUPPR CHBR SPRAY VALVE

3-FCV-74-73, RHR SYS II SUPPR POOL CLGITEST VL V

5. VERIFY RHR Pump 3B and/or 3D running.

6. WHEN ...... RPV pressure is below 450 psig, THEN ....... VERIFY OPEN 3-FCV-74-67, RHR SYS II LPCIINBD INJECT VALVE.

7. IF .............. RPV pressure is below 230 psig,

THEN ....... VERIFY CLOSED 3-FCV-68-3, RECIRC PUMP 3A DISCHARGE VALVE.

8. THROTTLE 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE, as necessary to control injection.

9. MONITOR RHR Pump NPSH using Attachment 1.

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV.

HLTS-3-1 0 Rev 0 Page 62 of 66 XII. Simulator Event Guide:

Event #8: Recirc Line Break/Emergency Depressurization (continued)

Position Expected Actions Time/Comments BOP 11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

12. NOTIFY Chemistry that RHRSW is aligned to in-service RHR heat exchangers Reports 3-FCV-74-53 did Not auto Open but was able to Open manually Crew Restores level to +2" to +51" with Core Spray and/or RHR

SRO Directs Drywell Sprays placed back in service when level> TAF (Appendix-17B) (If needed and in the safe area of the Spray Curve)

BOP Places Drywell sprays back in service if directed per Appendix-17B SRO Declares Site Area Emergency 1.1-S-1 1.1-51 Reactor water level can NOT be maintained above -162 inches. (TAF)

OPERATING CONDITION:

ALL

HLTS-3-1 0 Rev 0 Page 63 of 66 XIII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Sprays drywell after suppression chamber pressure exceeds 12 psig but before reaching 280°F Orywell temperature or unsafe area of PSP curve

2) Emergency depressurizes RPV when RPV water level decreases belowTAF (-162") and prior to -180".

3) Restores and maintains RPV water level above TAF

HLTS-3-1 0 Rev 0 Page 64 of 66 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-10

~ Total Malfunctions Inserted: List (4-8)

1) HPCI Logic Failure

2) RPS Level Instrument Failure

3) FPC Pump trip

4) RBCCW leak

5) Feedwater Line Break

6) LOCA

7) "30" OG Auto start Failure

8) 3B/30 RHR pump Auto start failure

9) FCV 75-25 Auto Open failure and FCV 75-53 failure

10) FCV 74-53 Auto Open failure 4 Malfunctions that occur after EOI entry: List (1-4)

1) "30" OG

2) 3B/30 RHR

3) FCV-75-53 and FCV 75-25

4) FCV 74-53 Abnormal Events: List (1-3)

1) FPC Pump trip (AOI)

2) RBCCW leak (AOI) 2 Major Transients: List (1-2)

1) Feedwater Line Break

2) Small LOCA L EOI's used: List (1-3)

1) EOI-1

2) EOI-2 2 EOI Contingencies used: List (0-3)

1) C1

2) C2 85 Run Time (minutes) 40 EOI Run Time (minutes): 47 % of Scenario Run Time

~ Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

38 Stator Cooling Water Pump - bearing replacement.

Operations/Maintenance for the Shift:

Remove RHR Loop I from Suppression Pool Cooling and return to standby readiness.

Increase power to 100% with Recirc flow at 10MWe/min. Rx Engineer monitoring all limits.

Unit 3 has been in continuous operation for 122 days. Units 1 and 2 at 100% power.

Unusual Conditions/Problem Areas:

None.

Appendix A (Page 2 of 2)

Name Of Radiation Protection Person Notified: _ _--=J=o=e...:..,N=e::..=u:..:,:tr=o.:....:.n_ _ _ _ _ __

Date: _---"T:...;:o;.::d=a'-'-y_ _ _ Time: _ _.,!...;N=o..:..:w_ __

Step# 5[16] Procedure: 3-GOI-100-12 (if not this procedure) Rev: Current RPHP Required by Ol? _(V) ~(N) RPHP Required For GOI? ~(Y) _(N)

RCI-17 Controls Necessary? ~(Y) _ _(N)

Radiation Protection Supervisor Signature for Release

_ _-==1-':-1o:...=:e~N---'-"'-e:;...:::u=tr'-"o~V'v-"--_ _ _ _ Date: _---"T:...;:o=d=a'-'-y_ _ _ Time: _ _.,!...;N=o..:..:w_ __

Comments: For returning Rx Power from 90% to 100%

Name Of Radiation Protection Person Notified: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date: _ _ _ _ _ _ _ _ Time: _ _ _ _ _ __

Step#_ _ _ _ Procedure: _ _ _ _ _ _ (if not this procedure) Rev: _ _ __

RPHP Required by Ol? _(V) _ _(N) RPHP Required For GOI? _ _(V) _(N)

RCI-17 Controls Necessary? __(V) _ _(N)

Radiation Protection Supervisor Signature for Release

_ _ _ _ _ _ _ _ _ _ _ _ Date: _ _ _ _ _ _ _ Time: _ _ _ _ _ __

Comments:

FORWARD copies of completed Appendix pages to Radiation Protection Supervisor.

Appendix D Scenario Outline Form ES-D-1 Facility:

Facility: Browns Ferry NPP Scenario No.:

No.: 3-12 Op-Test No.:

No.: HlT 0801 SRO: ' SROU-1 Examiners: . Operators: . ATC: RO-2 BOP: RO-7 Initial Unit 3 is at 100% power. The 38 Diesel Generator is tagged for annual Conditions: maintenance and the Main Generator Voltage Regulator is in MANUAL following a monthly Electrical Maintenance PM. Thunderstorm warnings in area.

Turnover: Units 1 and 2 are at 100%. On Unit 3, return the Main Generator Voltage Regulator to AUTO. Lower power to 95% with Recirc to perform 3-SR-3.1 .3.3, Control Rod Exercise Test for Partially Withdrawn Control Rods. Support maintenance on 38 Diesel Generator.

Event Event No. Malf. No. Type* Event Description N-80P 1 ------ Return Generator Voltage Regulator to Auto N-SRO R-ATC 2 ------ N-SRO Lower power N-80P N-BOP N-ATC 3 ------ N-SRO Perform CRD Exercise per 3-SR-3.1.3.3 I-ATC 4 nm16a APRM Hi/lNOP trip - bypass APRM 1 TS-SRO C-80P Trip of C3 EECW - ARP response and manual start of A3 EECW 5 sw03J C-SRO pump that fails to Auto start C-80P 6 rc02 Secure RCIC after inadvertent start TS-SRO Make-up H2 when leak noticed, power reduction I scram I turbine 7 eg0725 C-ALL trip 8 ed01 M-ALL Loss of Off-Site Power 9 rc09100 M-ALL Unisolable RCIC steam leak

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (C)omponent, (M)ajor ANTICIPATED EAL: 3.1-S 3.1 SITE AREA

.\

'\ ;;

S7J-I); /~

S7J-I)J ~~

J

Appendix 0 Scenario Outline Form ES-O-1 Facility: Browns Ferry NPP Scenario No.: 3-12 (2) Op-Test No.: HLT 0801 SRO: SROI-1 Examiners: Operators: '. .' ATC: RO-3 BOP: RO-8 Facility: Browns Ferry NPP Scenario No,: No.: 3-12 (3) Op-Test No.:

No. : HLT 0801

' SRO: SROI-2 I Examiners: .'OperatorS:

Operators: ATC: RO-4 I , BOP: RO-1 ANTICIPATED EAL: 3.1-5 3.1-S - SITE AREA

Scenario Narrative

The unit is at 100% power, with '38' Diesel Generator out of service for annual maintenance. Currently in the first day of a 7 day LCO for the Diesel Generator.

The Crew will perform actions necessary to return the Generator Voltage Regulator to Automatic per 3-01-47.

The Crew will Lower Reactor Power to 95% to rated per 3-GOI-100-12.

The Crew will perform 3-SR-3.1.3.3, Control Rod Exercise Test for Partially Withdrawn Control Rods.

APRM #1 receives a critical fault due to an input/output card failure, which requires it to be bypassed.

C3 EECW pump trips and will not restart requiring starting of the A3 EECW pump, which fails to Auto start.

RCIC receives an inadvertent auto start signal which requires the crew to secure RCIC.

A Hydrogen leak on the generator occurs which will result in decision to scram and trip the turbine. When the turbine is tripped, breaker failures occur and result in loss of offsite power.

HPCI aux oil pump fails to operate, but can be restored if crew requests maintenance to investigate (after RCIC is placed in service).

When RCIC is used a steam leak occurs and RCIC fails to auto isolate and cannot be manually isolated. The RCIC steam leak will require an emergency depressurization be performed due to High area temperatures/rad levels.

Diesel Generator '3C' starts, but fails to automatically tie to the shutdown board, but may be manually tied on.

ANTICIPATED EAL: 3.1 SITE AREA

Appendix D Scenario Outline Form ES-D-1 Facility: Browns Ferry NPP Scenario No.: 3-12 Op-Test No.:

No.: HLT 0801

[

Ir r----'"

SRO~

SRO: SROU-1 I

Ex '

amlners:

Examiners: *' !. rs :

Operators: ATC: RO-2 Opaoraro BOP:, RO-7 Initial Unit 3 is at approximately 90% power due to Control Valve testing last shift. shift. The Conditions: 38 Diesel Generator is tagged for annual maintenance and the Main Generator Voltage Regulator is in MANUAL following a monthly Electrical Maintenance PM. PM .

Turnover: Units 1 and 2 are at 100%. On Unit 3, return the Main Generator Voltage Regulator to AUTO . Raise power to 100% with Recirc@ 10 MWe/min. Support maintenance on 38 Diesel Generator.

Event Event No. Malf. No. Type* Event Description N-80P 1 ------ N-SRO Return Generator Voltage Regulator to Auto R-ATC 2 ------ R-SRO Raise power I-ATC 3 nm16a APRM HillNOP trip - bypass APRM 1 TS-SRO C-80P Trip of C3 EECW - ARP response and manual start of A3 EECW 4 sw03J C-SRO pump that fails to Auto start C-80P 5 rc02 Secure RCIC after inadvertent start TS-SRO Make-up H2 when leak noticed, power reduction / scram /

6 egO? 25 eg0725 C-ALL turbine trip 7

? ed01 M-ALL Loss of Off-Site Power 8 rc09100 M-ALL Unisolable RCIC steam leak

(N)ormal , (R)eactivity, (I)nstrument, (C)omponent, (C)omponent, (M)ajor ANTICIPATED EAL: 3.1-S 3.1 SITE AREA

Appendix 0 Scenario Outline Form ES-O-1 ES-O-1 Facility: Browns Ferry NPP Scenario No. : 3-12 (2) Op-Test No.: HLT 0801 I

SRO: . SROI-1 Examiners: Operators:

Operators: ATC: . RO-3 BOP: - RO-8 Facility: Browns Ferry NPP Scenario No. : 3-12 (3) Op-Test No.: HLT 0801 Examiners:

Examiners:

1--------------1 rr---

f Operators:

Operators:

.. ~ .

SRO:

ATC:

SROI-2 RO-4 BOP: . RO-1 ANTICIPATED EAL: 3.1-S - SITE AREA

Scenario Narrative

The unit is at - 90% at reduced power due to Control Valve testing last shift, with '38' Diesel Generator out of service for annual maintenance. Currently in the first day of a 7 day LCO for the Diesel Generator.

The Crew will perform actions necessary to return the Generator Voltage Regulator to Automatic per 3-01-47.

The Crew will increase Reactor Power from 90% to rated per 3-GOI-1 00-12.

APRM #1 receives a critical fault due to an input/output card failure, which requires it to be bypassed.

C3 EECW pump trips and will not restart requiring starting of the A3 EECW pump, which fails to Auto start.

RCIC receives an inadvertent auto start signal which requires the crew to secure RCIC.

A Hydrogen leak on the generator occurs which will result in decision to trip the turbine.

When the turbine is tripped, breaker failures occur and result in loss of offsite power.

HPCI aux oil pump fails to operate, but can be restored if crew requests maintenance to investigate (after RCIC is placed in service) .

When RCIC is used a steam leak occurs and RCIC fails to auto isolate and cannot be manually isolated. The RCIC steam leak will require an emergency depressurization be performed due to High area temperatures/rad levels.

Diesel Generator '3C' starts, but fails to automatically tie to the shutdown board, but may be manually tied on .

ANTICIPATED EAL: 3.1 SITE AREA

HLTS-3-12 Rev 0 Page 1 of 57

SIMULATOR EVALUATION GUIDE TITLE: APRM FAILURE, TRIP OF C3 EECW PUMP, INADVERTANT START OF RCIC, GENERATOR HYDROGEN LEAK, LOSS OF OFFSITE POWER, HPCI AUX OIL PUMP FAILURE, RCIC STEAM LINE BREAK WITHOUT ISOLATION REVISION: 0 DATE: Jan. 11,2009 PROGRAM: BFN Operator Training - Hot License An Rep is required to raise power 90% - 100% - provide at turnover An RPHP is required to raise power to 100% - provide at turnover (see attached)

PREPARED:

(Operations Instructor)

\

Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HL TS-3-12 Rev 0 Page 2 of 57

Revision Number Description of Changes Nuclear Training Revision/Usalle Revision/Usage Log Date Pages Affected Revised 0 Initial 01/11/09 All csf

HL TS-3-12 Rev 0 Page 3 of 57 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

APRM FAILURE, TRIP OF C3 EECW PUMP, INADVERTANT START OF RCIC, GENERATOR HYDROGEN LEAK, LOSS OF OFFSITE POWER, HPCI AUX OIL PUMP FAILURE, RCIC STEAM LINE BREAK WITHOUT ISOLATION IV. Length of Scenario - 1 to 1 1'2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment / unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HLTS-3-12 Rev 0 Page 4 of 57

B. Enabling Objectives:

1. The operating crew will perform actions necessary to return the Generator Voltage Regulator to Automatic per 3-0i-47.

2. The operating crew will raise Reactor Power per 3-GOI-100-12.

3. The operating crew will recognize and respond to an APRM failure per ARPs and Ols and Technical Specifications.

4. The operating crew will recognize and respond to a trip of C3 EECW pump

5. The operating crew will recognize and respond to an inadvertent start of RCIC.

6. The operating crew will recognize and respond to a loss of generator hydrogen per ARPs.

7. The operating crew will recognize and respond to a loss of offsite power with a diesel out of service, per 0-AOI-57-1A.

8. The operating crew will recognize and respond to a RCIC steam line break without isolation; in accordance with the EOls and AOls.

HL TS-3-12 Rev 0 Page 5 of 57 VI.

References:

The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

HL TS-3-12 Rev 0 Page 6 of 57 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat hlts-3-12 MF/RF/OR# Description

1) imf dg06b DG '38' fails to start

2) mrf dg01 b open DG '38' logic bkr open

3) ior zdi3hs35234a[3] close Fails 8kr 234 closed

4) ior zlo3hs35234a[4] on Fails Red light on

5) ior zlo3hs35234a[3] on Fails Red light on

6) ior zlo3hs35234a[1] off Fails Green light off

7) ior zdihs7553a null Removes amber light

8) imf dg03c DIG '3C' Tie 8kr Auto failure

9) imf sw07a

2. File: bat hlts-3-12-1 Auto start failure of A3 EECW pump MF/RF/OR# Description

1) ior an:ov:xa553b[27] alarm_off Overrides alarm

2) imf eg07 25 35:00 Generator H2 leak

3) imf rc02 RCIC auto start

HL TS-3-12 Rev 0 Page 7 of 57

3. File: bat hlts-3-12-2 MF/RF/OR# Description

1) imf rc09 (none 10:00) 10030:00 100% steam leak in RCIC Room

2) imf rc10 RCIC failure to Auto Isolate

3) imf ed01 Loss of offsite power

4) bat hlthpaop Fails HPCI aux oil pump & green light

5) ior zdihs712a open FCV-71-2 fails as is

6) ior zdihs713a open FCV-71-3 fails as is

7) mmf eg07 .01 : 10 Reduces generator H2 leak

8) ior zaoti7569a 0 Overrides indicator downscale

4. File: bat hlts-3-12-3 MF/RF/OR# Description

1) ior zaoti7569b 165 5:00 Overrides CS room temp indo To 165°F

2) ior zaori9026a 3 4:00 Overrides CS I/RCIC rm rad to max safe

3) ior zaori9027a 3 4:45 Overrides CS II rm rad to max safe

5. File: bat hlteecw MF/RF/OR# Description

1) ior zdihs6753b Allows opening EECW from 25-32

2) ior zdihs6751 b Allows opening EECW from 25-32

3) ior zdihs6750b Allows opening EECW from 25-32

4) bat hlteecw-1 Execute bat file

HL TS-3-12 Rev 0 Page 8 of 57

6. File: bat hlteecw-1 MF/RF/OR# Description

1) dor zdihs6753b Allows valves to reclose on low pressure

2) dor zdihs6751 b Allows valves to reclose on low pressure

3) dor zdihs6750b Allows valves to reclose on low pressure

4) bat hltrpsreset Execute bat file

7. File: bat hltrpsreset MF/RF/OR# Descri~tion Description

1) mrf rp01 reset Reset RPS A

2) mrf rp02 reset Reset RPS B

3) bat hltca Execute bat file

1)

8. File:

MF/RF/OR#

mrf ia05a reset bat hltca Description Reset A air compressor

2) mrf ia05d reset Reset 0 air compressor

3) mrf ia09 reset Reset G air compressor

9. File: bat hlthpaop MF/RF/OR# Description

1) imf hp05 fails HPCI aux oil pump

2) ior zlohs7347a[1] off fails HPCI aux oil pump green light

10. File: bat hlthpaop-1 MF/RF/OR# Description

1) dmf hp05

2) dor zlohs7347a[1]

Restores HPCI aux oil pump

HLTS-3-12 Rev 0 Page 9 of 57 IX. Console Operators Instructions HLTS 3-12 ELAP TIME DESCRIPTION/ACTION Simulator Setup - 90% Power MOC manual reset 238 (david)

J'f' .,.,

.-:. ' ____N<',

Simulator Setup See File summary

--~-l

_...v~~' ,-'~"~M"

,~-",".

Simulator Setup

!(

- I (bat hlts-3-12)

Verify Voltage Regulator in Manual manual Simulator Setup Tag 38 DIG manual ELAP TIME DESCRIPTION/ACTION 3 minutes after manually raising r~

...,..~~..,-~"""',..,----."'-<<""

" ~"" ,,",,-:;..,, >-~ ~----.

APRM 1 Critical Fault power to rated i I (imf nm16a)

ROLE PLAY: If Operator tries to check pnI9-14, Floor Examinator will provide what Operator should see - APRM Blue Bypass Lights are illuminated on pnl 3-9-14 voters for APRM 1 r---- "--'--" ..."""'......,.....

.' --- - Trip of C3 EECW pump

~- I 2 min After Tech Specs addressed for the APRM i ] (imf sw03J)

ROLE PLAY: If dispatched to check C3 EECW pump breaker, report breaker tripped on overload and breaker smells burnt but no visible smoke or flames ROLE PLAY: If called to investigate failure of A3 EECW pump to auto start, wait 2 minutes and report that pump will have to be secured to continue troubleshooting ROLE PLAY: If dispatched to Intake to visually inspect EECW pumps, wait 3 minutes and report everything looks the same as when inspected on rounds earlier except that A3 is running instead of C3

HLTS-3-12 Rev 0 Page 10 of 57 4 minutes after A3 EECW started [' "

" "'''>',_, ,,," -_,' _v,>_?

r' ' '~ ' '

m

~""""'"k" _:, _,,,'.' ,,,:>/,.

'.k"_:,_,,-.'*' ,,:>/>* Inadvertent start of RCIC & Starts and TS addressed Ij I

1~

1 the H2 leak on generator (bat hlts-3-12-1)

ROLE PLAY: If sent to Aux Inst Rm, report a burning smell in pnl 9 contacted EM to troubleshoot ROLE PLAY: After 5 minutes (as EM) report a short in panel - repair time unknown ROLE PLAY: If sent to pnl 25-31, report relays 13AK2, 13AK3, 13AK4, and 13AK37 energized r--"

r-"

---"-II

......,m,..".."'_.....,....."<< .

If requested to reset local H2 panel Resets local panel alarm

~M._

Ij It (mrf an01 b reset)

I ROLE PLAY: When generator gas pressure reaches 42 PSIG or if Field Temp High alarm is in then report as AUO that the leak is on one of the manways and cannot be isolated Immediately after turbine is tripped rf'-" ---" ......_.......... . Reduces hydrogen leak & LOSP &

Ii

""- "I, others/see summary

! (bat hlts-3-12-2)

ROLE PLAY: If directed to check on status of offsite power, report that 500 kv system was lost due to failure of 234 to trip and problems with 5264 and 5268 trip circuits. Will continue to work to restore power. Not sure why 161 kv system was lost ROLE PLAY: If requested to trip 234 breaker locally, report it will not trip ROLE PLAY: If requested to energize '38' KV SID 8d from U2, report as U2 that they cannot support due to their loading requirement.

If requested to reset EECW valves, reset RPS, & Control Air, wait 5 minutes I

I!

r-"'"

r-*** *-* ."

I II

-,',""" " " ,. ~

--I Resets EECW, RPS, & CA (bat hlteecw)

ROLE PLAY: If sent to investigate HPCI aux oil pump, wait 4 minutes and report control power fuses blown in 250v RMOV bd 3A compartment 4A.

After maintenance requested and RCIC placed in service

,!i i!I

,Ii j

Ii

-I 1

Fix HPCI aux oil pump (bat hlthpaop-1)

ROLE PLAY: (If requested, after entering above bat file) Call and report HPCI aux oil pump control power fuses replaced.

HLTS-3-12 Rev 0 Page 11 of 57 Xfer switch Emergency

t."".~

('-~>'~ 7" ...".~,~

.;v-_, .~

-~ - I

,. ,-~"

~

If requested to close 71-2 & 3 from

,I, I

I (mrf rc05k emer) r- ----~ ---~-II i

___'_"V'r breaker i"'~

Xfer switch Emergency

~

N

~

I t (mrf rc05s emer)

I ROLE PLAY: Report Valves will not close from Bkr MCC r* - ......-

r- ~-.

-- Xfer switch Normal

,I I

i (mrf rc05k norm)

If requested to return Xfer SW to I norm

( .............. -

...... ....... .. ~ ~

~ . --,,-

Xfer switch Normal I

I 1f (mrf rc05s norm)

I!.

ROLE PLAY: Report xfer switches have been returned to Normal When requested by examiner Overrides 2 na nd indicator to 165°F

.,., --,..yp"-"",,--,-.-,,

and ramps RM-90-26 and 27 to

~I

--~ ~,,-,-- ~

1 I

III max safe Rad (bat hlts-3-12-3)

Terminate the scenario when the following conditions are satisfied or upon request of instructor:

1) Emergency Depressurization has been initiated

2) Water level restored to +2" to +51" (or recovering)

HLTS-3-12 Rev 0 Page 12 of 57 Scenario Summary:

x.

The unit is at - 90% at reduced power due to Control Valve testing last shift, with '38' Diesel Generator out of service for annual maintenance. Currently in the first day of a 7 day LCO for the Diesel Generator.

The Crew will perform actions necessary to return the Generator Voltage Regulator to Automatic per 3-01-47.

The Crew will increase Reactor Power from 90% to rated per 3-GOI-100-12.

APRM #1 receives a critical fault due to an input/output card failure, which requires it to be bypassed.

C3 EECW pump trips and will not restart requiring starting of the A3 EECW pump, which fails to Auto start.

RCIC receives an inadvertent auto start Signal which requires the crew to secure RCIC.

A Hydrogen leak on the generator occurs which will result in decision to trip the turbine.

When the turbine is tripped, breaker failures occur and result in loss of offsite power.

HPCI aux oil pump fails to operate, but can be restored if crew requests maintenance to investigate (after RCIC is placed in service).

When RCIC is used a steam leak occurs and RCIC fails to auto isolate and cannot be manually isolated. The RCIC steam leak will require an emergency depressurization be performed due to High area temperatures/rad levels.

Diesel Generator '3C' starts, but fails to automatically tie to the shutdown board, but may be manually tied on.

HL TS-3-12 Rev 0 Page 13 of 57 XI. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. SRO: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. Emergency Depressurization has been initiated

2. Water level restored to +2" to +51" (or recovering)

HL TS-3-12 Rev 0 Page 14 of 57 XII. Simulator Event Guide:

Event #1: Return gOp to Automatic Position Expected Actions Time/Comments SRO Directs returning voltage regulator to automatic lAW 3-01-47, section 8.14.

BOP Transfers gOp to automatic lAW 3-01-47, section 8.14.

[1] VERIFY VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, is in MAN.

[2] PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (gOP), 3-HS-57-26, to RAISE UNTIL the upper limit is reached (red light illuminated).

[3] PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (gOP), 3-HS-57-26, to LOWER UNTIL the lower limit is reached (green light illuminated).

[4] ADJUST GENERATOR FIELD VOLTAGE AUTO ADJUST (gOP), 3-HS-57-26, UNTIL GEN TRANSFER VOLTS, 3-EI-57-41, indicates zero.

[5] PLACE VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, in AUTO.

[6] VERIFY GEN VOLT REGULATOR TRIP TO MAN, 3-EA-57-132 (3-XA-55-8A, window 3) alarms.

[7] RESET GEN VOLT REGULATOR TRIP TO MAN, 3-EA-57-132 (3-XA-55-8A, window 3).

Notify SRO Main Generator Voltage Regulator returned to Automatic.

HLTS-3-12 Rev 0 Page 15 of 57 XII. Simulator Event Guide:

Event #2: Return power to 100%

Position Expected Actions Time/Comments SRO Notify ODS of power increase.

Direct return of U3 to Full Power using Recirc Flow per 3-GOI-1 00-12 step 5[17] and 3-01-68.

ATC Raises Power w/Recirc using 3-GOI-100-12 and 3-01-68, section 6.2.

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-17A(17B)(17C),

push-buttons, to achieve balanced jet pump flows.

AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS-96-16A(16B)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-18A(18B)(18C),

push-buttons, to achieve balanced jet pump flows.

[2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 BOP Provides peer check for Recirc adjustment Continue to monitor BOP (transfer volts, condensate flow, etc).

HLTS-3-12 Rev 0 Page 16 of 57 XII. Simulator Event Guide:

Event #3: APRM #1 FAILURE Position Expected Actions Time/Comments ATC Announces alarm "APRM Hillnopffrip" and "Rod withdrawal block".

Consults ARP.

Determines that APRM 1 has critical self test fault.

NOTE: Floor Examinator will provide what Operator should see at pnl 3-9 APRM Blue Bypass Lights are illuminated on pnl 3-9-14 voters for APRM 1 SRO Directs bypassing APRM 1 and consults Tech.

Specs section 3.3.1.1-1 and TRM table 3.3.4-1 and determines that no further actions required.

ATC Bypasses APRM 1 per 01-92B, section 6.1

[1] REVIEW all precautions and limitations. REFER TO Section 3.0.

[2] PLACE APRM BYPASS, 3-HS-92-7B/S3, to desired channel to be bypassed.

[3] CHECK BLUE BYPASSED lights illuminated on Panel 3-9-14 Voters.

[4] VERIFY white bypass light on Panel 3-9-5 is illuminated.

Resets alarms.

HLTS-3-12 Rev 0 Page 17 of 57 XII. Simulator Event Guide:

Event #4: C3 EECW PUMP TRIP Position Expected Actions Time/Comments BOP Announces Alarms; 9-8C win 33 Motor Tripout, 9-20A win 35 EECW South Hdr DG Section Press Low, and 9-23B win 26 4KV SD Bd Bkr Motor OL Or Trip.

Reports C3 EECW pump tripped.

Reports A3 EECW pump failed to Auto start.

SRO Directs entry into ARP for 9-20A win 35.

Directs A3 EECW pump manually started.

BOP Responds per ARP 3-9-20A win 35.

A. CHECK indications:

1. Header pressure 0-PI-67 -24/3 on Unit 3 Panel 9-20

2. EECW S HDR PUMP B FLOW, 0-FI 6A13 on Panel 3-9-20

3. EECW S HDR PUMP D FLOW, 0-FI 12A13 on Panel 3-9-20 B. CHECK Panel 3-9-3 for status of north header pump(s) breaker lights and pump motor amps normal C. NOTIFY Unit Supervisor, U1 and U2 D. START standby pump for affected header.

REFER TO 0-01-67 Clears disagreement on C3 EECW pump

HL TS-3-12 Rev 0 Page 18 of 57 XII. Simulator Event Guide:

Event #4: C3 EECW PUMP TRIP Position Expected Actions Time/Comments BOP CHECK Panel 3-9-3 for status of north header pump(s) breaker lights and pump motor amps normal.

START A3 pump using RHRSW PUMP A3(C3)

EECW NORTH HDR, O-HS-23-85A/3(91A/3) on Unit 3, and verifies all alarms reset E. DISPATCH Personnel to check affected pump room and header for abnormal conditions F. IF low pressure is due to line rupture, THEN N/A DISPATCH Personnel to check affected pump room and header for abnormal conditions.

Dispatches personnel to check charging spring on A3 EECW pump after start, SRO Refers to Tech Specs 3.7.2 and determines no action is required (No Required pumps INOP - 3 required),

HLTS-3-12 Rev 0 Page 19 of 57 XII. Simulator Event Guide:

Event #5: INADVERTANT AUTO START OF RCIC Position Expected Actions Time/Comments CREW Recognizes RCIC auto started and injected to RPV SRO Determines that RPV water levels are normal and directs RCIC secured BOP Secures RCIC by tripping RCIC and refers to 3-01-71

[1] VERIFY the following initial conditions are satisfied:

A. RCIC System is in operation or RCIC Turbine was tripped. REFER TO Section 6.0 or 8.4.

B. All RPV low-low water level RCIC initiation signals have cleared N/A

[2] REVIEW Precautions and Limitations in Section 3.0

[3] DEPRESS RCIC AUTO-INIT RESET pushbutton, 3-XS-71-52 and CHECK RCIC AUTO-INIT amber light, 3-IL-71-52 extinguished N/A

[4] DEPRESS RCIC TURBINE TRIP pushbutton, 3-HS-71-9A, and VERIFY RCIC TURB TRIPITHROT VALVE, 3-FCV-71-9, closes

[5] CLOSE RCIC TURBINE STEAM SUPPLY VL V, 3-FCV-71-8 N/A

HL TS-3-12 Rev 0 Page 20 of 57 XII. Simulator Event Guide:

Event #5: INADVERTANT AUTO START OF RCIC Position Expected Actions Time/Comments BOP [6] CHECK RCIC TURBINE SPEED, 3-SI-71-42A, is zero rpm

[7] VERIFY CLOSED RCIC PUMP MIN FLOW VALVE,3-FCV-71-34

[8] NOTIFY Radiation Protection that RCIC System is shutdown. RECORD time Radiation Protection notified in the NOMS Narrative Log. [BFN PER 126211)

The rest of procedure is N/A since initiation signal sealed in - cannot return to standby readiness SRO Checks Tech. Specs. And determines that 3.5.3.

condition A applies aRplies A 1- Verify HPCI operable and A2- Restore to operable within 14 days App-R, 7 days on 71-9 (must remain open)

Calls Maintenance Manager for repairs on RCIC

Announces to Crew that RCIC is INOP but available for injection, if necessary

HL TS-3-12 Rev 0 Page 21 of 57 XII. Simulator Event Guide:

Event #6: Hydrogen Leak Position Expected Actions Time/Comments BOP Announces alarm 9-7A window 29, "Gen Hydrogen System Abnormal" Sy§tem Consults ARP 3-9-7A Window 29 A. CHECK H2 pressure on 3-PI-35-17A on Panel 3-9-8 B. VERIFY alarm by dispatching personnel to check the H2 Control Cabinet (Elevation 565') and O~erator of alarm status inform the Unit Operator C. REFER TO 3-01-35 as required to correct abnormal condition lowerin~

Reports H2 Pressure lowering Checks H2 purity on 3-9-8 and reports no change Checks Seal oil pressure on 3-9-8 and reports pressure 8-10 psig above H2 pressure and lowering Checks Generator H2 pressure versus Load Curve

SRO in 3-01-35 or 3-01-47 Directs personnel to look for H2 Leaks and directs BOP to add H2 per 3-01-35

HLTS-3-12 Rev 0 Page 22 of 57 XII. Simulator Event Guide:

Event #6: Hydrogen Leak Position Expected Actions Time/Comments BOP Monitors H2 pressure and generator temperatures Adds H2 per 3-01-35

[1] REVIEW Precautions and Limitations in Section 3.0

[2] ENTER the Beginning of Generator Hydrogen usa~e spreadsheet Fill data in the hydrogen usage s~readsheet

[3] IF it is desired to add hydrogen using PCV-35-9 bypass valve, THEN (otherwise N/A): N/A

[4] OPEN the desired H2 FLOW CONTROL VALVE(s).

H2 FLOW CONTROL VALVE A, 3-FCV 4A

H2 FLOW CONTROL VALVE B, 3-FCV 4B

[5] IF pressure in generator does not begin to rise, as indicated on 3-PI-035-0015 or 3-PI-035-17A,

THEN (otherwise N/A)

VERIFY INSTALLED spool piece downstream of SEC CONT STA H2 TO GEN SHUTOFF valve, 3-SHV-35-547

VERIFY OPEN SEC CONT STA H2 TO GEN SHUTOFF valve, 3-SHV-35-547 N/A Evacuates Turbine floor when notified of H2 leak on generator SRO Directs load reduction via Recirc pumps to stay within capability curve per the RCP

HL TS-3-12 Rev 0 Page 23 of 57 XII. Simulator Event Guide:

Event #6: Hydrogen Leak Position Expected Actions Time/Comments ATC [1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(158)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-17A(178)(17C),

push-buttons, to achieve balanced jet pump flows.

AND/OR ADJUST Recirc Pump speed 38 using, RAISE SLOW (MEDIUM), 3-HS-96-16A(168)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-18A(188)(18C),

push-buttons, to achieve balanced jet pump flows.

[2] WHEN desired to control Recirc Pumps 3A and/or 38 speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 38 using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 Inserts rods per the RCP (If needed to continue load drop)

SRO Directs Rx Scram and Turbine trip

HL TS-3-12 Rev 0 Page 24 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER Position Expected Actions Time/Comments ATC Manually Scrams Rx Provides Scram report to SRO Power Level Pressure Crew Reports MSIV closure Verify PCIS isolations (1,2,3,6, & 8)

BOP Trips Main Turbine Reports failure of bkr 234 to trip Identifies loss of offsite power SRO Enters EOI-1 Directs Reactor Pressure be maintained 1073 psig using

< 1073psig using MSRV per App-11A MSRV_per

Directs level be maintained 2"-51" using HPCI App-5D and, or RCIC App-5C

HLTS-3-12 Rev 0 Page 25 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER Position Expected Actions Time/Comments BOP Maintains Reactor pressure per Appendix-11 A

1. IF ..... Drywell Control Air is NOT available, THEN ... EXECUTE EOI Appendix 8G, CROSSTIE CAD TO DRYWELL CONTROL AIR, CONCURRENTLY with this procedure

2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE MSRVs and CONTROL RPV pressure using other options.

3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

a. 3-PCV-1-179 MN STM LINE A RELIEF VALVE.

b. 3-PCV-1-180 MN STM LINE D RELIEF VALVE.

c. 3-PCV-1-4 MN STM LINE A RELIEF VALVE.

d. 3-PCV-1-31 MN STM LINE C RELIEF VALVE.

e. 3-PCV-1-23 MN STM LINE B RELIEF VALVE.

f. 3-PCV-1-42 MN STM LINE D RELIEF VALVE.

g. 3-PCV-1-30 MN STM LINE C RELIEF VALVE.

h. 3-PCV-1-19 MN STM LINE B RELIEF VALVE.

i. 3-PCV-1-5 MN STM LINE A RELIEF VALVE.

j. 3-PCV-1-41 MN STM LINE D RELIEF VALVE.

k. 3-PCV-1-22 MN STM LINE B RELIEF VALVE.

I. 3-PCV-1-18 MN STM LINE B RELIEF VALVE.

m. 3-PCV-1-34 MN STM LINE C RELIE VALVE.

