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Initial Exam 2009-301 Final Sim/In-Plant JPMs
	ML100470611
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Site:	Catawba
Issue date:	02/02/2010
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CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09A JPM09 A Pressurize Cold Leg Accumulator 1A CANDIDATE EXAMINER JPM09A JPM09 A Page 1 of 9

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Pressurize Cold Leg Accumulator 1 1A A

Alternate Path:

No Facility JPM #:

CLA-109 KIA Rating(s):

SYS006 A 1.13 (3.5/3.7) Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits associated with operating the ECCS controls including - Accumulator pressure (level, boron concentration).

Task Standard:

Cold Leg Accumulator 1A is pressurized with nitrogen to clear annunciator 1AD-9, E/1.

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator X In-Plant _ __ Perform _~X.>....-

_-,-Xo-- Simulate _ __

References:

OP/1/A162001009 OP/1/A/6200/009 (Cold Leg Accumulator Operation), Enclosure 4.6 rev 073 OP/1/A162001010J OP/1/A/6200/010J (Annunciator Response for 1AD-9,1AD-9, E/1) rev 065DCS Validation Time: 8 min. Time Critical: No

=======================================================================

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: 1/

NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM09A Page 2 of 9

SIMULATOR SETUP SHEET

1. Reset to any 100% power IC set.

2. Reduce pressure in 1A CLA to approximately 600 psig

3. Ensure CLA 1A pressure is below 1AD-9, 1AO-9, E/1 setpoint and that the annunciator is lit.

4. Freeze simulator and write to a snap.

IC SELECTED _ _ _ _ __

SIMULATOR OPERATOR INSTRUCTIONS:

None.

Tools/Equipment/Procedures Needed:

OP/1/A/6200/009 (Cold Leg Accumulator Operation), Enclosure 4.6 revision 073

1. OP/1/A/62001009 JPM09 A Page 3 of 9

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

Reactor power level is at 100%. Cold Leg Accumulator 1A nitrogen overpressure has decreased and annunciator 1AD-9, E/1 ACCUM TANK A HI/LO PRESS is lit.

INITIATING CUES:

Restore CLA 1A pressure to clear annunciator 1AD-9, E/1. The initial conditions for OP/1/A16200/09, OP/1/A/6200109, Encl.

Enc!. 4.6 (Increasing Accumulator Pressure) have been satisfied.

JPM09 A JPM09A Page 4 of 9

START TIME: _ __

STEP 2.1: CRITICAL STEP Open 1NI-47A 1NI-47A (C-Leg Accum N2 Sup Cont Isol).

STANDARD: OPEN pushbutton depressed for 1NI-47A (Cold Leg Accum SAT N2 Supply Containment Isolation). RED "OPEN" light lit on 1MC-11.

COMMENTS: UNSAT NOTE: If N2 inlet temperature decreases to 65°F, accumulator N2 supply isolation valves will auto close. There is no alarm with this condition.

When N2 inlet temperature increased above 66°F, this condition will auto SAT clear.

CAUTION: Pressurization shall be performed on only one accumulator at a time. UNSAT STANDARD: Reads and acknowledges note and caution.

COMMENTS:

STEP 2.2: CRITICAL STEP Position 1CB-1 (located behind control panel 1MC-6, BB-56) to "ON".

STANDARD: Breaker 1CB-1 placed to the "ON" position. Located inside SAT 1MC-6 on right side of instrument rack support column.

UNSAT COMMENTS:

JPM08 A Page 5 of 9

STEP 2.3: CRITICAL STEP Open the corresponding valve to increase pressure in the desired accumulator:

1NI-50 (C-Leg Accum A N2 Supply Isol) SAT STANDARD: OPEN pushbutton depressed for 1NI-50 1NI-50 (Cold Leg Accum A N2 Supply Isol). RED "OPEN" light lit on 1MC-11. Verify UNSAT that 1A Cold Leg Accumulator pressure is increasing.

(1NIP5040, 1NIP5050, on 1MC-11).

COMMENTS STEP 2.4:

If the accumulator N2 supply isolation valve frequently auto closes, ensure SAT the following:

SMXB-F05E (Safety Injection Accumulator Nitrogen Heater) (AB-560, HH-52) is energized.

UNSAT

The thermostat is set at 75°F.

STANDARD: If 1NI-50 cycles closed and reopens, dispatch NLO to check power supply and thermostat setting.

EXAMINER NOTE: If examinee calls calis to dispatch an operator to check power supply for nitrogen heater and thermostat setting, repeat back only what you are told.

COMMENTS JPM08A JPM08 A Page 6 of 9

STEP 2.5: CRITICAL STEP When the accumulator is at the desired pressure, close the appropriate valve as follows:

SAT Depress the "CLS" pushbutton for the appropriate valve:

1NI-50 (C-Leg Accum A N2 Supply Isol)

UNSAT Verify the appropriate valve is closed:

1NI-50 (C-Leg Accum A N2 Supply Isol)

STANDARD: Determines Cold Leg Accumulator 1A N2 overpressure restored within limits by verifying annunciator 1AD-9, E/1 clears. Depress the CLOSE pushbutton for 1NI-50 (C-Leg Accum A N2 Supply Isol).

GREEN "CLSD" light lit on 1MC-11.

COMMENTS STEP 2.6:

If necessary, repeat Steps 2.3 through 2.5 to increase pressure in SAT additional accumulators.

STANDARD: Determines no other accumulators need pressure increased.

UNSAT COMMENTS STEP 2.7:

SAT Position 1CB-1 (located behind control panel 1MC-6, BB-56) to "OFF".

STANDARD: Breaker 1CB-1 placed to "OFF".

UNSAT COMMENTS JPM08 A Page 7 of 9

STEP 2.B:

1NI-47A (C-Leg Accum N2 Sup Cont 1501).

Close 1NI-47A Isol). - SAT 1NI-47A (C-Leg Accum STANDARD: Depress the CLOSE pushbutton for 1NI-47A Isol). GREEN "CLSD" light lit on 1MC-11.

N2 Supply Cont 1501).

- UNSAT COMMENTS This JPM is complete.

TIME STOP: _ __

JPMOB A JPMOBA Page B of 9

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Reactor power level is at 100%. Cold Leg Accumulator 1A nitrogen overpressure has decreased and annunciator 1AD-9, E/1 ACCUM TANK A HI/LO PRESS is lit.

INITIATING CUES:

1AD-9, E/1. The initial conditions for 1A pressure to clear annunciator 1AD-9, Restore CLA 1A OP/11A16200109, OP/1/A/6200/09, Encl. 4.6 (Increasing Accumulator Pressure) have been satisfied.

Duke Energy Procedure No.

Catawba Nuclear Station oP/l/A/6200/009 OPf IfA/6200f009 Cold Leg Accumulator Operation Revision No.

073 Electronic Reference No.

CN005FL7 Continuous Use PERFORMANCE I

- - - - UNCONTROLLEDFORPRmT**********

- - - - UNCONTROLLEDFORPruNT**********

(ISSUED) - PDF Format

OP/ll OP/VAl62001009 Al6200/009 Page 2 of3 Cold Leg Accumulator Operation

1. Purpose To outline the procedure for proper operation of the cold leg accumulators.

2. Limits and Precautions 2.1 When manually operating any motor operated valve, minimize the torque applied to the handwheel.

2.2 After manual operation, maintenance or packing adjustment of any motor operated safety related valve, it shall be cycled electrically to ensure reliable automatic operation.

2.3 Rapidly venting accumulator N2 pressure to containment may present a personnel hazard. If containment is occupied during accumulator venting, an O2 monitor shall be used to verify that oxygen levels remain> 19.6% in the immediate area of the vent. If oxygen levels decrease to::;

to S 19.6%, the venting shall be secured and affected areas of containment cleared.

2.4 When pressurized, accumulator temperature shall be maintained greater gr-eater than 60°F.

2.5 When increasing the pressure in an accumulator, ifN2 inlet inl-et temperature decreases to 65°F, auto closure of the N2 supply isolation valves will occur. When N2 inlet temperature increases above 66°F, this condition will auto clear.

2.6 If flow is initiated through any NC pressur-e pressure boundary check valves, notify Mechanical Systems Engineering to perform PT/1/Al42001001 N (Reactor Coolant System Pressure perfonn PT/1/Al4200/001 Boundary Isolation Valve Leak Rate Test) (SR 3.4.14.1).

2.7 After any volume increase to a cold leg accumulator of~ 75 gallons that is NOT the result of addition from the FWST, notify Chemistry to sample and verify boron concentration within six hours (SR 3.5.1.4).

2.8 Feed and bleed of a CLA shall begin prior to boron concentration decreasing to 25 ppm above the lower limit as specified in the COLR.

2.9 INI-120B (NI Pumps To C-Leg Accum Fill) and 1NI-363 Opening 1NI-120B INI-363 (NI To Cold Leg Accum Fill) will make one NI Pump inoperable due to potential diversion of flow to the NI Test/CLA TestiCLA Fill header. {PIP C-02-00864}

op;1/Al6200/009 OP/l!Al62001009 Page 3 of3 2.10 Operation of an NI Pump adds heated water to the top of the FWST via the pump mini flow. Due to the relatively small flow rates recirculated to the FWST, a stratified miniflow.

layer of hot water will form. Under worst case ambient conditions, NI Pump operation in excess of 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months in a 30 day period could result in this layer being deep enough to be drawn into the ECCS I/ NS pumps suctions during the injection phase of a LOCA. This layer of water could be at a higher temperature than that assumed by the accident analyses. IfNI Pump operation reach 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months in a 30 day period, recirculation with the OP/1/Al62001014 (Refueling Water System) or an NS Pump per FW Pump per OP/1/Al6200/014 Al62001007 (Containment Spray'System)

OP/1/Al62.00/007 Spray System) may be required to mix andlor and/or cool the FWST volume.

3. Procedure Refer to Section 4 (Enclosures).

4. Enclosures 4.1 Aligning the Accumulators for ES Actuation 4.2 Valve Checklist 4.3 Independent Verification Valve Checklist 4.4 Increasing Accumulator Level 4.5 Decreasing Accumulator Level 4.6 Increasing Accumulator Pressure 4.7 Decreasing Accumulator Pressure 4.8 Accumulator Feed and Bleed 4.9 Transfer of CLA Contents 4.10 Operation of Accumulator Discharge Valves 4.11 Increasing Accumulator Level During Reduced NC System Pressure Conditions with the NI System Aligned for Standby Readiness 4.12 Accumulator Feed and Bleed During Reduced NC System Pressure Conditions 4.13 Increasing Accumulator Level During Reduced NC System Pressure Conditions with the NI System Removed from Standby Readiness

Enclosure 4.6 op!l/

OP/l!A/6200/009 Al6200/009 Increasing Accumulator Pressure Page 1 of2

1. Initial Conditions

~ 1.1 Review the Limits and Precautions.

4- 1.2 Verify the GN System is in operation per OP/O/Al6450/008 OP/O/A/6450/008 (Nitrogen System).

~ 1.3 Verify the cold leg accumulators have been filled to the desired levels.

~ 1.4 Obtain key #11 to gain access to the backside of the control boards.

2. Procedure

- - 2.1 lNI-47A (C-Leg Accum N2 Sup Cont 1-s01).

Open 1NI-47A

- - 2.2 Position 1CB-1 (located behind control panel 1CB-1 1MC6, BB-56) to "ON".

panel1MC6, NOTE: IfN2 inlet temperature decreases to 65°F, accumulator N2 supply isolation valves will auto close. There is no alarm associated with this condition. When N2 inlet temperature increased above 66°F, this condition will auto clear.

CAUTION: Pressurization shall be performed on only one accumulator at a time.

2.3 Open the corresponding valve to increase pressure in the desired accumulator:

1NI-50 1NI-SO (C-Leg Accum A N2 Supply Isol)

1NI-61 (C-Leg Accum B N2 Supply Isol)

1NI- n (C-Leg Accum C N2 Supply Isol) 1NI-72

1NI-84 (C-Leg Accum D N2 Supply Isol) 2.4 IF the accumulator N2 supply isolation valve frequently auto closes, ensure the following:

-_. SMXB-F05E (Safety Injection Accumulator Nitrogen Heater) (AB-S60, SMXB-FOSE (AB-560, HH-S2)

HH->52) is energized.

-_. The thermostat is set at 75°F.

Enclosure 4.6 OP/l!A162001009 OP/li Al6200/009 Increasing Accumulator Pressure Page 2 of2 2.5 WHEN the accumulator is at the desired pressure, close the appropriate valve as follows:

2.5.1 Depress the "CLS" pushbutton for the appropriate valve:

1NI-50 (C-Leg Accum A N2 N z Supply Isol)

1NI-61 (C-Leg Accum B N! Supply Isol)

1NI-72 (C-Leg Accum C N2 N z Supply Isol)

1NI-84 (C-Leg Accum D N2 N z Supply Isol) 2.5.2 Verify the appropriate valve is closed:

1NI-SO 1NI-50 (C-Leg Accum A N2 Supply Isol)

1NI-61 (C-Leg Accum B N2 Supply Isol)

1NI-72 (C-Leg Accum C N2 Supply Isol)

1NI-84 INI-84 (C-Leg Accum D N2 N z Supply Isol) 2.6 IF necessary, repeat Steps 2.3 through 2.5 to increase pressure in additional accumulators.

--2.7 Position 1CB-1 (located behind control panel1MC6, BB-56)

BB-S6) to "OFF".

--2.8 Close 1NI-47A 1NI-47 A (C-Leg Accum N2 Sup Cont Isol).

2.9 Do NOT file this enclosure in the Control Copy folder of this proc-edure.

procedure.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 B Align the NS System to Cold Leg Recirculation CANDIDATE EXAMINER JPM09 B Page 1 of 11

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Align the NS System to Cold Leg Recirculation Alternate Path:

YES Facility JPM #:

NS-102 KIA Rating(s):

SYS026 A4.01 (4.5/4.3) Ability to manually operate and/or monitor in the control room: CCS controls.

Task Standard:

NS Pump 1B is in operation with suction aligned to the containment sump and RN flow established to the NS heat exchangers at ~ 4650 gpm per Hx.

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator X In-Plant _ __ Perform _~X,,--

_~X",-- Simulate _ __

References:

EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) Enclosure 2 rev 021 Validation Time: 15 min. Time Critical: No

=======================================================================

Candidate: Time Start: _ __

NAME Time Finish: _ __

Performance Rating: SAT ___ UNSAT _ __ Performance Time _ __

Examiner: _ _ _ _ _ _ _ _ _ _ _ __ 1 NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM09 B Page 2 of 11

SIMULATOR SETUP SHEET

1. Reset to any power IC snap.

2. Insert MAL-NC013A (Cold Leg Leak) set Severity Value = 27.5.

3. Insert VLV-NS010F (NS20A NS Pmp A Suct From RWST Isol Fail To Position) VALUE = 1

4. Insert MAL-NS001B (CONTAINMENT SPRAY NS PUMP 1A FAILURE), VALUE=AUTO

5. Insert OVR-W042D (ARF-1 B CNT AIR RET FAN ON POSITION), VALUE=OFF

6. Insert OVR-W038D (ARF-1A CNT AIR RET FAN ON POSITION), VALUE=OFF

7. Insert OVR-W042C (ARF-1(ARF-1B B CNT AIR RET FAN OFF POSITION), VALUE=ON

8. Insert OVR-W038C (ARF-1A CNT AIR RET FAN OFF POSITION), VALUE=ON

9. Insert LOA-AS007 (AS59 - To Unit 2 SUPPLY), VALUE = 1

10. Run simulator until "FWST LO-LO Level' alarm is received while performing all required actions of EP/E-O, EP/E-1 and EOP/ES-1.3 up to step 6.

11. Freeze and write to a snap.

IC SELECTED _ _ _ _ __

SIMULATOR OPERATOR INSTRUCTIONS:

Do not place simulator in RUN until the candidate signals that he/she is ready to begin.

Tools/Equipment/Procedures Needed:

1. EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation), Enclosure 2, rev 021 JPM09 B Page 3 of 11

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

A LOCA occurred on Unit 1.

Both 80th VX fans failed to operate.

EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) is in progress.

NS Pumps have just been secured per Step 6.

INITIATING CUES:

Perform Enclosure 2 (Aligning NS for Recirculation) of EP/1/A/5000/ES-1.3.

JPM09 B JPM098 Page 4 of 11

START TIME: _ __

STEP 1: CRITICAL STEP Close the following valves SAT

1NS-20A (NS Pump 1 1A A Suct From FWST) -

1NS-38 (NS Pump 18 Suct From FWST)

STANDARD: Determines 1NS-20A will not close. Depresses GREEN - UNSAT pushbuttons

'CLOSE' push buttons for 1NS-38. Verifies GREEN 'CLSD' light lit and RED 'OPEN' light dark.

COMMENTS:

STEP 2:

Verify at least one of the following annunciators - LIT - SAT

1AD-20, 8/3 "CO NT SUMP LEVEL> 3.3ft" OR

"CONT 1AD-21, 8/3 "CO NT SUMP LEVEL> 3.3ft"

- UNSAT STANDARD: Determines both lights are lit.

COMMENTS:

JPM088 Page 5 of 11

STEP 3:

Verify both NS trains - AVAILABLE FOR SERVICE.

- SAT STANDARD: Student may say that A train is available based on ability to align to the FWST and continue to step 4, however step 4b will not be met and the student will transition to Step 6 either

- UNSAT at this time or when step 4b is read.

COMMENTS STEP 3 RNO:

IF NS Train 1B available, THEN GO TO step 6. - SAT STANDARD: Determines 1B is available and goes to step 6 AlER A1ER column.

- UNSAT COMMENTS STEP 6a:

Align NS Train 1B as follows:

- SAT

a. Verify 1NI-184B (ND Pump 1B Cont Sump Suct) - OPEN.

STANDARD: Verifies RED 'OPEN' light lit and GREEN "CLSD' light dark. - UNSAT COMMENTS JPM08 B Page 6 of 11

STEP 6b:

SAT Verify 1NS-3B (NS Pump 1B Suet from FWST) - CLOSED.

STANDARD: Verifies GREEN "CLSD' light lit and RED 'OPEN' light dark UNSAT COMMENTS STEP 6e: CRITICAL STEP Open 1NS-1B (NS Pmp B Suet From Cont Sump).

SAT STANDARD: Depresses RED open pushbutton and verifies RED 'OPEN' light lit and GREEN 'Closed' light dark.

COMMENTS UNSAT STEP 6d:

SAT Ensure the following valves - OPEN:

1NS-1SB (NS Spray Hdr 1B Cont Isol)

1NS-12B 1NS-12B (NS Spray Hdr 1B1B Cont Isol) UNSAT STANDARD: Verifies RED 'OPEN' lights lit and GREEN 'CLOSED' lights dark.

COMMENTS JPM08 B Page 7 of 11

STEP 7:

Verifies containment pressure - HAS EXCEEDED 3 PSIG _SATSAT STANDARD: Determines containment pressure has exceeded 3 PSIG since NS has actuated and Phase B reset lights are dark.

_UNSAT UNSAT COMMENTS STEP 8:

Verify Containment pressure - GREATER THAN 1 PSIG. SAT STANDARD: Verifies containment pressure is > 1 psig using 1NSP5040/5050/5060/5070 (1 MC-11), or 1NCCR5040/5390 (pen 1) or 1MICR5340/5350 (pen 3) or OAC indication. UNSAT COMMENTS STEP 9: CRITICAL STEP Ensure NS pump(s) aligned to an open containment suction valve - ON. SAT STANDARD: Determines GREEN 'OFF' light is lit. Depresses RED 'ON' pushbutton and verifies 1B NS pump starts.

_UNSAT UNSAT EXAMINER NOTE: The 1B NS pump should have auto started, but auto start was blocked.

COMMENTS STEP 10:

Verify all Unit 1 and Unit 2 RN pumps - ON SAT STANDARD: Verifies RED 'ON' Lights lit and GREEN 'OFF' lights dark for all unit 1 and unit 2 RN pumps.

UNSAT COMMENTS JPM08 B Page 8 of 11

CAUTION: Exceeding 4650 GPM RN flow through an NS Hx will cause damage to the Hx tubes. SAT STANDARD: Acknowledges caution.

COMMENTS UNSAT STEP 11a:

Align RN to NS Hx(s) as follows: SAT

a. Open 1 1RN-144A RN-144A (NS Hx 1 1AA Inlet Isol)

STANDARD: Depresses the RED 'OPEN' pushbutton for 1RN-144A 1RN-144A UNSAT COMMENTS STEP 11b: CRITICAL STEP 1RN144A begins to open, THEN throttle open 1 WHEN 1RN144A RN-148A (NS Hx 1RN-148A 1A Otlt Isol) to obtain one of the following: SAT

4500 GPM flow through NS Hx 1A OR

1RN-148A full open UNSAT STANDARD: Begins to throttle open 1RN-148A1RN-148A to obtain 4500 gpm OR 1RN-148A full open. Completed with RN flow to NS Hx less than 4650 gpm. It is critical that at the end of the JPM, flow is :'5. 4650 gpm per NS Hx.

COMMENTS STEP 11c: CRITICAL STEP Open 1RN-225B (NS Hx 1B Inlet Isol) SAT STANDARD: Depresses the RED 'OPEN' pushbutton for 1RN-225B.

COMMENTS UNSAT JPM08 B Page 9 of 11

STEP 11d: CRITICAL STEP WHEN 1RN225B begins to open, THEN throttle open 1RN-229B (NS Hx SAT 1B Otlt Isol) to obtain one of the following:

4500 GPM flow through NS Hx 1A OR UNSAT

1RN-229B full open STANDARD: Begins to throttle open 1RN-229B to obtain 4500 gpm OR 1RN-229B full open. Completed with RN flow to NS Hx less than 4650 gpm.

COMMENTS STEP 11e:

SAT GO TO step 13 STANDARD: Goes to step 13 UNSAT COMMENTS STEP 13:

SAT Verify adequate RN heat sink as follows:

RN System - SUCTION ALIGNED TO LAKE WYLIE

RN essential header temperature at one of the following UNSAT locations - LESS THAN OR EQUAL TO 93°F o 1MC-9 OR o RO Logbook STANDARD: Verifies the RED 'OPEN lights lit and the GREEN 'CLOSED' lights dark for 1RN-1A, 1RN-1 A, 1RN-2B, 1RN-2B, 1RN-5A, 1RN-5A, and 1RN6B 1RN6B Verifies RN essential temp on 1MC-9 < 93°F using 1RNP5000 or 1RNP5010 (1MC-9) (1 MC-9) or request RN temp from RO Logbook.

EXAMINER CUE: If asked, state: "RO Logbook indicates essential header temp is 70°F."

COMMENTS This JPM is complete.

TIME STOP: _ __

JPM08 B Page 10 of 11

I I

I II I

I

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A LOCA occurred on Unit 1.

Both VX fans failed to operate.

EP/1/N5000/ES-1.3 (Transfer to Cold Leg Recirculation) is in progress.

EP/1/A/SOOO/ES-1.3

NS Pumps have just been secured per Step 6.

INITIATING CUES:

Perform Enclosure 2 (Aligning NS for Recirculation) of EP/1/N5000/ES-1.3.

EP/1/A/SOOO/ES-1.3.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 EP/1/Al5000/ES-1.3 21 of 38 Enclosure 2 - Page 1 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. Close the following valves:

1NS-20A (NS Pump 1A 1A Suct Suet From FWST)

1NS-3B NS-38 (NS Pump 18 1B Suct From FWST).

2. Verify at least one of the following Perform the following:

annunciators - LIT:

a. WHEN at least one "CONT. SUMP

_ . 1AD-20, B/38/3 "CONT.

"CO NT. SUMP LEVEL >3.3 fi" annunciator is LIT, LEVEL >3.3 ft" fi" ft" THEN GO TO Step 3.

OR b. Do not continue in this enclosure until at least one annuciator is LIT.

1AD-21, B/3 8/3 "CO NT. SUMP LEVEL >3.3 fi".

ft".

3. Verify both NS trains - AVAILABLE FOR Perform the following:

SERVICE.

a. IF NS Train 1A is available, THEN GO TO Step 5.

b. IF NS Train 18 1B is available, THEN GO TO Step 6.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 EP/1/A15000/ES-1.3 22 of 38 Enclosure 2 - Page 2 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. Align NS as follows:

a. Verify the following valves - OPEN: a. Perform the following:

NI-185A (NO Pump 1A Cont

1NI-18"5A Cant Sump _ 1) IF 1NI-185A closed, THEN GO TO Suct) Step 6.

1NI-184B (NO Pump 18 Cant Cont Sump Suct). _ 2) IF 1NI-184B 1NI-184B closed, THEN GO TO Step 5.

b. Verify 1NS-20A (NS Pump 1A Suct b. GO TO Step 6.

From FWST) - CLOSED.

c. Open 1NS-18A (NS Pmp A Suct Suet From Cant Sump).

Cont

d. Verify 1NS-3B (NS Pump 1B Suct From d. GO TO Step 5.

FWST) - CLOSED.

e. Open 1NS-1 B (NS Pmp B Suct From Cant Sump).

Cont

f. Ensure the following valves - OPEN:

1NS-29A (NS Spray Hdr 1A Cant Cont Isol) 1501)

1NS-32A (NS Spray Hdr 1A Cant Cont Isol) 1501)

1NS-15B NS-1SB (NS Spray Hdr 1B Cant Cont Isol) 1501)

1NS-12B (NS Spray Hdr 1B Cant Cont Isol).

1501).

_ g. GO TO Step 7.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 23 of 38 Enclosure 2 - Page 3 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. Align NS Train 1A as follows:

a. Verify 1 NI-185A (NO Pump 1A Cant a. GO TO Step 6.

Sump Suet)

Suct) - OPEN.

b. Verify 1NS-20A (NS Pump 1A Suct b. GO TO Step 6.

From FWST) - CLOSED.

c. Open 1NS-18A (NS Pmp A Suct From Cant Sump).

d. Ensure the following valves - OPEN:

1NS-29A (NS Spray Hdr 1A Cant Isol)

1NS-32A (NS Spray Hdr 1A Cant 1501).

Isol).

_ e. GO TO Step 7.

6. Align NS Train 1 B as follows:

18

a. Verify 1 NI-184B (NO Pump 1 1NI-184B B Cant 1B a. GO TO Step 5.

Sump Suct) - OPEN.

b. Verify 1NS-3B (NS Pump 1B Suct From b. GO TO Step 5.

FWST) - CLOSED.

c. Open 1NS-1 B (NS Pmp B Suct From Cant Sump).

d. Ensure the following valves - OPEN:

1NS-15B (NS Spray Hdr 1B Cant Isol)

1NS-12B (NS Spray Hdr 1B Cant 1501).

Isol).

7. Verify containment pressure - HAS _ GO TO Step 10.

EXCEEDED 3 PSIG.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A15000/ES-1.3 EP/1/A/SOOO/ES-1.3 24 of 38 Enclosure 2 - Page 4 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Verify containment pressure - GREATER Perform the following:

THAN 1 PSIG.

a. Reset NS.

b. Stop NS pumps.

c. GO TO Step 10.

9. pump(s) aligned to an open Ensure NS pump{s) containment sump suction valve - ON.

10. Verify all Unit 1 and Unit 2 RN pumps - _ GO TO Step 12.

ON.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 25 of 38 Enclosure 2 - Page 5 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Exceeding 4650 GPM RN flow through an NS Hx will cause damage to the Hx tubes.

11. Align RN to NS Hx(s) as follows:

a. Open 1RN-144A (NS Hx 1A Inlet Isol). 1501).

b. WHEN 1RN-144A begins to open, THEN throttle open 1RN-148A (NS Hx 1A Otlt Isol) 1501) to obtain one of the following:

_ . 4500 GPM flow through NS Hx 1A OR

_ . 1RN-148A full open.

c. Open 1RN-2258 RN-225B (NS Hx 18 1B Inlet Isol).

1501).

d. WHEN 1RN-2258 RN-225B begins to open, RN-2298 (NS Hx THEN throttle open 1RN-229B 18 1 1501) to obtain one of the B Otlt Isol) following:

_ . 4500 GPM flow through NS Hx 1 B 18 OR RN-2298 full open.

_ . 1RN-229B

e. GO TO Step 13.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 EP/1/A/SOOO/ES-1.3 26 of 38 Enclosure 2 - Page 6 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Exceeding 4650 GPM RN flow through an NS Hx will cause damage to the Hx tubes.

12. Align RN to NS Hx(s) based on RN and NS pump status as follows:

a. Verify NS Pump 1A - ON. a. Perform the following:

_ 1) IF only one B Train RN pump is on, THEN close 2RN-47A (RN Supply X-Over Isol).

2) IF only B Train RN pumps are on, THEN close one of the following valves:

_ . 2RN-48B (RN Supply X-Over Isol)

OR

_ . 2RN-47A (RN Supply X-Over Isol).

_ 3) Open 1RN-225B RN-22SB (NS Hx 1B Inlet Isol).

4) WHEN 1 RN-225B begins to open, 1RN-22SB THEN throttle open 1RN-229B (NS Hx 1B Otlt Isol) to obtain one of the following:

_

4S00 4500 GPM flow through NS Hx 1B OR

_ . 1RN-229B full open.

_ 5) GO TO Step 13.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A15000/ES-1.3 EP/1/A/5000/ES-1.3 27 of 38 Enclosure 2 - Page 7 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

12. (Continued)

b. Verify NS Pump 18 - ON. b. Perform the following:

_ 1) IF only one A Train RN pump is on, THEN close 2RN-488 (RN Supply X-Over Isol).

2) IF only A Train RN pumps are on, THEN close one of the following valves:

_ . 2RN-47A (RN Supply X-Over Isol)

OR

_ . 2RN-488 (RN Supply X-Over Isol).

_ 3) Open 1RN-144A (NS Hx 1A Inlet Isol).

Iso I).

1RN-144A begins to open,

4) WHEN 1RN-144A THEN throttle open 1RN-148A (NS Hx 1A Otlt Isol) to obtain one of the following:

_ . 4500 GPM flow through NS Hx 1A OR

_ . 1RN-148A full open.

_ 5) GO TO Step 13.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 28 of 38 Enclosure 2 - Page 8 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12.

1..2. (Continued)

c. Verify at least one A Train RN pump - c. Perform the following:

ON.

1) IF both B Train RN pumps are on, THEN close one of the following valves:

_ . 2RN-47A (RN Supply X-Over Isol) 1501)

OR

_ . 2RN-48B (RN Supply X-Over 1501).

Isol).

_ 2) IF only one B Train RN pump is on, THEN close 2RN-47A (RN Supply 1501).

X-Over Isol).

_ 3) Open 1RN-225B (NS Hx 1B Inlet 1501).

Isol).

4) WHEN 1RN-225B 1RN-225B begins to open, THEN throttle open 1RN-229B (NS 1501) to obtain one of the Hx 1B Otlt Isol) following:

_

4500 GPM flow through NS Hx 1B OR

_ . 1RN-229B full open.

_ 5) GO TO Step 13.

CNS TRANSFER TRANSfER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 29 of 38 Enclosure 2 - Page 9 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

12. (Continued)

d. Verify at least one B 8 Train RN pump - d. Perform the following:

ON.

1) IF both A Train RN pumps are on, THEN close one of the following valves:

_ . 2RN-47A (RN Supply X-Over Isol)

OR

_ . 2RN-48B 2RN-488 (RN Supply X-Over Isol).

_ 2) IF only one A Train RN pump is on, THEN close 2RN-488 2RN-48B (RN Supply X-Over Isol).

_ 3) Open 1RN-144A (NS Hx 1A Inlet Isol).

4) WHEN 1RN-144A begins to open, THEN throttle open 1RN-148A (NS Hx 1A Otlt Isol) to obtain one of the following:

_

4500 GPM flow through NS Hx 1A OR

_ . 1RN-148A full open.

_ 5) GO TO Step 13.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A15000/ES-1.3 EP/1/A/5000/ES-1.3 30 of 38 Enclosure 2 - Page 10 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

12. (Continued)

e. Verify RN Pump 1A and 2A - ON. e. Perform the following:

1) IF only one RN pump is on in .each each train, THEN align RN to only one NS Hx as follows:

NS Hx 1A:

_ a) Open 1RN-144A (NS Hx 1A Inlet Isol).

b) WHEN 1 RN-144A begins to 1RN-144A open, THEN throttle open 1RN-148A 1RN-148A (NS Hx 1A 1A Otlt Isol) to obtain one of the following:

_

4500 GPM flow through NS Hx 1A OR

_ . 1RN-148A full open.

_ c) GO TO Step 13.

OR

NSHx1B:

NS Hx 1B:

_ a) Open 1RN-225B (NS Hx 1B Inlet Isol).

b) WHEN 1RN-225B begins to open, THEN throttle open 1RN-229B (NS Hx 1B Otlt Isol) to obtain one of the following:

_

4500 GPM flow through NS Hx 1B OR

_ . 1RN-229B full open. open .

._ c) GO TO Step 13.

(RNO continued on nextn.ext page)

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000IES-1.3 EP/1/A15000/ES-1.3 31 of 38 Enclosure 2 - Page 11 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

12. {Continued)

(Continued)

_ 2) Open 1RN-225B (NS Hx 1B Inlet Isol).

3) WHEN 1RN-225B begins to open, THEN throttle open 1RN-229B (NS 1501) to obtain one of the Hx 1B Otlt Isol) following:

_ .* 4500 GPM flow through NS Hx 1B OR

_ . 1RN-229B full open.

_ 4) GO TO Step 13.

f. 1RN-144A (NS Hx 1A Inlet Isol).

Open 1RN-144A

g. WHEN 1 RN-144A begins to open, 1RN-144A THEN throttle open 1 1RN-148A RN-148A (NS Hx 1A Otlt Isol) to obtain one of the following:

_ .* 4500 GPM flow through NS Hx 1A OR

1RN-148A full open.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 EP/1/N5000/ES-1.3 32 of 38 Enclosure 2 - Page 12 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

13. Verify adequate RN heat sink as follows: Perform the following:

RN System - SUCTION ALIGNED TO -Ensure the following valves - OPEN:

a. Ensure LAKE WYLIE

1RN-3A (RN P/H Pit A IsolIso I From

RN essential header temperatures at one SNSWP) of the following locations - LESS THAN OR EQUAL TO 93°F:

1RN-4B RN-48 (RN P/H Pit B 8 Isol From SNSWP)

1MC-9

1RN-588 RN-58B (RN Hdr B 8 Ret To SNSWP)

OR

1RN-63A (RN Hdr A Ret To SNSWP)

RO Logbook.

1RN-846A (DIG 1A Hx Ret To SNSWP)

1RN-848B RN-8488 (DIG 18 1B Hx Ret To SNSWP)

2RN-846A (DIG 2A Hx Ret To SNSWP)

2RN-848B 2RN-8488 (DIG 28 2B Hx Ret To SNSWP).

(RNO continued on next page)

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/SOOO/ES-1.3 EP/1/A15000/ES-1.3 33 of 38 Enclosure 2 - Page 13 of 13 Revision 21 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

13. (Continued)

b. Ensure the following valves - CLOSED:

1RN-1A{RN 1 RN-1A {RN P/H Pit A Isol From Lake)

1RN-28 (RN P/H Pit A Isol From Lake)

1RN-"5A RN-5A (RN P/H Pit 8 Isol From Lake)

RN-S8 (RN P/H Pit 8 Isol From

1RN-68 Lake)

1RN-538 RN-S38 (Station RN Disch Hdr X-Over)

_ .* 1RN-S4A RN-54A (Station RN Disch Hdr X-Over)

11RN-57A RN-S7A (Station

{Station RN Disch To RL Sys)

1RN-8438 (Station RN Disch To RL Sys)

11RN-847A RN-847A (DIG 1A Hx Ret To Lake)

1RN-8498 (DIG 18 Hx Ret To Lake)

_ .* 2RN-847A (DIG 2A Hx Ret To Lake)

_

2RN-8498 (DIG 28 Hx Ret To Lake).

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 C

~usses per Restore Offsite Power to 6.9 kV Busses AP/07 (Loss of Normal Power)

Enclosure 21 (Black Restart Procedure)

CANDIDATE EXAMINER JPM09 C Page 1 of 11

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Restore Offsite Power to 6.9Kv per AP/O?

AP/07 (Loss of Normal Power) Enclosure 21 (Black Restart Procedure)

Alternate Path:

No Facility JPM #:

BANK KiA Rating(s):

EA 1.07 (4.3/4.5) Ability to operate and monitor the following as they apply to a Station EPE055 EA1.0?

Blackout - Restoration of power from offsite.

Task Standard:

Power has been restored to three 6.9 KV busses from the yellow buss via B train.

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator X In-Plant _ __ Perform _-,-X~

_~X",-- Simulate _ __

References:

AP/1/A/5500/007 AP/1/A/55001007 (Loss of Normal Power) Enclosure 21 (Black Start Procedure) rev 057 Validation Time: 18 min. Time Critical: No

=======================================================================

Candidate: Time Start: _ __

NAME Time Finish: _ __

Performance

.Performance Rating: SAT _____ _ UNSAT _ __ Performance Time - _- _- _

Examiner: _ _ _ _ _ _ _ _ _ _ __

~N~A~M~E~---------

NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM09 C Page 2 of 11

SIMULATOR SETUP SHEET

1. Reset to any 100% power IC set.

2. Place simulator in RUN.

3. Trip all Unit Tie PCBs.

4. Ensure turbine trips.

5. Perform appropriate actions of E-O and ES-0.1.

AP/1/A/55001007.

6. Perform actions of AP/1/A/5500/007.

7. Perform actions of Enclosure 21 through step 12.

8. Allow simulator to run until the plant is stable.

9. Freeze, and write to a snap.

IC SELECTED _ _ _ _ __

SIMULATOR OPERATOR INSTRUCTIONS:

None.

Tools/Equipment/Procedures Needed:

1. AP/1/A/5500/07 AP/1/A/5500107 (Loss of Normal Power) Enclosure 21 (Black Start Procedure) rev 057 JPM09 C*C Page 3 of 11

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

Both units experienced a loss of offsite power due to a Loss of Grid and AP/11A155001007 AP/1/A155001007 (Loss of Normal Power) is in progress.

The TCC has reported that the Yellow Bus is energized and can be used on a limited basis to re-energize plant equipment.

AP/1 I Al55001007 Enclosure 21 has been completed through AP/11A155001007 throug h step 12.

INITIATING CUES:

You are to restore power to the Unit 1 6.9 KV Busses per Enclosure 21 (Black Start Procedure) of AP/11A15500107 AP/1/A15500107 (Loss of Normal Power) starting at step 13.

JPM09 C Page 4 of 11

START TIME: _ __

NOTE Zone A or B lockout will occur if at least one main transformer cooling circuit is not restored within 15 minutes of re-energizing the main transformer.

STEP 13: Energize A train as follows:

a. Contact TCC for permission to close PCB 18.

SAT STANDARD: Calls TCC and requests permission.

INSTRUCTOR CUE: "You have permission to close PCB 18."

UNSAT EXAMINER NOTE: If the red phone is used, it will contact the SOC and the cue provided by the booth will be "This is the SOC; you need to contact the TCC at extension 3307."

COMMENTS:

STEP 13: CRITICAL STEP

b. WHEN permission is granted, THEN close PCB 18.

STANDARD: Depresses the CLOSE pushbutton for PCB 18 and notes SAT that the PCB 18 closes.

UNSAT COMMENTS:

STEP 13:

c. Do not continue until one of the following PCBs is closed: SAT

PCB18 OR

PCB 15.

UNSAT STANDARD: Determines PCB 18 is closed.

COMMENTS JPM08 C Page 5 of 11

NOTE:

Desired loading rate is 1-2 MW increments.

Total load per unit may be initially limited to approximately 11 MWs.

STEP 14: IF "TRANSF 1A" ,energized, energized, THEN perform the following:

STANDARD: Due to previous steps and plant condition should determine SAT Transformer 1A is NOT energized and continue to next step.

