Text

Initial Exam - 10/2002 - Draft Operating Examination
	ML030510245
Person / Time
Site:	Diablo Canyon
Issue date:	11/20/2002
From:	Gody A; Operations Branch IV
To:	Rueger G; Pacific Gas & Electric Co
References
	50-275/02-301, 50-323/02-301, ES-D-2, NUREG-1021, Rev 8, Suppl 1 50-275/02-301, 50-323/02-301
	Download: ML030510245 (279)
	v • d • e

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____1_____ Event No.: ____1____ Page __1__ of __7__

Event

Description:

Swap Condensate Booster Pumps Sets Time Position Applicant's Actions or Behavior BOP Refers to OP C7A:I.

Selects and start a standby booster pump set Secures other booster pump set and place in standby RO Performs peer check of pump start and securing SFM Performs tailboard of booster pump start Directs BOP to start the booster pump 1 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____1_____ Event No.: ____2____ Page __2__ of __7__

Event Description : Power Reduction for Heater 2 Drip Pump Oil Leak Time Position Applicant's Actions or Behavior BOP Coordinate with RO to perform the power decrease as directed by SFM Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Coordinate with BOP to perform the power decrease as directed by SFM Prepare the makeup system for boration and borate as required Prepare DEHC and start load reduction as directed by SFM Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Performs tailboard on power reduction and reactivity control Directs and monitors power reduction and boration 2 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: _________ Event No.: ____3____ Page __3__ of __7__

Event Description : Turbine Control Fail to Manual Time Position Applicant's Actions or Behavior BOP Assists in stabilizing plant on discovery of turbine control failure Assits in ramping turbine load to 80% manually Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Notices Tave/Tref mismatch and informs SFM Identifies Turbine Controls in Manual Stops boration initially Continues boration when directed to Assists in ramping turbine load to 80% manually Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Directs boration to stop and to stabilize the plant Determines need to continue power reduction to 80%

Calls for maintenance support Directs control room response 3 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___1____ Scenario No.: _____1_____ Event No.: ____4____ Page __4__ of __7__

Event

Description:

VCT Level Channel 112 Failure High Time Position Applicant's Actions or Behavior BOP Report alarm PK04-24, VCT Press, Lvl, Temp alarm Identifies VCT level high Redirects letdown to VCT after failed instrument identified as cause RO Assists in identifying VCT alarm as failed instrument Stops ramp if directed Continues ramp if directed SFM Acknowledges report on PK04-24 Directs crew to stabilize the plant Follows guidance of AR PK04-24 and OP AP-19 Directs and monitors control room response 4 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___1__ Scenario No.: ____1_____ Event No.: ____5 ___ Page __5__ of __7__

Event

Description:

MFW Pump Master Controller Failure (requiring manual control)

Time Position Applicant's Actions or Behavior BOP Acknowledges SG level alarms on PK09 and report to SFM Closely monitor primary and secondary parameters for proper response Control Turbine as directed RO Acknowledges SG level alarms Identifies MFW pump controller failing low Takes manual control or MFW pump master controller Recognize Master Controller failure and take Manual of MFW pump 1-1 and 1-2 controllers Restore MFW pump dp and SG level in manual control Closely monitor primary and secondary parameters for proper response Recommend Reactor trip if unable to control / maintain stable plant conditions SFM Acknowledges BOPCO on SG alarms Directs RO to take manual control of MFW pump master controller and stabilize the plant Directs BOP to control turbine load Request Asset Team assistance Order Reactor Trip if SG level cannot be maintained 5 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____1_____ Event No.: ____6 ___ Page __6__ of __7__

Event

Description:

ATWS Time Position Applicant's Actions or Behavior BOP Recognize and report Reactor Trip required Perform Immediate Actions of EOP E-0 Recognize failure of reactor to trip, ATWS and report status to SFM Open 13D and 13E ** Critical Task**

RO Recognize and report Reactor Trip required Perform Immediate Actions of EOP E-0 Recognize and report failure of reactor to trip, ATWS Perform manual reactor trip ** Critical Task**

Inform SFM when reactor trips SFM Recognize Reactor Trip required but did not occur Directs RO to manually trip the reactor ** Critical Task**

Directs BOPCO to open 13D and 13E ** Critical Task**

Enters EOP E-0 and directs control room response 6 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____1_____ Event No.: ____7 ___ Page __7__ of __7__

Event

Description:

SBLOCA with Loss of All Feedwater Time Position Applicants Actions or Behavior BOP Recognize and report LOCA Recognize and report NO AFW pumps and NO AFW flow Perform steps of E-0 and FR-H.1 as directed Establish forward flow from secondary system and depressurize 2 SGs ** Critical**

RO Recognize and report LOCA Perform steps of E-0 and FR-H.1 as directed Establish Bleed and Feed if conditions met ** Critical**

SFM Acknowledge LOCA report Directs EOP E-0 response for LOCA Transitions to FR-H.1 on exit from E-0 ** Critical**

Directs control room response per FR-H.1 Directs RO in Bleed and Feed requirement per Foldout Page ** Critical**

Directs continued attempts by BOPCO to establish feed during Bleed and Feed ** Critical**

NOTE: Terminate scenario when forward feed established to SGs.

7 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____1_____ Event No.: ____1____ Page __1__ of __6__

Event

Description:

Increase Accumulator 1-1 Pressure Time Position Applicant's Actions or Behavior BOP Refers to OP B-3B:I Pressurizes Accumulator 1-1 to within ITS limits RO Performs peer check of valve manipulations SFM Performs tailboard of accumulator pressurization Directs BOP to pressurize Accumulator 1-1 1 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____1_____ Event No.: ____2____ Page __2__ of __6__

Event Description : Power Reduction to 850 MW from EPOS Request Time Position Applicant's Actions or Behavior BOP Coordinate with RO to perform the power decrease as directed by SFM Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Coordinate with BOP to perform the power decrease as directed by SFM Prepare the makeup system for boration and borate as required Prepare DEHC and start load reduction as directed by SFM Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Performs tailboard on power reduction and reactivity control Directs and monitors power reduction and boration 2 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____1_____ Event No.: ____3____ Page __3__ of __6__

Event Description : Failure of 43/MU to Auto Borate Time Position Applicant's Actions or Behavior BOP Acknowledges RMUW Flow mismatch alarm Stabilizes plant on discovery of 43/MU failure Operates FCV-110 A/B and FCV-111 A/B as directed to manually borate ** Critical**

Assists in ramping turbine as needed Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Acknowledges RMUW Flow mismatch alarm Stops ramp Sets up and borates in Manual per OP B-1A:VII ** Critical**

Commences ramping turbine load to 850 MW Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Acknowledges RMUW alarm and enters PK05-11 Directs ramp to stop Enters AP-19 to troubleshoot problem with 43/MU Calls Asset Team for support Directs RO to manually borate per OP B-1A:VII and provides oversight ** Critical**

Directs ramp to recommence Directs control room response 3 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___2____ Scenario No.: _____1_____ Event No.: ____4____ Page __4__ of __6__

Event

Description:

Turbine Impulse Channel PT-505 Failure Low Time Position Applicant's Actions or Behavior BOP Report alarms PK08-11 (C-8) and PK12-14 (AMSAC)

Identifies PT-505 failure Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Reports rod motion Determines rod motion not required and takes rods to manual ** Critical**

Stops ramp if directed Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Acknowledges report on alarms Directs RO to take rods to manual ** Critical**

Directs crew to stabilize the plant Follows guidance of OP AP-5 and ITS 3.3.1 Requests Asset Team assistance Directs and monitors control room response 4 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___2__ Scenario No.: ____1_____ Event No.: ____5 ___ Page __5__ of __6__

Event

Description:

PZR Spray Controller Failure (requiring manual control)

Time Position Applicant's Actions or Behavior BOP Acknowledges PZR Pressure alarms on PK05-17 and report to SFM Closely monitor primary and secondary parameters for proper response RO Acknowledges PZR Pressure alarms on PK05-17 and report to SFM Identifies PZR spray controller failing and takes Manual control of spray valves ** Critical**

Closely monitor primary and secondary parameters for proper response SFM Acknowledges BOPCO and RO on PZR pressure alarms Directs RO to take manual control of PZR spray controller and stabilize the plant ** Critical**

Follows guidance of PK05-17 and AP-13.

Verifies ITS limits not exceeded Requests Asset Team assistance 5 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____1_____ Event No.: ____6 & 7 ___ Page __6__ of __6__

Event

Description:

PZR Steam Space LOCA with failure of SI Time Position Applicant's Actions or Behavior BOP Acknowledges PZR Pressure alarms on PK05-17 and report to SFM Closely monitor primary and secondary parameters for leak detection Perform Immediate Actions of EOP E-0 Recognize and report failure of Safety Injection Signal Perform manual SI at VB-1 Align SI per Attachment E of E-0 Perform actions of E-0 and E-1 as directed RO Acknowledges PZR Pressure alarms on PK05-17 and report to SFM Determine increasing leak rate Diagnose leak from steam space Trip Reactor prior to Low Pressure setpoint ** Critical Task**

Perform Immediate Actions of EOP E-0 Perform manual SI from CC1 ** Critical Task**

Perform actions of E-0 and E-1 as directed SFM Acknowledge PZR pressure alarm reports from RO/BOPCO Follow guidance of PK05-17 and AP-1 for leak Directs RO to manually trip the reactor ** Critical Task**

Directs RO and BOPCO to manually initiate SI ** Critical Task**

Enters EOP E-0 and directs control room response Transitions to E-1 and directs control room response Transitions to E-1.2 6 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 7 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____2_____ Event No.: ____1____ Page __1__ of __7__

Event

Description:

Swap CCW Heat Exchangers Time Position Applicant's Actions or Behavior BOP Refers to OP F-2:II and OP E-5:IV Starts ASW Train 1-2, secures ASW Train 1-1 Verifies proper system response of CCW Hx RO Performs peer check of pump start and securing SFM Performs tailboard of pump train swap Directs BOP to start the ASW pump train 1-2 and secure 1-1 1 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____2_____ Event No.: ____2____ Page __2__ of __7__

Event Description : Power Reduction for Fire at Midway Time Position Applicant's Actions or Behavior BOP Coordinate with RO to perform the power decrease as directed by SFM Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Coordinate with BOP to perform the power decrease as directed by SFM Prepare the makeup system for boration and borate as required Prepare DEHC and start load reduction as directed by SFM Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Performs tailboard on power reduction and reactivity control Directs and monitors power reduction and boration 2 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____2_____ Event No.: ____3____ Page __3__ of __7__

Event Description : RCS Tc (TE-441) Failed High Time Position Applicant's Actions or Behavior BOP Diagnose and report Loop 4 T-cold channel failure Assist in turbine controls as directed RO Recognize and report rod motion concurrent with T-cold channel failure Determine and report rod motion not required Place rod control in manual ** Critical Task Stop ramp as directed Deselect Loop 4 for T-avg and Delta-T control Return T-avg to T-ref (3 step pull and wait) and then place rod control back in auto Recommence ramp as directed SFM Direct plant stabilization until cause diagnosed and analyzed for impact Go to OP AP-5 and direct operator recovery actions Direct RO on rod control and failed channel input action ** Critical action Consult Tech Spec 3.3.1 for 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months action to trip bistables for OPT and OTT trips Direct turbine ramp to recommence 3 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___1____ Scenario No.: _____2_____ Event No.: ____4____ Page __4__ of __7__

Event

Description:

Loss of non-vital 120 VAC (PY-15)

