Text

Attachments - Initial Submittal of the Jpms for Duane Arnold Initial Exam - Jan/Feb 2005
	ML051240332
Person / Time
Site:	Duane Arnold
Issue date:	01/31/2005
From:	Hironori Peterson; NRC/RGN-III/DRS/OLB
To:	Peifer M; Nuclear Management Co
References
	50-331/05-301 50-331/05-301
	Download: ML051240332 (76)
	v • d • e

ABNORMAL OPERATING PROCEDURE AOP 410 LOSS OF RIVER WATER SUPPLY

9. Establish makeup to the RHRSW/ESW pits from GSW as follows:

(1) Verify at least one GSW pump is running. _______

(2) At panel 1C452 (located in the B RHRSW/ESW pump _______

room) open the following valves with the appropriate handswitch:

CV-8035A A RHRSW/ESW WET PIT CHLORINE HS-8035A INJECTION ISOLATION CV-8035B B RHRSW/ESW WET PIT CHLORINE HS-8035B INJECTION ISOLATION CV-8034 RHRSW/ESW DILUTION WATER HS-8034 SUPPLY VALVE (3) In the CHLORINE BOOSTER PUMP ROOM, note and record the position of V80-0154, then fully open V80-0154 GSW Dilution Water Supply Balancing valve using a wrench from the toolboard. _______

6.0 ISOLATION OF A MAIN STEAM LINE DURING POWER OPERATION ............................... 1 6.0ISOLATION OF A MAIN STEAM LINE DURING POWER OPERATION CAUTION Closure of MSIVs in two Main Steam Lines may result in a half scram on the Reactor Protection System.

(1) Reduce reactor power to 65 percent or less. ___________

NOTE Unless two valve isolation is required to meet PCIS criteria or other plant conditions, the CRS has the discretion to close only the outboard or the inboard MSIV in accordance with step 2 or step 3 below. (Due to the difficulty of equalizing around the first MSIV during recovery.)

(2) At 1C04, slow close CV4413 [CV4416, CV4419, or CV4421] A[B,C, or D] outboard MSIV. Control valve by holding HS4413B [HS4416B, HS4419B or HS4421B] in test. When MSIV CV4413 [CV4416, CV4419, or CV4421] indicates full closed, place HS4413A [HS4416A, HS4419A or HS4421A] in close, then release HS4413B

[HS4416B, HS4419B, or HS4421B]. ___________

CAUTION Exercise caution when performing the following step to ensure the inboard MSIV selected is in the same main steam line as the outboard MSIV closed in Step (2).

(3) At 1C03, slowly close CV4412 [CV4415, CV4418, or CV4420] A[B,C, or D] inboard MSIV. Control valve by holding HS4412B, [HS4415B, HS4418B, or HS4420B] in test. When MSIV CV4412 [CV4415, CV4418, or CV4420] indicates full closed, place HS4412A [HS4415A, HS4418A, or HS4420A] in close. Then release HS4412B [HS4415B, HS4418B, or HS4420B]. ___________

(4) If reactor operation is to continue at power levels greater than 65% with one steamline isolated, refer to IPOI 3, "Power Operations", Section 6.0, STEADY STATE POWER OPERATIONS ABOVE 65% POWER WITH ONE STEAMLINE ISOLATED. ___________

(5) To preclude cooling in the idle MSL and buildup of condensate, open MSL drain valves MO4423, MO-4424 and CV-1064 MSL Header Drain. ___________

12.0 DRAINING TO RADWASTE ................................................................................................. 1 12.0 DRAINING TO RADWASTE NOTE The preferred method of draining the Reactor vessel is through the RWCU System because the water can be treated, thus reducing the potential radiological hazard, prior to discharge to the Radwaste System.

This section may be used in conjunction with EOP 2, Primary Containment Control (T/L) when RHR is in the Torus Cooling Mode.

Reducing the Torus water level below 8 feet will uncover Torus coating repairs. This will require inspections/repairs to be performed to assure the coating repairs have not degraded/cracked.

CAUTION Do not exceed 150°F water temperature received in Radwaste due to Radwaste tank temperature limits.

(1) Inform Health Physics that RHR system mode of operation will be changing and radiation levels in the affected corner rooms, torus area, and RHR valve room may be changing. ___________

(2) If performing Torus drain to Radwaste in conjunction with EOP 2, perform EOP Defeat 13 if necessary. ___________

(3) Verify A[B] RHR LOOP is operating in one of the following modes:

(a) Torus Cooling mode per Section 5.3 or 5.4. ___________

(b) Shutdown Cooling mode per Section 5.5. ___________

(c) LPCI Mode per Section 4.2 or 5.1. ___________

(4) Notify RW Operator to line up to receive water from the RHR System. ___________

(5) When RW is aligned, open MO-1937 INBD RHR DRAIN TO RW ISOL valve on 1C03. ___________

CAUTION If operating the RHR System in the Shutdown Cooling mode, a rapid loss of Reactor vessel water inventory may result when flow is initiated from the RHR loop to RW.

NOTE When MO-1936 is throttled open, the increase in RHR loop flow will be the drain rate to RW.

MO-1936 and MO-1937 will close on a Group 2 PCIS isolation signal. MO-1937 will close on a Group 4 PCIS isolation signal if HS-1937A SHUTDOWN COOLING 135#

INTERLOCK ENABLE is in the SHUTDOWN CLG position.

