ML13148A014

Preoperational Test, 2-PTI-068-13, Rev. 1, Shutdown from Outside the Main Control Room.

ML13148A014
Person / Time
Site:	Watts Bar
Issue date:	04/04/2013
From:	Dobbs R Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
2-PTI-068-13, Rev 1
Download: ML13148A014 (36)

Text

WATTS BAR NUCLEAR PLANT UNIT 2 PREOPERATIONAL TEST TITLE: Shutdown from Outside the Main Control Room Instruction No: 2-PTI-068-13 Revision No: 0001 PREPARED BY: R. D. Dobbs R. z DATE: 414115 PRINT NAME I SIGNATURE REVIEWED BY: Donald R. Heard (PcL'iSZýL DATE: qti "q PRINT NAME / SIGNATURE INSTRUCTION APPROVAL JTG MEETING No: )- -Al 3 - DO JTG CHAIRMAN: _-___/,I_4__j_ DATE:

APPROVED BY: DATE:

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

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 2 of 36 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of RevisionlChange 0000 2/21/13 All Initial Issue - Unit 2 PTI developed from Unit 1 PTI-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 specific sections of 2-TOP-068-01. Changed Step 4.1 [9]

to read T-Mods instead of TAs and added "if required" to Step 4.1 [9] to reflect changes to GL-1, Rev. 11. Changed Step 6.0[4]B & C to attachment instead of checklist. Changed Figure 1 to reflect 450°F start of cooldown, and changed Figure 2 maximum temperature to 550 0 F.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 3 of 36 Table of Contents

1.0 INTRODUCTION

...................................................................................................... 4 1.1 Test Objectives ........................................................................................................ 4 1.2 Sc o p e ............................................................................................................................ 4

2.0 REFERENCES

........................................................................................................ 5 2.1 Performance References ........................................................................................ 5 2.2 Developmental References ...................................................................................... 5 3.0 PRECAUTIONS AND LIMITATIONS ...................................................................... 8 4.0 PREREQUISITE ACTIONS .................................................................................... 11 4.1 Preliminary Actions ..................................................................................................... 11 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies ............ 16 4.3 Field Preparations .................................................................................................. 16 4.4 Approvals and Notifications ................................................................................... 16 5.0 ACCEPTANCE CRITERIA .................................................................................... 17 6.0 PERFORMANCE .................................................................................................... 18 7.0 POST PERFORMANCE ACTIVITY ....................................................................... 26 8.0 RECORDS .................................................................................................................. 26 Appendix A: Test Procedures/instructions Reference Review ............................... 27 Appendix B: Temporary Condition Log .................................................................... 28 Appendix C: Permanent Plant Instrumentation Log ............................................... 29 Figure 1: RCS Cooldown Rate Graph .................................................................. 33 Figure 2: Pressurizer Cooldown Rate Graph ...................................................... 34 Figure 3: Pressure/Temperature Lim it Curves .................................................... 35

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 4 of 36 Date

1.0 INTRODUCTION

1.1 Test Objectives A. Demonstrate that the Reactor Coolant System (RCS) can be cooled down in a controlled manner from Hot Standby to Hot Shutdown conditions from outside the Main Control Room (MCR), without exceeding Technical Specification cool down limits.

B. Demonstrate the ability to cool down the plant in a controlled manner from the Auxiliary Control Room (ACR) utilizing the Residual Heat Removal (RHR)

System.

C. The plant can be maintained in a stable Hot Standby condition from outside the main control room for 30 minutes.

1.2 Scope This Preoperational Test Instruction (PTI) administratively controls performance of 2-TOP-068-01, which incorporates 2-AOI-27, Main Control Room Inaccessibility.