HLTS-3-12 Rev 0 Page 26 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER Position Expected Actions Time/Comments BOP Starts RCIC per Appendix-5C

1. IF ..... BOTH of the following exist:

RPV Pressure is at or below 50 psig, AND

Bypass of RCIC low RPV pressure isolation interlocks is necessary, THEN ... EXECUTE EOI Appendix 16A concurrently with this procedure

2. IF ..... BOTH of the following exist:

High temperature exists in the RCIC area, AND

SRO directs bypass of RCIC High Temperature Isolation interlocks, THEN ... PERFORM the following:

a. EXECUTE EOI Appendix 16K concurrently with this procedure

b. RESET auto isolation logic using RCIC AUTO-ISOL LOGIC A(B) RESET 3-XS 51A(B) pushbuttons

3. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPfTHROT VALVE RESET

4. VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller in AUTO with setpoint at 600 gpm

HL TS-3-12 Rev 0 Page 27 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER Position Expected Actions Time/Comments BOP 5. OPEN the following valves:

3-FCV-71-39, RCIC PUMP INJECTION VALVE

3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

3-FCV-71-25, RCIC LUBE OIL COOLING WTRVLV

6. PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START

7. OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbine

8. CHECK proper RCIC operation by observing the following:

a. RCIC Turbine speed accelerates above 2100 rpm

b. RCIC flow to RPV stabilizes and is

controlled automatically at 600 gpm

c. 3-FCV-71-40, RCIC Testable Check Vlv, opens by observing 3-ZI-71-40A, DISC POSITION, red light illuminated

d. 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE, closes as flow rises above 120 gpm gr:>m

9. IF ..... BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN ... VERIFY OPEN 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

HL TS-3-12 Rev 0 Page 28 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER Position Expected Actions Time/Comments BOP 10. ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller as necessary to control injection

11. IF ..... It is desired to align RCIC suction to the Suppression Pool, THEN ... PERFORM the following:

a. OPEN 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE

b. OPEN 3-FCV-71-18, RCIC SUPPR POOL OUTBD SUCT VALVE

c. WHEN ... 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE, and 3-FCV 18, RCIC SUPPR POOL OUTBD SUCT VALVE, are fully open, THEN '" VERIFY CLOSED 3-FCV-71-19, RCIC CST SUCTION VALVE NOTE: Step 12.b must be performed promptly following Step 12.a to avoid loss of suction path

12. IF ..... It is desired to align RCIC suction to the Condensate Storage Tank, THEN ... PERFORM the following:

a. CLOSE 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE

b. WHEN ... 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE starts traveling closed, THEN '" OPEN 3-FCV-71-19, RCIC CST SUCTION VALVE

c. CLOSE 3-FCV-71-18, RCIC SUPPR POOL OUTBD SUCT VALVE

HLTS-3-12 Rev 0 Page 29 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER Position Expected Actions Time/Comments BOP If HPCI used (Appendix-50),

(ApQendix-5D),

VERIFY 3-IL-73-18B, HPCI TURBINE TRIP RX LVL HIGH, amber light extinguished.

VERIFY at least one SGTS train in operation VERIFY 3-FIC-73-33, HPCI SYSTEM FLOWICONTROL, controller in AUTO and set for 5,000 gpm.

NOTE: HPCI Auxiliary Oil Pump will NOT start UNTIL 3-FCV-73-16, HPCI TURBINE STEAM SUPPL Y VLV, starts to open.

PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP, handswitch in START.

Reports failure of HPCI aux oil pump.

Request maintenance on HPCI aux oil pump.

ATC Reports that '3C' Diesel failed to tie to SID Bd.

SRO Directs '3C' Diesel be manually tied to SID Bd.

Direct entry into 3-AOI-100-1.

Directs execution of 0-AOI-57-1A.

HLTS-3-12 Rev 0 Page 30 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments ATC As time permits, performs actions per 3-AOI-100-1.

Executes 0-AOI-57-1A.

4.1 Immediate Actions

[1] VERIFY Diesel Generators have started and tied to respective 4kV Shutdown Boards, THEN DISPATCH personnel to Diesel Generators Closes breaker for 3C DIG tie to 4KV SID bd

[2] VERIFY two EECW Pumps (not using the same EECW strainer) are in service supplying Diesel Generators.

[2.1] IF two EECW Pumps (not using the same EECW strainer) are not in service supplying Diesel Generators, THEN PERFORM Attachment 9 (Cooling water is required to be established within 8 minutes)

(Otherwise N/A).

[3] PERFORM the following to ensure at least one train of Diesel Generator Room Fans are energized:

VERIFY 480V DSL Aux Board A or B energized.

VERIFY 480V DSL Aux Board 3EA or 3EB energized.

Clears electrical feeder disagreements

HLTS-3-12 Rev 0 Page 31 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments ATC 4.2 Subsequent Actions

[1] IF ANY EOI entry condition is met, THEN REFER TO the appropriate EOI(s). (Otherwise N/A)

[2] VERIFY automatic actions and PERFORM any that failed to occur.

[3] WHEN EECW header pressure is restored above the reset pressure setpoint (psig) for the valves listed below, THEN FCV-67 92 FCV-67-51 -113 RESET EECW supplies to Control Air compressors and RBCCW, at Unit 1 Panel 1-LPNL-925-0032 and Unit 2,3 Panels 2(3)-25-32.

REFER TO the EECW to the RCW Crossties for Control Air & RBCCW section of 0-01-67.

[4] START Control Air Compressors G,A, and 0 as required and MONITOR system pressure. REFER TO 0-AOI-32-1.

[4.1] IF an air compressor trips on high temperature, THEN (Otherwise N/A)

NOTIFY Unit Supervisor for instructions.

[5] REFER TO 1(2)(3)-AOI-32-2, Loss of Control Air, as necessary

[6] PLACE RPS MG Sets A and B in service.

REFER TO 1(2,3)-01-99.

HL TS-3-12 Rev 0 Page 32 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments ATC NOTES

1) Station Blackout (SBO) is defined as a loss of 161 and 500kV systems and a failure of the two diesel generators which supply normal power to the two 480 V Shutdown Boards on a unit. Exiting the SBO can occur through Cross-connect capabilities as long as it does not place the Non-SBO unit in jeopardy. Analysis takes credit for only one unit being in an SBO Event.

2) This section is to be performed if at anytime during the loss of 161 and 500 kV Offsite power, the required Diesel Generators (for the Unit's 480 V Shutdown Bds) become inoperable thereby placing the unit in a SBO event. All times start with the recognition of an SBO Event, except for the time since shutdown.

3) The purpose of the alternate curves are to replace the normal curves (especially the PSP curve) which would force an Emergency Depressurization (thus losing RCIC level control) before the end of the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months coping period of the SBO analysis. Cooldown must be commenced as soon as possible at near maximum allowable rates to ensure that reactor pressure on the SBO unit is below 235 psig before 155 minutes have elapsed.

4) To support one unit in a LOOP/LOCA and another unit in a LOOP, 3 RHR pumps, 2 Core Spray pumps, 3 RHRSW pumps and 2 EECW pumps are required long term (greater than 10 minutes). The unit in the LOOP requires one RHR pump and one RHRSW pump for long term cooling requirements. DG load management will ensure the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months de-rated DG limit is not exceeded by removing non-required manually removing non-re_quired loads.

HLTS-3-12 Rev 0 Page 33 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments ATC [7] IF the unit(s) is under a "Station Blackout" THEN PERFORM the following: (Otherwise N/A and PROCEED TO Step 4.2[8]) 4.2l8]) N/A

[8] START the Diesel Driven Fire Pump. REFER TO 0-01-26. N/A

[9] PLACE the 43 switch for the following Busses/Boards in MANUAL:

Start Busses 1B, 2B, 1A, 2A.

Unit Boards 1 (2) (3), A (B) (C)

Common Boards A, B

[10] [NRC/C] IF containment isolation is required, THEN VERIFY the following containment isolation valves closed UNLESS they are required to be open by EOls (RG 1.155):

FCV-1-56 MN STM LINE OUTBD DRAIN ISOL

FCV-69-2 RWCU OUTBD SUCT ISOLATION

FCV-71-3 RCIC OUTBD SUCT ISOLATION

FCV-71-18 RCIC SUPPR POOL OUTBD SUCTVALVE

FCV-73-3 HPCI STEAM LINE OUTBD ISOL VALVE

FCV-73-26 HPCI SUPPR POOL INBD SUCTION VLV

FCV-73-30 HPCI MAIN PUMP MINIMUM FLOWVLV

FCV-74-47 RHR SHUTDOWN COOLING SUCT OUTBD ISOL VL V

HLTS-3-12 Rev 0 Page 34 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments ATC [11] VERIFY the following boards are energized. IF NOT, THEN REFER TO Attachment 1 to restore affected busses while continuing with this instruction.

4KV Shutdown Boards 3EA, 3EB, 3EC, 3ED 480V Shutdown Boards 3A,3B 480V DSL Aux Boards 3EA,3EB 480V RMOV Boards 3A,3B 480V Control Bay Vent Boards B 480V HVAC Board. B SRO Enters EOI-2.

Directs venting per Appendix-12 and H2 0 2 analyzers in service.

BOP Places H2 02 Analyzers in service per EOI-2.

1. Place Analyzer isolation bypass keylock switches to bypass

2. Select DW or Supp Chmbr and momentarily pull out select switch handle to start sample pumps

HLTS-3-12 Rev 0 Page 35 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP Vents Containment per Appendix-12.

1. VERIFY at least one SGTS train in service.

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV,

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

3. IF ... While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN. PERFORM step 13 to secure the vent path

and reenter this procedure if further venting is required.

4. IF '" While executing this procedure, the desired vent path is lost or can not be established, THEN.

PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.

5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4 OR G-9, is to begin, THEN. BEFORE CAD is initiated, PERFORM Step 13 to secure the vent path.

HL TS-3-12 Rev 0 Page 36 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CONT OR 3-FIC-84-20, PATH A VENT FLOW CO NT NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented

6. IF ... ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR

Suppression Chamber can NOT be vented, OR

SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:

o Step 10 to vent the Drywell through 3-FCV-84-19, OR o Step 11 to vent the Drywell through 3-FCV-84-20.

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20.

HL TS-3-12 Rev 0 Page 37 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3 54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

3-9-55J

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3 55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12.

HLTS-3-12 Rev 0 Page 38 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

Release rates as determined below:

i. IF ... PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress THEN .. MAINTAIN release rates below those specified in Attachment 2.

ii. IF ... Severe Accident Management Guidelines are being executed, THEN .

.MAINTAIN release rates below those specified bythe the TSC SAM Team.

iii. IF ... Venting for ANY other reason than items i or ii above, THEN .. MAINTAIN release rates below Stack release rate of 1.4 x 10 7 J.jCi/s AND 0-SI-4.8.B.1.a.1 release fraction of 1.

Contacts LOG AUO to monitor release rates

HL TS-3-12 Rev 0 Page 39 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments SRO Directs all available RHR be placed in Suppression Pool Cooling per App-17 A after motor breakers tripped per AOI-57-1A BOP Places available RHR in Suppression Pool cooling per Appendix-17A

1. IF .............. Adequate core cooling is assured, OR Directed to cool the Suppression Pool irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS.

2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supp!ying each EECW header.

supplying

b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

c. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

HLTS-3-12 Rev 0 Page 40 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP d. IF ............. Directed by SRO, THEN ....... PLACE 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD in MANUAL OVERRIDE.

e. IF ............. LPCIINITIATION Signal exists, THEN ....... MOMENTARIL Y PLACE 3-XS-74-121 (129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT in SELECT.

f. IF ............. 3-FCV-74-53(67), RHR SYS 1(11) LPCIINBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV 52(66), RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

g. OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBRIPOOL ISOL VL V.

h. VERIFY desired RHR pump(s) for operatin~.

Suppression Pool Cooling are operating.

i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11) SUPPR POOL CLGITEST VL V, to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR SYS 1(11)

FLOW:

Between 7000 and 10000 gpm for one-pump operation. OR

At or below 13000 gpm for two-pump operation.

HLTS-3-12 Rev 0 Page 41 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

k. MONITOR RHR Pump NPSH using Attachment 1.

I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

m. IF ............. Additional Suppression Pool Cooling flow is necessary, THEN ....... PLACE additional RHR and RHRSW pumps in service using Steps 2.b through 2.1.

HL TS-3-12 Rev 0 Page 42 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments SRO Directs 38 CRD pump be placed in service for level control, as needed per App-58 ATC Places 38 CRD pump in service per Appendix-58

1. IF ..... Maximum injection flow is NOT required, THEN '" VERIFY CRD aligned as follows:

a. VERIFY at least one CRD pump in service and aligned to Unit 3 CRD system.

b. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, as necessary to obtain flow rate of 65 to 85 gpm.

c. THROTILE 3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VL V, to maintain 250 to 350 psid drive water header pressure differential.

d. EXIT this procedure.

2. IF ..... 80TH of the following exist:

CRD is NOT required for rod insertion, AND

Maximum injection flow is required, THEN ... LINE UP ALL available CRD pumps to the RPV as follows:

HL TS-3-12 Rev 0 Page 43 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments ATC a. IF ..... CRD Pump 3A is available, THEN

... VERIFY RUNNING CRD Pump 3A or 38.

b. IF ..... CRD Pump 3B is available, THEN

... VERIFY RUNNING CRD Pump 3A or 3B.

c. OPEN the following valves to increase CRD flow to the RPV:

3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VL V

3-PCV-85-27, CRD CLG WATER PRESS CONTROL VLV

3-FCV-85-50, CRD EXH RTN LINE SHUTOFF VALVE.

d. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, on Panel 9-5 to control injection WHILE maintaining 3-PI-85-13A, CRD ACCUM CHG WTR HDR PRESS,

above 1450 psig, if possible.

e. IF ....... Additional flow is necessary to prevent or mitigate core damage, THEN

..... DISPATCH personnel to fully open the following valves as required:

3-THV-085-0527, CRD PUMP DISCH THROTILING (RB NE, eI565')

3-BYV-085-0551, CRD PUMP TEST BYPASS (RB NE, el 565').

HLTS-3-12 Rev 0 Page 44 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP When notified by maintenance that HPCI aux oil pump control power fuses replaced (if requested),

initiates HPCI for level control per Appendix-50

1. IF ..... Suppression Pool level drops below 12.75 ft during HPCI operation, THEN ... TRIP HPCI and CONTROL injection using other options.

2. IF ..... Suppression Pool level CANNOT be maintained below 5.25 in.,

THEN ... EXECUTE EOI Appendix 16E concurrently with this procedure to bypass HPCI High Suppression Pool Water Level Suction Transfer Interlock.

3. IF ..... BOTH of the following exist:

High temperature exists in the HPCI area, AND

SRO directs bypass of HPCI High Temperature Isolation interlocks, THEN ... PERFORM the following:

a. EXECUTE EOI Appendix 16L concurrently with this procedure

b. RESET auto isolation logic using HPCI AUTO-ISOL LOGIC A(B) RESET 3-XS 58A(B) pushbuttons.

4. VERIFY 3-IL-73-18B, HPCI TURBINE TRIP RX LVL HIGH, amber light extinguished.

5. VERIFY at least one SGTS train in operation.

HL TS-3-12 Rev 0 Page 45 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP 6. VERIFY 3-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, controller in AUTO and set for 5,000 gpm NOTE: HPCI Auxiliary Oil Pump will NOT start UNTIL 3-FCV-73-16, HPCI TURBINE STEAM SUPPL Y VLV, starts to open.

7. PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP, handswitch in START.

8. PLACE 3-HS-73-10A, HPCI STEAM PACKING EXHAUSTER, handswitch in START.

9. OPEN the following valves:

3-FCV-73-30, HPCI PUMP MIN FLOW VALVE

3-FCV-73-44, HPCI PUMP INJECTION VALVE

10. OPEN 3-FCV-73-16, HPCI TURBINE STEAM

SUPPL Y VL V, to start HPCI Turbine

11. CHECK proper HPCI operation by observing the following:

a. HPCI Turbine speed accelerates above 2400 rpm

b. 3-FCV-73-45, HPCI Testable Check Vlv, opens by observing 3-ZI-73-45A, DISC POSITION, red light illuminated

c. HPCI flow to RPV stabilizes and is controlled automatically at 5000 gpm

d. 3-FCV-73-30, HPCI PUMP MIN FLOW VALVE, closes as flow exceeds 1200 gpm

12. VERIFY HPCI Auxiliary Oil Pump stops and the shaftdriven oil pump operates properly

13. WHEN ... HPCI Auxiliary Oil Pump stops, THEN .. , PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP, handswitch in AUTO

HL TS-3-12 Rev Page 46 of 57

° XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP 14. ADJUST 3-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, controller as necessary to control injection

15. IF ..... It is desired to align HPCI suction to the Suppression Pool, THEN .. , PERFORM the following:

a. OPEN 3-FCV-73-26, HPCI SUPPR POOL INBO SUCT VALVE

b. OPEN 3-FCV-73-27, HPCI SUPPR POOL OUTBO SUCT VALVE

c. WHEN .... 3-FCV-73-26, HPCI SUPPR POOL INBO SUCT VALVE, and 3-FCV 27, HPCI SUPPR POOL OUTBO SUCT VALVE, are fully open, THEN .... VERIFY CLOSED 3-FCV-73-40, HPCI CST SUCTION VALVE NOTE: Step 16.b must be performed promptly following Step 16.a to avoid loss of suction path.

16. IF ..... It is desired to align HPCI suction to the Condensate Storage Tank, THEN .. , PERFORM the following:

a. CLOSE 3-FCV-73-26, HPCI SUPPR POOL INBO SUCT VALVE

b. WHEN .... 3-FCV-73-26, HPCI SUPPR POOL INBO SUCT VALVE starts traveling closed, THEN .... OPEN 3-FCV-73-40, HPCI CST SUCTION VALVE

c. CLOSE 3-FCV-73-27, HPCI SUPPR POOL OUTBO SUCT VALVE

HL TS-3-12 Rev 0 Page 47 of 57 XII. Simulator Event Guide:

Event #7: LOSS OF OFFSITE POWER (continued)

Position Expected Actions Time/Comments BOP Announces alarm "RCIC Steam Line Leak Detection Temp. High" pn19-3D window 10 Checks temperature on Panel 9-21 SRO Enters EOI-3 on area Temperature (or Rad)

BOP Announces failure of RCIC to isolate Auto or manual SRO Directs RCIC isolation valves be closed locally Crew Identify 3-TS-71-41 A above max. safe value SRO Directs cooldown at < 100°F BOP Starts cooldown using MSRVs and/or HPCI (if

Crew repaired/needed)

Monitors Containment parameters Reports High radiation in CS/RCIC room 90-26a Evacuates that area of Rx Bldg

HL TS-3-12 Rev 0 Page 48 of 57 XII. Simulator Event Guide:

Event #8: RCIC LEAK WITHOUT ISOLATION Position Expected Actions Time/Comments ATC/BOP Reports CS Pump room high Humidity/temp high alarm and recognizes the B/D CS room temperatures are rising Report 2 areas above Max Safe on Temperature or Radiation SRO Enters C-2 and directs Emergency Depressurization BOP Opens 6 ADS valves Verifies 6 ADS valves open SRO Directs level be maintained 2"-51" with Core Spray (App-6D or 6E) or RHR (App-6B or 6C)

BOP Maintains level 2"-51", trims/throttles pumps as necessary

Recover level with CS Loop I 3-EOI Appendix-60

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VL V

3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VL V

3-FCV-75-23, CORE SPRAY SYS I OUTBD INJECT VALVE

2. VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALVE

3. VERIFY CS Pump 3A and/or 3C RUNNING

4. WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-25, CORE SPRAY SYS IINBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pump

5. MONITOR Core Spray Pump NPSH using Attachment 1

HL TS-3-12 Rev 0 Page 49 of 57 XII. Simulator Event Guide:

Event #8: RCIC LEAK WITHOUT ISOLATION Position Expected Actions Time/Comments BOP Recover level with CS Loop II 3-EOI Appendix-6E

1. VERIFY OPEN the following valves:

3-FCV-75-30, CORE SPRAY PUMP 3B SUPPR POOL SUCT VL V

3-FCV-75-39, CORE SPRAY PUMP 3D SUPPR POOL SUCT VL V

3-FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE

2. VERIFY CLOSED 3-FCV-75-50, CORE SPRAY SYS II TEST VALVE

3. VERIFY CS Pump 3B and/or 3D RUNNING

4. WHEN ... RPV pressure is below 450 psig, THEN .. , THROTTLE 3-FCV-75-53, CORE SPRAY SYS IIINBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pump

5. MONITOR Core Spray Pump NPSH using Attachment 1 Restores Reactor Level +2" to +51" with RHR I per 3-EOI Appendix-68

1. IF .............. Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN ....... PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL in 8YPASS

HL TS-3-12 Rev 0 Page 50 of 57 XII. Simulator Event Guide:

Event #8: RCIC LEAK WITHOUT ISOLATION Position Expected Actions Time/Comments BOP 2. VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VL V

3. VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VL V

4. VERIFY CLOSED the following valves:

3-FCV-74-61, RHR SYS I OW SPRAY INBD VLV

3-FCV-74-60, RHR SYS I OW SPRAY OUTBDVLV

3-FCV-74-57, RHR SYS I SUPPR CHBRIPOOL ISOL VL V

3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE

3-FCV-74-59, RHR SYS I SUPPR POOL CLGITEST VL V

5. VERIFY RHR Pump 3A and/or 3C running

6. WHEN ...... RPV pressure is below 450 psig, THEN ...... .vERIFY OPEN 3-FCV-74-53, RHR SYS I LPCIINBD INJECT VALVE

7. IF .............. RPV pressure is below 230 psig, THEN ....... VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE

8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, as necessary to control injection

9. MONITOR RHR Pump NPSH using Attachment 1

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV

HL TS-3-12 Rev 0 Page 51 of 57 XII. Simulator Event Guide:

Event #8: RCIC LEAK WITHOUT ISOLATION Position Expected Actions Time/Comments BOP 11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

12. NOTIFY Chemistry that RHRSW is aligned to in-service RHR heat exchangers Restores Reactor Level +2" to +51" with RHR II per 3-EOI Appendix-6C

1. IF .............. Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN ....... PLACE 3-HS-74-155B, LPCI SYS II OUTBO INJ VLV BYPASS SEL in BYPASS

2. VERIFY OPEN 3-FCV-74-24, RHR PUMP 3B SUPPR POOL SUCT VL V

3. VERIFY OPEN 3-FCV-74-35, RHR PUMP 30 SUPPR POOL SUCT VL V

4. VERIFY CLOSED the following valves:

3-FCV-74-75, RHR SYS II OW SPRAY INBO VLV

3-FCV-74-74, RHR SYS II OW SPRAY OUTBO VLV

3-FCV-74-71, RHR SYS II SUPPR CHBRIPOOL ISOL VL V

3-FCV-74-72, RHR SYS II SUPPR CHBR SPRAY VALVE

3-FCV-74-73, RHR SYS II SUPPR POOL CLGITEST VL V

HLTS-3-12 Rev 0 Page 52 of 57 XII. Simulator Event Guide:

Event #8: RCIC LEAK WITHOUT ISOLATION Position Expected Actions Time/Comments BOP 5. VERIFY RHR Pump 3B and/or 3D running

6. WHEN ..... .RPV pressure is below 450 psig, THEN ....... VERIFY OPEN 3-FCV-74-67, RHR SYS II LPCI INBD INJECT VALVE

7. IF .............. RPV pressure is below 230 psig, THEN ....... VERIFY CLOSED 3-FCV-68-3, RECIRC PUMP 3A DISCHARGE VALVE

8. THROTTLE 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE, as necessary to control injection

9. MONITOR RHR Pump NPSH using Attachment 1

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV

11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

12. NOTIFY Chemistry that RHRSW is aligned to in-service RHR heat exchangers

HLTS-3-12 Rev 0 Page 53 of 57 XII. Simulator Event Guide:

Event #8: RCIC LEAK WITHOUT ISOLATION Position Expected Actions Time/Comments Crew Recognizes load shed during depressurization

(>2.45 psig DW and <450 psig Rx) if applicable ATC Recognizes that "3C" DG failed to tie on again and ties "3C" DG to board Directs EECW valves reset, Air comp restarted and RPS restored again SRO Re-enters EOI-1 and EOI-2 on high Drywell pressure> 2.45 psig (if applicable)

ATC/BOP Secures pumps as necessary to maintain level SRO Classifies event as SAE 3.1-S

HLTS-3-12 Rev 0 Page 54 of 57 XIII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Maintains RPV water level above TAF (-162")

2) Emergency depressurizes when two Rx Bldg area Temperatures or Radiation exceed maximum safe operating values (within 5 minutes)

HLTS-3-12 HL TS-3-12 Rev 0 Page 55 of 57 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HL TS-3-12

..JL

~ Total Malfunctions Inserted: List (4-8)

1) APRM #1 FAILURE

2) C3 EECW pump Trip

3) Inadvertant start or RCIC

4) Generator H2 Leak

5) LOSP

6) HPCI Aux Oil Pump Failure

7) RCIC Leak

8) RCIC Isolation Failure (Auto and Manual)

9) DG '3C' Failure to auto tie

-+/-- Malfunctions that occur after EOI entry: List (1-4)

1) HPCI Aux Oil Pump Failure

2) RCIC Leak

3) RCIC Isolation Failure

4) DG '3C' Failure to auto tie

-L Abnormal Events: List (1-3)

1) C3 EECW pump Trip

2) Generator H2 Leak

3) LOSP 2 Major Transients: List (1-2)

1) LOSP

2) RCIC Leak

-L EOl's used: List (1-3)

1) EOI-1

2) EOI-2

3) EOI-3 1 EOI Contingencies used: List (0-3)

1) C-2

.Jill..-

...mL Run Time (minutes)

~ EOI Run Time (minutes): 56 % of Scenario Run Time

~

--L Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

38 diesel generator tagged out for annual maintenance 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months ago. Expected back in 5 days. 7 day LCO on DIG in effect per T.S. 3.8.1.8. Main Generator Voltage Regulator is in manual, Electrical Maintenance has just completed monthly PM on gOp rheostat.

Operations/Maintenance for the Shift:

Increase power to rated. 10 MWE/min per RCP and 3-GOI-100-12. step 5[171. Control valve

SR completed last shift. Support Maint on "38" Diesel Generator. Return Main Generator voltage regulator (gOP) to automatic per 3-01-47. section 8.14.

Units 1&2 at 100% power.

Unusual Conditions/Problem Areas:

Thunderstorm warnings are in effect for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Appendix A (Page 2 of 2)

Name Of Radiation Protection Person Notified: _ _--=J=oe.::::....!..N::..::e=u=tr=o.:....:.n_ _ _ _ _ __

Date: _----"T:...;:o:..;::d=a:.z..v_ _ _ Time: _ _..:....N=o;..:..:w'--_ _

Step# 5[16] Procedure: 3-GOI-100-12 (if not this procedure) Rev: Current RPHP Required by Ol? _(V) ~(N) RPHP Required For Gal? ~(Y) _(N)

RCI-17 Controls Necessary? ~(Y) _ _(N)

Radiation Protection Supervisor Signature for Release

_ _--==~Io~e~N--!....>::.e=u=ty'_"'o:..:..l/\.,~ _ _ _ _ Date: _ _T:...;:o=d=a:.z..v_ _ _ Time: _ _-,-N..:,.,o~w.!--_ _

Comments: For returning Rx Power from 90% to 100%

Name Of Radiation Protection Person Notified: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date: _ _ _ _ _ _ _ _ Time: _ _ _ _ _ __

Step#_ _ _ _ Procedure: _ _ _ _ _ _ (if not this procedure) Rev: _ _ __

RPHP Required by Ol? _(V) _ _(N) RPHP Required For Gal? _ _(V) _(N)

RCI-17 Controls Necessary? _(V) _ _(N)

Radiation Protection Supervisor Signature for Release

_ _ _ _ _ _ _ _ _ _ _ _ Date: _ _ _ _ _ _ _ Time: _ _ _ _ _ __

Comments:

FORWARD copies of completed Appendix pages to Radiation Protection Supervisor.

j Appendix D Scenario Outline Form ES-D-1 Facility: Browns Ferry NPP No.::

Scenario No. 3-13 Op-Test No.: HLT 0801 I

I! I SRO: . SROI-3 Examiners:

Operators: I

.

ATe:

ATe: .*.

. BOP:

RO-5 RO-2 Initial Unit 3 is at 100% power with 3A RHR Pump tagged to change oil due to Human Conditions: Performance error (incorrect oil was added).

Turnover: Units 1 and 2 are at 100%. On Unit 3, perform CRD Timer Test. Maintain power at 100%. Support maintenance on 3A RHR Pump; which is expected back in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Monitor Drywell pressure as there is a known N2 leak in the Drywell.

Thunderstorm warnings are in effect for the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .hours.

Event Event No. Malf. No. Type* Event Description N-ATC 1 ------ CRD Timer Test per 3-01-85, Control Rod Drive System N-SRO N-80P N-BOP Vent the Drywell per 3-01-64, Primary Containment System 2 ------ and/or 3-AOI-64-1, Drywell Pressure and/or Temperature High, N-SRO or Excessive Leakage Into Drywell I-ATC 3 rd07r3031 Respond to drifting Control Rod per 3-AOI-85-5, Rod Drift In TS-SRO R-ATC Raises power with Recirc flow after rod recovered, adjusts 2-190 4 ----- N-SRO valve and generator transfer volts N-80P N-BOP ed24a C-BOP C-80P Respond to loss of 3A 250v RMOV BD 80 and recovery, Loss of 5

hp07 TS-SRO HPCI 120v Power, C-BOP C-80P Respond to stuck open SRV per 3-AOI-1-1, Relief Valve Stuck 6 ad01c 70 C-SRO Open - valve closes when breaker opened C-BOP C-80P Respond to RWCU leak and failure of 69-1 to auto isolate per 3-7 cu04100 C-SRO AOI-64-2a, Group 3 Reactor Water Cleanup Isolation C-ATC 8 tc01 Respond to Turbine trip with failure to SCRAM C-SRO 9 th21 th215 5 M-ALL Recirc and steam line leak in Drywell

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 2.1-A or 2.4-A - ALERT

Appendix 0 D Scenario Outline Form ES-D-1 ES-O-1 Facility: Browns Ferry NPP Scenario No.

No.:: 3-13 (2) Op-Test No.:

No. : HLT 0801 r-----

.-- -----~-----------------. ...

SRO: SROI-4 I Examiners:

I ExaminlilJS: Operators: ,I.* ATC~

I-..:;...A;:.T . _~_..---:R...:..O=._-6=---_ _-1

.:. .C.;:;,; ,.;:. ._

i BOP: RO-3 ANTICIPATED EAL: 2.1-A or 2.4-A - ALERT

Scenario Narrative

Unit 3 is at 100% power with RHR Pump 3A tagged out.

The Crew will perform a CRD timer test lAW 01-85.

Drywell pressure will rise and the Crew will vent the Drywell per 3-01-64 or 3-AOI-64-1.

A control rod will drift into the core and the crew will respond lAW appropriate procedures.

The Crew will maneuver power to recover drifted rod.

A loss of 3A 250V RMOV Board occurs in conjunction with a loss of HPCI 120V power.

When the 3A 250V RMOV Board is restored, SRV 1-22 will fail open and the Crew will respond per 3-AOI-1-1 to close the valve when power is removed (if Crew elects to restore power, the SRV will re-open and stay open).

After the ARPs, TS, & TRM are addressed, the crew will respond to a RWCU leak and failure to auto isolate lAW 3-AOI-64-2A. Manual isolation of 69-1 valve will be successful.

The turbine will trip and the bypass valves will fail to operate. The Reactor will fail to auto scram on the turbine trip or the resulting high Reactor pressure but manual scram will function and insert all control rods.

Following the reactor scram Drywell pressure and temperature will rise requiring the Crew to enter and execute 3-EOI-2.

The Crew will spray the Pressure Suppression Chamber. When the Drywell is required to be sprayed, logic failure (Loop I) and inoperable valves (Loop II) will prevent the Drywell from being sprayed.

The Crew will have to Emergency Depressurize on Suppression Chamber pressure (PSP curve) or Drywell temperature (280°F).

Drywell Sprays will be made available after the Emergency Depressurization allowing the crew to spray the Drywell preventing possible loss of level instrumentation

ANTICIPATED EAL: 2.1-A or 2.4-A - ALERT

Appendix D 0 Scenario Outline Form ES*D*1 Facility: Browns Ferry NPP Scenario No.: 3-13 Op-Test No.:

No. : HLT 0801 r---:-c-"

~

¥_--.

I SRO: ,. SROI-3 I Examiners:

Examiners: . .Operators: ATC: ._--- RO-5 BOP: RO-2 Initial Unit 3 is at 100% power with 3A RHR Pump tagged to change oil due to Human Conditions: Performance error (incorrect oil was added)added)..

Turnover: Units 1 and 2 are at 92%. On Unit 3, perform CRO CRD Timer Test. Lower power to 92% with Recirc. Support maintenance on 3A RHR Pump; which is expected back in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Monitor Drywell Orywell pressure as there is a known N2 leak in the Drywell.

Orywell.

Thunderstorm warnings are in effect for the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . hours.

Event Event No. Malf. No. Type* Event Description N-ATC 1 ------ CRD Timer Test CRO N-SRO R-ATC 2 ------ R-SRO Lower power N-80P N-SOP 3 ------ Vent the Drywell Orywell per the 01 N-SRO I-ATC 4 rd07r3031 Respond to drifting Control Rod per the AOI TS-SRO ed24a C-80P C-SOP Respond to loss of 3A 250v RMOV 80 SO and recovery, Respond 5 hp07 TS-SRO to stuck open SRV per AOI - valve closes when breaker opened ad01c 70 C-80P C-SOP 6 cu04100 Respond to RWCU leak and failure of 69-1 to auto isolate C-SRO C-ATC 7 tc01 Respond to Turbine trip with failure to SCRAM C-SRO 8 th21 5 M-ALL Recirc and steam line leak in Drywell Orywell

(N)ormal, (R)eactivity, (I )nstrument, (I)nstrument, (C)omponent, (C)omponent, (M)ajor S *'-.A

~4~--t-~

4 ~-t-~ M~ II, ,t,~)~)

ANTICIPATED EAL: 2.1-A or 2.4-A - ALERT

Appendix D 0 Scenario Outline ES-O-1 Form ES*D*1 Facility: Browns Ferry NPP Scenario No.:

No.: 3*13 3-13 (2) Op-Test No.: HLT 0801 I Examiners: r--'

r-i 1~. Operators:

......."c SRO: SROI-4 Examineffi~:~________________~

ATC: RO-6 i[ . . BOP: RO*3 RO-3 ANTICIPATED EAL: 2.1-A2.1*A or 2.4-A - ALERT

Scenario Narrative

Unit 3 is at 100% power with RHR Pump 3A tagged out.

The Crew will perform a CRD timer test lAW 01-85.

The Crew will lower power to - 92% with Recirc flow.

Drywell pressure will rise and the Crew will vent the Drywell per 3-AOI-64-1.

A control rod will drift into the core and the crew will respond lAW appropriate procedures.

A loss of 3A 250V RMOV Board occurs in conjunction with a loss of HPCI 120V power.

When the 3A 250V RMOV Board is restored, SRV 1-22 will fail open and the Crew will respond per 3-AOI-1-1 to close the valve when power is removed (if Crew elects to restore power, the SRV will re-open and stay open).

After the ARPs, TS, & TRM are addressed, the crew will respond to a RWCU leak and failure to auto isolate lAW 3-AOI-64-2A. Manual isolation of 69-1 valve will be successful.

The turbine will trip and the bypass valves will fail to operate. The Reactor will fail to auto scram on the turbine trip or the resulting high Reactor pressure but manual scram will function and insert all control rods.

Following the reactor scram Drywell pressure and temperature will rise requiring the Crew to enter and execute 3-EOI-2.

The Crew will spray the Pressure Suppression Chamber. When the Drywell is required to be sprayed, logic failure (Loop I) and inoperable valves (Loop II) will prevent the Drywell from being sprayed.

The Crew will have to Emergency Depressurize on Suppression Chamber pressure (PSP curve) or Drywell temperature (280°F).

Drywell Sprays will be made available after the Emergency Depressurization allowing the crew to spray the Drywell preventing possible loss of level instrumentation.