Time Position Applicant's Actions or Behavior BOP Assists in diagnosing multiple alarms for PY-15 failure Takes manual control and stabilizes plant as needed Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Assists in diagnosing multiple alarms for PY-15 failure Takes manual control and stabilizes plant as needed Ensures rods stepping in to match Tave to Tref Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Diagnose PY-15 failure Directs crew to stabilize the plant and stop ramp Directs RO to maintain Tave to Tref with rods Follows guidance of OP AP - 4 Directs and monitors control room response Request Asset Team to energize PY-15 on backup supply 4 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___1__ Scenario No.: ____2_____ Event No.: ____5 ___ Page __5__ of __7__

Event

Description:

Turbine Governor Valve Failure (FCV-142)

Time Position Applicant's Actions or Behavior BOP Acknowledges various alarms and diagnoses load rejection Closely monitor primary and secondary parameters for proper response RO Acknowledges various alarms and diagnoses load rejection Closely monitor primary and secondary parameters for proper response SFM Acknowledges RO and BOPCO on alarms and diagnosis of load rejection Enters OP AP-25 and directs control room response Request Asset Team assistance 5 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____2_____ Event No.: ____6, 7 & 8 ___ Page __6__ of __7__

Event

Description:

Seismic induced SG 1-1 Feed Line Break with Failure of Train A SI signal Time Position Applicant's Actions or Behavior BOP Recognize and report Reactor Trip and Safety Injection Diagnose Feedline Break Perform Immediate Actions of EOP E-0 Recognize and report failure of Train A SI signal Attempt to Initiate SI Train A Align Train A SI components per Attachment E ** Critical Task**

Isolate SG 1-1 when directed ** Critical Task**

Throttle AFW to minimize cooldown as directed ** Critical Task**

Perform steps of E-0 and E-2 as directed RO Recognize and report Reactor Trip and Safety Injection Diagnose Feedline Break Perform Immediate Actions of EOP E-0 Recognize and report failure of Train A SI signal Attempt to Initiate SI Train A Perform steps of E-0 and E-2 as directed SFM Acknowledge Reactor Trip and SI Diagnose Feedline Break Direct control room response per E-0 Direct BOPCO and RO to manually initiate SI to align Train A Direct BOPCO to perform Attachment E to manually align Train A SI ** Critical Task**

Transition to E-2 when appropriate Direct BOPCO to isolate SG 1-1 ** Critical Task**

6 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 7 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__1__ Scenario No.: ____2_____ Event No.: ____9 ___ Page __7__ of __7__

Event

Description:

LBLOCA at 25% DBA Time Position Applicants Actions or Behavior BOP Recognize and report LOCA Trip RCPs as directed ** Critical Task**

Perform steps of E-1 as directed RO Recognize and report LOCA Perform steps of E-1 as directed SFM Acknowledge LOCA report Transitions from E-2 to E-1 Direct BOPCO to Trip RCPs ** Critical Task**

Directs control room response per E-1 NOTE: Terminate scenario when transition to E-1.3, Cold Leg Recirc, takes place 8 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____2_____ Event No.: ____1____ Page __1__ of __8__

Event

Description:

Increase Power to 50%

Time Position Applicant's Actions or Behavior BOP Coordinate with RO to perform the power increase as directed by SFM Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Coordinate with BOP to perform the power increase as directed by SFM Prepare the makeup system for dilution and dilutes as required Prepare DEHC and start load increase as directed by SFM Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Performs tailboard on power increase and reactivity control Directs and monitors power increase and dilution 1 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____2_____ Event No.: ____2____ Page __2__ of __8__

Event Description : PZR Level Channel 459 Fail Low Time Position Applicant's Actions or Behavior BOP Acknowledge and report PRZ level and Charging Mismatch alarms Diagnose level channel LT-459 failure Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Detect charging and PZR level increase Take manual control of charging to stabilize PZR level and maintain seal flow ** Critical**

Stops ramp as directed Deselect Channel 459 from service as directed Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Acknowledges report on PZR and Charging alarms Directs RO to take manual control of charging and stabilize the plant ** Critical**

Directs RO to stop the ramp Enters AP-5 and directs control room response Determine ITS 3.3.1 requirements for tripping bistables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Contacts Asset Team for assistance 2 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____2_____ Event No.: ____3____ Page __3__ of __8__

Event Description : Restore Letdown Time Position Applicant's Actions or Behavior BOP Restore Letdown per OP B-1A:XII ** Critical**

Closely monitor primary and secondary parameters for proper response RO Coordinate with BOPCO on Letdown restoration Maintain seal injection and PZR level within limits ** Critical**

Commence load ramp as directed Closely monitor primary and secondary parameters for proper response SFM Tailboard Letdown restoration per OP B-1A:XII Direct BOPCO to restore letdown per procedure Direct RO to continue with load ramp 3 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___2____ Scenario No.: _____2_____ Event No.: ____4____ Page __4__ of __8__

Event

Description:

SG 1-1 Pressure Channel 516 Fail High Time Position Applicant's Actions or Behavior BOP Detects steam flow from SG 1-1 and reports Identifies PT-515 failure and takes manual control of PCV-19 ** Critical**

Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Stops ramp if directed Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Acknowledges report on Steam Flow Directs BOPCO to manually close PCV-19 ** Critical**

Directs crew to stabilize the plant Follows guidance of OP AP-5 Determine ITS 3.3.2 requirements for tripping bistables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Requests Asset Team assistance Directs and monitors control room response 4 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___2__ Scenario No.: ____2_____ Event No.: ____5 ___ Page __5__ of __8__

Event

Description:

SGTL on SG 1-1 Time Position Applicant's Actions or Behavior BOP Acknowledge SJAE Rad Monitor alarm PK11-06 Identify RM-15 rad levels increasing Closely monitor primary and secondary parameters for proper response RO Observes charging letdown mismatch Take manual control as necessary to maintain charging/letdown balance Calculate charging mismatch to be around 5 gpm ** Critical**

Closely monitor primary and secondary parameters for proper response SFM Acknowledges BOPCO and RO on radiation alarms and charging mismatch Directs RO to stabilize the plant and calculate leak rate Enter AP-3 and OP O-4 and follows guidance Determine ITS limit 3.4.13.d and O-4 limit exceeded ** Critical**

Determine actions for plant shutdown IAW ITS and O-4 5 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____2_____ Event No.: ____6 ___ Page __6__ of __8__

Event

Description:

Vacuum Leak Time Position Applicant's Actions or Behavior BOP Acknowledges Condensate DO2 and conductivity alarms on PK12-04/05 and report to SFM Determine vacuum leak as cause and start diagnostics as directed Closely monitor primary and secondary parameters during power decrease RO Acknowledges Condensate DO2 and conductivity alarms on PK12-04/05 and report to SFM Commence boration for power decrease as directed Commence power decrease as directed SFM Acknowledge RO/BOPCO on DO2 and conductivity alarms and decreasing vacuum Enter AP-7 Direct RO to commence a power reduction Determine trip requirements per Attachment 4.2 of AP-7 6 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____2_____ Event No.: ____ 7, 8, 9 & 11 ___ Page __7__ of __8__

Event

Description:

Seismic with Generator Lockout, MSL 1-1 Break and Failure Phase A Time Position Applicant's Actions or Behavior BOP Acknowledges Generator Trip alarms and report to SFM Closely monitor primary and secondary parameters and response following turbine trip Diagnoses MSL 1-1 leak and recommends reactor trip Performs Immediate Actions for EOP E-0 Performs SG 1-1 isolation per E-2 ** Critical**

Determines Train B Phase A failed to actuate and perform manual alignment ** Critical**

Performs actions of E-0 and E-2 as directed RO Acknowledges Generator Trip alarms and report to SFM Closely monitor primary and secondary parameters and response following turbine trip Diagnoses MSL 1-1 leak and recommends reactor trip Trips the reactor as directed ** Critical**

Performs Immediate Actions for EOP E-0 Performs actions of E-0 and E-2 as directed SFM Acknowledge RO/BOPCO report of generator trip Determines Reactor tip NOT required in current condition (below P-9)

Direct control room response to generator trip at low power Acknowledge MSL leak and direct RO to trip the reactor ** Critical**

Direct control room response per E-0 Direct BOPCO to isolate SG 1-1 per E-2 ** Critical**

Direct BOPCO to perform Attachment E to align Phase A completely ** Critical**

Transition to E-2 and direct control room response 7 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 8 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____2_____ Event No.: ____ 10 ___ Page __8__ of __8__

Event

Description:

SGTR SG 1-1 Time Position Applicant's Actions or Behavior BOP Diagnoses SGTR and reports to SFM Verifies SG 1-1 isolation per E-3 as directed ** Critical**

Secures RCPs as directed ** Critical**

Performs actions of E-3 and ECA-3.1 as directed RO Diagnoses SGTR and reports to SFM Performs actions of E-3 and ECA-3.1 as directed SFM Acknowledge RO/BOPCO report of SGTR Transition to E-3 when appropriate Direct BOPCO to trip RCPs ** Critical**

Direct BOPCO to verify SG 1-1 isolation ** Critical**

Transitions to ECA-3.1 Direct control room response per E-3 and ECA-3.1 9 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____3_____ Event No.: ____1____ Page __1__ of __5__

Event

Description:

DRPI Data A Failure Time Position Applicant's Actions or Behavior BOP Acknowledge PK03-21 DRPI alarm and report Select S106 to B Only when directed Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Acknowledge PK03-21 DRPI alarm Monitor rods and plant reactivity for possible excursion Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Acknowledge reports on PK03-21 Directs BOPCO to select S106 to B Only Directs actions of control room pre AR PK03-21 1 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____3_____ Event No.: ____2 & 3____ Page __2__ of __5__

Event Description : LTBV (FCV-230) Fail Open Time Position Applicant's Actions or Behavior BOP Acknowledge and report PK10-07 Announce FCV-230 open Coordinate with RO to stabilize plant Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Acknowledge and report PK10-07 Announce runback Coordinate with BOPCO to stabilize plant Resets C-7 signal as directed Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Acknowledges report on FCV-230 opening and alarms Enters AP-25 and directs control room response to stabilize plant Directs RO to reset Steam Dump C-7 signal Contacts Asset Team for assistance 2 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:__2__ Scenario No.: ____3_____ Event No.: ____4____ Page __3__ of __5__

Event Description : RCP 1-1 #2 Seal Failure Time Position Applicant's Actions or Behavior BOP Acknowledge seal leakoff alarm PK05-01 and report Report Seal Leakoff to #2 seal high and to #1 low Closely monitor primary and secondary parameters for proper response RO Acknowledge seal leakoff alarm PK05-01 and report Coordinate with BOPCO and Aux Board on leak determination Maintain seal injection and PZR level within limits Commence load ramp as directed Closely monitor primary and secondary parameters for proper response SFM Acknowledge alarm and leakoff high on #2 Seal Guide and direct response per PK05-01 Direct power reduction as necessary 3 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___2____ Scenario No.: _____3_____ Event No.: ____5 & 6____ Page __4__ of __5__

Event

Description:

RCP 1-1 #1 Seal Failure and controlled shutdown Time Position Applicant's Actions or Behavior BOP Reports seal leakoff to #1 Seal increased to 7 gpm Coordinates with RO on power reduction Trip RCP if directed ** Critical Task**

Close RCP Seal Leakoff valve within 3-5 minutes of RCP trip if directed ** Critical Task**

Monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status RO Borate as necessary for plant shutdown Commence ramp for plant shutdown Closely monitor primary and secondary parameters for proper response Keep SFM appraised of plant conditions and status SFM Acknowledge increased leakoff on #1 seal Direct response per PK05-01 Determine plant shutdown required Tailboard shutdown Directs BOPCO to trip RCP 1-1 if seal leak off > 8 gpm ** Critical Task**

