ML112031001
| ML112031001 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/01/2011 |
| From: | NRC Region 1 |
| To: | |
| JACKSON D RGN-I/DRS/OB/610-337-5306 | |
| Shared Package | |
| ML110030662 | List: |
| References | |
| TAC U01832 | |
| Download: ML112031001 (515) | |
Text
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Determine QPTR, Analyze Results and Make Recommendations.
JPM Number: NRC RO A.1.1 (JPM-051) Revision: 1 chg 2 Initiated:
Dave Minnich 03/10/11 Developer Date Reviewed:
Robert Royce 5/9/11 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 03/10/11 Updated JPM to revision 004-08 to SP 31012. Modified ..IPM 11 (I format to be consistent with the NRC 2K11 JPM set.
Removed JPM steps associated with specific steps in AOP 3552, in that it added no value to this JPM. This did not remove any critical steps and shortened the overall time required to conduct the JPM. DLM 6/2/11 Modified the JPM to give the PRNI upper and lower detector 1 11 currents, and the average percent reactor power, as part of initial conditions. This resulted in modifying initial conditions, the initial cue, renumbering of steps and an additional !
handout. This will allow for efficient administration of the JPM in the classroom environment. Changed the applicable KIA from 2.1.19, to 2.1.20 for a better match. These changes are a result of NRC Exam comments on 5/2511. Added a calculator to required materials.
! 6/22/11 Corrected a typographical error in the comments associated 1 12 with JPM step 12; 'QPTR DOES exceed 1.02 on channel 44 (worst case).' It previously read channel 43. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep I Week).
2
JPM WORKSHEET Facility: _M_P_3_ _ __ Examinee:
JPM Number: NRC ROA.1.1 Revision: 1 chg 2 Task
Title:
Determine QPTR, Analyze Results and Make Recommendations.
System: Conduct of Operations Time Critical Task: ) YES (X) NO Validated Time (minutes): ___1...;..5_ _
Task Number(s): 341~01~788 Applicable To: SRO RO X PEO KIA Number: GEN.2.1.20 KIA Rating:
- -3.9/3.8 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In~Plant:
Task Standards: Perform a QPTR Required Materials: SP 31012, Quadrant Power Tilt Ratio, Rev. 004-08
{procedures, equipment, etc.}
Cycle 14 Middle of Life RE Curve and Data Book Calculator General
References:
MP3 Tech Specs AOP 3552, Malfunction of the Rod Drive System, Rev. 010-01 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: NRC RO A.1.1 Revision: 1 chg 2 Simulator Requirements: NONE Initial Conditions: The plant was at 100% power when Control Rod D4 dropped. The crew is carrying out the actions of AOP 3552, Malfunction of the Rod Drive System, Attachment B; Dropped Rod. The crew is at step 2.b of Attachment B (Determine QPTR). The PPC is out of service. NI channel recalibration is NOT in progress. You are the extra licensed operator on shift.
Initiating Cues: The US has directed you to determine QPTR using SP 31012, Quadrant Power Tilt Ratio, Section 4.2: QPTR By Measurement. The RO has already recorded average percent reactor power, and upper and lower detector readings on Attachment 1 to SP 31012.
- *
- 1< NOTES TO TASK PERFORMANCE EVALUATOR 1<
- 1< 1<
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: NRC RO A.1.1 Revision: 1 chg 2 Task
Title:
Determine QPTR, Analyze Results and Make Recommendations.
START TIME: _ _ __
PERFORMANCE STANDARD STEP Obtain proper Surveillance Procedure. Candidate obtains and refers to SP Critical: Grade
- 1 31012, Quadrant Power Tilt Ratio, Y[ ] S[ ]
SP 31012 Section 4.2: QPTR By Measurement. N[X] U[ ]
Step 2.1 Comments: When the Candidate requests or takes action to obtain SP 31012, provide the Candidate a copy of SP 31012, Quadrant Power Tilt Ratio, the partially completed QPTR Surveillance Attachment 1 (Handout 1).
Also provide a copy of the Cycle 14 Middle of Life RE Curve and Data Book to the Candidate (Handout 2, which gives the 100% NI Currents, are contained therein).
Cue:
STEP VERIFY "General Prerequisites" Candidate verifies 1STest Authorized By" Critical: Grade
- 2 completed. block is signed on SP 31012, Attachment Y[ ] S[]
SP 31012 1 Cover Sheet. N[X] U[ ]
Step 2.1 Reviews SP 31012, Section 3 Critical: Grade PRECAUTIONS Y[ ] S[ ]
N[X] U[ ]
Candidate initials for 'Prerequisites Critical: Grade Completed' and 'Precautions Noted' on Y[ ] S[ ]
Attachment 1 Cover Sheet. N[X] U[ ]
Comments:
Cue:
5
STEP QPTR By Measurement Candidate recognizes that average Critical: Grade
- 3 percent reactor power has already been Y[ ] S[ ]
RECORD average percent reactor power recorded on Attachment 1. N[X] U[ ]
SP 31012 Step 4.2.1 from NI cabinet meters NMP--NM41 F through NMP--NM44F or from the Plant Process Computer Calorimetric (CVRXPO) on Attachment 1.
Comments:
Cue:
STEP DETERMINE QPTR as follows: Candidate reviews the NOTE. Critical: Grade
- 4 Y[ ] S[ ]
SP 31012 N[X] U[ ]
Step 4.2.2 Attachment 2, "100% NI Currents," is NOTE maintained in the "Reactor Engineering Curve and Data Book."
Comments:
Cue:
STEP RECORD available upper and lower Candidate recognizes that upper and Critical: Grade
- 5 detector readings on Attachment 1. lower detector readings have already Y[X] S[ ]
been recorded on Attachment 1. N[ ] U[ ]
SP 31012 Step 4.2.2.a Comments:
Cue:
STEP On Attachment 1, RECORD 100% NI upper Candidate identifies and records the Critical: Grade
- 6 and lower currents obtained from correct 100% NI upper and lower currents Y[X] S[ ]
Attachment 2. on Attachment 1, for PRNI channels 41 N[ ] U[ ]
SP 31012 Step 4.2.2.b through 44.
I .....
6
,--~~
Comments: These 100% NI currents will be obtained from the Cycle 14 Middle of Life RE Curve and Data Book, Misc.
Data form RE-G-02 _(Handout 2).
Cue:
STEP RECORD data source and date of Locates Remarks" section on Attachment Critical: Grade
- 7 Attachment 2 entry in "Remarks" section 1 and records data source (RE Curve and Y[ J s[]
SP 31012 N[X] U[ ]
on Attachment 1 Data Book) and date of Attachment 2 Step 4.2.2.c entry.
Comments:
Cue:
STEP CALCULATE the detector ratio for each Candidate divides each detectors reading Critical: Grade
- 8 detector by dividing each detectors by that detectors 100% current to Y[X] S[]
determine the detector ratio for the upper N[ ] U[ ]
SP 31012 reading by that detectors 100% current Step 4.2.2.d and RECORD on Attachment 1. and lower detectors of PRNI channels 41 through 44.
- Comments:
Cue:
- Candidate records the detector ratios on Critical: Grade Attachment 1, for the upper and lower Y[ ] S[ ]
detectors. N[X] U[ ]
I Comments: The JPM Key (correctly completed Attachment;) shows the detector ratios that the Candidate should record. i Cue:
- STEP CALCULATE the average upper and lower Candidate calculates the average upper Critical: Grade
- 9 ratio and RECORD on Attachment 1. and lower detector ratios.
Y[X] S[ ]
N[ ] U[ ]
SP 31012 Step 4.2.2.e Comments: I Cue:
7
Candidate records the average upper and Critical: Grade lower detector ratios on Attachment 1 .
Y[ ] s[]
N[X] U[ ]
Comments: The JPM Key (correctly completed Attachment 1) shows the average upper and lower detector ratios that the Candidate should record.
Cue:
STEP Using the following equation, CALCULATE Candidate determines the power tilt Critical: Grade
- 10 power tilt for each detector and RECORD (QPTR) for the upper and lower detectors Y[X] S[ ]
in "QPTR" section of Attachment 1: associated with PRNI channel 41 through N[ ] U[ ]
SP 31012 Step 4.2.4.f 44 by dividing each detectors detector
=
Upper QPTR (Upper Detector Ratio) + ratio by the average ratio.
(Average Upper Ratio)
=
Lower QPTR (Lower Detector Ratio) +
(Average Lower Ratio)
Comments:
Cue:
Candidate records upper and lower Critical: Grade*
QPTR values in the "QPTR" section of Y[ ] S[ ]
Attachment 1. N[X] U[ ]
i Comments: The JPM Key (correctly completed Attachment 1) shows the QPTR values that the Candidate should I record in the 'QPTR' section.
Cue: I STEP RECORD maximum upper and lower Determines maximum upper and lower Critical: Grade
SP 31012 Attachment 1. N[ ] U[ ]
Step 4.2.4.f i
ICandidate records maximum upper and lower detector QPTR and associated channel on Attachment 1 .
Critical:
Y[ ]
N[X]
Grade S[ ]
U[ ]
'----- --~ ...........- . - -............- . - - .............- . - -........ -.. --~ .......... -..--- -- ............ -.-~
I 8
Comments: The JPM Key (correctly completed Attachment 1) shows the maximum upper and lower QPTR values and their associated channel.
Cue:
STEP VERIFY the following acceptance Candidate recognizes from calculated Critical: Grade
- 12 criteria are met: average reactor power (JPM step 4) that Y[ ] S[ ]
reactor power is greater than 50%. N[X] U[ ]
SP 31012 Step 4.2.3.a WHEN above 50% of Rated Thermal Power (RTP), VERIFY maximum QPTR does not exceed 1.02.
Comments:
Cue:
Candidate recognizes that QPTR IS Critical: Grade greater than 1.02. Y[X] S[ ]
N[ ] U[ ]
Comments: The JPM Key (correctly completed Attachment 1) shows QPTR DOES exceed 1.02 on channel 44 (worst case) upper and lower detectors.
Cue:
STEP IF QPTR is greater than 1.02 and power Candidate informs the US that QPTR is Critical: Grade
- 13 is above 50% RTP, NOTIFY Shift greater than 1.02 and that Technical Y[X1 S[ ]
Specification 3/4.2.4, "Quadrant Power N[ ] U[ ]
SP 31012 Manager that Technical Specification Step 4.2.3.b 3/4.2.4, "Quadrant Power Tilt Ratio," Tilt Ratio," action statement applies.
action statement applies.
Comments: I Cue: TERMINATION CUE: Acknowledge the Candidate's report and reply that the US is referring to T/S 3/4.2.4.
The evaluation for this JPM is concluded.
I STOP TIME: _ _ __
9
VERIFICATION OF JPM COMPLETION JPM Number: NRC RO A.1.1 Revision: 1 chg 2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 15 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
10
STUDENT HANDOUT JPM Number: NRC RO A.1.1 Revision: 1 chg 2 Initial Conditions: The plant was at 100% power when Control Rod 04 dropped. The crew is carrying out the actions of AOP 3552, Malfunction of the Rod Drive System, Attachment B; Dropped Rod. The crew is at step 2.b of Attachment B (Determine QPTR). The PPC is out of service. NI channel recalibration is NOT in progress. You are the extra licensed operator on shift.
Initiating Cues: The US has directed you to determine QPTR using SP 31012, Quadrant Power Tilt Ratio, Section 4.2: QPTR By Measurement.
The RO has already recorded average percent reactor power, and upper and lower detector readings on Attachment 1 to SP 31012.
11
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Perform a Shutdown Margin for MODE 3 with One Stuck Control Rod.
JPM Number: NRC RO A.1.2 (JPM 07BA) Revision: 2 chg 1 Initiated:
Dave Minnich 03/08/11 Developer Date Reviewed:
Robert Royce 516/11 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE I 03/08/11 Modified initial conditions to present cycle (14) conditions. 210 Modified JPM format to be consistent with the NRC 2K11 JPM set. Added critical steps (JPM-078A had no critical steps). DLM 6/22111 Added additional information to Initial Conditions on the 2/1 status of the Shutdown Margin Monitor channels. Moved a cue that was within the body of the JPM (perform a xenon correction), up into the initializing cue. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility: Millstone Unit 3 Examinee:
JPIVI Number: NRC RO A.1.2 Revision: 2 chg 1 Task
Title:
Perform a Shutdown Margin for MODE 3 with One Stuck Control Rod.
System: 001 (Control Rod Drive System)
Time Critical Task: ) YES (X) NO Validated Time (minutes): _ _..; . 3. ; . 0_ _
Task Number(s): 341-01-187 Applicable To: SRO RO PEO KIA 001-A4.11 KIA Rating: 3.5/4.1 Number: 2.1.25 3.9/4.2 Method of Testing: Simulated Actual x Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Correctly determines SHUTDOWN MARGIN Reguired Materials: OP 3209B Shutdown Margin (rev 010-06), Form 3209B-002 (rev 008 (procedures, equipment, etc.) 02), and Cycle 14 Middle of Life RE Curve Book General
References:
Unit 3 Technical Specifications, Technical Requirements 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: NRC ROA.1.2 Revision: 2 chg 1 Initial Conditions: Thirty minutes ago, the plant tripped from 100% steady-state equilibrium power after 2 months of operation. Control rod M-4 failed to insert on the trip. All other plant components and systems responded as designed. The plant is presently in MODE 3, and stable at normal temperature and pressure.
Other plant conditions are:
- Core Burnup is 10,500 MWD/MTU
- Both SMM channels are OPERABLE. Neither SMM channel is OPERABLE based solely on TS LeO 3.3.S.b.1 or 3.3.S.b.2.
Initiating Cues: The US has directed you to calculate SHUTDOWN MARGIN for current plant conditions per OP 3209B, Shutdown Margin.
If Shutdown Margin is not adequate for current plant conditions, perform a xenon correction for the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Assume it is one hour post trip for the xenon correction. An STA review of your results is not required.
Simulator Reguirements: NONE
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: NRC RO A.1.2 Revision: 2 chg 1 Task
Title:
Perform a Shutdown Margin for MODE 3 with One Stuck Control Rod.
STARTT~E: _______
PERFORMANCE STANDARD STEP Obtains copy of OP 3209B "Shutdown Obtains proper procedure. Critical: Grade
- 1 Margin". Y[ ] S[ ]
N[X] U Ll Comments: When candidate identifies that form 3209B-002 is required, provide a copy of the form.
Cue:
i STEP VERIFY "General Prerequisites" Candidate verifies "Test Authorized By" Critical: Grade
- 2 completed. block is signed on FORM 3209B-002. Y[ ] S[ ]
OP 3209B, N[X] U[ ]
step 4.2.1 Reviews OP 3209B Section 3 Critical: Grade PRECAUTIONS Y[ ] S[ ]
N[X] U[ ]
Candidate initials for 'Prerequisites Critical: Grade Completed' and 'Precautions Noted' on Y[ ] S[ ]
FORM 3209B-002 cover sheet. N[X] U[ ]
Comments:
Cue: I STEP Refer to OP 3209B-002 and RECORD time Records time and date on OP 3209B Critical: Grade
- 3 and date. 002. Y[ ] S[ ]
OP 3209B, N[X] U[ ]
step 4.2.2 Comments:
Cue:
- I 5
~~~ ~ ~ ~ ~~-~~
STEP With DRPI deenergized, verification of rod Candidate reviews the NOTE. Critical: Grade i
- 4 position is based upon the rod position prior Y[ ] S[ ]
OP 3209B, to deenergizing the Digital Rod Position N[X] U[ ]
step 4.2.3 NOTE Indication System.
Comments:
Cue: i STEP IF determining SHUTDOWN MARGIN for Candidate circles "3" for the current Critical: Grade
- 5 current plant conditions, Refer To OP MODE on OP 3209B-002. Y[ ] S[ ]
OP 3209B, 3209B-002 and PERFORM the following in N[X] U[ J step 4.2.3.a the Current Conditions section:
CIRCLE the current MODE, and if applicable, the RCS loops' condition (Refer To Definition 2.3.4).
Comments:
Cue:
STEP OBTAIN the present core burnup value Enters "10,500" MWD/MTU on OP Critical: Grade
- 6 from the Plant Process Computer and 3209B-002. Y[ ] S[ ]
OP 3209B, DOCUMENT. N[X] U[ ]
step 4.2.3.b Comments: The value for present core burnup was given in initial plant conditions.
Cue: !
STEP PERFORM the following to determine Candidate circles "557°F" for the Critical: Grade
- 7 temperature condition: temperature condition on OP 3209B-002. Y[ ] S[ ]
OP 3209B, N[X] U[ ]
step 4.2.3.c IF in MODE 3, AND maintaining no load Tavg, CIRCLE 55rF.
Comments:
Cue:
6
STEP IF performing SHUTDOWN MARGIN Candidate calls or requests the US call Critical: Grade
- 8 determination at increased surveillance the Chemistry Department to obtain an Y[ ] S[ ]
OP 3209B, frequency due to an inoperable control rod initial RCS boron sample and every 8 N[X] U[ ]
step 4.2.3.d OR an inoperable SMM, PERFORM the hours thereafter.
following:
REQUEST Chemistry Department obtain an initial sample of the RCS for boron concentration AND every 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> thereafter.
Comments:
Cue: The call has been made to Chemistry. Chemistry reports that an RCS boron sample has just been taken and the results are 1150 ppm.
STEP DOCUMENT the most current 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Candidate enters "1150" PPM for the Critical: Grade
32098-002. N[X] U[ ]
Comments:
Cue:
STEP Go To step 4.2.3.f. Candidate proceeds to step 4.2.3.f Critical: Grade i
- 10 Y[ ] S[ ]
N[X1 UIJ I Comments:
Cue: I STEP DOCUMENT the "Date and Time" the Candidate enters "today & 0700" for the Critical: Grade
OP 3209B, 3209B-002. N[X] U[ ]
step 4.2.3.1 I Comments: I Cue: i
~[dt STEP CIRCLE the status of the Shutdown 8anks Candidate circles "Inserted" for the Critical:
- 12 (shutdown banks may be withdrawn in Shutdown 8anks status on OP 32098- Y[ ] I OP 3209B, MODE 3 only). 002. N[X] U[ ]
step 4.2.3.9 7
Comments:
Cue:
STEP DOCUMENT the number of stuck rods Candidate enters "one" for the number of Critical: Grade
- 13 indicated by the DRPI System. stuck rods on OP 32098-002. Y[ J S[ J OP 3209B, N[X] U[ ]
step 4.2.3.h Comments: The number of stuck rods was given in initial plant conditions.
Cue:
STEP DOCUMENT "N/A" in the "Anticipated Enters "N/A" in the "Anticipated Critical: Grade
- 14 Conditions" section. Conditions" section of OP 32098-002. Y[ ] S[ ]
OP 3209B, N[X] U[ ]
step 4.2.3.i Comments:
Cue:
STEP Go To step 4.2.5. Candidate proceeds to step 4.2.5. Critical: Grade
- 15 Y[ ] S[]
OP 3209B, N[X] U[ ]
step 4.2.3.j Comments:
Cue:
Evaluator Provide a copy of the Cycle 14 Middle of Life RE Curve 800k to the Candidate.
Note:
8
STEP IF a control rod is known to be stuck, The Candidate identifies the correct Critical: Grade
- 16 DETERMINE the "Stuck Rod Boron graph (RE-F-03) in the RE Curve and Y[X] S[ ]
Equivalent" as follows: Data Book. N[ ] U[ ]
OP 3209B, step 4.2.5.a.1) Refer To "Boron Worth vs Boron Concentration And Temperature" graph in the RE Curve and Data Book and PERFORM the following:
SELECT the DBW curve based on the condition circled in step 4.2.3.c. or 4.2.4.c. and INDICATE on OP 3209B 002 the DBW curve selected:
- IE 55rF circled, USE the 55rF curve Comments:
Cue:
Candidate Writes "557°F" on OP 3209B Critical: Grade 002. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue:
STEP DETERMINE "Differential Boron Worth" Enters "*6.9" (-6.8 to -7.0) on OP 3209B Critical: Grade
OP 3209B, recorded in step 4.2.3.d. or 4.2.4.d. using minor curve interpolation error. N[ ] U[ ]
step 4.2.5.a.2) the selected curve and DOCUMENT as a negative value on OP 3209B-002.
Comments: It is acceptable for the applicant to use the corresponding TABLE (RE-F-03, page 2 of 2) associated with the correct Differential Boron Worth curve. However the acceptable range of values (-6.8 to -7.0) shall remain the same.
9
Cue:
STEP Refer To "Miscellaneous Core Data" in the Candidate refers to table RE-G-03 and Critical: Grade
- 18 RE Curve and Data Book and DETERMINE writes "-1283 pcm" on OP 3209B-002. Y[X1 S[1 OP 3209B, the 'Worst Case Stuck Rod Worth" and N[ ] U[ ]
step 4.2.5.0 DOCUMENT as a negative value on OP 3209B-002.
Comments:
Cue:
STEP CALCULATE the "Boron Equivalent RW" Candidate divides -1283 by DBW of -6.9 Critical: Grade
- 19 (DIVIDE the "Worst Case Stuck Rod pcm/ppm to determine a Boron Y[XJ S[ ]
OP 32098, Worth" by the "Differential Boron Worth") Equivalent RW of 186 ppm (183 to 189 N[ ] U[ ]
step 4.2.S.c and RECORD on OP 3209B-002 as a ppm). Records value and positive sign positive value. on OPS Form 3209B-002.
Comments: Number is approximate. Allow for a slight variation in DBW due to minor curve interpolation error.
Cue:
STEP CALCULATE the "Stuck Rod Boron Enters ONE and 186 ppm for Stuck Rod Critical: Grade
OP 32098, Rod Worth" by the number of known stuck 002. N[X] U[ ]
step 4.2.S.d rods) and DOCUMENT on OP 3209B-002.
Comments:
Cue:
STEP IF either SMM channel is OPERABLE Candidate recognizes that step 4.2.6 Critical: Grade
- 21 based on TIS LCO 3.3.S.b.1 or 3.3.S.b.2, does not apply. Proceeds to step 4.2.7. Y[ ] S[ ]
OP 3209B, PERFORM the following to determine the N[X] U[ ]
step 4.2.6 additional boron requirement .....
Comments:
Cue:
- 10
STEP Refer To "Shutdown Margin" curves in the The Candidate identifies the correct Critical: Grade
- 22 RE Curve and Data Book and DETERMINE graph (RE-B-02) in the RE Curve and Y[X] S[ ]
OP 3209B, the required xenon free boron Data Book (Shutdown Margin - MODE N[ ] U[ ]
step 4.2.7.a concentration as follows: 3).
SELECT the "Shutdown Margin" curve based on MODE AND RCS loop operating condition for which the calculation is being performed.
Comments:
Cue:
STEP Refer To OP 3209B-002 and INDICATE Candidate selects and indicates MODE 3 Critical: Grade
- 23 the SHUTDOWN MARGIN curve - ARI [557°F] on OP 3209B-002. Y[ ] S[ ]
OP 3209B, selected: N[X] U[ ]
step 4.2.7.b Comments:
Cue:
STEP IF MODE 3 curve selected, LOCATE the Candidate locates the intersection of Critical: Grade
- 24 intersection of core burnup and the curve 10,SOO MWD/MTU with the ARI [SSrF] Y[X] S[ ]
OP 3209B, representing the temperature and curve and determines a required xenon N[ ] U[ ]
step 4.2.7.c shutdown bank condition recorded in step free boron concentration of 1125 ppm 4.2.3 or 4.2A and DETERMINE the (1100 ppm t01150 ppm).
required xenon free boron concentration. Number is approximate. Allow for minor curve interpolation error.
Comments: It is acceptable for the applicant to use the corresponding TABLE (RE-B-02, page 2 of 2) associated with the correct Shutdown Margin curve. However the acceptable range of values (1100 ppm t011S0 ppm) shall remain the same.
Cue:
STEP IF a MODE 4 or S curve selected .... Candidate recognizes that step 4.2.7.d Critical: Grade
- 25 does not apply. Proceeds to step 4.2.7.8. vr
- L 1J ~
r L
1J OP 3209B, N[X] U[ ]
step 4.2.7.d 11
Comments:
Cue:
STEP Refer To OP 3209B-002 and RECORD the Candidate writes "1125 ppm" on OP Critical: Grade
OP 3209B, Concentration ." concentration. N[X] U[ ]
step 4.2.7.e Comments:
Cue:
STEP ADD the following values and DOCUMENT Candidate adds the values, 1125 ppm + Critical: Grade
- 27 as "Total Required Xe Free Ca" on OP 186 ppm + 0 ppm, to determine a value of Y[X] S[ ]
OP 3209B, 3209B-002. total required Xe free C a,of 1311 ppm. N[ ] U[ ]
step 4.2.8 Records 1311 ppm (1283 ppm to 1339
- Required Xe Free C B ppm) on OPS Form 3209B-002.
- Stuck Rod Boron Equivalent
Cue:
STEP SUBTRACT 'Total Required Xe Free C a" Candidate subtracts 1311 ppm from 1150 Critical: Grade
OP 3209B, RECORD value and sign (+/-) on OP 3209B records "-161 ppm" (-133 ppm to -189 N[ ] U[ ]
step 4.2.9 002. ppm) on OP 32098-002.
Comments:
Cue:
12
STEP IF RCS boron concentration is less than the Candidate recognizes that RCS boron Critical: Grade
- 29 total required Xe free boron concentration concentration IS less than the total Y[X] S[ ]
for current plant condition, PERFORM one required Xe free boron concentration. N[ ] U[ ]
OP 3209B, of the following:
step 4.2.10
- IF time after shutdown is less than 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> AND in MODE 3, Refer To Section 4.3 and PERFORM xenon correction.
- Refer To AOP 3566, "Immediate Boration," and PERFORM immediate boration and ESTABLISH actual boron concentration greater than total required boron concentration.
Comments: Candidate may report to the US that Shutdown Margin is not adequate for current plant conditions. The Candidate was given in the initiating cue to perform a xenon correction.
Cue:
Candidate proceeds to section 4.3 to Critical: Grade perform a xenon correction. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue:
STEP Xenon may not be credited when Candidate recognizes that current Critical: Grade
- 30 calculating SHUTDOWN MARGIN for conditions are MODE 3 and xenon may Y[ ] S[ ]
OP 3209B, MODEs 4 or 5. be cred ited. N[X] U[ ]
step 4.3.1 CAUTION Comments: -~
Cue:
13
STEP Performing a xenon correction for the next Candidate reviews the NOTE. Critical: Grade
- 31 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period versus hourly corrections is Y[ ] S[ ]
OP 3209B, usually the preferred method. N[X] U[ ]
step 4.3.1 NOTE Comments: Candidate was given in the initiating cue to perform a xenon correction for the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
Cue:
STEP To determine the xenon reactivity, Candidate reviews the step. Critical: Grade
- 32 PERFORM the following: Y[ ] S[ ]
N[X] U[ ]
OP 3209B, Refer To one of the following:
step 4.3.1.a
- RE Curve and Data Book, "Xenon Reactivity After Trip 30% to 60%"
- RE Curve and Data Book, "Xenon Reactivity After Trip 70% to 100%"
- Special Program R7/R9 Comments: The Candidate may ask whether to use the PPC or the RE Curve and Data Book. Provide the following cue:
Cue: The US directs you to use the RE Curve and Data Book STEP Refer To OP 3209B-002 and INDICATE The Candidate identifies the correct Critical: Grade
- 33 the xenon reactivity source selected: graph (70% to 100% graph) in the RE Y[X] S[ ]
Curve and Data Book. N[ ] U[ ]
OP 3209B, step 4.3.1.b
- 30% to 60% graph
- 70% to 100% graph
- Program R7/R9 Comments:
14
Cue:
Candidate Writes "70% to 100%" on OP Critical: Grade 3209B-002. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue:
STEP IF performing xenon correction for the Candidate refers to "Xenon Reactivity Critical: Grade
- 34 next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, PERFORM the After Trip 70% to 100%" (RE-C-02) and Y[X] S[ ]
following: locates the intersection of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> with N[ ] U[ ]
OP 3209B, the 100% power curve. Enters "-2238 step 4.3.1.c OBTAIN the xenon reactivity expected pcm" on OP 3209B-002. Number is at the end of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and approximate. (Accept -2188 to -2288 RECORD as a negative value on pcm).
OP 3209B-002.
Comments: It is acceptable for the applicant to use the corresponding TABLE (RE-C-02, page 2 of 5) associated with the "Xenon Reactivity After Trip 100%"curve. However the acceptable range of values (-2188 to -2288 pcm).shall remain the same.
Cue:
STEP CHECK box indicating calculation Candidate checks the box for 'Next 24 Critical: Grade
- 35 provided for the next 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. hours' on OP 3209B-002. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue:
STEP IF performing hourly xenon corrections, Candidate recognizes that step 4.3.1.d Critical: Grade
- 36 PERFORM the following ..... does not apply. Proceeds to step 4.3.2. Y[ ] S[]
OP 32098, N[X] U[ ]
step 4.3.1.d I~~ ----------
Comments:
-~~~
Cue:
15
STEP Refer To "Boron Worth vs Boron The Candidate identifies the correct Critical: Grade
- 37 Concentration And Temperature" curve in graph (RE-F-03) in the RE Curve and Y[X] S[ ]
the RE Curve and Data Book and Data Book, and uses the correct curve N[ ] U[ ]
OP 3209B, PERFORM the following: (SSrF).
step 4.3.2.a IF maintaining no load Tavg, using the 557°F curve, DETERMINE differential boron worth for the boron concentration recorded in step 4.2.3 or 4.2.4 and ENTER as a negative value on OP 3209B-002.
Comments:
Cue:
STEP Enters "*6.9" (-6.8 to -7.0) on OP Critical: Grade
- 38 3209B-002. Number is approximate. Y[X] S[]
Allow for minor curve interpolation error. N[ ] U[ ]
Comments:
Cue: .
STEP CALCULATE boron equivalent Xe (DIVIDE Candidate divides -2238 pcm by DBW of Critical: Grade
and RECORD as a positive value on OP Equivalent Xe of 324 ppm (313 to 336 N[ ] U[ ]
OP 3209B, 32098-002. ppm). Records value and positive sign step 4.3.3 on OPS Form 3209B-002. Number is approximate. Allow for minor curve interpolation error.
Comments:
- Cue:
STEP Refer To OP 3209B-002 and RECORD the Candidate refers step 4.2.8 of OP 3209B Critical: Grade
OP 3209B, concentration determined in step 4.2.8. 1339 ppm) N[X] U[ ]
step 4.3.4 Comments:
Cue:
16
STEP DETERMINE the required boron Candidate subtracts 324 ppm from 1311 Critical: Grade
- 41 concentration as follows: ppm and adds 60 ppm to yield 1047 ppm Y[X] S[ ]
(1007 ppm to 1086 ppm) as the value for N[ ] U[ ]
OP 3209B, SUBTRACT boron equivalent xenon total required Xe corrected Cs.
step 4.3.5 from total required xenon free boron concentration.
ADD 60 ppm.
Refer To OP 3209B-002 and RECORD resulting value as the total required Xe corrected CB.
Comments:
Cue:
Candidate records "1047 ppm" as total Critical: Grade required Xe corrected C s on OP 3209B Y[ ] S[ ]
002. N[X] U[ ]
Comments:
Cue:
STEP SUBTRACT total required xenon corrected Candidate subtracts 1047 ppm from 1150 Critical: Grade
OP 3209B, concentration and RECORD value and N[ ] U[ ]
step 4.3.6 sign (+/-) on OP 3209B-002.
Comments:
Cue:
Candidate records "+103 ppm" on OP Critical: Grade 32098-002. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue:
17
STEP IF RCS boron concentration is less than Candidate recognizes that RCS boron Critical: Grade
concentration, PERFORM the following .... required xenon corrected boron N[ ] U[ ]
OP 3209B, concentration and step 4.3.7 does not step 4.3.7 apply. Proceeds to step 4.3.8.
Comments:
Cue:
STEP Refer To the "Xenon Correction Log" of OP Candidate enters the date, time, required Critical: Grade
- 44 32098-002 and RECORD the following: C B, RCS C B and initials the Xenon Y[ ] S[ J Correction Log on line 1. N[X] U[ ]
OP 3209B, step 4.3.8
- Date
- Time for which xenon reactivity was determined
- ReS boron concentration
- Initials of person performing calculation Comments:
Cue:
Candidate reports to the US that Critical: Grade Shutdown Margin IS adequate for current Y[ J S[]
plant conditions with a xenon correction. N[X] U[ ]
Comments: Once the Candidate makes the report, provide the following cue:
I Cue: Terminatior:- Cue: The evaluatio" for this JPM is com~lete 18
ill
~
l n.
o I
en
VERIFICATION OF JPM COMPLETION JPM Number: NRC RO A.1.2 Revision: 2 chg 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 30 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
20
STUDENT HANDOUT JPM Number: NRC ROA.1.2 Revision: 2 chg 1 Initial Conditions: Thirty minutes ago, the plant tripped from 100% steady-state equilibrium power after 2 months of operation. Control rod M-4 failed to insert on the trip. All other plant components and systems responded as designed. The plant is presently in MODE 3, and stable at normal temperature and pressure.
Other plant conditions are:
- Core Burnup is 10,SOO MWD/MTU
- Both SMM channels are OPERABLE. Neither SMM channel is OPERABLE based solely on TS LCO 3.3.S.b.1 or 3.3.S.b.2.
Initiating Cues: The US has directed you to calculate SHUTDOWN MARGIN for current plant conditions per OP 3209B, Shutdown Margin. If Shutdown Margin is not adequate for current plant conditions, perform a xenon correction for the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Assume it is one hour post trip for the xenon correction. An STA review of your results is not required.
21
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Perform a Manual RCS Leakage Calculation
..IPM Number: NRC RO A.2 Revision: 0 chg 2 Initiated:
Dave Minnich 03/04/11 Developer Date Reviewed:
Robert Royce 516/11 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 6/2/11 Allowed for the termination of the JPM after JPM step 29. 0/1 Modified the JPM to give more information in the initial cue.
This allowed what was required cueing during the conduct of the JPM, to be moved forward. This will allow for efficient administration of the JPM in the classroom environment.
Incorporated as a result of NRC Exam comments made 5/25/11. Modified the initiating cue to provide direction for the applicant to write down any required actions on the student handout.
6/22/11 Corrected a typographical error in the standard associated 0/2 with JPM step 22; 'Using the recorded values for total RCS leakage (192.84 gal) ... ' It previously and incorrectly read 189.121 gal. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
..IPM WORKSHEET Facility: _M~P..;;;..3_ _ __ Examinee:
..IPM Number: NRC RO A.2 Revision: 0 chg 2 Task
Title:
Perform a Manual RCS Leakage Calculation.
System: Equipment Control Time Critical Task: ( ) YES (X) NO Validated Time (minutes): _ _ _ __
Task Number(s): 002-04-040 Applicable To: SRO X RO X PEO _ __
KIA Number: 2.2.12 KIA Rating: _ _3_.7_1_4_._1__
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Correctly perform a manual RCS water inventory balance to meet the requirements of TIS 4.4.6.2.1.d, "Reactor Coolant System, Operational Leakage."
Reg uired Materials: SP 3601F.6 (procedures, equipment, etc.)
Surveillance Form SP 3601 F.6 - 001 Calculator General
References:
SP 3601 F.6, Reactor Coo/ant System Water Inventory Measurement (revision 006-04)
Surveillance Form SP 3601F.6 - 001, RCS Inventory Balance, (revision 003-01 )
3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s} to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: NRC ROA.2 Revision: o chg 2 Initial Conditions: The plant is at 100% power and you are the Extra Licensed Operator on night shift. The PPC Program for RCS Leakage is malfunctioning and the RCS Leakage calculation is due. Computer Services has been notified.
Initiating Cues: The US has directed you perform a manual RCS water inventory balance using SP 3601 F.6, Reactor Coolant System Water Inventory Measurement. The on-shift ROs have gathered the initial and final data to be used in the manual calculation, and can be considered accurate. The proper initial conditions were established for the data gathering period. Other pertinent information:
- VCT Divert was not required during the data gathering period.
- Initial and final RCS specific volume values have been determined using R*Time and are 0.02258 ft 3 /lbm.
- 3DGS-V831 (radioactive gaseous waste AOV58 leakoff isolation) and 3DGS-V826 (radioactive gaseous waste AOV54 leakoff isolation) are open.
- 3GWS-V073 (degasifier recovery exchange A tube drain) and 3GWS-V071 (degasifier recovery exchange B tube drain) are closed.
Record any required actions as a result of your leak rate calculations at the bottom I back of this page.
4
Simulator Requirements: None
'* '* '* '* NOTES TO TASK PERFORMANCE EVALUATOR '* '* '* '*
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. 'What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: NRC RO A.2 Revision: o chg 2 Task
Title:
Perform a Manual RCS Leakage Calculation.
START TIME: _ _ __
PERFORMANCE STANDARD Evaluator Provide copy of SP 3601F.6 and a copy of Surveillance Form SP 3601F.6 - 001 (with Data Table filled in)
NOTE:
to the candidate.
STEP VERIFY "General Prerequisites" Verifies "Test Authorized By" block is Critical: Grade
- 1 completed. signed on FORM SP 3601 F.6 - 001. Y[ ] S[]
N[X] U[ ]
MB2B 2-9 Step 1 ------ ------
Reviews SP 3601 F.6, Section 3 Critical: Grade PRECAUTIONS Y[ ] S[]
N[X] U[ ]
Comments:
Cue:
STEP Locate correct procedure step. Candidate locates section 4.3 of SP Critical: Grade
- 2 3601 F.6. Y[ ] S[]
N[X] U[ ]
Comments:
Cue:
6
STEP The following assumptions apply to a Candidate reviews the NOTE. Critical: Grade
- 3 manual RCS leakage calculation ..... y [ ] S[ ]
N[X] U[ ]
3601F.6 step 4.3.1 NOTE Comments:
Cue:
STEP RECORD applicable initial readings on SP Candidate recognizes that step 4.3.1 is Critical: Grade
- 4 complete. Y[ ] S[ ]
3601 F.6---001 from the computer report 3601F.6 N[X] U[ ]
step 4.3.1 previously printed or from secondary sources using the instruments listed.
Comments:
Cue:
STEP Divert is necessary at EOL when dilution Candidate reviews the NOTE. Critical: Grade
- 5 makeup is required to maintain Tavg Y[ ] S[ ]
3601F.6 constant. N[X] U[ ]
step 4.3.2 NOTE Comments:
Cue:
STEP IF VCT divert is required during leak rate Candidate reviews step 4.3.2 and Critical: Grade
- 6 recognizes that VCT divert was not Y[ ] S[ ]
data gathering interval, PERFORM the 3601F.6 required during data gathering interval. N[X] U[ ]
step 4.3.2 following ...
Comments: VCT divert did not occur, as given in the initial cue. The Candidate may N/A the VCT Divert section of Calculation Table 7.
Cue:
---~-
7
STEP The normal required data gathering interval Candidate reviews the NOTE and Critical: Grade
- 7 is four to six hours. This interval may be recognizes from the Data Table on FORM Y[ J s[]
changed by the SM/US, depending on why SP 3601 F.6 - 001 that the data gathering N[X] U[ ]
step 4.3.3 NOTE 1 the surveillance is being performed. A data interval was 4.0 hours0 days <br />0 weeks <br />0 months <br />.
gathering interval less than four hours may provide less accurate leak rate results.
Comments:
Cue:
STEP If the computer is being used, the printed Candidate reviews the NOTE and Critical: Grade
- 8 report contains initial and final readings recognizes that it does not apply. Y[ ] S[ ]
step 4.3.3 since the report has been setup to run N[X] U[ ]
NOTE 2 automatically.
Comments:
Cue:
STEP WHEN the required data gathering interval Candidate recognizes that step 4.3.3 is Critical: Grade
- 9 has elapsed, RECORD applicable final complete. Y[ ] S[ ]
readings on SP 3601 F.6---001 from the N[X] U[ ]
step 4.3.3 computer report or from secondary sources using local instruments listed.
Comments:
Cue:
STEP If desired, calculations may be performed Candidate reviews the NOTE. Critical: Grade
- 10 after restoration of plant equipment Y[ ] S[ ]
step 4.3.4 N[X] U[ ]
NOTE 1 Comments:
Cue:
8
STEP Refer To SP 3601 F.6---001 and Candidate refers to Table 1A on SP Critical: Grade
- 11 PERFORM the following: 3601 F.6 - 001, and records Data Table Y[ ] S[ ]
values for initial and final PZR level and N[X] U[ ]
step 4.3.4.a CALCULATE and RECORD change in pressure.
volume using initial and final data for the following components in the Calculation Tables listed for each:
- Pressurizer, Calculation Table 1A Comments: Candidate calculations should be accurate however, the number of significant digits is not part of the critical nature of calculations.
Candidate refers to Table 1Bon SP Critical: Grade 3601 F.6 - 001, and determines the Y[X] S[ ]
appropriate 'K' value for plant conditions N [ ] U[ ]
is 74.15.
Candidate records 74.15 as the value for Critical: Grade
'K' on Table 1A. Y[ ] S[ ]
N[X] U[ ]
Using the recorded values for initial and Critical: Grade final PZR level and 'K', the Candidate Y[X] S[ ]
calculates and records a change in PZR N[ ] U[ ]
volume of 7.42 gallons.
Comments: The candidate may interpolate the value of 'K' between the pressure values of 2240 and 2250 psia. This is acceptable. Interpolated value for 'K' is about 74.19.
Cue:
STEP
- 12 3601 F.6 - 001, and records Data Table Y[ ] S[ ]
values for initial -and final VCT level.
N[X] U[ ]
--- --- ---- ........... -.-~
9
Using the recorded values for initial and Critical: Grade final VCT level and the conversion factor Y[X] S[ ]
18.92 gal/%, the Candidate calculates N[ ] U[ ]
and records a change in VCT volume of 185.42 gallons.
Comments:
Cue:
STEP
- 13
Y[ ]
Grade S[ ]
3601 F.6 - 001, and records Data Table values for initial PZR pressure (CVPZRP) N[X] U[ ]
and initial calculated average temperature.
Using the value given in the initial cue, Critical: Grade the Candidate records initial specific Y[ ] S[ ]
volume obtained from R*Time. N[X] U[ ]
Comments:
For initial and final specific volume the Candidate should use the value of 0.02258 fe /Ibm.
Cue:
Using the value recorded for initial Critical: Grade specific volume, the Candidate calculates Y[X] S[ ]
and records initial density. N[ ] U[ ]
Candidate refers to Table 3 on SP Critical: Grade 3601 F.6 - 001, and records Data Table Y[ ] S[ ]
values for final PZR pressure (CVPZRP) N[X] U[ ]
and final calculated average temperature.
Comments:
Cue:
Using the value given in the initial cue, Critical: Grade the Candidate records final specific y r 1
- L J sr
- L 1
J volume obtained from R*Time. N[X] U[ ]
10
Comments:
- Cue: :
Using the value recorded for final specific Critical: Grade I volume, the Candidate calculates and Y[X] S[ ]
N[ ] U []
records final density. i Comments:
Cue: i Using the recorded values for initial and Critical: Grade final density and the conversion factor Y[X] S[ ]
1251.9 gal ft3 /Ibm, the Candidate N[ ] U[ ]
I calculates and records a change in RCS volume of 0.0 g a l l o n S , _ ..~
Comments: Initial and final specific volume are effectively the same value, thus there is no change in RCS volume.
Cue:
STEP
- 14 3601 F.6 - 001, and records Data Table Y[ ] S[ ]
N[X] U[ ]
values for initial and final PRT level.
Comments:
Cue:
Using the recorded values for initial and Critical: Grade final PRT level and the conversion factor Y[X] S[ ]
N[ ] U[ ]
126.57 gal/%, the Candidate calculates and records a change in PRT volume of 0.0 gallons.
Comments: Initial and final PRT levels are the same value, thus there is no change in PRT volume.
Cue:
STEP
- 15
- POTT, Calculation Table 5 Candidate refers to Table 5 on SP Critical:
Y[ ]
Grade S[ ]
3601 F.6 - 001, and records Data Table N[X] U[ ]
values for initial and final PDn level.
Comments:
11
,--~~
Cue:
Using the recorded values for initial and Critical: Grade final POTT level, the Candidate calculates Y[X] S[ ]
and records a change in POTT volume of N[ J u[ ]
24.90 gallons.
Comments:
Cue:
STEP
- COTT, Calculation Table 6 Critical: Grade Candidate refers to Table 6 on SP
- 16 Y[ ] S[ ]
3601 F.6 - 001, and records Data Table N[X] U[ ]
values for initial and final COTT level.
Comments:
Cue:
Using the recorded values for initial and Critical: Grade final COTT level, the Candidate Y[X1 S[ J N[ ] U[ ]
calculates and records a change in COTT volume of 15.60 gallons.
Comments:
Cue:
STEP CALCULATE and RECORD volume of Candidate refers to Table 7 on SP Critical: Grade
- 17 makeups using initial and final makeup Y[ ] S[ ]
3601 F.6 - 001, and records Data Table step 4.3.4.b totalizer flow in Calculation Table 7. N[X] U[ ]
values for initial and final makeup totalizer flow.
Comments:
Cue:
Using the recorded values for initial and Critical: Grade Y[X] S[ ]
final makeup totalizer flow, the Candidate N[ ] U[ ]
calculates and records a total volume of makeup of 0.0 gallons.
Comments: No makeup occurred during the calculationai period.
Cue:
12
STEP CALCULATE volume diverted by Candidate recognizes that VCT divert Critical: Grade
- 18 performing the following in Calculation Y[ ] S[ ]
was NOT required during the leak rate step 4.3.4.c Table 7 ..... N[X] U[ ]
data gathering period.
Comments: VCT divert did not occur, as given in the initial cue. The Candidate may N/A the VCT Divert section of Calculation Table 7.
Cue:
STEP CALCULATE total leakage from other Candidate reviews step 4.3.4.d, and Critical: Grade
- 19 known sources in Calculation Table 8 as Y[ ] S[ ]
recognizes that there is no leakage from step 4.3.4.d follows: N[X] U[ ]
other sources.
Comments: There is no leakage from other known sources, as given in the initial cue. The Candidate may N/A Calculation Table 8.
Cue:
STEP CALCULATE and RECORD time difference Candidate refers to Table 9 on SP Critical: Grade
- 20 from initial data collection to final data 3601 F.6 - 001, and records Data Table Y[ ] S[1 Step 4.3.4.e collection in Calculation Table 9. N[X] U[ ]
values for the initial and final times associated with the data gathering period.
Comments:
Cue:
Using the recorded values for initial and Critical: Grade final times, the Candidate calculates and Y[X] S[ 1 N[ ] U[ ]
records a time difference of 240 minutes.
Comments:
Cue:
STEP CALCULATE and RECORD total RCS Candidate refers to Table 9 on SP Critical: Grade
- 21 leakage using the previously calculated Y[ ] S[]
3601 F.6 - 001, and records the volumes in Calculation Table 9. N[X] U[ ]
Step 4.3.4.f previously calculated volume changes associated with the PZR, VCT and RCS.
Comments:
l3
Cue:
Using the recorded values for volumes, Critical: Grade the Candidate calculates and records a Y[X] S[ ]
total RCS leakage of 192.84 gallons. N[ ] U[ ]
Comments:
Cue:
STEP CALCULATE and RECORD total RCS leak Using the recorded values for total RCS Critical: Grade
- 22 rate by dividing total RCS leakage by the leakage (192.84 gal) and the time Y[X] S[ ]
time difference in Calculation Table 9. difference (240 min), the Candidate N[ ] U[ ]
Step 4.3.4.g calculates and records a total RCS leak rate of 0.804 gal/min.
Comments:
Cue:
STEP CALCULATE and RECORD IDENTIFIED Candidate refers to Table 10 on SP Critical: Grade
- 23 LEAKAGE by dividing the sum of the total 3601 F.6 - 001, and records the Y[ ] S[ ]
collected leakage by the time difference in previously calculated volume changes N[X] U[ ]
Step 4.3.4.h Calculation Table 10. associated with the PRT, PDTT and CDTT.
Comments:
Cue:
Using the recorded values for collected Critical: Grade leakage (40.50 gal) and the time Y[X] S[ ]
difference (240 min), the Candidate N[ ] U[ ]
calculates and records an IDENTIFIED LEAKAGE of 0.169 gpm.
Comments:
Cue:
14
STEP CALCULATE and RECORD Candidate refers to Table 11 on SP Critical: Grade
- 24 UNIDENTIFIED LEAKAGE by subtracting 3601 F.6 - 001, and records total RCS Y[ ] S[ ]
IDENTIFIED LEAKAGE from total RCS leak rate (0.804 gpm), IDENTIFIED N[X] U[ ]
Step 4.3.4.i leak rate and adding the change in PDTT LEAKAGE (0.169 gpm), the PDTT volume in Calculation Table 11. volume change (24.90 gal) and the time difference (240 min).
Comments:
Cue:
Using the recorded values above, the Critical: Grade Candidate calculates and records an Y[X] S[]
UNIDENTIFIED LEAKAGE of 0.739 gpm. N[ ] U[ ]
Comments:
Cue:
STEP IF leakage approaches either of the Candidate writes down or otherwise Critical: Grade
- 25 following limits, INITIATE a Condition communicates that UNIDENTIFIED Y[ ] S[ ]
Report to ensure compliance with LEAKAGE (0.739 gpm) is approaching N[X] U[ J Step 4.3.5 Maintenance Rule requirements: 0.75 gpm, and a Condition Report needs to be initiated.
- IDENTIFIED LEAKAGE --- 2.5 gpm (25% of T.S. Limit)
- UNIDENTIFIED LEAKAGE --- 0.75 gpm (75% of T.S. Limit)
Comments:
Cue:
15
STEP IF UNIDENTIFIED LEAKAGE is Candidate writes down or otherwise Critical: Grade
- 26 abnormally high, greater than 0.6 gpm Y [ ] S[ ]
communicates that a call to Engineering or a step increase of 0.2 gpm, PERFORM N[X] U[ ]
Step 4.3.6.a needs to be made, to inform them of the the following: leak rate.
NOTIFY Engineering of leak rate.
Comments:
Cue:
STEP REVIEW computer printout or SP 3601 F.6 Candidate refers to Table 5 on SP Critical: Grade
- 27 -001, Table 5, and DETERMINE the Y[ ] S[ ]
3601 F.6 - 001, and reviews data volume changes associated with the PDTT. N[X] U[ ]
Step 4.3.6.b associated with the PDTT volume change.
Comments:
Cue:
16
... ~
STEP VERI FY all inventory changes to the PDTT Candidate recognizes that no SI or RHR Critical: Grade
pump was run during the data gathering follows: N[X] U[ ]
Step 4.3.6.c period.
- No SI pumps run during measurement
- No RHR pumps run during measurement
- 3DGS---V831, radioactive gaseous waste AOV58 leakoff isolation, closed
- 3DGS---V826, radioactive gaseous waste AOV54 leakoff isolation, closed
- 3GWS---V073, degasifier recovery exchange A tube drain, closed
- 3GWS---V071, degasifier recovery exchange B tube drain, closed Comments: SI or RHR pump was run, as given in the initial cue.
Cue:
Candidate recognizes that 3DGS-V831 Critical: Grade and V826 are OPEN.
Y[X] S[ ]
N[ ] U[ ]
Comments: The status of 3DGS-V831 and V826 were -.9Jven in the initial cue.
17
Cue:
Candidate recognizes that 3GWS-V073 Critical: Grade and V071 are closed.
Y[ ] S[ ]
N[X] U[ ]
Comments: The status of 3GWS-V073 and V071 were given in the initial cue.
Cue:
Candidate determines that all inventory Critical: Grade changes to the PDTT are NOT related to Y[X] S[ ]
N[ ] U[ ]
RCS or CVCS Comments: Since 3DGS-V831 and V826 are open, all inventory changes to the PDTT cannot be shown to be RCS or CVCS related.
Cue:
STEP IF all PDTT inventory changes are RCS or Candidate reviews step 4.3.6.d and Critical: Grade
Table 12 ..... N[X] U[ ]
Step 4.3.6.d Comments: At the Examiner's discretion, the JPM may be terminated at the completion of JPM step 29. In that case provide the following cue:
Cue: The evaluation for this JPM is concluded.
STEP IF PDTT inventory changes can not be Candidate takes action (or requests from Critical: Grade
leakage, Refer To SP 3601 F.6---001, Table N[X] U[ ]
Step 4.3.6.e UNIDENTIFIED LEAKAGE in the SM log.
11, and RECORD UNIDENTIFIED LEAKAGE from Table 11 in the SM log for the TIS surveillance.
I Comments: ---- -----
18
.--~~
Cue: The value for UNIDENTIFIED LEAKAGE is entered in the SM log.
I STEP IF leakage calculation was initiated for the Candidate recognizes that the last page Critical: Grade
- 31 required daily leakage determination (per Y[ J S[ J of the surveillance form needs to be SP 3670.1---001), ATTACH a copy of the N[XJ U[ ]
Step 4.3.7 attached to the Control Room Rounds.
last page of SP 3601 F.6---001, to SP 3670.1---001, "MODE 1---4 Daily and Shiftly Control Room Rounds."
I Comments:
Cue: Page 7 of SP 3601 F.6 - 001 is attached to the Control Room Rounds.
STEP If data is used from secondary sources Candidate reviews the NOTE. Critical: Grade
- 32 because of unavailability of computer Y[ ] S[ ]
points, leak rate results may be less N[X] U[ J Step 4.3.8 NOTE accurate or may trend differently than any computer generated leak rate results.
~-
Comments:
Cue: I STEP IF leakage exceeds any of the following Candidate writes down or otherwise Critical: Grade i
communicates the need to refer to C OP Leakage Trending and Investigation," and N[X] U[ ]
Step 4.3.8 200.15 to determine required actions.
PERFORM required actions .....
Comments: When the Candidate requests COP 200.15, provide the following cue:
Cue: TERMINATION CUE: The US will refer to C OP 200.15. The evaluation for this JPM is concluded.
STOP TIME: _ _ __
19
VERIFICATION OF JPM COMPLETION JPM Number: NRC RO A.2 Revision: 0 chg 2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 30 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
20
STUDENT HANDOUT JPM Number: NRC RO A.2 Revision: o chg 2 Initial The plant is at 100% power and you are the Extra Licensed Operator on Conditions: night shift. The PPC Program for RCS Leakage is malfunctioning and the RCS Leakage calculation is due. Computer Services has been notified.
Initiating The US has directed you perform a manual RCS water inventory balance Cues: using SP 3601 F.6, Reactor Coolant System Water Inventory Measurement. The on-shift ROs have gathered the initial and final data to be used in the manual calculation, and can be considered accurate. The proper initial conditions were established for the data gathering period.
Other pertinent information:
- All assumptions required in SP-3601 F.6 for a manual RCS leakage calculation can be considered valid.
- VCT Divert was not required during the data gathering period.
- Initial and final RCS specific volume values have been determined using R*Time and are 0.02258 fe Ilbm.
- 3DGS-V831 (radioactive gaseous waste AOV58 leakoff isolation) and 3DGS-V826 (radioactive gaseous waste AOV54 leakoff isolation) are open.
- 3GWS-V073 (degasifier recovery exchange A tube drain) and 3GWS-V071 (degasifier recovery exchange B tube drain) are closed.
Record any required actions as a result of your leak rate calculations on the bottom I back of this page.
21
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Actions and Expected Response for RMS Equipment failure Alarms JPM Number: NRC RO A.3 (2K7 RO A.3) Revision: 1 chg 1 Initiated:
Dave Minnich 03/03/11 Developer Date Reviewed:
Robert Royce 5111111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES All & DATE DESCRIPTIOI\J REV/CHANGE 03/03/11 Updated JPM to revision 008-04 to OP 3362. Changed the 1 /0 nomenclature of the equipment failure light override to the TRex designator. DLM 6/22/11 Added a comment and cue in JPM step 14, to disregard a 1/ 1
'dash' in performance step 4.16.3 (OP 3362), if the Candidate misinterprets it as a required keystroke on 3CMS*RE22 RIC.
Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
..IPM WORKSHEET Facility: _M:. :. ;,;. P. : :. 3_ _ __ Examinee:
JPM Number: NRC ROA.3 Revision: 1 chg 1 Task
Title:
Actions and Expected Response for RMS Equipment failure Alarms.
System: Radiation Control Time Critical Task: ) YES (X) NO Validated Time (minutes): _ _.. ;.1. : :. 0_ _
Task Number(s): 073-01-043 Applicable To: SRO X RO X PEO KIA Number: 2.3.5 KIA Rating: _ _ 2._9_'_2._9_ _
Method of Testing: Simulated Actual x Performance: Performance:
Location: Classroom: Simulator: x In-Plant:
Task Standards: Correctly determines the required actions for an RMS Equipment failure Alarm.
Reguired Materials: OP 3362, Radiation Monitor Display and Control System (rev. 008-04)
(procedures. equipment. etc.)
OP 3353.I\IIB2B-002-09, "RMS TROUBLE" (2-9), rev 000 Simulator General
References:
3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: NRC RO A.3 Revision: 1 chg 1 Simulator Requirements: Reset to any 100% power certified IC. Insert Annunciator override MB2B B-9 to "ON". Override the CMS22 RIC equipment failure light to 'ON' [(10 RML00045 (3CMS*RE22 EQFAIL) to 'ON'].
Initial Conditions: The plant is at 100% power and you are the Extra Licensed Operator on shift. MB2B 2-9 "RMS TROUBLE" has alarmed.
Initiating Cues: The US has directed you to respond to the annunciator.
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y", For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. 'What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: NRC RO A.3 Revision: 1 chg 1 Task
Title:
Actions and Expected Response for RMS Equipment failure Alarms.
START TIME:
PERFORMANCE STANDARD STEP Obtain proper Annunciator Response Obtains OP 3353.MB2B and refers to Critical: Grade
- 1 "RMS TROUBLE" (2-9). Y [ ] S[ ]
Procedure.
N[X] U[ ]
Evaluator The Candidate may refer to the RMS alarm display monitor on the RO/BOP desk to determine alarm NOTE:
source. If so, provide cue card #1 (where the events are listed) and verbally give the following cue:
Cue: The screen displays the following events.
STEP DETERMINE the cause of RMS trouble Candidate proceeds to the RMS Console. Critical: Grade
- 2 indication at RMS Control Room Operator If the Candidate observes the bottom of Y[ ] S[ ]
Console. the monitor screen to determine the N[X] U[ ]
MB2B 2-9 Step 1 specific alarm.
Comments: When the candidate observes the RMS Console monitor screen, provide cue card #2 (where the events are listed) and verbally give the following cue:
Cue: The yellow alarm line displays the following events.
Evaluator Any active RMS alarm will show up at the bottom of the RMS console monitor screen, regardless of what NOTE:
else is dispiayed.
I 5
~~~ -----
Candidate proceeds to the RMS Console Critical: Grade and calls up the status grid function Y[ ] S[ ]
and/or data base for 3 CMS*RE22 and N[X] U[ ]
determines that 'filter step' is in alarm.
Evaluator On the status grid function, all the RMUs are shown with a corresponding number that indicates monitor NOTE: status. '3' correlates to an equipment failure. If Candidate calls up status grid, provide the following cue:
Cue: A blue '3' is displayed for CMS22 2 monitor status.
Comments: On the 3CMS*RE22 particulate database display, top right, there is indication of whether the RMU is online, reachable and if there are any alarms in. When the Candidate calls up the database display and observes the top right of the screen, provide the following cue:
Cue: Screen shows a yellow 'ALARM'.
Evaluator On the 3CMS*RE22 particulate database display, there is an equipment failure column. When the NOTE: Candidate observes the equipment failure column, provide the following cue:
Cue: Filter step indicates 'yes' and is yellow for alarm status.
STEP IF alarm is due to equipment failure, Refer Candidate obtains and refers to OP 3362, Critical: Grade
- 3 To OP 3362, "Radiation Monitor System Section 4.13, Equipment Failure Alarms.
Y[ ] S[]
MB2B 2-9 Display and Control," and TAKE required N[X] U[ ]
Step 2 C!9tions for equipment failure alarms.
Comments:
Cue:
STEP Refer To Attachment 6 and PERFORM Candidate refers to OP 3362, Attachment Critical: Grade
- 4 the following: 6 and verifies that 3CMS*RE22 is listed. Y[X] S[]
OP 3362, N[ ] U[ ]
Section 4.13 CHECK monitor number is listed.
Step4~13.1.a Comments:
Cue: --~ --~
6
STEP IF monitor is listed, DETERMINE applicable Candidate refers to Attachment 6 and Critical: Grade
- 5 Trouble Response(s)." determines that for 3CMS*22, trouble Y[X] S[ ]
responses 1,2,3,6,7, 10, and 12 are N[ ] U[ ]
Step 4.13.1.b required.
Comments:
Cue:
STEP PERFORM applicable Trouble Candidate refers to Attachment 6 begins Critical: Grade
- 6 Response(s)" listed. to perform the identified responses. Y[ ] S[ ]
Step 4.13.1.c N[X] U[ ]
Evaluator The Candidate may ask whether the US desires him/her to perform the applicable trouble responses. If so, NOTE:
provide the following cue:
Cue: Yes, perform the applicable trouble responses.
STEP NOTIFY Instrument and Control Candidate notifies I &C that 3CMS*RE22 Critical: Grade
- 7 Department to check monitor. has an equipment failure alarm and to Y[ ] S[ ]
OP 3362 check the monitor. Telephone call is N[X] U[ ]
Att.6 Action 1 adequate for this notification.
Comments:
Cue: All notifications to I & C are complete.
STEP NOTIFY Health Physics Department for Candidate notifies Health Physics that Critical: Grade
- 8 area monitoring and sampling as required. 3CMS*RE22 has an equipment failure Y[ ] S[ ]
OP 3362 alarm and to conduct necessary N[X] U[ ]
AU. 6 Action 2 monitoring and sampling. Telephone call is adequate for this notification.
Comments:
Cue: All notifications to Health Physics are complete.
I 7
STEP NOTIFY Chemistry Department for Candidate notifies Chemistry Department Critical: Grade
- 9 sampling medium. that 3CMS*RE22 has an equipment Y[ ] S[ ]
OP 3362 failure alarm and to ready appropriate N[X] U[ ]
Att. 6 Action 3 sampling medium. Telephone call is adequate for this notification.
Comments:
Cue: All notifications to Chemistry are complete.
STEP IF a filter step alarm is recorded, ATTEMPT Informs the US that an attempt must be Critical: Grade
- 10 to step the filter as follows: made to step the 3CMS*22 filter at the Y[ ] S[ ]
OP 3362
'RIC'. N[X] U[ ]
Att.6 Action 6 IF 3CMS*RE22 filter needs to be manually stepped, Go To Section 4.16.