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0001 Page 5 of 36 Date

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 Temperature Limits 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-A Single Line Sh-4

b. 2-45W751-14, Rev 0, Wiring Diagram 480V Reac Mov Bd 2B1-B Single Line Sh-4

c. 45B2766-3F, Rev C, Wiring Diagram 480V Reac Mov Bd 2A1-A CONN DIAG COMPT 3F

d. 45B2766-17F, Rev D, Wiring Diagram 480V Reac Mov Bd 2A1-A CONN DIAG COMPT 17F

e. 45B2768-3F, Rev D, Wiring Diagram 480V Reac Mov Bd 2B1-B CONN DIAG COMPT 3F

f. 45B2768-16, Rev 4, F Wiring Diagram 480V Reac Mov Bd 2B1-B CONN DIAG COMPT 16F

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 6of36 Date 2.2 Developmental References (continued)

2. Logic/Control

a. 2-47W610-3-3, Rev 4, Electrical Control Diagram Auxiliary Feedwater System

b. 2-47W610-30-2, Rev 2, Electrical Control Diagram Ventilation System

c. 2-47W610-47-1, Rev 4, Electrical Control Diagram Turbo Generator Cont 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 Injection System

f. 1-47W610-67-1, Rev 29, Electrical Control Diagram ERCW System

g. 2-47W610-68-1, Rev 3, Electrical Control Diagram Reactor Coolant System

h. 2-47W610-68-4, Rev 3, Electrical Control Diagram Reactor Coolant System

i. 2-47W610-68-6, Rev 2, Electrical Control Diagram Reactor Coolant System

j. 1-47W610-70-1, Rev 28, Electrical Control Diagram Component Cooling Water System

k. 2-47W610-72-1, Rev 5, Electrical Control Diagram Containment Spray System I. 2-47W610-74-1, Rev 6, Electrical Control Diagram Residual Heat Removal System

m. 2-47W610-77-3, Rev 1, Electrical Control Diagram Waste Disposal System

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

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 7 of 36 Date 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 Demonstrate Remote 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 Switches and Various Handswitches

11. 2-TSD-68-6, Rev 0, Test Scoping Document for RCS Cooldown From Hot Functional Testing

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 8 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS A. Standard precautions shall be followed for working around energized electrical equipment 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 and a Chronological Test Log (CTL) entry made.

C. Discrepancies between component ID tags and the description in a procedure/instruction do not require a Test Deficiency Notice (TDN) in accordance with SMP-14.0, if the UNIDs match, exclusive of place-keeping zeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and the noun description are sufficient to identify the component. If the component label needs to be changed, a Tag Request Form (TR Card) should be processed in accordance with TI-12.14. Make an entry in the CTL and continue testing.

D. All wires removed/lifted from a terminal shall be identified and taped or covered with an insulator to prevent personnel or equipment hazard and possible spurious initiations. The wires should be grouped together and labeled with the work implementing document number that required them to be lifted if left unattended.

E. All open problems are to be tracked by a corrective action document and entered on the appropriate system punchlist.

F. Problems identified during the test shall be annotated on the Chronological Test Log from SMP-9.0 including a description of the problem, the procedure step when/where the problem was identified, corrective action steps taken to resolve the problem, and the number of the corrective action document, if one was required.

G. Observe all Radiation Protection (RP) requirements when working in or near radiological areas.

H. Control room observers, who are additional Operations personnel separate from the shutdown crew, shall remain in the Main Control Room. As a minimum, an SRO designated to have the control room command function and and two ROs shall remain in the MCR as control room observers. Additional Operations personnel, who are not confined to the MCR, report to the control room observers and shall NOT assist the shutdown crew nor communicate information to them except in an emergency.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 9 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS (continued)

Control room observers shall assume control of the plant should any emergencies or unsafe conditions arise during this test that are beyond the responsibilities or capabilities of the limited personnel or equipment involved in controlling the plant from the Auxiliary Control Room.

J. Termination Criteria: The test shall be terminated and control of the unit returned to the Main Control Room in a safe and orderly manner if any of the following conditions occur:

1. SRO in the Main or Auxiliary Control Room or Test Director believes there is 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 pressure Safety Injection.

3. A condition occurs which has the potential to damage equipment or injure personnel.

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 would not be required during an actual remote shutdown. These activities provide protection for non-safety related equipment from damage during the transient and include the placement of equipment into standby status when no longer required. These activities shall be recorded in the chronological test log and reviewed at the completion of the test to assess their impact on the validity of the test performance.

L. The shutdown crew shall not receive communications from the MCR except in an emergency to protect personnel or equipment. Such communications may invalidate the objectives of this test and should be recorded in the chronological test log.