ANTICIPATED EAL: 2.1-A or 2.4-A - ALERT

HLTS-3-13 Rev 0 Page 1 of 85

TITLE:

SIMULATOR EVALUATION GUIDE PERFORM CRD TIMER TEST, ROD DRIFT IN, POWER MANEUVER TO RECOVER ROD, LOSS OF 3A 250V RMOV BD, LOSS OF HPCI 120V, SRV FAILURE, RWCU LEAK WITH FAILURE TO AUTO ISOLATE, TURBINE TRIP WITHOUT BYPASS VALVES WITH AUTO SCRAM FAILURE, LOCA, FAILURE OF DRYWELL SPRAY VALVES REVISION: 0 DATE: Jan. 17,2009 PROGRAM: BFN Operator Training - Hot License Rep required for power reduction to recover rod (and pull sheet) with Recirc flow (Provide when required)

PREPARED:

REVIEWED:

(Operations Instructor)

\

Date (LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HLTS-3-13 Rev 0 Page 2 of 85

Revision Number Description of Changes Nuclear Training Revision/Usage Log Date Pages Affected Revised 0 Initial 1/17/09 All csf

HLTS-3-13 Rev 0 Page 3 of 85 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

PERFORM CRD TIMER TEST, ROD DRIFT IN, POWER MANEUVER TO RECOVER ROD, LOSS OF 3A 250V RMOV BD, LOSS OF HPCI 120V, SRV FAILURE, RWCU LEAK WITH FAILURE TO AUTO ISOLATE, TURBINE TRIP WITHOUT BYPASS VALVES WITH AUTO SCRAM FAILURE, LOCA, FAILURE OF DRYWELL SPRAY VALVES IV. Length of Scenario - 1 to 1 % hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment / unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HL TS-3-13 Rev 0 Page 4 of 85

B. Enabling Objectives:

1.

2.

The operating crew will perform a CRO timer test The operating crew will recognize and respond to a high OW pressure and vent OW per 01-64 and/or AOI-64-1.

3. The operating crew will recognize and respond to a control rod drift in per AOI-85-5

4. The operating crew will raise power after recovery of drifted rod.

5. The operating crew will recognize and respond to a loss of 2A 250V RMOV Bd and subsequent loss of 120V HPCI power supply.

6. The operating crew will recognize and respond to a failure of SRV 1-22 per 3-AOI-1-1 and determine Tech Specs with INOP SRV with HPCIINOP

7. The operating crew will recognize and respond to a RWCU leak per ARPs and 3-AOI-64-2A with failure to auto isolate (manual works).

8. The operating crew will recognize and respond to a turbine trip without bypass valves and failure to auto scram on turbine trip

9. The operating crew will recognize and respond to a LOCA per 3-EOI-1 and 3-EOI-2 and spray containment when sprays are made availible

HLTS-3-13 Rev 0 Page 5 of 85

References:

The procedures used in the simulator are controlled copies and are

VI. used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

HLTS-3-13 Rev 0 Page 6 of 85 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat hlts-3-13 MF/RF/OR# Description

1) ior zdihs7475a close Drywell spray valve failure

2) ior zdixs74121 null

3) imfdg01a 13A" DG fails to auto start

4) ior ypobkrpmparh faiLccoil 3A RHR pump tagout

5) ior zlohs745a[1] off 3A RHR pump green light off

6) imf rc08 71-8 auto open failure

7) trg e1 MODESW Assigns trigger

8) imf rp06 Fails Auto scrams (manual works)

9) 10) 11) imf rp14b imf tc02 (e1 1:00) 0 ior zdihs47130a[1] null Fails auto ARI Fails bypass valves closed Null bypass jack

2. File: bat hlts-3-13-1 MF/RF/OR# Description

1) mrf ed24a open Loss of 3A 250V RMOV Bd.

2) imf hp07 Loss of 120V HPCI power

3. File: bat hlts-3-13-2 MF/RF/OR# Description

1) mrf ed24a norm Restores power to 3A 250V RMOV Bd.

2) imf ad01c 70 SRV open at 70%

HL TS-3-13 Rev 0 Page 7 of 85

1) 4.

dmf ad01c File:

MF/RF/OR#

bat hlts-3-13-3 Description Deletes Stuck open SRV

2) mrf ad01 c out Pull SRV fuse / open breaker

5. File: bat hlts-3-13-4 MF/RF/OR# Description

1) imf cu06 RWCU leak & failure of 69-1 to auto isolate

2) imf cu04 100 10:00

3) imftc01 (none 10:00) Turbine trip

4) imf th21 (e1 15:00) 5 12:00

5) imfth22 (e1 5:00) 100 5:00 LOCA

6) imf th33a (e1 10:00) 10 15:00

6. File:

MF/RF/OR#

bat hlts-3-13-5 Description

1) dor zdihs7475a Deletes Loop II spray valve failure

2) dor zdixs74121 Deletes Loop I select logic failure

7. File: bat app18rhra MF/RF/OR# Description

1) mrf rh09 open Pump down Torus on Loop I

2) mrf rh11a on

HL TS-3-13 Rev 0 Page 8 of 85

1)

8. File:

MF/RF/OR#

mrf rh10 open bat app18rhrb Description Pump down torus on Loop"

2) mrf rh11 bon

9. File: bat app08ae MF/RF/OR# Description

1) mrf rp06a byp

2) mrf rp06b byp Bypasses MSIV isolation on low

3) mrf rp06c byp RPV water level (Appendix 8A)

4) mrf rp06d byp

5) mrf rp14a byp Bypasses Rx Bldg ventilation

6) mrf rp14b byp

10. File:

MF/RF/OR#

bat hlt3031 scram isolation on low RPV level Description

1) imf rd08r3031 0 Scram 30-31 from 9-16 & simulate closing 85-

2) mrf rd10r3031 scram 588 valve

11. File: bat hlt3031 reset MF/RF/OR# Description

1) mrf rd10r3031 norm reset scram switch on 30-31 from 9-16 &

2) dmf rd07r3031 remove drift

HLTS-3-13 Rev 0 Page 9 of 85

12. File: bat hltaddn2a MF/RF/OR# Description

1) ior zloOhs845a3[1] on Override 85-5a green light on (9-54)

2) ior zloOhs845a3[2] off Override 85-5a red light off (9-54)

3) ior zlofcv848a[1] on Override 85-8a green light on (9-54)

4) ior zlofcv848a[2] off Override 85-8a red light off (9-54)

5) ior zlozi848a[1] on Override 85-8a green light on (9-3)

6) ior zlozi848a[2] off Override 85-8a red light off (9-3)

7) ior an:ov:xa554c[29] alarm_off Override alarm 9-4c/29 off

8) ior zdiOhs845a3[1] open Override 85-5a open

9) ior zdihs848ab[1] dw Override 85-8a open to OW

1) 2)

13. File:

MF/RF/OR#

bat hltstopn2a ior zdiOhs845a3[1] close ior zdihs848ab[1] off Close HS 84-5a Description Return HS 84-8a to off

3) dor zloOhs845a3[1]

Delete green & red light overrides on 84-5a

4) dor zloOhs845a3[2]

5) dor zlofcv848a[1]

6) dor zlofcv848a[2]

Delete green & red light overrides on 84-8a

7) dor zlozi848a[1]

8) dor zlozi848a[2]

9) dor an:xa554c[29] Delete override on annunciator

10) dor zdiOhs845a3[1] Delete override on HS 84-5a

11) dor zdihs848ab[1] Delete override on HS 84-8a

HLTS-3-13 Rev 0 Page 10 of 85

14. File: bat hltsrv1-22 MF/RF/OR# Description

1) imf ad01c 50 re-opens valve

2) mrf ad01c in restores power

HLTS-3-13 Rev 0 Page 11 of 85 IX. Console Operators Instructions HLTS 3-13 ELAP TIME DESCRIPTION/ACTION Simulator Setup 100%, MOC manual Reset 256 (david)

Simulator Setup See Scenario Summary bat hlts-3-13 Simulator Setup Tag Out: 3A RHR Pump manual Simulator Setup Verify OW pressure - 1.48 psig manual ELAP TIME DESCRIPTION/ACTION After crew accepts shift and Add N2 to OW

completes CRO Timer Test When OW pressure - 1.6 psig and alarm (Pri Cont N2 pressure high) in, bat hltaddn2a Stop OW pressure increase bat hltstopn2a ROLE PLAY: When contacted as Control bay AUO, repeat will monitor release rates 2 minutes after Orywell pressure Drift rod 30-31 in alarm resets or when directed by imf rd07r3031 Lead Examiner ROLE PLAY: When contacted as Rx Engineer, repeat will check and monitor thermal limits ROLE PLAY: When dispatched to HCU as AUO, report

scram pilot air header aligned to scram inlet and outlet valves

scram riser has higher than normal temperatures

scram outlet valve 3-FCV-85-39A producing flow noise

ROLEPLAY: When directed to close 3-SHV-85-588, wait 1 minute and report valve closed (If asked status of accumulator pressure - report accumulator N2 pressure is stable)

HLTS-3-13 Rev 0 Page 12 of 85 ROLE PLAY: Establish communications as Operator at 9-16 and AUO at HCU If requested to scram rod 30-31 Scram rod 30-31 from 9-16, wait 3 minutes bat hlt3031 scram ROLE PLAY: Notify U3 UO that the scram switch for 30-31 is in scram (down)

When requested to return scram Remove scram & drift test switch to normal bat hlt3031 reset ROLE PLAY: As UO in Aux instrument room, Notify U3 UO that the scram switch for 30-31 is in normal (up position)

ROLE PLAY: As AUO at HCU, report solenoids operated normally without chatter or buzzing and the scram inlet and outlet valve stems indicate closed (also, if asked, the flow noise seems to have stopped)

When requested to slowly valve in Open 85-588 charging water (open 85-588), wait mmf rd08r3031 100 1 minute

ROLEPLAY: Call and report 85-588 valve open ROLE PLAY: Rx Engineer recommends maintaining power at - 92% with flow while notching CR 30-31 out to original position - (Provide RCP)

After rod retumed to position 12 Loss of 3A 250v RMOV bd and HPCI120v power bat hlts-3-13-1 ROLE PLAY: When dispatched to check 3A 250v RMOV bd, report that Laborers are cleaning in the area and possibly tripped the breaker (no relay targets picked up)

ROLE PLAY: When dispatched to check HPCI, report blown fuse on HPCI120VAC (3-FU2-73-33C, pnl 9-82). (If asked to replace fuse, wait 5 minutes and report fuse cleared again immediately)

When requested to close breaker Restore board, fail SRV 1-22 open for 3A 250v RMOV bd, (302 bkr or bat hIts-3-13-2 Alt bkr), then,

ROLEPLAY: Call and report that the 3A 250v RMOV Bd is re-energized

HLTS-3-13 Rev 0 Page 13 of 85 If asked to go to the Aux. Instrument Allows Control room to reset alarm room and reset ECCS ATU then mrf rc19 reset wait 1 minute ROLE PLAY: Call and report that ECCS ATU gross failures are reset When dispatched to open breaker / Close SRV 1-22 & removes power pull fuse for SRV-1-22, wait 2 bat hlts-3-13-3 minutes ROLE PLAY: Report breaker open! fuse removed for SRV-1-22 If directed to restore breaker / fuse Retum power and open SRV-1-22 for SRV-1-22, bat hltsrv1-22 ROLE PLAY: Report breaker closed! fuse reinstalled for SRV-1-22 If directed to re-open breaker / fuse Removes power / SRV stays open for SRV-1-22, mrf ad01c out

ROLE PLAY: Report breaker open! fuse removed for SRV-1-22 If directed to restore breaker / fuse Closes bkr for SRV-1-22 for SRV-1-22 (again), mrf ad01c in ROLE PLAY: Report breaker closed! fuse reinstalled for SRV-1-22 When directed by lead examiner, RWCU leak, Turbine trip, LOCA bat hlts-3-13-4 ROLE PLAY: If dispatched to check RWCU demins, report demins are on holding pumps ROLE PLAY: If requested to manually open drywell spray valve, wait for a return call on status and then report that engaging lever broke and that maintenance is working on it ROLE PLAY: If requested to look at "Select Logic" failure, wait 5 minutes and report that circuit is open and that you are still troubleshooting the problem

As soon as ED initiated, (If maintenance has been requested),

Fix 74-75 / fix select logic (Allow spraying DW) bat hlts-3-13-5

HLTS-3-13 Rev 0 Page 14 of 85

ROLEPLAY: Call and report 74-75 valve has been repaired on Loop II and/or select logic on Loop I After ED initiated, Lowers the severity of the steam break size mmf th33a 0.1 Pump torus down with Loop I or bat app18rhra If asked to execute Appendix 18 and which loop to use wait 10 Pump torus down with Loop II minutes bat app18rhrb Terminate the scenario when the following conditions are satisfied or upon request of instructor:

1) Reactor has been emergency depressurized

2) 3)

Sprays the Orywell when sprays are made available Rx water level restored +2" to +51" (or recovering)

HLTS-3-13 Rev 0 Page 15 of 85 Scenario Summary:

x.

Unit 3 is at 100% power with RHR Pump 3A tagged out.

The Crew will perform a CRD timer test lAW 01-85.

Drywell pressure will rise and the Crew will vent the Drywell per 3-01-64 or 3-AOI-64-1.

A control rod will drift into the core and the crew will respond lAW appropriate procedures.

The Crew will maneuver power to recover drifted rod.

A loss of 3A 250V RMOV Board occurs in conjunction with a loss of HPCI 120V power.

When the 3A 250V RMOV Board is restored, SRV 1-22 will fail open and the Crew will respond per 3-AOI-1-1 to close the valve when power is removed (if Crew elects to restore power, the SRV will re-open and stay open).

After the ARPs, TS, & TRM are addressed, the crew will respond to a RWCU leak and failure to auto isolate lAW 3-AOI-64-2A. Manual isolation of 69-1 valve will be successful.

The turbine will trip and the bypass valves will fail to operate. The Reactor will fail to auto scram on the turbine trip or the resulting high Reactor pressure but manual scram will function and insert all control rods.

Following the reactor scram Drywell pressure and temperature will rise requiring the Crew to enter and execute 3-EOI-2.

The Crew will spray the Pressure Suppression Chamber. When the Drywell is required to be sprayed, logic failure (Loop I) and inoperable valves (Loop II) will prevent the Drywell from being sprayed.

The Crew will have to Emergency Depressurize on Suppression Chamber pressure (PSP curve) or Drywell temperature (280°F).

Drywell Sprays will be made available after the Emergency Depressurization allowing the crew to spray the Drywell preventing possible loss of level instrumentation.

HLTS-3-13 Rev 0 Page 16 of 85 XI. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. SRO: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. Reactor has been emergency depressurized

2. Sprays the Drywell when sprays are made available

3. Rx water level restored +2" to +51" (or recovering)

HLTS-3-13 Rev 0 Page 17 of 85 XII. Simulator Event Guide:

Event #1: CRD Timer Test Position Expected Actions Time/Comments SRO Directs OATC to perform CRD timer test per 3 85, section 8.14 ATC Performs CRD timer test per 3-01-85, section 8.14

[1] REVIEW all Precautions and Limitations in Section 3.2 and Section 3.3.

[2] PLACE WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3AJS6, in TEST AND HOLD for at least two seconds.

[3] CHECK the white indicating light above the WITHDRAW AUXILIARY TIMER TEST, 3-HS 3AJS6, illuminates.

[4] CHECK the red indicating light above the WITHDRAW AUXILIARY TIMER TEST, 3-HS 3AJS6, illuminates after approximately two seconds.

[5] CHECK CONTROL ROD SELECT BLOCK TIMER MALFUNCTION annunciator (3-XA-55-5A, Window 21) in alarm.

[6] PLACE WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3AJS6, in RESET.

[7] CHECK all Reactor Manual Control System WITHDRAW AUXILIARY TIMER TEST, 3-HS 3AJS6, indicating lights are extinguished.

[8] RESET CONTROL ROD SELECT BLOCK TIMER MALFUNCTION annunciator (3-XA-55-5A, Window 21).

NOTE: The following steps allow the RMCS timer to be operationally checked without the possibility of moving a control rod. If rod motion is observed during the test of RMC, no further testing is to be performed without direction of the Unit Supervisor

HLTS-3-13 Rev 0 Page 18 of 85 XII. Simulator Event Guide:

Event #1: CRD Timer Test (continued)

Position Expected Actions Time/Comments ATC [9] LOWER the CRD DRIVE WTR HDR DP, 3-PDI-85-17A, to < 75 psid using CRD DRIVE WATER PRESS CONTROL VLV, 3-HS-85-23A.

[10] SELECT a peripheral control rod by depressing the appropriate CRD ROD SELECT pushbutton, 3-XS-85-40.

[11] IF Rod Motion is observed while performing Step 8.14[12], THEN

[11.1] IMMEDIATELY RELEASE CRD CONTROL SWITCH, 3-HS-85-48, and CONTACT System Engineer.

[11.2] ADJUST the CRD DRIVE WTR HDR DP, 3-PDI-85-17A, to between 250 psid and 270 psid, using CRD DRIVE WATER PRESS CONTROL VL V, 3-HS-85-23A.

[11 .3] STOP all tests or checks until authorized

by the Unit Supervisor.

[12] ATTEMPT to withdraw the peripheral control rod using CRD CONTROL SWITCH, 3-HS-85-48, while observing the RMCS timer in the Auxiliary Instrument Room and/or the indicating lights on Panel 3-9-5.

[13] REPEAT Step 8.14[12], as necessary, to determine that the RMCS timer is operating as required.

[13.1] IF the RMCS timer is not operating as required, THEN GENERATE a WOo

[14] IF the RMCS timer is operating as required, THEN ADJUST the CRD DRIVE WTR HDR DP, 3-PDI-85-17A, to between 250 psid and 270 psid, using CRD DRIVE WATER PRESS CONTROL VL V, 3-HS-85-23A.

HL TS-3-13 Rev 0 Page 19 of 85 XII. Simulator Event Guide:

Event #2: Vent the Drywell Position Expected Actions Time/Comments Crew Announces alarm Primary Containment N2 pressure high and responds per the ARP BOP A. VERIFY containment pressure using multiple indications.

B. CHECK containment temperature.

C. REFER TO 3-01-64 Venting the Drywell with Standby Gas Treatment Fan.

SRO IF Directs venting the DrywelllAW 3-01-64 BOP [1] REVIEW all Precautions and Limitations in Section 3.0.

[2] VERIFY all Prestartup/Standby Readiness requirements in Section 4.0 are satisfied.

[3] CHECK Group 6 Isolation Signal (Ventilation Systems) NOT present.

VERIFY Stack Dilution Fans in operation. REFER

TO 3-01-66.

[5] VERIFY 3-SI-4.7.A.2.a. is available for recording of venting activities.

[6] IF the Drywell DP Compressor is in operation, THEN STOP the compressor using 3-HS-64-142A (Panel 3-9-3).

[7] PERFORM the following:

[7.1] VERIFY CLOSED OW DP COMP SUCTION ISOL VLV, 3-FCV-64-139, using 3-ZI-64-139 on Panel 3-9-3.

[7.2] VERIFY CLOSED DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-29, using 3-HS-64-29 on Panel 3-9-3.

[7.3] CLOSE SUPPR CHBR INBD ISOLATION VL V, 3-FCV-64-34, using 3-HS-64-34 on Panel 3-9-3.

HL TS-3-13 Rev 0 Page 20 of 85 XII. Simulator Event Guide:

Event #2: Vent the Drywell (continued)

Position Expected Actions Time/Comments BOP [7.4] VERIFY OPEN DRYWELL INBD ISOLATION VLV, 3-FCV-64-31, using 3-HS 31 on Panel 3-9-3.

[7.5] VERIFY CLOSED PATH B VENT FLOW CONT, 3-FIC-84-19 on Panel 3-9-55.

[8] NOTIFY Unit 1 and 2 Control Room that Unit 3 Drywell venting with SGT A (B) (C) is about to start.

NOTE: Path A and B Vent valves, 3-FCV-84-19 and 3-FCV-84-20, isolate on Standby Gas duct high pressure of 1 psig.

[9] VERIFY PATH A VENT FLOW CONT, 3-FIC-84-20, in AUTO and set at 100 SCFM (Panel 3 55).

[10] REQUEST Unit 1 OR Unit 2 operator to START (or VERIFY in service) one of the following SGT trains (REFER TO 0-01-65):

SGT FAN A, 0-HS-65-18A on Panel 1-9-25

SGT FAN B, 0-HS-65-40A/1 on Panel 1 25

SGTS train C FAN, 0-HS-65-69A/2 on Panel 2-9-25 NOTE: A Standby Gas Treatment Fan is required to be running for 3-FCV-84-20 to operate.

[11] PLACE (or VERIFY), 3-FCV-84-20 CONTROL DW/SUPPR CHBR VENT, 3-HS-64-35, in OPEN (Panel 3-9-3).

NOTE: Depending upon plant conditions, it is possible that flow may indicate less than 100 SCFM even with the thumbwheel of 3-FIC-84-20, on Panel 3-9-55, is adjusted to the fully open position.

[12] VERIFY flow at approximately 100 SCFM on PATH A VENT FLOW CO NT 3-FIC-84-20 (Panel 3-9-55).

HLTS-3-13 Rev 0 Page 21 of 85 Simulator Event Guide:

Event #2: Vent the Drywell (continued)

Position Expected Actions Time/Comments BOP [13] MONITOR Drywell pressure (Panel 3-9-3).

NOTE: Drywell pressure is usually controlled to maintain the Drywell and Suppression Chamber differential pressure between 1.15 and 1.30 psid to provide a margin to the Tech Spec Limit.

[14] WHEN Drywell pressure has been reduced to the desired pressure, or the lower DP limit is reached as indicated by DRYWELL DP CPRSR DISCH VALVE, 3-HS-64-140, opening on Panel 3-9-3, THEN CLOSE 3-FCV-84-20 using 3-FCV 20, CONTROL DW/SUPPR CHBR VENT, 3-HS-64-35 (Panel 3-9-3).

Have Log AUO monitor release rates as required by NOTE.

SRO IF Directs venting the DrywelilAW 3-AOI-64-1 NOTE: This procedure covers possible multiple symptoms of a problem within primary containment. Any or all of the symptoms may exist.

The SRO will direct actions based on symptoms and experience.

1] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s). (Otherwise N/A)

BOP [1] CHECK Drywell pressure using multiple indications.

[2] ALIGN and START additional Drywell coolers and fans as necessary. REFER TO 3-01-64.

Transition to 3-01-64 as necessary NOTE: Normally, four of the five cooling units are placed in service in each train. The required number of cooling units should be placed in service to maintain Drywell temperatures at less than or equal to 135°F.

HLTS-3-13 Rev 0 Page 22 of 85 Simulator Event Guide:

Event #2: Vent the Orywell (continued)

Position Expected Actions Time/Comments BOP [3] IF personnel are present in the Orywell, THEN NOTIFY Radiation Protection of the impending startup. RECORD name and the time of notification in the NOMS narrative log

[4] OPEN the associated Orywell Cooler valve and damper, THEN START the associated Orywell Cooler Blower (Panel 3-9-25).

Component / Blower Hand-switch / Associated Valve and Damper Hand-switch OW CLG UNIT 3A1 BLOWER /3-HS-70-37A /3-HS-70-16A OW CLG UNIT 3A2 BLOWER /3-HS-70-38A /3-HS-70-18A OW CLG UNIT 3A3 BLOWER /3-HS-70-39A /3-HS-70-20A OW CLG UNIT 3A4 BLOWER /3-HS-70-40A /3-HS-70-22A OW CLG UNIT 3A5 BLOWER /3-HS-70-41A /3-HS-70-24A OW CLG UNIT 3B1 BLOWER /3-HS-70-42A /3-HS-70-26A OW CLG UNIT 3B2 BLOWER /3-HS-70-43A /3-HS-70-28A OW CLG UNIT 3B3 BLOWER /3-HS-70-44A /3-HS-70-30A OW CLG UNIT 3B4 BLOWER /3-HS-70-45A /3-HS-70-32A OW CLG UNIT 3B5 BLOWER /3-HS-70-46A /3-HS-70-34A

[5] PLACE OW CLR RBCCW OUTLET TEMP SEL, 3-XS-70-36, to a position corresponding to an operating cooling unit to monitor RBCCW outlet temperature (Panel 3-9-25).

[6] IF personnel are present in the orywe II , THEN NOTIFY Radiation Protection that the required startup has been completed.

Transition to 3-AOI-64-1 as necessary

HLTS-3-13 Rev 0 Page 23 of 85 Simulator Event Guide:

Event #2: Vent the Drywell (continued)

Position Expected Actions Time/Comments BOP WARNING: Stack release rates exceeding 1.4 X 107 Dci/sec, or a SI-4.8.B.1.a.1 release fraction above one will result in ODCM release limits being exceeded.

[3] VENT Drywell as follows:

[3.1] CLOSE SUPPR CHBR INBD ISOLATION VLV 3-FCV-64-34 (Panel 3-9-3).

[3.2] VERIFY OPEN, DRYWELL INBD ISOLATION VLV, 3-FCV-64-31 (Panel 3-9-3).

[3.3] VERIFY 3-FIC-84-20 is in AUTO and SET at 100 scfm (Panel 3-9-55).

[3.4] VERIFY Running, required Standby Gas Treatment Fan(s) SGTS Train(s) A, B, C (Panel 3-9-25).

[3.5] IF required, THEN REQUEST Unit 1 Operator to START Standby Gas Treatment

Fan(s) SGTS Train(s) A, B. (Otherwise N/A)

NOTE: If 3-FCV-84-20 closes after placing 3-HS-64-35 to open, the valve's closure signal must be reset and 3-HS-64-35 must be returned to the OPEN position in order for 3-FCV-84-20 to RE-OPEN.

[3.6] IF required, THEN RECORD venting data in 3-SI-4.7.A.2.a (Otherwise N/A)

[3.7] PLACE 3-FCV-84-20 CONTROL DW/SUPPR CHBR VENT, 3-HS-64-35, in OPEN (Panel 3-9-3).

[3.8] MONITOR stack release rates to prevent exceeding ODCM limits.

[3.9] WHEN Drywell pressure has been reduced as required, THEN STOP SGT Train(s).

HLTS-3-13 Rev 0 Page 24 of 85 Simulator Event Guide:

Event #2: Vent the Drywell (continued)

Position Expected Actions Time/Comments BOP [3.10] VERIFY 3-HS-64-35, in AUTO and 3-FCV-84-20 CLOSED (Panel 3-9-3).

[3.11] OPEN SUPPR CHBR INBD ISOLATION VLV 3-FCV-64-34 (Panel 3-9-3).

[3.12] VERIFY Drywell DP compressor operates correctly to maintain required Drywell to Suppression Chamber DP.

[3.13] RECORD SGTS Train(s) run time in appropriate Control Room Reactor Narrative Log for transfer to 1-SR-2.

HLTS-3-13 Rev 0 Page 25 of 85 XII. Simulator Event Guide:

Event #3: CONTROL ROD DRIFT Position Expected Actions Time/Comments ATC Announces "Control Rod Drift" alarm A. DETERMINE which rod is drifting from Full Core Display.

Identifies rod 30-31 as drifting in and is> 2 notches from original position B. IF rod drifting in, THEN REFER TO 3-AOI-85-5.

SRO Directs actions per 3-AOI-85-5 Directs rod be continuously inserted to 00 REFER TO Tech Spec Section 3.1.3,3.10.8.

ATC IMMEDIATE [1] IF multiple rods are drifting into core, THEN MANUALLY SCRAM Reactor.

REFER TO 3-AOI-100-1.

SUBSEQUENT [1] IF the Control Rod travels greater than two notches from its intended position, THEN INSERT Control Rod to position 00 using CONTINUOUS IN. (otherwise N/A)

SRO

[2] NOTIFY Reactor Engineer. (May be SRO)

[3] CHECK Thermal Limits on ICS (RUN OFFICIAL 3D).

Informs Reactor Engineer of drifting rod and directs an Rep to restore rod back to it's original position (if drifting problem can be corrected)

ATC [4] ADJUST control rod pattern as directed by Reactor Engineer and CHECK Thermal Limits on ICS (RUN OFFICIAL 3D).

[5] IF CRD Cooling Water Header DP is excessive and causing the control rod drift, THEN ALTERNATELY ADJUST tape setpoint of CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, and position of CRD DRIVE WATER PRESS CONTROL VLV, 3-HS-85-23A, to establish the following conditions (otherwise N/A):

HLTS-3-13 Rev 0 Page 26 of 85 XII. Simulator Event Guide:

Event #3: CONTROL ROD DRIFT (continued)

Position Expected Actions Time/Comments ATC

CRD CLG WTR HDR DP, 3-PDI-85-18A, of about 20 psid, and

CRD DRIVE WTR HDR DP, 3-PDI-85-17A, between 250 and 270 psid, and

CRD SYSTEM FLOW CONTROL, 3-FIC 11, between 40 and 65 gpm.

NOTE: All observations and checks made in the following steps should be made as a comparison and relative to the other Hydraulic Control Units.

[6] VERIFY scram pilot air header aligned to scram inlet and outlet valves.

[7] CHECK CRD SCRAM OUTLET VALVE, 3-FCV-085-398, for leakage as indicated by the following:

Scram riser for affected HCU has higher than normal temperature

CRD SCRAM OUTLET VALVE, 3-FCV-085-398, producing flow noise

[8] CHECK CRD SCRAM INLET VALVE, 3-FCV-085-39A, for leakage as follows:

[8.1] CHECK insert riser for affected HCU for higher than normal temperature.

NOTE: The CRD accumulator is considered inoperable per Technical Specifications 3.1.5 when the charging water is isolated.

SRO Directs charging water to 30-31 be closed ATC [8.2] CLOSE CHARGING WATER SOV, 3-SHV-085-588 and OBSERVE CRD ACCUMULATOR NITROGEN SIDE PRESS, 3-PI-085-034, for lowering trend.

SRO Declares accumulator inoperable per Tech Spec 3.1.5 and addresses actions (when charging water is isolated)

Directs scram of affected rod from panel 9-16 in Aux. Inst. Room

HLTS-3-13 Rev 0 Page 27 of 85 XII. Simulator Event Guide:

Event #3: CONTROL ROD DRIFT (continued)

Position Expected Actions Time/Comments ATC NOTES: 1) If either the Scram Inlet or Outlet valve is found to be leaking, the preferred action is to scram the affected rod at Panel 3-9-16 and initiate corrective maintenance if necessary.

2) Individual control rod scram to attempt to reset scram valves may be performed at discretion of Unit Supervisor. Reactor Engineer will determine impact on core thermal limits and preconditioning envelope.

[9] IF either Scram Inlet or Outlet Valve is found to be leaking, THEN PERFORM the following to scram the control rod (otherwise N/A):

[9.1] ESTABLISH communications between Control Room and the following locations:

Hydraulic control unit affected, elevation 565, Reactor Building

Panel 3-9-16 in Auxiliary Instrument Room, elevation 593, Control Bay

[9.2] VERIFY CLOSED CHARGING WATER SOV, 3-SHV-085-588. (AUO)

NOTE: Panel 3-9-16, containing the Rod Scram Switches is locked and a key from the Unit 3 Control Room key cabinet will be required to perform the next step.

[9.3] INITIATE individual rod scram by actuating selected rod scram switch on Panel 3-9-16 to its scram (DOWN) position. (AUO)

[9.4] VERIFY control rod has reached FULL IN on Panel 3-9-5.

[9.5] IF attempting to reseat scram valves, THEN RETURN rod scram switch for associated control rod to its normal (UP) position at Panel 3-9-16. (AUO)

HLTS-3-13 Rev 0 Page 28 of 85 XII. Simulator Event Guide:

Event #3: CONTROL ROD DRIFT (continued)

Position Expected Actions Time/Comments ATC [9.6] CHECK solenoid operation of CRD SCRAM INLET and OUTLET VALVEs 3-FCV-85-39A and 3-FCV-85-39B, (they should function normally without chatter or abnormal buzzing.) (AUO)

[9.7] CHECK stem travel indicators on CRD SCRAM INLET and OUTLET VALVEs 3-FCV-85-39A and 3-FCV-85-39B. IF either scram valve indicates OPEN, THEN NOTIFY control room. (AUO)

[9.8] CHECK blue Scram indicator light on Full Core Display extinguished.

[9.9] RESET Rod Drift Alarm and CHECK DRIFT indicator light on Full Core Display extinguished. (N/A if rod is still drifting in)

[9.10] CHECK annunciator CONTROL ROD DRIFT (3-XA-55-5A, Window 28) reset. (N/A if rod is still drifting in)

[9.11] SLOWLY OPEN CHARGING WATER SOV, 3-SHV-085-588. (AUO)

[9.12] CHECK amber ACCUM indicator light on Full Core Display extinguished.

[9.13] CHECK red indicating light for associated HCU extinguished on local Panel 3-28-4(3 22).

[9.14] NOTIFY Site Engineering.

[9.15] INITIATE a work order.

SRO Declares Rod 30-31 operable when charging water restored.

HL TS-3-13 Rev 0 Page 29 of 85 XII. Simulator Event Guide:

Event #4: Maneuver Power To Recover Rod Position Expected Actions Time/Comments SRO When RCP received from Rx Engineer, directs Operator to lower power with flow to - 90% (use upper power runback if aplicable), notch withdraw rod 30-31 to position 12, and return power to 100%

with Recirc flow at 10 MWe/min per 3-GOI-100-12 and 3-01-68.

Notifies ODS of power drop Crew Notifies Chemistry and RADCON of power drop ATC Transition to 3-GOI-100-12

[6.1] REDUCE Recirculation flow. REFER TO 3 68.

Transition to 3-01-68 Section 8.13

[1] IF time permits, THEN REVIEW Precautions and Limitations. REFER TO Section 3.0.

[2] IF desired to reduce Reactor Power to approximately 90%, THEN PERFORM the following: (Otherwise N/A)

[2.1] DEPRESS RECIRC PUMPS UPPER POWER RUNBACK push-button, 3-HS-68-42 BOP Provides peer check for Recirc adjustment ATC [2.2] VERIFY the following:

Push-button backlight blinks until setpoint is reached.

Reactor power lowers to approximately 90%.

Transition to 3-GOI-100-12

[7] IF required for power maneuvering, THEN PERFORM the following as directed by Reactor Engineer:

OBTAIN the Control Rod Movement Data Sheet.

ALIGN control rods .

Transition to 3-01-85 Section 6.6.2

[1] IF the control rod fails to withdraw, THEN

REFER TO Section 8.15 for additional methods to reposition control rod.

HLTS-3-13 Rev 0 Page 30 of 85 XII. Simulator Event Guide:

Event #4: Maneuver Power To Recover Rod (continued)

Position Expected Actions Time/Comments ATC [2] IF the control rod double notches, or withdraws past its correct/desired position, THEN REFER TO Section 6.7 for inserting control rod to its correct/desired position.

[3] IF at any time while driving a selected rod during the performance of this section, the Control Rod moves more than two notches from its intended position, THEN REFER TO 3-AOI-85-7, Mispositioned Control Rod.

[4] OBSERVE the following during control rod repositioning:

Control rod reed switch position indicators (four rod display) agree with the indication on the Full Core Display.

Nuclear Instrumentation responds as control rods move through the core (This ensures control rod is following drive during Control Rod movement.)

BOP Provides peer check for Rod Movement.

SRO Directs returning power to 100%.

ATC Transition to 3-GOI-1 00-12 Section 5.0

[6.3] WHEN desired to raise power, THEN PERFORM the following as directed by Unit Supervisor. (N/A Steps 5.0[7] through 5.0[19].

RAISE Recirculation flow. REFER TO 3-01-68.

Transition to 3-01-68 Section 6.2

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-17A(17B)(17C),

push-buttons, to achieve balanced jet pump flows.

AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS 16A(16B) I LOWER SLOW(MEDIUM)(FAST) 3-HS 18A(18B)(18C),push-buttons, to achieve balanced jet pump flows.

HLTS-3-13 Rev 0 Page 31 of 85 XII. Simulator Event Guide:

Event #4: Maneuver Power To Recover Rod (continued)

Position Expected Actions Time/Comments ATC AND/OR WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 BOP Provides peer check for Recirc adjustment.

Continue to monitor and adjust BOP (transfer volts, condensate flow, etc)

HLTS-3-13 Rev 0 Page 32 of 85

XII. Simulator Event Guide:

Event #5: LOSS AND RECOVERY OF 3A 250V RMOV BD (Loss of HPCI and ADS SRV)

Position Expected Actions Time/Comments Crew Recognizes the loss of 3A 250V RMOV Bd. using annunciators and loss of lights on handswitches BOP Refers to ARP's (various)

SRO Dispatches AUO/Outside US to 3A 250V RMOV Bd References T.S. 3.8.7.E and determines 7day LCO Enters T.S. 3.0.3 due to previous RHR LCO When discovered reason for board trip, Directs re-energizing 3A 250V RMOV Bd After board is re-energized, exits TS 3.8.7.E and 3.0.3 BOP After board is re-energized: Resets alarms and reports that HPCI 120V power supply failure and MSRV 1-22 is stuck open Transition to 3-ARP-9-3C (Window 25)

A. CHECK MSRV DISCHARGE TAILPIPE TEMPERATURE, 3-TR-1-1, on Panel 3-9-47 and SRV Tailpipe Flow Monitor on Panel 3-9-3 for rising temperature and flow indications.