(6) Slowly throttle open MO-1936 OUTBD RHR DRAIN TO RW THRTL ISOL valve on 1C03 until recorder FR-1971 A & B RHR LOOP FLOW indicates an increase in RHR loop flow. ___________

(a) If operating in the Shutdown Cooling mode, monitor Reactor vessel water level on either of the following level indications: ___________

Indication Description Panel LI-4541 FLOOD UP RANGE 1C04 LI-4559/4560/4561 A/B/C GEMAC LEVEL 1C05 (b) If operating in the Torus Cooling mode, monitor Torus level on UR-4325 on 1C03 or LR-4384C and 4385B on 1C29. ___________

(7) When the desired level has been reached secure draining to RW as follows: __________

(a) Close the following valves on 1C03: ___________

Valve Description Position MO-1936 OUTBD RHR DRAIN TO RW THRTL ISOL NORM/CLOSED MO-1937 INBD RHR DRAIN TO RW ISOL CLOSE (b) Notify the RW Operator that draining of the RHR System is complete. ___________

DEFEAT 13 RHR DISCHARGE TO RADWASTE ISOLATION DEFEAT 20 22 29 34 401 13 26 23 25 24 21 37 02 07 1C06 10 1C05 11 36 18 1C04 27 15 EOP Override Switch Locations 28 16 17 DEFEAT 13 1C03 19 30 41 39 45 42 35 32 33 1 2 14 43 44 402 38 40 DEFEAT 13 Page 1 of 4 Rev. 1

DEFEAT 13 RHR DISCHARGE TO RADWASTE ISOLATION DEFEAT (CONTINUED)

Purpose:

To allow RHR Discharge to Radwaste Valves to remain open with the presence of a Group II Isolation signal. This defeat allows the Torus to be drained via the Radwaste System as directed by EOP-2.

Location: Panels 1C05, 1C14, 1C32, and 1C33 Equipment Required: (2) Keys # 2235 Instructions:

NOTE Taking HS-1936A [HS-1937B] to OVERRIDE position will activate annunciator GROUP 2 MO-1936 OR MO-1937 OVERRIDE (1C14A, C-5).

(1) At Panel 1C32, place GROUP 2 MO-1936 ISOLATION OVERRIDE keylock switch HS-1936A in OVERRIDE position and confirm amber light is ON. __________

(2) At Panel 1C33, place GROUP 2 MO-1937 ISOLATION OVERRIDE keylock switch HS-1937B in OVERRIDE position and confirm amber light is ON. __________

(3) At 1C05 reset PCIS Division 1 and 2 with reset pushbuttons. __________

Restoration:

(1) At Panel 1C33, place keylock switch HS-1937B in NORMAL and confirm amber light is OFF. __________

(2) At Panel 1C32, place keylock switch HS-1936A in NORMAL and confirm amber light is OFF. __________

(3) At Panel 1C14, verify annunciator GROUP 2 MO-1936 OR MO-1937 OVERRIDE (1C14A, C-5) is reset. __________

DEFEAT 13 Page 2 of 4 Rev. 1

DEFEAT 13 RHR DISCHARGE TO RADWASTE ISOLATION DEFEAT (CONTINUED)

References:

(1) Bechtel E-122, Sheets 7 & 15 (2) APED A71-003, Sheets 1, 7, 9, 12, 13 & 16 (3) P&ID M-119 (4) DCP-1450, DCRDR 1C04 Modification DEFEAT 13 Page 3 of 4 Rev. 1

DEFEAT 13 RHR DISCHARGE TO RADWASTE ISOLATION DEFEAT (CONTINUED)

Usage Level CONTINUOUS USE Effective Date:

TECHNICAL REVIEW Prepared by: Date:

Technical Review by: Date:

Operations Staff Technical Review by: Date:

EOP Coordinator Reviewed by: Date:

Operations Committee PROCEDURE APPROVAL I am responsible for the technical content of this procedure.

Approved by Procedure Owner: Date:

Operations Approved by: Date:

Plant Manager, Nuclear DEFEAT 13 Page 4 of 4 Rev. 1

6.7 SECURING WELL WATER PUMPS TO ALLOW RESETTING/OVERRIDING GROUP 7 ISOLATION.............................................................................................................. 1 6.8 RESTARTING WELL WATER PUMPS AFTER RESETTING/OVERRIDING GROUP 7 ISOLATION.............................................................................................................. 2 6.7 SECURING WELL WATER PUMPS TO ALLOW RESETTING/OVERRIDING GROUP 7 ISOLATION (1) If a PCIS Group 7 isolation exists and a well water pump is running, perform the following steps, as applicable, to secure the operating well water pumps(s), otherwise N/A this step:

(a) Secure 1P-58A[B, C] as follows:

1. Reduce A[B, C] well water pump 1P-58A[B, C] flow to zero by either:

a. In remote: Adjust Flow Controller FC 4414A[B, C] at panel 1C23 to zero percent. ___________

b. In local: Close MO4414A[B, C] locally. ___________

2.Place the respective handswitches at panel 1C06 to the STOP position. _________

Switch Pump HS4417A A Well Water Pump 1P-58A HS4422A B Well Water Pump 1P-58B HS4483A C Well Water Pump 1P-58C

3. Observe the respective indicating lights at panel 1C06 and verify the affected well water pumps are secured. ___________

4. Adjust MO4414A[B, C] position as follows:

a. In remote: Adjust Flow Controller FC4414A[B, C] at panel 1C23 to 10%[20%, 10%] ___________

b. If operating in local, open MO4414A[B, C] to approximately 10%[20%,

10%] ___________

(b) Secure D Well Water Pump 1P-58D as follows:

1. Lower D well water pump 1P-58D flow to zero per one of the following:

a. In Auto: Flow Controller FC4414D on panel 1C23 ___________

b. In Hand: The manual speed adjustment dial at 1C373 ___________

2. Observe the respective indicating lights on panel 1C06 and verify that D well water pump 1P-58D is not running. ___________

Usage Level Continuous Use 6.8 RESTARTING WELL WATER PUMPS AFTER RESETTING/OVERRIDING GROUP 7 ISOLATION (1) If well water is not in operation, restore well water flow as follows:

NOTE It is preferable to start either well water pump 1P-58A or 1P-58C when restoring well water flow since they are lower head pumps and can be more easily controlled. Per CRS/OSM direction, any available well water pump may be started, as required.

