ML14091A213
| ML14091A213 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/13/2013 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-348/13-301, 50-364/13-301 | |
| Download: ML14091A213 (131) | |
Text
ILT-36 ADMIN JPM A.1.a RO Page 1 of 4 A.1.a Conduct of operations ADMIN RO TITLE: Evaluate Inoperable Plant Computer Based Alarm Functions EVALUATION LOCATION: X CLASS ROOM PROJECTED TIME: 25 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS:
- 1. Initiation of task may be in group setting, evaluation performed individually upon completion.
- 2. Provide student with HANDOUT pages and sign off applicable steps already completed.
Procedures provided will be:
- STP-37.0 version 25.1
- Picture of DRPI and group rod indication
- Picture of Yokagawa delta flux recorder.
- 3. Allow student time to review data.
- 4. Student will have access to the computer for material purposes. Access will be limited to the exam log in and NO internet access or lesson plan material can be accessed.
- 5. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Correctly assess and determine if STP-37.0 Acceptance Criteria is met.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Aaron Forsha Date: 2/13/2013 NRC Approval SEE NUREG 1021 FORM ES-301-3
HLT-36 ADMIN exam A.1.a - RO Page 2 of 5 CONDITIONS When I tell you to begin, you are to complete the Evaluate Inoperable Plant Computer Based Alarm Functions. The conditions under which this task is to be performed are:
- a. Unit 1 is Mode 1 and stable at 80% power.
- b. The Plant Computer became Inoperable twenty (20) minutes ago and is not expected to return for five (5) more hours.
- c. Another operator will record data for Appendix 3 of STP-37.0.
- d. Target Flux for 80% power is -2.00%
Your task is to complete the steps listed below of STP-37.0, POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE), using the data provided.
- 1. Step 5.1, to include step 5.1.2 and 5.1.3
- 2. Step 5.2 to include 5.2.1, 5.2.3 and 5.2.4.
- 3. Fill out the Acceptance Criteria table.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME
- 1. (step 5.1.2) Record Initial Rod Data Records Initial Data on S / U Appendix 1
- 2. (step 5.1.3) Determine if rod data meets Evaluates rod data and determines S / U acceptance criteria. that Acceptance Criteria is met.
- 3. (step 5.2.1) Record Initial AFD Data Records Initial Data on S / U Appendix 2
- 4. (step 5.2.3) Determine acceptance criteria of Using Figure 3 of the COLR AFD from COLR. determines AFD limits. S / U Tolerance allowed: -18 to -19.8
- 5. (step 5.2.3) Check Acceptance Criteria Determines channels 1, 2 and 3 are satisfied and initial Appendix 2 in the unacceptable region.
Channel 4 is in the acceptable S / U range.
Critical task is to determine that Acceptance criteria is NOT met
HLT-36 ADMIN exam A.1.a - RO Page 3 of 5 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 6. (step 5.2.4) Report Acceptance criteria is Reports to Shift Supervisor STP S / U NOT met to SS. results. (Cue Shift Supervisor acknowledges)
STOP TIME Terminate when Tech Spec requirements are provided.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number.
GENERAL
REFERENCES:
- 1. FNP-1-STP-37.0 Ver 25.1
- 2. COLR Unit 1 - Cycle 25
COLR, STP-37.0 Critical ELEMENT justification:
Part 1 KEY ACCEPTANCE CRITERIA Step 5.1.3 (Rods) MET NOT MET Step 5.2.3 (Flux) MET NOT MET STEP Evaluation
- 1. Not critical: This information is given in conditions.
- 2. Critical: This is the assigned task, results must be accurate.
- 3. Not critical: This information is given in conditions.
- 4. Critical: Accurately evaluating COLR is required to establish correct Acceptance Criteria.
- 5. Critical: This is the assigned task, results must be accurate.
HLT-36 ADMIN exam A.1.a - RO Page 4 of 5
- 6. Not critical: Notification step only.
COMMENTS:
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 5 of 11 (PLANT COMPUTER INOPERABLE) 1.0 Purpose To provide a means of determining and logging axial flux difference and rod position indication operability.
2.0 Acceptance Criteria 2.1 The indicated Axial Flux Difference (AFD) shall be maintained within the limits of the COLR.
2.2 All shutdown and control rod position indicator channels and the demand position indication system shall be operable and capable of determining the control rod positions within +/- 12 steps.