Directs BOPCO to close seal leakoff valve within 3-5 minutes after RCP Trip ** Critical Task**

Requests Asset Team assistance Directs and monitors control room response 4 NUREG-1021, Revision 8

Appendix D Operator Actions Form ES-D-2 Op-Test No.:___2__ Scenario No.: ____3_____ Event No.: ____7, 8 & 9 ___ Page __5__ of __5__

Event

Description:

Seismic W/LOCA and Loss of RWST Time Position Applicant's Actions or Behavior BOP Perform Immediate Actions of E-0 Perform actions of E-0 as directed Perform actions of E-1 and ECA-1.1 RO Perform Immediate Actions of E-0 Perform actions of E-0 as directed Determine and report no injection flow and cavitation on ECCS pumps Secure ECCS pumps as directed ** Critical Task**

Recommend NOT securing RCPs on loss of subcooling w/o CCPs ** Critical Task**

Perform actions of E-1 and ECA-1.1 as directed SFM Directs control room response per E-0 Directs outside control room response to no ECCS flow Directs RO to secure ECCS pumps **Critical Task**

Does NOT trip RCPs based on subcooling and CCP condition ** Critical Task**

Transitions to E-1 and directs control room response Transitions to ECA-1.1 and directs control room response 5 NUREG-1021, Revision 8

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: ADMNRC - 01

Title:

PERFORM SEALED VALVE CHECKLIST FOR CONTAINMENT SPRAY PUMP 1-1 Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: RCA Entry

References:

OP K-10C, Sealed Valve Checklist for Containment Spray Sytem, Rev. 9 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2,3,4,5,6 Job Designation: RO/SRO KA Number: G2.1.22, Ability to Determine Mode of Operation Rating: 2.8/3.3 AUTHOR: JACK BLACKWELL DATE : 2/13/2003 REVIEWED BY: N/A DATE :

JPM COORDINATOR APPROVED BY: N/A DATE :

TRAINING LEADER REV. 0

JPM TITLE: PERFORM SEALED VALVE CHECKLIST FOR JPM NUMBER: ADMNRC-01 CONTAINMENT SPRAY PUMP 1 - 1 INSTRUCTOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: OP K-10C, Sealed Valve Checklist for Containment Spray System Initial Conditions: Unit 1 is operating at 100%. OP K-10C is in progress with 1st Check completed and most of the Independent Verification completed, with the exception of CSP 1-1.

Initiating Cue: The SFM has directed you to complete the Independent Verification for Containment Spray Pump 1-1 per OP K-10C, Sealed Valve Checklist for Containment Spray Systems.

Task Standard: The Sealed Valve Checklist is completed and ready for SFM review.

ADMNRC01.DOC PAGE 2 OF 2 REV. 0

JPM TITLE: PERFORM SEALED VALVE CHECKLIST FOR JPM NUMBER: ADMNRC-01 CONTAINMENT SPRAY PUMP 1 - 1 INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions 1.Review OP K-10C. 1.1 Obtains correct procedure.

1.2 Reviews Prerequisites and Precautions and Limitations.

Cue: Give copy of procedure to Candidate Step was: SAT: ____ Unsat _____*

2.** Verifies CS 1- 8999A Sealed 2.1 Locates CS 1 - 8999A, CSP 1-1 Open. suction.

2.2 Verifies valve Sealed Open.

Step was: SAT: ____ Unsat _____*

3.** Verifies CS 1- 9000A Sealed 3.1 Locates CS 1 - 9000A, CSP 1-1 Closed. SIS test line stop.

3.2 Verifies valve Sealed Closed.

Step was: SAT: ____ Unsat _____*

4.** Verifies CS 1- 43 Sealed Open. 4.1 Locates CS 1 - 43, CSP 1-1 Eductor stop.

4.2 Verifies valve Sealed Open.

Step was: SAT: ____ Unsat _____*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC01.DOC PAGE 3 OF 3 REV. 0

JPM TITLE: PERFORM SEALED VALVE CHECKLIST FOR JPM NUMBER: ADMNRC-01 CONTAINMENT SPRAY PUMP 1 - 1 INSTRUCTOR W ORKSHEET Step Expected Operator Actions 5.** Verifies CS 1- 8997A Sealed Open 5.1 Locates CS 1 - 8997A, Spray Add Tank Outlet stop.

5.2 Verifies valve Sealed Open Step was: SAT: ____ Unsat _____*

6.** Verifies CS 1- 9015A Sealed Open 6.1 Locates CS 1 - 9015A, CSP 1-1 Discharge stop.

Cue: Inform operator the seal is missing.

If asked position of valve, the valve is open 6.2 Notes valve seal missing 6.3 Notes position of valve and marks it on form.

6.4 Contacts SFM and reports valve position and seal discrepancy and asks for instructions Step was: Sat: _______ Unsat _______*

Stop Time:

Total Time: ___________ (record on cover sheet)

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC01.DOC PAGE 4 OF 4 REV. 0

JPM NUMBER: ADMNRC-01 EXAMINEE W ORKSHEET Initial Conditions: Unit 1 is operating at 100%. OP K-10C is in progress with 1st Check completed and most of the Independent Verification completed, with the exception of CSP 1-1.

Initiating Cue: The SFM has directed you to complete the Independent Verification for Containment Spray Pump 1-1 per OP K-10C, Sealed Valve Checklist for Containment Spray Systems.

Task Standard: The Sealed Valve Checklist is completed and ready for SFM review.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: ADMNRC-02

Title:

DETERMINE QUADRANT POWER TILT RATIO Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments:

References:

STP R-25, Calculation of Quadrant Power Tilt Ratio, Rev. 20 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 5 minutes Critical Steps: 6, 8, 9, 10 Job Designation: RO/SRO KA Number: G2.1.7 Ability to Evaluate Plant Performance and Make Operational Judgements Rating: 3.7/4.4 AUTHOR: JACK BLACKWELL DATE : 2/13/2003 REVIEWED BY: N/A DATE : N/A JPM COORDINATOR APPROVED BY: N/A DATE : N/A TRAINING LEADER REV.0

JPM TITLE: DETERMINE QUADRANT POWER TILT RATIO JPM NUMBER: ADMNRC-02 INSTRUCTOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: PPC and a copy of STP R-25.

Initial Conditions: Unit 1 is operating at 100% power. Power range nuclear instrument calibration (STP I-2D) is to begin, starting with N41. The PPC is available. ALL power range NIs are OPERABLE.

Initiating Cue: A QPTR is needed prior to starting the calibration. The Shift Foreman has directed you to perform the QPTR.

Task Standard: Perform a QPTR.

ADMNRC02R.DOC PAGE 2 OF 6 REV. 0

JPM TITLE: DETERMINE QUADRANT POWER TILT RATIO JPM NUMBER: ADMNRC-02 INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References STP R-25.

Note: May review the scope, frequency, and Technical Specifications.

Step was: Sat: _______ Unsat _______*

2. Start data section. 2.1 Enters data for unit, operating MODE, and date/time.

Step was: Sat: _______ Unsat _______*

3. Review precautions and limitations. 3.1 Reviews and initials precautions and limitations.

Step was: Sat: _______ Unsat _______*

4. Review prerequisites. 4.1 Reviews and initials prerequisites.

Step was: Sat: _______ Unsat _______*

5. Determine power level. 5.1 Records approximate power level at step 12.1.

Step was: Sat: _______ Unsat _______*

6. ** Check power range detectors 6.1 Determines all four detectors are OPERABLE. OPERABLE and checks N/A for step 12.2.

Step was: Sat: _______ Unsat _______*

7. Prepare for QPTR on PPC. 7.1 Observes NOTE prior to step 12.3, checks step 12.3, and begins QPTR.

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC02R.DOC PAGE 3 OF 6 REV. 0

JPM TITLE: DETERMINE QUADRANT POWER TILT RATIO JPM NUMBER: ADMNRC-02 INSTRUCTOR W ORKSHEET

8. ** Access data. 8.1 Accesses GRPDIS on PPC and displays OP R-25 on 60 second update OR GRPDIS using QPTRTRAC on 60 second update, and initials step.

Step was: Sat: _______ Unsat _______*

9. ** Verify Data points good. 9.1 Verifies all data points good and initials step.

Step was: Sat: _______ Unsat _______*

10. ** Record indicated detector currents. 10.1 Records currents for step 12.3.3.

10.2 Records highest current for step 12.3.4.

Step was: Sat: _______ Unsat _______*

11. Complete personal data portion of STP. 11.1 Places name, date, time, and initials step 12.6.

Step was: Sat: _______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

Note: Instructor needs to evaluate the examinee's data sheet. Values do not have to be exactly the same, but need to be close enough to result in a final QPTR that is acceptable.

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC02R.DOC PAGE 4 OF 6 REV. 0

JPM NUMBER: ADMNRC-02 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is operating at 100% power. Power range nuclear instrument calibration (STP I-2D) is to begin, starting with N41. The PPC is available. ALL power range NIs are OPERABLE.

Initiating Cue: A QPTR is needed prior to starting the calibration. The Shift Foreman has directed you to perform the QPTR.

Task Standard: Perform a QPTR.

ADMNRC02R.DOC PAGE 5 OF 6 REV. 0

JPM TITLE: DETERMINE QUADRANT POWER TILT RATIO JPM NUMBER: ADMNRC-02 ATTACHMENT 1, SIMULATOR SETUP q Initialize the simulator to IC-1 (100%, BOL).

q Inform the examiner that the simulator setup is complete.

q Go to RUN when the examinee is given the cue sheet.

ADMNRC02R.DOC PAGE 6 OF 6 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT Job Performance Measure Number: ADMNRC-03RO

Title:

Annunciator Problem Evaluation Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments:

References:

OP1.DC24, Control of Main Annunciator System Problems AR PK03-10 AR A0542485 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 2,3,4,5,6,7 Job Designation: RO/SRO KA Number: G2.2.11 Rating: 2.5/3.4 AUTHOR: JACK BLACKWELL DATE : 2/13/2003 REVIEWED BY: N/A DATE :

JPM COORDINATOR APPROVED BY: N/A DATE :

TRAINING LEADER REV. 0

JPM TITLE: ANNUNCIATOR PROBLEM EVALUATION JPM NUMBER: ADMNRC-03RO INSTRUCTOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: Copy of OP1.DC24, Control of Main Annunciator System Problems Initial Conditions: Unit 2 is at 100% power. Alarm PK03-10 has been in alarm continually from input 464. An AR has been written, # A0542485 and The Control Room Asset Team has been contacted. The SFM had N-41B removed from the QPTR calculation at the NI cabinet, which stopped the alarm.

No evolutions are planned and no equipment is out of service.

Initiating Cue: The Unit 2 SFM has directed you to use OP1.DC24, steps 5.2 and 5.3 and fill in the Annunciator Problem Evaluation Sheet and any associated paperwork as required.

Task Standard: OP1.DC24 paperwork filled out appropriately.