Candidate proceeds to Section 4.16. Critical: Grade Y[X] S[ ]
N[ ] U[ ]
Comments:
Cue: If required, as US, direct the Candidate to attempt to step the filter.
STEP When the radiation monitor filter is Candidate reviews the NOTE. Critical: Grade
- 11 manually stepped, the monitor will be Y[ ] S[ ]
inoperable until the unit finishes the N[X] U[ ]
OP 3362, Section 4.16 process which includes a new calculation of NOTE background and returns to normal readings for plant conditions. This can take up to two hours.
Candidate informs the US that when the Critical: Grade filter is stepped, the monitor will be Y[ ] S[ ]
inoperable for up to two hours. N[X] U[ ]
I Comments:
8
,----~~~c ~~---~~
Cue: Acknowledge as th US STEP Refer to the following and PERFORM Candidate informs the US to refer to TIS Critical: Grade
- 12 applicable ACTIONs: 3.3.3.1 and 3.4.6.1, and perform required Y[X] S[ ]
actions. N[ ] U[ ]
Step 4.16.1
- TIS 3.3.3.1, "Radiation Monitoring for Plant Operations"
- TIS 3.4.6.1, "Leakage Detection Systems" Comments: When the Candidate informs the US to refer to Tech Specs, provide the following cue:
Cue: The US will refer to Tech Specs.
STEP At RIC-8B, 3CMS*RIY22A1B KERIC, Candidate obtains the key from the Critical: Grade
- 13 PLACE keyswitch to "ENABLE." simulator key locker for 3CMS*22 and Y[X] S[ ]
Step 4.16.2 N[ ] U[ ]
proceeds to the 3CMS*22 'RIC'.
At the 3CMS*22 'RIC', Candidate inserts Critical: Grade the key and turns the keyswitch to Y[X] S[ ]
"ENABLE." N[ ] U[ ]
Comments:
Cue:
STEP PRESS "STP -2 ENT." On the 'RIC' keyboard, Candidate Critical: Grade
- 14 presses 'STP' (step), followed by '2',
Y[X] S[ ]
Step 4.16.3 N[ ] U[ ]
followed by 'ENT' (enter).
Comments: If the Candidate questions the meaning of the 'dash' in performance step 4.16.3, provide the following cue: I Cue: Disregard the dash.
I I
9
STEP CHECK "PROC FUNC" light cycles on and Candidate observes the "PROC FUNC" Critical: Grade
- 15 then off. (process function) light. Y[ ] S[ ]
Step 4.16.4 N[X] U[ ]
Comments: When the Candidate monitors the process function light, provide the following cue:
Cue: The process function light cycles on and then off.
STEP At RIC-8B, 3CMS*RIY22A1B KERIC, At the 3CMS*22 'RIC', Candidate turns Critical: Grade
- 16 PLACE keyswitch to "DISABLE." the keyswitch to "DISABLE", removes Y[X] S[ ]
and returns the key to the key locker. N[ ] U[ ]
Step 4.16.5 Comments: Removing and returning the key is not part of the critical nature of this step.
Cue:
STEP WHEN two hours have elapsed AND Candidate informs the US that two hours Critical: Grade
- 17 monitor readings have stabilized for plant must elapse and monitor readings Y[ ] S[ ]
conditions, Refer to the following and stabilize before TIS 3.3.3.1 and 3.4.6.1 N[X] U[ ]
Step 4.16.6 PERFORM applicable ACTIONs ...... can be exited.
Comments: When the Candidate informs the US, provide the following cue:
Cue: The US will monitor the time from stepping the filter and then refer to Tech Specs.
Candidate returns to Attachment 6 to Critical: Grade perform the rest of the identified trouble Y[ ] S[ ]
responses (7,10, and 12). N[X] U[ ]
Comments:
Cue:
STEP IF a radiation monitor indicates "OFF Candidate proceeds to the RMS Console Critical: Grade
- 18 LINE," DECLARE the radiation monitor and calls up the status grid function or Y[ ] S[ ]
INOPERABLE and LOG into all applicable data base for 3CMS*RE22 and N[X] U[ ]
OP 3362 Att.6 LCOs. determines that the Rad Monitor does not Action 7 indicate "OFF-LINE."
Comments:
10
Cue:
STEP Refer To TIS 3.3.3.1 and Table 3.3-6, Candidate informs the US that TIS Critical: Grade
- 19 "Radiation Monitoring Instrumentation for 3.3.3.1, "Radiation Monitoring Y[X] S[ ]
OP 3362 N[ ] U[ ]
Att.6 Plant Operations," and PERFORM Instrumentation for Plant Operations,"
Action 10 applicable actions. must be referred to.
Comments:
Cue: Acknowledge the Candidate's report and reply that the US is referring to TIS 3.3.3.1.
STEP Refer To TIS 3.4.6.1, "Reactor Coolant Candidate informs the US that TIS Critical: Grade
- 20 System Leakage Detection Systems," and 3.4.6.1, "Reactor Coolant System Y[X] S[ ]
OP 3362 N[ ] U[ ]
Att.6 PERFORM applicable actions. Leakage Detection Systems," must be Action 12 referred to.
Comments:
Cue: Acknowledge the Candidate's report and reply that the US is referring to TIS 3.4.6.1.
STEP Candidate Reports Task Completion. Candidate reports to the US that the Critical: Grade
- 21 applicable trouble responses have been Y[ ] S[ ]
performed. N[X] U[ ]
Comments:
Cue: TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
11
VERIFICArlON OF JPM COMPLETION JPM Number: NRC RO A.3 Revision: 1 cllg 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is T~
Critical, it MUST be completed within the specified time to achieve a satisfactory grade. ----1 Time Critical Task? Yes No X Validated Time (minutes): 10 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
12
STUDENT HANDOUT JPM Number: NRC RO A.3 Revision: 1 chg 1 Initial Conditions: The plant is at 100% power and you are the Extra Licensed Operator on shift. MB2B 2-9 "RMS TROUBLE" has alarmed.
Initiating Cues: The US has directed you to respond to the annunciator.
l3
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Administrative Requirements for Shift Manning Activities - Minimum Crew Complement and Working Hour Limitations.
..IPM Number: NRC SRO A.1.1 (JPM-197) Revision: 0 chg 2 Initiated:
Dave Minnich 04/20/11 Developer Date Reviewed:
Robert Royce 5/10/11 Technical Reviewer Date Approved:
L. Armstrong 5/11111 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 6/3/11 Corrected ...IPM step 5 to indicate Operator 2, as opposed to 0/1 Operator 5, which was in error. Combined the first and second initiating cues into one initiating cue. This will allow for efficient administration of the JPM in the classroom environment. Incorporated as a result of NRC Exam comments made 5/25/11. Entered a 15 minute time for validated time.
6/22/11 Deleted a comment following JPM step 3 that stated 'provide 0/2 the candidate with Handout 2.' This comment was left in error, and should have been removed with Rev 0 chg 1.
Corrected a typographical error in the standard associated with ..IPM step 5, to indicate Operator 2, as opposed to Operator 1. Added a comment following JPM step 8 that allows for the Candidate to determine that Operator 5 IS available, but must recognize that Operator 5 is prohibited from working the following day shift. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility: _M_P__3_ _ __ Examinee:
..IPM Number: NRC SRO A.1.1 Revision: 0 chg 2 Task
Title:
Administrative Requirements for Shift Manning Activities - Minimum Crew Complement and Working Hour Limitations.
System: Conduct of Operations Time Critical Task: ) YES (X) NO Validated Time (minutes): ___1_S_ _
Task Number(s): 119-03-009 Applicable To: SRO X RO - - - PEO KIA Number: 2.1.S KIA Rating: _ _ _ 3._9_ __
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Examinee correctly determines minimum shift crew composition requirements and 10CFR26 Fatigue Rule limititations.
Reguired Materials: Unit 3 Technical Specifications (procedures, equipment, etc.)
LI-AA-700, Fatigue Management and Work Hour Limits for Covered Workers.
SY-AA-FFD-101, Fitness for Duty Program.
Calculator General
References:
Unit 3 Technical Specifications LI-AA-700, Fatigue Management and Work Hour Limits for Covered Workers.
3
- READ TO THE EXAMINEE *** __
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. W~en you ,
complete the task successfully, the objective for this JPM will be satisfied. You may use any approved
- reference material normally available in the Control Room, including logs. Make all written reports, oral .
I reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: NRC RO A.1.1 Revision: o chg 2 Initial The plant is in MODE 1 and stable at 100% power. You are the Unit Conditions: Supervisor on day shift. Several Licensed Operators are on vacation and the crew is at minimum staffing. The crew began its 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift at 0600.
The Balance of Plant Operator has become ill early (0630) on this last day of day Shift and has been sent home, which places the shift below minimum staffing levels. Current time and Date is 0630 on Wednesday, 13 July 2011.
The SM directed you to call Licensed Operators that are not on vacation to determine availability to take the shift. Their responses follow:
Name Response Operator 1 "I'm on the last day of my seven days off. It was my wife's birthday yesterday and we went to Margaritaville's last night to celebrate. I had some cocktails up d
until closing time and my wife drove home. I'll come in if you want me to. It I usually takes me 45 minutes to get to work, but I can be there in about 30
- minutes."
Operator 2 * "I have a bad cold and just took some Nyquil but, if you really need me, I can be
- I* there in about an hour and 15 minutes. I just need to clean up before I come in." i Operator 3 "It's the last day of my seven days off. I've been sleeping most of the day because I start Night Shift tomorrow night. There's a ball game on TV and I'd rather not come in, but, if you can't find anyone else, then I can be there In about
, an hour, if I really have to."
Operator 4 "I was called in to work control for 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> on Night Shift last night (got off at 2400) and I start Night Shift tomorrow night. IF I hurry, I could probably be there in about 40 minutes."
Operator 5 "I worked my fourth day of night shift on Sunday. I was held over about an hour and a half following the last night shift to discuss a performance issue with management. I start day shift tomorrow. I can be there in about 30 minutes."
4
Initiating Cues: The SM has directed you to determine how soon a relief must be found.
Additionally, determine the following:
- From the Operator list provided, who is eligible to assume shift duties?
- For those who are NOT eligible, what is the reason?
Simulator Reguirements: None
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: NRC RO A 1.1 Revision: 0 chg 2 Task
Title:
Administrative Requirements for Shift Manning Activities - Minimum Crew Complement and Working Hour Limitations.
START TIME: _ _ __
PERFORMANCE STANDARD Evaluator When requested, provide the candidate a copy of Unit 3 Technical Specifications.
NOTE:
~~~--
STEP Obtains and refers to proper procedure. Applicant obtains and refers to a copy of Critical: Grade
- 1 MP3 technical Specifications. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue:
STEP Refer To Technical Specifications, Section Candidate Refers to T.S. 6.2.2.a for Critical: Grade
- 2 6, ADMINISTRATIVE CONTROLS, TIS FACILITY STAFF and determines the Y[ ] S[ ]
6.2.2 for FACILITY STAFF; to determine LCO is specifed as follows: N[X] U[ ]
M P3 Tech minimum shift crew composition. "Each on-duty shift shall be composed of Spees at least the minimum shift crew composition shown in Table 6.2-1" Candidate refers to Table 6.2-1 and Critical: Grade Data Table correctly determines that the minimum Y[ ] S[ ]
NOTE 3 N[X] U[ ]
shift crew composition for the RO position is 2 individuals for MODE 1.
--~-
6
Comments:
Cue:
"The shift crew composition may be one Candidate determines that another RO Critical: Grade STEP less than the minimum requirements of must report within 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />. Y[X] S[]
- 3 Table 6.2-1 for a period of time not to N[ ] U[ ]
M P3 exceed 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> in order to accommodate Tech unexpected absence of on-duty shift crew Specs members provided immediate action is Ta b I e 6.2.1 taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1."
Comments: When requested, provide the candidate a copy of the following:
- SY-AA-FFD-1 01, Fitness for Duty Program .
- LI-AA-700, Fatigue Management and Work Hour Limits for Covered Workers .
The Candidate may evaluate Operator responses in any order.
If the Candidate attempts to contact other 'additional' individuals, provide the following cue:
Cue: No additional Operators will answer the phone or reply to a page.
I I 7
STEP Critical: Grade Determine if Operator 1 can be called in, Candidate refers to the response of
- 4 Y[X] S[ ]
and if not, determine the reason. Operator 1 and determines that Operator N[ ] U[ ]
SY-M-FFO 1 is NOT available due to the 101, section consumption of alcoholic beverages 3.18 Fitness For Duty Call-Out Process within the past 5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br />. (SY-AA-FFD 101).
EXHAUST all other options prior to requiring an individual who has consumed alcohol within the previous five hours to report for work.
Comments: If the Candidate requests additional information from Operator 1, provide any of the following cues as requested:
Cue: Closing time was 0230 II had at least 5 drinks I Started drinking at 2100 II weigh about 180 pounds.
STEP Critical: Grade Determine if Operator 2 can be called in, Candidate refers to the response of
- 5 Y[X) S[ ]
and if not, determine the reason. Operator 2 and determines that Operator N[ ] U[ ]
SY-M-FFO 2 is NOT available due to the use of over 101, section Fitness For Duty Self Reporting the-counter medication that may affect 3.17 hislher ability to perform required duties.
IF notified of the legitimate use of (SY-AA-FFD-1 01) prescription or over-the-counter drugs which may adversely affect an individual's ability to perform work duties, THEN PERFORM the following:
- a. CONTACT the FFDA for evaluation Comments: Although not explicitly restricted by SY-AA-FFD-101. an individual's availability if using over-the-counter medication that may affect hislher ability to the required duties, needs to be evaluated prior to assuming those duties.
8
Cue:
STEP Determine if Operator 3 can be called in, Candidate refers to the response of Critical: Grade
- 6 and if not, determine the reason. Operator 3 and determines that Operator Y[X] S[]
3 is available. Even though although the N[ ] U[ ]
Operator does not want to come in, he/she is the only individual that can assume shift duties.
Comments:
Cue:
STEP Determine if Operator 4 can be called in, Candidate refers to the response of Critical: Grade
- 7 and if not, determine the reason. Operator 4 and determines that Operator Y[X] S[]
4 is NOT available because he/she would N[ ] U[ ]
LI-M-700, section 3.3 work more than 16 hours0.667 days <br />0.0952 weeks <br />0.0219 months <br /> in any rolling 24 Work Hours, Breaks, and Days Off hour period or because he/she would NOT have a break of at least 10 hours0.417 days <br />0.0595 weeks <br />0.0137 months <br /> APPLY the following limits to between successive work periods. (LI individuals regardless of unit status:
M-700)
- No more than 16 work hours in any of night shift, plus 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> of rolling 24-hour period day shift (18 hours0.75 days <br />0.107 weeks <br />0.0247 months <br />)]. Also, the time between 0000 and 0710, is less than 10
- At least a 10-hour break between hours (7 hours0.292 days <br />0.0417 weeks <br />0.00959 months <br />, 10 minutes)].
successive work periods Comments:
Cue:
9
STEP Determine if Operator 5 can be called in, Candidate refers to the response of Critical: Grade
- 8 and if not, determine the reason. Operator 5 and determines that Operator VEX] S[ ]
5 is NOT available because he/she would N[ ] U[ ]
LI-AA-700, section 3.3 work more than 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> in any rolling Work Hours, Breaks, and Days Off 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> period. (LI-AA-700)
APPLY the following limits to
[4, twelve hour night shifts (48 hours2 days <br />0.286 weeks <br />0.0658 months <br />),
individuals regardless of unit status:
plus 1.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> of holdover Monday morning (49.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br />), plus 2, twelve hour
- No more than 72 work hours in any day shifts on 13 and 14 July (73.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br />) rolling 168-hour (7-day) period Comments: I NOTE: The SRO Candidate may determine that Operator 5 IS available, but must write, state or otherwise recognize that Operator 5 is prohibited from working on day shift July 14th (the start of his scheduled four days of day shift.). This is acceptable and meets the critical nature of the standard.
Cue: TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ __
10
VERIFICATION OF ..IPM COMPLETION JPM Number: NRC RO A.1.1 Revision: ~~
Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 15 Actual Time to Complete (minutes):
Overall Result of ..IPM: SAT UNSAT Areas for Improvement I Comments:
11
STUDENT HANDOUT JPM Number: NRC RO A.1.1 Revision: () chg 2 Initial The plant is in MODE 1 and stable at 100% power. You are the Unit Conditions: Supervisor on day shift. Several Licensed Operators are on vacation and the crew is at minimum staffing. The crew began its 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift at 0600.
The Balance of Plant Operator has become ill early (0630) on this last day of day Shift and has been sent home, which places the shift below minimum staffing levels. Current time and Date is 0630 on Wednesday, 13 July 2011.
The SM directed you to call Licensed Operators that are not on vacation to determine availability to take the shift. Their responses follow:
Name Response Operator 1 "I'm on the last day of my seven days off. It was my wife's birthday yesterday and we went to Margaritaville's last night to celebrate. I had some cocktails up until closing time and my wife drove home. I'll come in if you want me to. It usually takes me 45 minutes to get to work, but I can be there in about 30 minutes."
- Operator 2 "I have a bad cold and just took some Nyquil but, if you really need me, I can be there in about an hour and 15 minutes. I just need to clean up before I come in."
Operator 3 "It's the last day of my seven days off. I've been sleeping most of the day because I start Night Shift tomorrow night. There's a ball game on TV and I'd rather not come in, but, if you can't find anyone else, then I can be there In about an hour, if I really have to."
Operator 4 "I was called in to work control for 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> on Night Shift last night (got off at 2400) and I start Night Shift tomorrow night. IF I hurry, I could probably be there in about 40 minutes."
Operator 5 "I worked my fourth day of night shift on Sunday. I was held over about an hour and a half following the last night shift to discuss a performance issue with management. I start day shift tomorrow. I can be there in about 30 minutes."
12
Initiating The 8M has directed you to determine how soon a relief must be found.
Cues:
Additionally, determine the following:
- From the Operator list provided, who is eligible to assume shift duties?
- For those who are NOT eligible, what is the reason?
13
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Review a Surveillance for ReS Leakage, Analyze Results and Take Appropriate Action.
JPM Number: NRC SRO A.1.2 Revision: 0 chg 2 Initiated:
Dave Minnich 03/16/11 Developer Date Reviewed:
Robert Royce 5110111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 6/6/11 Allowed for the termination of the JPM after JPM step 20. 0/1 Modified the JPM to give more information in the initial cue.
This allowed what was required cueing during the conduct of the JPM, to be moved forward. This will allow for efficient administration of the JPM in the classroom environment.
Incorporated as a result of NRC Exam comments made 5/31/11. Modified the initiating cue to provide direction for the applicant to write down any required actions on the student handout. Corrected a typographical error in the JPM number listed on some pages of the JPM.
16/23/11 Added an evaluator note at the end of the ..IPM, stating that 0/2 the critical nature of several procedurally required actions is to successfully get the organization notified and involved with
- respect to the high Umdentlfled Leak rate. Incorporated as a
- result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility:
-MP3----- Examinee:
JPM Number: NRC SRO A.1.2 Revision: 0 chg 2 Task
Title:
Review a Surveillance for RCS Leakage, Analyze Results and Take Appropriate Action.
System: Equipment Control Time Critical Task: ) YES (X) NO Validated Time (minutes): _ _.. : .3. ; .0_ _
Task Number(s): 119-03-003 Applicable To: SRO X RO PEO KIA Number: 2.1.7 KIA Rating: _ _---'-4.;,.;..7_ __
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Review and correctly disposition the surveillance for Res Inventory Balance.
Required Materials: SP 3601F.6 (procedures, equipment, etc.)
Completed surveillance Form SP 3601 F.6 - 001 Calculator General
References:
SP 3601 F.6, Reactor Coolant System Water Inventory Measurement (revision 006-05)
Surveillance Form SP 3601 F.6 - 001, RCS Inventory Balance, (revision 003-01 )
Unit 3 Technical Specifications 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: NRC SRO A.1.2 Revision: () chg 2 Initial Conditions: The plant is at 100% power and you are the Unit Supervisor on shift. The PPC ReS Leakage Program is malfunctioning and the RCS Leakage calculation is due. Computer Services has been notified. You directed the Reactor Operator to perform a manual RCS water inventory balance using SP 3601 F.6, Reactor Coolant System Water Inventory Measurement, which he just completed.
Initiating Cues: Review and disposition the completed Surveillance Form SP 3601 F.6 - 001, RCS Inventory Balance. Other pertinent information:
- The proper initial conditions were established for the data gathering period .
- All assumptions listed in SP-3601 F.6 for a manual ReS leakage calculation can be considered valid.
- VCT Divert was not required during the data gathering period.
- There is no known ReS leakage from other sources inside or outside CTMT.
- 3DGS-V831 (radioactive gaseous waste AOV58 leakoff isolation) and 3DGS-V826 (radioactive gaseous waste AOV54 leakoff isolation) are open.
Record any required actions as a result of your surveillance review at the bottom / back of this page.
Simulator Requirements: None 4
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. 'What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: NRC SRO A.1.2 Revision: o chg 2 Task
Title:
Review a Surveillance for RCS Leakage, Analyze Results and Take Appropriate Action.
START TIME: _ _ __
PERFORMANCE STANDARD Evaluator Provide copy of SP 3601 F.6 and a copy of the completed Surveillance Form SP 3601 F.6 - 001 (with math NOTE: error) to the Candidate.
STEP Review 'Specific Information' blocks on the Verifies "Prerequisites Completed" block Critical: Grade
- 1 surveillance cover sheet. "General is initialed on FORM SP 3601 F.6 001. Y[ J S[ J Prerequisites" . N[X] U[ ]
Verifies "Precautions Noted" block is Critical: Grade initialed on FORM SP 3601F.6 - 001. Y[ ] S[ J N[X] U[ ]
Verifies "Test Authorized By" block is Critical: Grade signed on FORM SP 3601 F.6 - 001. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue:
STEP Review the Data Table. Candidate observes that initial and final Critical: Grade
- 2 data are filled in for the 3 channels of Y[ ] S[ J
'PZR LVL'. N[X] U[ ]
3601F.6 001 Pg 2 of 7 Comments:
6
Cue:
Candidate observes that computer point Critical: Grade Data Table 'CVPZRP' is available, entered as Y[ ] S[ ]
NOTE 3 average narrow range PZR pressure, and N[X] U[ ]
therefore N/A entered in "NARROW RANGE PRES" indication blocks.
Comments:
Cue:
Candidate observes that since RCS Critical: Grade Data Table temperature is > 530 of, data is entered Y[ ] S[ ]
NOTES 4, 5 in the "LOOP 1-4 AVG TEMP" blocks for N[X] U[ ]
calculated average temperature. The blocks for "COLD and HOT LEG WR TEMP" are N/A'd. I I
Comments:
Cue:
Candidate observes that since RCS Critical: Grade pressure is above 1,700 psia, data blocks Y[ ] S[ ]
Data Table for "WIDE RANGE LOOP PRES" are N[X] U[ ]
NOTE 6 N/A'd.
I Comments:
Cue:
Candidate observes that initial and final Critical: Grade data are filled in for PRT, VCT, POTT, Y[ ] s[]
Data Table and CDTT tank levels, as well as Make- N[X] U[ ]
NOTE 6 up Totalizer and the start and end time of the data gathering interval.
Comments:
7
Cue:
STEP Review Calculation Table 1A: f:.VpzR Candidate observes that Data Table Critical: Grade
- 3 values for initial and final PZR level and Y[ ] S[ ]
3601F.6 N[X] U[ ]
001 pressure are entered, and that the correct Pg 3 of 7 Table 18 value for' K' (74.15) for current plant conditions is entered on Table 1A.
Comments:
Cue:
Candidate reviews the calculation for the Critical: Grade change in PZR volume (f:.V PZR ) and Y[ ] S[ ]
determines the calculation is performed N[X] U[ ]
correctly.
Comments:
I Cue:
- STEP Review Calculation Table 2: f:.VVCT Candidate observes that Data Table Critical: Grade
- 4 values for initial and final VCT level are Y[X] S[ ]
3601F.6 entered, but the final value of VCT level N[ ] U[ ]
001 Pg 4 of 7 entered is incorrect.
Comments: The final value of VCT level as entered on the Data Table is 12.2, as opposed to the incorrect value of §2.2 entered on Table 2 (f:.VVCT).
Cue:
8
Candidate reviews the calculation for the Critical: Grade change in VCT volume (AVVCT) and Y[X] S[]
determines the calculation is performed N[ ] U[ ]
correctly, but with the incorrect value of final VCT level. Therefore the change in VCT volume is incorrect.
Evaluator Once the Candidate recognizes that the incorrect value of final VCT level was used in the calculation, Note:
he/she may direct the 'RO' to reperform the surveillance again using the correct value. This is satisfactory.
If so provide the following cue:
Cue: Here is the redone completed surveillance form up through calculating UNIDENTIFIED LEAKAGE.
I Evaluator IF the Candidate intends to continue the surveillance review, provide the following cue:
Note:
- Cue: You have directed the Reactor Operator to reperform the manual RCS water inventory balance.
Here is the redone completed surveillance form up through calculating UNIDENTIFIED LEAKAGE.
STEP Second review Calculation Table 2: Candidate observes that Data Table Critical: Grade *
- 5 AVVCT values for initial and final VCT level are Y[ ] S[ ]
3601F.6- N[X] U[ ]
001 correctly entered.
Pg 4 of 7 Comments:
Cue:
Candidate reviews the calculation for the Critical: Grade change in VCT volume (AVVCT) and Y[ ] S[ ]
determines the calculation is performed N[X] U[ ]
correctly.
Comments:
Cue:
9
STEP Review Calculation Table 3: /1VRCS Candidate observes that initial and final Critical: Grade
- 6 Data Table values for PZR pressure y [ ] S[ ]
3601F.6* N[X] U[ ]
001 (CVPZRP), calculated average Pg 4 of 7 temperature and specific volume are entered.
Comments:
Cue:
Candidate reviews the calculation for Critical: Grade initial and final density (p) and determines Y[ ] S[]
the calculations are performed correctly. N[X] U[ ]
Comments:
Cue:
f-------------
Candidate reviews the calculation for the Critical: Grade change in RCS volume (/1VRcs) and Y[ ] S[]
determines the calculation is performed N[X] U[ ]
correctly.
Comments:
~--'"~--~--
Cue:
STEP Review Calculation Table 4: /1VPRT Candidate observes that Data Table Critical: Grade
- 7 values for initial and final PRT level are Y[ ] S[ ]
3601F.6*
001 entered, and reviews the calculation for N[X] U[ ]
Pg 5 of 7 the change in PRT volume (/1 V PRT ) and determines the calculation is performed correctly.
Comments:
10
Cue:
STEP Review Calculation Table 5: L1V POTT Candidate observes that Oata Table Critical: Grade
- 8 values for initial and final POTT level are Y[ J S[J 3601F.6 001 entered, and reviews the calculation for N[X] U[ ]
Pg 5 of 7 the change in POTT volume (L1VPOTT) and determines the calculation is performed correctly.
Comments:
Cue:
STEP Review Calculation Table 6: L1VCOTT Candidate observes that Data Table Critical: Grade
- 9 values for initial and final CDTT level are y [ ] S[ ]
3601F.6 001 entered, and reviews the calculation for N[XJ U[ ]
Pg 5 of 7 the change in COTT volume (L1Vcon) and determines the calculation is performed correctly.
Comments:
Cue:
STEP Review Calculation Table 7: VMakeup and Candidate observes that Data Table Critical: Grade
- 10 VOivert values for initial and final makeup totalizer Y[ ] S[ ]
3601F.6 001 flow are entered, and reviews the N[X] U[ ]
Pg 6 of 7 calculation for the volume of makeup and determines that Makeup did not occur during the data gathering interval.
Comments:
Cue:
11
~~- '"~~~~~~ -------- ------
Candidate recognizes that the portion of Critical: Grade Table 7 that addresses the total volume Y[ J S[J diverted has been N/A'd by the RD. N[X] U[ J Comments:
Cue:
STEP Review Calculation Table 8: Other Candidate recognizes that Calculation Critical: Grade
- 11 Source of Leakage Table 8 for other sources of leakage has Y[ ] S[]
3601F.6 N[X] U[ J 001 been N/A'd by the RD.
Pg 6 of 7 Comments: A detailed review of these calculations is not required to meet the critical nature of the step; only that Total RCS Leakage and Total RCS Leak Rate will not be accurate values.
Cue:
STEP Review Calculation Table 9: ATime, Total Candidate observes that Data Table Critical: Grade
3601F.6 N[X] U[ ]
001 entered and reviews the calculation for Pg 6 of 7 ATime and determines the calculation is performed correctly.
Comments:
Cue:
Candidate observes that previously Critical: Grade calculated Table volumes are entered for Y[ J S[ ]
the total RCS leakage calculation. N[X] U[ ]
Comments:
Cue:
12
Candidate reviews the calculation for Critical: Grade Total RCS Leakage and determines the Y[ ] S[]
calculation is performed correctly. N[X] U[ ]
Comments:
Cue:
Candidate reviews the calculation for the Critical: Grade Total ReS Leak Rate and determines the Y[ ] S[ ]
calculation is performed correctly. N[X] U[ ]
Comments: The candidate may express concern about the significantly high total RCS Leak Rate (0.961 gpm) and desire to initiate immediate action. If so provide the following cue:
Cue: Continue with your review.
STEP Review Calculation Table 10: Candidate observes that previously Critical: Grade
- 13 IDENTIFIED LEAKAGE calculated collected volumes and ATime Y[ ] S[ ]
3601F.6 001 are entered for the identified leakage N[X] U[ ]
Pg 7 of 7 calculation.
Comments:
Cue:
Candidate reviews the calculation for Critical: Grade IDENTIFIED LEAKAGE and determines Y[ ] S[ ]
the calculation is performed correctly. N[X] U[ ]
Comments:
Cue:
13
Candidate recognizes that IDENTIFIED Critical: Grade LEAKAGE is less than 10 gpm, and Y[X] S[]
therefore the TIS acceptance criteria is N[ ] U[ ]
met.
STEP Review Calculation Table 11: Candidate observes that previously Critical: Grade
- 15 UNIDENTIFIED LEAKAGE calculated values Total RCS Leak Rate, Y[ ] S[ ]
3601F.6 N[X] U[ ]
001 IDENTIFIED LEAKAGE, change in PDTT Pg 7 of 7 volume and ~ Time are entered for the unidentified leakage calculation.
Comments:
Cue:
Candidate reviews the calculation for Critical: Grade UNIDENTIFIED LEAKAGE and Y[ ] S[ ]
determines the calculation is performed N[X] U[ ]
correctly.
Comments:
Cue:
Candidate recognizes that Critical: Grade UNIDENTIFIED LEAKAGE is less than 1 Y[X] S[ ]
gpm, and therefore the TIS acceptance N[ ] U[ ]
criteria is met.
Comments: The candidate may express concern about the significantly high value of UNIDENTIFIED LEAKAGE (0.913 gpm) and desire to initiate immediate action to get the organization involved. If so provide the following cue:
Cue: Continue with your review, including any SP 3601 F.6 actions required.
14
STEP IF leakage approaches either of the Candidate writes down or otherwise Critical: Grade
- 16 following limits, INITIATE a Condition communicates that actual Y[X] S[ ]
Report to ensure compliance with UNIDENTIFIED LEAKAGE (0.913 gpm) N[ ] U[ ]
SP 3601F.6 Step 4.3.5 Maintenance Rule requirements: is in excess of 0.75 gpm, and a Condition Report needs to be initiated.
- IDENTIFIED LEAKAGE --- 2.5 gpm (25% of T.8. Limit)
- UNIDENTIFIED LEAKAGE --- 0.75 gpm (75% of T.S. Limit)
Comments:
Cue:
STEP IF UNIDENTIFIED LEAKAGE is abnormally Candidate writes down or otherwise Critical: Grade
- 17 high, greater than 0.6 gpm or a step communicates that a call to Engineering Y[X] S[ ]
increase of 0.2 gpm, PERFORM the N[ ] U[ ]
Step 4.3.6.a needs to be made, to inform them of the following: leak rate.
NOTIFY Engineering of leak rate.
r-- ..----
Comments:
Cue:
REVIEW computer printout or SP Candidate refers to Table 5 on SP Critical: Grade Step 4.3.6.b 3601 F.6 -001, Table 5, and 3601 F.6 - 001, and reviews data Y[ ] S[ ]
DETERMINE the volume changes N[X] U[ ]
associated with the PDTT volume associated with the PDTT. change.
Comments:
Cue:
15
VERIFY all inventory changes to the Candidate recognizes that 3DGS-V831 Critical: Grade Step 4.3.6.c PDTT are related to RCS or CVCS Y[ ] S[ ]
and V826 are OPEN.
changes as follows ..... N[X] U[ ]
- 3DGS---V831, radioactive gaseous waste AOV58 leakoff isolation, closed
- 3DGS---V826, radioactive gaseous waste AOV54 leakoff isolation, closed Comments: The status of 3DGS-V831 and V826 were given in the initial cue and are open. Therefore, all PDTT inventory changes cannot be verified to be all RCS or CVCS related.
Cue:
Candidate determines that since Critical: Grade Y[ ] S[ ]
inventory changes to the PDTT are NOT N[X] U[ ]
all related to RCS or CVCS, UNIDENTIFIED LEAKAGE cannot be corrected.
Comments:
Cue:
IF all PDTT inventory changes are RCS or Candidate reviews step 4.3.6.d and Critical: Grade CVCS related, Refer To SP 3601 F.6---001, recognizes that it does not apply. Y[ ] S[ ]
Step 4.3.6.d N[X] U[ ]
Table 12 .....
Comments:
Cue:
16
~
STEP IF POD inventory changes can not be Candidate takes action or otherwise Critical: Grade
leakage, Refer To SP 3601 F.6---001, Table N[ ] U[ ]
Step 4.3.6.e UNIDENTIFIED LEAKAGE needs to be 11 , and RECORD UNIDENTIFIED entered in the SM log.
LEAKAGE from Table 11 in the SM log for the TIS surveillance.
Comments:
Cue: (If required) The value for UNIDENTIFIED LEAKAGE will be entered in the SM log by the STA.
STEP IF leakage calculation was initiated for the Candidate recognizes that the RO should Critical: Grade
- 19 required daily leakage determination (per have already attached a copy of the last Y[ ] S[]
SP 3670.1---001), ATTACH a copy of the N[X] U[ ]
Step 4.3.7 page to the Shiftly Control Room Rounds.
last page of SP 3601 F.6---001, to SP 3670.1---001, "MODE 1---4 Daily and Shiftly Control Room Rounds."
Comments:
Cue:
17
STEP IF leakage exceeds any of the following Candidate recognizes the need to refer to Critical: Grade
C OP 200.15 to determine required Leakage Trending and Investigation," and N[X] U[ ]
Step 4.3.8 actions.
PERFORM required actions:
- One seven (7) day rolling average of daily RCS UNIDENTIFIED LEAKAGE rates greater than 0.1 gpm
- Two consecutive daily RCS UNIDENTIFIED LEAKAGE rates greater than 0.15 gpm
- One daily RCS UNIDENTIFIED LEAKAGE rate greater than 0.3 gpm Comments: I When the Candidate requests a copy of C OP 200.15, provide the following cue:
Cue: I TERMINATION CUE: The evaluation for this JPM is concluded.
Evaluator Note:
IasThere are 3 critical standards associated with JPM steps 16, 17 and 18: Initiate a Condition Report a result of high Unidentified Leakage, notify Engineering of the leak rate and record the Unidentified Leakage in the SM log, respectively. If the Candidate writes down or otherwise recognizes 2 out of 3 of these requirements, consider the Candidate successfully completed the critical nature of these steps, which ultimately is to get the organization notified and involved.
STOP TIME: _ _ __
18
VERIFICA1"ION OF JPM COMPLE1"ION JPM Number: NRC SRO A.1.2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 30 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement / Comments:
19
STUDENT HANDOUT JPM Number: 1\1 RC SRO A.1.2 Revision: o chg 2 Initial Conditions: The plant is at 100% power and you are the Unit Supervisor on shift. The PPC RCS Leakage Program is malfunctioning and the RCS Leakage calculation is due. Computer Services has been notified. You directed the Reactor Operator to perform a manual RCS water inventory balance using SP 3601 F.6, Reactor Coolant System Water Inventory Measurement, which he just completed.
Initiating Cues: Review and disposition the completed Surveillance Form SP 3601 F.6 - 001, RCS Inventory Balance. Other pertinent information:
- The proper initial conditions were established for the data gathering period.
- VCT Divert was not required during the data gathering period.
- 3DGS-V831 (radioactive gaseous waste AOV58 leakoff isolation) and 3DGS-V826 (radioactive gaseous waste AOV54 leakoff isolation) are open.
Record any required actions as a result of your surveillance review at the bottom I back of this page.
20
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Determine Time to Core Boil to verify SBO Diesel availability after maintenance.
JPMNumber: NRCSROA.2 Revision:
Initiated:
Robert Royce 07114/2011 Developer Date Reviewed:
Date Approved:
1/""1/\\.
Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 07/14/2011 Completely changed JPM due to issues with previous JPM answer 2 2
JPM WORKSHEET Facility: Millstone Unit 3 Examinee:
JPMNumber: NRC SROA.2 Revision: 2 Task
Title:
Determine Time to Core Boil to verify SBO Diesel availability after maintenance.
System: Shutdown Safety Assessment Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 15 Task Number(s): 341-01-162, Perform a Shutdown Safety Assessment Checklist Applicable To: SRO X RO PEO K/A GEN.2.2.18 Knowledge of the process for managing maintenance activities KIA 2.6/3.9 Number: during shutdown operations, such as risk assessments, work prioritization, etc. Rating:
Method of Testing: Simulated Performance: Actual Performance: X Location: Classroom: X Simulator: In-Plant:
Task Standards: Determine time to core boil.
Required Materials: OU-M3-201, Shutdown Safety Assessment Checklist (Rev. 3)
Copy ofOU-M3-201 Attachment 1 with Train A circled, and specific dates and times filled in for
- Date/Time Performed: July 15,2011/0937 (9: 37 AM),
- Date/Time of Shutdown: July 12, 20111 0001 (1201 AM).
General
References:
None
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as ifthe evolution was actually being performed.
3
JPM WORKSHEET JPM Number: NRC SROA.2 Revision: 2 Initial Conditions: The plant is shutdown in mid-cycle for SG Relief Valve repairs.
Current conditions are as follows:
RCS Pressure: 70 psia RCS Temperature: 140°F RCS loops: All filled pzr level: Solid The SBO Diesel has been out of service for maintenance, and has just been restored.
The Date and time of shutdown was July 12,2011 at 0001 (1201 AM).
Initiating Cues: The SM directs you to perform the following:
Determine the time to core boiling using OU-M3-201, Shutdown Safety Assessment Checklist, sections 1 and 2, using July 15, 2011 at 0937 (9: 37 AM) as the current time, and Based on the time to core boiling, determine whether the SBO Diesel can be considered as available as a Shutdown Risk Power Source.
Simulator Requirements: None
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what hislher simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION lPMNumber: NRCSRO A_2 Revision: 2 Task Determine Time to Core Boil to verify SBO Diesel availability after maintenance.
STARTT~E: _______
STEP Performance: Completes OU-M3-201, Step Standard: Critical: Grade
- 1 3.2.1a (Section 1) 1. Train A already circled. Y [ ] N [X] S[]U[]
- 1. CIRCLE appropriate Protected Train.
- 2. CHECK box if single train exception in 2. Single train exception box is not checked.
effect.
- 3. RECORD date and time assessment is 3. Date and time already filled in.
being performed.
- 4. RECORD date and time of reactor 4. Date and time already filled in shutdown.
S. INDICATE if assessment is being S. "Actual Conditions" box already checked.
performed for Actual or Predicted Conditions.
- 6. CALCULATE and RECORD number 6. RECORDS 3.4 days of Days Shutdown between the (3 days, 9 hours0.375 days <br />0.0536 weeks <br />0.0123 months <br />, 36 minutes) date/time (Actual or Predicted) and shutdown date/time.
- 7. Enters Determine SBO diesel availability for
- 7. ENTER a brief description of the reason Shutdown Risk Power Source." Or similar assessment is being performed. statement.
Cue:
Comments:
5
STEP Performance: Step 3.2.1b (Section 2) Standard: Critical: Grade
- 2
- 1. IF in MODE 0, THEN CHECK "NA 1. Do NOT check the "NA (mode 0)" box, and do Y[ 1 N [X] S[]U[]
(Mode 0)" and GO TO step 3.2.l.c. NOT go to step 3.2.1 c.
Time to B0 i1 Cue:
Comments:
STEP Performance: Step 3.2.1b (Section 2) Standard: Critical: Grade
- 3
- 2. RKFER to applicable attachments in OP 2. Determines pressure, temp and level from Y [ ] N [X] S[] U[]
3216, Reactor Coolant System Drain initiating cues.
(ICCE), and OP 32601, RCS Inventory RCS Pressure: 70 psia Time Tracking, and DETERMINE RCS RCS Temperature: 140°F to Pressure, RCS Temp, and RCS Level. RCS Level: Loops Filled, Pzr Solid B0 i1 Cue: If asked for applicable attachments in OP 3216 and I or OP 32611, direct the candidate to use RCS Pressure, Temperature, and Level values provided in the Initial Conditions of the JPM.
Comments:
~.~--~~~~-~---
STEP Performance: Step 3.2.1 b (Section 2) Standard: Critical: Grade
- 4
- 3. REFER to Attachment 8 through 3. Moves to Attachment 8 ofOU-M3-201 Y [] N [X] S[] U[]
Attachment 24 and DETERMINE Time RCS Time to Boil.
to B0 i1 Cue:
6
STEP Perfonnance: Attachment 8, step 1.a Standard: Critical: Grade *
- 5 IF prior to core offload OR during core Detennines actions are required due to being in a non Y[ ] N[X] Sl]U[]
offload OR in a non-refueling outage, refueling outage.
THEN DETERMINE the time to core boiling as follows:
Time a. RECORD date and time of reactor July 12,2011/0001 (1201 AM) is already recorded as to shutdown on Attachment 1. date and time of shutdown.
B0 i1 Cue:
Comments:
STEP Perfonnance: Attachment 8, step 1.b Standard: Critical: Grade
- 6 Y[] N[X] S[]U[]
CALCULATE number of "Days Shutdown" RECORDS 3.4 days Time between SSSA perfonned date/time and (3 days, 9 hours0.375 days <br />0.0536 weeks <br />0.0123 months <br />, 36 minutes) to RECORED on Attachment 1.
B0 i 1 Cue:
Comments: Time shutdown was already recorded in JPM step 1.6 STEP Performance: Attachment 8, step l.c Standard: Critical: Grade
- 7 Y [ ] N [X] S[ ]U[]
Time IF the plant is in MODE 5, THEN Recognizes plant is in MODE 5 and continues in to PERFORM the following: Attachment 8, step l.c B0 i 1 Cue:
Comments:
7
- STEP Performance: Attachment 8, step I.c.1) Standard: Critical: Grade
- 8 Y [ ] N [Xl S[ ]U[]
Time IF bubble is being maintained in the Does not mark "NI A" for RCS Time to Boil to Pressurizer, THEN ENTER "NI A" for RCS B0 i1 Time to Boil.
Cue:
Comments:
STEP Performance: Attachment 8, step 1.c.2) Standard: Critical: Grade
- 9 Y[ ] N[X] S[ ] U[ ]
Ti me IF RCS is pressurized 2: 170 psia, THEN Does NOT go to attachment 9, 10, or 11.
to REFER to the attachment listed below ...
B0 i 1 Cue:
Comments:
1ST E P Ip~~formance: Attachment 8, step l.c.3) Standard: Critical: Grade
- 10 Y [ ] N [X] S [ ] U[ ]
Time IF RCS is pressurized 2: 30 psia AND <170 Refers to Attachment 12.
to psia, THEN REFER to the attachment listed B0 i1 below and SELECT "Time to Boil" based upon number of RCS loops and "Shutdown Time."
IF RCS temperature is::s 140°F AND
> 110°F, THEN use Attachment 12.
Cue:
Commcnts:
8
S T E P I Performance: Attachment 12 Standard: Critical: Grade
- 11 Y [X] N [ ] S[ ] U[
Time Per Table in Attachment 12 Determines time to core boil based on shutdown to time of3.25 days (it is NOT conservative to go B0 i I And Attachment 8, Notes prior to step 1: down to the 3.5 day line, since there is more decay Shutdown Time should be calculated from heat at 3.25 days, and the 3.5 day point has not the time when all Control Banks were fully been reached yet), with 4 Loops available, and inserted and should be rounded down to the determines time to core boil is 0.510 Hours nearest time listed on the applicable Time to Boil Table.
Cue:
Comments STEP Performance: Attachment 8, Notes prior Standard: Critical: Grade
- 12 to step 1. Y [X] N [ ] S[ ] U [ ]
ssa Diesel If time to core boiling is less::::: 30 Reports that the SBO diesel IS available as a power Avail- minutes, the SBO is considered source.
ability unavailable as a power source.
Cue:
Comments:
TERMINAnON CUE: The evaluation for this JPM is concluded.
STOP TIME: _ __
9
VERIFICATION OF JPM COMPLETION JPMNumber: NRCSROA,2 Revision: 2 Date Performed:
Student:
Evaluator:
For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 15 Actual Time to Complete (minutes):
JPM Work Practice Evaluation*: SAT UNSAT N/A Overall Result of JPM: SAT UNSAT
- Pass/Fail criteria for the Work Practice portion of the JPM is that the trainee must 1) Perform the task correctly and lAW procedure use and adherence requirements, 2) Never put anyone's safety at risk, 3) Never put equipment reliability at risk, 4) Never violate radiological work practices, 5)
Demonstrate effective use of event-free human performance tools. If a failure occurs, indicate why the failure occurred and which of these 5 task performance criteria contributed to the failure.
Areas for Improvement / Comments:
10
STUDENT HANDOUT JPMNumber: JPM SROA.2 Revision: 2 Initial Conditions: The plant is shutdown in mid-cycle for sa Relief Valve repairs. Current conditions are as follows:
Res Pressure: 70 psia Res Temperature: 140°F Res loops: All filled Pzr level: Solid The SBO Diesel has been out of service for maintenance, and has just been restored.
The Date and time of shutdown was July 12,2011 at 0001 (1201 AM).
Initiating Cues: The SM directs you to perform the following:
Determine the time to core boiling using OU-M3-201, Shutdown Safety Assessment Checklist, sections 1 and 2, using July 15,2011 at 0937 (9: 37 AM) as the current time, and Based on the time to core boiling, determine whether the SBO Diesel can be considered as available as a Shutdown Risk Power Source.
11
DOMINION OU*M3*201 REVISION 3 PAGE 16 OF 114 Millstone Unit 3 Shutdown Safety Assessment
'Dominion" (SSA) Checklist OU*M3*201 - Attachment 1 Page 1 of 7 D Single train exception in effect Date/Time Performed: :J: " 15/1/1 tJ Q'37 Date/Time of Shutdown:.h (r 12/1// 000 {
~tual Conditions Days Shutdown: _ _ _ _ _ __
D Predicted Conditions for _ _ _ _ _ _ __ Reason for SSA (e.g., 00:00 hour, mode change, configuration changes):
RCS Temp: _ _ OF ORCS Level: _ _ feet above flange ORCS Time to Soil: _ _ _ _ __
hours o 'A' Train RHR (1 )
RED D's' Train RHR (1 )
ORANGE D > 23' refuel cavity
(> 40.4% adjusted level RCS-Ll462)
{VA 2 YELLOW 3 GREEN D All conditions met to meet natural circul (1 )
the RCS 0 A / S f C{O) / C (P) f NA (Circle One)
Decay Heat Removal Total D NA for Mode 0 Form 1'10. 729450(Mar 2010)
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Evaluation of an Unplanned Gaseous Release.
JPM Number: NRC SRO A.3 Revision: 0 chg 2 Initiated:
Dave Minnich 03/14/11 Developer Date Reviewed:
Robert Royce 5110111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 6/7/11 Modified the JPM to give more information in the initial cue. 0/'1 This allowed what was required cueing during the conduct of the ...1PM, to be moved forward. This resulted in modifying initial conditions, the initial cue and renumbering of steps.
This will allow for efficient administration of the JPM in the classroom environment. Also deleted the first few JPM steps that involved the Candidate determining if the event was classifiable. Added JPM steps for the Candidate to actually perform the unplanned gaseous release rate calculation.
Incorporated as a result of NRC Exam comments made 5/31/11. Modified the initiating cue to provide direction for the applicant to write down any required actions or reporting requirements on the student handout.
6/23/11 In Initial Conditions, split one bulleted statement into two for 0/2 readability. In the Initiating Cue, separated the IVIP-26-EPI FAP06 step 2.1.3 description from the beginning and end of the cue for readability. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility: Millstone Unit 3 Examinee:
JPM Number: NRC SRO A.3 Revision: 0 chg 2 Task
Title:
Evaluation of an Unplanned Gaseous Release.
System: GENERIC Time Critical Task: ) YES (X) NO Validated Time (minutesi.___3_0_ __
Task Number(s): 301-05-366 Applicable To: SRO X RO _ __ PEO - - -
KIA Number: 2.3.11 KIA Rating: _ _ _ 4...;..3_ __
Method of Testing: Simulated Actual x Performance: Performance:
Location: Classroom: X Simulator: In-Plant:
Task Standards: Evaluate an unplanned gaseous release and as a result, the proper notifications and event reporting requirements.
Required Materials:
(procedures. equipment. RAC 14. Non-Emergency Station Events, Rev 003-01 etc.)
General
References:
RAC 05, Reportability Determinations and Licensee Event Reports AOP 3573, Radiation Monitor Alarm Response MP-26-EPA-REF03, Millstone Unit 3 Emergency Action Level (EAL)
Technical Basis Document 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: SRO A.3 Revision: o chg 2 Initial The plant is at 100% power, and you are the Extra Senior Licensed Conditions: Operator on shift. About 30 minutes ago MB2B 2-8 "RADIATION ALERT" alarmed. The RO has determined and reported that 3HVR*RE10B is in alert. The Control Room Team has entered AOP 3573, Radiation Monitor Alarm Response, and have completed actions for 3HVR*RE1 08. Other pertinent information:
- There is no indication that there is an equipment problem associated with 3HVR*RE10B.
- 3HVR*10B has cleared the alert setpoint. It is currently reading 1.0 x 10-5 jJCi/cc and slowly lowering. The highest reading during the event was 6.0 x 10-5 fCi/cc. The highest 10 minute average net increase was 3 x 10- jJCi/cc.
- The SM has already determined that the event is not Classifiable at the Alert level or above.
- The Chemistry Department has determined that Delta-Two Posture Code Limits (for OU1, Unplanned Release) have not been exceeded.
- The Chemistry Department has determined that the release did not exceed 40CFR302 limits (EPA Reportable Releases).
- HP, Chemistry, Environmental, Licensing and other personnel are in the Control Room ready to assist.
- The Control Room Team has determined that the cause of the release was a Degasifier overpressure event that lifted the degasifier condenser relief valve (3GWS-RV35). Initially, the relief valve failed to reseat, but has since drifted closed. Turbine Building vent stack flowrate is 186,000 cfm.
4
Initiating The SM has directed you to carry out step 2.1.3 of MP-26-EPI-FAP06, Cues: Classification and PARs .....
"IF the event has been evaluated and is not addressed by the Emergency Action Level tables, Go To RAC 14, "Non-Emergency Station Events."
Record any required actions or reporting requirements as a result of your review at the bottom of this page.
Simulator Requirements: NONE
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: NRC SRO A.3 Revision: o chg 2 Task
Title:
Evaluation of an Unplanned Gaseous Release.
START TIME: _ _ __
PERFORMANCE STANDARD Evaluator When requested, provide the Candidate a copy of RAe 14, Non-Emergency Station Events.
NOTE:
STEP IF the event has been evaluated and Obtains and refers to a copy of RAC Critical: Grade
- 1 is not addressed by the Emergency 14, Non-Emergency Station Events. Y [ ] N [X] S[]U[]
Action Level tables, Go To RAC 14, FAP06 step "Non-Emergency Station Events."
2.1 .3 The candidate may also request a copy of MP-26-EPI-FAP06 "Classification and PARs.
Comments:
Cue:
STEP Review Precautions. (RAC 14, Candidate reviews precautions 3.1 Critical: Grade
- 2 Y [ ] N [X] S[]U[]
Section 3) through 3.8.
Cue:
Comments:
6
STEP Initial Event Reportability Candidate recognizes that sufficient Critical: Grade
- 3 Determination cause may exist for reporting this Y[] N[X] S[]U[]
IF sufficient cause exists for reporting event.
RAG 14, step 4.1.1.a a non-emergency event, PERFORM the following:
ANALYZE available information and DEVELOP a general understanding of event in progress.
Comments:
Cue:
STEP ASSIGN staff to collect and track Candidate requests additional staff. Critical: Grade
- 4 Y[] N[X] S[]U[]
information.
RAG 14, step 4.1.1.b Comments: If the Candidate requests additional personnel to track the event, or requests additional assistance, provide the above cue:
Cue: Additional assistance will be available shortly. Continue with your task.
STEP IF necessary, REQUEST Candidate reviews the step. Critical: Grade
- 5 Y [ ] N [X] S[]U[]
assistance from any of the RAG 14, step following, as applicable, to 4.1.1.c determine reportability and respond to event:
comme~~j .
7
Cue:
STEP As required, REQUeST Station Duty Candidate recognizes the need to Critical: Grade
- 6 Officer (typically the non-affected unit call Unit 2 to request the Station Duty Y[] N[X] S[]U[]
STA) and Emergency Communicator Officer and Emergency RAe 14, step (typically the non-affected unit WC 4.1.1.d Communicator report to the Unit 3 SRO) report to the Control Room and Control Room.
prepare to send a Non Emergency Event Report.
Comments: The Candidate may wait to determine if the event is reportable prior to requesting the SDO and EC. This is acceptable.
Cue:
STEP Certain reportable environmental Candidate reviews the NOTE. Critical: Grade
- 7 events, including those not reportable Y [ ] N [X] S[]U[]
to the NRC, have reportable time RAe 14, step limits listed in Attachments 1 through 4.1.1.e NOTE 7.
Comments:
Cue:
STEP IF event is an unplanned or Candidate recognizes that the event Critical: Grade
- 8 unmonitored radioactive release, potentially is an unplanned Y[X]N[ ] S[]U[]
Refer To and PERFORM Section 4.2, radioactive release, and proceeds to RAe 14, step "Evaluation of an Unplanned 4.1.1.e Section 4.2.
Radioactive Release."
Comments:
8
Cue:
STEP Leaks from plant systems, e.g., aux Candidate reviews the CAUTION. Critical: Grade
- 9 steam, condensate. etc., that have the Y[] N[Xl S[]U[l potential to be radioactive could RAC 14, step 4.2.1 constitute an unplanned, unmonitored CAUTION radioactive release and must be evaluated.
Comments:
Cue:
STEP IF an unplanned or unmonitored Candidate recognizes the need to Critical: Grade
- 10 radioactive release has occurred call Health Physics, Environmental Y [ ] N [X] S[]U[]
including any spills and/or leaks of and Licensing.
RAC 14, step 4.2.1 radioactive liquid, NOTIFY the following, as applicable, for assistance in determining reportability requirements:
- Health Physics Supervision
- Unit Chemistry
- Environmental Compliance Coordinator
- Licensing I
9
-~~ ~~-~~
Comments:
Cue:
STEP IF release source is not identified, Candidate recognizes that the Critical: Grade
- 11 Refer To Attachment 8, Section 6, release source is already identified. Y[) N[X) S[)U[]
"Maintenance Operations," and RAC 14, step 4.2.2 REVI EW current plant operations to identify source of release.
Comments: The release source (3GWS-RV35) was given in Initial Conditions.
Cue:
STEP IF applicable, Refer To and Candidate recognizes that C OP Critical: Grade
- 12 IMPLEMENT C OP 200.4 "Response 200.4 does not apply and proceeds Y [ ] N [X] S[)U[)
to Plant Leaks." to step 4.2.4.
RAG 14, step
4.2.3 Comments
Cue:
STEP IF applicable, Refer To and Candidate recognizes that C OP Critical: Grade
- 13 IMPLEMENT C OP 200.5, "Oil, 200.5 does not apply and proceeds Y[] N[X] S[]U[]
Hazardous Material, Hazardous to step 4.2.5.
RAC 14, step 4.2.4 Waste, and Mixed Waste Contingency Plan."
Comments:
--- ............. _._ ~~~ -~~
-~--
10
~~~~c ~~-~~ ~~- ~-~~
Cue:
STEP IF applicable, Refer To C OP 200.11, Candidate recognizes that C OP Critical: Grade
- 14 "Operation of a Cross Contaminated 200.11 does not apply and proceeds Y[] N[X] S[]U[]
System," and simultaneously to step 4.2.6.
RAC 14, step 4.2.5 COMPLETE requirements.
Comments: The Degasifier relief valve and associated piping are considered contaminated.
Cue:
STEP Refer To Attachment 8, Section 2, Candidate refers to Attachment 8, Critical: Grade
- 15 "Reportable Releases," and REVIEW Section 2, and reviews for type of Y[] N[X] S[]U[]
for type of release involved. release involved.
RAG 14, step 4.2.6 -----
Comments:
Cue:
Candidate recognizes the following Critical: Grade RAG 14, AU 8 types of release may be involved: Y [ ] N [X] S[]U[]
Section 2
- 1. Releases Exceeding Gaseous Release Rate Limit
- 2. Unplanned Gaseous Releases Comments:
Cue:
I 11
STEP Refer To Attachment 8, Section 3, Candidate refers to Attachment 8, Critical: Grade
- 16 "Release Calculations," and Section 3, and reviews various the Y [ ] N [X] S[]U[]
COMPLETE calculations listed for Release Calculations to determine RAe 14, step 4.2.7 released material, or other method as which may apply.
approved by the Chemistry Department.
Comments: The various Release Calculations listed in Section 3 follow in JPM steps 17 through 20.
Cue:
STEP GASEOUS RELEASE RATE LIMIT Candidate recognizes that Critical: Grade
- 17 3HVR*RE10B did NOT exceed its Y [ ] N [X] S[]U[]
If an effluent radiation monitor alarm setpoint, therefore this release RAe 14, Att 8 Section 3 (HVR-RE 1OB), exceeds the alarm calculation does not apply.
setpoint request that Chemistry enter SP 823/2823/3823 to determine if the instantaneous release rate limit has been exceeded.
Comments:
Cue:
STEP UNMONITORED GASEOUS Candidate recognizes that the Critical: Grade
- 18 RELEASES: release was monitored, therefore this Y[] N[X] S[]U[]
calculation does not apply.
RAe 14, AU 8 Section 3 Comments:
12
Cue:
STEP UNPLANNED GASEOUS RELEASES Candidate recognizes that the Critical: Grade
- 19 release path was via the Unit 3 Vent Y[X] N[] S[]U[]
Unit 3 Vent (Turbine Building stack); therefore RAe 14, At! 8 Section 3 this calculation does apply.
Average 10 Minute Net Increase on HVR-RE 108 in IJci/cc x Flow Rate (CFM) x 472 cc/sec x Pressure Correction
= IJCi/sec Comments: When the Candidate requests information to begin the calculation, or requests Chemistry to perform the calculation, provide the following cue:
Cue: Perform the calculation.
Candidate refers to the initial Critical: Grade conditions and records values for the Y[] N[X] S[]U[]
average 10 minute net increase on 3HVR*RE10B (3 x 10-5 j.1Ci/cc) and Unit 3 Vent stack flowrate (186,000 cfm).
13
Using these recorded values, the Critical: Grade conversion factor of 472 cc/sec/cfm, Y [ ] N [X] S[]U[l and pressure correction (1.5), the Candidate calculates and records a release rate 3951 lJci/sec.
Comments:
Cue:
Unit 3 SLCRS Candidate recognizes that any Critical: Grade contribution from the SLCRS or ESF Y [ ] N [X] S[]U[]
Unit 3 ESF Bldg. Building effluent release paths will be negligible compared to Unit 3 Vent Unit 3 Total = <1500 ~Ci/sec path release.
Comments: Candidate may recognize at this point that 3951 J,Jci/sec is NOT <1500 ~Ci/sec. Therefore, an unplanned gaseous release has occurred from Unit 3.
Cue:
STEP UNPLANNED OR UNMONITORED Candidate recognizes that the Critical: I Grade
- 20 LIQUID RELEASE: release was gaseous, therefore this calculation does not apply .
Y [ ]N [X J IS[ J U[ J
.... r* .-----..
Comments:
Cue:
14
STEP Refer To the following and Candidate refers to Attachment 8, Critical: Grade
- 21 DETERMINE if release exceeds limits: Section 2, and reviews to determine if Y[] N[X] S[]U[]
the release exceeds a limit.
RAe 14, step 4.2.8 Attachment 8, Section 2, "Reportable Releases."
Attachment 8, Section 4, "EPA Reportable Releases."
Comments:
Cue: I STEP Unplanned Gaseous Releases (State Candidate recognizes that 3951 Critical: Grade
- 22 Regulation) tJci/sec is NOT <1500 tJCi/sec. Y[X] N[J S[]U(]
Therefore, an unplanned gaseous RAe 14, Ali 8 Section 2 Any increase in noble gas release release has occurred from Unit 3.
rates which, when averaged over 10 minutes, is greater than 1500 microcuries/sec above the normal (existing) release rate and this increase is not due to a planned or expected event as listed in Section 6, "Maintenance Operations."
Comments:
Cue:
~
15
Candidate recognizes from initial Critical: Grade conditions that the release did NOT Y [ ] N [X] S[]U[]
exceed 40CFR302 limits (EPA Reportable Releases).
Comments:
Cue:
STEP IF release exceeds limits, Refer To Candidate refers to Attachments 1 Critical: Grade
- 23 appropriate Attachments 1 through 7 through 7 and determines that Y [ ] N [X] S[]U[]
and DIRECT Emergency Attachment 2, "Radiological RAC 14, step 4.2.9 Communicator to perform Section 4.7, Events", is the applicable "Radiopager Notifications." attachment.
Comments:
Cue:
Candidate directs the Emergency Critical: Grade Communicator to perform Section Y [ ] N [X] S[]U[]
4.7, "Radiopager Notifications."
Comments: Provide the following cue:
Cue: The Emergency Communicator is performing Section 4.7, "Radiopager Notifications."
16
c-gTEP Candidate matches the event in Critical: Grade
- 24 progress with the following event Y [ ] N [X] S[]U[]
description in attachment 2:
"Any unplanned, unmonitored, or unauthorized release of radiological material to the environment."