COMMENTS UNSAT STEP 15: IF "TRANSF 1B" energized, THEN perform the following: CRITICAL

a. Energize 1TO TD as follows: STEP

1) Place "7KV BUS 1TO TD MODE SEL" switch in "MAN B&

B & TIE". SAT STANDARD: Place ITO lTD switch to Man B and tie.

UNSAT COMMENTS STEP 15a: 2) Close "7KV 1TD FDRFOR FRM 1T1B". CRITICAL STEP STANDARD: Closes "7KV 1TD TO FDR FOR FRM 1T1 B" SAT COMMENTS UNSAT STEP 15a: 3) Verify "7KV BUS 1TD TIE BKR" - CLOSED.

STANDARD: Verifies tie breaker closed on MC-11 SAT COMMENTS UNSAT JPM08 C Page 6 of 11

STEP 15: b. Energize 1TC as follows:

1) Verify with TCC that additional load can be accepted prior to energizing 6.9 KV bus. SAT STANDARD: Calls TCC and requests permission.

INSTRUCTOR CUE: "Additional load can be accepted at this time." UNSAT EXAMINER NOTE: If the red phone is used, it will contact the SOC and the cue provided by the booth will be "This is the SOC; you need to contact the TCC at extension 3307."

COMMENTS STEP 15b: 2) Place "7KV BUS 1TC MODE SEL" switch in "MAN B & & TIE". CRITICAL STEP STANDARD: Places 1TC in Man B and Tie position.

SAT COMMENTS UNSAT STEP 15b: 3) Close "7KV 1TC FDRFOR FRM 1T2B". CRITICAL STEP STANDARD: Closes "7KV 1TC FOR FDR FRM 1T2B" SAT COMMENTS UNSAT STEP 15b: 4) Verify "7KV BUS 1TC TIE BKR" - CLOSED.

STANDARD: Determines breaker is closed. SAT COMMENTS UNSAT JPM08 C Page 7 of 11

STEP 15: c. Verify 1AD-11 F/2 "TRANSFORMER 1B FORCED COOLING REDUCTION" - DARK.

SAT STANDARD: Determines the annunciator dark UNSAT COMMENTS STEP 15: d. Energize 1TB as follows:

1) Verify with TCC that additional load can be accepted prior to energizing 6.9 KV bus SAT STANDARD: Calls TCC and requests permission.

INSTRUCTOR CUE: "Additional load can be accepted at this time."

UNSAT EXAMINER NOTE: If the red phone is used, it will contact the SOC and the cue provided by the booth will be "This is the SOC; you need to contact the TCC at extension 3307."

COMMENTS STEP 15d: 2) Place "7KV BUS 1TB MODE SEL" switch in "MAN B & & TIE". CRITICAL STEP STANDARD: Places 1TB1TB in Man B and Tie SAT COMMENTS UNSAT STEP 15d: 3) Close "7KV 1TB FDRFOR FRM 1T1B". CRITICAL STEP STANDARD: Closes "7KV 1TB 1TB FDR FOR FRM 1T1B" 1T1 B" SAT COMMENTS UNSAT JPM08 C Page 8 of 11

STEP 15d: 4) Verify "7KV BUS 1TB TIE BKR" - CLOSED.

STANDARD: Determines breaker is closed. - SAT COMMENTS

- UNSAT STEP 15: e. Energize 1TA as follows:

1) Verify with TCC that additional load can be accepted prior to energizing 6.9 KV bus. - SAT STANDARD: Calls TCC and requests permission.

INSTRUCTOR CUE: "No additional loading should be attempted at - UNSAT this time."

EXAMINER NOTE: If the red phone is used, it will contact the SOC and the cue provided by the booth will be "This is the SOC; you need to contact the TCC at extension 3307."

COMMENTS STEP 15e RNO: 1) Do not energize 1 1TA TA until additional load can be accepted.

- SAT STANDARD: Does NOT energize 1 1TA.

TA.

COMMENTS - UNSAT STEP 15: f. Verify all 6.9 KV busses - ENERGIZED.

STANDARD: Determines "A" 6.9 KV is NOT energized and goes to RNO SAT COMMENTS

- UNSAT JPM08 C Page 9 of 11

STEP 15f RNO: Perform the following:

1) IF waiting on TCC approval to energize additional 6.9 KV busses, THEN RETURN TO Step 15 and energize busses as TCC allows. SAT STANDARD: Returns to Step 15.

EXAMINER CUE: "Another Operator will complete the procedure." - UNSAT COMMENTS This JPM is complete.

TIME STOP: _ __

JPM08 C Page 10 of 11

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Both units experienced a loss of offsite power due to a Loss of Grid and AP/1/A155001007 AP/1/A/55001007 (Loss of Normal Power) is in progress.

The TCC has reported that the Yellow Bus is energized and can by used on a limited basis to re-energize plant equipment.

AP/1/A155001007 Enclosure 21 has been completed through step 12.

AP/1/A/55001007 INITIATING CUES:

You are to restore power to the Unit 1 6.9 KV Busses per Enclosure 21 (Black Start Procedure) of AP/1/A/5500107 AP/1/A15500107 (Loss of Normal Power) starting at step 13.

CNS LOSS OF NORMAL POWER PAGE NO.

I Al55001007 AP/1/A/55001007 AP/1 125 of 154 Enclosure 21 - Page 1 of 12 Revision 57 Black Start Procedure ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. Ensure the following PCBs - OPEN:

J...

~. PCB 14

~. PCB 15

t.

~. PCB 17

-;r..

-;r. PCB 18.

2. Place the following pump switches in "OFF":

~. All hotwell pumps

..:1'

~.. All condensate booster pumps.

3. Depress OFF on the following equipment:

J.

d-. KR Pump A J.

1-. KR Pump B J. KR Pump C.

L 4. Dispatch operator to ensure breakers for all motor loads on all de-energized 6.9 KV busses open. REFER TO Enclosure 22 (Load Shed of 6.9 KV Busses).

~5. Dispatch operator to align 600 volt load centers for black start. REFER TO Enclosure 25 (600 Volt Load Center Black Start Alignment).

Ensure PZR HTR GROUP 1C - OFF.

.:J7.

.::/7. Place PZR HTR GROUP 1D in "MAN" and "OFF".

i8.

~8. Shutdown the rod control system.

REFER TO OP/1/Al6150/008 (Rod Control).

eNS CNS LOSS OF NORMAL POWER PAGE NO.

AP/1/A155001007 AP/1/A/5500/007 126 of 154 Enclosure 21 - Page 2 of 12 Revision 57 Black Start Procedure ACTION/EXPECTED RESPONSE NOT OBTAINED RESPONSE NDT The Tee TCC black start procedure energizes plant auxiliaries via A Train Main Power from the Yellow Bus for both units.

1- 9. Verify with TCC - YELLOW BUS ENERGIZED.

Do not continue until the Yellow Bus energized.

J.

~ 10. Ensure MOD 1A - CLOSED.

11. Do not continue until the following conditions are met:

~. Rod control system is shutdown

~. Enclosure 22 (Load Shed of 6.9 KV Busses) is complete

~. Enclosure 25 (600 Volt Load Center Black Start Alignment) is complete.

J..

-I 12. Coordinate energizing plant loads with Unit 2 to prevent over loading the grid.

CNS LOSS OF NORMAL POWER PAGE NO.

AP/11Al5500/007 AP/1/ Al55001007 127 of 154 Enclosure 21 - Page 3 of 12 Revision 57 Black Start Procedure ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Zone A or B lockout will occur if at least one main transformer cooling circuit is not restored within 15 minutes of re-energizing the main transformer.

13. Energize A train as follows:

a. Contact TCC for permission to close PCB 18.

b. WHEN permission granted, THEN b. IF PCB 18 cannot be closed, THEN close PCB 18. perform the following:

_ 1) Contact TCC for permission to energize Unit 1B train from the Yellow Bus.

2) WHEN permission granted, THEN perform the following:

_ a) Ensure MOD 1 1B B - CLOSED.

_ b) Ensure PCB 14 - OPEN.

_ c) Close PCB 15.

c. Do not continue until one of the following PCBs is closed:

PCB 18 OR

PCB 15.

CNS LOSS OF NORMAL POWER PAGE NO.

AP/1/N5500/007 128 of 154 Enclosure 21 - Page 4 of 12 Revision 57 Black Start Procedure ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

Desired loading rate is 1-2 MW increments .

Total load per unit may be initially limited to approximately 11 MWs.

14. IF "TRANSF 1A" energized, THEN perform the following:

a. Energize 1TD HD as follows:

_ 1) Place "7KV BUS HD MODE SEL" switch in "MAN A & & TIE".

_ 2) Close "7KV 1TD HD FDR FRM 1T1A".

_ 3) Verify "7KV BUS HD TIE BKR" -

CLOSED.

b. Energize 1TC HC as follows:

_ 1) Verify with TCC that additional load _ 1) Do not energize 1 HCTC until additional can be accepted prior to energizing load can be accepted.

6.9 KV bus.

_ 2) Place "7KV BUS HC MODE SEL" switch in "MAN A & TIE".

_ 3) Close "7KV 1TC HC 'FDR FRM 1T1A".

_ 4) Verify "7KV BUS 1 HCTC TIE BKR"-

BKR" -

CLOSED.

c. Verify 1AD-11 C/2 "TRANSFORMER c. Restore transformer cooling. REFER 1A FORCED COOLING REDUCTION" REDUCTION"-- TO OP/1/N6350/005 (Alternate AC DARK. Power Sources).

CNS LOSS OF NORMAL POWER PAGE NO.

AP/1/N5500/007 AP/1/A/5500/007 129 of 154 Enclosure 21 - Page 5 of 12 Revision 57 Black Start Procedure ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

14. (Continued)

{Continued)

d. Energize HB as follows:

_ 1) Verify with TCC that additional load _ 1) Do not energize 1TB until additional can be accepted prior to energizing load can be accepted.

6.9 KV bus.

_ 2) Place "7KV BUS 1TB MODE SEL" switch in "MAN A && TIE".

_ 3) Close "7KV HB FOR FDR FRM 1T2A".

_ 4) Verify "7KV BUS 1TB TIE BKR"-

CLOSED.

e. Energize 1T A as follows:

_ 1) Verify with TCC that additional load _ 1) Do not energize 1TA until additional can be accepted prior to energizing load can be accepted.

6.9 KV bus.

_ 2) Place "7KV BUS 1 TA MODE SEL" HA switch in "MAN A && TIE".

_ 3) Close "7KV HA FOR FDR FRM 1T2A".

_ 4) Verify "7KV BUS 1TA TIE BKR"-

CLOSED.

f. Verify all 6.9 KV busses - ENERGIZED. f. Perform the following:

_ 1) IF waiting on TCC approval to energize additional 6.9 KV busses, THEN RETURN TO Step 14 and energize busses as TCC allows.

_ 2) IF all available 6.9 KV busses are energized, THEN GO TO Step 16.

CNS LOSS OF NORMAL POWER PAGE NO.

AP/1/AJ55001007 AP/1/N5500/007 130 of 154 Enclosure 21 - Page 6 of 12 Revision 57 Black Start Procedure ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

15. IF "TRANSF 1B" energized, THEN perform the following:

a. Energize 1TD HD as follows:

_ 1) 1} Place "7KV BUS 1TD HD MODE SEL" switch in "MAN B & TIE".

_ 2} HD FDR FRM 1

2) Close "7KV 1TD T1 B".

1T1B".

_ 3) 3} Verify "7KV BUS 1TDHD TIE BKR"-

BKR" -

CLOSED.

b. Energize 1TC 1TC as follows:

_ 1) 1} Verify with TCC that additional load _ 1) Do not energize 1 1} TC until additional 1TC can be accepted prior to energizing load can be accepted.

6.9 KV bus.

_ 2) Place "7KV BUS 1TC 2} HC MODE SEL" switch in "MAN B & TIE".

_ 3) HC FDR FRM 1T2B".

3} Close "7KV 1TC

_ 4) Verify "7KV BUS 1TC 4} HC TIE BKR"-

CLOSED.

c. Verify 1AD-11 F/2 "TRANSFORMER 1B c. Restore transformer cooling. REFER FORCED COOLING REDUCTION" - TO OP/1/AJ63501005 OP/1/N6350/005 (Alternate AC DARK. Power Sources).

d. Energize 1TB as follows:

_ 1) 1} Verify with TCC that additional load _ 1} Do not energize 1TB until additional 1) can be accepted prior to energizing load can be accepted.

6.9 KV bus.

_ 2) Place "7KV BUS 1TB 2} HB MODE SEL" switch in "MAN B & TIE".

_ 3) Close "7KV 1TB 3} HB FDR FRM 1T1 B".

1T1B".

_ 4) 4} Verify "7KV BUS 1TBHB TIE BKR"-

CLOSED.

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15. (Continued)

e. Energize 1TA1T A as follows:

_ 1) Verify with TCC that additional load _ 1) Do not energize 1TA until additional can be accepted prior to energizing load can be accepted.

6.9 KV bus.

_ 2) Place "7KV BUS 1TA n A MODE SEL" switch in "MAN B & TIE".

_ 3) Close "7KV 1TAnA FDR FRM 1T2B".

n2B".

_ 4) Verify "7KV BUS 1TA nA TIE BKR"-

CLOSED.

f. Verify all 6.9 KV busses - ENERGIZED. f. Perform the following:

_ 1) IF waiting on TCC approval to energize additional 6.9 KV busses, THEN RETURN TO Step 15 and energize busses as TCC allows.

_ 2) IF all available 6.9 KV busses are energized, THEN GO TO Step 16.

16. Re-energize the shared 600 volt load centers that were isolated by Enclosure 25 (600 Volt Load Center Black Start Alignment) as follows:

a. Verify with TCC that additional load can a. Perform the following:

be accepted prior to energizing 600 volt load centers. _ 1) WHEN additional load can be accepted, THEN perform Step 16.

_ 2) GO TO Step 17.

b. Energize 1SLXD as follows:

_ 1) Verify 1TD nD - ENERGIZED. _ 1) GO TO Step 16.c.

_ 2) Close 1SLXD-4B (Load Center 1SLXD Incoming Breaker).

CNS LOSS OF NORMAL POWER PAGE NO.

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16. (Continued)

c. Energize 1SLXC as follows:

_ 1) Verify 1TC - ENERGIZED. _ 1) GO TO Step 16.d.

_ 2) Verify with TCC that additional load 2) Perform the following:

can be accepted prior to energizing 600 volt load center. _ a) WHEN additional load can be accepted, THEN perform Step 16.

_ b) GO TO Step 17.

_ 3) Close 1SLXC-4B (Load Center 1SLXC Normal Incoming Breaker).

d. Energize 1SLXB as follows:

_ 1) Verify 1TB - ENERGIZED. _ 1) GO TO Step 16.e.

_ 2) Verify with TCC that additional load 2) Perform the following:

can be accepted prior to energizing 600 volt load center. _ a) WHEN additional load can be accepted, THEN perform Step 16.

_ b) GO TO Step 17.

_ 3) Close 1SLXB-4B (Load Center 1SLXB Incoming Breaker).

e. Energize 1SLXG as follows:

_ 1) Verify 1TA - ENERGIZED. _ 1) GO TO Step 16.f.

_ 2) Verify with TCC that additional load 2) Perform the following:

can be accepted prior to energizing 600 volt load center. _ a) WHEN additional load can be accepted, THEN perform Step 16.

_ b) GO TO Step 17.

_ 1SLXG-4B (Load Center

3) Close 1SLXG-4B 1SLXG 1SLXG Incoming Breaker).

CNS LOSS OF NORMAL POWER PAGE NO.

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16. (Continued)

f. Energize 1SLXA as follows:

_ 1TA - ENERGIZED.

1) Verify 1TA- _ 1) GO TO Step 17.

_ 2) Verify with TCC that additional load 2) Perform the following:

can be accepted prior to energizing 600 volt load center. _ a) WHEN additional load can be accepted, THEN perform Step 16.

_ b) GO TO Step 17.

_ 3) Close 1SLXA-4B 1SLXA-4B (Load Center 1SLXA Incoming Breaker).

17. Ensure the following battery chargers energized as follows:

WHEN 1TB is energized, THEN ensure Switchyard battery chargers energized.

REFER TO OP/0/B/63501015 OP/0/B/6350/015 (230 KV Switchyard 125 VDC Power System) .

WHEN 1TC is energized, THEN ensure the following:

Aux Control Power battery chargers energized. REFER TO OP/1/B/63501009 OP/1/B/6350/009 (125 VDC 2401120 240/120 VAC Auxiliary Control Power System)

250 VDC battery chargers energized.

REFER TO OP/0/B/63501007 OP/0/B/6350/007 (250 VDC Auxiliary Power System).

18. Contact Chemistry to ensure YM is available for makeup to the UST.

CNS LOSS OF NORMAL POWER PAGE NO.

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19. IF AT ANY TIME the TCC requests additional load to stabilize the grid, THEN the following can be performed to provide rapid load to the grid:

a. Energize 1HTA as follows:

_ Verify 2HTA - DE-ENERGIZED.

1) Verify2HTA- 1)

1) IF 1HTA to be energized from Unit 2, THEN perform the following:

_ a) REFER TO OP/1/A16350/005 OP/1/N6350/005 (Alternate AC Power Sources).

_ b) WHEN power available to cooling tower fans, THEN start fans as needed to stabilize the grid.

_ c) GO TO Step 20.

_ 2) Place 1HT HTAJ2HTA Al2HTA MODE SELECT switch (2MC-11) in - MANUAL.

_ 1HTA-1 (Inc Fdr From Xfmr

3) Close 1HTA-1 1 ATE).

1ATE).

_ 4) Close 1HTA-3HTA-3 (600V Xfmr Xfm r 1&2 TXJ Fdr).

_ 5) Ensure relay targets on front of HTA Switchgear - RESET.

1HTA

b. Start 1 A cooling tower fans as needed 1A to stabilize the grid. REFER TO OP/1/B/6400/001A OP/1/S/6400/001A (Condenser Circulating Water System).

c. Start 2A cooling tower fans as needed to stabilize the grid. REFER TO o P/2/S/6400/00 1A (Condenser OP/2IB/6400/001A Circulating Water System).

CNS LOSS OF NORMAL POWER PAGE NO.

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19. (Continued)

d. IF desired to align 1TXL and 2TXL from Unit 1, THEN perform the following:

_ 1) Close 1HTA-4 (600 V Xfmr 1&2 TXL Fdr).

_ 2) Verify 2HTA-1 (600 V Xfmr 1&2 TXL Fdr) - OPEN.

e. Start 1C cooling tower fans as needed to stabilize the grid. REFER TO OP/1/B/64001001A OP/1 IB/6400/001 A (Condenser Circulating Water System).

f. Start 2C cooling tower fans as needed to stabilize the grid. REFER TO o P/2/B/6400100 1A (Condenser OP/2/B/6400/001A Circulating Water System).

_ g. IF desired to align 2HTA to Unit 1, THEN REFER TO OP/21A16350/005 OP/21A163501005 (Alternate AC Power Sources).

h. Place 1 HTAl2HTA MODE SELECT 1HTAl2HTA switch (2MC-11) in - AUTO.

20. Verify with TCC that additional Do not continue until additional load can equipment can be energized. be accepted.

21. Restore Turbine Building Ventilation.

REFER TO OP/1/B/6450/016 (Turbine Building Ventilation Systems).

CNS LOSS OF NORMAL POWER PAGE NO.

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22. Coordinate with Unit 2 to restore the following systems to normal operation:

a. RL system. REFER TO OP/O/B/64001003 (Low Pressure Service Water System).

b. KR system. REFER TO OP/O/B/64001004 (Recirculated Cooling Water System)

c. VI system. REFER TO OP/OIAf64501005 OP/O/Al64501005 (Instrument Air System).

d. WHEN the RL, KR and VI systems are operating as desired, THEN GO TO Step 23.

e. Do not continue.

23. Verify with TCC that additional Do not continue until additional load can equipment can be energized. be accepted.

24. Coordinate with Unit 2 to restore the following systems to normal:

Restore proper NF System operation.

REFER TO OP/OIAl62001008 (Ice System) .

Condenser Refrigeration System).

Restore cooling to OAC computer room.

REFER TO OP/O/B/64501014 (Computer Room Ventilation System).

25. RETURN TO step in effect.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 D Verify Adequate Shutdown Margin Following a Reactor Trip CANDIDATE EXAMINER JPM09 D Page 1 of 15

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Verify Adequate Shutdown Margin Following a Reactor Trip Alternate Path:

YES Facility JPM #:

NEW KIA Rating(s):

EPE007 EA 1.09 (3.2/3.3) Ability to operate and/or monitor the following as they apply to a reactor trip - CVCS.

Task Standard:

Initiates boration based on lowest Tcold @ 30 gallons for each degree less than limit of Rod Book section 2.6. (for EOl snap 450EFPD this is 529°F)

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator X In-Plant _

__ _ _ Perform _~X.!.....-

X Simulate ___ _ _

References:

EP/1/A/5000/ES-0.1 (Reactor Trip Response) Revision 030DCS Validation Time: 10 min. Time Critical: No

=======================================================================

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: I 1

NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM09 D Page 2 of 15

SIMULATOR SETUP SHEET

1. Reset to any 100% IC set.

2. Insert EVENT 1 - x1 Oi1160 x10i1160

3. Insert EVENT 2 - x10i218b

4. Insert MAL-SM002B (S/G PORV SV13 FAILURE), VALUE=58)

5. Insert VLV-NV044F (NV238A BORIC ACID BLEND FLOW CNTRL FAIL TO POSITION),

VALUE=0.8, EVENT 1

6. Insert VLV-NV044F (NV238A BORIC ACID BLEND FLOW CNTRL FAIL TO POSITION),

VALUE=0.8, EVENT 2

7. Insert OVR-SG047A (1SVML013 S/G 1B PORV - MAN CTRL LIGHTS GREEN LT), VALUE=ON (1 SVML013 S/G 1

8. Insert OVR-SG047B (1SVML013 B PORV - MAN CTRL LIGHTS RED LT),

1B LT), VALUE=OFF

9. Manually trip the reactor.

10. Cooldown using PORVs to -520°F on Tcolds while maintaining Pzr level >17%.

11. MAL-CA009B (MD CA CTRL VLV CA56 FAILURE), VALUE=85

12. IND-CA009 (1CAP5100 CA FLOW TO S/G 1B METER

13. IND-NC001 (1(1NCP5850 NCP5850 HOT LEG TEMP LOOP A METER TI-413A METER), VALUE 524

14. IND-NC002 (1NCP5870 (1 NCP5870 HOT LEG TEMP LOOP B METER TI-423B METER), VALUE 524

15. IND-NC007 (1 NCP5860 COLD LEG TEMP LOOP A METER TI-413A METER), VALUE 523.2

16. IND-NC012 (1 NCP5880 COLD LEG TEMP LOOP B METER TI-423B METER), VALUE 523.2

17. XMT-NC034 (TNC_5390 PZR SPRAY LN TEMP LOOP A TO DeS DCS (NCAA5390>>,

(NCAA5390)), VALUE 521.2

18. XMT-NC035 (TNC_5400 PZR SPRAY LN TEMP LOOP B TO DeS DCS (NCAA5400>>, VALUE 521.2 (NCAA5400)),

19. XMT-NC036 (TNC-5850 NC LOOP 1A HOT LEG TEMP (REC)), (REC>>, VALUE= 524

20. XMT-NC037 (TNC-5860 NC LOOP 1A COLD LEG TEMP (REC>>, (REC)), VALUE= 523.7 XMT -NC038 (TNC-5870 NC LOOP 1B

21. XMT-NC038 1B HOT LEG TEMP (REC>>,

(REC)), VALUE= 524

22. XMT-NC039 (TNC-5880 NC LOOP 1B 1B COLD LEG TEMP (REC>>,

(REC)), VALUE= 523.7

23. XMT-NC041 (TNC-5900 NC LOOP 1C HOT LEG TEMP (REC>>, (REC)), VALUE= 524

24. XMT-NC042 (TNC-5910 NC LOOP 1C COLD LEG TEMP (REC>>, (REC)), VALUE= 523.7

-NC043 (TNC-5920 NC LOOP 10 HOT LEG TEMP (REC)),

XMT-NC043

25. XMT (REC>>, VALUE= 524

26. XMT-NC044 (TNC-5930 NC LOOP 10 COLD LEG TEMP (REC>>, (REC)), VALUE= 523.7

27. XMT-NC057 (TNC-5440 NC LOOP 1A COLD LEG TEMP NIL), VALUE= 523.2

28. XMT-NC061 (TNC-5480 NC LOOP 1B 1B CL TEMP N/R), VALUE= 523.2

29. XMT-NC065 (TNC-5520 NC LOOP 1C CL TEMP N/R), VALUE= 523.2

30. XMT-NC069 (TNC-5560 NC LOOP 10 CL TEMP N/R), VALUE= 523.2

31. LOA-AS007 (AS59 - TO UNIT 2 SUPPLY) VALUE=1

32. Insert Event 1 - x10i1160 x1 Oi218b

33. Insert Event 2 - x10i218b

34. Freeze simulator and write to a SNAP.

IC SELECTED _ _ _ _ __

NOTE: All temperature indications for Thots and Tcolds are failed to ensure repeatable results for all students, a PORV is failed intermediate with no indication and a CA flow control valve is failed intermediate with no indication to maintain temperature approximately stable. This is to ensure that NC pressure does not increase significantly without a corresponding temperature increase since the temperature indications are failed.

JPM09D Page 3 of 15

SIMULATOR OPERATOR INSTRUCTIONS:

DO NOT go to RUN until candidate is ready to perform task.

Tools/Equipment/Procedures Needed:

EP/1/A15000/ES-O.1 (Reactor Trip Response) Revision 030DCS EP/1/A/5000/ES-O.1 JPM09 D Page 4 of 15

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

A reactor trip occurred due to an EHC leak causing a turbine trip at 100% power. Actions are being performed in EP/1/A/5000/ES-0.1 (Reactor Trip Response).

INITIATING CUES:

Perform a verification of shutdown margin per Step 7 of EP/1/A/5000/ES-0.1.

JPM09 D Page 5 of 15

START TIME: _ __

STEP 7.a

- SAT Verify adequate shutdown margin as follows:

a. DRPI indication - AVAILABLE.

STANDARD: Notes DRPI indication is available. - UNSAT COMMENTS:

STEP 7.b:

b. All control and shutdown rods - FULLY INSERTED. - SAT STANDARD: Checks DRPI panel and notes all rods inserted.

- UNSAT COMMENTS:

STEP 7.c: CRITICAL STEP

c. All NC T-Colds - GREATER THAN 545°F.

STANDARD: Notes temperatures are -523°F on Tcolds. SAT COMMENTS:

- UNSAT JPM09 D Page 6 of 15

STEP 7.c.1) 7 .c.1) RNO: CRITICAL STEP Perform the following:

Determine lowest T-Cold.

SAT STANDARD: Notes lowest Tcold is -523°F.

EXAMINER NOTE: The amount of boron to be added is based on the temperature noted by the candidate and may vary based on timing. UNSAT COMMENTS STEP 7.c.2) RNO CRITICAL STEP Determine core burnup in effective full power days (EFPD) (OAC Point P1457 ororfrom from Reactor Operators logbook). SAT STANDARD: Based on OAC, core burn up is 450 EFPD.

UNSAT COMMENTS STEP 7.c.3) RNO CRITICAL STEP Verify lowest current T-Cold is greater than or equal to the allowable limit at present burnup. REFER TO ROD Book, Section 2.6.

STANDARD: Determines lower limit is 529°F from ROD BOOK section SAT 2.6.

COMMENTS UNSAT

_UNSAT JPM09 D Page 7 of 15

STEP 7.cA) RNO (PART 1) CRITICAL STEP IF lowest T-cold is less than allowable limit, THEN immediately add 30 gallons of 7000 PPM boron solution at greater than or equal to 30 GPM for each degree lowest T-Cold is below limit of ROD Book, Section 2.6.

SAT STANDARD: Calculates amount of Boric acid to add based on temperature. Calculated the temperature difference using the value determined above and subtracts it from 529°F. Multiply the result by 30 to get the total number of gallons to be added as a minimum. UNSAT EXAMINER NOTE: All Tcolds indications are failed to 523.2 of OF to ensure all students get consistent data since temperatures maybe not be stable at exactly value and based on student speed could be different if they were not set at a specific temperature.

{529 - 523) x 30 = = 180 gallons (per embedded table on graph)

Using +/- 4 EFPD and Using.:!:. +/- 2 of and.:!:. OF (1/2 increment accuracy) would be 446 - 454 EFPD and 527-531 oF. This would yield total volumes of:

=

(527-523) x 30 = 120 gpm

=

(531-523) x 30 = 240 gpm To meet the Critical Step, total calculated acid addition should be 120-240 gpm.

COMMENTS JPM09 D Page 8 of 15

STEP 7.c.4) RNO (PART 2)

IF lowest T-cold is less than allowable limit, THEN immediately add 30 gallons of 7000 PPM boron solution at greater than or equal to 30 GPM for SAT

_SAT each degree lowest T-Cold is below limit of ROD Book, Section 2.6.

STANDARD: Establishes Establishes?:~ 30 gpm flow from the BAT using the emergency borate valve and determines the total amount to be added UNSAT

_UNSAT using the formula stated above.

EXAMINER NOTE:

The normal blender flowpath if used will fail to meet the required 30 gpm flow but the emergency borate valve will work. The student will likely try the OPf1fA/6150f09. Those steps are below.

normal blender flowpath first per OPf1fAl6150f09.

If the student goes directly to emergency borate, skip to page 14 of the JPM.

COMMENTS OPf1fA/6150f009 Step 2.2 OPf1fAl6150f009 Ensure the following valve control switches in "AUTO":

1NV-238A (BfAXfer Pmp To Blender Ctrl) SAT

1NV-186A (BfA Blender Otlt To VCT Otlt)

STANDARD: Checks 1NV-238A and 1NV-186A vavle control switches in AUTO. UNSAT COMMENTS JPM09 D Page 9 of 15

OPf1fA/6150f009 Step 2.3 OP/1/A161501009 Ensure 1NV-238A (B/A (BfA Xfer Pmp To Blender Ctrl) controller in auto.

- SAT STANDARD: Checks position of 1NV-238A is AUTO COMMENTS

- UNSAT OP/1/A161501009 OPf1fA/6150f009 Step 2.4 Ensure at least one boric acid transfer pump is in "AUTO" or "ON".

- SAT STANDARD: Places at least on boric acid transfer pump to ON.

COMMENTS

- UNSAT OP/1/A161501009 OPf1fA/6150f009 Step 2.5 Adjust the boric acid batch counter to the desired volume of boric acid to be added. (RM.)

(R.M.) - SAT STANDARD: Adjusts counter to value determined per step 7.c.4 above (total calculated acid addition should be 120-240 gpm.)

- UNSAT COMMENTS JPM09 D Page 10 of 15

OPf1fA/6150f009 Step 2.6 OPf1fAl6150f009 IF the blender is set up for automatic makeup per Enclosure 4.1 (Automatic Makeup). record the setpoint of the controller for 1NV-238A (BfA Makeup), (BfAXfer Xfer Pmp - SAT To Blender Ctrl). gpm STANDARD: Records the setpoint of the controller for 1NV-238A.

- UNSAT COMMENTS OPf1fA/6150f009 Step 2.7 OPf1fAl6150f009 Place the "NC MAKEUP MODE SELECT" switch in "BORATE".

- SAT STANDARD: Placed makeup switch to BORATE.

COMMENTS

- UNSAT NOTE: Boric Acid flow rates> 32 gpm may result in a boric acid flow deviation annunciator.

STANDARD: Acknowledges note and continues. - SAT COMMENTS

- UNSAT OPf1fA/6150f009 Step 2.8 OPf1fAl6150f009 Adjust the controller for 1NV-238A (BfA Xfer Pmp To Blender Ctrl) to the desired flow. - SAT STANDARD: Attempts to adjust 1NV-238A to get >30 gpm flow.

COMMENTS - UNSAT JPM09 D Page 11 of 15

NOTE: If necessary, boration can be manually secured at any time by placing the "NC MAKEUP CONTROL" switch to the "STOP" position.

SAT STANDARD: Acknowledges note and continues.

COMMENTS UNSAT OPf1fAl6150f009 Step 2.9 Place the "NC MAKEUP CONTROL" switch to the "START" position.

(R.M.). SAT STANDARD: Places makeup control to START.

COMMENTS UNSAT OPf1fAl6150f009 Step 2.10 Verify the following valves open:

1NV-238A (BfAXfer Pmp To Blender Ctrl) SAT

1NV-186A (BfA Blender Otlt To VCT Otlt)

STANDARD: Verifies 1NV-238A and 1NV-186A are open.

UNSAT COMMENTS OPf1fAl6150f009 Step 2.11 IF in "AUTO", verify the boric acid transfer pump starts.

SAT STANDARD: Verified the selected boric acid transfer pump starts.

COMMENTS UNSAT JPM09 D Page 12 of 15

NOTE: The total makeup flow totalizer is inaccurate at low flow rates.

STANDARD: Acknowledges note and continues.

- SAT COMMENTS

- UNSAT OP/11A161501009 OP/1/Al6150/009 Step 2.12 Verify proper flow by observing the boric acid flow totalizer.

{PIP 96-0137} - SAT STANDARD: Checks boration acid flow on either the controller for 1NV-238A or chart recorder on 1MC5 (1 NVCR5450)

- UNSAT If candidate dispatches an operator to investigate 1NV-238A, provide the following cue after 3 minutes:

EXAMINER CUE: 1NV*238A NV-238A is bound in an intermediate position.

EXAMINER NOTE:

Student should determine the need to use emergency boration due to inability to get ~ 30 gpm flow using normal flowpath and open 1NV-236B NV-2368 to establish the required flow.

COMMENTS JPM09 D Page 13 of 15

STEP 7.cA) RNO (PART 2)

CRITICAL Opens 1NV-236B (Boric Acid to NV Pumps Suct). STEP STANDARD: Opens 1NV-236B (and starts a boric acid pump if not already running) and establishes >30 gpm flow from the BAT using the emergency SAT borate valve as read on 1NVP5440 (EMER BORATE FLOW)

EXAMINER NOTE:

UNSAT

_UNSAT If student has not already attempted to use normal boration, he will start a boric acid transfer pump at this time as well.

It is critical that a boric acid pump be running and the valve above is open.

COMMENTS STEP 7.c.5) RNO GO TO Step 7.e.

SAT STANDARD: Goes to step 7.e COMMENTS UNSAT

_UNSAT STEP 7.e:

Stop any boron dilutions in progress.

SAT STANDARD: Ensures no dilutions are in progress.

COMMENTS UNSAT This JPM is complete.

TIME STOP: _ __

JPM09 D Page 14 of 15

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A reactor trip occurred due to an EHC leak causing a turbine trip at 100% power. Actions are being performed in EP/1/A/SOOO/ES-0.1 (Reactor Trip Response).

INITIATING CUES:

EP/1/A/SOOO/ES-0.1.

Perform a verification of shutdown margin per Step 7 of EP/1/A/5000/ES-0.1.

CNS REACTOR TRIP RESPONSE PAGE NO.

EP/1/N5000/ES-0.1 5 of 30 Rev 30DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. Verify adequate shutdown margin as follows:

a. DRPI indication - AVAILABLE. a. Verify adequate shutdown margin as follows:

1) Emergency borate 14,000 gallons of 7000 PPM boron solution as follows:

_ a) Open 1NV-236B (Boric Acid To NV Pumps Suct).

_ b) IF 1NV-236B NV-23"6B will not open, THEN dispatch operator to open 1NV-236B (Boric Acid To NV Pumps Suct) (AB-550, (AB-S50, HH-JJ, 53-54, Rm 234).

c) WHEN 1NV-236B is open, THEN:

_ (1) Start boric acid transfer pumps.

_ (2) Calculate required injection time based on boric acid flowrate.

_ (3) WHEN required boric acid is injected, THEN secure emergency boration.

_ 2) Notify Reactor Group Duty Engineer to perform analysis to determine required shutdown margin.

_ 3) GO TO Step 7.c.

CNS REACTOR TRIP RESPONSE PAGE NO.

EP/1/A/5000/ES-0.1 EP/1IAl5000/ES-0. 1 6 of 30 60f30 Rev 30DCS ACTION/EXPECTED RESPONSE R[SPONSE RESPONSE NOT OBTAINED

7. (Continued)

b. All control and shutdown rods - FULLY b. IF two or more rods are notfully not fully INSERTED. inserted, THEN:

1}

1) Emergency borate 150 PPM for each rod not fully inserted as follows:

_ a}

a) Open 1NV-236B (Boric Acid To NV Pumps Suct).

_ b} IF 1NV-236B will not open, b)

THEN dispatch operator to open 1NV-236B (Boric Acid To NV Pumps Suct) (AB-550, HH-JJ, 53-54, Rm 234).

c} WHEN 1NV-236B is open, c)

THEN:

_ (1) Start boric acid transfer pumps.

_ (2) Calculate required boron addition. REFER TO ROD Book, Section 4.1.

_ (3) Calculate required injection time based on boric acid flowrate.

_ (4) WHEN required boric acid is injected, THEN secure emergency boration.

_ 2} Notify Reactor Group Duty Engineer 2) to perform analysis to determine required shutdown margin.

CNS REACTOR TRIP RESPONSE PAGE NO.

EP/1/N5000/ES-0.1 EP/1/A/5000/ES-0.1 7 of 30 7of30 Rev 30DCS Rev30DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (Continued)

c. All NC T-Colds --GREATER THAN c. Perform the following:

545°F.

_ 1) Determine lowest T-Cold.

_1)

_ 2) Determine core burnup in effective

_2) full power days (EFPD) (OAC Point P1457 or from Reactor Operators logbook).

_ 3) Verify lowest current T-Cold is greater than or equal to the allowable limit at present burnup.

REFER TO ROD Book, Section 2.6.

_4) IF lowest T T-Cold

-Cold is less than allowable limit, THEN immediately add 30 gallons of 7000 PPM boron solution at greater than or equal to 30 GPM for each degree lowest T-Cold T -Cold is below limit of ROD Book, Section 2.6.

_ 5) GO TO Step 7.e.

d. IF AT ANY TIME NC T-Colds decrease to less than or equal to 545°F, THEN perform Step 7.c.

e. Stop any boron dilutions in progress.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 E Place Steam Dumps in Automatic Mode in Preparation for Unit Startup CANDIDATE EXAMINER JPM09 E Page 1 of 8

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Place Steam Dumps in Automatic Mode in Preparation for Unit Startup Alternate Path:

YES Facility JPM #:

N/A (new)

KIA Rating(s):

SYS041 A3.02 (3.3/3.4) - Ability to monitor automatic operation of the SDS, including RCS pressure, RCS ReS temperature, and reactor power.

Task Standard:

Places Steam Dumps in automatic operation per OP/1/N61 001001 (Controlling Procedure for Unit Startup).

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator X In-Plant _ __ Perform _~X,,---

_...:..XoO...-- Simulate _ __

References:

OP/1/N61001001 (Controlling Procedure for Unit Startup), Enclosure 4.1 revision 217DCS Validation Time: 10 min. Time Critical: No

=======================================================================

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: 1 NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM09 E Page 2 of 8

SIMULATOR SETUP SHEET

1. Reset to a BOL 10-8 amp snap

2. Reduce Tavg to -555°F

3. Adjust steam dump demand to something less than "1092" and place in manual

4. MAL-IDE003C (STEAM DUMP VLV SB9 FAIL TO POSITION) VALUE 15 EVENT 2

5. MAL-IDE003C (STEAM DUMP VLV SB9 FAIL TO POSITION) VALUE 0 EVENT 3

6. MAL-IPX005C (PERMISSIVE P-12 SIGNAL FAILS TO ACTUATE) VALUE BOTH

7. MAL-SLlM15_02 (1SMSS5200 STM DUMP Raise Setpoint Pushbutton fail to position) VALUE Button_Disabled

8. MAL-SLlM15_03 (1SMSS5200 STM DUMP Lower Setpoint Pushbutton fail to position) VALUE Button_Disabled Button Disabled

9. MAL-SLlM15_06 (1SMSS5200 STM DUMP Auto Pushbutton fail to position) VALUE Button_Disabled Button Disabled

10. When stable, freeze simulator and write to a SNAP.

& !x02i184L (both byp interlock not OFF)

11. Insert event 2 - !x02i186L &

12. Insert event 3 - x02i186L && rsbh009>0 I x02i184L & & rsbh009>0 IC SELECTED _ _ _ _ __

SIMULATOR OPERATOR INSTRUCTIONS:

Do not place the simulator in RUN until the candidate is ready to begin.