ADMNRC03RO.DOC PAGE 2 OF 9 REV. 0

JPM TITLE: ANNUNCIATOR PROBLEM EVALUATION JPM NUMBER: ADMNRC-03RO INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Reviews procedure 1.1 References OP1.DC24 1.2 Reads steps 5.2 and 5.3 1.3 Reviews Attachments 7.1 and 7.2 Step SAT:___________ UNSAT:________*

2. ** Fills out known information on 2.1 Performs the following:

Attachment 7.1, Evaluation Sheet

Checks Unit 2

Todays Date

PK03-10

Input # 464

AR# A0542482

Checks NO on Standing and Failed Alarms

Checks YES on Continual Alarm Step SAT:___________ UNSAT:________*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03RO.DOC PAGE 3 OF 9 REV. 0

JPM TITLE: ANNUNCIATOR PROBLEM EVALUATION JPM NUMBER: ADMNRC-03RO INSTRUCTOR W ORKSHEET Step Expected Operator Actions

3. ** Verifies alarm is used to satisfy 3.1 References ITS 3.2.4 and ECG 37.3 and Tech Spec requirement (#1) and determines the alarm is ITS related and checks provides warning that equipment both ITS boxes and implements TS Tracking is inoperable (#2). Sheet.

CUE: TS Tracking Sheet will be implemented by the SCO.

Step SAT:___________ UNSAT:________*

4. ** Verifies other alarms do NOT 4.1 Determines alarm does NOT have multiple have reflash input to this alarm inputs from other sources and an Annunciator

(#3), that equipment monitored Defeat Log is required.

can cause a Plant Trip (#4), and (critical component) the alarm is redundant (#5).

4.2 Determines alarm monitors equipment that could cause a trip and there are redundant alarms.

Step SAT:___________ UNSAT:________*

5. ** Determines: 5.1 Reviews ITS 3.2.4 and ECG37.3 and determines that compensatory measures require

Compensatory Measures QPTR every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by either the BOPCO,

Watchstation CO or SCO.

Frequency Step SAT:___________ UNSAT:________*

6. ** Complete form 6.1 Places sticker on PK03-10, initials and signs form.

Step SAT:___________ UNSAT:________*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03RO.DOC PAGE 4 OF 9 REV. 0

JPM TITLE: ANNUNCIATOR PROBLEM EVALUATION JPM NUMBER: ADMNRC-03RO INSTRUCTOR W ORKSHEET Step Expected Operator Actions

7. ** Fills in appropriate portions of 7.1 Fills in:

the Annuciator Defeat Log

AR # A0542485

PK03-10

Alarm Input 464

Other: Alarm defeated by removing N-41B from QPTR calculation on Misc.

Equipment & Control Panel at the NI racks behind VB-3 on Unit 2 (words similar to this effect)

Reference Drawing # 45209 (not critical)

Prepared by and date/time Step SAT:___________ UNSAT:________*

Stop Time: ___________

Total Time: ___________

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03RO.DOC PAGE 5 OF 9 REV. 0

JPM NUMBER: ADMNRC-03RO EXAMINEE CUE SHEET Initial Conditions: Unit 2 is at 100% power. Alarm PK03-10 has been in alarm continually from input 464. An AR has been written, # A0542485 and The Control Room Asset Team has been contacted. The SFM had N-41B removed from the QPTR calculation at the NI cabinet, which stopped the alarm.

No evolutions are planned and no equipment is out of service.

Initiating Cue: The Unit 2 SFM has directed you to use OP1.DC24, steps 5.2 and 5.3 and fill in the Annunciator Problem Evaluation Sheet and any associated paperwork as required.

Task Standard: OP1.DC24 paperwork filled out appropriately.

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03RO.DOC PAGE 6 OF 9 REV. 0

69-20275 03/28/97 Page 1 of 1 ATTACHMENT 7.1 TITLE: Annunciator Problem Evaluation Sheet UNIT 1[ ] 2[ X ] DATE PK # 03-10 ALARM INPUT # 464 AR# A0542485 YES NO STANDING ALARM [ ] [ X]

FAILED ALARM [ ] [ X]

CONTINUAL ALARM [ X]* [ ]

1. Is this alarm input utilized to satisfy Tech. Spec. Surveillance [ X] [ ]

Requirements? (If yes is checked, implement Tech. Spec. Tracking Sheet in accordance with OP1.DC17.)

2. Does this alarm provide warning that equipment required by the Tech. [ X] [ ]

Specs. may be inoperable?

3. Do other alarm contacts to this input have reflash capability? [ ] [X ]*

4. Does this alarm monitor equipment which could cause a Plant Trip if a [X ] [ ]

failure were to occur?

5. Is this alarm redundant to similar alarms on same equipment? [X ] [ ]

COMPENSATORY MEASURES: Perform T.S. Surveillance requirements of 4.2.4.1.b per ECG 37.3. (Perform QPTR once per shift).

Once per shift (not > SHIFTLY)

WATCHSTATION: BOPCO/CO/SCO FREQUENCY:

COMMENTS:

AR STICKER PLACED ON PK# 03-10 BY INIT PREPARED BY APPROVED BY (SFM)

If these boxes are checked, initiate Annunciator Defeat Log (Attachment 7.1) when determined to be appropriate by the Shift Foreman. If the Annunciator Defeat Log is not initiated, state the reason.

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03RO.DOC PAGE 7 OF 9 REV. 0

69-20276 02/18/01 Page 1 of 1 ATTACHMENT 7.2 TITLE: Annunciator Defeat Log PREPARATION Action Request # A0542485 AR PK # 03-10 Alarm Input # 464 Description of Defeat: (Indicate method, panel # or location, device #, terminal or contact # as applicable)

Y N Jumper/Lifter Lead [ ] [X]

Removed From Scan [ ] [X]

Other: Alarm defeated by removing N-41B from QPTR calculation on Misc. Equipment & Control Panel at the NI racks behind VB-3 on Unit 2.

Reference Drawing Number: 452094 Prepared By: Date/Time:

Authorized By: (Shift Manager) Date/Time:

DEFEAT Defeated By: Date/Time:

Verified By: Date/Time:

Alarm Removed from Initials Scan:

Info Tag hung at Annunciator Maintenance Terminal for all alarms removed from scan:

Initials: Location:

AR Updated: (Indicate alarm defeated. For jumper or lifted lead, indicate the location and that an Info Tag was attached).

Initials:

RESTORATION Restored By: Date/Time:

Verified By: Date/Time:

Info Tag Removed:

Initials:

AR Updated: (Indicate Info Tag removed and Attachment 7.2 has been closed out.)

Initials:

Repair/Removal W/O #

Alarm Returned to Scan: Initials:

Removal Noted By: Date/Time:

(C.O.)

69-11845 01/16/01 Page 1 of 1 ATTACHMENT 7.3 TITLE: Annunciator Problems Index UNIT 2 CURRENT YEAR This Year PAGE 1 OF 1 PK WINDOW DATE DATE AR NO. EQUIPMENT AFFECTED COMP NO. NO. ON OFF MEAS Y/N 03 10 Today A0542485 N-41B and QPTR Calc. Y

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT Job Performance Measure Number: ADMNRC-03SRO

Title:

Review of Annunciator Problem Evaluation Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments:

References:

OP1.DC24, Control of Main Annunciator System Problems AR PK03-10 AR A0542485 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2,3,4,5 Job Designation: SRO Task Number: G2.2.11 Rating: 3.4 AUTHOR: JACK BLACKWELL DATE : 2/13/2003 REVIEWED BY: N/A DATE :

JPM COORDINATOR APPROVED BY: N/A DATE :

TRAINING LEADER REV. 0

JPM TITLE: REVIEW OF ANNUNCIATOR PROBLEM EVALUATION ADMNRC-03SRO INITIAL CONDITIONS Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: OP1.DC24, Control of Main Annunciator System Problems AR PK03-10 AR A0542485 Initial Conditions: Unit 2 is at 100% power. Alarm PK03-10 has been in alarm continually from input 464. An AR has been written, # A0542485 and The Control Room Asset Team has been contacted. N-41B (lower) has been removed from the QPTR calculation at the NI cabinet. No evolutions are planned and no equipment is out of service.

Initiating Cue: The Unit 2 CO has performed OP1.DC24, steps 5.2 and 5.3 and filled in the Annunciator Problem Evaluation Sheet and the Preparation portion of the Annunciator Defeat log and has given them to you for review.

Task Standard: OP1.DC24 paperwork reviewed and filled out appropriately.

ADMNRC03SRO.DOC PAGE 2 OF 9 REV. 0

JPM TITLE: REVIEW OF ANNUNCIATOR PROBLEM EVALUATION ADMNRC-03SRO INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Reviews procedure 1.1 References OP1.DC24 1.2 Reads steps 5.2 and 5.3 1.3 Reviews Attachments 7.1 and 7.2 Step SAT:___________ UNSAT:________*

2. ** Verifies correct heading on 2.1 Notes correct entries:

Annunciator Problem Evaluation Sheet

Unit 2

Todays Date

PK03-10

Input # 464

AR# A0542482

NO checked on Standing and Failed Alarms

YES checked on Continual Alarm Step SAT:___________ UNSAT:________*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03SRO.DOC PAGE 3 OF 9 REV. 0

JPM TITLE: REVIEW OF ANNUNCIATOR PROBLEM EVALUATION ADMNRC-03SRO INSTRUCTOR W ORKSHEET Step Expected Operator Actions

3. ** Verifies 1 through 5 checked 3.1 Notes 1, 2, 4 and 5 checked YES, 3 checked appropriately. NO.

3.2 Checks for TS Tracking sheet 3.3 Checks for Annunciator Defeat Log CUE: TS Tracking Sheet will be implemented by the SCO.

Step SAT:___________ UNSAT:________*

4. ** Verifies Compensatory 4.1 Determines ECG reference and Watchstation measures correct and appropriate. correct, but ITS surveillance incorrect:

Should be SR 3.2.4.2, NOT 4.2.4.1.b

Should be QPTR surveillance every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , NOT every 7 days. (critical component) 4.2 Makes corrections to forms and approves Problem Evaluation Sheet.

Step SAT:___________ UNSAT:________*

5. ** Verifies Annunciator Defeat 5.1 Determines AR number incorrect and makes Log is correct correction. (A0542485 NOT A0524285)

Determines AR PK # incorrect and corrects.

5.2 (03-10 NOT 03-01)

Determines Jumper and Removed from Scan 5.3 boxes marked NO correctly.

Determines incorrect description in OTHER 5.4 and makes correction. (Removed N-41B (lower), NOT N-41A (upper) on NI panel)

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

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JPM TITLE: REVIEW OF ANNUNCIATOR PROBLEM EVALUATION ADMNRC-03SRO INSTRUCTOR W ORKSHEET Step Expected Operator Actions Approves Defeat log 5.5 Step SAT:___________ UNSAT:________*

Stop Time: ___________

Total Time: ___________

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03SRO.DOC PAGE 5 OF 9 REV. 0

ADMNRC-03SRO EXAMINEE CUE SHEET Initial Conditions: Unit 2 is at 100% power. Alarm PK03-10 has been in alarm continually from input 464. An AR has been written, # A0542485 and The Control Room Asset Team has been contacted. N-41B (lower) has been removed from the QPTR calculation at the NI cabinet. No evolutions are planned and no equipment is out of service.

Initiating Cue: The Unit 2 CO has performed OP1.DC24, steps 5.2 and 5.3 and filled in the Annunciator Problem Evaluation Sheet and the Preparation portion of the Annunciator Defeat log and has given them to you for review.

Task Standard: OP1.DC24 paperwork reviewed and filled out appropriately.

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03SRO.DOC PAGE 6 OF 9 REV. 0

69-20275 03/28/97 Page 7 of 1 ATTACHMENT 7.1 TITLE: Annunciator Problem Evaluation Sheet UNIT 1[ ] 2[ X ] DATE PK # 03-10 ALARM INPUT # 464 AR# A0542485 YES NO STANDING ALARM [ ] [ X]

FAILED ALARM [ ] [ X]

CONTINUAL ALARM [ X]* [ ]

1. Is this alarm input utilized to satisfy Tech. Spec. Surveillance [ X] [ ]

Requirements? (If yes is checked, implement Tech. Spec. Tracking Sheet in accordance with OP1.DC17.)