Candidate correctly determines the Critical: Grade NRC Reporting Requirement for the Y[X]N[] S[]U[]
event is as follows:
"Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> via ENS" (10CFRSO.72(b)(2)(xi)
Candidate correctly determines the Critical: Grade State posture code for the event is an Y[X]N[l S[]U[]
"Foxtrot" Candidate correctly determines the Critical: Grade State Reporting Requirement for the Y[X]N[ ] S[]U[]
event is as follows:
"Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of report to NRC" (State Reg. 22a-13S-1 / ENV 4.1.6.1)
Comments:
Cue:
17
STEP Determine additional requirements. Candidate correctly determines that Critical: Grade !
- 25 Y [ ] N [Xl S[]U[]
NOTEs 1, 17 and 19 to Attachment 2 of RAC 14 apply.
Comments: NOTES are located in Attachment 7 to RAC 14.
Refer To Attachment 15 for additional Candidate reviews Attachment 15 Critical: Grade RAC 14, Att 7 notifications. Y[] N[X] S[]U[]
NOTE 1 and determines that no additional notifications are required.
When Federal and State reporting Candidate reviews the NOTE. Critical: Grade RAC 14, Att 7 requirements overlap, the "Clock" for Y[] N[X] S[]U[]
NOTE 17 the State reporting does not start until the report is made to the Federal Authority.
The existing CR process is to be used Candidate recognizes that the Critical: Grade RAC 14, Att 7 to identify any spills and/or leaks of Y[] N[X] S[]U[]
NOTE 19 release was gaseous, therefore this radioactive liquid. Chemistry, HP NOTE does not apply.
and/or Station Licensing personnel will perform any necessary evaluations based on CR information and subsequent investigations as appropriate, and determine if GPI reporting is necessary.
I I 18
STEP IF applicable, Refer To Section 4.9, Candidate refers to Section 4.9. Critical: Grade
- 26 "NRC Notifications." Y [ ] N [X J S[]U[]
RAG 14, step 4.2.10 Comments: Once the Candidate refers to Section 4.9, provide the following cue:
Cue: The Emergency Communicator will prepare and send the Non Emergency Event Report and the Station Duty Officer will complete the remaining required notifications.
The evaluation for this JPM is complete.
STOP TIME: _ _ __
19
VERIFICATION OF JPM COMPLETION JPM Number: SRO A.3 Revision: 0 chg 2 Date Performed:
Student:
Evaluator:
For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
If task is Time Critical, it.M.Y.§! be completed within the specified time to achieve a satisfaetory grade.
Time Critical Task? Yes No X Validated Time (minutes): 30 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
20
STUDENT HANDOUT
...IPM Number: SRO A.3 Revision: o chg 2 Initial The plant is at 100% power, and you are the Extra Senior Licensed Conditions: Operator on shift. About 30 minutes ago MB2B 2-8 "RADIATION ALERT" alarmed. The RO has determined and reported that 3HVR*RE 1OB is in alert. The Control Room Team has entered AOP 3573, Radiation Monitor Alarm Response, and have completed actions for 3HVR*RE10B. Other pertinent information:
- There is no indication that there is an equipment problem associated with 3HVR*RE1 OB.
- 3HVR*10B has cleared the alert setpoint. It is currently reading 1.0 x 10-5 J.,JCi/cc and slowly lowering. The highest reading during the event was 6.0 x 10-5 ~Ci/cc. The highest 10 minute average net increase was 3 x 10- J.,JCi/cc.
- The SM has already determined that the event is not Classifiable at the Alert level or above.
- The Chemistry Department has determined that Delta-Two Posture Code Limits (for OU1, Unplanned Release) have not been exceeded.
- The Chemistry Department has determined that the release did not exceed 40CFR302 limits (EPA Reportable Releases).
- HP, Chemistry, Environmental, Licensing and other personnel are in the Control Room ready to assist.
- The Control Room Team has determined that the cause of the release was a Degasifier overpressure event that lifted the degasifier condenser relief valve (3GWS-RV35). Initially, the relief valve failed to reseat, but has since drifted closed. Turbine Building vent stack flowrate is 186,000 cfm.
21
Initiating The SM has directed you to carry out step 2.1.3 of MP-26-EPI-FAP06, Cues: Classification and PARs .. ...
"IF the event has been evaluated and is not addressed by the Emergency Action Level tables, Go To RAC 14, "Non-Emergency Station Events."
Record any required actions or reporting requirements as a result of your review at the bottom of this page.
22
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Emergency Plan Classification and PAR JPM Number: SRO A.4 JPM-A213 Revision: 1 chg 2 Initiated:
Dave Minnich 03/11/11 Developer Date Reviewed:
Robert Royce 5110111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 03/11/11 Modified the wind direction as stated in the initial conditions. 1 Modified the JPM to require KI strategy be implemented by State Officials based on dose projections greater than 5 Rem thyroid at the site boundary as shown on the provided MIDAS printout.
DLM 5/16111 Modified the JPM to require the Candidate to record classification w.
response on an Incident Report Form. Added Incident Report Form to required materials. Incorporated as a result of NRC Exam comments made 5/31/11. Added the correct title of the MIDAS printout - 'Radiological Status Form', where appropriate, and calling it 'Handout #2'. Modified the ...IPM to require the Candidate to record PAR recommendation response on a Control Room
- Handout #1). As a result added a ...IPM 'Key' that allows for an easy comparison between Candidate response and the correct response. Corrected given wind speed to 10 mph (typo).
6/23/11 Deleted the statement in the Initial Conditions; 'with no 1/2 corresponding increase in containment pressure', and added the statement; 'and CTMT pressure is 14.7 psia.' Deleted from Initial Conditions that the LOCA was in CTMT. It is now stated that a small break LOCA is in progress. In the Initiating Cue, added that Rad Monitor 3HVR*RE19B goes into alarm that allows the Candidate to properly fill out the IRF. Deleted from Initial
! Comditions that there is flooding in the ESF building to remove potential ambiguity in CTMT barrier status. In the Initiating Cue, added a requirement that the Candidate Report to the Examiner when the Classification is made. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility: _____
MP...;;..3_ _ __ Examinee:
JPM Number: SRO A.4 Revision: 1 chg 2 Task
Title:
Emergency Plan Classification and PAR System: NIA Time Critical Task: (X ) YES ( ) NO Validated Time (minutes) 20 Task Number(s): 301-05-366,301-05-449 Applicable To: SRO X RO _ __ PEO _ _
KIA 2.4.41 KIA Rating: 4.6/2.9 Number: 2.4.44 4.4/2.4 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: x Simulator: In-Plant:
Task Standards: Determine the EAL and State Posture Code Determine the minimum required PAR Required Materials:
- MP-26-EPI-FAP06-003, MILLSTONE UNIT 3 EMERGENCY ACTION LEVELS (procedures,
- MP-26-EPI-FAP06, CLASSIFICATION AND PARs (Rev 005) equipment, etc.)
- MP-26-EPI-FAP06-005, CONTROL ROOM PROTECTIVE ACTION RECOMMENDATIONS (Rev 003)
- Radiological Status Form (MIDAS Printout), showing dose projections greater than 5 Rem CDE thyroid at the site boundary (Handout #2).
- Incident Report Form (MP-26-EPI-FAP07-001)
General
References:
MP-26-EPI-FAP-01-001, CONTROL ROOM DIRECTOR OF STATION EMERGENCY OPERATION (CR DSEO) 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: SROA.4 Revision: 1 chg 2 Initial You are the Shift Manager at Millstone Unit 3. The time is 0900. The Conditions: plant has been on-line for 219 days. The "A" Charging pump is tagged out for an oil change. All other major plant equipment is in service. A Severe Thunderstorm Watch has been placed in effect for all Connecticut counties.
The following events occur:
- 1. (0910) A lightning strike causes a loss of offsite power.
- 2. (0910) Reactor trip, turbine trip. The "A" EDG starts, the "B" EDG fails to start. A small break LOCA is in progress.
- 3. (0911) Safety Injection on low Pressurizer pressure.
- 5. (0921) 3HVR*RE19B goes into alarm.
- 8. (0931) STA reports an Orange Path on Core Cooling.
The current wind speed is ten (10) miles per hour. The current wind direction is from 260 0
- 4
Initiating DETERMINE THE APPLICABLE EMERGENCY ACTION LEVEL AND Cues: MAKE ANY APPROPRIATE PROTECTIVE ACTION RECOMMENDATIONS.
This is a time critical task.
Record your Classification responses on the provided Incident Report Form. Report to the Examiner when your Classification is made.
Record your PAR recommendation responses on the provided Control Room PAR Process Flowchart" ARE THERE ANY QUESTIONS? YOU MAY BEGIN.
Simulator NONE Requirements:
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this ..IPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: SRO A.4 Revision: 1 chg 2 Task
Title:
Emergency Plan Classification and PAR START TIME: _ _ __
PERFORMANCE STANDARD STEP Obtain Proper procedure. Applicant obtains or requests copy of Critical: Grade
- 1 MP-26-EPI-FAP06-003, MP3 Y[] N[X] S[]U[]
Emergency Action Levels.
I Comments: Provide the Candidate a blank copy of an Incident Report Form and a Control Room PAR Process Flowchart (Handout #1 ).
Applicant may also request copies of:
- MP-26-EPI-FAP-01-001, CR-DSEO Checklist
- MP-26-EPI-FAP06, Classification and PARs
- MP-26-EPI-FAP06-005, CR PARs
- MP-26-EPI-FAP07, Notifications & Comms
- MP-26-EPI-FAP07-001, Incident Report Form The CR DSEO Notebook contains all these procedures.
Cue:
STEP Classify the Event. Applicant recognizes a loss of the Fuel Critical: Grade
- 2 Clad Barrier, based on > 200 Rlhr on Y [X] N [ ] S[]U[]
RE04/05, :::;;2hrs after shutdown.
(FCB3 AND Table 1 values)
Comments:
Cue:
6
Applicant recognizes a loss of the RCS Critical: Grade Barrier based on RCS Subcooling < Y[X] N[] S[]U[]
32°F Due to RCS leak. (RCB2)
Comments: Although not specifically stated in initial conditions, the applicant should determine that subcooling cannot exist with a valid orange path on Core Cooling.
Cue:
Pressure Increase when Expectation I exists. (CNB3)
Comments:
Cue:
Applicant reviews MP-26-EPI-FAP06- Critical: Grade I 003 and determines that a NRC EAl of Y[X] N[] S[]U[]
GENERAL EMERGENCY, BG1 exists.
Fuel Clad Barrier (l), RCS Barrier (l) and CTMT Barrier (l).
Comments:
Cue:
STEP Determine State Posture Code Applicant reviews MP-26-EPI-FAP06- Critical: Grade
- 3 003 and determines that the block for Y [Xl N [ ] S[]U[]
BG 1 is the same color as State Posture ALPHA.
i Comments: Tables are color coded to reflect the State Posture. I NOTE Record the Time Classification is Completed:
STEP Determine the State Protective Applicant uses MP-26-EPI-FAP06-005, Critical: Grade I
- 4 Action Recommendation Y [ ] N [X] S[]U[]
Section B, Control Room PAR Process Flowchart, to determine the PAR. i Comments:
i Cue:
7
Applicant reviews flowchart and Critical: Grade diagnoses that all 3 barriers ARE lost Y[X] N[] S[]U[]
(Yes) and transitions to "Is There a Release in Progress" Comments:
Cue:
Applicant reviews flowchart and Critical: Grade determines that a release IS in Y[X] N[] S[]U[]
progress. Transitions to "Is the Release Controlled" .
Comments: Although not specifically stated in initial conditions, the applicant should determine that a release is in progress based on no increase in containment pressure and "A" SI pump discharge pressure with attendant flooding in the ESF Building. The applicant should also reasonable determine that the release is NOT controlled.
Cue:
Applicant reviews flowchart and Critical: Grade determines that the release is NOT Y [X] N [ ] S[]U[]
controlled. Transitions to the Wind Direction Table to determine appropriate zone for evacuation.
Comments: I Cue:
Applicant marks the box associated Critical: Grade with wind direction from 258 0 - 2860 . Y[] N[X] S[]U[]
Comments: I Cue:
8
Applicant verbalizes or otherwise notes Critical: Grade that State officials should evacuate Y[X] N[] S[]U[]
Zones A and 8 and F and Groton City and Town in E. Shelter all other zones.
Comments:
Cue:
Applicant reviews flowchart and Critical: Grade transitions to the block for Potassium Y[] N[X] S[]U[]
Iodide (KI) issuance determination.
Comments: When applicant requests dose projections, provide the Candidate with Handout #2, the Radiological Status Form (MIDAS printout).
Cue:
Applicant verbalizes or otherwise notes Critical: Grade that State officials should implement Y [X] N [ ] S[]U[]
Potassium Iodide (KI) strategy for the general public.
Comments: KI strategy being implemented is based on dose projections greater than 5 Rem CDE thyroid at the site boundary as shown on the provided Radiological Status Form (MIDAS printout).
Cue:
NOTE Record the Time the PAR is determined:
STEP Communication of the State Applicant reviews flowchart and Critical: Grade
- 5 Protective Action transitions to Section A, Step 2 of MP- Y[] N[X] S[]U[]
Recommendation 26-EPI-FAP06-005 (Control Room ,
PAR) for the notification.
Comments:
Cue: I ---- ------ ----- -----
9
If a General Emergency ALPHA is Applicant verbalizes or otherwise notes Critical: Grade declared with actions necessary out that the DEP dispatcher in Hartford Y[]N[X] S[]U[]
to 10 miles, PARs are verbally should be contacted to communicate transmitted to the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DEP the applicable evacuation and Dispatcher in Hartford. sheltering recommendations, and KI strategy implementation. I Comments:
Optional Question: What conditions would cause you to change the PAR?
Answer: A change in wind direction could change the zones to evacuate.
J NOTE:
- 15 minutes to determine Emergency Action Level and State Postu.re Code . I
- 15 minutes after classifyina event to determine minimum required PAR.
Cue: The evaluation for this JPM is complete.
Evaluator The handed in IRF and PAR Flowchart should be reasonably like the JPM Key.
Note STOP TIME: _ _ __
10
VERIFICATION OF JPM COMPLETION JPM I\lumber: SRO A.4 Revision: 1 chg 2 Date Performed:
Student:
Evaluator:
For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
If task is Time Critical, it MUST be completed within specified time to achieve a satisfactory grade.
Time Critical Task? Yes X No Validated Time (minutes): 20 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
11
STUDENT HANDOUT Initial Conditions: You are the Shift Manager at Millstone Unit 3. The time is 0900.
The plant has been on-line for 219 days. The "An Charging pump is tagged out for an oil change. All other major plant equipment is in service. A Severe Thunderstorm Watch has been placed in effect for all Connecticut counties.
The following events occur:
- 1. (0910) A lightning strike causes a loss of offsite power.
- 2. (0910) Reactor trip, turbine trip. The "An EDG starts, the "B" EDG fails to start. A small break LOCA occurs in CTMT.
- 3. (0911) Safety Injection on low Pressurizer pressure.
S. (0921) 3HVR*RE19B goes into alarm.
- 8. (0931) STA reports an Orange Path on Core Cooling.
The current wind speed is ten (10) miles per hour. The current wind direction is from 260°.
Initiating Cues: DETERMINE THE APPLICABLE EMERGENCY ACTION LEVEL AND MAKE ANY APPROPRIATE PROTECTIVE ACTION RECOMMENDATIONS.
This is a time critical task.
Record your Classification responses on the provided Incident Report Form. Report to the Examiner when your Classification is made.
Record your PAR recommendation responses on the provided Control Room PAR Process Flowchart.
ARE THERE ANY QUESTIONS? YOU MAY BEGIN.
12
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Align Safety Grade Boration Path JPM Number: 2K11 NRC S.1 Revision: 0 chg 2 Initiated:
Dave Minnich 2/18/11 Developer Date Reviewed:
Robert Royce 5/5111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 5/26/11 Allowed for the termination of the JPM after JPM step 21 (the i 011 last critical step). Incorporated as a result of NRC Exam i comments made 5/25/11.
i 6/17111 Added the title of AOP 3566 to the Initiating 0 o 12~
Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility: _M_P...;..3_ _ __ Examinee:
JPM Number: 2K11 NRC S.1 Revision: 0 chg 2 Task
Title:
Align Safety Grade Soration Path System: 004 - CVCS Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 5 Task Number(s}: 344-05-043, 000-05-019 Applicable To: SRO X RO X PEO _ _
KIA APE: 024 AA1.17 KIA Rating: 3.9/3.9 Number: 004-A4.07 3.9/3.7 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: x In-Plant:
Task Standards: All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Required Materials: AOP 3566, Immediate Boration.
(procedures, equipment, etc.) MP3 Simulator General
References:
AOP 3566, Immediate Boration, Rev 010-01 ES-0.1, Reactor Trip Response, Rev 024 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s} to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC S.1 Revision: o chg 2 Simulator Requirements: 1. Reset to IC 291 .... OR
- 3. Insert malfunction R016 (Control Rods Fail to Fully Insert)
- 4. Insert malfunction E0040 (loss of emergency bus 340), and place the simulator in RUN.
- 5. Carry out the first 9 steps of AOP 3577 to stabilize the primary and secondary.
- 6. Insert malfunction CV18 at 0% (Fails 3CHS*FCV121 closed), and then TCO'! (turbine trip):
- a. Carry out the immediate actions of E-O and the first 5 steps of ES-O.1.
- b. Place the simulator in "Freeze" Approximate setup time is 10 minutes.
Initial Conditions: The plant was at 100% power with emergency bus 340 deenergized due to a bus differential lockout relay actuation.
Moments ago the turbine tripped which caused a reactor trip.
Several control rods failed to fully insert. The US has entered ES-O.1, Reactor Trip Response, and actions are complete up through step 5.
Initiating Cues: The US has directed you to initiate an immediate boration of the RCS, starting with step 1 of AOP 3566, Immediate Boration.
4
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are
- you looking at?" or "What are you observing?"). ~'
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.1 Revision: o chg 2 Task
Title:
Align Safety Grade Boration Path START TIME: _ _ __
PERFORMANCE STEP STANDARD STEP Obtains copy of AOP 3566. Obtains a copy of AOP 3566, and Critical: Grade
- 1 Y[]N[X] S[] U[]
refers to the CAUTION prior to step 1 Comments:
Cue:
STEP If SI actuation occurs during this Critical: Grade J
Candidate reviews CAUTION.
- 2 procedure, Go to E-O, Reactor Trip Y[]N[X] S[ ] U[ ]
or Safety Injection, and restore from 3566 step 1 immediate boration lineup.
CAUTION Comments:
Cue:
STEP Initiate Immediate Boration Of Determines that that the 'A' charging Critical: Grade
- 3 RCS. Y[]N[X] S[]U[]
pump is running by observation of 3566 indicating lights, amps, flow etc.
step 1.8 Check one charging pump RUNNING Comments:
Cue:
6
STEP Align boration flow path. Starts at least one boric acid transfer Critical: Grade
- 4 pump by depressing the START push Y[] N[X] S[]U[]
3566 step 1) START at least one boric acid button on pump controller and 1.b.1) transfer pump observes START push button lights and STOP push button extinguishes.
Comments:
Cue:
STEP 2) OPEN emergency boration Recognizes emergency boration valve Critical: Grade
- 5 valve (3CHS*MV81 04) (3CHS*MV81 04) will not open Y[]N[X] S[]U[]
3566 step indicating lights are all OFF.
1.b.2)
Transitions to the RNO column.
Comments: 3CHS*MV8104 is powered from 340 which is deenergized.
Cue:
STEP Perform the following: Opens the 'A' gravity boration valve, Critical: Grade
- 6 3CHS*MV8507 A, by depressing the Y[X]N[ ] S[]U[]
3566 step 1.b OPEN at least one gravity feed OPEN push button and observing RNO boration valve. lights shift to green OFF, red ON.
Comments: 3CHS*MV8507B is powered from 340.
Cue:
STEP Limit net charging flow to the RCS to Observes 3CHS*FCV121 indicates in Critical: Grade
- 7 the closed position. The candidate may Y[] N[X] S[]U[]
LESS THAN 75 gpm (Charging +
seal injection - RCP seal return) attempt to throttle FCV121 by depressing ft and/or U push button.
Comments: 3CHS*FCV121 is failed closed.
Cue:
STEP CLOSE at least one VCT outlet Closes the 'A' VCT outlet isolation Critical: Grade
- 8 isolation valve. valve 3CHS*LCV112B by depressing Y[X]N[] S[]U[]
CLOSE push button and observing indicating lights shift to green ON, red OFF.
IComments: ~QIj§:I.-C;V112C is powered from 340.
7
Cue:
STEP VERIFY closed both RWST to Determines that RWST to charging Critical: Grade
- 9 charging pump suction isolation pump suction isolation valve, Y[]N[X] S[lU[l valves. 3CHS*LCV112D is closed by observing indicating lights green ON, red OFF. Recognizes 3CHS* LCV112E has no power - indicating lights are all OFF.
Comments: Examinee may report to US that 3CHS* LCV112E has no power, but should be closed since SI has not occurred. If the Candidate asks for US direction, provide the following cue:
Cue: Assume 3CHS* LCV112E is closed and continue in AOP 3566.
STEP Check normal charging flow path Attempts to throttle charging flow Critical: Grade
- 10 aligned control valve (3CHS*FCV121) by Y[] N[X] S[]U[]
3566 step 1.e
- Charging flow control valve depressing ft and/or ij push button.
CAPABLE OF BEING Recognizes that 3CHS*FCV121 is THROTTTLED failed closed and is NOT capable of being throttled.
Transitions to the RNO column.
Comments: 3CHS*FCV121 is failed closed.
Cue:
STEP Position valves as required to Applicant proceeds to step 2 of AOP Critical: Grade
- 11 establish a controllable normal 3566. Y[] N[X] S[]U[]
3566 step 1.e charging flow path.
RNO IF a controllable normal charging flow path can NOT be established, THEN Proceed to steR_ 2.
Comments:
Cue: --~ --- ............ -.-~ ..........- . - - ......... -.. -~ ........... --~ ....... -.-~------- ...- .----
8
STEP Align Safety Grade Boration Path Determines Bus 34D is deenergized by Critical: Grade
- 12 observation of the MB8 emergency bus Y[]N[X] S[]U[]
3566 step 2.a Check emergency busses 34C voltage indicators reading 0 volts, and 34D BOTH emergency load center voltage ENERGIZED indicators (4) reading 0 volts, OR MB8C 4-2, BUS 34D BUS DIFF, LIT.
Applicant transitions to the RNO column.
I Comments: The applicant was given that 34D was deenergized in the initiating cue, and may already have verified as such.
Cue:
STEP Perform the applicable action: Determines Bus 34C is energized by Critical: Grade
- 13
- IF emergency bus 34C is observation of the MB 8 emergency Y[] N[X] S[]U[]
3566 step 2.a energized, bus voltage indicators reading about RNO THEN 4160 volts OR emergency load center Proceed to step 2.b. voltage indicators (8) reading about 480 volts.
Proceeds to step 2.b.
Comments:
Cue; STEP OPEN charging header flow control Applicant throttles open Critical: Grade
- 14 3566 valve (3CHS*HCV190A) 3CHS*HCV190A by depressing 11 push Y [Xl N [ ] S[]U[]
step 2.b button. Observes valve position indicate full open.
Comments:
Cue:
STEP OPEN charging header bypass Opens 3CHS*MV8116 by depressing Critical: Grade
- 15 isolation (3CHS*MV8116) the OPEN push button and observing Y [X] N [ ] S[]U[]
3566 step 2.c lights shift to green OFF, red ON.
Comments:
Cue:
9
STEP CLOSE charging flow control Recognizes 3CHS*MV81 06 has no Critical: Grade
- 16 outlet isolation (3CHS*MV8106) power - indicating lights are all OFF. Y[] N[X] S[]U[]
3566 step 2.d Transitions to the RNO column.
Comments:
Cue:
STEP Perform the applicable action: Observes 'A' charging pump is running Critical: Grade
- 17 3566
- IF a Train A charging pump by checking red indicating light, proper Y[ J N[X] S[]U[]
step 2.d is running, amps, flow, etc.
RNO THEN Proceed to step 2.h. Proceeds to step 2.h.
Comments:
Cue:
STEP Locally Perform the following while Applicant calls a PEO or requests from Critical: Grade
3566 step 2.h. between 8 and 13 gpm: Aux Building and establish
- 1) 1) Throttle Open the operating communications to throttle open charging pump bypass valve 3CHS*V272.
- For pump A 3CHS*V272 Comments:
Cue: BOOTH: Insert remote CVR84 and adjust to obtain 8 to 9 gpm (about 70%). Report as PEO that 3CHS*V272 has been throttled open.
STEP 2) Close the charging header Applicant directs the PEO to close Critical: Grade
- 19 to seals isolation valve (3CHS*V273) 3CHS*V273. Y[] N[X] S[]U[]
3566 step 2.h.
2)
Comments:
Cue: BOOTH: Insert remote CVR87 and adjust to 0% (closed). Report as PEO that 3CHS*V273 is closed. .
10
STEP Check Train A charging pump Observes 'A' charging pump is running Critical: Grade I
- 20 - RUNNING by checking red indicating light, proper Y[] N[X] S[]U[]j 3566 step 2.i amps, flow, etc.
Comments:
Cue:
STEP CLOSE charging header isolation Closes 3CHS*MV8438A by depressing Critical: Grade
- 21 valve (3CHS*MV8438A) CLOSE push button and observing Y[X] N[] S[]U[]
3566 slep 2.j indicating lights shift to green ON, red OFF.
Comments: At the Examiner's discretion, the JPM may be terminated at the completion of JPM step 21. In that case provide the following cue:
Cue: The evaluation for this JPM is concluded.
STEP Verify Boration Flow Verifies pressurizer pressure is less Critical: Grade
- 22 than 2350 psia by checking any of the Y[]N[X] S[]U[]
3566 step 3.a Check PZR pressure following:
LESS THAN 2350 psia Meters: RCS-PI455A, 456A, 457 or 458 Recorder: RCS-PR455.
Comments:
Cue:
STEP Check normal charging flow Checks charging flow and valve line up Critical: Grade
- 23 path - ALIGNED and recognizes that the Safety Grade Y[] N[X] S[]U[]
3566 step 3.b Boration flowpath is not the normal charging flow path.
Transitions to the RNO column.
Comments:
Cue:
11
STEP Isolate normal letdown. Candidate observes that a letdown Critical: Grade
- 24 orifice isolation is open, and closes Y[X]N[ ] S[]U[1 3566 step 3.b 3CHS*AV8149C by depressing the RNO CLOSE push button and observing indicating lights shift to green ON, red OFF.
Comments: The Candidate may instead close 3CHS*CV8160 or *CV8152 to isolate letdown. This is satisfactory.
Cue:
STEP Perform the following: Critical: Grade
- 25 IF a safety grade boration flow path Y[ 1 N[X] S[]U[1 is established, THEN Using GA-14, Establish reactor vessel head vent letdown to the VCT.
Comments: Once the applicant obtains GA-14, provide the following cue; Cue: Another RO will establish head vent letdown to the VCT.
TERMINATION CUE: The evaluation for this JPM is concluded.
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ __
12
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.1 Revision: 0 chg 2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical. it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 5 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
13
STUDENT HANDOUT JPM Number: 2K11 NRC S.1 Revision: o chg 2 Initial Conditions: The plant was at 100% power with emergency bus 340 deenergized due to a bus differential lockout relay actuation.
Moments ago the turbine tripped which caused a reactor trip.
Several control rods failed to fully insert. The US has entered ES 0.1, Reactor Trip Response, and actions are complete up through step 5.
Initiating Cues: The US has directed you to initiate an immediate boration of the ReS, starting with step 1 of AOP 3566, Immediate Boration.
14
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Respond to an Inadvertent Containment Isolation Phase 'A',
JPM Number: 2K11 NRC S.2 Revision: 0 chg 1 Initiated:
Dave Minnich 2/22/11 Developer Date Reviewed:
Robert Royce 5/5/11 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 6/17/11 Added additional cueing to JPM steps 31 and 35 that another 0/1 RO will interface with the PPC. This allows the Candidate to continue with the assigned task. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility: -MP3----- Examinee:
JPM Number: 2K11 NRC S.2 Revision: 0 chg 1 Task
Title:
Respond to an Inadvertent Containment Isolation Phase 'A'.
System: ESF (013)
Time Critical Task: ) YES (X) NO Validated Time (minutes): _ _.....1.....
2_ _
Task Number(s): 013-04-012 Applicable To: SRO X RO X PEO - - -
KIA 013 A4.02 KIA Rating: 4.3/4.4 Number:
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Required Materials: AOP 3578, Response to an Inadvertent Containment Isolation Phase A (procedures, equipment, etc.) MP3 Simulator General
References:
AOP 3578, Response to an Inadvertent Containment Isolation Phase A (revision 000) 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating CUElS. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC S.2 Revision: o chg 1 Simulator Requirements: 1. Reset to IC 254 .... OR
- 2. Reset to IC 18, 100% steady state, MOL (or any 100%
Power IC), and carry out steps 3 - 5 below.
- 3. Insert malfunctions RP03A1B (Containment Isolation phase A, train A and B.
- 4. Place the simulator in RUN, wait for all CIA actuated components to fully reposition.
- 5. Remove malfunctions RP03A1B (This will allow the examinee to reset CIA).
- 6. Place the simulator in "Freeze" Approximate setup time is 5 minutes.
Initial Conditions: The plant was at 100% power when an Inadvertent Containment Isolation Phase A (CIA) occurred while conducting SSPS surveillance testing.
Initiatinq Cues: The US has directed you to carry out the actions of AOP 3578, Response to an Inadvertent Containment Isolation Phase A, starting with step 1.
",,,,,,,,,, NOTES TO TASK PERFORMANCE EVALUATOR"'''''
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. 'What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.2 Revision: o chg 1 Task
Title:
Respond to an Inadvertent Containment Isolation Phase 'A'.
START TIME: _ _ __
PERFORMANCE STANDARD STEP Obtains copy of AOP 3578. Obtains a copy of AOP 3578 and refers to Critical: Grade
- 1 the CAUTION and NOTE prior to step 1. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue:
STEP If a Reactor Trip occurs or is required, go to Candidate reviews CAUTION. Critical: Grade
- 2 E-O, Reactor Trip or Safety Injection. Y[ ] S[ ]
AOP 3578 N[X] U[ ]
Step 1 CAUTION Comments:
Cue:
STEP Components and recovery actions are Candidate reviews NOTE. Critical: Grade
- 3 listed in OA 2, "OMOC On-Call Y[ ] S[ ]
3578 Step 1 Responsibilities" Attachment 3, "ESF N[X] U[ ]
NOTE Actuation Checklist".
Comments: If the Candidate takes action to reference OA 2, provide the following cue:
Cue: The SM will refer to OA 2.
5
STEP Verify Containment Isolation AT MB4 or MB2, observes that the Safety Critical: Grade
- 4 NOT REQUIRED Injection Actuation annunciator is NOT lit. Y[ ] S[ ]
3578 Step 1.a N[X] U[ ]
Check safety injection signal- NOT ACTUATED Comments:
Cue:
STEP Reset CIA Candidate resets CIA by depressing the Critical: Grade
- 5 Train A and Train B CIA reset push Y[X] S[ ]
3578 Step 1.b buttons on MB2. N[ ] U[ ]
Comments:
Cue:
STEP Notify I&C to investigate the cause of the Candidate calls I&C to investigate or Critical: Grade
- 6 inadvertent CIA signal requests the US make the call to I&C. Y[ ] S[ ]
3578 Step 1.c N[X] U[ ]
Comments:
Cue:
STEP Check If Letdown Is Isolated Candidate checks 3CHS*CV8152 and/or Critical: Grade
- 7 3CHS*CV8160 are Closed by observing Y[ ] S[ ]
Check letdown containment isolation indicating lights as green ON, red OFF. N[X] U[ ]
3578 Step 2 valves- CLOSED
- 3CHS*CV8152 OR
- 3CHS*CV8160 Comments:
Cue:
6
STEP CLOSE Letdown orifice Closes the 'C' Letdown orifice isolation Critical: Grade
- 8 isolation valves: valve, 3CHS*AV8149C by depressing Y[X] S[ ]
3578
- 3CHS*AV*8149A CLOSE push button and observing N[ ] U[ ]
Step 2.b
- 3CHS*AV*8149B indicating lights shift to green ON, red
- 3CHS*AV*8149C OFF.
Comments: I Cue:
STEP CLOSE charging flow control Throttle Closed charging flow control Critical: Grade
- 9 valve, 3CHS*FCV 121 valve (3CHS*FCV121 ) by depressing the Y[X] S[ ]
3578 Upush button and observes no charging N[ ] U[ ]
Step 2.c flow.
Comments:
Cue:
STEP Adjust seal injection flow, as necessary to Candidate throttles 3CHS*HCV182 as Critical: Grade
- 10 control pressurizer level- necessary by rotating potentiometer of Y[X] S[ ]
3578 Step 2.d 8 TO 13 GPM 3CHS*HC182 (MB3). N[ ] U[ ]
Observes seal flow between 8 and 13 Critical: Grade gpm by checking the RCP seal injection Y[ ] S[ ]
flow indicators (3CHS- N[X] U[ ]
FI145A1144A1143A1142A).
Comments: Candidate should throttle seal injection to the low end of the specified band (about 8gpm) to minimize the increase in PZR level.
Cue:
STEP Establish Instrument Air To Candidate determines that that the 'B' Critical: Grade
- 11 Containment instrument air compressor is running by Y[ ] S[ ]
observing indicating lights green OFF, red N[X] U[ ]
3578 Step 3.a Check instrument air compressors- ON (MB1).
AT LEAST ONE RUNNING Comments:
7
Cue:
STEP OPEN instrument air Ctmt isolation valves: Opens 3IAS*PV15 by depressing the Critical: Grade
- 12
- 3IAS*PV15 OPEN push button and observing lights Y[X] S[ ]
3578 Step 3 b
- 3IAS*MOV72 shift to green OFF, red ON. N[ ] U[ ]
Opens 3IAS*MOV72 by depressing the Critical: Grade OPEN push button and observing lights Y[X] S[ J shift to green OFF, red ON. N[ ] U[ ]
Comments: The instrument air Ctmt isolation valves can be opened in any order.
Cue:
STEP Align RCP Seal Return Flow To Opens 3CHS*MV81 00 by depressing the Critical: Grade
- 13 Charging Pump Suction OPEN push button and observing lights Y[X] S[ ]
shift to green OFF, red ON. N[ ] U[ ]
3578 Step 4.a OPEN seal return containment isolation valves:
- 3CHS*MV8100
- 3CHS*MV8112 Opens 3CHS*MV8112 by depressing the Critical: Grade OPEN push button and observing lights Y[X] S[ ]
shift to green OFF, red ON. N[ ] U[ ]
Comments: The seal return containment isolation valves can be opened in any order.
Cue:
STEP Check If Normal Letdown Can Be Candidate checks PZR level greater than Critical: Grade
- 14 Established 22% by observing CVCS trend for RCS- Y[ ] S[ ]
L461 on the PPC, OR checking meters NIX] U[ ]
3578 Step 5.a Check pressurizer level - RCS*Ll459A, Ll460A and Ll461A on GREATER THAN 22% MB4.
Comments:
8
Cue:
STEP Establish normal letdown flow using GA-13 Critical: Grade
- 15 3578 y [ 1 S[ 1 Step 5.b N[X] U[ 1 Comments: Once the Candidate obtains GA-13, provide the following cue; Cue: Another RO will establish normal letdown flow using GA-13.
STEP Restore RPCCW System To Normal Determines that there is adequate Critical: Grade
- 16 Thermal barrier cooling by observing y [ 1 S[ ]
Check RCP thermal barrier thermal barrier flow low annunciators not N[X] U[ ]
3578 Step 6.a cooling - ESTABLISHED TO ALL RCPs in alarm and/or valves 3CCP*AOV178NB/C/D open by observing indicating lights green OFF, red ON.
Comments:
Cue:
STEP Restore Reactor Plant Chill Water System: Candidate informs the US to Refer to T.S. Critical: Grade
- 17 3.6.1.4 and 3.7.14. Y[ ] S[ 1 3578 Ste p Refer to T.S. 3.6.1.4 and 3.7.14. N[X] U[ ]
- 6. b. 1 )
Comments:
Cue:
STEP Refer to OP 3330C, "Recover from Loss Of Critical: Grade
- 18 Power, Containment Isolation Phase A, or Y[ 1 S[ ]
3578 Step Loss of Instrument Air" and Restore N[X] U[ ]
6.b.2) containment and non-safety headers Comments:
Cue: Another RO will restore containment and non-safety headers, and complete step 6. Continue in AOP 3578.
9
STEP Restore Affected Systems Candidate determines that 3CMS*CTV20, Critical: Grade
- 19 21, 23 and MOV24 are CLOSED by Y[ ] S[ ]
Check RCS leakage monitor, 3CMS*RE 22 observing indicating lights as green ON, N[X] U[ ]
3578 Step 7 a - IN SERVICE WITH THE FOLLOWING red OFF.
VALVES OPEN:
Transitions to the RNO column.
- 3CMS*CTV 20
- 3CMS*CTV 21
- 3CMS*CTV23
- 3CMS*MOV 24 Comments:
Cue:
STEP Place 3CMS*RE 22 in service as follows: Candidate informs the US to refer to T.S. Critical: Grade
- 20 3.3.3.1 and 3.4.6.1. Y[ ] S[ ]
3578 Step Refer to T.S. 3.3.3.1 and 3.4.6.1 N[X] U[ ]
7.aRNO Comments:
Cue:
STEP OPEN the following Opens 3CMS*CTV20 by depressing the Critical: Grade
- 21 OPEN push button and observing lights Y[X] S[ ]
3578
- 3CMS*CTV20 shift to green OFF, red ON. N[ ] U[ ]
Step 7.aRNO
- 3CMS*CTV 21
- 3CMS*CTV 23
- 3CMS*MOV 24 Opens 3CMS*CTV21 by depressing the Critical: Grade OPEN push button and observing lights Y[X] S[ ]
shift to green OFF, red ON. N[ ] U[ ]
Opens 3CMS*CTV23 by depressing the Critical: Grade OPEN push button and observing lights Y[X] S[ ]
I I shift to green OFF, red ON. N[ ] I u[ ]
10
Opens 3CMS*MOV24 by depressing the Critical: Grade OPEN push button and observing lights Y[X] S[ ]
shift to green OFF, red ON. N[ ] U[ ]
Comments: The CMS containment isolation valves can be opened in any order.
Cue:
STEP Refer to OP 33128 and Restore Critical: Grade
- 22 3CMS*RE22 to service. Y[ ] S[ ]
3578 Step N[X] U[ ]
7.aRNO Comments:
Cue: Another RO will restore 3CMS*RE22 to service.
STEP 3DGS*CTV24 and 3DAS*CTV24 need to Candidate reviews NOTE. Critical: Grade
- 23 be reset following CIA by momentarily Y[ ] S[ ]
depressing AUTO I OPEN. When N[X] U[ ]
3578 Step 7.b momentarily depressing AUTO I OPEN, NOTE 3DGS*CTV24 or 3DAS*CTV24 may stay open until the next pumping operation occurs.
Comments:
Cue:
STEP Check Reactor Plant Gaseous Drains - IN Candidate determines that 3DGS*CTV24 Critical: Grade
- 24 SERVICE WITH THE FOLLOWING and 25 CLOSED by observing indicating Y[ ] S[ J 3578 Step 7.b VALVES OPEN: lights as green ON, red OFF. Transitions N[X] U[ ]
to the RNO column.
- 3DGS*CTV24
- 3DGS*CTV25 i
Comments:
__~Cue i 11
STEP Perform the following: Opens 3DGS*CTV25 by depressing the Critical: Grade
- 25 OPEN push button and observing lights Y[X] S[ ]
3578 Step 7.b OPEN 3DGS*CTV25. shift to green OFF, red ON. N[ ] U[ ]
RNO Comments:
I Cue:
STEP Momentarily press 3DGS*CTV24 Candidate Momentarily depresses the Critical: Grade
- 26 AUTO/OPEN. 3DGS*CTV24 AUTO /OPEN push button Y[ ] S[ ]
3578 Step 7.b and observes the valve remains closed. N[X] U[ ]
RNO Comments:
Cue:
STEP Check Reactor Plant Aerated Drains - IN Candidate determines that 3DGS*CTV24 Critical: Grade
- 27 SERVICE WITH THE FOLLOWING and 25 CLOSED by observing indicating Y[ ] S[ ]
VALVES OPEN: lights as green ON, red OFF. N[X] U[ ]
3578 Step 7.c
- 3DAS*CTV24 Transitions to the RNO column.
- 3DAS*CTV25 Comments:
Cue:
STEP Perform the following: Candidate informs the US to refer to T.S. Critical: Grade
- 28 3.4.6.1. Y[ ] S[ ]
3578 Step 7.c Refer to T.S. 3.4.6.1. N[X] U[ ]
RNO Comments:
Cue:
STEP OPEN 3DAS*CTV25. Opens 3DAS*CTV25 by depressing the Critical: Grade
- 29 OPEN push button and observing lights Y[X] S[ ]
shift to green OFF, red ON. N[ ] U[ ]
Comments:
I Cue: ------
12
STEP Momentarily press 3DAS*CTV24 Candidate Momentarily depresses the Critical: Grade
- 30 AUTO IOPEN. 3DAS*CTV24 AUTO IOPEN push button Y[ ] S[ ]
and observes the valve remains closed. N[X] U[ ]
Comments:
Cue:
STEP Verify 3DAS*P2A I Band 3DAS-P10 Candidate calls up Reactor Plant Aerated Critical: Grade
- 31 automatic operation. Drains - Containment Drains on R*Time Y[ ] S[ ]
(or corollary display on PPC) to monitor N[X] U[ ]
CTMT sump level and 3DAS*P2A I Band 3DAS-P10 activity.
Comments: Once the Candidate displays Reactor Plant Aerated Drains on the PPC, provide the following cue:
Cue: Another RO will monitor CTMT sump pump activity.
STEP Check Reactor Plant Gaseous Vents - IN Candidate determines that 3VRS*CTV20 Critical: Grade
- 32 SERVICE WITH THE FOLLOWING and 21 CLOSED by observing indicating Y[ ] S[ ]
VALVES OPEN: lights as green ON, red OFF. N[X] U[ ]
3578 Step 7.d
- 3VRS*CTV20 Transitions to the RNO column.
- 3VRS*CTV21 Comments:
Cue:
STEP Perform the following: Opens 3VRS*CTV20 by depressing the Critical: Grade
- 33 OPEN push button and observing lights Y[X] S[ ]
3578 Step 7.d OPEN 3VRS*CTV20. shift to green OFF, red ON. N[ ] U[ ]
RNO Comments:
Cue:
STEP OPEN 3VRS*CTV21. Opens 3VRS*CTV21 by depressing the Critical: Grade
- 34 OPEN push button and observing lights VEX] S[ ]
shift to green OFF, red ON. N[ ] U[ ]
13
Comments:
Cue:
STEP Reset RCS leak rate program. The Candidate calls up RCS Leakage on Critical: Grade
Leakage) to reset the RCS leak rate N[X] U[ ]
program.
Comments: Once the Candidate displays the RCS Leakage program on the PPC, provide the following cue:
Cue: Another RO will reset the RCS leak rate program.
STEP Check fire protection water to containment Candidate determines that 3FPW*CTV48 Critical: Grade
- 36 valves - OPEN: and 49 are CLOSED by observing Y[ ] S[ ]
3578 indicating lights as green ON, red OFF. N[X] U[ ]
Step 7.e
- 3FPW*CTV48
- 3FPW*CTV49 Transitions to the RNO column.
Comments:
Cue:
STEP Perform the following: Candidate informs the US to refer to Critical: Grade
- 37 3TRM 3.7.12.2 and 3TRM - 3.7.12.5. Y[ ] S[ ]
3578 Slep 7 e Refer to 3TRM-3.7.12.2 and N[X] U[ ]
RNO 3TRM-3.7.12.5.
Comments:
Cue:
STEP OPEN 3FPW*CTV48. Opens 3FPW*CTV48 by depressing the Critical: Grade
- 38 OPEN push button and observing lights Y[X] S[ ]
shift to green OFF, red ON. N[ ] U[ 1 Comments:
Cue:
14
, STEP OPEN 3FPW*CTV49. Opens 3FPW*CTV49 by depressing the Critical: Grade
- 39 OPEN push button and observing lights Y[X] S[ ]
shift to green OFF, red ON. N[ ] U[ ]
Comments:
Cue:
STEP Check PGS to containment valves- OPEN: Candidate determines that 3PGS* Critical: Grade
- 40 CV8046 and CV8028 are CLOSED by Y[ ] S[ ]
3578 Step 7.f
- 3PGS*CV8046 observing indicating lights as green ON, N[X] U[ ]
- 3PGS*CV8028 red OFF.
Transitions to the RNO column. ,
Comments:
Cue:
STEP OPEN valves as directed by SMI US. Candidate requests from the US whether Critical: Grade'
- 41 to open the PGS to containment valves. Y[ ] S[ ]
3578 Step 7.f N[X] U[ ]
RNO Comments: When asked, provide the following cue:
Cue: Open the PGS to containment valves.
STEP Opens 3PGS* CV8046 by depressing the Critical: Grade
- 42 OPEN push button and observing lights Y[X] S[ ]
shift to green OFF, red ON. N[ ] U [] !
Comments:
Cue:
STEP Opens 3PGS* CV8028 by depressing the Critical: Grade
- 43 OPEN push button and observing lights Y[X1 S[ ]
shift to green OFF, red ON. N[ ] U[ ]
Comments: The PGS to containment valves can be opened in any order. I Cue:
15
STEP If Necessary, Refer To OA 2 attachment Candidate informs the US to refer to OA 2 Critical: Grade
3578 Normal Component Position to verify normal component position. N[X] U[ ]
Step 8 Comments:
Cue: Another RO will carry out attachment 3 to OA 2.
STEP Determine If Plant Operation Can 1) Candidate informs the US to refer to Critical: Grade
- 45 Continue T.S. 3.3.2.a, 3.4.6.1, and 3.3.3.1. Y[ ] S[ ]
3578 Step 9 N[X] U[ ]
Comments: i Cue: The US will check Tech Specs.
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ __
16
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.2 Revision: ~lliLL Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ~ critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 12 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
17
STUDENT HANDOUT JPM Number: 2K11 NRC 8.2 Revision: o chg 1 Initial Conditions: The plant was at 100% power when an Inadvertent Containment Isolation Phase A (CIA) occurred while conducting SSPS surveillance testing.
Initiating Cues: The US has directed you to carry out the actions of AOP 3578, Response to an Inadvertent Containment Isolation Phase A, starting with step 1.
18
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Perform ReS Bleed and Feed Per FR-H.1 JPM Number: 2K11 NRC S.3 (JPM-039A) Revision: 0 chg 5 Initiated:
Dave Minnich 2/23/11 Developer Date Reviewed:
Robert Royce 5/5111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 02/23/11 Modified JPM format to be consistent with the NRC 2K11 o"l JPM set. Verified JPM updated through Revision 020-01 to FR-H.1. Changed the JPM standard for checking Charging and SI pumps running to 'andlor', as step 12 in FR-H.1 infers.
Combined two ...IPM steps into one for the check of PORV i open indications. Deleted TR-M-410 Pass/Fail criteria. i 6/17/11 Added that the Candidate may check the Group 2 Status :015 Panel when checking for a proper ECCS emergency valve alignment in JPM step 8. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week). I 2
JPM WORKSHEET Facility: ,....;M..;,.;..P.....;3::...-._ __ Candidate:
JPM Number: 2K11 NRC S.3 Revision: 0 chg 5 Task
Title:
Perform RCS Bleed and Feed Per FR-H.1 System: 3 - 010 (PZR Pressure Control)
Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 7 Task Number(s): 000-05-063 Applicable To: SRO X RO X PEO KIA Number: EPE: E05-EA1.1 KIA Rating: 4.1/4.0 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Satisfactorily complete the establishment of an ReS bleed and feed using FR-H.1.
All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Required Materials: FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK (procedures, equipment, etc.) MP3 Simulator General
References:
EOP 35 FR-H.1, Rev. 020-01 3
- READ TO THE CANDIDATE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC S.3 Revision: 0 chg 5 Simulator Requirements: 1 . Reset to any 100% Power IC.
- 2. Insert the following malfunctions (or run schedule JPM039A):
- FW18A - "A" MDAFW pump trip
- FW188 - "8" MDAFW pump trip
- FW19 - TDAFW pump trip
- RC08A - Pzr PORV PCV455 FC
- 3. Place simulator in "RUN" and Insert malfunction ED01, Loss of Offsite Power. Carry out EOP E-O and FR-H.1 actions through step 9. Allow the simulator to run until wide range level is < 29% in 3 of 4 SGs.
- 5. Acknowledge and clear annunciator alarms, place the master silence switch to "normal" and place the simulator in "FREEZE".
- 6. After the candidate has received the initiating cues and initial conditions, place the simulator in "RUN."
Approximate setup time is 25 minutes.
or Reset to IC 171, setup 5 minutes 4
Initial Conditions: A reactor trip occurred due to a loss of offsite power. A red path condition on heat sink is present due to no AFW pumps running. While carrying out the actions of FR-H.1 , wide range level in 3 SIGs fell to less than 29%.
Initiating Cues: The US has directed you to establish an RCS bleed and feed using FR-H.1 steps 10 thru 14.
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?").
! 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.3 Revision: o chg 5 Task
Title:
Perform RCS Bleed and Feed Per FR-H.1 START TIME: _ _ __
PERFORMANCE STEP STANDARD STEP Obtains copy of FR-H .1. Candidate obtains a copy of FR-H.1, Critical: Grade
- 1 Y[] N[X] S[]U[]
refers to CAUTIONS prior to step 10.
Comments:
Cue:
STEP
- Steps 10. through 14. must be Candidate reviews the CAUTIONS . Critical: Grade
- 2 performed quickly in order to Y[]N[X] S[]U[]
establish RCS heat removal by FR-H.1, step 10 ReS bleed and feed.
CAUTION
- During the remainder of the procedure, feed flow to the SGs must be established as specified by step 19.
Comments:
Cue:
STEP Check All RCPs - STOPPED At MB4, Candidate determines that all Critical: Grade
- 3 Reps are stopped by observation of Y[] N[X] S[]U[]
FR-H.1, green and amber indicating jights 'ON' step 10 and/or no flow, amps, etc.
Somments: ---- ---- ---- ----
6
Cue:
STEP Initiate 51. Rotates the SI switch on either MB4 or Critical: Grade
- 4 MB2 to the "ACTUATE" position. Y[X] N[] S[l U[l FR-H.1, Observes the safety injection actuation step11 annunciator illuminates.
Comments: Annunciator alarms consistent with the SI actuation and opening the PORVs will be received. The candidate should silence the alarms and acknowledge and clear annunciators as appropriate. This is not necessary to complete this critical step.
Cue: I STEP Verify ReS Feed Path Determines that that the 'A' and/or 'B' Critical: Grade I
- 5 charging pumps are running by Y[]N[X] S[]U[]
FR-H.1, Check charging pumps --- observation of indicating lights, amps, s te p
- 12. a AT LEAST ONE RUNNING flow etc.
I Comments:
Cue:
STEP OPEN charging pump cold leg Observes GREEN lights for the Critical: Grade
- 6 injection valves: charging pump cold leg injection Y[X] N[] S[]U[]
FR-H.1, valves. Candidate depresses s te p
- 12. b
- 3SIH*MV8801A 3SIH*MV8801A and 3SIH*MV8801 B
- 3SIH*MV8801B "OPEN" pushbuttons and observes that the indicating lights shift to green OFF, red ON.
Comments:
Cue:
STEP Check SI pumps --- Determines that that the 'A' and/or 'B' Critical: Grade
- 7 AT LEAST ONE RUNNING SI pumps are running by observation of Y[] N[X] S[]U[]
FR-H.1, indicating lights, amps, flow etc.
step
- 12. c Comments:
Cue: .. --~.~
7
STEP Check ECCS valve alignment -- Candidate checks the valve lineup by Critical: Grade
- 8 PROPER EMERGENCY Y[]N[X] S[]U[]
FR-H.1, observing appropriate indicating lights, ALIGNMENT and/or observing the appropriate lights step
- 12. d lit on the Group 2 ESF Status Panel.
Comments:
Cue:
STEP Establish ReS Bleed Path Determines PORV block valves Critical: Grade
- 9 3RCS*MV8000A and 3RCS*MV8000B Y[] N[X] S[]U[]
FR-H.1, open by valve indications red lights step
- 13. a Verify PZR PORV block valves- ON/green OFF.
BOTH OPEN.
Comments:
Cue:
STEP OPEN both PZR PORVs. Rotates the control switches for the Critical: Grade
- 10 PZR PORVs (3RCS*PCV455A and Y[X1 N[] S[]U[]
FR-H.1, 3RCS*PCV456) to the "OPEN" step
- 13. b position.
Comments: 3RCS*PCV455A will remain closed. Opening 3RCS*PCV456 is the critical nature of the step.
The candidate should silence and acknowledge annunciators that alarm due to the depressurization.
Cue:
STEP Verify Adequate ReS Bleed Path Observes the indicating lights shift to Critical: Grade
- 11 red ON, green OFF for 3RCS*PCV456 Y[] N[X] S[]U[]
FR-H.1, only.
step 14
- Check PZR PORVs - BOTH Recognizes that 3RCS*PCV*455A has OPEN.
remained closed.
- Check PZR PORV block valves - BOTH OPEN.
Transitions to the RNO column.
Comments:
Cue:
8
STEP Perform the following: Depresses OPEN pushbutton for Critical: Grade
- 12 3RCS*SV8095A,SV80958,SV8096A Y[X] N[] S[]U[]
F R- Establish head vent to PRT: and 3RCS*SV8096B and observes H.1, ste p position indicating lights shift to green OPEN reactor vessel head OFF and red ON.
14.a.1)
RNO vent isolation valves:
- 3RCS*SV8095A
- 3RCS*SV8095B
- 3RCS*SV8096A
- 3RCS*SV80968 Comments:
Cue:
STEP Candidate depresses OPEN ( ... ) Critical: Grade
- 13 OPEN reactor vessel head push buttons for 3RCS*HC442A and Y[X]N[] S[]U[]
FR-H.1, vents:
3RCS*HC442B and observes ( ... )
step 14.8.2)
- 3RCS*HC442A open light ON, (,o') close lights off.
RNO
- 3RCS*HC4428 Comments:
Cue:
STEP Consult ADTS for Candidate requests the SM/US contact Critical: Grade
- 14 recommendations on aligning any ADTS for recommendations on aligning Y[] N[X] S[]U[]
FR-H.1, available low pressure water any available low pressure water s te p
RNO i
Comments:
Cue: The SM will consult with the ADTS, no low pressure source is immediately available, proceed with the Locedure.
L -- ........ _._--_ ........... _._--- ---_ ............ _._--_ ............... _._--- ---
I 9
STEP IE a low pressure water source Candidate proceeds to step 15. Critical: Grade
- 15 can NOT be aligned, THEN Y[] N[X] S[lU[l Proceed to step 15 Comments:
Cue:
STEP Notify the US that an RCS bleed and Reports to the US that an RCS bleed Critical: Grade
- 16 feed is established. and feed has been established using Y[] N[X] S[JU[l steps 11 - 14 of FR-H.1.
Comments:
Cue:
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
10
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.3 Revision: ~~
Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 7 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
11
STUDENT HANDOUT JPM Number: 2K11 NRC S.3 Revision: o chg 5 Initial Conditions: A reactor trip occurred due to a loss of offsite power. A red path condition on heat sink is present due to no AFW pumps running.
While carrying out the actions of FR-H.1, wide range level in 3 SIGs fell to less than 29%.
Initiating Cues: The US has directed you to establish an ReS bleed and feed using FR-H.1 steps 10 thru 14.
12
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Respond to a Mode 4 LOCA (Alt. 1)
JPM Number: 2K11 NRC S.4 (JPM-135A) Revision: 1 chg 1 Initiated:
Dave Minnich 02/23/11 Developer Date Reviewed:
Robert Royce 519/11 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 02/23/11 Verified JPM to update to revision 017-02 to AOP 3555, ReS 1 Leak. Modified JPM format to be consistent with the NRC 2K11 JPM set. Deleted TR-AA-41 0 Pass/Fail criteria.
Added a comment that depending on the time to reach step 2.c of AOP 3555, Letdown may have auto isolated (PZR level 22%). DLM 6/17/11 Corrected the key number associated with the 1 11 RHS*MV8701 B 1 MV8702A control switch. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep
. Week).
2
JPM WORKSHEET Facility: Examinee:
JPM Number: 2K11 NRC S.4 Revision: 1 chg 1 Task
Title:
Respond to a Mode 4 LOCA (Alt. 1)
System: 005 (RHR)
Time Critical Task: ) YES (X) NO Validated Time (minutes): _ _ _ 5_ _
Task Number(s): 344-05-014 Applicable To: SRO X RO X PEO - - -
KIA Number: KIA Rating:
EPE: 009 - EA1.13
- -4.4/4.4 Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: - -X- In-Plant: - - -
Task Standards: Satisfactorily complete actions to respond to a Mode 4 LOCA lAW AOP 3555.
Reguired Materials: AOP 3555 (procedures. equipment. etc.) Simulator key #35 (PA 1235)
General
References:
AOP 3555 Rev. 017-02 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC S.4 Revision: 1 chg 1 Simulator Requirements: 1. Reset to IC 297 .... OR
- 3. Verify the 45 GPM orifice isolation (CHS*AV8149A) is open with either 75 GPM orifice in service.
- 4. Insert the following:
- b. 1/0 [RH] 3RHS*MV8701 8 (RHDI0013) to 'OPEN'
- c. I/O [RH] 3RHS*MV8702A (RHDI0017) to 'OPEN'
- 5. Place the simulator in "RUN". Acknowledge/clear annunciators and place the simulator in "FREEZE" once PZR level has decreased - 38%.
- 6. Ensure key #35 (PA 1235) is located in either RHS*MV8701 8 or MV8702A control switch.
- 7. Hang YC Tags on SIL*MV8812A & 8 per OP3310A stating "Maintain valve closed unless needed for inventory control"
- 8. After the examinee has received the initiating cues and initial conditions, place the simulator in "RUN".
Approximate simulator setup time is 15 minutes.
Initial Conditions: The plant is in Mode 4 cooling down to Mode 5 in preparation for a refueling outage. 80th Trains of RHR are in service in the COOLDOWN Mode. RCS and CTMT parameters began experiencing symptoms of a RCS leak a short time ago and the crew has entered AOP 3555.
Initiating Cues: The US has directed you to perform AOP 3555, Reactor Coolant System Leak, beginning with step 1.
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * *
- 4
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve~ a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.4 Revision: 1 chg 1 Task
Title:
RespondJQ~fv1()de 4 LOCA (AIt. 1)
START TIME: _ _ __
PERFORMANCE STANDARD Comments: Examinee may elect to trip RCPs any time after NPSH or seal parameters go below minimum specs.
STEP Check PZR Level - DECREASING Verifies PZR level decreasing by Critical: Grade
- 1 using hot and/or cold channel Y[] N[X] S[]U[] I 3555 step 1 indications.
Comments:
Cue:
STEP Increase Charging Flow Verifies normal flow path in service by Critical: Grade
- 2 verifying charging flow indicated Y[] N[X] S[]U[]
3555 step Check charging lineup-NORMAL and/or open indications for normal 2.8. charging line valves.
Comments:
Cue:
STEP Throttle Open charging line flow control Depresses increase pushbutton on Critical: Grade
- 3 valve to increase charging flow to maximum CHS-FK121 and increases output to Y[X]N[] S[]U[]
3555 step 100%.
2.b.
Comments:
Cue:
Verifies charging header flow Critical: Grade increases to maximum. Y[]N[X] S[]U[]
Comments:
Cue: I 6
STEP Check letdown orifice isolation valves - Observes that two letdown orifice Critical: Grade
- 4 ONLY ONE OPEN. isolation valves are open by observing Y[]N[X] Sf] U[]
3555 step 2.c. the indicating lights as green OFF, red ON.
Transitions to RNO column.
Comments:
Cue:
STEP CLOSE the 45 gpm letdown orifice isolation Depresses the CLOSE pushbutton for Critical: Grade
- 5 valve (3CHS*AV8149A). 3CHS* AV8149A and observes valve Y[ ]N[X] S[ ] U[ ]
3555 step 2.c. closes by red indicating light OFF, RNO green ON.
Comments: If PZR level reaches 22% prior to reaching step 2.c, Letdown will auto-isolate. This is acceptable and meets the intent of this step.
Cue:
STEP Verify PZR level - STABLE OR Verifies PZR level still decreasing by Critical: Grade
- 6 INCREASING using hot and/or cold channel Y[]N[X] Sf] U[]
3555 step 2.d indications.
Transitions to RNO column.
Comments:
Cue:
STEP Perform the applicable action: Proceeds to step 3. Critical: Grade
- 7 Y[]N[X] S[ ] U[ ]
3555 step ....lE in operational Mode 4, THEN 2.d.RNO Proceed to Step 3 Comments:
Cue:
STEP Align RHR In Mode 4 Stops RHS*P1A and RHS*P1B and Critical: Grade
- 8 places control switches in PTL. Y[X] N[] S[ ] U[ ]
3555 step 3.a Place RHR pumps lined up for shutdown coolina in PULL-TO-LOCK I Comments: I I - - - - - - - - - - - - - - - - - < - - - - - - - - - - - - - - - L . . - - - - - - - ' - - - - - - - - - - t 7
Cue:
STEP Check ONE TRAIN OF RHR LINED UP Recognizes that both trains are lined Critical: Grade
- 9 FOR INJECTION. up for cooldown mode by either Y[]N[X] S[]U[]
3555 step 3.b system alignment or from initial conditions.
Transitions to RNO column.
Comments:
Cue:
STEP Perform the applicable action to align one Proceeds to either step 4 or step 5. Critical: Grade
- 10 train of RHR for injection: Y[] N[X] S[] U[]
3555 step 3.b RNO
- aligning RHR Train 8, THEN, Proceed to Step 5 Comments: if examinee requests SM/US direction, provide the following cue:
Cue: Align RHR Train "A" for injection Comments: Remaining JPM steps are written such that either RHR train may be aligned for injection. "8" train steps and components are indicated in [ ].
STEP Align RHR Train A [8] For Injection Rotates CHS-HC128 controller Critical: Grade
- 11 potentiometer fully counter clockwise Y[X] N[] S[]U[]
3555 step 4.a CLOSE RHR letdown flow control valve to 0% output.
[5.a] (3CHS-HC128)
Comments:
Cue:
STEP CLOSE RHR outer Ctmt isolation valve Inserts (if necessary) key #35 Critical: Grade
- 12 (3RHS*MV87018) [3RHS*MV8702A] (PA1235) for RHS*MV87018 [8702A] Y[] N[X] S[]U[]
3555 step 4.b and rotates clockwise to close valve.