(a) Start well water pump 1P-58A[B, C] as follows:

1. At 1C23 verify FC4414A[B, C] well water controller is set at 10%[20%, 10%] open ______

a. If local control is desired, verify the local/remote handswitch for MO4414A[B, C] in LOCAL and verify that MO4414A[B, C] is approximately 10%[20%, 10%] open ___________

2. Start the A[B, C] well water pump 1P-58A[B, C] by performing the following as necessary:

a. If starting the pump from 1C06, momentarily place the respective handswitch to the START position. ___________

Switch Pump

HS4417A A Well Water Pump 1P-58A HS4422A B Well Water Pump 1P-58B HS4483A C Well Water Pump 1P-58C

b. At the respective well house, push the START button at the local pump control panel. ___________

3. Verify the red light is on for the respective well water pump on 1C06. ___________

4. Adjust flow as desired by adjusting FC4414A[B, C] at 1C23 or adjusting MO4414A[B, C] at the respective well house. ___________

(b) Start well water pump 1P-58D per one of the following methods:

1. If starting the pump from 1C23, perform the following:

a. Adjust FC4414D well water controller to start D well water pump 1P-58D and achieve the desired pump speed, system flow and pressure. _____

2. If starting the pump in HAND (local), perform the following:

a. Verify the speed dial is set at zero. ___________ .

b. Verify the HAND/OFF/AUTO switch at panel 1C373 is in the HAND position. ___________

c. Adjust the manual speed adjust knob to achieve the desired pump speed, system flow and pressure. ___________

3. Verify that the red running light is on at 1C06 for 1P-58D. ___________

DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT 20 22 29 34 2 1 401 13 26 23 25 24 21 37 02 07 1C06 10 1C05 11 36 18 1C04 27 15 EOP Override 28 16 Switch Locations 17 DEFEAT 4 1C03 19 30 41 39 45 42 35 32 33 14 43 44 402 38 40 DEFEAT 4 Page 1 of 6 Rev. 8

DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT

Purpose:

To restore Drywell Cooling and shift Drywell Cooling Fans to fast speed when plant conditions allow for their use.

Location: 1C25 Equipment Required: (2) Keys #2235 Instructions:

NOTE A PCIS Group 7 Isolation can be confirmed by the following indications:

Annunciator REACTOR LO-LO-LO LEVEL TRIP (1C05A, A-1) is activated.

At 1C31, the amber GROUP 7 SEALED-IN light is ON.

CAUTION If a PCIS Group 7 exists, the Drywell Cooling loops will automatically isolate. With Drywell Cooling isolated, the potential exits to void portions of the Drywell Cooling header. This could create the potential for a water hammer when the Well Water supply to Drywell Cooling is restored. To preclude a water hammer, Well Water must be secured prior to restoring Drywell Cooling.

(1) If a PCIS Group 7 Isolation exists AND any Well Water Pump is running, secure all ________

operating Well Water Pumps per OI 408, Section 6.7.

NOTE Taking HS-4321A[B] to OVERRIDE will activate annunciator DRYWELL COOLING ISOL VLV AND LOW SPEED FAN OVERRIDE (1C14B, C-4).

The following steps are performed at Control Room Panel 1C25.

(2) Place GROUP 7 CHANNEL A DW COOLING AND FAN SPEED OVERRIDE ________

keylock switch HS-4321A to OVERRIDE position and confirm amber light is ON.

(3) Place GROUP 7 CHANNEL B DW COOLING AND FAN SPEED OVERRIDE ________

keylock switch HS-4321B to OVERRIDE position and confirm amber light is ON.

DEFEAT 4 Page 2 of 6 Rev. 8

DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT (4) Verify the following:

(a) Any Drywell Cooling Fan that was operating in standby, starts in high ________

speed.

(b) If high Drywell pressure exists, verify that any running Drywell Cooling ________

Fan shifts from low speed (amber light) to high speed (red light).

(5) Verify MODE SELECT switches HS-5718A and B are in START position. ________

CAUTION If Well Water has been out of service, water could drain from Drywell Cooling loops.

Well Water must be restored in a slow, controlled manner to preclude the potential for a water hammer. A normal system startup meets this requirement.

(6) If Well Water was NOT in operation and a Well Water Pump can be restarted, start ________

a Well Water Pump and SLOWLY restore Well Water flow per OI 408, Section 6.8.

DEFEAT 4 Page 3 of 6 Rev. 8

DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT Restoration:

(1) If necessary, reset the PCIS Group 7 Isolation seal-in logic as follows: ________

(a) At 1C31, depress GROUP 7 ISOLATION RESET SWITCH HS-4841X to ________

reset the Group 7 logic.

(b) At 1C31, verify that the amber GROUP 7 SEALED-IN light is OFF. ________

(2) At 1C25, perform the following:

(a) Place keylock switch HS-4321A to NORMAL position and confirm amber ________

light is OFF.

(b) Place keylock switch HS-4321B to NORMAL position and confirm amber ________

light is OFF.

(c) Place Mode Select Switches HS-5718A to INOP and back to the START ________

position.

(d) Place Mode Select Switches HS-5718B to INOP and back to the START ________

position.

(3) At 1C14, verify annunciator DRYWELL COOLING ISOL VLV AND LOW SPEED ________

FAN OVERRIDE (1C14B, C-4) is reset.

DEFEAT 4 Page 4 of 6 Rev. 8

DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT

References:

(1) Bechtel E-113, Sheets 80, 86-90, 94 (2) P&IDs M-144 (Sheet 1), M-157 (3) M155-206, Sheets 3, 4, 5 (4) DCP-1450, DCRDR 1C04 Modification (5) NG-97-0666, Mitigating the Potential for Water Hammer In Drywell Cooling Piping (6) AR 96-1909.03 (7) AR 29294 (8) NG-02-0145, Response To Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions (9) NRC Safety Evaluation for DAEC Response To Generic Letter 96-06, dated March 29, 2002, Docket No. 50-331 (10) ECP 1569, Group 7 Isolation Seal-In Relay DEFEAT 4 Page 5 of 6 Rev. 8

DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT Usage Level CONTINUOUS USE Effective Date:

TECHNICAL REVIEW Prepared by: Date:

Technical Review by: Date:

Operations Reviewed by: Date:

Operations Committee PROCEDURE APPROVAL Approved by Procedure Owner: Date:

Operations Support Manager Approved by: Date:

DAEC Plant Manager DEFEAT 4 Page 6 of 6 Rev. 8

ABNORMAL OPERATING PROCEDURE AOP 672.2 OFFGAS RADIATION/REACTOR COOLANT HIGH ACTIVITY

5. If the MSIVs are closed and fuel failure is suspected, then obtain permission from the CRS and establish a leakage path to the main condenser as follows:

a. At 1C04, isolate the main steam supply to Offgas and SJAEs by placing the ________

following handswitches in the CLOSE position:

Switch Description HS-1362A SJAE & OFFGAS MSL A STEAM SUPPLY MO-1362A HS-1362B SJAE & OFFGAS MSL B STEAM SUPPLY MO-1362B

b. At 1C07, isolate the main steam supply to the Turbine Steam Seal System by ________

placing the following handswitches in the CLOSE position:

Switch Description HS-1169 MAIN STEAM SUPPLY MO-1169 HS-1170 REGULATOR BYPASS MO-1170

c. At 1C07, verify that the main steam supply to MSR 2nd Stage Reheat is ________

isolated by verifying the following handswitch is in the CLOSE position:

Switch Description HS-1054 MAIN STEAM TO MSR SECOND STAGE MO-1054 & MO-1055

d. At 1C07, verify that Mechanical Vacuum Pump 1P-32 is secured. ________

e. At 1C04, establish the preferred MSIV leakage path by placing the following ________

handswitches in the OPEN position Switch Description HS-1043 MSL HEADER DRAINS BYPASS MO-1043 HS-1044 MSL DRAIN ORIFICE BYPASS MO-1044

f. If the preferred MSIV leakage path cannot be established, establish the alternate ________

path by opening MSL HEADER DRAIN CV-1064 using HS-1064 on 1C04.

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

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Usage Level CONTINUOUS Effective Date: __________________

Verified By: Date:

Testing and Surveillance Validated By: Date:

Operations Verified By: Date:

System Engineering Approved By: Date:

Procedures Reviewed By: Date:

Operations Committee Approved By: Date:

DAEC Plant Manager

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

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1.0 PURPOSE 1.1 The purpose of this procedure is to functionally test the RPS Manual Scram Channels.

1.2 This procedure, when performed in its entirety, FULLY SATISFIES the RPS Instrumentation Channel Functional Test requirements for the Manual Scram function.

1.3 This procedure, when performed in its entirety, FULLY SATISFIES the RPS Instrumentation Logic System Functional Test (LSFT) requirements for the Manual Scram function.

2.0 BRIEFING INFORMATION 2.1 PERFORMANCE INFORMATION 2.1.1 There are two (2) RPS Manual Scram channels (A3 and B3) to be functionally tested within this procedure. Testing of individual logic trains is organized as follows:

STP Sections Logic Channel 7.1 Channel A3 7.2 Channel B3 Testing of logic channels may be performed in any convenient order provided only one logic channel is tested at a time. While an instrument channel in one trip system is being tested, all other instrument trip channels shall be operable and un-tripped to preclude an unwarranted RPS SCRAM. All steps pertaining to a particular channel are to be performed in sequence and the steps carried through to completion, unless stated otherwise.

2.1.2 The following personnel are recommended to perform this STP:

1 Operations 2.1.3 The following test equipment is required for performance of this STP:

None 2.1.4 Due to possible age-related failure, the Scram Pilot solenoid valves will be checked for blow fuses prior to performing this surveillance (Prerequisite 6.4). These fuses will be replaced in RFO 19. This verification will no longer be necessary after fuse replacement. (OTH027214) 2.2 GENERAL CAUTIONS 2.2.1 This test will initiate several Half Scrams for the channel under test.

2.3 SPECIAL PRECAUTIONS 2.3.1 None

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

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3.0 REFERENCES

3.1 Applicable drawings:

3.1.1 APED C71-004 <4,6,7,7A,8,9,11,14>

3.1.2 APED C51-027 <12,14,18,20,23,24,45,47>

3.1.3 NEDC-30851P-A, Technical Specification Improvement Analyses for BWR Reactor Protection System (AR 96-1409) 4.0 GENERAL INSTRUCTIONS 4.1 Steps marked with a "TS" immediately to the right of the step signoff line are required by Technical Specifications. If these steps do not meet their acceptance criteria or cannot be performed, a NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.

4.2 An Action Request (AR) shall be completed for any problems encountered with "TS" marked steps during the performance of this test/inspection.

4.3 The CRS shall be notified immediately and the appropriate Limiting Conditions for Operation section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.

4.4 If any equipment or components are observed to be in a state of disrepair during the performance of this STP, appropriate corrective maintenance shall be initiated.

5.0 APPENDICES 5.1 None

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

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Prerequisites Performance Date: ____________________ INITIALS 6.0 PREREQUISITES 6.1 Verify no testing or maintenance is being performed on any RPS channels. ________

(CRS) 6.2 At 1C05, verify the following:

6.2.1 SCRAM GROUP A 1 2 3 4 lights are on. ________

(OPS) 6.2.2 SCRAM GROUP B 1 2 3 4 lights are on. ________

(OPS) 6.3 At 1C05, verify the following annunciators reset:

6.3.1 "A" RPS AUTO SCRAM (1C05A, A-2) ________

(OPS) 6.3.2 "B" RPS AUTO SCRAM (1C05B, A-2) ________

(OPS) 6.3.3 "A" RPS BACK-UP SCRAM HALF SCRAM (1C05A, E-4) ________

(OPS) 6.3.4 "B" RPS BACK-UP SCRAM HALF SCRAM (1C05B, E-4) ________

(OPS) 6.4 At 1C131A through 1C131H, verify NO blown Scram Pilot solenoid valve ________

fuses. (OPS)

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

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Channel - A3 Performance Date: ____________________ INITIALS 7.0 PROCEDURE 7.1 RPS CHANNEL A3 MANUAL SCRAM FUNCTIONAL TEST 7.1.1 At 1C15, visually confirm the following:

a. Contact 5-6 for RPS TRIP SYSTEM A, SCRAM GROUP 1 ________

AND 4 RESET relay C71A-K19A is open.

b. Contact 5-6 for RPS TRIP SYSTEM A, SCRAM GROUP 2 ________

AND 3 RESET relay C71A-K19C is open.