M. Only that equipment for which credit would be taken in performing an actual remote plant shutdown shall be used for this test in order to satisfy the Acceptance Criteria.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 10 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS (continued)

N. Reactor Coolant temperature shall not be reduced at a rate that exceeds Technical 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 in any one hour period. Pressurizer cooldown rate should not exceed 100°F in any one hour.

P. Reactor Coolant System temperature and pressure shall be determined at least once each 30 minutes to be within the Pressure/Temperature Curve for plant cooldown.

Q. Pressurizer Spray should NOT normally be initiated if the temperature difference between the Pressurizer and spray fluid is greater than 100°F, although higher differential temperatures are acceptable for a few cycles in the life of the plant. Under no circumstances shall Pressurizer Spray be intiated if the temperature difference between the Pressurizer and the spray fluid is equal to or greater than 2601F. Any initations where the temperature difference is greater than 260°F shall be reported to Engineering for evaluation and accounted for in thermal cycle monitoring in the licensing basis. Auxiliary spray flow from charging pump should be intiated slowly.

R. 2-PTI-068-01, Hot Functional Test (HFT), contains prerequisites, the lineups for plant 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 to initial and date the steps as they are performed. In addition, the Test Engineer (TE) shall record in the Chronological Test Log the actual equipment or equipment loop which was used to perform this test.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 11 of 36 Date 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 Test Instruction (PTI) is the current revision including any change notices and as needed, each test person assisting in this test has the current revision including any change notices.

[2] OBTAIN copies of the applicable forms from the latest revision of 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 been reviewed, and determined not to adversely affect the test performance.

[4] VERIFY current revisions and change paper for referenced drawings has been reviewed and determined NOT to adversely affect the test performance, and ATTACH documentation of current drawing revision numbers and change paper that were reviewed to the data package.

[5] EVALUATE punchlist items on Open Watts Bar Integrated Task Equipment List (WITEL) and ENSURE they will NOT adversely affect the test performance.

[6] ENSURE the minimum shutdown crew composition, as defined by OPDP-1, Conduct of Operations, is available for the performance of this test: Shift Manager (SRO) = 1, Unit Supervisor (SRO) = 1, Shift Technical Advisor (STA) =1, Reactor Operator (RO) = 2, and Assistant Unit Operator (AUO) = 5].

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 12 of 36 Date 4.1 Preliminary Actions (continued)

[7] ENSURE the minimum observation crew is available for performance of this test: SRO designated to have the control room command function = 1, UOs for control board oversight and 2-SI-68-44 performance = 2.

[8] ENSURE required Component Testing has been completed prior to start of test.

[9] ENSURE outstanding Design Change Notices (DCN's),

Engineering Document Construction Releases (EDCR's) or Temporary Modifications (T-Mods) do NOT adversely impact testing, and ATTACH documentation of DCN's, EDCR's and T-Mod's that were reviewed to the data package.

[10] ENSURE a review of outstanding Clearances has been coordinated with Operations for impact to the test performance, and RECORD in Appendix B, Temporary Condition Log, if required. _

[11] VERIFY System cleanness as required for the performance of this test has been completed in accordance with SMP-7.0.

[12] VERIFY plant instruments, listed on Appendix C, Permanent Plant Instrumentation Log, are placed in service and are within their calibration interval.

[13] VERIFY Measuring and Test Equipment (M&TE) required for test performance has been (as required) filled, vented, place in service and recorded on Measuring and Test Equipment Log in SMP-9.0.

[14] VERIFY M&TE calibration due dates will support the completion 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.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 13 of 36 Date 4.1 Preliminary Actions (continued)

[17] ENSURE System 55, Annunciator and Sequential Events Recording System applicable Terminal Block (TBK) switches [in Panel 2-M-21] are ON, the applicable Master Switches are ON, and window software input(s) are ENABLED for 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 1B

[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 this test are under the jurisdictional control of Preoperational Startup Engineering (PSE) and/or Plant Operations.

[20] ENSURE the test performance personnel have been notified and are available to support the test.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 14 of 36 Date 4.1 Preliminary Actions (continued)

[21] PERFORM a pretest walk down on equipment to be tested to ensure no conditions exist that will impact test performance.