[5.b] Observes valve does not reposition.
Transitions to RNO column.
8
Comments:
Cue:
STEP CLOSE RHR inner Ctmt isolation valve Inserts key #35 (PA123S) for Critical: Grade
- 13 (3RHS*MV8701A) [3RHS*MV8702B] RHS*MV8701A [87028] and rotates Y[X] N[] S[]U[]
3555 step 4.b 3555 step 4.b. RNO [5.b.) RNO clockwise to close valve. Observes
[5.b] RNO valve closes by red indicating light OFF, green ON.
Comments:
Cue:
Comments: Sub steps 4.c. & 4.e. [S.c. & S.e.] are not critical in nature as sub step 4.d. [S.d.] opens the RHR HX bypass & outlet flow control valves to their SI position by placing the HX flow control switch in "NormaL" Cue:
STEP CLOSE the following: Depresses FK618 [FK619] decrease Critical: Grade
- 14 pushbutton until output is 100% Y[]N[X] S[]U[]
3555 step 4.c
[5.c]
- RHR heat exchanger bypass valve (3RHS-FK618) [FK619] (100%
output)
- RHR heat exchanger outlet flow control valve (3RHS-HC606)
[HC606]
Rotates HC606 [HC607] Critical: Grade potentiometer clockwise until output is Y[] N[X] S[]U[]
0% (10.0 pot setting)
Comments:
Cue:
STEP Place the "HX A [8] FLOW CONT" switch in Rotates the A [8] Flow control switch Critical: Grade
- i
- 15 the "NORMAL" position to NORMAL Y[X] N[] S[]U[]
3555 step 4.d
[5.d]
Comments:
Cue: i 9
STEP Perform the following: Depresses FK618 [FK619] increase Critical: Grade
- 16 pushbutton until output is 0%. Y[]N[X] S[]U[]
- Adjust RHR heat exchanger bypass 3555 step 4.e valve controller (3RHS-FK618) [619]
[5.e] in manual to full open (0% output)
- Adjust RHR heat exchanger outlet flow valve controller demand (3RHS-HC606) [607] to open Rotates HC606 [HC607] Critical: Grade potentiometer counter clockwise until Y[]N[X] S[]U[]
output is 100% (0.0 pot setting).
Comments:
Cue:
1~-------------------------------------------------------------------------------------1 STEP OPEN RWST to RHR pump suction Depresses open pushbutton for Critical: Grade
- 17 isolation valve (3SIL*MV8812A) [8812B] SIL *MV8812A [B] and observes valve Y[X]N[] S[]U[]
3555 step 4.f opens by red indicating light ON,
[5.f] green OFF.
Comments: ~I________________________________________________________________________________~
Cue:
STEP Verify RHR cold leg injection isolation valve Verifies MV8809A [B] open by Critical: Grade
- 18 (3SIL *MV8809A) [8809B] OPEN observing red indicating light ON, Y[] N[X] S[]U[]
3555 step 4.g green OFF.
[5.g]
Comments: ~I ________________________________________________________________________________~
Cue:
STEP Place RHR pump 3RHS*P1A [P1 B] in Removes RHS*P1A [P1B] control Critical: Grade
- 19 AUTO switch from PTL and places in Auto. Y[X] N[] Sf] U[]
3555 step 4.h
[5.h]
Comments: r l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~
Cue:
STEP I Initiate 81 Rotates either SI actuation switch Critical: Grade
- . 20 3555 step 4.i I (MB2 or MB4) clockwise until SI actuates.
Y[X]N[] S[]U[]
~.~=.i~]__~_____________________________L__________________________~________L __ _ _ _ _ _ _ _~
10
Comments:
Cue:
Verifies SI actuation by SI Critical: Grade annunciator(s), and/or equipment Y[]N[X] S[]U[]
repositioning, etc.
Comments:
Cue:
STEP Go to E-O, Reactor Trip or Safety Injection Informs SM/US of E-O transition Critical: Grade
- 21 Y[] N[X] S[]U[]
3555 step 4.j
[5*jl Comments:
Cue: TE!rmin~ting c;ue: Ttle ev~luati()n for !tlis JPM is concluded. ---
STOP TIME: _ _ __
11
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.4 Revision: 1 chg 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 5 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
12
STUDENT HANDOUT JPM Number: 2K11 NRC S.4 Revision: 1 chg 1 Initial Conditions: The plant is in Mode 4 cooling down to Mode 5 in preparation for a refueling outage. Both Trains of RHR are in service in the COOLDOWN Mode. RCS and Ctmt parameters began experiencing symptoms of a RCS leak a short time ago and the crew has entered AOP 3555.
Initiating Cues: The US has directed you to perform AOP 3555, Reactor Coolant System Leak, beginning with step 1.
13
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
SGTR Cooldown Using SG Atmospheric Relief or Relief Bypass Valves JPM Number: 2K11 NRC S.5 (JPM-036A) Revision: 5 chg 2 Initiated:
Dave Minnich 2/24/11 Developer Date Reviewed:
Robert Royce 5/5111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 02/24/11 Verified JPM to update to revision 022 to E-3 and revision § 001 to GA-26. Modified JPM format to be consistent with the NRC 2K11 JPM set. Added several comments in the body of the JPM to enhance the ability of the examiner to navigate the JPM and GA-27. Modified the JPM to start the task from E-3, step 6.d (as opposed to 6.a), and to provide to the examinee the target RCS temperature (which is an SRO task). This did not remove any critical steps and shortened the overall time required to conduct the JPM. Deleted TR-AA 410 Pass/Fail criteria. DLM 5/26/11 Corrected a typographical error. Specifically, the JPM step 5/1 number '31' was inadvertently left out. Incorporated as a result of NRC Exam comments made 5/25/11. Also, added an asterisk to JPM step number 30* (associated with operation of the atmospheric relief bypass valves).
6/17/11 Added a step to the Simulator setup to prepare and have 5/2 ready a copy of E-3 marked up through step 6.c. Made JPM steps 29 and 30 less specific in the critical nature of Valve Controller 1 Valve Control switch operation since the Candidate may reopen the cool down valves to control RCS temperature. Added a statement to the initiating cue that no GA-26 steps have been taken yet. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility: ~M:.:...P-=-3_ _ __ Candidate:
JPM Number: 2K11 NRC S.5 Revision: 5 chg 2 Task
Title:
SGTR Cooldown Using SG Atmospheric Relief or Relief Bypass Valves System: 041/039 Time Critical Task: ) YES (X) NO Validated Time (minutes): ____1...:.0_ _
Task Number(s): 000-05-023 Applicable To: SRO X RO X PEO KIA EPE:038-EA1.16 KIA Rating: 4.4/4.3 Number:
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Satisfactorily complete the RCS cooldown at the maximum rate to less than the required temperature per EOP 35 E-3.
All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Required Materials: GA-26 (procedures, equipment, etc.) MP3 Simulator General
References:
EOP 35 E-3, Steam Generator Tube Rupture, Rev 022 EOP 35 GA-26, Dumping Steam To Condenser Or Atmosphere, Rev 001 3
- READ TO THE CANDIDATE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC S.5 Revision: 5 chg 2 Simulator Requirements: 1. Reset to IC 302 OR reset to any 100% power IC AND
- 2. Insert malfunction SG01B at 40% severity -S/G "B" tube rupture of 400 gpm.
- 3. Place the simulator in "RUN"; allow the radiation levels to increase on ARC-21 until the "RADIATION ALERT" and uRad Hi" annunciators are received. Then trip the reactor and initiate an SI.
- 4. Carry out the actions of E-O, transition to E-3 and carry out the first 5 steps. Ensure intact SG levels are> 8%. AFW flow should be between 530 to 600 gpm to the intact SGs.
- 5. Insert malfunction FW01 at 100% to degrade condenser vacuum to > 5 in. Hg. Ensure "LOSS OF CONDENSER AVAILABLE PERM C9" is lit.
- 7. Acknowledge and clear annunciators and place the simulator in "FREEZE".
- 8. Ready a copy of E-3 marked up through step 6.c (US desk).
- 8. After the Candidate has received the initiating cues and initial conditions, place the simulator in "RUN".
Approximate setup time is 20 - 25 minutes.
Initial Conditions: The plant was operating at 100% power when a tube rupture occurred on the "8" SG. A manual Rx trip and Safety injection was initiated. The control room team has carried out EOP actions through E-3, step 6.c.
Initiatinq Cues: The US has directed you to conduct an RCS cooldown per EOP 35 E-3, Steam Generator Tube Rupture, starting at step 6.d. The required core exit temperature (target) is 515°F.
There have been no GA-26 steps carried out thus far.
4
1< 1< 1< 1< NOTES TO TASK PERFORMANCE EVALUATOR 1< 1< 1< 1<
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.5 Revision: 5 chg 2 Task
Title:
SGTR Cool down Using SG Atmospheric Relief or Relief Bypass Valves START TIME: _ _ __
PERFORMANCE STEP STANDARD STEP Using GA-26, Dump steam from Obtains a copy of GA-26, reviews the Critical: Grade
- 1 intact SGs at maximum rate Y[]N[X] S[]U[]
NOTEs prior to step 1 .
E-3 step 6.d Comments: The candidate may also request to review E-3 step 6. This is acceptable.
Comments: If the Candidate asks the status of the RCP overcurrent trip switches, provide the following cue:
Cue: RCP overcurrent trip switches are in the COLD position.
STEP After Low Steam line Pressure Safety Obtains a copy of GA-26, refers to the Critical: Grade
- 2 Injection signal is BLOCKED, MSI Y[]N[X] S[]U[]
NOTEs prior to step 1.
will occur if the High Steam Pressure GA-26 step 1, NOTE 3 Rate setpoint is exceeded.
Comments: The third NOTE prior to step 1 infers, the Candidate will block the Low Steam Line Pressure SI when (and if) pressurizer pressure is LESS THAN 2000 psia. When these conditions are met, this action can be taken by the operator at any time during this JPM as follows:
Cue:
STEP Block Low Steam Line Pressure SI Depresses STEAM LINE ISOL - SI Critical: Grade
- 3 block pushbuttons on MB2 Y[] N[X] S[]U[]
Comments:
Cue:
6
Observesl Acknowledges Mn Steam Critical: Grade Line SI Block Train AlB Annunciators Y[]N[X] S[]U[]
on MB4D 1-3 and 2-3.
Comments:
Cue:
STEP Verify Plant Conditions Observes that the 'A' IA Compressor is Critical: Grade
- 4 running. Y[] N[X] S[]U[]
Check instrument air compressors GA-26 AT LEAST ONE RUNNING step 1.a Comments:
Cue:
STEP Check Annunciator "MAIN STEAM Observes that intact SG MSIVs are Critical: Grade
- 5 LINE ISOLATION" (MB2B 5-7) OPEN and MB2B 5-7 is NOT lit. Y[] N[X] S[]U[]
GA-26 step 1.b NOT LIT Comments:
Cue:
STEP Determine Condenser Steam Candidate recognizes that C-9 is NOT Critical: Grade
- 6 lit and hence the condenser is not Y[] N[X] S[]U[]
Dump Availability available.
GA-26 Check the following:
step 2.a Candidate shifts to the RNO column.
- Using condenser steam dumps - DESIRED
- Annunciator "CONDENSER AVAIL FOR STM DUMP C-9" (MB4D 5-6) - LIT
Comments:
~~~~~~~
If the Candidate asks the US whether using condenser steam dumps is desired, provide the following cue:
Cue: Use the condenser steam dumps if possible.
STEP Perform the following: Candidate proceeds to the NOTE prior Critical: Grade
- 7 to step 4. Y[] N[X] S[]U[]
GA-26 step Proceed to NOTE prior to step 4.
2.8 RNO Comments: Candidate may inform the US that steam dumps are not available and the atmospheric relief valves or their associated bypass valves will have to be used for the cooldown. The candidate may place one or both steam dump interlock switches to OFF. This is satisfactory.
Cue:
STEP Following MSI reset, an actuation Candidate reviews NOTE. Critical: Grade
- 8 signal will re-initiate MSI. Y[] N[X] S[]U[]
GA 26, step 4 NOTE Comments:
Cue:
STEP Determine SG Atmospheric Relief Candidate recognizes that using SG Critical: Grade
- 9 atmospheric relief or bypass valves is Y[] N[X] S[]U[]
Valves Availability desired based on the unavailability of GA 26, Check using SG atmospheric relief the condenser.
step 4.8 valves - DESIRED Comments: IF the Candidate asks the US for guidance concerning which valves to use, or if the Candidate proceeds to step 6 to use the Bypass Valves, provide the following Cue:
Cue: Use the SG Atmospheric Relief Valves.
8
STEP Place SG atmospheric relief valve Takes manual control of the Critical: Grade
- 10 Y[X]N[ ] S[]U[]
controllers in MANUAL and Adjust to Atmospheric Relief Valves for each GA-26. zero output intact SG step 4.b (3MSS*PV20A)
(3MSS*PV20C)
(3MSS*PV20D)
By pressing the manual pushbutton and observing the auto light OFF and the manual light ON. Adjusts each for zero output. ~~-
Comments:
Cue:
STEP Check Annunciator "MAIN STEAM Observes that intact SG MSIVs are Critical: Grade
- 11 LINE ISOLATION" (MB2B 5-7) - LIT OPEN and MB2B 5-7 is NOT lit. Y[] N[X] S[]U[]
GA-26.
step 4.c Shifts to the RNO column. I Comments:
Cue:
STEP Proceed to step 5. Candidate proceeds to step 5. Critical: Grade
- 12 Y[] N[X] S[]U[]
GA-26.
step 4.c RNO I
Comments: I Cue:
STEP Dump Steam to Atmosphere Candidate recognizes that an RCS Critical: Grade
- 13 cooldown is desired. Y[] N[X] S[]U[]
Using SG Atmospheric Relief GA-26. Valves I step 5.2 Check RCS cooldown or SG depressurization - DESIRED Comments: !
9
Cue:
STEP Check the procedure in effect Candidate recognizes that step 6.d of Critical: Grade I
- 14 requires steam dump - AT A E-3 directed steam be dumped at the Y[]N[X] S[]U[]
MAXIMUM RATE maximum rate from the intact SGs.
GA-26, step 5.b Comments:
Cue:
STEP Adjust each selected SG Using the manual adjust levers, evenly Critical: Grade
- 15 and over the course of about a minute, Y[X]N[ ] S[]U[]
atmospheric relief valve controller evenly over an approximate one increases the output signal on the 'A',
GA-26, step 5.c minute time period to open the "C' and '0' SG atmospheric relief valve associated valve controllers until a 100% demand signal is obtained and the indicating lights for
- 3MSS-PIC20A 1 the atmospheric relief valves shift to
- 3MSS-PIC20B 1 green OFF, red ON.
- 3MSS-PIC20D1 Comments: If the Candidate performs the opening of the atmospheric relief valves too fast, a main steam line isolation will occur. The Candidate should recognize this and Return to NOTE prior to step 4 of GA-26.
The Candidate should NOT open the 'B' atmospheric relief valve.
Comments: JPM steps 16* - 23* are only performed if a main steam line isolation has occurred. This will involve using the SG Atmospheric Relief Bypass Valves.
Cue:
STEP Recognize a main steam line Acknowledges the Main Steam Line Critical: Grade
- 16* isolation has occurred. isolation annunciator and realizes the Y[] N[X] S[]U[]
atmospheric relief valves are closed and no longer available for cooldown.
Comments:
Cue:
10
STEP IF MSI actuates, THEN Return to Candidate after recognizing a main Critical: Grade
- 17* NOTE prior to step 4. steam line isolation has occurred, Y[]N[X] S [ ] U[ ]
returns to the note prior to step 4.
GA-26 step 4.c RNO Comments:
Cue:
STEP Determine SG Atmospheric Relief Candidate questions the US if using Critical: Grade
- 18* the SG atmospheric relief valves is Y[] N[X] S[]U[]
Valves Availability desired.
GA-26. Check using SG atmospheric relief step 4.a valves - DESIRED Comments: When the Candidate asks the US for guidance concerning if using the SG atmospheric relief valves is desired provide the following Cue:
Cue: Use the SG Atmospheric Relief Bypass Valves.
STEP Proceed to step 6. Candidate proceeds to step 6. Critical: Grade
- 19* Y[]N[X] S[]U[]
GA-26.
step 4.a RNO Comments:
Cue:
...... _. .... _. ........... ......... _._---_ ....... ------~~
11
'STEP Dump Steam to Atmosphere Candidate goes around the back of Critical: Grade
- 20* MBS and places the 'A', 'C' and '0' SG Y[lN[X] S[]U[]
Using SG Atmospheric Relief Bypass Valves atmospheric relief bypass valves' GA-26.
step 6.a CONTROL LOCKOUT switches in Place the desired SG atmospheric NORMAL, and observes the white relief bypass valves' CONTROL indicating lights turn ON.
LOCKOUT switches in NORMAL (MBSR)
- 3MSS*MOV74A
- 3MSS*MOV74B
- 3MSS*MOV74C
- 3MSS*MOV740 Comments: The Candidate should not place the 'B' CONTROL LOCKOUT switch in NORMAL.
Cue:
STEP Throttle the desired SG atmospheric Oepresses the "open" pushbuttons for Critical: Grade
- 21* Y[X]N[] S[]U[]
relief bypass valves to reduce or the atmospheric relief bypass valves GA-26. maintain RCS temperature or SG on the "A", "C" and "0" SGs step 6.b pressures as specified by the procedure in effect (3MSS*MOV74A)
- 3MSS*MOV74A (3MSS*MOV74C)
- 3MSS*MOV74B (3MSS*MOV740)
- 3MSS*MOV74C
- 3MSS*MOV740 and observes the indicating lights shift to green OFF, red ON then releases the "open" pushbutton.
Comments: The Candidate should NOT open the 'B' atmospheric relief bypass valve.
Comments: It takes about 2 minutes for the MSS*MOV74 valves to stroke fully open. The candidate may ask for SM's permission to use two-handed operation. If so, provide the following Cue:
I 12
Cue: You may use two-handed operation.
STEP Check dumping steam from any SG Candidate recognizes that the SG Critical: Grade
- 22* atmospheric relief isolation valve(s) are Y[ ]N[X] S[]U[]
using SG atmospheric relief isolation valve(s) - DESIRED not needed.
GA-26.
step 6.c Shifts to the RNO column.
Comments:
Cue:
STEP Proceed to step 8. Candidate proceeds to step 8. Critical: Grade
- 23* Y[] N[X] S[]U[]
GA-26 step 6.c RNO Comments:
Cue:
STEP Proceed to step 8. Candidate proceeds to step 8. Critical: Grade
- 24 Y[] N[X] S[]U[]
GA-26 step 5.c Comments:
Cue:
STEP Check If RCS Temperature Or Displays the core exit thermocouple Critical: Grade
- 25 map on the computer display screen or Y[] N[X] S[]U[]
Steam Generator Pressures Should Be Stabilized uses ICC cabinet. Monitors the GA 26.
step 8 a temperatures to ensure temperature is Check RCS temperature or SG lowering.
pressures - AT DESIRED VALUE Comments:
Cue:
13
STEP Continue dumping steam as Displays the core exit thermocouple Critical: Grade
- 26 map on the computer display screen or Y[]N[X] S[]U[]
specified by the procedure in effect and, WHEN RCS temperature or SG uses ICC cabinet. Monitors the GA-26, step 8.a pressures are at the desired value, temperatures to ensure temperature is RNO THEN Proceed to step B.b. lowering.
I Comments: The remaining steps are associated with stopping the cooldown, starting with E-3, step 6.e. Note that the Candidate should also be able to complete steps 27 and 2B using GA-27 alone Cue: I STEP Verify core exit TCs - LESS THAN Displays the core exit thermocouple Critical: Grade I
- 27 REQUIRED TEMPERATURE. map on the computer display screen or Y[X]N[ ] S[]U[]
uses ICC cabinet. Monitors the E-3 step 6.e temperatures to ensure temperature is below the temperature determined in E-3 step 6.c (given in the initiating cue). I Comments:
Cue:
STEP Using GA-26, Perform the following: Candidate returns to GA-26, step B.b. Critical: Grade
- 28 Y[] N[X] S[]U[]
- 1) Stop RCS cooldown E-3 step 6.f Comments: GA-26 step B.b (Check condenser steam dumps - IN USE), and its associated RNO will direct the operator to step 10 IF SG atmospheric relief valves are in use, or step 11 IF SG atmospheric relief bypass valves are in use.
Cue:
I _ ~J --~ ..........- . - -.........- .- -~ ........ -~ ...........-
14
STEP Stabilize Using SG Atmospheric Candidate recognizes that E-3 Critical: Grade
- 29 specified that the cooldown be Y[] N[X] S[]U[]
Relief Valves stopped.
GA-26 Adjust each selected SG step
- 10. a atmospheric relief valve controller as necessary to stabilize and maintain RCS temperature or SG pressures as specified by the procedure in effect Uses the atmospheric relief valve Critical: Grade controller manual adjust levers to Y[X]N[ ] S[]U[]
decrease the demand signal as necessary to stop the cooldown, and then control RCS temperature.
Comments:
Cue:
Comments: JPM step 30* is only performed if a main steam line isolation has occurred. This will involve closing the SG Atmospheric Relief Bvpass Valves.
STEP Stabilize Using SG Atmospheric Candidate recognizes that E-3 Critical: Grade I
- 30* Relief Bypass Or Isolation Valves specified that the cooldown be Y[] N[X] S[]U[]
stopped.
GA-26, Throttle the selected SG step 11.a atmospheric relief bypass valves to stabilize and maintain RCS temperature or SG pressures as specified by the procedure in effect
- 3MSS*MOV74A
- 3MSS*MOV74B
- 3MSS*MOV74C
- 3MSS*MOV740 Comments: !
15
Cue:
Depresses the "close" push buttons for Critical: Grade the atmospheric relief bypass valves Y[X]N[ ] S[]U[]
on the "A", "C" and "0" SGs (3MSS*MOV74A, C, D), and positions the valves as necessary to stop the cooldown, and then control RCS temperature.
Comments:
Cue:
STEP Notify the US that the required RCS Informs the US that the required RCS Critical: Grade
- 31 cooldown in accordance with E-3, Step Y[] N[X] S[]U[]
cooldown is complete.
6, has been completed.
Comments:
Cue:
TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ __
16
VERIFICATION OF JPM COMPLETION
..IPM Number: 2K11 NRC S.5 Revision: 5 chg 2 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 10 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
17
STUDENT HANDOUT JPM Number: 2K11 NRC 8.5 Revision: 5 chg 2 Initial Conditions: The plant was operating at 100% power when a tube rupture occurred on the "B" SG. A manual Rx trip and Safety injection was initiated. The control room team has carried out EOP actions through E-3, step 6.c.
Initiating Cues: The US has directed you to conduct an ReS cooldown per EOP 35 E-3, Steam Generator Tube Rupture, starting at step 6.d. The required core exit temperature (target) is 515°F. There have been no GA-26 steps carried out thus far.
18
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Respond To High Containment Pressure JPM Number: 2K11 NRC S.6 (JPM-128) Revision: 2 chg 1 Initiated:
Dave Minnich 2/17/11 Developer Date Reviewed:
Robert Royce 5/5111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 2/17/11 Updated JPM to revision 016-02 to FR-Z.1. This involved a 2/Q substantial rewrite of this JPM. Modified JPM format to be consistent with the NRC 2K11 JPM set. DLM 6/20/11 Modified the standard associated with JPM step 27 to be a 2/1 direct order from the RO to the PEO for specific field actions.
Incorporated as a result of NRC comments made the week of .
6/13/11 (Prep Week). Corrected a typographical error in the I !
i comment associated with JPM step 30. I I
2
JPM WORKSHEET Facility: _M;.;,,;.:....P-=.3_ _ __ Examinee:
JPM Number: 2K11 NRC S.6 Revision: 2 chg 1 Task
Title:
Respond To High Containment Pressure System: 005 - 026 (CTMT Spray System)
Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 10 Task Number(s): 000-05-052 Applicable To: SRO X RO X PEO KIA EPE: E14 - EA1.1 KIA Rating: 3.7/3.7 Number:
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: Start a containment spray pump by completing the first 5 steps of FR Z.1.
Required Materials: FR-Z.1, Response To High Containment Pressure (procedures, equipment, etc.)
MP3 Simulator General
References:
FR-Z.1, Response To High Containment Pressure, Revision 016-02 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating CW3S. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC S.6 Revision: 2 chg 1 Simulator Requirements: 1. Reset to Ie 301 .... OR
- 2. Reset to IC-18, or equivalent 100% power IC.
- 3. Insert the following malfunctions:
- CS018 - "8" Quench Spray Pump trip.
- 4. Insert the following I/O overrides:
- RPDI0004 (P81 CDA Actuate Train A) - 'NACTUATE'.
- RPDI0006 (P83 CDA Actuate Train 8) - 'NACTUATE'.
- 5. Place the "A" Quench Spray Pump in "PULL-TO-LOCK" and place a yellow caution tag on the control switch.
- 6. Place the simulator in "RUN."
- Take the MASTER SILENCE SWITCH to "SILENCE."
- Insert malfunction MS01A - S/G "A" faulted inside containment, at 100% severity.
- 7. Allow the simulator to run for 1-2 minutes. (Adverse CTMT will be met due to CTMT temperature.) During this time perform the following:
- Stop the "c" CAR fan.
- Stop the kitchen exhaust fan.
- Stop AFW flow to "A" S/G.
- Throttle AFW flow to 200 gpm to each of the other S/Gs.
- 8. When the above actions are complete and the Containment HI-3 setpoint is reached, perform the following:
- Acknowledge/clear all alarms
- Come out of Master Silence
- Place the simulator in 'FREEZE."
4
- 9. When the examinee has received the initial conditions and initiating cues, place the simulator in "RUN."
Approximate simulator setup time is 6-8 minutes.
Initial Conditions: A steam-line break inside containment has occurred. Based on plant conditions, a manual reactor trip and safety injection were initiated. The Control Room Team is progressing through the EOPs and during the transition to E-2, Faulted Steam Generator Isolation, a COA signal was received and an "orange" path for containment integrity. The "A" Quench Spray Pump is tagged out for maintenance.
Initiating Cues: The US has directed you to perform FR-Z.1, Response To High Containment Pressure, in an attempt to initiate containment spray.
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR"" * *
- 1. Critical steps for this JPM are indicated by checking "Y", For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.6 Revision: 2 chg 1 Task
Title:
Respond To High Containment Pressure START TIME: _ _ __
PERFORMANCE STEP STANDARD STEP Obtains copy of FR-Z.1 . Obtains a copy of FR-Z.1, refers to Critical: Grade I
- 1 Y[ ] S[ ]
Step 1, Caution.
N[X] U[ ]
Comments:
Cue:
STEP If RWST level decreases to LESS Applicant reviews CAUTION, and at Critical: Grade
- 2 THAN 520,000 gal, Go to ES-1.3, Y[JN[X] S[]U[]
MB2 observes that RWST level is Transfer to Cold Leg Recirculation, greater than 520,000 gallons.
FR-Z.1, to align the ECGS system.
step 1 CAUTION Comments:
Cue:
STEP Check IF CDA Required Applicant checks GTMT pressure is Critical: Grade
- 3 greater than 23 psia by checking any of Y[] N[X] S[]U[]
FR-Z.1, Check Ctmt pressure -- the following: Meters at MB2:
step 1.a GREATER THAN 23 psia LMS*PI934, 935, 936 or 937, or recorder 3LMS*PR934.
Comments:
Cue: - --~ ...........- .- ......... -.-~ ........- . - - ......... .. -~
-- --~
6
STEP Verify annunciator "CONTAINMENT Observes that annunciator MB2B:5-5 Critical: Grade
- 4 DE PRES ACTUATION" (MB2B 5-5) IS lit. Y[]N[X] S[]U[]
F R Z.1, --- LIT step step 1.b Comments:
Cue:
STEP Check RPCCW pumps - STOPPED Observes that RPCCW pumps Critical: Grade
- 5 3CCP*P1A & P1 B have no running Y [ ] N [X ] S[]U(]
FR-Z.1, amps indicated and the indicating lights step 1.c are green ON, red OFF.
Comments:
Cue:
STEP STOP all RCPs Rotates the 3RCS-P1 A control switch Critical: Grade
- 6 to "STOP" and observes the flag shifts Y[X] N[] S[]U[]
FR-Z.1, to "green;" amperage indication goes to step 1.d zero; and indicating lights shift to green ON, red OFF.
Rotates the 3RCS-P1 B control switch Critical: Grade to "STOP" and observes the flag shifts Y[X] N[] S[1U[1 to "green;" amperage indication goes to zero; and indicating lights shift to green ON, red OFF.
Rotates the 3RCS-P 1C control switch Critical: Grade to "STOP" and observes the flag shifts Y[X1 N[] S[1 U [11 to "green;" amperage indication goes to zero; and indicating lights shift to green ON, red OFF.
Rotates the 3RCS-P1 0 control switch Critical: Grade to "STOP" and observes the flag shifts Y[X]N[] S[1U[]
to "green;" amperage indication goes to zero; and indicating lights shift to green ON, red OFF.
Comments: The RCPs mC!}' be stoQped in any order.
7
Cue:
STEP Check CAR fans - STOPPED Observes at VP1 that the 'A', '8' and Critical: Grade
- 7 'c' CAR fans are stopped. Y[] N[X] S[]U[]
FR-Z.1, step 1.e Comments:
Cue:
STEP Check CRDM fans - STOPPED Observes at VP1 that the 'A' and '8' Critical: Grade
- 8 CRDM fans are stopped, but Y[] N[X] S[]U[]
FR-Z.1, recognizes the 'c' CRDM fan is still step 1.f running by indicating lights red ON, green OFF.
Transitions to the RNO column.
Comments:
Cue:
STEP STOP CRDM fans. Rotates the 3HVR-FN2C control switch Critical: Grade
- 9 Y[X] N[] S[]U[]
FR-Z.1, to "STOP" and observes the flag shifts step 1.f to "green;" and indicating lights shift to RNO green ON, red OFF.
Comments:
Cue:
STEP If ECA-1.1, Loss of Emergency Applicant reviews CAUTION, Critical: Grade
- 10 Coolant Recirculation, is in progress, Y[] N[X] S[]U[]
FR-Z.1, Ctmt spray should be operated as st ep 2 CAUTION directed in ECA-1.1 Comments: If the applicant questions the status of procedure ECA-1.1 due to the caution in FR-Z.1 , provide the following cue:
Cue: The Control Room Team has not yet entered ECA-1.1.
8
STEP Verify Quench Spray System Observes that annunciator MB2A 5-2 is Critical: Grade
- 11 Operation not lit (dark). Y[] N[X] S[]U[]
FR-Z.1, step 2.a Check annunciator RWST EMPTY QSS PP OFF (69,331 gal) (MB2A 5
- 2) - NOT LIT Comments:
Cue:
STEP Verify quench spray pumps - Observes that no amperage is Critical: Grade
- 12 RUNNING. indicated and the indicating lights are Y[] N[X] S[]U[]
FR-Z.1, green ON, red OFF for the 'B' QSS step 2.b pump. The pump is not running.
Applicant transitions to the RNO column.
Comments: Pump 3QSS*P3A is tagged out.
Cue:
STEP START pumps. Rotates the control switch for Critical: Grade
- 13 3QSS*P3B to liSTART" and observes Y[] N[X] S[]U[]
FR-Z.1, IF no QSS pump is running, that no amperage is indicated and the step 2.b RNO THEN indicating lights shift to green ON, Proceed to step 4. amber ON, red OFF. The pump did not start.
Applicant proceeds to step 4.
Comments:
Cue:
STEP Verify CIA Observes that the ESF Group 2 Status Critical: Grade
- 14 Lights in columns 2 through 10 are lit. Y[] N[X] S[]U[]
FR-Z.1, Check ESF Group 2, step 4.a columns 2 though 10 - LIT I Comments: I 9 I
Cue:
STEP Verify Recirculation Spray System Observes the indicating lights for Critical: Grade
- 15 Operation 3RSS*MOV23A - D are green OFF, Y[]N[X] S[]U[]
FR-Z.1, red ON. The valves are open.
step 5.a Check recirculation spray pump suction isolation valves - OPEN I
Comments:
Cue:
STEP Check recirculation spray pumps Recognizes that NO RSS pumps are Critical: Grade I
- 16 ANY RUNNING running by no running amps indicated Y[] N[X] S[]U[]
FR-Z.1, and the indicating lights are green ON, step 5.b red OFF.
Transitions to the RNO column.
Comments:
Cue:
STEP Perform the following: Applicant observes that RWST level is Critical: Grade
- 17 1) IF RWST level is GREATER greater than 520,000 gallons by Y[] N[X] S[]U[]
FR-Z.1, THAN 520,000 gal, THEN checking level on any of the meters at step S.b RNO Proceed to step S.d. MB2: QSS*U930, 931,932 or 933.
Applicant proceeds to step S.d.
Comments:
Cue:
STEP Check Ctmt WR sump level Applicant observes that CTMT Wide Critical: Grade
- 18 (3RSS*U22A, 3RSS*U22B) Range sump level is LESS than 7.5 Y[] N[X] S[]U[]
FR-Z.1, GREATER THAN 7.5 feet feet by checking meters 3RSS*Ll22A step 5.d and I or 3RSS*U22B level on Meters at MB2.
Transitions to the RNO column.
Comments:
Cue:
10
STEP Perform the applicable action: Applicant observes that ass flow is Critical: Grade
- 19 not indicated by checking meters ass- Y[] N[X] S[]U[]
FR-Z.1.
step S.d
- IF ass flow is NOT indicated, FI32A and FI32B at MB2.
RNO THEN Proceed to NOTE prior to step 6. Applicant proceeds to step 6.
Comments:
Cue:
STEP Applicant reviews NOTE. Critical: Grade
- 20
- The Locked Valve Key is Y[] N[X] S[]U[]
FR-Z.1, required for performance of some ste p 6 of the local actions in the NOTE following step.
- The preferred priority for selecting a recirculation spray pump is as follows:
- 1. Pump C or D
- 2. Pump Aor B Comments: After reading the notes, the examinee may ask about which pump to use. If asked, or if the Candidate selects the 'c' RSS pump, provide the following cue:
Cue: The US directs you to align recirculation spray pump "D."
......... _. ............ _._- --_ ......... _._- ----- ......... -.-~ ........ -.-~
11
STEP Check If Spray Using An RSS Applicant observes that RWST level is Critical: Grade *
- 21 Pump From The RWST Should Be greater than 520,000 gallons by Y[]N[X] S[]U[]
FR-Z.1, Established checking level on any of the meters at step 6.a MB2: QSS*Ll930, 931, 932 or 933.
Check the following:
- RWST level - GREATER THAN 100,000 gal
- Quench Spray pumps NONE RUNNING
Observes that the indicating lights are Critical: Grade green ON, red OFF for the 'B' QSS Y[] N[X] S[]U[]
pump. The pump is not running. Pump 3QSS*P3A is tagged out.
Comments: When the applicant asks for a AOTS/CR OSEO recommendation, provide the following cue:
Cue: The CR OSEO recommends using one RSS pump from the RWST to spray containment.
STEP RESET SI Applicant depresses the MB2 SI Critical: . Grade
- 22 RESET pushbuttons. Y[X] N[] S[]U[]
FR-Z.1, step~ ._-
12
-~
Comments: This action will cause several annunciators to clear and alarm. The examinee should acknowledge and I reset these annunciators as appropriate. However, this action is not required to complete the critical nature, of this step.
I Cue:
STEP Determine the RSS pump to be The applicant should recognize that the Critical: Grade
- 23 placed in service 'D' RSS pump will be placed in service. Y[] N[X] S[]U[1 FR-Z.1, step 6.c Comments: The "0" recirculation spraYRum~ will be used (cue provided in JPM step 20)
Cue: ,
STEP Place the selected recirculation Rotates the 3RSS*P1 0 control switch Critical: Grade
- 24 spray pump in PULL TO LOCK to the PULL TO LOCK position and Y[X1N[] S[1U[]
FR-Z.1, then pulls the switch handle up into step 6.d "PULL-TO-LOCK".
Comments:
Cue:
STEP For the selected RSS pump, At VP1 , the applicant rotates the Critical: Grade
- 25 START the associated RECIRC 3HVQ*ACU2B control switch to Y[X] N[] S[]U[]
FR-Z.1, SPRAYACU "START" and observes indicating lights step 6.e (3HVQ*ACUS2A or 3HVQ*ACUS2B) shift to green OFF, red ON.
~_C~
Comments:
Cue:
Comments: 3QSS*AOV27 and 3QSS*AOV28 may be operated in any order.
STEP OPEN RWST recirculation suction Depresses the 3QSS*AOV27 OPEN Critical: Grade
- 26 valves (MB1) pushbutton, observes the indicating Y[X] N[] S[]U[]
FR-Z.1, lights shift to green OFF, red ON, then step 6.f
- 3QSS*AOV27 releases the pushbutton.
- 3QSS*AOV28 Comments:
Cue: -- ~-- ............. -.-~
13
Depresses the 3QSS*AOV28 OPEN Critical: Grade pushbutton, observes the indicating Y[X] N[] S[]U[]
lights shift to green OFF, red ON, then releases the pushbutton.
Comments:
Cue:
STEP Using Attachment 8, locally align the Contacts a PEO and directs, "locally Critical: Grade
- 27 selected RSS pump align the '0' recirculation spray pump Y[] N[X] S[]U[]
FR-Z.1, for CTMT spray from the RWST, in step 6.9 accordance with Attachment 8 to FR Z.1."
Comments: As PEO acknowledge the request.
f-----~~.
Cue:
BOOTH: At the instructor station enter the following:
- Remote Functions: CSR05 to "OPEN" I/O override: CSL00047 (3RSS*MOV23D red light) to 'OFF'.
Comments: BOOTH: Once these remotes are active, provide the following cue:
I Cue: The '0' recirculation spray pump has been locally aligned for CTMT spray from the RWST, in accordance with Attachment B to FR-Z.1 .
STEP Check the selected recirculation Observes the indicating lights for Critical: Grade
- 28 spray pump RHR isolation - 3RSS*MV88388 are green ON, red Y[] N[X] S[]U[]
FR-Z.1. CLOSED OFF. The valve is closed.
step 6.h
- For pump 0 3RSS*MV88388 Comments:
Cue:
14
STEP Check the selected recirculation Observes the indicating lights for Critical: Grade
- 29 spray pump spray header isolation 3RSS*MOV200 are green OFF, red Y[] N[X] S[]U[]
FR-Z.1, valve - OPEN ON. The valve is open.
step 6.i
- For pump 0 - 3RSS*MOV200 Comments:
Cue:
STEP Check local system alignment - Verifies that the local system alignment Critical: Grade
- 30 COMPLETED is complete. Y[] N[X] S[]U[]
FR-Z.1, step 6.j Comments: The examinee was informed when lineup was completed (JPM step 27).
Cue:
STEP START the selected RSS pump Pushes down on the "0" recirculation Critical: Grade
- 31 spray pump control switch to take it out Y[X] N[] S[]U[]
FR-Z.1, of "PULL-TO-LOCK." Rotates the step 6.k control switch to "START" and observes that amperage is indicated and the indicating lights shift to green OFF, red ON.
Comments:
Cue:
The applicant should also check that Critical: Grade flow is present by observing flow Y[] N[X] S[]U[]
indication on 3RSS-FI400.
Comments:
Cue:
STEP Notify the US that containment Applicant informs the US that Critical: Grade
- 32 spray has been initiated containment spray has been initiated Y[] N[X] S[]U[]
using the "0" recirculation spray pump.
Comments:
Cue: TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
15
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.6 Revision: E~
Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 10 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
16
STUDENT HANDOUT JPM Number: 2K9 NRC 8.6 Revision: 2 chg 1 Initial Conditions: A steam-line break inside containment has occurred. Based on plant conditions, a manual reactor trip and safety injection were initiated. The Control Room Team is progressing through the EOPs and during the transition to E-2, Faulted Steam Generator Isolation, a COA signal was received and an "orange" path for containment integrity. The "A" Quench Spray Pump is tagged out for maintenance.
Initiating Cues: The US has directed you to perform FR-Z.1, Response To High Containment Pressure, in an attempt to initiate containment spray.
17
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Energize SBO Auxiliaries with the SBO Diesel JPM Number: 2K11 NRCS.7 Revision: 0 chg 1 Initiated:
Dave Minnich 2/19/11 Developer Date Reviewed:
Robert Royce 5/5111 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 6/21/11 Modified the standards associated with JPM steps 8, 9, 19, 0/1 20,22 and 23 to be direct orders from the RO to the PEO for specific field actions. Also, added specific pump designations
. to the standards associated with JPM steps 16 and 17.
Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
i i
2
JPM WORKSHEET Facility: _M:. :. :. ;. .P. ; ;. 3_ _ __ Examinee:
JPM Number: 2K11 NRC S.7 Revision: 0 chg 1 Task
Title:
Energize SBO Auxiliaries with the SBO Diesel System: 062 - AC Electrical Distribution Time Critical Task: ) YES (X) NO Validated Time (minutes): ___1_2_ _
Task Number(s): 000-05-124 Applicable To: SRO X RO X PEO _ __
KIA 062 A1.01 KIA Rating: 3.4/3.8 Number:
Method of Testing: Simulated Actual X Performance: Performance:
Location: Classroom: Simulator: X In-Plant:
Task Standards: All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Required Materials: GA-27, Energizing sao Diesel Auxiliaries With sao Diesel (procedures, equipment. etc.)
General
References:
GA-27, Energizing sao Diesel Auxiliaries With sao Diesel, Revision 000 ES-0.1, Reactor Trip Response, Revision 024 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating CUE~S. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC S.7 Revision: o chg 1 Simulator 1. Reset to IC 253 .... OR Requirements:
- 3. Insert malfunction ED01 - Loss of Offsite Power.
- 4. To give the appearance that the control room team has carried out the actions in E-O and ES-0.1 through step 7, perform the following.
- Take motor driven feed pump control switch to PULL-TO-LOCK.
- Take all condensate pump control switches to PULL-TO-LOCK.
- Transfer condenser steam dumps to Steam Pressure mode.
- Start the 'B' lAS Compressor, and the "A' and 'B' PZR heaters.
- Reenergize 32-3T.
- Reset LOP from MB2.
- Allow reactor power to decrease into the source range and shift the NR45 recorder to the source ranges.
- 5. Acknowledge and clear alarms. Place the simulator in "Freeze"
- 6. After the examinee has the initiating cues and initial conditions, place the simulator in "RUN".
Approximate setup time is 10 minutes.
4
Initial Conditions: A turbine trip occurred and the reactor tripped. Moments later, a loss of offsite power occurred. Information indicates that offsite power will not be restored for an extended period of time. The control room team has carried out E-O immediate actions, transitioned to ES-O.1 and completed steps 1 through 7.
Initiating Cues: The US has directed you carry out step 8 of ES-O.1, Check Power To SBO Diesel Auxiliaries. The SBO is not running.
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?").
Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only). J 5
PERFORMANCE INFORMATION JPM Number: 2K11 NRC S.7 Revision: o chg 1 Task
Title:
Energize SBO Auxiliaries with the SSO Diesel START TIME: _ _ __
PERFORMANCE STEP STANDARD STEP Obtains copy of ES-O.1. Obtains a copy of ES-O.1, refers to Critical: Grade
- 1 Y[]N[X] S[]U[]
Step 8, NOTES.
Comments:
Cue:
STEP
- If the SBO diesel auxiliaries Candidate reviews the NOTES . Critical: Grade
- 2 are not repowered within an Y[]N[X] S[]U[]
hour, the SBO diesel may be E SO.1, s te p 8 unavailable for starting.
NOTES
- Power to the SBO diesel auxiliaries should be monitored and if power is lost, GA-25 or GA-27, as applicable, should be used to re-establish power.
Comments:
Cue:
--- ~
6
STEP Check Power To SBa Diesel At MB8, Candidate observes that Bus Critical: Grade
- 2 Auxiliaries Y[] N[Xl S[lU[l 34A and 34B are both de-energized.
E 80 .1, Verify any SBO bus tie step a.a breaker - CLOSED TO AN ENERGIZED BUS
- Bus 34A: 34A1-2
- Bus 34B: 34B1-2
- Bus 24E: A505 (Unit 2)
Comments:
Cue:
Call Unit 2 for breaker A505 status. Candidate calls the Unit 2 Control Critical: Grade Room and asks for the status of the Y[] N[X] S[ ] U[ ]
A505 breaker.
Comments: As the Unit 2 BOP operator, provide the following cue:
Cue: The A505 breaker is open.
Recognizes that NO SBO bus tie Critical: Grade breaker is closed to an energized bus. Y[]N[X] S[]U[]
Transitions to the RNO column.
Comments:
Cue:
STEP Perform the applicable action: Candidate recognizes that Bus 34A Critical: Grade
- 3 and 34B are still both de-energized and Y[]N[X] S[]U[]
E 8 0.1, step B.a
- IF busses 34A AND 34B are GA-27 is required.
RNO NOT energized, THEN Using GA-27, Establish power to SBO diesel auxiliaries.
7
Comments:
Cue:
STEP Obtains copy of GA-27. Obtains a copy of GA-27, refers to Critical: Grade
- 4 Y [ ] N [X ] S[]U[]
Step 1, NOTE.
Comments:
Cue:
STEP If the SBO diesel auxiliaries are not Candidate reviews the NOTE. Critical: Grade
- 5 reenergized within an hour, the SBO Y [ ] N [X ] S[]U[]
GA-27, diesel may be unavailable for step 1 NOTE starting.
Comments:
Cue:
STEP Check S80 Diesel - NOT Candidate recognizes form the initial Critical: Grade
- 6 RUNNING cue that the SBO Diesel is not running. Y[]N[X] S[]U[]
GA-27, step 1 Comments: If the Candidate questions the status of the SBO Diesel, provide the following cue:
Cue: The SBO Diesel is not running.
STEP Align To Energize Auxiliaries Observes the breaker status, opens Critical: Grade
- 7 34A 1-2 at Bus 34A. Observes that the Y[X] N[] S[]U[]
GA-27, OPEN all SBO bus tie breakers indicting lights for breaker 34A 1-2 are step 2.8 green "ON", red "OFF" and the control
- Bus 34A: 34A1-2 (MB8) switch flag is green.
- Bus 34B: 34B1-2 (MB8)
- Bus 24E: A505 (Unit 2)
I----~~~ ~ ~ ~ -~~ ~
Comments: The breaker cubicle associated with Bus tie breaker 34B 1-2 has no breaker. The Candidate should recognize that Unit 2 already reported that the A505 breaker is open.
Cue:
8
STEP Locally check SSO MCC transfer Candidate contacts a PEO, dispatches Critical: Grade
- 8 switch (3SGS-TRS 1) in - him to the SSO Enclosure and directs, Y[]N[X] S[]U[]
GA-27, SACKFEEWNORMALSOURCE "Report the position of the SSO MCC step 2.b transfer switch, 3SGS-TRS 1."
Comments: SOOTH: Call the Control Room as the PEO in the SSO Enclosure and provide the following cue:
Cue: The SSO MCC transfer switch 3SGS-TRS1 is in the BACKFEED/NORMAL SOURCE position.
Comments: The substeps associated with step 3 of GA-27 are all local actions.
Cue:
I I
STEP At the SBO DIG control panel Candidate contacts the PEO in the Critical: Grade
- 9 (section 1), Start the SSO Diesel SSO Enclosure and directs, "Start the Y [ ] N [X ] S[]U[]
GA-27, SSO Diesel in accordance with step 3 step 3 of GA-27."
Comments:
SOOTH: Insert the following Remote Functions to start the SSO and close its output breaker; EGR08 to
'START' and EDR32 to 'CLOSE'. When the remotes are active, call the Control Room as the PEO in the SSO Enclosure and provide the following cue; Cue: The SSO Diesel is started and powering auxiliaries.
STEP Loading of the SSO diesel is to Candidate reviews the NOTE. Critical: Grade
- 10 preclude excessive oil going past the Y [ ] N [X ] S[]U[]
GA-27, piston rings and accumulating in the step 4 NOTE exhaust of the SSO Diesel.
Comments:
Cue: ......
9
STEP Check loading SSO diesel - The Candidate should question the US Critical: Grade
- 11 DESIRED if loading the SBO Diesel is desired. Y[]N[X] S[]U[]
GA-27, s te p 4 Comments: As the US provide the following cue; Cue: Yes, loading the SBO Diesel is desired.
STEP Align For SSO Diesel Loading Recognizes that the SBO bus tie Critical: Grade
- 12 breaker is racked up in bus 34A. Y [ ] N [X ] S[]U[]
GA-27, Check SBO bus tie breaker step S.a ALIGNED TO SELECTED NON EMERGENCY BUS Comments: The Candidate may question the US which is the selected non-emergency bus. Provide the following cue; Cue: Bus 34A is the selected non-emergency bus.
STEP OPEN NSST feeder for selected Rotates the control switch for breaker Critical: Grade
- 13 non-emergency bus (MB8) NSSA-34A-2 to the trip position. Y[] N[X] S[]U[]
GA-27, Observes the indicating flag goes to step S.b
- For Bus 34A: NSSA-34A-2 green, the amber light goes out and the green light remains lit.
Comments: Annunciator MB8A 5-9 "BUS 34A NORM SPLY AUTO TRIP" clears. The examinee should acknowledge the clearing of this alarm. However, this action is not necessary to complete this step.
Comments: Since the breaker is already open, the examinee may elect not to rotate the switch to the trip position.
Either action is acceptable to complete this step.
Cue:
10
STEP OPEN tie breaker between selected Rotates the control switch for breaker Critical: Grade
- 14 non-emergency and emergency bus 34C*1T-2 to the trip position. Y[] N[X] S[]U[]
GA-27, (MB8) Observes the indicating flag goes to s te p step S.c green, the amber light goes out and the
- For Bus 34A: 34C*1T-2 green light remains lit.
Comments: I Since the breaker is already open, the examinee may elect not to rotate the switch to the trip position.
Either action is acceptable to complete this step.
Cue:
STEP OPEN the following load center For each of the listed breakers, rotates Critical: Grade
- 15 supply breakers for selected non the control switch to the "TRI P" Y[X] N[] S[]U[]
GA-27, emergency bus: (MB8) position and observes the flags shift to step S.d green and the indicating lights shift to For Bus 34A: green "ON", red "OFF".
32A (32A-2) 32B (32B-2) 32C (32C-2) 320 (320-2) 32E (32E-2) 32F (32F-2) 32G (32G-2)
Comments: I The Candidate may elect to also open breaker SWYO/FWPH (XFMR SUPPLY /.
Cue:
STEP Align Selected Non-Emergency At MB6, positions the control switch for Critical: Grade
- 16 Bus the "A" screen wash pump (SWT-P1A) Y[X] N[] S[]U[]
GA-27, to "pull-to-Iock" and observes that all step 6.a Place the following switches in the indicating lights go out.
PULL-TO-LOCK:
- Screen wash pump
- Circulating water pumps
- TPCCW pump(s) 11
At MB6, positions the control switches Critical: Grade for the "A", "C" and "E" circulating water Y[X] N[] S[]U[]
pumps (CWS-P1A, P1C, P1E) to "pull to-lock" and observes that all of the indicating lights go out.
At MB6, positions the control switches Critical: Grade for the "A" and "C" TPCCW pumps Y[X] N[] S[]U[]
(CCS-PP1A, PP1C) to "pull-to-Iock" and observes that all of the indicating lights go out.
Comments: The switches may be operated in any order. Candidate may elect to also place the non-selected train switches in PTLIOFF in the following steps. Critical performance is satisfied as long as the selected switches are correctly positioned.
Cue:
STEP Place the following switches to At MB1, positions the control switches Critical: Grade
- 17 STOP: for COS chillers "1A" (CDS-CHLR1A) Y[X] N[] S[]U[]
GA-27, (and "1 B" if aligned) to the "stop" step 6.b
- CDS chiller{s) position and observes that the amber
- Heater drain pump(s) light goes out and the green light
- MSR drain pump remains on.
I Comments: The switches may be operated in any order.
Cue:
At MB6, rotates the control switches for Critical: Grade heater drain pumps "A" and "C" Y[X] N[] S[]U[]
(HDL-P1A, P1C) to the "stop" position and observes that the amber light goes out and the green light remains on.
12
At MB6, rotates the control switch for Critical: Grade MSR drain pump "A" (DSM-P1 A) to the Y[X] N[] S[]U[]
"stop" position and observes that the amber light goes out and the green light remains on.
Comments:
Cue:
STEP CLOSE SBC Bus Tie Breaker Rotates the control switch for breaker Critical: Grade
- 18 (MB8) To Selected Non- 34A 1-2 to the "close" position and Y[X] N[] S[]U[]
GA-27, Emergency Bus observes the flag shifts to red and the step 7 indicating lights shift to green OFF, red
- For Bus 34A: 34A 1-2 ON.
Comments: Annunciator MB8A 2-9 "BUS 34A UNDERVOLTAGE" will clear. The examinee should acknowledge the clearing of this alarm. However, this is not necessary to complete the critical nature of this step.
Cue:
STEP Increase SBC Diesel Load To Candidate contacts the PEO in the Critical: Grade
- 19 Greater Than 500 Kw SSO Enclosure and directs, "Place the Y [ ] N [X 1 S[]U[]
GA 27, START MODE switch in NORM."
step 8.a At the SBO Engine Control Panel Place the START MODE switch in NORM
--- ---~-
Comments: BOOTH: Report as the PEO in the SBO Enclosure the following cue:
Cue: The START MODE switch is in NORM.
13
STEP Check SBO diesel load (SBO DIG Candidate contacts the PEO in the Critical: Grade
- 20 Control Panel) - SBO Enclosure and directs, "Report Y[]N[X] S[]U[]
GA-27, LESS THAN 500 Kw SBO Diesel load."
step S.b Comments: BOOTH: Report as the PEO in the SBO Enclosure the following cue:
Cue: SBO Diesel load is 0 Kw.
STEP Using the load list on Table 1, Candidate refers to Table 1 in GA-27 to Critical: Grade
- 21 Energize selected load determine the appropriate load(s) to Y [ ] N [X ] S[]U[]
GA-27, energize.
step S.c Comments: Note; the only listed loads on Table 1 that are powered from non-emergency bus 34A are load centers 32E, 32G and HVT - FN2A.
Comments: The Candidate may question the US which load(s) to energize. Provide the following cue; Cue: Energize Load Center 32G.
STEP Note 3 - Open breaker 32-5G-1 M to Recognizes that Note 3 on Table 1 Critical: Grade
- 22 deenergize HVY-FN 1A before applies if energizing Load Center 32G. Y[] N[X] S[]U[]
energizing load center.
GA-27, Table 1, Note 3 Comments:
Cue:
~
14
Candidate contacts a PEO and directs, Critical: Grade "Proceed to the 'A' Service water pump Y[X] N[] S[]U[]
cubicle and open breaker 32-5G-1 M."
Comments: BOOTH: After being dispatched, call the Control Room as the PEO in the field and provide the following cue; Cue: Breaker 32-5G-1 M is open.
For load center supply breaker 32G Critical: Grade (32G-2), rotates the control switch to Y[X] N[] S[]U[]
the "CLOSE" position and observes the flags shift to red and the indicating lights shift to green "OFF", red "ON".
J Comments:
Cue: I STEP Check SSO diesel load (SBO DIG Candidate contacts the PEO in the Critical: Grade
- 23 Control Panel, section 1) - SSO Enclosure and directs, "Report Y [ ] N [X ] S[]U[]
GA-27, GREATER THAN 500 Kw SBO Diesel load."
step B.d Comments: BOOTH: Report as the PEO in the SBO Enclosure the following cue:
- j Cue: SSO Diesel load is 530 Kw
- i Candidate recognizes the SSO Diesel Critical: Grade
- is loaded greater than the required 500 Y [ ] N [X ] S[]U[]
Kw.
J Comments: I Cue: j 15
STEP Notify the SM/US the SBO Diesel is Candidate reports to US that the SBO Critical: Grade
- 24 loaded Diesel is loaded by energizing load Y[]N[X] S[]U[]
GA 27, center 32G.
step 8.e Comments:
Cue: TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ __
16
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.7 Revision: 0 chg 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it.MY.§! be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 12 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
17
STUDENT HANDOUT JPM Number: 2K11 NRC S.7 Revision: o chg 1 Initial Conditions: A turbine trip occurred and the reactor tripped. Moments later, a loss of offsite power occurred. Information indicates that offsite power will not be restored for an extended period of time. The control room team has carried out E-O immediate actions, transitioned to ES-O.1 and completed steps 1 through 7.
Initiating Cues: The US has directed you carry out step 8 of ES-O.1, Check Power To SSO Diesel Auxiliaries. The SSO is not running.
18
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Aux Bldg EI. 24'6" South Floor Area Fire (All Chg Lost/Alt Path 2)
JPM Number: 2K11 NRC S.8 (JPM-206D) Revision: 1 chg 1 Initiated:
Dave Minnich 02/25/11 Developer Date Reviewed:
Robert Royce 515/11 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE i 02/25/11 JPM updated to revision 004-03 to EOP 3509.2. Added 1 malfunctions RP09A and B (reactor trip switches fail) to modify the JPM. Added as the last step of the JPM to stop RCPs (step 21 of EOP 3509.2). Aded that the task is time i
critical to the initiating cue. Modified JPM format to be consistent with the NRC 2K11 JPM set. Deleted TR-M-410 Pass/Fail criteria. DLM 6/21/11 Added a step to the Simulator setup to prepare and have 1 /1 ready a copy of EOP 3509.2 marked up through step 14.
Added the title of EOP 3509.2 to the initiating cue. Added the approximate stroke time of 3CHS*MV8112 to the comment associated with JPM step 5. Added the specific Candidate action whereby the first critical time will end to the comment associated with JPM step 6. Incorporated as a result of NRC comments made the week of 6/13/111Prep Week}.
2
JPM WORKSHEET Facility: _M;,.;. :. :. . P-=.3_ _ __ Candidate:
JPM Number: 2K11 NRC S.8 Revision: 1 chg 1 Task
Title:
Aux Bldg EI. 24'6" South Floor Area Fire (All Chg Lost/Alt Path 2)
System: 7 - 012 Time Critical Task: (X) YES ( ) NO Validated Time (minutes): 5 Task Number(s): 000-05-172, 600-05-032 Applicable To: SRO X RO X PEO KIA APE:067 -AA2.16 KIA Rating: 3.3/4.0 Number:
Method of Testing: Simulated Actual x Performance: Performance:
Location: Classroom: Simulator: x In-Plant:
Task Standards: Satisfactorily implement EOP 3509.2, "Aux Bldg EL. 24'6", South Floor Area, 43'6" & 66'6" Fire," in response to a fire that disables all charging pumps. Time critical steps must be performed within analyzed times.
All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Required Materials: EOP 3509.2 (procedures, equipment, etc.) MP3 Simulator General
References:
EOP 3509.2, "Aux Bldg EL. 24'6", South Floor Area, 43'6" & 66'6" Fire",
Revision 004-03 3
- READ TO THE CANDIDATE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC S.8 Revision : 1 chg 1 Simulator Requirements: Reset to IC 287 ..... OR
- 1. Reset to any 100% power IC.
- 2. Insert 1/0 [CV] 3CHS*MV8112 red "ON" (CVL00072)
- 3. Insert malfunctions RP09A and B.
Placekeep a copy of EOP 3509.2, up through step 14 for the Candidate.
Place simulator in "RUN" after the operator receives instructions Initial Conditions: A fire is in progress in the Auxiliary Building 24'6" South Floor area. The control room team is implementing EOP 3509, Fire Emergency, and EOP 3509.2, Aux Bldg EL. 24'6", South Floor Area, 43'6" & 66'6" Fire. The Fire Brigade Adviser has just reported probable fire involvement of all charging pumps is expected.
Initiating Cues: The US has directed you to perform EOP 3509.2, Aux Bldg EL. 24'6", South Floor Area, 43'6" & 66'6" Fire, beginning with step 15 (Isolate ReS). This is a time critical task.
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "yn. For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary. question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K11 NRC S_8 Revision: 1 chg 1 Task
Title:
Aux Bldg EI. 24'6" South Floor Area Fire (All Chg Lost/Ait Path 2)
START TIME: _ _ __
PERFORMANCE STEP STANDARD STEP Obtains copy of EOP 3509.2. Candidate obtains a copy of EOP Critical: Grade
- 1 Y[]N[X] S[]U[]
3509.2, refers to Step 15.
Comments:
Cue: 1 STEP Isolate ReS Depresses the CLOSE pushbutton for Critical: Grade
- 2 Y[X] N[] S[]U[l 3CHS*AV8149C (or AV8149B if in CLOSE letdown orifice isolation 3509_2. service) and observes valve closes by valves step red indicating light OFF, green ON.
15 _a Comments:
Cue: 1I STEP
- 3 Verify excess letdown and reactor Verifies that 3RCS*SV8095A1B and Critical:
Y[] N[Xl Grade S[]U[]
1 head vent isolation valves 3RCS*SV8096A1B are closed by 3509.2. observing the indicating lights green 5 te p CLOSED 15 _b ON, red OFF.
1 I
Comments:
I Cue: ,
-- -- -- -- --- 1 5
Verifies that 3RCS*AV8153 is closed Critical: Grade by observing the indicating lights green Y[] N[X] S[]U[]
ON, red OFF.
I, Comments: Other valves in the flowpath can be checked closed as well.
Cue:
STEP STOP all charging pumps and Place Rotates 3CHS*P3B control switch to Critical: Grade
- 4 all charging pump control switches in stop, confirms running charging pump Y[X] N[] S[]U[]
3509.2, step PULL---TO---LOCK has stopped, and places all charging
- 15. C pump control switches in PULL---TO--
LOCK.
Comments: ,
Cue:
STEP CLOSE RCP seal leakoff Depresses close pushbutton for Critical: Grade
- 5 3CHS*MV8112 and observes red open Y [ ] N [X ] S[]U[]
3509.2, containment inner isolation valve step (3CHS*MV8112) indication does not extinguish.
1 5. d Transitions to RNO column Comments: NOTE; The stroke time of 3CHS*MV8112 is long - about 45 seconds.
Cue:
STEP CLOSE RCP seal leakoff Depresses close pushbutton for Critical: Grade
- 6 3CHS*MV8100 and observes valve Y[X] N[] S[]U[]
3509.2, containment outer isolation valve step (3CHS*MV81 00) closes by red indicating light OFF,
- 15. d green ON.