2. Does this alarm provide warning that equipment required by the Tech. [ X] [ ]

Specs. may be inoperable?

3. Do other alarm contacts to this input have reflash capability? [ ] [X ]*

4. Does this alarm monitor equipment which could cause a Plant Trip if a [X ] [ ]

failure were to occur?

5. Is this alarm redundant to similar alarms on same equipment? [X ] [ ]

COMPENSATORY MEASURES: Perform T.S. Surveillance requirements of 4.2.4.1.b per ECG 37.3. (Perform QPTR once per shift).

Every 7 days (not > SHIFTLY)

WATCHSTATION: BOPCO/CO/SCO FREQUENCY:

COMMENTS:

AR STICKER PLACED ON PK# 03-10 BY JO INIT Joe Operator PREPARED BY APPROVED BY (SFM)

If these boxes are checked, initiate Annunciator Defeat Log (Attachment 7.1) when determined to be appropriate by the Shift Foreman. If the Annunciator Defeat Log is not initiated, state the reason.

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC03SRO.DOC PAGE 7 OF 9 REV. 0

69-20276 02/18/01 Page 1 of 1 ATTACHMENT 7.2 TITLE: Annunciator Defeat Log PREPARATION Action Request # A0524285 AR PK # 03-01 Alarm Input # 464 Description of Defeat: (Indicate method, panel # or location, device #, terminal or contact # as applicable)

Y N Jumper/Lifter Lead [ ] [X]

Removed From Scan [ ] [X]

Other: Alarm defeated by removing N-41A (upper) from QPTR calculation on Misc. Equipment

& Control Panel at the NI racks behind VB-3 on Unit 2.

Reference Drawing Number: 452094 Prepared By: Date/Time:

Authorized By: (Shift Manager) Date/Time:

DEFEAT Defeated By: Date/Time:

Verified By: Date/Time:

Alarm Removed from Initials Scan:

Info Tag hung at Annunciator Maintenance Terminal for all alarms removed from scan:

Initials: Location:

AR Updated: (Indicate alarm defeated. For jumper or lifted lead, indicate the location and that an Info Tag was attached).

Initials:

RESTORATION Restored By: Date/Time:

Verified By: Date/Time:

Info Tag Removed:

Initials:

AR Updated: (Indicate Info Tag removed and Attachment 7.2 has been closed out.)

Initials:

Repair/Removal W/O #

Alarm Returned to Scan: Initials:

Removal Noted By: Date/Time:

(C.O.)

69-11845 01/16/01 Page 1 of 1 ATTACHMENT 7.3 TITLE: Annunciator Problems Index UNIT 2 CURRENT YEAR This Year PAGE 1 OF 1 PK WINDOW DATE DATE AR NO. EQUIPMENT AFFECTED COMP NO. NO. ON OFF MEAS Y/N 03 10 Today A0542485 N-41B (lower) and Y QPTR Calc.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: ADMNRC-04

Title:

Perform personnel frisk upon exiting Surface Contamination Area (SCA)

Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Perform while in RCA

References:

RP1.ID9, Radiation Work Permits, Attachment 9.1, Rev. 4; RCP D-911, Operation of Eberline Count Rate Meters, Rev. 3; RCP D-600, Personnel Decontamination and Evaluation, Rev. 19 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 Minutes Critical Steps: 1, 2, 3, 4 Job Designation: RO/SRO Task Number: G2.3.4 Rating: 2.5/3.1 AUTHOR: JACK BLACKWELL DATE : 2/13/2003 REVIEWED BY: N/A DATE : N/A JPM COORDINATOR APPROVED BY: N/A DATE : N/A TRAINING LEADER REV. 0

JPM TITLE: PERFORM PERSONNEL FRISK JPM NUMBER: ADMNRC-04 INSTRUCTOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the procedure and told the step with which to begin.

Required Materials: RM-14 or RM-3C-4 personnel frisker Initial Conditions: While performing an inspection of CCP 1-3, you discovered water on the floor by the pump discharge pulsation damper vent, 1-8391. You stopped the leak by tightening the isolation valve. You contacted Radiation Protection and informed them of the situation.

Initiating Cue: RP has requested you perform a Hand and Foot survey, in accordance with RP1.ID9, to verify you are not contaminated.

Task Standard: Hand and Foot survey completed in accordance with RP1.ID9.

ADMNRC04.DOC PAGE 2 OF 5 REV. 0

JPM TITLE: PERFORM PERSONNEL FRISK JPM NUMBER: ADMNRC-04 INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. **Operator operates detector per 1.1 Operator verifies that power is RCP D-911 & RCP D-600. available. (Either battery check or plugged in to 120VAC power supply.)

1.2 Operator verifies that the detector is in the X1 or X10 scale positions.

Note: The X1 or X10 scales may be used per RCP D-600.

1.3 Operator verifies background radiation is <300cpm.

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC04.DOC PAGE 3 OF 5 REV. 0

JPM TITLE: PERFORM PERSONNEL FRISK JPM NUMBER: ADMNRC-04 INSTRUCTOR W ORKSHEET Step Expected Operator Actions

2. **Operator performs personnel frisk. 2.1 Operator performs frisk of Hands.

2.2 Operator performs frisk of feet.

Cue: Red alarm light is lit and audible alarm is heard.

Step was: Sat: _______ Unsat _______*

3. **Operator contacts Radiation 3.1 Operator contacts Access Senior.

Protection.

Note: Operator does not need to actually contact the Access Senior, task complete when a phone is located and operator tells evaluator who he would be contacting.

Step was: Sat: _______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC04.DOC PAGE 4 OF 5 REV. 0

EXAMINEE CUE SHEET JPM NUMBER: ADMNRC-04 Initial Conditions: While performing an inspection of CCP 1-3, you discovered water on the floor by the pump discharge pulsation damper vent, 1-8391. You stopped the leak by tightening the isolation valve. You contacted Radiation Protection and informed them of the situation.

Initiating Cue: RP has requested you perform a Hand and Foot survey, in accordance with RP1.ID9, to verify you are not contaminated.

Task Standard: Hand and Foot survey completed in accordance with RP1.ID9.

ADMNRC04.DOC PAGE 5 OF 5 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: ADMNRC-05SRO

Title:

PERFORM AN OFF-SITE DOSE ASSESSMENT - SGTR WITH A 10%

STEAM DUMP LIFT Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments:

This JPM does NOT need to be performed in the simulator. It can be performed in the Control Room or in a classroom with the Cues.

References:

EP G-1, Accident Classification and Emergency Plan Activation, Rev. 31 EP R-2, Release of Airborne Radioactive Materials Initial Assessment, Rev. 19 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2, 3, 5 Job Designation: SRO KA Number: G2.4.41 Knowledge of Emergency Action Levels thresholds and classifications Rating: 4.1 AUTHOR: JACK BLACKWELL DATE : 2/13/2003 REVIEWED BY: N/A DATE : N/A JPM COORDINATOR APPROVED BY: N/A DATE : N/A TRAINING LEADER REV. 0

JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - SGTR WITH JPM NUMBER: ADMNRC-05SRO A 10% STEAM DUMP LIFT INSTRUCTOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: Calculator Initial Conditions: Unit 1 experienced a SGTR in steam generator 14.

Initiating Cue: EOP E-3 is in progress. During the event, it was noted that the 10%

steam dump on steam generator 14 had opened for approximately 12 minutes and was manually isolated. The Shift Manager directs you to perform a dose assessment and recommend an emergency classification, based on your dose assessment. The PPC program for R-2 calculations is unavailable.

Task Standard: Dose assessed and a recommendation made for the emergency classification.

ADMNRC05SRO.DOC PAGE 2 OF 7 REV. 0

JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - SGTR WITH A JPM NUMBER: ADMNRC-05SRO 10% STEAM DUMP LIFT INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EP R-2.

Step was: Sat: _______ Unsat: _______*

2. ** Determine the total effluent release 2.1 References Attachment 10.1, page 3, rate. of EP R-2.

2.2 Fills out section 1 and notes the CAUTION referencing RE-74 readings.

2.3 Determines RE-74 reading from trend recorder or radiation monitor.

Cue: RE-74 reading is 200 cpm.

2.4 Determines SG level from LI-547.

Cue: LI-547 reading is 80%.

2.5 Determines SG flowrate from FI-542.

Cue: FI-542 reading is 0%.

2.6 Uses alternate steam flow rate of 4.0 E+5 lbm/hr.

2.7 Determines monitor factor is 6.75 E-10.

2.8 Determines total effluent release rate of 0.054 ci/sec.

Step was: Sat: _______ Unsat: _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC05SRO.DOC PAGE 3 OF 7 REV. 0

JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - SGTR WITH A JPM NUMBER: ADMNRC-05SRO 10% STEAM DUMP LIFT INSTRUCTOR W ORKSHEET

3. ** Perform dose calculations. 3.1 References Attachment 10.2 of EP R-2.

3.2 Obtains met data from PPC.

Cue: X/Q reading is 3.93 E-04 sec/m3.

3.3 Determines DCF to be 4.3 E+4 (SG - Normal).

3.4 Calculates TEDE rate of 0.91 mR/hr, and a total dose of 0.182 mR.

3.5 Calculates thyroid CDE rate of 3.18 mR/hr and a total dose of 0.636 mR.

Step was: Sat: _______ Unsat: _______*

4. Obtain the correct procedure. 4.1 References EP G-1.

Step was: Sat: _______ Unsat: _______*

5. ** Recommend event classification. 5.1 Recommends event classification as a notification as an Alert #4 per EP G-1.

Step was: Sat: _______ Unsat: _______*

Stop Time:

Total Time: (Enter total time on the cover page)

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC05SRO.DOC PAGE 4 OF 7 REV. 0

JPM TITLE: JPM NUMBER: ADMNRC-05SRO EXAMINEE CUE SHEET Initial Conditions: Unit 1 experienced a SGTR in steam generator 14.

Initiating Cue: EOP E-3 is in progress. During the event, it was noted that the 10%

steam dump on steam generator 14 had opened for approximately 12 minutes and was manually isolated. The Shift Manager directs you to perform a dose assessment and recommend an emergency classification, based on your dose assessment. The PPC program for R-2 calculations is unavailable.

Task Standard: Dose assessed and a recommendation made for the emergency classification.