ENSURE controller is in MANUAL prior to each run.

Tools/Equipment/Procedures Needed:

JPM09 E Page 3 of 8

OP/1/A/61001001 (Controlling Procedure for Unit Startup), Enclosure 4.1 revision 217 OP/1/Al6100/001 JPM09 E Page 4 of 8

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

Unit 1 is preparing to increase power from 1 x 10-8 amps.

INITIATING CUES:

Complete steps 2.137 - 2.139 of OP/1/A161 001001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup) to place steam dumps in automatic operation in preparation for increasing power to 1%. 1%.

JPM09 E Page 5 of 8

START TIME: _ __

STEP 2.137: CRITICAL STEP Establish automatic steam dump control as follows: (RM) 2.137.1 Adjust the "Stm Dump Ctrl" setpoint to 1092 psig. _SATSAT STANDARD: Sets "Stm Dump Ctrl" to 1092 psig.

UNSAT COMMENTS:

STEP 2.137.2:

Ensure MSIVs are open per Step 2.136.3. SAT STANDARD: Notes that MSIVs are open per Step 2.136.3 and checks off.

UNSAT COMMENTS:

STEP 2.137.3:

Ensure T -AVG is less than or equal to 557°F per Step 2.134.1.

T-AVG SAT STANDARD: Notes that current Tavg is -556°F and checks off.

COMMENTS UNSAT STEP 2.137.4: CRITICAL STEP Place the "Stm Dump Ctrl" in auto.

STANDARD Depresses the "A" pushbutton on the steam dump controller.

SAT COMMENTS UNSAT JPM09 E Page 6 of 8

STEP 2.138: CRITICAL STEP Turn the following switches to the "ON" position:

Steam Dump Intlk Byp Trn A

Steam Dump Intlk Byp Trn B SAT STANDARD Turns hand switches to the ON position.

COMMENTS UNSAT STEP 2.139: CRITICAL STEP

When the MSIVs are open verify the steam dumps maintain approximately 1090 psig.

STANDARD Notes that steam pressure and temperature are decreasing. SAT EXAMINER NOTE: P*12 P-12 interlock (close steam dumps on 10 tavg) is blocked so temperature will continue to decrease without operator action. Also, the steam dump controller will not function to close the UNSAT dumps. The Steam Dump Intlk Byp switches must be returned to "OFF". And the dumps will close. (only one switch is required to close the dump valve)

EXAMINER CUE: Once the steam dumps are closed and the CRS has been notified of the problem provide the following cue: "This JPM is complete."

COMMENTS This JPM is complete.

TIME STOP: _ __

JPM09 E Page 7 of 8

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 is preparing to increase power from 1 x 10-8 amps.

INITIATING CUES:

Complete steps 2.137 - 2.139 of OP/1/A/61 00/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup) to place steam dumps in automatic operation in preparation for increasing power to 1%.

Enclosure 4.1 OP/liA/6 100/00 1 OPIVA/6l00100l Unit Startup Page 1 of66

1. Initial Conditions

-YJ!-

~ 1.1 Review the Limits and Precautions.

NOTE: 1. LTOP may be satisfied by the ND Pump suction relief valves or the PZR PORVs. Refer to CNSD 3.1.30 (Unit Shutdown and Configuration Control (Mode 5, 6, or No Mode),

Tech Spec 3.4.12, and the Outage Guidelines for the allowable and recommended vent paths.

2. AnyAnyNCNC PORV NOT selected to "LOW PRESS" shall be tracked in the TSAIL.

4 4 1 . 12.2 Verify LTOP is met by any two of the following:

ofthe

~"PORV Mode Sel NC-34A" (selected to "LOW PRESS")

LJ "PORV Mode Sel NC-32B" (selected to "LOW PRESS")

D lND-3 (lA ND Pump Suction From NC Loop B Header Relief) aligned D lND-38 (lB ND Pump Suction From NC Loop C Header Relief) aligned 1

1 1 . 13.3 Verify the ND System is in operation per OPIlIA/62001004 System).

OP/1/A/6200/004 (Residual Heat Removal

2. Procedure 1-2.1 While continuing in the procedure begin signing off items on the following:

0" Enclosure 4.2 (Operations Pre-Heatup Checklist) ur Enclosure 4.3

[]' (Support Pre-Heatup Checklist) o 0" Enclosure 4.4 (Operations Mode 4 Checklist)

D"Enclosure 4.5 CVEnclosure (Support Mode 4 Checklist) 1 2 .2 Determine the required boron concentration to maintain the SDM within limits specified in COLR for above 200 oo P, (without xenon credit) per OP/O/A/6100/006 (Reactivity Balance Calculation). (R.M.)

Required boron concentration I~

Irq q7 ppm

-.12.3

--.12.3 Begin signing off the initial conditions of ofOP/1/B/6300/00l OPIl/B/63 00100 1 (Turbine-Generator) to ensure they will be met prior to rolling the main turbine.

~2.4 IF desired, align the AS header supply such that Unit 2 Main Steam is supplying AS per the OP/O/B/6250/007 A (Auxiliary Steam) enclosure for cross-connecting the Unit 1 and Unit 2 OP/O/B/62501007 AS headers. (R.M.)

Enclosure 4.1 OP!l/A/61 00/00 1 OP;1/A/6100/001 Unit Startup Page 2 of66 2.5 Perform the following in preparation for NC System heatup:

1 2 .5.1

.5 . 1 Initiate Increased Monitoring for In-Plant Valves and an Increased Surveillance for Control Room Valves to drain the piping specified on Enclosure 4.12 (Secondary Heatup Checklist) as follows:

bVOpen each drain valve/dump valve slowly to prevent water hammer.

~ Allow each drain valve/dump valve to remain open long enough to drain the cf accumulated moisture.

B4Jrain each isolated section of piping every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

81Jrain 2.5.2 Position the valves listed on Enclosure 4.12 (Secondary Heatup Checklist) in the Heatup Position.

GYbose GY60se each valve listed on the checklist.

cV'Initial by each in the "Heatup Position" column.

NOTE: 1. The following step will provide a means to begin warming of the Unit 1 Main Turbine using Auxiliary Steam from Unit 2 via 1AS-4 lAS-4 (Main Steam to Aux Steam Header Control Bypass) (TB-610, 1M-32).

IM-32). This will allow turbine warming to be performed prior to and concurrent with heatup of the NC System.

2. Steam usage may result in an approximate 5 MW reduction in generation on Unit 2.

1 2 .6 IF desired to use Auxiliary Steam supplied from Unit 2 for turbine warming, perform the following: (R.M.)

2.6.1 Ensure the following valves are closed.

r;r lSM-1 cT ISM-l (S/G 1DID SM Isol)

~lSM-3 (S/G 1C lC SM Isol)

GV 1lSM-S SM-5 (S/G 1BIB SM Isol)

Gf ISM-7 lSM-7 (S/G 1AIA SM Isol)

Q' ISM-9 lSM-9 (S/G 1DID SM Isol Byp)

GYlSM-10 (S/G 1C GY1SM-10 lC SM Isol Byp)

[2(

[L( ISM-II lSM-ll (S/G 1BIB SM Isol Byp)

CY lSM-12 ISM-12 (S/G lA SM Isol Byp) 1j 2.6.2 Verify the Unit 2 AS System is aligned supplying the Unit 1 AS header per OP/O/B/6250/007 OP/0/B/6250/007 A (Auxiliary Steam System Alignment).

Enclosure 4.1 OP/l!Al6100/001 OP/l!A/6 100/001 Unit Startup Page 3 of66 2.6.3 Notify the Control Room Supervisor that an approximate 5 MW reduction in generator output on Unit 2 may occur when using the AS System for Unit 1 Turbine Shell Warming.

2.6.4 Have the Turbine Building rounds NEO monitor the Unit 1 SM piping for water hammer.

~2.6.5

~ 2.6.5 Notify the Control Room Supervisor to monitor Unit 2 Reactor Power, Generator MW, and AS Header pressure while performing the following step.

2.6.6 Slowly open lAS-4 (Main Steam to Aux Steam Header Control Bypass) (TB-610, IM-32).

j 2.6.7 Verify the Unit 1 SM Header pressure is approximately equal to AS Header Pressure.

NOTE: / If turbine prewarming is NOT to begin at this time, continue with the procedure and sign off V Steps 2.6.8 and 2.6.9 when ready to begin prewarming the high pressure turbine shelL shell.

2.6.8 Verify the turbine initial conditions contained in the turbine generator startup enclosure of OP/1/B/63 00/00 1 (Turbine-Generator) have been signed off.

Enclosure 4.1 OP/lIAJ61 00/0011 OP/liAl61 00100 Unit Startup Page 4 of66 CAUTION: Do NOT exceed 50 psig in the high pressure shell while doing Step 2.6.9 until PZR pressure is greater than 1945 psig (PZR Low Pressure Rx Trip Setpoint). This is to prevent P-13 (56 psig impulse pressure) enabling P-7 to unblock the Lo Power Reactor Trips (PZR High Level, PZR Low Pressure, Low NC Flow on 2/4 Loops, NC Pump Undervoltage, NC Pump Underfrequency).

NOTE: 1. Step 2.6.9 may be done at anytime during plant heatup to 2235 psig/557°F.

psigIS57°F. The warming does NOT have to be at 60-100 psig as required by OP/lIB/63 OPIlIB/63 00/00 00100 1 (Turbine-Generator). This warming is to reduce the amount of time required before v placing the Turbine-Generator on the line.

2. Turbine warming guidelines:

~ -Prior to reaching PZR pressure of 1945 psig (PZR Low Pressure Rx Trip Setpoint):

Perform shell/chest warming per OP/IIB/6300/001 OP/1/B/63001001 (Turbine-Generator). Do NOT exceed 50 psig in the high pressure shell or a Reactor Trip may occur.

-When PZR pressure> 1945 psig (PZR Low Pressure Rx Trip Setpoint): Perform shell/chest warming per OP/IIB/6300/001 OP/1/B/63001001 (Turbine-Generator) with steam pressure in the high pressure shell 60 - 100 psig.

-After completion of shell warming, prior to placing turbine on line: Maintain First Stage Shell Lower Inner Metal temperature> 250°F until the turbine is placed on line.

1- 2.6.9 2.6.9 WHEN Main Steam pressure> 100 psig, prewarming of the turbine may begin per OP/l IB/63 00100 OP/1/B/63 00/00 1 (Turbine-Generator).

-12.7

- 12.7 IF PZR bubble established per OP/lIAJ6150/001 OPIlIAl61501001 (Filling and Venting the Reactor Coolant System), N/A Steps 2.8 - 2.68 and continue with the procedure.

w/A12.8 2 .8 IF the blind flange downstream of INC-300 (NC Vac Fill Isol) is removed, issue Model W/O # 00886186 (Forced Outage) or Model W/O # 00886776 (Refueling Outage) to have Maintenance install it.

~2.9 Ensure Model W/O # 00897964 to perform loose parts testing has been issued.

-1 2 .10 Ensure charging and letdown in service per OP/lIAJ6200/001 Control System).

OPIlIAl62001001 (Chemical and Volume

~ 2.11

,-- Ensure actual PZR level is adjusted to 85% in preparation for drawing a bubble in the PZR.

r---

~2.12 Ensure INC-297 (PRT Vent To PZR Relief Disch Bypass Vlv) (CV-565, 27'-90°, LC) is closed.

Enclosure 4.1 OP/l!Al61 00/00 1 OP!l/A/6100/001 Unit Startup Page 5 of66 L 2.13 J- Ensure the PZRPORVs PZR PORVs are closed.

Ef E:f (PZR PORV)

INC-32 (pZR Gr INC-34 (PZR PORV)

[S CY"INC-36

[Y""INC-36 (PZR PORV) 4- 2.14 Ensure the PZRPORVs are in "AUTO".

EnsurethePZRPORVsarein"AUTO".

Q/INC-32 (PZR PORV)

(PZRPORV)

B"J-NC-34 (PZR PORV)

C3"1NC-34 B'" INC-36 (PZR E::(INC-36 PORV)

(PZRPORV)

~ 2.15 Ensure the following key switches are in the "NORM" position:

G:r

[3" "INC27 PZR SPRAY VALVE MODE SELECT" CJ-.!.!.i'NC29 c:J.3fNC29 PZR SPRAY VALVE MODE SELECT" 2.16 Perfonn the following before beginning PZR heatup:

Perform

+2.16.12.16.1 Notify the Primary Chemist for the following r-easons:

J 6~ 5111 1-\ rt Person notified ---=~~~==~~~------------

6'<. SIl1I-1 r4 detennine ifhydrazine is required to be added to the PZR.

0'To determine

~ determine detennine ifhydrazine is required to be added to the NC 'System.

System.

~To determine detennine any heat up or chemistry limits which shall be observed during heatup.

0k

v/Jr tj 2.16.2 IF required document any limits in the RO logbook.

~ ~ 2.17 Notify Chemistry to initiate any chemical additions required per the Chemistry Guidelines.

---r-Person notified G 0() V (b \/1 LL A V ILL

~t2.18 riA 12.18 IF a PZR hydrazine addition is required, align charging to the PZR to allow for chemical addition as follows: {PIP C98-3960}

2.18.1 Close the following valves:

o Fnn Loop A)

INC-27 (PZR Spray Ctrl Frm o lNC-29 (PZR Spray Ctrl Frm INC-29 Fnn Loop B)

Enclosure 4.1 OP/l!Al61 00/00 1 OP/l!A/6100/001 Unit Startup Page 6 of66 2.18.2 Open INV-37A (NV Supply To PZR Aux Spray).

2.18.3 Isolate the charging path which is in service and record the initial status of each valve position:

D 1NV-32B INV-32B (NY Supply To Loop A Isol)

Position' -

D 1NV-39A (NV-Supply To Loop D Isol)

INV-39A (NV-Supp1y Iso1)

Position--- --- -- -

2.19 WHEN notified by Primary Chemistry that chemical addition is complete AND 15 minutes has passed to ensure the hydrazine has entered the PZR, perform the following:

2.19.1 Open the valve closed in Step 2.18.3 to establish the desired charging path:

D INV-32B INV -32B (NV Supply To Loop A Isol)

D INV-39A (NY Supply To Loop D Isol) Iso1) 2.19.2 Close 1NV-37A INV-37A (NV Supply To PZR Aux Spray).

2.19.3 Open the following valves:

D 1NC-27 INC-27 (PZR Spray Ctrl Frm Loop A)

D 1NC-29 INC-29 (PZR Spray Ctrl Frm Loop B)

Enclosure 4.1 OP/1!A/6100/001 OP/l!A/6 100/00 1 Unit Startup Page 7 of66 NOTE: ~ procedure may continue while performing Step 2.20 and 2.21.

--.:f-.

~ 2.20 Perform the following:

Place the following PZR Heater Breakers in the "RACKED IN" position:

~ILXC-5C

~lLXC-5C (Pressurizer Heater Power PanellC) r:YlLXD-5C (Pressurizer Heater Power PanellD) r:YILXD-5C PanelID) g Q' lLXH-6C (Pressurizer Heater Power PanellB)

B"'lLXI-6C (Pressurizer Heater Power PanellA)

B"ILXI-6C

Place the following breaker in the "ON" position:

cY'SMXG-P05C (Unit 1 NC System Pressurizer Heaters 28, 55 &56) cY'SMXG-F05C

Place the following PZR Heater Breaker Control Panel switches in the "CLOSED" position:

~ILXD

~lLXD "BREAKER CONTROL lLXD-5C" g- j.k'XH "BREAKER CONTROL lLXH-6C" ILXH-6C"

~lLXI Gr 1LXI "BREAKER CONTROL lLXI-6C" CAUTI~: NC System may NOT be heated above 200 P or pressure increased to greater than 350 0

200°F

--J V psig until RVLIS venting has been completed.

4:L- 2.21 IAE Ensure RVLIS venting is completed prior to the NC System exceeding 200°F 200 0 P or 350 psig.

-1 2.22 While plant heatup is in progress periodically reset the Shutdown Margin Monitor/Boron Dilution Mitigation System "Alarm Setpoint" to prevent a system activation.

CAUTION: 1. To limit thermal stress, it is recommended that the PZR heatup be as linear as 0

. /"

/ possible. (Example: Do NOT do a step heatup like 40 40°F P in ten minutes, then wait 50

~ minutes before increasing temperature again.

J. Do NOT exceed 250 0 250°F P PZR water temperature until notified by Primary Chemistry that all hydrazine additions necessary for subsequent heatup are completed.

V u n t i l stable PZR level control is established at 70% (85% if nitrogen blanket o

established in the PZR) PZR Cold Calibration level (150 P-215°P), maintain a PZR (150°F-215°F),

o to Loop B Hot Leg temperature differential of:s:; 80 80°F.

P.

-:1-

-..:l- 2.23 Begin documenting the PZR heatup and NC System heatup every 30 minutes per PT/1/A/4600/0l6 (Surveillance Requirements Por PT/1/A/46001016 For Unit 1 Startup).

Enclosure 4.1 OP/lJA161001001 OP/liA/61001001 Unit Startup Page 8 of66 NOTE:~ize activities that affect the temperature of the secondary side of the S/Gs since this ofthe will also have an effect on the temperature of the NCS.

4- 2.24 Begin heatup of the NC system to 150-180 0oP T-Hot by adjusting the appropriate valve for the ND Train in service to obtain a heatup rate of 20 to 40 00 P per hour:

IND-26 (ND Hx IA Outlet Ctrl)

OR

IND-60 (ND Hx IB Outlet Ctrl)

--1 J 2.25 IF desired, WHEN RVLIS venting by IAE has been "Completed, completed, the NCS heatup rate may be increased to the normal Administrative Limits.

NOTE: ~edure may continue while performing Step 2.26.

~

~4-~ 2.26 IF desired, WHEN the desired heatup rate CANNOT be maintained, perform the following:

~

2.26.1 OP11/AI62001004 Restore air to any KCHX outlet valve that was failed open in OP/lIA/62001004 (Residual Heat Removal System).

2.26.2 Isolate cooling to the in service ND heat exchanger:

Close lKC-56A IKC-56A (KC To ND Hx lA Sup Isol) Iso1)

OR

Close IKC-8IB (KC To ND Hx IB Sup Isol) Iso1) 2.26.3 WHEN NC temperature is 150-160 oo P, restore cooling to the in service ND heat exchanger isolated in Step 2.26.2.

Open IKC-56A (KC To ND Hx IA lA Sup Iso1)

Isol)

OR

IKC-8IB (KC To ND Hx IB Sup Isol)

Open IKC-SIB Iso1) 2.27 IF a nitrogen blanket was NOT established in the PZR, open one PZR PORV:

-L.

~. INC-32B (PZR PORV)

INC-34A (PZR PORV)

INC-36B (PZR PORV)

Enclosure 4.1 OP/l!Al6100/001 OP/l!Al61 001001 Unit Startup Page 9 of66 Once NC System heatup begins, refer to OAC point CIP0301 C1P0301 (Actual Average PZR Level) and Revised Data Book Figures 49, 50, and 51 to monitor PZR level.

240°F PZR steam space temperature equates to ~ 10 psig ofPZR ofPZRpressure pressure or approximately 48 psig of pressure on the suction of an ND pump aligned to the NCS loops.

LY V The intention of the following step is to maintain PZR level close to 85% (with nitrogen blanket established in the PZR) while allowing for level fluctuations due to expected collapse of voids and providing a slow outflow from the PZR.

~ The presence of voids may slow PZR pressure changes.

~s PZR steam space temperature approaches saturation, the steam space temperature will quickly rise. {PIP C98-396l}

L.6..---lUs preferable to have ND Pump A in service during the PZR heatup to limit thermal L.6.---JtAs stresses on the PZR surge line to the NCS nozzle.

t- 2.28

I- IF available, ensure ND Train 1A is operating during the heatup to promote circulation in the NC Loop B hot leg.

~ 2.29 Energize PZR heaters as necessary to commence PZR heatup to establish approximately

---r- 240°F PZR temperature while maintaining the following:

PZR heatup rate $~ 80°Fihr 80°Flhr

PZR Spray nozzle !1 T $~ 320°F

~T

PZR level at 85% (if a nitrogen blanket is established in the PZR) 2.30 Record the time below that the PZR heaters are energized.

Time: joO

/ )0 0 NOTE: y. Outsurge from the PZR may result in temperature at the suction of the ND pump

. / anproaching 200°F especially if A train ND is in service.

~e procedure may continue while performing Step 2.31.

1j 2.31 Monitor surge line temperature to confirm outsurge from the PZR by ensuring the following:

~ra PZR heater capacity is energized.

~NC, NY NV or ND PZR spray is indicated.

~ZR surge line temperatures and PZR water space temperatures are approximately equal.

Enclosure 4.1 op;1/A/61 00/00 1 OP;1/A/6l00/00l Unit Startup Page 10 of66 L 2.32 WHEN reducing or stopping the heatup, adjust charging and letdown to maintain a steady or slowly decreasing PZR level to prevent an insurge and sudden PZR surge line temperature changes. {PIP C98-396l}

C98-3961}

he procedure may continue while performing Step 2.33.

2.33 Align for ND Auxiliary Pzr spray flow as follows:

~2.33.1

~ 2.33.1 valve"s are closed.

Ensure both normal spray valves oD INC-27 (PZR Spray Ctrl Frm Loop A) lNC-27 oD lNC-29 INC-29 (PZR Spray Ctrl Frm Loop B) 12.33.2 2.33.2 Verify the PZR steam space temperature is s 240°F. {PIP COO-4752}

~

---,-- 2.33.3 INV-857 (Pressurizer Aux Spray Ctrl) (lMCll)

Verify lNV-857 (1MC11) is closed.

6 12.33.4 Unlock 1NV-862 lNV-862 (ND To Pzr Spray Isol Otsd Cont) (AB-552, (AB-SS2, DD-S2, DD-52, Rm 217).

6($ L 2.33.5 Open 1NV-862 lNV-862 (ND To Pzr Spray Isol Otsd Cont).

2.33.6 Place the following breakers in the "ON" position:

1MXJ-R01D lMXJ-R01D (ND Train 1A lA Aux Pressurizer Spray Isol Valve 1ND90) lND90)

(AB-594, MM-52)

MM-S2) lMXK-R02D (ND Train 1B 1MXK-R02D lB Aux Pressurizer Spray Isol Valve 1ND91) lND9l)

(AB-S77, JJ-57)

JJ-S7)

NOTE: ~water temperature approaches saturation, the steam space temperature will quickly rise. {PIP C98-3961}

C98-396l} 22.3434 Reduce the rate of temperature increase as the PZR temperature approaches saturation to prevent exceeding 80°F per hour heatup of the PZR steam space.

-+

--+ 2.35 WHEN the PZR steam space temperature reaches 240°F, stabilize the PZR at this temperature using the PZR heaters.

Enclosure 4.1 OP!l/A/61 00/00 1 OP/l!A/61 Unit Startup Page 11 of66 2.36 WHEN the PZR steam space temperature reaches 240°F, 240 0 P, perform the following:

--*- 2.36.1 IF a nitrogen blanket was NOT placed in the PZR, 30 minutes after the PZR steam space temperature reaches 240°F,240 0 P, close the PZR PORV opened in Step 2.27.

L 22.36.2

.36 .2 Ensure lWL-805A (NCDT Pump Disch Cont Isol) Iso1) (lMC-ll) is open .

.y/- 2.36.3 Ensure an NCDT Pump is in service per OP/1/A/6500/014 (Operations Controlled Liquid Waste System).

The procedure may continue while performing Steps 2.36.4 thru 2.36.9.

~2.36.4 IF PRT pressure is greater than 8 psig, attempt to decrease the pressure to < 8 psig by lowering PRT level per OP/1/A/6150/004 (Pressurizer Relief Tank).

rJb...:!2.36.5 rJU2.36.5 IF PRT pl'essure cannot be lowered to less than 8 psig by adjusting PRT level, perform the following: {PIP C98-3961}

o 2.36.5.1 Notify Radiation Protection of the venting.

Person notified o 2.36.5.2 Connect tygon tubing (3/4 inch) to the vent at INC-51 (PRT Vent To Atmos Isol)

Iso1) (CV-565; 27'-90°, Le). LC).

o 2.36.5.3 Route the tygon tubing to the suction of an in service Containment Auxiliary Charcoal Pilter Filter Unit.

o 2.36.5.4 Open INC-51 (PRT Vent To Atmos Isol). Iso1).

o 2.36.5.5 WHEN PRT pressure is less than 8 psig, close INC-51 (PRT Vent Iso1).

To Atmos Isol).

o 2.36.5.6 Remove the tygon tubing from the vent at INC-51 (PRT Vent To Atmos Isol).

Iso1).

M~j2.36.6

vill'j

---f-2.36.6 IF NOT previously performed, establish normal operating conditions in the PRT per OP/1/A/6150/004 OP/l/A/6150/004 (Pressurizer Relief Tank).

tJ/Lt-rJ/Lt- 2.36.7 IF PRT temperature is > 120 0 P, cool the PRT to < 120 120°F, (Pressurizer Relief Tank). {PIP C98-3961}

120°F0 P per OP/1/A/6150/004

Enclosure 4.1 OP/l!A/6100/001 OP/l!Al61 00/00 1 Unit Startup Page 12 of66

---..:I-

~2.36.8 2.36.8 Notify Primary Chemistry to sample the PZR and PRT.

Person notified ~6f:. C; 1'4

.-.J0<2: ;-r 1-1

/'VIl-r1-l 1 2 .36 .9 Notify Primary Chemistry to establish a PZR steam space purge.

~6~ <; 1'4 Person notified .-.J0f:: /'VI )}-rl-l

-rl-l NOTE: ~cedure may continue while performing Step 2.37.

2.37 Complete the following steps to vent the seal return piping:

~2.37.1

~2.37.l Coordinate with Radiation Protection to minimize airborne and surface contamination.

Person notified _ _ _Rt----"--'(~!C'---'D<-=-../"--"'-'ES=-=_~_~

Rt----'-~(~!C-=--...!:D<-=--..;-=..::::ES=._~_"___

---4

---# 2.37.2 Perform the following for lNV-5lINV-Sl (NC Pump lA Seal Return Vent)

(CV-573, 35'-69°, LC):

~Remove vent valve pipe cap.

~tt1e open valve until all air is removed, then close the valve.

u(~ttle eI erReplace ErR..eplace pipe cap.

~ 2.37.3 Perform the following for lNV-62INV-62 (NC Pump IB lB Seal Return Vent)

(CV-573, 35'-130°, LC):

rr

[2( Remove vent valve pipe cap.

[J./fhrottle open valve until all air is removed, then close the valve.

[J/fhrottle Q/Replace pipe cap.

-:f- 2.37.4 Perform the following for lNV-73 (CV-573, 35'-235°, LC):

INV-73 (NC Pump lC Seal Return Vent)

~move vent valve pipe cap.

r:::t1lemove

~hrottle open valve until all air is removed, then close the valve.

[6""fhrottle kI' Replace pipe cap.

C;V

~ 2.37.5 Perform the following for lNV-84INV-84 (NC Pump lD ID Seal Return Vent)

(CV-573, 35'-316°, LC):

I2f I2f'Remove Remove vent valve pipe cap.

[2( Thyottle open valve until all air is removed, then close the valve.

~place pipe cap.

Enclosure 4.1 OP/liAl61001001 OP/l!Al6l00/00l Unit Startup Page 13 of66 al~i1iary spray provides tempering flow through the spray nozzle to allow initiation of NOTE: ND alYkiliary

~£al spray from NCPs with PZR steam space temperature greater than 240 oo P. ND

~"thaJ auxiliary P ZR spray flow must be maintained continuously to keep the spray nozzle tempered PZR and PZR spray line ~T less than 260 o0 P. {PIP COO-4752}

2.38 Establish ND Auxiliary PZR spray flow as follows:

-:I- 2.38.1 Verify Step 2.33 has been completed.

2.38.2 Open the following valve for the desired Train:

TrainA 6-d-- ~. 1ND-90 IND-90 (ND Tm A Aux Pzr Spray Isol)

OR Train B (J

(5 ~. IND-91 (ND Tm B Aux Pzr Spray Isol) 2.38.3 Maintain a steady or slowly decreasing PZR level using charging and letdown while initiating ND PZR spray.

4- 2.38.4 Adjust INV -857 (Pressurizer Aux Spray Ctrl) as necessary to establish PZR INV-857 outflow and support NC System pressure increase.

~ 2.39 Ensure the PZR outflow by verifying the following:

~xtra PZR heater capacity is energized.

~C, NY or ND PZR spray is indicated.

~ZR surge line temperatures and PZR water space temperatures are approximately equal.

4 2 .40 Verify with Chemistry that all required hydrazine additions for exceeding 250 00 P PZR temperature have been made.

Person contacted: Joe Sf"! T 51'" I J-ftt

~2.41

~2.4l Begin increasing NCS pressure using PZR heaters and ND PZR spray to between 325 and 340 psig.

Enclosure 4.1 OP/l!Al61 00/00 00100 1 Unit Startup Page 14 of66 NOTE:.....,.....l.

NOTE:...--1. 240°F PZR steam space temperature is equivalent to ~ 10 psig ofPZR pressure.

~

2. 338°F PZR steam space temperature is equivalent to ~ 100 psig ofPZRpressure.

ofPZR pressure.

42.42

-#-2.42 As PZR steam space temperature increases from 240°F to 338°F, slowly decrease PZR level to "50%.

ventin~s considered complete when PRT pressure does NOT increase with a NOTE: \ N2 ventin9fls

~ding PRT level increase.

IF a nitrogen blanket was established in the PZR, vent N2 from PZR as a steam bubble is formed:

oD WHEN NC pressure starts to increase, cycle a PZR PORV to vent the N2 to the PRT.

oD Vent PRT to WG System per OP/lIAl61 501004 (Pressurizer Relief OP/1/Al6150/004 Tank) as required to RdiefTank) maintain PRT pressure less than 8 psig.

oD Cycle PZR heaters and PORVs PORVs to limit NC System pressure to less than 100 psig until N2 venting from PZR is completed.

oD WHEN N z venting is complete, open a PZR PORV for 15 seconds to ensure pure steam exists in the PZR steam space, then close the PZR PORV.

The procedure may continue while completing Step 2.44 and 2.45.

-42.44 WHEN PZR level is at approximately 50%, adjust charging/letdown flows as necessary to maximize letdown while maintaining PZR level at approximately "50% 50% .

.:1-

...f 22.45

--t-

.45 Prior to the first NCP start ensure loose parts monitoring testing is completed by the Reactor (W/0 00897964)

Group. (W/O -:::z..

-:2..

Person contacted St: 1"f('

'6~ -rf(' U<::?().p

Enclosure 4.1 OP/l!Al6 100/00 1 OP/l!AJ6100/001 Unit Startup Page 15 of66 he procedure may continue while performing Step 2.46 thru 2.49.

2.46 Vent the Reactor Vessel head as follows:

L 2.46.1 Open the following valves to vent the r-eactor vessel head:

~C-250A G:t"l'NC-250A (Rx Head Vent Block)

[2](NC-25lB

!2lfNC-251B (Rx Head Vent) cr Ei lpTC-252B IpTC-252B (Rx Head Vent Block) mNC-253A (Rx Head Vent)

--1

~ 2.46.2

-,-- Slowly throttle open the following:

[3"'lNC-223 (Rx Vessel Head Vent To PRT Isol) (LC 574, 34'-50°, LC).

13"'INC-223

~NC-224 (Rx Vessel Head Vent and PZR Vent To PRT Isol)

(CV 572,33'-69°, LC).

L 2.46.3 WHEN a solid stream of water from the reactor vessel head vent is observed at flow glass lNCFG6230 INCFG6230 (CV-573, 28'-65°, LC), close the following valves:

[CINC-250A rClNC-250A (Rx Head Vent Block)

~ lNC-25lB INC-251B (Rx Head Vent)

~lNC-252B (Rx Head Vent Block) cr lNC-253A

[J' INC-253A (Rx Head Vent) r;YJNC-223 r;Y)NC-223 (Rx Vessel Head Vent To PRT Isol)

Iso1)

CYINC-224 tvlNC-224 (Rx Vessel Head and PZR Vent To PRT Isol) Iso1)

(CV-S72, 33'-69°, LC)

(CV-572, 2.47 Position the following breakers to "OFF": {PIP C98-4076}

o 1.. lEMXL-FlOC lEMXL-FI0C (Reactor Vessel Head Vent Valve lNC252B)

INC252B)

(AB-560, BB, 47-48, Rm 372)

({ L.

0' lEMXS-F03E (Reactor Vessel Head Vent Valve INC253A)

(AB-577, BB-49, Rm 496)

~ 1. 2.48 Place the "SSF PWR DISCONNECT FOR INC-252B" switch in the "OFF" position. This breaker is located in the "B" Train Disconnect Box in the lETA Switchgear Room.

{PIP C98-4076}

Enclosure 4.1 OP!l/A/61 00/00 1 Unit Startup Page 16 of66 2.49 Perform the following to vent the reactor vessel head 3 inch vent line:

L 2.49.1 Ensure the NCDT is no longer being used to establish normal PRT conditions.

-L

-.:I-- 2.49.2 Stop any operating NCDT pump.

2.49.3 Open the following valves:

INC-311 (Rx Vessel Head Vent Drn 1NC-311 Dm Isol) (CV-S99, (CV-599, 13'-158°, WNDW)

INC-312 (Rx Vessel Head Vent Dm (CV-S99, 13'-158°, WNDW)

Drn Isol) (CV-599, 2.49.4 WHEN level in the NCDT increases 5 to 10%, close the following valves:

=1: INC-311 (Rx Vessel Head Vent Drn INC-312 (Rx Vessel Head Vent Dm Dm Isol)

Drn Isol)

J 2.49.5 IF needed, restart an NCDT pump.

-L 2.50 WHEN requested by Primary Chemistry, realign letdown to the demineralizers by placing INV-153A (Letdown Hx Otlt 3-Way Vlv) in the "AUTO" position. (R.M.)

Chemistry contact -.>

--J rf2 5~ I T/../

f$:: 5tv'.

2.51 At 100 psig NC System pressure, perform the following:

--.:t

~ 2.51.1 Ensure Step 2.37 is completed.

-L

-.:I-- 2.51.2 Open the following valves:

ET)NV-52A (NC Pump 1A lA Seal Return)

Gr)NV-63B GY)NV-63B (NC Pump IB Seal Return) 1B IT'INV-74A (NC Pump G"'INV-74A lC Seal Return) g/INV-85B cY1NV-85B (NC Pump ID Seal Return) 1D

-:I-

-:f- 2.51.3 Ensure the following valves are open: {PIP 95-0510}

~-89A (NC Pmps Seal Ret Cont Isol) 8"'INV-91B cr'INV-91B (NC Pmps Seal Ret Cont Isol)

-L

-.:I-- 2.52 Open 1NV-101A INV-I01A (NC Pumps #1 Seal Byp) for 5 minutes and then close to vent the NC pumps #1 seal bypass lines.

Enclosure 4.1 OP!l/AJ6100/001 OP/l!A/6100/001 Unit Startup Page 17 of66 NOTE: Step 2.53 may be repeated as required to hand rotate all NCP's if necessary.

~t 2.53 IF desired, or NOT previously performed, hand rotate NC Pump(s) to aid in the prevention of rubs on #1 seal due to crud blockage as follows:

2.53.1 Ensure each NCP that requires hand rotation is red tagged per the following:

IF required for hand rotation ensure NC Pump lA red tagged

IF required for hand rotation ensure NC Pump IB red tagged

IF required for hand rotation ensure NC Pump 1C red tagged

IF required for hand rotation ensure NC Pump ID red tagged peration of the oil lift pumps shall be minimized to minimize the stress on the oil nozzles.

2.53.2 Start one associated NC pump oil lift pump as necessary to facilitate hand rotation of the desired NCP.

"NC PUMP OIL LIFT PUMP AI"

"NC PUMP OIL LIFT PUMP A2"

"NC PUMP OIL LIFT PUMP Bl"B 1"

"NC PUMP OIL LIFT PUMP B2"

"NC PUMP OIL LIFT PUMP Cl"

"NC PUMP OIL LIFT PUMP C2"

"NC PUMP OIL LIFT PUMP Dl"

"NC PUMP OIL LIFT PUMP D2" 2.53.3 Hand rotate each NC pump(s) that require hand rotation counterclockwise (looking down) per the following:

IF required hand rotate NC Pump lA

IF required hand rotate NC Pump IB

IF required hand rotate NC Pump 1C

IF required hand rotate NC Pump ID

Enclosure 4.1 OP/l!Al61 OP!lIAJ61 00100 1 Unit Startup Page 18 of66 NOTE:/. Natural circulation will begin at about 320 psig which will tend to cooldown the NC System.

--r

~ Expediting placing the NCPs in service per this procedure will minimize the NCS cool down from natural circulation.

cooldown

~ize activities that cause temperature changes to the secondary-side of the S/Gs since this will have an effect on NCS temperature.

L2.54 Operate PZR heaters as needed to increase and maintain NC system pressure pres-sure between 325 and 340 psig.

~2.55 IF desired, swap operating ND Trains such that the preferred train is in servi{;e servi{:e per OP/1/A/62001004 (Residual Heat Removal System). (R.M.)

OP/lIA/62001004 2.56 Ensure the out of service ND cold leg injection isolation valve "PWR DTSCON" the "DISCON" position.

DI'SCON" switch is in INI-173A (ND Hdr To Cold Legs C and D)

OR

-#- - INI-178B (ND Hdr To Cold Legs A and B) lNI-178B Th~llowing step shall NOT be performed until the hand rotation of CAUTION: Thsfollowing the NC Pumps is ofthe

/mpleted and all personnel are cleared from the area.

2.57 Per the startup requirements rack in the following required NC Pump breakers per OP/OIA/63501010 (Operation of Station Breakers and Disconnects):

of'Station RCP lA (Reactor Coolant Pump Motor lA)

RCP IB (Reactor Coolant Pump Motor IB)

RCP 1C (Reactor Coolant Pump Motor 1C)

RCP ID (Reactor Coolant Pump Motor ID)

Enclosure 4.1 AJ61 00100 1 OP!l/Al6100/001 opill Unit Startup Page 19 of66 NOTE: .v

.J.! Starting an NC Pump in the next step will initiate mixing of the NC System which will cause NC System temperature to decrease.

- . / NC Pump 1A

-./." lA or 1B IB are the preferred NCP's to be placed in service in Step 2.'58 2:58 or Step 2.60.

~ The NCP flow transmitters may not be available due to lAB IAE removing the NCS Nitrogen Rig fittings.

fittings .

..4.-'"

~ Closing 1NM-26B INM-26B (Hot Leg Smpl Smp1 Hdr Cont Isol)

Iso1) prior to starting NC Pumps will prevent the transfer of crud to the hot leg sample line.

-5. Starting an NC Pump may induce a crud burst. Ifpossib1e, 5.&tarting Ifpossible, it is recommended that NC Pumps NOT be started until only one train ofND is in service. PIP C-03-4966 2.58 2.'58 Start an NC Pump as follows: (R.M.)

~ 2.58.12.'58.1 Notify Primary Chemistry that 1NM-26BINM-26B (Hot Leg SmplSmp1 Hdr Cont Isol)

Iso1) will be closed.

Of:: "rv.

Person notified .......1JUt::. "(V. If rJ

~J

-X 22.58.2

-1 .58 .2 Close 1NM-26B INM-26B (Hot Leg Smpl Smp1 Hdr Cont Iso1).

Isol).

~ 2.58.3 OP/1/Al6150/002A (Reactor Coolant Pump Start the first NC Pump per OP/1/AJ61501002A Operation).