RNO Comments: *Time (ends as soon as Candidate depresses 3CHS*MV8100 close pushbutton) must be.:5 5 minutes from JPM start for SAT grade. Time:
Cue:
--- --~
.. ....... .. ... .. --~
6
STEP
- 00 NOT Go To E-O, Reactor Candidate reviews the NOTES. Critical: Grade
- 7 Trip or Safety Injection Y[] N[X] S[]U[]
3509 2,
- The reactor can be interpreted step 16 as "tripped" when any two of the NOTES three bullet substeps of step 17.
are satisfied Comments:
Cue:
STEP TRIP The Reactor AND Remain In Rotates the reactor trip switch on MB4 Critical: Grade
- 8 Y[] N[X] S[]U[]
3509.2.
This Procedure to the "trip" position.
I step 16 I Comments:
Cue:
STEP Verify Reactor Trip Observes that the reactor trip breakers Critical: Grade
- 9 are closed, no rod bottom lights are lit Y[]N[X] S[]U[]
- Check reactor trip and bypass and that reactor power is not 3509.2. breakers - OPEN decreasing. The reactor is not tripped.
step 17
- Check rod bottom lights - LIT
- Check neutron flux Shifts to the actions required in the DECREASING RNO.
Comments:
Cue:
STEP TRIP the reactor. Rotates the reactor trip switch on MB7 Critical: Grade
- 10 to the "trip" position. Observes that the Y[ J N[X] S[]U[]
3509.2, step 17 IF reactor will NOT trip, reactor trip breakers are closed, no rod RNO THEN bottom lights are lit and that reactor power is not decreasing. The reactor TRIP Bus 32B and 32N. is still not tripped.
Comments:
Cue:
7
STEP Proceeds to MB8 and rotates the Critical: Grade
- 11 supply Breaker switches for load Y[X]N[ ] S[]U[]
centers, 32B & 32N to the "open" positions.
Comments: All 4 breakers {high side and low side supply breakers} need not be operated.
Comments: *Time must be < 10 minutes from JPM start for SAT grade. Time:
Cue:
STEP Observes that all rod bottom lights are Critical: Grade
- 12 lit and that neutron flux is decreasing. Y[] N[X] S[]U[]
The reactor is tripped.
Comments:
Cue:
STEP Dispatch an operator to locally TRIP Either contacts the PEO or requests Critical: Grade
- 13 the reactor trip and bypass breakers. the US contact the PEO to locally trip Y[] N[X] S[]U[]
the reactor trip and bypass breakers.
Proceeds to step 18.
Comments: If requested, as the US provide the following cue:
Cue: A PEO has been dispatched to trip the reactor trip breakers.
STEP Verify Turbine Trip Verifies turbine tripped by checking the Critical: Grade
- 14 Y[] N[X] S[]U[]
3509.2, stop valve meter indications on the step 18 Check all turbine stop valves EHC insert on MB7 and observes that CLOSED all of the turbine stop valves are closed.
Comments:
I Cue: ------ ----- ---- -----
8
STEP Verify Power To AC Emergency Checks voltage indication for either bus Critical: Grade
- 15 34C or 340 on MB8 and observes that Y[] N[X] S[]U[]
3509.2, Busses step voltage is present. Both busses 34C
- 19. a and 340 are energized.
Check busses 34C and 340 AT LEAST ONE ENERGIZED Comments:
Cue:
STEP Check busses 34C and 340 Checks voltage indication for busses Critical: Grade
- 16 BOTH ENERGIZED 34C and 340 on MB8 and observes Y[] N[X] S[]U[]
3509.2, step that voltage is present. Both busses
- 19. b 34C and 340 are energized.
Comments:
Cue:
STEP CLOSE The MSIVs And MSIV Candidate locates on MB5 and rotates Critical: Grade
- 17 Bypass Valves the control switch for the 'A', 'B', 'C' Y[X] N[] S[]U[]
3509.2, and 'OJ S/G MSIVs (3MSS*CTV27A-D) step 20 to the "close" position and observes the indicating lights shift to green ON, red OFF.
Comments: *Time must be ~ 11 minutes from JPM start for SAT grade Time:
Cue:
Candidate verifies the MSIV bypass Critical: Grade valves are closed by observing the Y[] N[X] S[]U[]
indicating lights are green ON, red OFF.
Comments:
Cue: - --- -- --
9
STEP STOP all RCPs Candidate locates on MB4 and rotates Critical: Grade
- 18 the control switches for the 'A', '8', 'C' Y[X] N[] S[]U[]
3509.2, step 21 and '0' RCPs to the stop position observes the indicating lights shift to green ON, red OFF and/or ReS loop flow decrease.
Comments:
Cue: TERMINATION CUE: The evaluation for this JPM is concluded.
STOP TIME: _ _ __
10
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC S.B Revision: 1 chg 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? YES X NO Validated Time (minutes):
OCA: Req. Actual
- 1) Isolate Letdown 5min
- 2) Trip Reactor 10 min
- 3) Close MSIV's & Bypass Valves 11 min Result of JPM: ("S" for satisfactory, "U" for unsatisfactory)
Result of oral questions (if applicable):
Number of Questions:
Number of Correct Responses:
Score:
Areas for Improvement I Comments:
11
STUDENT HANDOUT JPM Number: 2K11 NRC S.8 Revision: 1 chg 1 Initial Conditions: A fire is in progress in the Auxiliary Building 24'6" South Floor area.
The control room team is implementing EOP 3509, Fire Emergency, and EOP 3509.2, Aux Bldg EL. 24'6", South Floor Area, 43'6" &
66'6" Fire. The Fire Brigade Adviser has just reported probable fire involvement of all charging pumps is expected.
Initiating Cues: The US has directed you to perform EOP 3509.2, Aux Bldg EL.
24'6", South Floor Area, 43'6" & 66'6 Fire, beginning with step 15 11 (Isolate ReS). This is a time critical task.
12
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Remove Service Water Cubicle Sumps From Service JPM Number: 2K11 NRC P.1 ( .IPIVI-191) Revision: 2
~_7/_12/1_1 Initiated:
Dave Minnich _
Developer Date Reviewed:
r I Date Approved:
Supervisor, Nuclear Imn9 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 02125/11 Verified updated to Rev 013-04 of OP3335B. Modified JPM 1/0 format to be consistent with the NRC 2K11 JPM set. Deleted TR-AA-410 Pass/Fail criteria. DLM 7112/11 Verified updated to Rev 013-07 of OP33358. Removed the 2/0 alternate path to replace 3PBS-P1B with spare pump (OP 33358 steps 4.2.1.b.4 and 5). This JPM is a complete replacement JPM for 2K11 NRC P.1, Revision 1. change 1.
2
JPM WORKSHEET Facility: .....;M~P3~_ __ Examinee:
JPM Number: 2K11 NRC P.1 Revision:
2 Task
Title:
Remove Service Water Cubicle Sumps From Service System: 4.2 - 076 (Service Water)
Time Critical Task: ( ) YES (X) NO Validated Time (minutes): 10 Task Number(s): 069-01-001, 344-05-026 Applicable To: SRO X RO X PEO X KIA Number: GEN 2.4.35 KIA Rating: _ _ _ 3 ...,;.8_'_4_.0_ _
Method of Testing: Simulated x Actual Performance: Performance:
Location: Classroom: Simulator:
--- In-Plant: X Task Standards: Remove Service Water Cubicle Sumps from Service All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Required Materials: OP 33358. section 4.2.1.
(procedures, eqUipment, etc.)
General
References:
OP 33358, Reactor Plant Aerated Drains Rev. 013-07 3
- - READ TO THE EXAMINEE ***
I will explain the initial conditions, which step{s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including Jogs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed..
JPM WORKSHEET JPM Number: 2K11 NRC P.1 Revision: 2 Initial Conditions: A Hurricane Warning has been issued for the SE Connecticut area.
Winds in excess of 90 mph are expected within the next 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
The Control Room Team is performing the actions of AOP 3569, Severe Weather Conditions.
Initiating Cues: The US has directed you to remove the service water cubicle sumps from service using OP 33358, section 4.2.1.
Simulator Requirements: NONE
". ". ".
- NOTES TO TASK PERFORMANCE EVALUATOR'" * * ,..
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K11 NRC P.1 Revision: 2 Task
Title:
Remove Service Water Cubicle Sumps From Service START TIME: _ _ __
PERFORMANCE STANDARD STEP IF removing Service Water Pump Candidate enters the "A" SelVice Water Critical:
- 1 Cubicles Subsystem from service, Pump cubicle and locates storage box. Y[ ]
PERFORM the following: N[X]
OP 3335B 4.2.1.a.1 )
To place 3PBS-sump 1A in severe weather mode, PERFORM the following:
Obtain dedicated extension cord and drain pipe threaded cap from storage box near sumo.
Comments: I Once storage box is located and opened, provide the following cue:
Cue: 1ft' Ie h9tri~¢~*~~~rY,tq.r~~9y~]tL~~::~~~r,r,~i§,:ry;ffitg'!~dq't~Rif~,Qm;;!:~'~':~!Bf~Q~'~g~l':
,'::i.:
STEP
- 2 OP 3335B 4.2.1.a.2)
Comments:
Cue:Tne i'='~,'~~~~~~~~~~'~"~'~""""~'~~
5
STEP VERIFY sump pump operates by Lifts float arm momentarily. Critical: Grade
- 3 momentarily lifting the float arm Y [ Jt S[]
OP 3335B N[X] U[ 1 4.2.1.a.3)
Comments: Steps 4.2.1.a.(4) and (5) not required as pump operates Cue:
STEP Places drain cap over sump drain pipe
- 4 and installs by spinning in the clockwise OP 3335B direction 4.2.1.a.6}
Comments: 1..,-1~,..",..",...,-.."..,..,.,,.,..
Cue:
STEP To place 3PBS-sump1B in severe Candidate enters the "B" Service Water
- 5 weather mode, PERFORM the following: Pump cubicle and locates storage box.
OP 3335B 4.2.1.b.1) Obtain dedicated extension cord and drain pipe threaded cap from storage box near sump Comments: I Once storage box is located and opened, provide the following cue:
Cue:
.It*', js.n.0t. nec~.s~~~::t.O'*jfTo:v~!:~~~:~m~~:~i~~*',.~r~,:.~p~,:,.~~iB;:rt9W'.
STEP PLUG-IN 3PBSwP1 B using extension cord
- 6 to the special receptacle on the side of OP 33358 4.2.1.b.2) 3LAW-PNL3CW2P Comments:
Cue: ... .. . .....,.=.. ~,...~".... ..,..... ., ,. ,. ,:;-;:
1-:1:=:"""""""=~=-":-,,~,,::-:-,"~,'7"'"~~~===~""".,..i"""""""'''~~"..""'. . .....,.~. .".. . .,.:c':"""~,.,.....,."~,.. ~=~.......,.."~~~~.,,.,...,.,......,.....,......,....,....,-~,..,,...,,.d,,1 6
STEP VERIFY sump pump operates by Lifts float arm momentarily. Critical: Grade
- 7 momentarily lifting the float arm Y[ ] S[]
OP 3335B N[X] U[ ]
4.2.1.b.3)
Comments: teps 4.2.1.b.(4) and (5) not required as pump operates Cue:
STEP
- 8 drain cap threaded cap I
ISOLATE 3PBS-sump 1B drain by installing Places drain cap over sump drain pipe and installs by spinning in the clockwise OP3335B 4.2.1.b.6) direction.
Comments:
Cue: 1-:::1.,~.,~,.,.=,,,,,,,=
...,,,=,.
STEP
- 9 Comments:
Cue:
STOP TIME: _ _ __
7
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 N~C P.1 Revision: 2
-~-.
Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, Abb critical steps must be completed correctly. If task is Tim~
Critical, it l!Y§I be completed within the specified time to achieve a satisfactory grade. ---.J Time Critical Task? Yes No X Validated Time (minutes): 10 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
8
STUDENT HANDOUT
..IPM Number: 2K11 NRC P.1 Revision: 2 Initial Conditions: A Hurricane Warning has been issued for the SE Connecticut area.
Winds in excess of 90 mph are expected within the next 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
The Control Room Team is performing the actions of AOP 3569, Severe Weather Conditions.
Initiating Cues: The US has directed you to remove the service water cubicle sumps from service using OP 3335B. section 4.2.1.
9
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Primary Side PEG Actions on a Control Room Evacuation (Part 2)
,JPM Number: 2K11 NRC P.2 ( JPM-011A) Revision: 1 chg 1 Initiated:
Dave Minnich 2/28/11 Developer Date Reviewed:
Robert Royce 5/5/11 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 02/25/11 Verified updated to Rev 013 of EOP 3509.1. lVIade JPM step 1 1()
6 (Place breaker 32-4U-R5H to OFF). non-critical based on the NOTE prior to ATT A step 8. Modified ...IPM format to be consistent with the NRC 2K11 JPM set. Deleted TR-AA-41 0 PasslFail criteria. DLM 06/17/11 Increased validated time from 20 to 30 minutes based on 1 1 11 validation walkdown. Added an OPS Locked Door Key to the list of required materials. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility: _M_P_3_ _ __ Examinee:
JPIVI Number: 2K11 NRC P.2 Revision: _...;.1...;.C_h9",,--1_
Task
Title:
Primary Side PEO Actions on a Control Room Evacuation (Part 2)
System: 6 - 062 Time Critical Task: ) YES (X) NO Validated Time (minutes): _ _.. .:.3. :;.0_ _
Task Number(s): 069-01-001,344-05-026 Applicable To: SRO X RO X PEO X KIA Number: 062-A4.04 KIA Rating: 2.6/2.7 APE-068-AA1.14 4.2/4.4 APE-068-AA1 .10 3.7/3.9 Method of Testing: Simulated X Actual Performance: Performance:
Location: Classroom: Simulator: In-Plant: X Task Standards: Satisfactorily complete primary side PEO actions on a control room evacuation lAW 3509.1 Att. A, steps 6 -11 All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Reguired Materials: EOP 3509.1, Attachment A, rev. 013 (procedures, equipment, etc.)
OPS Locked Door Key General
References:
EOP 3509.1, Control Room, Cable Spreading Area Or Instrument Rack Room Fire, Attachment A, rev. 013 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET
..IPM Number: 2K11NRCP.1 Revision: 1 chg 1 Initial Conditions: A fire event has occurred requiring shut down outside the control room. The control room team is carrying out actions of EOP 3509.1, Control Room, Cable Spreading Area, or Instrument Rack Room Fire.
Initiating Cues: The US directs you to perform primary side PEO actions on a control room evacuation lAW EOP 3509.1, Attachment A, steps 6 through 11 only, after referring to the "Appendix "R" Lighting Illuminated Path" maps at the end of the attachment.
Another operator is performing steps 1 through 5. You have the locked valve key.
Simulator Requirements: NONE
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPIVI are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the student be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K11 NRC P.2 Revision: 1 chg 1 Task
Title:
Primary Side PEO Actions on a Control Room Evacuation (Part 2)
START TIME: _ _ __
PERFORMANCE STANDARD Comments: Direction to refer to maps is step 1 of Attachment A and was included as part of initiating cue. Examinee may elect to review all steps prior to step 6.
STEP Refer to "Appendix R" Lighting Illuminated Candidate locates maps at end of Critical: Grade
- 1 Path" maps at end of attachment prior to attachment and reviews. Y[ ] S[ ]
performing local actions. N[X] U[ ]
3509.1, Att A step 1 Comments: When examinee reviews maps provide the following cue Cue: Adequate emergency lighting is in operation to allow the use of normal access/egress paths.
STEP Verify Reactor Tripped Locates reactor trip breakers, Critical: Grade
- 2 3RPS*SWGR-1 & -2] [West MCC*SWGR, Y[X] S[ ]
Check Reactor Trip and Bypass Breakers - Aux Bldg 46'] N[X] U[ ]
3509.1, Att A step 6.a OPEN Comments:
Cue:
Locates OPEN / CLOSED position Critical: Grade indicating flags for each breaker and Y[X] S[ ]
determines TRIP breakers indicate N[ ] U[ ]
CLOSED.
I Proceeds to RNO column.
5
Evaluator Show the picture of the inside of the reactor trip and bypass breaker cabinets so the candidate can i NOTE: determine that the reactor trip breaker flags indicate CLOSED and the bypass breakers indicate OPEN. .
Cue (if You see the reactor trip breaker CLOSED flags and the bypass breaker OPEN flags.
- required):
STEP TRIP the reactor trip and bypass breakers. Locates red TRIP push button (PB) and Critical: Grade
- 3 simulates pushing TRIP PB. [RNO Y[X] S[ ]
direction]. N[ ] U[ ]
AttA step 6.a RNO Locates breaker flag indication; both trip Critical: Grade breakers are OPEN. Y[ ] S[ ]
N[X] U[ ]
Evaluator Show the picture of the inside of the reactor trip breaker cabinet so the candidate can determine that the NOTE: Breaker TRI PIOPEN flag is visible.
The RNO must be performed.
Cue (if You see the reactor trip breaker TRIPIOPEN flag.
required):
STEP Block Open Auxiliary Building North Locates North doors A-24-2 [inner] & A- Critical: Grade
- 4 Doors to Outside on EI. 24'-6" 24-1 [outer] and simulates propping Y[X] S[ ]
BOTH doors open - applicant explains N[ J U[ ]
AttA step 7 Door A-24-1 method and component(s) used to Door A-24-2 achieve blocking OPEN.
Cue: You have material to block the doors open.
Comments: As each door is simulated blocked open, provide the following cue:
6
Cue: The door is blocked open.
STEP NOTE: Opening the breaker for Reviews the note prior to step 8. Critical: Grade
- 5 3MSS*MOV 17A at 32-4U-R5H is not an Y[ ] S[ ]
Appendix "Rn required action. If there is no N[X] U[ ]
AttA Step 8 NOTE lighting available to access this area the action is not required.
Comments: If examinee questions the status of lighting, provide the following cue:
Cue: Adequate emergency lighting is in operation to allow access in this area.
Comments: The following breakers may be operated in any order.
STEP De-energize TO AFW Pump Steam Locates breaker R5H on MCC 32-4U Critical: Grade
- 6 Supply Isolation Valves (ESF Bldg 36') and simulates placing the Y[ ] S[]
breaker in the OFF position N[X] U[ ]
AttA step 8
- For 3MSS*MOV17A, Place breaker [3MSS*MOV17 A].
32-4U-R5H to OFF
- For 3MSS*MOV17B, Place breaker 32-4T-R6E to OFF
- For 3MSS*MOV17D, Place breaker 32-4T-R6H to OFF STEP Locates breaker R6E on MCC 32-4T Critical: Grade
- 7 (ESF Bldg 36') and simulates placing the Y[X] S[ ]
breaker the OFF position N[ ] U[ ]
[3MSS*MOV17B]
7
STEP Locates breaker R6H on MCC 32-4T Critical: Grade
- 8 (ESF Bldg 36') and simulates placing the Y[X] S[ ]
breaker in the OFF position N[ ] U[ ]
[3MSS*MOV17D]
Comments: As each breaker is located, provide the following cue:
Cue: Breaker as-found is ON/CLOSED.
Comments: As each breaker is simulated operated, provide the following cue:
Cue: Breaker is in the OFF position.
STEP Block Open TO AFW Pump Cubicle Simulates blocking open the TD AFW Critical: Grade
- 9 Doors pump area outside door and the door to Y[X] S[ ]
MOV17 A, B & D - student explains N[ ] U[ ]
AttA step 9 Door SF-24-1 method and component(s) used to Door SF-24-2 achieve blocking OPEN.
Cue: You have material to block the doors open.
Comments: As each door is simulated blocked open, provide the following cue:
Cue: The door is blocked OPEN.
Comments: Location for steps 10 - 12 is ESF Bldg. TD AFW pump valve room 24'. The position of the 3MSS*MOV17 valves may be checked in any order.
8
STEP Verify TD AFW Pump Steam Isolation Locates valve 3MSS*MOV17A and Critical: Grade
- 10 Valves - OPEN Y[ ] S[ ]
checks the position indicator (rod).
N[X] U[ J AttA step 10 3MSS*MOV17A OR 3MSS*MOV17B Manually checks valve position by 3MSS*MOV170 engaging the manual handwheel.
Checks SG A TO AFW Pump Non-Return Valve 3MSS*MOV17A OPEN.
Comments:
Cue: Stem position rod is as you see it.
(---THIS STEP IS COMPLETE---)
OR Cue: The MOV clutch is disengaged.
Rotates the handwheel in the clockwise Critical: Grade direction to confirm the valve is open. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue: Valve handwheel rotates in the clockwise direction.
Rotates the handwheel in the Critical: Grade counterclockwise direction until the valve Y[ ] S[ ]
is fully open. N[X] U[ ]
Comments:
- Cue: Valve handwheel rotates briefly in the counterclockwise direction, resistance is met and the valve comes to a hard stop.
9
STEP Locates valve 3MSS*MOV17B and Critical: Grade
checks the position indicator (rod).
Valve 3MSS*MOV17B OPEN. N[X] U[ ]
OR Manually checks valve position by engaging the manual handwheel.
Comments:
Cue: Stem position rod is as you see it.
(---THIS STEP IS COMPLETE---)
OR Cue: The MOV clutch is disengaged.
Rotates the handwheel in the clockwise Critical: Grade direction to confirm the valve is open. Y[ ] S[ ]
N[Xl U[ 1 Comments:
Cue: Valve handwheel rotates in the clockwise direction.
Rotates the handwheel in the Critical: Grade counterclockwise direction until the valve Y[ ] S[ ]
is ful!y open. N[X] U [] I Comments:
Cue: Valve handwheel rotates briefly in the counterclockwise direction, resistance is met and the valve comes to !
a hard stop. I STEP Locates valve 3MSS*MOV170 and Critical: Grade I
checks the position indicator (rod).
Valve 3MSS*MOV170 OPEN. N[X] U[ ]
OR Manually checks valve position by engaging the manual handwheel.
Comments:
10
Cue: Stem position rod is as you see it.
---THIS STEP IS COMPLETE--
OR Cue: The MOV clutch is disengaged.
Rotates the handwheel in the clockwise Critical: Grade direction to confirm the valve is open. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue: Valve handwheel rotates in the clockwise direction.
Rotates the handwheel in the Critical: Grade counterclockwise direction until the valve Y[ J s[]
is fully open. N[X] U[ ]
Comments:
Cue: Valve handwheel rotates briefly in the counterclockwise direction, resistance is met and the valve comes to a hard stop.
STEP Perform the Following: Candidate locates phone, sound-powered Critical: Grade
- 13 phone or walkie-talkie and simulates Y[ ] S[]
Establish communication with the ASP establishing communication with ASP N[X] U[ ]
AttA step 11 operator operator.
Report Attachment A complete Provide support as required Simulates communicating Attachment A Critical: Grade steps 6 through 11 are complete. Y[ ] S[]
N [X] I u[ ]
I I I 11
"'0 (I)
"'0
- J 13 c:
8
.~
N
~ .
a..
.~
.c
.e c:
0 ttl
- J m>
(I)
(I)
.c l
CI)
- s
(.)
en c
+=RS
.-S C
CI)
I w
iri ~
- J 0 I 0...
0 I-Cf)
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC P.2 Revision: 1 c:hg 1 Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, ALL critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 30 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
13
STUDENT HANDOUT JPM Number: 2K11 NRC P.2 Revision: 1 chg 1 Initial Conditions: A fire event has occurred requiring shut down outside the control room. The control room team is carrying out actions of EOP 3509.1, Control Room, Cable Spreading Area, or Instrument Rack Room Fire.
Initiating Cues: The US directs you to perform primary side PEO actions on a control room evacuation lAW EOP 3509.1, Attachment A, steps 6 through 11 only, after referring to the "Appendix "R" Lighting Illuminated Path" maps at the end of the attachment. Another operator is performing steps 1 through 5. You have the locked valve key.
14
JOB PERFORMANCE MEASURE APPROVAL SHEET JPM
Title:
Spent Fuel Pool Emergency Make Up JPM Number: 2K11 NRC P.3 ( JPM-016) Revision: 8 chg 1 Initiated:
Dave Minnich 03/01/11 Developer Date Reviewed:
Robert Royce 515/11 Technical Reviewer Date Approved:
L. Armstrong 5/11/11 Supervisor, Nuclear Training Date 1
SUMMARY
OF CHANGES DATE DESCRIPTION REV/CHANGE 03/01/11 Verified updated to Rev 008-02 of EOP 3505A. Modified the 8/C>
standard for 'Align discharge of gooseneck into the spent fuel pool'. to have the examinee describe the method used. Made the first two standards of JPM step 15 (3SWP*V30 locking device removal and wingnut loosened) non-critical. Modified JPM format to be consistent with the NRC 2K11 JPM set.
Deleted TR-AA-410 Pass/Fail criteria. DLM 06/17/11 Increased validated time from 15 to 25 minutes based on 8n validation walkdown. Modified ..IPM step 14 comment to delete the statement about obtaining a ladder. Scaffolding has been installed. Specified that it is not required to climb the installed scaffolding to reach SWP*V700. Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
2
JPM WORKSHEET Facility:
-I\IIP3
Examinee:
JPM Number: 2K11 NRC P.3 Revision: 8 chg 1 Task
Title:
Spent Fuel Pool Emergency Make Up System: 8 - 033 Time Critical Task: ) YES (X) NO Validated Time (minutes): 25 Task Number(s): 344-05-042 Applicable To: SRO X RO X PEO X KiA Number: 033.A2.03 KiA Rating: _ _..:;. ;3.;. .:. 1. :.-'-=.3: .;:.5_ _
Method of Testing: Simulated X Actual Performance: Performance:
Location: Classroom: Simulator: In-Plant: X Task Standards: Satisfactorily complete emergency make up to the spent fuel pool using EOP 3505A.
All critical steps are performed satisfactorily. All sequential steps are performed in proper procedural sequence.
Required Materials: PEO Rounds Key (procedures, equipment, etc.) EOP 3505A, Rev. 008-02 General
References:
EOP 3505A, Loss of Spent Fuel Pool Cooling, Rev. 008-02 3
- READ TO THE EXAMINEE ***
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this JPM will be satisfied. You may use any approved reference material normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgements, and log entries as if the evolution was actually being performed.
JPM WORKSHEET JPM Number: 2K11 NRC P.3 Revision: 8 chg 1 Initial Conditions: A loss of all AC power occurred and the control room team is carrying out actions of EOP 35 ECA-O.O.
The spent fuel pool low level alarm has been received and, due to a loss of all AC power, the normal method of make-up is not available.
Additionally, 3SFC-V31, RWST to fuel pool isolation valve, is stuck closed.
Initiating Cues: While maintenance works on 3SFC-V31, the US directs you to make up to the spent fuel pool using the emergency method of EOP 3505A starting with Attachment A, Step 9.
The OMOC has granted permission to perform this step.
Simulator Reguirements: NONE
- * *
- NOTES TO TASK PERFORMANCE EVALUATOR * * * *
- 1. Critical steps for this JPM are indicated by checking "Y". For the student to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When the student states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question student for details of simulated actions/observations (Le. "What are you looking at?" or "What are you observing?").
i 4. Under NO circumstances must the student be allowed to manipulate any devices during the I performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM Number: 2K11 NRC P.3 Revision: 8 chg 1 Task
Title:
Spent Fuel Pool Emergency Make Up START TIME: _ _ __
PERFORMANCE STANDARD Comments: If at any time during this JPM, the candidate checks fuel pool level indication or requests level information from the Control Room, provide the following cue:
Cue: Spent Fuel Pool level is 34%.
STEP Locally Establish Emergency Makeup To Candidate recognizes form the initial cue Critical: Grade
- 1 The Spent Fuel Pool From The Fire that the OMOC granted permission to Y[ J S[ J Protection Water System perform this step. N[X] U[ J 3505A, AttA step 9.a Check OMOC -- AUTHORIZES USE OF FIREWATER Comments: If the Candidate questions OMOC authorization, provide the following cue:
Cue: The OMOC authorizes use of fire water.
STEP Check radiation levels at spent fuel pool - Candidate requests HP coverage to Critical: Grade
- 2 ACCEPTABLE check radiation levels at the spent fuel Y[ ] S[ ]
pool to determine if they are acceptable. N[X] U[ ]
AltA step 9.b Comments: When examinee requests HP coverage to check radiation levels, provide the following cue:
Cue: HP conducts a survey and determines the fuel pool area is accessible, highest readings are 6 mr/hr.
5
STEP In the spent fuel pool area Perform the Locates emergency supply connection Critical: Grade
- 3 vent (EL 51 '6") and simulates rotating Y[ ] S[ ]
following:
valve handwheel in counter clockwise N[X] U[ ]
AttA step 9.c.1) direction until valve is open.
Vent the fire protection water system connection using the fuel pool emergency supply connection vent (3FPW-V1355)
Cue: 3FPW-V1355 handwheel rotates in the counter clockwise direction until resistance is felt and handwheel no longer rotates, valve is open. There is no flow out of the vent.
Closes vent when completed venting. Critical: Grade Y[ ] S[ ]
N [Xl U[ ]
Cue: Valve hand wheel rotated in the clockwise direction until hard stop.
Comments: The procedure step only states to vent the connection.
STEP Connect emergency makeup gooseneck Locates emergency make up gooseneck Critical: Grade
- 4 to the fire protection water system (EL 51 '6") and simulates connecting Y[ ] S[ ]
connection gooseneck to fire protection water N[X] U[ ]
AttA step 9.c.2) system.
Comments:
Cue: Emergency make up gooseneck is connected to the fire protection water system.
6
STEP Align discharge of gooseneck into the Candidate should describe how he/she Critical: Grade
- 5 spent fuel pool would align the gooseneck to ensure its Y[ ] S[ ]
discharge is to the spent fuel pool. N[X] U[ ]
AttA step 9.c.3)
Comments:
Cue: Emergency make up gooseneck is aligned to discharge into the spent fuel pool.
STEP OPEN fire protection water system supply Locates supply valve 3FPW-V766 (Fuel Critical: Grade
- 6 to fuel pool (3FPW-V766) located in Fuel Bldg. EI. 51 '6" by the Fuel Pool). Y[ ] S[ ]
Building 51' Simulates rotating the handwheel for N[X] U[ ]
AttA step 9.d 3FPW-V766 in the counter-clockwise direction until the valve is open.
Cue: Valve hand wheel rotates in counter-clockwise direction - Eventually, some resistance is met and the valve comes to a stop.
Simulates rotating valve hand wheel Y4 Critical: Grade turn in the clockwise direction. Y[ ] S[ ]
N[X] U[ ]
Cue: The valve hand wheel is rotated Y4 turn in the clockwise direction.
STEP Check spent fuel pool level -- Checks for water flow out of gooseneck Critical: Grade
- 7 INCREASING into fuel pool. Y[ ] S[ ]
N[X] U[ ]
AttA step 9.e Comments:
Cue: No flow is visible from the gooseneck.
Transitions to RN.O. column. Critical: Grade Y[ ] S[ ]
N[X] U[ ]
7
STEP Critical: Grade
- 8 Perform the following: Y[ ] S[ ]
N[X] U[ ]
Atl A step9.e RNO Direct fire water into the spent fuel pool from the following sources as necessary utilizing the connected hose and if necessary connect a hose to the fire department connections:
Hose rack #69 Hose rack #94 Site fire pumper Comments: When the Candidate initiates action to rig another fire water source, provide the following cue:
Cue: The Control Room informs you that the fire water system is not pressurized, and other personnel have been dispatched to the fire pumper. The Control Room has obtained OMOC permission to establish make up to the fuel pool from the service water system and you are to close 3FPW-V766 and proceed to Step 10.
STEP Close 3FPW-V766 Simulates rotating hand wheel in the Critical: Grade
- 9 clockwise direction and locking valve. Y[ ] S[ ]
N[X] U[ ]
Comments:
Cue: Valve hand wheel rotates in clockwise direction - Eventually, some resistance is met and valve hand wheel comes to a hard stop_
Candidate proceeds to STEP 10 in Critical: Grade Attachment A. Y[ ] S [] I NJX] U[J 8
STEP Locally Establish Emergency Make Up Candidate recognizes that the Control Critical: Grade
- 10 to Spent Fuel Pool from the Service Room has obtained OMOC permission to Y[ ] S[ ]
Water System use the service water system, based on a N[X] U[ ]
AttA step 10.a previous cue.
Check the following:
- OMOC - AUTHORIZES USE OF SERVICE WATER
- Service water pump A or C RUNNING Calls Control Room to verify either Critical: Grade service water pump A or C is running. Y[ ] S[ ]
N[X] U[ ]
Comments: When the Candidate simUlates calling the Control Room, provide the following cue:
Cue: The Unit Supervisor informs you that the SBO Diesel has been started and placed on bus 34C. The "A" service water pump is running.
STEP Check service water supply to fuel pool Locates 3SWP*V30 (Fuel Bldg EI 24', fuel Critical: Grade
- 11 (3SWP*V30) located in Fuel Building 24' - receiving bay) and checks valve closed Y[ ] S[ ]
CLOSED by observing handle is not in the in-line N[X] U[ ]
AttA step 10.b ~osition.
Comments: When the Candidate checks the position of 3SWP*V30, provide the following cue:
Cue: Valve handle is perpendicular to the pipe.
STEP In the spent fuel pool area Perform the Locates the service water fuel pool blank Critical: Grade
- 12 following: flange vent (EL 51 '6") and simulates Y[X] S[ ]
rotating valve handwheel in counter N[ ] U[ ]
AttA step 1 O.c.1) Vent the service water system clockwise direction until valve is open.
connection using the fuel pool blank flange vent (3SWP*V741 )
9
Comments:
Cue: 3SWP*V741 handwheel rotates in the counter clockwise direction until resistance is felt and handwheel no longer rotates, valve is open. There is no flow out of the vent.
Closes vent when completed venting. Critical: Grade Y[ ] S[ ]
N[X] U[ ]
Cue: Valve hand wheel rotated in the clockwise direction until hard stop.
Comments: To complete the next step, the Candidate needs some tools. It is not necessary that these tools be obtained, however have the candidate explain where he/she obtains the tools.
STEP Remove blank flanges (2) and Install Locates spool piece, simulates unbolting Critical: Grade
- 13 spool piece in service water line to spent flanges and bolting spool piece into the Y[X] S[ ]
fuel pool service water line (Fuel Bldg EI 43' above N[ ] U[ ]
AttA step 10.c.2) filter demin bunker).
Comments:
Cue: Spool piece is bolted in place.
STEP Open service water supply to fuel pool Locates 3SWP*V700 (Aux Bldg EI 4'6") Critical: Grade
- 14 isolation (3SWP*V700) located in Aux and simulates turning valve handle to a Y[X] S[ ]
Building 4' position in line with pipe. N[ ] U[ ]
AttA step 10.d Comments: Valve handle rotates to a position in line with the SWP pipe.
Cue: For this JPM it is not necessary to climb the installed scaffolding. However, the candidate should positively point out to you the physical location of 3SWP*V700.
T-- r--
STEP Open service water supply to fuel pool Simulates unlocking and removing Critical: Grade I
- 15 (3SWP*V30) locking device on valve 3SWP*V30. Y[ ] S[ ]
N[X] U [] I AttA step 10.e ,..,I Cue: Locking device is unlocked and removed.
I Simulates loosening wingnut locking Critical: Grade I device on valve 3SWP*V30. Y[ ] S[ ]
N[X] U[ ]
Cue: Wingnut is loosened (if wingnut is not loosened, inform operator that valve will not move when attempt is made to open valve.)
Simulates positioning valve handle to the Critical: Grade in-line position to open the valve. Y[X] S[ ]
N[ ] U[ ]
Cue: Valve handle is aligned to the in-line position. Water flow is heard as the valve is opened.
STEP Check spent fuel pool level -- Verifies spent fuel pool level increasing Critical: Grade
- 16 INCREASING by either local (3SFC-Ll26 at the fuel pool Y[ ] S[]
cooling panel) indication or by requesting N[X] U[ ]
AttA step 10J information from control room (computer point SFC-L26).
Comments: Candidate may either go to the local spent fuel pool cooling panel or call the control room to obtain level information. In either case, provide the following cue:
Cue: Spent fuel pool level is 34% and slowly increasing.
STEP Notify the control room that emergency Candidate reports to US that he/she has Critical: Grade
- 17 make up to the spent fuel pool is initiated, initiated emergency make up from the Y[ ] S[]
controlling level between 36% and 44%. service water system to the spent fuel N[X] U[ ]
pool in accordance with EOP 3505A, Attachment A.
11
VERIFICATION OF JPM COMPLETION JPM Number: 2K11 NRC P.3 Revision: E~
Date Performed:
Student:
Evaluator:
To achieve a satisfactory grade, All critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 25 Actual Time to Complete (minutes):
Overall Result of JPM: SAT UNSAT Areas for Improvement I Comments:
13
STUDENT HANDOUT JPM Number: 2K11 NRC P.3 Revision: 8 chg 1 Initial Conditions: A loss of all AC power occurred and the control room team is carrying out actions of EOP 35 ECA-O.O.
The spent fuel pool low level alarm has been received and, due to a loss of all AC power, the normal method of make-up is not available.
Additionally, 3SFC-V31, RWST to fuel pool isolation valve, is stuck closed.
Initiating Cues: While maintenance works on 3SFC-V31, the US directs you to make up to the spent fuel pool using the emergency method of EOP 3505A starting with Attachment A. Step 9.
The OMOC has granted permission to perform this step.
14
MILLSTONE POWER STATION SIMULATOR EXAM GUIDE APPROVAL SHEET Exam
Title:
Loss of Secondary Heat Sink Revision: o chg 2 ID Number: 2K11 NRC-01 This document is the property of the Millstone Power Station which controls its distribution. Further transfer, copying, or modification of this document is strictly prohibited without the written consent of the Millstone Power Station.
Submitted by: D. Minnich 03/21/11 Developer Date Validated by: Robert Ro~ce 519/11 Technical Reviewer Date Approved by: L. Armstrong 5/11/11 Training Supervisor Date STOP THINK ACT REVIEW
SUMMARY
OF CHANGES Change Description REV/CHG Date of Change Added applicable TIS 3.7.1.2 (two AFW pumps INOP) to the loss of 0/1 5/26/11 Bus 34C event. Added the expected RCS pressure to the Instructor Information column at step 12 of E-1. These changes are a result of NRC Exam comments on 5/25/11. Modified the Exam Overview to describe initial conditions as middle of core life, as opposed to end of core life. This change was self discovered, editorial and aligns the Overview with form ES-D-1 and the body of the Exam Guide.
Lowered the severity of malfunction RC02D to 65 Ibm/sec. This will 0/2 6/21/11 provide additional time margin to CTMT going 'Adverse'. Delayed the trip of the TDAFW pump until after the E-O step 16 brief. These changes will minimize the chance of meeting FR-H.1 Bleed and Feed criteria. Added a malfunction to fail open one MSIV to ensure to ensure the manual trip of the turbine remains a valid critical task.
Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
STOP THINK ACT REVIEW
SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER
- 1. Cover Page
- 2. Table of Contents
- 3. Exercise/Exam Overview
- 4. Exam Guide Attachments:
Shift Turnover Report Validation Checklist Scenario Outline (ES-D-1)
Attributes Checklist Summary of Changes Page 3 of 80
SECTION 3 EXAM OVERVIEW
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: o chg 2
- 1. The Session will begin with the plant at 100% power and at middle of life. The "A" TPCCW pump is out of service for oil replacement.
Shortly after turnover a PEO on rounds will report a large quantity of lube oil around the "B" MOAFW pump. The lube oil system bubbler assembly will appear to have been inadvertently damaged by a maintenance crew moving heavy equipment in the vicinity of the pump. Tech Spec 3.7.1.2 (72 hr action statement) should be entered and actions taken to remove the MOAFW Pump from service. Assessments will report the expected return of the pump in 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
While Tech Specs and other actions for the MOAFW Pump are in progress, thE!
controlling channel of Pressurizer level will slowly fail to a point just below program level, resulting in charging flow increasing. The crew should use channel checking and other diagnostics skills to determine the failure is an instrument malfunction and not an RCS leak. Pressurizer level on the failed instrument will cause charging flow to rise until manual control of charging flow is established. The crew should enter AOP 3571, Instrument Failure Response, to address and mitigate the failed instrument up to and including the tripping of associated bistables. Applicable Tech Specs are identified within the guide.
After actions of AOP 3571 are complete, 3MSS-PT20A will fail high resulting in 3MSS PV20A ('A' SG Atmospheric Relief Valve) opening. The crew should take manual control of the atmospheric relief valve controller and close PV20A once SG Pressure is verified to be less than 1125 psig. The crew should identify the cause as a failed instrument and address the problem using ARP MB5C 5-7, MAINSTEAM RELIEF W NOT CLOSED, and then AOP 3571, Instrument Failure Response.
Event number 4 is a Loss of Main Condenser Vacuum that will begin slowly. The crew initially enters AOP 3559, Loss Of Condenser Vacuum, to commence a rapid load reduction in accordance with AOP 3575, Rapid Downpower. As load is lowered!
approximately 15% and with the concurrence of the lead examiner, the condenser vacuum will stabilize and the crew can stop the load reduction.
Once the downpower is stopped and the plant stable, a loss of emergency bus 34C will occur. The crew will mitigate the event by carrying out the actions as specified in AOP 3577, Loss of Power to a 4. 16KV Emergency Bus. Actions will include aligning service water, RPCCW and CVCS as required for a loss of bus 34C. Tech Specs will need to be addressed.
Once actions are complete up to bus restoration, an unisolable reactor coolant leak will occur in CTMT. The crew should carry out the actions as specified in AOP 3555, Reactor Coolant Leak, but with normal charging and letdown isolated due to the loss of Bus 34C, there is nothing the crew can do to control the inventory loss, and the leak is severe enough to require a Reactor Trip and Safety Injection. Upon the Manual Reactor Trip, the Page 4 of 80
Main Turbine fails to trip automatically or manually, and requires a turbine runback
[Critical Task]. In addition, the '0' MSIV will fail open.
The crew should carry out the actions of E-O, Reactor Trip Or Safety Injection. The 'B' SI pump will fail to auto-start (fA' SI pump has no power) and will have to be manually started [Critical Task]. The size of the break will be such that RCS pressure lowers sufficiently to require the Reps be tripped based on E-O Foldout Page criteria [Critical TaskJ.
At a predetermined point in E-O, the TO AFW pump trips on overspeed. At step 17 of E-O, the crew will transition to FR-H.1, Response To Loss Of Secondary Heat Sink, and establish feedwater flow to at least one S/G [Critical Task]. Attempts to restore Auxiliary Feedwater will not be successful (the 'A' MO AFW pump is deenergized due to loss of bus 34C, 'B' MO AFW pump in PTL due to no oil). The crew should recognize that feeding SGs from the Main Feed system (IVIOMFP) is their most likely success path. Once a secondary heat sink is established, the crew will transition back to E-O, step 18 and then transition to E-1, Loss of Reactor or Secondary Coolant. The scenario will end when the crew has made the decision to transition to ES-1.2, Post LOCA Cooldown and Depressurization.
- 2. The SRO candidate (US) should classify this event as an ALERT-Charlie One based on failure of the RCS Barrier, BA1. The SRO candidate (US) may consider an update to the classification due to Heat Sink being RED if required feed flow cannot be established within 15 minutes.
- 3. Duration of Exam: 120 minutes Page 5 of 80
SECTION 4 EXAM GUIDE
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:
All Control Room Conduct, Operations and Communications shall be in accordance with OP-AA 100, Conduct of Operations.
"Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded."
(NSEM 6.06)
Page 6 of 80
SECTION 4 EXAM GUIDE
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision:
SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that training interruptions have a minimum negative impact on the Crew and the training we provide. Use your judgment on whether to stop the training and how the training should be commenced after the problem is corrected.
Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.
As soon as the Instructors are aware of a simulator problem that will adversely affect the training in progress (computer fault, etc.) the Instructor should:
- 1. Place the simulator in FREEZE if possible.
- 2. Announce to the Crew that there is a simulator problem.
- 3. Request that the Crew either standby (for minor trouble that can be handled quickly) or leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).
- 4. Deal with the problem (reboot, close tripped breaker, call STSB, etc.)
- 5. After the Instructors believe the simulator is restored to service, the Crew should be told how training will continue. If it is possible and felt to be acceptable to the Instructors, training can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If training will not begin where it left off, the crew should be told how and where training will begin again.
- 6. Once the Crew has been told how and where training will begin, have the crew conduct a brief so that the Instructor can insure that the crew has all the necessary information to continue with the scenario.
- 7. Once all Crew members and Instructors are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the training session.
Page 7 of 80
S. (ION 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS Simulator Setup Checklist
- 1. VERIFY that the current approved training load is loaded.
- 2. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.
- 3. RESET to le# 18 or Temp IC# N/A, LOAD Schedule file 2K11 NRC-01 and, if needed, LOAD or VERIFY BASIC.EVT file
- 4. Wait at least one minute, PLACE Simulator to RUN.
- 5. ENSURE Simulator fidelity items cleared
- 6. If Necessary, RESET the Plant Calorimetric at the Instructor Station PPC going to Unit 3 top menu, then selecting BOP Menu, then selecting Plant Calorimetric Menu.
- a. Verify calorimetric calculation selected appropriately for the plant conditions. (Normally steam flow for 100% power.
- 1. CHECK the STEP COUNTERS at correct position for plant conditions.
- 2. PLACE _7_ tiles under the DEMINS IN SERVICE lama cord label on MB6.
- 3. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.
- 4. PLACE the Westronic (2) recorders in active/run by depressing up or down arrow for each.
- 5. For the NR45 recorder: select group 3 or 4 at power setting
- 7. Reset SMM alarms if required.
- 8. Select Status Grid on the RMS console.
- 9. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT.
- 10. As needed, RESET Computer Terminals to At Power displays if 100% power IC.
- 11. Ensure that the protected train and environmental placards are appropriately hung
- 12. Verify various pot setting correct for plant conditions.
Equipment OOS: "C" TPCCW pump (Caution Tag on control switch and place in PTL)
Verify the MONITOR Time Display the same as the digital time display on MB4. If not page/call the Unit Tech.
Page 8 of 80
S_ I"ION 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS Initial MalfunctionsllOsllDAs:
PLACE GREEN PLACARDS FOR ALL INTAKE PARAMETERS ON MB6 PLACE THE "A" TRAIN PROTECTED PLACARD ON MB4
~ ~~~ c~~~ ~~~-~~~ ,--~~~~
-~~~
Delay Ramp Event Severity Final Relative Description Time Time Trigger Or Value Value Order MALFUNCTIONS
----- ------- ~~~-~~~-~~~ ~~~~ r~~~ ~~-~~~ ,--~~~~~
S 107A 'A' Safety Injection pump fails to automatically start. Initial
~~~- ------- ~ ~~ ~~~~~~~ ~~-~~~
I---~~~
S 107B 'B' Safety Injection pump fails to automatically start. Initial T C03 Turbine fails to Trip automatically or from MB7 Initial pushbutton MIS12D 'D' MSIV fails open Initial TP02A "A" TPCCW Pump fails to auto-start Initial RX10A PZR level transmitter failure (LT459) 60 sec 1 62.0%
~~~- ---- -
MS11A 'A' Atmospheric Relief Valve pressure channel failure 60 sec 4 100%
high. (3MSS-PT20A)
F N01 Loss of Condenser Vacuum 5 1000 E )04C Deenergize Emergency Bus 34C rl:tn' Page 9 of 80
SL ."'ON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS
..... ~ --------- ............
Delay Ramp Event Severity Final Relative ID Number Description Time Time Trigger Or Value Value Order RC020 RCS Hot Leg leak (loop 4) 60 s 10 100 Ibm/sec FW19 TO AFW pump trip 11 REMOTE FUNCTIONS
------
- __* * * * *
- T - * * * - - * * * --_...
RXR106 Protection Set #1 2 OPEN RXR25 PZR HI LEV Rx TRIP LS/459A, C1-751 BS-1 (PZR LVL f 3 TRIP B/S LB459A)
RXR106 Protection Set #1 30 sec 3 CLOSE SWR25 Locally operates 3SWP*MOV71A 7 0%
(CLOSED)
CCR08,09 Locally opens 3 CCP-V186, 167, 187, 177 to cross- 8 OPEN connect non-safety headers EDR07 Shifts lAC 6 to the alternate source (32-2P) 9 ALT EDR06 Shifts lAC 5 to the alternate source (32-1 F) 240 s 9 ALT RPR44,45 SSPS A213 Cards 12 OUT OVERRIDES I
Page 10 of 80
5... ION4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew. Go over the Plant/simulator differences, which follow.
Booth Instructor: IF desired by the NRC Exam Team, commence recording Simulator session Booth Instructor: Perform the crew turnover (Initial Conditions page at end of LP) with the US. Have the US brief his crew on plant conditions and any major equipment OOS.
PLANT/SIMULATOR DIFFERENCES:
- Rad Monitor Historical Data--Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.
- If not using the speed dial option on the phone system, the operator must dial either #3333 or #3334 to reach the person/department they desire.
- The following PPC programs do not function on the simulator:
- Samarium Follow
- Xenon Follow
- Sequence of Events
- Flow indications 3SIH-F1917 (charging ECCS flow), 3SIH-F1918 (A SI pump flow) and 3SIH-F1922 (8 SI pump flow) will show flow at low flow rates.
Page 11 of 80
SEC ..IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malt Instructor Information/Activity _ .... J.\ssign Expected Action Standard Event 1: 'B' MD AFW pump oil leak. (Tech Spec entry)
T+1 min of BOOTH Call and report that you have found a turnover large pool of oil around the "B" MDAFW Pump. The lube oil system bubbler assembly appears to have been inadvertently damaged. A couple of mechanics say they hit it by accident while moving equipment around.
Tech Spec 3.7.1.2.c (72 hr action US Review Tech Specs.
statement) should be entered.
When the 'B' MDAFW Pump is placed Crew Actions should be taken to remove the in Pull-To-Lock, the Bypass MOAFW Pump from service, including Annunciator for" MO AFW System" will placing the pump in Pull-To-Lock.
come in.
US Contact the OMOC to request Maintenance assistance. The US may contact Security to investigate for potential tampering.
T=10min BOOTH Call as OMOC and report the expected from call to return of the pump in 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
OMOC.
Event 2: Controlling channel of PZR level fails just below setpoint.
T= RX10A, 62% This will activate the PZR Level Page 12 of 80
SEt. IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Evaluator channel failure to just below the Cue Program set point.
Trigger 1 It will take several minutes before The crew should use MB indications and PZR level, CHS Flow and VCT level computer trends to diagnose an to respond. instrument failure versus an RCS leak.
AOP 3571 Actions (rev 009-07)
RO Do not leave the rod selector switch in AOP 3571 AUTO while diagnosing a related Step 1, instrument failure unless the reason for CAUTION rod movement is a turbine run back.
CREW If a reactor trip occurs, immediately go AOP 3571 to E-O, Reactor Trip or Safety Injection. Step 1, NOTE The RO should place the Master PZR RO Determine the Initiating Parameter AOP 3571 level controller or 3CHS*FCV121 in and Place the affected controller in Step 1 manual. MANUAL CREW Stabilize the Plant Parameters AOP 3571 Step 2 US It is desired that I&C personnel trip the AOP 3571 bistables specified in this procedure. If, Step 3, NOTE during off - hours, I&C personnel are not able to trip the necessary bistables Page 13 of 80
SEC ..ON 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard within the time limitations required by the Technical Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.
The appropriate attachment for this US Perform Corrective Actions Using AOP 3571 failure is "C". The US should announce Appropriate Attachment Step 3 to the crew.
Instrument Failure Attachment PZR Level Channel Failure C RO Defeat the failed channel input. AOP 3571 Attachment C Step 1 RO should select some other channel than 1.
- Pressurizer Level Select Control- 3RCS-LS459D RO should select some other channel than 1.
- Pressurizer Level Select Record - 3RCS-LS459E The US should give specific direction RO Restore PZR level to normal. AOP 3571 to the RO to restore PZR level to Attachment C program for the present power level. Step 2 Letdown should not have isolated. RO If necessary, using OP 3304A, AOP 3571 "Charging and Letdown," Restore Attachment C letdown. Step 3 RO Place PZR level controller in automatic. AOP 3571 Attachment C Page 14 of 80
SEC .IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Step 4 RO Reset pressurizer heaters as necessary. AOP 3571 Attachment C Step 5 RO When conditions have stabilized, AOP 3571 Observe MB annunciators and Attachment C parameters. Immediately report any Step 6 unexpected or unexplained conditions to the SM.
US,I&C Trip the associated Reactor Protection AOP 3571 System bistable(s); Attachment C Step 7 US Place a check mark in the box above the AOP 3571 appropriate channel that requires Attachment C tripping on the last page of this Step 7a Attachment.
The US should identify the applicable us Refer to Technical Specification 3.3.1, AOP 3571 TIS and T/R which are: 3.3.3.5, and 3.3.3.6. Attachment C Step 7b
[Tech Specs] 3.3.1, Functional Unit 11, Action 6 IF PZR level deviates from program level by + or - 6%, then also 3.4.3.1, Action b.
The RO should do a lamp check to RO Check the existing bistable status to AOP 3571 ensure all bistable lights are ensure a reactor trip will not occur when Attachment C functional. the failed channel is tripped. Step 7c The following step will distinguish AOP 3571 whether the failure is within SSPS or the Attachment C Page 15 of 80
SEt. IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Protection channel. Step 7d NOTE NOTE: This is not the case. The If bistable status light(s) ( MB4F) AOP 3571 channel has failed. The US should go indicate that a single bistable input has Attachment C to step 7.e. tripped and channel indication is normal, Step 7d PERFORM the following:
T=2 mins of RXR106 Protection Set 1 Door I&C Request the I&C Department trip the AOP 3571 request 'OPEN' appropriate bistables using Attachment Attachment C C and Attachment S. Step 7e Trigger 2 T=3 mins of RXR25 PZR High Level Trip B/S RO Verify the appropriate bistable status AOP 3571 request 'TRIP' lights are lit. Attachment C
("PZR LEVEL HI" will alarm on Step 7f Trigger 3 MB4)
RXR106
'CLOSE' Protection Set 1 Door PZR level control may still be in US If indicator 3RCS*LI 459C is failed, AOP 3571 manual. It is satisfactory to move Refer to TRM Table 7.4.1, Fire Related Attachment C on to Event 3. Safe Shutdown Components, "Reactor Step 8 Coolant System."
US Request I&C Department perform AOP 3571 corrective maintenance on failed Attachment C instrument. Step 9 EVENT 3: 'A' Atmospheric Relief Valve pressure channel fails high (3MSS-PT20A)
Page 16 of 80
SEC .IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit~ Assign E:xpected Action Standard T = Bistables MS11A, 3MSS-PT20A fails high tripped 100%
Trigger 4 The first indication the crew will receive of the 3MSS-PT20A failure will be the annunciator "MAIN STEAM RELIEF W NOT CLOSED" MB5C 5-7 3353.MB5C 5-7 (rev 004-03)
Corrective Actions CHECK the following steam generator BOP should check SG pressures for pressures for proper operation of main steam MB5C proper operation of SG Atmospheric pressure relief valve (MB5): Step 1 Relief Valve. BOP should identify that
- 3MSS-PIC20A the process input (3MSS-PT20A) to
- 3MSS-PIC20B 3MSS-PIC20A is pegged high as indicated by the controller red pointer.
- 3MSS-PIC20D IF a pressure controller has failed, MB5C PERFORM the following (MB5): Step 2 The BOP should take manual control of PLACE applicable controller in "MAN" and MB5C MSS-PIC20A (liN SG Atmospheric CLOSE valve: Step 2.1 Relief Valve Controller) and close the "An atmospheric relief valve.
- 3MSS-PIC20A1, "ATMOSPHERIC RELlEFWS" IF relief valve does not close, CLOSE the applicable isolation valve: MB5C Page 17 of 80
SEC .IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Step 2.2
- 3MSS*MOV18A, "ATMOSPHERIC RELIEF ISOL" "SG 3" Refer To Technical Specification 3.7.1.6 and The US should refer to Technical DETERMINE Limiting Condition for MB5C Specification 3.7.1.6. No action will be Operation. Step 3 required.
IF failure is due to an instrument problem, Go To AOP 3571, "Instrument Failure MB5C Response." Step 4 The US should go to AOP 3571 AOP 3571 Actions (Rev 009-07) Do not leave the rod selector switch in AUTO AOP 3571 while diagnosing a related instrument failure Step 1, unless the reason for rod movement is a CAUTION turbine runback.
If a reactor trip occurs, immediately go to E-O, AOP 3571 Reactor Trip or Safety Injection. Step 1, NOTE Determine the Initiating Parameter and AOP 3571 Place the affected controller in MANUAL Step 1 Stabilize the Plant Parameters AOP 3571 Step 2 It is desired that I&C personnel trip the AOP 3571 bistables specified in this procedure. If, during Step 3, off - hours, I&C personnel are not able to trip NOTE the necessary bistables within the time limitations required by the Technical Page 18 of 80
SEtJN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chq 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Specifications, Operations Department personnel may trip the bistables using the guidance provided within this procedure.
The appropriate attachment for this Perform Corrective Actions Using AOP 3571 failure is "I". The US should announce Appropriate Attachment Step 3 to the crew.
Rated thermal power (3650 Mwth) The following are symptoms of an AOP 3571 may be exceeded as a result of the atmospheric relief valve pressure channel Attachment transient. The crew should recognize failure (3MSS-PT20A, 20B, 20C or 200): I NOTE this and take appropriate action (lower turbine load) as specified in OP 3204, At Power Operations.
- Actuation of the following annunciator:
MAIN STEAM RELIEF W NOT CLOSED MB5C 5-7
- Abnormal indication on any of the following indicators on MB-5 3MSS-PIC20A 1 3MSS-PIC20B 1 3MSS-PIC20C1 3MSS-PIC20D1 Defeat the failed instrument input by placing AOP 3571 the affected SG atmospheric relief valve Attachment controller in MANUAL and Close the valve. I Step 1 When conditions have stabilized, Observe MB AOP 3571 annunciators and parameters and Attachment Page 19 of 80
SEt .IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time I~A/Malt Instructor Information/Activity Assign Expected Action Standard immediately report any unexpected or I Step 2 unexplained conditions to the Shift Manager.
There are no Technical Specifications or AOP 3571 bistables associated with this instrument. Attachment I Step 3 NOTE Request I&C Department perform corrective AOP 3571 maintenance on failed instrument. Attachment I Step 3 Event 4: Loss of condenser vacuum and procedurally directed rapid downpower T=AOP FW01, This will insert a loss of condenser 3571 (1000 vacuum complete cfm)
Trigger 5 Goal is to have crew respond to loss of vacuum by performing a rapid load reduction. When the Examiners are satisfied with the Crew's performance, the cause will be found and corrected. The crew should then stop the downpower. AOP 3575, Rapid Downpower, follows AOP 3559, Loss of Condenser Vacuum.
AOP 3559 Actions (rev 009)
The Foldout page must be open. AOP 3559 Step 1 NOTE Page 20 of 80
SEt.. .IN 4 Lesson
Title:
Loss of Secondary Heat Sink Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Check If Turbine Load Should Be Reduced AOP 3559 Step 1 Condenser backpressure will be less Verify condenser backpressure - LESS THAN AOP 3559 than 7.5 inches Hg. OR EQUAL TO 7.5 inches Hg Absolute Step 1.a Verify condenser backpressure - GREATER AOP 3559 THAN 5 inches Hg Absolute Step 1.b Turbine load will be greater than 389 Verify turbine load - GREATER THAN 389 AOP 3559 MWe, the US should Using AOP Mwe Step 1.c 3575, "Rapid Downpower" to lower turbine load at 5%/min.
Using AOP 3575, "Rapid Downpower," Lower AOP 3559 turbine load at 5%/min. Step 1.d Proceed to step 2 and WHEN one of the following occurs:
- Backpressure LESS THAN EQUAL TO 5 inches Hg Absolute OR
- Turbine load at 389 Mwe THEN Proceed to step 1.e.
Check Circulating Water System Operation AOP 3559 Step 2 Page 21 of 80
SE<:.. ')N 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Yes, all 6 circulating water pumps Verify circulating water pumps - ONE PER AOP 3559 should be running. CONDENSER RUNNING Step 2.a All water box outlet isolation valves will Verify water box outlet isolation valves - OPEN AOP 3559 be open Step 2.b Verify all circulating water pumps - RUNNING AOP 3559 Step 2.c Yes, all traveling screen DPs will be Verify the traveling screen differential AOP 3559 less than 12 inches H2 0 pressure - LESS THAN 12 inches H20 Step 2.d Check Condenser Air Removal Alignment AOP 3559 Step 3 Verify steam jet air ejector auxiliary steam AOP 3559 supply valve (3ASS-AOV22) - OPEN Step 3.a Using OP 3329, "Condenser Air Removal," AOP 3559 locally Perform the following: Step 3.b Verify both sets of steam jet air ejectors in AOP 3559 service Step 3.b.1 Verify all first stage jets in service on each air AOP 3559 ejector Step 3.b.2 Verify air ejectors - NOT BACKFIRING AOP 3559 Step 3.b.3 3GWS*AOD78A and 3GWS* AOD788 Verify isolation dampers for gaseous waste to AOP 3559 are open (VP1) Unit 1 stack (3GWS*AOD78A and Step 3.c 3GWS*AOD78B) - OPEN T =when BOOTH Report as PEa that 3GWS-FN1A is At Gas Waste Panel (3GWS-PNL-P6), Verify AOP 3559 called as running. process vent fans (3GWS-FN1A or 3GWS Step 3.d Page 22 of 80
SEl IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign _ I:xpected Action Standard PEO FN1B) - ONE RUNNING T=when BOOTH Report as PEO that 3ARC-AOV36A Locally (Turbine Bldg 38' southwest) Verify AOP 3559 called as and 3ARC-AOV36B are open. steam jet air ejector exhaust valves (3ARC Step 3.e PEO AOV36A and 3ARC-AOV36B) - OPEN Gland Seal Pressure will be about 3.5 Check Gland Seal Pressure - BETWEEN 2 AOP 3559 psig and 6 pSig Step 4 Locked valve key is required for some local AOP 3559 operations. Step 5 Note Surge Tank Level will be about 95,000 Check Condensate Surge Tank Level AOP 3559 gal and stable. Step 5
- GREATER THAN 18,000 gal
- NOT DECREASING IN AN UNEXPECTED MANNER A turbine trip occurs if the exhaust hood AOP 3559 temperature exceeds 225°F. Step 6 Note These Annunciators will not be lit Check Exhaust Hood Temperature AOP 3559 Annunciators EXH HOOD A, B, and C Step 6 TEMP HI (175°F) (MB6A 5-4, 5-5, and 5-6)
NOT LIT T = After LOWER Check For Condenser In-Leakage AOP 3559
'CONDENSER FW01 Step 7 VACUUM LO Severity alarms. to 200 cfm Verify condenser vacuum breakers (MB7) AOP 3559 Page 23 of 80
SEC. .IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDAlMalf Instructor Information/Activity Assign Expected Action Standard (3ARC-MOV20A-B-C) - CLOSED Step 7.a IF any valve will NOT close, THEN AOP 3559 Step 6.a Locally Close valve(s) (Turbine Bldg 60' RNO west).