3.0 Initial Conditions 3.1 The version of this procedure has been verified to be the current version.
(OR 1-98-498) _____
3.2 This procedure has been verified to be the correct unit for the task.
(OR 1-98-498. _____
3.3 The plant is in Mode 1 or 2 _____
3.4 One of the following conditions requires performance of this test: _____
- The plant computer is inoperable, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Main Control Board Annunciator FF5 is inoperable, or in an alarm condition, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Main Control Board Annunciator FC4 is inoperable, or in an alarm condition, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
3.5 Record date/time condition entered requiring performance of this test.
Date Time 4.0 Precautions and Limitations 4.1 IF the plant computer goes out of service, THEN annunciators FF5 and FC4 are considered to have been inoperable. This procedure must be performed to completion.
KEY
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 6 of 11 (PLANT COMPUTER INOPERABLE) 5.0 Instructions NOTES If the plant computer and annunciator FF5 is returned to service within one hour step 5.1 is N/A.
FSAR Section 15.2.3.1 states If the rod deviation alarm is not operable, the operator is required to log the RCCA positions in a prescribed time sequence to confirm alignment.
Within one hour was picked as a conservative and realistic time frame to take this action.
If necessary, additional copies of Appendix 1, 2 or 3 may be attached, as required, until the computer is declared operable.
5.1 IF annunciator FF5, COMP ALARM ROD SEQ/DEV OR PR FLUX TILT, is inoperable either due to the computer being inoperable or due to some other cause, THEN perform the following:
5.1.1 Closely monitor individual rod position during control rod movement to ensure correct rod control system and control rod position indicator response. (NSAL-93-007) _____
5.1.2 Within one hour record current power level, bank demand position, and individual rod position, and every four (4) hours there after until the computer and the alarm are declared operable. (Appendix 1) _____
5.1.3 Check that Acceptance Criteria is met and initial Appendix 1 in the space provided. Inform Shift Supervisor of any readings not meeting Acceptance Criteria. _____
KEY
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 7 of 11 (PLANT COMPUTER INOPERABLE)
NOTES If the plant computer and annunciator FC4 is returned to service within one hour step 5.2 is N/A.
The ITS AFD surveillance frequency of seven days is considered adequate based on AFD being monitored by the computer and any deviation from requirements is alarmed. Within one hour to take initial compensatory actions is considered conservative and realistic. The old requirement to log AFD once per hour when the alarm is inoperable has been deleted.
5.2 IF annunciator FC4, DIFF FLUX DEV ALERT, is inoperable due to the computer being inoperable or to some other cause, AND power is greater than 50%, THEN record axial flux difference for each operable excore channel as follows, and inform Shift Supervisor of any readings not meeting Acceptance Criteria.
5.2.1 Record INITIAL DATA within one hour of the computer or the alarm being declared inoperable. (Appendix 2) _____
Student may 5.2.2 Every four hours record current target value and axial flux N/A or leave difference until the computer and annunciator FC4 are blank 5.2.2 declared operable. (Appendix 2) _____
since its not directed to be 5.2.3 Check Acceptance Criteria satisfied and initial Appendix 2 in completed space provided. _____
5.2.4 Inform Shift Supervisor of any readings not meeting Acceptance Criteria. _____
5.2.5 WHEN the computer and the alarm are declared operable, THEN record one set of OPERABLE DATA readings of target value and axial flux difference to channel check Delta I channels. (Appendix 2) _____
NOTE If the plant computer is returned to service within one hour step 5.3 is N/A.
5.3 IF the plant computer is inoperable, THEN record power level once per hour per Appendix 3. _____
KEY
UNIT 1 5/2/2012 14:40:31 KEY Farley Nuclear Plant POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE)
Procedure Number Ver FNP-1-STP-37.0 Page Number 8 of 11 25.1 Appendix 1 CAUTION While annunciator FF5 is inoperable, closely monitor individual rod position during control rod movement to ensure correct rod control system and control rod position indicator response. (NSAL-93-007)
Time Time Rx Power 80%
Rod No. 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other CB A Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D Demand [ ] [ ] [ ] 147 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A F2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A B10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A K14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A P6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A K2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A B6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A F14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A P10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B F4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B D10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B K12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B M6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B K4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B D6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B F12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B M10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C D4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C D12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C M12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C M4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C H6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C F8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
KEY CB C H10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C K8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
UNIT 1 5/2/2012 14:40:31 KEY Farley Nuclear Plant POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE)
Procedure Number Ver FNP-1-STP-37.0 Page Number 9 of 11 25.1 Appendix 1, continued Rod No. 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other CB D H2 [ ] [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D B8 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D H14 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D P8 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D F6 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D F10 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D K10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
150 CB D K6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A G3 [ ] [ ]
150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A C9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A J13 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A N7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A J3 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A C7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A G13 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A N9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B E5 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B E11 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B L11 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B L5 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B G7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B G9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B J9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B J7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
ACCEPTANCE CRITERIA All Shutdown and Control Rod position indicator channels and the demand position indication system are operable and capable of determining control rod positions within +/- 12 steps.
Acceptance Criteria met:
(initials)
Record data every four hours, per step 5.1.2 KEY
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 10 of 11 (PLANT COMPUTER INOPERABLE)
Appendix 2 Computer Inoperable Axial Flux Difference (%)
ACCEPTANCE CRITERIA Indicated AFD is within the limits specified in the COLR.
Date: today Time Target N-41 N-42 N-43 N-44 Acceptance Criteria met:
(initials)
INITIAL time -2.00%
DATA
-20.20% -21.03% -23.00% -16.48%
OPERABLE DATA KEY
- Record data every four hours, per step 5.2.2
This page is intentionally blank.
HLT-36 ADMIN exam A.1.a - RO Page 1 of 1 HANDOUT CONDITIONS When I tell you to begin, you are to complete the Evaluate Inoperable Plant Computer Based Alarm Functions. The conditions under which this task is to be performed are:
- a. Unit 1 is Mode 1 and stable at 80% power.
- b. The Plant Computer became Inoperable twenty (20) minutes ago and is not expected to return for five (5) more hours.
- c. Another operator will record data for Appendix 3 of STP-37.0.
- d. Target Flux for 80% power is -2.00%
Your task is to complete the steps listed below of STP-37.0, POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE), using the data provided.
- 1. Step 5.1, to include step 5.1.2 and 5.1.3
- 2. Step 5.2 to include 5.2.1, 5.2.3 and 5.2.4.
- 3. Fill out the Acceptance Criteria table.
Circle your answer below ACCEPTANCE CRITERIA Step 5.1.3 (Rods) MET NOT MET Step 5.2.3 (Flux) MET NOT MET
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 1 of 11 (PLANT COMPUTER INOPERABLE)
S A
F E
T Y
POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE)
R E
L A
T E
D PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL
Reference:
NONE Information: NONE Approved By: David L Reed (for) Effective Date: April 8, 2012 Operations Manager
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 2 of 11 (PLANT COMPUTER INOPERABLE)
SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-1-STP-37.0 SR 3.2.3.1 Bases, FSAR 15.2.3 TITLE MODE(S) REQUIRING TEST:
POWER DISTRIBUTION SURVEILLANCE 1, 2 (PLANT COMPUTER INOPERABLE)
TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)
PERFORMED BY / DATE/TIME (PRINT) (SIGNATURE)
COMPONENT OR TRAIN TESTED (if applicable)
[ ] ENTIRE STP PERFORMED [ ] FOR SURVEILLANCE CREDIT
[ ] PARTIAL STP PERFORMED [ ] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL:
TEST COMPLETED: [ ] Satisfactory [ ] Unsatisfactory
[ ] The following deficiencies occurred:
[ ] Corrective action taken or initiated:
SHIFT SUPERVISOR/ SHIFT SUPPORT SUPERVISOR REVIEW
[ ] Procedure properly completed and satisfactory per step 9.1 of FNP-0-AP-5.0.
[ ] Comments:
REVIEWED BY / DATE (PRINT) (SIGNATURE)
ENGINEERING SUPPORT SCREENED BY DATE GROUP SCREENING (IF APPLICABLE)
[ ] Comments:
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 3 of 11 (PLANT COMPUTER INOPERABLE)
Procedure Version Description Version Number Version Description 25.0 Updated procedure to requirements of NMP-AP-002, SNC FLEET PROCEDURES WRITERS GUIDE.
25.1 Updated ARO Rod Height from 227 to 230 for Fuel Cycle 25.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 4 of 11 (PLANT COMPUTER INOPERABLE)
Table of Contents Page 1.0 Purpose .........................................................................................................................................5 2.0 Acceptance Criteria .......................................................................................................................5 3.0 Initial Conditions ............................................................................................................................5 4.0 Precautions and Limitations ..........................................................................................................5 5.0 Instructions ....................................................................................................................................6 Appendix 1 ....................................................................................................................................8 Appendix 2 ..................................................................................................................................10 Appendix 3 ..................................................................................................................................11
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 5 of 11 (PLANT COMPUTER INOPERABLE) 1.0 Purpose To provide a means of determining and logging axial flux difference and rod position indication operability.