Document NC Pump started and time of start 0L 0 0 (:)

NOTE: ~he

-Y'The following step provides a conditional option in case the second NCP has been started insi~e inside t e 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months window following the first NCP start.

~edureProcedure may continue while waiting to perform Step 2.58.4.

~ 2.58.4 WHEN greater than 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months has elapsed since starting the first NC Pump, perform the following:

J 2.'58.4.1 2.58.4.1 IF the second NC Pump has NOT been started, open 1NM-26B Smpl Hdr Cont Isol).

Leg Smp1 INM-26B (Hot

Enclosure 4.1 OP/l!Al6100/001 Unit Startup Page 20 of66 rocedure may continue while performing Step 2.59.

NOTE: \./Procedure 442.59 2 .5 9 Adjust the appropriate valve for the ND Train in service to maintain ND HX inlet temperature as high as possible without exceeding 200 00 P:

~D-26 (ND Hx lA Outlet Ctrl)

OR D IND-60 (ND Hx IB Outlet Ctrl)

NOTE~

NOTE':"-y' Starting an NC Pump in the next step will initiate mixing of the NC System which will cause NC System temperature to decrease.

~ is recommended that NC Pump lA or IB be placed in service in Step 2.58 thatNC 2.'58 or Step 2.60.

k~ The NCP flow transmitters may not be available due to IAElAE removing the NCS Nitrogen Rig fittings.

~Closing INM-26B (Hot Leg Smpl Hdr Cont Isol) prior to starting NC Pumps will prevent the transfer of crud to the hot leg sample line.

Y s:-' Starting an NC Pump may induce a crud burst. If possible, it is recommended that NC Pumps NOT be started until only one train ofND is in service. PIP C-03-4966 L 2.60 1-2.60 IF desired, start the second NC Pump as follows: (R.M.)

~.60.1 v\/I J ~.60.1 IF NOT already closed, notify Primary Chemistry that INM-26B (Hot Leg Smpl 7--l "" Hdr Cont Isol) will be closed.

Person notified - - - - - -

~1 -., 2.60.2 IF NOT already closed, close INM-26B (Hot Leg Smpl Hdr Cont Isol).

1 2 .60 ..33 Start the second NC Pump per OP/1IA16150/002A (Reactor Coolant Pump Operation).

start~_O_£_{)_O Document NC Pump started and time of start. _ _O_b_O_O___

Enclosure 4.1 OP/l;A/61 00/00 OP!l/A/61 00/0011 Unit Startup Page 21 of66 rocedure may continue while performing Step 2.60.4.

2.60.4 WHEN greater than 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months has elapsed since starting the second NC Pump, perform the following:

1. 2.60.4. 1

--1. Open lNM-26B INM-26B (Hot Leg Smpl Hdr Cont Isol).

J 2.60.4.2 Notify Primary Chemistry that lNM-26B INM-26B (Hot Leg Smpl Hdr Cont Isol) is open.

Person notified J Q (j '0

\& SJV\W I~

SJV\rf

::f- 2.61 Notify RES Engineering that 2 NCP's are in service and RVLIS data can be checked for accuracy.

Person notified 6e fl'e "'-.)

f"-J Sf) srI L~ Ss NOTE: he procedure may continue while performing the Step 2.62.

1- 2.62 Adjust charging and letdown to slowly reduce PZR level to 25%.

Enclosure 4.1 OP/liA/6100/001 OP!lIA/61 00/001 Unit Startup Page 22 of66 2.63 WHEN PZR spray line ilT ~T is less than 260°F, establish normal PZR spray flow as follows:

NOTE: .-t.....-t. It is desirable to only have two NCPfs NCP's in operation until ND is secured in Mode 4.

~p 2.63.1 is to ensure normal spray flow is available to the pressurizer.

--.:t-

--.:!.- 2.63.1 Ensure either NCP 1A and/or NCP 1B is in service per OPIlIAI61S01002 (Reactor Coolant Pump Operation).

OP/1/A/61S0/002 A 2.63.2 Verify VerifY the following valves in "MAN":

~:

1NC-27 (PZR Spray Ctrl Frm Loop A) 1NC-29 (PZR Spray Ctrl Frm Loop B) 2.63.3 va1ve(s) as needed in the loop for the pumps that were Open the pressurizer spray valve(s) verified in service in Step 2.58 2.:58 or 2.60 as follows:

For NC Pump 1A:

~. 1NC-27 (PZR Spray Ctrl Frm Loop A)

For NC Pump 1B:

1NC-29 (PZR Spray Ctrl Frm Loop B)

--.:t- 2.64

--.:!.- Record below the time for placing normal PZR spray in service in the previous step.

Time:

Enclosure 4.1 00100 1 OP/l!A/6100/001 OP!lIA/61 Unit Startup Page 23 of66 2.65 Secure ND auxiliary spray flow as follows:

12.65.1 WHEN pressurizer spray from the ND System is no longer needed, ensure lNV-8S7 (Pressurizer Aux Spray Ctrl) is closed.

INV-857

~ 2..65.2 65 .2 Close lNV-862 INV-862 (ND To Pzr Spray Isol Otsd Cont).

d-(J- ~ 2.65.3 INV-862 (ND To Pzr Spray Isol Otsd Cont).

Lock lNV-862 2.65.4 Ensure the following valves are closed:

~ -1. 1IND-90 ND-90 (ND Tm A Aux Pzr Spray Isol)

.2:S... .

---.2S... -#-. IND-91 (ND Tm B Aux Pzr Spray lND-91 Spraylsol)

Isol) 2.65.5 Place the following breakers in the "OFF" position.

6 If . IMXJ-ROID (ND Train lA Aux Pressurizer Spray Isol Valve IND90) lMXJ-R01D

~ 1. IMXK-R02D (ND Train IB Aux Pressurizer Spray Isol Valve IND91) lMXK-R02D

~ 2.66 Ensure the PZR outflow by verifying the following:

D-1fxtra r::vtfxtra PZR heater capacity is energized.

[;}-"NC, NV or ND PZR spray is indicated.

~ surge line temperatures and PZR water space temperatures are approximately equal.

~-;fJ 2.67 Notify Primary Chemistry to perform the following:

!6r6 Sample NC System hot leg for Dissolved Oxygen (D.O.)

[2( Sample PZR for Dissolved Oxygen (D.O.)

Person notified S/VI l-r

.JCE.. S""

...JcE. I""" HH

...-Y. It is desirable to only have two NCPs in operation until ND is secured in Mode 4.

NOTE: .-t:' 4.

..-i

-d. Starting an NC Pump may induce a crud burst. Ifpossible, it is recommended that NC Pumps NOT be started until only one train ofND is in service. PIP C-03-4966

~

A":" Closing INM-26B (Hot Leg Smpl Hdr Cont Isol) prior to starting NC Pumps will prevent the transfer of crud to the hot leg sample line.

12.68 1 2.68 Operate NC Pumps as desired per OP/l/A/6l501002 OP/1/A/6150/002 A (Reactor Coolant Pump Operation).

(R.M.)

Enclosure 4.1 OPIl!A/61 00100 1 OP;1/A/6l00100l Unit Startup Page 24 of66 NOTE: ~waste Chemistry will begin regas of the NC System after the hydrazine has been added, the NC Pumps are in service, and NC System oxygen is in spec.

~procedure may continue performing Step 2.69.

-.:J.-

--:I- 2.69 WHEN notified by Radwaste Chemistry, establish a H2 or N2 blanket on the NCDT per OP/lIAI65001014 (Operations Controlled Liquid Waste Systems).

OP/lIA/650010l4 NOTE: l.../The L./The VCT pressure shall be maintained as low as possible until notified by Chemistry that the VCT gas space H2 concentration is acceptable. At that time they will request Operations to adjust the H2 regulator for approximately 35 psig.

2~e procedure may continue while performing Step 2.70.

2.70 Establish a H2 purge of the VCT as follows:

4- 2.70.1 Notify Radwaste Chemistry that a H2 purge of the VCT may be established per OP/OIA/65001003 (Radwaste Chemistry Operating Procedure for the Gaseous Waste (WG) System).

--.loe.. SIV\

...Joe.. <;'cv\ I'fl...l Person notified~------~=-~~~-------

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

l' (J 12.70.2 WHEN notified by Chemistry, adjust the H2 regulator as requested to establish the desired purge flow.

Person making notification J ILL \ Jl..{)..>. Lt.. S 5> Jl-f'

-:J- 2.71 While plant heatup is in progress, periodically reset the A & B SID Margin Monitor System "Alarm Setpoint" to prevent a system activation.

NOTE: --FiR

--PZR outflow shall be maintained until the PZR and NC System heatup is complete.

---...:!- 2.72 Energize extra PZR heater capacity as necessary to achieve an outflow from the PZR.

-L 2.73 Ensure the PZR outflow by verifying the following:

Extra P ZR heater capacity is energized.

PZR

NC, NV or ND PZR spray is indicated.

PZR *surge line temperatures and PZR water space temperatures are approximately equal.

PZR spray valve for idle NC Pumps closed.

Enclosure 4.1 OP/liAl6100/001 OP/l!Al61 001001 Unit Startup Page 25 of66 NOTE: ~ng plant heatup, count rate on source range instruments will increase due to increased n4ng

'~e:;on leakage, causing the hi flux at shutdown alarm to be reached, requiring lAE to

'~:U;~on periodically reset the alarm setpoint.

--.:!- 2.74

-.:!- IF the Boron Dilution Mitigation System is inoperable, ensure the source range monitors are placed in service per OP/1/Al63S0/013 OP/lIAl63S01013 (Source Range Detector).

~2.75 IF two ND trains are in operation, secure one train ofND per OP/1/Al6200/004 OP/lIAl62001004 (Residual Heat Removal System).

--.:!- 2.76

-.:!- IF both trains ofKC are in operation, secure the KC train corresponding to the ND train secured in Step 2.75 per OP/1IA16400/005 OP/lIAl64001005 (Component Cooling System).

2.77 Prior to exceeding 200°F NC temperature, do the following:

L L 2.77.1 Ensure S/G(s) are removed from wet layup recirculation with S/G no-load levels established per OP/1IA16250/003 OP/lIAl62501003 A (Steam Generator Cold Wet Layup Recirculation).

NOTE: The procedure may continue while performing Step 2.77.2, if applicable.

L L 2.77.2 IF N2 was aligned to the S/G's per OP/lIA/61 00/002 (Controlling Procedure For OP/l/A/6 1001002 Unit Shutdown), verify N2 is isolated to the S/G's as follows:

L. Close IGN-94 (N2 To S/G Wet Layup Unit 1 Isol) (AB-57 (AB-571,1, DD-EE, 52-53, Rm 333).

NOTE: -.-SteP 2.77.2.1 through Step 2.77.2.4 maymaybe be performed in any order.

2.77.2.1 For S/G lA (DH-582, FF-44):

A. Close the following valves:

~

r "1 *

lSM-113 I SM-113 (N, To S/G 1lA ISM-73 (N2 To S/G lA).

A Outlet Hdr Supply)

---ii- -*

--il.- -#- B. Lock ISM-73 (Nz(N2 To S/G lA).

~ C. Verify lAB has removed temporary gauge installed at ISMPT5520 per Model W/O # 00887893.

J D. Verify MM has installed ISM-117 (N2 To S/G lA Wet Layup Check) internals per Model W/O # 00887893.

Enclosure 4.1 OP/liA/6 100/00 1 OP/l!Al61001001 Unit Startup Page 26 of66 2.77.2.2 For S/G lB IB (DH-582, FF-53):

A. Close the following valves:

lSM-112 ISM-1I2 (Nz To S/G lB IB Outlet Hdr Supply)

lSM-72 ISM-72 (Nz To S/G lB).

IB).

B. Lock lSM-72 (N2 To S/G IB).

ISM-72 (Nz c.

C. Verify IAE has removed temporary gauge installed at SMPTS5 10 per Model W/O # 00887894.

1ISMPTS510 D. Verify MM has installed lSM-116 ISM-1I6 (N2 To S/G lBIB Wet Layup Check) internals per Model W/O # 00887894.

2.77.2.3 For S/G lC IC (DH-579, FF-52):

A. Close the following valves:

~

ISM-Ill (N2 To S/G lC ISM-lIl IC Outlet Hdr Supply) d ~

lSM-7l ISM-7I (Nz To S/G lC).

IC).

c B. Lock lSM-7l ISM-7I (N2 To S/G lC).

IC).

4-

~ C. Verify IAE has removed temporary gauge installed at ISMPT5500 per Model W/O # 00887895.

lSMPT5500 D. VerifyMM Verify MM has installed ISM-lIS (N2 To S/G IC Wet Layup Check) internals per Model W/O W/0 # 00887895.

2.77.2.4 For S/G ID (DH-578, FF-44):

A. Close the following valves:

ISM-UO (N2 To S/G ID Outlet Hdr Supply)

ISM-lIO

ISM-70 (N2 To S/G lD).

lSM-70 ID).

B. Lock lSM-70 ISM-70 (N2 To S/G lD).

ID).

C. Verify IAE has removed temporary gauge installed at SMPT5490 per Model W10 1I SMPTS490 /0 # 00887896.

D. VerifyMM Verify MM has installed lSM-ll4 ISM-114 (N2 To S/G ID Wet Layup Check) internals per Model WIO W10 # 00887896.

Enclosure 4.1 OP/l!A/6100/001 Unit Startup Page 27 of66 NOTE: Step 2.5 had the operator initiate an Increased Surveillance and complete Enclosure 4.12 (S~ndary Heatup Checklist) in preparation for NC 'System heatup. The positions of the

~e~mline drain valves listed on Enclosure 4.12 will need to he be coordinated with steps in this enclosure to maintain control of the positions of these. Step 2.184 will restore valves positioned per Enclosure 4.12 and secure from the associated Increased Surveillance.

2.77.3 Open the following valves: (lMC2)

~L. ISM-74B (S/G ID Otlt Hdr Bldwn CN)

--d:- . 1ISM-75A SM -75A (S/G 1lCC Otlt Odt Hdr Bldwn CN) o0' ~. 1ISM-76B SM-76B (S/G IB Otlt Odt Hdr Blwdn CN)

~ ~. 1ISM-77A SM -77A (S/G lA Otlt Odt Hdr Bldwn CN).

~ 2.77.4 blowdown Ensure S/G blow down is aligned as recommended by the SecondalY Secondary Chemist per OP/1/Al6250/008 OP/l/A/6250/008 (Steam Generator Blowdown) .

.:I-

.:f!- 2.77.5 Maintain S/G level at 39% NR level using one of the following methods:

~F bypass valve oD Manual operation ofofCA CA per OP/1/

OP/1/A/6250/002 A/6250/002 (Auxiliary Feedwater System).

~ 2.77.6 Place the following "Auto/Open" switches in the "OPEN" position:(rear of IMC9) cY')SM-89 (S/G lA Otlt Bldwn OrifByp) ct')SM-89 B'

B" ISM-88 (S/G IB OtltOdt Bldwn OrifByp)

I2(jSM-87 (S/G lC Odt I2r)SM-87 Otlt Bldwn OrifByp) c;YlSM-86 (S/G ID Otlt Bldwn OrifByp).

C:VlSM-86

-:t 2.77.7 Verify open indication (rear of IMC9) to ensure the following drain valves are open:

Gi..sM-89 01..sM-89 (S/G lA Otlt Bldwn OrifByp) mSM-88 (S/G IB Otlt Bldwn OrifByp)

WlS~ (S/G lC Odt Otlt Bldwn OrifByp)

G:nSM-86 (S/G ID Odt G:YlsM-86 Otlt Bldwn OrifByp).

Enclosure 4.1 OP;1/A/61 00100 OPIl!A/61 00/0011 Unit Startup Page 28 of66 CAUTI~ Main steamline drains shall be open for at least 15 minutes prior to opening MSIVs or MSIV Bypasses.

NOTE: If~ain Turbine warming is being performed using AS from the opposite Unit and the NC

~tem heatup will be performed with the MSIV's closed, Steps 2.77.8 - 2.77.12 are to be

...-BYStem N/A'd.

~ 2.77.8 Open the following valves:

[3' ISM-132 (SM Equalization Hdr Trap T-05 Byp) (TB-594, IH-32) 0' ISM-139 (SM Equalization Hdr Trap T-06 Byp).(TB-594, IH-32)

Ei

-:I-

--:I- 2.77.9 After 15 minutes, close the following valves:

r:::(

r:( ISM-132 (SM Equalization Hdr Trap T-05 Byp) m.SM-139 (SM Equalization Hdr Trap T-06 Byp).

G11SM-139 J

-12.77.102.77.10 Slowly open the following valves:

~J$M-9 (S/G ID SM Isol Byp) fflSM-10 (S/G lC SM Isol Byp)

[3/I;;M-ll W1.$M-ll (S/G IB SM Isol Byp)

B'lSM-12 mSM-12 (S/G lA SM Isol Byp).

CAUTION ~f after the 30 minute wait pressure is still trending down, the MSIV shall NOT be CAUTION:Jf opened until steam line pressure is no longer trending down.

~ 2.77.11 After 30 minutes, open the following valves:

~V;M-l B'lpM-l (S/G ID SM Isol)

CY'iSM-3 cYiSM-3 (S/G lC SM Isol)

[YlSM-S IT"ISM-S (S/G IB SM Isol) g......}-8M-7 g......r.gM-7 (S/G IA SM Isol).

lA

-.:1-

--.:1- 2.77.12 WHEN the SM isolation valves are fully open, close the following valves:

B'l"SM-9 (S/G ID SM Isol Byp)

B'lSM-9 D---fSM-I0 (S/G lC cvrSM-I0 IC SM Isol Byp) c}"" ISM-II (S/G lB C;V IB SM Isol Byp)

CYrSM-12 (S/G lA SM Isol Byp).

Enclosure 4.1 OP!l/A/6100/o01 OP;1/A/6l00/00l Unit Startup Page 29 of66

--- 2.77.13 Place the following "Auto/Open"switches "Auto/Open" switches in the "AUTO" position to return main steamline drain control to auto:

~M-89 (S/G lA Otlt Bldwn OrifByp)

[2( lSM-88 (S/G lB Otlt Bldwn OrifByp) mSM-87 (S/G lC Otlt Bldwn OrifByp)

Q-"lSM-86 WlSM-86 (S/G lD Otlt Bldwn OrifByp).

4- 2.77.14 Complete the following enclosures:

cr~nclosure 4.4 (Operations Mode 4 Checklist) o Enclosure 4.5 (Support Mode 4 Checklist).

--.::!I- 2.77.15

--.::f!- Align S/Gs for reverse purge flow as follows:

2.77.15.1 Open the following valves:

WfiCF-90 (S/G lA CF Cont Isol Byp) 0-- lCF-89 (S/G lB CF Cant 0-" Cont Isol Byp) g/ lCF-88 (S/G lC CF Cont Isol Byp)

~ lCF-87 (S/G lD CF Cant

{2( Iso1 Byp)

Cont Isol

~

Ef lCA-185 (S/G lA CA Nozz Tempering Isol) Iso1)

~./ lCA-186 (S/G 1B lB CA Nozz Tempering Iso1) 1Lr.

Ea". lCA-187 (S/G lC CA Nozz Tempering Isol)

Iso1)

[i' lCA-188 (S/G lD CA Nozz Tempering Isol).

Iso1).

NOTE: he procedure may continue while performing Step 2.77.15.2 thru 2.77.15.6.

Er 2.77.15.2 EY Open lCM-839 (S/G Warming Isol To Cond lA) to initiate S/G reverse purge flow .

/"""'

[d--L.77.15.3 c::Y2.77.15.3 lCA-223 (S/G 1A Close 1CA-223 lA CA Nozzle Tempering Flow Isol)

Iso1) (DR-589, EE-45, Rm 591).

I2r 2.77.15.4 0' Close lCA-226 (S/G lD CA Nozzle Tempering Flow Isol) (DR-589, (DR-S89, EE-45, Rm 591).

[d 2.77.15.5 Close ICA-224 lCA-224 (S/G lB CA Nozzle Tempering Flow Isol) (DR-S88, Iso1) (DR-588, DD-52, Rm 572).

[zj rzj 2.77.15.6 Close lCA-225 (S/G lC CA Nozzle Tempering Flow 1'801)

Isol) (DR-SS8, (DR-588, DD-52, Rm 572).

Enclosure 4.1 OP/l!AJ61 00/001 OPlliAJ61001001 Unit Startup Page 30 of of66 66

~2.77.15.7 EJ"2.77.15.7 Record the temperature for the following OAC points: (OAC Group Display GD OPCFTEMP)

CIA0141 (S/G A After CF Isol Vlv Line Temp) ) 95

CIA0148 (S/G A Inlet Temp (Feedwater)) /11 111

CIA0125 (S/G B After CF Isol Vlv Line Temp) 86"77

CIA0154 (S/G B Inlet Temp (Feedwater)) f<t'f l<i'l

CIA0275 (S/G C After CF 1'801 1"801 Vlv Line Temp) ---.t3..:L

~1'7 1

C]

CIA0160 (S/G C Inlet Temp (Feedwater)) ~

CIA0815 (S/G DAfter CF Isol Vlv Line Temp) --1..9Z..

~

CIA0166 (S/G D Inlet Temp (Feedwater)) ~

~7.15.8 Monitor OAC Group Display OPCFTEMP for increasing temperatures as a sign of reverse purge while continuing with the procedure.

~ 2.77.16 IF boration necessary to establish boron concentration determined in Step 2.2, then perform the following: (RM.)

I2f'

!2( 2.77.16.1 Borate the NC System per OP/1/AJ6150/009 OP/lIAJ61501009 (Boron Concentration Control).

E1 2.77.16.2 Ef Energize PZR heaters as necessary to provide PZR spray flow for equalizing PZR and NC System boron concentration.

J- 2.77.17 Remove any temporary temperature alarms installed on the following OAC (TEMP ALM) points: (TEMPALM)

[3'" r~4 (ND Pmp B Discharge Temp)

GY

~lAo9io (ND Pmp A Discharge Temp).

cr<:iA09io

~ 2.77.18 Review the OAC points that will be in alarm in Mode 4 by using the OAC "Plant Mode" application to perform an alarm look ahead.

L2.78 Notify IAE to verify there is no leakage at the seal table.

Person notified J306 V /L L A

~2.79 Prior to entering Mode 4, do the following:

~otify the Security Lieutenant or designee that Unit 1 is entering Mode 4.

GYNotify Person notified ~\

C::s- JD~

j D~

~Notify the Secondary Chemist to verify that the S/G chemistry is acceptable.

Person notified D~

....... ) Dr; 5M 171-(" H Wcomplete the Unit 1 Control Room Indication Checklist, OMP 2-22 (Shift Turnover).

Enclosure 4.1 OP!l/Al61 00/001 OP/l!Al6100/001 Unit Startup Page 31 of66

-:J- 2.80 While plant heatup is in progress control T-AVG using S/G blowdown, S/G reverse purge, turbine wanning, S/G PORV's, PORV's, or condenser steam dumps.

NOTE:----rhe' NOTE:-----rhe" Outage Guidelines will provide details on when to secure the last train ofND.

---.:I-

.:f!- 2.81 IF desired, secure the last train ofND per OP/lIA/62001004 OP/IIA/6200/004 (Residual Heat Removal System).

---:I- 2:82

--t- Prior to entering Mode 4 ensure all Steps in Step 2.79 complete.

--.:!.- 2.83 Record Mode 4 entry time.

Mode 4 1'2-06

=--

=---

2.84 After entering Mode 4, change the OAC to "Mode 4" by using the OAC "Plant Mode" application.

~2.85 After entering Mode 4, change DCS to "Mode 4" by using DCS graphic 6012 (PLANT MODE SELECTION).

12.86 Prior to exceeding 250°F NC System temperature, notify the Primary Chemist to verify that the NC System chemistry (dissolved oxygen and sulfates) is acceptable to continue heatup.

(SLC 16.5-3)

Joe:; ~! _ _'____!T~

Person notified _ _--'J=-=O:::...>,;;;f;'---_~ LI_~+__---------

---.:!- 2.87

--.:!- While perfonning the following step maintain a PZR outflow per Steps 2.72 and 2.73.

/

.,,;fhe ND System shall be secured prior to 250°F in Step 2.88 to prevent the water in the NOTE: ../fhe suction pipes ofND flashing to steam when aligned from the FWST.

~ 2.88 Prior to exceeding 250°F, ensure the operating train ofND is secured and align for standby OP/IIA16200/004 (Residual Heat Removal System).

readiness per OP/lIAl62001004 2.89 IEMF-39 setpoints have been reset as follows:

Ensure lEMF-39 1

1 1 21. 8 92.89.1 .1 Trip 2 = 3 X Containment Atmosphere Activity (sampled at lower Containment) as indicated by EMF allowing 15 minutes for indication to stabilize.

1~ L L2.89.2 2.89.2 Trip 1I == Trip 2 X .70.

~ 2.89.3 Log the new setpoints for lEMF-39 in the EMF Logbook.

Enclosure 4.1 OP!l/AJ6100/001 OPiliAl61 00100 1 Unit Startup Page 32 of66

'!&t

"!&t 2.90 IF NOT already performed, perfonned, prior to closing the reactor trip breakers with the rods capable of withdrawal, review TSAIL to ensure that none of the items listed below are entered as ofthe inoperable and ensure surveillances are current per the listed work orders below: {PIP 97-2423}

D Manual Reactor Trip (TS.3.3.1) WO# 00880613 D Reactor Trip Breaker Train A (TS.3.3.1) WO# 00880225 or 00897998 D Reactor Trip Bypass Breakers Train A (TS.3.3.1) WO# 00880225 or 00897998 D Reactor Trip Breaker Train B (TS 3.3.1) WO# 00874198 or 00897999 D Reactor Trip Bypass Breakers Train B (TS 3.3.1) WO# 00874198 or 00897999 D Automatic Trip and Interlock Logic Train A (TS.3.3.1) WO# 00880223 or 00897996 D Automatic Trip and Interlock Logic Train B (TS.3.3.1 WO# 00874197 or 00897997 D Digital Rod Position Indication System (SLC (,SLC 16.7-11) WO# 00874186 D Source Range, Neutron Flux (TS 3.3.1). WO# 00874212,00874313,00880078, 00874212, 00874313, 00880078, 00874209,00874318 and 00880076 NOTE: ~ocedure may continue while perfonning performing Step 2.91 and 2.92.

-4 22.9191 Ensure CRDM fans are in service as required per OP/1/AJ6150/008 OP/lIAl61501008 (Rod Control).

-42.92

-42.92 OPIlIAl61501008 (Rod Control).

Ensure rod control system started per OP/1/AJ6150/008 rJ/~~

rJJl!~ 2.93 IF the Boron Dilution Mitigation System is inoperable, ensure Hi flux at shutdown a1annalarm setpoints are reset prior to withdrawing shutdown rods.

L2.94 IF the Boron Dilution Mitigation System is operable, perform perfonn one of the following prior to withdrawing shutdown rods:

D Ensure Hi flux at shutdown alarm a1ann setpoints are reset OR ra--1Iace "HI FLUX SHUTDOWN" switches to "BLOCK" AND enter SR Hi flux at g-1lace shutdown in the TSAIL as a tracking item for TS 3.3.9

~U2.95 IF Shutdown Bank A & B rods will be withdrawn AND cycle burnup bumup (C1P1457) > 350 K -eff < 0.99 for 400°F per OP/OI EFPD, verify K-eff Ai6100/006 OP /0/AJ61 001006 (Reactivity Balance Calculation). (R.M.)

~2.96 IF conditions allow, withdraw Shutdown Bank A & B rods to provide trippab1e trippable rod worth OPIlIAl61501008 (Rod Control). (R.M.)

per OP/1/AJ6150/008

Enclosure 4.1 OP/1IA161 00/001 OP/l!Al61001001 Unit Startup Page 33 of66 CAUTION~ exceed 360 psig in Low Pressure Mode to prevent opening PZR PORVs.

{PIP 95-0185}

-1 2.97 While heatup and pressurization the NC System is in progress maintain NCS parameters within the limits specified by Figures 44 and 45 of the Unit One Revised Data Book.

ofthe (R.M.)

2.98 WHEN all T-COLDs are greater than 210°F, do the following:

---:I-

~ 2.98.1 Ensure two charging pumps are operable (SLC 16.9-10).

~ 2.98.2 Ensure two boron injection flow paths are operable (SLC 16.9-8) by ensuring PTIlIA/42001006 A (Boron Injection Valve Lineup Verification) has been PT/lIA/42001006 completed within its surveillance interval.

~ 2.98.3 Verify the YD System is in its normal alignment per OP/O/B/64001065 OP10/B/64001065 (Drinking

r-

---r- Water System) with system pressure ,::::50 psig. (SLC 16.9-24)

~DPG52S0 (SB-594, T-16117)

~DPG5250 OR o OYDPG5270 (SB-S94, (SB-594, T-16117)

-:1 2 .99 Continue NC System heatup and pressurization within the limits specified by Figures 44 and 45 of the Unit One Revised Data Book.

Enclosure 4.1 Opll/A/6100/001 OPil/A/6 100/00 1 Unit Startup Page 34 of66

-:!- 2.100

-:I- Verify S/G(s) reverse purge flow byperfonning by perfonning the following:

~00.1 Record the temperature for the following OAC points: (OAC 'Group Group Display GD OPCFTEMP)

ClA014l CIA0141 (S/G A After CF Isol Vlv Line Temp)

ClA0148 CIA0148 (S/G A Inlet Temp (Feedwater))

CIAOl25 CIA012'S (S/G B After CF Isol Vlv Line Temp)

ClA0154 CIA0154 (S/G B Inlet Temp (Feedwater))

ClA0275 (S/G C After CF Isol Vlv Line Temp)

CIA027'S

ClA0160 (S/G C Inlet Temp (Feedwater))

CIA0160

ClA08l5 (S/G DAfter CF Isol Vlv Line Temp)

CIA0815

CIA0166 (S/G D Inlet Temp (Feedwater))

ClA0166 e(2.100.2 Compare the values recorded above to the values recorded in Step 2.77.15.7 to verifY reverse purge (increasing temperature).

verify

~~

n~ IF no sign of reverse purge, detennine what is causing the loss of reverse purge and correct the problem.

~.100.4 Monitor OAC Group Display OPCFTEMP for increasing temperatures as a sign of reverse purge while continuing with the procedure.

12.101 WHEN NC temperature greater than 210°F, do the following:

2.101.1 Select "NORM" on the following:

~RV Mode Sel NC-34A"

[Y"'PORV Mode Sel NC-32B".

2.101.2 VerifY the following valves are closed:

Verify E1 lNI-439B

[::f (EmerN2 INI-439B (Emer N z From CLA B To lNC-32B)

INC-32B)

CJ-tNI-438A CJ.-tNI-438A (Emer N2 From CLA A To lNC-34A).

INC-34A).

NOTE: A challenge to LTOP may occur due to the single failure loss of lEPA resulting in lNC-34A and lNV-lOA INV-IOA failing closed (UFSAR 5.2.2.2). If lNV-llA INV-IIA or INV-13A is also open, the 10s~lEPA will NOT result in both INC-34A failing closed and a total loss ofletdown.

~C-34A shall be logged inoperable for LTOP if the only letdown path aligned is via the variable orifice. INC-34A shall be logged or tracked in TSAIL based on the letdown C-OI-0545}

alignment. {PIP C-Ol-OS4S}

Gr1101.3 GYilO1.3 Verify VerifY PZR PORVs operable and logged appropriately per TS 3.4.12.

Enclosure 4.1 OP/I/A/6100/001 OP/VA/61 00/001 Unit Startup Page 3:5 3S of 66 of66 NOTE:?

NOTE: 7 When NC System pressure is greater than or equal to 1000 psig, steps 2.117 and 2.118

/ / can be performed at the same time as Step 2.102 .

yo y o ensure optimum NC System pressure boundary check valve leak test conditions, it is r-ecommended recommended that NC pressure be increased to the required value quickly (higher dp will seat valves better) and the test performed as soon as the required test pressure is obtained (lower temperature at NI valves will result in less flashing). (PIP C-03-496S) i--1 2.102 pressure IF NC System pressure boundary check valve leak testing is required, increase NC System to between 1000 to 1400 psig while maintaining NC System temperature less pressure to between 1000 to 1400 psig while maintaining NC System temperature less o P.

3S0oP.

than 350 NAt- 2.103 IF CA is being used for S/G feed AND it is desired to continue feeding the S/G's with CA Pumps, do the following:

o 2.103.1 N/A and initial Steps 2.105.1 and 2.105.2.

o 2.103.2 NotifySecondary Notify Secondary Chemistry of the source of water being used to feed the S/Gs.

Person notified

-:I- 2.104 Maintain a PZR outflow per Steps 2.72 and 2.73 while performing the following step.

CAUTION: Stroking CF Containment Isolation Valves (CF-33, CF-42, CF-51, CF-60) during heatup m~ cause them to stick in the closed position during nozzle transfers. To prevent this, it m9'

~recommended that these valves NOT be cycled unless final feedwater temperature>

250°F and pressure> 1000 psig.

2:50°F 2.105 WHEN desired, place a CF Pump in service as follows:

J 2.105.1 Place one CF pump in operation per OP/1/A/6250/001 Feedwater System).

OP/1IA/6250/001 (Condensate and J2.105.2 IF desired, place the CFPT speed control in auto as follows:

NOTE:~PT speed is less than minimum speed of3800 RPM for auto control, the CFPT speed will increase to 3800 RPM after performing the following step.

~.1 Place the "CFPT 1A (lB) Speed Ctrl" for the operating CFPT in auto.

i 2.106

--1 While heatup is in progress monitor the CF pump discharge pressure.

L 2.107 PT/O/A/41:50/019 B (NC IF requested by Duty Rx Group Engineer, perform dilution per PT/0/A/41501019 System Dilution Following Refueling). (R.M.)

Enclosure 4.1 OP/l!A/61 00/001 Unit Startup Page 36 of66 NOTE: liNC System pressure is to remain greater than or equal to 1000 psig, then the CLAs shall be

~ligned per Step 2.110 prior to entering Mode 3.

-f 2.108 Prior to exceeding 350°F NC System temperature, do the following:

~Complete Enclosure 4.6 (Operations Mode 3 Checklist).

Gi

~omplete Enclosure 4.7 (Support Mode 3 Checklist).

~otif)r

~otify the Security Lieutenant or designee that Unit 1 will be entering Mode 3 and the SSF is in degrade due(;;.the CAPT.

Person notified l\ --.J

~U uE

~Review the OAC points that will be in alarm in Mode 3 by using the OAC "Plant Mode" Er"Review application to perform an alarm look ahead.

+

-#- 2.109 2.109 Continue NC System heatup and pressurization within the limits specified by Figures 44 and 45 of the Unit One Revised Data Book.

NOTE: St~ 2.110 may be performed with pressure greater than 1000 psig following the performance St9J

,/'()fNC

"...-ofNC System pressure boundary check valve testing, since the unit may enter Mode 3 with pressure greater than 1000 psig.

~ 2.110 With NC System pressure between 800 psig and 1000 psig, open the cold leg accumulator OP/lIA/6200/009 (Cold Leg Accumulator Operation). (R.M.)

discharge valves per OP/1/A/6200/009 4- 2.111 Record Mode 3 entry time below:

Mode 3 2.112 After entering Mode 3, change the OAC to "Mode 3" by using the OAC "Plant Mode" application.

--:I- 2.113 After entering Mode 3, change DCS to "Mode 3" by using DCS graphic 6012 (PLANT MODE SELECTION).

Enclosure 4.1 OP/l!A/61 00/00 1 OP!l/A/6100/001 Unit Startup Page 37 of66 L 2.114 Verify S/G(s) reverse purge flow by performing the following:

[3 2.114.1 Record the temperature for the following OAC points: (OAC Group Display GD OPCFTEMP)

CIA0141 (S/G A After CF Isol Vlv Line Temp) 2?S 2'JS

CIA0148 (S/G A Inlet Temp (Feedwater))

CIA0125 (S/G B After CF Isol Vlv Line Temp)

CIAOl54 (S/G B Inlet Temp (Feedwater))

CIA0154 tJbb t7bb

CIA0275 (S/G C After CF Isol Vlv Line Temp) ~

CIA0160 (S/G C Inlet Temp (Feedwater)) Cf.-7P d-.7P

CIA0815 (S/G DAfter CF Isol Vlv Line Temp) d~

CIA0166 (S/G D Inlet Temp (Feedwater)) a") 00 a""

~4.2 D-rii4.2 Compare the values recorded above to the values recorded in Steps 2.77.1S.7 2.77.15.7 and 2.100.1 to verify reverse purge (increasing temperature).

0--2.114.3 0--1.114.3 IF no sign of reverse purge, determine what is causing the loss of reverse purge and correct the problem.

~14.4 Monitor OAC Group Display OPCFTEMP for increasing temperatures as a sign of reverse purge while continuing with the procedure.

NOTE: ,..,..1.

. . . '1. If turbine warming is in progress, Steps 2.115 and 2.116 can be N'A'd.

A.

/"2. If turbine warming is NOT to begin at this time, continue with the procedure and sign off Steps 2.115 and 2.116 when ready to begin warming the high pressure turbine shell.

J 2.115 Verify the turbine initial conditions contained in the turbine generator startup enclosure of OP/l/B/63001001 OPIlIB/6300/001 (Turbine-Generator) have been signed off.

Enclosure 4.1 OP!l/Al61 OP/l!A/61 00100 00/0011 Unit Startup Page 38 of66 CAUTION: Dj}NOT exceed 50 psig in the high pressure shell while doing Step 2.116 until PZR

Pressure is greater than 1945 psig (PZR Low Pressure Rx Trip Setpoint, P-ll). P-11). This is to prevent P-13 (56 psig impulse pressure) enabling P-7 to unblock the Lo Power Reactor Trips (PZR High Level, PZR Low Pressure, Low NC Flow on 2/4 Loops, NC Pump Undervoltage, NC Pump Underfrequency).

NOTE: Step 2.1 may be done at anytime during plant heatup to 2235 psig/557°F. The purpose of this p is to use any extra steam available to start warming the high pressure shell of the urbine when the NC System heatup is being performed with the MSIV's open. The warming does NOT have to be at 60-100 psig as required by OP/lIB/6300/001 OP/1/B/6300/001 (Turbine-Generator).

This warming is to reduce the amount of time required before placing the Turbine-Generator on the line.

J 2.116 IF the MSIV MSIVss are open AND S/G pressure> 100 psig, begin warming of the turbine per OP/l/B/6300/001 (Turbine-Generator). (R.M.)

-1 J 2.117 With NC pressure approximately 1000 psig, visually check the following areas for NC leaks that could impact unit startup:

~Lo~ containment (including reactor cavity).

~actor vessel head area.

1 NOTY. It is recommended to use a 2 lh6

/ 16 (preferred) or 2 33h6 / 16 inch socket on the torque wrench.

//" 2. Maintenance assistance will be needed to perform Step 2.118.

~. The procedure may continue while performing Step 2.118.

.:!- 2.118 WHEN NC pressure is approximately 1000 psig, then perform Enclosure 4.10 (1000 psig Critical Valve Checklist) as follows: {PIP 97-4407}

~ 2.118.1 Contact Maintenance for support when checking the closed torque value on the NC Loop drains per Enclosure 4.10 (1000 psig Critical Valve Checklist).

Person notified M_l_K-=--=t;-

notified.__M_.:...l __

k:::...:::::::..."""t;-_ _O_V--,-I O..::V---,-I__

-y- 2.118.2

-j- Check the closed torque value on the NC Loop drains per Enclosure 4.10 (1000 psig Critical Valve Checklist).

J 2.119 Increase NC pressure to between 1700 and 1800 psig. 2.120 Complete the PZR pressure surveillance item data enclosure of PT/1IA146001016 (Surveillance Requirements For Unit Startup).