B. REFER TO 3-AOI-1-1.

SRO Directs performance of 3-AOI-1-1 BOP Transition to 3-AOI-1-1 Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 3-FMT 4, on Panel 3-9-3, OR

MSRV DISCHARGE TAILPIPE TEMP, 3-TR-1-1 on Panel 3-9-47.

HLTS-3-13 Rev 0 Page 33 of 85 XII. Simulator Event Guide:

Event #5: LOSS AND RECOVERY OF 3A 250V RMOV BD (Loss of HPCI and ADS SRV)

Position Expected Actions Time/Comments BOP [2] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch several times as required:

CLOSE to OPEN to CLOSE positions

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A)

Subsequent Action 4.2.1 Attempt to close valve from Panel 9-3:

[1] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the OFF position.

[2] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON position.

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A)

[4] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT, 3-XS-1-202 in INHIBIT:

[5] IF relief valve closes, THEN OPEN breaker or PULL fuses as necessary using Attachment 1 (Unit 3 SRV Solenoid Power Breaker/Fuse Table).

[6] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT 3-XS-1-202, in AUTO.

NOTES: 1) Only the appropriate sections for the stuck open relief valve is required to be performed.

[7] IF the SRV valve did not close, THEN PERFORM the appropriate section from table below.

SRV 1-22 Step 4.2.2[2] Panel 25-32 Multiple Panel 25-32 (Excerpt from Table)

SRO Dispatches outside US to investigate HPCI power failure

HLTS-3-13 Rev 0 Page 34 of 85 XII. Simulator Event Guide:

Event #5: LOSS AND RECOVERY OF 3A 250V RMOV BD (Loss of HPCI and ADS SRV) (continued)

Position Expected Actions Time/Comments SRO When US reports that HPCI fuse was replaced and immediately cleared again, Refers to T.S. and determines T.S. 3.5.1.H and enters 3.0.3 immediately due to ADS valve and HPCI inoperability Calls Rx Engineer for required shutdown sequence Calls Plant Management Notifies Chern Lab and Rad Con Calls SW dispatcher and ODS about impending shutdown Informs crew that unit shutdown is required (lAW 3-GOI-1 00-12A) due to ADS valve and HPCI INOP Reviews SPP-3.5 and determines 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report for a T.S. required shutdown (3.1.C.1)

BOP 4.2.2 Attempt to close valve from outside the control room: (continued)

NOTES: 1) 3-PCV-1-22 is an ADS Valve

2) 3-PCV-1-22 has two power supplies, it will auto transfer on loss of power and is Normal Seeking.

[2] IF 3-PCV-1-22 is NOT closed, THEN PERFORM the following: (Otherwise N/A this section.) (CONTACTS AUO /OUTSIDE US)

[2.1] On Panel 3-25-32 PLACE the transfer switch associated MAIN STM LINE B XFER, 3-XS-1-22 in EMERG position. (AUO)

HL TS-3-13 Rev 0 Page 35 of 85 XII. Simulator Event Guide:

Event #5: LOSS AND RECOVERY OF 3A 250V RMOV BD (Loss of HPCI and ADS SRV) (continued)

Position Expected Actions Time/Comments BOP [2.2] IF the SRV does NOT close, THEN PERFORM the following while OBSERVING the indications for the 3-PCV-1-22 on the Acoustic Monitor: (Otherwise N/A) (AUO)

CYCLE the MAIN STM LINE B RELIEF VALVE, 3-HS-1-22C to the following positions several times.

CLOSE/AUTO to OPEN to CLOSE/AUTO (AUO)

[2.3] IF the SRV does NOT close, THEN PERFORM the following: (Otherwise N/A)

A. VERIFY the MAIN STM LINE B RELIEF VALVE, 3-HS-1-22C, in the CLOSE/AUTO position. (AUO)

B. PLACE the transfer switch associated MAIN STM LINE B XFER, 3-XS-1-22 in NORM position. (AUO)

[2.4] IF the SRV does NOT close, THEN REMOVE the power from 3-PCV-1-22 by performing one of the following: (Opening breakers are the preferred method) (Otherwise N/A)

A. OPEN the following breakers: (Preferred method) (AUO)

3A 250V RMOV, Compartment 11C2

3B 250V RMOV, Compartment 1C1 OR

HLTS-3-13 Rev 0 Page 36 of 85 XII. Simulator Event Guide:

Event #5: LOSS AND RECOVERY OF 3A 250V RMOV BD (Loss of HPCI and ADS SRV) (continued)

Position Expected Actions Time/Comments BOP B. In Panel 3-25-32 (Bay 3)

PULL the following fuses as necessary:

(AUO)

Fuse 3-FU1-001-0022A (Block EE, F2)

Fuse 3-FU1-001-0022B (Block EE, F7)

Fuse 3-FU1-001-0022C (Block EE, F12)

Fuse 3-FU1-001-0022D (Block EE, F15)

[2.5] IF the valve does NOT close, THEN CLOSE the breakers or REINSTALL fuses removed in Step 4.2.2[2.4]. (AUO)

[2.6] CONTINUE at Step 4.2.3.

4.2.3 Other Actions and Documentation

[1] IF ANY EOI entry condition is met, THEN ENTER the appropriate EOI(s).

[2] REFER TO Technical Specifications Sections 3.5.1 and 3.4.3 for Automatic Depressurization System and relief valve operability requirements.

4.2.3 Other Actions and Documentation (continued)

[3] INITIATE suppression pool cooling as necessary to maintain suppression pool temperature less than 95°F.

[4] IF the relief valve can NOT be closed AND suppression pool temperature Can NOT be maintained less than or equal to 95°F, THEN PLACE the reactor Modeo4 in accordance with 3-GOI-100-12A.

[5] DOCUMENT actions taken and INITIATE Work Order for the valve.

HL TS-3-13 Rev 0 Page 37 of 85 XII. Simulator Event Guide:

Event #5: LOSS AND RECOVERY OF 3A 250V RMOV BD (Loss of HPCI and ADS SRV) (continued)

Position Expected Actions Time/Comments BOP Transition to 3-ARP-9-3F (Window 7 HPCI 120V)- may have occurred while waiting for outside actions on SRV A. DISPATCH personnel to check the following:

Inverter fuses 3-FU2-073-0033C, Panel 3 82

DIV II ECCS ATU inverter.

RMOV BD 3A, compt 11 A 1.

REFER TO Tech Spec 3.3.5.1 and Table 3.3.5.1-1.

Crew Recognizes PI-64-67B downscale Recognizes loss of C & D Rx Press. Transmitters causing Header Pressure Control to take over.

01-47, step 8.3 to un-bypass and step 8.2 to

SRO transfer to Reactor pressure control Reviews T.S. 3.3.3.1-1 on PI-64-67B and determines 30 day LCO and Tech Spec 3.3.5.1 and Table 3.3.5.1-1.

When US reports that HPCI fuse was replaced and immediately cleared again, Refers to T.S. and determines T.S. 3.5.1.H and enters 3.0.3 immediately due to ADS valve and HPCI inoperability Calls Rx Engineer for required shutdown sequence Calls Plant Management Notifies Chem Lab and Rad Con Calls SW dispatcher and ODS about impending shutdown Informs crew that unit shutdown is required (lAW 3-GOI-100-12A) due to ADS valve and HPCIINOP Reviews SPP-3.5 and determines 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report for a T.S. required shutdown (3.1.C.1)

HLTS-3-13 Rev 0 Page 38 of 85 XII. Simulator Event Guide:

Event #5: LOSS AND RECOVERY OF 3A 250V RMOV BD (Loss of HPCI and ADS SRV) (continued)

Position Expected Actions Time/Comments SRO Directs "un-bypassing" "C" and "0" transmitters per 3-01-47 section 8.3 Directs transferring back to Reactor Pressure Control (from Header Pressure Control) per 3 47 section 8.2 ATC Transition to 3-01-47, section 8.3

[1] With Unit Supervisor approval, PERFORM the following to bypass a EHC Control System reactor pressure instrument:

[1.1] BYPASS one of the desired Reactor Pressure instruments by performing the following:

To bypass Reactor Pressure C, DEPRESS REACTOR PRESS C BYPASS pushbutton, 3-HS-47-204C.

To bypass Reactor Pressure 0, DEPRESS REACTOR PRESS 0 BYPASS pushbutton, 3-HS-47-204D.

[1.2] CHECK backlight is illuminated for the pushbutton used in Step 8.3[1.1].

[1 .3] CHECK Reactor pressure and Reactor power are stable.

[1.4] NOTIFY Unit Supervisor that reactor pressure instrument is bypassed.

Transition to 3-01-47, section 8.2

[1] OBTAIN Unit Supervisor approval to perform this section.

[2] TRANSFER pressure control to Reactor Pressure as follows:

[2.1] DEPRESS REACTOR PRESSURE CONTROL pushbutton, 3-HS-47-204.

[2.2] CHECK the following:

HLTS-3-13 Rev 0 Page 39 of 85 XII. Simulator Event Guide:

Event #5: LOSS AND RECOVERY OF 3A 250V RMOV SO (Loss of HPCI and ADS SRV) (continued)

Position Expected Actions Time/Comments ATC [2.2] CHECK the following: (continued)

REACTOR PRESSURE CONTROL pushbutton, 3-HS-4 7-204, backlight is illuminated.

HEADER PRESSURE CONTROL pushbutton, 3-HS-1-16, backlight is extinguished.

[2.3] CHECK Reactor pressure and Reactor power stable.

[2.4] NOTIFY Unit Supervisor that EHC Pressure Control has been transferred to Reactor Pressure.

[2.5] RECORD the transfer in the narrative log.

HLTS-3-13 Rev 0 Page 40 of 85 XII. Simulator Event Guide:

Event #6: RWCU leak Position Expected Actions Time/Comments Crew Reports alarm(s) 9-5B Windows 32 and lor 33-RWCU ISOL LOGIC CHANNEL A (B) TEMP HIGH or 9-3D Window 17 - RWCU LEAK DETECTION TEMP HIGH and reports high RWCU temperatures to SRO BOP Transition to 3-ARP-9-5B A. VERIFY alarm by b~ checking:

1. ATUs on Panel 3-9-83 and 3-9-85.

2. RWCU LEAK DETECTION TEMP HIGH annunciator in alarm i3-XA-55-3D, (3-XA-55-3D, Window 17).

3. Area temperature indication on LEAK DETECTION SYSTEM TEMPERATURE, 3-TI 29, on Panel 3-9-21.

4. ARMs 3-RR-90-1, 3-CONS-90-50A on Panel 3-9-2 and 0-CONS-90-361 B).

5. ICS 'HPTURB' & 'RWCU' mimics for the 834 and 835 temperature loops.

B. IF leak is suspected, THEN MANUALLY ISOLATE RWCU or if RWCU automatically isolates, REFER TO 3-AOI-64-2A. Notices 69-1 failure to auto isolate C. IF TIS-69-835A(C) indicates greater than 131°F, THEN ENTER 3-EOI-3.

SRO Directs entry into 3-AOI-64-2A Directs RWCU secured and isolated BOP Transition to 3-AOI-64-2A Immediate Actions

[1] VERIFY automatic actions occur.

[2] PERFORM any automatic actions which failed to occur.

Subsequent Actions

[1] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s).

[2] CHECK the following to confirm high area temperature condition exists:

LEAK DETECTION SYSTEM TEMPERATURE, 3-TI-69-29 (Panel 3-9-21)

ATUs in Auxiliary Instrument Room

HLTS-3-13 Rev 0 Page 41 of 85 XII. Simulator Event Guide:

Event #6: RWCU leak (continued)

Position Expected Actions Time/Comments BOP [3] IF isolation is caused by high area temperature, THEN DETERMINE if a line break exists by:

RWCU ARMs 3-RI-90-9A, 13A, and 14A

Visual Observation

Rx Zone Exhaust Rad Monitors 3-RE 142A, 142B, 143A, and 143B

[4] REQUEST Reactor Engineering to make the necessary Heat Balance adjustments.

[5] CHECK the following monitors for a rise in activity:

AREA RADIATION, 3-RR-90-1, Points 9, 13, and 14 (Panel 3-9-2)

AIR PARTICULATE MONITOR CONSOLE, 3-MON-90-50, 3-RM-90-55 and 57 (Panel 3-9-2)

RB, TB, and Refuel Zone Exhaust Rad on

CONTROL ROOM CONSOLE, O-CONS 361A (Panel 1-9-44)

[6] IF it has been determined that leakage is the cause of the isolation, THEN NOTIFY RADCON of RWCU status.

[7] NOTIFY Chemistry that RWCU has been removed from service for the following evaluations:

The need to begin sampling Reactor Water

The need to remove the Durability Monitor from service

[8] IF the isolation cannot be reset, THEN PERFORM the following:

[8.1] ISOLATE the CRD System by closing the following seal water valves in the Unit 3 Reactor Bldg EI. 593:

3-69-592A

3-69-614B

HLTS-3-13 Rev 0 Page 42 of 85 XII. Simulator Event Guide:

Event #6: RWCU leak (continued)

Position Expected Actions Time/Comments BOP [8.2] REFER TO 3-01-68 for Recirc System operating restrictions while RWCU is isolated.

[9] EVALUATE Technical Requirements Manual Section 3.4.1, Coolant Chemistry, for limiting conditions for operation.

SRO Refers to TRM 3.4.1 for sampling requirements Refers to Tech Specs 3.6.1.3 and determines action A is applicable to isolate flow path within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and once per 31 days

HLTS-3-13 Rev 0 Page 43 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM Position Expected Actions Time/Comments Crew Recognizes / reports Turbine trip Reports turbine bypass valves closed ATC Recognizes failure to scram on turbine trip Inserts a manual scram, mode sw, to SID, ARI Gives scram report (all rods in)

BOP Verifies all rods in Crew Announces Rx scram SRO Enters EOI-1 (RPV level and pressure)

Directs Rx pressure maintained 800-1000 using

SRV's App-11A,

RCIC App-11 B,

MSL Drains App-11 0, and/or

RFP's App-11 F Directs RPV level maintained +2" to +51" with:

RFP's App-5A

ATC

RCIC App-5C Inserts IRMs and follows lowering Rx power by ranging

HLTS-3-13 Rev 0 Page 44 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP Maintains RPV pressure between 800 and 1000 psig with one or more of the following:

SRV's App-11A,

RCIC App-11 B, and/or

MSL Drains App-11 D Controls pressure as directed using SRVs, Appendix-11A

1. IF ..... Drywell Control Air is NOT available, THEN ... EXECUTE EOI Appendix 8G, CROSSTIE CAD TO DRYWELL CONTROL AIR, CONCURRENTLY with this procedure.

2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE MSRVs and CONTROL RPV pressure using other options.

3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

a.1 3-PCV-1-179 MN STM LINE A RELIEF VALVE

b. 2 3-PCV-1-180 MN STM LINE D RELIEF VALVE

c. 3 3-PCV-1-4 MN STM LINE A RELIEF VALVE

d. 43-PCV-1-31 MN STM LINE C RELIEF VALVE

e. 5 3-PCV-1-23 MN STM LINE B RELIEF VALVE

f. 6 3-PCV-1-42 MN STM LINE D RELIEF VALVE

g. 7 3-PCV-1-30 MN STM LINE C RELIEF VALVE

h. 8 3-PCV-1-19 MN STM LINE B RELIEF VALVE

i. 9 3-PCV-1-5 MN STM LINE A RELIEF VALVE

j. 10 3-PCV-1-41 MN STM LINE D RELIEF VALVE

k. 11 3-PCV-1-22 MN STM LINE B RELIEF VALVE I. 12 3-PCV-1-18 MN STM LINE B RELIEF VALVE

m. 13 3-PCV-1-34 MN STM LINE C RELIEF VALVE

HLTS-3-13 Rev 0 Page 45 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP I FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP Controls pressure as directed using RCIC, Appendix-11 B

1. IF ..... Emergency RPV Depressurization is required, OR Steam Cooling is required, THEN ... EXECUTE EOI Appendix 16A and 16B as necessary to bypass RCIC Low RPV Pressure and Test Mode Isolation Interlocks

2. IF ..... Suppression Pool level CANNOT be maintained below 5.25 in.,

THEN ... EXECUTE EOI Appendix 16E concurrently with this procedure to bypass HPCI High Suppression Pool Level Suction Transfer Interlock

3. IF ..... RCIC Turbine is operating and NOT required for RPV level control, THEN ... ALIGN RCIC in test mode as follows:

a. OPEN 3-FCV-71-38, RCIC PUMP CST TESTVLV

b. VERIFY OPEN 3-FCV-73-36, HPCI/RCIC CSTTESTVLV

c. CLOSE 3-FCV-71-39, RCIC PUMP INJECTION VALVE

d. CONTINUE in this procedure at Step 5

HLTS-3-13 Rev 0 Page 46 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP I FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP 4. IF ..... RCIC is in standby readiness, THEN ... START RCIC as follows:

a. VERIFY CLOSED 3-FCV-71-39, RCIC PUMP INJECTION VALVE

b. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPITHROT VL V RESET

c. VERIFY OPEN the following valves:

3-FCV-71-38, RCIC PUMP CST TESTVLV

3-FCV-71-25, RCIC LUBE OIL COOLING WTRVLV

3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

3-FCV-73-36, HPCI/RCIC CST TESTVLV

d. PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START

e. OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbine

f. VERIFY RCIC Turbine speed accelerates to above 2100 rpm

5. VERIFY proper RCIC minimum flow valve operation as follows:

a. IF ..... RCIC flow is above 120 gpm, THEN ... VERIFY CLOSEDD 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

b. IF ..... BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN ... VERIFY OPEN 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

HLTS-3-13 Rev 0 Page 47 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP I FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP 6. THROTTLE 3-FCV-71-38, RCIC PUMP CST TEST VL V, to control RCIC pump discharge pressure at or below 1100 psig

7. ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller to control RPV pressure

8. IF ..... RCIC injection to the RPV becomes necessary, THEN ... ALIGN RCIC to RPV as follows:

a. OPEN 3-FCV-71-39, RCIC PUMP INJECTION VALVE

b. CLOSE 3-FCV-71-38, RCIC PUMP CST TESTVLV

c. GO to EOI Appendix 5C

HLTS-3-13 Rev 0 Page 48 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP Controls pressure as directed using MSL Drains, Appendix-11D

1. IF ..... BOTH of the following exist:

Emergency RPV Depressurization is required, AND

Group 1 Isolation Signal exists, THEN ... EXIT this procedure and ENTER EOI Appendix 11 H

2. VERIFY hotwell pressure below -7 in. Hg

3. CONTROL RPV pressure with Main Steam line drains as follows:

a. VERIFY PCIS reset

b. OPEN the following valves (Panel 3-9-3):

0 3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VL V 0 3-FCV-1-56, MN STM LINE DRAIN OUTBD ISOLATION VLV 0 3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER

4. THROTTLE 3-FCV-1-59, DOWNSTREAM MSL DRAIN TO CONDENSER, as necessary to control cooldown rate

HLTS-3-13 Rev 0 Page 49 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments

5. IF ..... At least one main steam line is open AND EITHER of the following exist:

Turbine bypass valves are NOT available, OR

Additional RPV pressure control is necessary, THEN ... CONTROL RPV pressure with Main Turbine and RFPT drains as follows:

a. OPEN the following Main Turbine Drain valves (Panel 3-9-7):

0 3-FCV-6-100, STOP VALVE 1 BEFORE SEAT DR VLV 0 3-FCV-6-101, STOP VALVE 2 BEFORE SEAT DR VL V 0 3-FCV-6-102, STOP VALVE 3 BEFORE SEAT DR VL V 0 3-FCV-6-103, STOP VALVE 4 BEFORE SEAT DR VLV

b. OPEN the following RFPT drain valves (Panel 3-9-6):

0 3-FCV-6-122, RFPT 3A HP STOP VLV ABOVE SEAT DR 0 3-FCV-6-127, RFPT 3B HP STOP VL V ABOVE SEAT DR 0 3-FCV-6-132, RFPT 3C HP STOP VLV ABOVE SEAT DR

HLTS-3-13 Rev 0 Page 50 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP Maintains RPV level +2" to +51" with:

RFP's App-5A

RCICApp-5C Maintains Reactor level with RFP's, Appendix-5A

1. VERIFY Condensate System in service, supplying suction to RFPs

2. VERIFY OPEN MSIVs, supplying steam to RFPTs

3. VERIFY Hotwell Pressure below -7 in. Hg

4. VERIFY CLOSED 3-FCV-1-121(129)(137),

RFPT 3A(3B)(3C) LP STEAM SUPPLY VALVE

5. VERIFY OPEN 3-FCV-1-125(133)(141), RFPT 3A(3B)(3C) HP STEAM SUPPLY VALVE

6. DEPRESS 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT RAISE/LOWER, and VERIFY amber light is illuminated

7. VERIFY a Main Oil Pump is running for RFPT to be started

8. VERIFY for EACH of the following pushbuttons, the green light is illuminated and the red light is extinguished:

3-HS-3-208A, RX WTR LVL CH A HI RFPT/MTTRIP RESET

3-HS-3-208B, RX WTR LVL CH B HI RFPT/MT TRIP RESET

HLTS-3-13 Rev 0 Page 51 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP 9. VERIFY OPEN the following valves:

3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV

3-FCV-3-76, HP HTR 3B1 FW OUTLET ISOL VLV

3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV

10. DEPRESS 3-HS-3-124A(150A)(175A), RFPT 3A(3B)(3C) TRIP RESET, and CHECK the following:

Blue light extinguished

HP Stop Valve open as indicated by red light above the following, as applicable:

0 3-HS-3-108, RFPT 3A HP STOP VLV TEST 0 3-HS-3-134, RFPT 3B HP STOP VLV TEST 0 3-HS-3-159, RFPT 3C HP STOP VLV TEST

LP Stop Valve open as indicated by red light above the following, as applicable:

0 3-HS-3-107, RFPT 3A LP STOP VLV TEST 0 3-HS-3-133, RFPT 3B LP STOP VLV TEST 0 3-HS-3-158, RFPT 3C LP STOP VLV TEST

HL TS-3-13 Rev 0 Page 52 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP 11. VERIFY OPEN 3-FCV-3-20(13)(6), RFP 3A(3B)(3C) MIN FLOW VALVE

12. PLACE 3-HS-46-112A(138A)(163A), RFPT 3A(3B)(3C) START/LOCAL ENABLE, in START

13. CHECK RFPT 3A(3B)(3C) speed increases to approximately 600 rpm

14. VERIFY OPEN 3-FCV-3-19(12)(5), RFP 3A(3B)(3C) DISCHARGE VALVE

15. RAISE RFPT 3A(3B)(3C) speed UNTIL RFP discharge pressure is approximately equal to RPV pressure using ANY of the following methods on Panel 3-9-5:

Using individual 3-HS-46-8A(9A)(1 OA),

RFPT 3A(3B)(3C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 3-SIC-46-8(9)(1 0), RFPT 3A(3B)(3C) SPEED CONTROL PDS in MANUAL, OR

Using 3-UC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 3-SIC-46-8(9)(1 0), RFPT 3A(3B)(3C) SPEED CONTROL PDS in AUTO

HLTS-3-13 Rev 0 Page 53 of 85 XII. Simulator Event Guide:

Event #7: TUR81NE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments 80P 16. SLOWLY RAISE speed of RFPT UNTIL RFW flow to the RPV is indicated using ANY of the following methods on Panel 3-9-5:

Using individual 3-HS-46-8A(9A)(10A),

RFPT 3A(38)(3C) SPEED CO NT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in MANUAL, OR

Using 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in

AUTO

17. ADJUST RFPT speed as necessary to control injection using ANY of the following methods on Panel 3-9-5:

Using individual 3-HS-46-8A(9A)(10A),

RFPT 3A(38)(3C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in MANUAL, OR

Using 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 3-SIC-46-8(9)(1 0), RFPT 3A(38)(3C) SPEED CONTROL PDS in AUTO

HLTS-3-13 Rev 0 Page 54 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP 18. WHEN ... RPV level is approximately equal to desired level AND automatic level control is desired, THEN ... PLACE 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in AUTO with individual 3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED CONTROL PDS in AUTO

HL TS-3-13 Rev 0 Page 55 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP Maintains Reactor level with RCIC per Appendix-5C

1. IF ..... BOTH of the following exist:

RPV Pressure is at or below 50 psig, AND

Bypass of RCIC low RPV pressure isolation interlocks is necessary, THEN ... EXECUTE EOI Appendix 16A concurrently with this procedure

2. IF ..... BOTH of the following exist:

High temperature exists in the RCIC area, AND

SRO directs bypass of RCIC High Temperature Isolation interlocks, THEN ... PERFORM the following:

a. EXECUTE EOI Appendix 16K

concurrently with this procedure

b. RESET auto isolation logic using RCIC AUTO-ISOL LOGIC A(B) RESET 3-XS 51A(B)pushbuttons

3. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPITHROT VALVE RESET

4. VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller in AUTO with setpoint at 600 gpm

HL TS-3-13 Rev 0 Page 56 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP I FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP 5. OPEN the following valves:

3-FCV-71-39, RCIC PUMP INJECTION VALVE

3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

3-FCV-71-25, RCIC LUBE OIL COOLING WTRVLV

6. PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START

7. OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbine

8. CHECK proper RCIC operation by observing the following:

a. RCIC Turbine speed accelerates above 2100 rpm

b. RCIC flow to RPV stabilizes and is

controlled automatically at 600 gpm

c. 3-FCV-71-40, RCIC Testable Check VI v, opens by observing 3-ZI-71-40A, DISC POSITION, red light illuminated

d. 3-FCV-71-34, RCIC PUMP MIN FLOW VAL VE, closes as flow rises above 120 gpm

9. IF ..... BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN ... VERIFY OPEN 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

HLTS-3-13 Rev 0 Page 57 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP I FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP 10. ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller as necessary to control injection

11. IF ..... It is desired to align RCIC suction to the Suppression Pool, THEN ... PERFORM the following:

a. OPEN 3-FCV-71-17, RCIC SUPPR POOL INBD SUCTVALVE

b. OPEN 3-FCV-71-18, RCIC SUPPR POOL OUTBD SUCT VALVE

c. WHEN ... 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE, and 3-FCV 18, RCIC SUPPR POOL OUTBD SUCT VALVE, are fully open, THEN ... VERIFY CLOSED 3-FCV-71-19, RCIC CST SUCTION VALVE NOTE: Step 12.b must be performed promptly following Step 12.a to avoid loss of suction path

12. IF ..... It is desired to align RCIC suction to the Condensate Storage Tank, THEN ... PERFORM the following:

a. CLOSE 3-FCV-71-17, RCIC SUPPR POOL INBD SUCTVALVE

b. WHEN ... 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE starts traveling closed, THEN ... OPEN 3-FCV-71-19, RCIC CST SUCTION VALVE

c. CLOSE 3-FCV-71-18, RCIC SUPPR POOL OUTBD SUCT VALVE

HLTS-3-13 Rev 0 Page 58 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments SRO When RPV level decreases below +2" ensures Groups 2, 3 and 6 isolate Crew Reports Groups 2, 3 and 6 isolated SRO Directs RHR be placed in Suppression Pool cooling per 3-01-74 (until EOI-2 entered) or Appendix-17 A BOP Places RHR in Suppression Pool Cooling per Appendix-17 A

1. IF .............. Adequate core cooling is assured, OR Directed to cool the Suppression Pool irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VL V BYPASS SEL in BYPASS.

2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

HL TS-3-13 Rev 0 Page 59 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP 1 FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP c. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

d. IF ............. Directed by SRO, THEN ....... PLACE 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD in MANUAL OVERRIDE.

e. IF ............. LPCI INITIATION Signal exists, THEN ....... MOMENTARIL Y PLACE 3-XS

121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT in SELECT.

f. IF ............. 3-FCV-74-53(67), RHR SYS 1(11) LPCI INBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV-74-52(66),

RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

g. OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBR/POOL ISOL VL V.

HLTS-3-13 Rev 0 Page 60 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments BOP h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating.

i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11)

SUPPR POOL CLGITEST VLV, to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR SYS 1(11) FLOW:

Between 7000 and 10000 gpm for one-pump operation. OR

At or below 13000 gpm for two-pump operation.

j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

k. MONITOR RHR Pump NPSH using Attachment 1.

I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

m. IF ., ........... Additional Suppression Pool Cooling flow is necessary, THEN ....... PLACE additional RHR and RHRSW pumps in service using Steps 2.b through 2.1

HLTS-3-13 Rev 0 Page 61 of 85 XII. Simulator Event Guide:

Event #7: TURBINE TRIP / FAILURE TO AUTO SCRAM (continued)

Position Expected Actions Time/Comments SRO Dispatches personnel to investigate bypass valve failure Directs entry into AOI-100-1 ATe Performs actions of AOI-100-1 (as time permits)

Crew Reports OW pressure/temperature rising SRO Re-enters EOI-1, Enters EOI-2, and Directs following:

Venting per App-12

H2 0 2 analyzers placed in service

HLTS-3-13 Rev 0 Page 62 of 85 XII. Simulator Event Guide:

Event #8: LOCA Position Expected Actions Time/Comments BOP Vents Containment per Appendix-12

1. VERIFY at least one SGTS train in service.

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VL V,

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

3. IF ... While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN. PERFORM step 13 to secure the vent path

and reenter this procedure if further venting is required.

4. IF ... While executing this procedure, the desired vent path is lost or can not be established, THEN.

PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.

5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4 OR G-9, is to begin, THEN. BEFORE CAD is initiated, PERFORM Step 13 to secure the vent path.

HL TS-3-13 Rev 0 Page 63 of 85 XII. Simulator Event Guide:

Event #8: LOCA Position Expected Actions Time/Comments BOP NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CO NT OR 3-FIC-84-20, PATH A VENT FLOW CO NT NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented

6. IF ... ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR

Suppression Chamber can NOT be vented, OR

SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:

o Step 10 to vent the Drywell through 3-FCV-84-19, OR o Step 11 to vent the Drywell through 3-FCV-84-20.

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20.

HLTS-3-13 Rev 0 Page 64 of 85 XII. Simulator Event Guide:

Event #8: LOCA Position Expected Actions Time/Comments BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-position (Panel 3-9-54).

CHBR _position

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV 19 CONTROL, in OPEN (Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12.

12. ADJUST 3-FIC-84-19, PATH B VENT FLOW

CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

Release rates as determined below:

HL TS-3-13 Rev 0 Page 65 of 85 XII. Simulator Event Guide:

Event #8: LOCA Position Expected Actions Time/Comments BOP i. IF ... PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress THEN .. MAINTAIN release rates below those specified in Attachment 2.

ii. IF ... Severe Accident Management Guidelines are being executed, THEN .. MAINTAIN release rates below those specified by the TSC SAM Team.

iii. IF ... Venting for ANY other reason than items i or ii above, THEN .. MAINTAIN release rates below Stack release rate of 1.4 x 107 J.JCi/s AND O-SI-4.8.B.1.a.1 release fraction of 1.

Contacts LOG AUO to monitor release rates Places H2 0 2 Analyzers in service per EOI-2

1. Place Analyzer isolation bypass keylock switches to bypass

ATC

2. Select OW or Supp Chmbr and momentarily pull out select switch handle to start sample pumps Verifies DIG start on high OW pressure except for 3A DIG fails to start Manually starts 3A DIG Dispatches AUO to monitor DIG's SRO Re-enter EOI-2 (DWT)

Directs all OW Blowers verified in service ATC Verifies all OW blowers in service

HL TS-3-13 Rev 0 Page 66 of 85 XII. Simulator Event Guide:

Event #8: LOCA Position Expected Actions Time/Comments SRO Determines PSC pressure cannot be maintained

<12 psig and directs PSC sprayed BOP Sprays Suppression Chamber per Appendix-17C

1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in this procedure at Step 6.

2. IF .............. Adequate core cooling is assured, OR Directed to spray the Suppression Chamber irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS.

3. IF .............. Directed by SRO to spray the Suppression Chamber using Standby Coolant Supply, THEN ....... CONTINUE in this procedure at Step 7.

4. IF .............. Directed by SRO to spray the Suppression Chamber using Fire Protection, THEN ....... CONTINUE in this procedure at Step 8.

HLTS-3-13 Rev 0 Page 67 of 85 XII. Simulator Event Guide:

Event #8: LOCA Position Expected Actions Time/Comments BOP 5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

LPCI Initiation signal is NOT present, OR

Directed by SRO, THEN ....... PLACE keylock switch 3-XS 122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121(129),

RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11)

INBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV-74-52(66),

RHR SYS 1(11) OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired RHR System lill) pump(s) for Suppression Chamber Spray.

1(11)

f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBR/POOL ISOL VLV.

g. OPEN 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.

HL TS-3-13 Rev 0 Page 68 of 85 XII. Simulator Event Guide:

Event #8: LOCA Position Expected Actions Time/Comments BOP h. IF ............. RHR System 1(11) is operating ONLY in Suppression Chamber Spray mode, THEN ....... CONTINUE in this procedure at Step 5.k.

i. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

j. RAISE system flow by placing the second RHR System 1(11) pump in service as necessary.

k. MONITOR RHR Pump NPSH using Attachment 2.

I. VERIFY RHRSW pump supplying desired RHR Heat Exchanger( s).

m. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

HLTS-3-13 Rev 0 Page 69 of 85 XII. Simulator Event Guide:

Event #8: LOCA Position Expected Actions Time/Comments BOP n. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

6. WHEN ...... EITHER of the following exists:

Before Suppression Pool pressure drops below 0 psig, OR

Directed by SRO to stop Suppression Chamber Sprays, THEN ....... STOP Suppression Chamber Sprays as follows:

a. CLOSE 3-FCV-74-58(72), RHR SYS 1(11)

SUPPR CHBR SPRAY VALVE.

b. VERIFY CLOSED 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE

c. IF ............. RHR operation is desired in ANY other mode, THEN ....... EXIT this EOI Appendix.