T = Rapid BOOTH Report as the PEa that the loop seal Locally Check vacuum breaker loop seals AOP 3559 Downpower associated with 3ARC-MOV23C has (Turbine Bldg 60' west) - FILLED Step 7.b started no water and air can be heard rushing into the seal pipe.
The US should direct the PEO to fill the Locally Fill loop seals. AOP 3559 loop seal. Step 7.b RNa T= 2 min REMOVE This will simulate filling the loop seal Locally Check for unusual noises indicative of AOP 3559 from being FW01 and allow backpressure to stabilize. air in-leakage Step 7.c directed to fill seai BOOTH Report as the PEa that the loop seal Check seal water supply pressure annunciator AOP 3559 is filled. EXT STM NRV SEAL PRES LO (MB6A 3-6B) Step 7.d
- NOT LIT This Annunciator will not be lit Using OP 3353. MB6A, "Main Board 6A AOP 3559 Annunciator Response," Perform corrective Step 7.d actions for MB6A 3-68. RNa The US should contact the Engineering Contact Engineering to assist in locally AOP 3559 Duty Manager for assistance. checking condenser penetrations for air in Step 7.e leakage T= when BOOTH Report that the System Engineer is called as on his way to the TB.
EDM Page 24 of 80
SEL .IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Review Current Maintenance and Testing AOP 3559 Activities. Step 8 Verify Condenser Backpressure - STABLE AOP 3559 OR DECREASING Step 9 Return to step 1. AOP 3559 Step 9 RNO AOP 3575 Actions (Rev 017-03)
If at any time either of the following AOP 3575 annunciators is received, Immediately perform Step 1 step 7: NOTE
>> ROD CONTROL BANKS LIMIT LO (MB4C 3-9)
>> ROD CONTROL BANKS LIMIT LO-LO (MB4C 4-9)
Rod Control will be in Auto. Check Rod Control - IN AUTO AOP 3575 Step 1 Align EHC Panel AOP 3575 Step 2 The crew may perform down power on Check load reduction using load set AOP 3575 load limit or load set. Either is DESIRED Step 2.a acceptable.
Page 25 of 80
SELJN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malt Instructor Intormation/Activit~ Assign Expected Action Standard Proceed to Note prior to step 3. AOP 3575 Step 2.a RNO Using Attachment E align EHC panel for AOP 3575 LOAD SET operation. Step 2.b CONVEX requested load reductions should be AOP 3575 performed at 5%/min and completed within 15 Step 3 minutes of notification. NOTE CREW Determine Power Reduction Rate (%/min). AOP 3575 Step 3 Load reductions should be performed at Check desired power reduction rate - 3% / AOP 3575 5%/min as specified in AOP 3559. min OR 5% / MIN Step 3.a If SI actuation occurs during this procedure, AOP 3575 Go to E-O, Reactor Trip or safety Injection, Step 4 and restore from rapid boration lineup. CAUTION RO Initiate Rapid Boration AOP 3575 Step 4 Verify RCS makeup system in - AUTO AOP 3575 Step 4.a START one boric acid transfer pump. AOP 3575 Step 4.b 1\ An 'lc~r::.
OPEN emeigency bOiation valve /"\vr 0iJ f iJ (3CHS*MV81 04). Step 4.c RO Verify direct boric acid flow (3CHS-FI 183A) AOP 3575 INDICATED. Step 4.d Page 26 of 80
SEt .IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard OPEN charging line flow control valve, to AOP 3575 match boric acid flow (3CHS-FI 183A) Step 4.e RO Record time boration started AOP 3575 Step 4.f Time - - - - - - - -
Check Rod Control-AVAILABLE FOR ROD AOP 3575 INSERTION Step 4.g Check use of "Rapid Downpower Summary AOP 3575 Sheet" (RE-H-17) in the RE Curve and Data Step 4.h Book - DESIRED Proceed to step 4.k. AOP 3575 Step 4.h.
RNO About 17 minutes if "Rapid Downpower Using the "Rapid Downpower Summary AOP 3575 Summary Sheet" is used. Sheet" (RE-H-17), Determine approximate Step 4.i boration time Proceed To step 6. AOP 3575 Step 4.j Use 18 gal BAI% Power to determine boration AOP 3575 time in step 4.1 Step 4.k Using formula, Determine boration time AOP 3575 gravity borating, use net charging flow (chg + Step 4.1 seal inj-seal return total flow) for BA flow rate:
Total Power Change (Ll %) X (gal BAI% = min Power)
Page 27 of 80
SEl .ON 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BA Flow Rate Boration Time Proceed to step 6. AOP 3575 Step 4.m If at any time the power reduction rate or final AOP 3575 desired power level must be changed. Return Step 6 to step 1. NOTE US/BOP Initiate Load Reduction AOP 3575 Step 6 US Check Rapid or gravity boration -IN AOP 3575 PROGRESS Step 6.a Check turbine OPERATING MODE AOP 3575 MANUAL Step 6.b Check load reduction using load set AOP 3575 DESIRED Step 6.c Perform the following: AOP 3575 Step 6.c
- 1) Using Attachment F, Rotate LOAD RNO LIMIT SET in CCW direction consistent desired down power schedule.
- 2) Proceed to step 6.f.
5% should be selected. Select LOAD RATE LIMIT %/MIN to the AOP 3575 desired value (1%. 3%, or 5%) Step 6.d Page 28 of 80
SEC .,)N 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard The BOP should adjust Load Set to Utilizing DECREASE LOAD pushbutton, AOP 3575 about 360 MWe. Adjust LOAD SET to desired final MWe Step 6.e Energize all PZR heaters AOP 3575 Step 6.f Adjust Pzr Spray Valves to 50% setpoint AOP 3575 (RCS-PK 455B and RCS-PK 455C) Step 6.g Adjust boration time and/or flow rate as AOP 3575 necessary to maintain:
Step 6.h
- Rods above the Rod Insertion Limit (RIL)
- Tavg within +/-S_F of Tref
- AFD within COLR limits Check rapid OR gravity boration performed AOP 3575 for the time determined in steps 4.i. or 4.1. Step 6.i Proceed to step 6.k. and, WHEN Boration has AOP 3575 been performed for the desired time, THEN Step 6.i Using Attachment G, stop boration. RNO Using Attachment G, stop boration AOP 3575 Step 6.j Check power reduction - CONVEX AOP 3575 REQUESTED Step 6.k Inform CONVEX of load reduction rate AOP 3575 (MWe/min) and final MWe level. Step 6.k RNO Verify Rod Position Above RIL AOP 3575 Page 29 of 80
SEt IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assig" Expected Action Standard Step 7 Check ROD CONTROL BANKS LIMIT LO-LO AOP 3575 (MB4C 4-9) annunciator- Step 7.a Proceed to step 7.g and, IF at any time, the AOP 3575 annunciator is received, Step 7.a RNO THEN Perform steps 7.c, 7.d and 7.e Check ROD CONTROL BANKS LIMIT LO AOP 3575 (MB4C 3-9) annunciator - LIT Step 7.g Proceed to step 8 and AOP 3575 Step 7.g IF the annunciator is received, RNO THEN Perfrom step 7.h and 7.i C-7 (Turbine Load Reject Arm) may Using Attachment C, "Rapid Downpower AOP 3575 come in. If so, the BOP will need to Parameters" MONITOR parameters Step 8 reset C-7.
Degrade Condenser Backpressure AOP 3575 Step 9 Verify Final Desired Turbine Load (MWe) AOP 3575 LESS THAN 72% 972 MWe) Step 9.a Condenser backpressure will already be Using OP 3329, "Condenser Air Removal", AOP 3575 degraded due to the loss of vacuum. Degrade condenser backpressure to between Step 9.b 2.0 in. HgA and 4.0 in. HgA.
T = when BOOTH Report as the PEO that the loop seal Page 30 of 80
SEl')N 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard called as associated with 3ARC-MOV23C has PEO no water and air can be heard rushing into the seal pipe.
The US should direct the PEO to fill the loop seal.
T= 2 min REMOVE This will simulate filling the loop seal from being FW01 and allow backpressure to stabilize.
directed to fill seal BOOTH Report as the PEa that the loop seal is filled.
The US should direct the down power be stopped since condenser vacuum has stabilized. Once the downpower is stopped and the plant stable, proceed to the next event.
Event 5: Loss of emergency bus 34C.
T = load ED04C Emergency Bus 34C will deenergize reduction is due to a bus differential relay trip and stopped and lockout.
the plant stable Trigger 6 US The US will enter AOP 3577, Loss Of Normal AOP 3577 (rev 001-02) Actions And Offsite Power To A 4.16 Kv Emergency Page 31 of 80
SEc.. ')N 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Ex~e~~c;lAction Standard Bus The US should direct the board CREW The Foldout page must be open. AOP 3577 operators to open and review their Step 1 foldout pages. NOTE US Check If Letdown Should Be Isolated AOP 3577 Step 1 Yes, 34C is deenergized. Check either 4.16 KV emergency bus- AOP 3577 DE-ENERGIZED Step 1.a BOP Check affected bus - BUS 34C AOP 3577 Step 1.b RO Simultaneously Perform the following: AOP 3577 Step 1.c
- CLOSE the charging flow control valve
- CLOSE letdown orifice isolation valves RO CLOSE charging header isolation valve AOP 3577 (3CHS*MV81 06) Step 1.d US Try To Restore Power To Affected AOP 3577 Emergency Bus Step 2 BOP Check bus differential annunciator for the AOP 3577 affected bus - LIT Step 2.a YES
- For bus 34C - BUS 34C BUS OIFF (MB8A 4-12)
- For bus 340 - BUS 340 BUS OIFF (MB8C 4-2)
Page 32 of 80
SEt IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard The US should direct the BOP to Perform the following: AOP 3577 emergency stop the 'A' EOG. Step 2.b
- 1) STOP affected bus EOG by pressing both emergency stop push buttons.
- 2) Proceed to step 3.
US Check If A Charging Pump Should Be AOP 3577 Started Step 3 The 'B' CHS pump will be running. RO Check charging pumps - NONE RUNNING AOP 3577 Step 3.a US Proceed to step 4. AOP 3577 Step 3.a RNO US Check Service Water Alignment AOP 3577 Step 4 BOP Check Affected bus - OEENERGIZEO AOP 3577 Step 4.a PEO Locally Close service water supply valve to AOP 3577 TPCCW from affected train Step 4.b Locally operates MOV71A T = 3 min
- For Train A: 3SWP*MOV71 A from request Report as PEO that 3SWP*MOV71A SWR25 is closed Trigger 7 0% (closed))
The RO will start the 'B' SW pump. RO START the second SW pump in the non- AOP 3577 affected Train Step 4.c Page 33 of 80
SEC ')N 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify service water supply valve to TPCCW AOP 3577 from the operating SW train (3SWP*MOV71A Step 4.d or 3SWP*MOV71 B) - OPEN The RO will need to open RO OPEN valve. AOP 3577 3SWP*MOV71 B, or a turbine runback Step 4.d will occur due to high Stator Water RNO temperatures.
US Cross-Connect RPCCW Containment AOP 3577 Headers Step 5 RO Verify the RPCCW containment supply and AOP 3577 return header isolation valves in the operating Step 5.a train - OPEN
- For Train B:
Flow indicated - 3CCP-FI15B, CTMT SPL Y FLOW OR 3CCP*MOV45B 3CCP*MOV48B 3CCP*MOV49B (ESF Status Group 4, 9-25, 10-24, and 11-25)
RO OPEN the RPCCW containment header AOP 3577 cross-connect valves: Step 5.b 3CCP*AOV179A 3CCP*AOV179B Page 34 of 80
SEC. IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard 3CCP*AOV180A 3CCP*AOV180B RO CLOSE RPCCW containment return header AOP 3577 isolation valve in the affected train Step 5.c For Train A: 3CCP*MOV49A For Train B: 3CCP*MOV49B Check Boric Acid Transfer Pump AOP 3577 Alignment Step 6 Verify the boric acid transfer pump selected AOP 3577 for AUTO ENERGIZED Step 6.a Select AUTO on energized pump. AOP 3577 Step 6.a RNO Adjust boric acid blend flow pot setting to the AOP 3577 appropriate setpoint Step 6.b US Restore Containment Cooling AOP 3577 Step 7 CREW LOP signal may take up to six minutes before AOP 3577 it can be reset with the bus de-energized. Step 7.a NOTE RO RESET both trains LOP AOP 3577 Step 7.a BOP Check affected bus - Bus 34C AOP 3577 Step 7.b Page 35 of 80
SEc.. IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO OPEN RPCCW non-safety header AOP 3577 supply/return isolation valves Train B Step 7.c (3CCP*AOV197B/194B)
RO CLOSE RPCCW non-safety header AOP 3577 supply/return isolation valves Train A Step 7.d (3CCP* AOV197 Al194A)
RO Verify CDS chiller on train with power - AUTO AOP 3577 STARTS Step 7.e T+ 3 mins This will manually open 3 CCP-V186, RO Using OP 3330A, Reactor Plant Component AOP 3577 CCR08 from request 167, 187, 177 per OP3330A. Cooling Water," Cross-connect Non-safety Step 7.f CCR09 related RPCCW headers.
Trigger 8 "OPEN" NOTE: Once the non-safety headers RO Verify associated CDS chiller - STARTS AOP 3577 are cross-connected, the max flow Step 7.g allowed through a CCP HX (81 00 gpm) will be challenged. The crew should discuss methods to reduce the '8' train CCPflow.
START chiller. AOP 3577 Step 7.g RNO BOP Check CAR fans - TWO FANS RUNNING AOP 3577 Step 7.h START fan(s), if available. AOP 3577 Step 7.h RNO BOP Check CRDM fans - TWO FANS RUNNING AOP 3577 Page 36 of 80
SEL .IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity ASl!ii9 1l Expected Action Standard Step 7.i The BOP will need to start the 'B' START fan(s), if available. AOP 3577 CRDM fan. Step 7.i RNO RO Check containment pressure - STABLE OR AOP 3577 DECREASING Step 7.j Perform the following: AOP 3577 Step 7.j RNO RO 1. Using OP 3313E, "Containment Vacuum," Maintain normal operating containment pressure.
If CTMT pressure exceeds 14.0 psia, US 2. Refer to Technical Specification the US should enter the LCO for TS 3.6.1.4, "Containment Pressure,"
3.6.1.4, "Containment Pressure" (one for additional actions.
hour action statement)
US Align Charging And Letdown AOP 3577 Step 8 BOP Check the affected bus - Bus 34D AOP 3577 Step 8.a RO Perform the following: AOP 3577 Step 8.a RNO The RO will Use GA-14, to establish 1. Using GA-14, Establish head vent head vent letdown to the PRT. This is letdown to the PRT.
necessary to balance RCS inventory due to ongoing seal injection.
Page 37 of 80
SEL .IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assig~ Expected Action Standard US 2. Proceed to step 9.
US Isolate Auxiliary Steam To Auxiliary AOP 3577 Building Step 9 BOP CLOSE auxiliary steam isolation valves to the AOP 3577 Auxiliary Building Step 9.a 3ASS*AOV102A 3ASS*AOV1 02B US Verify Service Water Flow To The AOP 3577 Operating Control Building Chiller Heat Step 10 Exchanger BOP Using OP 3314F, "Control Building Heating, AOP 3577 Ventilation, Air Conditioning and Chill Water," Step 10 Perform operation of Control Building AC RNO System to start the other chiller and its associated service water booster pump.
- For chiller A (HVK(CHL 1A) Check annunciator CONTROL BLDG CHLR CNDSR A SW FLOW LO (VP1A 3-3)
NOT LIT
- For chiller B (HVK(CHL 1B) Check annunciator CONTROL BLDG CHLR CNDSR A SW FLOW LO (VP1 C 3-3)
NOT LIT RO Verify Spent Fuel Pool Cooling Alignment AOP 3577 Step 11 Page 38 of 80
SEt. IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Yes, the 'B' spent fuel cooling pump is Check spent fuel cooling pumps - ONE AOP 3577 running. RUNNING Step 11.a Perform the following: AOP 3577 Step 11.a RNO Check RPCCW to the in-service spent fuel AOP 3577 pool cooling heat exchanger - FLOW Step 11.b INDICATED Flow will be indicated.
- RPCCW safety header flow indication minus RHR HX RPCCW flow indication Using OP 3305, "Fuel Pool Cooling and AOP 3577 Purification," Perform Spent Fuel Pool Cooling Step 11.b System HX shift.
US Restore Auxiliary Building Ventilation AOP 3577 Step 12 BOP Using GA-20, Place charging and RPCCW AOP 3577 area a ventilation in service. Step 12.a US Block Automatic Loading Of Affected AOP 3577 Emergency Bus Step 13 CREW Place the following control switches for AOP 3577 equipment on the affected bus in PULL-TO Step 13.a LOCK
- One service water pump
- RPCCW pumps Page 39 of 80
SEt IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity_ Assign Expected Action Standard
- Quench spray pump
- Recirc spray pumps
- SI pump
- RHR pump
- Charging pumps
- MOAFW pump
- Control Bldg chiller
- Aux Building filter US Maintain Stable Plant Conditions AOP 3577 Step 14 RO Energize available PZR heaters as necessary AOP 3577 Step 14.a An instrument air compressor is RO Start an instrument air compressor, if AOP 3577 running. necessary Step 14.b RO Maintain the following parameters stable at or AOP 3577 trending to desired values. Step 14.c
- PZR pressure
- PZR level
- SG levels Page 40 of 80
SEt IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard CREW If power is not restored to Bus 34C or AOP 3577 computer panels (3VBA-PNL-6A and 6B) are Step 15 not energized by the alternate source within NOTE 30 minutes, Inverter 6 deenergizes making the process computer unavailable.
US Check If Non-Vital Panels Should Be AOP 3577 Energized By Alternate Source Step 15 BOP Check affected bus - Bus 34C AOP 3577 Step 15.a BOP Check Bus 34C - NOT ENERGIZED AOP 3577 Step 15.b T=4 min EDR07 and Shifts lAC 6 to the alternate source PEO 1. Using OP 3345A, "120 Volt Non-Vital from EDR06 (32-2P) Instrument AC," Perform transferring dispatch (delayed 4 min) 3VBA-PNL-6A and 3VBA-PNL-6B to 'ALT' Shifts lAC 5 to the alternate source power from 3VBA-INV-6 to alternate Trigger 9 (32-1 F) AC source.
PEO 2. Using OP 3345A, "120 Volt Non-Vital Instrument AC," Perform transferring 3VBA-PNL-5 and 3VBA-PNL-5C power from 3VBA-INV-5 to alternate AC source USISM Refer To The Following Technical AOP 3577 Specifications For Any Additional Required Step 16 Actions TIS 3,8.1.1, AC Sources - Operating TIS 3,8.1.2, AC Sources - Shutdown Page 41 of 80
SEC .IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard TS 3.8.2.1 (action a), DC Sources and TIS 3,8.2.1, DC Sources - Operating 3.8.3.1 (action a), Onsite Power Distribution apply due to the loss of 34C. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action statement for DC Sources.
Additionally, since the loss of the TIS 3,8.2.2, DC Sources - Shutdown bus makes the 'A' MD AFW pump unavailable, TS 3.7.1.2, action d should be entered for two AFW pumps INOPERABLE (6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action statement).
Also, 3.8.1.1, AC Sources, has an TIS 3,8.3.1 Onsite Power Distribution action (b.1) to conduct the surveillance Operating for Offsite Sources within one hour if an EDG is INOPERABLE. Although the
'A' EDG is OPERABLE it is in effect not usable, so the surveillance should be conducted.
T TIS 3,8.3.2 Onsite Power Distribution Shutdown T =When BOOTH Reply as Maintenance that repair is TRM 7.4.1, Fire Related Safe Shutdown called possible in 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />, bus differential Components (A train only) relay is bad EVENT 6: Small Break LOCA inside CTMT.
Page 42 of 80
SEC .ON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RC02D (65 . .
T= Tech Ibm/sec 60 Malfunction entry will cause a small Specs Sec) I unisolable RCS leak to occur on the addressed loop 4 hot leg.
Trigger 10 The leak is about 335 gpm, well in excess of the capacity of two CHS pumps.
The first indication of the RCS leak will be PZR level and pressure lowering, followed by computer point alarms associated with CTMT Unidentified sump and CTMT high pressure alarms.
CMS22 will also show an adverse trend, but does not reach the alert setpoint for several minutes.
AOP 3555 Actions (Rev 017-02)
YES, PZR level will be decreasing.
RO Check PZR Level - DECREASING AOP 3555 Step 1 Charging and Letdown were isolated as US Increase Charging Flow AOP 3555 procedurally directed in AOP 3577. Step 2 Charging fiow cannot be increased.
RO Check charging lineup-NORMAL AOP 3555 Step 2.a Align valves as necessary. AOP 3555 Page 43 of 80
SEC. ..ON 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit~ ).\t;t;i91"L Expected Action Standard Step 2.a, RNO RO Throttle Open charging line flow control valve AOP 3555 to increase charging flow to maximum Step 2.b NO letdown orifice isolation valves will Check letdown orifice isolation valves - ONLY AOP 3555 be open. ONE OPEN Step 2.c There is nothing the crew can do to control the inventory loss. Based on the rapid lowering of PZR level, the US should direct a Reactor Trip and an initiation of Safety Injection.
PZR level will be rapidly lowering. RO Verify PZR level- STABLE OR INCREASING AOP 3555 Step 6.a Perform the following: AOP 3555 Step 6.a, RNO
- 1) TRIP the reactor.
- 2) Initiate SI.
- 3) Go to E-O, Reactor or Safety Injection.
NOTE: US should go to "Master Silence" before ordering reactor trip.
Page 44 of 80
SEC. ,ON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Task Revision: ° chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard E-O (Rev. 026) STEPS Crew
- Foldout page must be open E-O, Step 1, NOTE The only available source of AFW will
- ADVERSE CTMT defined as GREATER 5
be from the TD AFW pump. THAN 180°F or GREATER THAN 10 R/hr in containment.
- The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.
- are satisfied.
RO Verify Reactor Trip E-O, Step 1
- Check reactor trip and bypass breakers - OPEN
- Check rod bottom lights - LIT
- Check neutron flux - DECREASING RO TRIP the reactor. E-O, Step 1, RNO EVENT 7: Turbine Fails To Trip Verify Turbine Trip E-O, Step 2 Turbine stop valves will NOT be closed. Check all turbine stop valves - CLOSED E-O, Step 2.a
[*] Critical Task- Trip the Turbine E-O, Step 2.a Page 45 of 80
SEL .. ON4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity _ _ .. Ass~ E:xpected Action Standard The BOP should recognize that the If the Turbine will Not Trip RNO turbine failed to trip and manually THEN [*]
runback the turbine Runback the turbine to close the control valves.
The operators may close the MSIVs if If the turbine cannot be runback E-O, they do not believe the turbine control Step 2.a THEN valves are closing quickly enough.
However, the '0' MSIV will fail to close, RNO CLOSE MSIVs & MSIV bypass valves necessitating the BOP to runback the turbine.
BOP Verify Power to AC Emergency Busses E-O, Step 3 BOP Check busses 34C and 340 - E-O, Step 3.a BOTH ENERGIZED us Check If SI Is Actuated E-O, Step 4 RO Verify SAFETY INJECTION ACTUATION E-O, annunciator - (MB4D 1-6 or MB2B 5-9) - LIT Step 4.a us Check if SI is required E-O, Step 4.a, RNO
SEC .. IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit~ Assign Expected Action Standard
- PZR pressure LESS THAN 1890 psia OR
- PZR level LESS THAN 9%
Check Reactor trip and bypass breakers E-O, OPEN Step 4.c RO Verify Service Water Pumps - AT LEAST E-O, Step 5 ONE PER TRAIN RUNNING START pump(s} E-O, Step 5, RNO RO Verify Two RPCCW Pumps - ONE PER E-O, Step 6 TRAIN RUNNING EVENT 8: SIH pumps fails to RO Verify ECCS Pumps Running E-O, Step 7 Auto-Start.
Critical Task
- Check SI pumps - RUNNING Page 47 of 80
SEC, .. IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity ~_ .. J.\ssign Expected Action Standard Crew should identify that the "8' SI pump did not automatically start and manually start the pump.
- Check RHR pumps - RUNNING
- Check two charging pumps - RUNNING BOP Verify AFW Pumps Running E-O, Step 8 Check MD pumps - RUNNING E-O, Step 8.a Check turbine - driven pump - RUNNING, IF E-O, NECESSARY Step 8.b The safety Injection closed the BOP Verify FW Isolation E-O, Step 9 RPCCW CTMT cross-connect valves. As a result, the 'A' and '0' RCPs have no motor lube oil cooling and RCP bearing temperatures will start to increase. The crew should identify this and trip the 'A' and '0' Reps.
- Check SG feed regulating valves CLOSED
- Check SG feed regulating bypass valves CLOSED
- Check FW isolation trip valves - CLOSED Page 48 of 80
SEL ..ON 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
- Check TO FW pump - TRIPPED
- Check SG blowdown isolation valves CLOSED
- Check SG blowdown sample isolation valves - CLOSED
- Check SG chemical feed isolation valves CLOSED BOP Align component(s) as necessary for minimum E-O, Step 9 safety function. RNO BOP Check If Main Steam Lines Should Be E-O, Isolated Step 10 MSI will already have occurred, Check Ctmt pressure GREATER THAN 18 E-O, however the '0' MSIV is stuck open and psi a Step 10.a cannot be closed.
OR Any SG pressure LESS THAN 660 psig OR Annunciator "MAIN STEAMLINE ISOLATION" (MB2B 5-7) - LIT Proceed to Step 11 E-O, Step 10.a, RNO Verify MSIVs and MSIV bypass valves- E-O, Page 49 of 80
SEt. ..ON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assi9 1l Expected Action Standard CLOSED Step 10.b Check ESF Group 3 lights - LIT. E-O, Step 10.c
[*] Critical Task - RO Check if CDA Required E-O, Step 11 RCS pressure will eventually lower to <
1500 psia. Crew should identify this and trip all RCPs.
Check Ctmt pressure is GREATER THAN 23 E-O, psi a Step 11.a OR Annunciator "CONTAINMENT DEPRES ACTUATION" (MB2B 5-5) - LIT US Proceed to Step 12. E-O, Step11,a, RNO BOP Verify CAR Fans Operating In Emergency E-O, Mode Step 12 BOP Check CAR fan status: E-O, Step 12.a
- CAR fans A and B - RUNNING
SEc. ,ON 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify RPCCW Ctmt supply and return header E-O, isolations - OPEN Step 12.b RO Verify Train A and B RPCCW supply and E-O, return to chill water valves - OPEN Step 12.c RO Verify CIA E-O, Step 13 RO Check ESF Group 2 status columns 2 through E-O, 10 - LIT Step 13.a RO Verify Proper ESF Status Panel Indication E-O, Step 14
- Verify ESF Group 1 lights - OFF
- Ctmt temperature GREATER THAN 180°F OR 5
- Ctmt radiation GREATER THAN 10 R/ hr RO Verify ECCS Flow E-O, Step 16 Check PZR pressure - GREATER THAN E-O, 1900 psia Step 16.a Proceed to step 16.d. E-O, Step 16.a RNO Page 51 of 80
SEt. .* ON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chQ 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Check PORV block valves - OPEN E-O, Step 16.b Proceed to step 17. E-O, Step 16.c Check charging pumps E-O, Step 16.d FLOW INDICATED RO START pumps and Align valves. E-O, Step 16.d, RNO RO Check RCS pressure - GREATER THAN 1650 E-O, psia (1950 psia ADVERSE CTMT) Step 16.e US Proceed to Step 17 E-O, Step 16.e, RNO Check SI pumps - FLOW INDICATED E-O, Step 16.f START pumps and Align valves. E-O, Step 16.f RNO Check RCS pressure - LESS THAN 300 psia E-O, (500 psia ADVERSE CTMT) Step 16.g Proceed to step 17. E-O, Step 16.g RNO Check RHR pumps - FLOW INDICATED. E-O, Step 16.h Page 52 of 80
SEC. JON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard START pumps and Align valves. E-O, Step 16.h RNO CREW should perform a short brief and come out of "Master Silence" at the completion of Step 16.
EVENT 9: Loss of Secondary Heat Sink.
T = At the FW19 This will trip the TD AFW pump. Loss of BOP Verify Adequate Heat Sink E-O, completion aIlAFW. Step 17 of step 16 brief.
Trigger 11 Heat sink will be RED due to loss of a!1 Check NR level in at least one SG E-O, AFW. GREATER THAN 8% (42% ADVERSE CTMT) Step 17.a Proceed to step 17.d. E-O, Step 17.a RNa Verify Total AFW Flow - GREATER THAN E-O, 530 gpm Step 17.d The US should transition to FR START pumps and Align valves as necessary.
E-O, H.1. IF AFW Flow GREATER THAN 530 gpm can Step 17.d NOT be established, THEN Initiate monitoring RNO of CSF Status Trees and Go to FR-H.1, Response to Loss of Secondary Heat Sink.
Page 53 of 80
SEL. ,ON 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: a chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard FR-H.1 Actions (Rev. 020-01)
Check If Secondary Heat Sink Is yes ROI Required FRH.1 step Verify RCS pressure 1 BOP GREATER THAN ANY NON-FAULTED SG PRESSURE Verify RCS hot leg WR temperature BOP GREATER THAN 350°F Check Charging Pump Status RO AT LEAST ONE RUNNING FRH.1 step 2
Done in E-O us Try to Establish AFW Flow to at Least One FR-H.1 SG. Step 3 RO Check SG blowdown isolation FR-H.1 Step 3.a Blowdown will be isolated. RO
- Verify SG blowdown sample isolation valves - CLOSED Verify AFW valve alignment - PROPER FR-H.1 EMERGENCY ALIGNMENT. Step 3.b DWST level will be> 80,000 gal. BOP Check DWST level - LESS THAN 80,000 gal FR-H.1 Step 3.c us Proceed to step 3.f and, IF DWST level FR-H.1 decreases to LESS THAN 80,000 gal, THEN Step 3.c Perform step 3.d. RNO Page 54 of 80
SEc... .ON 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard OWST suction valves will be open. BOP Verify OWST suction valves (3FWA*AOV61A FR-H.1 and 3FWA*AOV61B) - OPEN. Step 3.f The 'A MO AFW pump is deenergized BOP Check MO pumps - RUNNING. FR-H.1 due to bus 34C being deenergized, the Step 3.g
'B' MO AFW pump is tagged out.
BOP/US START pumps. FR-H.1 Step IF the pump{s) do NOT start, THEN 3.gRNO Restore power to the pumps (MB or locally).
The TO AFW pump tripped. BOP Check TO AFW pump - RUNNING. FR-H.1 Step 3.h OPEN steam supply valve(s). FR-H.1 Step 3.h IE the pump does NOT start, THEN RNO OPEN steam supply isolation valves:
3MSS*MOV17A 3MSS*MOV17B 3MSS*MOV170 Check total flow to SGs - GREATER THAN FR-H.1 530 gpm. Step 3.i The US should dispatch at least one US Perform the applicable action: FR-H.1 PEO to carry out local actions in Step 3.i Attachment 'A', specifically the actions
associated with the TO AFW pump.
- IE no AFW flow indicated, THEN The US should proceed to step 4. 1) Locally restore AFW flow using Attachment A, if required.
Page 55 of 80
SEC .. ON4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time 10A/Malf Instructor Information/Activity Assi9 11 Expected Action Standard
- 2) Proceed to step 4. and, IF AFW flow is established prior to step 10. THEN Return to step 3.i.
The RCPs should already be stopped. RO STOP All Reps. FR-H.1 Step 4 T= 5 min BOOTH Report as PEO that the TO AFW trip CREW
- DO NOT reinstall the A213 logic cards FR-H.1 from being throttle valve has tripped (MSV-5). until an adequate heat sink has been Step 5 dispatched Attempting to reset. made available. Reinstallation of a lobic CAUTION card may cause actuation of the FWI circuit.
T = 6 min BOOTH Report as PEO that the MSV-5 CREW
- Removal of the A213 cards defeats the from being latching mechanism is damaged and low steam pressure SI from Loops 1 and dispatched the valve cannot be reset. Request 2. Manual actions may be required to Maintenance assistance. initiate safety injection for a low steam pressure condition.
US Try to Establish Main FW Flow to At Least FR-H.1 One SG. Step 5 Two condensate pumps will be running. BOP Verify at least one condensate pump FR-H.1 RUNNING. Step 5.a BOP Check FW isolation trip valves - OPEN. FR-H.1 Step 5.b T=3 min RPR44, This will simulate removing the A213 BOP/RO Perform the following: FR-H.1 from 45 to cards from SSPS. Step 5.b
- 1. !E SI OR P-14 has actuated, WHEN RNO request 'OUT' SG levels LESS THAN the P-14 Trigger 12 setpoint, Page 56 of 80
SEC:.. .. ON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard THEN RESET SI AND Remove universal logic card A213 from both Trains of the Solid State Protection System (3RPS*RAKLOGA and 3RPS*RAKLOGB).
- 2. RESET FWI at MB2.
- 3. RESET FWI at MB5.
- 5. RESET and OPEN the FW isolation trip valves.
- 6. IF no FW isolation trip valve can be opened, THEN Proceed to Step 9.
US Perform the following to start the MD FW FR-H.1 pump: Step 5.c BOP Place FW pumps P4 trip bypass selector FR-H.1 switch to BYPASS Step 5.c.1 BOP Place the MD FW pump control switch in FR-H.1 STOP. Step 5.c.2 BOP START the MD FW pump. FR-H.1 Step 5.c.3 BOP Verify MD FW pump startup valve (3FWS FR-H.1 HIC590) - 50% OPEN. Step 5.d Page 57 of 80
SEc" .. ON 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard The US should direct the BOP to use US/BOP Feed the SGs using SG feed regulating FR-H.1 the PPC to assist in NOT overfeeding bypass valves to restore SG narrow range Step 5.e the SGs and causing an uncontrolled level consistent with preventing excessive cooldown. This should include a RCS cooldown.
specific band of flowrate such that WR levels in SGs are going up but not such that the BOP loses RCS temperature.
CLOSE the FW control isolation valves: FR-H.1 Step 5.f 3FWS-MOV35A 3FWS-MOV35B 3FWS-MOV35C 3FWS-MOV350 BOP Verify feed flow - ESTABLISHED FR-H.1 Step 5.g BOP CLOSE each TO FW pump's discharge FR-H.1 isolation valve Step 5.h
- 3FWS-MOV23C US Check SG Levels FR-H.1 Step 6 BOP Verify NR level in at least one SG - GREATER FR-H.1 THAN 8% (42% ADVERSE CTMT) Step 6.a WR levels should be increasing, Core BOP Perform the following: FR-H.1 Exit TCs decreasing. Step 6.a
- 1. Verify a secondary heat sink established:
RNa
SEt. ..IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit}' Assign __ . Expected Action Standard AND
- Core Exit TCs are stable OR decreasing lE a secondary heat sink established can NOT be established, THEN Proceed to CAUTION prior to Step 7.
- 2. Maintain feed flow to restore NR level to GREATER THAN 8% (42% ADVERSE CTMT).
The US should announce transition to US Go to procedure and step in effect. FR-H.1 E-O step 18, and hold a transition brief. Step 6.b Verify AFW Valve Alignment - PROPER EMERGENCY ALIGNMENT E-O, Step 18 Verify ECCS Valve Alignment - PROPER EMERGENCY ALIGNMENT E-O, Step 19 Check If CBI Required E-O, Step 20 Yes, CBI will be lit. RO Check CONTROL BUILDING ISOLATION E-O, annunciator (MB4D 3-6) - LIT Step 20.a Check Train A Control Building filter fan BOP E-O, (3HVC*FN1A) - RUNNING Step 20.b Page 59 of 80
SEC, .. IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity A~sign E~ected Action Standard Check recirc damper for the running BOP E-O, Control Building filter fan Step 20.c (3HVC*AOD119A or B)
-OPEN RO Verify ESF Group 2 CBI lights - LIT E-O, Step 20.d BOP Verify control building purge supply fan and E-O, purge exhaust fan - NOT RUNNING Step 20.d BOP Verify control building purge supply fan and E-O, purge exhaust fan - NOT RUNNING Step 20.e BOP Place kitchen exhaust fan in OFF E-O, Step 20.f T=When BOOTH When asked, REPORT that "all SLCRS Verify SLCRS doors - CLOSED E-O, called as doors indicate closed." Step 20.g SSS T = When BOOTH When called, WAIT 3 - 5 min, Then PEO CLOSE and DOG the following Control E-O, called as REPORT "Control Building pressure Building pressure boundary doors ..... Step 20.h PEO boundary doors are Closed and Dogged or verified closed as directed,"
RO Check RCS Temperature E-O, Step 21 Page 60 of 80
SEC .. IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP Using GA-26, Dump steam as necessary E-O, to control RCS cold leg WR temperature Step 21.a BETWEEN 550°F AND 560°F BOP Verify RCS cold leg WR temperature E-O, GREATER THAN 550°F Step 21.b US Proceed to Step 22 E-O, Step 21.c Check Power To sao Diesel Auxiliaries E-O, Step 22 BOP E-O, Verify any SBO bus tie breaker - CLOSED Step 22.a TO AN ENERGIZED BUS
- Bus 34A: 34A1-2
- Bus 34B: 34B 1-2
- Bus 24E: A505 (Unit 2)
RO Check PZR Valves E-O, Step 23 Verify PORVs - CLOSED E-O, Step 23.a RO Verify normal PZR spray valves - CLOSED E-O, Step 23.b RO Verify PORV block valves - AT LEAST E-O, ONE ENERGIZED VALVE OPEN Step 23.c RO Verify PZR safety valves - CLOSED E-O, Page 61 of 80
SEL ..IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Step 23.d CREW To prevent seal damage, seal injection flow E-O, should be maintained to all RCPs. Step 24, CAUTION RO Check If RCPs Should Be Stopped E-O, Step 24 Verify RCPs - ANY RUNNING E-O, Step 24.a RO Verify RCS pressure - LESS THAN 1500 psia E-O, (1800 psia ADVERSE CTMT) Step 24.b us Proceed to Step 25 E-O, Step 24.b, RNO Verify either of the following:
RO E-O, Step 24.c
- Charging pumps - AT LEAST ONE RUNNING AND AT LEAST ONE COLD LEG INJECTION VALVE OPEN OR
- SI pumps - AT LEAST ONE RUNNING
[*] Critical Task- RO STOP all RCPs E-O, Step 24.d RCS pressure will eventually lower Page 62 of 80
SEC. _.IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity_ Assign Expected Action Standard to < 1500 psia. Crew should identify this and trip all RCPs. [*]
BOP Check If SG Secondary Boundaries Are E-O, RO Intact Step 25 Check pressure in all SGs E-O, Step 25.8
- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
- NO SG COMPLETELY DEPRESSURIZED BOP Check If SG Tubes Are Intact E-O, Step 26 RO Sample all SGs for activity E-O, Step 26.a
- 1. RESET SG blowdown sample isolation
- 2. OPEN SG blowdown sample isolation valve(s)
BOOTH Acknowledge the request to 3. Request Chemistry obtain activity samples perform the SIG samples. Ensure using HP coverage crew request activity samples with HP coverage BOP Check steam generator levels - NO SG E-O, LEVEL INCREASING IN AN Step 26.b UNCONTROLLED MANNER Verify trend history and alarm status of E-O, Page 63 of 80
SEC .. IN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malt Instructor Information/Activity Assign Expected Action Standard radiation monitors Step 26.c
- Main steam line - NORMAL
- Condenser air ejector - NORMAL
- Verify Ctmt radiation using 3CMS*RE22 (pre-trip) - NORMAL
- Verify Ctmt radiation using radiation monitoring group histogram (CTMT)
NORMAL CTMT pressure will not be normal.
- Verify Ctmt pressure - NORMAL
- Verify Ctmt recirculation sump level NORMAL The crew should conduct a short US Initiate monitoring of CSF Status Trees and E-O, transition brief and transition to E-1. Go to E-1, Loss of Reactor or Secondary Step 26 Coolant. RNO E-1 (rev 024) Actions RO To prevent seal damage, seal injection flow E-1, Step 1 should be maintained to all RCPs. CAUTION Note The US should remind the operators US Note: Foldout page must be open. E-1, Step 1 to review their Foldout Page Books NOTE RCP's should have been stopped in US Check If RCPs Should Be Stopped E-1, Step 1 Page 64 of 80
SEL .. JN4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard E-O.
RO Verify RCP's - ANY RUNNING E-1 Step 1a US Proceed to step 2 E-1 Step 1a RNO US Check If SG Secondary Boundaries Are E-1, Step 2 Intact BOP! Check pressures in all SGs. E-1, Step 2.a RO
- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
- NO SG COMPLETELY DEPRESSURIZED US Check Intact SG Levels E-1, Step 3 BOP Verify NR level- GREATER THAN 8% (42% E-1, ADVERSE CTMT) Step 3.a BOP Control feed flow to maintain NR level E-1, between 8% and 50% (42% and 50% Step 3.b ADVERSE CTMT)
US Check Secondary Radiation E-1, Step 4 RO Sample all SGs for activity. E-1, Step 4.a Page 65 of 80
SEC, ,ON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
- 1) RESET SG blowdown sample isolation.
- 2) OPEN SG Blowdown sample isolation valve(s)
- 3) Request Chemistry obtain activity samples using HP coverage RO Verify trend history and alarm status of E-1, radiation monitors Step 4.b
- Main steam line - NORMAL
- Condenser air ejector - NORMAL
- SG blowdown - NORMAL us Check PZR PORVs and Block Valves E-1, Step 5 RO Verify PORVs - CLOSED E-1, Step 5.a RO Verify block valves - AT LEAST ONE OPEN E-1, Step 5.b us Check If ECCS Flow Should Be Reduced E-1, Step 6 Subcooling should be <32°F and/or RO Verify RCS subcooling based on core exit t::_1 L..- I, PZR level < 16%. TCs - GREATER THAN 32°F (115°F Step 6.a ADVERSE CTMT)
BOP Verify secondary heat sink E-1 Step 6.b Page 66 of 80
SEC .. ON 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malt Instructor Intormation/Activit~ .._"~1!!gl1 Expected Action Standard
- Narrow range level in at least one intact SG - GREATER THAN 8% (42%
ADVERSE CTMT)
RO Verify RCS pressure - STABLE OR E-1 INCREASING Step 6.c RO Verify PZR level- GREATER THAN 16% E-1 (50% ADVERSE CTMT) Step 6.d US Proceed to CAUTION prior to step 7. E-1, Step 6, RNO us To ensure adequate ECCS flow, do not stop E-1, Step 7 any recirculation spray pumps used for core CAUTION injection flow.
US The recirculation spray pumps are E-1, Step 7 sequenced to automatically start 11 minutes NOTE after a CDA.
RO Check it containment spray should be E-1, step 7 stopped.
RO Verify quench spray pumps - RUNNING E-1, Step 7.a US Proceed to CAUTION prior to step 8. E-1, Page 67 of 80
SEc.., ,uN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDAIMalf Instructor Information/Activity Assign Expected Action Standard Step 7,a, RNO After SI reset, manual operator action is E-1, Step 8 required to: CAUTION
- Open the charging cold leg injection valves when RCS pressure decreases to LESS THAN 1900 psia.
- Restart the RHR pumps if RCS pressure decreases in an uncontrolled manner to LESS THAN 300 psia (500 psia ADVERSE CTMT).
- Restart safeguards equipment if offsite power is lost.
US Check RHR pumps - ANY RUNNING IN SI E-1, MODE Step 8.a RCS pressure should be around RO Check RCS pressure E-1, 1200 psia and stable. But Step 8.b depending on the speed of the 1) Verify pressure - GREATER THAN 300 crew, RCS pressure may still be psia (500 psia ADVERSE CTMT) going down very slowly_ If the crew elects NOT to stop RHR pumps 2) Verify pressure - STABLE OR based on this trend, this is INCREASING satisfactory_
Crew should reset SI RO RESET SI, if necessary E-1, Page 68 of 80
SEt.. ,IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Step B.c RO STOP RHR pumps and Place in Auto E-1, Step B.d US Check RCS and SG Pressures E-1, Step 9 BOP
- Check RCS pressure - DECREASING E-1, Step 9 OR STABLE US Check If Diesel Generators Should Be E-1 Stopped Step 10 No BOP Verify AC emergency busses - BOTH E-1 ENERGIZED BY OFFSITE POWER Step 10a BOP Proceed to step 10.c. E-1 Step 10a, RNO RESET LOP at MB2, if required. E-1 Step 10c Offsite power is available, however it is Check offsite power from RSSA or NSSA - E-1 NOT available to be closed in on bus AVAILABLE Step 10d 34C. The US should recognize this and invoke the RNO.
Proceed to step 10.g and, E-1 Step WHEN 10d RNO Offsite power becomes available, Page 69 of BO
SEL"vN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard THEN Perform step 10.e and 10.f.
Perform the following as required (observe E-1 EDG loading requirements): Step 10.g 1} START an instrument air compressor 2} Turn ON PZR backup heaters (H1A and H1B)
- 3) Check one RPCCW pump - RUNNING
- 4) Using GA-5, Startup spent fuel pool E-1 cooling Step 10.g.5 RESET SI, if required E-1 Step 10h PEO Perform the following to energize MCC32-3T E-1 Step 10i Check Bus 34C -ENERGIZED E-1 Step 10.i.1 Proceed to step 10.j and, E-1 Step 10.i.1 WHEN RNa Power is restored to emergency bus 34C, THEN Page 70 of 80
SEt. .. IN 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDAlMalf Instructor Information/Activity Assign Expected Action Standard Perform step 10.i.2).
Check emergency diesel generators - BOTH E-1 RUNNING UNLOADED Step 10.j USI SM Consult with the ADTS and RMT prior to E-1 performing any local inspections in the Step 11 Auxiliary Building or ESF Building. CAUTION US Initiate Evaluation Of Plant Status E-1 Step 11 US Verify cold leg recirculation capability E-1 Step 11.a BOP 1) Power to recirculation spray pumps AVAILABLE RO 2) Using Attachment A, Verify power for cold leg recirculation valves - AVAILABLE Auxiliary Building and ESF Building RO Check Auxiliary Building and ESF Building E-1 radiation will be normal. radiation (radiation monitoring group Step 11.b histograms)
- Auxiliary Building (AUX) - NORMAL
- SLCRS Area (SLRW) - NORMAL Page 71 of 80
SEC ..JN 4 Lesson
Title:
Loss of Secondary Heat Sink 10 Number: 2K11 NRC-01 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Check for Auxiliary Building of ESF Building E-1 flooding Step 11c
- 1. Verify SUMP LEVEL HI lights (MB1) - NOT LIT
- ESF PIPE TNL
- ECCS PIPE CUB
- 2. Verify Annunciator SAFEGUARDS AREA FLOODING (MB1C 2-8) - NOT LIT us Check If RCS Cooldown And E-1 Depressurization Is Required Step 12 RCS pressure will be about 1200 psia. RO Verify RCS pressure - GREATER THAN 300 E-1 psia (500 psia ADVERSE CTMT) Step 12a US Go to ES-1.2, post LOCA Cooldown and E-1 Depressurization Step 12b The scenario may be terminated once the transition to ES-1.2 is announced.
Page 72 of 80
SECTION 4 Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 EVALUATION GUIDE I. Crew FOLLOW-UP QUESTIONS
- 1. What is the Emergency Classification for this event?
ALERT* Charlie One based on failure of the RCS Barrier, BA1. The SRO candidate (US) may consider an update to the classification due to Heat Sink being RED if required feed flow cannot be established within 15 minutes.
- 2. What plant condition(s) is(are) of greatest concern for (this event)?
- 3. What actions did the crew take to directly mitigate (this event)?
- 4. Which safety function(s) were challenged or had the greatest potential for challenge? Describe why.
Page 73 of 80
SECTION 4 EXAM GUIDE
SUMMARY
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision:
II. Critical Tasks Note: Critical Tasks are not required for Progress Review Exams.
TASK DESCRIPTION TASK # KIA >/= 3.0 BASIS SELECTION Manually trip the main 045-010 Failure to trip the main E-O -- Q turbine [before a severe turbine under the postulated A3.01 3.5/3.6 (orange-path) challenge plant conditions causes develops to either the challenges to CSFs beyond subcriticality or the 045-050 those irreparably introduced integrity CSF]5 or [before by the postulated conditions.
A1.01 3.8/4.1 transition to ECA-2.1],6 Additionally, such an whichever happens first A 1.02 3.3/3.7 omission constitutes a A3.01 3.3/3.5 demonstrated inability by the crew to "take an action ...that would prevent a challenge to plant safety."
Failure to establish the Establish feed flow to at FR-H.1-A E05 minimum required feedwater least one SG before flow rate, under the bleed and feed is EA2.2 3.7 / 4.3 postulated plant conditions, required.
EA2.1 3.4 / 4.2 results in "adverse consequence(s) or a significant degradation in the mitigative capability of the plant" and represents a "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety.
3.6/3.6 Failure to trip the RCPs Trip all RCPs so that an E-1 --C 009 EA1.09 under the postulated plant Orange Path on Core 4.2/4.3 conditions leads to core Cooling based on core 009 EK3.23 uncovery and to fuel exit thermocouples cladding temperatures in (718°F) does not occur excess of 2200°F, whic~1 is when forced circulation the limit specified in the in the RCS stops (small ECCS acceptance criteria.
break LOCA).
01 I EA 1.13 4.1 Failure to manually start at Establish flow from at E-O -- J 4.2 least one intermediate-head least one SI pump 009 EA 1.04 3.4 ECCS pump under the before transition out of 3.4 postulated conditions E-O, during a Small constitutes "mis-operation or Break LOCA where RCS Page 74 of 80
pressure remains incorrect crew performance between 300 psia and which leads to degraded 1650 psia. ECCS capacity."
Note: [*] Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide.
Page 75 of 80
SIMULATOR TRAINING SHIFT TURNOVER REPORT DATE-'"IME PREPARED BY SHIFT Today Now I Shift Manager I Q{5:00 - 18:00 PLANT STATUS:
Mode: 1 Rx Power: 100%
Megawatts: Thermal: 3649 MWTH PZR Pressure: 2250 psia Electric: 1284 MWe ReS T-AVE: 587 degF Res Leakage: Identified: 0.015 gpm Protected Train/Facility: A TRAIN Orange Unidentified: 0.036 gpm PRA: Green Date/Time: Todav 0015 Active Tracking Records and Action Statements Equipment/Reason LCO IAction I Date I Time in LCO I Action Requirement I Time Left I I I I I 00 Compensatory Actions / Temp Logs Watch Open Date Class Reason Reason Position None
,"", i Surveillances I Evolutions in Progress I OP 3204 I Steady State Operation Reactivity Briefing (see reactivity thumbrules I spread sheet for additional info)
Current Rod Height eBD @ 219 Xenon Trend Stable Current Boron 1046 ppm Shift Orders The "A" TPCCW pump is out of service for oil replacement.
Page 76 of 80
ATTACHMENT 2 VALIDATION CHECKLIST
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: o chg 2 Verified By:
(Initials)
Initial Conditions:
The initial condition(s) contained in the guide are certified or have been DM developed from certified ICs.
Test Run:
The scenario contained in the guide has been test run in part or whole on DM the simulator. The simulator response is reasonable and as expected. If a simulator guide revision does not affect original Test Run, then enter N/A.
Simulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or DM anomalous response by reviewing the Simulator Modeling and Anomalous Response List.
For Examination Scenario:
The Scenario Attributes Checklist is complete and attached. This is not DM required for Progress Review Exams.
Dave Minnich Actions Complete (Signature) Date Page 77 of 80
Appendix D Scenario Outline Form ES-D-1 Facility: Millstone 3 Scenario No.: 2K11 NRC-01 Op-Test No.: 2K11 Examiners: Operators:
Initial Conditions: IC-18, 100% Power, Middle of life, Eguilibrium Xe.
Turnover:
The I2lant is at 100% 120wer and at the middle of life. The itA" TPCCW l2uml2 is out of service for oil rel2lacement.
Event Malt. No Event Event No. Type'" Description 1 'B' MD AFW pump oil leak. (Tech Spec entry) 2 RX10A I (RO) Controlling channel of PZR level fails just below setpoint. (AOP 3571) (Tech Spec entry) 3 MS11A I (BOP) 'A' SG Atmospheric Relief Valve pressure channel fails high. (3MSS-PT20A) (Annunciator response, AOP 3571) 4 FW01 R (RO) Loss of condenser vacuum and procedurally directed R (SRO) rapid downpower (5%/min). Vacuum will stabilize.
N (BOP) (AOP 3559, AOP 3575) 5 ED04C C (RO) Loss of emergency bus 34C. (AOP 3577) (Tech Spec C (BOP) entry) 6 RC02D M (ALL) Small break LOCA (220 gpm) inside CTMT. RequirE~s Reactor Trip and Safety Injection. (AOP 3555)
I 7 TC03 C (BOP) Turbine fails to trip automatically or manually, and MS12D requires a turbine runback.
8 S107A1B C (RO) SIH pumps fail to auto-start.
9 FW19 M (ALL)
- Loss of Secondary Heat Sink. TD AFW pump trips, 'A'
. MD AFW pump deenergized due to loss of bus 34C, I 'B' MD AFW pump in PTL due to no oil. (success path will be to establish Main Feed) 1* N)ormal, (R eactivity, (I}nstrument, (C)omponent, (M)ajor Page 78 of 80
Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Assessor: Dave Minnich QUALITATIVE ATTRIBUTES The initial conditions are realistiC, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.
The scenario consists mostly of related events.
Each event description consists of:
the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
The events are valid with regard to physics and thermodynamics.
Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
The simulator modeling is not altered.
The scenario has been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure functional fidelity is maintained while running the planned scenario.
Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section D.5 of ES-301.
All individual operator competencies can be evaluated, as verified using form ES-301-6.
Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-S.
Level of difficulty is appropriate to support licensing decisions for each crew position.
Page! 79 of 80
Lesson
Title:
Loss of Secondary Heat Sink ID Number: 2K11 NRC-01 Revision: 0 chg 2 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.
- 01. Total Malfunctions (TM) - 5 to 8 required Total _8_
(1) PZR level fails just below setpoint, (2) 'A' ARV pressure channel failure, (3) Loss of condenser vacuum, (4) Loss of emergency bus 34C, (5) Small break LOCA inside CTMT, (6)
Turbine fails to Trip, (7) SIH pumps fail to auto-start, (8) TD AFW pump trips
- 02. Malfunctions after EOP entry (EM's) - 1 to 2 required Total 3 (1) Turbine fails to Trip, (2) SIH pumps fail to auto-start, (3) TD AFW pump trips
- 03. Abnormal Events (AE) - 2 to 4 required Total ._5_
(1) PZR level fails just below setpoint, (2) 'A' SG pressure channel failure, (3) Loss of condenser vacuum, (4) Loss of emergency bus 34C, (5) Small break LOCA inside CTMT
- 04. Major Transients (MT) - 1 to 2 required Total 2 (1) Small break LOCA inside CTMT (2) Loss of Secondary Heat Sink
- 05. EOP's (EU) entered/requiring sUbstantive actions -- 1 to 2 required Total 2 (1) FR-H.1, (2) E-1
- 06. EOP Contingencies requiring substantive actions [ECAs/FRsl] (EC)-- Total 1 o to 2 required (1) FR-H.1
- 07. Critical Tasks (CT) - 2 to 3 required Total __4_
E-O-- Q Manually trip the main turbine E-O -- J Establish flow from at least one SI pump FR-H.1 --A Establish feed flow to at least one SG before bleed and feed is required.
E-1 -- C Trip all Reps
- 08. Approximate Scenario Run Time: 60 to 90 min. Total 120 min
- 09. EOP run time: Total 45 min
- 10. Technical Specifications are exercised during the scenario. (Y/N)_Y_
Page 80 of 80
MILLSTONE POWER STATION SIMULATOR EXAM GUIDE APPROVAL SHEET Exam
Title:
Faulted, Ruptured Steam Generator Revision: o chg 2 ID Number: 2K11 NRC-02 This document is the property of the Millstone Power Station which controls its distribution. Further transfer, copying, or modification of this document is strictly prohibited without the written consent of the Millstone Power Station.
Submitted by: D. Minnich 03/21/11 Developer Date Validated by: Robert Ro~ce 5/9/11 Technical Reviewer Date Approved by: L. Armstrong 5/11/11 Training Supervisor Date STOP THINK ACT REVIEW
SUMMARY
OF CHANGES Change Description REV/CHG Date of Change Added the valve numbers that need to be manually closed to 0 11 5/26/11 properly isolate the faulted 'B' SG. Added the components that need to be manually repositioned as a result of malfunction RP11 E (HPSI components fail to respond to a safety injection).
Added the valves the BOP will need to close to properly isolate the faulted SG. These changes are a result of NRC Exam comments made on 5/25/11.
Modified the ramp time of malfunction MS01 B (Steamline break 0 12 6/21/11 in CTMT) from 60 to 10 seconds. Added a statement to press the Bypass Annunciator for the 'A' EDG to the simulator setup.
Corrected a typographical error in the Instructor Info 1 Activity column for event 1 (loop 1 as opposed to loop 3). Removed any reference to 3ARC-RE21 (Condenser Air Ejector Rad Monitor) being in 'ALARM' since only the 'ALERT' setpoint was reached.
Added a statement that a cooldown may already be in progress as a result of ECCS flow, and the BOP may not need to immediately initiate an operator controlled cooldown (ECA-3.1).
Incorporated as a result of NRC comments made the week of 6/13/11 (Prep Week).
THINK ACT REVIEW
SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER
- 1. Cover Page
- 2. Table of Contents
- 3. Exercise/Exam Overview
- 4. Exam Guide Attachments:
Shift Turnover Report Validation Checklist Scenario Outline (ES-D-1)
Attributes Checklist Summary of Changes
SECTION 3 EXAM OVERVIEW
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: o chg 2
- 1. The Session will begin with the plant at 100% power and at middle of life. The "A" EDG is out of service for planned maintenance.
Shortly after turnover, a narrow range Th instrument will fail high. Rods will begin stepping in. The RO should verify no runback in progress and take rod control to manual. The crew will utilize AOP 3571, Instrument Failure Response to mitigate the failure, up to and including the tripping of associated bistables. Applicable Tech Specs are identified within the guide.
Once the actions of AOP 3571 for the failed Th instrument are complete, the "C" SG controlling NR level channel will slowly fail to 0%. The BOP will need to take manual control of the 'C' FRV. Once identified, the crew should respond by entering AOP 3571, to address the problem, which will include shifting to an alternate channel and addressing Tech Specs.
Once actions in AOP 3571 are complete, the "B" S/G will develop a tube leak as indicated by the N-16 Monitoring System in ALERT. The crew will respond by transitioning to AOP 3576, Steam Generator Tube Leak. The crew should determine that the CVCS system will be able to stabilize PZR level in AUTO, but that initial tube leakage does warrant a plant shutdown and will be in excess of the Operational Leakage Tech Spec 3.4.6.2. After consulting with Plant Management, the crew will commence a rapid load reduction in accordance with AOP 3575, Rapid Downpower, at 3%/min.
When the Lead Examiner is satisfied with the reactivity manipulation, a major steam line break will occur in CTMT ('B' SG). The break will be severe enough to require a Reactor Trip and Safety Injection, and a Reactor Trip 'First Out' will be received prior to the crew taking action. Automatic and the I\I1B7 manual reactor trip switch are failed requiring the RO to manually trip the reactor from MB4 [Critical Task]. In addition, MSI Fails to auto actuate and will have to be manually actuated by the SOP [Critical Task]. Also, Several High Pressure Safety Injection components will fail to reposition requiring manual action to assure minimum safety function.
The crew will carry out the actions of E-O, Reactor Trip Or Safety Injection and transition to E-2, Faulted Steam Generator Isolation, to isolate the faulted SG [Critical Task]. After isolation the steam generator will continue to blow down into CTMT. When the "S" SG tubes become hot and dry, a SG Tube Rupture will occur. The crew will ultimately identify wide range levels andlor pressure going up in "S" SG and transition to E-3, Steam Generator Tube Rupture, from E-2. Once in E-3, the crew will determine that ruptured SG pressure is not sufficient to support the cooldown and depressurization method specified in E-3, and will transition to ECA-3.1, SGTR With Loss of Reactor Coolant - Subcooled Recovery Desired. The crew will initiate an RCS cooldown as specified in ECA-3.1. Once the crew has shown that the cooldown rate is controlled [Critical Task], the session will end.
Page 4 of 74
- 2. The SRO candidate (US) should classify this event as an ALERT- Charlie One, Barrier Failure, BA1.
- 3. Duration of Exam: 75 minutes Page 5 of 74
SECTION 4 EXAM GUIDE
Title:
Faulted. Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision:
All Control Room Conduct, Operations and Communications shall be in accordance with OP-AA 100, Conduct of Operations.
"Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded."
(NSEM 6.06)
Page 6 of 74
SECTION 4 EXAM GUIDE
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: o chg 2 SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that training interruptions have a minimum negative impact on the Crew and the training we provide. Use your judgment on whether to stop the training and how the training should be commenced after the problem is corrected.
Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.
As soon as the Instructors are aware of a simulator problem that will adversely affect the training in progress (computer fault, etc.) the Instructor should:
- 1. Place the simulator in FREEZE if possible.
- 2. Announce to the Crew that there is a simulator problem.
- 3. Request that the Crew either standby (for minor trouble that can be handled quickly) or leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).
- 4. Deal with the problem (reboot, close tripped breaker, call 8T8B, etc.)
- 5. After the Instructors believe the simulator is restored to service, the Crew should be told how training will continue. If it is possible and felt to be acceptable to the Instructors, training can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If training will not begin where it left off, the crew should be told how and where training will begin again.
- 6. Once the Crew has been told how and where training will begin, have the crew conduct a brief so that the Instructor can insure that the crew has all the necessary information to continue with the scenario.
- 7. Once all Crew members and Instructors are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the training session.
Page 7 of 74
s~ . nON 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS Simulator Setup Checklist
- 1. VERIFY that the current approved training load is loaded.
- 2. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.
- 3. RESET to IC# 18 or Temp IC# N/A, LOAD Schedule file 2K11 NRC*02 and, if needed, LOAD or VERIFY BASIC.EVT file
- 4. Wait at least one minute, PLACE Simulator to RUN.
- 5. ENSURE Simulator fidelity items cleared
- 6. If Necessary, RESET the Plant Calorimetric at the Instructor Station PPC going to Unit 3 top menu, then selecting BOP Menu, then selecting Plant Calorimetric Menu.