7.1.2 At 1C05, perform the following:

a. Depress and release REACTOR MANUAL SCRAM A ________

pushbutton C71A-S3A.

b. Confirm "A" RPS MANUAL SCRAM annunciator (1C05A, A-3) ________

is actuated.

c. Confirm "A" RPS BACK-UP SCRAM HALF SCRAM ________

annunciator (1C05A, E-4) is actuated.

d. Confirm white SCRAM GROUP A 1 2 3 4 lights are off. ________ TS

e. Confirm red REACTOR MANUAL SCRAM A pushbutton ________

C71A-S3A indicating light is on.

7.1.3 Confirm the following computer points type out:

a. B657 C71A-K15A1 REACTOR MANUAL SCRAM SCRAM ________

b. D536 MANUAL SCRAM CHNL A TRIP ________

7.1.4 At 1C15, confirm white SCRAM GROUP A 1 2 3 4 lights are off. ________

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

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Channel - A3 Performance Date: ____________________ INITIALS 7.1.5 At 1C05, perform the following:

a. Reset Half Scram using REACTOR SCRAM RESET ________

handswitch C71A-S5.

b. Confirm "A" RPS MANUAL SCRAM annunciator (1C05A, A-3) ________

is reset.

c. Confirm "A" RPS BACK-UP SCRAM HALF SCRAM annunciator (1C05A, E-4) is reset. ________

d. Confirm white SCRAM GROUP A 1 2 3 4 lights are on. ________

e. Confirm red REACTOR MANUAL SCRAM A pushbutton ________

C71A-S3A indicating light is off.

7.1.6 Confirm the following computer points type out:

a. B657 C71A-K15A1 REACTOR MANUAL SCRAM RSET ________

b. D536 MANUAL SCRAM CHNL A RSET ________

7.1.7 At 1C15, confirm white SCRAM GROUP A 1 2 3 4 lights are on. ________

7.1.8 At 1C15, visually confirm the following:

a. Contact 5-6 for RPS TRIP SYSTEM A, SCRAM GROUP 1 ________

AND 4 RESET relay C71A-K19A is open.

b. Contact 5-6 for RPS TRIP SYSTEM A, SCRAM GROUP 2 ________

AND 3 RESET relay C71A-K19C is open.

Performed by: Date: Time:

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

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Channel - B3 Performance Date: ____________________ INITIALS 7.2 RPS CHANNEL B3 MANUAL SCRAM FUNCTIONAL TEST 7.2.1 At 1C17, visually confirm the following:

a. Contact 5-6 for RPS TRIP SYSTEM B, SCRAM GROUP 1 ________

AND 4 RESET relay C71A-K19B is open.

b. Contact 5-6 for RPS TRIP SYSTEM B, SCRAM GROUP 2 ________

AND 3 RESET relay C71A-K19D is open.

7.2.2 At 1C05, perform the following:

a. Depress and release REACTOR MANUAL SCRAM B ________

pushbutton C71A-S3B.

b. Confirm "B" RPS MANUAL SCRAM annunciator (1C05B, A-3) ________

is actuated.

c. Confirm "B" RPS BACK-UP SCRAM HALF SCRAM ________

annunciator (1C05B, E-4) is actuated.

d. Confirm white SCRAM GROUP B 1 2 3 4 lights are off. ________ TS

e. Confirm red REACTOR MANUAL SCRAM B pushbutton ________

C71A-S3B indicating light is on.

7.2.3 Confirm the following computer points type out:

a. B615 C71A-K15B1 REACTOR MANUAL SCRAM SCRAM ________

b. D537 MANUAL SCRAM CHNL B TRIP ________

7.2.4 At 1C17, confirm white SCRAM GROUP B 1 2 3 4 lights are off. ________

7.2.5 At 1C05, perform the following:

a. Reset Half Scram using REACTOR SCRAM RESET ________

handswitch C71A-S5.

b. Confirm "B" RPS MANUAL SCRAM annunciator (1C05B, A-3) ________

is reset.

c. Confirm "B" RPS BACK-UP SCRAM HALF SCRAM ________

annunciator (1C05B, E-4) is reset.

d. Confirm white SCRAM GROUP B 1 2 3 4 lights are on. ________

e. Confirm red REACTOR MANUAL SCRAM B pushbutton ________

C71A-S3B indicating light is off.

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

8 of 10 1

Channel - B3 Performance Date: ____________________ INITIALS 7.2.6 Confirm the following computer points type out:

a. B615 C71A-K15B1 REACTOR MANUAL SCRAM RSET ________

b. D537 MANUAL SCRAM CHNL B RSET ________

7.2.7 At 1C17, confirm white SCRAM GROUP B 1 2 3 4 lights are on. ________

7.2.8 At 1C17, visually confirm the following:

a. Contact 5-6 for RPS TRIP SYSTEM B, SCRAM GROUP 1 ________

AND 4 RESET relay C71A-K19B is open.

b. Contact 5-6 for RPS TRIP SYSTEM B, SCRAM GROUP 2 ________

AND 3 RESET relay C71A-K19D is open.

Performed by: Date: Time:

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

9 of 10 1

Performance Date: ____________________ INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 If this STP is performed for any reason other than for satisfying the PURPOSE as stated in Section 1.0, indicate below (otherwise mark this step "N/A"):

8.2 If a DCF, Procedure Work Request (PWR), or Action Request (AR) was written due to problems encountered with the performance of this procedure, list the applicable number(s) below and attach a copy of each to this procedure. ("N/A" blocks as appropriate.)

DCF No. ________ PWR No. _________ AR No. _________

8.3 All Technical-Specification-required items, as indicated by "TS", have been performed satisfactorily.

8.3.1 Section 7.1 ( ) YES ( ) NO CRS notified ________

8.3.2 Section 7.2 ( ) YES ( ) NO CRS notified ________

8.4 All other items checked in this test have been performed satisfactorily.

8.4.1 Section 7.1 ( ) YES ( ) NO CRS notified ________

8.4.2 Section 7.2 ( ) YES ( ) NO CRS notified ________

SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.

10 of 10 1

Performance Date: ____________________ INITIALS 8.5 Indicate any relevant test comments below, otherwise mark this step "N/A":

Operations Date Surveillance Coordinator Date 9.0 ATTACHMENTS 9.1 None

OPERATING INSTRUCTION OI 358 REACTOR PROTECTION SYSTEM 6.3 POWER TRANSFER OF ALTERNATE POWER SUPPLY SOURCE FROM 1Y1A TO 1Y2A

[1Y2A TO 1Y1A] ....................................................................................................................

6.3 POWER TRANSFER OF ALTERNATE POWER SUPPLY SOURCE FROM 1Y1A TO 1Y2A [1Y2A TO 1Y1A]

CAUTION Operation with both RPS ALT SUPPLY to 1Y36 circuit breakers 1Y16-10 at 1Y16 and 1Y26-10 at 1Y26 closed is prohibited in order to prevent the possibility of cross-connecting regulating transformers 1Y1A and 1Y2A through a malfunction in manual transfer switch 1Y36.

(1) If either RPS bus is being powered from the alternate power supply source and that bus's associated RPS MG set is available, transfer power to the MG set per Section 6.2. ___________

(2) Verify the Regulating Transformer 1Y2A [1Y1A] is available and in service per OI 317.1. ___________

(3) If an RPS half scram is anticipated because of the RPS bus power supply sources alignment, perform RPS Power Supply Transfer Half Scram Preparation Checklist (Appendix 3). (NA if RPS bus is already deenergized). ___________

CAUTION If either RPS bus is being powered from the alternate power supply source. The following step will cause a reactor half scram and a PCIS Groups 1 through 5 isolation (except MSIVs) signal.

(4) At Panel 1Y30A, open the RPS ALTERNATE FEED XFMR circuit breaker 1Y30A-00. ___________

(5) At the RPS Alternate Source Electrical Protection Assemblies, open the EPA-C2 circuit breaker. ___________

(6) At EPA-C1, open the circuit breaker. ___________

(7) At Panel 1Y26 [1Y16], verify the RPS ALT SUPPLY to 1Y36 circuit breaker 1Y26-10

[1Y16-10] is in the OFF position. ___________

(8) At Panel 1Y16 [1Y26], open the RPS ALT SUPPLY to 1Y36 circuit breaker 1Y16-10

[1Y26-10]. ___________

(9) At 1Y2A [1Y1A], verify circuit breaker 1Y2A02 [1Y1A02] is closed. (REGULATING TRANSFORMER 1Y2A [1Y1A] SUPPLY TO 1Y26 [1Y16]). ___________

(10) At Panel 1Y26 [1Y16], close the RPS ALT SUPPLY to 1Y36 circuit breaker 1Y26-10

[1Y16-10]. ___________

(11) At Panel 1Y36, select 1Y26 [1Y16]. ___________

(a) The manual transfer switch inside 1Y36 rotates counterclockwise only and will "snap" into the desired position.

(12) At EPA-C1, observe that the POWER IN light is ON and the following lights are OFF: ___________

OVER-VOLTAGE UNDER-VOLTAGE UNDER-FREQUENCY POWER OUT (a) If the OVER-VOLTAGE, UNDER-VOLTAGE, and/or UNDER-FREQUENCY trip status light(s) is/are ON, momentarily place the TRIP/RESET keylock switch EPA-C1-S2 in the RESET position and verify the light(s) turn(s) OFF; then place the switch back to the OPER position. ___________

(13) Close the EPA-C1 circuit breaker and observe that the POWER OUT light turns ON. ____

(14) At EPA-C2, observe the POWER IN light is ON and the following lights are OFF: ______

OVER-VOLTAGE UNDER-VOLTAGE UNDER-FREQUENCY POWER OUT (a) If the OVER-VOLTAGE, UNDER-VOLTAGE, and/or UNDER-FREQUENCY trip status light(s) is/are ON, momentarily place the TRIP/RESET keylock switch EPA-C2-S2 in the RESET position and verify the light(s) turn(s) OFF; then place the switch back to the OPER position. ___________

(15) Close the EPA-C2 circuit breaker and observe the POWER OUT light turns ON. _______

(16) At Panel 1Y30A, close the RPS ALTERNATE FEED XFMR circuit breaker 1Y30A-00. ___________

(17) At Panels 1C15 and/or 1C17, verify the white ALT XFMR indicating light(s) above the RPS ALTERNATE POWER TRANSFER switch(es) C71B-S1A (1C15) and/or C71B-S1B (1C17) is/are ON. ___________

NOTE If an RPS bus power supply source was selected to the alternate supply, the white ALT XFMR indicating light above the RPS ALTERNATE POWER TRANSFER switch on the opposite control panel will be OFF. (This is because the two RPS ALTERNATE POWER TRANSFER switches are interlocked so only one RPS bus at a time may be powered from the alternate power supply source.

(18) If an RPS bus was selected to be powered from the alternate power supply source, verify the RPS bus loads were reenergized. ___________

(19) If a half scram occurred as a result of the transfer, complete RPS Power Supply Transfer Half Scram Recovery Checklist (Appendix 4). ___________

OPERATING INSTRUCTION OI 317.1 120 VAC INSTRUMENT CONTROL POWER SYSTEM 5.5 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A [1Y2A]Error! Bookmark not defined.

5.5 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A [1Y2A]

(1) At Panel 1Y36, verify the RPS alternate power supply source is not selected to 1Y16 [1Y26]. ___________

(a) If necessary, transfer the RPS alternate power supply source to 1Y2A [1Y1A]

per OI 358. ___________

(2) If necessary, start up and transfer load to Inverter 1D15 [1D25] per Section 3.5, or transfer loads to an operating inverter per Section 4.2. ___________

(3) At 1D15 [1D25], momentarily depress the LAMP TEST/ALARM RESET pushbutton. ____

(4) At 1D15[1D25] put on electrical safety gear, then open right cabinet door and place inverter ALARM BYPASS SWITCH to BYPASS. ___________

(5) Confirm the FORWARD TRANSFER light is ON. ___________

(6) At 1Y15 [1Y25], confirm switch 1Y1504 [1Y2504] in the INVERTER position.

(1Y15 [1Y25] MAINTENANCE SWITCH) ___________

CAUTION Opening or closing of breaker 1Y1503 [1Y2503] could result in a Reactor Recirc MG Set Scoop Tube lockup due to a problem in the scoop tube positioner circuitry.

(7) Turn circuit breaker 1Y1503 [1Y2503] OFF. (REGULATING TRANSFORMER 1Y1A

[1Y2A] SUPPLY TO JS1501 [JS2501]) ___________

(8) At 1Y1A [1Y2A], turn circuit breaker 1Y1A02 [1Y2A02] OFF.

(REGULATING TRANSFORMER 1Y1A [1Y2A] SUPPLY TO 1Y16 [1Y26]) ___________

(9) Turn circuit breaker 1Y1A01 [1Y2A01] OFF.

(REGULATING TRANSFORMER 1Y1A [1Y2A] INPUT) ___________

(10) At 1B32 [1B42], turn circuit breaker 1B3216A [1B4203A] OFF.

(REGULATING TRANSFORMER 1Y1A [1Y2A] AC SUPPLY) ___________

ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 1 of 7 Usage Level Information Use Effective Date:

TECHNICAL REVIEW Prepared by: Date:

Validated by: Date:

Operations Staff PROCEDURE APPROVAL I am responsible for the technical content of this procedure.

Verified and Approved by Procedure Owner: Date:

DAEC Plant Manager Concurred by: Date:

Chairman, Operations Committee Reviewed by: Date:

Manager, Regulatory Affairs Approved by: Date:

Site Vice President

ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 2 of 7 1.0 PURPOSE (1) This procedure provides policy guidelines for overtime limits and requirements for personnel working at the Duane Arnold Energy Center (DAEC). These guidelines are provided to prevent situations where fatigue could reduce the mental alertness or decision-making capability of plant personnel.

(2) This procedure applies to salaried, hourly, and union personnel in the Nuclear Division working at the DAEC. (Reference 7) {C002}

(3) This procedure applies to all contractor and vendor personnel working at DAEC.

(4) This procedure does not apply to Security personnel.

2.0 DEFINITIONS The following definition supplements those contained in the Quality Assurance Manual, Appendix B, Glossary of Terms.

(1) Key Maintenance Personnel - Those personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of safety-related structures, systems or components. This includes personnel performing or immediately supervising the performance of such activities.

(2) Shift Turnover - The time frame when an individual assumes the responsibilities from the onshift person. This time will vary depending upon the responsibilities being transferred.

The goal of shift turnover should be to communicate effectively to the oncoming workers to allow them to perform their jobs safely and effectively.

(3) Work Period - The pre-scheduled shift or time slot a worker is assigned to work.

Callouts, downpowers, and/or other emergent work activities may require a worker to return to work or arrive earlier than their pre-scheduled work period. In such cases, authorization for less than the 8-hour break between work periods is not required as long as the remaining overtime limits are met or deviation to those limits is authorized.

However, after the emergent work or unscheduled overtime period is complete, the 8-hour break shall be granted or appropriate authorization obtained.

ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 3 of 7 3.0 INSTRUCTIONS 3.1 RESPONSIBILITIES (1) The Plant Manager and other managers are responsible for authorizing any deviations from the overtime requirements.

(2) The Control Room Supervisor (CRS) is responsible for ensuring shift manning requirements are met.

(3) All supervisors are responsible for assuring that personnel under their supervision do not exceed the overtime requirements of this procedure without prior authorization. If overtime requirements are exceeded due to circumstances beyond the control of the supervisor (e.g., relief overslept or is ill), authorization to exceed the overtime requirement may be granted at the time of the deviation.

(4) The DAEC Administrative Secretary is responsible for maintaining the authorized overtime deviation forms and file for personnel under the Plant Manager. Other departments (e.g.,

Regulatory Affairs, Engineering, Nuclear Oversight, etc.) will maintain their authorized overtime deviation forms.

(5) All project leads are required to discuss this procedure with all contract personnel.

(6) All personnel are responsible for:

Monitoring their work hours and notifying their supervisor prior to exceeding any overtime limits.

Informing their supervisor if they believe that fatigue has or will make them unfit for duty.

3.2 REQUIREMENTS (1) When overtime is required, it shall be authorized and controlled in accordance with this procedure.

ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 4 of 7 NOTE Hours worked do not include work breaks such as shift turnover.

(2) An individual shall not be permitted to work more than the following:

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day (168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months ) period (3) A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , including shift turnover time, shall be allowed between work periods.

(4) The use of overtime shall be considered on an individual basis. During refueling outages, management may provide blanket overtime authorization within the requirements of this procedure.

(5) Deviations from the above requirements shall be documented in writing and authorized by personnel noted in step 3.1(1) using Attachment 1.

(6) The following requirements apply to Operations Department personnel:

(a) If a Reactor Operator (RO) or a Senior Reactor Operator (SRO) has been working more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during periods of extended shutdown (e.g., at duties away from the control board), such individuals shall not be assigned shift duty in the Control Room without at least a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months break preceding such an assignment.

(b) If a Reactor Operator is required to work in excess of 8 continuous hours, he shall be periodically relieved of primary duties at the control board, such that periods of duty at the board do not exceed 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at a time.

(c) The Operations Department staffing policy should be developed in a manner that permits licensed Reactor Operators to be periodically assigned to other duties away from the control board during their normal tours of duty.