If Loop I tried, notifies US of Logic failure SRO Directs that PSC sprays be stopped if PSC pressure 0 psig psi~

Dispatches personnel to investigate select power loss on Loop I RHR

HL TS-3-13 Rev 0 Page 70 of 85 XII. Simulator Event Guide:

Event #9: DW Spray failure and repair Position Expected Actions Time/Comments Crew Monitors Rx level and PC pressure and reports to US when PSC pressure is 12 psig SRO Verifies Recirc pumps tripped Directs all DW blowers secured Verifies in safe region of DW spray curve ATC Secures all DW blowers SRO Directs DW sprayed lAW App-17B BOP Attempts to spmythe spray the DW with App-17B Reports RHR Loop I select logic not working (if not already identified)

Reports 74-75 Loop II spray valve will not open

SRO ATC Directs DW spray spray valve 74-75 be manually opened Directs DW Blowers returned to service Directs IMs to checking Loop I logic failure (if not already done)

Restarts all DW blowers BOP Reports start of Core Spray pumps

HLTS-3-13 Rev 0 Page 71 of 85 XII. Simulator Event Guide:

Event #9: DW Spray failure and repair (continued)

Position Expected Actions Time/Comments SRO Monitors DW pressure and temperature Determines that DW temperature cannot be maintained < 280°F Directs Emergency Depressurization if cannot maintain < 280°F in drywell BOP Opens 5 ADS valves and 1 additional valve and verifies open SRO Directs level be restored and maintained between

+2" to +51" with:

Condensate App-6A

Core Spray App-6D or 6E

RHR App-6B or 6C Re-enters Enters EOI-2 on Suppression Chamber LevellTemp

ATC Recover level with Condensate, 3-EOI Appendix-6A

1. VERIFY CLOSED the following Feedwater heater return valves:

3-FCV-3-71, HP HTR 3A1 LONG CYCLE TO CNDR

3-FCV-3-72, HP HTR 3B1 LONG CYCLE TOCNDR

3-FCV-3-73, HP HTR 3C1 LONG CYCLE TOCNDR

HLTS-3-13 Rev 0 Page 72 of 8S XII. Simulator Event Guide:

Event #9: OW Spray failure and repair (continued)

Position Expected Actions Time/Comments ATC 2. VERIFY CLOSED the following RFP discharge valves:

3-FCV-3-19, RFP 3A DISCHARGE VALVE

3-FCV-3-12, RFP 38 DISCHARGE VALVE

3-FCV-3-S, RFP 3C DISCHARGE VALVE

3. VERIFY OPEN the following drain cooler inlet valves:

3-FCV-2-72, DRAIN COOLER 3AS CNDS INLET ISOL VL V

3-FCV-2-84, DRAIN COOLER 38S CNDS INLET ISOL VL V

3-FCV-2-96, DRAIN COOLER 3CS CNDS INLET ISOL VL V

4. VERIFY OPEN the following heater outlet valves:

3-FCV-2-124, LP HEATER 3A3 CNDS OUTL ISOL VL V 3-FCV-2-12S, OUTL ISOL VL V LP HEATER 383 CNDS

3-FCV-2-126, LP HEATER 3C3 CNDS OUTL ISOL VL V

HLTS-3-13 Rev 0 Page 73 of 85 XII. Simulator Event Guide:

Event #9: DW Spray failure and repair (continued)

Position Expected Actions Time/Comments ATC 5. VERIFY OPEN the following heater isolation valves:

3-FCV-3-38, HP HTR 3A2 FW INLET ISOL VLV

3-FCV-3-31, HP HTR 382 FW INLET ISOL VLV

3-FCV-3-24, HP HTR 3C2 FW INLET ISOL VLV

3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV

3-FCV-3-76, HP HTR 381 FW OUTLET ISOL VLV

3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV

6. VERIFY OPEN the following RFP suction valves:

3-FCV-2-83, RFP 3A SUCTION VALVE

3-FCV-2-95, RFP 38 SUCTION VALVE

3-FCV-2-108, RFP 3C SUCTION VALVE

7. VERIFY at least one condensate pump running

8. VERIFY at least one condensate booster pump running

9. ADJUST 3-LlC-3-53, RFW START-UP LEVEL CONTROL, to control injection (Panel 3-9-5)

10. VERIFY RFW flow to RPV

HL TS-3-13 Rev 0 Page 74 of 85 XII. Simulator Event Guide:

Event #9: OW Spray failure and repair (continued)

Position Expected Actions Time/Comments BOP Restores Reactor Level +2" to +51" with RHR I per 3-EOI Appendix-6B

1. IF ..............Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN ....... PLACE 3-HS-74-155A, LPCI SYS I OUTBO INJ VLV BYPASS SEL in BYPASS

2. VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VL V

3. VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VL V

4. VERIFY CLOSED the following valves:

3-FCV-74-61, RHR SYS I OW SPRAY INBO VLV

3-FCV-74-60, RHR SYS I OW SPRAY OUTBO VLV

3-FCV-74-57, RHR SYS I SUPPR CHBRIPOOL ISOL VL V

3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE

3-FCV-74-59, RHR SYS I SUPPR POOL CLGITEST VL V

5. VERIFY RHR Pump 3A and/or 3C running

6. WHEN ...... RPV pressure is below 450 psig, THEN ....... VERIFY OPEN 3-FCV-74-53, RHR SYS I LPCIINBO INJECT VALVE

HL TS-3-13 Rev 0 Page 75 of 85 XII. Simulator Event Guide:

Event #9: DW Spray failure and repair (continued)

Position Expected Actions Time/Comments BOP 7. IF .............. RPV pressure is below 230 psig, THEN ....... VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE

8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, as necessary to control injection

9. MONITOR RHR Pump NPSH using Attachment 1

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV

11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

12. NOTIFY Chemistry that RHRSW is aligned to in-service RHR heat exchangers

HL TS-3-13 Rev 0 Page 76 of 85 XII. Simulator Event Guide:

Event #9: OW Spray failure and repair (continued)

Position Expected Actions Time/Comments BOP Restores Reactor Level +2" to +51" with RHR II per 3-EOI Appendix-6C

1. IF .............. Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN ....... PLACE 3-HS-74-155B, LPCI SYS II OUTBO INJ VLV BYPASS SEL in BYPASS

2. VERIFY OPEN 3-FCV-74-24, RHR PUMP 3B SUPPR POOL SUCT VLV

3. VERIFY OPEN 3-FCV-74-35, RHR PUMP 30 SUPPR POOL SUCT VL V

4. VERIFY CLOSED the following valves:

3-FCV-74-75, RHR SYS II OW SPRAY INBOVLV

3-FCV-74-74, RHR SYS II OW SPRAY OUTBO VLV

3-FCV-74-71, RHR SYS II SUPPR CHBRIPOOL ISOL VL V

3-FCV-74-72, RHR SYS II SUPPR CHBR SPRAY VALVE

3-FCV-74-73, RHR SYS II SUPPR POOL CLGITEST VL V

5. VERIFY RHR Pump 3B and/or 30 running

6. WHEN ...... RPV pressure is below 450 psig, THEN ....... VERIFY OPEN 3-FCV-74-67, RHR SYS II LPCIINBO INJECT VALVE

HLTS-3-13 Rev 0 Page 77 of 85 XII. Simulator Event Guide:

Event #9: OW Spray failure and repair (continued)

Position Expected Actions Time/Comments BOP 7. IF .............. RPV pressure is below 230 psig, THEN ....... VERIFy CLOSED 3-FCV-68-3, RECIRC PUMP 3A DISCHARGE VALVE

8. THROTTLE 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE, as necessary to control injection

9. MONITOR RHR Pump NPSH using Attachment 1

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV

11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-52, OUTLETVLV RHR HX 3D RHRSW

12. NOTIFY Chemistry that RHRSW is aligned to in-service RHR heat exchangers

HL TS-3-13 Rev 0 Page 78 of 85 XII. Simulator Event Guide:

Event #9: OW Spray failure and repair (continued)

Position Expected Actions Time/Comments BOP Recover level with CS Loop I 3-EOI Appendix-6D

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VLV

3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VL V

3-FCV-75-23, CORE SPRAY SYS IOUTBO INJECT VALVE

2. VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALVE

3. VERIFY CS Pump 3A and/or 3C RUNNING

4. WHEN ... RPV pressure is below 450 pSig, THEN ... THROTTLE 3-FCV-75-25, CORE SPRAY SYS IINBO INJECT VALVE, as necessary to control injection at or below 4000gpm 4000 gpm per r:>er pump

5. MONITOR Core Spray Pump NPSH using Attachment 1 Recover level with CS Loop II 3-EOI Appendix-6E

1. VERIFY OPEN the following valves:

3-FCV-75-30, CORE SPRAY PUMP 3B SUPPR POOL SUCT VLV

3-FCV-75-39, CORE SPRAY PUMP 3D SUPPR POOL SUCT VLV

3-FCV-75-51, CORE SPRAY SYS II OUTBO INJECT VALVE

2. VERIFY CLOSED 3-FCV-75-50, CORE SPRAY SYS II TEST VALVE

3. VERIFY CS Pump 3B and/or 3D RUNNING

4. WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-53, CORE SPRAY SYS IIINBO INJECT VALVE, as necessary to control injection at or below 4000 i1pm gpm per pump

5. MONITOR Core Spray Pump NPSH using Attachment 1

HL TS-3-13 Rev 0 Page 79 of 85 XII. Simulator Event Guide:

Event #9: OW Spray failure and repair (continued)

Position Expected Actions Time/Comments SRO When notified 74-75 valve repaired; Directs a" OW blowers secured again Verifies in safe area of OW spray curve Directs OW sprayed lAW App-17B ATC Secures al OW blowers (again)

BOP Sprays Drywe" with Loop II RHR per Appendix-17B

1. BEFORE Drywe" pressure drops below 0 psig, CONTINUE in this procedure at Step 7.

2. IF .............. Adequate core cooling is assured, OR Directed to spray the Drywe" irrespective of adequate core cooling, THEN ...... .BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS

155A(B), LPCI SYS 1(11) OUTBD INJ VL V BYPASS SEL in BYPASS.

3. VERIFY Recirc Pumps and Drywe" Blowers shutdown.

4. IF .............. Directed by SRO to spray the Drywe" using Standby Coolant supply, THEN ....... CONTINUE in this procedure at Step 8.

5. IF .............. Directed by SRO to spray the Drywe" using Fire Protection, THEN ....... CONTINUE in this procedure at SteR Step 9.

HL TS-3-13 Rev 0 Page 80 of 85 XII. Simulator Event Guide:

Event #9: DW Spray failure and repair (continued)

Position Expected Actions Time/Comments BOP D~ell Sprays

6. INITIATE Drywell SQI"ays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

LPCI Initiation signal is NOT present, OR

Directed by SRO, THEN ....... PLACE keylock switch 3-XS 122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121 (129),

RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11)

LPCIINBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV-74-52(66),

RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired System 1(11)

RHR pump(s) for Dl)"I{eli Drywell Spray.

f. OPEN the following valves:

3-FCV-74-60(74), RHR SYS 1(11) DW SPRAY OUTBD VL V

3-FCV-74-61 (75), RHR SYS 1(11) DW SPRAY INBD VL V

g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

HLTS-3-13 Rev 0 Page 81 of 85 XII. Simulator Event Guide:

Event #9: OW Spray failure and repair (continued)

Position Expected Actions Time/Comments BOP h. IF ............. Additional Orywell Spray flow is necessary, THEN ....... PLACE the second System 1(11) RHR Pump in service.

i. MONITOR RHR Pump NPSH using Attachment 2.

j. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

k. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

HLTS-3-13 Rev 0 Page 82 of 85 XII. Simulator Event Guide:

Event #9: DW Spray failure and repair (continued)

Position Expected Actions Time/Comments BOP 7. WHEN ...... EITHER of the following exists:

Before drywell pressure drops below 0 psig, OR

Directed by SRO to stop Drywell Sprays, THEN ....... STOP Drywell Sprays as follows:

a. VERIFY CLOSED the following valves:

3-FCV-74-100, RHR SYS I U-2 DISCH XTIE

3-FCV-74-60(74), RHR SYS 1(11) DW SPRAY OUTBD VLV

3-FCV-74-61 (75), RHR SYS 1(11) DW SPRAY INBD VL V

b. VERIFY OPEN 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

c. IF ............. RHR operation is desired in ANY other mode, THEN ....... EXIT this EOI Appendix.

SRO Directs DW sprays secured if pressure lowers to 0 psig Declares event Alert 2.1-A or 2.4-A

HLTS-3-13 Rev 0 Page 83 of 85 XIII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Inserts a manual scram within 1 minute of failure to scram on turbine trip

2) Emergency depressurizes RPV within 5 minutes of exceeding 280°F

3) Restores / maintains water level above TAF (-162")

HLTS-3-13 Rev 0 Page 84 of 85 XV. SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HL TS-3-13

-.JL Total Malfunctions Inserted: List (4-8)

1) Control Rod Drift

2) Loss of 3A 250V RMOV Bd

3) Loss of HPCI120V power supply

4) Failure of ADS/SRV 1-22

5) RWCU leak with failure to auto isolate

6) Turbine trip / Bypass valve failure

7) Drywel/ Leak

8) Drywel/ Spray Failure

9) DG "3A" auto start Failure

~ Malfunctions that occur after EOI entry: List (1-4)

1) Drywel/ Leak

2) Drywel/ Spray Failure

3) DG "3A" auto start Failure Abnormal Events: List (1-3)

1) Control Rod Drift (3-AOI-85-5)

2) Loss of 3A 250V RMOV Bd

3) Failure of ADS/SRV 1-22

4) RWCU leak with failure to auto isolate (AOI-64-2A)

5) High DW pressure (AOI-64-1)

_1_ Major Transients: List (1-2)

1) Drywel/ Leak EOJ's used: List (1-3)

1) EOI-1

2) EOI-2

3) EOI-3

~ EOI Contingencies used: List (0-3)

1) C-1 (possible)

2) C-2 JSL Run Time (minutes)

~ EOI Run Time (minutes): 50 % of Scenario Run Time

~ Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

RHR Pump 3A tagged 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago to change oil because wrong oil was used (7 day LCO per 3.5.1.A and 30 day LCO per 3.6.2.3.A 4, &5A). Expected back in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Operations/Maintenance for the Shift:

Perform CRO Timer Test per 3-01-85. Maintain power at 100%. Support maintenance on RHR Pump 3A. Continue to monitor OW pressure - known Nz leak in Orywell Unusual Conditions/Problem Areas:

Severe Thunderstorms in the area for the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

Appendix D Scenario Outline Form ES-D-1 Facility: Browns Ferry NPP Scenario No.:

No. : 3-16 Op-Test No.: HLT 0801 r--

r - ,.-----

r-----

I!t SRO:,:

SRO: SROI-5 II I

Examiners: Operators:

operators:. ATe: *.*

ATC: RO-7 BOP: RO-4 Initial Unit 3 is at 100% power with an 8% power reduction scheduled. HPCI is currently Conditions: tagged to repair the Auxiliary Oil Pump; and Feedwater Flow Indicator 3-788 is out of service with the 1M Technicians searching for a replacement transmitter.

Turnover: Units 1 and 2 are at approximately 92%. On Unit 3, reduce power to 92% due to low system load demand. Continue with performance of Core Spray II Flow Rate SR (in progress) . Support maintenance on HPCI; which is expected back in three hours.

hours. Additionally, support maintenance on Feedwater Flow Indicator 3-788.

Thunderstorm warnings are in effect for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Event Event No. Malf. No. Type* Event Description R-ATC 1 ------ Lowers power N-SRO C-80P 2 cs01d Core Spray Flow rate SR where 3D Core Spray Pump fails TS-SRO C-80P 3 pc12d 3A Reactor Zone Exhaust Fan belts shear, swap fans C-SRO C-ATC 4 multiple 3A Recirc Pump speed failure (increase), trip pump, insert rods TS-SRO C-ATC Power oscillations with failure to scram, insert rods, manual 5 cr02a 55 C-SRO scram 6 multiple M-ALL ATWS 7 th234 M-ALL Fuel failure

(N)ormal, (R)eactivity, (R )eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 1.2-5 1.2-S - SITE AREA

Appendix 0 Scenario Outline Form ES-O-1 Facility: Browns Ferry NPP Scenario No.: 3-16 (2) Op-Test No.: HLT 0801

~.------~------------------~

~'-------~-------------------. r . .

I SRO: SROU-1 Examiners: ..

r-----------------~

~----------------~

l Operators: ATC: RO-8 I * . BOP: RO-5 ANTICIPATED EAL: 1.2-S - SITE AREA

Scenario Narrative

The unit is operating at 100% power with an 8% power reduction scheduled. HPCI is tagged out for maintenance on the Auxiliary Oil Pump and is expected to be returned to service within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . It has been out of service for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months .

While performing the Core Spray Loop II Flowrate SR (3-SR-3.S.1.6(CS II)), a trip of 3D Core Spray pump is received and the Crew must consult Technical Specifications to determine required actions.

The belts will shear on 3A Rx Zone Exhaust Fan causing a low Reactor Building dIp and corresponding alarm where the crew will start standby fan per ARP and 3-AOI-30B.

A 3A Recirc Pump speed control failure (> 1S00 rpm) will occur. The crew will not be able to lower speed and will respond per 3-AOI-68-3; which will necessitate tripping the pump and responding per 3-AOI-68-1A. The Reactor will enter Region 2 of the Power to Flow Map and Power Oscillations will increase until the OPRM trip setpoint is exceeded. The crew will recognize failure to automatically scram and will insert a manual scram (If manual scram not already inserted prior to OPRMs exceeding scram setpoint).

The crew will experience a hydraulic ATWS and respond per 3-EOI-1 and CS. The crew will have to lower Reactor Water Level to control power per CS and App-4. The SDV will fail to drain totally, thus requiring multiple reactor scrams to insert Control Rods.

Due to the Fuel failure from the power oscillations, The Main Steam Line Rad Hi Hi Alarm will be received and the crew will recognize that MSIVs cannot be closed until after the control rods have all been inserted.

r, '-

t i- ~~~< ",,-

ANTICIPATED EAL: 1.2 SITE AREA

Appendix D Scenario Outline Form ES-D-1 Facility: Browns Ferry NPP No. :

Scenario No.: 3-16 Op-Test No.: HLT 0801 SRO: SROI-5 Examiners: Operators: ATC: RO-7 BOP: RO-4 I Initial Unit 3 is at 100% power with an 8% power reduction scheduled scheduled.. HPCI is currently Conditions: tagged to repair the Auxiliary Oil Pump; and Feedwater Flow Indicator 3-788 is out of service with the 1M Technicians searching for a replacement transmitter.

Turnover: Units 1 and 2 are at approximately 92%. On Unit 3, reduce power to 92% due to low system load demand. Continue with performance of Core Spray II Flow Rate SR (in progress). Support maintenance on HPCI; which is expected back in three hours. Additionally, support maintenance on Feedwater Flow Indicator 3-788.

Thunderstorm warnings are in effect for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Event Event No. Malf. No. Type* Event Description R-ATC 1 ------ Lowers power R-SRO N-80P 2 cs01d Core Spray Flow rate SR where 3D Core Spray Pump fails TS-SRO C-80P 3 pc12d 3A Reactor Zone Exhaust Fan belts shear, swap fans C-SRO C-ATC 4 multiple 3A Recirc Pump speed failure failure. (increase), trip pump C-SRO C-ATC 5 cr02a 55 Power oscillations with failure to scram C-SRO 6 multiple M-ALL ATWS 7 th234 M-ALL Fuel failure

(N)ormal, (R)eactivity, (I)nstrument, (I )nstrument, (C)omponent, (M)ajor DRAFT ANTICIPATED EAL: 1.2-S - SITE AREA

Appendix 0 Scenario Outline Form ES-O-1 Facility: Browns Ferry NPP Scenario No.:

No.: 3-16 (2) Op-Test No.:

No.: HLT 0801 SRO: SROU-1 Examiners: Operators: ATe: RO-8 BOP: RO-5 ANTICIPATED EAL: 1.2 SITE AREA

Scenario Narrative

The unit is operating at 100% power with an 8% power reduction scheduled. HPCI is tagged out for maintenance on the Auxiliary Oil Pump and is expected to be returned to service within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . It has been out of service for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months .

While performing the Core Spray Loop II Flowrate SR (3-SR-3.S.1.6(CS II)), a trip of 3D Core Spray pump is received and the Crew must consult Technical Specifications to determine required actions.

The belts will shear on 3A Rx Zone Exhaust Fan causing a low Reactor Building dIp and corresponding alarm where the crew will start standby fan per ARP and 3-AOI-30B.

A 3A Recirc Pump speed control failure (> 1S00 rpm) will occur. The crew will not be able to lower speed and will respond per 3-AOI-68-3; which will necessitate tripping the pump and responding per 3-AOI-68-1 A. The Reactor will enter Region 2 of the Power to Flow Map and Power Oscillations will increase until the OPRM trip setpoint is exceeded. The crew will recognize failure to automatically scram and will insert a manual scram (If manual scram not already inserted prior to OPRMs exceeding scram setpoint).

The crew will experience a hydraulic ATWS and respond per 3-EOI-1 and CS. The crew will have to lower Reactor Water Level to control power per CS and App-4. The SDV will fail to drain totally, thus requiring multiple reactor scrams to insert Control Rods.

Due to the Fuel failure from the power oscillations, The Main Steam Line Rad Hi Hi Alarm will be received and the crew will recognize that MSIVs cannot be closed until after the control rods have all been inserted.

ANTICIPATED EAL: 1.2 SITE AREA

HLTS-3-16 Rev 0 Page 1 of 62

SIMULATOR EVALUATION GUIDE TITLE: POWER REDUCTION, CORE SPRAY LOOP II FLOWRATE SR WITH FAILURE OF 3D PUMP, RECIRCULATION PUMP RUNAWAYITRIP, REACTOR POWER OSCILLATIONS, ATWS WITH MSIVS OPEN REVISION: 0 DATE: Feb. 1,2009 PROGRAM: BFN Operator Training - Hot License Examiner Note: This scenario requires a copy of 3-SR-3.5.1.6(CS II) complete thru step 7.3, ICS available, no DVM required RCP required for power reduction to 92% with Recirc flow (Provide at turnover)

PREPARED:

(Operations Instructor)

\

Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HL TS-3-16 Rev 0 Page 2 of 62

Revision Number Description of Changes Nuclear Training Revision/Usage Log Date Pages Affected Revised 0 Initial 02/01/09 All csf

HLTS-3-16 Rev 0 Page 3 of 62 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

POWER REDUCTION, CORE SPRAY LOOP II FLOWRATE SR WITH FAILURE OF 3D PUMP, RECIRCULATION PUMP RUNAWAYfTRIP, REACTOR POWER OSCILLATIONS, ATWS WITH MSIVS OPEN IV. Length of Scenario - 1 to 1 Y2 hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment / unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HL TS-3-16 Rev 0 Page 4 of 62

B. Enabling Objectives:

1. The operating crew will reduce Reactor power to - 92% lAW 3-GOI-1 00-1 and 3-01-68.

2. The operating crew will recognize and respond to a failure of a Core Spray pump 3D during a flowrate SR and determine required actions per Technical Specifications

3. The operating crew will recognize and respond to sheared belts on 3A Rx Zone exhaust fan and respond per ARP and 3-AOI-30B

4. The operating crew will recognize and respond to the 3A Recirc pump speed control failure (and subsequent manual trip) in accordance with 3-AOI-68-3 and 3-AOI-68-1A

5. The operating crew will recognize and respond to reactor power oscillations in accordance to 3-AOI-68-1A and 3-GOI-100-1

6. The operating crew will recognize and respond to an A TWS in accordance with EOI-1 and C5

7.

8.

The operating crew will recognize and respond to high suppression pool temperature in accordance with EOI-1 and EOI-2.

The operating crew will recognize and respond to high radiation in accordance with EOI-3

HLTS-3-16 Rev 0 Page 5 of 62

References:

The procedures used in the simulator are controlled copies and are

VI. used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

HL TS-3-16 Rev 0 Page 6 of 62 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat hlts-3-16 MF/RF/OR# Description

1) imffw26b 0 '8' FW flow failure

2) imftc020 Fails bypass valves closed

3) bat tohpci Tags out HPCI

4) trg e1 MODESW Sets trigger

5) trg e2 CSDSTART Sets trigger

6) trg e3 RXZFANS Sets trigger 6)

6) imf th23 (e1 0) 4 15:00 Fuel failure

7) imf rp08a RPS A 1 scram failure

8) imf rp08b RPS A2 scram failure

9) imf cs01d (e2 0:30) CS pump 3D trip after 30 seconds

10) dor an:xa553d[32] (e3 0) Delete alarm after fan swap

2. File: bat hlts-3-16-1 MF/RF/OR# Description

1) 2)

I imf pc12d I ior an:ov:xa553d[32] alarm on

3. File: bat hlts-3-16-2 Shears 3A Rx Zone Exh Fan belts Ann - Rx bldg low dp sealed in MF/RF/OR# Description

1) bat 3ainc 3A Recirc pump runaway (-1535 rpm)

2) imf cr02a 55 6:00 Power Oscillations

3) bat atws95east 95% Hydraulic ATWS east side

4. File: bat tohpci MF/RF/OR# Description

1) ior ypomtrglesh fail cn _po Tag gland seal exhauster

2) ior ypovfcv733a close 73-3 close

3) y~ovfcv733 fail now ior ypovfcv733 Tag FCV 73-3

4) ior ypovfcv7316 fail now Tag FCV 73-16

5) ior ypovfcv7381 fail now Tag FCV 73-81

6) ior zdihs7347a ptl Tag HPCI Aux oil pump

7) ior zohs7347a[1] off Green light off

8) imf hp05 HPCI trip

HLTS-3-16 Rev 0 Page 7 of 62

1) 2)

5. File:

MF/RF/OR#

mrf rp13a byp mrf rp13b byp bat app01f Description Bypasses automatic scrams

3) mrf rp13c byp

4) mrf rp13d byp

6. File: bat app02 MF/RF/OR# Description 11

1) I mrf rp12a test Bypasses ARI

2) 1I mrf rp12b test

7. File: bat app08ae MF/RF/OR# Description

1) mrf rp06a byp

2) mrf rp06b byp Bypasses Gp 1 isolation on low level

3) mrf rp06c byp

4) mrf rp06d byp

5) 6)

mrf rp14a byp mrf rp14b byp

8. File: bat atws95east Bypasses Gp 6 isolation on low level MF/RF/OR# Description

1) I imf rd17a SDV level switch failure

2) I imf rd09a 95 95% hydraulic A TWS east side

9. File: bat sdv MF/RF/OR# Description

1) I dmf rd17a Deletes SDV level switch failure 2J

2) I dmf rd17b

10. File: bat sdvtd MF/RF/OR# Description

1) dmf rd17a Deletes SDV level switch failure

2) dmf rd17b

3) imf rd17a (none 8:00)

Inserts level switch failure after 8 minutes

4) imf rd17a (none 8:00)

HLTS-3-16 Rev 0 Page 8 of 62

IX. Console Operators Instructions ELAP TIME HLTS 3-16 DESCRIPTION/ACTION Simulator Setup 100% MOC manual reset 255 (david)

Simulator Setup imffw26b 0 imftc020 bat tohpci imf rp08a verify imf rp08b trg e1 MOOESW trg e2 CSOSTART trg e3 RXZFANS Simulator Setup Tag out HPCI. Hang out of service cover on "8" FW Flow Indicator.

manual Place toilet bowl on ann. 9-6C win 14

Simulator Setup manual Start A3 EECW pump, place HPCI AOP and Steam packing exhauster in PTL, place testing borders on ann windows 9-3C/10, 9-3F/1, 9-23C/33, and 9-230/33 ROLE PLAY: At SR step 7.3[1] report CS static suction pressures at 6 psig (both pumps)

ROLE PLAY: At SR step 7.3[2] report Motor power on indicating light is extinguished (38 480v rmov / 88) and no air flow can be felt above either CS pump motor ROLE PLAY: At SR step 7.3[6.6] report pressure is 248 psig ROLE PLAY: At SR step 7.3[6.9] report lowest pressure observed is 220 psig ROLE PLAY: At SR step 7.3[7.3] report suction pressure as 5 psig

(259 psig - if asked for local disch)

HLTS-3-16 Rev 0 Page 9 of 62 ROLE PLAY: If asked for 3-FM-75-49 mV reading (step 7.3[7.6]) not taken due to dvom not installed - ICS used instead ROLE PLAY: At SR step 7.3[9] report vibration readings obtained ROLE PLAY: At SR step 7.3[10] report Motor power on indicating light is illuminated (38 480v rmov I 88) and flow detected above both pump motors ROLE PLAY: At SR step 7.3[11] (if asked) report pump started and tripped 3 minutes after Tech. Specs. Shear belts on 3A Rx Zone exh Addressed for tripped CS pump bat h Its-3-16-1 ROLE PLAY: If directed to check local bldg dp, report Rx Zone dp (+0.2 psid)

ROLE PLAY: If directed to investigate 3A Rx Zone exhaust fan locally, report all belts are sheared (motor running but not fan)

When 38 Rx zone fans placed liS, Delete override on dp alarm VERIFY alarm gets deleted, dor an:xa553d[32]

otherwise, press button to delete alarm ROLE PLAY: If directed to check local bldg dp after 38 fans placed in service, report Rx Zone dp (- 0.27 psid) (If 3A fans secured but 38 fans not started, report dp 0.0 psid) 3 minutes after 38 Rx Zone fans Recirc runaway - pwr osci" placed in service bat hlts-3-16-2 Immediately after scram enable SDV switches bat sdv As soon as scram is reset Disable SDV switches for 7 min bat sdvtd If requested to close 3-85-586 wait closes85-586 5 minutes mrf rd06 close

ROLE PLAY: Call and report 2-85-586 closed

HLTS-3-16 Rev 0 Page 10 of 62

If requested to perform Appendix 2 bypasses ARI scram wait 3 minutes bat app02 If requested to perform Appendix 1F bypasses auto scram signals wait 5 minutes bat app01f ROLE PLAY: Call and report App-2 & 1 F complete If requested to perform Appendix 8A PCIS Group bypasses

& E wait 6 minutes batapp08ae ROLE PLAY: Call and report App-8A & 8E complete When requested to open 2-85-586 Opens 3-85-586 mrf rd06 open ROLE PLAY: Call and report 3-85-586 open

When RWL lowered for power control. ..

Immediately after 2 na scram Delete power oscillations dmf cr02a Enable SDV switches bat sdv As soon as scram is reset Disable SDV switches for 8 min bat sdvtd After 2na scram reset if Lead Removes ATWS Examiner is satisfied with RC/Q bat atws-1 usage and power control Terminate the scenario when the following conditions are satisfied or upon request of instructor:

1) All rods fully inserted

2) MSIV's closed after all control rods inserted and C5 exited

3) RPV water level +2" to +51" (or recovering)

HLTS-3-16 Rev 0 Page 11 of 62 Scenario Summary:

x.

The unit is operating at 100% power with a 8% power reduction scheduled. HPCI is tagged out for maintenance on the Auxiliary Oil Pump and is expected to be returned to service within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . It has been out of service for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months .

While performing the Core Spray Loop II Flowrate SR (3-SR-3.5.1.6(CS II>> a trip of 3D Core Spray pump is received and the Crew must consult Tech Specs to determine required actions.

The belts will shear on 3A Rx Zone exhaust fan causing a low Rx bldg dp and corresponding alarm where the crew will start standby fan per ARP and 3-AOI-30B 3A Recirc pump speed control failure (> 1500 rpm), the crew will not be able to lower speed and will respond per 3-AOI-68-3 and have to trip the pump and will respond per 3-AOI-68-1A. The Reactor will enter Region 2 of the power to flow map and power oscillations will increase until the OPRM trip setpoint is exceeded. The crew will recognize failure to auto scram and will insert a manual scram (If manual scram not already inserted prior to OPRM's exceeding scram setpoint).

The crew will experience a hydraulic ATWS and respond per 3-EOI-1 and C5. The crew will have to lower RWL to control power per C5 and App-4. The SDV will fail to drain totally, thus requiring multiple reactor scrams to insert control rods.

Due to the Fuel failure from the power oscillations, The Main Steam Line Rad HiHi alarm will be received and the crew will recognize Not to close MSIV's until after the control rods have all been inserted.

HLTS-3-16 Rev 0 Page 12 of 62 XI. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. US: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. All rods fully inserted

2. RPV water level +2" to +51 " (or recovering)

HL TS-3-16 Rev 0 Page 13 of 62 XII. Simulator Event Guide:

Event #1 : Lower Rx Power with Recirc Flow Position Expected Actions Time/Comments SRO Notifies ODS of power drop Direct lowering U3 Power to 92% using Recirc Flow per 3-GOI-100-12 step 5.0[6] and 3-01-68 step 6.2 Crew Notifies Chemistry and RADCON of power drop ATC [1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)/LOWER SLOW(MEDIUM)(FAST) 3-HS-96-17A(17B)(17C),

push-buttons, to achieve balanced jet pump flows.

AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS 16A(16B) / LOWER SLOW(MEDIUM)(FAST) 3-HS

18A(18B)(18C),push-buttons, to achieve balanced jet pump flows.

AND/OR WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 LOWER SLOW, 3-HS-96-33 LOWER MEDIUM, 3-HS-96-34 LOWER FAST, 3-HS-96-35 If speeds are between 1200 and 1300 rpm then speeds should be mismatched by 60 rpm BOP Provides peer check for Recirc adjustment Continue to monitor BOP (transfer volts, condensate flow, etc)

HL TS-3-16 Rev 0 Page 14 of 62 XII. Simulator Event Guide:

Event #2: Core Spray Pump Failure Position Expected Actions Time/Comments SRO Directs BOP to continue with Core Spray flowrate SR 3-SR-3.5.1.6(csll)

BOP Resumes Core Spray Loop II Flow rate SR 3-SR-3.5.1.6(csll) at step 7.3, performs required manipulations per the SR 7.3 Core Spray Pump Flow and Valve Testing

[1] VERIFY CS Pump 3B and 3D pretest static suction pressures are adequate and RECORD below:

records pump suction pressures

[2] CHECK Core Spray NE Room Cooler Fan is NOT operating as follows:

On 480V RMOV Board 3B, Compartment 8B (EI 593') CHECK the fan motor Power On light 3-IL-064-0073 is extinguished.

Above CS Pump 3B, CHECK that no air flow can be felt from the duct louvers while standing next to the pump.

Above CS Pump 3D, CHECK that no air flow can be felt from the duct louvers while standing next to the pump.

[3] START CS Pump 3B using 3-HS 33A.

[4] THROTTLE 3-FCV-75-50 using CORE SPRAY SYS II TEST VALVE, 3-HS-75-50A to obtain an average CS LOOP II flow of 3200 gpm as indicated by 3-FI-75-49.

[BFPER98-004734-000]

HL TS-3-16 Rev 0 Page 15 of 62 XII. Simulator Event Guide:

Event #2: Core Spray Pump Failure Position Expected Actions Time/Comments BOP [5] CHECK the following annunciators on Panels 3-9-3 and 3-9-23C are in alarm:

CORE SPRAY SYS II PUMP B START (3-XA-55-3F, window 1)

RHR OR CS PUMPS RUNNING ADS BLOWDOWN PERMISSIVE (3-XA-55-3C, window 10)

CORE SPRAY PUMP 3B RUNNING (3-XA-55-23C, window 33)

[6] PERFORM the following to verify 3-CKV-075-0570B operation:

[6.1] THROTTLE 3-FCV-75-50 using CORE SPRAY SYS II TEST VALVE, 3-HS-75-50A to obtain a CS LOOP II flow of approximately 1800 gpm as indicated by 3-FI-75-49

[6.2] VERIFY CORE SPRAY SYS II MIN FLOW VALVE, 3-FCV-75-37 opens

[6.3] THROTTLE 3-FCV-75-50 using CORE SPRAY SYS II TEST VALVE, 3-HS-75-50A to obtain a flow of approximately 2800 gpm as indicated by 3-FI-75-49

[6.4] VERIFY CORE SPRAY SYS II MIN FLOW VALVE, 3-FCV-75-37 is closed

HLTS-3-16 Rev 0 Page 16 of 62 XII. Simulator Event Guide:

Event #2: Core Spray Pump Failure Position Expected Actions Time/Comments BOP [6.5] THROTTLE 3-FCV-75-50 using CORE SPRAY SYS II TEST VALVE 3-HS-75-50A to obtain a flow of approximately 3200 gpm as indicated by 3-FI-75-49

[6.6] On 3-LPNL-25-0060, RECORD the local CS Pump 3B discharge pressure below using 3-PI-075-0035:

Pum~ 3B Disch Press CS Pump psig

[6.7] NOTIFY Operations personnel to monitor CS Pump 3B discharge pressure measured locally by 3-PI-075-0035 on 3-LPNL-25-0060 for minimum reading obtained while opening the CORE SPRAY SYS II MIN FLOW VALVE 3-FCV-75-37

[6.8] CONTINUOUSLY HOLD the CORE SPRAY SYS II MIN FLOW VALVE, 3-HS-75-37A, in the OPEN position until Step 7.3[6.10]

[6.9] RECORD below the lowest CS Pump 3B discharge pressure measured locally by 3-PI-075-0035 on 3-LPNL-25-0060:

CS Pump 3B Disch Press pSig psig

HLTS-3-16 Rev 0 Page 17 of 62 XII. Simulator Event Guide:

Event #2: Core Spray Pump Failure Position Expected Actions Time/Comments BOP [6.10] RELEASE 3-HS-75-37A to the AUTO position

[6.11] CALCULATE the change in CS Pump 3B discharge pressure as stipulated below:

Initial Discharge Pressure __psig (Step 7.3[6.6])

Lowest Discharge Pressure - _psig (Step 7.3[6.9])

Discharge Pressure Change = _psi

.psi

[6.11.1] VERIFY calculation performed is correct (IV)

[6.12] CHECK the discharge pressure change recorded is greater than or equal to 10 psid

[6.13] CHECK CORE SPRAY SYS II MIN FLOW VALVE 3-FCV-75-37 is closed by noting valve position indicating lights above 3-HS-75-37A

[7] PERFORM the following ASME OM Code pump flow and pressure measurements for CS Pump 3B operation:

HLTS-3-16 Rev 0 Page 18 of 62 XII. Simulator Event Guide:

Event #2: Core Spray Pump Failure Position Expected Actions Time/Comments 80P [7.1] IF the ICS is available to obtain CS LOOP II flow rate data, THEN PERFORM the following; (Otherwise N/A.)

[7.1.1] CHECK no gross instrument channel failures have occurred by noting the ICS-displayed flow rate is within 100 gpm of the flow rate shown on CORE SPRAY SYS II FLOW Indicator 3-FI-75-49

[7.1.2] THROTTLE 3-FCV 50 using CORE SPRAY SYS II TEST VALVE, 3-HS-75-50A to obtain an average ICS display reading of 3200 gpm. [BFPER98-004734-000]

[7.2] IF the ICS is NOT available to obtain CS LOOP II flow rate data, THEN THROTTLE 3-FCV-75-50 using CORE SPRAY SYS II TEST VALVE, 3-HS-75-50A to obtain an average reading of 349 mV (+/- 0.5 mV) at the DVOM installed at Panel 3-9-19; (Otherwise N/A). [BFPER98-004734-000]

[7.3] WHEN stable conditions are obtained, THEN PERFORM the following:

RECORD CS Pump 38 suction pressure from Pressure Gauge A, (Ensure appropriate scale is used.)