- a. Verify calorimetric calculation selected appropriately for the plant conditions. (Normally steam flow for 100% power.
- 1. CHECK the STEP COUNTERS at correct position for plant conditions.
- 2. PLACE _7_ tiles under the DEMINS IN SERVICE lama cord label on MB6.
- 3. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.
- 4. PLACE the Westronic (2) recorders in active/run by depressing up or down arrow for each.
- 5. For the NR4S recorder: select group 3 or 4 at power setting
- 7. Reset SMM alarms if required.
- 8. Select Status Grid on the RMS console.
- 9. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT.
- 10. As needed, RESET Computer Terminals to At Power displays if 100% power IC.
- 11. Ensure that the protected train and environmental placards are appropriately hung
- 12. Verify various pot setting correct for plant conditions.
Equipment 005: The "An EDG is out of service. "A" EDG (Yellow Tag on Start Switch, Output Breaker and Prelube pump), Depress the Bypass Annunciator for the 'A' EDG.
Verify the MONITOR Time Display the same as the digital time display on MB4. If not page/call the Unit Tech.
Page 8 of 74
S,- _ nON 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS Initial Malfunctions/IOs/l DAs:
PLACE GREEN PLACARDS FOR ALL INTAKE PARAMETERS ON MBS PLACE THE "A" TRAIN PROTECTED PLACARD ON MB4 Delay Ramp Event Severity Final Relative Description Time Time Trigger Or Value Value Order MALFUNCTIONS RP10A Train 'A' Automatic Reactor Trip Fails Initial RP10B Train 'B' Automatic Reactor Trip Fails Initial RP09B MB7 Manual Reactor Trip Switch Fails Initial RP08A Train 'A' Main Steamiine Isolation Fails Initiai RP08B Train 'B' Main Steam line Isolation Fails Initial RP11E HPSI components fail to respond to a SI signal Initial EG07A 'A' EDG Trip Initial MB8A B11 34C Bus Loss of Control Power ON Initial RX05D Loop 4 narrow range Th, 3RCS*TE441 A 60 sec 1 650°F RX121 "C" SG NR Controlling Channel fail low (FT539) 60 sec 4 0%
SG03B 'B' SG Tube Leak 90 sec 7 0.3 gpm Page 9 of 74
S,- _ I-ION 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS
-~~~ ------- -~~~
Delay Ramp Event Severity Final Relative 10 Number Description Time Time Trigger Or Value Value Order MS01B Steam line break in CTMT from the 'B' SG. 10 sec 10 1.5E6 Ibm/hr I SG01B 'B' SG Tube Rupture 11 1000 gpm
~. ~
REMOTE FUNCTIONS ~ ~
I RXR 109 Protection Set #4 2 OPEN RXR04 Loop 4 OP~ T Bistable 3 TRIP RXR33 Loop 4 C-4 Bistable 20 sec 3 TRIP j RXR08 Loop 4 OT~T Bistable 40 sec 3 TRIP RXR37 Loop 4 C-3 Bistable 60 sec 3 TRIP RXR 113 Loop 4 Low Tavg Bistable 80 sec 3 TRIP RXR 117 Loop 4 P-12 Bistable 100 sec 3 TRIP
- RXR 109 Protection Set #4 120 sec 3 CLOSE RXR 106 Protection Set #1 5 OPEN RXR96 LS 539A (P-14) 6 TRIP RXR84 LS 539B (LO-LO Level) 20 sec 6 TRIP RXR 106 Protection Set #1 40 sec 6 CLOSE I
MSR 01 Aux Boilers 8 ON Page 10 of 74
SL ."ION 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS
~- ----~~-- --~~ ~---~----~~ ~~--
Delay Ramp Event Severity Final Relative ID Number Description Time Time Trigger Or Value Value Order FWR33,62 3CNS-V9, V11 9 CLOSE EDR18 Resets MCC 32-3T 12 RESET EDR44 Acknowledges Inverter 6 Alarms 120 sec 12 RESET
~-
RCR23 -26 RCP Overcurrent Switch Position 13 COLD
~-~
~ ~- ~ ~-~
~-~ ~-~
f--
OVERRIDES
---~~ ~--
EGLOOOO1 'A' EDG Pre-Lube Pump 'red' OFF ,
EGLOOOO2 'A' EDG Pre-Lube Pump 'green' OFF
~-~
EGLOOO12 'A' EDG Output Breaker 'green' OFF Initial *
~-~
EGLOOO13 'A' EDG Output Breaker 'red' OFF Initial
--~
EGLOOO14 'A' EDG Output Breaker 'amber' OFF Initial
~-~
Page 11 of 74
S... dON4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew. Go over the Plant/simulator differences, which follow.
Booth Instructor: IF desired by the NRC Exam Team, commence recording Simulator session Booth Instructor: Perform the crew turnover (Initial Conditions page at end of LP) with the US. Have the US brief his crew on plant conditions and any major equipment OOS.
PLANT/SIMULATOR DIFFERENCES:
- Rad Monitor Historical Oata--Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.
- If not using the speed dial option on the phone system, the operator must dial either #3333 or #3334 to reach the person/department they desire.
- The following PPC programs do not function on the simulator:
- Samarium Follow
- Xenon Follow
- Sequence of Events
- Flow indications 3SIH-F1917 (charging ECCS flow), 3SIH-F1918 (A SI pump flow) and 3SIH-F1922 (8 SI pump flow) will show flow at low flow rates.
Page 12 of 74
SEc.. .. IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time 10A/Malf Instructor Information/Activity Assign Expected Action Standard Event 1: Loop 4 Tavg fails high T+1 min of RX050 Loop 4 narrow range Th, turnover 3RCS*TE441A Trigger 1 Tave will fail high. Rods will drive in.
Delta T for "0" Loop will go up.
AOP 3571 (Rev. 009-07) Actions US Transition to AOP 3571, Instrument Failure Response The RO will place Rod Control in CREW Determine the initiating parameter and AOP 3571 manual; PZR level control is already place the effective controller in manual. Step 1 at 100% program. Steam Dumps not armed so no immediate impact CREW Stabilize the plant parameters. AOP 3571 Step 2 The US should recognize the correct US Perform Corrective Actions Using AOP 3571 attachment is 'A' and announce as Appropriate Attachment Step 3 such.
Instrument Failure Attachment RCS NR Temperature Channel Failure A After discussing the expected RO Defeat the failed channel input. AOP 3571 response, the US should direct the RO Att.A Step 1 to place the cutout switches in loop 3 Loop Temp Cutout - delta T and pull out.
Loop Temp Cutout - Tavg Page 13 of 74
SEC ..JN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit~ .._.A.!,sign Expected Action Standard Expected response is as follows: OT/OP delta T Record Select TREF/AUCT TAVE DEVIATION and TAVE HI should clear when loop Temp Cutout for TAVG is pulled out.
Check the following annunciators NOT AOP 3571 LIT: Att.A Step 2 TREF/AUCT TAVE DEVIATION MB4C 6-5 TAVE HI MB4C 5-6 No action may be required RO Restore TAVE - T REF error to within 1 AOP 3571 depending on when crew placed Att.A Step 3 OF and return rod control to automatic.
rods in manual.
RO Monitor PZR level until stable. If PZR AOP 3571 levei controller is in manual, Restore Att.A Step 4 pressurizer level to program level and Place PZR level controller in automatic.
NA If RCS loop 3 cold leg narrow range AOP 3571 temperature channel computer point Att.A Step 5 (RCS-T431E) is X-tagged, the plant Note calorimetric program will automatically shift to an NI based output.
CREW When conditions have stabilized, AOP 3571 Observe MB annunciators and Att.A Step 5 parameters. Immediately report any unexpected or unexplained conditions to the Shift Manager.
Page 14 of 74
SEC .. IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US Trip the associated Reactor Protection AOP 3571 System bistable(s): Att.A Step 6 US Place a check mark in the box above AOP 3571 the appropriate channel that requires Att.A Step 6a tripping on page 6 of this Attachment.
Table 3.3.1 - FU 6, 8 Action 6 applies USI Refer to Technical Specification 3.3.1 AOP 3571 Table 3.3.2 - FU 50 Action 20 applies and 3.3.2. Att.A Step 6b SM These are 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> requirements to trip bistables.
Expect the RO to do a lamp test of MB2 RO Check the existing bistable status to AOP 3571 and MB4. ensure a reactor trip will not occur when Att.A Step 6c the failed channel is tripped.
CREW If the General Warning lamp is lit on AOP 3571 3RPS*RAKLOGB, Placing train A SSPS Att.A Step 6.d "Multiplexer Test" switch in "A+B" will CAUTION cause the reactor to trip.
Failure is not SSPS CREW The following step will distinguish AOP 3571 whether the failure is within SSPS or the Att.A Step 6d Protection channel. NOTE Channel indication is NOT normal. Step If bistable light(s) (MB2D or MB4F) AOP 3571 6.d is N/A. indicate that a single bistable input has Att.A Step 6d tripped and channel indication is normal, PERFORM the following ....
T=2 mins of RXR109 Protection Set 4 Door Request the I&C Department trip the AOP 3571 request 'OPEN' appropriate bistables using Attachment Att.A Step 6e A and Attachment S.
Trigger 2 Page 15 of 74
SEt. ..IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard T=3 mins of Will trip bistables (with 20 second time RO Verify the appropriate bistable status AOP 3571 request delays between each bistable) and light(s) are lit. Att.A Step 6f Trigger 3 close the door.
RXR04 (trip) TRIP* OP DELTA T RXR33 (trip) TRIp* C-4 RXR08 (trip) TRIp* OT DELTA T RXR37 (trip) TRIP* C-3 RXR113 (trip) TRIp* Low Tave RXR117 (trip) TRIP - P-12 RXR109 (close) CLOSE - Protection Set 4 door Once the US has addressed Tech Specs and bistables are tripped, move on to EVENT 2.
EVENT 2: "e" SG NR Level Controlling Channel fails Low T= Bistables RX121, "C" SG Narrow Range Level Crew should enter AOP 3571, "Instrument tripped (0%.60 Transmitter Fails low over 60 Failure Response."
sec ramp) seconds.
Trigger 4 AOP 3571 Actions (rev 009-07)
RO Do not leave the rod selector switch in AUTO AOP 3571 Page 16 of 74
SEC, .. IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign __ E:.xpected Action Standard while diagnosing a related instrument failure Step 1 unless the reason for rod movement is a CAUTION turbine runback.
MB Annunciator "SG C LEVEL CREW If a reactor trip occurs, immediately go to E-O AOP 3571 DEVIATION" will be the first to alarm. Reactor Trip or Safety Injection. Step 1 NOTE US Determine The Initiating Parameter And AOP 3571 "c" Feed Reg. Valve is the affected Place The Affected Controller In MANUAL. Step 1 Controller. The BOP should take the "C" Feed Reg. Valve Controller to
'Manual'.
CREW Stabilize The Plant Parameters. Step 2 US It is desired that I&C personnel trip the AOP 3571 bistables ... Step 3 NOTE Appropriate Attachment is "N" Perform Corrective Actions Using Appropriate AOP 3571 Attachment Step 3 Instrument Failure Attachment Narrow Range SG Level Channel Failure N If the failed NR level channel is selected as AOP 3571 the input to SG level control, Perform the Attachment following: N Step 1 The BOP should have already placed BOP Verify the affected SG feed regulating valve is AOP 3571 the 'C' SG feed regulating valve in in MANUAL. Att. N MANUAL. Step 1.a BOP should restore level to 50% BOP Restore SG level to normal. AOP 3571 Att. N Page 17 of 74
SEc.. .. IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Step 1.b The US should direct the BOP to BOP Defeat the failed channel input by selecting AOP 3571 select channel 2 as the controlling the alternate channel on the level selector. Att. N channel. Step 1.c BOP When SG level is restored to normal and AOP 3571 feed/steam flow are matched, Place the Att.N affected steam generator feed regulating Step 1.d valve controller in AUTO.
CREW When conditions have stabilized, observe MB AOP 3571 annunciators and parameters. Immediately Att.N report any unexpected or unexplained Step 1.e conditions to the Shift Manager.
US Trip the associated Reactor Protection AOP 3571 System bistable(s): Att.N Step 2 US Place a check mark in the box above the AOP 3571 appropriate channel that requires tripping on Att.N the last pages of this Attachment. Step 2a Crew should log into 3.3.1, FU 13, SM/US Refer to Technical Specification 3.3.1, 3.3.2, AOP 3571 action 6 3.3.3.5 and 3.3.3.6. Att.N Step 2.b 3.3.2, FU 6.c, action 20 (3.3.2 FU 5.b I action 21 is for < minimum channels, which is not the case)
Channels operable requirements for 3.3.3.5 and 3.3.3.6 are met. However the US should verify that they don't apply.
RO Check the existing bistable status to ensure a AOP 3571 reactor trip will not occur when the failed Att.N channel is tripped. Step 2.c Page 18 of 74
SEL ,.IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard This will not be applicable If bistable status light(s) (MB2D or MB4G) AOP 3571 indicate that a single bistable input has Att. N tripped and channel indication is normal, Step 2.d PERFORM the following:
Annunciator "SG LEVEL HI HI" comes in during the tripping of B/Ss.
The task of tripping bistables was already conducted for the Tave failure. At the examiner's discretion, once Tech Specs are addressed, move on to Event 3, without tripping bistables.
T=2 mins of RXR 106 Protection Set 1 Door US Request the IC&E Department trip the AOP 3571 request 'OPEN' appropriate bistables using Attachment Nand Att.N Attachment S. Step 2.e Trigger 5 RXR96 HI HI Level for SG 3, then T=3 mins of
'TRIP' request RXR84 LO LO Level SG 3, til en Trigger 6 'TRIP' RXR 106 protection set 1 door
'CLOSE' RO Verify the appropriate bistable status lights AOP 3571 are lit Att N Step 2.f Not Applicable as LT539 is failed US If any two of the NR level channels which AOP 3571 serve as inputs to AMSAC are failed (LT- Attachment 551, LT-552, LT-538, or LT-547), Perform N step 3 Page 19 of 74
SEL .ON 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activi!y Assign Expected Action Standard the following:
NA If either indicator 3FWS*LI 529A or AOP 3571 3FWS*LI 548A is failed, Refer to TRM Table Attachment 7.4.1, Fire Related Safe Shutdown N step 4 Components, "Auxiliary Feedwater System."
US/SM Request I&C Department perform AOP 3571 corrective maintenance on failed Attachment instrument. N step 5 Event 3: 'B' SG Tube Leak (AOP 3576), and subsequent procedurally required rapid downpower.
T=AOP SG03B, SIG B TUBE LEAK, - 410 gpd 3571 sev 0.3 complete or gpm, 90 examiner's sec ramp}
cue Trigger 7 Indications of the tube leak includes ARC-21 going into ALERT then ALARM, as well as N-16 ALERT and N 16 HIGH.
Entry conditions are met for AOP 3576.
The US should announce and enter Page 20 of 74
SEL .ON 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard AOP 3576.
AOP 3576 Actions (Rev 004-02)
Foldout Page must be open. 3576 Step 1 NOTE Step 1 is a continuous action step and should be performed at any time additional charging flow is required to maintain pressurizer level.
Verify PZR Level 3576 Step 1 The leak rate is small enough such that RO Check PZR Level - DECREASING 3576 minimal adjustment of the charging flow Step 1.a control valve will be necessary.
Proceed to step 2. 3576 Step 1.a RNO Fully Open charging line flow control valve 3576 Step 1.b Check letdown orifice isolation valves - ONLY 3576 ONE OPEN Step 1.c Check PZR level- DECREASING 3576 Step 1.d Proceed to step 1.g 3576 Step 1.d RNO Page 21 of 74
SEL .ON 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Adjust charging flow control valve to maintain 3576 PZR level on level setpoint. Step 1.g If desired, Place charging line flow controller 3576 in AUTO. Step 1.h Notify Chemistry 3576 Step 2 Request Chemistry perform SP 3861, 3576 "Primary to Secondary Leak Rate Step 2.a Determination," to:
- 1. Determine the presence of primary to secondary leakage.
- 2. Determine the leak rate.
- 3. Identify the leaking SG.
SG tube leakage can be interpreted as 3576 "verified" when any two of the bulleted Step 3 substeps of step 3 are satisfied. NOTE Primary To Secondary Leakage will be Verify Primary To Secondary Leakage 3576 verified based on N-16 Monitoring Step 3 System and abnormal trends on ARC 21.
- Check trend history and alarm status of 3576 condenser air ejector radiation monitor Step 3 NOT NORMAL
- Check trend history and alarm status of steam generator blowdown radiation monitor - NOT NORMAL Page 22 of 74
SEc... .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
- Check trend history and alarm status of main steam line radiation monitors - NOT NORMAL
- Check Chemistry grab sample INDICATES PRESENCE OF PRIMARY TO SECONDARY LEAKAGE
- Check trend history and alarm status of N16 monitors - NOT NORMAL Perform Monitoring Of N16 Monitor Trends 3576 Step 4 Initiate monitoring of N16 monitor trends 3576 Step 4.a Verify SG Blowdown Status 3576 Step 5 Blowdown will need to be isolated Check if blowdown should be isolated 3576 based on N-16 HIGH in alarm. Step 5.a
- Condenser air ejector radiation monitor ALARM OR
- Steam generator blowdown radiation monitor - IN ALARM OR
- Chemistry grab sample indicates primary to secondary leakage - GREATER THAN OR EQUAL TO 75 gpd Page 23 of 74
SEt. ')N 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity_... J\!isi911 Expected Action Standard OR
- Annunciator N16 HIGH (MB2B 3-6A) -IN ALARM Check SG blowdown isolation valves 3576 CLOSED Step 5.b
- 3BDG-CTV22D The BOP will need to close the SG CLOSE valves. 3576 blowdown isolation valves. Step 5.b RNa Proceed to step 6. 3576 Step 5.c Limit Effects Of Secondary Contamination 3576 Step 6 Check auxiliary steam - SUPPLED FROM 3576 MAIN STEAM Step 6.a Using OP 3331A, "Auxiliary Boiler, Steam and 3576 Condensate" Perform the following: Step 6.b T=when MSR01 to This will start the Aux Boilers. 1. Startup of auxiliary boiler A (B) directed 'ON' Trigger 8 Page 24 of 74
SE(;'JN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
- 2. Shift auxiliary steam from main steam to auxiliary boiler system.
Notify Unit 2 of auxiliary steam status. 3576 Step 6.b RNO This will close 3CNS*V9 & 3CNS* Locally Close condensate T= 5 min FWR33,62 recirculation to condensate 3576 from being to 'CLOSE' V11, and then ..... Step 6.c surge tank isolation valves dispatched (3CNS-V9 and 3CNS-V11)
Trigger 9 BOOTH Report as PEO that 3CNS*V9 & Request HP determine if personnel should be 3576 3CNS-V11 are closed evacuated from affected areas Step 6.d T=when BOOTH Report as HP that surveys will be
- Turbine Bldg (north end) called taken to determine if these areas are safe.
- Secondary sample sink
- MS Valve Bldg Evacuate personnel from affected areas 3576 Step 6.e Examiner Inform the US that the SM will Refer Refer to C OP 200.11, "Operation of a Cross 3576 to C OP 200.11. Contaminated System," and Perform any Step 6.f required actions Check If Unit Shutdown Should Be Initiated 3576 Step 7 Page 25 of 74
SEC,.,vN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Check any of the following: 3576 Step 7.a
- Condenser air ejector radiation monitor IN ALARM OR
- Chemistry grab sample indicates primary to secondary leakage in any SG GREATER THAN OR EQUAL TO 75 gpd OR
- Condenser air ejector radiation monitor correlation to leak rate (gpd) indicates primary to secondary leakage - GREATER THAN OR EQUAL TO 75 gpd OR
- Annunciator N-16 HIGH (MB2B 3-6A) -IN ALARM Examiner Inform the US that the SM will Evaluate event using MP-26-EPI-FAP06-003, 3576 evaluate for classification. Unit 3 Emergency Action Levels (Barrier Step 7.b Failure)
Check plant status - MODE 1 OR 2 3576 Step 7.c A plant shutdown will be required based Proceed to step 9. 3576 on N-16 HIGH in alarm. Step 7.d The US should proceed to the 'Perform Unit Shutdown' step 9.
Page 26 of 74
SE~ ..IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Perform Unit Shutdown 3576 Step 9 T = brief for Report as chemistry "8" S/G sample Verify a leakage rate of increase limit met: 3576 plant results indicate the presence of Step 9.a shutdown primary to secondary leakage.
occurs
- Check leakage increased in any SG by GREATER THAN OR EQUAL TO 15 gpd IN A 30 min PERIOD AFTER THE INITIAL SPIKE OR
- Check condenser air ejector radiation monitor RATE OF CHANGE ALARM -IN ALARM OR Rate of Increase limit NOT met, but
- Check N 16 S/G Leak Detection Status leakage> 150 gpd (PPC) HIGH RATE (75 GPO & 15 GPO RISE IN 30 MIN) - IN ALARM Proceed to step 9.c 3576 Step 9.a RNO Check charging pumps - TWO REQUIRED 3576 TO MAINTAIN PZR LEVEL Step 9.c Proceed to step 9. i 3576 Step 9.c RNO Page 27 of 74
SEt ')N 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDAlMalf Instructor Information/Activity Assign Ex:pected Action Standard Check SG leakage: 3576 Step 9.i
- Condenser air ejector radiation monitor IN ALARM OR Ensure The US enters the LCO for
- Chemistry grab sample indicates any SG 3.4.6.1, OPERATIONAL LEAKAGE for leakaage - GREATER THAN OR EQUAL primary to secondary leakage (150 gpd, TO 150 gpd 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AOT to hot standby).
- N16 S/G Leak Detection Status (PPC)
HIGH HIGH (>150 GPO) - IN ALARM
=
T Calls the BOOTH Direct as OMOC to commence a Initiate power reduction to be in MODE 3 3576 OMOC rapid load reduction in accordance within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />. Step 9.j with AOP 3575, Rapid Downpower, at 3%/min.
Check plant status - MODE 3 3576 Step 9.k Return to NOTE prior to step 9. 3576 Step 9.k RNO AOP 3575 Actions (Rev 017-03)
If at any time either of the following AOP 3575 annunciators is received, Immediately perform Step 1 Page 28 of 74
SEC, .. IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malt Instructor Information/Activity Assign Expected Action Standard step 7: NOTE
);> ROD CONTROL BANKS LIMIT LO (MB4C 3-9)
);> ROD CONTROL BANKS LIMIT LO-LO (MB4C 4-9)
Rod Control will be in Auto. Check Rod Control-IN AUTO AOP 3575 Step 1 Align EHC Panel AOP 3575 Step 2 The crew may perform down power on Check load reduction using load set AOP 3575 load limit or load set. Either is DESIRED Step 2.8 acceptable.
Proceed to Note prior to step 3. AOP 3575 Step 2.a RNO Using Attachment E align EHC panel for AOP 3575 LOAD SET operation. Step 2.b CONVEX requested load reductions should be AOP 3575 performed at 5%/min and completed within 15 Step 3 minutes of notification. NOTE CREW Determine Power Reduction Rate (%/min). AOP 3575 Step 3 The load reduction should be performed Check desired power reduction rate - 3% I AOP 3575 at 3%/min as directed by Plant min OR 5% I MIN Step 3.a Management.
If SI actuation occurs during this procedure, AOP 3575 Page 29 of 74
SEL .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Go to E-O, Reactor Trip or safety Injection, Step 4 and restore from rapid boration lineup. CAUTION RO Initiate Rapid Boration AOP 3575 Step 4 Verify RCS makeup system in - AUTO AOP 3575 Step 4.a START one boric acid transfer pump. AOP 3575 Step 4.b OPEN emergency boration valve AOP 3575 (3CHS*MV81 04). Step 4.c RO Verify direct boric acid flow (3CHS-FI 183A) AOP 3575 INDICATED. Step 4.d OPEN charging line flow control valve, to AOP 3575 match boric acid flow (3CHS-FI 183A) Step 4.e RO Record time boration started AOP 3575 Step 4.f Time - - - - - -
Check Rod Control- AVAILABLE FOR ROD AOP 3575 INSERTION Step 4.g Check use of "Rapid Downpower Summary AOP 3575 Sheet" (RE-H-17) in the RE Curve and Data Step 4.h Book - DESIRED Proceed to step 4.k. AOP 3575 Step 4.h.
RNO About 19 minutes if "Rapid Downpower Using the "Rapid Downpower Summary AOP 3575 Page 30 of 74
SEtt IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Summary Sheet" is used. Sheet" (RE-H-17), Determine approximate Step 4.i boration time Proceed To step 6. AOP 3575 Step 4.j Use 18 gal BN% Power to determine boration AOP 3575 time in step 4.1 Step 4.k Using formula, Determine boration time AOP 3575 gravity borating, use net charging flow (chg + Step 4.1 seal inj-seal return total flow) for BA flow rate:
Total Power Change (1\ %) X (gal BN% = min Power)
BA Flow Rate Boration Time Proceed to step 6. AOP 3575 Step 4.m If at any time the power reduction rate or final AOP 3575 desired power level must be changed, Return Step 6 to step 1. NOTE US/BOP Initiate Load Reduction AOP 3575 Step 6 US Check Rapid or gravity boration - IN AOP 3575 PROGRESS Step 6.a Check turbine OPERATING MODE AOP 3575 Page 31 of 74
SEL IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit}'. Assign Expected Action Standard MANUAL Step 6.b Check load reduction using load set AOP 3575 DESIRED Step 6.c Perform the following: AOP 3575 Step 6.c
- 1) Using Attachment F, Rotate LOAD RNO LIMIT SET in CCW direction consistent with desired down power schedule.
- 2) Proceed to step 6.f.
3% should be selected. Select LOAD RATE LIMIT %/MIN to the AOP 3575 desired value (1%, 3%, or 5%) Step 6.d The BOP should adjust Load Set to Utilizing DECREASE LOAD pushbutton, AOP 3575 about 300 MWe. Adjust LOAD SET to desired final MWe Step 6.e Energize all PZR heaters AOP 3575 Step 6.f Adjust Pzr Spray Valves to 50% setpoint AOP 3575 (RCS-PK 455B and RCS-PK 455C) Step 6.g Adjust boration time and/or flow rate as AOP 3575 necessary to maintain:
Step 6.h
- Rods above the Rod Insertion Limit (RIL)
- Tavg within +/-5_F of Tref
- AFD within COLR limits Check rapid OR gravity boration performed AOP 3575 for the time determined in steps 4.i. or 4.1. Step 6.i Page 32 of 74
SEt, ..ON 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Proceed to step 6.k. and, WHEN Boration has AOP 3575 been performed for the desired time, THEN Step 6.i Using Attachment G, stop boration. RNO Using Attachment G, stop boration AOP 3575 Step 6.j Check power reduction - CONVEX AOP 3575 REQUESTED Step 6.k Inform CONVEX of load reduction rate AOP 3575 (MWe/min) and final MWe level. Step 6.k RNO Verify Rod Position Above RIL AOP 3575 Step 7 Check ROD CONTROL BANKS LIMIT LO-LO AOP 3575 (MB4C 4-9) annunciator - LIT Step 7.a Proceed to step 7.g and, IF at any time, the AOP 3575 annunciator is received, Step 7.a RNO THEN Perform steps 7.c, 7.d and 7.e Check ROD CONTROL BANKS LIMIT LO AOP 3575 (MB4C 3-9) annunciator LIT Step 7.g Proceed to step 8 and AOP 3575 Step 7.g IF the annunciator is received, RNO THEN Perfrom step 7.h and 7.i Page 33 of 74
(
SE~ ')N 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Using Attachment C, "Rapid Downpower AOP 3575 Parameters" MONITOR parameters Step 8 Degrade Condenser Backpressure AOP 3575 Step 9 Verify Final Desired Turbine Load (MWe) AOP 3575 LESS THAN 72% 972 MWe) Step 9.a Using OP 3329, "Condenser Air Removal", AOP 3575 Degrade condenser backpressure to between Step 9.b 2.0 in. HgA and 4.0 in. HgA.
T= When the Examiners are satisfied Examiners with the reactivity manipulation, Cue move on to the next event.
Event 4: '8' main steam line break in CTMT.
T= MS01B This will intiate the Steamline Examiners break in CTMT from the fB' SG.
Cue 1.5E6,10 sec Trigger 10 The break will be severe enough to require a Reactor Trip and Safety Injection, and a Reactor Trip 'First Out' will be reCeiVed prior to the crew taking action. Automatic and the MB7 manual reactor trip switch are failed requiring the RO to manually trip the reactor from MB4 [Critical Task] [*].
Page 34 of 74
SEC .. IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard The US should direct a manual reactor trip and safety injection.
NOTE: US should go to "Master Silence" before ordering reactor trip.
E-O (Rev. 026) STEPS Crew
- Foldout page must be open E-O, Step 1, NOTE
- ADVERSE CTMT defined as GREATER THAN 180°F or GREATER THAN 105 R/hr in containment.
- The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.
EVENT 5: Automatic and MB7 manual reactor trip switch fail.
RO Verify Reactor Trip E-O, Step 1
- Check reactor trip and bypass breakers - OPEN
- Check rod bottom lights - LIT
- Check neutron flux - DECREASING A Reactor First Out annunciator is in. RO TRIP the reactor. E-O, Page 35 of 74
SEt. IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/ActivitL ._ J.\ssigl"!.. Expected Action Standard the RO should trip the reactor manually Step 1, from MB4. [*] [Critical Task] RNO
[*]
Verify Turbine Trip E-O, Step 2 Check all turbine stop valves - CLOSED E-O, Step 2.a BOP Verify Power to AC Emergency Busses E-O, Step 3 BOP Check busses 34C and 340 - E-O, Step 3.a BOTH ENERGIZED The crew should have manually US Check If 51 Is Actuated E-O, Step 4 initiated 51.
RO Verify SAFETY INJECTION ACTUATION E-O, annunciator - (MB4D 1-6 or MB2B 5-9) - LIT Step 4.a US Check if SI is required E-O, Step 4.a, RNO
- PZR pressure LESS THAN 1890 psia OR
- PZR level LESS THAN 9%
Page 36 of 74
SELJN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activit"l_ ._ Assign Expected Action Standard OR
- SG pressure LESS THAN 660 psig Check Reactor trip and bypass breakers E-O, OPEN Step 4.c 800TH NOTE: Monitor "8" SG WR level. RO Verify Service Water Pumps - AT LEAST E-O, Step 5 When it reaches 10% Insert the ONE PER TRAIN RUNNING SGTR malfunction START pump(s) E-O, Step 5, RNO RO Verify Two RPCCW Pumps* ONE PER E-O, Step 6 TRAIN RUNNING EVENT 7: HPSI components fails to Auto-Actuate.
RO Verify ECCS Pumps Running E-O, Step 7 RO manually should manually start
- Check SI pumps - RUNNING the 51 pumps. The CCI pumps (51 pump cooling) should start when the 51 pumps are started. In addition, 3SIH*MV8801A and 8 (Charging Cold Leg Injection valves) will need to be OPENED.
- Check RHR pumps - RUNNING Page 37 of 74
SEt:..JN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
- Check two charging pumps - RUNNING BOP Verify AFW Pumps Running E-O, Step 8 Check MD pumps - RUNNING E-O, Step 8.a Check turbine - driven pump - RUNNING, IF E-O, NECESSARY Step 8.b The BOP should isolate feed to the BOP Verify FW Isolation E-O, Step 9 faulted SG as soon as identified.
- Check SG feed regulating valves CLOSED
- Check SG feed regulating bypass valves CLOSED
- Check FW isolation trip valves - CLOSED
- Check TO FW pump - TRIPPED
- Check SG blowdown isolation valves CLOSED
- Check SG blowdown sample isolation vaives - CLOSED
- Check SG chemical feed isolation valves CLOSED BOP Align component(s) as necessary for minimum E-O, Step 9 Page 38 of 74
SEl ')N 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDAlMalt Instructor Information/Activity ~ssig",--._ _ E)(pected Action Standard safety function. RNO EVENT 6: Main Steamline Isolation fails to automatically actuate.
[*] Critical Task - The BOP needs to BOP Check If Main Steam Lines Should Be E-O, Isolated Step 10 initiate a manual MSI from main board 5.
Check Ctmt pressure GREATER THAN 18 E-O, psia Step 10.a OR Any SG pressure LESS THAN 660 psig OR Annunciator "MAIN STEAMLINE ISOLATION" (MB2B 5-7) - LIT Verify MSIVs and MSIV bypass valves E-O, CLOSED Step 10.b BOP Initiate MSI. E-O, Step 10.b, RNO [*]
Check ESF Group 3 lights - LIT. E-O, Step 10.c CTMT pressure will ultimately reach RO Check if CDA Required E-O, the CDA setpoint. Step 11 Check Ctmt pressure is GREATER THAN 23 E-O, psia Step 11.a Page 39 of 74
SEt ,IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit~ __Assign .._ Expected Action Standard OR Annunciator "CONTAINMENT DEPRES ACTUATION" (MB2B 5-5) LIT US Proceed to Step 12. E-O, Step11,a, RNO BOP Verify CAR Fans Operating In Emergency E-O, Mode Step 12 BOP Check CAR fan status: E-O, Step 12.a
- CAR fans A and B - RUNNING
- CAR fan C - STOPPED BOP START/STOP CAR fans as necessary. E-O, Step 12.a, RNO RO Verify RPCCW Ctmt supply and return header E-O, isolations - OPEN Step 12.b RO Verify Train A and B RPCCW supply and E-O, return to chill water valves - OPEN Step 12.c RO Verify CIA E-O, Step 13 RO Check ESF Group 2 status columns 2 through E-O, 10 - LIT Step 13.a RO Verify Proper ESF Status Panel Indication E-O, Page 40 of 74
SEt. .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Step 14
- Verify ESF Group 2 lights - LIT and B (Charging Cold Leg Injection valves).
CTMT will be Adverse on RO Determine If ADVERSE CTMT Conditions E-O, temperature. Exist Step 15
- Ctmt temperature GREATER THAN 180°F OR 5
- Ctmt radiation GREATER THAN 10 RO Verify ECCS Flow E-O, Step 16 Check PZR pressure - GREATER THAN E-O, 1900 psia Step 16.a Proceed to step 16.d. E-O, Step 16.a RNO Check PORV block valves - OPEN E-O, Step 16.b Proceed to step 17. E-O, Step 16.c Check charging pumps E-O, Step 16.d FLOW INDICATED Page 41 of 74
SEt. .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO START pumps and Align valves. E-O, Step 16.d, RNO RO Check RCS pressure - GREATER THAN 1650 E-O, psia (1950 psia ADVERSE CTMT) Step 16.e US Proceed to Step 17 E-O, Step 16.e, RNO Check SI pumps - FLOW INDICATED E-O, Step 16.f START pumps and Align valves. E-O, Step 16.f RNO Check RCS pressure - LESS THAN 300 psi a E-O, (500 psia ADVERSE CTMT) Step 16.g Proceed to step 17. E-O, Step 16.g RNO Check RHR pumps - FLOW INDICATED. E-O, Step 16.h START pumps and Align valves. E-O, Step 16.h RNO CREW should perform a short brief and come out of "Master Silence" at the completion of Step 16.
Page 42 of 74
SEL ')N 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Check NR level in at least one SG - E-O, GREATER THAN 8% (42% ADVERSE Step 17.a CTMT)
US Proceed to Step 17.d. E-O, Step 17.a, RNO BOP Verify Total AFW Flow - GREATER THAN E-O, 530 gpm Step 17.d BOP Verify AFW Valve Alignment - PROPER E-O, EMERGENCY ALIGNMENT Step 18 RO Verify ECCS Valve Alignment - PROPER E-O, EMERGENCY ALIGNMENT Step 19 Check if CBI is required E-O, Step 20 RO Check CONTROL BUILDING ISOLATION E-O, annunciator (MB4D 3-6) - LIT Step 20.a RO Check if CBI is required E-O, Step 20.a, RNO RO
- Control Building radiation monitor in alarm OR Page 43 of 74
SEt.. .')N 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit~~ssign Expected Action Standard
US IF CBI is NOT required, THEN Proceed to Step 20.g.
Check Train A Control Building filter fan E-O, (3HVC*FN1A) - RUNNING Step 20.b Check recirc damper for the running E-O, Control Building filter fan Step 20.c (3HVC*AOD119A or 8) OPEN RO Verify ESF Group 2 CBI lights - LIT E-O, Step 20.d RO Align HVAC components as necessary for E-O, minimum safety function. Step 20.d, RNO BOP Verify control building purge supply fan and E-O, purge exhaust fan - NOT RUNNING Step 20.e BOP Place kitchen exhaust fan in OFF E-O, Step 20J T=When BOOTH When asked, REPORT that "all SLCRS US Verify SLCRS doors - CLOSED E-O, Page 44 of 74
SEt .ON 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDAlMalf Instructor Information/Activity Assign Expected Action Standard called as doors indicate closed." Step 20.g SSS Perform the following: E-O, Step 20.h T=When BOOTH When called, WAIT 3 - 5 min, Then PEO CLOSE and DOG the following Control called as REPORT "Control Building pressure Building pressure boundary doors.
PEO boundary doors are Closed and Dogged or verified closed as directed."
- CB west 47'6" (C-47-1A)
- CB east 64' 6" (C-64-1B)
Verify the following Control Building pressure boundary doors - CLOSED
- CB west 47'6" (C-47-1)
- CB north 64'6" chiller room door (C 64-4)
- CB north 64'6" chiller room door (C 64-5)
Event 8: Hot, dry '8' SG results in
T = "B" SG SG01B, At 10% WR level, the 'B' SG will be RO Check RCS Temperature E-O, WR level sev=1000 hot and dry. Malfunction insertion Step 21 reaches 10% gpm will rupture the 'B' SG.
Trigger 11 Page 45 of 74
SEL .0N 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP Using GA-26, Dump steam as necessary to E-O, control RCS cold leg WR temperature Step 21.a BETWEEN 550°F AND 560°F RCS cold leg WR temperature will be BOP Verify RCS cold leg WR temperature E-O, less than 550°F GREATER THAN 550°F Step 21.b Proceed to step 21.d. E-O, Step 21.b RNO BOP Maintain total feed flow BETWEEN 530 and E-O, 600 gpm until NR level is GREATER THAN Step 21.d 8% (42% ADVERSE CTMT) in at least one SG BOP CLOSE SG atmospheric relief and relief E-O, bypass valves Step 21.e BOP Check the following valves - CLOSED E-O, Step 21.f
- MSIV bypass valves Check Power To SBO Diesel Auxiliaries E-O, Step 22 Yes, breaker 34A1-2 will be closed.
Verify any SBO bus tie breaker - CLOSED TO E-O, AN ENERGIZED BUS Step 22.a
- Bus 34A: 34A 1-2
- Bus 34B: 34B1-2
- Bus 24E: A505 (Unn2)
Page 46 of 74
SEL .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity_ Assign Expected Action Standard RO Check PZR Valves E-O, Step 23 Verify PORVs - CLOSED E-O, Step 23.a RO Verify normal PZR spray valves - CLOSED E-O, Step 23.b RO Verify PORV block valves - AT LEAST E-O, ONE ENERGIZED VALVE OPEN Step 23.c RO Verify PZR safety valves - CLOSED E-O, Step 23.d CREW To prevent seal damage, seal injection flow E-O, should be maintained to all RCPs. Step 24, CAUTION RO Check If RCPs Should Be Stopped E-O, Step 24 Verify RCPs - ANY RUNNING E-O, Step 24.a RO Verify RCS pressure - LESS THAN 1500 psia E-O, (1800 psia ADVERSE CTMT) Step 24.b US Proceed to Step 25 E-O, Step 24.b, RNO Verify either of the following:
RO E-O, Step 24.c Page 47 of 74
SEt. .ON 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/ActivitL~_ Assig_n__ ~~ __ Expected Action Standard
- Charging pumps AT LEAST ONE RUNNING AND AT LEAST ONE COLD LEG INJECTION VALVE OPEN OR
- SI pumps - AT LEAST ONE RUNNING RCS pressure will eventually lower RO STOP all RCPs E-O, to < 1500 psia. Crew should identify Step 24.d this and trip all RCPs.
BOP Check If SG Secondary Boundaries Are E-O, RO Intact Step 25 Check pressure in all SGs E-O, Step 25.a
- NO SG COMPLETELY DEPRESSURIZED US Initiate monitoring of CSF Status Trees and E-O, Go to E-2, Faulted Steam Generator Isoiation. Step 25.a RNO The US should announce and make the transition to E-2.
Page 48 of 74
SEL .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard E-2, Faulted Steam Generator US At least one SG must be maintained available E-2 Isolation, Rev. 011 for RCS cooldown. CAUTION US Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown or sampling is required.
US If RWST level decreases to LESS THAN 520,000 gal, Go to ES-1.3, Transfer to Cold Leg Recirculation, to align the ECCS system.
BOP Check Main Steam Isolation And Bypass E-2, Step 1 Valves - CLOSED US US Check at least one SG boundary intact. E-2, step 2 ROJ Check pressures in all SGs - AT LEAST ONE E-2, step BOP STABLE OR INCREASING 2.a US Identify Faulted SGS E-2, Step 3 The'S' SG will be depressurized. ROI Check pressure in all SGs E-2, Step BOP 3.a ANY SG PRESS DECREASING IN AN UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED If the TD AFW pump is the only available E-2, Step 4 source of feed flow, a steam supply to the TD CAUTION AFW pump must be maintained from at least Page 49 of 74
SEtJN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malt Instructor Information/Activity Assign Expected Action Standard one steam generator rl [Critical Task] Isolate the ROt Isolate each faulted SG. E-2, step 4 faulted S/G before transition out BOP
- Isolate main feed line [*]
of E-2. ROt BOP
- CLOSE steam supply isolation valve to TDAFW pump 3MSS*MOV17B (TO AFW pump steam supply) Verify SG atmospheric relief and bypass valves - CLOSED 30TM*AOV29B, 61B, 63B, 64B (Upstream Traps) Verify SG blowdown isolation valve CLOSED The 'B' SG blowdown sample isolation valve (3SSR*CTV19B) could
- Verify SG blowdown sample isolation be open for sampling and should be valve - CLOSED closed.
- Verify SG chemical feed isolation valve CLOSED The 'B' main feed line valves, 'B' MSIV and its bypass valve, 'B' Using table, Verify main steam line atmospheric relief and bypass valves drains upstream of MSIVs and TO AFW should already be closed due to the pump - CLOSED Main Steam line and Feedwater Isolation signals. The 'B' SG Blowdown Isolation and Chemical Feed Isolation valves should already be closed due to the CI'A',
Page 50 of 74
SEt IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: a chg 2 Task Time IOA/Malf Instructor Information/Activity Assign Expected Action Standard SGA SGB SGC SG 0 3DTM* AOV29A 3DTM* AOV29B 3DTM* AOV29C 3DTM* AOV29 0 3DTM*AOV61A 3DTM*AOV61B 3DTM*AOV61 C 3DTM*AOV61D 3DTM*AOV63A 3DTM*AOV63B 3DTM*AOV63D 3DTM*AOV64A 3DTM*AOV64B 3DTM* AOV64 0 Main steam safety valve flow indication E-2, step 5 (derived from differential temperature CAUTION switches) may erroneously indicate flow if the common drain header is warmed by previous steam releases. Flow indication should be verified by local observation and other plant response indications.
US Check SG Code Safety Valves Closed E-2, step 5
- Flow switches (MB5) - NOT LIT BOP
- Locally observation of safety valves (MSVB Roof) - NO STEAM OBSERVED PEO Check AFW Suction Source E-2, step 6 Check DWST level - LESS THAN 80,000 gal E-2, step 6.a Proceed to step 7 and, IF DWST level E-2, step decreases to LESS THAN 80,000 gal, 6.a RNO Page 51 of 74
SEc.. .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard THEN Perform step 6.b NO: '8' SG is ruptured Check If SG Tubes Are Intact E-2, step 7 Align all SGs for activity samples: E-2, step 7.a The rupture will not show on the rad 3. RESET SG blowdown sample isolation monitor, since it occurred post trip.
- 4. OPEN SG blowdown sample isolation valve(s)
- 5. Request Chemistry provide activity samples using HP coverage BOOTH Verify 'B' SG WR level is rising. Check steam generator levels - NO SG E-2, step LEVEL INCREASING IN AN 7.b It takes approximately 4 - 5 minutes UNCONTROLLED MANNER after the SGTR for wide range level to start rising. The crew may also identify that '8' SG pressure is slowly increasing.
Verify trend history and alarm status of E-2, step radiation monitors: 7.c
- Main steam line - NORMAL
- Condenser air ejector - NORMAL
- SG blowdown - NORMAL The US should announce and make Go to E-3, Steam Generator Tube Rupture. E-2. step Page 52 of 74
SEt, .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity ~~igl'1 Expected Action Standard the transition to E-3. 7.b RNO Check If ECCS Flow Should Be Reduced E-2, step 8 Go to E-1, Loss Of Reactor Or Secondary E-2, step 8 Coolant RNO Verify RCS subcooling based on core exit E-2, step TCs - GREATER THAN 32°F (115°F 8.a ADVERSE CTMT)
Verify secondary heat sink step 8.b
- Narrow range level in at least one intact SG - GREATER THAN 8% (42%
ADVERSE CTMT)
Verify RCS pressure - STABLE OR E-2, step INCREASING 8.c Verify PZR level - GREATER THAN 16% E-2, step (50% ADVERSE CTMT) 8.d Go to ES-1.1, SI Termination E-2, step 8.e E-3, SGTR (rev 022) Actions CREW To prevent seal damage, seal injection flow E-3 Step 1 Page 53 of 74
SEt. ..IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malt Instructor Information/Activity Assign Expected Action Standard should be maintained to all Reps. CAUTION
- Foldout page must be open E-3, Step 1,
- The RCP trip criteria is only applicable NOTE until a controlled cooldown is initiated in step 6.
RO Check It RCPs Should Be Stopped E-3, Step 1 Check RCP's - ANY RUNNING E-3, Step 1.a Verify RCS pressure - LESS THAN 1500 psia E-3, (1800 psia ADVERSE CTMT) Step 1.b E-3, Verify either of the following:
Step 1.c Charging pumps - AT LEAST ONE RUNNING AND AT LEAST ONE COLD LEG INJECTION VALVE OPEN OR SI pumps - AT LEAST ONE RUNNING US Proceed to step 2. E-3, Step 1.b, RNO RO STOP all RCPs E-3, Step 1.d Page 54 of 74
SEc. .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity_ Assign Expected Action Standard CREW Identify Ruptured SGs E-3, Step 2
- High radiation from any SG sample CREW
- If the TD AFW pump is the only available E-3, source for feed flow, a steam supply to the Step 3, TD AFW pump must be maintained from CAUTION at least one SG.
BOP Isolate Flow From Each Ruptured SG E-3, Step 3 Verify each ruptured SG atmospheric relief E-3, Step valve controller-IN AUTO AT 1125 psig 3.a Check each ruptured SG atmospheric relief E-3, valve - CLOSED Step 3.b 3MSS*MOV18A 3MSS*MOV188 3MSS*MOV18C 3MSS*MOV18D Page 55 of 74
~
SEt. .ON 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity_ .~ Assign Expected Action Standard BOP Check each ruptured SG atmospheric relief E-3, bypass valve - CLOSED. Step 3.c BOP CLOSE each ruptured SG steam supply E-3, Step isolation valve to TD AFW pump. 3.d
- 3MSS*MOV17A
- 3MSS*MOV17B
- 3MSS*MOV17D RO Verify each ruptured SG blowdown isolation E-3, valve - CLOSED Step 3.e RO CLOSE each ruptured SG blowdown sample E-3, Step isolation valve 3.f RO Verify each ruptured SG chemical feed E-3, isolation valve - CLOSED Step 3.g BOP Using table, CLOSE the main steam line E-3, drains upstreams of MSIVs and TO AFW Step 3.h SGA SG a sac sao I 3DTM*AOV29A 3DTM*AOV29B 3DTM*AOV29C 3DTM*AOV29D 3DTM*AOV61A 3DTM*AOV61B 3DTM*AOV61 C 3DTM*AOV61D 3DTM*AOV63A 3DTM*AOV638 3DTM*AOV630 3DTM*AOV64A 3DTM* AOV64B --_ ....... _.. _ 3DIM*AOV64D_
BOP CLOSE each ruptured SG MSIV and MSIV E-3, bypass valve Step 3.i Page 56 of 74
SEt. .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard This caution applies. Feed flow CREW If any ruptured SG is faulted, feed flow to that E-3, should remain isolated to the "B" SG should remain isolated during subsequent Step 4, SG. The other SGs are available for recovery actions unless the SG is needed for CAUTION cooldown. RCS cooldown.
Check Ruptured SG Level E-3, step 4 Level will not be > 67% WR or > 8% RO Verify one of the following is satisfied: E-3, NR. However, feed flow to the '8' SG Ruptured SG WR level - GREATER THAN Step 4.a should remain isolated. 67% (95% ADVERSE CTMT)
OR Ruptured SG NR level- GREATER THAN 8% (42% ADVERSE CTMT)
BOP Stop feed flow to ruptured SGs. E-3, Step 4.b US Major steam flow paths from the ruptured E-3, SG(s) must be isolated prior to RCS Step 5, cooldown. Major flowpaths include the main CAUTION steam line, TO AFW pump steam supply, and SG atmospheric relief and bypass lines.
'8' SG pressure will NOT be greater BOP Check Ruptured SGs Pressure - GREATER E-3, Step 5 than 530 psig. THAN 530 psig The US should announce and make the US Go to ECA - 3.1, SGTR With Loss of Reactor E-3, Step 5 transition to ECA-3.1. Coolant - Subcooled Recovery Desired. RNO ECA-3.1 (rev 019-02) Actions Page 57 of 74
SEl.ON 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard After SI reset, manual operator action is ECA-3.1 required to: Step 1, Caution
- Open the charging pump cold leg injection valves when RCS pressure decreases to less than 1900 psia.
- Restart safeguards equipment If offsite power is lost.
CREW Foldout page must be open. ECA-3.1 Step 1, Note RESET ESF Actuation Signals, If Required ECA-3.1 Step 1 RO RESET SI ECA-3.1 Step 1a RESET the following ECA-3.1 Step 1b
- COA
- CIA
- CIS Establish Instrument Air to Ctmt ECA-3.1 Step 2 Check instrument air compressors - AT ECA-3.1 Page 58 of 74
SEL ')N 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard LEAST ONE RUNNING Step 2.a START one instrument air compressor. ECA-3.1 Step 2.a, RNO OPEN instrument air Ctmt isolation valves ECA-3.1 Step 2.b Check Electrical Alignment ECA-3.1 Step 3 Verify AC emergency busses - ENERGIZED ECA-3.1 BY OFFSITE POWER Step 3.a Proceed to step 3.g. ECA-3.1 Step 3.b Perform the following to energize MCC 32-3T: ECA-3.1 Step 3.g
- 1. Check emergency bus 34C ENERGIZED T =4 minutes EDR18 (Will reenergize 32-3T) 2. Using GA-1, Energize MCC 32-3T after being dispatched EDR44 Then report as PEO that 32 3T is energized lAW GA-1, with the TRIGGER 12 exception of arming the lift pumps.
Verify busses 34A and 34B - BOTH ECA-3.1 ENERGiZED BY OFFSITE POWER Step 3.h Proceed to step 3.1. ECA-3.1 Step 3.i Check RCPs - ANY RUNNING ECA-3.1 Page 59 of 74
SEl .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Step 3.1 T = 4 minutes RCR 23*26 (Selects COLD for RCPs) Locally, Place the eight RCP overcurrent trip ECA-3.1 after being switches (43PP and 43PB) in the COLD Step 3.m dispatched Then report as PEO that the eight position using CO Key Locker key #7.
RCP overcurrent trip switches are in the TRIGGER 13 COLD position.
Deenergize PZR Heaters ECA-3.1 Step 4 Turn OFF all Pzr heaters ECA-3.1 Step 4.a T =When BOOTH REPORT as ADTS to use 22% as the Consult AOTS for a recommended minimum ECA-3.1 Called level that covers PZR Heaters. indicated PZR water level to ensure heaters Step 4.b are covered Check If Containment Spray Should Be ECA-3.1 Stopped Step 5 Yes, quench spray pumps will be Verify quench spray pumps - RUNNING ECA-3.1 running. Step 5.a Verify Ctmt pressure - LESS THAN 17.5 psia ECA-3.1 Step 5.b Proceed to CAUTION prior to step 5 and ECA-3.1 WHEN Step 5.b, RNO Ctmt pressure is LESS THAN 17.5 psia, THEN Return to step 4.c.
Examiner Inform the US that an extra RO will Using GA-8, Stop Ctmt spray ECA-3.1 Page 60 of 74
SEt. .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard perform GA*8. Step 5.c If any ruptured SG is faulted, feed flow to that ECA-3.1 SG should remain isolated during subsequent Step 6 recovery actions unless the SG is needed for CAUTION RCS cooldown.
Since the '8' SG is faulted, feed flow Check Ruptured SG Level ECA-3.1 should remain isolated, per the Step 6 CAUTION.
Verify one of the following is satisfied: ECA-3.1 Step 6.a
Perform the following: ECA-3.1 Step 6.a RNO
- 1) Maintain feed flow to the ruptured SGs.
- 2) Proceed to CAUTION prior to step 6 and, WHEN WR level is GRATER THAN 67% (95%
ADVERSE CTMT)
Page 61 of 74
SEL')N 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard OR NR level is GREATER THAN 8% (42%
ADVERSE CTMT)
THEN Stop feed flow to ruptured SG.
Stop feed flow to ruptured SGs ECA-3.1 Step 6.b After SI reset, manual operator action is ECA-3.1 required to restart the RHR pumps if RCS Step 7 pressure decreases in an uncontrolled CAUTION manner to LESS THAN 300 psia (500 psia ADVERSE CTMT).
Check If RHR Pumps Should Be Stopped ECA-3.1 Step 7 Check RHR Pumps - ANY RUNNING IN SI ECA-3.1 MODE Step 7.a RCS pressure mayor may not be Check RCS pressure ECA-3.1 stable, depending on the timing of the Step 7.b crew.
- RCS pressure - STABLE OR INCREASING Proceed to step 8. and, IF conditions for ECA-3.1 stopping RHR pumps are met, THEN Step 7.b, Perform step 7.c. RNO Page 62 of 74
SEt IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity _As~gn_ Expected Action Standard STOP RHR pumps and Place in AUTO ECA-3.1 Step 7.c Initiate Evaluation of Plant Status ECA-3.1 Step 8 Radiation in the Auxiliary Building and Check Auxiliary Building and ESF Building ECA-3.1 ESF Building will be normal. radiation (radiation monitoring group Step 8.a histogram)
- Auxiliary Building (AUX) - NORMAL
- ESF Building (ESF) - NORMAL Examiner Inform the US that the Tech Support Request ADTS obtain samples using any ECA-3.1 Center will carry out ECA-3.1 steps means possible ..... Step 8.b S.b, c and d.
Evaluate plant equipment for continued usage ECA-3.1 capabilities .... Step 8.c Start additional plant equipment as needed for ECA-3.1 plant recovery ..... Step 8.d Check If SG Secondary Boundaries Are ECA-3.1 Intact Step 9 Check pressures in all SGs ECA-3.1 Step 9.a e NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
- NO SG COMPLETELY DEPRESSURIZED Page 63 of 74
SEt .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit}'__ Assign Expected Action Standard The 'B' SG should already be isolated. Verify each faulted SG NOT required for ECA-3.1 cool down is isolated ..... Step 9.a RNO Check Intact SG Levels ECA-3.1 Step 10 Verify NR level- GREATER THAN 8% (42% ECA-3.1 ADVERSE CTMT) Step 10.a Control feed flow to maintain NR level ECA-3.1 BETWEEN 30% and 50% (42% and 50% Step 10.b ADVERSE CTMT)
- Shutdown margin must be monitored ECA-3.1 during RCS cooldown using GA---15, Step 11 Establishing RCS Boron Concentration For NOTE Shutdown Margin.
- Ensure Low Steam Line Pressure SI is blocked when pressurizer pressure is LESS THAN 2000 psia.
Initiate RCS Cooldown To Cold Shutdown. ECA-3.1 Step 11 NOTE: A cooldown may already be in Maintain cooldown in RCS cold legs --- AT A progress as a result of ECCS flow, and MAXIMUM RATE NOT TO EXCEED 800F'hr the BOP may not need to immediately initiate an operator controlled cooldown at this point.
Use RHR System if in service ECA-3.1 Step 11.b Page 64 of 74
SE~ .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard The BOP should use GA-26 to Using GA-26, Dump steam from intact SGs ECA-3.1 commence the cooldown (if required), Step 11.c using the atmospheric relief bypass valves.
Check If Saturated Recovery Should Be ECA-3.1 Performed Step 12 Depending on the timing of the crew, Check RWST level - LESS THAN 920,000 gal ECA-3.1 RWST level mayor may not < 920,000 Step 12.a gal.
Proceed to step 11.d ECA-3.1 Step 12.a RNO WR sump level should be in the Using Attachment A, Check Ctmt WR sump ECA-3.1 acceptable leakage region. level - IN UNACCEPTABLE LEAKAGE Step 12.b REGION Proceed to step 12.d ECA-3.1 Step 12.b RNO Go to ECA - 3.2, SGTR With Loss of Reactor ECA-3.1 Coolant - Saturated Recovery Desired Step 12.c Check ruptured SG NR level- GREATER ECA-3.1 THAN OR EQUAL TO 87% (68% ADVERSE Step 12.d CTMT)
Proceed to step 13 ECA-3.1 Step 12.d RNO Page 65 of 74
SEC .IN 4 Lesson
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity As::;ign Expected Action Standard Check ADTS determines - RECOVERY TO ECA-3.1 BE COMPLETED USING ECA - 3.2, SGTR Step 12.e WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED Proceed to step 13 ECA-3.1 Step 12.e RNO Go to ECA - 3.2, SGTR With Loss of Reactor ECA-3.1 Coolant - Saturated Recovery Desired Step 12.f The scenario may be terminated once the RCS cooldown is shown to be controlled and the US makes the decision to transition ECA-3.2, or remain in ECA-3.1.
Page 66 of 74
SECTION 4 Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: QJ;hg 2 EVALUATION GUIDE I. Crew FOLLOW-UP QUESTIONS
- 1. What is the Emergency Classification for this event?
ALERT-Charlie One, Barrier Failure, BA 1.
- 2. What plant condition(s) is(are) of greatest concern for (this event)?
- 3. What actions did the crew take to directly mitigate (this event)?
- 4. Which safety function(s) were challenged or had the greatest potential for challenge? Describe why.
Page 67 of 74
SECTION 4 EXAM GUIDE
SUMMARY
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: o chg 2 II. Critical Tasks Note: Critical Tasks are not required for Progress Review Exams.
TASK DESCRIPTION TASK # KJA >/= 3.0 BASIS SELECTION Manually trip the reactor E-O -- A 029-EA1.08 Failure to manually trip the from the control room with 4.5/4.5 reactor causes a challenge to either Main Board trip 029-EA1.12 the subcriticality CSF beyond switch or by opening 32B 4.1/4.0 that irreparably introduced by and 32N supply breakers the postulated conditions.
before completing step 1 of Also, it constitutes an "incorrect E-O. performance that requires the crew taking compensating action which complicates the event mitigation strategy and demonstrates the inability by the crew to recognize a failure of the automatic actuation of the RPS."
Isolate the faulted SIG E-2 -- A 040 AA1.04 Failure to isolate a faulted before transition out of 4.3/4.3 SG that can be isolated E-2 causes challenges to CSFs beyond those irreparably introduced by the postulated conditions.
Manually actuate Main E-O-P E12-EA1.13.8/3.8 Failure to close the MSIVs Steamline isolation or close 039-K4.053.7/3.7 under the postulated plant MSIVs before a severe conditions causes challenges (orange path) challenge to CSF s beyond those develops to either the irreparably introduced by the subcriticality or the integrity postulated conditions. Such an CSF or before transition to omission constitutes a ECA-2.1, whichever "demonstrated inability by the happens first. crew to recognize a failure of the auto actuation of an ESF system or component and to take an action tilat would prevent a challenge to plant safety."
Cool down the RCS to ECA-3.1 - 011 EA1 .11 4.2 4.2 Depending upon the plant cold shutdown B 011 EA1 .15 4.2 4.2 conditions, failure to perform conditions at the allowed the critical task either causes 038 EA1.16 4.4 4.3 accelerated depletion of RWST by procedure inventory leading to loss of SI (80°F/HR), but such 038 EA1.27 3.93.9 and eventual core uncovery or that a severe (orange causes increased primary-to path) challenge to the 038 EA1.32 4.64.7 secondary leakage leading to Integrity CSF is not SG overfill and more radioactive release. Thus, Page 68 of 74
encountered. failure to perform the critical 038 EA1.35 3.53.6 task leads to a "significant reduction in safety margin beyond that irreparably introduced by the scenario." It also represents a "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety."
Note: [*] Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide.
Page 69 of 74
SIMULATOR TRAINING SHIFT TURNOVER REPORT DATE*TIME PREPARED BY SHIFT PLANT STATUS:
Toda~ Now I Shift Manager I 06:00 - 18:00 Mode: 1 Rx Power: 100%
Megawatts: Thermal: 3649 MWTH PZR Pressure: ?250 psia Electric: 1284 MWe RCS T-AVE: 5BZdegF RCS Leakage: Identified: 0.015 gpm Protected Train/Facility: A TRAIN Orange Unidentified: 0.036 gpm PRA: Green Date/Time: Todav 0015 Active Tracking Records and Action Statements I
Equipment/Reason LCO Action Date Time in LCO Action Requirement Time Left 3.8.1.1 b.1, b.2, b.3, b.4, b.5 yesterday 18 hours0.75 days <br />0.107 weeks <br />0.0247 months <br /> SR4.B.1.1.1.a due in 3 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> 13 days 7.4.1 a.1, a.3 yesterday 18 hours0.75 days <br />0.107 weeks <br />0.0247 months <br /> 13 days 00 Compensatory Actions I Temp Logs Watch Open Date Class Reason Reason Position None Surveillances / Evolutions in Progress OP 3204 J Steady State Operation Reactivity Briefing (see reactivity thumbrules I spread sheet for additional info) I Current Rod Height CBD@219 Xenon Trend Stable Current Boron 1046 ppm Shift Orders The "A" EDG is out of service for planned maintenance.
Page 70 of 74
ATTACHMENT 2 VALIDATION CHECKLIST
Title:
Faulted, Ruptured Steam Generator 10 Number: 2K11 NRC-02 Revision: o chg 2 Verified By:
(Initials)
Initial Conditions:
The initial condition(s) contained in the guide are certified or have been OM developed from certified ICs.