PT/l/A/4600/016

Enclosure 4.1 OP/l!A/61 00/00 1 OP;1/A/6100/001 Unit Startup Page 39 of66

-:l- 2.121 Prior to exceeding 500°F NC System temperature, notify Primary Chemistry to verify NC System gross specific activity is acceptable to continue heatup. (TS 3.4.16)

---..J W notified........J Person notified ~I II I-t i If

-:l- 2.122 Verify S/G(s) reverse purge flow by performing the following:

VerifyS/G(s)

CY2.122.1 c:Y1.122.1 Record the temperature for the following OAC points: (OAC Group Display GD OPCFTEMP)

C1A0141 (S/G A After CF Isol Vlv Line Temp)

C1A0148 (S/G A Inlet Temp (Feedwater))

CIA0125 C1A0125 (S/G B After CF Isol Vlv V1v Line Temp)

C1A0154 (S/G B Inlet Temp (Feedwater))

C1A0275 (S/G C After CF IsolIso1 Vlv V1v Line Temp)

C1A0160 (S/G C Inlet Temp (Feedwater))

CIA0160

CIA0815 (S/G DAfter CF Isol C1A0815 Iso1 Vlv Line Temp)

C1A0166 (S/G D Inlet Temp (Feedwater))

G--"2.122.2 8""2.122.2 Compare the values recorded above to the values recorded in Steps 2.77.15.7, 2.100.1 and 2.114.1 to verify reverse purge (increasing temperature).

rr 2.122.3 IF no sign of reverse purge, determine detennine what is causing the loss of reverse purge and correct the problem.

~22.4 Gr2i22.4 Monitor OAC Group Display OPCFTEMP for increasing temperatures as a sign of reverse purge while continuing with the procedure.

CAUTION: Do NOT exceed 1955 psig NC System pressure prior to S/G pressure reaching greater

~an or equal to 900 psig. This is to prevent a SM isolation on low steam pressure (775 psig) .

..:t!--

..:f!- 2.123 Continue NC System heatup and pressurization within the limits specified by Figures 44 and 45 of the Unit One Revised Data Book.

Enclosure 4.1 OP;1/A/61 00100 0010011 Unit Startup Page 40 of66 NOT~. PT/1/A/42001030 PTIlIAl42001030 A (SM Valve Inservice Test) is required after every refueling outage.

(SR 3.7.2.1, T.S. 5.5.8)

--- 2. The procedure may continue while performing Step 2.124, if applicable.

- 2.124 IF required, WHEN S/G pressure is greater than 950 psig AND after the MSIV's have been opened, perform MSIV Hot Strokes per PT/1/A/4200/030 PT/lIAl42001030 A (SM Valve Inservice Test).

t_ 2.125 1_ At 1955 psig (P-11) NC System pressure, verify the following status lights on 1SI-13 are dark:

/'

eJ "PZR LO PRESS S/I S/1 TRAIN A BLOCKED"

[J-A'PZR o-A'PZR LO PRESS S/I S/1 TRAIN B BLOCKED"

~'}I1AIN STEAM 1S0L G0'}I1AIN ISOL TRAIN A BLOCKED"

[j"MAIN G'"""MAIN STEAM 1S0L ISOL TRAIN B BLOCKED".

NOTE;.---111e following pressure limit is to ensure the PZR safety valves have reached thermal NOTE;...--Tlie stabilization. Refer to OAC point C1A0653.

L 2.126 Prior to the NCS pressure exceeding 2000 psig ensure the following PZR steam temperature parameters have been met:

~~ steam temperature> 500°F for> 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

~R steam temperature> 575°F for> 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D¥zR D-FZR steam temperature> 600°F for> 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

-:f- 2.127 Remove the plastic collars on the following "ResetIBlock" pushbuttons:

~CS Tm A PZR Press"

~ECCS Tm B PZR Press" o-AECCS B"""ECCS B""'ECCS Tm A Stm Press" O/'ECCS Tm B Stm Press".

NOTEL-ltis recommended that Seal Injection Filter dp be in the normal range when verifying seal NOTEt....--Itis injection flow.

-#- 2.128 WHEN NC System pressure reaches 2235 psig, verify NC pump seal injection manual control valves are adjusted to provide the following:

r::(

r::J'88 gpm NC pump seal injection flow rate for each NC pump.

Q/!NV-309 (Seal Water Injection Flow) demand position 60% to 70% open.

CY1NV-309

~lNV-294 (NV Pmps A &

cY1NV-294 & B Disch Flow Ctrl) demand position 50% to 60% open.

Enclosure 4.1 00100 1 OP/l!Al61001001 OP/l!Al61 Unit Startup Page 41 of66 12.129 Perform PT/1/A/41501001 PT/1/A/4150/o01 C (NC Pump Seal Injection Flow Verification) within four hours of stabilizing NC System pressure pr-essure at 2215 - 2255 psig. (TS SR 3.5.5.1)

NOTE: v1i v.-1t is recommended to use a 2 1/ 16 (preferred) or 2 3/ 16 inch socket on the torque wrench.

2:Maintenance assistance will be needed to perform Step 2.130.

7:'

'£" Continue on with the procedure while performing Steps 2.130 and 2.131.

-1 J 2.130 WHEN NC system is at normal temperature and pressure, then perform Enclosure 4.11 (Normal Temperature And Pressure Critical Valve Checklist). {PIP 97-4407}

L~

--+--

2.130.1 Contact Maintenance for support when checking the closed torque value on the NC Loop drains per Enclosure 4.11 (Normal Temperature And Pressure Critical Valve Checklist).

K:--,,0~:__O_T--,--_-.....:.1_

notified.LJY1-----'I'--K:--'>.,~:,L-:--O-TL...-=-I-Person notified..LJY1_,--'

:1

:1 2 .130.2 Check the closed torque value on the NC Loop drains per Enclosure 4.11 (Normal Temperature And Pressure Critical Valve Checklist).

L 2.131 WHEN the NC System reaches normal operating temperature and pressure, perform PT/1/Al41501001 D (NC System Leakage Calculation) within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Enclosure 4.1 OP!l/AJ6100/001 OP/l/Al61 00/00 1 Unit Startup Page 42 of66 J 2.132 WHEN NC System pressure reaches 2235 psig, ensure the following controllers are in auto with proper setpoints (Figure 25 of the Unit One Revised Data Book).

NOTE0r NOTE0rany any of the PZR heaters are required to remain in manual for PZR pressure control or PZR mixing, the following item can be signed off.

ct "PZR Htr Rtr Ctrl Ctr11A" lA" o--nPZR Htr o-nPZR Rtr Ctrl IB" Ctr11B"

~:rZR Htr 8"',:PZR Rtr CtrllD" Ctr11D"

~'PZR Press Master" Gj"'PZR

PZR Spray Controllers:

~ INC-27 (PZR Spray Ctrl Frm Loop A)

[3/

L:r INC-29 (PZR Spray Ctrl Frm Loop B)

PORVs:

IT INC-32B (PZR PORV) 8' ~!iC-34A 1J~~:C-34A (PZR PORV)

~NC-36B (PZR PORV)

~'PZR Level Master".

D~-294 (NY Pmps A && B Disch Flow Ctrl).

NOTE: e procedure may continue while performing Step 2.133.

-4 2.133 IF the NC System has been opened for refueling or maintenance (ex., seal replacement, PORV repair, pressure boundary repair, etc.), then perform PT/1/AJ4150/001 PT/1/Al4150/001 A (Reactor Coolant System Leak Test).

NOTE: The Outage Guidelines will specify when to open the MSIV's and place the condenser steam dumps in service.

~-1 4 2.134 IF the condenser steam dumps are NOT available, perform the following:

oD 2.134.1 Manually control T-AVG 557°0 Fusing S/G blowdown, S/G T -AVG at approximately 557 reverse purge, turbine warming, or S/G PORV's.

oD 2.134.2 WHEN condenser steam dumps are available perform Steps 2.136 - 2.140.

Enclosure 4.1 OP;1/A/6100/001 OP/IIA161 001001 Unit Startup Page 43 of66

-:I-~ 2.135

t-IF Step 2.6 was completed to supply Unit 1I Turbine warming from the AS System, perform the following to restore AS to normal alignment: (R.M.)

1 12.135.12.135.1 Ensure turbine warming has been secured.

-.::I-

~

,- 2.135.2 Notify the Control Room 'Supervisor Supervisor that an approximate 5 MW increase in generator output on Unit 2 may occur when isolating the Unit 2 supply via the AS System for Unit 1 Turbine Shell Warming.

L 2.l35.3 2.135.3 Monitor the Unit 1 SM piping for water hammer.

4- 2.135.4 Notify the Control Room Supervisor to monitor Unit 2 Reactor Power, Generator MW, and AS header pressure while performing the following step.

4 2.135.5

---1I 2 . 135 .5 Slowly close 1AS-4 IM-32).

lAS-4 (Main Steam to Aux Steam Header Control Bypass) (TB-61O, (TB-610, NU 2.136 IF the NC System heatup was performed with the MSIV's closed, open the MSIV's as follows:

CAUTIO~ain steamline drains shall be open for at least 15 minutes prior to opening MSIVs or MSIV Bypasses.

- - 2.136.1 Open the following valves:

o ISM-132 (SM Equalization Hdr Trap T-05 Byp) (TB-594, 1H-32) IH-32) o ISM-139 (SM Equalization Hdr Trap T-06 Byp).(TB-594, IH-32) lSM-139

- - 2.136.2 After 15 minutes, close the following valves:

o 1SM-132 (SM Equalization Hdr Trap T-05 1SM-132 T-05 Byp) o ISM-139 (SM Equalization Hdr Trap T-06 Byp).

NOTE: ..Xe ~ following step will take a minimum of 30 minutes to perform. The procedure may of30 continue while performing Step 2.136.3 2.l36.3 2.136.3 Equalize pressure across and open the MSIV's per OP/lIAl62501006 OP/1/A/6250/006 (Main Steam).

Enclosure 4.1 OP/l!A/61 OPllJAl6 100/00 00100 1 Unit Startup Page 44 of66 2.137 Establish automatic steam dump control as follows: (R.M.)

o 2.137.1 Adjust the "Stm Dump Ctrl" setpoint to 1092 psig.

o 2.137.2 Ensure MSIV's are open per Step 2.136.3.

o 2.137.3 Ensure T-AVG is less than or equal to -SS7°F 557°F per Step 2.134.1.

o 2.137.4 Place the "Stm Dump Ctrl" in auto.

2.138 Turn the following switches to the "ON" position:

o "Steam Dump Intlk Byp Tm A" o "Steam Dump Intlk Byp Tm B".

2.139 WHEN MSIV's are open verify the steam dumps maintain approximately 1090 psig (approximately 557° T-AVG).

2.140 Ensure S/G PORV's in "AUTO".

2.141 Verify S/G(s) reverse purge flow by performing the following:

o 2.141.1 Record the temperature for the following OAC points: (OAC Group Display GD OPCFTEMP)

CIA0141 C1A0141 (S/G A After CF Isol Vlv Line Temp)

CIA0148 C1A0148 (S/G A Inlet Temp (Feedwater))

CIA0125 C1A0125 (S/G B After CF Isol Vlv Line Temp)

CIA0154 (S/G B Inlet Temp (Feedwater))

CIA0275 (S/G C After CF Isol Vlv Line Temp)

CIA0160 (S/G C Inlet Temp (Feedwater))

CIA0815 (S/G DAfter CF Isol Vlv Line Temp)

CIA0166 (S/G D Inlet Temp (Feedwater))

o 2.141.2 Compare the values recorded above to the values recorded in Steps 2.77.15.7, 2.100.1, 2.114.1 and 2.122.1 to verify reverse purge (increasing 2.77.15.7,2.100.1,2.114.1 temperature).

o 2.141.3 IF no sign of reverse purge, determine what is causing the loss of revers*e purge and correct the problem.

o 2.141.4 Monitor OAC Group Display OPCFTEMP for increasing temperatures as a 1>ign ~ign of reverse purge while continuing with the procedure.

Enclosure 4.1 OP;1/A/61 001001 Unit Startup Page 45 of66 2.142 IF desired to perfonn control rod drop testing, ensure heatup of the NC System is complete.

2.143 Prior to entering Mode 2, do the following:

_ _

Ensure the Reactor Building Entry Logbook is transferred to the Operations Shift Manager in accordance with Site Directive 3.1.2.

_ _

Complete Enclosure 4.8 (Operations Mode 1 and 2 Checklist).

_ _

Complete Enclosure 4.9 (Support Mode 1 and 2 Checklist).

_ _

IF startup is following a seismic event, then notify IAE lAE to calibrate OTDT and OPDT trips by completing the following procedures:

IP/1/A/3222/076A (Channell Delta T/Tavg Channel Calibration) (W/O # 00874141)

IP/1/A/32221076B (Channel 2 Delta T/Tavg Channel Calibration) (W/O # 00874142)

IP/1/A/3222/076B

IP/1/A/3222/076C (Channel 3 Delta T/Tavg Channel Calibration) (W/O # 00874143)

IP/1/A/3222/076D (Channel 4 Delta T/Tavg Channel Calibration) (W/O # 00874144)

IP/lIA/3222/076D Person notified

_ _

Review the OAC points that will be in alann in Mode 2 by using the OAC "Plant Mode" application to perfonn an alann look ahead.

_ _

Ensure the following surveillances are current:

IN41 Channel COT at Startup (W/O # 00889962)

lN42 Channel COT at Startup (W/O 1N42 # 00889963)

IN43 Channel COT at Startup (W/O # 00889964)

IN44 Channel COT at Startup (W/O # 00889965)

Person notified 2.144 Prior to entering Mode 2, notify Primary Chemistry to verify that NC System hydrogen is acceptable for entry into Mode 2.

Person notified----------------

Enclosure 4.1 OP/l!A/61 00100 1 OPIl!A/61001001 Unit Startup Page 46 of66 NOTE: The procedure may continue while perfonning performing Step 2.145.

2.145 Verity one group of cooling fans and oil pumps for each main transfonner transformer are in operation:

2.145.1 Perfonn the following for each cooler breaker group that is desired to be in Perform operation:

2.145.1.1 Place each desired group cooler breaker in "ON" (located inside local alann panel) one at a time per the list below.

alarm 2.145.1.2 IF cooler oil pump does NOT indicate "PUMP ON", then return cooler breaker to "OFF" and notity the UnitlWCC SRO .

Main Transfonner Transformer 1A. Group1

Main Transfonner Transformer 1lA,A, Group 2 o 1A IA Cooler Bkr 8-1 o 1A Cooler Bkr 8-2 o 1A IA Cooler Bkr 8-3 o 1A IA Cooler Bkr 8-4 o 1A IA Cooler Bkr 8-5 o 1A IA Cooler Bkr 8-7 o 11AA Cooler Bkr 8-8 o 1A 1A Cooler Bkr 8-9 o 1A Cooler Bkr 8-10 Transformer 1B. Group 1

Main Transfonner

Main Transfonner Transformer 1B,IB, Group 2 o 11BB Cooler Bkr 8-1 o 1B Cooler Bkr 8-2 o 1B Cooler Bkr 8-3 o 1B Cooler Bkr 8-4 o 1B Cooler Bkr 8-5 o 1B Cooler Bkr 8-7 o 1B Cooler Bkr 8-8 o 1B 1B Cooler Bkr 8-9 o 1B IB Cooler Bkr 8-10

_ _ 2.146 Ensure containment auxiliary carbon filter units are off per OP/lI Al645 0100 1 (Containment OP/1/Al64501001 Ventilation (VV) Systems).

_ _ 2.147 Verity the following on the "Diagnostic" page for each ICCS Monitor with four NC pumps runmng:

runnmg:

"Train A ICCS Monitor":

D "UR Level" --less less than 64%

D "LR Level" - greater than 63%.

"Train B ICCS Monitor":

D "UR Level" -less than 64%

D "LR Level" - greater than 63%.

2.148 Ensure Step 2.133 has been signed off or NIA'd.

Enclosure 4.1 op!l IA/6 100100 OP/liA/61 0010011 Unit Startup Page 47 of66

_ _ 2.149 Prior to closing the reactor trip breakers with the rods capable of withdrawal, review TSAIL to ensure that none of the items listed below are entered as inoperable and ensure surveillances are current per the listed work orders below: {PIP 97-2423}

Manual Reactor Trip (TS 3.3.1) W/O # 00880613

Reactor Trip Breaker Train A (TS 3.3.1) WO# 00880225

Reactor Trip Breaker Train B (TS 3.3.1) WO# 00874198

Reactor Trip Bypass Breaker Train A (TS 3.3.1) WO# 00880225

Reactor Trip Bypass Breaker Train B (TS 3.3.1) WO# 00874198

Automatic Trip and Interlock Logic Train A (TS 3.3.1) WO# 00880223

Automatic Trip and Interlock Logic Train B (TS 3.3.1) WO# 00874197

Digital Rod Position Indication System (TS 3.1.7, SLC 16.7-11) WO# 00874180 or W/O# 00876835

Source Range, Neutron Flux (TS 3.3.1). WO# 00874212, 00874313, 00880078, 00874209,00874318 and 00880076 NOTE: The procedure may continue while performing Step 2.150 and 2.151.

- - 2.150 IF NOT already performed, startup the Rod Control System per OP/1/A/61501008 OP/lIA/61501008 (Rod Control).

- _ 2.151 Determine the desired critical rod position and corresponding boron concentration (ECB) per OP101A/6l 001006 (Reactivity Balance Calculation). (R.M.)

OP/OIA/61001006 NOTE: The Operations Shift Manager shall be contacted to determine if it is desired to withdraw shutdown banks and remain in Mode 3.

- - 2.152 IF it is desired to withdraw shutdown banks and remain in Mode 3, then do the following:

(R.M.)

o D 2.152.1 Determine the time the unit will remain in Mode 3 with the shutdown banks withdrawn at the present boron concentration or the ECB minus 20 ppm (used as the present boron concentration) whichever is lower per OP/oIA/6l001006 (Reactivity Balance Calculation).

OP/OIA/61001006 2.152.2 IF it is determined the time the unit will remain in Mode 3 with the shutdown banks withdrawn is acceptable, then proceed to Step 2.153.

Enclosure 4.1 00100 1 OPIVA/61001001 OP/l!A/61 Unit Startup Page 48 of66

- _ 2.153 Prior to withdrawing shutdown banks, ensure NC System boron concentration greater than or equal to ECB minus 20 ppm as follows: (R.M.)

oD 2.153.1 Record ECB as determined in Step 2.151. _ _ _ _ _ _ ppm oD 2.153.2 Subtract 20 ppm and enter required concentration. _ _ _ _ _ _ ppm oD 2.153.3 Record actual NC System boron concentration. _ _ _ _ _ _ ppm 2.153.4 Verify actual> required boron concentration. YES I NO 2.153.5 Perform an independent second check of the above requirement.

- - 2.154 IF NOT already performed, withdraw the shutdown banks to 100% withdrawn per OP/lIA/61501008 (Rod Control). (R.M.)

OP/1/A/61501008

_ _ 2.1'55 2.155 Place the "CFPT RUNBK ON RX TRIP" in the "NORM" position.

500 o -S57°F

- - 2.156 IF NC System dilution is desired to be performed at a temperature between 500°-557°F AND while maintaining Mode 3 with the shutdown banks withdrawn, then ensure the following before proceeding to Step 2.157:

oD 2.156.1 The NC System boron will NOT be reduced below the Mode 3 boron concentration for any temperature between the present temperature and 557°F.

oD 2.156.2 The NC System boron will NOT be reduced below the ECB minus 20 ppm for any temperature between the present temperature and 557°F.

NOTE: Radwaste Chemistry shall be notified prior to transferring any water to the waste or recycle systems.

- - 2.157 IF required, dilute NC System to ECB per one of the following as determined by Duty Rx Group Engineer: (R.M.)

Person notified - - - - - - - - - - - - - - - - - - - - -

oD OP/1/A/61501009 (Boron Concentration Control) oD PT/OIA/41501019 (lIM Approach To Criticality) oD PT/OIA/41501019B (NC System Dilution Following Refueling)

Enclosure 4.1 00100 1 OP;1/AJ6100/001 OP/l!Al61 Unit Startup Page 49 of66 NOTE: It is recommended that the NC System sample NOT be obtained for at least 60 minutes following a dilution to allow for proper mixing.

2.157.1 OP/1/AJ6150/009 (Boron IF a dilution of the NC System was performed per OP/1/Al61501009 Concentration Control), notify Primary Chemistry to determine NC System boron concentration.

Person notified - - - - - - -

- - 2.158 IF running AND it is desired to remove the operating CA pumps from service, do the following:

o 2.158.1 Start a CF pump per OP/1/AJ6250/001 OP/lIAl62S01001 (Condensate and Feedwater System).

o 2.158.2 Secure CA pumps per OP/1/Al62501002 OP/1/A/6250/002 (Auxiliary Feedwater System).

o 2.158.3 Ensure CA is in standby readiness per OP/1/AJ6250/002 OP/lIAl62501002 (Auxiliary Feedwater System).

2.159 After entering Mode 2, then change the OAC to Mode 2 using the OAC "Plant Mode" application.

- - 2.160 After entering Mode 2, change DCS to "Mode 2" by using DCS graphic 6012 (PLANT MODE SELECTION).

- - 2.161 Perform approach to criticality per one of the following: (R.M.)

o PT /0/AJ4150100 1J (Zero Power Physics Testing), if first startup following refueling.

PT/OIAl4150100lJ o PT/0/AJ4150/019 PT/OIAl41S01019 (11M(lIM Approach To Criticality), for all other startups.

2.162 Record mode 2 entry time below:

Mode 2. __ _- _-_ -_ -_-

- - 2.163 IF this is the first startup after a refueling outage, notify the Security Lieutenant or designee that Unit 1 is in Mode 2 and to take the appropriate action based on SSF operability.

Person notified

~-------

- - 2.164 Notify Radiation Protection of the reactor startup and to sample and analyze gaseous effluents per S.L.C.

S.L.e. 16.11-6.

Person notified

- - 2.165 WHEN reactor power has been stabilized at 10- 10-88 amps, ensure at least one power range IENCRSOOO (Startup, Intermediate, & Power Range Nls).

channel is selected on lENCR5000

Enclosure 4.1 OP/l!Al6100/001 Unit Startup Page 50 of66 2.166 Ensure Steps 2.137 - 2.139 have been completed to ensure automatic steam dump control has been established.

NOTE: 1. Control rod withdrawal shall NOT exceed the temporary rod withdrawal limits specified in Unit One R.O.D. Section 2.3.

2. Refer to Unit One R.O.D. Section 2.4 for the rate at which reactor power can be changed.

3. The throttling of a S/G bypass reg valve affects the other S/G bypass reg valves.

Thefefore, SM/CP i1P needs to be monitored as the unit approaches POAH.

Therefore,

4. IfNC boron concentration is greater than 1000 ppmB, T-AVG control may be very sensitive above the POAH due to a positive MTC. Refer to Unit One R.O.D.

Section 5.10 for the MTC at the current conditions.

5. When approaching the POAH, a startup rate of< of < 0.2 dpm is recommended; it is l'ecommended recommended that this rate NOT be exceeded until the turbine is placed online.

on line. (,SOMP (SOMP 01-02). (R.M.)

- - 2.167 Increase reactor power to 1%. (R.M.)

2.168 Begin reviewing the items listed in Step 2.176 so that Unit 1 will NOT enter Mode 1 until all substeps of 2.176 are signed off.

- - 2.169 IF necessary, continue heatup to no load T -AVG (557°P).

(5S7°P).

- - 2.170 Increase S/G blowdown flowrate as recommended by Secondary Chemistry for S/G chemistry control and within guidelines ofOP/1/A/6250/008 ofOP/lIA/6250/008 (Steam Generator Blowdown).

(R.M.)

Person making recommendation recommendation._ _ _ _ _ _ _ _ _ __

2.171 Coordinate with Chemistry to determine when blowdown flowrate can be subsequently reduced.

Enclosure 4.1 OP/l!Al61100/00 OP!l/Al6 00100 1 Unit Startup Page '51 of 66 Page'Slof66

- - 2.172 Verify S/G( s) reverse purge flow by performing the following:

o 2.172.1 Record the temperature for the following OAC points: (OAC Group Display GD OPCFTEMP)

CIA0141 (S/G A After CF Isol Vlv Line Temp)

CIA0148 (S/G A Inlet Temp (Feedwater))

C1A012S CIA0125 (S/G B After CF Isol Vlv Line Temp)

CIA0154 (S/G B Inlet Temp (Feedwater))

C1A0275 (S/G C After CF Isol Vlv Line Temp)

CIA0275

C1A0160 (S/G C Inlet Temp (Feedwater))

CIA0160

CIA0815 (S/G DAfter CF Isol Vlv Line Temp)

C1A0166 CIA0166 (S/G D Inlet Temp (Feedwater))

o 2.172.2 Compare the values recorded above to the values recorded in steps 2.77 2.77.1 5.7,

.15.7, 2.1 00.1,2.114.1,2.122.1 and 2.141.1 to verify reverse purge (increasing 2.100.1,2.114.1,2.122.1 temperature).

o 2.172.3 IF no sign of reverse purge, determine what is causing the loss of reverse purge and correct the problem.

o 2.172.4 Monitor OAC Group Display OPCFTEMP for increasing temperatures as a sign of reverse purge while continuing with the procedure.

- - 2.173 IF the CA pumps are in service, do the following:

o 2.173.1 Start a CF pump per OP/lIAl62501001 OP/1/Al6250/001 (Condensate and Feedwater System).

o 2.173.2 Secure CA pumps per OP/lIA/62501002 OP/1/A/6250/002 (Auxiliary Feedwater System).

o 2.173.3 Ensure CA is in standby readiness per OP/lIA/62501002 OP/1/A/6250/002 (Auxiliary Feedwater System).

NOTE: IfCFPT speed is less than minimum speed of3800 RPM for auto control, CFPT speed will increase to 3800 RPM after performing the following step.

2.174 IF NOT in auto by approximately 2% reactor power, Place the "CFPT 1A lA (lB) Speed Ctrl" for the CFPT in auto.

Enclosure 4.1 OP!l/Al61 00/00 1 OP;1/Al6100/001 Unit Startup Page 52 of66 NOTE: The procedure can be continued while waiting for the CF bypass valves to reach 40% open.

Therefore, Step 2.175 can be signed off out of sequence if required by plant conditions. It is recommended that the CF pump be in auto before opening the isolation valves around the CF reg valves.

2.175 WHEN the CF bypass valves are approximately 40% open, unisolate the CF reg valves by opening the following valves:

S/G lA D lCF-29 (S/G lA CF CIY Otlt Isol)

D lCF-27 (S/G lA CF CN Inlt InIt Isol)

S/G IB D lCF-38 (S/G IB CF CN Otlt Isol) Iso1)

D lCF-36 (S/G lB IB CF CN InIt Inlt Isol)

S/G lC D lCF-47 (S/G lC IC CF CN Otlt Isol)

D lCF-45 (S/G lC CF C/V InIt Inlt Isol)

S/G ID lCF-S6 (S/G ID CF CN Otlt Isol)

D lCF-56 D lCF-S4 lD CF CN InIt Isol) lCF-54 (S/G ID

- - 2.176 Prior to entering Mode 1, do the following:

NOTE: Appropriate Chemistry Supervisor shall confirm any administrative holds preventing a power lllcrease.

mcrease.

D 2.176.1 Notify Secondary Chemistry to verify S/G and final feedwater water quality is acceptable for power increase.

Person notified -------------------------------

D 2.176.2 Ensure PT/1IA14700/002 PT/IIA14700/002 (Periodic Test Performance Verification For Mode Change) Premo de 1 PT Checklist is completed.

D 2.176.3 Verify with Primary Chemistry that NC System H2 Hz concentration and Dose Equivalent Iodine are in spec to allow entry into Mode 1.

Ferson Person notified _______________________________

Enclosure 4.1 OP/liA/61 00100 1 OPil/A/61 Unit Startup Page 53 of66 o 2.176.4 Verify the PCMC data base has been reviewed for items required for Mode 1 entry.

o 2.176.5 Review the OAC points that will be in alarm in Mode 1 by using the OAC "Plant Mode" application to perform an alarm look ahead.

- - 2.176.6 Ensure the CF temperatures between each feedwater isolation valve and S/G is greater than 107°F: (OAC Group Display GD OPCFTEMP)

S/G lA:

o C1A0141 CIA0141 (S/G A After CF Isol Vlv Line Temp) o CIAOI48(S/G A Inlet Temp. (Feedwater))

S/G IB:

o CIAOI25(S/G B After CF Isol Vlv Line Temp)

CIAOI2S(S/G o CIAOI54(S/G B Inlet Temp. (Feedwater))

S/G lC:

o CIA0275 (S/G C After CF Isol Vlv Line Temp) o CIA0160(S/G C Inlet Temp. (Feedwater))

CIAOI60(S/G

S/G ID:

o CIA0815(S/G DAfter CF Isol Vlv Line Temp) o CIA0166(S/G D Inlet Temp. (Feedwater))

CIAOI66(S/G 2.177 Prior to entering Mode 1, perform the following to ensure the primary to secondary leakage program inputs are current:

o Notify RP to ensure EMF-33 background counts in the EMF-33 Background Spreadsheet is current.

Person Notified- - - - - - - - - - - -

o Notify Primary Chemistry to ensure the NC Xenon Equivalent in the Chemistry Database is current.

Person Notified~-----------

o Record current air ejector off gas flowrate. ___________

o Update "EMF33 Prim/Sec Leakage" program on the Unit 1 OAC.

Enclosure 4.1 OPIVA/61 OP/lJA/61 001001 Unit Startup Page 54 of66 2.178 Record Mode 1 entry time below:

Mode 1- ---- - -- -- -

_ _ 2.179 Ensure the following steps have been signed off or NIA'd as applicable:

o Step 2.115 2.l15 o Step 2.116.

2.180 After entering Mode 1, then change the OAC to Mode 1 using the OAC "Plant Mode" application.

_ _ 2.181 After entering Mode 1, change DCS to "Mode 1" by using DCS graphic 6012 (PLANT MODE SELECTION).

CAUTION: To prevent T-AVG from decreasing while performing Steps 2.182, 2.184,2.186, 2.184, 2.l86 , and 2.189 reactor power shall be adjusted to ensure condenser steam dumps are open maintaining T-AVG hot versus T-REF based on required Reactor Power prior to placing the turbine generator on line (T.S. Limit is 551°F).

- - 2.182 Begin increasing reactor power to between 13% and 15% in preparation for placing the turbine generator on line. (R.M.)

- - 2.183 WHEN reactor power is steady at or being increased above 10%, verify the following:

o "P-I0 NUCLEAR AT POWER" light on 1ISI-18 SI-18 is lit.

o "P-7 LO PWR RX TRIPS BLOCKED" light on 11SI-18 SI-18 is dark.

o "SIR HI SHUTDOWN FLUX ALM BLOCKED" annunciator on lAD-2 (D/2) is dark.

o "SIR HI VOLTAGE FAILURE" annunciator on lAD-2 (D/l) is dark.

2.184 Perform the following to restore from Enclosure 4.12 (Secondary Heatup Checklist):

(R.M.)

2.184.1 2.184 .1 For Enclosure 4.12 (Secondary Heatup Checklist):

o Slowly open each valve listed on the checklist.

o Initial by each in the "Return Position" column.

2.184.2 Secure from the Increased Monitoring and Increased Surveillance initiated to drain the piping specified on Enclosure 4.12 (Secondary Heatup Checklist) every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2.185 IF required ensure venting of the high pressure feedwater heaters has been secured per OP/lIA/62501001 (Condensate and Feedwater System). {PIP 03-591}

OPIlIA/62501001

Enclosure 4.1 OP/l!Al61 00100 1 OP/l!A/61 Unit Startup 55 of 66 Page 5S

- - 2.186 Bring the turbine generator to 1800 rpm per OPIl/B/63 00100 1 (Turbine-Generator). (R.M.)

OPIl/B/63001001 2.187 IF required due to GeneratorlAutomatic Voltage Regulator (AVR) testing at Turbine-Generator Rated Speed (1800 RPM) perform the following:

2.187.1 IF performing Generator/Automatic Voltage Regulator (AVR) testing, HOLD until GeneratorlA VR personnel are ready for Operations to continue with placing Unit 1 Turbine-Generator on line.

oD 2.187.2 Once notified by GeneratorlAVR personnel that A VR testing is complete for the 1800 RPM HOLD point continue with placing Unit 1 Turbine-Generator on line.

Person making notification_ _ _ _ _ _ _ _ _ __

2.188 Do NOT continue until Reactor power is between 13% and 15% power.

NOTE: While placing the turbine generator on line the steam dumps will begin closing and T-REF indication will start to increase.

- - 2.189 Place turbine generator on line per OPIl/B/63 00100 1 (Turbine-Generator). (R.M.)

NOTE: The procedure can be continued while waiting for Turbine Impulse Pressure Channell to reach 56 psig. Therefore, Step 2.190 can be signed off out of sequence if required by plant conditions.

- - 2.190 WHEN Turbine Impulse Pressure Channell is greater than or equal to 56 psig, verify the "P_13 TURBINE NOT AT POWER" "P-13 POWER"lightlight on 1SI-18 lSI-18 is dark.

- - 2.191 Verify the following P-1 P-lO0 bistable lights on 1lSI-2 SI-2 are in the proper state for plant conditions:

oD PIR P10 NC41M oD P10 NC42M PIRP10NC42M PIR o

D PIRP10NC43M o

D P/RP10NC44M 2.192 IF P-1 0 bistable lights are NOT in the proper state for plant conditions, then have IAE perform Model W/O # 00874531.

Person notified

Enclosure 4.1 OP!l/A/61 00/001 OP/I/A/61001001 Unit Startup Page 56 of66 NOTE: If reactor power decreases to less than 10%, the low power trips will unblock.

- - 2.193 IF required due to plant conditions depress the following pushbuttons to block the intennediate range high level trip and rod stop: (R.M.)

intermediate D "Tm A IIR Block" D "Tm B IIR Block".

- - 2.194 Verify the following lights on 1SI-18 are lit:

"I!R TRAIN A TRIP BLOCKED" D "IIR D "I/R TRAIN B TRIP BLOCKED".

- - 2.195 IF required due to plant conditions depress the following pushbuttons to block the power range low setpoint trip: (R.M.)

D "Tm A PIR.

P/R Block" PIR Block".

D "Tm B PIR.

- - 2.196 Verify the following lights on 1lSI-18 SI-18 are lit.

D "PIR "PIRLOLO SETPOINT TRAIN A TRIP BLKD" BUm" D "PIR LO SETPOINT TRAIN B TRIP BUill". Bum".

2.197 IF required due to Generator/Automatic Voltage Regulator (AVR) testing, at a turbine power of 130 - 150 MWe perfonn perform the following:

2.197.1 IF performing Generator/Automatic perfonning Generatorl (AVR)

Automatic Voltage Regulator (A VR) testing, HOLD Generator/A VR personnel are ready for Operations to continue with the until Generatorl procedure.

D 2.197.2 Once notified by Generator/

GeneratorlA VR personnel that A VR testing is complete for the 1800 RPM HOLD point continue with placing Unit 1 Turbine-Generator on line.

notification._ _ _

Person making notification'---_ ____ ______ __ __ __

Enclosure 4.1 OP;1/A/61001001 OP/IIA161 00100 1 Unit Startup Page 57 of66 NOTE: A decrease in RC temperature (starting Cooling Tower Fans or RC Pumps) may result in a decrease in exhaust hood temperature. A minimum exhaust hood temperature of>85°F is required for the turbine overspeed test.

2.198 IF required, perform PT/lIAl42501002 PT/1/A/42S01002 D (Main Turbine Actual Overspeed Test) as follows:

(R.M.)

2.198.1 Ensure the following:

o D 2.198.1.1 The turbine has carried 10% or greater load for at least 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

o D 2.198.1.2 Exhaust hood temperature has been maintained greater than 85°F8SOF for at least 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

2.198.2 Ensure steam dumps are in the steam pressure mode as follows:

oD 2.198.2.1 Ensure "STM DUMP CTRL" (MIA Station) is in auto.

oD 2.198.2.2 Ensure the pot on "STM DUMP CTRL" (MIA Station) is set to control for 1090 psig. (Figure 25, Unit 1 Revised Data Book) oD 2.19'8.2.3 Ensure "STEAM DUMP SELECT" in "PRESS" controL control.

oD 2.198.2.4 Slowly reduce the pot on "STM DUMP CTRL" (MIA Station) to match the current steam pressure.

NOTE: The steam dumps will open as turbine load is decreased. Reactor power will remain stable.

2.198.3 While reducing turbine load per OPIl/B/63 00100 I (Turbine Generator), verify OPIl/B/63001001 steam load is transferred to the steam dumps.

2.198.4 IF required due to Generatorl Automatic Voltage Regulator (AVR) testing perform Generator/Automatic the following:

o 2.198.4.1 D Notify Generator AVR personnel prior to removing the turbine generator from service.

Person Notified 2.198.5 Remove the turbine from service per the Turbine Generator Shutdown enclosure ofOPIl/B/63001001 ofOP/1/B/63001001 (Turbine Generator) and complete the steps up to and including the step to perform PT/I/A/42501002 PT/lIAl42501002 D (Main Turbine Actual Overspeed Test).

2.198.6 Perform PT/I/A/42S01002 PTIlIAl42501002 D (Main Turbine Actual Overspeed Test).

Enclosure 4.1 OP/l!Al61001001 OP!lIA/61001001 Unit Startup Page 58 of66 NOTE: Steps in the startup enclosure of OP/1/B/63001001 OP/IIB163001001 (Turbine Generator) prior to the step when the turbine reaches 1800 rpm shall be reviewed for preparations made to place the turbine generator back on line.

2.198.7 Obtain and begin signing offaoff a new Startup enclosure ofOP/lIAl63001001 of OP/1 IA/63 00100 1 (Turbine Generator) in preparation for placing the turbine generator back on line.

2.198.8 IF required due to GeneratorlAutomatic Voltage Regulator (AVR) testing perform the following:

oD 2.198.8 .1 2.198.8.1 Notify Generator A VR personnel prior to placing the turbine generator back on line.

Person notified 2.198.8.2 IF required per Generator/Automatic Voltage Regulator (A (AVR)

VR) testing HOLD until Generator/AVR Generator/AVR personnel are ready for Operations to place the turbine generator back on line.

Person making notification notification'--____________________

- - 2.198.9 Place the turbine generator on line per OPIlIB163001001 OP/1 IB/63 00100 1 (Turbine Generator).

2.199 At approximately 15% reactor thermal power, perform the following to ensure the primary to secondary leakage program inputs are current:

o Notify RP to ensure EMF-33 background counts in the EMF-33 Background D

Spreadsheet is current.

Person Notified----------------

o Notify Primary Chemistry to ensure the NC Xenon Equivalent in the Chemistry D

Database is current.

Person Notified o Record current air ejector D ej ector off gas fiowrate.

flowrate. ________________

o Update "EMF33 PrimlSec D Prim/Sec Leakage" program on the Unit 1 OAC.

o Update "OAC Primary to Secondary Leakrate" program on DAE.

D

Enclosure 4.1 OP!l/A/61 00/001 OP/l/A/6100/001 Unit Startup Page 59 of66 power ~ 15%, perform the following within the next 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s:

- - 2.200 WHEN reactor thermal power;;::

(SR 3.3.1.2)

D 2.200.1 Verify no excore ex core power range channels differ from OAC point C1P1385 (Reactor Thermal Power, Best) by greater than 2%.

D 2.200.2 Have IAE lAE adjust power range channels as required per model W/O # 00874628.

Person notified D 2.200.3 Document each power range channel differs from OAC point C1P1385 (Reactor Thermal Power, Best) by NOT more than +/- 2% in the RO Logbook.

NOTE: The CF flow in "Step Step 2.201 is looking at the average of all four CF flows to the S/Gs.

2.201 WHEN the average CF flow to each S/G is greater than 15% (0.56 MPPH), perform the following:

NOTE: If having problems reaching 250°F, the source of cold water in the CF System needs to be determined and isolated.