CS Pump 38 suction press (M&TE) -psig

RECORD the pressure reading at 3-PI-075-0035 below:

CS Pump 38 discharge pressure psig

HLTS-3-16 Rev 0 Page 19 of 62 XII. Simulator Event Guide:

Event #2: Core Spray Pump Failure Position Expected Actions Time/Comments BOP [7.4] CALCULATE CS Pump 3B differential pressure as follows and VERIFY the differential pressure meets the acceptance criteria:

Discharge Pressure __ _ _ psig (Step 7.3[7.3])

Suction Pressure - __ _ _ psig (Step 7.3[7.3])

Differential Pressure = __

_ _ psid Acceptance Criteria: 223.6 to 273.4 psid

[7.5] VERIFY calculation is correct (IV)

[7.6] RECORD the following data for CS Pump 3B:

Core Spray Sys II Flow, or ICS Display _gpm AC=3200gpm Core Spray Sys II Disch Pressure 3-PI-75-48 _psig AC=N/A Core Spray Sys II Flow 3-FM-75-49 mV AC=349mV+/- 0.5mV Core Spray Pump 3B Motor Current 3-EI-75-33 _amps AC=N/A 4kV Shutdown Bd 3EC Voltage

_ _VAC AC=N/A N/A reading for 3-FM-75-49, CS SYS II FLOW, if DVOM was NOT installed

[8] [QMOS] NOTIFY EM to perform 0-TI-230 vibration measurements as indicated on Attachment 4 for CS PumpPump_ 3B

[9] RECORD CS Pump 3B vibration readings below:

AA AH1 AH2 BH CH1 CH2 in/sec

HLTS-3-16 Rev 0 Page 20 of 62 XII. Simulator Event Guide:

Event #2: Core Spray Pump Failure Position Expected Actions Time/Comments BOP [10] CHECK the Core Spray NE Room Cooler Fan is ON as follows:

On 480V RMOV Board 3B, Compartment 8B (EI 593')

CHECK the fan motor Power On indicating light 3-IL-064-0073 is illuminated

Above CS Pump 3B CHECK that air flow from the duct louver can be felt while standing next to the pump

Above CS Pump 20 CHECK that air flow from the duct louver can be felt while standing next to the pump

[11] START CS Pump 3D using 3-HS

42A

[12] THROTTLE 3-FCV-75-50 using CORE SPRAY SYS II TEST VALVE, 3-HS-75-50A as necessary to obtain a CS LOOP II flow of 6250 to 6350 gpm as indicated by 3-FI 49 or ICS display displa}'_

Reports trip of 3D Core Spray pump 30 seconds after starting per the SR

HLTS-3-16 Rev 0 Page 21 of 62 XII. Simulator Event Guide:

Event #2: Core Spray Pump Failure Position Expected Actions Time/Comments SRO Directs SR stopped at point where failure occurred.

May request clearance for 3D Core Spray pump Contact maintenance to investigate pump trip Directs UO to secure 3B Core Spray pump Consults Tech Spec 3.5.1 A, C, and 0 determines that a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO is in effect with HPCI and one (1) Low Pressure ECCS system inoperable Briefs Crew on Tech Spec requirements of Core Spray pump INOP with HPCIINOP BOP Stops SR performance Stops 3B Core Spray pump

HLTS-3-16 Rev 0 Page 22 of 62 XII. Simulator Event Guide:

Event #3: Shear of 3A Rx Zone Exhaust fan belts Position Expected Actions Time/Comments BOP Announces alarm 3-9-30 window 32 Reactor zone differential pressure low SRO Directs BOP to respond per ARP BOP A. IF the alarm is intermittent, THEN CHECK for high wind conditions (ex., >20 mph) on ICS B. IF high wind conditions CANNOT be confirmed, THEN REQUEST personnel to check local Reactor Building differential pressure C. IF alarm is due to high wind conditions, THEN EOI-3 entry is NOT required D. IF alarm is valid, THEN NOTIFY Unit Supervisor of 3-EOI-3 entry condition When building dp is reported + 0.2 psig, notifies SRO of EOI-3 entry condition

SRO BOP Enters EOI-3 Directs BOP to investigate Rx Bldg exhaust fan for proper operation E. REQUEST personnel to check fans locally for any apparent problems Checks fans on pnl 9-25 Notices Rx Zone exhaust flow reading 0 but fans indicate running

HLTS-3-16 Rev 0 Page 23 of 62 XII. Simulator Event Guide:

Event #3: Shear of 3A Rx Zone Exhaust fan belts Position Expected Actions Time/Comments BOP F. REFER TO 3-01-30B and PLACE standby fan in service to restore normal differential pressure When noticed exhaust flow 0 or when AUO reports exhaustfan belts sheared, enters 3-AOI-30B-1 and 3-01-30B places 3B fans in service 6.1 Alternating Reactor Zone Supply and Exhaust Fans

[1] VERIFY the Reactor Zone supply and exhaust fans are operating. REFER TO Section 5.1

[2] REVIEW all Precautions and Limitations in Section 3.0

[3] IF Reactor Zone Supply and Exhaust Fans will NOT be operated in fast speed, THEN SHUT DOWN Steam Vault Exhaust Booster Fan. REFER TO Section 7.4. (N/A if

Reactor Building Ventilation has been lost and it desired to run the booster fan to cool the steam tunnel) N/A

[4] PLACE REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-11A, in OFF

[5] [IIIC] VERIFY dampers close and fans stop as indicated by illuminated green lights above the following switches:

REACTOR ZONE SPLY OUTBD ISOL DMPR, 3-HS-64-13

REACTOR ZONE SPLY INBD ISOL DMPR, 3-HS-64-14

REACTOR ZONE EXH INBD ISOL DMPR, 3-HS-64-42

REACTOR ZONE EXH OUTBD ISOL DMPR, 3-HS-64-43

REACTOR ZONE FANS AND DAMPERS, 3-HS-64-11A [11/8-92-072]

HL TS-3-16 Rev 0 Page 24 of 62 XII. Simulator Event Guide:

Event #3: Shear of 3A Rx Zone Exhaust fan belts Position Expected Actions Time/Comments BOP [6] PLACE REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-11A, in SLOW A (SLOW B) to start alternate fans

[7] VERIFY dampers open and fans start as indicated by illuminated red lights above the following switches:

REACTOR ZONE SPLY OUTBD ISOL DMPR, 3-HS-64-13

REACTOR ZONE SPLY INBD ISOL DMPR, 3-HS-64-14

REACTOR ZONE EXH INBD ISOL DMPR, 3-HS-64-42

REACTOR ZONE EXH OUTBD ISOL DMPR, 3-HS-64-43

REACTOR ZONE FANS AND DAMPERS,3-HS-64-11A

[8] IF fast speed Reactor Zone Supply and Exhaust Fan operation is required, five minutes should be allowed after slow start for the discharge dampers to FULLY OPEN, THEN

[8.1] PLACE REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-11A, in FAST A (FAST B)

[8.2] VERIFY that the two green lights A(B) remain extinguished and the two red lights A(B) remain illuminated above REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-11A Places "B" Fans in fast speed after 5 minutes

HL TS-3-16 Rev 0 Page 25 of 62 XII. Simulator Event Guide:

Event #3: Shear of 3A Rx Zone Exhaust fan belts Position Expected Actions Time/Comments BOP [9] VERIFY the following conditions:

[9.1] VERIFY REACTOR ZONE PRESS DIFFERENTIAL Indicator, 3-PDIC-064-0002, on 3-LPNL-925-0213, located at R17-P EI639',

indicates between -0.25 inches and -

0.40 inches H2O

[9.2] IF REACTOR ZONE PRESS DIFFERENTIAL Indicator, 3-PDIC-64-2, is NOT between -0.25 inches and -0.40 inches H20, THEN REFER TO 3-AOI-30B-1, Reactor Building Ventilation Failure

[10] IF required, THEN START Steam Vault Exhaust Booster Fan. REFER TO Section 5.4 N/A Verifies low building dp alarm clears and notifies SRO SRO Exits EOI-3 when low bldg dp alarm clears

HL TS-3-16 Rev 0 Page 26 of 62 XII. Simulator Event Guide:

Event #4: 3A Recirc Pump Runaway / Trip / Power Oscillations Position Expected Actions Time/Comments ATC Notices 3A Recirc pump speed increasing by;

actually seeing pump speed increase

actually seeing core flow increase

noticing Rx Power (MWe or APRM's) increasing SRO Directs entry into 3-AOI-68-3 Directs lowering speed of 3A Recirc pump ATC Attempts to lower speed of 3A Recirc pump using individual lower fast/lower medium/lower slow pushbuttons (may also try master lower fast/lower mediumllower slow pushbuttons - but they will not work either)

Notifies SRO of inability to lower 3A Recirc pump speed

SRO Directs tripping 3A Recirc pump Directs entering 3-AOI-68-1A for tripped pump /

core flow lowering Contacts Management Contacts ODS / SW dispatcher of power drop ATC May dispatch licensed operator with key locally to VFD (but will NOT be able to wait for him/her to get there before having to trip 3A pump)

Trips / Shutdown 3A Recirc pump by depressing 3-HS-96-19

HLTS-3-16 Rev 0 Page 27 of 62 XII. Simulator Event Guide:

Event #4: 3A Recirc Pump Runaway I Trip I Power Oscillations (cont)

Position Expected Actions Time/Comments ATC Enters 3-AOI-68-1 A Subsequent Actions

[1] IF both Recirc Pumps are tripped in modes 1 or 2, THEN (Otherwise N/A),

A. SCRAM the Reactor.

A. RESTART affected Reactor Recirculation pumps. Refer to 3-01-68 Section 8.0.

[2] IF the flT between the Rx vessel bottom head temperature and the moderator temperature precludes restart of a Recirc pump, OR forced Recirculation flow CANNOT be established for any reason, THEN (Otherwise NA)

B. INITIATE a plant cooldown to prevent exceeding the pressure limit for the Rx vessel bottom head temperature indicated on 3-PNL-9-47, 3-TR-56-4 pt. 10 and based on Tech Specs Figure 3.4.9-1.

C. INFORM the Unit Supervisor, Tech Spec 3.4.1 requires the Reactor be placed in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Refer to 3-GOI-100-12A and Tech Specs 3.4.1.B.

[2] IF Region lor II of the Power to Flow Map (Illustration 1) is entered, THEN (Otherwise N/A)

IMMEDIATELY take actions to INSERT control rods to less than 95.2% loadline. Refer to 0-TI-464, Reactivity Control Plan Development and Implementation.

HLTS-3-16 Rev 0 Page 28 of 62 XII. Simulator Event Guide:

Event #4: 3A Recirc Pump Runaway I Trip I Power Oscillations (cont)

Position Expected Actions Time/Comments ATC [3] RAISE core flow to greater than 45%. Refer to 3-01-68.

[4] INSERT control rods to exit regions if not already exited. Refer to O-TI-464, Reactivity Control Plan Development and Implementation.

[5] CLOSE tripped Recirc Pump discharge valve.

[6] MAINTAIN operating Recirc pump flow less than 46,600 gpm. Refer to 3-01-68.

[7] [NERlC] WHEN plant conditions allow, THEN, (Otherwise N/A)

MAINTAIN operating jet pump loop flow greater than 41 x 106 Ibm/hr (3-FI-68-46 or 3-FI-68-48).

[GE SIL 517]

[8] IF Recirc Pump was tripped due to dual seal failure, THEN (Otherwise N/A)

[8.1] VERIFY TRIPPED, RECIRC DRIVE 3A(3B) NORMAL FEEDER, 3-HS 17(14).

[8.2] VERIFY TRIPPED, RECIRC DRIVE 3A(3B) ALTERNATE FEEDER, 3-HS 15(12).

[8.3] CLOSE tripped recirc pump suction valve using, RECIRC PUMP 3A(3B)

SUCTION VALVE, 3-HS-68-1(77).

[8.4] IF it is evident that 75°F between the dome AND the idle Recirc loop cannot be maintained, THEN COMMENCE plant shut down and cool down. Refer to 3-GOI-100-12A.

HLTS-3-16 Rev 0 Page 29 of 62 XII. Simulator Event Guide:

Event #4: 3A Recirc Pump Runaway / Trip / Power Oscillations (cont)

Position Expected Actions Time/Comments ATC [9] NOTIFY Reactor Engineer to PERFORM the following:

Tech Specs 3.4.1

3-SR-3.4.1 (SLO), Reactor Recirculation System Single Loop Operation

0-TI-248, Core Flow Determination in Single Loop Operation

[10] [NERlC] WHEN the Recirc Pump discharge valve has been closed for at least five minutes (to prevent reverse rotation of the pump) [GE SIL-517], THEN (N/A if Recirc Pump was isolated in Step 4.2[8])

OPEN Recirc Pump discharge valve as necessary to maintain Recirc Loop in thermal equilibrium.

[11] REFER TO the following ICS screens to help

determine the cause of recirc pump trip/core flow lowering.

VFDPMPA{VFDPMPB),

VFDPMPA(VFDPMPB), VFDAAL(VFDBAL)

HLTS-3-16 Rev 0 Page 30 of 62 XII. Simulator Event Guide:

Event #4: 3A Recirc Pump Runaway / Trip / Power Oscillations (cont)

Position Expected Actions Time/Comments ATC [12] CHECK parameters associated with Recirc Drive and Recirc Pump/Motor 3A(3B) on ICS and 3-TR-68-58(84) to determine cause of trip.

[13] PERFORM visual inspection of tripped Reactor Recirc Drive.

[14] PERFORM visual inspection of Reactor Recirc Pump Drive relay boards for relay targets.

[15] IF necessary, THEN (Otherwise N/A)

Refer to Illustration 5 of 3-01-68 for Reactor Recirc Pump trips.

[16] INITIATE actions required to make the necessary repairs. (Otherwise N/A)

[17] For Single Loop Operation, PERFORM the following:

[17.1] Refer to 3-01-68 for guidance on

single loop operation.

[17.2] Refer to Tech Specs 3.4.1.

[17.3] WHEN available, THEN RETURN tripped Recirc Pump to service. Refer to 3-01-68.

HL TS-3-16 Rev 0 Page 31 of 62 XII. Simulator Event Guide:

Event #4: 3A Recirc Pump Runaway / Trip / Power Oscillations (cont)

Position Expected Actions Time/Comments Crew Notifies Rx Engineer to perform;

3-SR-3.4.1 (SLO), Reactor Recirculation System Single Loop Operation

O-TI-248, Core Flow Determination in Single Loop Operation SRO Checks Tech Specs 3.4.1 ATC Monitors Reactor for power oscillations Recognizes power oscillations Notifies SRO of power oscillations When recognizes the Rx failed to scram when OPRM setpoint exceeded, inserts manual scram (contingent - manual scram may be inserted prior to exceeding scram setpoint - SRO conservative decision making)

HLTS-3-16 Rev 0 Page 32 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure Position Expected Actions Time/Comments ATC Recognizes hydraulic A TWS Takes mode switch to shutdown Initiates one channel of ARI Gives scram report SRO Enters 3-EOI-1 and C5 Directs initiating 2na channel of ARI Directs tripping 3B Recirc pump ATC Initiates 2 na channel of ARI Trips 3B Recirc pump Reports Rx power> 5%

Crew Announces Rx scram SRO Directs ADS inhibited

BOP SRO Inhibits ADS Directs bypassing scrams per App-1 F Directs bypassing ARI per App-2 Directs ATC to insert control rods per App-1 D BOP Calls for App-1 F and App-2

HLTS-3-16 Rev 0 Page 33 of 62 XII. Simulator Event Guide:

Event #5: ATVVS with Fuel Failure Position Expected Actions Time/Comments ATC Performs App-1 0

1. VERIFY at least one CRD pump in service

2. IF ..... Reactor Scram or ARI CANNOT be reset, THEN ... DISPATCH personnel to CLOSE 3-SHV-085-0586, CHARGING WATER SOV (RB NE, EI 565 ft)

3. VERIFY REACTOR MODE SWITCH in SHUTDOWN

4. BYPASS Rod Worth Minimizer

5. REFER to Attachment 2 and INSERT control rods in the area of highest power as follows:

a. SELECT control rod

b. PLACE CRD NOTCH OVERRIDE switch in EMERG ROD IN position UNTIL control rod is NOT moving inward

c. REPEAT Steps 5.a and 5.b for each control rod to be inserted

6. WHEN ... NO further control rod movement is possible or desired, THEN ... DISPATCH personnel to VERIFY OPEN 3-SHV-085-0586, CHARGING WATER SOV (RB NE, EI 565 ft)

Crew Recognizes and reports Group 2, 3, and 6 isolations if water level decrease below +2" SRO Directs App-8A and App-8E

HLTS-3-16 Rev 0 Page 34 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments SRO Directs Rx pressure be maintained BOO - 1000 psig with any of the following;

MSRV's - App-11A

MSL Drains - App-11 0 BOP Controls Rx pressure as directed with App-11A

1. IF ..... Drywell Control Air is NOT available, THEN ... EXECUTE EOI Appendix BG, CROSSTIE CAD TO DRYWELL CONTROL AIR, CONCURRENTL Y with this procedure.

2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE MSRVs and CONTROL RPV pressure using other options.

3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

a.1 3-PCV-1-179 MN STM LINE A RELIEF VALVE

b. 2 3-PCV-1-1BO MN STM LINE 0 RELIEF VALVE

c. 3 3-PCV-1-4 MN STM LINE A RELIEF VALVE

d. 4 3-PCV-1-31 MN STM LINE C RELIEF VALVE

e. 5 3-PCV-1-23 MN STM LINE B RELIEF VALVE

f. 6 3-PCV-1-42 MN STM LINE 0 RELIEF VALVE

g. 7 3-PCV-1-30 MN STM LINE C RELIEF VALVE

h. B 3-PCV-1-19 MN STM LINE B RELIEF VALVE

i. 9 3-PCV-1-5 MN STM LINE A RELIEF VALVE

j. 10 3-PCV-1-41 MN STM LINE 0 RELIEF VALVE

k. 11 3-PCV-1-22 MN STM LINE B RELIEF VALVE I. 12 3-PCV-1-1B MN STM LINE B RELIEF VALVE

m. 13 3-PCV-1-34 MN STM LINE C RELIEF VALVE

HLTS-3-16 Rev 0 Page 35 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP Controls Rx pressure as directed with App-11 D (If directed)

1. IF ..... BOTH of the following exist:

Emergency RPV Depressurization is required, AND

Group 1 Isolation Signal exists, THEN ... EXIT this procedure and ENTER EOI Append ix 11 H

2. VERIFY hotwell pressure below -7 in. Hg

3. CONTROL RPV pressure with Main Steam line drains as follows:

a. VERIFY PCIS reset

b. OPEN the following valves (Panel 3-9-3):

0 3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV

0 0

3-FCV-1-56, MN STM LINE DRAIN OUTBD ISOLATION VL V 3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER

4. THROTTLE 3-FCV-1-59, DOWNSTREAM MSL DRAIN TO CONDENSER, as necessary to control cooldown rate

HLTS-3-16 Rev 0 Page 36 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP 5. IF ..... At least one main steam line is open AND EITHER of the following exist:

Turbine bypass valves are NOT available, OR

Additional RPV pressure control is necessary, THEN ... CONTROL RPV pressure with Main Turbine and RFPT drains as follows:

a. OPEN the following Main Turbine Drain valves (Panel 3-9-7):

0 3-FCV-6-100, STOP VALVE 1 BEFORE SEAT DR VLV 0 3-FCV-6-101, STOP VALVE 2 BEFORE SEAT DR VLV 0 3-FCV-6-102, STOP VALVE 3 BEFORE SEAT DR VLV 0 3-FCV-6-103, STOP VALVE 4 BEFORE SEAT DR VLV

b. OPEN the following RFPT drain valves (Panel 3-9-6):

0 3-FCV-6-122, RFPT 3A HP STOP VL V ABOVE SEAT DR 0 3-FCV-6-127, RFPT 3B HP STOP VL V ABOVE SEAT DR 0 3-FCV-6-132, RFPT 3C HP STOP VL V ABOVE SEAT DR

HLTS-3-16 Rev 0 Page 37 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure Position Expected Actions Time/Comments SRO Directs Rx water level be lowered to control power to -50" per C5 and App-4 BOP Performs Appendix-4 on 9-3 as follows:

1. PREVENT injection to RPV from the following systems in any order as required:

a. HPCI

1) IF .............. HPCI Turbine is NOT at zero speed, THEN ........ PRESS and HOLD 3-HS-73-18A, HPCI TURBINE TRIP push-button

2) WHEN ...... HPCI Turbine is at zero speed, THEN ........ PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK and RELEASE 3-HS-73-18A, HPCI TURBINE TRIP push-button

b. RCIC

1) IF .............. DIRECTED by SRO to allow RCIC injection, THEN ........

EXIT step 1. b

2) PRESS 3-HS-71-9A, RCIC TURBINE TRIP push-button to trip RCIC Turbine

c. CORE SPRAY NOTE: After receipt of an automatic initiation signal, it is NOT necessary to wait until the pump actually starts before performing the next step.

Following an initiation signal, PLACE ALL Core Spray pumppumJ> control switches in STOP

HLTS-3-16 Rev 0 Page 38 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure Position Expected Actions Time/Comments BOP d. LPCI SYSTEM I PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM I pump control switches in STOP OR

BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL, in BYPASS AND

2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE

e. LPCI SYSTEM II PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM II pump control switches in STOP OR

BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155B, LPCI SYS II OUTBD INJ VL V BYPASS SEL, in BYPASS AND

2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE

HL TS-3-16 Rev 0 Page 39 of 62 XII. Simulator Event Guide:

Event #5: A TWS with Fuel Failure Position Expected Actions Time/Comments ATC Performs Appendix-4 on 9-5 & 9-6 as follows:

f. CONDENSATE and FEEDWATER

1) LOWER RFPT 3A(38)(3C) speed to minimum setting (approximately 600 rpm) using ANY of the following methods on Panel 3-9-5:

0 Using 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL AND individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C)

SPEED CONTROL PDS in AUTO, OR 0 Using individual 3-SIC 8(9)(10), RFPT 3A(38)(3C)

SPEED CONTROL PDS in MANUAL, OR 0 Using individual 3-HS 8A(9A)(10A), RFPT 3A(38)(3C)

SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR

HLTS-3-16 Rev 0 Page 40 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure Position Expected Actions Time/Comments ATC 2) CLOSE the following valves BEFORE RPV pressure drops below 450 psig:

0 3-FCV-3-19, RFP 3A DISCHARGE VALVE 0 3-FCV-3-12, RFP 3B DISCHARGE VALVE 0 3-FCV-3-5, RFP 3C DISCHARGE VALVE 0 3-LCV-3-53, RFW START-UP LEVEL CONTROL

3) TRIP RFPTs as necessary to prevent injection by DEPRESSING the following push-buttons:

0 3-HS-3-125A, RFPT 3A TRIP 0 3-HS-3-151A, RFPT 3B TRIP 0 3-HS-3-176A, RFPT 3C TRIP SRO When Rx water level is lowered to -50", directs water level be maintained -50" to -162" with RFP's per App-5A (directed water level band may be smaller if directed by SRO, i.e. -50" to -100")

ATC Re-establishes injection with a RFP in the directed water level band per App-5A

1. VERIFY Condensate System in service, supplying suction to RFPs

2. VERIFY OPEN MSIVs, supplying steam to RFPTs

HLTS-3-16 Rev 0 Page 41 of 62 XII. Simulator Event Guide:

Event #5: A TWS with Fuel Failure Position Expected Actions Time/Comments ATC 3. VERIFY Hotwell Pressure below -7 in. Hg

4. VERIFY CLOSED 3-FCV-1-121(129)(137),

RFPT 3A(38)(3C) LP STEAM SUPPLY VALVE

5. VERIFY OPEN 3-FCV-1-125(133)(141), RFPT 3A(38)(3C) HP STEAM SUPPLY VALVE

6. DEPRESS 3-HS-46-8A(9A)(1 OA), RFPT 3A(38)(3C) SPEED CONT RAISE/LOWER, and VERIFY amber light is illuminated

7. VERIFY a Main Oil Pump is running for RFPT to be started

8. VERIFY for EACH of the following pushbuttons, the green light is illuminated and the red light is extinguished:

3-HS-3-208A, RX WTR LVL CH A HI RFPT/MT TRIP RESET

3-HS-3-2088, RX WTR LVL CH 8 HI

RFPT/MT TRIP RESET

9. VERIFY OPEN the following valves:

3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV

3-FCV-3-76, HP HTR 381 FW OUTLET ISOL VLV

3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV

HLTS-3-16 Rev 0 Page 42 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure Position Expected Actions Time/Comments ATC 10. DEPRESS 3-HS-3-124A(150A)(175A), RFPT 3A(3B)(3C) TRIP RESET, and CHECK the following:

Blue light extinguished

HP Stop Valve open as indicated by red light above the following, as applicable:

0 3-HS-3-108, RFPT 3A HP STOP VLV TEST 0 3-HS-3-134, RFPT 3B HP STOP VLV TEST 0 3-HS-3-159, RFPT 3C HP STOP VLV TEST

LP Stop Valve open as indicated by red light above the following, as applicable:

0 3-HS-3-107, RFPT 3A LP STOP VLV TEST 0 3-HS-3-133, RFPT 3B LP STOP VLV TEST 0 3-HS-3-158, RFPT 3C LP STOP VLV TEST

11. VERIFY OPEN 3-FCV-3-20(13)(6), RFP 3A(3B)(3C) MIN FLOW VALVE

12. PLACE 3-HS-46-112A(138A)(163A), RFPT 3A(3B)(3C) START/LOCAL ENABLE, in START

13. CHECK RFPT 3A(3B)(3C) speed increases to approximately 600 rpm

14. VERIFY OPEN 3-FCV-3-19(12)(5), RFP 3A(3B)(3C) DISCHARGE VALVE 3A(3B)(3Cl

HL TS-3-16 Rev 0 Page 43 of 62 XII. Simulator Event Guide:

Event #5: A TWS with Fuel Failure Position Expected Actions Time/Comments ATC 15. RAISE RFPT 3A(38)(3C) speed UNTIL RFP discharge pressure is approximately equal to RPV pressure using ANY of the following methods on Panel 3-9-5:

Using individual 3-HS-46-8A(9A)( 1OA),

RFPT 3A(38)(3C) SPEED CO NT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in MANUAL, OR

Using 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 3-SIC-46-8(9)(1 0), RFPT 3A(38)(3C) SPEED CONTROL PDS in AUTO

16. SLOWLY RAISE speed of RFPT UNTIL RFW flow to the RPV is indicated using ANY of the following methods on Panel 3-9-5:

Using individual 3-HS-46-8A(9A)(1 OA),

RFPT 3A(38)(3C) SPEED CO NT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in MANUAL, OR

Using 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 3-SIC-46-8(9)(1 0), RFPT 3A(38)(3C) SPEED CONTROL PDS in AUTO

HLTS-3-16 Rev 0 Page 44 of 62 XII. Simulator Event Guide:

Event #5: A TWS with Fuel Failure Position Expected Actions Time/Comments ATC 17. ADJUST RFPT speed as necessary to control injection using ANY of the following methods on Panel 3-9-5:

Using individual 3-HS-46-8A(9A)( 1OA),

RFPT 3A(38)(3C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 3-SIC-46-8(9)(1 0), RFPT 3A(38)(3C) SPEED CONTROL PDS in MANUAL, OR

Using 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in AUTO

18. WHEN ... RPV level is approximately equal to desired level AND automatic level control is desired, THEN ... PLACE 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in AUTO with individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in AUTO

HLTS-3-16 Rev 0 Page 45 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure Position Expected Actions Time/Comments ATC Continues in Appendix-1 D When notified that App-2 is complete and outside portion of App-1 F is complete, continues in Appendix-1F and resets scram and starts draining SDV's

2. WHEN ... RPS Logic has been defeated, THEN ... RESET Reactor Scram

3. VERIFY OPEN Scram Discharge Volume vent and drain valves

4. DRAIN SDV UNTIL the following annunciators clear on Panel 3-9-4:

WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM (3-XA-55-4A, Window 1)

EAST CRD DISCH VOL WTR LVL HIGH HALF SCRAM (3-XA-55-4A, Window 29)

5. DISPATCH personnel to VERIFY OPEN 3-SHV-

085-0586, CHARGING WATER SOV NOTE: If EOI Appendix 2 has been executed, ARI initiation or reset will NOT be possible or necessary in Step 6

6. WHEN ... CRD Accumulators are recharged, THEN ... INITIATE manual Reactor Scram and ARI

7. CONTINUE to perform Steps 1 through 6 UNTIL ANY of the following exists:

ALL control rods are inserted to or beyond position 02, OR

NO inward movement of control rods is observed, OR

SRO directs otherwise

HLTS-3-16 Rev 0 Page 46 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments Crew Recognize and reports "OG Pretreatment Radiation High" and "OG Annual Release Limit Exceeded", notifies RadCon, and Chemistry SRO When the Suppression Pool temperature reaches 95°F (or level -1"), enters EOI-2 and directs;

all available Suppression Pool cooing per App-17A

H2 0 2 Analyzers placed in service

vent containment per App-12 (if needed)

BOP Places suppression pool cooling in service per Appendix-17A

1. IF .............. Adequate core cooling is assured, OR Directed to cool the Suppression Pool irrespective

of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VL V BYPASS SEL in BYPASS.

2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

HLTS-3-16 Rev 0 Page 47 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP c. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

d. IF ............. Directed by SRO, THEN ....... PLACE 3-XS-74-122(130), RHR SYS 1(11) LPCI2/3 CORE HEIGHT OVRD in MANUAL OVERRIDE.

e. IF ............ .LPCIINITIATION Signal exists, THEN ....... MOMENTARIL Y PLACE 3-XS-74-121 (129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT in SELECT.

f. IF ............. 3-FCV-74-53(67), RHR SYS 1(11) LPCIINBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV 52(66), RHR SYS 1(11) LPCI OUTBD INJECT VALVE.

g. OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBRIPOOL ISOL VL V.

h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating.

HLTS-3-16 Rev 0 Page 48 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11) SUPPR POOL CLGITEST VL V, to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR SYS 1(11)

FLOW:

Between 7000 and 10000 gpm for one-pump operation. OR

At or below 13000 gpm for two-pump operation.

j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

k. MONITOR RHR Pump NPSH using Attachment 1.

I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

m. IF ............. Additional Suppression Pool Cooling flow is necessary, THEN ....... PLACE additional RHR and RHRSW pumps in service using Steps 2.b through 2.1.

Places H202 Analyzers in service per EOI-2

1. Place Analyzer isolation bypass keylock switches to bypass

2. Select OW or Supp Chmbr and momentarily pull out select switch handle to start sample pumps

HLTS-3-16 Rev 0 Page 49 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP Vents Containment per Appendix-12 (If directed)

1. VERIFY at least one SGTS train in service.

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV,

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

3. IF ... While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN. PERFORM step 13 to secure the vent path

and reenter this procedure if further venting is required.

4. IF ... While executing this procedure, the desired vent path is lost or can not be established, THEN.

PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.

5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4 OR G-9, is to begin, THEN. BEFORE CAD is initiated, PERFORM Step 13 to secure the vent path.

HLTS-3-16 Rev 0 Page 50 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CO NT OR 3-FIC-84-20, PATH A VENT FLOW CONT NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented

6. IF ... ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR

Suppression Chamber can NOT be vented, OR

SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:

o Step 10 to vent the Drywell through 3-FCV-84-19, OR o Step 11 to vent the Drywell through 3-FCV-84-20.

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20.

HL TS-3-16 Rev 0 Page 51 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CO NT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3 54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CO NT, in AUTO with setpoint at 100 scfmJPanel scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3 55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12.

HL TS-3-16 Rev 0 Page 52 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

Release rates as determined below:

i. IF ... PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress THEN .. MAINTAIN release rates below those specified in Attachment 2.

ii. IF ... Severe Accident Management Guidelines are being executed, THEN .. MAINTAIN release rates below those specified by the TSC SAM Team.

iii. IF .. .venting for ANY other reason than items i or ii above, THEN .. MAINTAIN release rates below Stack release rate of 1.4 x 107 ~Ci/s AND O-SI-4.8.B.1.a.1 release fraction of 1.

Contacts LOG AUO to monitor release rates Crew Recognizes fuel damage from multiple Rad alarms and recognizes MSL Hi Hi Rad alarm SRO Directs MSIV remain open due to ongoing ATWS

HLTS-3-16 Rev 0 Page 53 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments ATC After SDV drained (alarms 9-4A windows 1 and 28 clear) directs85-586 re-opened (If closed)

After accumulators recharged, inserts 2na scram Recognizes some control rod movement, but all control rods not in SRO Directs reactor reset, drain SDV, and re-scram Directs SLC injection (conditional - if Suppression Pool temp ~11 OaF)

ATC After SDV drained again, inserts 3 ra scram Recognizes and reports all control inserted on scram BOP Verifies all rods in

HLTS-3-16 Rev 0 54 of 62 Page S4 XII. Simulator Event Guide:

Event #S:

5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments SRO Exits C5 CS to RCL (EOI-1 )

Exits RCO and directs OATC enter 3-AOI-100-1 Directs level be restored +2" to +S1"

+51" with RCIC (App-5C)

(App-SC) , and/or CRD (App-5B)

(App-SB)

Directs SLC stopped (if injected)

Directs closing MSIV's due to MSL Hi Hi alarm and no longer in C5 CS ATC Performs actions in AOI-1 00-1 BOP Appendix-SC Aligns and injects with RCIC per Appendix-5C

1. IF ..... BOTH of the following exist:

RPV Pressure is at or below 50 SO psig, AND

Bypass of RCIC low RPV pressure isolation interlocks is necessary,

THEN ... EXECUTE EOI Appendix 16A concurrently with this procedure

2. IF ..... BOTH of the following exist:

High temperature exists in the RCIC area, AND

SRO directs bypass of RCIC High Temperature Isolation interlocks, THEN ... PERFORM the following:

a. EXECUTE EOI Appendix 16K concurrently with this procedure

b. RESET auto isolation logic using RCIC AUTO-ISOL LOGIC A(B) RESET 3-XS S1A(B)pushbuttons 51 A(B) pushbuttons

HL TS-3-16 Rev 0 Page 55 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP 3. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPITHROT VALVE RESET

4. VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller in AUTO with setpoint at 600 gpm

5. OPEN the following valves:

3-FCV-71-39, RCIC PUMP INJECTION VALVE

3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

3-FCV-71-25, RCIC LUBE OIL COOLING WTRVLV

6. PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START

7. OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPL Y VLV, to start RCIC Turbine

8. CHECK proper RCIC operation by observing the following:

a. RCIC Turbine speed accelerates above 2100 rpm

b. RCIC flow to RPV stabilizes and is controlled automatically at 600 gpm

c. 3-FCV-71-40, RCIC Testable Check Vlv, opens by observing 3-ZI-71-40A, DISC POSITION, red light illuminated

d. 3-FCV-71-34, RCIC PUMP MIN FLOW VAL VE, closes as flow rises above 120 gpm

9. IF ..... BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN ... VERIFY OPEN 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

HL TS-3-16 Rev 0 Page 56 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP 10. ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller as necessary to control injection

11. IF ..... It is desired to align RCIC suction to the Suppression Pool, THEN ... PERFORM the following:

a. OPEN 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE

b. OPEN 3-FCV-71-18, RCIC SUPPR POOL OUTBD SUCT VALVE

c. WHEN ... 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE, and 3-FCV 18, RCIC SUPPR POOL OUTBD SUCT VAL VE, are fully open, THEN ... VERIFY CLOSED 3-FCV-71-19, RCIC CST SUCTION VALVE NOTE: Step 12.b must be performed promptly following Step 12.a to avoid loss of suction path

12. IF ..... It is desired to align RCIC suction to the Condensate Storage Tank, THEN ... PERFORM the following:

a. CLOSE 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE

b. WHEN ... 3-FCV-71-17, RCIC SUPPR POOL INBD SUCT VALVE starts traveling closed, THEN ... OPEN 3-FCV-71-19, RCIC CST SUCTION VALVE

c. CLOSE 3-FCV-71-18, RCIC SUPPR POOL OUTBD SUCT VALVE

HL TS-3-16 Rev 0 Page 57 of 62 XII. Simulator Event Guide:

Event #5: ATVVS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP Aligns and injects with CRD per Appendix-5B

1. IF ..... Maximum injection flow is NOT required, THEN ... VERIFY CRD aligned as follows:

a. VERIFY at least one CRD pump in service and aligned to Unit 3 CRD system.

b. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, as necessary to obtain flow rate of 65 to 85 gpm.

c. THROTTLE 3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VL V, to maintain 250 to 350 psid drive water header pressure differential.

d. EXIT this procedure.