Test Run:
The scenario contained in the guide has been test run in part or whole on OM the simulator. The simulator response is reasonable and as expected. If a simulator guide revision does not affect original Test Run, then enter N/A.
Simulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or OM anomalous response by reviewing the Simulator Modeling and Anomalous Response List.
For Examination Scenario:
The Scenario Attributes Checklist is complete and attached. This is not OM required for Progress Review Exams.
Dave Minnich 4/30/11 Actions Complete (Signature) Date Page 71 of 74
Appendix D Scenario Outline Form ES-D-1 Facility: Millstone 3 Scenario No.: 2K11 NRC-02 Op-Test No.: 2K11 Examiners: Operators:
Initial Conditions: IC-1B, 100% Power, Middle of life, Eguilibrium Xe.
Turnover:
The Qlant is at 100% Qower and at middle of life. The "A" EDG is out of service for Qlanned maintenance.
I Event Malf. Event Event No. No Type* Description 1 RX05D I (RO) Loop 4 Tavg fails high (loop 4 narrow range Thot).
(AOP 3571) (Tech Spec entry) 2 RX12G I (BOP) 'C' steam generator level channel (controlling) fails low.
(AOP 3571) (Tech Spec entry) 3 SG03B R (RO) 'B' SG Tube Leak (410 gpd), and subsequent R (SRO) procedurally required rapid downpower. (3%/min).
N (BOP) (AOP 3576, AOP 3575) (Tech Spec entry) i 4 MS01B M (ALL) 'B' main steam line break in CTMT. Requires Reactor Trip and Safety Injection.
5 RP10AlB C (RO) Automatic and MB7 manual reactor trip switch fail.
RP09B Successful manual reactor trip MB4.
6 RPOBAIB C (BOP) Main Steam line Isolation fails to automatically actuate.
7 RP11E C (RO) Several HPSI components fail to respond to a Safety Injection signal.
i B SG01B M (ALL) . Hot, dry 'B' SG results in a SGTR. Faulted, ruptured Ii SG.
i
.* N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 72 of 74
Lesson
Title:
Faulted. Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Assessor: Dave Minnich QUALITATIVE ATTRIBUTES The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service. but it does not cue the crew into expected events.
The scenario consists mostly of related events.
Each event description consists of:
the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
The events are valid with regard to physics and thermodynamics.
Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
The simulator modeling is not altered.
The scenario has been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure functional fidelity is maintained while running the planned scenario.
Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section 0.5 of ES-301 All individual operator competencies can be evaluated, as verified using form ES-301-6.
Each operator will be significantly involved in the minimum number of transients and events specified on Form ES-301-S.
Level of difficulty is appropriate to support licensing decisions for each crew position.
Page 73 of 74
Lesson
Title:
Faulted, Ruptured Steam Generator ID Number: 2K11 NRC-02 Revision: 0 chg 2 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in natu(e.
- 01. Total Malfunctions (TM) - 5 to 8 required Total 8 (1) Loop 4 Tavg failure, (2) 'c' steam generator level channel failure, (3) 'B' SG Tube Leak, (4)
'B' main steam line break, (5) Automatic reactor trip failure, (6) ESF (MSI) Auto Actuation Failure, (7) ESF (HPSI components) Auto Actuation Failure, (8) Faulted, ruptured SG.
- 02. Malfunctions after EOP entry (EM's) - 1 to 2 required Total 3 (1) ESF (MSI) Auto Actuation Failure, (2) ESF (HPSI components) Auto Actuation Failure, (3)
Faulted, ruptured SG.
- 03. Abnormal Events (AE) - 2 to 4 required Total 3 (1) Loop 4 Tavg failure (AOP 3571). (2) "C' steam generator level channel failure (AOP 3571),
(3) 'B' SG Tube Leak (AOP 3576)
- 04. Major Transients (MT) -1 to 2 required Total._2=--_
(1) 'S' main steam line break, (2) Faulted, ruptured SG
- 05. EOP's (EU) entered/requiring substantive actions -- 1 to 2 required Total --=..3_
(1) E-2. (2) E-3, (3) ECA-3.1
- 06. EOP Contingencies requiring substantive actions [ECAs/FRsl] (EC) -- Total...-...;~_
o to 2 required (1) ECA-3.1
- 07. Critical Tasks (CT) - 2 to 3 required Total ---!o4_
E-O -- A Manually trip the reactor E-2-A Isolate the faulted S/G before transition out of E-2 E-O -- P Manually actuate Main Steamline isolation or close MSIVs ECA 3.1 - B Cool down the ReS
- 08. Approximate Scenario Run Time: 60 to 90 min. Totall5 min
- 09. EOP run time: Total_ 35 min
- 10. Technical Specifications are exercised during the scenario. (Y/N)_Y_
Page 74 of 74
MILLSTONE POWER STATION SIMULATOR EXAM GUIDE APPROVAL SHEET Exam
Title:
Large Break LOCA Revision: o chg 2 ID Number: 2K11 NRC-04 This document is the property of the Millstone Power Station which controls its distribution. Further transfer, copying, or modification of this document is strictly prohibited without the written consent of the Millstone Power Station.
Submitted by: D. Minnich 3/21/11 Developer Date Validated by: Robert RO;ice 5/9/11 Technical Reviewer Date Approved by: L. Armstrong 5/11/11 Training Supervisor Date STOP THINK ACT REVIEW
SUMMARY
OF CHANGES Change Description Date of Change Rev 0 change 1: Removed any reference to the OMOC giving crew 6/2/11 guidance with respect to halting the uppower or checking Tech Specs associated with events 2 and 5. Modified the description the critical task E-O E (Initiate CTMT spray) in the body of the Exam Guide, to clarify that it is only one Critical Task. It could have been interpreted as two.
These changes are a result of NRC Exam comments made on 5/25/11.
Rev 0 change 2: Added a statement to the Instructor Activity column 6/22/11 associated with Event 4 (PRNI Channel Failure); 'At the examiner's discretion, move on to Event 5, without tripping bistables.' Deieted the Annunciator Response to RCP Vibration HI (no substantial crew actions), to proceed directly to the Annunciator response for RCP Vibration HI HI. Deleted a statement to the Instructor Activity column associated with E-1 step 6 that stated subcooling will be < 32 degrees (subcooling was> 32 degrees.) Added a statement to the Turnover Sheet that there will be minimum staffing for the plant startup. Lowered the severity of malfunction RC02B ('B' Loop Hot Leg Break) to 75 Ibm/sec. This will allow the crew to get to E-1 where status trees are effective, and exercise FR-Z.1 once the large break LOCA occurs.
Incorporated as a result of NRC comments made the week of 6/13/11
! (Prep Week).
STOP THINK REVIEW
SECTION 2 SIMULATOR EXAM GUIDE TABLE OF CONTENTS SECTIONS LISTED IN ORDER
- 1. Cover Page
- 2. Table of Contents
- 3. Exercise/Exam Overview
- 4. Exam Guide Attach ments:
Shift Turnover Report Validation Checklist Scenario Outline (ES-D-1)
Attributes Checklist Summary of Changes Page 3 of 58
SECTION 3 EXAM OVERVIEW
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: o chg 2
- 1. The crew will take the shift with reactor power stable, low in the power range (rE!actor power 7%), following a reactor startup by the previous shift. This is the initial plant startup from a refueling outage. OP 3203, Plant Startup, is in progress and complete up through step 4.3.7, Main Turbine shell warming. The crew is to raise reactor power from 7% to 15 to 19% in accordance with step 4.3.9. The US should facilitate a brief of the evolution prior to taking the shift. The MP3 simulator briefing room may be used for this purpose.
During the power ascension, and when power rises above 11 %, the Crew will find that the P-10
'PERMISSIVE STATUS 'annunciator has failed to energize. The US should refer to Technical Specifications and recognize that 3.0.3 applies, and results in a termination of the startup. The US should contact Plant Management for maintenance assistance and guidance.
While the organization is developing a shutdown plan, the 'c' (lead) Service Water pump will trip, and the 'A' (follow) Service Water pump will start. The crew should respond by addressing the Annunciator Response Procedure for the service water pump trip. Actions will include reestablishing service water supply flow to the TPCCW system, which isolated on low service water pressure, as well as addressing Technical Requirements.
When actions are complete for the tripped service water pump, Power Range Nuclear Instrument (NI) Channel 42 Lower Detector will fail high and the appropriate annunciators will alarm. Rod control is in manual so no rod motion will occur, but the auctioneered high PRNI channel inputs to the control circuitry for the FRV Bypass valves. The FRV Bypass valve controllers should be placed in manual and the crew should respond using AOP 3571, Instrument Failure Response.
Tech Specs will need to be addressed.
After Tech Specs are addressed, shaft vibration on the 'B' RCP will increase. The crew should address the RCP vibration alarm using the Main Board 4 Annunciator Response Procedure for RCP B VIBRA TlON HI-HI. The procedure requirements will have the operator transition to AOP 3554, RCP Trip or Removing a RCP from Service At Power, to stop the affected RCP.
After the RCP is tripped, a loss of off-site power will occur resulting in a reactor trip. The "A" EDG will fail to start automatically and must be manually started by the BOP from MB8. Additionally, the EDG output breakers fail to auto-close and the BOP must manually close the 'A' and 'B' EDG output breakers [critical task].
At the time of the reactor trip, a small break LOCA on loop 2 occurs (simulating a total failure of the #2 RCP #1 seal). The crew will carry out the immediate actions of E-O, Reactor Trip and Safety Injection, determine that automatic safety injection (SI) actuation has failed, and manually initiate SI [Critical Task]. In addition, Feedwater Isolation fails to automatically actuate, requiring the BOP to manually position feedwater components.
The crew will execute the actions as specified in E-O, and then transition to E-1, Loss of Reactor or Secondary Coolant. While in E-1, the crew will stop the RHR pumps when procedurally directed. After the crew trips the RHR pumps, the LOCA will rapidly increase in severity forcing Page 4 of 58
- the restart of the RHR pumps. As the break size increases an "Orange" Path will be generated based on CTMT pressure. The crew should respond by transitioning to FR-Z.1, Response to High CTMT Pressure. CDA Train "A" & "B" will fail to automatically or manually actuate. This will require the crew to manually manipulate individual components [Critical Task]. Once FR-Z.1 is complete, the crew transitions back to E-1, the session can be terminated.
- 2. The SRO candidate (US) should classify this event as an ALERT- Charlie One based on failure of the RCS Barrier, BA 1.
- 3. Duration of Exam: 90 minutes (without crew startup brief).
Page 5 of 58
SECTION 4 EXAM GUIDE
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision:
All Control Room Conduct, Operations and Communications shall be in accordance with OP-AA 100, Conduct of Operations.
"Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded,"
(NSEM 6.06)
Page 6 of 58
SECTION 4 EXAM GUIDE
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision:
SIMULATOR PROBLEMS DURING EXAMS It is the responsibility of the Instructors in the simulator to insure that training interruptions have a minimum negative impact on the Crew and the training we provide. Use your judgment on whether to stop the training and how the training should be commenced after the problem is corrected.
Be aware that at all times the Operators should treat the simulator as if it were the plant and you too should treat it as much like the plant as possible when they are in the simulator.
As soon as the Instructors are aware of a simulator problem that will adversely affect the training in progress (computer fault, etc.) the Instructor should:
- 1. Place the simulator in FREEZE if possible.
- 2. Announce to the Crew that there is a simulator problem.
- 3. Request that the Crew either standby (for minor trouble that can be handled quickly) or leave the simulator control room. (The Crew should leave the simulator for problems which involve major switch alignments).
- 4. Deal with the problem (reboot, close tripped breaker, call STSB, etc.)
- 5. After the Instructors believe the simulator is restored to service, the Crew should be told how training will continue. If it is possible and felt to be acceptable to the Instructors, training can begin where it left off with an update on plant parameters and each Crew member is prepared to restart. If training will not begin where it left off, the crew should be told how and where training will begin again.
- 6. Once the Crew has been told how and where training will begin, have the crew conduct a brief so that the Instructor can insure that the crew has all the necessary information to continue with the scenario.
- 7. Once all Crew members and Instructors are satisfied that they have the necessary information to continue the scenario, place the simulator in RUN and announce to the Crew that you have continued the training session.
Page 7 of 58
SEL .IN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS
- 1. START the Sun Workstation.
- a. IF the Sun Workstation is running THEN go to SIM ACTIVE.
- 2. PLACE Recorder Power to ON.
- 3. VERIFY that the current approved training load is loaded.
- 4. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.
- 5. RESET to IC 312 (modified IC08), Load Schedule NRC-04.sch. if needed, Load BASIC.EVT file (boolean triggers)
- 6. ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC. Pay particular attention to the Pzr spray valves and their setpoints.
- 7. PLACE Simulator to RUN.
- 8. If Necessary, RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT' and "F6" simultaneously.
- 9. ENSURE Simulator fidelity items cleared.
- a. CHECK the STEP COUNTERS at correct position for plant conditions.
- b. PLACE _4_ tiles under the DEMINS IN SERVICE lamacord label on MB6.
- c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.
- d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.
- e. For the RIL recorder: select printer to "ON" when command? appears select "Autojog".
- g. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT.
- 10. As needed, RESET Computer Terminals to At Power displays if 100% power IC.
- 11. RESET Rad Monitor Screen to Status Grid.
Page 8 of 58
SE....IN 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS
- 12. IF placing equipment ~OS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment O~S.
- 13. Ensure that the protected train and environmental placards are appropriately hung.
Equipment ODS: NONE Insert applicable Crew Training Tape/CD into the DVDNCR.
Verify the MONITOR Time Display the same as the digital time display on MB4. If not page/call the Unit Tech.
MalfunctionsIlOs/IDAs:
PLACE GREEN PLACARDS FOR ALL INTAKE PARAMETERS ON MB6 PLACE THE "An TRAIN PROTECTED PLACARD ON MB4 Page 9 of 58
SEL IN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS ID Number Description Delay Time Ramp Time Event Trigger I Severity Or Value I
Final Relative Value Order MALFUNCTIONS RP06A I 'A' Train CDA fails to Auto-Actuate Initial RP06B I 'B' Train CDA fails to Auto-Actuate Initial RP07A I 'A' Train Safety Injection fails to Auto-Actuate Initial RP07B I 'B' Train Safety Injection fails to Auto-Actuate Initial NI11 P-10 Permissive failure Initial EG13A 'A' EDG fails to automatically start Initial RP11M 1A' and 'B' EDG output breakers fail to Auto-Close Initial RP11L Feedwater Isolation fails to automatically actuate Initial SW01C fC' Service Water Pump trip. 11 NI09B PRNI 42 lower detector fails High 5mAMP RC25B 'B' RCP shaft vibration 19.2 mils RC25B 1 'B' RCP shaft vibration 115 mils ED01 I Loss of Offsite Power I 10 I
Page 10 of 58
SEt ")N 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS RC02B I "B" Hot Leg break (Inside CTMT on reactor trip) 30 75 Ibm/sec RC02B I uB" Hot Leg break (Inside CTMT on reactor trip) 11 7E4lbm/sec REMOTE FUNCTIONS SWR01 'A' Train SWP Lead/Follow 2 'A'Lead RXR107 PS Ooor#2 4 OPEN RXR35 OTOT 421C 5 TRIP RXR06 OTOT 4210 20 sec 5 TRIP RXR107 PS Ooor#2 40 sec I 15 I CLOSE OVERRIDES RPOI0004 RPOI0006 PB1 COA Actuate Train 'A' PB3 COA Actuate Train 'B' II NACTUATE NACTUATE Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew. Go over the Plant/simulator differences, which follow.
Booth Instructor: Commence recording Simulator session Page 11 of 58
SEl ')N 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 INITIAL SETUP INSTRUCTIONS Booth Instructor: Perform the crew turnover (Initial Conditions page at end of LP) with the SM . Have the SM brief his crew on plant conditions and any major equipment OOS.
PLANT/SIMULATOR DIFFERENCES:
- Rad Monitor Historical Data--Simulator Rad Monitor historical data not valid prior to the beginning of this exercise.
- If not using the speed dial option on the phone system. the operator must dial either #3333 or #3334 to reach the person/department they desire.
- The following PPC programs do not function on the simulator:
- Samarium Follow
- Xenon Follow
- Sequence of Events
- Flow indications 3SIH-F1917 (charging ECCS flow). 3SIH-F1918 (A SI pump flow) and 3SIH-F1922 (8 SI pump flow) will show flow at low flow rates.
Page 12 of 58
SEG .* ON4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard EVENT 1: Power increase to place the Main Turbine online using OP 3203.
OP 3203, Plant Startup, is in progress and complete up through step 4.3.8, Main Turbine shell warming. The crew is to raise reactor power from 7% to 15 to 19% in accordance with step 4.3.9.
The US should facilitate a brief of the evolution prior to taking the shift.
OP 3303, Plant Startup (rev 019-11)
With the SG bypass level control valves in OP 3203 "AUTO", reactor power should be increased Step 4.3.9 slowly to avoid feed control instabilities.
CAUTION As Main Generator Output increases to OP 3203 approximately 15% (194 MWe), "Power Step 4.3.9 System Stabilizer" PPC Point: EXS-PSSACT, will change from inactive to active. NOTE The reactivity plan specifies control US I RO INCREASE reactor power to between 15% OP 3203 rods be used to raise reactor power. and 19% by one of the following methods Step 4.3.9 while continuing with this procedure:
- W!THDFV\W control rods at a rate not greater than 2 steps/minute
Page 13 of 58
SEC .. IN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard If reactor power is allowed to decrease below OP 3203 9.2% subsequent to blocking the Intermediate Step 4.3.10 and Power Range Reactor Trips, the trips will CAUTION be reinstated.
Event 2: P-10 Permissive failure results in a termination of the startup and Tech Spec 3.0.3 entry.
WHEN reactor power increases above OP 3203 approximately 11 %, PERFORM the following Step 4.3.10 (MB4):
CHECK the following blue "PERMISSIVE "REACTOR AT POWER P-10" will STATUS" lights:
NOT be lit.
- MB4D 4-3, "REACTOR AT POWER P-10" lit
- MB4D 5-3, "RX OR TURB NOT AT POWER P-7" not lit The US should notify the OMOC (Operations Manager On Call) and RE that P-10 is not in its required state. The US should halt the startup.
T = US calls BOOTH As OMOC, acknowledge the US's OMOC for report. Ask the US what are you're guidance. your intentions / recommendations?
The US should enter TIS 3.3.1, Reactor Trip System Page 14 of 58
SEC. ION 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malt Instructor Information/Activity Assign Expected Action Standard Instrumentation. Functional Unit 17.b (RT System Interlock P-10),
Action 8 specifies: With less than the minimum channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
Evaluator If the Tavg - Tref Deviation alarm comes in, report that another RO will perform SP 3601G.3, Tavg Monitoring
=
T When BOOTH Report as RE to maintain reactor power requested stable using control rods. A reactivity plan is forthcoming.
EVENT 3: 'C' Service Water Pump trip.
T= SW01C This the 'C' Service Water The crew should respond using ARP 3353.
examiner's pump. MB1C 5-3, "SERV WTR PP AUTO TRIP I cue OVERCU RRENT".
Trigger 1 ARP 3353.MB1C 5-3 Actions (rev 005-15)
T+4 minutes from being IF PEa dispatched to breaker cube report that the 50GS is flagged and the dispatched.
86E is picked up. The 86E will be reset WHEN the control switch for the pump is taken to the stop position Page 15 of 58
SEt,. ,ON 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit~~ssign Expected Action Standard Automatic Function: Follow service Automatic Function: Follow service water water pump starts on low header pump starts on low header pressure.
pressure (26 psig). 3SWP*MOV 71A1B close on low header pressure (25 psig).
RO If annunciator MB1 C 4-3, "SERVICE WTR MB1C 5-3 PUMP DIS PRES LO" is lit, Go To that Step 1 annunciator's response procedure.
The 'A' SWP started automatically on RO low header pressure. START follow service water pump on the MB1C 5-3 affected train. Step 2 RO lE follow service water pump fails to start, Go MB1C 5-3 To AOP 3560, "Loss of Service Water." Step 3 The US should direct the RO to open RO 3SWP*MOV71 A and OPEN "3SWP*MOV71A, SERVICE WATER MB1C 5-3 3SWP*MOV71 B. TRAIN A, A HDR TPCCW SPLY," and Step 4 3SWP*MOV71B, "SERVICE WATER TRAIN B, B HDR TPCCW SPLY."
T+4 minutes BOOTH If PEO is dispatched to swap US/PE from LEAD/FOLLOW SW Pumps, then o Refer To OP 3328, "Hypochlorite," and SHIFT MB1C 5-3 perform the following: after SWR01 hypochlorite injection. Step 5 request. SWR01 to Trigger 2 'A'Lead is 'A' lead, report "'A' SW pump is lead, 'C' SW pump is follow" US/SM .
TRM 3.7.4, action 'a' should be Refer To the follOWing and DETERMINE MB1C 5-3 Limiting Condition for Operation. Step 6 entered (14 day action statement).
TIS 3.7.4, "Service Water System,"
and TRM 7.4.1, for 'C' SWP, and 3HVR*ACU1A (14 day action Technical Requirements 3.7.4, "Service statement) Water Pump" TRM 7.4.1 for 3HVR*ACU1A11B Page 16 of 58
SEt.. ,ON 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US/SM REVIEW OP 3326 "Service Water System," MB1C 5-3 for swapping service water pumps. Step 7 Once Tech Specs are addressed, move on to Event 4.
Event 4: Power Range Nuclear Instrument (NI) Channel 42 Lower Detector fails high.
N109B,5 3571 Entry T= Tech PRNI 42 lower detector will fail High US The US should recognize the entry conditions MAMP Conditions Spec for AOP 3571 are met and announce entry.
(100%)
addressed Trigger 3 AOP 3571 Actions (rev 009-07)
All Feed Reg Bypass Valves will go full BOP Determine the Initiating Parameter and AOP 3571 open. Place the affected controller in MANUAL Step 1 The BOP should place all SG level Control Bypass Valve controllers in manual and stabilize steam generator level.
Stabilize the Plant Parameters AOP3~1 S~p2 The appropriate attachment for this Perform Corrective Actions Using AOP3~1 failure is "D". The US should announce Appropriate Attachment S~p3 Page 170f58
SEl.. ,ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard to the crew.
Instrument Failure Attachment Power Range Nuclear Instrument Channel 0 Failure US Power Range Nuclear Instrument Channel Failure Failure of two or more channels of PR AOP 3571 instrumentation may prevent P-10 from Attachment resetting when power is reduced below 10%. o Step 1 If P-10 fails to reset, the following automatic CAUTION reactor trip signals are lost:
- 1. SR HIGH FLUX TRIP (10 5 CPS)
- 2. IR HIGH FLUX TRIP (25%)
- 3. PR HiGH FLUX LOW STPT TRIP (25%)
- The reactor operator must remain alert to any power increases which would necessitate a manual reactor trip.
- The Gamma Metrics Nuclear Instrumentation System shall be used during the reactor shutdown in lieu of the source range channels.
RO Defeat the failed channel input. AOP 3571 Attachment o Step 1 Page 18 of 58
SEt. .. ON 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activit~ Assign Expected Action Standard At the detector current comparator drawer, AOP 3571 Turn the following switches to the failed Attachment channel: D Step 1a Rod Stop Bypass Upper Section Lower Section Power Mismatch Bypass.
At the comparator and rate drawer, Turn the AOP 3571 following switch to the failed channel: Attachment D Step 1b Comparator Channel Defeat.
Defeating the failed channel will remove it AOP 3571 from the rod control circuit and may create an Attachment artificial primary to secondary power rate of D Step 2 change signal to rod control. Placing rod NOTE control in automatic, prior to the signal dissipating, may result in rod motion.
There should be no error, since rod RO Restore TAVE* TREF error to within 1°F and AOP 3571 control was in manual Place rod control in automatic. Attachment D Step 2 If the plant calorimetric source is NI's, the AOP 3571 failure of one NI channel will disable the Attachment calorimetric program. D Step 3 NOTE CREW When conditions have stabilized, observe AOP 3571 MB board annunciators and parameters Attachment and immediately report any unexpected or D Step 3 unexplained conditions to the Shift Page 19 of 58
SEC .. IN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard Manager.
US Trip the associated Reactor Protection AOP 3571 System bistable(s): Attachment D Step 4 Place a check mark in the box above the AOP 3571 appropriate channel that requires tripping on Attachment page 6 or 7 of this Attachment. D Step 4a
[Tech Specs] Refer to Technical Specification 3.3.1. AOP 3571 Attachment LCO 3.3.1 (FU2) D Step 4b 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action statement to trip bistables.
Check the existing bistable status to ensure a AOP 3571 reactor trip will not occur when the failed Attachment channel is tripped. D Step 4c If the General Warning lamp is lit on AOP 3571 3RPS*RAKLOGB, Placing train A SSPS Attachment "Multiplexer Test" switch in "A+B" will cause D Step 4.d the reactor to trip. CAUTION The following step will distinguish whether the AOP 3571 failure is within SSPS or the Protection Attachment channel. D Step 4.d NOTE This is not the case. The channel has If bistable status light(s) ( MB4F or MB4G) AOP 3571 failed. The US should proceed to step indicate that a single bistable input has Attachment 4.e. tripped and channel indication is normal, D Step 4.d Page 20 of 58
SEt... ,ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard PERFORM the following:
At the examiner's discretion, move on to Event 5, without tripping bistables.
=
T after RXR107 Protection Set Door 2 Open Request the I&C Department trip the AOP 3571 brief for appropriate bistables using Attachment 0 and Attachment tripping of Attachment S. o Step 4e bistables.
Trigger 4
=
T after RXR35 OTDT 421C Bistable door open RXR06 OTDT 4210 Bistable Trigger 5 RXR107 Protection Set Door 2 Closed Verify the appropriate bistable status lights AOP 3571 are lit. Attachment D Step 4f US Within one hour, Determine by AOP 3571 observation of the associated permissive Attachment annunciator window (s) that the following o Step 5 interlocks are in their required state for the existing plant condition (Tech, Spec.
3.3.1, Action 8):
- Rx or turbine not at power P-7 (MB40 5-3)
Page 21 of 58
SEC.,uN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
- Three loop permissive P-8 (MB4D 3 3)
- NIS power range P-9 permissive (MB4D 6-1)
- Reactor at power P-10 (MB4D 4-3).
- The following step for removing the AOP 3571 failed PR channel from Program 3R5 Attachment restores OPERABILITY to the AFD D Step 6 Monitor Alarm and must be completed NOTE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or SURVEILLANCE REQUIREMENT 4.2.1.1.1.b must be performed.
- The following step for removing the failed PR channel from Program 3R5 does NOT restore OPERABILITY to the QPTR Alarm Monitor; therefore, TABLE 3.3-1, ACTION 2.c and SURVEILLANCE REQUIREMENTS 4.2.4.1.b and 4.2.4.2 are in effect.
US I Perform the following to remove the AOP 3571 CREW affected power range input to the AFD and Attachment QPTR monitor alarm (Program 3RS): D Step 6 Using PPC display "TILT_CHANNEL," Press AOP 3571 the button that corresponds to the channel to Attachment be removed. D Step 6a Press "Apply" button to remove channel input. AOP 3571 Attachment Page 22 of 58
SEt. .ON 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard D Step 6b Refer to the following Technical AOP 3571 Specifications and Perform any required Attachment actions: D Step 7
- Surveillance Requirement 4.2.1.1.1.b The US should enter T/S 3.3.1,
- TABLE 3.3-1, ACTION 2.c Action 2
- Surveillance Requirement 4.2.4.2 US Request I&C Department perform AOP 3571 corrective maintenance on failed Attachment instrument. D Step 8 EVENT 5: '8' RCP high shaft vibration requiring an immediate shutdown of the affected RCP T= RC25B to This will cause shaft vibrations for '8' Examiner's 15 mils RCP to increase to above the alarm Cue setpoint for HI-HI vibes.(Alarm setpoint is 20 mils)
Trigger 7 The crew should respond using ARP OP Entry NOTE: The malfunctions for the RCP Crew vibrations are additive to the existing 3353. MB4B 3-3, "Rep B ViBRATION Hi-Hi" Conditions vibrations. Therefore, if current vibrations are 7.0 mils and RC25B is inserted at 8 mils the result will be an indication of 15.0 mils on the RCP.
Page 23 of 58
SEt. ..ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity_ Assign Expected Action Standard MB4B 3-3, RCP B VIBRATION HI-HI Corrective Actions (rev 004-11).
An overranged probe may read zero while the MB4B 3-3 other channel reads high. Step 1 CAUTION RO CHECK reactor coolant pump vibration MB4B 3-3 monitor panel to confirm alarm (MB3R). Step 1 Indicated vibration level is higher than IF indicated vibration level is less than alarm MB4B 3-3 the alarm setpoint for shaft. setpoint, RESET the alarm. Step 2 Reactor power is NOT greater than P- IF reactor power is greater than P-8 (50%), MB4B 3-3
- 8. PERFORM the following .... Step 3 Refer To AOP 3554, "RCP Trip or Stopping MB4B 3-3 an RCP at Power," and REMOVE RCP B Step 4 from service.
The US should recognize the entry conditions 3554 Entry US for AOP 3554 are met, announce entry and Conditions direct the steps to take the 'B' RCP out of service.
AOP 3554 ACTIONS (rev 008-01)
Yes, all RCPs are running. RO Check RCP Status - ALL PUMPS RUNNING AOP 3554 Step 1 US Check Reactor Power AOP 3554 Step 2 Yes, the P-8 annunciator is LIT. RO Verify THREE LOOP PERMISSIVE P-8 AOP 3554 Page 24 of 58
SEt.. ,ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard annunciator (MB40 3-3) - LIT. Step 2.a N/A CREW If stopping the RCP due to No.1 seal failure, AOP 3554 steps 3 through 5 should be completed as Step 3 quickly as possible in order to isolate the NOTE affected pump No. 1 seal within the recommended 5 minutes.
There will be negligible shrink at the While removing the RCP from service, it is AOP 3554 current power level. desirable to maintain feedwater flow to the Step 3 affected steam generator, to ensure that the NOTE reactor does not trip on low-low steam generator level from the shrink that will occur.
Approximately 0.5 MPPH excess flow is sufficient. Feedwater flow to the affected steam generator should be stopped once shrink has stopped.
BOP Feed Affected Loop SG NR Level to AOP 3554 Between 65% and 70% Step 3 ESTABLISH approximately 0.5 MPPH excess AOP 3554 feed flow to raise affected SG level. Step 3.a RO Defeat Affected Loops Temperature Input AOP 3554 Step 4 Loop 2 Place loop temperature cutout switch for ~T AOP 3554 to the affected loop and pull out. Step 4.a Loop 2 Place loop temperature cutout switch for Tavg AOP 3554 to the affected loop and pull out. Step 4.b Loop 1, 3, 4 Place OT/OP ~T recorder select switch to an AOP 3554 unaffected loop. Step 4.c Page 25 of 58
SEt.. .* uN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assi9 11 E:x:pected Action Standard US Remove Affected RCP From Service AOP 3554 Step 5 RO Check RCP status - ALL PUMPS RUNNING. AOP 3554 Step 5.a US Check the following conditions: AOP 3554 Step 5.b BOP
- Affected SG NR level- GREATER THAN 65%.
- THREE LOOP PERMISSIVE P-8 annunciator (MB4D 3-3) - LIT RO STOP affected RCP. AOP 3554 Step 5.c Verify affected S/G level- STABLE AOP 3554 Step 5.d Stop feeding the affected S/G AOP 3554 Step 5.e RO Check RCP 1 and 2 - BOTH RUNNING. AOP 3554 Step 5.f RO should take the loop 2 Spray to RO Place affected PZR Spray Controller in AOP 3554 manual and close manual and CLOSE spray valve. Step 5.f RNO Once step 6 of AOP 3554 is reached US Check if Rep Seal Leakoff should be AOP 3554 and with Examiner's concurrence, isolated Step 6 move on to the next event.
Page 26 of 58
SEc.-. ION 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard NO, not a seal failure. us Verify RCP - STOPPED AS A RESULT OF AOP 3554 SEAL FAILURE REQUIRING IMMEDIATE Step 6.a SHUTDOWN EVENT 6: Loss of Offsite Power T= BIS ED01 This will initiate a loss of offsite cannot be power causing a reactor trip.
tripped Trigger 10
'A' Emergency Diesel Generator (EDG) fails to automatically start and must be manually started from MB8. BOP must manually close the 'A' and 'B' EDG output breakers.
EVENT 7: Small break LOCA inside CTMT RC02C, NOTE:
CV13B
=
T Reactor The failure of the 'B' RCP seal Trip package and small break LOCA will initiate upon the reactor trip.
NOTE: US should go to "Master RO Silence" before ordering reactor trip.
Page 27 of 58
SEt. .. ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard E-O (Rev. 026) STEPS Crew
- Foldout page must be open E-O, Step 1, NOTE
- ADVERSE CTMT defined as GREATER THAN 180°F or GREATER THAN 105R/ hr in containment.
- The reactor can be interpreted as "tripped" when any two of three bulleted substeps of Step 1.* are satisfied.
RO Verify Reactor Trip E-O, Step 1
- Check reactor trip and bypass breakers - OPEN Rod bottom lights are out due to loss of
- Check rod bottom lights - LIT power.
The crew still meets two of three
- Check neutron flux - DECREASING Verify Turbine Trip E-O, Step 2 Check all turbine stop valves - CLOSED E-O, Step 2.a BOP Verify Power to AC Emergency Busses E-O, Step 3 Neither bus is energized. BOP Check busses 34C and 340 E-O, Step 3.a BOTH ENERGIZED Page 28 of 58
SEt. .ON 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
[Critical Task] [*] Try to energize the affected buss(es) from its E-O, associated EDG. Step 3.a, The BOP must manually start the 'A' RNO [*]
EDG from MBS. BOP must manually close the 'A' and 'B' EDG output breakers.
US IF power can NOT be restored to at least one AC emergency bus, THEN Go to ECA-O.O, Loss of All AC Power, Step 3. (Observe NOTE prior to step 1).
US Check If SI Is Actuated E-O, Step 4 RO Verify SAFETY INJECTION ACTUATION E-O, annunciator - (MB4D 1-6 or MB2B 5-9) - LIT Step 4.a EVENT 8: Safety Injection fails to Auto-Actuate.
[Critical Task] [*] US Check if SI is required E-O, Step 4.a, Crew should identify that SI did not actuate and it is required. SI RNO [*]
should be manually actuated.
- PZR pressure LESS THAN 1890 psia OR Page 29 of 58
SEt. _.ON 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
- PZR level LESS THAN 9%
Check Reactor trip and bypass breakers - E-O, OPEN Step 4.c RO Verify Service Water Pumps - AT LEAST E-O, Step 5 ONE PER TRAIN RUNNING START pump(s) E-O, Step 5, RNO RO Verify Two RPCCW Pumps - ONE PER E-O, Step 6 TRAIN RUNNING RO Verify ECCS Pumps Running E-O, Step 7
- Check SI pumps - RUNNING
- Check RHR pumps - RUNNING
SEC, .. IN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Task Revision: °chg 2 Time 10A/Malf Instructor Information/Activity Assi9 1l E1Y:)ected Action Standard Check MD pumps - RUNNING E-O, Step 8.a Check turbine - driven pump - RUNNING, IF E-O, NECESSARY Step 8.b EVENT 9: Feedwater isolation fails to Auto- BOP Verify FW Isolation E-O, Step 9 Actuate.
BOP should identify that FWI did not
- Check SG feed regulating valves CLOSED actuate and it is required. FWI components should be manually actuated.
Specifically, 3FWS*CTV41A- 410
- Check SG feed regulating bypass valves CLOSED (Main Feed Isolation Trip valves) will need to be closed.
- Check FW isolation trip valves - CLOSED
- Check TD FW pump - TRIPPED
- Check SG blowdown isolation valves CLOSED
- Check SG blowdown sample isolation valves - CLOSED
- Check SG chemical feed isolation valves CLOSED BOP Align component(s) as necessary for E-O, Step 9 Page 31 of 58
SEC .. uN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard minimum safety function. RNO BOP Check If Main Steam Lines Should Be E-O, Isolated Step 10 Check Ctmt pressure GREATER THAN 18 E-O, psia Step 10.a OR Any SG pressure LESS THAN 660 psig OR Annunciator "MAIN STEAMLINE ISOLATION" (MB2B 5-7) - LIT Verify MSIVs and MSIV bypass valves- E-O, CLOSED Step 10.b Check ESF Group 3 lights - LIT. E-O, Step 10.c RO Check if CDA Required E-O, Step 11 CTMT pressure will ultimately reach Check Ctmt pressure is GREATER THAN 23 E-O, the CDA setpoint. psia Step 11.a OR Annunciator "CONTAINMENT DEPRES ACTUATION" (MB2B 5-5) - LIT US Proceed to Step 12. E-O, Step11,a, Page 32 of 58
SEC;;. ,ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RNO BOP Verify CAR Fans Operating In Emergency E-O, Mode Step 12 BOP Check CAR fan status: E-O, Step 12.a
- CAR fans A and B - RUNNING
- CAR fan C - STOPPED BOP START/STOP CAR fans as necessary. E-O, Step 12.a, RNO RO Verify RPCCW Ctmt supply and return header E-O, isolations - OPEN Step 12.b RO Verify Train A and B RPCCW supply and E-O, return to chill water valves - OPEN Step 12.c RO Verify CIA E-O, Step 13 RO Check ESF Group 2 status columns 2 through E-O, 10-LIT Step 13.a RO Verify Proper ESF Status Panel Indication E-O, Step 14
- Verify ESF Group 1 lights OFF
- Verify ESF Group 2 lights - LIT CTMT will not yet be adverse RO Determine If ADVERSE CTMT Conditions E-O, Exist Step 15 Page 33 of 58
SEC. ,ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
- Ctmt temperature GREATER THAN 180°F OR
- Ctmt radiation GREATER THAN 105 RO Verify ECCS Flow E-O, Step 16 Check PZR pressure - GREATER THAN E-O, 1900 psia Step 16.a Proceed to step 16.d. E-O, Step 16.a RNO Check PORV block valves - OPEN E-O, Step 16.b Proceed to step 17. E-O, Step 16.c Check charging pumps - E-O, Step 16.d FLOW INDICATED RO START pumps and Align valves. E-O, Step 16.d, RNO RO Check RCS pressure - GREATER THAN E-O, 1650 psia (1950 psia ADVERSE CTMT) Step 16.e US Proceed to Step 17 E-O, Step 16.e, Page 34 of 58
SEC .. ON 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RNO Check SI pumps - FLOW INDICATED E-O, Step 16.f START pumps and Align valves. E-O, Step 16.f RNO Check RCS pressure - LESS THAN 300 psia E-O, (500 psia ADVERSE CTMT) Step 16.g Proceed to step 17. E-O, Step 16.g RNO CREW should perform a short brief and come out of "Master Silence" at the completion of Step 16.
BOP Verify Adequate Heat Sink E-O, Step 17 Check NR level in at least one SG E-O, GREATER THAN 8% (42% ADVERSE Step 17.a CTMT)
Proceed to step 17.d. E-O, Step 17.a RNO Verify Total AFW Flow - GREATER THAN E-O, 530 gpm Step 17.d BOP Verify AFW Valve Alignment - PROPER E-O, EMERGENCY ALIGNMENT Step 18 Page 35 of 58
SEt.. ,uN 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify ECCS Valve Alignment - PROPER E-O, EMERGENCY ALIGNMENT Step 19 Check if CBI is required E-O, Step 20 Yes. RO Check CONTROL BUILDING ISOLATION E-O, annunciator (MB4D 3-6) - LIT Step 20.a Check Train A Control Building filter fan E-O, (3HVC*FN1A) - RUNNING Step 20.b Check recirc damper for the running E-O, Control Building filter fan Step 20.c (3HVC*AOD119A or B) - OPEN RO Verify ESF Group 2 CBI lights - LIT E-O, Step 20.d RO Align HVAC components as necessary for E-O, minimum safety function. Step 20.d, RNO BOP Verify control building purge supply fan and E-O, purge exhaust fan - NOT RUNNING Step 20.e BOP Place kitchen exhaust fan in OFF E-O, Step 20J BOOTH INST NOTE When asked, REPORT that "all SLCRS US Verify SLCRS doors - CLOSED E-O, doors indicate closed." Step 20.g Perform the following: E-O, Step 20.h T=4min BOOTH REPORT "Control Building pressure PEO CLOSE and DOG the following Control Page 36 of 58
SEC., ,uN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard from being boundary doors are Closed and Building pressure boundary doors.
dispatched Dogged or verified closed as directed."
- CB west 47'6" (C-47-1A)
- CB east 64' 6" (C-64-1 B)
Verify the following Control Building pressure boundary doors - CLOSED
- CB west 47'6" (C-47-1)
- CB north 64'6" chiller room door (C 64-4)
- CB north 64'6" chiller room door (C 64-5)
- CB east 49'6" (C-49-1)
RO Check RCS Temperature E-O, Step 21 Verify RCS cold leg WR temperature GREATER THAN 550°F Proceed to step 21.c.
BOP Maintain total feed flow BETWEEN 530 and E-O, 600 gpm until NR level is GREATER THAN Step 21.c 8% (42% ADVERSE CTMT) in at least one SG BOP CLOSE SG atmospheric relief and relief E-O, bypass valves Step 21.d Page 37 of 58
SEC. .. IN 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard BOP Check the following valves - CLOSED E-O, Step 21.e
- MSIV bypass valves Check RCS cold leg WR temperature E-O, GREATER THAN 550°F Step 21.f Proceed to step 22. and, WHEN RCS E-O, temperature GREATER THAN 550°F, Step 21.f THEN Perform step 21.g. RNO Check Power To SBa Diesel Auxiliaries E-O, Step 22 E-O, Verify any SBO bus tie breaker - CLOSED Step 22.a TO AN ENERGIZED BUS
- Bus 34A: 34A1-2
- Bus 34B: 34B1-2
- Bus 24E: A505 (Unit 2)
=
T step 22.a Examiner "The extra licensed operator will IE busses 34A AND 34B are NOT energized, E-O, RNO carry out GA-27." THEN Using GA-27, Establish power to SBO Step 22.a reached diesel auxiliaries. RNO RO Check PZR Valves E-O, Step 23 Verify PORVs - CLOSED E-O, Step 23.a Page 38 of 58
SEC .. IN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Task Revision: °chg 2 Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify normal PZR spray valves - CLOSED E-O, Step 23.b RO Verify PORV block valves - AT LEAST E-O, ONE ENERGIZED VALVE OPEN Step 23.c RO Verify PZR safety valves - CLOSED E-O, Step 23.d CREW To prevent seal damage, seal injection flow E-O, should be maintained to all RCPs. Step 24, CAUTION RO Check If RCPs Should Be Stopped E-O, Step 24 Verify RCPs - ANY RUNNING E-O, Step 24.a RO Verify RCS pressure - LESS THAN 1500 psia E-O, (1800 psia ADVERSE CTMT) Step 24.b US Proceed to Step 25 E-O, Step 24.b, RNO Verify either of the following:
RO E-O, Step 24.c
- Charging pumps - AT LEAST ONE RUNNING AND AT LEAST ONE COLD LEG INJECTION VALVE OPEN OR
- SI pumps - AT LEAST ONE Page 39 of 58
SEC.. ,ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RUNNING RO STOP all RCPs E-O, Step 24.d
[*]
BOP Check If SG Secondary Boundaries Are E-O, RO Intact Step 25 Check pressure in all SGs E-O, Step 25.a
- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
- NO SG COMPLETELY DEPRESSURIZED BOP Check If SG Tubes Are Intact E-O, Step 26 RO Sample all SGs for activity E-O, Step 26.a
- 1. RESET SG blowdown sample isolation
- 2. OPEN SG blowdown sample isolation valve(s)
BOOTH Acknowledge the request to 3. Request Chemistry obtain activity samples perform the S/G samples. Ensure using HP coverage crew request activity samples with HP coverage Page 40 of 58
SEt. .. ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard NOTE: The BOP/Crew may observe BOP Check steam generator levels - NO SG E-O, level going up in the 'B' SG more LEVEL INCREASING IN AN Step 26.b rapidly than the other SGs. This is due UNCONTROLLED MANNER to tripping of the 'B' RCP due to high vibrations, NOT a rupture in the 'B' SG.
Verify trend history and alarm status of E-O, radiation monitors Step 26.c
- Main steam line - NORMAL
- Condenser air ejector - NORMAL
- Verify Ctmt radiation using 3CMS*RE22 (pre-trip) - NORMAL
- Verify Ctmt radiation using radiation monitoring group histogram (CTMT)
NORMAL CTMT pressure will not be normal.
- Verify Ctmt pressure - NORMAL
- Verify Ctmt recirculation sump level NORMAL The crew should conduct a short US Initiate monitoring of CSF Status Trees and E-O, transition brief and transition to E-1. Go to E-1, Loss of Reactor or Secondary Step 26 Coolant. RNO Page 41 of 58
SEC. ,ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard E-1 (rev 024) Actions RO To prevent seal damage, seal injection flow E-1, Step 1 should be maintained to all RCPs. CAUTION Note The US should remind the operators US Note: Foldout page must be open. E-1, Step 1 to review their Foldout Page Books NOTE RCP's are stopped due to the loss of US Check If RCPs Should Be Stopped E-1, Step 1 offsite power.
RO Verify RCP's - ANY RUNNING E-1 Step 1a US Proceed to step 2 E-1 Step 1a RNO US Check If SG Secondary Boundaries Are E-1, Step 2 Intact BOP! Check pressures in all SGs. E-1, Step 2.a RO
- NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
- NO SG COMPLETELY DEPRESSURIZED US Check Intact SG Levels E-1, Step 3 BOP Verify NR level - GREATER THAN 8% (42% E-1, ADVERSE CTMT) Step 3.a BOP Control feed flow to maintain NR level E-1, Page 42 of 58
SEC, ,ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard between 8% and 50% (42% and 50% Step 3.b ADVERSE CTMT)
US Check Secondary Radiation E-1, Step 4 RO Sample all SGs for activity. E-1, Step 4.a
- 1) RESET SG blowdown sample isolation.
- 2) OPEN SG Slowdown sample isolation valve(s)
- 3) Request Chemistry obtain activity samples using HP coverage RO Verify trend history and alarm status of E-1, radiation monitors Step 4.b Main steam line - NORMAL Condenser air ejector - NORMAL
- SG blowdown - NORMAL CRE If any PZR PORV opens because of high E-1, Step 5 W PZR pressure, step 5.a should be repeated CAUTION after pressure decreases to LESS THAN 2350 psia.
US Check PZR PORVs and Block Valves E-1, Step 5 RO Verify PORVs - CLOSED E-1, Step 5.a Page 43 of 58
SEC-,ION 4 Lesson
Title:
Large Break LOCA Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RO Verify block valves - AT LEAST ONE OPEN E-1, Step 5.b US Check If ECCS Flow Should Be Reduced E-1, Step 6 RO Verify RCS subcooling based on core exit E-1, TCs - GREATER THAN 32°F (115°F Step 6.a ADVERSE CTMT)
BOP Verify secondary heat sink E-1 Step 6.b
- Narrow range level in at least one intact SG - GREATER THAN 8% (42%
ADVERSE CTMT)
RO Verify RCS pressure - STABLE OR E-1 INCREASING Step 6.c PZR level will be < 16% RO Verify PZR level - GREATER THAN 16% E-1 (50% ADVERSE CTMT) Step 6.d US Proceed to CAUTION prior to step 7. E-1, Step 6, RNO US To ensure adequate ECCS flow, do not stop E-1, Step 7 any recirculation spray pumps used for core CAUTION injection flow.
Page 44 of 58
SEC, ION 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: a chg 2 Task Time IDA/Malf Instructor Information/Activit~ nAssign Expected Action Standard US The recirculation spray pumps are E-1, Step 7 sequenced to automatically start 11 minutes NOTE after a CDA.
RO Check if containment spray should be E-1, step 7 stopped.
RO Verify quench spray pumps - RUNNING E-1, Step 7.a US Proceed to CAUTION prior to step 8. E-1, Step 7,a, RNO After SI reset, manual operator action is E-1, Step 8 required to: CAUTION
- Open the charging cold leg injection valves when RCS pressure decreases to LESS THAN 1900 psia.
- Restart the RHR pumps if RCS pressure decreases in an uncontrolled manner to LESS THAN 300 psia (500 psia ADVERSE CTMT).
- Restart safeguards equipment if offsite power is lost.
US Check If RHR Pumps Should Be Stopped E-1, Step 8 Page 45 of 58
SEC .. JN4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard US Check RHR pumps - ANY RUNNING IN SI E-1, MODE Step 8.a RCS pressure should be around RO Check RCS pressure E-1, 1400 psia and stable. But Step 8.b depending on the speed of the 1) Verify pressure - GREATER THAN 300 crew, RCSpressure may still be psia (500 psia ADVERSE CTMT) going down very slowly. If the crew elects NOT to stop RHR 2) Verify pressure - STABLE OR pumps based on this trend, this is INCREASING satisfactory.
Crew should reset SI RO RESET SI, if necessary E-1, Step 8.c NOTE: This step will stop the RHR RO STOP RHR pumps and Place in Auto E-1, Pumps. If stopped, the pumps will Step 8.d need to be restarted when the LOCA becomes larger.
US Check RCS and SG Pressures E-1, Step 9 BOP
- Check RCS pressure - DECREASING E-1, Step 9 OR STABLE T= step 10 RC02B This will increase the severity of US Check If Diesel Generators Should Be E-1 the SBLOCA to a point where Stopped Step 10 Trigger 11 sev= ADVERSE CTMT will occur and if 100% stopped, the RHR pumps will need Page 46 of 58
SEt, .*ON 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard to be restarted.
The crew will need to recognize 3 items:
1- The rise in CTMT pressure will generate an orange path (no CTMT spray pumps are running) on CTMT, and require transition to FR Z.1 2* CDA has failed to actuate.
3- If stopped, RHR pumps will need to be restarted.
Note A red path on Integrity may come in US Go to FR-Z.1 and restart the RHR pumps E-1, step 8 first. If so the crew will perform FR caution P.1 first as it has a higher priority. and OP3272 FR*P.1 (rev 015) Steps CRE
- If DWST level decreases to LESS THAN FR-P.1 W 80,000 gal, Shift AFW pump suction to Step 1 the CST using GA-4. CAUTION
- If RWST level decreases to LESS THAN 520,000 gal, Go to ES-1.3, Transfer to Cold Leg Recirculation, to align the ECCS system.
RCS pressure will be less than 300 RO Check RCS Pressure - GREATER THAN FR-P.1, psia. 300 psia (500 psia ADVERSE CTMT) Step 1 Page 47 of 58
SEt. ..ON 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard RHR pumps may be started by the crew at this point.
us Perform the applicable action: FR-P.1, Step 1, RNO
RHR Pump flow should be > 1.000
- IE RHR pump flow is GREATER THAN gpm. The appropriate transition will 1000 gpm THEN Go to procedure and be to FR-Z.1 step in effect.
FR-Z.1, Response to CTMT High Pressure, Rev. 016-02 If RWST level decreases to LESS THAN FR-Z.1, 520,000 gal, Go to ES-1.3, Transfer to Cold Step 1 Leg Recirculation, to align the ECCS CAUTION system.
US/RO Check if CDA Required FR-Z.1, Step 1 Yes. CTMT pressure will be greater RO Check CTMT pressure GREATER THAN 23 FR-Z.1, than 23 psia. psia Step 1.a "CONTAINMENT DEPRESS Verify Annunciator "CTMT DEPRES FR-Z.1, ACTUATION" will NOT be lit. ACTUATION" (MB2B 5-5)-LlT Step 1.b Page 48 of 58
SEc" .. uN 4 Lesson
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard The RO is expected to attempt to RO Initiate CDA. FR-Z.1, manually initiate CDA using the Step 1.b main board push buttons RNO RO Check RPCCW pumps - STOPPED FR-Z.1, Step 1.c The RPCCW pumps will have to be RO STOP pumps. FR-Z.1, manually stopped. Step 1.c RNO RCPs have already been stopped. RO STOP all RCPs FR-Z.1, Step 1.d The BOP will have to manually stop the BOP Check CAR fans - STOPPED FR-Z.1, CAR and CRDM fans. Step 1.e Check CRDM fans - STOPPED FR-Z.1, Step 1.f If ECA-1.1, Loss of Emergency Coolant FR-Z.1, Recirculation, is in progress, Ctmt spray Step 2 should be operated as directed in ECA-1.1 CAUTION US Verify Quench Spray System Operation FR-Z.1, Step 2 RO Check annunciator RWST EMPTY QSS PP FR-Z.1, OFF (69,331 gal)(MB2A 5-2) - NOT LIT Step 2.a NO. RO Verify quench spray pumps - RUNNING FR-Z.1, Step 2.b Critical Task r1 RO START pumps. FR-Z.1, Step 2.b, Page 49 of 58
SEt. .. IN 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard The RO must manually start the RNO [*]
QSS pumps and manually open the quench spray pump discharge valves.
RO Verify running quench spray pump discharge FR-Z.1, valves - OPEN Step 2.c
- 3QSS*MOV34A
- 3QSS*MOV34B RO OPEN valves. FR-Z.1, Step 2.c, RNO [*]
US Check Ctmt Status FR-Z.1, Step 3 CTMT pressure will be less than 60 Check Ctmt pressure - LESS THAN 60 FR-Z.1, psia. psia Step 3.a The US should transition back to E- Go to procedure and step in effect and, FR-Z.1, 1, step 10. after evaluating step applicability based Step 3.b on plant conditions, Perform the remainder of this procedure as time allows The scenario may be terminated upon completion of FR-Z.1.
Page 50 of 58
SEL-, ION 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Task Time IDAlMalt Instructor Information/Activity Assign Expected Action Standard Page 51 of 58
SECTION 4 Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 EVALUATION GUIDE I. Crew FOLLOW-UP QUESTIONS
- 1. What is the Emergency Classification for this event?
ALERT - Charlie One based on failure of the RCS barrier. (BA1)
- 2. What plant condition(s) is(are) of greatest concern for (this event)?
- 4. What actions did the crew take to directly mitigate (this event)?
- 5. Which safety function(s) were challenged or had the greatest potential for challenge? Describe why.
Page 52 of 58
SECTION 4 EXAM GUIDE
SUMMARY
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: o chg 2 II. Critical Tasks Note: Critical Tasks are not required for Progress Review Exa~
TASK DESCRIPTION TASK # KJA >/= 3.0 BASIS SELECTION Energize at least one ac E-O ~- C 055 EA1.02 4.3 4.4 055 EA1.06 4.14.5 Failure to energize an ac emergency bus before emergency bus constitutes 055 EA2.02 3.9 4.7 transition out of E-O, "mis-operation or incorrect 055 EA2.06 3.74.1 unless the transition is to crew performance which ECA-O.O, in which case leads to degraded the critical task must be emergency power capacity."
performed before Failure to perform the placing safeguards critical task also results in equipment handswitches needless degradation of a in the pull-to-Iock barrier to fission product position. release, specifically of the RCS barrier at the point of the RCP seals.
Manually actuate at E-O--D 4.5/4.8 Failure to manually actuate least one train of SIS 006030 Sl represents a actuated safeguards A2.01 "demonstrated in-ability by before completion of the crew to take an action step 4 of E-O. or combination of actions that would prevent a challenge to plant safety."
Establish at least one EO-E 026000 Failure to establish at least Quench Spray train flow A1.01 one Quench Spray train before completion of 3.9/4.2 flow under th~9 postulated FR-Z.1 step 4. conditions constitutes a "demonstrated inability by the crew to recognize a failure/incorrect auto actuation of an ESF system or component."
Note: [*] Used to designate critical tasks. Should also be incorporated into column 3 or 4 of Instructor Guide.
Page 53 of 58
SIMULATOR TRAINING SHIFT TURNOVER REPORT DATE-TIME PREPARED BY SHIFT PLANT STATUS:
Today Now I Shift Manager I 06:00 18:00 Mode: 1 Rx Power: I%
Megawatts: Thermal: 256 MWTH PZR Pressure: ?250 pSia Electric: 0 MWe RCS T-AVE: .T'degF RCS Leakage: Identified: 0.015 gpm Protected Train/Facility: A TRAIN Orange Unidentified: 0.036 gpm PRA: Green Date/Time: Todav0015 Active Tracking Records and Action Statements Equipment/Reason LCO Action Date Time in LCO Action Requirement Time Left 00 Compensatory Actions / Temp Logs Watch Open Date Class Reason Reason Position None Surveillances f Evolutions in Progress OP 3204 I Steady State Operation Reactivity Briefing (see reactivity thumbrules / spread sheet for additional info)
Current Rod Height CBD@90 I
Xenon Trend Stable Current Boron 1868 ppm I
Shift Orders Reactor power is stable low in the power range (reactor power 7%), following a reactor startup by the previous shift. This is the initial plant startup from a short non-refueling outage. OP 3203, Plant Startup is in progress and complete up through step 4.3.8. The crew is to raise reactor power from 7% to 15 to 19%
in accordance with step 4.3.9. The reactivity plan is to raise reactor power using rods at no more than 2 steps per minute. Feed Control is on the FRV Bypass Valves in automatic, with the "A" TO MFP in service, with it's recirc valve open to minimize feed control instabilities.
There will be minimum staffing for this plant startup. This has been approved by Plant Management.
Page 54 of 58
ATTACHMENT 2 VALIDATION CHECKLIST
Title:
Large Break LOCA ID Number: 2K11 NRC-04 Revision: o chg 2 Verified By:
(Initials)
Initial Conditions:
The initial condition(s) contained in the guide are certified or have been DM developed from certified ICs.
Test Run:
The scenario contained in the guide has been test run in part or whole on the simulator. The simulator response is reasonable and as expected. If a simulator guide revision does not affect original Test Run, then enter N/A.
Simulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or anomalous response by reviewing the Simulator Modeling and Anomalous Response List.
For Examination Scenario:
The Scenario Attributes Checklist is complete and attached. This is not required for Progress Review Exams.
Dave Minnich 5/7/11.
Actions Complete (Signature) Date Page 55 of 58
Appendix D Scenario Outline Form ES-D**1 Facility: Millstone 3 Scenario No.: 2K11 NRC-04 Op-Test No.: 2K11 Examiners: Operators:
Initial Conditions: IC-08 (modified), 7% 120wer, Beginning of life, No Xe.
, Turnover:
The crew will take the shift with reactor Qower stable and just having entered MODE 1 (reactor Qower 7%), following a reactor startul2 by: the I2revious shift. This is the initial I2lant startuQ from a refueling outage. OP 3203, Plant StartuQ. is in Qrogress.
Event No.
Malf.
No I Event Type*
Event Description I
1 R (RO) Power increase to place the Main Turbine online using I
R (SRO) OP 3203, Plant Startup. (Section 4.3)
N (BOP) 2 NI11 P-10 Permissive failure results in a termination of the startup and Tech S!2.ec 3.0.3 entry.
3 I S\N01C C (RO) 'C' Service Water Pump trip. (Annunciator response)
- (Tech Spec entry) 4 I NI09B I (BOP) Power Range Nuclear Instrument (N I) Channel 42 Lower Detector fails high requiring FRV Bypass valve controllers to be Q)aced in rnanual.1Tech Spec enlJYl 5 RC25B C (RO) 'B' RCP high shaft vibration requiring an immediate C (BOP) shutdown of the affected RCP. (Annunciator response, AOP 3554) ~
6 ED01 Loss of offsite power. 'A' Emergency Diesel Generator EG13A C (BOP) (EDG) fails to automatically start and must be manually RP11M started from MB8. BOP must manually close the 'A' and 'B' EDG output breakers. -~
7 CV13B M (ALL) Small break LOCA inside CTMT (catastrophic loss of RC02B 'B' RCP seal packagel. Safety Injection re_quired.
8 RP07A1B C (RO) Safety 'nlection fails to automatica"~ actuate.
9 RP11L C (BOP) Feedwater Isolation fails to automaticall~ actuate.
10 I RC02C C (RO) I Large break LOCA inside CTMT. CDA fails to auto-IRP06A1B actuate. .
- N)ormal, R )eactivity, ~
{Qnstrument, {C~omponent, ~Mlajor Lesson
Title:
Large Break LOCA Page 56 of 58
ID Number: 2K11 NRC-04 Revision: 0 chg 2 Assessor: Dave Minnich QUALITATIVE ATTRIBUTES The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.
The scenario consists mostly of related events.
Each event description consists of:
the point in the scenario when it is to be initiated the malfunctions(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
The events are valid with regard to physics and thermodynamics.
Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
The simulator modeling is not altered.
The scenario has been validated. Pursuant to 10 CFR 5!i.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure functional fidelity is maintained while running the planned scenario.
- o. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered lAW Section 0.5 of ES-301.
- 1. All individual operator competencies can be evaluated, as verified using form ES-301-6, Each operator will be Significantly involved in the minimum number of transients and events specified on Form ES-301-5.
level of difficulty is appropriate to support licensing decisions for each crew position.
Page 57 of 58
Lesson
Title:
Large Break LOCA 10 Number: 2K11 NRC-04 Revision: 0 chg 2 Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.
- 01. Total Malfunctions (TM) - 5 to 8 required Total __8_
(1) 'c' Service Water Pump trip, (2) PRNI Channel Failure, (3) RCP High Vibrations, (4) Loss of Offsite Power / EOG fails to automatically start, (5) Small break LOCA, (6) Safety Injection Auto Actuation Failure, (7) Feedwater Isolation fails to auto-actuate, (8) Large Break LOCA / COA fails to auto-actuate.
(1) EOG fails to automatically start, (2) Safety Injection Auto Actuation Failun9, (3) Feedwater Isolation fails to auto-actuate, (4) Large Break LOCA / COA fails to auto-actuate.
- 03. Abnormal Events (AE) - 2 to 4 required Total __3_
(1) 'C' Service Water Pump trip (ARP), (2) PRNI Channel Failure (AOP 3571), (3) RCP High Vibrations / RCP Trip (AOP 3554)
- 04. Major Transients (MT) - 1 to 2 required Total __1 _
(1) Small break LOCA
- 05. EOP's (EU) entered/requiring substantive actions -- 1 to 2 required Total __2_
(1) E-1, (2) FR-Z.1
- 06. EOP Contingencies requiring substantive actions [ECAs/FRs/] (EC) -- Total 1 o to 2 required (1) FR-Z.1
- 07. Critical Tasks (CT) - 2 to 3 required Total __3_
E-O- C Energize at least one ac emergency bus E-O-O Manually actuate at least one train of SI E-O-E Establish at least one Quench Spray train flow
- 08. Approximate Scenario Run Time: 60 to 90 min. Total J50 min
- 09. EOP run time: Total 60 min
- 10. Technical Specifications are exercised during the scenario.
Pagel 58 of 58