2.201.1 Prior to transferring to main feedwater nozzles ensure the following conditions are met:

CF temperature to the main feedwater nozzle for each S/G is greater than 250°F: (OAC Group Display GD OPCFTEMP)

D CIA0129 C1A0129 (S/G A Before CF Isol Vlv Line Temp)

C1A0141 (S/G A After CF Isol Vlv Line Temp)

D CIA0141 D CIA0148 C1A0148 (S/G A Inlet Temp (Feedwater))

D CIA0268 C1A0268 (S/G B Before CF Isol Vlv Line Temp)

D CIA0125 C1A0125 (S/G B After CF Isol Vlv Line Temp)

C1A0154 (S/G B Inlet Temp (Feedwater))

D CIA0154 D C1A0269 (S/G C Before CF Isol Vlv Line Temp)

CIA0269 D CIA0275 C1A0275 (S/G C After CF Isol Vlv Line Temp)

D C1A0160 (S/G C Inlet Temp (Feedwater))

CIA0160 C1A0281 (S/G D Before CF Isol Vlv Line Temp)

D CIA0281 D CIA0815 C1A0815 (S/G DAfter CF Isol Vlv Line Temp)

D CIA0166 C1A0166 (S/G D Inlet Temp (Feedwater)

D S/G reverse purge flow has been in service for greater than or equal to 30 minutes.

Enclosure 4.1 OP/l!Al61 OP/l!A/61 00/00 1 Unit Startup Page 60 of66 NOTE: The procedure may continue while perfonning performing Step 2.201.2 thru thm 2.201.9.

o 2.201.2 D Open 1CA-223 lCA-223 (S/G 1A lA CA Nozzle Tempering Flow Isol) (DH-589, EE-45, Rm591).

Rm 591).

o 2.201.3 D Open 1CA-226 lCA-226 (S/G 1D ID CA Nozzle Tempering Flow Isol) (DH-589, (DH-"'S89, EE-45, Rm 591).

oD 2.201.4 Open 1CA-224 lCA-224 (S/G 1B IB CA Nozzle Tempering Flow Isol) (DH-:588, (DH-588, DD-52, Rm 572).

o 2.201.5 D Open 1CA-225 lCA-225 (S/G 1C lC CA Nozzle Tempering Flow Isol) (DH-S'89, (DH-589, DD-52, Rm 572).

oD 2.201.6 Close 1CM-839 lCM-839 (S/G Warming Wanning Isol To Cond 1A) lA) to secure reverse purge flow to S/Gs.

oD 2.201.7 Compare S/G pressure and OAC point CIA1116 C1All16 (S/G Common Tempering Flow Line Pressure) to verify the S/G reverse purge line and tempering flow line pressure has increased to approximately S/G pressure.

oD 2.201.8 Open 1CF-100 lCF-100 (S/G CA Nozz Tempering Ctrl) to align CA tempering flow.

oD 2.201.9 Coordinate with Security to restrict access to the doghouses while transferring feedwater nozzles to only those personnel who are directly involved with nozzle swap activities. Refer to CNSD 3.1.2 (Access to Reactor Building and Areas Having High Pressure Steam Relief Devices).

Enclosure 4.1 OP;1/A/61 00/00 1 OP/l!A/6100/001 Unit Startup Page 61 of66 NOTE:

The CF Containment Isolation Valves have a history of sticking closed because reverse purge creates a temperature difference across the valve that can place it in a thermal bind.

Reducing the nitrogen overpressure (IAE procedure) has been effective in the past for getting the valves open. {PIP 00-1916}

The CF Containment Isolation Valve Lo Lo Nitrogen Pressure OAC almms alarms (CIA0001, (ClA0001, CIA0002, CIA0003, CIA0004)

ClA0004) may be generated in following step.

2.202 Issue the following Model W/O's for IAE to reduce the nitrogen overpressure in the valve actuators as required to get the valves to open:

o 00997487 (lCF-33) o 00997490 (lCF-42)

(ICF-42) o 00997492 (lCF-S1) o 00997494 (lCF-60)

Enclosure 4.1 OP/l!Al61 00/00 1 OP;1/A/6100/001 Unit Startup Page 62 of66 NOTE: 1. The CF Nozzle Swap Permissive lights are lit by

lCF-lOO lCF-100 (S/G CA Nozz Tempering Ctrl) being open

lCM-839 (S/G Warming Isol to Cond lA) being closed

Feedwater Isolation Valve for the S/G being closed.

2. The S/G automatic transfer for CA to CF per step 2.203 may be performed in any order.

3. When the last CF containment isolation is opened, operating CF pump speed will decrease by 150 rpm.

- - 2.203 IF automatic swap from the CA nozzle to CF nozzle is desired, do the following:

2.203.1 For S/G IA:lA:

o 2.203.1.1 Verify the "CF NOZZLE" light on "S/G lA NOZZLE SWAP PERMISSIVE" is lit.

o 2.203.1.2 IF "CF NOZZLE" is dark, perform a manual nozzle swap on this S/G per step Error! Reference source not found.

o 0 2.203.1.3 Press the "CF NOZZLE" on "S/G lA NOZZLE SEL".

2.203.1.4 2.203 .1.4 Verify the following:

o0 A. 1lCF-90 CF-90 (S/G 1A lA CF Cont Isol Byp Ctrl) closes.

o0 B. 1CF-33 lCF-33 (S/G lA CF Cont Isol) opens.

o 0 C. lCA-149 (S/G lA CF Byp To CA Nozzle) closes.

2.203.2 For S/G IB:lB:

o 2.203.2.1 Check that the "CF NOZZLE" light on "S/G IB NOZZLE SWAP PERMISSIVE" is lit.

o 2.203.2.2 IF "CF NOZZLE" is dark, perform a manual nozzle swap on this S/G per step Error! Reference source not found ..

o 2.203.2.3 Press the "CF NOZZLE" on S/G "S/G 1BIB NOZZLE SEL".

2.203.2.4 Verify the following:

o A. lCF-89 (S/G 1B IB CF Cont Isol Byp Ctrl) closes.

o B. lCF-42 (S/G IB CF Cont Isol) opens.

1CF-42

Enclosure 4.1 OP!l/A/6l 00/00 1 OP/l!A/6l00/00l Unit Startup Page 63 of66 o C. lCA-ISO (S/G lB lCA-lSO IB CF Byp To CA Nozzle) closes.

2.203.3 For S/G lC:

o 2.203.3.1 Check that the "CF NOZZLE" light on "S/G lC NOZZLE SWAP PERMISSIVE" is lit.

o 2.203.3.2 IF "CF NOZZLE" is dark, perform a manual nozzle swap on this S/G per step Error! Reference source not found ..

0 2.203.3.3 Press the "CF NOZZLE" on "S/G lC NOZZLE *SEL". SEL".

2.203.3.4 Verify the following:

0 A. lCF-88 (S/G lC CF Cont Isol Iso1 Byp Ctrl) closes.

0 B. ICF-5l (S/G lC CF Cont Iso1) opens.

lCF-5l 0 C. lCA-15l (S/G lC CF Byp To CA Nozzle) closes.

lCA-ISl 2.203.4 For S/G ID:

lD:

o 2.203.4.1 Check that the "CF NOZZLE" light on "S/G lD ID NOZZLE SWAP PERMISSIVE" is lit.

o 2.203.4.2 IF "CF NOZZLE" is dark, perform a manual nozzle swap on this S/G per step Error! Reference source not found.

0 2.203.4.3 Press the "CF NOZZLE" on "S/G lD NOZZLE SEL".

2.203.4.4 V erify the following:

Verify 0 A. lCF-87 (S/G lD CF Cont Isol Byp Ctrl) closes.

0 B. lCF-60 (S/G lD CF Cont Isol) opens.

0 C. lCA-152 (S/G lD CF Byp To CA Nozzle) closes.

Enclosure 4.1 OP/liAl61 001001 OP/l!Al6100/001 Unit Startup Page 64 of66 NOTE: 1. The hydraulic pump for the CF containment isolation valve will start whenever the "OPEN" pushbutton for the valve is pressed and continue to operate until the valve is open. If the valve does NOT open, the "CLOSE" pushbutton can be pressed to stop the hydraulic pump.

2. The S/G manual nozzle "Swapswap per Step 2.204 may be performed in any order.

3. When the last CF containment isolation is opened, operating CF pump speed will decrease by 1501SO rpm.

- - 2.204 IF manual transfer from the CA nozzles to CF nozzles desired, do the following:

2.204.1 For S/G 1A:

lA:

oD 2.204.1.1 Close 1CF-90 lCF-90 (S/G 1A lA CF Cont Isol Byp Ctrl).

oD 2.204.1.2 Open 1CF-33 (S/G 1AlA CF Cont Isol).

oD 2.204.1.3 Close 1CA-149 (S/G 1A CF Byp To CA Nozzle).

2.204.2 For S/G 1B:

oD 2.204.2.1 Close 11CF-89 CF-89 (S/G 1B CF Cont Isol Byp Ctrl).

oD 2.204.2.2 Open 1CF-42 (S/G 1BIB CF Cont 1'801).

Isol).

oD 2.204.2.3 Close 1CA-1S0 (S/G 1B CF Byp To CA Nozzle).

2.204.3 For S/G 1C:

oD 2.204.3.1 Close 1CF-88 (S/G 1C CF Cont Isol Byp Ctrl).

oD 2.204.3.2 lCF-51 (S/G 1C Open lCF-Sl lC CF Cont Isol).

oD 2.204.3.3 Close 1CA-1S1 lCA-lSl (S/G 1C CF Byp To CA Nozzle).

2.204.4 For S/G 1D:

lD:

oD 2.204.4.1 1CF-87 (S/G 1ID Close 1CF-87 D CF Cont 1'801 Isol Byp Ctrl).

oD 2.204.4.2 lCF-60 (S/G 1D CF Cont Isol).

Open 1CF-60 oD 2.204.4.3 1CA-1S2 (S/G 1D CF Byp To CA Nozzle).

Close 1CA-IS2 2.205 WHEN the last nozzle been transferred, verify operating feedpump speed decreases by 1 2.20'S 150

'SO rpm.

Enclosure 4.1 OP/l!Al61 00100 OP/I/A/61 00/0011 Unit Startup Page 65 of66 lCF-105 (S/G Tempering Flow Supply Throttle) (TB 580, 1H-33) 2.206 Throttle 1CF-105 lH-33) as necessary to establish between 80 and 135 gpm tempering flow to each S/G (lCAP5090, (1CAP5090, 1CAP5100, 1CAP5110, 1CAP5120). (R.M.)

NOTE: maybe Step 2.207 may N/A'd be NIA'd if the W/O's W10's issued in Step 2.202 are used to restore nitrogen pressure in the CF Containment Isolation Valve actuators.

- - 2.207 Issue the following model W lOs as required to restore N2 pressure on the CF containment isolation valves:

oD lCF-33 Model W/O 1CF-33 # 00875391 lCF-42 Model W/O D 1CF-42 # 00875392 lCF-51 Model W/O D 1CF-51 # 00875393 ICF-60 Model W/O D lCF-60 # 00875394.

2.208 Verify the following computer points on CF containment isolation valve N2 pressure have cleared:

D C1A0001 (Vlv CF33 S/G A CF Cont Isol N2 Press)

D C1A0002 (Vlv CF42 S/G B CF Cont Isol N2 Press)

D C1A0003 (Vlv CF51 CIA0003 S/G C CF Cont Isol N2 Press)

D C1A0004 (Vlv CF60 S/G D CF Cont Isol N2 Press)

NOTE: 1. The CF pump recirc valves will be automatically positioned to the full open condition whenever CF pump suction flow decreases to 4500 gpm or on a reactor trip signal.

However, the valve positioner on the electronic controller will maintain manual control of the valves. When the CFPT is in the tripped condition, the recirc valves need only to be adjusted manually once and subsequent signals

'signals will have no effect.

2. It is recommended that CF pump recirc valves completely closed by approximately 25%

reactor power.

- - 2.209 Start slowly closing the CF pump recirc valve for the operating pump as required to maintain suction flow approximately 6000 gpm.

D For 1A CF Pump Turbine, slowly close 1CF-6 lCF-6 (CF Pump 1A lA Recirc Ctrl).

D For 1B CF Pump Turbine, slowly close 1CF-13 (CF Pump 1B Recirc Ctrl).

Enclosure 4.1 0010011 OP/l!A/61 00100 Unit Startup Page 66 of66 CAUTION: Prior to placing control rods in automatic, T-AVO T-AVG shall be maintained within +/- 1°F of T-REF.

2.210 WHEN "C-5 LO TORB TURB IMPULSE PRESS ROD BLOCK" status light on IS1-18 ISI-18 clears, OP/1/A/61501008 (Rod Control). (R.M.)

place control rods in auto per OP/lIA/61501008

- - 2.211 WHEN the steam dump valves are closed, perform the following:

o 2.211.1 Ensure C-7A and C-7B are reset.

o 2.211.2 Transfer the "Steam Dump Select" switch to "T"T-AVO"

-AVG" control.

o 2.211.3 Ensure the pot on "STM DUMP CTRL" (MIA Station) is set to control for 1090 psig. (Figure 25, Unit 1 Revised Data Book) 2.212 IF continuing further power increases, go to OP/lIA/61001003 OP/1/A/61001003 (Controlling Procedure for Unit Operation).

2.213 File this enclosure in the Control Copy folder of this procedure.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Transfer Emergency Core Cooling System to Hot Leg Recirculation JPM09 F CANDIDATE EXAMINER JPM09 F Page 1 of 12

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Transfer Emergency Core Cooling System to Hot Leg Recirculation Alternate Path:

YES Facility JPM #:

NI-098 KIA Rating(s):

SYS006 A4.07 (4.4/4.4) Ability to manually operate and/or monitor in the control room: ECCS pumps and valves.

Task Standard:

Hot leg recirculation flow indicated from both trains of the ND system.

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator X In-Plant _ __ Perform _...:..X~

_..!.X.!....- Simulate _ __

References:

EP/1/A/5000/ES-1.4 (Transfer to Hot Leg Recirculation) revision 005 Validation Time: 15 min. Time Critical: No

=======================================================================

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM09 F Page 2 of 12

SIMULATOR SETUP SHEET

1. Reset to any 100% power IC set.

2. Insert MAL-NC013A (NC COLD LEG LEAK) VALUE 27.5

3. Complete required steps of E-O, E-1 and ES-1.3

4. Once swap to CLR is complete insert the following:

MAL-NI001A (SI Pump A failure), VALUE = BOTH

MAL-NI001 B (SI Pump B failure), VALUE= MANUAL MAL-NI001B

LOA-AS007 (AS59 - TO UNIT 2 SUPPLY), VALUE = 1

LOA-NI003 (RACKOUT NS PUMP 1A), VALUE= RACKOUT

5. Freeze simulator and write to a snap.

IC SELECTED _ _ _ _ __

SIMULATOR OPERATOR INSTRUCTIONS:

None Tools/Equipment/Procedures Needed:

EP/1/A/5000/ES-1.4 (Transfer to Hot Leg Recirculation) revision 005 EP/1/N5000/ES-1.4 JPM09 F Page 3 of 12

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

A LOCA on the NC System has been in progress for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The Emergency Core Cooling System (ECCS) is in the Cold Leg Recirculation lineup. 1A NI pump failed to start automatically and could not be manually started. An NLO has been dispatched to rack-out the 1A NI pump.

INITIATING CUES:

Transfer the ECCS System to Hot Leg Recirculation per EP/1/N5000/ES-1.4 (Transfer to Hot Leg Recirculation)

JPM09 F Page 4 of 12

START TIME: _ __

STEP 1a:

Align NI pumps for Hot Leg Recirc as follows: - SAT

a. Stop NI Pump 1A.

STANDARD: Notes pump is off.

- UNSAT COMMENTS:

STEP 1b:

b. Close 1 1NI-118A(NI NI-118A (NI Pump 1AC-Leg 1A C-Leg Inj Isol). - SAT STANDARD: Depresses the GREEN "CLOSED" pushbutton and verifies the GREEN "CLSD" light is LIT.

- UNSAT COMMENTS:

STEP 1.c:

Place "PWR DISCON FOR 1NI-121A" switch in "ENABLE"

- SAT STANDARD: Places "PWR DISCON FOR 1NI-121A" switch to the "ENABLE" position.

COMMENTS - UNSAT STEP 1.d:

- SAT 1NI-121A (NI To H-Legs B &

Open 1NI-121A & C).

STANDARD: Depresses the RED "OPEN" pushbutton and verifies the RED "OPEN" light is LIT. - UNSAT COMMENTS JPM09 F Page 5 of 12

STEP 1.e:

- SAT I. WHEN 1NI-121A is open, THEN start NI Pump 1A.

STANDARD: Depresses the red "ON" pushbutton and notes it will not start and continues. - UNSAT COMMENTS STEP 1.f:

f. Stop NI Pump 1B. - SAT STANDARD: Depressed the GREEN "OFF" pushbutton and verified the GREEN "OFF" light is lit.

- UNSAT COMMENTS STEP 1.9:

g. Close 1NI-150B (NI Pump 1B C-Leg Inj Isol). - SAT STANDARD: Depresses the GREEN "CLOSED" pushbutton and verifies the GREEN "CLSD" light is LIT.

- UNSAT COMMENTS STEP 1.h:

Place "PWR DISCON FOR 1NI-162A" switch in "ENABLE"

- SAT STANDARD: Places "PWR DISCON FOR 1NI-162A" switch to the "ENABLE" position.

COMMENTS - UNSAT JPM09 F Page 6 of 12

STEP 1.i:

- SAT Close 1NI-162A (NI To C-Legs Inj Hdr Isol).

STANDARD: Depresses the GREEN "CLOSED" pushbutton and verifies the GREEN "CLSD" light is LIT. - UNSAT COMMENTS STEP 1.j:

j. Place "PWR DISCON FOR 1NI-152B" switch in "ENABLE". - SAT STANDARD: Places "PWR DISCON FOR 1NI-152B" switch to the "ENABLE" position

- UNSAT COMMENTS STEP 1.k:

k. Open 1NI-152B (NI Pump 1B To H-Legs A&D). - SAT STANDARD: Depresses the RED "OPEN" pushbutton and notes the RED "OPEN" light is lit.

- UNSAT COMMENTS STEP 1.1:

I. WHEN 1NI-152B is open, THEN start NI Pump 1B. - SAT STANDARD: Depresses the red "ON" pushbutton and notes it will not start and continues.

- UNSAT COMMENTS JPM09 F Page 7 of 12

STEP 2:

Verify flow from at least one train of NI. - SAT STANDARD: Notes that both NI pumps are off and goes to RNO.

COMMENTS - UNSAT STEP 2 RNO:

Perform the following: - SAT

a. Notify station management that NI flow not indicated.

b. GO TO Step 4.

STANDARD: Notifies management that no NI flow is indicated and goes to - UNSAT step 4.

EXAMINER NOTE: When step to notify management is read, provide the following cue: "The eRS will notify site management that NI flow is not indicated,"

indicated."

COMMENTS STEP 4a:

Reeire as Align ND pumps for Hot Leg Recirc follows: - SAT

a. Verify the following valves - CLOSED.

1ND-1 B (ND Pump 1A SuctSuet Frm Loop B)

1ND-2A (ND Pump 1A Suct Suet Frm Loop B)

1ND-36B (ND Pump 1B Suct Suet Frm Loop C) - UNSAT

1ND-37 ND-37A A (ND Pump 1B Suct Suet Frm Loop C)

1ND-32A (ND Train 1A Hot Leg Inj Isol)

1ND-65B ND-6SB (ND Train 1B Hot Leg Inj Isol).

STANDARD: All valves should be noted closed.

COMMENTS JPM09 F Page 8 of 12

STEP 4b: CRITICAL STEP

b. Place "PWR DISCON FOR 1 1NI-183B" NI-183B" in "ENABLE".

- SAT STANDARD: Places "PWR DISCON FOR 1NI-183B" to the "ENABLE" position.

COMMENTS - UNSAT STEP 4c: CRITICAL STEP Open 1NI-183B (ND Hdr A&B Hot Leg Inj Isol).

- SAT STANDARD: Depresses RED "OPEN" pushbutton and verifies RED "OPEN" light is LIT.

COMMENTS - UNSAT STEP 4d: CRITICAL STEP

e. For A ND Train:

1) Verify 1NS-43A (ND Pmp 1A To Cont Spray Hdr) - CLOSED.

2) Place "PWR DlSCON FOR 1NI-173A" switch in "ENABLE". - SAT

3) Close 1NI-173A (NO Hdr 1A To Cold Legs A&B).

NO-32A (NO Train 1A Hot Leg Inj 1501).

4) Open 1ND-32A Isol).

STANDARD: - UNSAT

1. Notes 1NS-43A is closed.

2. Places "PWR DISCON FOR 1NI-173A" switch to the "ENABLE" position.

3. Depresses the GREEN "CLOSE" pushbutton on 1NI-173A 1NI-173A and verifies the GREEN "CLSD" light is LIT.

4. Depresses the RED "OPEN" pushbutton for 1ND-32A and verifies the RED "OPEN" light is LIT.

EXAMINER NOTE:

BOLD steps are required to meet the CRITICAL STEP.

COMMENTS JPM09 F Page 9 of 12

STEP 4e: CRITICAL STEP

e. For B ND NO Train:

(ND Pmp 1B To Cont Spray Hdr) - CLOSED.

1) Verify 1NS-38B (NO SAT

2) Place "PWR DISCON OISCON FOR 1 NI-178B" switch in "ENABLE".

1NI-178B"

3) Close 1NI-178B (NO (ND Hdr 1B To Cold Legs A&B).

4) Open 1ND-6SB (NO Train 1B Hot Leg Inj 1501).

NO-6SB (ND UNSAT STANDARD:

1. Notes 1NS-38B is closed.

2. Places "PWR DISCON FOR 1NI-178B" switch to the "ENABLE" position.

3. Depresses the GREEN "CLOSE" pushbutton on 1NI-178B and verifies the GREEN "CLSD" light is LIT.

4. Depresses the RED "OPEN" pushbutton for 1ND-65B and verifies the RED "OPEN" light is LIT.

EXAMINER NOTE:

BOLD steps are required to meet the CRITICAL STEP.

COMMENTS STEP 5:

Ensure Monitor Light Panel Group 6 HLR lights - LIT. SAT STANDARD: All lights are noted to be in the correct state.

COMMENTS UNSAT STEP 6:

Verify flow to NC hot legs from at least one train of ND.

NO. SAT STANDARD: Notes flow to the hot legs with both 1 1A A and 1B ND NO pump in service.

UNSAT COMMENTS JPM09 F Page 10 of 12

STEP 7:

RETURN TO procedure and step in effect. - SAT STANDARD: Reads step.

COMMENTS - UNSAT This JPM is complete.

TIME STOP: _ __

JPM09 F Page 11 of 12

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A LOCA on the NC System has been in progress for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The Emergency Core Cooling System (ECCS) is in the Cold Leg Recirculation lineup. 1A NI pump failed to start automatically and could not be manually started. An NLO has been dispatched to rack-out the 1A NI pump.

INITIATING CUES:

Transfer the ECCS System to Hot Leg Recirculation per EP/11A15000/ES-1.4 (Transfer to Hot Leg Recirculation)

Duke Power Company Procedure No.

Catawba Nuclear Station EP/I/A/SOOO/ES-1.4 EP/I/A/5000/ES-1.4 Revision No.

005 Transfer to Hot Leg Recirculation Electronic Reference No.

Continuous Use CPOO94CX PERFORMANCE I

* * * * * * * *

UNCONTROLLED FOR PRINT * * * * * * * * * *

(ISSUED) - PDF Format

CNS TRANSFER TO HOT LEG RECIRCULATION PAGE NO.

EP/11A15000/-ES-1.4 EP/1/A/5000/-ES-1.4 1 of 5 Revision 5 A. Purpose This procedure provides the necessary instructions for transferring the safety injection system to Hot Leg Recirculation.

B. Symptoms or Entry Conditions This procedure is entered from:

EP/11A15000/E-1 (Loss Of Reactor Or Secondary Coolant), Step 20, when the specified

a. EP/1/A/5000/E-1 time interval has elapsed.

b. When a decision is made, based upon the recommendation of station management, that transfer to Hot Leg Recirc is required. Transfer to Hot Leg Recirc might be required eventually, after transferring to Cold Leg Recirc during the implementation of:

EP/11A15000/ES-1.2 EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization)

EP/1/A/5000/ECA-3.1 EP/11A15000/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired)

EP/11A15000/ECA-3.2 EP/1/A/5000/ECA-3.2 (SGTR With Loss Of Reactor Coolant - Saturated Recovery Desired).

CNS TRANSFER TO HOT LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.4 EP/1/Al5000/ES-1.4 2 of 5 20f5 Revision 5 RevisionS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions

1. Align NI pumps for Hot Leg Recirc as follows:

a. Stop NI Pump 1A.

b. Close 1NI-118A (NI Pump 1A C-Leg Inj b. Perform the following:

Isol).

_ 1) Dispatch operator to close 1NI-118A 1}

(NI Pump 1A C-Leg Inj Isol)

(AB-553, GG-HH, 53-54, Rm 235).

_ 2) WHEN 1NI-118A 2} 1NI-118Aisclosed, is closed, THEN perform steps 1.c through 1.e.

_ 3) GO TO Step 1.f.

3}

c. Place "PWR DISCON FOR 1NI-121A" switch in "ENABLE".

d. Open 1NI-121A (NI Pump 1A To d. Dispatch operator to open 1NI-121A (NI H-Legs B&C). Pump 1A To H-Legs B&C) (AB-5?2, (AB-572, FF-GG, 52, Rm 318).

e. WHEN 1NI-121A is open, THEN start NI Pump 1A.

f. Stop NI Pump 1B.

_ g. Close 1NI-150B 1NI-150B (NI Pump 1B1B C-Leg Inj g. Perform the following:

Isol).

_ 1) Dispatch operator to close 1NI-150B 1} 1N 1-150B (NI Pump 1B C-Leg Inj Isol)

(AB-550, HH-JJ, 53-54, Rm 234).

_ 2) WHEN 1NI-150B is closed, THEN 2}

perform steps 1.h through 1.1.

_ 3}

3) GO TO Step 2.

h. Place "PWR DISCON FOR 1NI-162A" switch in "ENABLE".

i. 1NI-1'62A (NI To C-Legs Inj Hdr Close 1NI-t62A i. Dispatch operator to close 1NI-162A (NI Isol). To C-Legs Inj Hdr Isol) (AB-567, JJ-51 ,

(AS-56?, JJ-S1, Rm 318A).

CNS TRANSFER TO HOT LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.4 EP/1/Al5000/ES-1.4 3 of 5 Revision 5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. (Continued)

_ j. Place "PWR DISCON FOR 1NI-152B" switch in "ENABLE".

k. Open 1 NI-152B (NI Pump 1 1NI-152B B To 1B k. Dispatch operator to open 1NI-152B 1NI-152B (NI H-Legs A&D). Pump 1 1BB To H-Legs A&D) (AB-580, GG-HH, 52-'53, Rm 419).

I. WHEN 1NI-152B 1NI-152B is open, THEN start NI Pump 1B.

2. Verify flow from at least one train of NI. Perform the following:

a. Notify station management that NI flow not indicated.

b. GO TO Step 4.

3. RETURN TO Procedure and step in effect.

4. Align NO pumps for Hot Leg Recirc as follows:

a. Verify the following valves - CLOSED. a. Perform the following:

11ND-1B ND-1 B (ND Pump 1 1A A Suct Frm _ 1) 1} Contact station management for Loop B) guidance to align NI or ND for Hot

1ND-2A (ND Pump 1A Suct Frm Leg Recirc.

Loop B) 1ND-36B (ND Pump 1

1ND-36B B Suet 1B Suct Frm _ 2) 2} RETURN TO Procedure and step in Loop C) effect.

1 ND-37A (ND Pump 1 1ND-37A B Suct Frm 1B Loop C)

1ND-32A (ND Train 1A Hot Leg Inj Isol)

1 ND-65B (ND Train 1 1ND-65B B Hot Leg Inj 1B Isol).

b. Place "PWR DISCON FOR 1NI-183B" 1NI-183B" in "ENABLE".

CNS TRANSFER TO HOT LEG RECIRCULATION PAGE NO.

EP/1/N5000/ES-1.4 4 of 5 Revision 5 ACTION/EXPECTED RfSPONSE RESPONSE NOT OBTAINED

4. (Continued)

c. Open 1NI-183B HdrA&B 1NI-183B (ND Hdr A&B Hot Leg c. Perform the following:

Inj Isol).

1) 1} Close ND train discharge crossovers:

1ND-32A (ND Train 1A Hot Leg Inj Isol)

1ND-65B (ND Train 1B Hot Leg Inj Isol).

_ 2) 2} Open 1NI-173A (ND Hdr 1A To Cold Legs C&D).

_ 3} Dispatch operator to open 1NI-183B 3)

(ND Hdr A&B Hot Leg Inj Isol)

(AB-571, EE-FF, 52-53, Rm 333A).

_ 4) WHEN 1NI-183B is open, THEN 4}

perform Step 4.

_ 5} GO TO Step 5.

5)

d. For A ND Train:

_ 1) Verify 1NS-43A (ND Pmp 1A 1} 1A To _ 1} GO TO Step 4.e.

1)

Cont Spray Hdr) - CLOSED.

_ 2) 2} Place "PWR DISCON FOR 1NI-173A" switch in "ENABLE".

_ 3) Close 1NI-173A (ND Hdr 1A To 3} _ 3} Dispatch operator to close 1NI-173A

3) 1NI-173A Cold Legs C&D). (ND Hdr 1A To Cold Legs C&D)

(AB-566, HH-52, Rm 318A).

_ 4) Open 1ND-32A (ND Train 1A Hot 4} _ 4) 4} Dispatch operator to open 1ND-32A Leg Inj Isol). (ND Train 1A Hot Leg Inj Isol)

(AB-568, LL-MM, 51-52, Rm 434).

CNS TRANSFER TO HOT LEG RECIRCULATION PAGE NO.

EP/1/A15000/ES-1.4 EP/1/A/5000/ES-1.4 5 of 5 Revision 5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. (Continued)

e. For B NDNO Train:

_ 1) Verify 1NS-38B (ND (NO Pmp 1 B To 1B _ 1) GO TO Step 5.

Cont Spray Hdr) - CLOSED.

_ 2) Place "PWR DISCON FOR 1NI-178B" switch in "ENABLE".

1NI-178B"

_ 3) Close 1NI-178B (ND Hdr 1B 1NI-178B (NO 1B To _ 3) Dispatch operator to close 1NI-178B Cold Legs A&B). (ND (NO Hdr 1B To Cold Legs A&B)

(AB-561, FF-GG, 52-53, Rm 318A).

_ 4) Open 1 NO-'65B (NO 1ND--65B (ND Train 1B Hot 1B _ 4) Dispatch operator to open 1ND-USB ND--65B Leg Inj Isol). (ND Train 1B Hot Leg Inj Isol)

(NO (AB-570, KK-LL, 51-52, Rm 435).

5. Ensure Monitor Light Panel Group 6 HLR lights - LIT.

6. Verify flow to NC hot legs from at least _ Contact station management for one train of NO. guidance to align NO for Hot Leg Recirc.

7. RETURN TO procedure and step in effect.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 G Start Reactor Coolant Pump 1B CANDIDATE EXAMINER JPM09 G Page 1 of 14

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Start Reactor Coolant Pump 181B Alternate Path:

YES Facility JPM #:

NCP-081 KIA Rating(s):

SYS003 A 1.01 (2.9/2.9) Ability to manually operate and lor monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCP controls including: RCP vibration.

Task Standard:

Seal injection flow to 118 B NCP is restored to 7-10 gpm. 18 1B reactor coolant pump is tripped when vibration is noted to be greater than NC Pump trip criteria.

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator X In-Plant _ __ Perform _..!..X,,--

_...!.X-,-- Simulate _ __

References:

OP/1/A/61501002A (Reactor Coolant Pump), Enclosure 4.1 rev 061DCS OP/11A161501002A Validation Time: 25 min. Time Critical: No

=======================================================================

Candidate: Time Start:

NAME Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM09 G Page 2 of 14

SIMULATOR SETUP SHEET

1. Reset to any 100% power IC set.

2. Manually trip the reactor at 1MC-1.

3. Trip all (4) four NCP breakers at 1MC-10.

4. Place CF pump in service for auto S/G level control and secure CA.

5. Place 1NV-309 in manual and reduce total seal water flow to - 12 gpm

6. Insert MAL-NCP005FXB (NCP VIB B MOUNT HORIZ FAILURE) Initial =3.4 Ramp =480 Value=10, Value=1 0, EVENT = =1,1, Delay = 5

6. Insert MAL-NCP005FYB (NCP VIB B MOUNT VERT FAILURE) Initial =3.4 Ramp =480 Value=10, Value=1 0, EVENT =1, Delay = 5

6. Insert MAL-NCP005SXB (NCP VIB B MOUNT HORIZ FAILURE) Initial =16 Ramp =240 Value=30, EVENT = =1, 1, Delay = 5

6. Insert MAL-NCP005SYB (NCP VIB B MOUNT VERT FAILURE) Initial =16 Ramp =240 Value=30, EVENT = =1, 1, Delay = 5

7. Insert EVENT 1 = x10d185M x1 Od185M >400 (NCP B AMPS>400)

8. Freeze simulator and write to a snap.

IC SELECTED _ _ _ _ __

SIMULATOR OPERATOR INSTRUCTIONS:

ENSURE BENTLEY NEVADA VIBRATION MONITORS ON BACK BOARD ARE RESET AND THAT ALARMS 1AD-6 Af5 Al5 AND B/5 ARE CLEARED BETWEEN STUDENTS.

Tools/Equipment/Procedures Needed:

1. OP/1/Al6150/002A (Reactor Coolant Pump), Enclosure 4.1 rev 061 061DCS DCS JPM09 G Page 3 of 14

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

EP/11A15000/ES-O.2, Natural Circulation Cooldown has been implemented following a Reactor Trip.

EP/1/A/5000/ES-O.2, Control problems with 1NV-309 require the valve be operated in manual.

INITIATING CUES:

Start NC Pump 18 1B by completing OP/11A161501002A, OP/1/A/6150/002A, NC Pump Operation Enclosure 4.1. The Initial Conditions of Enclosure 4.1 have been satisfied.

JPM09 G Page 4 of 14

START TIME: _ __

CAUTION: An NC Pump shall NOT be started if associated 6.9 KV switchgear is supplying essential switchgear 1ETA or 1ETB and switchyard voltage is less than or equal to 223 KV or only one off-site source of power - SAT is available.

NOTE: 1. In order to start an NC Pump, the underfrequency condition must be cleared by having at least three of four 6900V breakers (1TA, B, C, 0-3) - UNSAT racked in and energized.

2. NC Pump operational configuration restrictions, as follows, will ensure adequate PZR spray for press control, maintain spray line water solid, and prevent thermal stratification of spray line {PIP C-OO-04752}:

-For single pump operation, ensure NC Pump B is in service,

-For multiple pump operation, if NC Pump B is NOT in service, NC Pumps A, C and 0 will need to be in service, {PIP C-01-4130}

otherwise, Auxiliary PZR spray flow will have to be used.

STANDARD: Acknowledges notes and cautions.

COMMENTS:

STEP 2.1 If Unit 1 is in Mode 5 ...

STANDARD: This step is N/A per plant conditions.

COMMENTS:

STEP 2.2 If the pump to be started will be the fourth NC pump in service on Unit 1...

- SAT STANDARD: This step is N/A per plant conditions.

COMMENTS: UNSAT JPM09 G Page 5 of 14

NOTE: If #1 Seal boP f:.P gauge overranged, boP f:.P can be determined using 1NV125B (Excess Letdn Hx Otlt Ctrl) "VCT" or "NCDT" switch position as follows: SAT

=

"VCT" position: NC Press minus Excess Letdn Hx Otlt Press = #1 Seal boP f:.P

"NCDT" position: NC Press minus VCT Press =#1 Seal boP f:.P STANDARD: Acknowledges note. UNSAT COMMENTS:

STEP 2.3:

Verify No.1 Seal DIP is greater than 200 psig for the pump to be started SAT per the following gauges: (Control Board MC-5)

1B NCP: 1NVP 5220 UNSAT STANDARD: Verifies seal DIP> 200 psig using stated gauge.

OR For "VCT" position: NC Press minus Excess Letdn Hx Otlt Press = =#1 Seal f:.P boP COMMENTS STEP 2.4:

Verify that the standpipe level for the pump to be started is normal by its SAT associated annunciator DARK.

"NCP B #2 SEAL S-PIPE HIILO LVL" 1AD-7 Al2 UNSAT STANDARD: Notes the stated alarm is DARK.

COMMENTS JPM09 G Page 6 of 14

STEP 2.5:

Verify VCT pressure is equal to or greater than 15 psig.: SAT

_SAT STANDARD: Verifies VCT pressure is ~ 15 psig

_UNSAT COMMENTS STEP 2.6: CRITICAL STEP Verify 7-10 gpm seal injection flow on the pump to be started by the following gauges: (Control Board MC-5) SAT

_SAT

1B NCP: 1NCP5320 STANDARD: Notes seal injection flow is <7 gpm on stated gauge. Adjusts UNSAT

_UNSAT 1NV-309 in manual to restore seal injection flow to proper range of 7-10 GPM.

EXAMINER CUE: IF student contacts supervision, state:

"Restore seal injection to its required range."

COMMENTS NOTE:

1. If #1 Seal Leakoff Flow rate is < 1.0 gpm, the # 1 Seal Low Flow SAT indication shall be used.

~P gauge overranged, .6.P Seal.6.P

2. If #1 Seal ~P can be determined using 1NV125B (Excess Letdn Hx Otlt Ctrl) "VCT" or "NCDT" switch position as follows:

=

"VCT" position: NC Press minus Excess Letdn Hx Otlt Press #1 Seal UNSAT

~P

.6.P

=

"NCDT" position: NC Press minus VCT Press = #1 Seal ~P Seal.6.P STANDARD: Acknowledges note.

COMMENTS JPM09 G Page 7 of 14

STEP 2.7 Verify adequate #1 Seal Leakoff Flow on the pump to be started as follows: - SAT 2.7.1 Determine required #1 Seal Leakoff Flow from Revised Data Book Figure 26 (NC Pump No.1 Seal Normal Operating Range).

- UNSAT STANDARD: Determines that based on data book Figure 26 or OAC databook that -1 gpm is the minimum required.

COMMENTS STEP 2.7 2.7.2 Add 0.26 gpm to the minimum required #1 Seal Leakoff Flow of - SAT Figure 26 to correct for an expected drop in leakoff flow on pump start (0.20 gpm) and instrument inaccuracy (0.06 gpm).

STANDARD: Determines that the minimum required is 1+0.26 =1.26 - UNSAT COMMENTS STEP 2.7 2.7.3 Obtain the current #1 Seal Leakoff Flow per one of the following: - SAT DCS graphic 6002 (NC PUMPS)

OR Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR - UNSAT 1NVCR5140 (NC Pump Lo Leakoff Flow) (1MC5) (1 MC5)

OR 1NVCR5121 1NVCR5121 (NC Pump Hi Leakoff Flow) (1MC5) (1 MC5)

OR Appropriate GAC OAC point C1A1376 (NC Pmp B No.1 Seal Leakoff Lo Flow)

C1A0442 (NC Pmp B No.1 Seal Leakoff Flow)

STANDARD: Notes sealleakoff seal leakoff is within limits.

COMMENTS JPM09 G Page 8 of 14

STEP 2.7 2.7.4 IF the current #1 Seal Leakoff Flow (Step 2.7.3) is less than the SAT minimum flow ...

STANDARD: Determines that this step is N/A and continues.

UNSAT COMMENTS STEP 2.7 2.7.5 Verify the indicated #1 Seal Leakoff Flow (Step 2.7.3) is within the SAT range of Revised Data Book Figure 26 as adjusted per Step 2.7.2.

STANDARD: Determines that the sealleakoff is within the normal range.