ADMNRC05SRO.DOC PAGE 5 OF 7 REV. 0

JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - SGTR WITH JPM NUMBER: ADMNRC-05SRO A 10% STEAM DUMP LIFT ATTACHMENT 1, SIMULATOR SETUP q Initialize the simulator to IC-1 (100%, BOL).

q Enter drill file 1150 or manually insert the following:

Command Description

1. mal rcs4d act,100,0,0,d,0 100 gpm SG 14 tube leak

2. mal ppl2a act,0,0,40,d,2 Inadvertent SI, train A

3. mal ppl2b act,0,0,40,d,2 Inadvertent SI, train B

4. mal mss6d act,100,0,0,d,200 Fails open SG 14 safety valve for 200 seconds

5. cnv mss25 2,1,0,0,c,fnispr.lt.10,0 Fails PCV-22 SG 14 10% stm dump vlv open

6. xmt rms43 3,200,0,0,c,fnispr.lt.10,0 Fails RE-74 main steam line radiation monitor to 200 cpm

7. xmt mfw40 3,81,120,0,c,fnispr.lt.10,0 SG 14 NR level (LI-547) to 81%

8. xmt mfw43 3,80,120,0,c,fnispr.lt.10,0 SG 14 NR level (LI-548) to 80%

9. xmt mfw46 3,79,120,0,c,fnispr.lt.10,0 SG 14 NR level (LI-549) to 79%

10. xmt mfw12 3,94,120,0,c,fnispr.lt.10,0 SG 14 WR level (LR-537) to 94%

11. set cmetchiq=3.93E-04 Sets CHI/Q @ 3.93E-04

12. ovr xc3i136m act,1,0,0,c,fnispr.lt.10,0 Takes FWRVs to manual and close

13. ovr xc3i136L act,1,0,0,c,fnispr.lt.10,0 "

14. ovr xc3i137M act,1,0,0,c,fnispr.lt.10,0 "

15. ovr xc3i137L act,1,0,0,c,fnispr.lt.10,0 "

16. ovr xc3i138M act,1,0,0,c,fnispr.lt.10,0 "

17. ovr xc3i138L act,1,0,0,c,fnispr.lt.10,0 "

18. ovr xc3i139M act,1,0,0,c,fnispr.lt.10,0 "

19. ovr xc3i139L act,1,0,0,c,fnispr.lt.10,0 "

20. pmp cnd6 3,0,0,0,d,0 Blocks AUTO/MAN start CND/BSTR PP 1-3

21. ovr xc3i224o ACT,1,0,0,c,fnispr.lt.10,0 Stops CND/BSTR PP 1-2

22. ovr xc3i194C ACT,1,0,0,c,fnispr.lt.10,0 Places FCV-53 in RECIRC

23. ovr xc3i197C ACT,1,0,0,c,fnispr.lt.10,0 Places FCV-54 in RECIRC

24. vlv afw3 2,0.015,0,0,d,0 Throttles AFW PP 1-1 LCVs

25. vlv afw4 2,0.015,0,0,d,0 "

ADMNRC05SRO.DOC PAGE 6 OF 7 REV. 0

JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - SGTR WITH JPM NUMBER: ADMNRC-05SRO A 10% STEAM DUMP LIFT ATTACHMENT 1, SIMULATOR SETUP

26. vlv afw5 2,0.015,0,0,d,0 Throttles AFW PP 1-1 LCVs

27. vlv mss10 2,0,0,120,c,fnispr.lt.10,0 Closes MSIV 4

28. loa mss16 ACT,0,60,100,c,fnispr.lt.5,0 Isolates PCV-22 SG 14 10% stm dump vlv

29. vlv sgb8 2,0,0,60,c,fnispr.lt.5,0 Closes I.C. blowdown isolation vlv (FCV-763)

30. vlv afw6 2,0,0,0,d,0 Closes AFW pp 1-1 LCV-109

31. cnv afw4 2,0,10,0,c,fnispr.lt.5,0 Places LCV-113 in manual and closes vlv

32. ovr xv3o152a act,0,0,10,c,fnispr.lt.5,0 "

33. ovr xv30152m act,0,0,10,c,fnispr.lt.5,0 "

34. ovr xv2I357c act,0,0,0,d,0 Cuts out TE-443 to SMM

35. run 210 Freezes simulator after 210 seconds q Perform the following, while the simulator is running:

1. Place FCV-53/54 in RECIRC.

2. Place CND/BST pp set 1-3 in manual.

3. Verify MSR vlvs are closed (hit RESET to close vlvs).

4. Set PCV-22 10% steam dump pot to 8.67 turns.

5. Display METP on the PPC.

q Inform the examiner that the simulator setup is complete.

q EXAMINER'S DISCRETION: Go to RUN when the examinee is given the cue sheet.

ADMNRC05SRO.DOC PAGE 7 OF 7 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT Job Performance Measure Number: ADMNRC-06RO

Title:

PERFORM SHUTDOWN MARGIN CALCULATION Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments:

References:

STP R-19, Shutdown Margin Determination Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 4,5,6,7,8,9 Job Designation: RO/SRO KA Number: G2.1.25, Ability to Obtain and Interpret Station Reference Material Rating: 2.8/3.1 AUTHOR: JACK BLACKWELL DATE : 2/13/2003 REVIEWED BY: N/A DATE :

JPM COORDINATOR APPROVED BY: N/A DATE :

TRAINING LEADER REV. 0

JPM TITLE: PERFORM SHUTDOWN MARGIN CALCULATION JPM NUMBER: ADMNRC-06RO INSTRUCTOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: Copy of STP R-19, Shutdown Margin Determination Initial Conditions: Unit 1 tripped from 100% power 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months ago. Rod K6 did not insert into the core and is stuck at 220 steps. Current conditions are: TAVG =

548°F, CB = 1356, Core Burnup = 127 MWD/MTU.

Initiating Cue: The SFM has assigned you to manually perform STP R-19, Shutdown Margin Determination, taking NO credit for Xe/Sm and without APEX.

Task Standard: A completed SDM Determination ready for SFM review.

ADMNRC06RO.DOC PAGE 2 OF 13 REV. 0

JPM TITLE: PERFORM SHUTDOWN MARGIN CALCULATION JPM NUMBER: ADMNRC-06RO INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Reviews Start Data Section 1.1 Fills in Unit (1), Mode (3) and Date/Time 1.2 Reviews Precautions and Limitations and initials Step SAT:___________ UNSAT:________*

2. Determines which data sheet 2.1 Determines data sheet 2 of STP R-19 must be used and initials 2.2 Reads and initials information concerning data sheet 2 NOTE: May enter Remark noting this is a Xe/SM calculation.

Step SAT:___________ UNSAT:________*

3. Completes Section A of Data 3.1 Fills in:

Sheet 2 Unit 1, Cycle 12, Mode 3, Todays Date and Time Step SAT:___________ UNSAT:________*

4. ** Completes Section B 4.1 Fills in:

TAVG = 548°F, CB = 1356, Core Burnup = 127 MWD/MTU, Time since Shutdown = 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months Step SAT:___________ UNSAT:________*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC06RO.DOC PAGE 3 OF 13 REV. 0

JPM TITLE: PERFORM SHUTDOWN MARGIN CALCULATION JPM NUMBER: ADMNRC-06RO INSTRUCTOR W ORKSHEET Step Expected Operator Actions

5. ** Completes Section C 51 Determines Section C is N/A and enters 0 in Step C.4 Step SAT:___________ UNSAT:________*

6. ** Completes Section D 6.1 Determines:

Most reactive rod worth = 680 pcm

Stuck rods = 1

Total stuck rod worth = 680 pcm

Worth of withdrawn rod is N/A CUE: When asked physics testing data on stuck rod, feedback this will not be included in the calculation and to mark it N/A.

6.2 Determines total stuck rod worth is 680 pcm Step SAT:___________ UNSAT:________*

7. ** Completes Section E 7.1 Determines Section E does not apply and marks N/A Step SAT:___________ UNSAT:________*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC06RO.DOC PAGE 4 OF 13 REV. 0

JPM TITLE: PERFORM SHUTDOWN MARGIN CALCULATION JPM NUMBER: ADMNRC-06RO INSTRUCTOR W ORKSHEET Step Expected Operator Actions

8. ** Completes Section F 8.1 Determines:

Minimum CB to 548°F is 1211 ppm

Add 100 ppm to have 1311 ppm

Boron Worth for 1311 at 548°F = 10125 pcm

Boron worth multiplier = 1

Total worth corrections = +680 pcm

Net required boron worth = -10805 pcm

Required CB per BOL table = 1216 ppm Step SAT:___________ UNSAT:________*

9. ** Complete Section G 9.1 Determine Actual CB of 1356 ppm > Required CB of 1216 ppm 9.2 Sign and present to SFM for review.

Step SAT:___________ UNSAT:________*

Stop Time: ___________

Total Time: ___________

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC06RO.DOC PAGE 5 OF 13 REV. 0

JPM NUMBER: ADMNRC-06RO EXAMINEE CUE SHEET Initial Conditions: Unit 1 tripped from 100% power 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months ago. Rod K6 did not insert into the core and is stuck at 220 steps. Current conditions are: TAVG =

548°F, CB = 1356, Core Burnup = 127 MWD/MTU.

Initiating Cue: The SFM has assigned you to perform STP R-19, Shutdown Margin Determination, taking NO credit for Xe/Sm.

Task Standard: A completed SDM Determination ready for SFM review.

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC06RO.DOC PAGE 6 OF 13 REV. 0

Answer Key PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 15 PAGE 4 OF 6 TITLE: SHUTDOWN MARGIN DETERMINATION UNITS 1 AND 2 START DATA SECTION UNIT 1 OPERATING MODE 3 DATE/TIME Today/Now PRECAUTIONS AND LIMITATIONS INITIALS Wherever a (+) or (-) sign is given on data sheets, the correct number may be entered with no other signs. ___JO_

For the purpose of SDM verification, the plant is considered to have been at equilibrium conditions if the power level did not vary more than +/-5% RTP in the 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months before shutdown. ___JO _

PREREQUISITES None ADMNRC06RO.doc 06 7

Answer Key PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 15 PAGE 6 OF 6 TITLE: SHUTDOWN MARGIN DETERMINATION UNITS 1 AND 2 PERF PROCEDURE Determine the correct Data Sheet or STP to use:

for Initial Which MODE With Use Selected 1 Normal conditions STP I-1A 1 Stuck Rod(s) STP R-19 DATA SHEET 1 1 a Dropped Rod STP R-19 DATA SHEET 4 2 Normal conditions STP I-1A 2 ECP Criticality STP R-17 2 Stuck Rod(s) STP R-19 DATA SHEET 1 2 Physics Testing in progress STP R-6 2 a Dropped Rod STP R-19 DATA SHEET 4 3 Normal conditions STP R-19 DATA SHEET 2 or STP I-1B 3 Stuck Rod(s) STP R-19 DATA SHEET 2 JO 3 Shutdown Banks Out STP R-19 DATA SHEET 3 3 Rod Drop Testing STP R-19 DATA SHEET 3 3 Physics Testing in progress STP R-19 DATA SHEET 2 4 Normal conditions STP R-19 DATA SHEET 2 or STP I-1B 4 Stuck Rod(s) STP R-19 DATA SHEET 2 5 Normal conditions STP R-19 DATA SHEET 2 or STP I-1B 5 For Mode 6 Entry STP I-1B 5 Stuck Rods STP R-19 DATA SHEET 2 6 Normal conditions STP I-1B If the method is Data Sheet 2: N/A [ ]

If the reactor was not at equilibrium conditions prior to shutdown, consult Reactor Engineering before continuing. It may be necessary to calculate Xenon and Samarium worths for Section C of the Data Sheet.

N/A [ ] ______

ADMNRC06RO.doc 06 8

Answer Key PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 15 PAGE 6 OF 6 TITLE: SHUTDOWN MARGIN DETERMINATION UNITS 1 AND 2 PERF CAUTION: If credit is taken for Xe/Sm, the SDM calculation must be repeated every four hours For conservatism and ease of calculation, Xe/Sm may be ignored. This will increase the required boron concentration and therefore may not be desirable at EOL.

N/A [ ] ___ JO ___

If the "APEX" code is used to calculate xenon and samarium worths, assume "N-1" rods and no boron (see Reference 6.8 as needed).

N/A [X] ______

REVIEW AND ROUTING SFM Review completed procedure. If Acceptance Criteria are not met, refer to the applicable LCO and initiate an Action Request.

AR # _________________________

REMARKS: 1- 12.2.1 This R-19 is for Xe/Sm free Reviewed By: Date/Time /

Shift Foreman PPE (Reactor Engineering) review test for completeness and acceptability.