2. IF ..... BOTH of the following exist:

CRD is NOT required for rod insertion, AND

Maximum injection flow is required, THEN ... LINE UP ALL available CRD pumps to the RPV as follows:

a. IF ..... CRD Pump 3A is available, THEN

... VERIFY RUNNING CRD Pump 3A or 3B.

b. IF ..... CRD Pump 3B is available, THEN

... VERIFY RUNNING CRD Pump 3A or 3B.

HLTS-3-16 Rev 0 Page 58 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP c. OPEN the following valves to increase CRD flow to the RPV:

3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VL V

3-PCV-85-27, CRD CLG WATER PRESS CONTROL VL V

3-FCV-85-50, CRD EXH RTN LINE SHUTOFF VALVE.

d. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, on Panel 9-5 to control injection WHILE maintaining 3-PI-85-13A, CRD ACCUM CHG WTR HDR PRESS, above 1450 psig, if possible.

e. IF ....... Additional flow is necessary to prevent or mitigate core damage, THEN

..... DISPATCH personnel to fully open the following valves as required:

3-THV-085-0527, CRD PUMP DISCH THROTTLING (RB NE, el 565')

3-BYV-085-0551, CRD PUMP TEST BYPASS (RB NE, el 565').

HLTS-3-16 Rev 0 Page 59 of 62 XII. Simulator Event Guide:

Event #5: ATWS with Fuel Failure (cont)

Position Expected Actions Time/Comments BOP Stops SLC (if injected)

Closes MSIV's when directed Crew Recognize RM-90-29A Rx Bldg High Radiation (conditional)

Evacuates Rx Bldg SRO If Rx Bldg High Rad alarm received, enters EOI-3 (conditional)

Classifies event as a Site Area Emergency (1.2-S)

HLTS-3-16 Rev 0 Page 60 of 62 XIII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Insert manual scram within 1 minute of OPRM failure to scram (conditional - Crew may insert manual scram prior to OPRM's exceeding trip setpoint)

2) Prevent Auto ADS actuation

3) Controls power by :

Inserting control rods per RC/Q-21 Lowering water level per C5 and App-4

4) When all rods are inserted restores and maintains RPV water level above T AF

5) Close MSIV's within 5 minutes of exiting C5

HLTS-3-16 Rev 0 Page 61 of 62 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-16

~ Total Malfunctions Inserted: List (4-8)

1) Core Spray failure (SR)

2) Rx Zone fan failure

3) Recirc pump runaway/trip

4) Power Oscillations

5) Failure of OPRM's to auto scram

6) ATWS

7) Fuel failure 2 Malfunctions that occur after EOI entry: List (1-4)

1) ATWS

2) Fuel failure 2 Abnormal Events: List (1-3)

1) Rx Zone fan failure

2) Recirc pump runaway/trip 2 Major Transients: List (1-2)

1) ATWS

2) Fuel failure EOl's used: List (1-3)

1) EOI-1

2) EOI-2

3) EOI-3

_1_ EOI Contingencies used: List (0-3)

1) C5 90 Run Time (minutes) 45 EOI Run Time (minutes): 50 % of Scenario Run Time

~ Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

HPCI tagged out for 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months to repair Auxiliary Oil Pump. Expected back in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . T.S.

3.5.1. 14 days LCO. Feedwater flow indicator 3-788 out of service, 1M's are looking for a new transmitter Operations/Maintenance for the Shift:

Reduce power to 92% with recirculation flow (due to system load not required). Core Spray

Loop" Flow Rate SR 3-SR-3.5.1.6(CS I/) in progress, continue SR at step 7.3.[11. Prejob brief completed for SR and power reduction. Units 1 & 2 are at 92% power Unusual Conditions/Problem Areas:

Severe thunderstorms in area for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

iI Appendix D Scenario Outline Form ES*D*1

"'~r

..' "'., :.", ~

0 I Facility: Browns Ferry Scenario No.: 3-17 Op-Test No.: 0801 SRO:

Examiners: Operators: ATC:

ATe:

, -. BOP:

Initial Conditions: 6% power with RHR Loop II tagged and 3A & B RFP's being tagged Turnover: Lower power to < 5%, swap steam loads, place Mode switch in Mode 2, start de-inerting Drywell, swap to RCIC for level control and close MSIV's. Severe thunderstorm warnings for the next 10 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Event Event No. Malf. No. Type* (Credited Position) I Event Description R-ATC 1 nja Lower power to < 5%

N-SRO -

0 2 nja N-BOP N-SRO place SJAE & OG preheaters on Aux steam C-ATC Continue to lower power, respond to CRD pump trip per 3-AOI-3 rd01a C-SRO 85-3, CRD System Failure I-ATC 4 nm05a 100 Respond to IRM failure upscale (after in Mode 2) (bypass)

TS-SRO N-BOP 5 nja De-inert Drywell per 3-01-76, Containment Inerting System N-SRO C-BOP 6 ypomtro2pmpb ypomtr02pmpb Respond to failure of 02 sample pump, swap analyzers TS-SRO C-BOP Respond to 3C RFP trip and place RCIC in service per 3-01-71, 7 fw13c C-SRO Reactor Core Isolation Cooling System 8 mult M-ALL Respond to scram j ATWS Respond to Steam line break in Drywell j Terminate and Prevent 9 th33a 10 M-ALL j Emergency Depressurize at - 180" (N)ormal, (N)ormal, (R)eactivity, (I )nstru ment, (I)nstrument, (C)omponent, (M)ajor :,. ...

,.. ""-~~.

""-~ . =-;.

-.-.../

-~ ."

ANTICIPATED EAL: 1.1*5 SITE AREA

.I Appendix 0 Scenario Outline Form ES-D-1

Starting - 6% power, the crew will lower power to < 5% by inserting control rods per 3-GOI-100-12A, RCP, and 3-01-85 Turbine sealing steam has already been swapped to aux boiler steam and the crew will swap the operating SJAE and Off-Gas Preheater from nuclear steam to aux boiler steam per 3-GOI-100-12A and 3-01-66 The crew will continue the power reduction and respond to 3A CRD pump trip per 3-AOI-85-3 After the Mode Switch is placed in Mode 2, 3A IRM fails upscale and will cause a % scram and the crew will by-pass the IRM and reset the % scram The crew will commence de-inerting containment per 3-01-76 for personnel entry and inspection at power The H202 Analyzer selected for the Drywell will fail requiring swapping the Analyzer selected for Suppression Chamber to the Drywell The only remaining RFP will trip (shortly after low oil level alarm and low bearing oil pressure alarms) and the crew will respond per 3-AOI-3-1 and place RCIC in service per 3-01-71, but power is still too high for RCIC alone and HPCI aux oil pump will not start,

requiring a manual scram Several control rods (8) fail to insert on the scram and will not be able to be inserted. The rods are clustered together and the Reactor Engineer will determine that the Reactor will NOT remain subcritical under all conditions A Drywell leak will cause level to lower and Drywell pressure to increase and the crew will respond per EOI-1, EOI-2, and C-5 to spray the Suppression Chamber and Drywell before having to terminate and prevent prior to emergency depressurization when level drops to -

180".

Only 2 ADS valves will open due to a Drywell Control Air header break, requiring opening 3 additional valves (for a total of 5 valves which changes MARF to 230 psig)

ANTICIPATED EAL: 1.1-5 SITE AREA

Appendix D Scenario Outline Form ES-D-1 Q Facility: Browns Ferry Scenario No.: 3-17 Op-Test No.: 0801 i

Examiners:

[i i Operators:

SRO:

ATe : .

ATC:

i L_._____. L L BOP: '

Initial Conditions: 6% power with RHR Loop II tagged and 3A & B RFP's being tagged Turnover: Lower power to < 5%, swap steam loads, place Mode switch in Mode 2, start de-inerting Drywell, swap to RCIC for level control and close MSIV's. Severe thunderstorm warnings for the next 10 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Event Event No. Malf. No. Type* (Credited Position) I Event Description R-ATC 1 n/a Lower power to < 5%

R-SRO N-BOP 2 n/a place SJAE & OG preheaters on Aux steam N-SRO 0 3 n/a - Continue to lower power I-ATC 4 nm05a 100 Respond to IRM failure upscale (after in Mode 2) (bypass)

TS-SRO N-BOP 5 n/a De-inert Drywell per 01OJ N-SRO C-BOP 6 mult. Respond to failure of 02 sample pump, swap analyzers TS-SRO C-BOP 7 mult. Respond to 3C RFP trip and place RCIC RCJC in service C-SRO 8 mult M-ALL Respond to scram / ATWS Respond to Steam line break in Drywell / Terminate and Prevent 9 th33a 10 M-ALL

/ Emergency Depressurize at - 180"

(N)ormal, (R)eactivity, (R )eactivity, (I)nstrument, (I )nstrument, (C )omponent, (M)ajor ANTICIPATED EAL: 1.1-5 SITE AREA

Appendix D Scenario Outline Form ES-D-1

Starting - 6% power, the crew will lower power to < 5%% by inserting control rods per 3-GOI-100-12A, RCP, and 3-01-85 Turbine sealing steam has already been swapped to aux boiler steam and the crew will swap the operating SJAE and Off-Gas Preheater from nuclear steam to aux boiler steam per 3-GOI-100-12A and 3-01-66 The crew will continue the power reduction until- 1% power per 3-GOI-100-12A, RCP, and 3-01-85 After the Mode Switch is placed in Mode 2, 3A IRM fails upscale and will cause a Y2 scram and the crew will by-pass the IRM and reset the Y2 scram The crew will commence de-inerting containment per 3-01-76 for personnel entry and inspection at power The H202 Analyzer selected for the Drywell will fail requiring swapping the Analyzer selected for Suppression Chamber to the Drywell The only remaining RFP will trip (shortly after low oil level alarm and low bearing oil pressure alarms) and the crew will respond per 3-AOI-3-1 and place RCIC in service per 3-01-71, but power is still too high for RCIC alone and HPCI aux oil pump will not start,

requiring a manual scram Several control rods (8) fail to insert on the scram and will not be able to be inserted. The rods are clustered together and the Reactor Engineer will determine that the Reactor will NOT remain subcritical under all conditions A Drywell leak will cause level to lower and Drywell pressure to increase and the crew will respond per EOI-1, EOI-2, and C-5 to spray the Suppression Chamber and Drywell before having to terminate and prevent prior to emergency depressurization when level drops to -

180".

Only 2 ADS valves will open, requiring opening 3 additional valves (for a total of 5 valves which changes MARF to 230 psig)

ANTICIPATED EAL: 1.1-5 SITE AREA

HLTS-3-17 Rev 0 Page 1 of 60 SIMULATOR EVALUATION GUIDE TITLE: Downpower from -6% to -1 %, de-inert containment, respond to 3A CRD pump trip, IRM failure upscale and % scram, swap steam loads to aux boiler, RFP trip -

swap to RCIC, close MSIV's and maintain level with RCIC until a Dryweilleak develops and level lowers to -180" and the crew will Terminate and prevent and Emergency Depressurize (opening 3 additional valves to get a total of 5) and re-commence injection at MARF of 230 psig REVISION: 0 DATE: Mar. 7,2009 PROGRAM: BFN Operator Training - Hot License RCP required for power reduction from -6% to -1 % by inserting Control Rods (Provide at turnover)

Verify IRM recorders have alarms set for 75 per 3-GOI-1 00-12A step 5.0[32.5]

Supply current Rev of 3-SR-3.6.2.1.1 to monitor Suppression Pool level and temperature when RCIC placed in service PREPARED: \

(Operations Instructor) Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HL TS-3-17 Rev 0 Page 2 of 60

Revision Number Description of Changes Nuclear Training Revision/Usage Log Date Pages Affected Revised 0 Initial 03/07/09 All csf

HLTS-3-17 Rev 0 Page 3 of 60 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

Downpower from -6% to -1 %, de-inert containment, respond to 3A CRD pump trip, IRM failure upscale and ~ scram, swap steam loads to aux boiler, RFP trip - swap to RCIC, close MSIV's and maintain level with RCIC until a Drywell leak develops and level lowers to -180" and the crew will Terminate and prevent and Emergency Depressurize (opening 3 additional valves to get a total of 5) and re-commence injection at MARF of 230 psig IV. Length of Scenario - 1 to 1 ~ hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment / unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HLTS-3-17 RevO Page 4 of 60

B. Enabling Objectives:

1. The operating crew will lower power to < 5% by inserting control rods per 3-GOI-100-12A and 3-01-85

2. The operating crew will swap steam loads from nuclear steam to aux boiler steam per 3-01-66

3. The operating crew will continue to lower power and place the Mode Switch in Mode 2 and will recognize and respond to a trip of 3A CRD pump and place 3B in service per 3-AOI-85-3

4. The operating crew will recognize and respond to an IRM failure upscale and subsequent Y2 scram and recovery per 3-01-92A and 3-01-99

5. The operating crew will de-inert containment per 3-01-76

6. The operating crew will recognize and respond to a trip of the H202 Analyzer aligned to the Drywell and will swap analyzers

7. The operating crew will recognize and respond to a trip of the only remaining RFP per 3-AOI-3-1 and place RCIC in service per 3-01-71

8. The operating crew will recognize and respond to an ATWS and Drywell leak per EOI-1, EOI-2, and C-5

9. The operating crew will terminate and prevent injection and emergency depressurize the Reactor when level drops to -180" per Appendix-4 and C-2

10. The operating crew will recognize and respond to a Drywell control air leak and open additional relief valves when ADS valves fail to open (total of 5 that can open causing MARF to be 230 psig)

HLTS-3-17 Rev 0 Page 5 of 60

References:

The procedures used in the simulator are controlled copies and are

VI.

used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

HLTS-3-17 Rev 0 Page 6 of 60 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat hlts-3-17 MF/RF/OR# Description

1) mrf ms01 on Aux boilers in service

2) m rf pc06 sta rt Pri Cont Purge Filter Fan I/S

3) mrf eg03 oos Gen Core monitor OOS

4) imffw13a Places trip on RFP 3A

5) imffw13b Places trip on RFP 38 6) 61 imf hp05 Prevents HPCI aux oil pump from starting

7) imf ad03a Fail closed (electrically)ADS (electrically) ADS valve 1-5

8) imf ad03b Fail closed (electrically) ADS valve 1-19

9) imf ad03c Fail closed (electrically) ADS valve 1-22

10) imf ad03d Fail closed (electrically) ADS valve 1-18

11) ior zdihs0142[1] close/auto Fail handswitch on SRV 1-42

12) bat rhr2to Tag 38 & 3D RHR pump motors onlY only

13) bat hlts-3-17-1 Stick 8 control rods (all in a close cluster)

14) bat h Its-3-17-6 Tag 3A & 38 RFP's - start sw, steam valves, pump suction and discharge valves

15}

15) 16) 17) 18) 19) ior zdihs7117a[1] null mrf ia02 align sev iavhcv311736 1 ior zdihs8550a[2] close ior zdihs8448[1] close Null RCIC CST suction valve Align CA to DWCA AlIgn Open 32-1736 85-50 overridden closed

20) ior zdihs8449[1] close Tag N2 to OW

21) ior zdihs848ab[1] off

22) ior zdihs848cd[1] off

2. File: bat hlts-3-17-1 MF/RF/OR# Description

1) imf rd06r2227

2) imf rd06r2631

3) imf rd06r3431

4) imf rd06r2623

5) imf rd06r3035 Stick 9 control rods (grouped together)

6) imt rd06r3027

7) imf rd06r2235

8) imf rd06r2639 9)

9) imf rd06r3043

HLTS-3-17 Rev 0 Page 7 of 60

1) 2)

3. File:

MF/RF/OR#

bat hlts-3-17-2 I ior zdihs03153a[3] stop I ior zlohs03153a[1] on Trip 3C3 E80P Description Override green light

4. File: bat hlts-3-17-3 MF/RF/OR# Description

1) I dor an:ov:xa556c[26] Delete oil pressure alarm override after oil

2) I dor an:ov:xa556c[16] pumps secured

5. File: bat hlts-3-17-6 MF/RF/OR# Description

1) ior zdihs46112a[1] norm

2) ior zdihs46138a[1] norm

3) ior zlohs46112a[2] off

4) ior zlohs46138a[2] off

5) ior zlohs03124[1] off

6) ior zlohs03150[1] off

7) 8)

9) 10) 11) ior zlohs01125a[2] off ior ziohs01121 a[2] off ior zlohs01133a[2] off ior zlohs01129a[2] off ior zdihs0319a[1] null Tag 3A & 38 RFP's - start / local enable switch,

12) ior zlohs0319a[2] off HP & LP steam valves, suction, discharge, and

13) ior zlohs0319a[1] off min flow valves

14) zdihs0283a[1] null ior zdihs0283a[11

15) ior zlohs0283a[2]

zlohs0283aI2] off

16) ior zlohs0283a[1] off

17) ior zdihs0312a[1] null

18) ior zlohs0312a[2] off

19) ior zlohs0312a[1] off

20) ior zdihs0295a[1] null

21) ior zlohs0295a[2] off

22) ior zlohs0295a[1] off

23) ior ypovfcv0320 fail control _power

24) ior ypovfcv0313 fail control _power

HL TS-3-17 Rev 0 Page 8 of 60

1) 2)

6. File:

MF/RF/OR#

bat hlts-3-17-7 ior an:ov:xa556c[26] alarm on ior zdihs03156a[1] test 5t 51 1 low oil press alarm Description Auto start of EBOP 3C3 oil pump

3) useless commands for time delay

4) ior an:ov:xa556c[4] alarm on Low oil level alarm

5) useless commands for time delay

6) ior an:ov:xa556c[16] alarm on 2 na nd low oil press alarm

7) imfnv13c(none:15) Trip 3C RFP after 10 sec time delay

8) imfth22100 Bottom drain leak

7. File: bat app07b l MF/RF/OR# Description Descri tion I 1) I mrf sl01 align ali n Alignn SLC to test tank

8. File: bat rhr2to MF/RF/OR# Description

1) I ior ypobkrpmpbrh fail power Tag 3B & 3D RHR pump motors only

2) I ior ypobkrpmpdrh y~obkrpmpdrh fail power

HLTS-3-17 Rev 0 Page 9 of 60 IX. Console Operators Instructions HLTS 3-17 ELAP TIME DESCRIPTION/ACTION Simulator Setup - 6% power MaC manual reset IC-233 (david)

Simulator Setup Main batch file - see summary bat hlts-3-17 Simulator Setup Place in run and reset RWM -

should latch into group 51 with rod manual 30-31 selected (clear rod block alarms if in)

Pnl 9 Push in on 3A RFP Speed Control (3-HS-46-8A)

Pnl 9 Push in on 38 RFP Speed Control (3-HS-46-9A)

Place HO cards on all the following:

Pnl 9 38 RHR pump HS (3-HS-74-28A)

Pnl 9 3D RHR pump HS (3-HS-74-39A)

Pnl 9 3A RFP LP Steam valves (3-HS-1-121A)

Pnl 9 3A RFP HP Steam valves (3-HS-1-125A)

Pn19 38 RFP LP Steam valves (3-HS-1-129A) manual Pn19 38 RFP HP Steam valves (3-HS-1-133A)

Simulator Pnl 9 3A RFP start I local enable HS (3-HS-46-112A)

Setup (should be 16 Pnl 9 38 RFP start I local enable HS (3-HS-46-138A) cards total)

Pnl 9 3A RFP Discharge valve (3-HS-3-19A)

Pnl 9 3A RFP Suction valve (3-HS-2-83A)

Pnl 9 38 RFP Discharge valve (3-HS-3-12A)

Pnl 9 38 RFP Suction valve (3-HS-2-95A)

Pnl 9 CAD A Cross Tie to DWCA (3-HS-84-48)

Pn19 Suppr Chbr I DW CAD 3A Sply Sel (3-HS-84-8A/8)

Pnl 9 CAD 8 Cross Tie to DWCA (3-HS-84-49)

Pnl 9 Suppr Chbr I DW CAD 38 Sply Sel (3-HS-84-8C/D)

HLTS-3-17 Rev 0 Page 10 of 60 ROLE PLAY: If requested as Aux Boiler AUO, report Aux Boilers in service and pressure is 180 psig (01-66 step 8.12[1.3])

ROLE PLAY: When requested, report 3-12-679 is open (SJAE STM SPLY valve)

(01-66 step 8.12[2])

ROLE PLAY: When requested, report STEAM TO SJAE STAGE I & II pressure at 3-PI-001-0150 and 0152 on Panel 25-105, is 180 psig (01-66 step 8.12[3])

When requested 66 step 8.12 Low Steam pressure permissive

[5] mrf og1 0 norm ROLE PLAY: Report SJAE TRAIN PERMISSIVE 3-HS-001-0375 is in NORM (01-66 step 8.12 [5])

manual valve to 3A SJAE open or mrf og03a open When requested 66 step 8.12

[6] manual valve to 38 SJAE open mrf og03b open

ROLE PLAY: Report AUX STM TO SJAE A(B) 1ST, 2ND & 3RD STG, 3-HS 3A(5A) open (01-66 step 8.12 [6]) (report the valve associated with the SJAE they are trying to place in service)

Steam inlet to 3A preheater open and mrf og04a aux When requested 66 step 8.12

[9.1] & [9.2] Steam inlet to 38 preheater open mrf og04b aux ROLE PLAY: When requested, report AUX STEAM TO OFF-GAS PREHEATER A and B, 3-HS-12-74B and 3-HS-12-75B are open (01-66 step 8.12 [9.1 &

9.2])

ROLE PLAY: When requested, report MAIN STEAM TO OFF-GAS PREHEATER 3A and 3B, 3-HS-1-176C and 3-HS-1-176D are closed (01-66 step 8.12 [9.3

& 9.4])

Trip 3A CRD pump After 02 sample pump swapped or imf rd01a when continuing power descent ROLE PLAY: If dispatched to investigate trip of 3A CRD pump, report breaker tripped on overload and the pump motor extremely hot

HLTS-3-17 Rev 0 Page 11 of 60

ROLEPLAY: If asked to check 38 CRD pump, report all oil levels are good and slinger rings are turning After Mode Switch taken to Mode 2 FaillRM A upscale imf nm05a 100 0:40 ROLE PLAY: If dispatched to check I align control air to drywell control air, report That 3-SHV-32-332 valve is unlocked and open and the 3-SHV 3278 is closed. The tagging crew is in the Process of tagging N2 to Containment Fail O2 sample pump S (OW) ior ypomtro2pmpb After Oe-inerting established faiLcontroLpower ROLE PLAY: If dispatched to investigate loss of O2 sample pump, report pump is extremely hot and the rotor is locked up ROLE PLAY: (3 minutes after O2 sample pump swapped) As AUO on rounds, report a large puddle of oil visible on floor between the turbine and pump of 3C RFP. Oil discharge pressure is 150 psig and lowering and bearing oil pressure is 45 psig and lowering. The oil tank indicates that level is lowering 3C RFP ESOP auto starts & low press alarm - RFP trips on low pressure alarm / low level, after 2 minutes after AUO report time delay - small OW leak bat hlts-3-17-7 ROLE PLAY: If dispatched to investigate 3C RFP after trip, wait 1 minute and report nothing notable except oil puddle is larger ROLE PLAY: Respond as needed as Radwaste UO if contacted to lock-out U3 Turbine bldg floor drain sump pumps If 3C RFP oil pumps secured Clear low oil pressure alarms bat hlts-3-17-3

When EOI-2 entered on Orywell temperature RCIC trip on low suction pressure imf rc03

HLTS-3-17 Rev 0 Page 12 of 60 6 minutes after scram or sooner if Recirc leak in Orywell needed to get level down sooner imf th21 1 15:00 If dispatched to close 3-85-586 Close 3-85-586 valve, wait 3 minutes mrf rd06 close ROLE PLAY: Call and report 3-85-586 closed If dispatched to open 3-85-586 Open 3-85-586 valve, wait 1 minute mrf rd06 open ROLE PLAY: Call and report 3-85-586 open If dispatched to perform App-7S, Align SLC to test tank wait 25 minutes batapp07b ROLE PLAY: If directed to perform any sections of 3-01-85 section 8.19 to insert stuck control rods, (i.e. vent overpiston area, etc.) repeat back directions (but you'll never get there) If called back requesting status report you lost your TLD badge and you're at the Radcon office ROLE PLAY: If dispatched to investigate HPCI aux oil pump failure to start, wait 4 minutes and report everything looks normal at breaker and at HPCI skid If requested to test breaker for HPCI Green light off for HPCI AOP -

aux oil pump, or if Maintenance simulate racking out breaker dispatched to look at breaker ior zlohs7347a[1] off ROLE PLAY: If requested to test breaker for HPCI aux oil pump, or if Maintenance dispatched to look at breaker, report breaker will not test and that maintenance is troubleshooting If requested to rack HPCI AOP Green light on for HPCI AOP -

breaker back in simulate racking in breaker dor zlohs7347a[1]

ROLE PLAY: If requested to make determination if the Rx will remain subcritical under all conditions without boron, after 5 minutes call back as Reactor Engineer and report that the Rx will NOT remain subcritical under all conditions

HL TS-3-17 Rev 0 Page 13 of 60 When Suppression Chamber sprays Break the "A" DWCA header placed in service imf ia02a ROLE PLAY: If dispatched to investigate loss of Orywell Control Air A header, Wait 5 minutes and report no indications of a leak outside of Containment and all valves aligned properly After 4 minutes (but prior to crew Bring in alarm MS Relief Accum trying to ED) Press Low (9-30 win 18) ior an:ov:xa5533d[18] alarm_on Terminate the scenario when the following conditions are satisfied or upon request of instructor:

1) Emergency Depressurization completed

2) Reactor water level restored to 2" to 51" (or recovering)

HLTS-3-17 Rev 0 Page 14 of 60 Scenario Summary:

x.

Starting - 6% power, the crew will lower power to < 5%% by inserting control rods per 3-GOI-100-12A, RCP, and 3-01-85 Turbine sealing steam has already been swapped to aux boiler steam and the crew will swap the operating SJAE and Off-Gas Preheater from nuclear steam to aux boiler steam per 3-GOI-100-12A and 3-01-66 The crew will continue the power reduction and respond to 3A CRD pump trip per 3-AOI-85-3 After the Mode Switch is placed in Mode 2, 3A IRM fails upscale and will cause a Y:z scram and the crew will by-pass the IRM and reset the Y:z scram The crew will commence de-inerting containment per 3-01-76 for personnel entry and inspection at power The H2 02 Analyzer selected for the Drywell will fail requiring swapping the Analyzer selected for Suppression Chamber to the Drywell The only remaining RFP will trip (shortly after low oil level alarm and low bearing oil pressure alarms) and the crew will respond per 3-AOI-3-1 and place RCIC in service per 3-01-71 , but power is still too high for RCIC alone and HPCI aux oil pump will not start, requiring a manual scram Several control rods (8) fail to insert on the scram and will not be able to be inserted.

The rods are clustered together and the Reactor Engineer will determine that the Reactor will NOT remain subcritical under all conditions A Drywell leak will cause level to lower and Drywell pressure to increase and the crew will respond per EOI-1, EOI-2, and C-5 to spray the Suppression Chamber and Drywell before having to terminate and prevent prior to emergency depressurization when level drops to -180".

Only 2 ADS valves will open, requiring opening 3 additional valves (for a total of 5 valves which changes MARF to 230 psig)

HL TS-3-17 Rev 0 Page 15 of 60 XI. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. SRO: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. Emergency Depressurization completed

2. Reactor water level restored to 2" to 51 " (or recovering)

HLTS-3-17 Rev 0 Page 16 of 60 XII. Simulator Event Guide:

Event #1: Continue lowering power per 3-GOI-100-12A Position Expected Actions Time/Comments SRO Directs ATC to continue in 3-GOI-100-12A at step 5.0[32] to get < 5% power ATC Continues to lower Reactor Power per 3-GOI-1 00-12A by inserting control rods PLACE alllRM Range switches on Range 10. (N/A if power is less than Range 10 and indication is between approximately 25 and 75.)

INSERT all operable IRMs or VERIFY full-in.

SELECT IRM on both IRM/RBM recorders.

VERIFY IRM recorder High Alarm setpoint programmed ON with setpoint at 75.

SELECT IRM on alllRM/APRM recorders.

Continues to lower power by inserting control rods per the RCP, shove sheets, and RWM (step 5.0[33])

RANGE IRMs down as necessary to maintain between approximately 25 and 75 using IRM range switches.

When power is < 5% stops lowering power to allow BOP to swap steam loads (step 5.0[33])

HL TS-3-17 Rev 0 Page 17 of 60 XII. Simulator Event Guide:

Event #2: Swap SJAE and Off-Gas Preheaters to Aux Boiler steam Position Expected Actions Time/Comments SRO Directs BOP to swap SJAE and OG preheaters to Aux steam per 3-01-66 section 8.12 BOP CHECK all Precautions and Limitations in Section 3.0 have been reviewed.

CHECK SJAE and/or preheaters are in service using main steam.

CHECK Swapping to Aux Boiler Steam has been directed by Shift Manager or 3-GOI-1 00-12A.

CHECK Auxiliary Boiler(s) in service per 0-01-12 and boiler pressure greater than or equal to 165 psig Directs AUO VERIFY OPEN the SJAE STM SPL Y valve, 3-12-679 (T13.5-H EL 565') locally to open 3-12-679 and verify pressures 170 - 250 psig PLACE both of the following to CLOSE at Panel 3-9-7.

A. SJAE 3A PRESS CONTROLLER, 3-HS-1-150 B. SJAE 3B PRESS CONTROLLER, 3-HS-1-152 Directs AUO locally to VERIFY in NORM SJAE TRAIN PERMISSIVE 3-HS-001-0375.

Directs AUO locally to DEPRESS the open pushbutton for AUX STM TO SJAE A(B) 1ST, 2ND

& 3RD STG, 3-HS-12-3A(5A) for the SJAE to be returned to service, UNTIL the valve is fully open at JB 3525 EI. 586' T12-C

HLTS-3-17 Rev 0 Page 18 of 60 XII. Simulator Event Guide:

Event #2: Swap SJAE and Off-Gas Preheaters to Aux Boiler steam (cont)

Position Expected Actions Time/Comments MONITOR hotwell pressure as indicated on HOTWELL TEMP AND PRESS recorder, 3-XR 2, on Panel 3-9-6 AND VERIFY proper operation of SJAE placed in service.

PLACE the following valves to CLOSE at Panel 3-9-7.

A. STEAM TO SJAE 3A, 3-HS-1-155A B. STEAM to SJAE 3B, 3-HS-1-156A Directs AUO locally to SWAP steam to the preheaters at JB 6305 located in the Turbine Building breezeway: (T13 B-Line EI 586')

HLTS-3-17 Rev 0 Page 19 of 60 XII. Simulator Event Guide:

Event #3: Mode Switch to Start I Hot Standby and 3A CRD Failure Position Expected Actions Time/Comments SRO Directs ATC to continue in 3-GOI-100-12A step 5.0[34])

ATC OBTAIN Unit Supervisor's permission and VERIFY or PLACE REACTOR MODE SWITCH in START

& HOT STANDBY position.

Places Reactor Mode Switch in Start & Hot Standby position SRO NOTIFY Instrument Maintenance to PERFORM OR VERIFY within required frequency the following surveillances: (Required to be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of entering the Mode 2 from Mode 1)

A. 3-SR-3.3.1.1.3(IRMs) (N/A if a condition is reached within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months where IRM operability is not required by Tech Specs.)

B. 3-SR-3.3.1.2.5&6, Source Range Monitor (SRM) Functional Test With Reactor Mode Switch Not In Run Position NOTIFY Instrument Maintenance to PERFORM OR VERIFY within required frequency the following surveillance's:

A. 3-SR-3.3.1.1.13 (APRM-1-4), Average Power Range Monitor Calibration-APRM 4. (N/A if not required.)

B. 3-SR-3.3.1.1.16(APRM 1-4), Average Power Range Monitor Functional Test-APRM-1-4.

(N/A if not required.)

C. 3-SR-3.3.1.1.14(2e), Average Power Range Monitor (APRM) 2-0UT-OF-4 Voter Logic Functional Test.) (N/A if not required)

ATC CONTINUE inserting control rods in accordance with 3-SR-3.1.3.5(A), Control Rod Movement Data Sheets.

HLTS-3-17 Rev 0 Page 20 of 60

XII. Simulator Event Guide:

Event #3: Mode Switch to Start / Hot Standby and 3A CRD Failure (cont)

Position Expected Actions Time/Comments Crew Announces alarm 9-8C window 33 "Motor Tripout" ATC Recognizes 3A CRD pump tripped SRO Directs entry into 3-AOI-85-3, CRD System Failure ATC Performs Immediate Operator actions of 3-AOI 3

[1] IF operating CRD PUMP has TRIPPED AND STANDBY CRD PUMP is AVAILABLE, THEN (Otherwise N/A)

PERFORM the following at Panel 3-9-5:

[1.1] PLACE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, in MAN at minimum setting

HLTS-3-17 Rev 0 Page 21 of 60

XII. Simulator Event Guide:

Event #3: Mode Switch to Start I Hot Standby and 3A CRD Failure (cont)

Position Expected Actions Time/Comments ATC [1.2] START associated standby CRD Pump using one of the following:

CRD PUMP 3B, using 3-HS-85-2A

CRD Pump 3A, using 3-HS-85-1A

[1.3] ADJUST CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, to establish the following conditions:

CRD CLG WTR HDR DP, 3-PDI-85-18A, approximately 20 psid

CRD SYSTEM FLOW CONTROL, 3-FIC 11, between 40 and 65 gpm 65llPm

[1.4] BALANCE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, and PLACE in AUTO or BALANCE

[2] IF operating CRD PUMP has tripped and BACKUP CRD PUMP is NOT available, THEN (Otherwise N/A) N/A

[3] IF Reactor Pressure is LESS THAN 900 PSIG AND ANY ONE of the following conditions exist:

In service CRD Pump tripped and NEITHER CRD Pump can be started, OR

Charging Water Pressure can NOT be restored and maintained above 940 PSIG, THEN PERFORM the following: (Otherwise N/A)

N/A

HL TS-3-17 Rev 0 Page 22 of 60

XII. Simulator Event Guide:

Event #3: Mode Switch to Start I Hot Standby and 3A CRD Failure (cont)

Position Expected Actions Time/Comments ATC Subsequent Actions

[1] IF Reactor Pressure is GREATER THAN OR EQUAL TO 900 PSIG AND

Charging Water Pressure can NOT be restored and maintained above 940 PSIG within 20 minutes, AND

Two or more Scram accumulators inop, and associated control rod NOT fully inserted, THEN PERFORM the following: (Otherwise N/A)

N/A

[2] IF operating CRD Pump has NOT tripped, THEN PERFORM the following:

(REFER TO 3-01-85) (Otherwise N/A) N/A

[3] IF CRD System hydraulic pressure is restored,

SRO THEN RESTORE Control Rod Drive System alignment. REFER TO 3-01-85. (Otherwise N/A)

Refers to 3-01-85 Request investigation of 3A CRD pump failure

HLTS-3-17 Rev 0 Page 23 of 60 XII. Simulator Event Guide:

Event #4: IRM Failure Position Expected Actions Time/Comments ATC Announces alarm 3-XA-55-3-5A window 26 IRM HIGH VERIFY alarm by multiple indications.

VERIFY control rod block.

RANGE OR BYPASS affected channel as desired.

ATC/BOP Announces alarm 3-XA-55-3-5A window 33 IRM CH A, C, E, G HI-HI/INOP and 3-XA-55-3-5B window 1 REACTOR CHANNEL A AUTO SCRAM ATC STOP any reactivity changes.

NOTIFY Reactor Engineer.

SRO Directs bypassing failed IRM per 3-01-92A section 6.1 and Reset % scram and affected systems per 3-01-99 section 6.1 ATC Bypasses IRM Rer per 3-01-92A section 6.1 REVIEW precautions and limitations in Section 3.0

PLACE the appropriate IRM Bypass selector switch to the BYPASS position:

IRM BYPASS, 3-HS-92-7A/S4A CHECK Bypassed light is illuminated.

Resets % scram per 3-01-99 section 6.1 VERIFY Reactor Protection System in prestartup/standby readiness alignment in accordance with Section 4.0 REVIEW Precautions and Limitations in Section 3.0.

VERIFY RPS Bus for tripped channel energized.

CHECK trip signals NOT present.