UNSAT COMMENTS STEP 2.8:

Verify upper and lower oil pot levels normal, for the pump to be started, via one of the following: SAT

Unit 1 Reactor Coolant Pump graphic (NCPMPALL)

OR

Visual Inspection UNSAT OR

Associated annunciators DARK:

"NCP A UPPER/LOWER OIL RESERVOIR LO LEVEL" 1AD-6 F/2 STANDARD: Verifies upper and lower pot levels normal NCP GRAPHIC or Visual inspection (local) or Annunciator 1AD-6 F/2, "NCP B PPER/LOWER OIL RESERVOIR LO LEVEL" Dark.

COMMENTS JPM09 G Page 9 of 14

NOTE: KC flow is NOT required to the Thermal Barrier Hx whenever NC system temperature is less than 200°F. - SAT STANDARD: Acknowledges note and continues.

COMMENTS - UNSAT STEP 2.9:

Verify KC flow to the Thermal Barrier Heater Exchanger normal, for the pump to be started,via one of the following: - SAT Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR Associated annunciators DARK:

- UNSAT "NCP B THERMAL BARRIER KC OUTLET HIILO FLOW" 1AD-6 E/2 STANDARD: Verifies KC flow to Thermal Barrier Heat Exchanger: NC Pump GRAPHIC or Annunciator 1AD-6 E/2, "NCP B THERMAL BARRIER KC OUTLET HIILO FLOW", Dark is normal.

COMMENTS STEP 2.10:

Verify KC flow to the Upper Motor Bearing Oil Cooler normal, for the pump to be started, via one of the following: - SAT Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR Associated annunciators DARK:

"NCP B MTR UPPER BRG KC OUTLET HIILO FLOW" 1AD-6 C/2 - UNSAT STANDARD: Verifies KC flow to upper motor bearing oil cooler: NCP GRAPHIC or Annunciator 1AD-6 C/2 "NCP B MTR UPPER BRG KC OUTLET HIILO FLOW", Dark is normal.

COMMENTS JPM09 G Page 10 of 14

STEP 2.11:

Verify KC flow to the Lower Motor Bearing Oil Cooler normal, for the pump to be started, via one of the following: SAT Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR Associated annunciators DARK:

"NCP B MTR LOWER BRG KC OUTLET LO FLOW" 1AD-6 0/2 D/2 UNSAT STANDARD: Verifies KC flow to lower motor bearing oil cooler (NCP GRAPHIC or Annunciator 1AD-6 0/2 D/2 "NCP B MTR LOWER BRG KC OUTLET LO FLOW", Dark) is normal.

COMMENTS STEP 2.12:

Verify "230KV SWITCHYARD VOLTAGE LO" Annunciator on 1AD-11, Kl6 dark. SAT STANDARD: Verifies Annunciator "230KV Swyd Volt Lo" on 1AD-11, Kl6 is dark.

UNSAT COMMENTS STEP 2.13: CRITICAL Two minutes prior to starting NC pump, start one oil lift pump for NCP to be STEP started by pressing the "ON" pushbutton for:

"NC PUMP OIL LIFT PUMP B1" SAT "NC PUMP OIL LIFT PUMP B2" STANDARD: Depresses RED "ON" pushbutton for NC PMP OIL LIFT PMP B1 or B2 approximately two minutes prior to starting 1B NC Pump. UNSAT Verifies RED "ON" light lit.

It is critical that the pump be started. The 2 minute wait is NOT critical per the NCP principle engineer.

COMMENTS JPM09 G Page 11 of 14

NOTE:

1. If NC pump is NOT started, the oil lift pump shall be secured to minimize stress on oil nozzles. SAT

2. The Degraded Bus Voltage Relays (27N) may actuate on the essential bus being supplied by the 6.9KV Switchgear associated with the NC Pump to be started in the following step. The alarm condition is expected to clear within 36 seconds.{PIP 95-0287} UNSAT STANDARD: Acknowledges note.

COMMENTS STEP 2.14: CRITICAL Start desired NC pump by pressing the "ON" pushbutton for: STEP "NC PMP 1B" STANDARD: Depress RED "ON" pushbutton for NC PMP 1B. Verifies SAT RED "ON" light lit and pump amps stabilized near midscale on ammeter.

Once Hi Hi vibration is verified, the pump should be tripped.

EXAMINER NOTE: UNSAT Alarms: 1AD-6, Al5 NCP HI VIBRATION 1AD-6, B/5 NCP HI-HI VIBRATION Approximately 5 seconds after the NCP is started, the HI Vibration alarm will come in. The shaft vibration will reach 20 mils prior to reaching 5 on the mount. Per the annunciator response, the pump should be tripped at

>20 mils in Modes 1 and 2, but not until >30 mils in Mode 3 (current condition). At 5 mils on the mount, the pump is tripped regardless of mode.

5 mils on the mount will occur before 30 mils on the shaft.

COMMENTS JPM09 G Page 12 of 14

EXAMINER CUE: When pump is tripped, state: "The CRS has pulled AP/1/Al5500/004 (Loss of Reactor Coolant Pump) and is ready to proceed."

- SAT STANDARD: Determines that the task has been completed.

COMMENTS

- UNSAT This JPM is complete.

TIME STOP: _ __

JPM09 G Page 13 of 14

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

EP/11A15000/ES-O.2, EP/1/A/SOOO/ES-O.2, Natural Circulation Cooldown has been implemented following a Reactor Trip.

Control problems with 1NV-309 require the valve be operated in manual.

INITIATING CUES:

Start NC Pump 1 1BB by completing OP/11A16150/002A, OP/1/A/61S01002A, NC Pump Operation Enclosure 4.1. The Initial Conditions of Enclosure 4.1 have been satisfied.

Enclosure 4.1 OP/liA/6150/002 A OP/liAI61501002 Startup and Operation of the NC Pumps Page 1 of7

1. Initial Conditions

~ 1.1 Review the Limits and Precautions.

~ 1.2 Verify seal injection flow has been established to each Reactor Coolant Pump per OP/1/A/6200/001 (Chemical and Volume Control System).

OP/1/A162001001

~ 1.3 OP/1/A/6400/o05 (Component Verify Component Cooling System is in Operation per OP/1/A/64001005 Cooling System).

~ 1.4 OP/1/A/6150/002 B (NC Pump Motor Oil Verify Reactor Coolant Pumps are aligned per OP/1/Al61501002 Fill and Drain System).

--'~1.5 R 1.5 OP/1/A/6150/001 Verify Reactor Coolant System is filled per OP/1/

Reactor Coolant System).

Al6150100 1 (Filling and Venting The

~

--k 1.6 Verify the NCDT is aligned for operation per OPI Liquid Waste Systems).

OP/1/A/65 00/0 14 (Operations Controlled l/Al65 0010

~ 1.7 IF NC Pump operation is expected to exceed one minute, verify NCP motor cooling water from YV (preferred) or RN has been established.

~

--R 1.8 Ensure that a Written prejob briefing has been performed per Site Directive 3.0.21 (Prejob Briefing) that includes a discussion of reactivity management concerns with this procedure.

Enclosure 4.1 OP!l/A/6150/002 A Startup and Operation of the NC Pumps Page 2 of7

2. Procedure CAUTION: An NC Pump shall NOT be started if associated 6.9 KV switchgear is supplying essential switchgear lETA or 1ETBIETB and switchyard voltage is less than or equal to 223 KV or only one off-site source of power is available NOTE: 1.

I. In order to start an NC Pump, the underfrequency condition must be cleared by having at least three of four 6900V breakers (1 TA, B, C, D-3) racked in and energized.

2. NC Pump operational configuration restrictions, as follows, will ensure adequate PZR spray for press control, maintain spray line water solid, and prevent thermal stratification of spray line {PIP C-00-04 752}:

For single pump operation, ensure NC Pump B is in 'service, service,

For multiple pump operation, ifNC Pump B is NOT in service, NC Pumps A, C and D will need to be in service, {PIP C-01-4130}

otherwise, Auxiliary PZR spray flow will have to be used.

2.1 IF Unit 1I is in Mode 5, refer to Tech Spec Table 3.4.12-1 (Reactor Coolant Pump Operating Restrictions For Low Temperature Overpressure Protection) for temperature limitations on NC Pump starts.

2.2 IF the pump to be started will be the fourth NC Pump in service on Unit 1, I, verity NC temperature is:::: 130°F. {PIP 96-1290, PIP 02-484}

is ?130°F.

NOTE: If#l Seal ~P gauge overranged, ~P can be determined using 1NV125B 1f#1 INV125B (Excess Letdn Hx Otlt Odt Ctrl) "VCT" or "NCDT" switch position as follows:

"VCT" position: NC Press minus Excess Letdn Hx Odt ~P Otlt Press == #1 Seal L1P

"NCDT" position: NC Press minus VCT Press == #1 Seal ~P 2.3 Verify that No.1 seal M ~P is greater than 200 psig for the pump to be started per the following gauges: (Control Board 1MC5) IMC5)

D 1A lA NCP: 1NVP5230 INVP5230 D 1B IB NCP: 1NVP5220 INVP5220 D 1C lC NCP: INVP5210 D 1D ID NCP: 1NVP5200 INVP5200

Enclosure 4.1 OP!l/A/6l50/002 A OP!lIAl61501002 Startup and Operation of the NC Pumps Page 3 of7 2.4 Verify that the standpipe level for the pump to be started is normal by its associated annunciator DARK:

o "NCP A #2 SEAL S-PIPE HI!LO LVL" 1AD-7 All lAD-7 A/I o "NCP B #2 SEAL S-PIPE HI!LO LVL" LVL" 1AD-7 lAD-7 A/2 Al2 o "NCP C #2 SEAL S-PIPE HI!LO LVL" 1AD-7 lAD-7 A/3 o "NCP D #2 SEAL S-PIPE HIILO LVL" 1AD-7 lAD-7 A/4 2.5 Verify that VCT pressure is ~ 15 psig.

2.6 Verify 7-10 gpm seal injection flow on the pump to be started by the following gauges:

(Control Board 1MC5) lMC5) o 1AlA NCP: 1NVP5330 lNVP5330 o 1B lB NCP: 1NVP5320 lNVP5320 o 1lC C NCP: 1NVP531O lNVP53l0 o 1D lD NCP: 1NVP5300 lNVP5300

Enclosure 4.1 OP;l/A/61S0/002 OP!l/A/61S0/002 A Startup and Operation of the NC Pumps Page 4 of7 NOTE: 1. If#1 Seal LeakoffFlow rate is < 1.0 gpm, the # 1 Seal Low Flow indication shall be used.

2. If#1 Seal i!P ~P gauge overranged, M1

~P can be detennined determined using 1NV125B INV125B (Excess Letdn Hx Otlt Ctrl) "VCT" or "NCDT" switch position as follows:

"VCT" position: NC Press minus Excess Letdn Hx Otlt Press == #1 Seal i!P ~P

"NCDT" position: NC Press minus VCT Press == #1 Seal i!P ~P 2.7 Verify adequate #1 Seal LeakoffFlow on the pump to be started as follows:

2.7.1 Determine required ##11 Seal Leakoff Detennine LeakoffFlow Flow from Revised Data Book Figure 26 (NC Pump No.1 Seal Normal Nonnal Operating Range).

2.7.2 Add 0.26 gpm to the minimum required #1 Seal LeakoffFlow of Figure 26 to correct for an expected drop in leakoffflow on pump start (0.20 gpm) and instrument inaccuracy (0.06 gpm).

2.7.3 Obtain the current #1 Seal LeakoffFlow per one of the following:

oD DCS graphic 6002 (NC PUMPS)

OR oD Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR oD 1NVCR5140 (NC Pump Lo LeakoffFlow) (lMCS) (lMC5)

OR Do 1NVCR5121 (NC Pump Hi LeakoffFlow) (lMC5) (lMCS)

OR

Appropriate OAC point oD C1A1370 CIA1370 (NC Pmp A No.1 Seal LeakoffLo Flow) oD C1A0436 (NC Pmp A No.1 Seal LeakoffFlow) oD C1A1376 (NC Pmp B No.1 Seal LeakoffLo Flow) oD C1A0442 CIA0442 (NC Pmp B No.1 Seal LeakoffFlow) oD C1A1382 (NC Pmp C No.1 Seal LeakoffLo Flow) oD C1A0448 (NC Pmp C No.1 Seal LeakoffFlow) oD C1A1388 CIA1388 (NC Pmp D No.1 Seal LeakoffLo Flow) oD CIA0454 C1A0454 (NC Pmp D No.1 Seal LeakoffFlow) 2.7.4 IF the current #1 Seal LeakoffFlow (Step 2.7.3) is less than the minimum flow determined in Step 2.7.2, refer to Enclosure 4.4 (Operator Action For Low #1 Seal detennined LeakoffFlow).

2.7.S 2.7.5 Verify the indicated #1 Seal LeakoffFlow (Step 2.7.3) is within the range of Revised Data Book Figure 26 as adjusted per Step 2.7.2.

Enclosure 4.1 OPIl!Al61501002 A OP!lIA/61501002 Startup and Operation of the NC Pumps Page 5 of7 2.8 Verify VerifY upper and lower oil pot levels normal, for the pump to be started, via one of the following:

o Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

(NCPMPALL)

OR o Visual inspection (local)

OR

Associated annunciators DARK:

o "NCP A UPPERILOWER OIL RESERVOIR La LO LEVEL" lAD-6 FIl 1AD-6 o "NCP B UPPERILOWER OIL RESERVOIR La LO LEVEL" lAD-6 F/2 1AD-6 F12 o "NCP C UPPER/LOWER UPPERILOWER OIL RESERVOIR La LO LEVEL" lAD-6 F/3 1AD-6 o "NCP D UPPERILOWER OIL RESERVOIR La LO LEVEL" lAD-6 F/4 NOTE: KC flow is NOT required to the Thennal Thermal Barrier Hx whenever NC System temperature is less than 200°F.

2.9 Verify KC flow to the Thermal Thennal Barrier Heater Exchanger normal, nonnal, for the pump to be started, via one of the following:

o Unit 1 Reactor Coolant Pumps graphic (NCPMP (NCPMPALL)ALL)

OR

Associated annunciators DARK:

o "NCP A THERMAL BARRIER KC OUTLET HIILO HIlLa FLOW" lAD-6 Ell 1AD-6 o "NCP B THERMAL BARRIER KC OUTLET HIILO HIlLa FLOW" lAD-6 E/2 1AD-6 o "NCP C THERMAL BARRIER KC OUTLET HIlLa HIILO FLOW" lAD-6 E/3 o "NCP D THERMAL BARRIER KC OUTLET HIILO FLOW" lAD-6 E/4 2.10 Verify KC flow to the Upper Motor Bearing Oil Cooler normal, VerifY nonnal, for the pump to be started, via one of the following:

o Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR

Associated annunciators DARK:

o "NCP A MTR UPPER BRG KC OUTLET HIlLa HIILO FLOW" lAD-6 CIl 1AD-6 CII o "NCP B MTR UPPER BRG KC OUTLET HIILO FLOW" lAD-6 C/2 1AD-6 C12 o "NCP C MTR UPPER BRG KC OUTLET HIILO HIlLa FLOW" lAD-6 C/3 o "NCP D MTR UPPER BRG KC OUTLET HIlLa HIILO FLOW" lAD-6 C/4 1AD-6

Enclosure 4.1 OP;l/A/6 150/002 A OP!l/A/61501002 Startup and Operation of the NC Pumps Page 6 of7 2.11 Verify KC flow to the Lower Motor Bearing Oil Cooler normal, for the pump to be started, via one of the following:

D Unit 1 Reactor Coolant Pumps graphic (NCPMPALL)

OR

Associated annunciators DARK:

D "NCP A MTR LOWER BRG KC OUTLET LO FLOW" 1AD-6 DIl lAD-6 DII D "NCP B MTR LOWER BRG KC OUTLET LO FLOW" 1AD-6 lAD-6 D/2 D "NCP C MTR LOWER BRG KC OUTLET LO FLOW" 1AD-6 lAD-6 D/3 D "NCP D MTR LOWER BRG KC OUTLET LO FLOW" 1AD-6 lAD-6 D/4 2.12 Verify annunciator lAD-II, K-6, "230 KV SWITCHYARD VOLTAGE LO" is dark.

2.13 Two minutes prior to starting NC pump, start one oil lift pump for NCP to be started statied by pressing the "ON" pushbutton for:

D "NC PUMP OIL LIFT PUMP AI" D "NC PUMP OIL LIFT PUMP A2" D "NC PUMP OIL LIFT PUMP Bl" B 1" D "NC PUMP OIL LIFT PUMP B2" D "NC PUMP OIL LIFT PUMP C1" Cl" D "NC PUMP OIL LIFT PUMP C2" D "NC PUMP OIL LIFT PUMP Dl" D1" D "NC PUMP OIL LIFT PUMP D2" NOTE: 1. IfNC pump is NOT started, the oil lift pump shall be secured to minimize stress on oil nozzles.

2. The Degraded Bus Voltage Relays (27N) may actuate on the essential bus being supplied by the 6.9KV Switchgear associated with the NC Pump to be statied sta11ed in the following step. The alarm condition is expected to clear within 36 seconds. {PIP 95-0287}

2.14 Start desired NC pump by pressing the "ON" pushbutton for: (R.M.)

D "NC PUMP lA" 1A" D "NC PUMP lB" 1B" D "NCPUMP lC" 1C" D "NC PUMP 1D" lD"

Enclosure 4.1 OP/l!A/6150/002 A OP/I/A/61'S01002 A Startup and Operation of the NC Pumps Page 7 of7 2.15 Observe all pump and motor parameters to verify proper operation.

NOTE: If#1 Seal LlP 1f#1 i1P gauge overranged, i1P LlP can be determined using Il\TVI2'SB INV125B (Excess Letdn Hx Otlt Ctrl) "VCT" or "NCDT" switch position as follows:

"VCT" position: NC Press minus Excess Letdn Hx Otlt Press = #1 Seal LlP

=#1 i1P

"NCDT" position: NC Press minus VCT Press = #1 Seal LlP i1P

#1 Seal LlP 2:. 200#.

i1P .:::

Inlet Seal Water Flow Plow 7 gpm to 10 gpm.

NOTE: If#1 Seal LeakoffFlow 1f#1 LeakoffPlow Rate is < 1.0 gpm, the #1 Seal Low Plow Flow indication shall be used.

The 0.26 gpm flow correction for the required flow rate per Step 2.7.2 of Enclosure 4.1 (Startup and Operation of the NC Pumps), shall be reduced to 0.06 gpm (instrument accuracy).

LeakoffPlow per Step 2.7.

1 Seal LeakoffFlow

Pump Radial Bearing Temp. < 22'S°F. 225°P.

No.1 Seal Outlet temp. between 60°F 60 0 P and 23'S 235°P.

OF.

Pump shaft vibration < 15 1'S mils.

190 0 P.

Motor bearings < 190°F.

Motor winding temp. < 302°F.302°P.

Motor frame vibration < 3 mils.

2.16 Three minutes after flow in the affected NC Loop exceeds 90%, stop the oil lift pump started in Step 2.13.

2.17 Repeat Steps 2.1 through 2.16 of this enclosure for starting additional NC pumps.

2.18 Do NOT file this enclosure in the Control Copy folder of this procedure.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 H Shift Operating RC Pumps CANDIDATE EXAMINER JPM09 H Page 1 of 12

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Shift Operating RC Pumps.

Alternate Path:

YES Facility JPM #:

NRC BANK KIA Rating(s):

SYS075 G 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. 4.3/4.4 Task Standard:

1A and 1D RC pumps are in service and 1RC-22 is closed.

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator _....:...X-,--

_....<..X,,-- In-Plant _ __ Perform _~X",--

_....<..X,,-- Simulate _ __

{

References:

OP/1/B/6400/001A (Condenser Circulating Water) Enclosure 4.7 rev 066 Validation Time: 10 min. Time Critical: No

=======================================================================

Candidate: Time Start: _ __ ____

NAME Time Finish: - _- _-_-

Performance Rating: SAT ___ UNSAT _ __ Question Grade _ __ _-

Performance Time - _- _

-'"_ _ _ _ ~--:::-------_

Examiner: ....:. _--=::--_ _ _ _ __ ---------------~/_~~

~~~~~---~/------

NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM09 H Page 2 of 12

SIMULATOR SETUP SHEET

1. Reset to any 50% power snap.

2. Ensure 1A and 1B RC pumps in service.

3. Insert XMT-RC063 (TRC_6960 RC PUMP B LOWER GUIDE BRG TEMP (OAC) VALUE = 235, RAMP 600

4. Insert LOA-RC066 (RACKOUT RC PMP 1B), VALUE= RACKOUT, EVENT=1, DELAY = 360 s

5. Insert VLV-RC011 VLV-RC011F F (RC23 CCW PUMP 1C DISCHARGE VLV FAIL TO POSITION)

VALUE = 0, EVENT = 1, DELAY = 15 s

6. Insert EVENT 1 as: x13i159n (This is the ON pushbutton for 1C RC pump being depressed.)

7. SNAP to an open IC set.

SIMULATOR OPERATOR INSTRUCTIONS:

Do not go to RUN until the student is ready to proceed.

Tools/Equipment/Procedures Needed:

1. OP/1/B/6400/001A (Condenser Circulating Water), Enclosure 4.7 rev 066 JPM09 H Page 3 of 12

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

Unit 1 is operating at 50% power following repair of a condenser tube leak.

The turbine building rounds NLO reports severe vibration and noise coming from 18 1B RC pump and states that the motor is extremely hot to the touch.

The NLO has checked out 1C RC Pump and it is not rotating in the reverse direction.

The NLO is standing by to check 1C RC pump after it starts.

INITIATING CUES:

Start 1C RC Pump and secure 1B RC Pump per Enclosure 4.7 of OP/1 18/64001001IB/64001001 A (Condenser Circulating Water). Initial Conditions are complete.

(

JPM09 H Page 4 of 12

START TIME: _ __

I EXAMINER NOTE: Due to the imminent failure of 1B RC pump (based on the

( fording of the initiating cue) the operator may decide to use OMP 1-8 (Authority and lording Responsibility of On-shift Operations Personnel) guidance to start or secure RC pumps as required to prevent a plant transient. It is acceptable use of OMP 1-8 in lieu of the OP to stabilize the plant and then use the OP to follow-up the OMP 1-8 actions to ensure the plant is in proper alignment. This may include stopping 1B RC pump prior to starting another RC pump.

STEP 2.1:

_SAT 2.1 Start the desired RC pump as follows:

2.1.1 Verify the RC pump to be started is NOT rotating in the reverse direction.

_UNSAT STANDARD: Per initiating cue it is NOT rotating in reverse.

COMMENTS:

STEP 2.1:

SAT

~.1.2

<.1.2 Ensure "RCP DISCH VALVE MODE SEL" in the "NORM" position.

f I,

STANDARD: Check switch in NORM position.

_UNSAT COMMENTS:

STEP 2.1 SAT NOTE:

To start a third RC pump three cooling towers are required to be in service to meet the interlock. This is accomplished by temporarily opening a third tower inlet isolation, it will be reclosed by Step 2.3. _UNSAT UNSAT STANDARD: Acknowledges note.

COMMENTS:

JPM09 H Page 5 of 12

STEP 2.1:

_SATSAT

.1.3.1 IF starting a third RC pump, indicate which cooling tower inlet isolation is closed:

o 1RC-25 (Cool Twr 1A Inlet Isol)

_UNSAT STANDARD: Examinee notes that 1RC-25 is closed.

COMMENTS:

STEP 2.1:

SAT 2.1.3.2 ENSURE all three cooling tower inlet isolation valves are open o 1RC-25 (Cool Twr 1A Inlet Isol)

UNSAT

_UNSAT STANDARD: Examinee opens 1RC-25 by depressing the RED "OPEN" pushbutton and noting the RED "OPEN" light illuminates.

EXAMINER NOTE: This is a large valve and takes -3.5 minutes to stroke.

COMMENTS:

STEP 2.1.

NOTE; Wait approximately two minutes after starting an RC pump before stopping _SAT SAT the desired RC pump to allow flow to stabilize.

Following each configuration change, sufficient time should be allowed for RC Cooling Tower Levels to stabilize prior to aligning additional components

_UNSAT STANDARD: Examinee acknowledges notes.

COMMENTS:

JPM09 H Page 6 of 12

2.1 .

STEP 2.1.

.,1.4 1.4 Start the desired RC pump _SAT SAT STANDARD: Examinee starts 1C 1C RC Pump per the initiating cue.

_UNSAT UNSAT COMMENTS:

Critical Step STEP 2.1:

2.1.5 Ensure that its discharge valve fully opens. (Valve begins to open six seconds _SAT SAT after pump start.)

STANDARD: Examinee should note that valve 1RC-23 begins to open and then recloses and 1C RC pump trips.

reeloses _UNSAT UNSAT EXAMINER NOTE: Examinee should realize that it is critical that 1B pump be shut down and that 1D RC pump is available to start. The candidate should go back and re-perform step 2.1.4 and 2.1.5 for 1D RC pump, however, he may use OMP 1-8 guidance (see examiner note at beginning of JPM) and either starts 1D pump directly, or secures I, j1B RC pump and then starts 1 D RC pump. He is still obligated to verify that 1D RC

( Jmp is operating correctly per the OP (pump starts and discharge valve opens fully),

'yand and at the completion of the JPM, have the RC system back in normal alignment with 1A and 1D RC pumps in service.

1A EXAMINER CUE: If notified that 1C RC pump discharge valve did NOT open provide the following cue: "Start 1D RC Pump and secure 1B RC Pump".

EXAMINER NOTE: If asked by student to verify 1D RC Pump is not rotating in the reverse condition or to checkout 1D RC pump prior to start, provide the following cue:

"1 D RC pump is not rotating in the reverse direction and all local parameters are normal."

COMMENTS:

(

JPM09 H Page 7 of 12

STEP 2.1.

OTE; Wait approximately two minutes after starting an RC pump before stopping _SAT SAT the desired RC pump to allow flow to stabilize.

Following each configuration change, sufficient time should be allowed for RC Cooling Tower Levels to stabilize prior to aligning additional components

_UNSAT STANDARD: Examinee acknowledges notes.

COMMENTS:

Critical Step STEP 2.1.

2.1.4 Start the desired RC pump _SAT SAT STANDARD: Examinee starts 1 D RC Pump.

1D EXAMINER NOTE: Candidate may start 1D RC pump using OMP 1-8 guidance. This UNSAT is acceptable (see examiner note at beginning of JPM)

(

COMMENTS:

STEP 2.1:

SAT 2.1.6 Ensure that its discharge valve fully opens. (Valve begins to open six seconds after pump start.)

STANDARD: Examinee notes that 1RC-24 reaches fully open. UNSAT EXAMINER NOTE: Candidate may verify 1 RC-24 reaches full open OMP 1-8 1RC-24 guidance. This is acceptable (see examiner note at beginning of JPM)

COMMENTS:

(

JPM09 H Page 8 of 12

Critical Step STEP 2.2:

\ .2 Stop the desired RC pump as follows: SAT 2.2.1 Dispatch an operator to the cooling tower area to monitor for cooling tower overflow periodically for the next hour.

UNSAT

_UNSAT STANDARD: Dispatched operator as stated.

EXAMINER CUE: This is Rob, I will monitor Unit 1 Cooling Tower levels.

EXAMINER NOTE: Candidate may secure 1B RC pump prior to starting 1D RC pump using OMP 1-8 guidance. This is acceptable (see examiner note at beginning of JPM),

however, the candidate MUST start a second RC pump (1D) (1 D) in order to support long term plant operation)

COMMENTS:

STEP 2.2: Critical Step 2.2.2 Close the discharge valve of the pump to be stopped:

( 0 1RC-22 (RC Pump 1B Disch Isol) o _SAT STANDARD: Depresses the CLOSE button for 1RC-22 and noted the Green CLOSED light illuminates.

_UNSAT EXAMINER NOTE: The valve may take 1 minute to close.

EXAMINER NOTE: The 1B RC Pump may trip before it can be manually secured.

COMMENTS:

JPM09 H Page 9 of 12

STEP 2.2:

- SAT

.2.3 Ensure that the pump stops when the valve closes.

STANDARD: Notes the 1B RC Pump GREEN "OFF" light is illuminated either because the valve has closed, or because it tripped off due to the - UNSAT malfunction.

COMMENTS:

Critical Step STEP 2.3:

- SAT If step 2.1.3.1 indicates a cooling tower inlet isolation valve was initially closed, close that cooling tower inlet isolation valve:

1501) 1RC-25 (Cool Twr 1A Inlet Isol) - UNSAT STANDARD: Notes the 1RC-25 was originally closed and recloses the valve ensuring the GREEN "CLSD" light illuminates when it closes.

OMMENTS:

JPM09 H Page 10 of 12

STEP 2.4:

Ensure the cooling towers are aligned properly for the number of pumps remaining in peration per the cooling tower configuration limits: SAT Riser Bypasses Riser Bypasses Open Tower Inlets RC Pumps Open Passing Flow Isolated Running 3 2 1 1 (Throttled) UNSAT 3 2 1 2 (Throttled) 2 o 2 1 (Throttled)

.1 '2' o o o 3 STANDARD: Notes configuration is proper. (see highlighted line)

COMMENTS:

This JPM is complete.

TIME STOP: _ __

JPM09 H Page 11 of 12

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 is operating at 50% power following repair of a condenser tube leak.

The turbine building rounds NLO reports severe vibration and noise coming from 1B RC pump and states that the motor is extremely hot to the touch.

The NLO has checked out 1C RC Pump and it is not rotating in the reverse direction.

The NLO is standing by to check 1C RC pump after it starts.

INITIATING CUES:

Start 1C RC Pump and secure 1B RC Pump per Enclosure 4.7 of OP/1 IB/64001001 A (Condenser Circulating Water). Initial Conditions are complete.

(

(,

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 is operating at 50% power following repair of a condenser tube leak.

The turbine building rounds NLO reports severe vibration and noise coming from 1B RC pump and states that the motor is extremely hot to the touch.

The NLO has checked out 1C RC Pump and it is not rotating in the reverse direction.

The NLO is standing by to check 1C RC pump after it starts.

INITIATING CUES:

Start 1C RC Pump and secure 1B RC Pump per Enclosure 4.7 of OP/1/B/64001001 A OP/1/B/64001001A (Condenser Circulating Water). Initial Conditions are complete.

Enclosure 4.7 OPil/B/6400/001 A OP!lIB/6400/001 Shifting of Operating RC Pumps Page 1 of3

1. Initial Conditions 6 1.1 Review the Limits and Precautions.

oa 1.2 Verify two or more RC pumps are running per Enclosure 4.2 (Placing Cooling Towers In Service).

2. Procedure NOTE: If it is desired to swap which RC pumps are in service while reducing or increasing the Ifit number of ofRCRC pumps and cooling towers in service, this enclosure is used first.

Enclosure 4.3 (Removing Cooling Towers From Service) is then used to remove RC pump(s) and cooling tower(s) from service OR Enclosure 4.2 (Placing Cooling Towers In Service) is then used to place RC pump(s) and cooling tower(s) in service.

2.1 "Start the desired RC Pump as follows:

2.1.1 Verify the RC pump to be started is NOT rotating in the reverse direction.

2.1.2 Ensure "RCP DISCH VALVE MODE SEL" in the "NORM" position.

NOTE: To start a third RC pump three cooling towers are required to be in service to meet the interlock. This is accomplished by temporarily opening the third tower inlet isolation, it will be reclosed by Step 2.3.

2.1.3 IF starting a third RC pump, perform the following:

2.1.3.1 Indicate below which cooling tower inlet isolation is closed:

o 1RC-25 (Cool Twr 1A Inlet Isol)

D Iso1) o 1RC-26 D lRC-26 (Cool Twr 1B Inlet Iso1) o 1RC-27 D lRC-27 (Cool Twr 1C Iso1)

IC Inlet Isol) 2.1.3.2 Ensure, all three cooling tower inlet isolation valves are open:

o 1RC-25 D lRC-25 (Cool Twr 1A IA Inlet Iso1)

Isol) o lRC-26 D IRC-26 (Cool Twr 1B IB Inlet Isol)

Iso1) o 1RC-27 (Cool Twr 1C D IC Inlet Isol)

Iso1)

Enclosure 4.7 OP/l/B/6400/001 A OP!l/B/64001001 A Shifting of Operating RC Pumps Page 2 of3 NOTE:

Wait approximately two minutes after starting an RC pump before stopping the desired RC pump to allow flow to stabilize.

Following each configuration change, sufficient time needs to be allowed for RC Cooling Tower Levels to stabilize prior to aligning additional components.

2.1.4 Start the desired RC pump 2.1.5 seconds Ensure that its discharge valve fully opens. (Valve begins to open six -seconds after pump start.)

2.2 Stop the desired RC pump as follows:

2.2.1 Dispatch an operator to the cooling tower area to monitor for cooling tower overflow periodically for the next hour.

2.2.2 Close the discharge valve of the pump to be-stopped:

be stopped:

o lRC-2l D lRC-21 (RC Pump lA Disch Isol) oD IRC-22 (RC Pump IB Disch Isol) lRC-22 oD lRC-23 (RC Pump 1lC C Disch Isol) o lRC-24 (RC Pump ID Disch Isol)

D 2.2.3 Ensure that the pump stops when the valve closes.

2.3 IF Step 2.1.3.1 indicates a cooling tower inlet isolation was initially closed, close that cooling tower inlet isolation.

o D IRC-25 (Cool Twr lA Inlet Isol) lRC-2S o

D lRC-26 (Cool Twr IB Inlet Isol) o D lRC-27 (Cool Twr 1lC C Inlet Isol) 2.4 Ensure the cooling towers are aligned properly for the number of pumps remaining in operation per the following cooling tower configuration limits:

Riser Bypasses Riser Bypasses Open Tower Inlets RCPumps Open Passing Flow Isolated Running 3 2 1 1 (Throttled) 3 2 1 2 (Throttled) 2 0 2 1 (Throttled) 1 0 1 2 0 0 0 3

Enclosure 4.7 OP/l/B/64001001 OP/l!B/64001001 A Shifting of Operating RC Pumps Page 3 of3 2.5 File this enclosure in the Control Copy folder of this procedure.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 I Transfer Control to the Standby Shutdown System CANDIDATE EXAMINER JPM091 Page 1 of 11

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Transfer Control to the Standby Shutdown System Alternate Path:

No Facility JPM #:

AD-001 KIA Rating(s):

APE068 AA 1.21 Ability to operate or monitor the following as they apply to the control room evacuation: Transfer of controls from the control room to shutdown panel or local control (3.9/4.1)

Task Standard:

Control is transferred to the Standby Shutdown System, solenoid isolation valve disconnects transferred, CAPT T&T valve power is transferred and Train A Neutron Monitoring System power is transferred.

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator _ __ IIn-Plant ---'X-'---_

n-P lant ----'X'-'--_ Perform _ __ X Simulate -"'-'---

_.!..:X'---_

References:

OP/0/B/61 OP/01B/61 00/013 (Standby Shutdown Facility Operation) Enclosure 4.2 revision 049 Validation Time: 10 min. Time Critical: No

=======================================================================

Candidate: Time Start: _ _ __

NAME Time Finish: _ _ __

Performance Rating: SAT ___ UNSAT _ __ Question Grade _ __ Performance Time _ __

Examiner: _ __ __ __ _ _ _ _ _ _ _ ____

Examiner: _~~~----- ___ ---------------~/_---

~~~~~~---~/_~~-

NAME SIGNATURE DATE

=======================================================================

COMMENTS JPM091 Page 2 of 11

SIMULATOR SETUP SHEET N/A SIMULATOR OPERATOR INSTRUCTIONS:

N/A Tools/Equipment/Procedures Needed:

OP/O/B/61 001013 (Standby Shutdown Facility Operation) Enclosure 4.2 revision 049 JPM091 Page 3 of 11

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

Unit 2 has just suffered a fire that results in evacuation of the control room.

INITIATING CUES:

Transfer control to the Standby Shutdown System per OP/0/B/61 001013 Enclosure 4.2 steps OP/O/B/61001013 2.1 through 2.4. All initial conditions have been satisfied.

JPM091 Page 4 of 11

START TIME: _ __

EXAMINER NOTE: Candidate should locate local copy of the procedure, and when he does, hand him a copy of OP/0/Al61 00/013 Enclosure 4.2.

STEP 2.1:

Transfer control to the Standby Shutdown System (SSS) as follows: SAT NOTE: These breakers are kirk-key interlocked to prevent both feeders from being closed at the same time.

_UNSAT UNSAT STANDARD: Acknowledges note.

COMMENTS:

STEP 2.1.1: CRITICAL STEP Open 2EMXS-F01A (Normal Incoming Breaker Fed From Motor Control Center 2EMXA) (AB-577, BB-65, Rm 486). _SATSAT STANDARD: Rotate 2EMXS-F01A switch to "OFF".

EXAMINER CUE: "2EMXS-F01A is OFF." _UNSAT UNSAT COMMENTS:

STEP 2.1.2 CRITICAL STEP Close 2EMXS-F03A (Alternate Incoming Bkr Fed From Motor Control Center SMXG) _SATSAT STANDARD: Rotate Kirk-Key in 2EMXS-F01A and remove.

Insert Kirk-Key in 2EMXS-F03A and rotate.

Rotate 2EMXS-F03A switch to "ON" _UNSAT UNSAT EXAMINER NOTE: Kirk Key must be obtained from 2EMXS-F01A to be inserted into 2EMXS-F03A.

EXAMINER CUE: "2EMXS-F03A is ON."

COMMENTS:

JPM091 Page 5 of 11

CRITICAL STEP STEP 2.1.3:

Close 2EMXS-F03E (Reactor Vessel Head Vent Motor (2NC253A) to restore power _SATSAT to 2NC-253A (Rx Head Vent).

STANDARD: Rotate 2EMXS-F03E switch to "ON".

_UNSAT EXAMINER CUE: "2EMXS-F03E is ON."

COMMENTS:

STEP 2.2:

SAT Ensure significant solenoid isolation valve are closed by transferring disconnects as follows:

CAUTION: The plugs shall be inserted squarely and the ring tightened to ensure UNSAT

_UNSAT proper connection of all pins.

STANDARD: Acknowledges Caution.

COMMENTS:

CRITICAL STEP STEP 2.2.1:

Remove Train A Plug 1 disconnect from the "PLUG 1: PLANT MODE" receptacle and SAT connect to the" PLUG 1: SSF MODE" receptacle located in terminal box 2TBOX0396 (Train A SSF Disconnect Enclosure) (AB-577, BB-69, Rm 486).

STANDARD: Rotate lock ring and remove Train "A" Plug 1 from "PLANT MODE" UNSAT

_UNSAT and place in "SSF MODE" receptacle and tighten lock ring EXAMINER CUE: "Train "A" Plug 1 is installed in "SSF Mode".

COMMENTS:

JPM091 Page 6 of 11

CRITICAL STEP STEP 2.2.2 Remove Train A Plug 2 disconnect from the" PLUG 2: PLANT MODE" r.eceptacle receptacle _SATSAT and connect to the" PLUG 2: SSF MODE" receptacle located in terminal box 2TBOX0396 (Train A SSF Disconnect Enclosure) (AB-577, BB-69, Rm 486).

STANDARD: Rotate locking ring and Remove Train "B" disconnect from "PLANT UNSAT

_UNSAT MODE" and place in "SSF MODE" receptacle and tighten lock ring.

EXAMINER CUE: "Train "A" Plug 2 is installed in "SSF Mode".

COMMENTS:

CRITICAL STEP STEP 2.2.3:

Remove Train B disconnect from the "PLANT OPERATION" receptacle and SAT connect to the "SSF OPERATION" receptacle located in 2TBOX0395 (Train B SSF Disconnect Enclosure) (inside small door "Unit 2 Auxiliary Building SSF Disconnect") (AB-577, BB-69, Rm 486).

UNSAT STANDARD: Rotate locking ring and Remove Train "B" disconnect from "PLANT OPERATION" and place in "SSF OPERATION" receptacle and tighten lock ring.

EXAMINER CUE: "Train "B" disconnect is installed in "SSF OPERATION."