[22] CONDUCT a pretest briefing with Test and Operations personnel in accordance with SMP-9.0.

[23] ENSURE communications are available between the following designated locations and the Auxiliary Control Room using the Backup 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 following designated locations and the Auxiliary Control Room using the plant 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 Turbine Driven (TD) Auxiliary Feedwater (AFW) pump area.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 15 of 36 Date 4.1 Preliminary Actions (continued)

[25] VERIFY HFT is being performed with the RCS at Hot Standby Conditions, and RECORD RCS Temperature from 2-TI-68-1, LOOP 1 HL TEMP, on 2-M-5.

OF 450OF (425°F - 475OF)

[26] ESTABLISH additional qualified Operations crew as directed by the Shift Manager (SM) in the MCR who can take control of the plant should any emergencies or unsafe conditions arise during the performance of this test. (See Precautions And Limitations 3.OH)

[27] VERIFY/CLOSE the following breakers at 480V Reactor MOV Board 2A1-A (2-MCC-213-A1):

A. SIS CL ACCUM 3 OUT ISOL, (2-FCV-63-80), Shunt Trip Breaker, 2-BKR-63-80A, at Cubicle 17F2.

B. SIS CL ACCUM 1 OUT ISOL, (2-FCV-63-118), Shunt Trip Breaker, 2-BKR-63-118A, at Cubicle 3F2.

[28] VERIFY/CLOSE the following breakers at 480V Reactor MOV Board 2B1-B (2-MCC-213-B1):

A. SIS CL ACCUM 2 OUT ISOL, (2-FCV-63-98), Shunt Trip Breaker, 2-BKR-63-98A, at Cubicle 3F2.

B. SIS CL ACCUM 4 OUT ISOL, (2-FCV-63-67), Shunt Trip Breaker, 2-BKR-63-67A, at Cubicle 16F2.

[29] VERIFY 2-PTI-068-01 prerequisites are complete for the 5570F plateau.

[30] VERIFY the Condensate Storage Tank B is at normal operating level. (Greater than 200,000 gallons).

[31] ENSURE the System. and Equipment Status Control, NGDC-PI-8, Preoperational Configuration Log has been evaluated.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 16 of 36 Date 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies

[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 sound powered telephones are available.

[3] ESTABLISH a means of identifying the Main Control Room observation crew and Aux Control Room shutdown crew for this test performance.

4.3 Field Preparations None 4.4 Approvals and Notifications

[1] OBTAIN permission of the Preoperational Startup Manager to start the test.

Preoperational Startup Manager Date Signature

[2] OBTAIN the Unit 2 (U2) Supervisor's (US/SRO) or Shift Manager's (SM) authorization.

U2 US/SRO/SM Signature Date

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 17 of 36 Date 5.0 ACCEPTANCE CRITERIA A. Plant cooldown is performed from outside the MCR from Hot Standby [TAVG of 450-F (425°F - 4750 F)] to Hot Shutdown (TAVG between 200OF and 3501F) conditions, without exceeding the Technical Specification cooldown rate limit of 100°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 least 50 0 F, from outside the MCR, without exceeding the Technical Specification cooldown rate limit of 100°F/Hr as plotted on Figure 1. (Steps 6.0[12]D and 6.0[13])

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 18 of 36 Date 6.0 PERFORMANCE NOTES

1) Any activities performed that are outside the scope of this test will be recorded in the Chronological Test Log by the TE and evaluated for their impact on the validity of total test performance after this PTI is completed.

2) Step 6.0[1] ensures Tech Spec compliance and must not be communicated with shutdown crew unless limit is about to be exceeded.

[1] INITIATE applicable sections of 2-SI-68-44, RCS Temperature/Pressure Limits And Pressurizer Temperature Limits, and ACCESS ICS screens HC and HCRGRPH to monitor RCS and Pzr Temperature/Pressure Limits from ICS to ensure Tech Spec criteria NOT violated.

MCR Observer Date

[2] ANNOUNCE over the public address system to notify plant personnel of the control transfer from the U-2 Main Control Room to the U-2 Auxiliary Control Room.