REMARKS:

Reviewed By: Date PPE (Reactor Engineering)

ADMNRC06RO.doc 06 9

Answer Key 69-9241 05/31/00 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:

STP R-19 ATTACHMENT 8.1 1 2 AND Data Sheet 1, SHUTDOWN MARGIN Calculation in MODES 1 and 2 with Stuck Control Rods*

UNIT _____ CYCLE _____ MODE __________ DATE _____________ TIME ____________

1. CURRENT CORE CONDITIONS (for time of SDM)

a. Control bank position c. Power level _________% RTP (bank/step) ______/_____ d. Burnup (from PEP R-5) _________MWD/T

b. Boron concentration _________ ppm e. Number of stuck rods** _________

2. AVAILABLE ROD WORTH FOR SHUTDOWN Available rod worth for shutdown from Volume 9, Section IB at control bank position (Step 1.a.) and burnup (Step 1.d.). Use Figure R19-1F-2 (Unit 1) or Figure R19-2F-2 (Unit 2) (-)_______ pcm

3. POWER DEFECT Total Power Defect from Volume 9, Section ID, Figure R17-1F-3 (Unit 1) or R17-2F-3 (Unit 2) at power level (Step 1.c.), boron concentration (Step 1.b.), and burnup (Step 1.d) (+)_______ pcm

4. WORTH OF STUCK ROD(S)**

a. Most reactive rod worth from Volume 9, Section ID, Table R19-1T-1 (Unit 1) or R19-2T-1 (Unit 2) (+)_______ pcm

b. Total stuck rod worth (Step 4.a. x Step 1.e.) (+)_______ pcm

5. AVAILABLE SHUTDOWN WORTH Total net worth of withdrawn rod banks, power defect and stuck RCCA's (Step 2 + Step 3 + Step 4.b)

(-)_______ PCM

6. SHUTDOWN MARGIN

% K/K Shutdown (Step 5 ÷ (-1000)) __________%K/K YES NO

7. MINIMUM SHUTDOWN MARGIN DETERMINATION Is the SHUTDOWN MARGIN determined in Step 6 greater than or equal to

+1.6% K/K? [ ] [ ]

If the answer is YES, the core has sufficient SHUTDOWN MARGIN. If the answer is NO, immediately follow the appropriate Tech Spec Action Statement, notify the Shift Foreman, and submit an Action Request.

NOTE: If no immovable or untrippable control rods, use STP I-1A to verify SHUTDOWN MARGIN

- NOTE: Stuck is defined as untrippable or immovable due to excessive friction or mechanical interference.

REMARKS:

PERFORMED BY __________________________________ DATE/TIME ____________/ ____________

REVIEWED BY ____________________________________ DATE/TIME ____________/ ____________

hift Foreman)

REVIEWED BY ____________________________________ DATE _________________

E (Reactor Engineering)

ADMNRC06RO.doc 06 7 6

69-11137-1 05/31/00 Page 1 of 1 Answer Key DIABLO CANYON POWER PLANT TITLE:

STP R-19 ATTACHMENT 8.2 Data Sheet 2, SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods 1 2 AND A. UNIT 1 CYCLE 12 MODE 3 DATE Today TIME Now WARNING : 1. With stuck* rod(s), perform this calculation within ONE hour and every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

2. If credit is taken for Xenon (Step C.2), repeat this calculation at least every FOUR hours.

B. CURRENT CORE CONDITIONS F. REQUIRED BORON CONCENTRATION (At the time of this SDM Calculation) 1. Minimum required boron

1. RCS Temperature (TAVG) __ 548_ ___ ºF concentration for Temp B.1 and

2. RCS Boron Concentration __1356____ PPM burnup B.3 from R19-1T-2 or R19-2T-2 __1211_____ PPM

3. Core Avg Burnup (PEP R-5) MWD 2. Add 100 PPM to concentration F.1 __1311_____ PPM

___127____ MTU NOTE: If Steps C, D & E = N/A, skip to F.8 and

4. Time Since Plant Shutdown [ ] N/A enter concentration F.2 (N/A startup after refueling) ____23____ HRS 3. Boron worth for concentration

___________________________________________________ F.2 and Temp B.1 from C. XENON AND SAMARIUM WORTH [X] N/A R19-1T-5 or R19-2T-5 ()

__10125____ PCM (If no credit is taken for Xe/Sm, check N/A, Circle Table per B.3: BOL MOL EOL enter Ø pcm in Step C.4, and go to Step D.) 4. Boron worth multiplier for worth YES NO N/A C.4 from R17-1F-1 or R17-2F-1 ____1______

(If Step C.4 = Ø pcm, enter 1)

1. Power history determined 5. Boron worth corrected for and attached [ ] [ ] [ ] Xe/Sm (F.3 x F.4) ()

__10125____ PCM

2. If at equilibrium, estimated 6. Total worth corrections Xenon worth from R17-1T-2 (C.4 + D.5 + E.1) ( +) __680______ PCM or R17-2T-2 () ___________ PCM 7. Net required boron worth Circle Table per B.3: BOL MOL EOL (F.5 - F.6) ( -)

__10805_____ PCM

3. If at equilibrium, Samarium If positive, enter Ø pcm worth from R17-1T-3 or 8. Required boron concentration R17-2T-3 () ___________ PCM for worth F.7, and Temp B.1 from

4. Total Xe & Sm worth R19-1T-5 or R19-2T-5 __1216_____ PPM (C.2 + C.3) or "APEX" Select Table per B.3: BOL MOL EOL output or zero () ____0______ PCM D. WITHDRAWN ROD/BANK WORTH (N/A if APEX) [ ] N/A G. ACCEPTANCE CRITERIA (If any rods not FULLY inserted, do not 1. Is the actual boron concentration B.2 greater than enter Ø pcm in Step D.5.) or equal to the required concentration F.8?

1. Most reactive rod worth [X] YES (ACCEPTABLE) [ ] NO (NOT ACCEPTABLE) from R19-1T-1 or R19-2T-1 (+) __680______ PCM If this SDM is NOT ACCEPTABLE immediately

2. Number of stuck rods* ____1______ follow the appropriate Tech Spec Action Statement,

3. Total stuck rod worth (+) __680______ PCM notify the SFM, and submit an Action Request.

(D.1 x D.2)

4. Worth of withdrawn rod/bank __________________________________________________________

during physics tests N/A [ ](+) _____0_____ PCM H. OPTIONAL EXPLICIT SDM CALCULATION

5. Total stuck and withdrawn 1. Boron worth for concentration B.2 rod worth (D.3 + D.4) (+) ___680_____ PCM and Temp. B.1 from R19-1T-5 or (not zero if any rods out) R19-2T-5 ()

___________ PCM

____________________________________________________ Select Table per B.3: BOL MOL EOL E. SDM REQUIREMENT CORRECTION [X] N/A 2. Total Present Worth

1. If this SDM calculation is for (H.1 + C.4 + D.5 - 1600 pcm) ()

___________ PCM MODE 5 (B.1 200ºF), enter 3. Actual SHUTDOWN MARGIN

-600 pcm, or check N/A ( ) __________ PCM (H.2 - F.3)/(-1000 x F.4) ( )

Stuck is defined as untrippable or immovable due to excessive friction or mechanical interference.

REMARKS ______________________________________________________________________________________________________________________

ADMNRC06RO.doc 06 8 7

69-11137-1 05/31/00 Page 2 of 1 STP R-19 (UNITS 1 AND 2)

ATTACHMENT 8.2 TITLE: Data Sheet 2, SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods PERFORMED BY Joe Operator DATE Today TIME Now REVIEWED BY DATE TIME Shift Foreman REVIEWED BY: DATE TIME PPE (Reactor Engineering) 00393511.06 2

69-9242 05/31/00 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:

STP R-19 ATTACHMENT 8.3 1 2 AND Data Sheet 3, SHUTDOWN MARGIN Verification, MODE 3 to Pull or with S/D Banks Out or Rod Drop Testing UNIT _______ CYCLE ____________ DATE _______________ TIME _______________

This SHUTDOWN MARGIN verification is for MODE 3 to pull or with Shutdown Banks out or to perform rod drop testing.

WARNING: If Xenon is present, this calculation should be repeated at least every FOUR hours.

ACTUAL CORE CONDITIONS (at the time of SDM calculation)

a. Core average cycle burnup (PEP R-5) __________ MWD/T

b. Moderator average temperature (Tavg) __________ °F

c. RCS boron concentration __________ ppm MINIMUM REQUIRED BORON CONCENTRATION

a. Obtain the MINIMUM REQUIRED BORON CONCENTRATION for MODE 6 listed on Table R19-1(2)T-1 or perform an ECP calculation per STP R-17. Assume rods are at or above the zero power rod insertion limit for R-17.

b. Required boron concentration determined in Step 2.a. above.

Attach R-17 calculation if performed __________ ppm YES NO

c. Is the actual boron concentration in the core (Step 1.c) greater than or equal to the required boron concentration (Step 2.b)? [] [ ]

d. Is the moderator average temperature (Step 1.b) equal to or greater than 541°F? [] [ ]

SHUTDOWN MARGIN ACCEPTABILITY Answers to 2.c and 2.d:

[ ] both YES (ACCEPTABLE) [ ] any NO (NOT ACCEPTABLE)

If this SDM is NOT ACCEPTABLE, immediately comply with the appropriate Technical Specification Action Statement, notify the SFM and submit an Action Request.

REMARKS:

PERFORMED BY ______________________________________ DATE/TIME __________/ ___________

REVIEWED BY _______________________________________ DATE/TIME __________/ ___________

M REVIEWED BY _______________________________________ DATE ___________________

PPE (Reactor Engineering)

ADMNRC06RO.doc 06 9 8

05/31/00 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:

STP R-19 ATTACHMENT 8.4 1 2 Data Sheet 4, SHUTDOWN MARGIN Calculation in MODES 1 and with a Dropped AND Control Rod UNIT _____ CYCLE _____ MODE __________ DATE _____________ TIME ____________

1. CURRENT CORE CONDITIONS (for time of SDM)

a. Control bank position c. Power level _________% RTP (bank/step) ______/_____ d. Burnup (from PEP R-5) _________MWD/T

b. Boron concentration _________ ppm e. Number of dropped rods _________

2. AVAILABLE ROD WORTH FOR SHUTDOWN Available rod worth for shutdown from Volume 9, Section IB at control bank position (Step 1.a.). Use Figure R19-1F-2 (Unit 1) or Figure R19-2F-2 (Unit 2) (-)_______ pcm

3. POWER DEFECT Total Power Defect from Volume 9, Section ID, Figure R17-1F-3 (Unit 1) or R17-2F-3 (Unit 2) at power level (Step 1.c.), boron concentration (Step 1.b.), and burnup (Step 1.d) (+)_______ pcm

4. MAXIMUM WORTH OF DROPPED ROD(S)

a. Most reactive rod worth from Volume 9, Section ID, Table R19-1T-1 (Unit 1) or R19-2T-1 (Unit 2) (+)_______ pcm

b. Total dropped rod worth (Step 4.a. x Step 1.e.) (+)_______ pcm

5. AVAILABLE SHUTDOWN WORTH Total net worth of withdrawn rod banks, power defect and dropped RCCA's (Step 2 + Step 3 + Step 4.b)

(-)_______ PCM

6. SHUTDOWN MARGIN

% K/K Shutdown (Step 5 ÷ (-1000)) __________%K/K YES NO

7. MINIMUM SHUTDOWN MARGIN DETERMINATION Is the SHUTDOWN MARGIN determined in Step 6 greater than or equal to

+1.6% K/K? [ ] [ ]

If the answer is YES, the core has sufficient SHUTDOWN MARGIN. If the answer is NO, immediately comply with the appropriate Technical Specification Action Statement, notify the Shift Foreman, and submit an Action Request.