COMMENTS:

NOTE: The power disconnect breaker for 2NC-252B (Rx Head Vent Block) is located in 2TBOX0395 (Train B SSF Disconnect Enclosure) (inside small door "Unit 2 _SATSAT Auxiliary Building SSF Disconnect") (AB-577, BB-69, Rm 486).

STANDARD: Acknowledges note.

UNSAT COMMENTS:

JPM091 Page 7 of 11

STEP 2.2.4

_SATSAT Ensure the 600V power disconnect breaker (SSF Pwr Disconnect For 2NC-252B) for 2NC-252B (Rx Head Vent Block) is in the "OFF" position.

STANDARD: Ensures 2NC-252B disconnect BKR in "OFF" position. _UNSAT EXAMINER CUE: "2NC-2S2 "2NC-252 disconnect BKR is in the OFF position" COMMENTS:

STEP 2.3

_SATSAT Transfer power for CAPT Trip and Throttle valve as follows:

NOTE: These breakers are Kirk-Key interlocked to prevent both feeders from being closed at the same time. (on 2ELCP0250 (125 VDC CAPT Trip And Throttle Valve _UNSAT Power Transfer Panel>>

Panel))

STANDARD: Acknowledges note.

COMMENTS:

CRITICAL STEP STEP 2.3.1:

Open 2ELCP0250-F01 B (Incoming Line From 2EDE 125 VDC 1E) (AB-577, _SATSAT BB-64, Rm 486).

STANDARD: Rotate 2ELCP0250-F01 B, switch to :"OFF".

UNSAT

_UNSAT "2ELCP02S0-F01 B is OFF" EXAMINER CUE: "2ELCP0250*F01 COMMENTS:

JPM091 Page 8 of 11

CRITICAL STEP STEP 2.3.2

- SAT Close 2ELCP0250-F01 C (Incoming Line From SDSP2 125 VDC NE).

STANDARD: Rotate Kirk-Key in 2ELCP0250-F018 2ELCP0250-F01 B and remove.

Insert Kirk-Key in 2ELCP0250-F01 C and rotate. - UNSAT 2ELCP0250*F01 C switch to "ON" Rotate 2ELCP0250-F01 EXAMINER NOTE: Kirk Key must be obtained from 2ELCP0250-F01 B 8 to be inserted into 2ELCP0250-F01 C.

EXAMINER CUE: "2ELCP0250-F01C switch to "ON""

COMMENTS:

CRITICAL STEP STEP 2.4 Transfer power to Train A Neutron Monitoring System as follows: (2TBOX0603, (2T80X0603, A8-577, BB-62, AB-577, 88-62, Rm 486) - SAT 2.4.1 Disconnect the power plug from the "NORMAL IE OPERATION" receptacle.

STANDARD: Rotate lock ring and remove plug from "NORMAL IE OPERATION" - UNSAT EXAMINER CUE: "Power Plug is disconnected."

COMMENTS:

JPM091 Page 9 of 11

CRITICAL STEP STEP 2.4.2 CAUTION: The plug shall be inserted squarely and the ring tightened to ensure proper connection of all pins. - SAT Connect the power plug to the "SSF NE OPERATION" receptacle.

ST ANDARD: Acknowledges caution and Installs power plug in "SSF NE STANDARD: - UNSAT OPERATION" receptacle and tighten lock ring.

EXAMINER CUE: "Power Plug is connected."

COMMENTS:

This JPM is complete.

TIME STOP: _ __

JPM091 Page 10 of 11

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 2 has just suffered a fire that results in evacuation of the control room.

INITIATING CUES:

Transfer control to the Standby Shutdown System per OP/O/Bf6100/013 OP/O/B161 001013 Enclosure 4.2 steps 2.1 through 2.4. All initial conditions have been satisfied.

Enclosure 4.2 OP/O/B/61 001013 OP/01B161001013 Maintaining Unit 2 in Hot Standby Following Page 1 of 11 a Fire Event

1. Initial Conditions

~ 1.1 Review the Limits and Precautions.

6 1.2 Preferred controls necessary to maintain Hot Standby (Control Room and Auxiliary Shutdown Panels) are unresponsive or NOT accessible due to fire.

AP121Al550010 17 (Loss of Control Room).

The following actions have been completed by AP/2/A!55001017

~ Reactor tripped

~Turbine tripped r::(

~ll NC pumps tripped g/CFPTs tripped

2. Procedure NOTE: 1. NC System will NOT be able to be cooled down below approximately 567°F, because the lowest steam line safety valve is set at 1175 psig.

2. Steps 2.1 through 2.5 maybe AP/21A/5 5 0010 17 (Loss of Control may be in progress per AP/21A155001017 Room), Enclosure 8 (Transfer Control to SSF) and AP/1/A/5)001017 AP/lIAl55001017 (Loss of Control Room), Enclosure 10 (SSF DIG Startup).

3. Steps 2.1 through 2.4 may be performed concurrently with Steps 2.5 2.) through 2.8.

4. For a list of valves affected by the transfer, see Enclosure 4.6 (Equipment Affected on Transfer).

2.1 Transfer control to the Standby Shutdown System (SSS) as follows:

NOTE: These breakers are kirk-key interlocked to prevent both feeders from being closed at the same time.

oD 2.1.1 Open 2EMXS-FOIA (Normal Incoming Breaker Fed From Motor Control Center 2EMXA) (AB-577, BB-65, Rm 486).

oD 2.1.2 Close 2EMXS-F03A (Alternate Incoming Bkr Fed From Motor Control Center SMXG).

oD 2.1.3 Close 2EMXS-F03E (Reactor Vessel Head Vent Motor (2NC253A)) to restore power to 2NC-253A (Rx Head Vent).

Enclosure 4.2 OP/O/B/61001013 OP/O/BI6100/013 Maintaining Unit 2 in Hot Standby Following Page 2 of 11 a Fire Event 2.2 Ensure significant solenoid isolation valves are closed as follows:

CAUTION: The plugs shall be inserted squarely and the ring tightened to ensure proper connection of all pins.

D 2.2.1 Remove Train A Plug 1 disconnect from the "PLUG 1: I: PLANT MODE" receptacle and connect to the" PLUG 1: I: SSF MODE" receptacle located in terminal box 2TBOX0396 (Train A SSF Disconnect Enclosure) (AB-577, BB-69, Rm 486).

D 2.2.2 Remove Train A Plug 2 disconnect from the" PLUG 2: PLANT MODE" receptacle and connect to the" PLUG 2: SSF MODE" receptacle located in terminal box 2TBOX0396 (Train A SSF 'SSF Disconnect Enclosure) (AB-577, BB-69, RID Rm 486).

D 2.2.3 Remove Train B disconnect from the "PLANT OPERATION" receptacle and connect to the "SSF OPERATION" receptacle located in 2TBOX0395 (Train B SSF Disconnect Enclosure) (inside small door "Unit 2 Auxiliary Building SSF Disconnect") (AB-577, BB-69, Rm 486).

NOTE: The power disconnect breaker for 2NC-252B (Rx Head Vent Block) is located in 2TBOX0395 (Train B SSF Disconnect Enclosure) (inside small door "Unit 2 Auxiliary Building SSF Disconnect") (AB-577, BB-69, Rm 486).

D 2.2.4 Ensure the 600V power disconnect breaker (SSF Pwr Disconnect For 2NC-252B) for 2NC-252B (Rx Head Vent Block) is in the "OFF" position.

2.3 Transfer power for CAPT Trip and Throttle valve as follows:

NOTE: These breakers are Kirk-Key interlocked to prevent both feeders from being closed at the same time. (on 2ELCP0250 (125 VDC CAPT Trip And Throttle Valve Power Transfer Panel))

D 2.3.1 Open 2ELCP0250-FOIB (Incoming Line From 2EDE 125 VDC IE) (AB-577, (AB-'S77, BB-64, Rm 486).

D 2.3.2 2ELCP0250-FOIC (Incoming Line From SDSP2 125 VDC NE).

Close 2ELCP02SO-FOIC

Enclosure 4.2 OP/O/B/61001013 OP/O/B/61 0010 13 Maintaining Unit 2 in Hot Standby Following Page 3 of 11 a Fire Event 2.4 Transfer power to Train A Neutron Monitoring System as follows: (2TBOX0603, AB-577, BB-62, Rrn Rm 486) o 2.4.1 D OPERAnON" receptacle.

Disconnect the power plug from the "NORMAL IE OPERATION" CAUTION: The plug shall be inserted squarely and the ring tightened to ensure proper connection of all pins.

o 2.4.2 D Connect the power plug to the SSF NE OPERA nON" receptacle.

OPERATION" 2.5 IF at any time power is lost to ISLXG as indicated by "LINE VOLTS" voltmeter (located on SSF Control Console panel), place SSF diesel in operation as follows:

CAUTION: The emergency mode overrides the SSF Diesel Generator "High Jacket Water Temperature" and "Low Lube Oil Pressure" trips.

o 2.5.1 D Ensure the "SSF DIG MODE" switch is in the "EMERG" position on the SSF console.

o 2.5.2 D Place the "SSF DIG" switch in the "ON" position.

o 2.5.3 D IF the engine does NOT start within 30 seconds, perform the following:

Do 2.5.3.1 Place the "SSF DIG" switch in the "OFF" position.

oD 2.5.3.2 IF DIG turned over but did NOT fire during the DIG start attempt, tum the manual override knob on the shutdown valve (shown in Enclosure 4.7, Top View of Fuel Oil Pump) clockwise to permit fuel flow through the valve.

oD 2.5.3.3 After 1 to 2 minutes has passed, return to Step 2.5.2 to attempt to re-start the DIG.

o 2.5.4 D Adjust "SSF DIG VOLT ADJUST" until generator voltage is 600 volts.

o 2.5.5 D Adjust the "SSF DIG GOV CTRL" to bring frequency to 60 +/- 1.2 Hz.

o 2.5.6 D "1 SLXG NORM FDR FRM ITA" on the SSF Press the "TRIP" pushbutton on "ISLXG console.

Enclosure 4.2 OPiO/B/61 0010 13 OPiO/B/61001013 Maintaining Unit 2 in Hot Standby Following Page 4 of 11 a Fire Event 2.S.7 2.5.7 Open the following breakers:

o 1SLXG-4C (Motor Control Center SMXG Supply) o lSLXG-4D ISLXG-4D (SSF Nonnal Battery ChargerSDSCI ChargerSDSCl Feeder) o lSLXG-SC ISLXG-5C (SSF Nonnal Battery Charger SDSC2 Feeder) o lSLXG-SD ISLXG-5D (SSF Standby Battery Charger SDSCS Feeder) o 2.S.8 2.5.8 Press the "CLOSE" pushbutton for the "SSF DIG BKR" on the SSF Control Console panel.

o 2.S.9 2.5.9 After allowing the diesel generator to run for 10 seconds, close 1SLXG-4C lSLXG-4C (Motor Control Center SMXG Supply).

2.5.10 Close the following breakers at 10 second intervals:

o lSLXG-4D (SSF Nonnal Battery Charger SDSC1 Feeder) 1SLXG-4D o lSLXG-SC ISLXG-SC (SSF Nonnal Battery Charger SDSC2 Feeder) o 1 lSLXG-SD SLXG-SD (SSF Standby Battery Charger SDSCS Feeder) o 2.5.11 WHEN another operator arrives, have the operator refer to OP/O/B/63501011 OP/OIB/635010 11 (Standby Shutdown Facility Diesel Operations), Enclosure 4.5 (Emergency Operation) for continued operation of the SSF diesel.

2.6 Verify "UNIT 2 SSF CONTROLS ENGAGED" light is lit.

NOTE: Valves 2ND-2A (ND Pump 2A Suct Fnn Loop B) and 2ND-37A 2ND-37A (ND Pump 2B Suct Fnn Loop C) are nonnally closed with their breakers in the "OFF" position. If no indication is seen at the SSF, the 2A and 2B ND Pump Suction Pressure gauges can be used to detennine ND suction source. IfND suction pressure is < NC pressure, the associated ND train loop suction isolation is closed.

2NDPGS100 2NDPG5100 (2A ND Pump Suction Pressure) (AB-522, FF-60, Rm 112)

2NDPG5110 (2B ND Pump Suction Pressure) (AB-S23, 2NDPGS11O (AB-523, GG-61, Rm 112) 2.7 Ensure the following valves are closed:

o 2ND-2A (ND Pump 2A Suct Fnn Loop B) o 2ND-37A 2ND-3 7A (ND Pump 2B Suct Fnn Loop C) o 2NV-89A (NC Pmps Seal Ret Cont Isol) o 2NV-876 (Stdby MlU To Cont Equip Smp 2A)

Enclosure 4.2 OP/O/B/61001013 Maintaining Unit 2 in Hot Standby Following Page 5 of 11 II a Fire Event 2.8 Ensure the following valves are open:

o M/U Pmp Suet Frm Xfr Tube)

-865A (Stdby MIU 2NV-865A 2NV o 2NV-872A (Stdby MIU Pmp Filt Otlt) o 2NY-877 (Stdby MlU To NC Pmp Seal Inj) 2.9 Start Standby Makeup Pump #2. (Stdby MIU Pump #2)

NOTE:

The Standby Makeup Pump Filter DIP gauge (2NVPG6160) shall be monitored periodically to ensure it reads on scale between 0-25 psid. (This gauge is located in the S59 ft., 153°).

annulus at Elev. 559

Operator dispatched to transfer control to the SSF in AP121A/550010 17 (Loss of Control Room), Enclosure 8 (Transfer Control to SSF) has guidance on how to perform perfonn Step 2.10.

The procedure may be continued while Step 2.10 is in progress.

2.10 Pull all control power fuses and manually "TRIP" the following 4160V breakers:

o 2ETA-12 (2A NV Pump Motor) o 2ETA-13 (2A CA Pump Motor) o 2ETB-12 (2B NY Pump Motor) o 2ETB-13 (2B CA Pump Motor) 2.11 In the compartment (Inc ore Thermocouple Transfer (NC)) on the left hand side of the SSF Control Console panel, transfer the incore thermocouples indication to the SSF Control Console panel by disconnecting the cable from the "ICS INCORE THERMOCOUPLE" INCORE receptacle and connecting the cable to the SSF INC ORE THERMOCOUPLE" receptacle.

2.12 Verify transfer to SSF control is complete by the following indicating lights being lit:

o "UNIT 2 SSF CONTROLS ENGAGED" o "UNIT 2 SSF DISCONNECT ENGAGED"

Enclosure 4.2 OP/O/B/6 10010 13 OP/O/B/61001013 Maintaining Unit 2 in Hot Standby Following Page 6 of 11 a Fire Event CAUTION: The PZR heaters in Group D controlled from the SSF will NOT de-energize on Low PZR level. Operator action will be required to prevent the loss of the heaters ifPZR level goes below 17%.

2.13 Select "LOCAL" on "PZR HTR GRP 2D MODE".

2.14 IF W/R level in two S/Gs is less than 45%, depress "ON" for 2SA-5 (S/G 2C To CAPT).

2.15 Ensure "CAPT #2 RM SUMP PMP 2A" in "AUTO".

NOTE: 1. Control switches and indicating lights for 2WL-847 and 2WL-848 are located on the Auxiliary Waste Processing Control Panel (lELCC0013) (AB-543, MM-53, Rm 200).

2. 2WL-847 will fail open and 2WL-848 will fail closed on loss ofVl of VI air pressure.

2.15.1 As time pennits permits (within 2 hrs), ensure one of the following valves is open:

o 2WL-847 (Floor Drain Sump C Disch To ND IINS D NS Sump) (AB-5S5, (AB-555, BB-62, Rm260) o 2WL-848 (Floor Drain Sump C Disch To Turbine Building Sump) (AB-551, D (AB-55l, CC-62, Rm 260) 2.16 Ensure SSF SUMP PUMP" in "AUTO".

2.17 Maintain PZR level greater than 25% and less than 92% (2NCP5154):

2.17.1 To lower PZR level, open the following valves and close them WHEN the level is reached:

o 2NC-2S0A D 2NC-250A (Rx Head Vent Block) o 2NC-2S3A D 2NC-253A (Rx Head Vent) 2.17.2 IF PZR level continues to decrease, dispatch operator to ensure 2NV-lOIA 2NV-l01A (NC Pumps #1# 1 Seal Bypass) is closed by failing air locally to the valve (CV-S57, (CV-SS7, 56'-181°).

Enclosure 4.2 OP/O/B/6100/013 OP/O/B/61001013 Maintaining Unit 2 in Hot Standby Following Page 7 of 11 a Fire Event CAUTION: The PZR heaters in Group D controlled from the SSF will NOT de-energize on Low PZR level. Operator action will be required to prevent the loss of the heaters ifPZR level goes below 17%.

2.18 Maintain NC System pressure (2NCP5121 (Unit 2 Loop B Press)) by manual control of "PZR HTR GROUP 2D" on SSF Control Console panel.

2.19 IF NC System pressure continues to increase uncontrollably with "PZR HTR GROUP 2D" off, dispatch operator to open the following breakers:

2LXI-6C (2A NC Pzr Heater Power Panel (PHP2A) Feeder)

2LXH-6C (2B NC Pzr Heater Power Panel (PHP2B) Feeder)

2LXC-5C (2C Reactor Coolant Pressurizer Heater Power Panel (PHP2C))

2LXD-5C (2D Reactor Coolant Pressurizer Heater Power Panel (PHP2D))

Enclosure 4.2 OP/O/B/6100/013 Maintaining Unit 2 in Hot Standby Following Page 8 of 11 a Fire Event NOTE: If suction supply sources to the CAPT #2 are lost, 2CA-174 (RC To CA Suct Isol) and 2CA-175 (RC To CA Suct Isol) will open and align the pump to the embedded RC pipe provided 2CA-178 (RC Supply To CA Pumps Isol) is open.

2.20 Maintain S/G levels between 65% and 70% WR (as read on SSF gauges) by controlling CA using one or more of the four (4) following methods, as conditions warrant:

NOTE: If either of the below conditions exist, depressing "OFF" on the switch for 2SA-5 (S/G 2C SM To CAPT) on the SSF Control Console panel will NOT secure steam to CAPT #2:

An auto start signal has failed open 2SA-2 (S/G 2B SM To CAPT) providing an alternate steam supply from S/G 2B,

Any two S/Gs reach their Lo-Lo level setpoint (less than 45% WR Indicated) failing open 2SA-5 (S/G 2C SM To CAPT).

Start and stop CAPT #2 by pressing "ON" or "OFF" on the switch for 2SA-5 (S/G 2C SM To CAPT) on the SSF Control Console panel.

Manually throttle CA flow to each S/G with one valve from each pair of the following valves:

D 2CA-48 (CA Pump #2 Flow To S/G 2C) (AB-552, DD-61, Rm 227) OR D 2CA-50A (CA Pmp 2 Disch To S/G 2C Isol) (DH-585, (DR-585, DD-61, Rm 562)

D 2CA-52 (CA Pump #2 Flow To S/G 2B) (AB-550, DD-62, Rm 227) OR D 2CA-54B (CA Pmp 2 Disch To S/G 2B Isol) (DR-585, (DH-585, DD-61, Rm 562)

D 2CA-36 (CA Pump #2 Flow To S/G 2D) (AB-554, BB-65, Rm 260) OR D 2CA-38A (CA Pmp 2 Disch To S/G 2D Isol) (DR-585, (DH-585, DD-70, Rm 581)

D 2CA-64 (CA Pump #2 Flow To S/G 2A) (AB-557, BB-64, Rm 260) OR D 2CA-66B (CA Pmp 2 Disch To S/G 2A Isol) (DH-585, (DR-585, DD-69, Rm 581)

Manually throttle steam flow to CAPT #2 by removing breakaway locks and throttling the following valves:

2SA-6 (2C S/G Main Steam to Unit 2 CAPT Stop Check) (AB-553, DD-61, Rm 227)

2SA-3 (2B S/G Main Steam to Unit 2 CAPT Stop Check) (AB-553, DD-60, Rm 227)

NOTE: The use of the CAPT Trip and Throttle valve shall only be as a last resort. If it is used to start the pump, there is a possibility that the CAPT will overspeed.

Start and stop the CAPT #2 by pressing "OPEN" or "CLS/TRIP" on the switch "CAPT 2 TRIP TN CTRL" on the SSF Control Console panel.

Enclosure 4.2 OP/O/B/6100/013 Maintaining Unit 2 in Hot Standby Following Page 9 of 11 a Fire Event 2.21 IF S/G levels continue to decrease, ensure an available CA flowpath to S/Gs as follows:

2.21.1 Ensure the following valves are open by locally failing air to the valves:

2CA-48 (CA Pump #2 Flow To S/G 2C) (AB-552, DD-61, Rm 227)

(AB-550, DD-62, Rm 227) 2CA-52 (CA Pump #2 Flow To S/G 2B) (AB-S50,

2CA-36 (CA Pump #2 Flow To S/G 2D) (AB-554, BB-65, Rm 260)

2CA-64 (CA Pump #2 Flow To S/G 2A) (AB-557, BB-64, Rm 260) 2.21.2 Ensure the following valves are open by locally opening the valves:

(DH-585, DD-61, Rm 562) 2CA-50A (CA Pmp 2 Disch To S/G 2C Isol) (DR-585,

2CA-S4B (DH-585, DD-61, Rm 562) 2CA-54B (CA Pmp 2 Disch To S/G 2B Isol) (DR-585,

2CA-38A (CA Pmp 2 Disch To S/G 2D 1'801) (DH-585, DD-70, Rm 581)

Isol) (DR-585,

(DH-585, DD-69, Rm 581) 2CA-66B (CA Pmp 2 Disch To S/G 2A Isol) (DR-585, 2.22 IF accessible, close the following valves to prevent the possible exposure of personnel in the Auxiliary Building:

2WL-869B (Unit 2 Vent Unit Condensate Drain Tank Containment Isol)

(AB-553, CC-62, Rm 260)

2WL-827B (Cont Smp Pmps Disch Cont Isol) (AB-554,(AB-S54, JJ-63, Rm 227) 2.23 Ensure natural circulation exists as follows:

NOTE: Indication for the five core exit thermocouples is provided on Chart Recorder 2ENCR9005.

2ENCR900S.

These thermocouple temperature signals are automatically compensated for any changes in reference junction temperature. {CNCE 61598}

2.23.1 Record the highest core temperature from 2ENCR9005.

OF 2.23.2 Record UNIT 2 LOOP B PRESS.

_ _ _ _ _ pSlg 2.23.3 Verify NC System is subcooled by comparing Actual Core Temp and Loop B Press from previous steps with Unit 2 Revised Data Book Figure 57.

Enclosure 4.2 OP/OIB161 0010 13 OP/O/B/6100/013 Maintaining Unit 2 in Hot Standby Following Page 10 of 11 a Fire Event 2.23.4 IF subcooling margin is being lost due to a decreasing NC System pressure, perform the following:

D 2.23.4.1 Ensure PZR heaters are "ON".

NOTE: Valves 2ND-2A (ND Pump 2A 2A'Suct Suct Frm Loop B) and 2ND-37A (ND Pump 2B Suct Frm Loop C) are normally closed with their breakers in the "OFF" position. If no indication is seen at the SSF, the 2A and 2B ND Pump Suction Pressure gauges can be used to determine ND suction source. IfND suction pressure is < NC pressure, the associated ND train loop suction isolation is closed.

2NDPG5100 (2A ND Pump Suction Pressure) (AB-522, FF-60, Rm 112)

2NDPG5110 (2B ND Pump Suction Pressure) (AB-523, GG-61, Rm 112)

D 2.23.4.2 Ensure the following valves are closed:

D 2ND-2A (ND Pump 2A Suct Frm Loop B) 2ND-37A (ND Pump 2B Suct Frm Loop C)

D 2ND-37A D 2NV-89A (NC Pmps Seal Ret Cont Isol) Iso1)

D 2NC-250A (Rx Head Vent Block) o 2NC-253A 2NC-2S3A (Rx Head Vent) 2.23.5 IF sub cooling margin is being lost due to an increasing NC temperature, attempt subcoo1ing to establish better heat sink conditions by increasing secondary side inventory as described in Step 2.20.

NOTE:

S/G pressure is controlled by S/G safeties while operating at the SSF. The lowest S/G Safety setpoint is 1175 psig. If actual S/G pressure is NOT known, use 1175 psig in the following step.

Revised Data Book Figure 57 can be used to determine saturation temperature of steam even-though the X axis is labeled NC System Temperature and the Y axis is labeled NC System pressure.

2.23.6 Verify UNIT 2 C-LEG TEMP for LOOP 2B and LOOP 2C at or near saturation temperature for S/G pressure using Unit 2 Revised Data Book Figure 57.

Enclosure 4.2 OP/O/B/61 001013 0010 13 Maintaining Unit 2 in Hot Standby Following Page 11 of 11 a Fire Event CAUTION: Use borated water only to makeup to the spent fuel pool.

NOTE: It takes approximately 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months for the Standby Makeup pump to pump the Fuel Pool down 1 foot.

2.24 Periodically (about every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ) check the spent fuel pool level and makeup to it as necessary to maintain level between approximately 2 ft. below and equal to the skimmer trough elevation. Makeup per OP/2/A/62001005 (Spent Fuel Cooling System).

2.25 Perform OP/2/A/61001020 (Operational Guidelines For Achieving Cold Shutdown Following a Fire in the Plant) in conjunction with one of the following for guidance on accessing systems as required:

OP/2/A/61001002 (Controlling Procedure for Unit Shutdown)

OR

OP/2/A/61001004 (Shutdown Outside the Control Room From Hot Standby To Cold Shutdown)

NOTE: This enclosure shall be kept at the Unit Control Center until normal shutdown conditions are achieved.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 J Locally Operate Steam Generator PORVs During a SGTR CANDIDATE EXAMINER JPM09 J Page 1 of 10

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Locally Operate Steam Generator PORVs During a SGTR Alternate Path:

No Facility JPM #:

EP4-009 KIA Rating(s):

EPE038 EA 1.41 Venting of the S/G to the atmosphere (3.4/3.4)

Task Standard:

Steam Generator PORV 2SV-1 is manually engaged for local operation and the operator has demonstrated rotation of the handwheel in the proper direction to open the valve within 18 minutes Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator -_- _-_ In-Plant ----'X-'---_

---,X--,--_ Perform _ __ Simulate _,,-,X,--_

_.!...:X'---_

References:

EP/21A15000/E-3 (Steam Genratior Tube Rupture) Enclosure 3 revision 032 EP/21N5000/E-3 Validation Time: 10 min. Time Critical: Yes 12 minutes

=======================================================================

Candidate: Time Start: -

NAME Time Finish: _ _ __

Performance Rating: SAT ___ UNSAT _ __ Question Grade - _- _-_ Performance Time - _- _-_

Examiner: _ _ _ _--:-:--:-:-=-_

NAME

__ ____ ___ ------~~~~~

~- _____

SIGNATURE

____ ~/ __

~/_~~ -

DATE

=======================================================================

COMMENTS JPM09 J Page 2 of 10

SIMULATOR SETUP SHEET N/A SIMULATOR OPERATOR INSTRUCTIONS:

N/A Tools/Equipment/Procedures Needed:

EP/21A15000/E-3 (Steam Generator Tube Rupture) Enclosure 3 revision 032 EP/2/A/5000/E-3 JPM09 J Page 3 of 10

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

A SGTR has occurred coincident with a loss of offsite power and 2ERPO. 2ERPD. The CRS has EP/21A15000/E-3 (Steam Generator Tube Rupture). Step 19 is currently in effect implemented EP/2/A/5000/E-3 to cooldown the NCS.

INITIATING CUES:

The CRS directs you to fully open 2SV-1 (S/G 2D 20 PORV) locally per EP/21A15000/E-3 EP/2/A/5000/E-3 Enclosure 3 (Local Operation of S/G PORVs).

This JPM is time critical.

JPM09 J Page 4 of 10

START TIME: _ __

EXAMINER NOTE:

In the analysis for this event, it has been determined that a maximum of 18 minutes is allowed from the time the NLO is given the procedure in the control room, to the time the valve is fully open. Since 10 minutes were allotted to get to the valve, and 2 minutes are allotted to expose the shaft for manual engagement, the trainee must have 6 minutes left to fully open the valve once the clevis is engaged, and he has demonstrated the proper direction to turn the handwheel to open the valve.

Critical Time starts when the student states he/she is ready to proceed.

TIME CRITICAL START TIME:

STEP 1:

NOTE Emergency flashlights and Merlin-Gerins are available in the control room. - SAT Obtain the following:

o Flashlight o Merlin-Gerin. - UNSAT STANDARD: Obtains flashlight.

EXAMINER CUE: "Flashlight and Merlin-Gerin obtained."

EXAMINER NOTE: This is for outside Doghouse, Merlin Gerin not required.

Emergency Flashlights and Merlin-Gerins are located in the Control Room (SSA desk)

COMMENTS:

JPM09 J Page 5 of 10

STEP 2:

2. Establish communications with the control room as follows: SAT

a. Obtain sound powered phones from storage on 627' elevation.

- Outside doghouse (DH-627, FF-70, Rm 581)

b. Establish communications from the nearest phone jack at the selected PORV( s):

S/G PORV(s): UNSAT

- Outside doghouse (DH-627, FF-70, Rm 581)

STANDARD: Eastablishes CR communications by locating a sound powered phone and phone jack ..

EXAMINER CUE: "Communication has been established with the Control Room."

COMMENTS:

Caution: Severe damage to the actuator assembly can result if operated with the clevis engaged to the actuator shaft and the equalizing valve closed.

SAT Note: 2SV-13 turns counterclockwise to open. 2SV-1, 2SV-7 and 2SV-19 turn clockwise to open.

STANDARD: acknowledges note and caution. UNSAT COMMENTS:

STEP 3a:

SAT Place S/G PORV(s)

PORV( s) in local operation as follows:

a. Select desired PORV(

PORV(s):s):

D 2SV-1 (S/G 202D PORV Manual Ctrl) (DH-635, FF-GG, 69-70, Rm 581) 581 )..

UNSAT STANDARD: 2SV-1 selected based on initial conditions.

COMMENTS:

JPM09 J Page 6 of 10

CRITICAL STEP STEP 3.b:

SAT Unscrew clevis from manual override shaft.

STANDARD: Examinee describes unscrewing clevis from manual override shaft.

_UNSAT EXAMINER CUE: "Clevis has been removed."

COMMENTS:

CRITICAL STEP STEP 3.c:

Turn handwheel in the "close" direction to expose actuator shaft below manual SAT override shaft.

STANDARD: Examinee describes turning the handwheel COUNTERCLOCKWISE to expose actuator shaft below manual override shaft. UNSAT EXAMINER CUE: "Actuator shaft has been exposed."

COMMENTS:

CRITICAL STEP STEP 3.d Open equalizing valve on side of PORV actuator. SAT STANDARD: Examinee locates and describes attaching valve handle to the equalizing valve (on the side of the PORV actuator) and opens the equalizing valve. UNSAT EXAMINER CUE: "Equalizing valve is open."

COMMENTS:

JPM09 J Page 7 of 10

CRITICAL STEP STEP 3.e:

Slide clevis onto actuator shaft. SAT STANDARD: Examinee describes sliding the clevis onto the exposed actuator shaft.

_UNSAT EXAMINER CUE: "Clevis is secure on the shaft."

COMMENTS:

CRITICAL STEP STEP 3.f Turn handwheel to position valve as desired. SAT STANDARD: Examinee describes turning handwheel in the CLOCKWISE direction to fully open the valve.

UNSAT EXAMINER CUE: "Open 2SV-1 to the full open position."

EXAMINER NOTE: The time critical activity ends at this point. Actual time critical activity is 18 minutes but 12 minutes is allotted for this point assuming 6 minutes to fully open the valve.

TIME CRITICAL END TIME: _ _ __

COMMENTS:

JPM09 J Page 8 of 10

STEP 4

- SAT WHEN directed by the control room, THEN restore S/G PORV(s) to control room control as follows: ...

STANDARD: Waits for Control Room direction. - UNSAT EXAMINER CUE: "Another operator will return PORV to control room control."

controL" COMMENTS:

This JPM is complete.

TIME STOP: _ __

JPM09 J Page 9 of 10

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A SGTR has occurred coincident with a loss of offsite power and 2ERPO. The CRS has implemented EP/2/A/5000/E-3 (Steam Generator Tube Rupture). Step 19 is currently in effect to cooldown the NCS.

INITIATING CUES:

The CRS directs you to fully open 2SV-1 (S/G 20 PORV) locally per EP/2/A/5000/E-3 Enclosure 3 (Local Operation of S/G PORVs).

This JPM is time critical.

CNS STEAM GENERATOR TUBE RUPTURE PAGE NO.

EP/21A15000/E-3 EP/2/A/5000/E-3 65 of 110 Enclosure 3 - Page 1 of 2 Revision 32 Local Operation of S/G PORVs Emergency flashlights and Merlin-Gerins are available in the control room.

1. Obtain the following:

_ **** Flashlight

- - - Merlin-Gerin.

The following are preferred routes to the doghouses:

- Outside doghouse (2A and 20 Unit 2 turbine 2D S/G) - Through northeast door of Unit,2 building

Inside doghouse (2B and 2C S/G) - Through northeast control room exit to the auxiliary building.

2. Establish communications with the control room as follows:

a. Obtain sound powered phones from storage on 627' elevation.

_ ** Outside doghouse (OH-627, (DH-627, FF-70, Rm 581)

_ * **Inside (DH..:627, FF-61 Inside doghouse (OH-'627, FF-61,, Rm 562).

b. Establish communications from the nearest phone jack at the selected S/G PORV(s):

_ ** Outside doghouse (OH-627, (DH-627, FF-70, Rm 581)

_ ** Inside doghouse (OH-627, (DH-627, FF-61 FF-61,, Rm 562).

CNS STEAM GENERATOR TUBE RUPTURE PAGE NO.

EP/2/N5000/E-3 EP/21N5000/E-3 66 of 110 Enclosure 3 - Page 2 of 2 Revision 32 Local Operation of S/G PORVs CAUTION Severe damage to the actuator assembly can result if operated with the clevis engaged to the actuator shaft and the equalizing valve closed.

NOTE 2SV-13 turns counter clockwise to open. 2SV-1, 2SV-7 and 2SV-19 turn clockwise to open.

3. Place S/G PORV(s) in local operation as follows:

a. Select desired PORV(s):

_ 0 o2SV-19 (S/G 2A PORV Manual Control) (DH-635, (OH-635, FF-GG, 70-71, Rm 581)

_ 0 o2SV-13 (S/G 2B PORV Manual Control) (DH-635, FF~GG, 60-61, Rm 562)

(OH-635, FF;.GG,

_ 0 o2SV-7 (S/G 2C PORV Manual Control) (OH-635, (DH-635, FF-GG, 61-62, Rm 5'62) 5'(2)

_ 0* o2SV-1 (S/G 20 2D PORV Manual Control) (DH-635, (OH-635, FF-GG, 69-70, Rm 581).

b. Unscrew clevis from manual override shaft.

c. Turn handwheel in the "close" direction to expose actuator shaft below manual override shaft.

d. Open equalizing valve on side of PORV actuator.

e. Slide clevis onto actuator shaft.

f. Turn handwheel to position valve as desired.

4. WHEN directed by the control room, THEN restore S/G PORV(s) to control room control as follows:

a. Notify the control room to transmit a closed actuating signal from MCB to the valve positioner.

b. Turn handwheel until the PORV is in the "closed" position and pressure is relieved from the clevis and actuator shaft.

c. Remove clevis from actuator shaft.

d. Turn handwheel until manual override shaft is fully extended.

e. Screw clevis onto manual override shaft.

f. Close equalizing valve on side of PORV actuator.

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM09 K Locally Trip the Reactor CANDIDATE EXAMINER JPM09 K Page 1 of 7

CATAWBA NUCLEAR STATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Locally Trip the Reactor Alternate Path:

No Facility JPM #:

IPX-016 Rating(s}:

KIA Rating(s):

EPE029 EA1.12 ATWS - MIG set power supply and reactor trip breakers (4.1/4.0)

Task Standard:

At least one Motor or Generator breaker on each train is open isolating all power to the control rod drive system.

Preferred Evaluation Simulator: Preferred Evaluation Perform Simulator _ __ In-Plant ----!X~_

In-Plant ---"X-'--_ Perform _ __ Simulate _~X,--_

_-'-'X'--_

References:

EP/1/A15000/FR-S.1 EP/1/N5000/FR-S.1 (Response to Nuclear Power GenerationlATWS)

Generation/ATWS)

Validation Time: 8 min. Time Critical: No

=======================================================================

Candidate: Time Start: _ __

NAME Time Finish: _ __

Performance Rating: SAT ___ UNSAT _ __ Question Grade _ __ Performance Time _ __

Examiner: _ _ _ _ _ _ _ _ _ _ _ __

NAME SIGNATURE

~/_-----

- ~/

DATE

=======================================================================

COMMENTS JPM09 K Page 2 of 7

SIMULATOR SETUP SHEET N/A SIMULATOR OPERATOR INSTRUCTIONS:

N/A Tools/Equipment/Procedures Needed:

None JPM09 K Page 3 of 7

READ TO OPERATOR DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

Unit 1 was operating at 100% power when the main turbine tripped. The reactor could not be tripped from the control room and the crew entered EP/11A15000/FR-S.1 (Response to Nuclear Power Generation (ATWS)).

INITIATtNG CUES:

The CRS directs you to open the following:

Reactor Trip breakers

Reactor Trip Bypass breakers

The following breakers for CRD MIG sets:

o "MOTOR" Breaker o "GENERATOR" Breaker JPM09 K Page 4 of 7

START TIME: _ __

Open Reactor Trip Breakers.

STANDARD: Depress the RED "TRIP" plate for Reactor Trip Breaker A. SAT COMMENTS: UNSAT Open Reactor Trip Breakers.

STANDARD: Depress the RED "TRIP" plate for Reactor Trip Breaker B. SAT COMMENTS: UNSAT Open the Reactor Trip Bypass Breakers.

STANDARD: Depress the RED TRIP plate for Bypass Breaker A. SAT EXAMINER NOTE: Reactor Trip Bypass Breakers are normally "OPEN".

UNSAT COMMENTS:

Open the Reactor Trip Bypass Breakers.

STANDARD: Depress the RED "TRIP" plate for Bypass Breaker B. SAT EXAMINER NOTE: Reactor Trip Bypass Breakers are normally "OPEN".

UNSAT COMMENTS:

JPM09 K Page 5 of 7

Open the following breakers for CRD MIG sets on 1MGBA: CRITICAL STEP o "MOTOR" Breaker o "GENERATOR" Breaker SAT STANDARD: Circuit Breaker Control switch for MG set 1A "MOTOR" breaker and "GENERATOR" breaker is turned to the (left) "TRIP" position and notes GREEN "OPEN" light lit. UNSAT EXAMINER CUE: As each breaker is opened, (if asked), state "The green

'OPEN' light is lit."

EXAMINER NOTE: It is critical that at least one of these two breakers be opened.

COMMENTS:

Open the following breakers for CRD MIG sets on 1MGBB: CRITICAL STEP o "MOTOR" Breaker o "GENERATOR" Breaker SAT STANDARD: Circuit Breaker Control switch for MG set 1 B "MOTOR" breaker and 1B "GENERATOR" breaker is turned to the (left) "TRIP" position and notes GREEN "OPEN" light lit. UNSAT EXAMINER CUE: As each breaker is opened, (if asked), state "The green

'OPEN' light is lit."

EXAMINER NOTE: It is critical that at least one of these two breakers be opened.

COMMENTS:

This JPM is complete.

TIME STOP: _ __

JPM09 K Page 6 of 7

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 was operating at 100% power when the main turbine tripped. The reactor could not be tripped from the control room and the crew entered EP/1/A15000/FR-S.1 EP/11A15000/FR-S.1 (Response to Nuclear (ATWS)).

Power Generation (ATWS>>.

INITIATING CUES:

The CRS directs you to open the following:

Reactor Trip breakers

Reactor Trip Bypass breakers

The following breakers for CRD MIG sets:

o "MOTOR" Breaker o "GENERATOR" Breaker

ML100470611

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