ML023510113
| ML023510113 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 02/25/2002 |
| From: | Gody A Division of Reactor Safety IV |
| To: | Denise Wilson Nebraska Public Power District (NPPD) |
| References | |
| 50-298/02-301 50-298/02-301 | |
| Download: ML023510113 (306) | |
Text
Facility: Cooper Date of Examination: August 2002 Examination Level (circle one): RO Operating Test Number: Cat A Describe method of evaluation:
- 2. TWO Administrative Questions A.1 JPM: Admin JPM, PMIS Point Review (Section 12.0 of Plant Parameter CONDUCT OF OPERATIONS PROCEDURE 2.0.2) (RO Verfication will obtain a daily listing of computer points that are unhealthy, print, review the points and determine if any of the points are unexpected).
K/A: 2.1.19 (3.0/3.0)
JPM: Perform RO Review of selected Daily Surveillance Logs per Logs 6.LOG.601. (The RO will be required to enter relevant information from that provided onto 6.LOG.601 Attachment 3, Unidentified Leakage Log Sheet, and complete the associated calculations using this information. When the log sheet is completed, the RO will be required to review the information, identify the excessive leakage rate increase, enter it on a discrepancy sheet, and inform the CRS).
K/A: 2.1.23 (3.9)
A.2 JPM: Apply valve testing requirements when performing stroke timing.
Surveillance (The RO will be given the stroke time for the first valve/damper Testing tested and directed to complete the applicable data sheet and determine how to proceed based upon the entry. Upon determining that the valve must be retested, the retest stroke time will be provided as a CUE. The RO will be required to enter the retest stroke time on the data sheet and determine whether or not to proceed and the associated administrative actions).
K/A: 2.2.12 (3.0)
A.3 Q.1. Given an accumulated TEDE and an expected Significant additional exposure for outage work that results in Radiation Hazards /
exposure above the station administrative limit Reduce Excessive Levels Of Radiation determine the requirements/approvals to perform the And Guard Against work.
Personnel Exposure CLOSED REFERENCE.
K/A: 2.3.1 (2.6), 2.3.4 (2.5)
Q.2. Given plant radiological conditions and an EOP support task that needs to be performed in the plant, evaluate the conditions and determine the maximum amount of time allowed using emergency exposure limits.
K/A: 2.3.1 (2.6), 2.3.10 (2.9)
A.4 Q.1. Determine the emergency facilities activated at Emergency the ALERT emergency classification level if this is the Facilities /
initial emergency classification.
Communications CLOSED REFERENCE.
K/A: 2.4.29 (2.6), 2.4.39 (3.3)
Q.2. Given the location and duties of a licensed operator in the plant, determine the evacuation requirement if an ALERT is declared and this is the initial emergency classification.
CLOSED REFERENCE.
K/A: 2.4.29 (2.6), 2.4.39 (3.3)
Facility: COOPER Date of Examination: August 2002 Examination Level (circle one): SRO Operating Test Number: Cat A Administrative Topic/Subject Describe method of evaluation:
Description 1. ONE Administrative JPM, OR
- 2. TWO Administrative Questions A.1 Parameter Verification JPM: Perform a Time To Boil Determination (Loss of SDC) per 2.4 SDC (The SRO will be required to evaluate time to boil based on plant conditions that are provided at the start of the JPM. The SRO must use the relevant information to select the appropriate figures and then apply the information to the correct figure to determine time to boil).
K/A 2.1.23 (4.0), 2.1.25 (3.1)
Logs JPM: Perform SRO Review of Daily Surveillance Logs per 6.LOG.601.
(The SRO will be required to review 6.LOG.601 Attachment 3, Unidentified Leakage Log Sheet. This includes recognition of TS non-compliance, identification of TS ACTIONS, and other administrative actions required as a result of the excessive leakage rate increase).
K/A: 2.1.23 (4.0)
A.2 Equipment Control/ JPM: Perform a log entry into the TS tracking system LCO Tracking per 2.0.11. (The SRO will be required to make an entry for TS equipment removed from service for maintenance. Because the equipment will be restored to OPERABE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the SRO will make a narrative log entry and provide documentation to the SS).
K/A: 2.2.23 (3.8)
A.3 Significant Q.1. Given a valve to be stroked by operators, Radiation Hazards / considering the station administrative limits and Reduce Excessive collective/individual exposure for ALARA performance Levels Of Radiation And Guard Against recommendations, determine if shielding should be Personnel Exposure installed and whether one or two operators should be used. (The SRO must determine if less total dose will be received by using one or 2 operators. Then he must determine if less cumulative dose will be received if shielding is installed or not.)
K/A: 2.3.1 (3.0), 2.3.4 (3.1)
Q.2. Given plant radiological conditions during an emergency, determine the emergency radiation exposure control requirements for the conditions. (The SRO will be required to determine the applicable emergency radiation exposure control requirements given plant conditions, including selection of the person to receive the emergency exposure based on descriptions of available personnel).
CLOSED REFERENCE.
K/A: 2.3.1 (3.0), 2.3.10 (3.3)
A.4 EAL and Q.1. Given plant conditions, determine the reporting Classification, requirement(s) per 10CFR50.72 and 10CFR50.73.
Communications K/A: 2.4.30 (3.6)
Q.2. Given plant conditions at the completion of the scenario as the SRO, determine the emergency classification.
K/A: 2.4.40 (4.0), 2.4.41 (4.1)
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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level RO Administrative Topic A.3 Subject
Description:
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Question:
You have an accumulated TEDE of 0.5 Rem for the year. Because of dose projections for work in the outage, you are expected to receive an additional TEDE of 0.8 Rem.
What authorization is required for you to receive the expected dose?
Answer:
Individuals Supervisor (SS), and ALARA Supervisor.
Justification:
The total expected dose is 1300 mrem. Approvals for dose above 1000 mrem are required by the ALARA Supervisor.
Technical Reference(s):
9.ALARA.1: 6.2.1 K/A #: Importance:
2.3.1 2.6 2.3.4 2.5 Comments:
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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level RO Administrative Topic A.3 Subject
Description:
Radiation Protection Question Number: 2 Question:
An MSIV closure scram has occurred with an ATWS. The RPV was emergency depressurized due to exceeding the Heat Capacity Temperature Limit (HCTL). Current power level is 10% with RPV water level at TAF. The Plume Exposure pathway has been evacuated. The scram discharge volume must be manually drained to insert control rods to shut the reactor down. Dose rates in the area are 15 Rem/hr.
What is the time limit (if any) the Station Operator is allowed to spend on the draining evolution if the Emergency Director consents to the maximum dose he can authorize?
Answer:
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 40 minutes.
Justification:
25 Rem/15 Rem/hr = 1.6666 hours0.0772 days <br />1.852 hours <br />0.011 weeks <br />0.00254 months <br /> or 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 40 minutes.
5.7.12, step 3.1.2.2, 25 Rem is the maximum dose for Undertaking corrective action on station equipment and systems to protect large populations from radiological exposure.
If rods are not inserted, containment failure will result in large releases of radiation to the public, but not extensive dose to large populations (unlimited dose).
Technical Reference(s):
5.7.12; Section 2.6, Attachment 1 K/A #: Importance:
2.3.1 2.6 2.3.10 3.3 Page 20 of 218
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STUDENT HANDOUT Question:
An MSIV closure scram has occurred with an ATWS. The RPV was emergency depressurized due to exceeding the Heat Capacity Temperature Limit (HCTL). Current power level is 10% with RPV water level at TAF. The Plume Exposure pathway has been evacuated. The scram discharge volume must be manually drained to insert control rods to shut the reactor down. Dose rates in the area are 15 Rem/hr.
What is the time limit (if any) the Station Operator is allowed to spend on the draining evolution if the Emergency Director consents to the maximum dose he can authorize?
Page 22 of 218
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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level RO Administrative Topic A.4 Subject
Description:
Emergency Facilities / Procedures Question Number: 1 CLOSED REFERENCE!
Question:
What emergency facilities are activated for an ALERT emergency classification if this is the INITIAL emergency plan classification?
Answer:
TSC (0.4 pt.), OSC (0.4 pt.), and EOF (0.2 pt.) are activated for an Alert, Site Area Emergency, and General Emergency.
Technical Reference(s):
5.7.2, Att. 4 5.7.7: Section 1 5.7.8: Section 1 5.7.9: Section 1 K/A #: Importance:
2.4.29 2.6 2.4.39 3.3 Comments:
Page 23 of 218
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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level RO Administrative Topic A.4 Subject
Description:
Emergency Facilities / Procedures Question Number: 2 CLOSED REFERENCE!
Question:
You are a licensed Reactor Operator on day shift assigned to the RELIEF CREW. You are escorting two (2) visitors who are auditing clearances in the Work Control Center. A transient occurs that results in the initial declaration of an ALERT and a site evacuation.
What are your required actions regarding the location that you and the visitors physically report to?
Answer:
Escort the visitors to the exit turnstile and direct them to go to Training Building Classroom J, H or I and then report to the Control Room.
Justification:
Personnel escorting visitors shall take them to the exit turnstile and direct them to report to the Training Building Classroom j, H, or I for assembly. Escorts then report to their own designated assembly area. Operations personnel acting as relief crew shall report to the Control Room.
Technical Reference(s):
5.7.10: 4.2, 4.3.2 K/A #: Importance:
2.4.29 2.6 2.4.29 3.3 Comments:
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 27 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
Trainee: Examiner:
Pass: Fail: Examiner Signature:
Date:
Performed faulted/non-faulted: Faulted Additional Program Information:
- 1. Appropriate Performance Locations: CR, SIM, EOF
- 2. Appropriate Trainee level: RO/SRO
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 10 minutes
- 5. NRC K/A 2.1.23 (3.9/4.0)
Directions to Examiner:
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. All blanks must be filled out with either initials or an "NP" for "not performed"; an explanation may also be written in the space if desired by the examiner.
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 28 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
- 4. Brief the trainee, place the simulator in run, and tell the trainee to begin.
- 5. Hand the candidate the correct ATTACHMENT 3 example attached to this JPM. ENSURE the RO Candidates are NOT provided the SRO attachment!
Directions to Trainee:
When I tell you to begin, you are to perform an RO(SRO) review of the daily logs. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to perform an average drywell temperature calculation.
During performance, state the actions you are taking, e.g.:
repositioning controls and observing instrumentation.
==============================
================
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 29 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
General Conditions:
- 1. The plant is operating at 100% power.
- 2. Current reading on RW-FQ-527 is 3692.
General
References:
- 1. Procedure 6.LOG.601 General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 2. Critical checks denoted by "*".
- 2. Simulator cues denoted by "#".
- 3. Faulted steps denoted by "ó"
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to perform an RO(SRO) review of the daily logs.
- 2. Accurately locate and identify all instrumentation required to be monitored to perform an RO(SRO) review of the daily logs.
- 3. Correctly interpret instrument and system responses and their interrelationships when performing an RO(SRO) review of the daily logs.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 30 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 31 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
Initiating Cue(s):
(RO) You are to fill out Attachment 3, UNIDENTIFIED LEAK RATE CHECKS, using the data provided and complete an RO review of the log sheet per 6.LOG.601. Inform the CRS when the review is complete.
(SRO) You are to perform a SRO review of Attachment 3, UNIDENTIFIED LEAK RATE CHECKS, per 6.LOG.601 and determine applicable actions based upon your review. Inform the SS when the review is complete.
NOTE: Place the Simulator in RUN and tell the trainee to begin.
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 32 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
Performance Checklist Standards Initials NOTE: If performing as RO perform the following steps. If performing as SRO, go to page 6.
- 1. Refer to 6.LOG.601. Refers to 6.LOG.601 Attachment 3.
- 2. Present Grand Record RW-FQ-527 reading of 3692 on Total. Attachment 3. ________*
- 3. Previous Grand Record RW-FQ-527 reading of 2252 on Total. Attachment 3. ________*
- 4. Calculate total Subtract previous grand total from present gallons. grand total. Enter 1440 on Attachment 3. ________*
- 5. Time interval Calculates time interval (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> x 60 (minutes). minutes/hour) and enters 480 on attachment ________*
3.
- 6. Calculate leak Calculates leak rate (1440 ÷ 480) and enters rate. 3.0 on Attachment 3. ________*
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 33 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
Performance Checklist Standards Initials
- 7. Change in leak Subtracts previous day leak rate from rate. calculated leak rate (3.0 - 0.8) and records 2.2 ________*
on attachment 3.
- 8. Review and Identifies change in leak rate is above the evaluate OPERABILITY LIMIT. ________*
readings.
- 9. Informs CRS. Informs CRS that the change in leak rate is above the OPERABILITY LIMIT. ________
CUE: As the CRS, acknowledge the report.
This JPM is complete NOTE: It is not necessary to sign the sign-off and review sheet.
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 34 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
Performance Checklist Standards Initials NOTE: If performing as SRO, perform the following steps.
- 10. Review data sheet. Reviews Attachment 3 and identifies the change in leak rate is above the ________*
OPERABILITY LIMIT.
- 11. References References Attachment 20 and NOTE 51.
Attachment 20. Determines the NOTE applies to SR ________
3.4.4.1 and LCO 3.4.4.
- 12. References References Attachment 3 footnote ( c ).
Attachment 3 Determines TS 3.4.4 LCO statement is not ________*
footnotes. met and the ACTIONS must be entered.
- 13. Determines TS References TS 3.4.4 and determines entry Required Action. into Condition B must be entered. ________*
- 14. Determines TS References TS 3.4.4 and determines Required Action. unidentified leakage increase must be ________*
within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
CUE: If asked for DW Particulate Monitor reading, respond 200 cpm.
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 35 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299015O0301
==========================================================
Task
Title:
PERFORM RO/SRO REVIEW OF DAILY LOG
==========================================================
Performance Checklist Standards Initials
- 15. Informs the SS. Informs the SS of that the unidentified leakage increase is not within the limit ________
and TS 3.4.4 Condition B has been entered.
CUE: As the SS, acknowledge the report.
This task is complete.
NOTE: It is not necessary to sign the sign-off and review sheet.
Page 35 of 218
Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 36 of 218 Job Performance Measure Revision 00 ATTACHMENT 1 (RO)
Directions to Trainee:
When I tell you to begin, you are to enter the data on the appropriate log sheet and complete the RO review of the daily log. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to enter the data on the appropriate log sheet and complete the RO review of the daily log. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. The plant is operating at 100% power.
- 2. Current reading on RW-FQ-527 is 3692.
Initiating Cues:
You are to fill out Attachment 3, UNIDENTIFIED LEAK RATE CHECKS, using the data provided and complete an RO review of the log sheet per 6.LOG.601. Inform the CRS when the review is complete.
Page 36 of 218
Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 37 of 218 Job Performance Measure Revision 00 ATTACHMENT 2 (SRO)
Directions to Trainee:
When I tell you to begin, you are to perform a SRO review of the daily logs.
Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to perform an SRO review of the daily logs. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. The plant is operating at 100% power.
Initiating Cues:
You are to perform a SRO review of Attachment 3, UNIDENTIFIED LEAK RATE CHECKS, per 6.LOG.601 and determine applicable actions based upon your review. Inform the SS when the review is complete.
Page 37 of 218
Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 38 of 218 Job Performance Measure Revision 00 RO DATA SHEET ATTACHMENT 3, UNIDENTIFIED LEAK RATE CHECKS Time Last Pumped (Previous Day): 1600 0000 0800 1600 OPERABILITY APPLICABLE ATT. 20 RW-FQ-527 (a) READING READING READING LIMIT MODES NOTES Present Grand 1580 2252 Total
(-) Previous Grand 1100 1580 Total N/A N/A N/A
(=) Total Gallons 480 672
(÷) Time Interval 480 480 (minutes)
(=) Leak Rate (gpm) 1.0 1.4 # 4 gpm (b) 1, 2, 3 51
(-) Previous Day 0.7 0.7 0.8 N/A N/A N/A Leak Rate (gpm)
(=) Change In Leak + 0.3 + 0.7
- +1.5 gpm (c) 1 51 Rate (gpm)
(a) If Sump F Totalizer has failed, determine Total Gallons per failed Sump F Totalizer table and ensure the Conditions and Required Actions of LCO 3.4.5 are entered.
(b) If leak rate > 4 gpm, enter Conditions and Required Actions of LCO 3.4.4, then contact Engineering to determine available instrument margin. If leak rate > 5 gpm, ensure Conditions and Required Actions of LCO 3.4.4 are entered.
(c) If change in leak rate > +1.5 gpm, enter Conditions and Required Actions of LCO 3.4.4, then contact Engineering to determine available instrument margin. If change in leak rate > +2 gpm, ensure Conditions and Required Actions of LCO 3.4.4 are entered. If change in leak rate > +2 gpm and drywell monitor particulate channel indicates $ 8.0E4 cpm rise in activity during previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or subsequent 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, source of leakage from Type 304 or Type 316 austenitic stainless steel can not be ruled out. If drywell monitor particulate channel indicates < 8.0E4 cpm rise in activity during previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or subsequent 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, source of leakage is not due to Type 304 or Type 316 austenitic stainless steel.
Page 38 of 218
Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 39 of 218 Job Performance Measure Revision 00 SRO DATA SHEET ATTACHMENT 3, UNIDENTIFIED LEAK RATE CHECKS Time Last Pumped (Previous Day): 1600 0000 0800 1600 OPERABILITY APPLICABLE ATT. 20 (a)
RW-FQ-527 READING READING READING LIMIT MODES NOTES Present Grand 1580 2252 3692 Total
(-) Previous Grand 1100 1580 2252 Total N/A N/A N/A
(=) Total Gallons 480 672 1440
(÷) Time Interval 480 480 480 (minutes)
(=) Leak Rate (gpm) 1.0 1.4 3.0 # 4 gpm (b) 1, 2, 3 51
(-) Previous Day 0.7 0.7 0.8 N/A N/A N/A Leak Rate (gpm)
(=) Change In Leak + 0.3 + 0.7 + 2.2
- +1.5 gpm (c) 1 51 Rate (gpm)
(a) If Sump F Totalizer has failed, determine Total Gallons per failed Sump F Totalizer table and ensure the Conditions and Required Actions of LCO 3.4.5 are entered.
(b) If leak rate > 4 gpm, enter Conditions and Required Actions of LCO 3.4.4, then contact Engineering to determine available instrument margin. If leak rate > 5 gpm, ensure Conditions and Required Actions of LCO 3.4.4 are entered.
(c) If change in leak rate > +1.5 gpm, enter Conditions and Required Actions of LCO 3.4.4, then contact Engineering to determine available instrument margin. If change in leak rate > +2 gpm, ensure Conditions and Required Actions of LCO 3.4.4 are entered. If change in leak rate > +2 gpm and drywell monitor particulate channel indicates $ 8.0E4 cpm rise in activity during previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or subsequent 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, source of leakage from Type 304 or Type 316 austenitic stainless steel can not be ruled out. If drywell monitor particulate channel indicates < 8.0E4 cpm rise in activity during previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or subsequent 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, source of leakage is not due to Type 304 or Type 316 austenitic stainless steel.
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Nebraska Public Power District NRC ADMIN RO/SRO A.1-2 Cooper Nuclear Station Page 40 of 218 Job Performance Measure Revision 00 Page 40 of 218
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Performance Checklist Standards Initials
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Initiating Cues:
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Page 9 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Trainee: Examiner:
Pass: Fail: Examiner Signature:
Date:
Performed faulted/non-faulted: NON-Faulted Additional Program Information:
- 1. Appropriate Performance Locations: CR, SIM, EOF
- 2. Appropriate Trainee level: SRO
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 25 minutes
- 5. NRC K/A 2.2.23 (3.8)
Directions to Examiner:
- 1. This JPM evaluates the trainees ability to log a TS entry.
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
Page 10 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
- 3. All blanks must be filled out with either initials or an ANP@ for Anot performed@; an explanation may also be written in the space if desired by the examiner.
- 4. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Directions to Trainee:
When I tell you to begin, you are to log an entry into the narrative logs. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to log a TS entry. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
==============================
====================
Page 11 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
General Conditions:
- 1. The plant is at 100% power. HPCI has planned maintenance on the auxiliary oil pump planned to begin at 0000. The maintenance is scheduled for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 3. T.S. Tracker and SAP are unavailable General
References:
- 1. 2.0.11
- 2. TS 3.5.1 General Tools and Equipment:
- 1. Computer that provides access to the narrative log and has print capability.
Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by "*".
Page 12 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
- 2. Simulator cues denoted by "#".
- 3. Faulted steps denoted by "ó."
- 4. Ensure active log available for exam date.
Page 13 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to log a TS entry.
- 2. Accurately locate and identify all instrumentation required to be monitored to log a TS entry.
- 3. Correctly interpret instrument and system responses and their interrelationships when logging a TS entry.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
You are to assess plant conditions and perform a log entry into the narrative log and provide a printed copy for the SS to review. DO NOT approve the log entry.
Page 14 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Page 15 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Performance Checklist Standards Initials
- 6. Refer to Technical Determine HPCI is inoperable during aux oil pump Specifications maintenance. (TS 3.5.1.C HPCI System inoperable; ________*
RA C.1, Verify by administrative means RCIC system is OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND RA C.2 Restore HPCI to OPERABLE status within 14 days.)
CUE: If asked, RCIC is OPERABLE.
- 7. Refer to 2.0.11. Refers to 2.0.11 Step 3.1.7 for guidance.
- 8. Accesses narrative log. Accesses narrative log.
Enters date (todays date) and time
- 9. Date and time. (0000) of inoperability.
Enters LCO Condition (TS 3.5.1.C HPCI System
- 10. Condition, Required inoperable; RA C.1, Verify by administrative means Action, and Completion RCIC system is OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND RA ________*
Times C.2 Restore HPCI to OPERABLE status within 14 days.
CUE: If asked, RCIC is OPERABLE.
- 11. Work Order Enters Work Order #4000089. ________*
Prints a report of the entry and provides it to the SS.
- 12. Prints a report.
CUE: This JPM is complete. ________
Page 16 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Page 17 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.3 Subject
Description:
Radiation Protection Question Number: 1 Question:
A valve must be manually stroked repeatedly by operations personnel as part of corrective maintenance. The valve is in a high radiation area. Information pertinent to the work to be performed is as follows:
- Unshielded Dose Rate 350 mrem/hr
- Shielded Dose Rate 150 mrem/hr
- Time to install shielding (1 man) 20 minutes
- Time to complete valve stroking (1 operator) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 20 minutes
- Time to complete valve stroking (2 operators) 35 minutes Considering the guidelines associated with radiological protection:
- 1. Should 1 or 2 operators be assigned to the task?
- 2. Should shielding be installed?
Page 18 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Answer:
(NOTE: Only the bolded portion is required for full credit)
- 1. Two operators Explanation: The total man-hours to perform the work with 1 man is 1.33 man-hours. 2 men is 1.17 man-hours. Man-hours X dose = man-rem, irrespective of dose rate. Two men will receive less cumulative dose than one man performing the task.
- 2. YES Explanation: The dose to install the shielding is 116.7 milli-rem.
The dose savings for the task with shielding is 234 milli-rem when compared to the dose without shielding. (409.5 - 175.5) Total job dose is 117.3 milli-rem.
Technical Reference(s):
9.RADOP.1: 3.7.5 3.14, Temporary Shielding K/A #: Importance:
2.3.1 3.0 2.3.4 3.1 Comments:
Page 19 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Page 20 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Page 21 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.3 Subject
Description:
Radiation Protection Question Number: 2 CLOSED REFERENCE!
Question:
During an emergency, it is necessary to enter a Very High Radiation Area to stop a discharge to prevent large release to the general public. The general area dose rate is 156 Rem/hr and time in the area for one worker to stop the discharge is estimated at 10 minutes.
What emergency exposure control requirements must be met for this individual before entering the area to stop the effluent discharge?
Answer:
Page 22 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Note: Only the BOLDED information is required to answer the question. The other information supports the correct answer and justification for the response.
(156r/hr) x (1 hr/60 min) x (10 min) = 26 Rem exposure to the worker. Exposure above 25 Rem is permitted to save a life or to protect the general public. For emergency exposures above 25 Rem, several requirements must be met.
Be a volunteer.
NOT a declared pregnant worker.
NO previous emergency exposure.
Aware of the hazards associated with the emergency exposure.
Technical Reference(s):
5.7.12; Section 2.6, Attachment 1 K/A #: Importance:
2.3.1 3.0 2.3.10 3.3 Comments:
Page 23 of 218
JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
STUDENT HANDOUT Question:
A valve must be manually stroked repeatedly by operations personnel as part of corrective maintenance. The valve is in a high radiation area. Information pertinent to the work to be performed is as follows:
- Unshielded Dose Rate 350 mrem/hr
- Shielded Dose Rate 150 mrem/hr
- Time to install shielding (1 man) 20 minutes
- Time to complete valve stroking (1 operator) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 20 minutes
- Time to complete valve stroking (2 operators) 35 minutes Considering the guidelines associated with radiological protection:
- 1. Should 1 or 2 operators be assigned to the task?
- 2. Should shielding be installed?
Page 24 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
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ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are perform a log entry into the narrative logs. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to perform a log entry into the TS Tracking System. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. The plant is at 100% power. HPCI has planned maintenance on the auxiliary oil pump planned to begin at 0000. The maintenance is scheduled for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 3. T.S. Tracker and SAP are unavailable Initiating Cues:
You are to assess plant conditions and perform a log entry into the narrative log and provide a printed copy for the SS to review. DO NOT approve the log entry.
Page 25 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
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Page 26 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.3 Subject
Description:
Radiation Protection Question Number: 2 CLOSED REFERENCE!
Question:
During an emergency, it is necessary to enter a Very High Radiation Area to stop a discharge to prevent large release to the general public. The general area dose rate is 156 Rem/hr and time in the area for one worker to stop the discharge is estimated at 10 minutes.
What emergency exposure control requirements must be met for this individual before entering the area to stop the effluent discharge?
Answer:
Page 27 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
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Note: Only the BOLDED information is required to answer the question. The other information supports the correct answer and justification for the response.
(156r/hr) x (1 hr/60 min) x (10 min) = 26 Rem exposure to the worker. Exposure above 25 Rem is permitted to save a life or to protect the general public. For emergency exposures above 25 Rem, several requirements must be met.
Be a volunteer.
NOT a declared pregnant worker.
NO previous emergency exposure.
Aware of the hazards associated with the emergency exposure.
Technical Reference(s):
5.7.12; Section 2.6, Attachment 1 K/A #: Importance:
2.3.1 3.0 2.3.10 3.3 Comments:
Page 28 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.4 Subject
Description:
EAL Classification / Communications Question Number: 2 Question:
Based on the current plant conditions for the scenario you just completed, determine the highest emergency classification.
Answer:
Scenario Classification required Classification Made (circle applicable one)
Site Area Emergency NRC Scenario #1 (based on EAL 3.3.4)
Site Area Emergency NRC Scenario #2 (based on EAL 2.3.3)
Site Area Emergency NRC Scenario #3 (based on EAL 2.3.3)
ALERT NRC Scenario #4 (based on EAL 2.2.1)
Page 29 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
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Technical Reference(s):
5.7.1 K/A #: Importance:
2.4.40 4.0 2.4.41 4.1 Comments:
Page 30 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
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ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Cooper Nuclear Station Date of Examination: ______________
Exam Level (circle one): RO / SROU / SROI B.1 Control Room Systems System / JPM Title Type Safety Code* Function PLANT AT POWER, CORE FLOW <40 LBM/HR, JPMs 1-1 AND 1-2 ARE CONCURRENT.
1-13 Start and Load the Diesel Generator (SKL034-21-42) M, S, A 6 K/A 264000 A4.04 (3.7/3.7)
ALTERNATE PATH: Respond to a DG trouble once loaded, requiring DG shutdown.
1-2 Respond to One RFP in Track and Hold (SKL034-21-43) N, S, A 2 K/A 259001 A4.05 (4.0/3.9)
ALTERNATE PATH: Subsequent malfunction while recovering from Track and Hold requires tripping RFP A.
SRO UPGRADE LOCA CONDITIONS FOLLOWNG A SCRAM. JPMs 1-3 & 1-4 ARE CONCURRENT.
3HUIRUP6%*76\VWHP'HFD\+HDW5HPRYDO 6./ D, S 9 K/A 261000 A4.07 (3.1/3.2)
Last NRC Page 31 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
/2*(175<,1727+(1$55$7,9(/2*66<67(0 65221/<
System / JPM Title Type Safety Code* Function 1-4 Separation of REC Critical Loops (SKL34-21-44) N, S, A 8 K/A 295018 AA1.03 (3.3/3.4), K/A 295018 AK3.07 (3.1/3.2)
ALTERNATE PATH: When first pump is started, it will trip, requiring starting of alternate pump.
NORMAL RPV WATER LEVEL AFTER A SCRAM WITH MSIVS CLOSED. THREE CONTROL RODS [26-27, 30-23, 22-23] FAIL TO INSERT. JPMs 1-5 & 1-6 ARE CONCURRENT.
1-5 Operate HPCI in Pressure Control (Hard Card) (SKL034-21-45) D, S, A 4 K/A 206000 K3.02 (3.8/3.8) and A4.01 (3.8/3.7)
ALTERNATE PATH: HPCI controller will fail in automatic requiring the candidate to take manual control of HPCI.
SRO UPGRADE 1-6 Perform Alternate Control Rod Insertion Using Individual Rod Scram Switches per N, S, L 1 5.8.3, ATT 1 (SKL034-21-41).
K/A 201001 A2.04 (3.8/3.9)
SRO UPGRADE LOCA CONDITIONS. JPM 1-7 WILL BE SIMULATED IN THE CONTROL ROOM. THE SIMULATOR DOES NOT SUPPORT THIS TASK.
1-7 Transfer H2/O2 Monitoring System from Standby to Operation (SKL34-21-01) D, C 5 K/A 223001 A4.04 (3.5/3.6), K/A 223001 A4.05 (3.6/3.6)
B.2 Facility Walk-Through Page 32 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
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System / JPM Title Type Safety Code* Function 1-8 Transfer an MCC to the Alternate Power Supply (SKL034-40-28) D 6 K/A 262001 A1.05 (3.2/3.5)
SRO UPGRADE 1-9 Install and Remove PTMs (PTM #41 AND #42) D 7 K/A 295031 EA1.05 (4.3/4.3)
SRO UPGRADE 1-10 Conduct Alternate Rod Insertion (Vent Scram Air Header) (SKL034-10-65) D, R 2 K/A 295032 EA1.05(3.9/4.0)
Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NOTE: RO and SRO(I) perform all 10 JPMS.
SRO(U) performs JPM 1-2, 1-5, 1-6, 1-8, and 1-9 as indicated.
Page 33 of 218
Nebraska Public Power District NRC ADMIN SRO A.2
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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R 341030O0303 Task
Title:
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Page 34 of 218
Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 35 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
==========================================================
Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
Trainee: Examiner:
Score: Pass Fail Examiner Signature: Date:
ALTERNATE PATH Additional Program Information:
- 1. Appropriate Performance Locations: SIM
- 2. Appropriate Trainee Levels: RO/SRO
- 3. Evaluation Method: Simulate
- 4. Performance Time: 15 minutes
- 5. NRC K/A 264000 A4.04 (3.7/3.7)
Directions to Examiner:
- 1. This JPM evaluates the trainees ability to start and load the diesel generator.
- 2. If this JPM is to be performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Brief the trainee IAW NTP 5.4, On-the-Job-Training and Task Performance Evaluation, (Attachments 1, 2, and 3).
- 4. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.
- 5. All blanks must be filled out with either initials or an "NP" for "not performed, " and an explanation may also be written in the space if desired by the examiner.
- 6. Give the trainee his copy of the Directions to the Trainee (Attachment 2) when ready to start the JPM.
- 7. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Page 35 of 218
Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 36 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
==========================================================
Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
Directions to Trainee:
When I tell you to begin, you are to start and load the diesel generator using the FAST MODE.
Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to start and load the diesel generator.
=========================================================
General Conditions:
- 1. The #1 Diesel Generator is in a Standby lineup and all prerequisites are met for diesel generator operation.
- 2. The Turbine Building Station Operator has performed local preparations for running the
- 1 Diesel Generator and reports that he has completed steps 5.1 through 5.8.6.
General
References:
- 1. Procedure 2.2.20
- 2. Procedure 2.2.20.1 General Tools and Equipment:
None.
Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by "*."
- 3. Simulator cues denoted by "#."
- 4. Alternate Path steps denoted by "."
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Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 37 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
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Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to start and load the #1 diesel generator.
- 2. Accurately locate and identify all instrumentation required to be monitored to start and load the #1 diesel generator.
- 3. Correctly interpret instrument and system responses and their interrelationships when starting and loading the #1 diesel generator.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
You are the BOP operator and the CRS has directed you to start the #1 Diesel Generator and apply a 3200 KW load using SOP 2.2.20.1. Steps 5.1 through 5.8.6 have been completed. You are to inform the CRS when a 3200 KW load has been applied to #1 DG. A SO is available at DG1 Room.
NOTE: Tell the trainee to begin and NOT to make any plant announcements.
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Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 38 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
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Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
Performance Checklist Standards Initials
- 1. Start DIESEL GEN 1. The operator places DG-1 STOP/START switch to START CUE: Stop light turns off
- 2. Adjust Voltage. Using DIESEL GEN 1 VOLTAGE REGULATOR, adjust voltage to ~4200V CUE: Voltage is ~4200 Volts
- 3. Records. Record Date/Time DG1 started on Attachment 3
- CUE: A second operator has recorded the required information.
- 4. Local Checks. Coordinate with the Station Operator and check the following before loading (all items in step 5.13)
- CUE: Items 5.13.1 through 5.13.8 have been satisfactorily completed.
- CUE: Five minutes have elapsed.
- 5. Synch Switch. Place SYNCH SWITCH EG1 OR 1FE TO EG1 CUE: Switch is in EG1
- 6. Adjust DG1 speed so The operator adjusts DG1 speed so SYNCHROSCOPE is SYNCHROSCOPE is rotating slowly in clockwise
- rotating slowly in (fast) direction.
clockwise (fast) direction.
CUE: The SYNCHROSCOPE is rotating slowly in the FAST direction.
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Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 39 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
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Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
Performance Checklist Standards Initials
- 7. Adjust DG-1 VOLTAGE The operator adjusts DG-1 VOLTAGE REGULATOR. REGULATOR switch so DG-1 VOLTS are slightly
- higher than BUS 1F VOLTS.
CUE: Higher VOLTS obtained.
- 8. CLOSE EG1. The operator CLOSES DIESEL GEN 1 BKR, EG1 when SYNCHROSCOPE at 11 oclock.
- CUE: BKR EG1red light is lit and green light is out as SYNCHROSCOPE passed 11 oclock and Synchroscope indicates 12:00.
NOTE: When DG1 load is 900 KW, a trigger will activate the DIESEL GEN 1 TROUBLE alarm after a 1 minute time delay.
- 9. Adjust kW & VARS. The operator raises load to 1000 kW (+/- 50kW) using
- DIESEL GEN 1 GOVERNOR switch and 500 kVAR
(+/- 50 kVAR) using DIESEL GEN 1 VOLTAGE REGULATOR switch.
CUE: The DG load is 1000 kW and 500 kVAR.
NOTE: Critical step at steady state.
NOTE: The following step may not be performed if the Diesel Trouble alarm is received before load is raised.
- 10. Raises load to 3200 kW RO raises load at a rate # 500 (+/- 50) kW averaged over any one minute until 3200 (+/- 100) kW is reached CUE: DG load is XX (500 kW increments, 1-minute wait).
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Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 40 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
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Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
Performance Checklist Standards Initials
- 11. Respond to DIESEL The operator presses either OPERATOR GEN 1 TROUBLE NOTIFICATION button on Panel C.
- alarm.
- CUE: Call as SO at DG1 in response to blue flashing light.
- 12. Direct Station The operator directs the Station Operator to Operator to report report the cause of the DIESEL GEN 1 TROUBLE
- cause of DIESEL GEN alarm.
1 TROUBLE alarm.
- CUE: As the SO, acknowledge request to report DG1 Control Panel alarms.
- 13. Adjust DG1 kW and The operator lowers load to 1000 kW (+/- 50 kW)
KVARs. using DIESEL GEN 1 GOVERNOR switch and
- maintains 500 kVAR (+/- 50 kVAR) using DIESEL GEN 1 VOLTAGE REGULATOR switch.
CUE: The DG load is 1000 kW and 500 kVAR.
CUE: When KW and KVAR at target, inform trainee 15 minutes have elapsed.
NOTE: Critical step at steady state.
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Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 41 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
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Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
Performance Checklist Standards Initials
- 14. Adjust DG1 kW and The operator lowers load to 400 kW (+/- 50 kW) using KVARs. DIESEL GEN 1 GOVERNOR switch and lowers
- kVAR to 0 (+/- 50 kVAR) using DIESEL GEN 1 VOLTAGE REGULATOR switch.
CUE: The DG load is 400 KW and 0 KVAR.
NOTE: Critical step at steady state.
- 15. OPEN EG1. The operator OPENS DIESEL GEN 1 BKR, EG1.
CUE: BKR EG1 green light is lit and red light is out.
- 16. Place DROOP Directs AO to place DROOP PARALLEL switch to PARALLEL switch to ISOCH.
- ISOCH.
CUE: Acknowledge request and report DROOP PARALLEL switch in ISOCH.
- 17. Adjust DG1 speed. The operator lowers DG1 speed to 600 rpm (+/- 50 rpm) using DIESEL GEN 1 GOVERNOR switch.
- CUE: The DG speed is 600 rpm.
NOTE: Critical step at steady state.
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Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 42 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
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Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
Performance Checklist Standards Initials
- 18. Adjust DG1 voltage. The operator adjusts DG1 voltage to 4200 VAC (+/-
50 VAC) using DIESEL GEN 1 VOLTAGE
- REGULATOR switch.
CUE: The DG voltage is 4200 VAC.
NOTE: Critical step at steady state.
- 19. Stop DG1. The operator PLACES and HOLDS DIESEL GEN 1 STOP/START switch to STOP for 1 to 2 seconds (-0
- to +5 seconds).
CUE: STOP light turns on.
- CUE: If asked as CRS, mechanical testing of DG1 is not in progress. Continue with DG1 shutdown.
DG1 is stopped.
- CUE: The CRS acknowledges the report.
This JPM is now complete.
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Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 43 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
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Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in any IC and place in RUN.
Batch File Name - JPM/342142 C. Change the simulator conditions as follows:
- 1. Triggers Number File Name Description E1 None trgset 1 "zaodgwiwm1 .gt. 0.13" DG load >900 KW
- 2. Malfunctions None
- 3. Remotes Number Title Trigger Value Ramp DG03 #1 DG Parallel / Isoch Switch A Parallel N/A
- 4. Overrides Instrument Tag Trigger TD Value Ramp Ann C-1/E-3 RA: MUX01C002 E1 1:00 ON N/A Page 43 of 218
Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 44 of 218 Job Performance Measure for Operations Revision 00 Task No.: 226002O0101; 230002O0101
==========================================================
Task
Title:
START AND LOAD THE DIESEL GENERATOR (Alternate Path)
==========================================================
- 5. Panel Setup Perform steps 5.1 through 5.8.6 (including verifying the Droop Parallel switch in PARALLEL) of 2.2.20.1.
Note: If this JPM is to be performed more than once, snap the simulator into an IC after the panel setup is complete.
Page 44 of 218
Nebraska Public Power District SKL034-21-42 Cooper Nuclear Station Page 45 of 218 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to start and load the diesel generator using the FAST MODE. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to start and load the diesel generator.
General Conditions:
- 1. The #1 Diesel Generator is in a Standby lineup and all prerequisites are met for diesel generator operation.
- 2. The Turbine Building Station Operator has performed local preparations for running the #1 Diesel Generator and reports that he has completed steps 5.1 through 5.8.6.
Initiating Cues:
You are the BOP operator and the CRS has directed you to start the #1 Diesel Generator and apply a 3200 KW load using SOP 2.2.20.1. Steps 5.1 through 5.8.6 have been completed. You are to inform the CRS when a 3200 KW load has been applied to #1 DG. A SO is available at DG1 Room. For the purpose of this examination, do NOT make any plant announcements Page 45 of 218
Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 46 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
=========================================================
Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
Trainee: Examiner:
Pass Fail Examiner Signature: Date:
ALTERNATE PATH Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 2. Appropriate Trainee Levels: RO/SRO
- 3. Evaluation Method: Perform Simulate
- 4. Performance Time: 10 minutes
- 5. NRC K/A 259002A4.09, 3.4/3.1 Directions to Examiner:
- 2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. All blanks must be filled out with either examiners initials or an "NP" for "not performed, "
and an explanation may also be written in the space if desired by the examiner.
- 5. Give the trainee his copy of the Directions to the Trainee (Attachment 2) when the trainee is ready to start the JPM.
- 6. Brief the trainee, place the Simulator in run, and tell the trainee to begin.
Directions to Trainee:
When I tell you to begin, you are to perform the required actions as the Balance-Of-Plant Operator to respond to a RFP in FW Track and Hold. Before you start, I will state the general plant conditions, initiating cues, and answer any questions you may have. During performance, state the actions you are taking, e.g., repositioning control and observing instrumentation.
When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them to respond to a RFP in FW Track and Hold.
========================================================
General Conditions:
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Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 47 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
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Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
- 1. The plant is operating at power, steady-state.
- 2. A failure of feedwater controller RFC-MA-84A has occurred, causing the "A" Reactor Feed Pump to lock up and shift to Track and Hold operation.
- 3. No operator actions have yet been taken in response to this condition.
- 4. I & C has replaced a faulty connector and the controller can be returned to service.
- 5. An SO is at the Lovejoy Monitor.
General
References:
- 1. Procedure 2.4RXLVL, RPV Water Level Control Trouble
- 2. Procedure 2.2.28.1, Feedwater System Operations
- 3. Procedure 2.3_A.1/E-6 General Tools and Equipment:
None Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by "*."
- 2. Simulator cues denoted by "#."
- 3. Faulted steps denoted by "ó."
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to respond to RFP in Track and Hold.
- 2. Accurately locate and identify all instrumentation required to be monitored to respond to RFP in Track and Hold.
- 3. Correctly interpret instrument and system responses and their interrelationships when responding to RFP in Track and Hold.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error and
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) and management expectations for TPE evaluated as satisfactory (SAT) or not applicable (N/A).
Page 47 of 218
Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 48 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
=========================================================
Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
Initiating Cue(s):
The Control Room Supervisor orders you to respond to "A" Reactor Feed Pump in Track and Hold in accordance with the applicable procedure(s).
NOTE: Place the Simulator in RUN and tell the trainee to begin.
Page 48 of 218
Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 49 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
=========================================================
Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
Performance Checklist Standards Initials NOTE: Entry into 2.4RXLVL is made based upon alarm response procedure guidance.
- 4. Enter procedure 2.4RXLVL. Locate and retrieve procedure 2.4RXLVL from the procedure rack.
- 5. Enter Attachment 3 of Recognizes from the Subsequent Actions of 2.4RXLVL procedure 2.4RXLVL. that Attachment 3 must be entered.
- 6. Ensure "B" RFP is controlling Monitors Reactor Water level to determine if "B" RFP RPV level. is maintaining set level.
CUE: RPV water level is steady at 35" on the narrow range.
- 7. Contact Station operator to Contacts Station Operator to determine actual alarm.
determine actual alarm at RFP A Signal Processor Cabinet.
- CUE: As Station Operator LOSS OF FEEDWATER DEMAND SIGNAL is indicated locally.
- 8. Ensure RFC-MA-84A is in MAN. (If not already done) Place RFC-MA-84A function selector knob in MAN.
- CUE: The selector knob for RFC-MA-84A is lined up with MAN.
NOTE: RFC-M84A may have to be adjusted to bring the deviation meter on scale to monitor for proper resonse.
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Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 50 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
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Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
Performance Checklist Standards Initials
- 9. Evaluate whether cause of lockout Determine cause of lockout need not be corrected to must be corrected before moving move on in procedure.
on.
NOTE: Cause has been corrected.
- 10. Slowly adjust RFC-LC-83 and Adjust RFC-LC-83 and observe response on RFC-MA-check RFC-MA-84A deviation 84A deviation meter.
meter responds.
CUE: As output signal from RFC-LC-83 is adjusted and the deviation meter for RFC-MA-84A is observed, the red pointer in the uppermost indicator on 84A is moving.
- CUE: If asked long term operation is not anticipated.
- RESET.
CUE: The lockout device handle has rotated to the RESET position and remains there.
- 12. Adjust RFC-MA-84A until Adjust manual output signal from RFC-MA-FW DEMAND is # 4% higher 84A until FW DEMAND window for RFPT A
CUE: When the correct displays are being monitored, indicate FW DEMAND is at a value # 4% higher than the indicated value for FW HOLD.
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Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 51 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
=========================================================
Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
Performance Checklist Standards Initials NOTE: The following step will reset the Track and Hold annunciator. After the Track and Hold annunciator resets, the Dual Power Supply Failure will occur causing A-1/E-6, RFP TURBINE A CONTROL TROUBLE to alarm.
- condition on RFPT A.
CUE: Button is depressed.
CUE: Amber light above FW HOLD display window is OFF.
TURBINE A TRACK & HOLD, clear. Reset alarm.
HOLD, clear.
CUE: A-1/F-6 is clear.
NOTE: The following step should be NOT applicable as the other RFP is maintaining reactor water level and no adjustment to the Startup Demand is required. The following 2 steps may not be performed due to the RFP Trouble annunciator.
- 16. Raise STARTUP DEMAND Raise STARTUP DEMAND to maximum with to maximum with MANUAL MANUAL STARTUP SPEED CONTROL.
STARTUP SPEED CONTROL.
CUE: STARTUP DEMAND has been raised to maximum and the indication is no longer changing.
Page 51 of 218
Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 52 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
=========================================================
Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
Performance Checklist Standards Initials
- 17. Ensure the RFP is Monitor RPV water level. Ensure that B controlling RPV water level. RFP has control of it.
CUE: RPV water level is under the control of the B RFP.
ó18. Respond to A-1/E-1 Reference the alarm response procedure for alarm. A-1/E-1 and direct a Station Operator to report cause of alarm.
CUE: A-1/E-6, RFP TURBINE A CONTROL TROUBLE, alarms.
- CUE: As the S.O. report the DUAL POWER SUPPLY FAILURE AT CONTROLLER is alarming at the Signal Processor Cabinet.
ó19. Enter Attachment 6 References Attachment 6 of 2.4RXLVL.
of 2.4RXLVL.
ó20. Ensure core flow is Checks core flow below 40X106 lb/hr.
below 40X106 lb/hr.
CUE: Core flow is 39X106 lb/hr.
ó21. Trip RFP "A." Press RFP "A" TRIP push button and observe RFP "A" tripped.
- CUE: RFP "A" TRIP push button is pressed.
CUE: RFP "A" is tripped.
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Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 53 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
=========================================================
Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
Performance Checklist Standards Initials
- 22. Inform CRS of status. Informs CRS that the "A" RFP has been tripped because of the loss of power. The "B" RFP is controlling RPV level.
CUE: Respond to the report as CRS.
This JPM is complete.
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Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 54 of 218 Job Performance Measure for Operations Revision 00 Task No.: 259043P0401
=========================================================
Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in any power IC with both Reactor Feed pumps in service.
Batch File Name - none.
C. Change the Simulator conditions as follows:
- 1. Triggers Number File Name Description E2 None trgset 2 "zdirfcma84a(2) == 1 .and. ra:mux15c061 ==
0" Trigger will go active when Track and Hold annunciator is reset and 84A is in MANUAL.
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial FW05A A Reactor Feedwater E1 0 0 0 As Is Pump Individual Controller Failure FW23A RFP Lovejoy Controller E2 10 10 5:00 17.5 Failure RFP 1A Page 54 of 218
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=========================================================
Task
Title:
RESPOND TO ONE RFP IN FW TRACK AND HOLD (Alternate Path)
=========================================================
- 3. Remotes None
- 4. Overrides Instrument Tag Trigger TD Value Ramp A-1/E-6 RFP TURBINE A RA: MUX15C060 E2 10 ON N/A CONTROL TROUBLE
- 5. Panel Setup
- a. Place the Simulator in RUN.
- b. Load Bat file JPM/342143
- c. Activate Trigger E1.
- d. Acknowledge annunciators.
- e. DELETE malfunction FW05A, A Reactor Feedwater Pump Individual Controller Failure.
- f. Lower Recirculation Pump speed to 35%.
- g. FREEZE the Simulator.
Note: If this JPM is to be performed more than once, take a SNAPSHOT or store in a spare IC after the panel setup is complete.
Page 55 of 218
Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 56 of 218 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to perform the required actions as the Balance-Of-Plant Operator to respond to a RFP in FW Track and Hold. Before you start, I will state the general plant conditions, initiating cues, and answer any questions you may have.
During performance, state the actions you are taking, e.g., repositioning control and observing instrumentation.
When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them to respond to a RFP in FW Track and Hold.
General Conditions:
- 1. The plant is operating at power, steady-state.
- 2. A failure of feedwater controller RFC-MA-84A has occurred, causing the "A" Reactor Feed Pump to lock up and shift to Track and Hold operation.
- 3. No operator actions have yet been taken in response to this condition.
- 4. I & C has replaced a faulty connector and the controller can be returned to service.
- 5. An SO is at the Lovejoy Monitor.
Initiating Cue(s):
The Control Room Supervisor orders you to respond to "A" Reactor Feed Pump in Track and Hold in accordance with the applicable procedure(s).
Page 56 of 218
Nebraska Public Power District SKL034-21-43 Cooper Nuclear Station Page 57 of 218 Job Performance Measure for Operations Revision 00 Page 57 of 218
Nebraska Public Power District SKL034-20-70 Cooper Nuclear Station Page 58 of 218 Job Performance Measure Revision 09 Task No.: 261009P0101
=========================================================
Task
Title:
PERFORM STANDBY GAS TREATMENT SYSTEM DECAY HEAT REMOVAL
=========================================================
Trainee: Examiner:
Pass: Fail: Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 15 minutes
- 5. NRC K/A 261000 A4.07 (3.1/3.2) A3.04 (3.0/3.1)
Directions to Examiner:
- 4. This JPM evaluates the trainees ability to perform Standby Gas Treatment system decay heat removal.
- 5. The examiner is to obtain the AJPM Comment Form@ (Attachment C of ODG 206) prior to administering the JPM.
- 6. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.
- 7. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 8. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 9. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space if desired by the examiner.
- 10. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Page 58 of 218
Nebraska Public Power District SKL034-20-70 Cooper Nuclear Station Page 59 of 218 Job Performance Measure Revision 09 Task No.: 261009P0101
=========================================================
Task
Title:
PERFORM STANDBY GAS TREATMENT SYSTEM DECAY HEAT REMOVAL
=========================================================
Directions to Trainee:
When I tell you to begin, you are to perform Standby Gas Treatment system decay heat removal. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to perform Standby Gas Treatment system decay heat removal. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
=========================================================
General Conditions:
- 1. The plant is in the post LOCA mode of operation.
- 3. A Group 6 isolation signal is present.
General
References:
- 1. Procedure 2.2.73 General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 11. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by "*".
- 3. Simulator cues denoted by "#".
Page 59 of 218
Nebraska Public Power District SKL034-20-70 Cooper Nuclear Station Page 60 of 218 Job Performance Measure Revision 09 Task No.: 261009P0101
=========================================================
Task
Title:
PERFORM STANDBY GAS TREATMENT SYSTEM DECAY HEAT REMOVAL
=========================================================
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to perform Standby Gas Treatment system decay heat removal.
- 2. Accurately locate and identify all instrumentation required to be monitored to perform Standby Gas Treatment system decay heat removal.
- 3. Correctly interpret instrument and system responses and their interrelationships when performing Standby Gas Treatment system decay heat removal.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
The CRS has directed you to perform SGT subsystem A Decay Heat Removal per procedure 2.2.73. Inform the CRS when SGT subsystem A Decay Heat Removal is in progress.
NOTE: Place the Simulator in RUN and tell the trainee to begin.
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Nebraska Public Power District SKL034-20-70 Cooper Nuclear Station Page 61 of 218 Job Performance Measure Revision 09 Task No.: 261009P0101
=========================================================
Task
Title:
PERFORM STANDBY GAS TREATMENT SYSTEM DECAY HEAT REMOVAL
=========================================================
Performance Checklist Standards Initials
CUE: RED light ON. GREEN light OFF.
Starts ________
CUE: RED light ON. GREEN light OFF.
- 3. Verify OPEN SGT-AO-250 Check SGT-AO-250, SGT B INLET Opens.
CUE: RED light ON. GREEN light OFF.
- 4. Verify OPEN SGT-AO-252 Check SGT-AO-252, SGT B DISCHARGE Opens.
CUE: RED light ON. GREEN light OFF.
CUE: GREEN light ON. RED light OFF.
STOPS. _________
CUE: GREEN light ON. RED light OFF.
- 7. Verify CLOSED SGT-AO-249 Check SGT-AO-249, SGT A INLET Closes.
Page 61 of 218
Nebraska Public Power District SKL034-20-70 Cooper Nuclear Station Page 62 of 218 Job Performance Measure Revision 09 Task No.: 261009P0101
=========================================================
Task
Title:
PERFORM STANDBY GAS TREATMENT SYSTEM DECAY HEAT REMOVAL
=========================================================
Performance Checklist Standards Initials CUE: GREEN light ON. RED light OFF.
- 8. Verify CLOSED SGT-AO-251 Check SGT-AO-251, SGT A DISCHARGE Closes.
CUE: GREEN light ON. RED light OFF.
- 9. OPEN SGT-AO-270 Place to AUTO control switch for SGT-AO-270, SGT A DILUTION AIR. ________*
CUE: GREEN light OFF. RED light ON.
- 10. Verify reactor building Check £ -0.25" WG on HV-DPR-835, RX differential pressure BLDG/ATMOS DP (VBD-R). _________
CUE: Rx Bldg HV-DPR-835 indicates -0.35" WG.
CUE: Carbon Outlet Temperature is 210 F.
- 12. Inform the CRS that the task Inform the Control Room Supervisor that SGT is Complete. train A Decay Heat Removal is in progress. _________
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Nebraska Public Power District SKL034-20-70 Cooper Nuclear Station Page 63 of 218 Job Performance Measure Revision 09 Task No.: 261009P0101
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Task
Title:
PERFORM STANDBY GAS TREATMENT SYSTEM DECAY HEAT REMOVAL
=========================================================
ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator and load batch file.
Batch File Name - JPM 342070 C. Change the simulator conditions as follows:
- 1. Triggers None
- 2. Malfunctions None
- 3. Remotes None Page 63 of 218
Nebraska Public Power District SKL034-20-70 Cooper Nuclear Station Page 64 of 218 Job Performance Measure Revision 09 Task No.: 261009P0101
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Task
Title:
PERFORM STANDBY GAS TREATMENT SYSTEM DECAY HEAT REMOVAL
=========================================================
ATTACHMENT 1 (continued)
- 4. Overrides Instrument Tag Trigger TD Value Ramp 18A2M06 SGT TI 537A ZAOSGTTI537A A 0 253 N/A 18A2M08 SGT TI 547 ZAOSGTTI547 A 0 254 N/A K-1 A-01 Ann K-1 A-1 RA:MUX13C017 E2 10 ON N/A
- 5. Panel Setup
- a. Perform procedure 2.2.73, section for RESPONSE TO AUTOMATIC INITIATION.
- b. Place the Simulator in FREEZE.
Note: If this JPM is to be performed more than once, snap the simulator into an IC after the panel setup is complete.
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Nebraska Public Power District SKL034-20-70 Cooper Nuclear Station Page 65 of 218 Job Performance Measure Revision 09 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to perform Standby Gas Treatment system decay heat removal. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to perform Standby Gas Treatment system decay heat removal. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. The plant is in the post LOCA mode of operation.
- 3. A Group 6 isolation signal is present.
Initiating Cues:
The CRS has directed you to perform SGT subsystem A Decay Heat Removal per procedure 2.2.73. Inform the CRS when SGT subsystem A Decay Heat Removal is in progress.
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Nebraska Public Power District SKL034-21-41 Cooper Nuclear Station Page 66 of 218 Job Performance Measure for Operations Revision 00 Task No.: 200076I0502
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
Trainee: Examiner:
Score: Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 2. Appropriate Trainee Levels: RO/SRO
- 3. Evaluation Method: _____ Perform _____ Simulate
- 4. Performance Time: 15 minutes
- 5. NRC K/A 201001 A2.04 (3.8/3.9)
Directions to Examiner:
- 1. This JPM evaluates the trainees ability to insert control rods during a failure to scram condition using the individual rod scram switches.
- 2. If this JPM is to be performed on the Simulator, only the cues preceded by "#" should be given.
- 3. Brief the trainee IAW NTP 5.4, On-the-Job-Training and Task Performance Evaluation, (Attachments 1, 2, and 3).
- 4. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.
- 5. All blanks must be filled out with either initials or an "NP" for "not performed, " and an explanation may also be written in the space if desired by the examiner.
- 6. Give the trainee his copy of the Directions to the Trainee (Attachment 2) when ready to start the JPM.
- 7. Brief the trainee, place the simulator in run, and tell the trainee to begin.
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
Directions to Trainee:
When I tell you to begin, you are to insert control rods 26-27, 30-23, and 22-23 using the individual rod scram switches. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to individually scram the control rods.
==========================================================
General Conditions:
- 1. The plant scrammed and 3 control rods (control rods 26-27, 30-23, and 22-23) failed to insert.
- 3. The last step performed was 5.8.3, Attachment 1, AR-16.
- 4. PTMs 31, 32, 33, 34, 61, and 62 have been installed.
General
References:
- 13. Procedure 5.8.3, Section 4
- 14. Procedure 5.8.3, Attachment 1 (Path D)
General Tools and Equipment:
None.
Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by "*."
- 3. Simulator cues denoted by "#."
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to insert control rods using the individual rod scram switches.
- 2. Accurately locate and identify all instrumentation required to be monitored to insert control rods using the individual rod scram switches.
- 3. Correctly interpret instrument and system responses and their interrelationships when inserting control rods using the individual rod scram switches.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
You are the RO and the CRS has directed you to insert control rods 26-27, 30-23, and 22-23 using the individual rod scram switches per 5.8.3 Attachment 1 path D and Section 4. You are to inform the CRS when all control rods are fully inserted.
NOTE: Tell the trainee to begin.
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
Performance Checklist Standards Initials
CUE: Switch is positioned to ISOL.
NOTE: This step will be Not Applicable as it would have been performed previously by the operators performing previous 5.8.3 steps.
CUE: Switch is positioned to BYPASS.
- 17. Reset scram. The operator places REACTOR SCRAM RESET switch to Group 1 and 4, Group 2 and 3, then back to
- NORM and CHECKS SCRAM INDICATIONS GROUP A and GROUP B lights are ON.
CUE: Switch placed to Group 1 and 4 and Group 2 and 3.
CUE: SCRAM INDICATIONS GROUP A and GROUP B lights are on.
- 18. Wait for all scram valves to close. The operator checks all scram valves on full core display are CLOSED.
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
Performance Checklist Standards Initials
- CUE: Switch is positioned to NORM.
CUE: SDV VENT AND DRAIN VALVES are Red lights are on and Green lights are off.
- CUE: SDV HIGH LEVEL alarm is clear.
CUE: Switch is positioned to ISOL.
NOTE: The following step is only applicable and critical if the CRD-29 had been closed previously.
- CUE: As the SO, report CRD-29 is open.
CUE: All accumulator trouble lights are out.
NOTE: The order that control rods 26-27, 30-23, and 22-23 are inserted is NOT critical. The critical element is the control rods are fully inserted. If the order in section 4 is NOT followed, this is a competency concern related to procedure compliance.
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
Performance Checklist Standards Initials
- 23. Individually scram control rod 26- The operator places ROD SCRAM SWITCH for
- 27. control rod 26-27 to SCRAM for 10 seconds then
- returns switch to NORMAL AND observe control rod inserted.
CUE: ROD SCRAM SWITCH for selected control rod is positioned to SCRAM/NORMAL as actions are taken.
CUE: Selected control rod is inserted.
- 24. Individually scram control rod 30- The operator places ROD SCRAM SWITCH for
- 23. control rod 30-23 to SCRAM for 10 seconds then
- returns switch to NORMAL AND observe control rod inserted.
CUE: ROD SCRAM SWITCH for selected control rod is positioned to SCRAM/NORMAL as actions are taken.
CUE: Selected control rod is inserted.
- 25. Individually scram control rod 22- The operator places ROD SCRAM SWITCH for
- 23. control rod 22-23 to SCRAM for 10 seconds then
- returns switch to NORMAL AND observe control rod inserted.
CUE: ROD SCRAM SWITCH for selected control rod is positioned to SCRAM/NORMAL as actions are taken.
CUE: Selected control rod is inserted.
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
Performance Checklist Standards Initials
- 26. Inform the CRS that all control rods The operator informs the CRS all control rods are fully are fully inserted. inserted.
ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in any power IC and place in RUN.
Batch File Name - JPM/342141 C. Change the simulator conditions as follows:
- 1. Triggers Number File Name Description E2 None trgset 2 "zdirpssws7s19 == 0" (Set up trigger 2 to activate when 26-27 scram test in test) trg 2 "dmf rd122627" (Set up trigger 2 to delete a malfunction)
E4 None trgset 4 "zdirpssws8s20 == 0" (Set up trigger 4 to activate when 30-23 scram test in test) trg 4 "dmf rd123023" (Set up trigger 4 to delete a malfunction)
E6 None trgset 6 "zdirpssws7s21 == 0" (Set up trigger 6 to activate when 22-23 scram test in test) trg 6 "dmf rd122223" (Set up trigger 6 to delete a malfunction)
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
Page 73 of 218
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial RD122627 Stuck Control Rod 26-27 A 0 N/A N/A N/A RD123023 Stuck Control Rod 30-23 A 0 N/A N/A N/A RD122223 Stuck Control Rod 22-23 A 0 N/A N/A N/A
- 3. Remotes Number Title Trigger Value Ramp RD18 EOP PTMs #61 & #62 A REMOVE N/A
- 4. Overrides Instrument Tag Trigger TD Value Ramp A1" Channel 5.8.3 jumpers ZDIRPSSCRMJA1 A 0 IN N/A A2" Channel 5.8.3 jumpers ZDIRPSSCRMJA2 A 0 IN N/A B1" Channel 5.8.3 jumpers ZDIRPSSCRMJB1 A 0 IN N/A B2" Channel 5.8.3 jumpers ZDIRPSSCRMJB2 A 0 IN N/A Page 74 of 218
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
- 5. Panel Setup
- a. Run batch file.
- b. Manually scram the reactor.
- c. Perform initial scram actions and stabilize the plant.
- d. Ensure Reactor Mode Switch is in Shutdown.
- e. Place a key in the SDV high level trip bypass and place in override.
- f. Reset annunciators.
- g. Place simulator in freeze.
Note: If this JPM is to be performed more than once, snap the simulator into an IC after the panel setup is complete.
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Task
Title:
ALTERNATE CONTROL ROD INSERTION - INDIVIDUAL ROD SCRAM SWITCHES
==========================================================
BATCH FILE IOR ZDIRPSSCRMJA1 IN IOR ZDIRPSSCRMJA2 IN IOR ZDIRPSSCRMJB1 IN IOR ZDIRPSSCRMJB2 IN imf rd122627 imf rd123023 imf rd122223 irf rd18 remove trgset 2 "zdirpssws7s19 == 0"
^set up trigger 2 to activate when 26-27 scram test in test trgset 4 "zdirpssws8s20 == 0"
^set up trigger 4 to activate when 30-23 scram test in test trgset 6 "zdirpssws7s21 == 0"
^set up trigger 6 to activate when 22-23 scram test in test trg 2 "dmf rd122627" trg 4 "dmf rd123023" trg 6 "dmf rd122223" Page 76 of 218
Nebraska Public Power District SKL034-21-41 Cooper Nuclear Station Page 77 of 218 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to insert control rods 26-27, 30-23, and 22-23 using the individual rod scram switches. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to start and load the diesel generator.
General Conditions:
- 1. The plant scrammed and 3 control rods (control rods 26-27, 30-23, and 22-23) failed to insert.
- 3. The last step performed was 5.8.3, Attachment 1, AR-16.
- 4. PTMs 31, 32, 33, 34, 61, and 62 have been installed.
Initiating Cues:
You are the RO and the CRS has directed you to insert control rods 26-27, 30-23, and 22-23 using the individual rod scram switches per 5.8.3 Attachment 1 path D and Section 4. You are to inform the CRS when all control rods are fully inserted.
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Nebraska Public Power District SKL034-21-45 Cooper Nuclear Station Page 78 of 218 Job Performance Measure for Operations Revision: 00 Task No.: 206029P0201
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Task
Title:
OPERATE HPCI IN PRESSURE CONTROL (Hard Card) (Alternate Path)
==========================================================
Trainee: Examiner:
Pass: Fail: Examiner Signature: Date:
ALTERNATE PATH Additional Program Information:
- 1. Appropriate Performance Locations: CR / SIM
- 3. Evaluation Method: Perform Simulate
- 4. Performance Time: 8 minutes
- 5. NRC K/As 206000 K3.02 (3.8/3.8) and A4.01 (3.8/3.7)
Directions to Examiner:
NOTE: THIS IS A ALTERNATE PATH JPM. THE FLOW CONTROLLER WILL FAIL TO OPERATE IN AUTOMATIC AND MUST BE PLACED IN MANUAL.
- 27. This JPM evaluates the trainees ability to perform the pressure control mode of operation of HPCI per the guidance of procedure 2.2.33.1, High Pressure Coolant Injection System Operations.
- 28. The examiner is to obtain the JPM Comment Form (Attachment C of ODG 206) prior to administering the JPM.
- 29. If this JPM is performed on the Simulator, only the cues preceded by # should be given.
- 30. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.
- 31. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 32. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.
- 33. Brief the trainee, place the Simulator in RUN, and tell the trainee to begin.
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Task
Title:
OPERATE HPCI IN PRESSURE CONTROL (Hard Card) (Alternate Path)
==========================================================
Directions to Trainee:
When I tell you to begin, you are to operate HPCI in the pressure control mode using the hard card. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to place HPCI in the pressure control mode. During performance, state the actions you are taking (e.g.: repositioning controls and observing instrumentation).
==========================================================
General Conditions:
- 1. The Reactor is shutdown following a scram.
- 2. The MSIVs have closed on a PCIS Group 1 signal, caused by improper operation of the Reactor Mode Switch following the scram.
- 3. Reactor water level is being controlled by another operator.
- 4. Reactor pressure is currently being maintained by Low-Low Set.
- 5. Suppression Pool Cooling will be placed in service by the another licensed operator.
General
References:
- 1. Procedure 2.2.33.1, High Pressure Coolant Injection System Operation.
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Task
Title:
OPERATE HPCI IN PRESSURE CONTROL (Hard Card) (Alternate Path)
==========================================================
General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical steps denoted by *.
- 3. Simulator cues denoted by #.
- 4. Faulted steps denoted by "°.
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized in order to place HPCI in the pressure control mode per 2.2.33.1.
- 2. Accurately locate and identify all instrumentation required to be monitored in order to place HPCI in the pressure control mode per 2.2.33.1.
- 3. Correctly interpret instrument and system responses and their interrelationships while placing HPCI in the pressure control mode per 2.2.33.1.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
The Control Room Supervisor directs you to place HPCI in the pressure control mode using the hard card and maintain Reactor pressure from 800 to 1000 psig. Inform the CRS when HPCI is operating in the pressure control mode.
NOTE: Place the Simulator in RUN and tell the trainee to begin.
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Task
Title:
OPERATE HPCI IN PRESSURE CONTROL (Hard Card) (Alternate Path)
==========================================================
Performance Checklist Standards Initials
- 1. Place GLAND SEAL CNDSR The operator places the control switch for the GLAND BLOWER control switch in SEAL CNDSR BLOWER in START.
START.
CUE: The red light for the GLAND SEAL CNDSR BLOWER is lit, the green light is out.
- 2. Open HPCI-MO-21, TEST The operator places the control switch for the HPCI-BYPASS TO ECST. MO-21 in OPEN.
- CUE: HPCI-MO-21 red light is on, green light is off.
- 3. Open HPCI-MO-24, ECST TEST The operator places the control switch for the HPCI-
- LINE SHUTOFF VLV. MO-24 in OPEN.
CUE: HPCI-MO-24 red light is on, green light is off.
- 4. Open HPCI-MO-14, STM TO The operator places the control switch for the HPCI-
- TURB VLV. MO-14 in OPEN.
CUE: HPCI-MO-14 red light is on, green light is off.
- 5. Start AUXILIARY OIL PUMP by The operator places the control switch for the Auxiliary
- placing control switch in START. Oil Pump switch to START.
CUE: HPCI Aux Oil pump red light is on, green light is off.
° 6. Adjust FLOW CONTROLLER Operator attempts to control HPCI flow with the Set HPCI-FIC-108 setpoint to maintain Tape.
desired RPV pressure, as necessary.
CUE: HPCI flow remains almost zero, irrespective of Set Tape setting.
° 7. Operator recognizes and reports Operator reports to CRS that HPCI controller has failed failed controller in automatic.
CUE: CRS acknowledges, directs operator to control HPCI with controller in manual.
° 8. Operator places HPCI controller in Operator turns HPCI controller AUTO/BAL/MAN
- manual. switch to MAN.
CUE: HPCI controller AUTO/BAL/MAN switch is in MAN.
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Task
Title:
OPERATE HPCI IN PRESSURE CONTROL (Hard Card) (Alternate Path)
==========================================================
Performance Checklist Standards Initials
° 9. Operator adjusts HPCI controller Operator turns HPCI controller manual knob clockwise
- in manual to control flow and to raise flow, counter-clockwise to lower flow.
cooldown rate.
CUE: HPCI flow responds to manual control knob adjustment as appropriate.
- 10. Ensure REC-MO-711 or REC-MO- Operator verifies that REC-MO-711 or REC-MO-714 is 714 is open. open.
CUE: Both REC-MO-711 and REC-MO-714 are open.
CUE: Both trains of SGT have automatically started and are operating normally.
- 12. Operator reports HPCI is in Operator reports to the CRS that HPCI is in pressure pressure control mode. control mode per the hard card.
CUE: The CRS acknowledges the report. The JPM is complete.
Page 82 of 218
Nebraska Public Power District SKL034-21-45 Cooper Nuclear Station Page 83 of 218 Job Performance Measure for Operations Revision: 00 ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None C Initialize the Simulator in any IC that will support HPCI pressure control mode after a scram (IC-18, 19 or 20 suggested)
Batch File name - none.
C. Change the Simulator conditions from those of the IC as follows:
- 1. Triggers None
- 2. Malfunctions None
- 3. Remotes None
- 4. Overrides Instrument Tag Trigger TD Value Ramp HPCI Set Tape ZAIHPCIFC108[2] A 0 200 0 Page 83 of 218
Nebraska Public Power District SKL034-21-45 Cooper Nuclear Station Page 84 of 218 Job Performance Measure for Operations Revision: 00
- 5. Panel Set-up (suggested. Any setup is allowed that supports performance of the HPCI pressure control mode)
- a. Place the Simulator in RUN.
- b. Manually scram the Reactor using 9-5 pushbuttons. Leave the Reactor Mode Switch in RUN until low Reactor pressure Group 1 isolation is received, then place RMS in SHUTDOWN.
- e. Place MSIV control switches in CLOSE.
- f. Maintain RPV water level below +20" on the Narrow Range and above -20" on the Wide Range.
- g. Let the simulator run until the first SRV opens.
- h. Reset all high level trip signals (if present).
- i. Insert listed override.
- j. Place the Simulator in FREEZE.
Note: If this JPM is to be performed more than once, snap the Simulator into an IC after the panel set-up is complete.
Page 84 of 218
Nebraska Public Power District SKL034-21-45 Cooper Nuclear Station Page 85 of 218 Job Performance Measure for Operations Revision: 00 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to operate HPCI in the pressure control mode using the hard card. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to place HPCI in the pressure control mode per the hard card. During actual performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. The Reactor is shutdown following a scram.
- 2. The MSIVs have closed on a PCIS Group 1 signal, caused by improper operation of the Reactor Mode Switch following the scram.
- 3. Reactor water level is being controlled by another operator.
- 4. Reactor pressure is currently being maintained by Low-Low Set.
- 5. Suppression Pool Cooling will be placed in service by the another licensed operator.
Initiating Cue(s):
The Control Room Supervisor directs you to place HPCI in the pressure control mode using the hard card and maintain Reactor pressure from 800 to 1000 psig. Inform the CRS when HPCI is operating in the pressure control mode.
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Nebraska Public Power District SKL034-21-44 Cooper Nuclear Station Page 87 of 218 Job Performance Measure for Operations Revision 00 Task No.:208028P0101
========================================================
Task
Title:
Separation of REC Critical Loops (Alternate Path)
========================================================
Trainee: Examiner:
Pass: Fail: Examiner Signature: Date:
ALTERNATE PATH Additional Program Information:
- 1. Appropriate Performance Locations: CR/SIM
- 2. Appropriate Trainee level: RO/SRO
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 5 minutes
- 5. NRC K/A 295018; AA1.03 (3.3/3.4), AK3.07 (3.1/3.2)
Directions to Examiner:
- 7. The examiner is to obtain the JPM Comment Form (Attachment C of ODG 206) prior to administering the JPM.
- 9. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.
- 11. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 13. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.
- 15. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space if desired by the examiner.
- 17. Brief the trainee, place the simulator in run, and tell the trainee to begin.
Directions to Trainee:
When I tell you to begin, you are to separate the REC Critical Loops. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated to separate the REC Critical Loops. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
========================================================
General Conditions:
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========================================================
Task
Title:
Separation of REC Critical Loops (Alternate Path)
========================================================
- 2. Several alarms associated with the REC system have been recieved in the Control Room.
- 2. Emergency Procedure 5.2REC, Loss of REC, has been entered and actions taken up to separating the REC Critical Loops.
General
References:
- 1. Procedure 5.2REC
- 2. Procedure 2.2.65.1 General Tools and Equipment:
- 1. None Special Conditions, References, Tools, Equipment:
- 1. Simulator Setup: See Attachment 1.
- 2. Critical checks denoted by "*".
- 3. Simulator cues denoted by "#".
- 4. Faulted steps denoted by "°.
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to separate the REC Critical Loops.
- 2. Accurately locate and identify all instrumentation required to be monitored to separate the REC Critical Loops.
- 3. Correctly interpret instrument and system responses and their interrelationships when separating the REC Critical Loops.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
The Control Room Supervisor directs you to separate the REC Criticial Loops per 2.2.65.1, using the NORTH Critical Loop. Inform the CRS when you have separated the REC Critical Loops.
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Task
Title:
Separation of REC Critical Loops (Alternate Path)
========================================================
NOTE: Place the Simulator in RUN and tell the trainee to begin. (Delete malfunction SW12b).
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Task
Title:
Separation of REC Critical Loops (Alternate Path)
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Performance Checklist Standards Initials
- 1. Close REC-MO-695. Close REC-MO-695, CRITICAL LOOP SUPPLY CROSSTIE _________*
CUE: GREEN light ON, RED light OFF.
- 2. Close REC-MO-694. Close REC-MO-694, CRITICAL LOOP SUPPLY CROSSTIE _________*
CUE: GREEN light ON, RED light OFF.
- 3. Close REC-MO-721. Close REC-MO-721, NON CRITICAL HEADER RETURN CUE: GREEN light ON, RED light OFF.
- 4. Close REC-MO-722. Close REC-MO-722, NON CRITICAL HEADER RETURN CUE: GREEN light ON, RED light OFF.
- 5. Ensure REC-19 is open. Directs the S.O. to ensure REC-19 is open. REC HX B INLET (R-931-N REC Hx area) _________
- CUE: As the S.O., report REC-19 is open.
- 6. Ensure REC-21 is open. Directs the S.O. to ensure REC-21 is open. REC HX A INLET (R-931-N REC Hx area) _________
- CUE: As the S.O., report REC-21 is open.
- CUE: As the S.O., report REC-18 is closed.
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Task
Title:
Separation of REC Critical Loops (Alternate Path)
========================================================
Performance Checklist Standards Initials
- CUE: As the S.O., report REC-20 is closed.
- 9. Ensure REC-TCV-451A Ensure REC-TCV-451A, REC HX A SW OUTLET switch is in open. TEMPERATURE CONTROL, switch is in OPEN. _________
CUE: Switch is in OPEN.
- 10. Throttle open SW-MO-650 Throttle open SW-MO-650 to obtain 400 to 1200 gpm flow on SW-FI-387A, REC HX A SW OUTLET. _________
CUE: SW-FI-387A indicates 600 gpm.
closed _________
CUE: GREEN light On, RED light Off.
- 12. Ensure REC-MO-711 is open Ensure REC-MO-711, NORTH CRITICAL LOOP SUPPLY is open _________
CUE: GREEN light OFF, RED light ON.
CUE: If asked as the Station Operator report that no visible leaks exist on the system.
NOTE: Student may make decision regarding REC Surge Tank availability by status of annunciator M1/A3, REC SURGE TANK LOW Level.
- 13. Open REC-MO-722 If REC Surge Tank is available, open REC-MO-722 CUE: IF student chooses to open REC-MO-722, the red _________
light is lit and green light is out.
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Task
Title:
Separation of REC Critical Loops (Alternate Path)
========================================================
Performance Checklist Standards Initials
° 14. Ensure REC PUMP C or STARTS REC PUMP C or D.
D is running _________
CUE: REC PUMP C (D) red light is out and green light is lit. Annunciator M-1/B-3 REC PUMP C FAILURE (M-1/B-4 REC PUMP D FAILURE) is alarming
° 15. Recognize and respond Respond per annunciator M-1/B-3 REC PUMP C FAILURE to REC pump trip. (M-1/B-4 REC PUMP D FAILURE) and determine direction _________
is to start another REC pump.
CUE: If asked as CRS, direct the operator to start C (D)
REC pump (the pump that did not trip).
° 16. Start REC PUMP C or STARTS REC PUMP C or D.
D. _________*
CUE: REC PUMP C (D) red light is lit and green light is out and the JPM is complete.
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Task
Title:
Separation of REC Critical Loops (Alternate Path)
========================================================
ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in any power IC.
DO NOT LOAD BATCH FILE UNTIL DIRECTED BY SETUP!!
Batch File Name - JPM/342144 C. Change the simulator conditions as follows:
- 1. Triggers Number File Name Description E2 None Default to false E18 None trgset 18 "zdirecswrecpc[4]==1" (C REC in start)
E20 None trgset 20 "zdirecswrecpc[4]==1" (C REC in start) trg 20 "dmf sw11d" E22 None trgset 22 "zdirecswrecpd[4]==1" (D REC in start)
E24 None trgset 24 "zdirecswrecpd[4]==1" (D REC in start) trg 24 "dmf sw11c"
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial Page 93 of 218
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Task
Title:
Separation of REC Critical Loops (Alternate Path)
========================================================
SW12b REC HX 1B Tube Leak 2 N/A 60% N/A N/A SW11C C REC pump trip 18 2 N/A N/A N/A SW11D D REC pump trip 22 2 N/A N/A N/A
- 3. Remotes Number Title Trigger Value Ramp SW02 REC HX1B Inlet Isol Vlv (REC-V- 2 CLOSE N/A 18)
SW04 REC HX1A Inlet Isol Vlv (REC-V- 2 CLOSE N/A 20)
RR03 RRMG A DC Oil Pump A STOP N/A RR04 RRMG B DC Oil Pump A STOP N/A
- 4. Overrides None Page 94 of 218
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Task
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Separation of REC Critical Loops (Alternate Path)
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- 5. Panel Setup
- 1. Place the Simulator in RUN.
- b. Insert batch file (JPM/342144).
- c. Activate Trigger 2.
- d. Run the simulator long enough for the surge tank level to drop.
- e. Perform actions of EP 5.2REC up to the point of splitting the REC Critical Loops (all REC pumps off). These actions include scramming the reactor, tripping the RR pumps, Stopping the RRMG oil pumps, and stopping the running CRD pump.
- f. The batch file will make the first REC pump that is started trip and automatically delete the trip malfunction from the second pump, allowing the second pump to be started. No instructor actions are required for the alternate path after the batch file has been run.
- g. FREEZE the simulator.
- h. When JPM begins and simulator is taken to RUN, DELETE the malfunction SW12b.
Note: If this JPM is to be performed more than once, snap the simulator into an IC after the panel setup is complete.
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Nebraska Public Power District SKL034-21-44 Cooper Nuclear Station Page 96 of 218 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 Directions to Trainee:
When I tell you to begin, you are to separate the REC Critical Loops. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to separate the REC Critical Loops. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.
General Conditions:
- 1. Reactor was operating at 100% rated power, with the B REC HX in operation when a transient occured in the REC system.
- 2. Several alarms associated with the REC system have been recieved in the Control Room.
- 3. Emergency Procedure 5.2REC, Loss of REC, has been entered and actions taken up to separating the REC Critical Loops.
Initiating Cues:
The Control Room Supervisor directs you to separate the REC Criticial Loops per 2.2.65.1, using the NORTH Critical Loop. Inform the CRS when you have separated the REC Critical Loops.
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Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 97 of 218 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
Trainee: Examiner:
Score: Pass Fail Examiner Signature: Date:
Performed faulted/non-faulted: NON-Faulted Additional Program Information:
- 1. Appropriate Performance Locations: Perform in the plant only.
- 2. Appropriate Trainee Levels: RO/SRO
- 3. Evaluation Method: Perform Simulate
- 4. Performance Time: 35 minutes
- 5. NRC K/A: 2.1.30 (3.9/3.4)
Directions to Examiner:
- 1. This JPM evaluates the trainees ability to transfer H2/O2 monitoring system monitors from Standby to Operation.
- 2. Brief the trainee and tell the trainee to begin.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.
5 All blanks must be filled out with either initials or an "NP" for "not performed", and an explanation may also be written in the space if desired by the examiner.
Directions to Trainee:
When I tell you to begin, you are to transfer Division 1 H2/O2 monitors from standby to operation.
Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using.
State the position of controls as you would have manipulated them to transfer H2/O2 monitoring system monitors from standby to operation.
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Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 98 of 218 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
=========================================================
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
General Conditions:
- 1. Division II H2/O2 System is scheduled to be removed from service.
- 2. Division I H2/O2 System is in Standby.
General
References:
- 1. Procedure 2.2.60.1 General Tools and Equipment:
None Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by "*".
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to transfer H2/O2 monitoring system monitors from Standby to Operation.
- 2. Accurately locate and identify all the instrumentation required to be monitored to transfer H2/O2 monitoring system monitors from standby to operation.
- 3. Correctly interpret instrument and system responses and their interrelationships when transferring H2/O2 monitoring system monitors from Standby to Operation.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
The CRS has directed you to place the Division I monitoring system in Operation from standby. You are to notify the CRS when Division I H2/O2 monitoring system has been placed in operation.
NOTE: Tell the trainee to begin.
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
Note to Examiner: The trainee may perform either Step 1 or Step 2 to satisfy the critical step.
Performance Checklist Standards Initials Performance Checklist Standards Initials
- 1. Place DIV I H2/O2 ANALYZER The operator places Div I H2/O2 ANALYZER RESET RESET switch to RESET and then switch to RESET and then to ON.
- to ON.
CUE: Switch is positioned to RESET and then to ON.
- 2. Place POWER switch to RESET and The operator places POWER switch to RESET and release at PC-CS-H2/O2 I (Cable release at PC-CS-H2/O2 I (Cable Spreading Room).
- Spreading Room)
CUE: Switch is positioned toward RESET and RELEASED.
- 3. Ensure power switch in ON The operator ensures power switch in ON.
CUE: Switch is positioned toward ON.
- 4. Check pump P-1 is running with The operator checks pump P-1 is running with PUMP PUMP switch in RUN. switch in RUN.
CUE: Pump switch is in RUN, red light is lit for the P-1 pump.
- 5. Ensure only one sample stream The operator ensures only one sample stream solenoid solenoid valve and H2/O2 Pump P-1 valve and H2/O2 Pump P-1 discharge valve indicates
- discharge valve indicates OPEN. OPEN.
CUE: One sample stream solenoid valve light is red, the others are green. (Select and indicate one of the valves one away from the Div II monitor current sample point).
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
Performance Checklist Standards Initials
- 6. Advance sample stream by pressing The operator advances the sample stream by pressing Key 7 until Div I and Div II are on Key 7 until Div I and Div II are on different streams with different streams with one line one line between them.
between them.
CUE: Provide response to match action taken by operator. (The sample stream should advance one for each press of Key 7.)
- 7. Re-initialize the monitor by pressing The operator presses Key 1.
Key 1.
- CUE: Key 1 has been pressed.
- 8. Place Div I H2/O2 ANALYZER The operator places Div I H2/O2 ANALYZER RESET RESET switch to OFF. switch to OFF.
CUE: Switch is positioned toward OFF.
- 9. Place PC-R-H2 I, CONTAINMENT The operator places PC-R-H2 I, CONTAINMENT HYDROGEN, PRINT-HOLD switch HYDROGEN, PRINT HOLD switch in PRINT.
- in PRINT.
CUE: Switch is positioned toward PRINT.
- 10. Place PC-R-O2 I, CONTAINMENT The operator places PC-R-O2 I, CONTAINMENT OXYGEN, PRINT-HOLD switch in OXYGEN, PRINT-HOLD switch in PRINT.
- PRINT.
CUE: Switch is positioned toward PRINT.
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
Performance Checklist Standards Initials
- 11. Check PC-R-H2 I and PC-R-O2 I The operator checks that digital displays indicate number PC-R-H2 I and PC-R-O2 I digital displays indicator associated with stream being number associated with stream being sampled as sampled as indicated on indication on PC-CS-H2/O2 I.
PC-CS-H2/O2 I.
CUE: Recorders are synchronized CUE: One hour has elapsed after recorders were synchronized.
- 12. LCD displays H2 and O2 values with The operator ensures the LCD displays H2 and O2 values no alarm messages. with no alarm messages.
CUE: Only H2 and O2 values are indicated.
- 13. Ensure no alarm indicating lights are The operator ensures no alarm indicating lights are on.
on.
CUE: No red lights are illuminated.
CUE: The CRS acknowledges the report. This JPM is now complete.
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to transfer Division 1 H2/O2 monitors from standby to operation. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to transfer H2/O2 monitoring system monitors from standby to operation.
General Conditions:
- 1. Division II H2/O2 System is scheduled to be removed from service.
- 15. Division I H2/O2 System is in standby.
Initiating Cues:
The CRS has directed you to place the Division I monitoring system in operation from standby. You are to notify the CRS when Division I H2/O2 monitoring system has been placed in operation.
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Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 105 of 218 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101
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Task
Title:
Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)
========================================================
Page 105 of 218
Nebraska Public Power District SKL034-40-28 Cooper Nuclear Station Page 106 of 218 Job Performance Measure Revision 03 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104
========================================================
Task
Title:
TRANSFER AN MCC TO THE ALTERNATE POWER SUPPLY
========================================================
Trainee: Examiner:
Score: Pass Fail Examiner Signature: Date:
Additional Program Information:
- 16. Appropriate Performance Locations: Plant
- 17. Appropriate Trainee Levels: SO/RO/SRO
- 18. Evaluation Method: Perform Simulate
- 19. Performance Time: 30 minutes
- 20. NRC K/A: 2.1.30 (3.9/3.4) 262001 A4.03 (3.2/3.4)
Directions to Examiner:
- 2. If any steps of this JPM are to be performed and not simulated, inform the Shift Supervisor prior to commencing. Upon completion, inform the Shift Supervisor of any system restoration that may be required.
- 3. Brief the trainee and tell the trainee to begin.
- 4. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 5. All blanks must be filled out with either initials or an "NP" for "not performed", and an explanation may also be written in the space if desired by the examiner.
Directions to Trainee:
When I tell you to begin, you are to transfer an MCC to the alternate power supply. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to transfer an MCC to the alternate power supply.
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Nebraska Public Power District SKL034-40-28 Cooper Nuclear Station Page 107 of 218 Job Performance Measure Revision 03 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104
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Task
Title:
TRANSFER AN MCC TO THE ALTERNATE POWER SUPPLY
========================================================
General Conditions:
- 1. A Maintenance outage is in progress (Plant is in Mode 4).
- 2. MCC-T is to be deenergized for cleaning and inspection.
- 3. Diesel Generator #1 is operable.
General
References:
- 1. Procedure 2.2.19 General Tools and Equipment:
- 1. Key 43 Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by "*".
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to transfer an MCC to the alternate power supply.
- 2. Accurately locate and identify all instrumentation required to be monitored to transfer an MCC to the alternate power supply.
- 3. Correctly interpret instrument and system responses and their interrelationships when transferring an MCC to the alternate power supply.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
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Nebraska Public Power District SKL034-40-28 Cooper Nuclear Station Page 108 of 218 Job Performance Measure Revision 03 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104
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Task
Title:
TRANSFER AN MCC TO THE ALTERNATE POWER SUPPLY
========================================================
Initiating Cue(s):
The CRS has directed you to transfer MCC-X from normal to emergency power in accordance with SOP 2.2.19. You are to inform the CRS when MCC-X is powered from emergency power.
NOTE: Tell the trainee to begin.
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Nebraska Public Power District SKL034-40-28 Cooper Nuclear Station Page 109 of 218 Job Performance Measure Revision 03 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104
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Task
Title:
TRANSFER AN MCC TO THE ALTERNATE POWER SUPPLY
========================================================
Performance Checklist Standards Initials
- 1. Obtain Key 43. The operator obtains Key 43 from the Control Room.
CUE: If asked at the MCC, only the right white light is ON, green light is ON.
- 2. Unlock Emergency feeder breaker. At MCC-L, the operator unlocks and removes the padlock from Breaker 2B, MCC-X EMERGENCY
- FEEDER.
CUE: Padlock is removed.
- 3. CLOSE Emergency feeder breaker. At MCC-L, the operator CLOSES Breaker 2B, MCC-X EMERGENCY FEEDER.
- CUE: The top of the breaker handle is to the right, the bottom is to the left.
- 4. Verify emergency power available. At MCC-X Transfer Switch, the operator ensures the EMERGENCY POWER AVAILABLE light is ON.
CUE: Both WHITE power available lights are ON.
CUE: If asked, green light is ON, red light is OFF.
- 5. Transfer MCC to emergency At MCC-X Transfer Switch, the operator momentarily source. presses the EMERGENCY button.
- CUE: Mechanical "clunking" sound is heard.
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Nebraska Public Power District SKL034-40-28 Cooper Nuclear Station Page 110 of 218 Job Performance Measure Revision 03 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104
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Task
Title:
TRANSFER AN MCC TO THE ALTERNATE POWER SUPPLY
========================================================
Performance Checklist Standards Initials
- 6. Verify MCC transfer. At MCC-X Transfer Switch, the operator ensures the MCC-X FED FROM MCC-L light is ON.
CUE: RED light is ON, GREEN light is OFF.
- 7. OPEN Normal feeder breaker At MCC-T, the operator OPENS Breaker 3C, MCC-X NORMAL FEEDER.
- CUE: The top of the breaker handle is to the left, the bottom is to the right.
- 8. LOCK OPEN Normal feeder At MCC-T, the operator installs the padlock removed breaker. earlier on Breaker 3C, MCC-X NORMAL FEEDER.
CUE: Padlock is installed.
CUE: If asked, at MCC-X red light is ON, left power avail light is ON.
- 9. Return Key 43. The operator returns Key 43 to the Control Room.
CUE: The key has been returned.
- 10. Inform CRS The operator informs the CRS that MCC-X is powered from its emergency source and that proper operation of equipment is to be verified.
CUE: I have been informed. I will verify proper operation of equipment powered from MCC-X. This JPM is now complete.
Page 110 of 218
Nebraska Public Power District SKL034-40-28 Cooper Nuclear Station Page 111 of 218 Job Performance Measure Revision 03 ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to transfer an MCC to the alternate power supply. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to transfer an MCC to the alternate power supply.
General Conditions:
- 1. A Maintenance outage is in progress. (Plant is in Mode 4)
- 2. MCC-T is to be deenergized for cleaning and inspection.
- 3. Diesel Generator #1 is operable.
Initiating Cue(s):
The CRS has directed you to transfer MCC-X from normal to emergency power in accordance with SOP 2.2.19. You are to inform the CRS when MCC-X is powered from emergency power.
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Nebraska Public Power District SKL034-40-28 Cooper Nuclear Station Page 112 of 218 Job Performance Measure Revision 03 Page 112 of 218
Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 113 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104
=========================================================
Task
Title:
INSTALL & REMOVE PTMs (PTM #41 & 42)
=========================================================
Trainee: Examiner:
Score: Pass Fail Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: Plant
- 2. Appropriate Trainee Levels: SO/RO/SRO
- 3. Evaluation Method: Simulate Perform
- 4. Performance Time: 20 minutes
- 5. NRC K/A: 2.1.30 (3.9/3.4); 2.4.34 (3.8/3.6)
Directions to Examiner:
- 1. This JPM evaluates the trainees ability to defeat RCIC low Reactor pressure isolation using PTM #41 and #42 per 5.8.20.
- 2. ENSURE THE OPERATOR COMPLIES WITH ALL ELECTRICAL SAFETY PRECAUTIONS.
- 3. Brief the trainee and tell the trainee to begin.
- 4. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.
- 5. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 6. All blanks must be filled out with either initials or an "NP" for "not performed", and an explanation may also be written in the space if desired by the examiner.
Directions to Trainee:
When I tell you to begin, you are to perform the steps necessary to defeat RCIC low Reactor pressure isolation using PTM #41 and #42 per 5.8.20. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to complete EOP PTM #41 and #42.
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Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 114 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104
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Task
Title:
INSTALL & REMOVE PTMs (PTM #41 & 42)
=========================================================
========================================================
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Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 115 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104
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Task
Title:
INSTALL & REMOVE PTMs (PTM #41 & 42)
=========================================================
General Conditions:
- 1. The plant has scrammed.
- 2. The MSIVs are closed.
- 3. HPCI is being used for pressure control.
- 4. RCIC is being used for level control.
General
References:
- 5. Emergency Support Procedure 5.8.20, EOP Plant Temporary Modifications General Tools and Equipment:
- 1. Flat tipped screwdriver.
- 2. Key for Aux Relay Room (Grand Master will work)
- 3. Electrical tape.
- 4. Key for PTM Box in Aux Relay Room (Master Lock J423)
- 5. Flashlight.
Special Conditions, References, Tools, Equipment:
l
- 1. Critical checks denoted by "*".
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to install EOP PTMs #41 and #42.
- 2. Accurately locate and identify all instrumentation required to be monitored when installing EOP PTMs #41 and #42.
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Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 116 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104
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Task
Title:
INSTALL & REMOVE PTMs (PTM #41 & 42)
=========================================================
- 3. Correctly interpret instrument and system responses and their interrelationships when installing EOP PTMs #41 and #42.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
The Reactor Operator has directed you to defeat RCIC low Reactor pressure isolation by installing EOP PTMs #41 and #42 per ESP 5.8.20. You are to inform the Reactor Operator when the EOP PTMs #41 and #42 have been installed.
NOTE: Tell the trainee to begin.
Page 116 of 218
Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 117 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104
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Task
Title:
INSTALL & REMOVE PTMs (PTM #41 & 42)
=========================================================
Performance Checklist Standards Initials
- 1. Obtain flat-tipped The operator obtains flat-tipped screwdriver screwdriver and electrical and electrical tape.
- tape.
NOTE: Procedure 5.8.20 is staged NOTE: The student must show you a flat-tipped in the Relay Room. screwdriver and electrical tape. These are in the PTM box, but a Master Lock NOTE: Key J423 is required to key is required. Any flat-tipped open the PTM Box in the Aux screwdriver and electrical tape will Relay room. work.
- 2. Identify Wire RC27-4 on The operator correctly identifies Wire RC27-4 Terminal BB-43 in PNL 9-30 on Terminal BB-43 in PNL 9-30.
(C-903-AUX RELAY RM).
- 3. Install EOP PTM Number 41 The operator loosens the screw and removes by lifting Wire RC27-4 from Wire RC27-4 from Terminal BB-43 in PNL 9-30.
CUE: The lead is lifted.
- 4. Insulate the lifted lead The operator wraps tape around the end of the wire lifted.
CUE: The end of the wire has electrical tape wrapped around it.
Page 117 of 218
Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 118 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104
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Task
Title:
INSTALL & REMOVE PTMs (PTM #41 & 42)
=========================================================
Performance Checklist Standards Initials
- 5. Hang PTM tag. The operator hangs the PTM 41 tag on the lifted lead.
CUE: The PTM 41 tag is attached to the lifted lead.
- 6. Identify Wire RC-35-3 on The operator correctly identifies Wire RC-35-3 Terminal DD-28 in BAY-3 of on Terminal DD-28 in BAY-3 of PNL 9-33.
PNL 9-33 (C-903-AUX RELAY RM).
NOTE: Panel 9-33 bays are numbered from right to left, bay 3 is the bay farthest to the left.
- 7. Install EOP PTM Number 42 The operator loosens the screw and removes by lifting Wire RC-35-3 from Wire RC-35-3 from Terminal DD-28 in BAY-3 of
- Terminal DD-28, BAY-3, PNL PNL 9-33.
9-33 (C-903-AUX RELAY RM).
CUE: The lead is lifted.
- 8. Insulate the lifted lead The operator wraps tape around the end of the wire lifted.
CUE: The end of the wire has electrical tape wrapped around it.
Page 118 of 218
Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 119 of 218 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104
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Task
Title:
INSTALL & REMOVE PTMs (PTM #41 & 42)
=========================================================
Performance Checklist Standards Initials
- 9. Hang PTM tag. The operator hangs the PTM 42 tag on the lifted lead.
CUE: The PTM 42 tag is attached to the lifted lead.
- 10. Inform CRS that RCIC low The operator informs the CRS (RO) that EOP reactor pressure isolation has PTM 41 and 42 has been installed.
been defeated.
CUE: The CRS (RO) acknowledges. This JPM is complete.
Page 119 of 218
Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 120 of 218 Job Performance Measure Revision 00 ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to perform the steps necessary to defeat RCIC low Reactor pressure isolation using PTM #41 and #42 per 5.8.20. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to complete EOP PTM
- 41 and #42.
General Conditions:
- 1. The plant has scrammed.
- 2. The MSIVs are closed.
- 3. HPCI is being used for pressure control.
- 4. RCIC is being used for level control.
Initiating Cue(s):
The Reactor Operator has directed you to defeat RCIC low Reactor pressure isolation by installing EOP PTMs #41 and #42 per ESP 5.8.20. You are to inform the Reactor Operator when the EOP PTMs #41 and #42 have been installed.
Page 120 of 218
Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 121 of 218 Job Performance Measure Revision 00 Page 121 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 122 of 218 Job Performance Measure for Operations Revision 07 Task No.: 200076A0504
=======================================================
Task
Title:
CONDUCT ALTERNATE ROD INSERTION (Vent Scram Air Header)
=======================================================
Trainee: Examiner:
Pass: Fail: Examiner Signature: Date:
Additional Program Information:
- 1. Appropriate Performance Locations: Plant
- 3. Evaluation Method: Simulate
- 4. Performance Time: 15 minutes
- 5. Importance Factor 3.5
- 6. NRC K/A 2.1.30 (3.9/3.4); 295037 EA1.05(3.9/4.0)
Directions to Examiner:
- 1. This JPM evaluates the trainees ability to conduct alternate rod insertion by venting the scram air header.
- 3. Observe the trainee during performance of the JPM for proper use of self-checking methods.
- 4. All blanks must be filled out with either initials or an "NP" for "not performed"; an explanation may also be written in the space if desired by the examiner.
- 5. Brief the trainee and tell the trainee to begin.
Directions to Trainee:
When I tell you to begin, you are to conduct alternate rod insertion by venting the scram air header. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them to conduct alternate rod insertion by venting the scram air header.
=======================================================
Page 122 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 123 of 218 Job Performance Measure for Operations Revision 07 Task No.: 200076A0504
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Task
Title:
CONDUCT ALTERNATE ROD INSERTION (Vent Scram Air Header)
=======================================================
General Conditions:
- 3. A failure of RPS and ARI to insert the control rods has occurred.
- 4. The Control Room operator has placed all keylock RPS test trip switches to TRIP.
- 6. The TSC is not yet operational.
- 7. No ARMs are alarming.
- 8. The In-Containment Rad Monitors are reading 100 REM/HR.
General
References:
- 1. Emergency Operating Procedure 5.8.3 General Tools and Equipment:
- 1. Crescent Wrench (attached by wire lanyard at IA-1601).
Special Conditions, References, Tools, Equipment:
- 1. Critical checks denoted by "*".
Task Standards:
- 1. Accurately locate, identify, operate and/or manipulate all component controls required to conduct alternate rod insertion by venting the scram air header.
- 2. Accurately locate and identify all instrumentation required to be monitored to conduct alternate rod insertion by venting the scram air header.
- 3. Correctly interpret instrument and system responses and their interrelationships when conducting alternate rod insertion by venting the scram air header.
- 4. Satisfactory completion of TPE requires a minimum of:
- a. 100% of critical elements, as defined in the JPM, successfully completed without error.
- b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).
Initiating Cue(s):
Page 123 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 124 of 218 Job Performance Measure for Operations Revision 07 Task No.: 200076A0504
=======================================================
Task
Title:
CONDUCT ALTERNATE ROD INSERTION (Vent Scram Air Header)
=======================================================
You have been assigned to conduct alternate rod insertion per Emergency Operating Procedure 5.8.3. The Control Room Supervisor directs you to manually vent the scram air header and to restore the scram air header when specifically directed to do so. Notify the CRS when the task is complete.
Note: Tell the trainee to begin.
Page 124 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 125 of 218 Job Performance Measure for Operations Revision 07 Task No.: 200076A0504
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Task
Title:
CONDUCT ALTERNATE ROD INSERTION (Vent Scram Air Header)
=======================================================
Performance Checklist Standard Initials
- 1. Close IA-985 Close IA-985, SCRAM DISCHARGE VOLUME and SCRAM PILOT AIR SUPPLY ROOT (R-903-SE). __________*
CUE: The handwheel is fully clockwise and the valve stem is down.
- 2. Ensure IA-244 Open. Ensure open IA-244, PI-229 and PS-230 ROOT.
CUE: The handwheel is fully counter clockwise.
- 3. Remove pipe cap from IA- Remove pipe cap from IA-1601, PI-229 and PS-230 1601. DRAIN line, utilizing the wrench attached by lanyard to *
. IA-1601.
CUE: The pipe cap is turning.
CUE: The pipe cap is removed.
- 4. Open IA-1601 Open IA-1601, PI-229 and PS-230 DRAIN.
CUE: Valve handwheel is turning counter-clockwise.
There is the sound of rushing air.
CUE: The valve handwheel is fully counter clockwise.
Page 125 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 126 of 218 Job Performance Measure for Operations Revision 07 Task No.: 200076A0504
=======================================================
Task
Title:
CONDUCT ALTERNATE ROD INSERTION (Vent Scram Air Header)
=======================================================
Performance Checklist Standard Initials
- 5. Inform Control Room that Notify Control Room that venting is in progress.
venting is in progress.
CUE: When notified:
C Acknowledge venting is in progress and DIRECT operator to stay on the line.
C (After ~1 minute) report that all control rods are inserted and DIRECT restoration of the scram air header.
- 6. Close IA-1601 Close IA-1601, PI-229 & PS-230 DRAIN.
CUE: The valve handwheel is fully clockwise.
- 7. Install pipe cap on IA-1601 Install and tighten the pipe cap on IA-1601, PI-229 & PS-230 DRAIN.
- CUE: The pipe cap is in place and turning.
CUE: The pipe cap is tight.
- 8. Open IA-985 Open IA-985, CRD SCRAM DISCHARGE VOLUME &
SCRAM PILOT AIR SUPPLY.
- CUE: The handwheel is fully counter clockwise and the valve stem is up.
- 9. Inform the CRS that the task Inform the CRS that the scram air header has been is complete manually vented and that the scram air header is restored.
CUE: The CRS acknowledges the report. This JPM is complete.
Page 126 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 127 of 218 Job Performance Measure for Operations Revision 07 ATTACHMENT 1 Directions to Trainee:
When I tell you to begin, you are to conduct alternate rod insertion by venting the scram air header. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.
When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them to conduct alternate rod insertion by venting the scram air header.
General Conditions:
- 1. A failure of RPS and ARI to insert the control rods has occurred.
- 2. The Control Room operator has placed all keylock RPS test trip switches to TRIP.
- 4. TSC is not yet operational.
- 5. No ARMs are alarming.
- 6. The In-Containment Rad Monitors are reading 100 REM/HR.
Initiating Cues:
You have been assigned to conduct alternate rod insertion per Emergency Operating Procedure 5.8.3. The Control Room Supervisor directs you to manually vent the scram air header and to restore the scram air header when specifically directed to do so. Notify the CRS when the task is complete.
Page 127 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 128 of 218 Job Performance Measure for Operations Revision 07 Cooper Scenario No. 1 Operating Test Station No. 1 Examiners: Candidates:
Page 128 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 129 of 218 Job Performance Measure for Operations Revision 07 Objectives The crew assumes the shift with the plant operating at 70% power with all systems operable except the Emergency Transformer and the "A" CRD Pump. The crew will perform a routine shifting of RBHVAC Fans.
Shortly after the fan swap the "B" REC Pump will trip.
This will require entry into 2.4REC and T.S. 3.7.3. After conditions are stabilized the load dispatcher will request raising main generator load 100 Mwe which requires raising reactor power with recirc flow. While raising load the "A" Average Power Range Monitor (APRM) will fail high, initiating a half scram. This will require resetting RPS, bypassing the APRM, and checking Technical Specifications (Tracking LCO only). Main Condenser vacuum will decrease as air in-leakage rises. Lowering condenser vacuum will result in a turbine trip and reactor scram. When a reactor scram is attempted, an ATWS requires entry into EOPs 1A, 6A and 7A. ARI will fail to insert Control Rods. When Vacuum lowers to the MSIV isolation setpoint, the MSIVs will fail to close and must be manually closed. Some Control Rods will insert on the first manual scram after the ATWS. A second manual scram will insert more Control Rods, and the third manual scram will insert the remaining Control Rods.
PRA: ATWS Initial Conditions: 70% Full Power Operation, (EOC) (IC-20) with all systems operable except the Emergency Transformer and "A" CRD Pump Page 129 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 130 of 218 Job Performance Measure for Operations Revision 07 Turnover: The plant has just completed a rod pattern adjustment, continue at current power level, until Reactor Engineering has completed a plan for returning to 100% power. The "A" CRD Pump is inoperable because of a severe oil leak on the speed increaser. Maintenance is putting together a work package. The station is in Day 1 of 7 day LCO (3.8.1, condition A) due to Emergency Transformer being OOS for planned maintenance on 69KV line by OPPD. After assuming the shift, the crew will perform shifting of the RBHVAC fans.
Event Malf. No. Type Event Description No.
1 N/A N Shift RB HVAC Fans 2 SW11B C REC Pump Trip.
3 N/A R Scheduled power increase 4 NM9A I (RO/SRO) "A" APRM fails high.
(100%)
Page 130 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 131 of 218 Job Performance Measure for Operations Revision 07 5 MC01 C (SRO/RO/BOP) Loss of vacuum (High air in-leakage) 6 RD02 M (Crew) ATWS (Hydraulic Lock on HCUs).
(90%)
7 MS07 C (SRO/BOP) MSIVs fail to close following loss of vacuum. MSIVs must be manually CLOSED.
Page 131 of 218
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 132 of 218 Job Performance Measure for Operations Revision 07 Simulation Facility Cooper Nuclear Station Scenario No.: 1 Op Test No.:
Examiners: Operators: CRS RO BOP Initial 70% Full Power Operation, (EOC) (IC-20) with all systems operable except the Emergency Transformer Conditions: and A CRD Pump.
Turnover: See attached turnover sheet Event No. Event Position Event Type* Description Pre-insert N/A ATWS Pre-insert N/A Group 1 isolation failure Pre-insert N/A Loss of power, Emergency Transformer 1 N BOP Shift RB HVAC Fans 2 C CRS/BOP REC Pump Trip.
3 R CRS/RO Scheduled power increase 4 I CRS/RO A APRM fails high.
5 C Crew Loss of main condenser vacuum 6 M Crew ATWS (Hydraulic Lock on HCUs).
7 C CRS/BOP MSIVs fail to close following loss of vacuum.
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Page 132 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 133 of 218 Job Performance Measure for Operations Revision 07 SCENARIO #1
SUMMARY
The crew assumes the shift with the plant operating at 70% power with all systems operable except the Emergency Transformer and the A CRD Pump. The crew will perform a routine shifting of RBHVAC Fans; shortly after the fan swap, the B REC Pump will trip. This will require entry into 2.4REC and T.S. 3.7.3. After conditions are stabilized, the load dispatcher will request raising main generator load 100 Mwe which requires raising reactor power with recirc flow. While raising load the A Average Power Range Monitor (APRM) will fail high, initiating a half scram. This will require bypassing the APRM, resetting RPS and checking Technical Specifications (tracking LCO only). Main Condenser vacuum will degrade as air in-leakage rises from a leak in the turbine/condenser boot. This will require a turbine trip and reactor scram. When a reactor scram is attempted, an ATWS requires entry into EOPs 1A, 6A and 7A.
ARI will also fail to insert Control Rods. When Vacuum lowers to the MSIV isolation setpoint, the MSIVs will fail to close and must be manually closed. Some Control Rods will insert on the first manual scram after the ATWS. A second manual scram will insert more Control Rods, and the third manual scram will insert the remaining Control Rods.
Page 133 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 134 of 218 Job Performance Measure for Operations Revision 07 Scenario No: 1 Event No. 1 Event
Description:
Shift Reactor Building H & V Exhaust Fans Time Position Applicants Actions or Behavior CRS Directs Shift Reactor Building H & V Exhaust Fans per Section 5.0 of OP 2.2.47.
BOP Place Controller HV-DPIC-835A, RX BLDG/ATMOS DP, to MANUAL (M) and adjust signal to stabilize Reactor Building pressure at -0.30" to -0.33" wg.
Place control switch for SUPPLY FAN selected to AUTO to RUN.
NOTE - Performance of the next step should be rapid and may result in RX BLDG LOW D/P alarm and entry into EOPs and T.S. if RX BLDG d/p goes above zero.
BOP Place control switch for EXHAUST FAN selected to STBY to RUN.
Place control switch for fan to be removed from service to OFF and back to STBY.
Ensure Reactor Building pressure is being maintained at -0.30" to -0.33" wg.
Adjust HV-DPIC-835A, to stabilize Reactor Building pressure at -0.30" to -0.33" wg.
Place control switch for SUPPLY FAN selected to RUN to AUTO.
Place control switch for EXHAUST FAN selected to RUN to AUTO.
Place Controller HV-DPIC-835A, RX BLDG/ATMOS DP, in AUTO (A). Ensure Reactor Building pressure continues to be maintained at -0.30" to -0.33" Page 134 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 135 of 218 Job Performance Measure for Operations Revision 07 Scenario No: 1 Event No. 2 Event
Description:
REC Pump Trip Time Position Applicants Actions or Behavior BOP Reports Annunciator: M-1/B-2, REC PUMP B FAILURE. and possibly LOW HEADER PRESSURE.
BOP Diagnoses the loss of the B REC Pump CRS Directs the start of necessary REC pumps.
BOP Starts the C REC Pump and verifies normal system operation.
Directs an SO to inspect the REC Pump area for unusual conditions and verify the C REC Pump is operating correctly.
Verifies correct valve lineup and monitors REC Pump discharge pressures.
CRS Initiates investigation and repair of REC Pump B Enters T.S. 3.7.3.A1 and declares a 30 day LCO Page 135 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 136 of 218 Job Performance Measure for Operations Revision 07 Scenario No: 1 Event No. 3 Event
Description:
Power Increase Time Position Applicants Actions or Behavior CRS Direct the RO to increase station output by 100 MWe by raising recirc flow in accordance with station procedure 2.1.10.
NOTE:
CRS may act as Reactivity Manager.
RO Enters 2.1.10, STATION POWER CHANGES Raises power by increasing RR pump flow, maintaining loop flows balanced. Maintains rate of power change consistent with system capabilities as determined by Load Dispatcher.
Discontinues power rise when directed or station output has risen 100 MWe.
BOP Monitors secondary plant parameters and reports Mwe changes to RO.
Page 136 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 137 of 218 Job Performance Measure for Operations Revision 07 Scenario No: 1 Event No. 4 Event
Description:
A APRM Fails High Time Position Applicants Actions or Behavior RO Reports Annunciators 9-5-1/A-4, ROD WITHDRAWAL BLOCK 9-5-1/A-7 APRM RPS CH A UPSCALE TRIP OR INOP 9-5-2/A-1 RX SCRAM CHANNEL A alarm.
Diagnoses half scram and APRM A High CRS Directs BOP to back panels to check APRM drawers for indications and trouble shooting.
BOP Locates APRM A on back panels Reports APRM A failed upscale CRS Directs RO to BYPASS APRM A and reset half scram.
May check T.S. 3.3.1 (Minimum channel requirments are met) and declare a Tracking LCO on the failed APRM.
RO Bpasses APRM A Resets half scram per 2.1.5 Page 137 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 138 of 218 Job Performance Measure for Operations Revision 07 Scenario No: 1 Event No. 5 Event
Description:
Loss of Main Condenser vacuum Time Position Applicants Actions or Behavior BOP Operator diagnoses loss of vacuum from Control Room indications or annunciator B-1/A-3, TG LOW VACUUM PRE-TRIP Announces degrading condenser vacuum.
CRS Enters ABNORMAL PROCEDURE 2.4.VAC, LOSS OF CONDENSER VACUUM Directs a reactor power reduction by reducing recirculation flow.
Notifies Load Dispatcher.
Directs BOP operator to keep him informed of vacuum When it is determined that vacuum cannot be recovered to >23" Hg, directs a Reactor Scram and Turbine Trip.
RO Lowers power by lowering RR pump flow. Maintains rate of power change consistent with system capabilities.
When directed, manually scrams the reactor, reports failure to scram.
Page 138 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 139 of 218 Job Performance Measure for Operations Revision 07 Scenario No: 1 Event No. 6 Event
Description:
ATWS (Hydraulic Lock)
Time Position Applicants Actions or Behavior CRS Enters EOP-1A and transitions to 6A/7A. Directs:
Place the Mode switch in S/D ARI initiated Manually runback RR pumps to minimum Trip Recirc pumps Insert control rods using 5.8.3 actions.
Verify group isolations.
Inhibit ADS Pressure be maintained 800 to 1000 psig.
RPV Low Water Level Group 1 be defeated. (This step may not be taken if the MSIVs have closed or the CRS anticipates MSIV closure on the loss of vacuum.)
RO Mode switch to SHUTDOWN.
Initiate ARI.
Run Recirc pumps to minimum.
Trip Recirc pumps.
Insert control rods per 5.8.3 Begins actions to reset the scram and re-inserting additional scrams.
Verify Group isolations (MSIVs should isolate by 8" Hg vac).
Maintain RPV pressure 800 to 1000 psig with Turbine Bypass Valves and SRVs.
Initiates SLC (If directed at this time) and confirms injection.
Provides initial SLC Tank level to the CRS.
CRS Directs terminating and preventing injection except for RCIC, CRD and Boron injection be terminated and prevented until RPV water level is < +100" (corrected FZ)
Before BIIT, direct SLC be initiated.
When RPV water level reaches +100" (corrected FZ), direct RPV water level be maintained between -
25" and +100" (corrected FZ) (LL).
Scenario No: 1 Event No. 6 Page 139 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 140 of 218 Job Performance Measure for Operations Revision 07 Event
Description:
ATWS (Hydraulic Lock)
Time Position Applicants Actions or Behavior BOP Lowers RPV water level to +100" and reports to CRS. When and if directed, maintains RPV water level -25" to +100".
CRS When torus temperature reaches 95?F, enter and direct the activities of EOP-3A.
Direct torus cooling be placed in service.
When all rods have been inserted or HSBW injected, direct RPV water level be restored and maintained +15" to +40".
RO Direct SO to install EOP PTM 61 & 62.
Install jumpers to defeat RPS.
Reset scram.
Allow SDV to drain.
Insert manual scram, report rod movement.
Reset scram and continue inserting manual scrams.
Report when 26% (HSBW) of the SLC tank has been injected.
BOP Initiates RHR in Suppression Pool Cooling.
When directed, maximizes Suppression Pool Cooling.
Restore and maintain RPV water level +15" to +40".
CRS Classifies event as a Site Area Emergency (based on EAL 3.3.4) and implements EPIP 5.7.2, Shift Supervisor EPIP.
Page 140 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 141 of 218 Job Performance Measure for Operations Revision 07 Scenario No: 1 Event No. 7 Event
Description:
MSIVs failure to automatically isolate Time Position Applicants Actions or Behavior BOP Report MSIVs have not isolated on low cond. vacuum (10").
CRS Direct maually closing the MSIVs.
BOP Place all MSIV control switches to CLOSE.
Verify all MSIVs are closed.
Page 141 of 17
Nebraska Public Power District SKL034-10-65 Cooper Nuclear Station Page 142 of 218 Job Performance Measure for Operations Revision 07 Critical Tasks Sat Unsat Scenario #1 The Crew shall stop injection within 5 minutes of directing injection be stopped.
The crew shall insert the control rods.
Page 142 of 17
Instructor Station Instructions Scenario #1 SIMULATOR SET-UP A. Initialize the simulator in IC 20, Full Power Operation (EOL).
- 1. Transfer to RUN.
- 2. Load batch file A:\nrc1 1-3 Lower Reactor power to 70% using recirc flow 1-4 Adjust generator to +100 MVARs.
1-5 Balance voltage regulator.
1-6 Balance all controllers.
1-7 Place breakers 1FS and 1GS in PTL 1-8 Ensure PMIS IDTs are blank 1-9 Red tag the "A" CRD Pump 1-10 Red tag breaker C/S for 1FS & 1GS.
1-11 Clear all annunciators 1-12 Turn recorder power ON 1-13 Adjust GAFs B. Verify simulator conditions as follows:
- 1. Triggers Number File Name Description E1 None Default to False E2 None Default to False E3 None Default to False E4 None Default to False E5 None Default to False
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial RP04 Group 1 Isolation Failure Active N/A N/A N/A N/A Page 143 of 17
Instructor Station Instructions Scenario #1 Number Title Trigger TD Severity Ramp Initial RD02 ATWS Active N/A 90% N/A N/A ED06 Loss of Power Emergency Active N/A N/A N/A N/A Transformer SW11B Trip of B REC Pump E1 0 N/A N/A N/A NM09A APRM Signal Failure E3 0 100% N/A N/A MC01 Main Condenser Air In-Leakage E4 0 100% 10:00 N/A
- 3. Remotes Number Title Trigger Value Ramp RD18 Install ARI PTMs E4 N/A N/A RD04 Manually Close CRD-29 E5 CLOSE N/A
- 4. Overrides Instrument Tag Trigger TD Value Ramp Control Switch for CRD zdicrdsws3a[1] A N/A STOP N/A Pump A (START, STOP)
Control Switch for CRD zdocrdsws3a[1] A N/A OFF N/A Pump A green light Page 144 of 17
Instructor Station Instructions Scenario #1 Pre Events:
Allow the operators several minutes to review the panels and set up the controls and displays as they desire.
Event #1:Shift Reactor Building H & V Exhaust Fans ROLE PLAY:
None Event #2: REC Pump Trip ACTION:
When the crew has swapped RBHVAC fans and Secondary Containment Parameters are normal and when directed by the lead examiner Activate Trigger E1: REC Pump B Trip ROLE PLAY:
If asked as the Station Operator to investigate wait 1 minute and report that the pump motor is hot and it smells of hot insulation.
ROLE PLAY:
If asked to check the C REC Pump as the SO report that it is operating normally.
Event #3: Power Increase ROLE PLAY:
Contact the Control Room via extension 5271 as the load dispatcher and direct that net load be raised 100 MWe. In addition direct that MVARs remain at +100 MVARs.
ROLE PLAY:
If contacted as the reactor engineer direct the crew to raise power using recirc flow.
Page 145 of 17
Instructor Station Instructions Scenario #1 Event #4: A APRM Fails High ACTION:
After the crew has completed the power change and when directed by the lead examiner Activate Trigger E3: APRM Signal Failure.
ROLE PLAY:
If contacted as I & C report that you will get a tech and be up in the control room in about 15 minutes.
Event #5: Loss of Main Condenser vacuum ACTION:
After the crew has reponded to the APRM failure and when directed by the lead examiner Activate Trigger E4:Main Condenser Air In-Leakage.
ROLE PLAY:
If called as the load dispatcher acknowledge the load reduction.
Event #6: ATWS ROLE PLAY:
If asked as the Station Operator to install ARI PTMs, wait 2 minutes, then Insert REMOTE FUNCTION RD18, EOP PTMs 61 and 62 and inform the Control Room.
ACTION:
One minute after the first manual scram, modify malfunction RD02, ATWS to 80%
After the second scram modify malfunction RD02, ATWS to 60%
After the third scram delete malfunction RD02.
ACTION:
When the following conditions are reached, place the simulator in FREEZE:
- 1. The MSIVs are closed.
- 2. Reactor is shutdown under all conditions without boron.
- 3. When directed by the lead examiner.
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Instructor Station Instructions Scenario #1 Batch File
^NRC Scenario 1 imf rp04 imf rd02 90 imf ed06 ior zdicrdsws3a[1] stop ior zlocrdsws3a[1] off imf sw11b(1) imf nm09a(2) imf mc01(3) 100 10:00 irf rd18(4) remove irf rd04(5) close Page 147 of 17
Turnover Information Scenario #1 Plant Status:
- 1. The plant is operating at approximately 70% power near the end of the operating cycle.
- 2. Rod Sequence Information: Step: 1 Rod: 18-27 Notch: 26
- 3. Tech. Spec. Limitations in effect:
Day 1 of 7 day LCO (3.8.1, condition A) due to Emergency Transformer being OOS for planned maintenance on 69KV line by OPPD. All associated surveillances are current. SR6.EE.610 was performed one hour ago.
- 4. Significant problems/abnormalities:
- "A" CRD Pump is tagged out. The speed increaser gearbox is being replaced after complete failure.
- Emergency Transformer estimated return to service this shift.
- Southeast Nebraska is in a severe thunderstorm warning and flash flood watch.
- 5. Evolutions/maintenance for the on-coming shift:
- When contacted, raise power level.
- Mechanics working on "A" CRD Pump.
- OPPD expediting return of 69KV line due to weather
- As soon as possible after assuming the shift, shift RBHVAC fans to permit maintenance to lubricate Exhaust Fan EF-R-1A Page 148 of 17
Instructor Station Instructions Scenario #1 Page 149 of 17
Instructor Station Instructions Scenario #1 Cooper Station Scenario No. 2 Operating Test No. 1 Examiners: Candidates:
Objectives:
The crew assumes the shift with the plant operating at 100% power with all systems operable except the Emergency Transformer and "A" CRD Pump. The crew will start the "A" CRD Pump and place it in service.
After the CRD system is operating normally, Doniphan will notify Cooper that the south interface load has exceeded 1190 MVA and that Cooper must lower load 100 MWe immediately. After a sufficient power change is observed, the DEH oil pressure pilot valve spring will fail, causing DEH pressure oscillation, this will require stopping the power reduction. When conditions have stabilized, a 20% spurious runback signal will force the reactor into the Stability Exclusion Region and power oscillations will occur. Since these are large power oscillations with the auto scram function defeated, the crew must manually scram the reactor. When the reactor scrams off-site power will be lost and a small break will start on the B Recirc Loop discharge line. The DGs will start and provide power to emergency buses. A failure of the HPCI Auxiliary Oil Pump will prevent operation of HPCI. RCIC will fail to automatically start and must be manually started. After its started it will trip. It may be restarted, but will continue to trip. When RPV water level cannot be maintained, the crew must Emergency Depressurize and restore RPV water level with low pressure ECCS systems with power supplied by the DGs.
PRA Station Blackout and LOCA Initial Conditions: 100% Full Power Operation (EOC) (IC-20). All systems operable except the Emergency Transformer and "A" CRD Pump.
Turnover: Continue power operations. All systems are operable except the Emergency Transformer and the "A" CRD Pump. The station is in day 1 of 7 day LCO (3.8.1, condition A) due to Emergency Transformer being OOS for planned maintenance on 69KV line by OPPD. The "A" CRD Pump had been out of service for an oil leak and has been repaired. Maintenance is standing by for the crew to start the pump and place it in service.
Event Malf. No. Type Event Description No.
1 N/A N (SRO/BOP) Start the "A" CRD pump and place it in service. Secure the "B" CRD Pump.
2 N/A R (SRO/RO) Power reduction to lower load on the south interface.
3 TC04 I (SRO/BOP) DEH Oil System Pressure Oscillation requires shifting DEH Pumps.
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Instructor Station Instructions Scenario #1 4 RR12A I (SRO/RO) Recirculation Pump Runback to 20% with power oscillations.
RR12BC R04 5 ED05 C (Crew) Loss of all off-site power.
ED07 ED15 6 RR20B M (Crew) Small break LOCA with a failure of the HPCI Auxiliary Oil Pump, HP10 resulting in an inability to restore RPV water level, requiring Emergency Depressurization.
7 RC02 C (SRO/BOP) RCIC fails to start then trips on high exhaust pressure after it is manually started.
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Simulation Facility: Cooper Nuclear Station Scenario No. 2 Op. Test No.
Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation, (EOC) (IC-20) with all systems operable except the Emergency Conditions: Transformer.
Turnover: See attached turnover sheet.
Event No. Event Position Event Description Type Pre-insert N/A RRMG A Scoop Tube Lockout P/B failure Pre-insert N/A RRMG B Scoop Tube Lockout P/B failure Pre-insert N/A RCIC system failure to automatically start Pre-insert N/A HPCI Auxiliary Oil Pump failure to start Pre-insert N/A 4160 Bus auto transfer failure Pre-insert N/A Loss of power Emergency Transformer 1 N (CRS/BOP) Start the A CRD pump and place it in service. Secure the B CRD Pump.
2 R (CRS/RO) Power reduction to lower load on the south interface.
3 C (CRS/BOP) DEH Oil System Pressure Oscillations.
4 I (CRS/RO) Recirculation Pump Runback to 20% with power oscillations.
5 C (CRS/BOP) (Crew) Loss of all off-site power.
6 M (CREW) Small break LOCA with an HPCI Aux oil pump failure 7 C (CRS/BOP) (CRS/BOP) RCIC fails to automatically start then trips.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient Page 152 of 18
SCENARIO # 2
SUMMARY
The crew assumes the shift with the plant operating at 100% power with all systems operable except the Emergency Transformer and A CRD Pump. The crew will start the A CRD Pump and place it in service. After the CRD system is operating normally, Doniphan will notify Cooper that the south interface load has exceeded 1190 MVA and that Cooper must lower load 100 MWe immediately. After a sufficient power change is observed, the DEH oil pressure pilot valve spring will fail, causing DEH pressure oscillation, this will require stopping the power reduction. When conditions have stabilized, a 20%
spurious runback signal will force the reactor into the Stability Exclusion Region and eventual power oscillations will occur.
Entry into the Stability Exclusion Region will require entry into T.S. 3.4.1. The power oscillations will become large and may reach the APRM High setpoints with the auto scram function defeated. The crew must manually scram the reactor. When the reactor scrams off-site power will be lost and a small break will start on the B Recirc Loop discharge line. The DGs will start and provide power to emergency buses. A failure of the HPCI Auxiliary Oil Pump will prevent operation of HPCI. RCIC will fail to automatically start and must be manually started. After its started it will trip. It may be restarted, but will continue to trip. When RPV water level cannot be maintained, the crew must Emergency Depressurize and restore RPV water level with low pressure ECCS systems with power supplied by the DGs.
Page 153 of 18
Scenario No: 2 Event No. 1 Event
Description:
Start the A CRD Pump and secure the B CRD Pump Time Position Applicants Actions or Behavior CRS Directs the BOP to establish communication with the CRD Room, then start the A CRD pump and when proper operation is established shutdown the B CRD Pump.
BOP Establish communications between Control Room and CRD pump area.
BOP Check the A CRD pump is lined up for operation.
BOP At Panel 9-5, balance CRD-FIC-301, CRD FLOW CONTROL, and place to MANUAL.
Start standby CRD pump.
BOP Shut down CRD pump to be removed from service.
adjust manual control on CRD-FC-301 to obtain flow of 50 gpm.
Balance CRD-FC-301 and place to BAL.
At Panel 9-5, check charging water pressure and drive water DP and adjust if needed.
Page 154 of 18
Scenario No: 2 Event No. 2 Event
Description:
Power Reduction Time Position Applicants Actions or Behavior The Control Room is contacted by Doniphan and notified that the Cooper south interface load has exceeded 1190 MVA and that an immediate load reduction of 100 Mwe is required.
CRS Enters 5.3GRID.
Direct an immediate power reduction of 100 Mwe using recirculation flow.
Acts as Reactivity Manager.
RO Enters 2.1.10, STATION POWER CHANGES
- Lowers power by lowering RR pump flow. Maintains rate of power change at 10 MWe per minute
- Enters 5.3GRID.
BOP Monitors plant parameters.
Evaluates which plant loads may be secured.
CRS Notifies station management and the system load dispatcher.
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Scenario No: 2 Event No. 3 Event
Description:
DEH Oil System Pressure Oscillation requires stopping power reduction.
Time Position Applicants Actions or Behavior Annunciator B-1/A-6 TURB EH FLUID LOW PRESSURE alarms BOP Determines standby pump starts (both pumps are running).
Directs an SO to check the EHC pumps and piping Diagnoses oscillating DEH relief valve from oscillating pressure on DEH pressure indication.
Requests SO to verify proper operation of pumps and check for leaks.
Remove standby pump from service per 2.2.80.
CRS Directs stopping any power changes in progress Directs RO to monitor reactor pressure set Enters 2.4DEH Gives Scram Actions Directs securing one DEH Pump Directs restoring DEH to a normal lineup in accordance with 2.2.80.
Initiates a work order for the oscillating DEH Valve.
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Scenario No: 2 Event No. 4 Event
Description:
Recirculation Pump Runback to 20% with power oscillations.
Time Position Applicants Actions or Behavior Annunciators 9-4-3/D-3 RECIRC A FLOW LIMIT alarms 9-4-3/D-7 RECIRC B FLOW LIMIT alarms Followed by:
Annunciators 9-5-1/A-4 ROD WITHDRAWAL BLOCK 9-5-1/B-7 LPRM UPSCALE 9-5-1/C-7 LPRM DOWNSCALE 9-5-1/B-8 APRM UPSCALE and others indicating core power oscillations.
RO Monitors recirculation flow and reactor power.
Attempts to limit the transient by pressing the SCOOPTUBE LOCKOUT buttons.
Press RR PUMP RUNBACK RESET button.
Determines that feedwater flow is > 20% and RR-MO-53A/B are full open.
Monitors for power oscillations.
Informs CRS of entry into stability exclusion region.
Inserts control rods per Attachment 7, Emergency Power Reduction Rods.
When directed by the CRS or the RO determines reactor safety in jeopardy depresses both RX SCRAM buttons (Panel 9-5).
Verifies all rods in Monitors nuclear instrumentation:
- Insert SRM and IRM detectors.
- Change APRM recorders to IRMs.
- Range IRMs on scale.
- Check reactor power is lowering.
Verifies all SDV vent and drain valves are closed.
CRS Directs RO to press SCOOPTUBE LOCKOUT buttons.
Enters 2.4RR, REACTOR RECIRCULATION ABNORMAL Enter Attachment 4 when entry in or near the stability exclusion region is determined.
Enters T.S. 3.4.1 Increase speed of operating recirculation pump(s) per Procedure 2.1.10.
Insert Emergency Power Reduction Rods per Procedure 10.13.
When core power oscillations reach the APRM scram set point directs a MANUAL SCRAM.
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Scenario No. 2 Event No. 4 (continued)
Event
Description:
Recirculation Pump Runback to 20% with power oscillations Time Position Applicants Actions or Behavior BOP Monitors secondary plant response.
After the reactor is scrammed:
Trips one reactor feedwater pump Trips all but one condensate booster pump and condensate pump.
Ensure Main turbine automatically trips or manually trip the turbine when main generator output is <
80 Mwe.
Diagnoses Loss of Off-Site Power.
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Scenario No: 2 Event No. 5 Event
Description:
Loss of all off-site power.
Time Position Applicants Actions or Behavior The following annunciators alarm:
C-2/D-9 STARTUP XFMR SECONDARY UNDERVOLTAGE C-2/C-9 STARTUP XFMR LOW VOLATAGE C-2/A-1 4160V BUS 1A UNDERVOLTAGE. (and 1B, 1E, 1G, etc.)
CRS Enters EMERGENCY PROCEDURE 5.3EMPWR, EMERGENCY POWER and directs actions for a loss of off-site AC power.
Establishes a pressure band of 800 to 1000 psig using SRVs.
Establishes a RPV level band of 10 to 40.
Enters EOP-5A is the loss of power causes a high temperature in the MS Tunnel.
Verifies:
BOP 4160V Buses 1A, 1B, 1C, 1D, and 1E de-energized.
Both DGs have started and loaded.
4160V Bus 1F/1G energized by emergency source.
Monitors DG load to prevent exceeding maximum load (4000 kW and 694 amps; DG may be overloaded to 4400 kW and 763 amps for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period).
Places DRYWELL REC ISOL VALVE CONTROL switch to OPEN.
Throttles open REC HX outlet valve for a HX that was in service, as necessary, to maintain REC-PI-452, REC HEADER PRESSURE, in green band:
Ensures the emergency DC lube oil pumps have started Places Condensate and Condensate Booster Pump switches to TRIP.
Places Air Compressor A or B switch to RUN.
RO Restores CRD System per Procedure 2.2.8.
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Scenario No.: 2 Event No.: 6 Event
Description:
Small break LOCA with inability to restore RPV water level Time Position Applicants Actions or Behavior Monitors RPV water level and Primary Containment parameters.
RO/BOP Diagnose LOCA by lowering RPV water level and rising Drywell pressure.
Diagnoses HPCI Aux Oil Pump failure.
BOP Diagnoses RCIC failure to start.
Initiates torus spray.
Initiates drywell sprays
- Shuts down drywell coolers (if operating)
- Shuts down recirc pumps
- Initiates drywell sprays Throttles drywell spray to prevent torus pressure from dropping to 0 psig.
Controls low pressure ECCS to restore and maintain RPV water level between TAF and MSL.
Monitors DG load to prevent exceeding maximum load (4000 kW and 694 amps; DG may be overloaded to 4400 kW and 763 amps for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.)
RO Inhibits ADS when timer initiates.
Controls low pressure ECCS to restore and maintain RPV water level between 15 and 40.
Restores REC Re-establishes drywell cooling by re-starting FCUs CRS Enters EOP-1A and 3A Directs attempt to maintain RPV water level between 15 and 40.
Directs restoring REC Directs re-establishing Drywell FCUs Directs maximizes CRD flow and initiating SLC pumps.
Directs inhibiting ADS Before Torus pressure reached 10 psig directs initiating torus spray.
When Torus pressure exceeds 10 psig directs initiating drywell spray.
When RPV water level cannot be maintained >-25 enters EOP-2A, EMERGENCY DEPRESSURIZATION.
Directs opening six SRVs and controlling low pressure injection to restore level.
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Scenario No: 2 Event No. 7 Event
Description:
RCIC fails to auto start.
Time Position Applicants Actions or Behavior CRS Directs attempting to manually restore RCIC.
BOP Uses RCIC SYSTEM OPERATION HARDCARD to start RCIC.
Open RCIC-MO-132.
Start GLAND SEAL VACUUM PUMP.
Open RCIC-MO-21.
Adjust RCIC-FIC-91, RCIC flow controller, as required, to maintain level.
Diagnoses RCIC trip on high exhaust pressure.
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CRITICAL TASKS SAT UNSAT The Crew shall emergency depressurize when RPV water level cannot be restored and maintained >-25.
The Crew shall initiate drywell sprays at >10 psig torus pressure and before PSP is exceeded.
The Crew shall initiate a manual scram when oscillations reach the APRM Scram setpoint.
1983.
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Instructor Station Instructions Scenario #2 SIMULATOR SET-UP A. Initialize the simulator in IC 20, Full Power Operation (EOL).
- 1. Transfer to RUN.
- 2. Load batch file A:\nrc2.
- 3. Balance all controllers.
- 4. Place breakers 1FS and 1GS in PTL
- 5. Ensure PMIS IDTs are blank
- 6. Red tag breaker C/S for 1FS & 1GS.
- 7. Clear all annunciators
- 8. Turn recorder power ON
- 9. Adjust GAFs Verify simulator conditions as follows:
B. Triggers Number File Name Description E1 None Default to False E2 None Default to False E3 nrc2 Activates when #1 TSV closes E4 None Default to False E5 None Default to False C. Malfunctions Number Title Trigger TD Severity Ramp Initial RC01 RCIC System Failure to Auto Start A 0 N/A N/A N/A ED06 Loss of Power, Emergency A 0 N/A N/A N/A Transformer HP11 HPCI Aux Oil Pump Failure A 0 N/A N/A N/A ED03B Transfer Failure A 0 N/A N/A N/A TC04 DEH Oil System Pressure Oscillation E1 0 N/A N/A N/A RR12A A RR Pump Runback 20% E2 0 N/A N/A N/A Page 163 of 18
Instructor Station Instructions Scenario #2 Number Title Trigger TD Severity Ramp Initial RR12B B RR Pump Runback 20% E2 0 N/A N/A N/A CR04 Low-Flow Hi-Power Instability E5 0 80% 3 min N/A Loss of Power Startup Transformer E3 0 N/A N/A N/A ED05 ED07 Loss of Power Normal Transformer E3 0 N/A N/A N/A ED15 Loss of 12.5 KV power E3 0 N/A N/A N/A RR20B Coolant Leak inside the PC E3 2 min 70 15 N/A RC02 RCIC Turbine Trip E4 0 N/A N/A N/A D. Remotes None E. Overrides Instrument Tag Trigger TD Value Ramp RRMG A Scoop Tube lockout P/B ZDIRRMGSWS16A A N/A OFF N/A RRMG B Scoop Tube lockout P/B ZDIRRMGSWS16B A N/A OFF N/A PTM #31 RPS Scram Bypass Jumper ZDIRPSSCRM JA1 IN A N/A IN N/A PTM #32 RPS Scram Bypass Jumper ZDIRPSSCRM JA2 IN A N/A IN N/A PTM #33 RPS Scram Bypass Jumper ZDIRPSSCRM JB1 IN A N/A IN N/A PTM #34 RPS Scram Bypass Jumper ZDIRPSSCRM JB2 IN A N/A IN N/A Page 164 of 18
Instructor Station Instructions Scenario #2 Pre Events Allow the operators three to five minutes to review the panels and set up the controls and displays as they desire.
Event # 1: Start the A CRD Pump and place it in service. Secure the B CRD Pump.
ROLE PLAY:
As the AO in the CRD Room report you and a maintenance mechanic are standing by for the pump start.
ROLE PLAY:
Report the following:
- Suction valve full open.
- Minimum flow valve open.
- Discharge valve open.
- Pump and motor oil levels normal.
- Pump casing and suction filter vented.
ROLE PLAY:
From the CRD Pump room report that the A CRD Pump is operating normally.
Event #2: Power Reduction ROLE PLAY:
When the crew has placed the A CRD Pump in service and secured the B CRD Pump contact the Control Room as Doniphan and notify the CRS the Cooper south interface load has exceeded 1190 MVA and that an immediate load reduction of 100 Mwe is required.
Page 165 of 18
Instructor Station Instructions Scenario #2 Event #3: DEH Oil System Pressure Oscillation requires stopping power reduction.
ACTION: When directed by the Chief Examiner Activate Trigger E1: DEH Oil Pressure Oscillation ROLE PLAY:
As SO sent to DEH area; report that the discharge relief valve is periodically lifting.
Report that there are no leaks.
When the standby pump has been started and the oscillating pump shutdown, report all conditions are normal.
NOTE:
Delete the malfunction when the B DEH Pump is secured Event #4: Recirculation Pump Runback to 20% with power oscillations.
ACTION: When directed by the Chief Examiner Activate Trigger E2: Recirculation Pump Runback ROLE PLAY:
If contacted as Reactor Engineering, request the CRS to wait five minutes while you run some computer analysis to determine the correct rod sequence to use for a power reduction.
ACTION: After the CRS has determined the T.S. Entry (3.4.1) Active Trigger E5: Power Oscillations.
NOTE:
The LOOP and small break LOCA (LOCA is on a time delay and ramp) are automatically triggered by the Main Turbine Stop Valves leaving the full open position when the turbine is tripped following the reactor scram.
Event #5: Loss of Off-Site Power.
ROLE PLAY:
If sent to the Diesel Genrators as the SO to check the DGs report that they are operating normally.
Event #6: Small break LOCA resulting in an inability to restore RPV water level requiring Emergency Depressurization.
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Instructor Station Instructions Scenario #2 Event #7: RCIC fails to auto start then (when manually started) trips on high exhaust pressure.
ACTION:
When the following conditions are reached, place the simulator in FREEZE.
- RPV Water level is being controlled above + 3.
- Drywell pressure is being maintained below 10 psig.
Page 167 of 18
Instructor Station Instructions Scenario #2 imf rc01 imf ed06 imf hp11 imf tc04(1) imf rr12a(2) imf rr12b(2) imf cr04(2 2:00)80 3:00 Put this on a separate trigger (E5 and remove the TD) imf ed03b imf ed05(3) imf ed07(3) imf ed15(3) imf rr20b(3 2:00) 70 15:00 imf rc02(4)
IOR ZDIRPSSCRMJA1 IN IOR ZDIRPSSCRMJA2 IN IOR ZDIRPSSCRMJB1 IN IOR ZDIRPSSCRMJB2 IN ior zdirrmgsws16a off ior zdirrmgsws16b off trgset 3 "zlotcltsv1[2] == 1"
^set up trigger 3 to activate when the #1 TSV is closed Page 168 of 18
Turnover information Scenario 2 Plant Status:
- 1. The plant is operating at 100% power, near the end of the current cycle.
- 2. Rod Sequence Information: Step: 01 Rod: 26-27 Notch: 36
- 3. Tech. Spec. Limitations in effect:
Day 1 of 7 day LCO (3.8.1, condition A) due to Emergency Transformer being OOS for planned maintenance on 69KV line by OPPD. All associated surveillances are current.
- 4. Significant problems/abnormalities:
0.1 "A" CRD Pump was tagged out. The tags (Clearance) have been cleared and maintenance and an AO are standing by for a pump start to verify proper operation.
0.2 Emergency Transformer estimated return to service this shift.
- 5. Evolutions/maintenance for the on-coming shift:
Start the A CRD Pump and if it is operating properly, place it in service and secure the B CRD Pump.
Page 169 of 18
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 OPPD expediting return of 69KV line due to weather.
Page 170 of 18
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Cooper Scen Op Station erat ario No. 3 ing Tes t
No.
1 Examiners: Candidates:
Page 171 of 18
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Objectives:
The crew assumes the shift with the plant operating at 100% power.
Core Spray Pump "B" is tagged out for maintenance while replacing the pump seal. SGT "B" was started earlier for the system engineer who requested a vibration measurement. The measurement was completed all data has been taken. The crew is to shutdown SGT "B" and place it in a standby lineup. When SGT is secured and in a standby lineup, the 125 VDC Panel AA3 will fail, requiring entry into 5.3DC125. The loss of this panel results in:
- Trip of the "A" Recirculation Pump
- Loss of trip capability for the "A" CRD Pump and "A" Air Compressor.
- Loss of control of the "A" and "C" SW Pumps.
- Inoperability of CS "A", RCIC, DG-1, RHR Subsystems "A" and "B" RHR SW Pumps "A" and "C" and SW Pumps "A" and "C".
The loss of AA3 will require the crew to enter T.S. 3.0.3 and determine a plant shutdown is required. When Cooper management is notified they will direct an immediate shutdown.
After the initial portion of the power reduction is completed, the Master Feedwater Controller will fail low. If the operator catches the failure, operation in manual is possible. After controlling feedwater in manual, if a decision to manually scram is not reached, then the feedwater pumps will trip. This will result in a loss of Feedwater and a Reactor Scram. HPCI will initiate (or be manually initiated) and must be shutdown manually. Group 6 will fail to automatically isolate and must be diagnosed and manually isolated. EOP-1A must be entered.
During the HPCI initiation, HPCI will develop a steam line break and fail to isolate. EOP-5A must be entered. As Reactor Building temperatures rise, the crew will rapidly depressurize using the Turbine Bypass Valves and/or the SRVs, EOP-1A and/or 2A. In either case, the first method attempted will partially fail (up to five SRVs do not open or the Turbine Bypass valves fail closed). Alternate steps for emergency de-pressurization must be taken.
PRA Loss of Containment Initial Conditions: 100% Full Power Operation (EOC) (IC-20). Core Spray Pump "B" is out of service.
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Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Turnover: Continue power operations. Core Spray Pump "B" is tagged out for maintenance while replacing the pump seal. SGT "B" was started earlier for the system engineer who requested a vibration measurement. The measurement was completed all data has been taken.
The crew is to shutdown SGT "B" and place it in a standby lineup.
Page 173 of 18
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Event Malf. No. Type Event Description No.
1 N/A N (SRO/BOP) Shutdown SGT "B" and place it in a standby lineup.
2 ED19 C (SRO/BOP/RO) 125 VDC Panel AA3 failure (Instrument power supplies ).
3 N/A R (SRO/RO) Power reduction for T.S. 3.0.3 required shutdown.
4 FW09 I (SRO/BOP/RO) Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.
5 HP06 M (CREW) HPCI un-isolatable steam line leak (and trip of running (5% over feedwater pumps).
20 Min)
HP09 6 RP09 I (CRS/RO) Failure of the auto isolation of Group 6 7 AD06 C (SRO/BOP) Failure of the Turbine Bypass Valves to remain (A,C,D,E open and/or failure of up to five SRVs to open.
,H)
TC07 (A, B, C)
Page 174 of 18
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Cooper Station Alternate Scenario (Scenario 4) Operating Test No. 1 Examiners: Candidates:
Objectives:
The crew assumes the shift with the plant operating at 100% power with all systems operable except the "A" CRD Pump. The crew will perform a routine shifting of SW Pumps after maintenance has completed a breaker inspection on the "B" SW Pump Breaker. During this pump swap several Tech. Specs. considerations should be made. After the SW Pump swap the load dispatcher will request lowering main generator load 100 Mwe which requires lowering reactor power with recirc flow. While lowering load the "D" Main Steam Line Flow Transmitter will fail upscale. This will require stabilizing RPV water level, taking manual control of water level and placing feedwater in single element. After the actions are completed a steam leak will develop in the Drywell. Drywell pressure will rise and the crew will manually scram the reactor (If they dont the reactor will scram on high drywell pressure).
After the reactor is scrammed the "B" Feedwater Pump will fail to trip on high level, additionally HPCI will initiate on high drywell pressure. These two large pumps injecting will cause a rapid level rise which will require the crew to close the MSIVs and/or trip the pumps. As Drywell pressure rises the "A" RHR loop containment spray valves will fail.
When the "B" loop is used the containment spray switch will fail. At some time into the LOCA a downcomer will fail preventing the pressure suppression chamber from working.
This failure will cause a rapid rise in drywell temperatures and pressures. Drywell pressure will reach PSP (Drywell temperature will also rise rapidly) requiring an Emergency Depressurization. After the reactor is depressurized. I & C will restore the "B" RHR loop containment spray and the crew will spray the torus and drywell. Drywell temperatures will be high enough to warrant determining that RPV water level instruments are operable.
PRA: Loss of Containment Heat Sink Initial Conditions: 100% Power Operation (EOC) (IC-20) power with all systems operable except the "A" CRD Pump.
Page 175 of 18
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Turnover: Continue power operations. The "A" CRD Pump is inoperable because of a severe oil leak on the speed increaser. The crew is to perform a routine shift the Service Water Pumps.
Event Malf. No. Type Event Description No.
1 N/A N (CRS/BOP) Shift Service Water Pumps 2 N/A R (CRS/RO) Scheduled power reduction of 100 Mwe 3 FW13D I (CRS/RO) Failure of the "D" Steam Line Flow Transmitter 4 FW01A C (CRS/BOP) "A" Feedwater Pump Trips Page 176 of 18
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 5 MS01D M (Crew) Steam leak in the Drywell 50%
10 Min Ramp 6 FW28B I (CRS/RO) Failure of the "B" Feedwater Pump High Level Trip.
7 ZDIRHRS I/C (Crew) Failure of Containment Spray with torus downcomer WS17A & failure.
B PC12 Page 177 of 18
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Simulation Facility Cooper Nuclear Scenario No.: 3 Op Test No.:
Station Examiners Operators CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).
Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.
2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.
4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.
5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).
6 I Crew Failure of the auto isolation of Group 6.
7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Page 178 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 SCENARIO #3
SUMMARY
The crew assumes the shift with the plant operating at 100% power. Core Spray Pump B is tagged out for maintenance to perform a 4160 V Breaker inspection. SGT B was started earlier for the system engineer who requested a vibration measurement. The measurement was completed all data has been taken. The crew is to shutdown SGT B and place it in a standby lineup. When SGT is secured and in a standby lineup, the 125 VDC Panel AA3 will fail, requiring entry into 5.3DC125.
The loss of this panel results in:
- Trip of the A Recirculation Pump
- Loss of trip capability for the A CRD Pump and A Air Compressor.
- Loss of control of the A and C SW Pumps.
- Inoperability of CS A, RCIC, DG-1, RHR Subsystems A and B RHR SW Pumps A and C and SW Pumps A and C.
The loss of AA3 will require the crew to enter T.S. 3.0.3 and determine a plant shutdown is required.
When Cooper management is notified they will direct an immediate shutdown.
After the initial portion of the power reduction is completed, the Master Feedwater Controller will fail low. If the operator catches the failure, operation in manual is possible. After controlling feedwater in manual, if a decision to manually scram is not reached, then the feedwater pumps will trip. This will result in a loss of Feedwater and a Reactor Scram. HPCI will initiate (or be manually initiated) and must be shutdown manually. Group 6 will fail to automatically isolate and must be diagnosed and manually isolated. EOP-1A must be entered. During the HPCI initiation, HPCI will develop a steam line break and fail to isolate. EOP-5A must be entered. As Reactor Building temperatures rise, the crew will rapidly depressurize using the Turbine Bypass Valves and/or the SRVs, EOP-1A and/or 2A. In either case, the first method attempted will partially fail (up to five SRVs do not open or the Turbine Bypass valves fail closed). Alternate steps for emergency de-pressurization must be taken.
Page 179 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Scenario No: 3 Event No. 1 Event
Description:
Shutdown SGT B and place it in a standby lineup.
Time Position Applicants Actions or Behavior CRS Directs the BOP operator to shutdown SGT B and place it in a standby lineup.
BOP Verifies RB HVAC is operating and RB pressure at -.25 in. wg.
At VBD-R insures HV-DPIC-835B is in MANUAL set at 100 (0 on the Controller).
Places EF-R-1F, SGT B EXH FAN C/S to AUTO Verifies SGT B stops
- SGT INLET (AO-250) and OUTLET (AO-252) close Verifies DPCV-546B, D/P Controller switch is in AUTO Requests independent verification. (RO goes to back panel to verify)
Page 180 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Time Position Applicants Actions or Behavior Page 181 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Scenario No: 1 Event No. 2 Event
Description:
125 VDC Panel AA3 failure (Instrument power supplies).
Time Position Applicants Actions or Behavior CREW Recognize and report multiple alarms caused by the power loss.
Diagnose loss of panel AA3.
Respond to Loss of:
- A RRMG Air Compressor
Enters 2.4RR, REACTOR RECIRCULATION ABNORMAL Announces Scram actions to the Crew.
RO Determines reactor is NOT in the Stability Exclusion region, announces to the CRS.
Closes RR-MO-53A, PUMP DISCHARGE VLV.
After RR-MO-53A has been closed for 5 minutes, open valve for 6 seconds Direct SO to RRMG set A to throttle REC-49(51), MG SET A OIL HX OUTLET (R-931-SW), to maintain oil outlet temperature 90 F to 130 F.
Enters Single Loop Operation per Procedure 2.2.68.1.
Monitor temperature differential between bottom head drain and dome.
Direct the SO to locally, open RRMG A drive motor field breaker.
Page 182 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Time Position Applicants Actions or Behavior CRS Declare the following equipment inoperable:
- CS Pump A.
- RCIC.
- DG-1.
- RHR SWBPs A and C.
- SW Pumps A and C.
- 4160V Bus 1F.
Enter T.S. 3.0.3 Determine a rapid shutdown is required per step 1.5 of 5.3DC125.
Notify maintenance and station management.
Scenario No: 1 Event No. 2 Event
Description:
125 VDC Panel AA3 failure (Instrument power supplies).
Time Position Applicants Actions or Behavior BOP Direct an SO to the air compressors to Start Air Compressor B or C and Transfer Tendamatic to B-C-A or C-A-B.
Send an SO to open EE-CB-4160F to stop SW Pump A and SW Pump C Page 183 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Time Position Applicants Actions or Behavior Page 184 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Scenario No: 3 Event No. 3 Event
Description:
Power Reduction for T.S. 3.0.3 required shutdown Time Position Applicants Actions or Behavior CRS Direct a rapid shutdown per 2.1.4.1 When feedwater flow is 5.2 to 6.5x106 lbs/hr, direct securing one RFP.
Contacts RE for control rods to use during shutdown.
RO While monitoring rod line and feedwater flow, reduce core flow to 35x106 lbs/hr using Reactor Recirculation.
BOP Monitor secondary plant parameters.
When directed secure one RFP.
Page 185 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Scenario No: 3 Event No. 4 Event
Description:
Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.
Time Position Applicants Actions or Behavior BOP While monitoring secondary plant parameters diagnose failure of Master Feedwater Controller.
CRS Direct entry into 2.4RXLVL, RPV WATER LEVEL CONTROL TROUBLE.
Direct Stopping the power reduction while RPV water level is stabilized.
Direct placing RFC-LC-83, MASTER LEVEL CONTROLLER in MANUAL.
Direct I & C to investigate the Feedwater Controller failure.
RO Stop lowering Recirc Flow.
BOP Place RFC-LC-83, MASTER LEVEL CONTROLLER in MANUAL and restore RPV water level to its normal band.
ACTION:
If the decision to manually scram is made continue with the scenario. If not initiate the HPCI Steam line leak.
Page 186 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Scenario No: 3 Event No. 5 Event
Description:
HPCI steam line leak.
Time Position Applicants Actions or Behavior RO Scram the reactor when RPV level cannot be maintained above +12" on narrow range instruments OR respond to automatic scram.
Provide a scram report.
Carry out scram actions per 2.1.5.
Assign RPV level / pressure control RO Restore and maintain RPV water level between +15 and +40".
NOTE:
It will take ~ 5 minutes from malfunction activation until the high temperature alarm.
BOP Maintain Rx pressure 600 to 800 psig.
Ensure PCIS Group 2,3 and 6 isolations.
Secure the HPCI turbine before RPV water level reaches +112".
Diagnose rising secondary containment temperatures and radiation levels.
Report:
annunciator 9-3-1/E-10: AREA HIGH TEMP.
Checks temperatures on the 9-21 panel.
May diagnose HPCI steam line break by observing that indicated steam pressure to HPCI is less than indicated steam pressure to RCIC.
CRS Enter EOP-5A, SECONDARY CONTAINMENT CONTROL Direct HPCI isolation.
Direct the Reactor Building be isolated (if high radiation signal is present).
Direct all quad coolers be started.
Direct verification of sump pump operation Direct HPCI be manually isolated.
Page 187 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Time Position Applicants Actions or Behavior Scenario No: 3 Event No. 5 Event
Description:
HPCI steam line leak.
Time Position Applicants Actions or Behavior BOP Attempt to manually isolate HPCI, report HPCI failure to isolate.
CRS Direct area temperatures be monitored.Dispatch personnel to investigate the steam leak Monitor for any secondary containment parameter reaches its maximum safe operating value:
Temperatures (TABLE 9)
Radiation (TABLE 10)
Water levels (TABLE 11)
Re-enter EOP-1A Declare a Site Area Emergency per EAL 2.3.3.
Direct a cooldown be commenced at
< 100 F/hr.
BOP Perform cooldown as directed.
CRS May anticipate emergency depressurization and direct rapid depressurization using bypass valves.
If 2 areas exceed Maximum Safe Operating Values, direct an Emergency Depressurization be performed.
Exit the pressure leg of 1A, Enter and direct 2A.
Verify PC level is > 6'.
Direct 6 SRVs be opened.
Direct RPV water level be maintained above TAF.
BOP If directed to rapidly depressurizes RPV using Bypass valves but bypass valves will not open (DEH Pump trips).
Page 188 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Time Position Applicants Actions or Behavior If directed to emergency depressurize RPV then open 6 SRV s. five SRVs will not open.
Restores and maintains RPV level +15" to +40" band with limited low pressure ECCS systems.
Page 189 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Scenario No: 3 Event No. 6 Event
Description:
Failure of the auto isolation of Group 6 Time Position Applicants Actions or Behavior RO Diagnoses failure of Group 6 and a full Group 2 isolation from the isolation status panel on the 9-5 Panel.
Reports failure to isolate to the CRS.
SRC Directs the RO to manually isolate Group 2 and 6.
RO Obtains Group Isolation Hard Card (2.1.22)
Manually isolates the listed valves and dampers.
Verifies SGT A and B operating Verifies the following valves OPEN SW-MO-650 SW-MO-651 REC-MO-711 REC-MO-714 Page 190 of 20
Instructor Station Instructions Turnover information Scenario #2 Time Position Scenario 2 Actions or Behavior Applicants Scenario No: 3 Event No. 7 Event
Description:
Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.
Time Position Applicants Actions or Behavior BOP Diagnoses failure of SRVs.
Notifies Crew CRS Directs the use of alternate depressurization systems EOP-2A, TABLE 2.
Main Steam and Turbine Bypass Vavles Main Steam Line Drains RCIC Gland Sealing Steam RFPTs A and B Steam Jet Air Ejectors RWCU AOG Steam Line Drains BOP Lowers RPV pressure using alternate depressurization systems.
Page 191 of 20
Instructor Station Instructions Turnover information Scenario #2 Scenario 2 Critical Tasks Sat Unsat The crew shall manually initiate a Reactor Building Isolation prior to exceeding 49mr on the Reactor Building Ventilation Radiation monitors.
The crew shall either rapidly depressurize the reactor to prevent exceeding Maximum Safe Operating Temperature (MSOT) in 2 areas OR Emergency Depressurize if MSOT is exceeded in 2 areas.
The crew shall manually isolate the Reactor Building, by performing a manual isolation of the Group 6 isolation valves.
Page 192 of 20
Instructor Turnover Station Instructions information Scenario #3 Scenario 2 SIMULATOR SET-UP A. Initialize the simulator in IC 20, Full Power Operation (EOL).
- 1. Transfer to RUN.
- 2. Load batch file A:\nrc3 1-3 Ensure PMIS IDTs are blank 1-4 Place B Core Spray in PTL 1-5 Place a red tag on B Core Spray pump switch.
1-6 Update the Safety System Status panel to reflect B Core Spray out of service.
1-7 Turn recorder power ON 1-8 Adjust GAFs B. Verify simulator conditions as follows:
- 1. Triggers Number File Name Description E1 None Default to False E2 None Default to False E3 None Default to False E4 None Default to False E5 None Default to False Page 193 of 20
Instructor Turnover Station Instructions information Scenario #3 Scenario 2
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial AD06A Reactor Pressure Relief Valve A N/A N/A N/A As-Is Failure AD06C Reactor Pressure Relief Valve A N/A N/A N/A As-Is Failure AD06D Reactor Pressure Relief Valve A N/A N/A N/A As-Is Failure AD06E Reactor Pressure Relief Valve A N/A N/A N/A As-Is Failure AD06H Reactor Pressure Relief Valve A N/A N/A N/A As-Is Failure TC07A Bypass Valve #1 Failure A N/A N/A N/A As-Is TC07B Bypass Valve #2 Failure A N/A N/A N/A As-Is TC07C Bypass Valve #3 Failure A N/A N/A N/A As-Is ED19C Loss of 125 VDC Power Panel E1 0 N/A N/A As Is AA3 FW09 Master Feedwater Master E3 0 50% 60 sec As Is Controller Failure HP06 HPCI Steam Line Break E5 5:00 5% 10:00 1 FW01A RFP Trip RFP 1A E5 0 N/A 0 N/A FW01B RFP Trip RFP 1B E5 0 N/A 0 N/A
- 3. Remotes Number Title Trigger Value Ramp RR15 RRMG A Field Breaker Local E7 Not Open Manual Control 1A01 Air Compressor Tendamatic E7 Sequence Select 1A04 Air Compressor Reset E7 1A07 Air Compressor 1A 480V Breaker E7 Local Manual SW38 SW Pump 1A 4160V Breaker E9 Local Manual Control SW40 SW Pump 1C 4160V Breaker E9 Page 194 of 20
Instructor Turnover Station Instructions information Scenario #3 Scenario 2 Number Title Trigger Value Ramp Local Manual Control RP04 EOP PTM 53 thru 56 A INSTALL N/A HP02 EOP PTMs #46 & #47, #65 & #66 A LIFTED N/A
- 4. Overrides Instrument Tag Trigger TD Value Ramp Core Spray Pump (14P-1B) ZLOCSSWS5B[1] A 0 OFF N/A HPCI MO-15 switch (ASD) ZDIHPCISWMO15[2] A 0 OPEN N/A HPCI MO-16 switch (ASD) ZDIHPCISWMO16[2] A 0 OPEN N/A
- 4. Take the simulator out of FREEZE and allow to run for several minutes to verify stable plant conditions. FREEZE the simulator.
Page 195 of 20
Instructor Turnover Station Instructions information Scenario Scenario 2#3 Event #1: Shutdown SGT B and place it in a standby lineup.
ROLE PLAY:
If directed by the Control Room to walk down the SGT area and verify all conditions are normal reply that you have performed and area inspection and all conditions are normal.
Event #2: 125 VDC Panel AA3 failure (Instrument power supplies).
ACTION After crew has secured the SGT and placed it in a standby lineup, and when directed by the Chief Examiner, INSERT TRIGGER E1 to de-energize 125 VDC panel AA3.
ROLE PLAY:
If called as I & C to investigate the loss of 125 VDC report that you will get a technician and go to the panel and investigate.
ROLE PLAY:
If asked to investigate the loss of panel AA3:
As SO, report the supply fuse has blown.
As maintenance, report there is no apparent cause of the fuse blowing.
ACTION If asked to replace the fuse for panel AA3, delete malfunction ED19C, then immediately reinsert the malfunction:
ROLE PLAY:
As SO sent to A RRMG set establish oil outlet temperature 90 F to 130 F.
Locally, open RRMG A drive motor field breaker.
As SO sent to air compressors Start Air Compressor B or C and Transfer Tendamatic to B-C-A or C-A-B.
As SO sent to EE-CB-480F open Breaker 4B, to stop CRD Pump A.
As SO sent to EE-CB-4160F open breakers to stop SW Pump A and SW Pump C ROLE PLAY:
As the SO when directed to the air compressors report that you have started Air Compressor B or C and transferred Tendamatic to B-C-A or C-A-B.
ROLE PLAY:
As SO sent to open Breaker 4B, EE-CB-480F(CRDP-A), to stop CRD Pump A. Report you have opened Breaker 4B, EE-CB-480F and shutdown CRD Pump A.
Page 196 of 20
Instructor Turnover Station Instructions information Scenario Scenario 2#3 ROLE PLAY:
As an SO sent to open EE-CB-4160F to stop SW Pump A and SW Pump C. Report that you have manually shutdown SW Pump A and SW Pump C ROLE PLAY:
As Station Management when notified of the T.S. 3.0.3 entry direct an immediate shutdown per 2.1.4.1, RAPID SHUTDOWN.
Event #3: Power reduction for T.S. 3.0.3 required shutdown.
ROLE PLAY:
When contacted as RE to give a control rod insertion sequence. Direct the person calling to insert rods in accordance with the rapid shutdown rod patern.
ACTION:
After crew has completed the Tech Spec assessment, and the crew has performed a significant power reduction, and/or when directed by the Chief Examiner Insert TRIGGER E2 to cause the feedwater Master Controller to fail low.
Event #4: Loss of Feedwater Controller ROLE PLAY:
As I & C state you will investigate and you will call back in 20 minutes.
ACTION:
If the decision to manually scram is made continue with the scenario and insert Trigger E5 when the reactor is scrammed. If no decision to scram is made insert Trigger E5 when directed by the Chief Examiner.
Event #5: HPCI Steam Line Leak ROLE PLAY:
If directed as the SO to determine the location of the steam leak report that the Reactor Buildign is filling with steam and that an exact location cannot be determined but that the steam appears to be coming from the HPCI area.
ROLE PLAY:
If directed as the SO to close HPCI MO-15 & 16 from the ASD room, wait 2 minutes, then turn the ASD panel ISOL switches for HPCI MO-15 & 16. Call the control room and report the valves will not close from the ASD room.
Page 197 of 20
Instructor Turnover Station Instructions information Scenario Scenario 2#3 ROLE PLAY:
If directed as the SO to close HPCI MO-16 manually (local), wait 2 minutes, then report steam in the Rx Bldg prohibits access to the valve.
When the RPV has been depressurized and RPV water level is being controlled in the +15" to +40" band, FREEZE the simulator.
Page 198 of 20
Instructor Station Turnover Instructions information Scenario Scenario 2#3
^ NRC Scenario 3 imf ia04c(1) imf ed19c(2) imf fw09(3) 1 00:15 imf hp06(5 5:00) 5 10:00 imf fw01a(5) imf fw01b(5) imf ad06a 0 imf ad06c 0 imf ad06d 0 imf ad06e 0 imf ad06h 0 imf tc07a 0 imf tc07b 0 imf tc07c 0 irf rp04 install irf hp02 lifted irf rr15(7) open irf ia01 irf ia04 irf ia07 irf sw38(9) open irf sw40(9) open ior zdihpcisws2 open ior zdihpcisws32 off ior zdihpciswmo15[2] open ior zdihpciswmo16[2] open ior zlocssws5b[1] off Page 199 of 20
Turnover Information Scenario #3 Plant Status:
- 1. The plant is operating at 100% power near the end of the operating cycle, steady state.
- 2. Rod Sequence Information: Step: 01 Rod: 18-27 Notch: 26
- 3. Tech. Spec. Limitations in effect:
We are in Day 3 of a 7 day LCO under specification 3.5.1
- 4. Significant problems/abnormalities:
B Core Spray is tagged out for 4160V breaker inspection. Electricians expect to complete inspection within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SGT B is operating per 2.2.73, section 7 for vibration measurement.
- 5. Evolutions/maintenance for the on-coming shift:
- 1. Continue full power operation.
- 2. Shutdown B SGT and place in a normal standby lineup.
- 3. Restore B Core Spray to service.
Page 200 of 20
Instructor Station Instructions Scenario #3 SimulatCooper Nuclear Scenario 4 Op Test No.:
ion Station No.:
Faci lity Examiners: Operators: CRS RO BOP Initial Conditions: 100% Full Power Operation, (EOC) (IC-20) with all systems operable except the "A" CRD Pump.
Turnover: See attached turnover sheet Event No. Event Position Event Type* Description Pre-insert N/A RHR "B" Loop Containment Spray Failure Pre-insert N/A "B" Feedwater Pump High Level Trip Defeated 1 N BOP Shift Service Water Pumps 2 R CRS/RO Scheduled power reduction of 100 MWe 3 I CRS/RO Failure of the "D" Steam Line Flow Transmitter 4 C CRS/BOP A Feedwater Pump Trips 5 M Crew Steam leak in the Drywell 6 I CRS/RO Failure of the B Feedwater Pump High Level Trip.
7 C CRS/BOP Failure of Containment Spray
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Page 201 of 18
Instructor Station Instructions Scenario #3 SCENARIO #4
SUMMARY
The crew assumes the shift with the plant operating at 100% power with all systems operable except the A CRD Pump. The crew will perform a routine shifting of SW Pumps after maintenance has completed a breaker inspection on the B SW Pump Breaker. During this pump swap several Tech.
Specs. considerations should be made. After the SW Pump swap the load dispatcher will request lowering main generator load 100 Mwe which requires lowering reactor power with recirc flow.
While lowering load the D Main Steam Line Flow Transmitter will fail upscale. This will require stabilizing RPV water level, taking manual control of water level and placing feedwater in single element. After the actions are completed a steam leak will develop in the Drywell. Drywell pressure will rise and the crew will manually scram the reactor (If they dont the reactor will scram on high drywell pressure). After the reactor is scrammed the B Feedwater Pump will fail to trip on high level, additionally HPCI will initiate on high drywell pressure. These two large pumps injecting will cause a rapid level rise which will require the crew to close the MSIVs and/or trip the pumps. As Drywell pressure rises the A RHR loop containment spray valves will fail. When the B loop is used the containment spray switch will fail. At some time into the LOCA a downcomer will fail preventing the pressure suppression chamber from working. This failure will cause a rapid rise in drywell temperatures and pressures. Drywell pressure will reach PSP (drywell temperature will also rise rapidly) requiring an Emergency Depressurization. After the reactor is depressurized, I & C will restore the B RHR loop containment spray and the crew will spray the torus and drywell. Drywell temperatures will be high enough to warrant determining that RPV water level instruments are operable.
Page 202 of 18
Instructor Station Instructions Scenario #3 Scenario No: 4 Event No. 1 Event
Description:
Shift operating SW Pumps per 2.2.71 Time Position Applicants Actions or Behavior CRS Directs BOP operator to shift operating SW Pumps by placing B SW Pump in service and securing the D SW Pump per 2.2.71.
BOP Contacts SO at the B SW Pump to insure pump is ready to start.
Place mode selector switch for the B SW Pump in MAN.
Start B SW Pump by placing CS to START.
Verify normal system pressures.
Place mode selector switch for B SW Pump to STANDBY.
Place mode selector switch for the D SW Pump in MAN.
Stop D SW Pump by placing CS to STOP.
Verify mode selector switch for pump D in AUTO.
Verify mode selector switch positioned per 2.2.71.
Report to CRS SW Pumps are shifted.
CRS Checks T.S. 3.7.2 for SW operability.
Checks T.S. 3.8.1 for DG operability.
Page 203 of 18
Instructor Station Instructions Scenario #3 Scenario No: 4 Event No. 2 Event
Description:
Power Reduction Time Position Applicants Actions or Behavior CRS When notified by the load dispatcher direct the RO to lower station output by 100 MWe by lowering recirc flow in accordance with station procedure 2.1.10.
RO Enters 2.1.10, STATION POWER CHANGES.
Lowers power by decreasing RR pump flow, maintaining loop flows balanced.
Maintains rate of power change consistent with system capabilities as determined by Load Dispatcher and 2.1.10 (10 MWe/Min).
Discontinues power rise when directed or station output has risen 100 MWe.
BOP Monitors secondary plant parameters and reports MWe changes to RO.
Page 204 of 18
Instructor Station Instructions Scenario #3 Scenario No: 4 Event No. 3 Event
Description:
Failure of the D Steam Line Flow Transmitter Time Position Applicants Actions or Behavior RO Responds to Annunciator: 9-5-2/G-1 REACTOR LOW WATER LEVEL Stop any power changes in progress.
Diagnoses a failure of a steam line flow instrument.
If level doesnt stabilize places Master Feedwater Controller in MANUAL to control RPV water level.
CRS Directs taking manual control of feedwater if required.
Enters 2.4RXLVL.
BOP Dispatches an SO to the 903 level of the Reactor Building to locally check the steam flow instruments.
RO Places RFC-LC-83, MASTER LEVEL CONTROLLER in MAN.
Places 1 OR 3 ELEMENT LVL CONT SELECT to 1.
Returns RPV level controller to BAL per Procedure 2.2.28.1.
Adjust manual control on RFC-MA-83 to null its deviation meter.
Place RFC-MA-83 in BAL.
Slightly vary settape on RFC-LC-83 to ensure control transferred (slight RFP speed change).
Reports Feedwater control in Automatic, Single Element Control.
CRS Initiates a notification for repair of the Steam Line Flow Transmitter.
Page 205 of 18
Instructor Station Instructions Scenario #3 Scenario No: 4 Event No. 4 Event
Description:
A Reactor Feedwater Pump trips Time Position Applicants Actions or Behavior RO Monitors RPV water level and responds to Recirculation Pump runback.
Monitors reactor power.
Monitors Recirc Flow and determines Stability Exclusion Region is NOT entered.
BOP Responds to A-1/A-4, RFP TURBINE A TRIP.
Places Feedwater Master Controller in Man and controls RPV water level.
Enters 2.4MC-RF, CONDENSATE AND FEEDWATER ABNORMAL and determines applicability.
Directs an SO to the feedwater pump to diagnose conditions.
Enters 2.2.28.1, Feedwater System Operation to restore A Feedwater Pump.
CRS Directs entry into 2.4MC-RF, CONDENSATE AND FEEDWATER ABNORMAL.
Page 206 of 18
Instructor Station Instructions Scenario #3 Scenario No: 4 Event No. 5 Event
Description:
Steam leak in the Drywell Time Position Applicants Actions or Behavior RO/BOP Monitors RPV water level and Primary Containment parameters.
Diagnoses LOCA by rising Drywell pressure.
Carries out scram actions per 2.1.5.
Diagnoses high RPV water level.
Trips B feedwater pump.
CRS Enter EOP 1A.Assign RPV level / pressure control.
Determine RPV water level and pressure and sets bands.
May direct venting the Primary Containment.
When drywell pressure exceeds 1.84 psig, re-enter EOP 1A and enter EOP 3A..
May direct re-starting drywell FCUs.
Directs securing HPCI (if not tripped).
May direct securing low pressure ECCS systems that are not needed.
Directs an SO be sent to check the Emergency Diesel Generators.
BOP Maintain Rx pressure 800 to 1000 psig (RPV pressure may be lower because of the overfeed, pressure band may be 600 to 800 psig).
Ensure PCIS Group 2, 3 and 6 isolations.
If directed re-starts drywell FCUs.
Verifies HPCI high water level trip.
Diagnoses rising primary containment temperatures and pressure.
RO Directs an SO to the Emergency Diesel Generators.
Scenario No: 4 Event No. 5 Event
Description:
Steam leak in the Drywell Page 207 of 18
Instructor Station Instructions Scenario #3 Time Position Applicants Actions or Behavior CRS When torus pressure is between 2 and 10 psig, directs RHR be placed in Torus spray mode.
When notified that RHR A Torus Spray valve would not open, directs using the B Loop of RHR.
When torus pressure exceeds 10 psig, directs Drywell spray.
Checks that operation is in the SAFE region of the DWSIL.
Directs drywell coolers be secured.
Directs Recirc pumps be tripped.
When notified the B Loop of RHR is not available, directs using the A loop of RHR in Drywell Spay BOP Attempts to line up RHR (A) in Torus Spray.
Reports that Torus Spray Valve RHR-MO-39A will not open.
Attempts to line up the other loop of RHR (B)..
Determines Spray valve failure.
Notifies CRS.
When directed attempts to line up RHR A in Drywell Spray.
Secures drywell fans.
Secures recirc pumps.
Attempts to Initiate Drywell spray as directed.
Determines RHR-MO-26 will not open.
Reports spray logic failure for RHR loop A (if not already reported).
Directs SO to manually open Spray Valves.
CRS Monitors Drywell and Torus parameters.
Determines PSP is exceeded.
Directs Emergency Depressurization..
Instructs operators to monitor RPV water level instruments because drywell temperature will exceed RPV saturation pressure.
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Instructor Station Instructions Scenario #3 Scenario No: 4 Event No. 5 Event
Description:
Steam leak in the Drywell Time Position Applicants Actions or Behavior BOP Opens six SRVs and emergency depressurizes the RPV.
Monitors RPV water level indication for boiling characteristics.
Controls RPV injection to maintain control of RPV water level.
RO Monitors RPV water level indication for boiling characteristics.
Controls RPV injection to maintain control of RPV water level.
CRS When notified by I & C that the Containment Spray permissive switch has been repaired, directs BOP to initiate Drywell Sprays using the B RHR Loop.
BOP When directed lines up RHR B in Drywell Spray.
Verifies drywell fans secured.
Verifies recirc pumps secured.
Initiates Drywell spray as directed.
CRS Classify the event as an ALERT IAW 5.7.1 section 2.2.1.
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Instructor Station Instructions Scenario #3 Scenario No: 4 Event No. 7 Event
Description:
RPV High Water Level Time Position Applicants Actions or Behavior RO Report RPV water level above +60 to +100 inches.
Determine MSIVs are not isolated.
CRS Direct manually closing the MSIVs.
RO Place all MSIV control switches to CLOSE.
Verify all MSIVs are closed.
Critical Tasks Sat Unsat Scenario #4 Page 210 of 18
Instructor Station Instructions Scenario #3 The Crew shall Emergency Depressurize when Torus pressure cannot be maintained below Pressure Suppression Pressure (PSP) or Drywell temperature cannot be maintained below 280EF.
The Crew shall manually close the MSIVs to prevent flooding the Main Steam Lines.
The Crew shall initiate Drywell Sprays following an Emergency Depressurization before elevated Drywell temperatures cause RPV water level reference leg boiling.
Page 211 of 18
Instructor Station Instructions Scenario #4 SIMULATOR SET-UP A. Initialize the simulator in IC 20, Full Power Operation (EOL).
- 1. Transfer to RUN.
- 2. Load batch file A:\nrc4
- 3. Balance all controllers.
- 4. Ensure PMIS IDTs are blank
- 5. Red tag the "A" CRD Pump
- 6. Clear all annunciators
- 7. Turn recorder power ON
- 8. Adjust GAFs B. Verify simulator conditions as follows:
- 1. Triggers Number File Name Description E1 None Default to False E2 None Default to False E3 None Default to False E4 None Default to False E5 None Default to False
- 2. Malfunctions Number Title Trigger TD Severity Ramp Initial SW01B Service 1 N/A N/A N/A N/A Water Pump Trip B Page 212 of 18
Instructor Station Instructions Scenario #4 Number Title Trigger TD Severity Ramp Initial FW13D Steam 2 N/A 100 N/A N/A Flow signal failure to RVLC Sys.
FW01A FRP Trip 3 N/A N/A N/A N/A RFP1A MS01D Steam leak 4 N/A 50 10:00 N/A Inside Primary Contain ment PC12 Primary 6 N/A 100 N/A N/A Contain ment Downc omer Leak FW28B RFPB A N/A N/A N/A N/A High level Trip Failure
- 3. Remotes Number Title Trigger Value Ramp irfRh29A RHR-MO- E5 de-energized N/A 39A power control
- 4. Overrides Page 213 of 18
Instructor Station Instructions Scenario #4 Instrume Tag Trigger TD Value Ramp nt Control zdicr A N/A STOP N/A Switc ds h for w CRD s3 Pump a[
A 1]
)
Control zdocr A N/A OFF N/A Switc ds h for w CRD s3 Pump a[
A 1]
green light Containm zdirh A N/A CLOSE N/A ent rs Spray w Outbo s9 ard a V[10-26A]
Containm zdirh A N/A NAR N/A ent rs Spray w Contr s1 ol 7 Reset/ b Norm/
Man 9-3-1D- RA: 5 N/A ON N/A 04 m RHR u A x MO- 1 39A 7c VAL 0 VE 1 OVL 1 D
Page 214 of 18
Instructor Station Instructions Scenario #4 Pre Events:
Allow the operators several minutes to review the panels and set up the controls and displays as they desire.
Event #1: Shift operating SW Pumps per 2.2.71 ROLE PLAY:
As SO at the B SW Pump report the pump is ready for operation.
ROLE PLAY:
If contacted after the pump swap report that the B SW Pump is ready operating normally.
Event #2: Power reduction ROLE PLAY:
Call the Control Room as the load dispatcher and notify the CRS that Cooper is scheduled for a load reduction to 680 MWe.
ROLE PLAY:
As Reactor Engineer if called report that power may be lowered using recirculation flow.
Event #3: Failure of D Main Steam Line Flow Transmitter ACTION:
When directed by the Chief Examiner Activate Trigger E1: Failure of D Main Steam Line Flow Transmitter.
ROLE PLAY:
As SO sent to the 903 level of the Reactor Building, report that the D Main Steam Flow Instrument (FT-51D) appears normal.
ROLE PLAY:
If contacted as I & C and directed to investigate the MS Flow instrument failure, report that you will get a technician and investigate.
Event #4: A Reactor Feedwater Pump trips ACTION:
When the CRS has complleted his Technical Specification call or when directed by the Chief Examiner Activate Trigger E2: Feedwater Pump A Trip.
Event #5: Steam leak in Drywell Page 215 of 18
Instructor Station Instructions Scenario #4 ACTION:
When the Crew has re-established RPV water level control or when directed by the Chief Examiner Activate Trigger E3: Steam Leak in the Drywell.
ACTION:
Adjust leak rate as necessary to obtain high drywell temperatures and PSP ROLE PLAY:
If called as an SO to investigate the RHR-MO-39A failure. Report that the valve actuator is very hot.
ROLE PLAY:
If asked as the SO to operate the valves manually, report they are bound and will not move.
ACTION:
After the Containment Spray Valve failures have been identified, Activate Trigger E6:
Downcomer Failure.
ACTION:
After the crew has emergency depressurized report as I & C that you have repaired the RHR B Containment Spray permissive switch.
ACTION:
When the following conditions are reached, place the simulator in FREEZE:
- 1. The MSIVs are closed.
- 2. The reactor has been depressurized.
- 3. Drywell temperature is below RPV saturation temperature.
- 4. When directed by the lead examiner.
Page 216 of 18
Instructor Station Instructions Scenario #4 Batch File
^NRC Scenario 4 trgset 1 "zloswswswpbcs(3) == 1" trgset 5 "zlorhrsws14a(2) == 1" imf sw01b (1 2:00) imf fw13d (2) 100 imf fw01a(3) imf ms01d (4) 50 10:00 imf pc12 (6) 100 imf fw28b irf rh29a(5)de-ener ior zdirhrsws9a close ior zdirhrsws17b nar ior RA:mux17c011 (5) on ior zdicrdsws3a[1]stop ior zlocrdsws3a[1]off Page 217 of 18
Turnover Information Scenario #4 Plant Status:
- 1. The plant is operating at approximately 100% power near the end of the operating cycle.
- 2. Rod Sequence Step: 1 Information:
Rod: 18-27 Notch: 26
- 3. Tech. Spec. Limitations in effect:
Day 1 of 30 day LCO (3.7.2) due to the B SW Pump being inoperable while its breaker was out for inspection. The breaker was removed from service 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.
- 4. Significant problems/abnormalities:
C "A" CRD Pump is tagged out. The speed increaser gearbox is being replaced after complete failure.
- 5. Evolutions/maintenance for the on-coming shift:
- When contacted, lower power level. Reactor Engineering has approved the power reduction (up to 150 MWe) using recirculation flow.
- Mechanics working on "A" CRD Pump.
- As soon as possible after assuming the shift, shift SW Pumps by starting the B SW Pump and securing the D SW Pump. Maintenance and an SO are standing by the pump and breaker.
Page 218 of 18