[3] ELECTRONICALLY MARK the following MCR chart recorders by depressing the keyboard button and entering 2-PTI-068-13 denoting the start of process control from outside the Main Control 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]

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 19 of 36 Date 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 in accordance with 2-TOP-068-01.

A. RECORD time at which all Aux Control Room shutdown personnel are assembled in the Aux Control Room.

Time B. RECORD time at which each 2-TOP-068-01 Attachment is completed below:

Attachment Time Initial

1. 1

1. 2

1. 3

1. 4 C. RECORD time process control transfer from the MCR to ACR is complete, the time the last attachment is complete from step above.

Process Control in ACR Time

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 20 of 36 Date 6.0 PERFORMANCE (continued)

[5] ESTABLISH Hot Standby conditions in accordance with 2-TOP-068-01, and START stopwatch when stable Hot Standby conditions are attained.

M&TE

[6] MAINTAIN stable Hot Standby conditions from the ACR for a minimum of 30 minutes to ensure control of the unit in accordance with 2-TOP-068-01 and, RECORD total time Hot Standby maintained before commencing plant cooldown.

Elapsed Time minutes CAUTION RCS Cooldown rate should not exceed 50°F/hour.

[7] MONITOR appropriate Cooldown Pressure-Temperature Curves of the appropriate Figure 3 Curves, and PLOT every 30 minutes during all cooldown operations to ensure acceptable region maintained.

[8] INITIATE plant cooldown from Hot Standby to Hot Shutdown conditions in accordance with 2-TOP-068-01, and PERFORM the following:

A. RECORD RCS Loop temperatures [450°F (4250 F - 4750 F)]

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

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 21 of 36 Date 6.0 PERFORMANCE (continued)

B. RECORD RCS average temperature from Step 6.0[8]A by adding all four temperatures and dividing by four.

Average Temp. OF Initials Date Verified Date C. START stopwatch, and PLOT the following temperatures at time zero and at 15 minute intervals:

" RCS temperature using 2-TI-68-1 C on Figure 1.

• PZR temperature as determined by Pressurizer Pressure indication for T-sat on Figure 2 using steam tables located in storage locker.

D. RECORD RCS loop temperatures when Hot Shutdown condition is established. (less than 350OF)

UNID Temperature Panel Initial CV 0

2-T1-68-1C F 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

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 22 of 36 Date 6.0 PERFORMANCE (continued)

E. RECORD RCS average temperature from Step 6.0[8]D by adding 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 are less than 350 0 F. (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 during HFT, and should be identified in the Chronological Test Log by the TE.

[9] ESTABLISH RCS cooldown utilizing RHR in accordance with 2-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

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 23 of 36 Date 6.0 PERFORMANCE (continued)

[11] RECORD RCS average temperature from Step 6.0110] by adding all four temperatures and dividing by four.

Average Temp. OF Initials Date Verified Date

[12] LOWER RCS average temperature to 275 0 F (270°F - 280 0 F) using RHR System from outside the MCR in accordance with 2-TOP-068-01.

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]A by adding all four temperatures and dividing by four.

Average Temp. OF Initials Date Verified Date

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 24 of 36 Date 6.0 PERFORMANCE (continued)

C. DETERMINE temperature in Step 6.0[10] minus temperature in Step 6.0[12]A:

Temperatures UNID (Step 6.0110] - Step 6.0[12]) INITIAL CV 2-T1 1C OF 2-TI-68-24C OF 2-TI-68-43C °F 2-TI-68-65C OF D. VERIFY all calculated temperatures recorded in Step 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 exceed the 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 in accordance with 2-TOP-068-01.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 25 of 36 Date 6.0 PERFORMANCE (continued)

[16] ELECTRONICALLY MARK the following MCR recorders denoting the end of process control from the Auxiliary Control Room:

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]

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 26 of 36 Date 7.0 POST PERFORMANCE ACTIVITY

[1] VERIFY the following:

A. Post-test calibration of the M&TE used to record quantitative acceptance criteria has been satisfactorily performed.

B. The results recorded on Measuring and Test Equipment (M&TE) Log in SMP-9.0.

[2] VERIFY Post-test calibration of permanent plant instruments used to record quantitative acceptance criteria has been satisfactorily 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 out of 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 system alignment.