3.3 GENERAL INSTRUCTIONS (1) Staffing and work assignments should be such that adequate coverage will be maintained without routine or heavy use of overtime.

(2) Overtime shall be considered on an individual basis except for extended outages.

ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 5 of 7 (3) Department supervisors should balance scheduled work activities with resource availability as necessary to maintain a normal 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months work week. When required, overtime work should be scheduled such that the requirements of this procedure are not exceeded without prior authorization.

(4) Due to the inability to pre-schedule all overtime, it is the responsibility of the respective department supervisors to ensure that personnel who are asked to work emergent overtime meet the overtime requirements of this procedure.

3.4 DEVIATIONS (1) When necessary, supervisors may request authorization to deviate from the established overtime limits. The reason for the deviation shall be documented by the person authorizing the overtime on an Overtime Deviation Form (Attachment 1) and submitted to the Plant Manager or authorized alternate for approval. Other managers are considered to be authorized alternates.

(2) Deviations from the working hour guidelines that are solely-related to the transition to/from daylight savings time and standard time are authorized in advance under this procedure based on the limited duration (one hour) and infrequent application. No additional documentation of this deviation beyond that wholly contained in this procedural step is required.

(3) When authorizing deviations, consideration shall be given for the following:

Reduction in the effectiveness of personnel.

Utilizing personnel on overtime away from control panel and/or safety-related duties.

Fitness for duty.

(4) A copy of the approved Overtime Deviation Form shall be transmitted to the DAEC Administrative Secretary or appropriate department secretary for record keeping.

(5) This procedure requires an Operations Committee review and DAEC Plant Manager approval per DAEC Technical Specifications. {C001} (References 1 and 8) 4.0 RECORDS (1) Approved Overtime Deviation Forms shall be maintained as non-permanent Quality Assurance records for six (6) months as a minimum.

ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 6 of 7

5.0 REFERENCES

(1) DAEC Technical Specifications, Administrative Controls-Procedures section (2) NUREG-0737, Task Action Plan I.A.1.3, Shift Planning (3) Nuclear Regulatory Commission (NRC) Circular No. 80-02, Nuclear Power Plant Staff Work Hours (4) NRC Generic Letter 82-02, NRC Policy on Factors Causing Fatigue of Operating Personnel at Nuclear Reactors (5) NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours (6) NRC Generic Letter 83-14, Definition of Key Maintenance Personnel (7) {C002} NRC Inspection Report 93-015 (8) {C001} QDR 94-038 (9) AR 98-1930.01 (10) AR 14817 (11) AR 24662

ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 7 of 7 ATTACHMENT 1 OVERTIME DEVIATION FORM OVERTIME DEVIATION FORM INDIVIDUAL:

DEPARTMENT: SAMPLE LENGTH OF DEVIATION: FROM TO Date/Time Date/Time OVERTIME LIMITATION TO BE EXCEEDED:

Work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight Work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24-hour period Work more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48-hour period Work more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7-day period (168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months )

Break of less than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months between work periods.

JUSTIFICATION FOR EXCEEDING THE LIMITATION:

WORK TO BE PERFORMED:

RECOMMENDED BY: DATE: _______________

Department Supervisor APPROVED BY: DATE: _______________

Plant Manager/Alternate AUTHORIZED APPROVAL ALTERNATES:

Managers of Training, Engineering, Regulatory Affairs, Operations, Maintenance, Radiation Protection, Nuclear Oversight, and Operations Shift Manager.

cc: DAEC Administrative Secretary NG-148K Rev. 10

ABNORMAL OPERATING PROCEDURE AOP 149 LOSS OF DECAY HEAT REMOVAL 3.2 Feed and Bleed to the Torus via Safety/Relief Valves

a. Verify the reactor head is on and tensioned, head vents closed and at least one SRV with N2 supply is available. _______

b. Evacuate all personnel from the Drywell and Torus areas except personnel assigned to monitor for leakage and/or increased airborne radioactivity levels. _______

c. To prevent flow down the main steam lines, verify at least one valve in each steam line is closed: _______

Main Steam Line A CV-4412 or CV-4413 Main Steam Line B CV-4415 or CV-4416 Main Steam Line C CV-4418 or CV-4419 Main Steam Line D CV-4420 or CV-4421 HPCI Steam Line MO-2238 or MO-2239 RCIC Steam Line MO-2400 or MO-2401 Steam Line Drains MO-4423 or MO-4424

d. Place handswitch for one SRV in the open position. _______

e. If available, place RHR in Torus Cooling per OI 149. _______

f. Commence and raise injection into the RPV with either a Condensate, Core Spray or RHR pump until the SRV is open and RPV pressure is 50 psig above Torus pressure, but as low as practical. _______

Usage Level - Reference Use CORE SPRAY RAPID START IMMEDIATE ACTIONS (1) Start 1P-99A[B], ESW Pumps A[B]. __________

(2) Start 1P-211A[B], Core Spray Pump A[B]. __________

(3) Open MO-2117[2137], Core Spray Inboard Injection Valve, when reactor pressure is <450 psig. __________

(4) Verify MO-2104[2124], Core Spray Min Flow Bypass Valve, closes when system flow is >600 gpm. __________

FOLLOW-UP ACTIONS (1) Throttle MO-2117[2137], Core Spray Inboard Injection Valve, to maintain system flow <3100 gpm. __________

(2) Verify RHR/CS Pump Room Cooling Units operating. __________

1P-211A : 1V-AC-12 __________

1P-211B: 1V-AC-11 __________

(3) Verify operating Core Spray Pump motors <95 amps. __________

OI 151 QRC 1 Page 1 of 1 Rev. 1

OI 151 QRC 1 CORE SPRAY RAPID START Usage Level Reference Use Effective Date:

TECHNICAL REVIEW Verified by: Date:

Procedures Staff Validated by: Date:

Operations Staff Reviewed by: Date:

Operations Committee PROCEDURE APPROVAL I am responsible for the technical content of this procedure.

Approved by Procedure Owner: Date:

Operations Approved by: Date:

DAEC Plant Manager OI 151 QRC 1 Rev 1