MOMENTARILY PLACE SCRAM RESET, 3-HS-99-5A/S5, as follows:

A. RESET FIRST B. RESET SECOND C. NORMAL

HLTS-3-17 Rev 0 Page 24 of 60

XII. Simulator Event Guide:

Event #4: IRM Failure (continued)

Position Expected Actions Time/Comments SRO Refers to Tech Spec Table 3.3.1.1-1, TRM Tables 3.3.4-1 and 3.3.5-1 and determines no LCO with IRM bypassed ATC CHECK the following conditions:

A. All eight SCRAM SOLENOID GROUP AlB LOGIC RESET lights illuminated.

B. The following four lights illuminated:

SYSTEM A BACKUP SCRAM VALVE, 3-1 L-99-5A1AB

SYSTEM B BACKUP SCRAM VALVE, 3-IL-99-5A1CD C. Scram Discharge Volume vent and drain valves indicate open.

D. Points SOE033 (Channel A3 manual scram) and SOE035 (Channels A1&A2 Auto Scram) on ICS computer or on the First Out Printer reads "NOT TRIP" for RPS "A".

E. Points SOE034 (Channel B3 manual scram) and SOE036 (Channels B1&B2 Auto Scram) on ICS computer or on the First Out Printer reads "NOT TRIP" for RPS "B".

HLTS-3-17 Rev 0 Page 25 of 60 XII. Simulator Event Guide:

Event #5: De-inert Containment Position Expected Actions Time/Comments SRO Directs BOP to start de-inerting Containment per 3-01-76, section 7.1 BOP Starts de-inerting CTMT per 3-01-76, section 7.1 VERIFY CLOSED the following vlvs (Panel 3-9-3):

DW/SUPPR CHBR N2 MU PRESS CONTROL, using 3-PC-76-14

PRI CTMT N2 MAKEUP OUTBD ISOLATION VLV, using 3-HS-76-17

DRYWELL N2 MAKEUP INBD ISOLATION VLV, using 3-HS-76-18

SUPPR CHBR N2 MAKEUP INBD usin~ 3-HS-76-19 ISOLATION VLV, using PURGE the Drywell and Suppression Chamber.

REFER TO 3-01-64 REVIEW all Precautions and Limitations in Section 3.0

VERIFY all Prestartup/Standby Readiness requirements in Section 4.0 are satisfied.

VERIFY the following initial conditions are satisfied:

H202 analyzers are in service REFER TO 3-01-76.

Drywell vented to less than 0.25 psig.

Reactor Zone Fans in operation with Reactor Zone Supply and Exhaust Fan in fast speed. REFER TO 3-01-30B.

REQUEST Chemistry to obtain a Drywell sample per 3-SI-4.8.B.2-6.

IF sample is within limits of 3-SI-4.8.B.2-6, THEN NOTIFY Shift Manager.

Verifies OW DP compressor already secured Acknowledges DWCA aligned to plant control air

HLTS-3-17 Rev 0 Page 26 of 60

XII.

Position Simulator Event Guide:

Event #5: De-inert Containment (continued)

Expected Actions Time/Comments BOP VERIFY CLOSED the following valves (Panel 3 3):

DRYWELL INBD ISOLATION VLV, 3-FCV-64-31

SUPPR CHBR INBD ISOLATION VLV, 3-FCV-64-34

DRYWELL N2 MAKEUP INBD ISOLATION VLV,3-FCV-76-18

SUPPR CHBR N2 MAKEUP INBD ISOLATION VLV, 3-FCV-76-19

PRI CTMT N2 PURGE OUTBD ISOLATION VLV,3-FCV-76-24

SUPPR CHBR VENT INBD ISOL VALVE, 3-FCV-64-32

SUPPR CHBR VENT OUTBD ISOLATION VLV, 3-FCV-64-33

DW/SUPPR CHBR VENT TO SGT, 3-FCO-64-36 IF the Reactor Mode switch is in RUN, THEN PLACE the following switches in the BYPASS position (Panel 3-9-3):

(not in Run)

PC PURGE DIV I RUN MODE BYPASS, 3-HS-64-24

PC PURGE DIV II RUN MODE BYPASS, 3-HS-64-25

HLTS-3-17 Rev 0 Page 27 of 60

XII.

Position Simulator Event Guide:

Event #5: De-inert Containment (continued)

Expected Actions Time/Comments BOP RECORD start time in Narrative log OPEN the following valves (Panel 3-9-3):

DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-29, using 3-HS-64-29 DO

DRYWELL VENT OUTBD ISOLATION VL V, 3-FCV-64-30, using 3-HS-64-30 MONITOR Drywell Pressure (Panel 3-9-3).

Contacts AUO to START CTMT PURGE FILTER Bldg., EI 621).

FAN using 3-HS-64-131 (Reactor BldjJ.,

OPEN the following valves (Panel 3-9-3):

DW/SUPPR CHBR AIR PURGE ISOL VALVE, 3-FCV-64-17, using 3-HS-64-17

DRYWELL ATM SUPPLY INBD ISOLATION VLV, 3-FCV-64-18, using 3-HS-64-18 DISPATCH personnel to Aux Inst Room to reset GROSS FAILURES on associated RPS and ECCS

ATUs, THEN RESET Control Room annunciators (Panel 3-9-3 and 3-9-5).

PLACE 02 ANALYZER 3A and 3B 02 RANGE SELECT switches, 3-HS-76-72 and 82 in HIGH (Panels 3-9-54 and 55).

HL TS-3-17 Rev 0 Page 28 of 60

XII.

Position Simulator Event Guide:

Event #6: H20 2 Analyzer Failure Expected Actions Time/Comments BOP Announces alarm 3-XA-55-3-7C window 22, DRYWELLISUPPR CHAMBER H202 ANAL YZER FAILURE CHECK Panel 3-9-54 and 3-9-55 for abnormal indicating lights such as low flow, H2 or 02 downscale, pump off, etc. (low flow, H2 or 02 downscale, and pump off may exist if analyzer(s) are in standby)

Notes that the Analyzer selected for the Drywell shows the O2 sample pump tripped / not running and the low flow white light illuminated If attempts to re-start the tripped O2 sample pump, notes that pump failed to start DISPATCH personnel to Panels25-340 and 25-420 or 25-341

SRO Notifies SRO to REFER TO Tech Spec 3.3.3.1, R~quirements Manual Section 3.6.2 Technical Requirements Swaps the operable Analyzer from Suppression Chamber to Drywell Refers to Tech Spec 3.3.3.1 and TRM 3.6.2 and acknowledges that Tech Spec 3.3.3.1 and TRM 3.6.2 do not apply under the current conditions

HLTS-3-17 Rev 0 Page 29 of 60

XII.

Position Simulator Event Guide:

Event #7:

Expected Actions Continue lowering power per 3-GOI-1 00-12A I 3C RFP TRIP Time/Comments SRO Directs ATC to continue in 3-GOI-1 00-12A step 5.0[38]

ATC CONTINUE inserting control rods in accordance with 3-SR-3.1.3.5(A), Control Rod Movement Data Sheets.

MONITOR power reduction on IRMs, keeping them on scale between approximately 25 and 75 using IRM range switches.

If it is desired to close the MSIVs as directed by the Unit Supervisor, Then (Otherwise, N/A.)

Perform Attachment 3 and continue in the procedure as directed by the Unit Supervisor (step 5.0[42])

BOP Notifies SRO of AUO report of oil leak in 3C RFP

room (call from TB AUO)

Announces alarm 3-XA-55-3-6C window 4 RFPT OIL TANK LEVEL ABNORMAL Directs AUO to ADD oil as needed per 3-01-20.

Announces alarm 3-XA-55-3-6C window 26 RFPT BRG OIL PRESS LOW, quickly followed by 3-XA-55-3-6C window 16 RFPT BRG OIL PRESS LOW If not manually secured, announces 3C RFP tripped (15 seconds after second oil pressure low alarm Recognizes 3C RFP trip is still present and, therefore, not available to re-start

HLTS-3-17 Rev 0 Page 30 of 60

XII.

Position Simulator Event Guide:

Event #7:

Expected Actions Continue lowering power per 3-GOI-100-12A / 3C RFP TRIP (continued)

Time/Comments SRO Directs entry into 3-AOI-3-1 Directs placing RCIC per 3-01-71 and or HPCI in service per 3-01-73 to restore / maintain Rx level BOP Places RCIC in service per 3-01-71 section 5.2 NOTIFY Radiation Protection of the impending action to manually start the RCIC System.

RECORD time Radiation Protection notified in the NOMS Narrative Log REVIEW all Precautions and Limitations in Section 3.0.

OBTAIN 3-SR-3.6.2.1.1 to check Suppression Pool level and temperature every 5 min.

ESTABLISH communication with the personnel locally at the RCIC turbine.

ENSURE all unnecessary personnel have exited the general area of the RCIC turbine and rupture discs prior to rolling the RCIC turbine.

ANNOUNCE on the plant PA system, "Unit Three is starting RCIC, all unnecessary personnel stay clear of the NW RX BLDG. QUAD."

HL TS-3-17 Rev 0 Page 31 of 60

XII.

Position Simulator Event Guide:

Event #7:

Expected Actions Continue lowering power per 3-GOI-1 00-12A I 3C RFP TRIP (continued)

Time/Comments BOP OPEN RCIC LUBE OIL COOLING WTR VLV, 3-FCV-71-25.

START RCIC VACUUM PUMP, 3-HS-71-31A.

OPEN RCIC PUMP INJECTION VALVE, 3-FCV-71-39.

OPEN RCIC PUMP MIN FLOW VALVE, 3-FCV 34.

START RCIC Turbine by opening RCIC TURBINE STEAM SUPPLY VLV, 3-FCV-71-8 and OBSERVE the following:

RCIC Turbine speed accelerates above 2100 rpm, on RCIC TURBINE SPEED indicator,3-SI-71-42A

Flow to the RPV stabilizes and is controlled automatically at 600 gpm

RCIC TESTABLE CHECK VLV, 3-FCV 40, DISC POSITION indicates open

RCIC PUMP MIN FLOW VLV, 3-FCV-71-34, is closed when flow is above 120 gpm

RCIC STEAM LINE DR INBD and OUTBD ISOL VLVs, 3-FCV-71-6A and -6B, close REFER TO Section 6.0 to control and monitor RCIC turbine operation.

[place HPCI in service per 3-01-73,

HLTS-3-17 Rev 0 Page 32 of 60

XII.

Position Simulator Event Guide:

Event #8: Reactor SCRAM / ATWS Expected Actions Time/Comments BOP If attempted to places HPCI in service per 3-01-73 section 5.2 NOTIFY Radiation Protection of the impending action to manually start the HPCI System.

RECORD time Radiation Protection notified in the NOMS Narrative Log.

REVIEW Precautions and Limitations in Section 3.0.

OBTAIN 3-SR-3.6.2.1.1 to check Suppression Pool level and temperature every 5 minutes.

REQUEST SGTS placed in operation.

ESTABLISH communication with the AUO locally in the HPCI room.

DEPRESS and HOLD HPCI AUX OIL PUMP, 3-HS-73-47B, START pushbutton (local) for approximately 2 minutes to prime the oil system.

SRO Reports to US that the HPCI aux oil pump failed to start After BOP report about HPCI aux oil pump failure and / or when discovered inadequate high pressure injection systems available to maintain Reactor level, directs manual scram ATC Inserts manual scram - notes that some control rods did not insert on the scram Takes mode switch to shutdown Initiates one channel of ARI Gives scram report (reports power < range 7 on IRM's)

HLTS-3-17 Rev 0 Page 33 of 60

XII.

Position Simulator Event Guide:

Event #8:

Expected Actions Reactor SCRAM / ATWS (continued)

Time/Comments SRO Enters 3-EOI-1 and C5 na Directs initiating 2nd channel of ARI ATC Initiates 2 no na channel of ARI Crew Announces Reactor scram SRO Exits RC/Q and directs OATC to enter 3-AOI-100-1 and to insert control rods with 3-01-85 (8.19)

Verifies Reactor pressure being maintained on bypass valves Enters C-5 and directs ADS inhibited Directs App-8A and App-8E BOP Inhibits ADS

Crew BOP Recognizes and reports Group 2, 3, 6, and 8 isolations if water level decreases below (+) 2" Calls for App-8A and App-8E SRO Directs Rx water level be maintained (+) 2" to

(+) 51" with RCIC per App-5C

HL TS-3-17 Rev 0 Page 34 of 60

XII.

Position Simulator Event Guide:

Event #8:

Expected Actions Reactor SCRAM I ATWS (continued)

Time/Comments BOP Performs 3-EOI Appendix-SC to inject with RCIC IF ..... BOTH of the following exist:

RPV Pressure is at or below SO psig, AND Bypass of RCIC low RPV pressure isolation interlocks is necessary, THEN ... EXECUTE EOI Appendix 16A concurrently with this procedure.

IF ..... BOTH of the following exist:

High temperature exists in the RCIC area, AND SRO directs bypass of RCIC High Temperature Isolation interlocks, THEN ... PERFORM the following:

VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPITHROT VALVE RESET.

VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller in AUTO with setpoint at 600 gpm.

OPEN the following valves:

3-FCV-71-39, RCIC PUMP INJECTION VALVE

3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

3-FCV-71-2S, RCIC LUBE OIL COOLING WTRVLV.

PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START.

HLTS-3-17 Rev 0 Page 35 of 60 XII. Simulator Event Guide:

Event #8: Reactor SCRAM I ATWS (continued)

Position Expected Actions Time/Comments OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbine.

CHECK proper RCIC operation by observing the following:

a. RCIC Turbine speed accelerates above 2100 rpm.

b. RCIC flow to RPV stabilizes and is controlled automatically at 600 gpm.

c. 3-FCV-71-40, RCIC Testable Check Vlv, opens by observing 3-ZI-71-40A, DISC POSITION, red light illuminated.

d. 3-FCV-71-34, RCIC PUMP MIN FLOW VLV, closes as flow rises above 120 gpm.

IF ..... BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN ... VERIFY OPEN 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE.

ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOWICONTROL, controller as necessary to control injection.

Monitor containment parameters

HL TS-3-17 Rev 0 Page 36 of 60 XII. Simulator Event Guide:

Event #8: Reactor SCRAM / ATWS (continued)

Position Expected Actions Time/Comments ATC Insert control rods per 3-01-85 section 8.19 If Removal and Replacement of RPS Scram Solenoid Fuses is desired, Then: N/A If Venting and Repressurizing the Scram Pilot Air Header is desired, Then: N/A If it is desired to Individually Scram Control Rods, Then: (if this section is tried on the 8 rods that will not drive in -the support people needed will encounter obstacles such that they will not be available) N/A If it is desired to Insert Control Rods Using Reactor Manual Control System, then:

VERIFY the reactor scram has been reset. REFER TO 3-AOI-100-1 (scram will not be able to be reset after Drywell pressure> 2.45 - unless the SRO called for App-2 & 1F prior to exiting RC/Q)

IF scram CANNOT be reset, THEN CLOSE CHARGING WATER SHUTOFF, 3-SHV-085-0586 (RB, EL 565, NE Corner).

(RB, DEMAND, Print Rod Position Log, to edit control rod positions.

BYPASS the Rod Worth Minimizer. REFER TO Section 8.17.

HLTS-3-17 Rev 0 Page 37 of 60 XII. Simulator Event Guide:

Event #8: Reactor SCRAM / ATWS (continued)

Position Expected Actions Time/Comments ATC 3-01-85 section 8.17 Manual Bypass of the Rod Worth Minimizer VERIFY the following initial conditions are satisfied:

The Shift Manager/Reactor Engineer has directed the Rod Worth Minimizer to be bypassed.

A second licensed operator is available to verify control rod position.

PLACE RWM SWITCH PANEL, 3-XS-85-9025, in BYPASS.

CHECK the Manual Bypass light is illuminated.

CHECK all other indications on the Rod Worth Minimizer Operator's Panel are extinguished.

CHECK the Blue Rod Out Permit light above 3-HS-85-48 is illuminated.

RESET CONTROL ROD WITHDRAWAL BLOCK

annunciator (3-XA-55-5A, Window 7).

Back to 3-01-85 section 8.19 REFER TO Illustration 4 and DEPRESS the appropriate CRD Rod Select pushbutton on 3-XS-85-40.

CHECK the backlit CRD ROD SELECT pushbutton is brightly illuminated and that the white indicating light on the Full Core Display is illuminated.

HLTS-3-17 Rev 0 Page 38 of 60

XII.

Position Simulator Event Guide:

Event #8: Reactor SCRAM / ATWS (continued)

Expected Actions Time/Comments ATC CONTINUOUSLY INSERT the control rod to Position 00, by holding the CRD CONTROL SWITCH, 3-HS-85-48, in ROD IN or CRD NOTCH OVERRIDE SWITCH, 3-HS-85-47 in EMERG ROD IN.

IF a control rod is difficult to insert, THEN REFER TO Section 8.16.

REPEAT Steps 8.19[4.6] through 8.19[4.8] for each Control Rod to be inserted Reports No rod movement on initial attempt to insert rods 3-01-85 section 8.16 VERIFY the control rod will NOT notch in, in accordance with Section 6.7 or Section 8.19 CHECK CRD SYSTEM FLOW is between 40 gpm and 65 gpm, indicated by 3-FIC-85-11

CHECK CRD DRIVE WTR HDR DP, 3-PDI-85-17A is between 250 psid and 270 psid

HLTS-3-17 Rev 0 Page 39 of 60

XII.

Position Simulator Event Guide:

Event #8:

Expected Actions Reactor SCRAM / ATWS (continued)

Time/Comments ATC IF CRD SYSTEM FLOW or CRD DRIVE WTR HDR DP had to be adjusted, THEN PROCEED to Section 6.7.

If control rod motion is observed, but the CRD fails to notch-in with normal operating drive water pressure, Then: N/A If the control rod problem is believed to be air in the hydraulic system, Then Flush the control rod by placing CRD control switch, 3-HS-85-48, in ROD IN, for several minutes Or until the control rod begins to insert N/A If Manual Insertion of Control Rods by Venting the Over Piston Area is desired, Then: (if this section is tried on the 9 rods that will not drive in -the support people needed will encounter obstacles such that they will not be available) May dispatch operator to

perform this but will not occur.

HL TS-3-17 Rev 0 Page 40 of 60

XII.

Position Simulator Event Guide:

Event #8: Reactor SCRAM / ATWS (continued)

Expected Actions Time/Comments Crew Report increase in Drywell pressure and temperature SRO At 2.45 psig Drywell pressure or 160°F Drywell temperature, re-enters 3-EOI-2 and EOI-1 Directs BOP to place available H2 0 2 system in service Directs BOP to vent containment per App-12 BOP Places H2 0 2 analyzer in service per 3-EOI-2 Place Analyzer isolation bypass keylock switches to bypass Select OW or Supp Chmbr and momentarily pull out select switch handle to start sample pumps Vents Containment per 3-EOI Appendix-12 VERIFY at least one SGTS train in service.

VERIFY CLOSED the following valves (Panel 3 3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV, 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

HLTS-3-17 Rev 0 Page 41 of 60

XII. Simulator Event Guide:

Event #9: Drywell Leak (continued)

Position Expected Actions Time/Comments BOP IF ... While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN . PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.

IF ... While executing this procedure, the desired vent path is lost or can not be established, THEN . PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.

PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3-9-55).

VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

HL TS-3-17 Rev 0 Page 42 of 60 XII. Simulator Event Guide:

Event #9: Drywell Leak (continued)

Position Expected Actions Time/Comments BOP ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

Release rates as determined below:

i. IF ... PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress, THEN . .MAINTAIN release rates below those specified in Attachment 2.

iLiF ... Severe Accident Management

Guidelines are being executed, THEN . .MAINTAIN release rates below those specified by the TSC SAM Team.

iii. IF .. .venting for ANY other reason than items i or ii above, THEN . .MAINTAIN release rates below

Stack release rate of 1.4 x 107 ~Ci/s _ _

AND

0-SI-4.8.8.1.a.1 release fraction of 1.

SRO Determines that Suppression Chamber and Drywell Pressure cannot be maintained < 12 psig and direct the Suppression Chamber sprayed per App-17C

HL TS-3-17 Rev 0 Page 43 of 60 XII. Simulator Event Guide:

Event #9: Drywell Leak (continued)

Position Expected Actions Time/Comments BOP Sprays Suppression Chamber per Appendix-17C (only Loop I available)

1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in this procedure at Step 6.

2. IF .............. Adequate core cooling is assured, OR Directed to spray the Suppression Chamber irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS.

3. IF .............. Directed by SRO to spray the Suppression Chamber using Standby Coolant Supply, THEN ....... CONTINUE in this procedure at Step 7.

4. IF .............. Directed by SRO to spray the Suppression Chamber using Fire Protection, THEN ....... CONTINUE in this procedure at Step 8.

5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

LPCI Initiation signal is NOT present, OR

Directed by SRO, THEN ....... PLACE keylock switch 3-XS 122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121 (129),

RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11)

INBD INJECT VALVE, is OPEN, THEN ....... VERIFY CLOSED 3-FCV-74-52(66),

RHR SYS 1(11) OUTBD INJECT VALVE.

HL TS-3-17 Rev 0 Page 44 of 60

XII.

Position Simulator Event Guide:

Event #9:

Expected Actions Drywell Leak (continued)

Time/Comments BOP e. VERIFY OPERATING the desired RHR System 1(11) pump(s) for Suppression Chamber Spray.

f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBRIPOOL ISOL VL V.

g. OPEN 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.

h. IF ............. RHR System 1(11) is operating ONLY in Suppression Chamber Spray mode, THEN ....... CONTINUE in this procedure at Step 5.k.

i. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

j. RAISE system flow by placing the second RHR System 1(11) pump in service as necessary.

k. MONITOR RHR Pump NPSH using Attachment 2.

I. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

m. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

n. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

HLTS-3-17 Rev 0 Page 45 of 60

XII.

Position Simulator Event Guide:

Event #9:

Expected Actions Drywell Leak (continued)

Time/Comments BOP 6. WHEN ...... EITHER of the following exists:

Before Suppression Pool pressure drops below 0 psig, OR

Directed by SRO to stop Suppression Chamber Sprays, THEN ....... STOP Suppression Chamber Sprays as follows:

a. CLOSE 3-FCV-74-58(72), RHR SYS 1(11)

SUPPR CHBR SPRAY VALVE.

b. VERIFY CLOSED 3-FCV-74-100, RHR SYS 1 U-2 DISCH XTIE

c. IF ............. RHR operation is desired in ANY other mode, THEN ....... EXIT this EOI Appendix.

SRO Directs App-5B (CRD) if all attempts have been exhausted trying to insert the stuck rods

ATC 1. IF ..... Maximum injection flow is NOT required, THEN ... VERIFY CRD aligned as follows:

a. VERIFY at least one CRD pump in service and aligned to Unit 3 CRD system.

b. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, as necessary to obtain flow rate of 65 to 85 gpm.

c. THROTTLE 3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VLV, to maintain 250 to 350 psid drive water header pressure differential.

d. EXIT this procedure.

HLTS-3-17 Rev 0 Page 46 of 60

XII.

Position Simulator Event Guide:

Event #9:

Expected Actions Drywell Leak (continued)

Time/Comments ATC 2. IF ..... BOTH of the following exist:

CRD is NOT required for rod insertion, AND

Maximum injection flow is required, THEN ... LINE UP ALL available CRD pumps to the RPV as follows:

a. IF ..... CRD Pump 3A is available, THEN ... VERIFY RUNNING CRD Pump 3A or 3B.

b. IF ..... CRD Pump 3B is available, THEN ... VERIFY RUNNING CRD Pump 3A or 3B.

Reports 3B CRD pump will Not start and 3-FCV-85-50 will Not open Dispatches personnel to investigate 3B CRD and 3-FCV-85-50 BOP Reports RCIC tripped and will Not reset Dispatches personnel to investigate RCIC loss

SRO When Drywell temperature approaches 280°F or Suppression Chamber pressure exceeds 12 psig, directs the following;

Verify Suppression Pool level is below 18 ft

Verify in safe area of Curve 5

Verify Recirc pumps tripped

Secure Drywell blowers

Spray the Drywell per App-17B

HLTS-3-17 Rev 0 Page 47 of 60

XII. Simulator Event Guide:

Event #9: Drywell Leak (continued)

Position Expected Actions Time/Comments BOP 3-EOI APPENDIX-17B

1. BEFORE Drywell pressure drops below 0 psig, CONTINUE in this procedure at Step 7.

2. IF .............. Adequate core cooling is assured, OR Directed to spray the Drywell irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS.

3. VERIFY Recirc Pumps and Drywell Blowers shutdown.

4. IF .............. Directed by SRO to spray the Drywell using Standby Coolant NIA

5. IF .............. Directed by SRO to spray the Drywell using Fire Protection, NIA

6. INITIATE Drywell Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

OR

LPCI Initiation signal is NOT present,

Directed by SRO, THEN ....... PLACE keylock switch 3-XS 122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

HLTS-3-17 Rev 0 Page 48 of 60 XII. Simulator Event Guide:

Event #9: Drywell Leak (continued)

Position Expected Actions Time/Comments BOP c. MOMENTARILY PLACE 3-XS-74-121(129),

RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11)

LPCIINBD INJECT VALVE, is OPEN, THEN .......

VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11)

LPCI OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired System 1(11)

RHR pump(s) for Drywell Spray.

f. OPEN the following valves:

3-FCV-74-60(74), RHR SYS 1(11) OW SPRAY OUTBD VL V

3-FCV-74-61(75), RHR SYS 1(11) OW SPRAY INBD VLV.

g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

h. IF ............. Additional Drywell Spray flow is necessary, THEN ....... PLACE the second System 1(11) RHR Pump in service.

i. MONITOR RHR Pump NPSH using Attachment 2.

j. VERIFY RHRSW pump supplying desired RHR Heat Exchanger( s) .

HLTS-3-17 Rev 0 Page 49 of 60 XII. Simulator Event Guide:

Event #9: Drywell Leak (continued)

Position Expected Actions Time/Comments BOP k. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV.

I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

Reports drywell pressure and temperature decrease

HLTS-3-1 7 Rev 0 Page 50 of 60

XII.

Position Simulator Event Guide:

Event #10: Drywell Control Air Leak Expected Actions Time/Comments BOP Announces alarm 9-3E window 35 / DRYWELL CONTROL AIR PRESS LOW Refer To 3-AOI-32A-1 Realizes from turnover that plant control air is supplying DWCA and steps to align CAD would not serve any purpose (and is tagged)

SRO Directs AUO / Outside US to verify alignment of Control air to DWCA BOP Announces alarm 9-30 window 18 / MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW Check Drywell Control Air System, if malfunctioning, refer to 3-AOI-32A-1 BOP Continues to monitor RWL decrease

SRO Determines cannot restore/maintain RPV level above -180" Directs to Stop and Prevent ALL injection into the RPV except from RCIC, CRD, and SLC (App-4)

HLTS-3-17 Rev 0 Page 51 of 60

XII.

Position Simulator Event Guide:

Event #10:

Expected Actions Drywell Control Air Leak (continued)

Time/Comments ATC Performs Appendix-4 on pnl 9-5 and 9-6

1. PREVENT injection to RPV from the following systems in any order as required:

f. CONDENSATE and FEEDWATER

1) LOWER RFPT 3A(38)(3C) speed to minimum setting (approximately 600 rpm) using ANY of the following methods on Panel 3-9-5:

Using 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL AND individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in AUTO, OR

Using individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in MANUAL,

OR

Using individual 3-HS-46-8A(9A)(10A),

RFPT 3A(38)(3C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR.

2) CLOSE the following valves 8EFORE RPV pressure drops below 450 psig:

3-FCV-3-19, RFP 3A DISCHARGE VALVE

3-FCV-3-12, RFP 38 DISCHARGE VALVE

3-FCV-3-5, RFP 3C DISCHARGE VALVE

3-LCV-3-53, RFW START-UP LEVEL CONTROL.

3) TRIP RFPTs as necessary to prevent injection by DEPRESSING the following push-buttons:

3-HS-3-125A, RFPT 3A TRIP

3-HS-3-151A, RFPT 38 TRIP

3-HS-3-176A, RFPT 3C TRIP.

HLTS-3-17 Rev 0 Page 52 of 60

XII.

Position Simulator Event Guide:

Event #10:

Expected Actions Drywell Control Air Leak (continued)

Time/Comments BOP Performs Appendix-4 on pnl 9-3

1. PREVENT injection to RPV from the following systems in any order as required:

c. CORE SPRAY NOTE: After receipt of an automatic initiation signal, it is NOT necessary to wait until the pump actually starts before performing the next step.

Following an initiation signal, PLACE ALL Core Spray pump control switches in STOP.

d. LPCI SYSTEM I PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM I pump control switches in STOP.

OR

BEFORE RPV pressure drops below 450 psig, 1)PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL, in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE.

e. LPCI SYSTEM II PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM II pump control switches in STOP.

OR

BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155B, LPCI SYS II OUTBD INJ VL V BYPASS SEL, in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE.

HL TS-3-17 Rev 0 Page 53 of 60

XII.

Position Simulator Event Guide:

Event #10: Drywell Control Air Leak (continued)

Expected Actions Time/Comments SRO Directs opening 6 ADS valves BOP Reports only 2 ADS valves able to be opened SRO Directs opening additional valves until 6 are open (if possible)

BOP Opens additional valves and reports only 5 can be opened SRO Directs no additional injection until MARF is achieved ( 5 valves - 230 psig)

Once MARF pressure is obtained, directs Slowly raising RPV level with Condensate (App-6A), or RHR I (App-6B) and restore level to + 2" to + 51"

ATC Recover level with Condensate, 3-EOI Appendix-6A

1. VERIFY CLOSED the following Feedwater heater return valves:

3-FCV-3-71, HP HTR 3A1 LONG CYCLE TOCNDR

3-FCV-3-72, HP HTR 3B1 LONG CYCLE TO CNDR

3-FCV-3-73, HP HTR 3C1 LONG CYCLE TO CNDR.

2. VERIFY CLOSED the following RFP discharge valves:

3-FCV-3-19, RFP 3A DISCHARGE VALVE

3-FCV-3-12, RFP 3B DISCHARGE VALVE

3-FCV-3-5, RFP 3C DISCHARGE VALVE.

HL TS-3-17 Rev 0 Page 54 of 60

XII. Simulator Event Guide:

Event #10: Drywell Control Air Leak (continued)

Position Expected Actions Time/Comments ATC 3. VERIFY OPEN the following drain cooler inlet valves:

3-FCV-2-72, DRAIN COOLER 3A5 CNDS INLET ISOL VLV

3-FCV-2-84, DRAIN COOLER 385 CNDS INLET ISOL VLV

3-FCV-2-96, DRAIN COOLER 3C5 CNDS INLET ISOL VLV.

4. VERIFY OPEN the following heater outlet valves:

3-FCV-2-124, LP HEATER 3A3 CNDS OUTL ISOL VL V

3-FCV-2-125, LP HEATER 383 CNDS OUTL ISOL VL V

3-FCV-2-126, LP HEATER 3C3 CNDS OUTL ISOL VLV.

5. VERIFY OPEN the following heater isolation valves:

3-FCV-3-38, HP HTR 3A2 FW INLET ISOL VLV 3-FCV-3-31, HP HTR 382 FW INLET ISOL VLV

3-FCV-3-24, HP HTR 3C2 FW INLET ISOL VLV

3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV

3-FCV-3-76, HP HTR 381 FW OUTLET ISOL VLV

3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV.

HL TS-3-17 Rev 0 Page 55 of 60

XII.

Position Simulator Event Guide:

Event #10: Drywell Control Air Leak (continued)

Expected Actions Time/Comments ATC 6. VERIFY OPEN the following RFP suction valves:

3-FCV-2-83, RFP 3A SUCTION VALVE

3-FCV-2-95, RFP 38 SUCTION VALVE

3-FCV-2-108, RFP 3C SUCTION VALVE.

7. VERIFY at least one condensate pump running.

8. VERIFY at least one condensate booster pump running.

9. ADJUST 3-LlC-3-53, RFW START-UP LEVEL CONTROL, to control injection (Panel 3-9-5).

10. VERIFY RFW flow to RPV.

Manually make-up (bypass) to the Hotwell from the CST as needed

HL TS-3-17 Rev 0 Page 56 of 60

XII.

Position Simulator Event Guide:

Event #10:

Expected Actions Drywell Control Air Leak (continued)

Time/Comments BOP Restores Reactor Level +2" to +51" with RHR I per 3-EOI APPENDIX-6B (Loop 1 only)

1. IF .............. Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN ....... PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL in BYPASS.

2. VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VL V

3. VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VLV

4. VERIFY CLOSED the following valves:

3-FCV-74-61, RHR SYS I DW SPRAY INBD VLV

3-FCV-74-60, RHR SYS I DW SPRAY OUTBDVLV

3-FCV-74-57, RHR SYS I SUPPR CHBRIPOOL ISOL VL V

3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE 3-FCV-74-59, RHR SYS I SUPPR POOL CLGITEST VL V

5. VERIFY RHR Pump 3A and/or 3C running.

6. WHEN ...... RPV pressure is below 450 psig, THEN ....... VERIFY OPEN 3-FCV-74-53, RHR SYS I LPCIINBD INJECT VALVE.

HLTS-3-17 Rev 0 Page 57 of 60

XII.

Position Simulator Event Guide:

Event #10:

Expected Actions Drywell Control Air Leak (continued)

Time/Comments BOP 7. IF .............. RPV pressure is below 230 psig, THEN ....... VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE.

8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, as necessary to control injection.

9. MONITOR RHR Pump NPSH using Attachment 1.

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV.

11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

SRO

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV.

12. NOTIFY Chemistry that RHRSW is aligned to in-service RHR heat exchangers.

Directs Drywell Sprays placed back in service when level> TAF (Appendix-17B) (If needed and in the safe area of the Spray Curve)

BOP Places Drywell sprays back in service if directed per Appendix-17B SRO Declares Site Area Emergency 1.1-S-1

HLTS-3-17 Rev 0 Page 58 of 60 XIII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Prevent Auto ADS actuation

2) Terminate and prevent injection prior to Emergency Depressurize

3) Emergency Depressurize when required by EOI's - When level reaches (-) 180"

4) Restore/Recover Reactor water level above top of active fuel (-)162"

r HL TS-3-17 Rev 0 Page 59 of 60 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-17

_9_ Total Malfunctions Inserted: List (4-8)

1) 3A CRD Pump Trip

2) H2 0 2 Analyzer Failure

3) IRM Failure

4) RFP Trip

5) HPCI Aux Oil Pump failure

6) ATWS

7) Drywell Leak

8) OW Control air header break / Failure of ADS valves

9) 3B CRD trip

_4_ Malfunctions that occur after EOI entry: List (1-4)

1) ATWS

2) Drywell Leak

3) OW Control air header break / Failure of ADS valves

4) 3B CRD trip

_4_ Abnormal Events: List (1-3)

1) 3A CRD Pump Trip

2) IRM Failure

3) H2 0 2 Analyzer Failure

4) RFP Trip

_2_ Major Transients: List (1-2)

1) ATWS

2) orywe II leak

_2_ EOI's used: List (1-3)

1) EOI-1

2) EOI-2

_2_ EOI Contingencies used: List (0-3)

1) C-5

2) C-2 Run Time (minutes)

EOI Run Time (minutes): _ % of Scenario Run Time

_4_ Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

3A and 3B RFP's are being tagged for outage work. Loop II RHR is tagged to bridge and meggar their motors, 7 day LCO's for T.S. 3.5.1.A and 3.6.2.3A, 4A, & 5A.

Operations/Maintenance for the Shift:

Continue to lower power with control rods per 3-GOI-1 00-12A step 5.0[32) until < 5% and then stop to place SJAE's and OG pre-heaters on aux boiler steam (Turbine seal steam has already

been swapped to aux boiler steam). The 1M's have completed all SR's for SRM's and IRM's and they have been declared Operable. Then after Mode switch is placed in START & HOT STANDBY, start de-inerting the Drywell (3-01-76 section 7.1 and 3-01-64 section 8.2) and continue lowering power to - 1% and close MSIV's per 3-GOI-1 00-12A Attachment 3 (step 5.0[42]). Maintain Rx power - 1% while Drywell inspection and turbine work is performed.

Control air has been aligned to DWCA and all N~ to Containment is being tagged out.

Unusual Conditions/Problem Areas:

Severe thunderstorm warnings in area for the next 10 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ML092870796

Contents

Text

Title:

References:

Title:

References:

Title:

References:

Title:

References:

Title:

References:

Title:

References:

Navigation menu

ML092870796

Text

Title:

References:

Title:

References:

Title:

References:

Title:

References:

Title:

References:

Title:

References:

Navigation menu

Search