REMARKS:

PERFORMED BY ___________________________________________DATE/TIME ___________/ ___________

REVIEWED BY ____________________________________________DATE/TIME ___________/ ___________

(Shift Foreman)

REVIEWED BY ____________________________________________DATE _______________

PPE (Reactor Engineering)

ADMNRC06RO.doc 06 10 9

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT Job Performance Measure Number: ADMNRC-06SRO

Title:

VERIFY SHUTDOWN MARGIN CALCULATION Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments:

References:

STP R-19, Shutdown Margin Determination Table R19-1T-5, Rev 14 ITS 3.1.1, Shutdown Margin Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 8,9,10 Job Designation: SRO KA Number: G2.1.25, Ability to Obtain and Interpret Station Reference Material Rating: 3.1 AUTHOR: JACK BLACKWELL DATE : 2/13/2003 REVIEWED BY: N/A DATE :

JPM COORDINATOR APPROVED BY: N/A DATE :

TRAINING LEADER REV. 0

JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: ADMNRC-06SRO INSTRUCTOR W ORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: Copy of completed STP R-19, Shutdown Margin Determination Initial Conditions: Unit 1 tripped from 100% power 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months ago. Rod K6 did not insert into the core and is stuck at 220 steps. Current conditions are: TAVG =

548°F, CB = 1356, Core Burnup = 127 MWD/MTU.

Initiating Cue: The CO has completed a manual calculation of STP R-19, Shutdown Margin Determination, taking NO credit for Xe/Sm and without APEX, and is ready for your review.

Task Standard: Completed SDM Determination verification.

ADMNRC06SRO.DOC PAGE 2 OF 14 REV. 0

JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: ADMNRC-06SRO INSTRUCTOR W ORKSHEET Start Time:

Step Expected Operator Actions

1. Verifies Start Data Section 1.1 Notes Unit (1), Mode (3) and Date/Time 1.2 Reviews Precautions and Limitations and initials Step SAT:___________ UNSAT:________*

2. Verifies which data sheet to use 2.1 Verifies data sheet 2 of STP R-19 must be used 2.2 Verifies information concerning data sheet 2 NOTE: May enter Remark noting this is a Xe/SM calculation.

Step SAT:___________ UNSAT:________*

3. Verifies Section A of Data Sheet 2 3.1 Verifies correct input:

completed correctly Unit 1, Cycle 12, Mode 3, Todays Date and Time Step SAT:___________ UNSAT:________*

4. Verifies Section B completed 4.1 Verifies input:

correctly TAVG = 548°F, CB = 1356, Core Burnup = 127 MWD/MTU, Time since Shutdown = 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months Step SAT:___________ UNSAT:________*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC06SRO.DOC PAGE 3 OF 14 REV. 0

JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: ADMNRC-06SRO INSTRUCTOR W ORKSHEET Step Expected Operator Actions

5. Verifies Section C completed 51 Determines Section C is N/A and verifies 0 correctly entered in Step C.4 Step SAT:___________ UNSAT:________*

6. Verifies Section D completed 6.1 Verifies:

correctly

Most reactive rod worth = 680 pcm

Stuck rods = 1

Total stuck rod worth = 680 pcm

Worth of withdrawn rod is N/A CUE: When asked physics testing data on stuck rod, feedback this will not be included in the calculation and to mark it N/A.

6.2 Verifies total stuck rod worth is 680 pcm Step SAT:___________ UNSAT:________*

7. Verifies Section E competed 7.1 Verifies Section E does not apply and marked correctly N/A Step SAT:___________ UNSAT:________*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC06SRO.DOC PAGE 4 OF 14 REV. 0

JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: ADMNRC-06SRO INSTRUCTOR W ORKSHEET Step Expected Operator Actions

8. ** Verifies Section F completed 8.1 Verifies:

correctly

Minimum CB to 548°F is 1211 ppm

Add 100 ppm to have 1311 ppm

Boron Worth for 1311 at 548°F = 10125 pcm

Boron worth multiplier = 1

Total worth corrections = +680 pcm

Net required boron worth = -9445 pcm

Required CB per BOL table = 1216 ppm Step SAT:___________ UNSAT:________*

9. ** Determine error in calculation 9.1 Determines Net required boron is -10805 +/_

20 pcm, NOT -9445 pcm 9.2 Determines Required CB per BOL table = 1405

+/- 10 ppm Step SAT:___________ UNSAT:________*

10. ** Verifies Section G completed 10.1 Verifies Actual CB of 1356 ppm < Required CB correctly of 1405 +/- 10 ppm 10.2 Determines ITS 3.1.1 requires boration initiated within 15 minutes to achieve > 1405

+/- 10 ppm Step SAT:___________ UNSAT:________*

Stop Time: ___________

Total Time: ___________

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC06SRO.DOC PAGE 5 OF 14 REV. 0

JPM NUMBER: ADMNRC-06SRO EXAMINEE CUE SHEET Initial Conditions: Unit 1 tripped from 100% power 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months ago. Rod K6 did not insert into the core and is stuck at 220 steps. Conditions at the time of trip were: TAVG = 548°F, CB = 1356, Core Burnup = 127 MWD/MTU.

Initiating Cue: The CO has completed a manual calculation of STP R-19, Shutdown Margin Determination, taking NO credit for Xe/Sm and without APEX, and is ready for your review.

Task Standard: Completed SDM Determination verification.

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

ADMNRC06SRO.DOC PAGE 6 OF 14 REV. 0

PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 15 PAGE 4 OF 6 TITLE: SHUTDOWN MARGIN DETERMINATION UNITS 1 AND 2 START DATA SECTION UNIT 1 OPERATING MODE 3 DATE/TIME Today/Now PRECAUTIONS AND LIMITATIONS INITIALS Wherever a (+) or (-) sign is given on data sheets, the correct number may be entered with no other signs. ___ JO ___

For the purpose of SDM verification, the plant is considered to have been at equilibrium conditions if the power level did not vary more than +/-5% RTP in the 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months before shutdown. ___ JO ___

PREREQUISITES None ADMNRC06SRO.doc 06 7

PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 15 PAGE 6 OF 6 TITLE: SHUTDOWN MARGIN DETERMINATION UNITS 1 AND 2 PERF PROCEDURE Determine the correct Data Sheet or STP to use:

for Initial Which MODE With Use Selected 1 Normal conditions STP I-1A 1 Stuck Rod(s) STP R-19 DATA SHEET 1 1 a Dropped Rod STP R-19 DATA SHEET 4 2 Normal conditions STP I-1A 2 ECP Criticality STP R-17 2 Stuck Rod(s) STP R-19 DATA SHEET 1 2 Physics Testing in progress STP R-6 2 a Dropped Rod STP R-19 DATA SHEET 4 3 Normal conditions STP R-19 DATA SHEET 2 or STP I-1B 3 Stuck Rod(s) STP R-19 DATA SHEET 2 3 Shutdown Banks Out STP R-19 DATA SHEET 3 3 Rod Drop Testing STP R-19 DATA SHEET 3 3 Physics Testing in progress STP R-19 DATA SHEET 2 4 Normal conditions STP R-19 DATA SHEET 2 or STP I-1B 4 Stuck Rod(s) STP R-19 DATA SHEET 2 5 Normal conditions STP R-19 DATA SHEET 2 or STP I-1B 5 For Mode 6 Entry STP I-1B 5 Stuck Rods STP R-19 DATA SHEET 2 6 Normal conditions STP I-1B If the method is Data Sheet 2: N/A [ ]

If the reactor was not at equilibrium conditions prior to shutdown, consult Reactor Engineering before continuing. It may be necessary to calculate Xenon and Samarium worths for Section C of the Data Sheet.

N/A [X] ______

ADMNRC06SRO.doc 06 8

PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 15 PAGE 6 OF 6 TITLE: SHUTDOWN MARGIN DETERMINATION UNITS 1 AND 2 PERF CAUTION: If credit is taken for Xe/Sm, the SDM calculation must be repeated every four hours For conservatism and ease of calculation, Xe/Sm may be ignored. This will increase the required boron concentration and therefore may not be desirable at EOL.

N/A [ ] ___ JO ___

If the "APEX" code is used to calculate xenon and samarium worths, assume "N-1" rods and no boron (see Reference 6.8 as needed).

N/A [X] ______

REVIEW AND ROUTING SFM Review completed procedure. If Acceptance Criteria are not met, refer to the applicable LCO and initiate an Action Request.

AR # _________________________

REMARKS: 1- 12.2.1 This R-19 is for Xe/Sm free Reviewed By: Date/Time /

Shift Foreman PPE (Reactor Engineering) review test for completeness and acceptability.

REMARKS:

Reviewed By: Date PPE (Reactor Engineering)

ADMNRC06SRO.doc 06 9

69-9241 05/31/00 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:

STP R-19 ATTACHMENT 8.1 1 2 AND Data Sheet 1, SHUTDOWN MARGIN Calculation in MODES 1 and 2 with Stuck Control Rods*

UNIT _____ CYCLE _____ MODE __________ DATE _____________ TIME ____________

1. CURRENT CORE CONDITIONS (for time of SDM)

a. Control bank position c. Power level _________% RTP (bank/step) ______/_____ d. Burnup (from PEP R-5) _________MWD/T

b. Boron concentration _________ ppm e. Number of stuck rods** _________

2. AVAILABLE ROD WORTH FOR SHUTDOWN Available rod worth for shutdown from Volume 9, Section IB at control bank position (Step 1.a.) and burnup (Step 1.d.). Use Figure R19-1F-2 (Unit 1) or Figure R19-2F-2 (Unit 2) (-)_______ pcm

3. POWER DEFECT Total Power Defect from Volume 9, Section ID, Figure R17-1F-3 (Unit 1) or R17-2F-3 (Unit 2) at power level (Step 1.c.), boron concentration (Step 1.b.), and burnup (Step 1.d) (+)_______ pcm

4. WORTH OF STUCK ROD(S)**

a. Most reactive rod worth from Volume 9, Section ID, Table R19-1T-1 (Unit 1) or R19-2T-1 (Unit 2) (+)_______ pcm

b. Total stuck rod worth (Step 4.a. x Step 1.e.) (+)_______ pcm

5. AVAILABLE SHUTDOWN WORTH Total net worth of withdrawn rod banks, power defect and stuck RCCA's (Step 2 + Step 3 + Step 4.b)

(-)_______ PCM

6. SHUTDOWN MARGIN

% K/K Shutdown (Step 5 ÷ (-1000)) __________%K/K YES NO

7. MINIMUM SHUTDOWN MARGIN DETERMINATION Is the SHUTDOWN MARGIN determined in Step 6 greater than or equal to

+1.6% K/K? [ ] [ ]

If the answer is YES, the core has sufficient SHUTDOWN MARGIN. If the answer is NO, immediately follow the appropriate Tech Spec Action Statement, notify the Shift Foreman, and submit an Action Request.

NOTE: If no immovable or untrippable control rods, use STP I-1A to verify SHUTDOWN MARGIN

- NOTE: Stuck is defined as untrippable or immovable due to excessive friction or mechanical interference.

REMARKS:

PERFORMED BY ___________________________________________DATE/TIME ____________/ ____________

REVIEWED BY ____________________________________________DATE/TIME ____________/ ____________

(Shift Foreman)

REVIEWED BY ____________________________________________DATE _________________

PPE (Reactor Engineering)

ADMNRC06SRO.doc 06 7 6

69-11137-1 05/31/00 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE: