WATTS BAR NUCLEAR PLANT UNIT 2 PREOPERATIONAL TEST TITLE: Shutdown from Outside the Main Control Room Instruction No: Revision No: 2-PTI-068-13 0001 PREPARED BY: REVIEWED BY: R. D. Dobbs . R z PRINT NAME I SIGNATURE Donald R. Heard (PcL'iSZýL DATE: 414115 DATE: qti "q PRINT NAME / SIGNATURE INSTRUCTION APPROVAL JTG MEETING No: )- -Al 3 - DO JTG CHAIRMAN: _-___/,I_4__j_ DATE: DATE: APPROVED BY: PREO RAiIONAL STARiUP MANAGER TEST RESULTS APPROVAL JTG MEETING No: JTG CHAIRMAN: DATE: APPROVED BY: DATE:__ _ _ _ _ _ PREOPERATIONAL STARTUP MANAGER SMP-8.0, Administration of Preoperational Test instructions, Appendix B . 12/07/2010
Transcript
WATTS BAR NUCLEAR PLANTUNIT 2 PREOPERATIONAL TEST
TITLE: Shutdown from Outside the Main Control Room
Instruction No:
Revision No:
2-PTI-068-13
0001
PREPARED BY:
REVIEWED BY:
R. D. Dobbs .R zPRINT NAME I SIGNATURE
Donald R. Heard (PcL'iSZýL
DATE: 414115
DATE: qti "qPRINT NAME / SIGNATURE
INSTRUCTION APPROVAL
JTG MEETING No: )- -Al 3 - DO
JTG CHAIRMAN: _-___/,I_4__j_ DATE:
DATE:APPROVED BY:PREO RAiIONAL STARiUP MANAGER
TEST RESULTS APPROVAL
JTG MEETING No:
JTG CHAIRMAN: DATE:
APPROVED BY: DATE:__ _ _ _ _ _
PREOPERATIONAL STARTUP MANAGER
SMP-8.0, Administration of Preoperational Test instructions, Appendix B . 12/07/2010
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Revision Log
Revision Affectedor Change Effective Page
Number Date Numbers Description of RevisionlChange
0000 2/21/13 All Initial Issue - Unit 2 PTI developed from Unit 1PTI-068-13, Revision 0.
0001 II 2,15, 19, Changed temperature in Steps 4.1[25] and.20, 23, 33, 6.0[8]A to reflect acceptance criteria start
34 temperature. Deleted references to specificsections of 2-TOP-068-01. Changed Step 4.1 [9]to read T-Mods instead of TAs and added "ifrequired" to Step 4.1 [9] to reflect changes to GL-1, Rev. 11. Changed Step 6.0[4]B & C toattachment instead of checklist. Changed Figure1 to reflect 450°F start of cooldown, and changedFigure 2 maximum temperature to 5500F.
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Figure 3: Pressure/Temperature Lim it Curves .................................................... 35
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1.0 INTRODUCTION
1.1 Test Objectives
A. Demonstrate that the Reactor Coolant System (RCS) can be cooled down in acontrolled manner from Hot Standby to Hot Shutdown conditions from outsidethe Main Control Room (MCR), without exceeding Technical Specification cooldown limits.
B. Demonstrate the ability to cool down the plant in a controlled manner from theAuxiliary Control Room (ACR) utilizing the Residual Heat Removal (RHR)System.
C. The plant can be maintained in a stable Hot Standby condition from outside themain control room for 30 minutes.
1.2 Scope
This Preoperational Test Instruction (PTI) administratively controls performance of2-TOP-068-01, which incorporates 2-AOI-27, Main Control Room Inaccessibility.
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2.0 REFERENCES
2.1 Performance References
A. SMP-7.0, Control Of Cleanness, Layup, And Flushing
B. SMP-9.0, Conduct of Test
C. 2-PTI-068-01, Hot Functional Test
D. 2-TOP 068-01, Rev 0, Main Control Room Inaccessibility
E. 2-SI-68-44, RCS Temperature/Pressure Limits and Pressurizer TemperatureLimits
2.2 Developmental References
A. Unit 2 Final Safety Analysis Report (FSAR) - Amendment 109, Table 14.2-1(Sheets 77, 78 and 79 of 89) Integrated Hot Functional Tests Test Summary
B. Drawings
1. Electrical
a. 2-45W751-13, Rev 0, Wiring Diagram 480V Reac Mov Bd 2A1-ASingle Line Sh-4
b. 2-45W751-14, Rev 0, Wiring Diagram 480V Reac Mov Bd 2B1-BSingle Line Sh-4
f. 45B2768-16, Rev 4, F Wiring Diagram 480V Reac Mov Bd 2B1-BCONN DIAG COMPT 16F
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2.2 Developmental References (continued)
2. Logic/Control
a. 2-47W610-3-3, Rev 4, Electrical Control Diagram Auxiliary FeedwaterSystem
b. 2-47W610-30-2, Rev 2, Electrical Control Diagram Ventilation System
c. 2-47W610-47-1, Rev 4, Electrical Control Diagram Turbo GeneratorCont Sys
d. 2-47W610-62-1, Rev 4, Electrical Control Diagram Chemical &Volume Control Sys
e. 2-47W610-63-1, Rev 8, Electrical Control Diagram Safety InjectionSystem
f. 1-47W610-67-1, Rev 29, Electrical Control Diagram ERCW System
g. 2-47W610-68-1, Rev 3, Electrical Control Diagram Reactor CoolantSystem
h. 2-47W610-68-4, Rev 3, Electrical Control Diagram Reactor CoolantSystem
i. 2-47W610-68-6, Rev 2, Electrical Control Diagram Reactor CoolantSystem
j. 1-47W610-70-1, Rev 28, Electrical Control Diagram ComponentCooling Water System
k. 2-47W610-72-1, Rev 5, Electrical Control Diagram Containment SpraySystem
I. 2-47W610-74-1, Rev 6, Electrical Control Diagram Residual HeatRemoval System
m. 2-47W610-77-3, Rev 1, Electrical Control Diagram Waste DisposalSystem
3. Instruments & Controls
a. 2-47W600-52, Rev 2, Electrical Instruments and Controls
b. 2-47W600-55, Rev 0, Electrical Instruments and Controls
c. 2-47W600-58, Rev 0, Electrical Instruments and Controls
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2.2 Developmental References (continued)
d. 47W600-57, Rev 10, Electrical Instruments & Controls
e. 47W600-60, Rev 8, Electrical Instruments & Controls
C. Documents
1. NRC Regulatory Guide 1.68.2, Initial Startup Test Program to DemonstrateRemote Shutdown Capability for Water-Cooled Nuclear Power Plants,Revision 1, July 1978.
2. WBN Unit 2, Technical Specifications, dated 2/28/2012
a. Section 3.4.3, RCS Pressure and Temperature (P/T) Limits
b. Section 5.2.2, Minimum Shift Crew Composition
3. NPG-SDD-WBN2-68-4001, Rev 2
4. NPG-SDD-WBN2-68-4001, Rev 2, Appendix B, PTLR
5. WBT-D-2776, Design Specification 67904, Rev 10
6. OPDP-1, Rev 23, Conduct of Operations
7. 2-AOI-27, Rev 0, Main Control Room Inaccessibility
8. 2-IMI-63.001, Rev 0, Low Steam line Pressure SI Block
9. 2-1MI-63.002, Rev 0, Low Pressurizer Pressure SI Block
10. 2-TI-57.002, Rev 0, Verification of Normal Position For Nor-Aux Switchesand Various Handswitches
11. 2-TSD-68-6, Rev 0, Test Scoping Document for RCS Cooldown From HotFunctional Testing
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3.0 PRECAUTIONS AND LIMITATIONS
A. Standard precautions shall be followed for working around energized electricalequipment in accordance with TVA Safety Manual Procedure 1021.
B. Steps may be repeated if all components cannot be tested in a step. However,if the test has been exited, prerequisite steps are required to be re-verified anda Chronological Test Log (CTL) entry made.
C. Discrepancies between component ID tags and the description in aprocedure/instruction do not require a Test Deficiency Notice (TDN) inaccordance with SMP-14.0, if the UNIDs match, exclusive of place-keepingzeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and thenoun description are sufficient to identify the component. If the componentlabel needs to be changed, a Tag Request Form (TR Card) should beprocessed in accordance with TI-12.14. Make an entry in the CTL and continuetesting.
D. All wires removed/lifted from a terminal shall be identified and taped or coveredwith an insulator to prevent personnel or equipment hazard and possiblespurious initiations. The wires should be grouped together and labeled with thework implementing document number that required them to be lifted if leftunattended.
E. All open problems are to be tracked by a corrective action document andentered on the appropriate system punchlist.
F. Problems identified during the test shall be annotated on the Chronological TestLog from SMP-9.0 including a description of the problem, the procedure stepwhen/where the problem was identified, corrective action steps taken to resolvethe problem, and the number of the corrective action document, if one wasrequired.
G. Observe all Radiation Protection (RP) requirements when working in or nearradiological areas.
H. Control room observers, who are additional Operations personnel separatefrom the shutdown crew, shall remain in the Main Control Room. As aminimum, an SRO designated to have the control room command function andand two ROs shall remain in the MCR as control room observers. AdditionalOperations personnel, who are not confined to the MCR, report to the controlroom observers and shall NOT assist the shutdown crew nor communicateinformation to them except in an emergency.
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3.0 PRECAUTIONS AND LIMITATIONS (continued)
Control room observers shall assume control of the plant should anyemergencies or unsafe conditions arise during this test that are beyond theresponsibilities or capabilities of the limited personnel or equipment involved incontrolling the plant from the Auxiliary Control Room.
J. Termination Criteria: The test shall be terminated and control of the unitreturned to the Main Control Room in a safe and orderly manner if any of thefollowing conditions occur:
1. SRO in the Main or Auxiliary Control Room or Test Director believes thereis a loss of control of any function needed to safely control the unit.
2. RCS pressure is less than 1900 psig prior to blocking PZR low pressureSafety Injection.
3. A condition occurs which has the potential to damage equipment or injurepersonnel.
4. Safety Injection occurs.
5. Steam Generator Narrow Range Level less than 0% or greater than 90%.
6. Pressurizer Level less than 17% or greater than 92%.
7. Loss of Offsite Power.
K. Control room observers shall perform non-safety related activities that wouldnot be required during an actual remote shutdown. These activities provideprotection for non-safety related equipment from damage during the transientand include the placement of equipment into standby status when no longerrequired. These activities shall be recorded in the chronological test log andreviewed at the completion of the test to assess their impact on the validity ofthe test performance.
L. The shutdown crew shall not receive communications from the MCR except inan emergency to protect personnel or equipment. Such communications mayinvalidate the objectives of this test and should be recorded in the chronologicaltest log.
M. Only that equipment for which credit would be taken in performing an actualremote plant shutdown shall be used for this test in order to satisfy theAcceptance Criteria.
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3.0 PRECAUTIONS AND LIMITATIONS (continued)
N. Reactor Coolant temperature shall not be reduced at a rate that exceedsTechnical Specification cooldown limits of 100OF in any one hour period.Cooldown should be performed at a rate of no more than 50°F/hour.
0. Pressurizer temperature shall not be reduced at a rate that exceeds 200OF inany one hour period. Pressurizer cooldown rate should not exceed 1 00°F inany one hour.
P. Reactor Coolant System temperature and pressure shall be determined at leastonce each 30 minutes to be within the Pressure/Temperature Curve for plantcooldown.
Q. Pressurizer Spray should NOT normally be initiated if the temperaturedifference between the Pressurizer and spray fluid is greater than 1 00°F,although higher differential temperatures are acceptable for a few cycles in thelife of the plant. Under no circumstances shall Pressurizer Spray be intiated ifthe temperature difference between the Pressurizer and the spray fluid is equalto or greater than 2601F. Any initations where the temperature difference isgreater than 260°F shall be reported to Engineering for evaluation andaccounted for in thermal cycle monitoring in the licensing basis. Auxiliary sprayflow from charging pump should be intiated slowly.
R. 2-PTI-068-01, Hot Functional Test (HFT), contains prerequisites, the lineups forplant support systems, instrumentation, and controls associated with HFT,which includes this PTI.
S. During the performance of 2-TOP-68-01, Operations personnel are required toinitial and date the steps as they are performed. In addition, the TestEngineer (TE) shall record in the Chronological Test Log the actual equipmentor equipment loop which was used to perform this test.
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4.0 PREREQUISITE ACTIONS
NOTE
Preliminary action steps may be performed in any order with Test Directors approval.
4.1 Preliminary Actions
[1] VERIFY the test/performance copy of this Preoperational TestInstruction (PTI) is the current revision including any changenotices and as needed, each test person assisting in this testhas the current revision including any change notices.
[2] OBTAIN copies of the applicable forms from the latest revisionof SMP-9.0, and
ATTACH to this PTI for use during the PTI performance.
[3] ENSURE changes to the references listed on Appendix A,Test Procedure/Instruction Reference Review, have beenreviewed, and determined not to adversely affect the testperformance.
[4] VERIFY current revisions and change paper for referenceddrawings has been reviewed and determined NOT toadversely affect the test performance, and
ATTACH documentation of current drawing revision numbersand change paper that were reviewed to the data package.
[5] EVALUATE punchlist items on Open Watts Bar IntegratedTask Equipment List (WITEL) and
ENSURE they will NOT adversely affect the test performance.
[6] ENSURE the minimum shutdown crew composition, asdefined by OPDP-1, Conduct of Operations, is available for theperformance of this test: Shift Manager (SRO) = 1,Unit Supervisor (SRO) = 1, Shift Technical Advisor (STA) =1,Reactor Operator (RO) = 2, and Assistant UnitOperator (AUO) = 5].
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4.1 Preliminary Actions (continued)
[7] ENSURE the minimum observation crew is available forperformance of this test: SRO designated to have the controlroom command function = 1, UOs for control board oversightand 2-SI-68-44 performance = 2.
[8] ENSURE required Component Testing has been completedprior to start of test.
[9] ENSURE outstanding Design Change Notices (DCN's),Engineering Document Construction Releases (EDCR's) orTemporary Modifications (T-Mods) do NOT adversely impacttesting, and
ATTACH documentation of DCN's, EDCR's and T-Mod's thatwere reviewed to the data package.
[10] ENSURE a review of outstanding Clearances has beencoordinated with Operations for impact to the testperformance, and
RECORD in Appendix B, Temporary Condition Log, ifrequired. _
[11] VERIFY System cleanness as required for the performance ofthis test has been completed in accordance with SMP-7.0.
[12] VERIFY plant instruments, listed on Appendix C, PermanentPlant Instrumentation Log, are placed in service and are withintheir calibration interval.
[13] VERIFY Measuring and Test Equipment (M&TE) required fortest performance has been (as required) filled, vented, place inservice and recorded on Measuring and Test Equipment Login SMP-9.0.
[14] VERIFY M&TE calibration due dates will support thecompletion of this test performance.
[15] VERIFY the Unit 2 Plant Computer System 261 is in service.
[16] VERIFY the Unit 2 Annunciator System 55 is in service.
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4.1 Preliminary Actions (continued)
[17] ENSURE System 55, Annunciator and Sequential EventsRecording System applicable Terminal Block (TBK)switches [in Panel 2-M-21] are ON, the applicable MasterSwitches are ON, and window software input(s) are ENABLEDfor the following Annunciator windows:
A. 2-XA-55-1 B Annunciator Panel in 2-M-1, Window 14-D,M-1 THRU M-6 MOTOR OVERLOAD
B. 2-XA-55-1B Annunciator Panel in 2-M-1, Window 14-E,M-1 THRU M-6 MOTOR TRIPOUT
C. 2-XA-55-5B Annunciator Panel in 2-M-5, Window 95-E,RCP BD 2A UV/CNTL PWR FAILURE/TRANSFER
D. 2-XA-55-5B Annunciator Panel in 2-M-5, Window 96-E,RCP BD 2B UV/CNTL PWR FAILURE/TRANSFER
E. 2-XA-55-5B Annunciator Panel in 2-M-5, Window 97-E,RCP BD 2C UV/CNTL PWR FAILURE/TRANSFER
F. 2-XA-55-5B Annunciator Panel in 2-M-5, Window 98-E,RCP BD 2D UV/CNTL PWR FAILURE/TRANSFER
G. 2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-A,RCP BD 2AI2BI2C/2D
H. 2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-B,ACR PNL 2-L-1IA
I. 2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-C,
ACR PNL 2-L-1 1 B
[18] VERIFY the following annunciator windows on 2-M-6 are clear:
A. Window 148-B, ACR PNL 2-L-11A
B. Window 148-C, ACR PNL 2-L-11B
[19] ENSURE components contained within the boundaries of thistest are under the jurisdictional control of PreoperationalStartup Engineering (PSE) and/or Plant Operations.
[20] ENSURE the test performance personnel have been notifiedand are available to support the test.
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4.1 Preliminary Actions (continued)
[21] PERFORM a pretest walk down on equipment to be tested toensure no conditions exist that will impact test performance.
[22] CONDUCT a pretest briefing with Test and Operationspersonnel in accordance with SMP-9.0.
[23] ENSURE communications are available between the followingdesignated locations and the Auxiliary Control Room using theBackup Control Center sound powered phone system:
A. 6.9 KV Shutdown Board Room (Train A)
B. 6.9 KV Shutdown Board Room (Train B)
C. 480V Shutdown Board Room (Unit 2)
D. Reactor MOV Board Room (Unit 2)
[24] ENSURE communications are available between the followingdesignated locations and the Auxiliary Control Room using theplant telephone system:
A. 6.9 KV Shutdown Board Room (Train A)
B. 6.9 KV Shutdown Board Room (Train B)
C. 480V Shutdown Board Room (Unit 2)
D. Reactor MOV Board Room (Unit 2)
E. 6.9 KV Reactor Coolant Pump (RCP) Boards
F. Main Control Room
G. Auxiliary Building, EL 692', East side, near TurbineDriven (TD) Auxiliary Feedwater (AFW) pump area.
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4.1 Preliminary Actions (continued)
[25] VERIFY HFT is being performed with the RCS at Hot StandbyConditions, and
RECORD RCS Temperature from 2-TI-68-1, LOOP 1 HLTEMP, on 2-M-5.
OF 450OF (425°F - 475OF)
[26] ESTABLISH additional qualified Operations crew as directedby the Shift Manager (SM) in the MCR who can take control ofthe plant should any emergencies or unsafe conditions ariseduring the performance of this test. (See Precautions AndLimitations 3.OH)
[27] VERIFY/CLOSE the following breakers at 480V ReactorMOV Board 2A1-A (2-MCC-213-A1):
A. SIS CL ACCUM 3 OUT ISOL, (2-FCV-63-80), Shunt TripBreaker, 2-BKR-63-80A, at Cubicle 17F2.
B. SIS CL ACCUM 1 OUT ISOL, (2-FCV-63-118), Shunt TripBreaker, 2-BKR-63-118A, at Cubicle 3F2.
[28] VERIFY/CLOSE the following breakers at 480V Reactor MOVBoard 2B1-B (2-MCC-213-B1):
A. SIS CL ACCUM 2 OUT ISOL, (2-FCV-63-98), Shunt TripBreaker, 2-BKR-63-98A, at Cubicle 3F2.
B. SIS CL ACCUM 4 OUT ISOL, (2-FCV-63-67), Shunt TripBreaker, 2-BKR-63-67A, at Cubicle 16F2.
[29] VERIFY 2-PTI-068-01 prerequisites are complete for the5570F plateau.
[30] VERIFY the Condensate Storage Tank B is at normaloperating level. (Greater than 200,000 gallons).
[31] ENSURE the System. and Equipment Status Control,NGDC-PI-8, Preoperational Configuration Log has beenevaluated.
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4.2 Special Tools, Measuring and Test Equipment, Parts, andSupplies
[1] VERIFY a M&TE Qualified Stopwatch, 0-60 minutes,±0.1 second accuracy is available.
[2] VERIFY four sets of Backup (Shutdown) Control Center soundpowered telephones are available.
[3] ESTABLISH a means of identifying the Main Control Roomobservation crew and Aux Control Room shutdown crew forthis test performance.
4.3 Field Preparations
None
4.4 Approvals and Notifications
[1] OBTAIN permission of the Preoperational Startup Manager tostart the test.
Preoperational Startup ManagerSignature
Date
[2] OBTAIN the Unit 2 (U2) Supervisor's (US/SRO) or ShiftManager's (SM) authorization.
U2 US/SRO/SM Signature Date
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5.0 ACCEPTANCE CRITERIA
A. Plant cooldown is performed from outside the MCR from Hot Standby [TAVG of450-F (425°F - 4750F)] to Hot Shutdown (TAVG between 200OF and 3501F)conditions, without exceeding the Technical Specification cooldown rate limit of100°F/Hr as plotted on Figure 1. (Steps 6.0[8]F and 6.0[13])
B. The RHR System is used to cool down the Reactor Coolant System at least500F, from outside the MCR, without exceeding the Technical Specificationcooldown rate limit of 1 00°F/Hr as plotted on Figure 1. (Steps 6.0[12]D and6.0[13])
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6.0 PERFORMANCE
NOTES
1) Any activities performed that are outside the scope of this test will be recorded in theChronological Test Log by the TE and evaluated for their impact on the validity of totaltest performance after this PTI is completed.
2) Step 6.0[1] ensures Tech Spec compliance and must not be communicated withshutdown crew unless limit is about to be exceeded.
[1] INITIATE applicable sections of 2-SI-68-44, RCSTemperature/Pressure Limits And Pressurizer TemperatureLimits, and
ACCESS ICS screens HC and HCRGRPH to monitor RCSand Pzr Temperature/Pressure Limits from ICS to ensure TechSpec criteria NOT violated.
MCR Observer Date
[2] ANNOUNCE over the public address system to notify plantpersonnel of the control transfer from the U-2 Main ControlRoom to the U-2 Auxiliary Control Room.
[3] ELECTRONICALLY MARK the following MCR chart recordersby depressing the keyboard button and entering 2-PTI-068-13denoting the start of process control from outside the MainControl Room:
A. Pressurizer (PZR) Pressure (2-PR-68-340) [2-M-5]
B. PZR Level (2-LR-68-339) [2-M-5]
C. HL & CL Temperature (Leg 1) (2-TR-68-1) [2-M-5]
D. HL & CL Temperature (Leg 2) (2-TR-68-24) [2-M-5]
E. HL & CL Temperature (Leg 3) (2-TR-68-43) [2-M-5]
F. HL & CL Temperature (Leg 4) (2-TR-68-65) [2-M-5]
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6.0 PERFORMANCE (continued)
G. HL Pressure (2-PR-68-63) [2-M-5]
H. Steam Generator (SG) Level % (2-LR-3-43) [2-M-4]
I. SG Level % (2-LR-3-98) [2-M-4]
J. SG I & 2 Pressure (2-PR-1-2) [2-M-4]
K. SG 3 & 4 Pressure (2-PR-1-23) [2-M-4]
[4] TRANSFER process control from the MCR to ACR inaccordance with 2-TOP-068-01.
A. RECORD time at which all Aux Control Room shutdownpersonnel are assembled in the Aux Control Room.
Time
B. RECORD time at which each 2-TOP-068-01 Attachmentis completed below:
Attachment Time Initial
#1
#2
#3
#4
C. RECORD time process control transfer from the MCR toACR is complete, the time the last attachment is completefrom step above.
Process Control in ACR Time
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6.0 PERFORMANCE (continued)
[5] ESTABLISH Hot Standby conditions in accordance with2-TOP-068-01, and
START stopwatch when stable Hot Standby conditions areattained.
M&TE
[6] MAINTAIN stable Hot Standby conditions from the ACR for aminimum of 30 minutes to ensure control of the unit inaccordance with 2-TOP-068-01 and,
RECORD total time Hot Standby maintained beforecommencing plant cooldown.
Elapsed Time minutes
CAUTION
RCS Cooldown rate should not exceed 50°F/hour.
[7] MONITOR appropriate Cooldown Pressure-TemperatureCurves of the appropriate Figure 3 Curves, and
PLOT every 30 minutes during all cooldown operations toensure acceptable region maintained.
[8] INITIATE plant cooldown from Hot Standby to Hot Shutdownconditions in accordance with 2-TOP-068-01, and
PERFORM the following:
A. RECORD RCS Loop temperatures [450°F (4250F - 4750F)]
UNID Temperature Panel Initial CV
2-T1-68-1C OF 2-L-10
2-TI-68-24C TF 2-L-10
2-TI-68-43C OF 2-L-1 0
2-TI-68-65C TF 2-L-10
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6.0 PERFORMANCE (continued)
B. RECORD RCS average temperature from Step 6.0[8]A byadding all four temperatures and dividing by four.
Average Temp. OF
Initials
Verified
Date
Date
C. START stopwatch, and
PLOT the following temperatures at time zero and at 15minute intervals:
" RCS temperature using 2-TI-68-1 C on Figure 1.
* PZR temperature as determined by PressurizerPressure indication for T-sat on Figure 2 using steamtables located in storage locker.
D. RECORD RCS loop temperatures when Hot Shutdowncondition is established. (less than 350OF)
UNID Temperature Panel Initial CV
2-T1-68-1C 0F 2-L-10
2-TI-68-24C OF 2-L-10
2-TI-68-43C OF 2-L-10
2-TI-68-65C OF 2-L-1 0
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6.0 PERFORMANCE (continued)
E. RECORD RCS average temperature from Step 6.0[8]D byadding all four temperatures and dividing by four.
Average Temp. OF
Initials Date
Verified Date
F. VERIFY all recorded temperatures in Step 6.0[8]D areless than 350 0F. (Acc Crit 5.OA)
CAUTION
RCS Cooldown rate should not exceed 50°F/hour.
NOTE
Plant conditions warrant that only one train of RHR is needed to perform cooldown duringHFT, and should be identified in the Chronological Test Log by the TE.
[9] ESTABLISH RCS cooldown utilizing RHR in accordance with2-TOP-068-01.
[10] WHEN RHR System is placed in service, THEN
RECORD RCS loop temperatures
UNID Temperature Panel Initial CV
2-Tl-68-IC OF 2-L-10
2-TI-68-24C OF 2-L-10
2-TI-68-43C OF 2-L-10
2-TI-68-65C TF 2-L-10
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6.0 PERFORMANCE (continued)
[11] RECORD RCS average temperature from Step 6.0110] byadding all four temperatures and dividing by four.
Average Temp. OF
Initials
Verified
[12] LOWER RCS average temperature to 2750 F (270°F - 2800 F)using RHR System from outside the MCR in accordance with2-TOP-068-01.
Date
Date
A. RECORD RCS loop temperatures:
UNID Temperature Panel Initial CV
2-T1-68-1C OF 2-L-10
2-TI-68-24C OF 2-L-10
2-TI-68-43C OF 2-L-10
2-TI-68-65C OF 2-L-10
B. RECORD RCS average temperature from Step 6.0[12]Aby adding all four temperatures and dividing by four.
Average Temp. OF
Initials Date
Verified Date
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Date
6.0 PERFORMANCE (continued)
C. DETERMINE temperature in Step 6.0[10] minustemperature in Step 6.0[12]A:
D. VERIFY all calculated temperatures recorded inStep 6.0[12]C are greater than or equal to 50 0F.(Acc Crit 5.0B)
[13] VERIFY cooldown rate plotted on Figure 1 does not exceedthe Technical Specification limit of 100°F/hour.(Acc Crit 5.0B)
[14] STOP the stopwatch, and
DISCONTINUE plotting RCS temperature.
[15] TRANSFER process control from the ACR to MOR inaccordance with 2-TOP-068-01.
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Date
6.0 PERFORMANCE (continued)
[16] ELECTRONICALLY MARK the following MCR recordersdenoting the end of process control from the Auxiliary ControlRoom:
A. PZR Pressure (2-PR-68-340) [2-M-5]
B. PZR Level (2-LR-68-339) [2-M-5]
C. HL & CL Temperature (Leg 1) (2-TR-68-1) [2-M-5]
D. HL & CL Temperature (Leg 2) (2-TR-68-24) [2-M-5]
E. HL & CL Temperature (Leg 3) (2-TR-68-43) [2-M-5]
F. HL & CL Temperature (Leg 4) (2-TR-68-65) [2-M-5]
G. HL Pressure (2-PR-68-63) [2-M-5]
H. SG Level % (2-LR-3-43) [2-M-4]
I. SG Level % (2-LR-3-98) [2-M-4]
J. SG 1 & 2 Pressure (2-PR-1-2) [2-M-4]
K. SG 3 & 4 Pressure (2-PR-1-23) [2-M-4]
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Date
7.0 POST PERFORMANCE ACTIVITY
[1] VERIFY the following:
A. Post-test calibration of the M&TE used to recordquantitative acceptance criteria has been satisfactorilyperformed.
B. The results recorded on Measuring and Test Equipment(M&TE) Log in SMP-9.0.
[2] VERIFY Post-test calibration of permanent plant instrumentsused to record quantitative acceptance criteria has beensatisfactorily performed and
RECORD the results on Appendix C, Permanent Plant
Instrumentation Log.
[3] ATTACH completed copy of 2-TOP-068-01 used for this test.
[4] NOTIFY Instrument Maintenance to make available a print outof recorder charts used for this test, and
ENSURE they are accurately marked (date, time, parameter,recorder number).
[5] NOTIFY the Unit 2 US/SRO of the test completion and systemalignment.
8.0 RECORDS
A. QA Records
Completed Test Package
B. Non-QA Records
None
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Appendix A
(Page 1 of 1)
Test Procedures/Instructions Reference Review
Date
NOTES
1) Additional copies of this table may be made as necessary.
2) Initial and date indicates review has been completed for impact.
PROCEDURE/ IMPACT INITIAL AND DATE.INSTRUCTION Yes/No (N/A for no change)
Unit 2 FSAR Table 14.2-1 Amendment 109(Sheets 77, 78 and 79 of 89)Integrated Hot Functional TestsTest Summary
NRC Regulatory Guide 1.68.2, Revision 1, July 1978Initial Startup Test Program toDemonstrate Remote ShutdownCapability for Water-CooledNuclear Power Plants.
WBN Unit 2, Technical Dated 2/28/2012Specifications,
RCS Pressure and Temperature Rev 0, March 2011Limits Report (PTLR)
2-TOP 068-01, Main Control Room Rev 0Inaccessibility
2-AOI-27, Main Control Room Rev 0Inaccessibility
2-IMI-63.001, Low Steam line Rev 0Pressure SI Block
2-IMI-63.002, Low Pressurizer Rev 0Pressure SI Block
2-TI-57.002, Verification of Normal Rev 0Position For Nor-Aux Switches andVarious Handswitches
2-TSD-68-6, Test Scoping Rev 0Document for RCS Cooldown FromHot Functional Testing
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Appendix B(Page 1 of 1)
Temporary Condition Log
Date
NOTE
These steps will be N/A'd if no temporary condition existed. Additional copies of this tablemay be made as necessary.
PERFORMED RETURNED TO NORMALITEM TEMPORARY CONDITION Step Performed By/Date Step Returned By/DateNo. DESCRIPTION No. CV By/Date No. CV By/Date
I /
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
__ _ _ _ _ _ _ _ _ _ _ _ /_
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Appendix C(Page 1 of 4)
Permanent Plant Instrumentation Log
Date
USED FORINSTRUMENT FILLED AND PLACED IN QUANTITATIVE
OR VENTED1 SERVICE1 ACC CRIT POST-TEST CALIBRATIONINSTRUMENT CAL DUE/ POST-TEST CAL ACCEPTABLE 2
LOOP # CAL DATE 3 INIT/DATE INIT/DATE YES NO DATE 2 INITIAL/DATE
2-TI-68-1 C
2-TI-68-24C
2-TI-68-43C
2-TI-68-65C
2-LI-68-325C
2-LI-68-326C
2-PI-68-336C
2-PI-68-337C
2-PI-1-1C
2-PI-1-8C
2-PI-1-19C
2-PI-1-26C
2-FI-3-142C
2-FI-3-163C
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Appendix C(Page 2 of 4)
Permanent Plant Instrumentation Log
Date
USED FORINSTRUMENT FILLED AND PLACED IN QUANTITATIVE
OR VENTED1 SERVICE1 ACC CRIT POST-TEST CALIBRATIONINSTRUMENT CAL DUEl POST-TEST CAL ACCEPTABLE 2
LOOP # CAL DATE 3 INITIDATE INITIDATE YES NO DATE2 INITIAUDATE
2-FI-3-155C
2-FI-3-147C
2-FI-3-170C
2-LI-3-164C
2-LI-3-156C
2-LI-3-148C
2-LI-3-171C
2-PI-62-92C
2-FI-62-93C
2-PI-62-81 C
2-TI-62-80C
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Appendix C(Page 3 of 4)
Permanent Plant Instrumentation Log
Date
USED FORINSTRUMENT FILLED AND PLACED IN QUANTITATIVE
OR VENTED1 SERVICE1 ACC CRIT POST-TEST CALIBRATIONINSTRUMENT CAL DUE/ POST-TEST CAL ACCEPTABLE 2
LOOP # CAL DATE 3 INITIDATE INITIDATE YES NO DATE 2 INITIAL/DATE
2-LI-62-129C
2-FI-63-173C
2-FI-63-91C
2-FI-67-92C
2-FI-67-61C
2-FI-67-62C
2-TI-74-38C
2-Ti-74-40C
2-FI-70-164C
2-LI-70-63C
2-LI-70-99C
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Appendix C(Page 4 of 4)
Permanent Plant Instrumentation Log
Date
USED FORINSTRUMENT FILLED AND PLACED IN QUANTITATIVE
OR VENTED1 SERVICE1 ACC CRIT POST-TEST CALIBRATIONINSTRUMENT CAL DUE/ POST-TEST CAL ACCEPTABLE 2
LOOP # CAL DATE 3 INITIDATE INIT/DATE YES NO DATE 2 INITIAL/DATE
2-PI-70-17C
2-FI-70-159C
2-FI-70-165C
4 4 + 4 4 4-
2
2
3
These items may be initialed and dated by personnel performing the task. Instrumentation not required to be filled and vented may be identified as Not Applicable. (N/A)
May be identified as Not Applicable (N/A) if instrument was not used to verify/record quantitative acceptance criteria data.
Enter the Cal Date for instruments/loops that do not have a "Cal Due Date". The Cal Date shall be within 12 months at the start of the test. Enter "CD" and the date forCal Due Date and "C" and the date for Cal Date.
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