8.0 RECORDS A. QA Records Completed Test Package B. Non-QA Records None

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 27 of 36 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 Tests Test Summary NRC Regulatory Guide 1.68.2, Revision 1, July 1978 Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants.

WBN Unit 2, Technical Dated 2/28/2012 Specifications, RCS Pressure and Temperature Rev 0, March 2011 Limits Report (PTLR) 2-TOP 068-01, Main Control Room Rev 0 Inaccessibility 2-AOI-27, Main Control Room Rev 0 Inaccessibility 2-IMI-63.001, Low Steam line Rev 0 Pressure SI Block 2-IMI-63.002, Low Pressurizer Rev 0 Pressure SI Block 2-TI-57.002, Verification of Normal Rev 0 Position For Nor-Aux Switches and Various Handswitches 2-TSD-68-6, Test Scoping Rev 0 Document for RCS Cooldown From Hot Functional Testing

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 28 of 36 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 table may be made as necessary.

PERFORMED RETURNED TO NORMAL ITEM TEMPORARY CONDITION Step Performed By/Date Step Returned By/Date No. 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

_ _ __ __ _ _ _ _ _ /_

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 29 of 36 Appendix C (Page 1 of 4)

Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT FILLED AND PLACED IN QUANTITATIVE OR VENTED1 SERVICE 1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT 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

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 30 of 36 Appendix C (Page 2 of 4)

Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT FILLED AND PLACED IN QUANTITATIVE OR VENTED 1 SERVICE 1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUEl POST-TEST CAL ACCEPTABLE 2 LOOP # CAL DATE 3 INITIDATE INITIDATE YES NO DATE 2 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

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 31 of 36 Appendix C (Page 3 of 4)

Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT FILLED AND PLACED IN QUANTITATIVE OR VENTED1 SERVICE 1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT 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

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 32 of 36 Appendix C (Page 4 of 4)

Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT FILLED AND PLACED IN QUANTITATIVE OR VENTED 1 SERVICE 1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT 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 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) 2 May be identified as Not Applicable (N/A) if instrument was not used to verify/record quantitative acceptance criteria data.

3 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 for Cal Due Date and "C" and the date for Cal Date.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 33 of 36 Figure 1 (Page 1 of 1)

RCS Cooldown Rate Graph Date 0 30 60 90 120 150 180 210 240 270 300 330 360 390 420 450 480 Time (minutes) 1 00F.,hr . . . . .50Fllhr Plotted By: Vertical Axes in OF

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 34 of 36 Figure 2 (Page 1 of 1)

Pressurizer Cooldown Rate Graph Date 0 30 60 90 120 150 180 210 240 270 300 330 360 390 420 450 480 Time (minutes) i rUhr

/nr Plotted By: Vertical Axes in 'F

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 35 of 36 Figure 3 (Page 1 of 2)

Pressure/Temperature Limit Curves Date RCS COOLDOWN WITH ONE RCP RUNNING

/,JUU 2400 2300 2200 2100 2000 1900 1800--

1700-- U NACCEPTABLEH 1600-C, 1500 a- 1400 cn 1300-U)

'Li 1200/

0. 1100-0)

U 1000.

900 800 7nn __

600 J

/#.,-- - UUI 500 FIH~r 1ACCEPTABLEF I I 400 300 160F/HR 200 - +

100 tEoF/H R 0

0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 RCS TEMP (F)

Plotted By:_____ _____

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0001 Page 36 of 36 Figure 3 (Page 2 of 2)

Pressure/Temperature Limit Curves Date RCS COOLDOWN WITH TWO RCPs RUNNING 2500 2400 2300 2200 2100 m

2000 1900 1800 1700- UNACCEPTABLE]""//

1600

_21500 1400 1300

"' 1200 O. 1100 C 1000 900 800 700 600 500

- IIIIACCEPTABLEý 400 300-200 100- 7SF/HR _______~___1 OOF/HRT______

0 0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 RCS TEMP (T)

Plotted By:

Lý