2.0 Acceptance Criteria 2.1 The indicated Axial Flux Difference (AFD) shall be maintained within the limits of the COLR.
2.2 All shutdown and control rod position indicator channels and the demand position indication system shall be operable and capable of determining the control rod positions within +/- 12 steps.
3.0 Initial Conditions 3.1 The version of this procedure has been verified to be the current version.
(OR 1-98-498) _____
3.2 This procedure has been verified to be the correct unit for the task.
(OR 1-98-498. _____
3.3 The plant is in Mode 1 or 2 _____
3.4 One of the following conditions requires performance of this test: _____
- The plant computer is inoperable, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Main Control Board Annunciator FF5 is inoperable, or in an alarm condition, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Main Control Board Annunciator FC4 is inoperable, or in an alarm condition, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
3.5 Record date/time condition entered requiring performance of this test.
Date Time 4.0 Precautions and Limitations 4.1 IF the plant computer goes out of service, THEN annunciators FF5 and FC4 are considered to have been inoperable. This procedure must be performed to completion.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 6 of 11 (PLANT COMPUTER INOPERABLE) 5.0 Instructions NOTES If the plant computer and annunciator FF5 is returned to service within one hour step 5.1 is N/A.
FSAR Section 15.2.3.1 states If the rod deviation alarm is not operable, the operator is required to log the RCCA positions in a prescribed time sequence to confirm alignment.
Within one hour was picked as a conservative and realistic time frame to take this action.
If necessary, additional copies of Appendix 1, 2 or 3 may be attached, as required, until the computer is declared operable.
5.1 IF annunciator FF5, COMP ALARM ROD SEQ/DEV OR PR FLUX TILT, is inoperable either due to the computer being inoperable or due to some other cause, THEN perform the following:
5.1.1 Closely monitor individual rod position during control rod movement to ensure correct rod control system and control rod position indicator response. (NSAL-93-007) _____
5.1.2 Within one hour record current power level, bank demand position, and individual rod position, and every four (4) hours there after until the computer and the alarm are declared operable. (Appendix 1) _____
5.1.3 Check that Acceptance Criteria is met and initial Appendix 1 in the space provided. Inform Shift Supervisor of any readings not meeting Acceptance Criteria. _____
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 7 of 11 (PLANT COMPUTER INOPERABLE)
NOTES If the plant computer and annunciator FC4 is returned to service within one hour step 5.2 is N/A.
The ITS AFD surveillance frequency of seven days is considered adequate based on AFD being monitored by the computer and any deviation from requirements is alarmed. Within one hour to take initial compensatory actions is considered conservative and realistic. The old requirement to log AFD once per hour when the alarm is inoperable has been deleted.
5.2 IF annunciator FC4, DIFF FLUX DEV ALERT, is inoperable due to the computer being inoperable or to some other cause, AND power is greater than 50%, THEN record axial flux difference for each operable excore channel as follows, and inform Shift Supervisor of any readings not meeting Acceptance Criteria.
5.2.1 Record INITIAL DATA within one hour of the computer or the alarm being declared inoperable. (Appendix 2) _____
5.2.2 Every four hours record current target value and axial flux difference until the computer and annunciator FC4 are declared operable. (Appendix 2) _____
5.2.3 Check Acceptance Criteria satisfied and initial Appendix 2 in space provided. _____
5.2.4 Inform Shift Supervisor of any readings not meeting Acceptance Criteria. _____
5.2.5 WHEN the computer and the alarm are declared operable, THEN record one set of OPERABLE DATA readings of target value and axial flux difference to channel check Delta I channels. (Appendix 2) _____
NOTE If the plant computer is returned to service within one hour step 5.3 is N/A.
5.3 IF the plant computer is inoperable, THEN record power level once per hour per Appendix 3. _____
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 Page Number 5/2/2012 14:40:31 POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE) 8 of 11 Appendix 1 CAUTION While annunciator FF5 is inoperable, closely monitor individual rod position during control rod movement to ensure correct rod control system and control rod position indicator response. (NSAL-93-007)
Time Rx Power Rod No. 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other CB A Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A F2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A B10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A K14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A P6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A K2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A B6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A F14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A P10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B F4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B D10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B K12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B M6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B K4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B D6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B F12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B M10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C D4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C D12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C M12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C M4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C H6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C F8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C H10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C K8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 Page Number 5/2/2012 14:40:31 POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE) 9 of 11 Appendix 1, continued Rod No. 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other CB D H2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D B8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D H14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D P8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D F6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D F10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D K10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D K6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A G3 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A C9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A J13 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A N7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A J3 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A C7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A G13 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A N9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B E5 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B E11 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B L11 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B L5 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B G7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B G9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B J9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B J7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
ACCEPTANCE CRITERIA All Shutdown and Control Rod position indicator channels and the demand position indication system are operable and capable of determining control rod positions within +/- 12 steps.
Acceptance Criteria met:
(initials)
Record data every four hours, per step 5.1.2
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 10 of 11 (PLANT COMPUTER INOPERABLE)
Appendix 2 Computer Inoperable Axial Flux Difference (%)
ACCEPTANCE CRITERIA Indicated AFD is within the limits specified in the COLR.
Date:
Time Target N-41 N-42 N-43 N-44 Acceptance Criteria met:
(initials)
INITIAL DATA OPERABLE DATA
- Record data every four hours, per step 5.2.2
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 11 of 11 (PLANT COMPUTER INOPERABLE)
Appendix 3 Computer Inoperable Reactor Power (%)
Date:
Time Reactor Power (%)
Record reactor power level hourly, per step 5.3
-20.20 -21.03 -23.00 -16.48 CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 25 FEBRUARY 2012 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110
(-12, 100) (+9, 100) 100 UNACCEPTABLE UNACCEPTABLE 90 OPERATION OPERATION Power (% of RATED THERMAL POWER) 80 ACCEPTABLE 70 OPERATION 60 50
(-30, 50) (+24, 50) 40 30 20 10 0
-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Axial Flux Difference (Delta I) %
Page 11 of 12
ILT-36 ADMIN JPM A.1.a SRO Page 1 of 4 A.1.a Conduct of operations ADMIN SRO TITLE: Evaluate Inoperable Plant Computer Based Alarm Functions EVALUATION LOCATION: X CLASS ROOM PROJECTED TIME: 25 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS:
- 1. Initiation of task may be in group setting, evaluation performed individually upon completion.
- 2. Provide student with HANDOUT pages and sign off applicable steps already completed.
Procedures provided will be:
- STP-37.0 version 25.1
- Picture of DRPI and group rod indication
- Picture of Yokagawa delta flux recorder.
- 3. Allow student time to review data.
- 4. Student will have access to the computer for material purposes. Access will be limited to the exam log in and NO internet access or lesson plan material can be accessed.
- 5. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Correctly assess and determine if STP-37.0 Acceptance Criteria is met.
- Correctly assess Tech Spec requirements.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Aaron Forsha Date: 2/13/2013 NRC Approval SEE NUREG 1021 FORM ES-301-3
HLT-36 ADMIN exam A.1.a - SRO Page 2 of 6 CONDITIONS When I tell you to begin, you are to Evaluate Inoperable Plant Computer Based Alarm Functions.
The conditions under which this task is to be performed are:
- a. Unit 1 is Mode 1 and stable at 80% power.
- b. The Plant Computer became Inoperable twenty (20) minutes ago and is not expected to return for five (5) more hours.
- c. N-44 has been declared INOPERABLE.
- d. Another operator will record data for Appendix 3 of STP-37.0.
- e. Target Flux for 80% power is -2.00%
Your task is to complete the steps listed below of STP-37.0, POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE), using the data provided.
- 1. Step 5.1, to include step 5.1.2 and 5.1.3
- 2. Step 5.2 to include 5.2.1, 5.2.3 and 5.2.4.
- 3. Fill out the Acceptance Criteria table.
INITIATING CUE: You may begin.
Part 2 - administer this portion of the JPM after completion of the above task.
JPM DIRECTIONS:
- 1. Provide student with Part 2 HANDOUT and Tech Spec 3.2.3.
CONDITIONS Based on your previously provided conditions, evaluate Tech Spec Implications (if any).
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME
- 1. (step 5.1.2) Record Initial Rod Data Records Initial Data on S / U Appendix 1
- 2. (step 5.1.3) Determine if rod data meets Evaluates rod data and determines S / U acceptance criteria. that Acceptance Criteria is met.
- 3. (step 5.2.1) Record Initial AFD Data Records Initial Data on S / U Appendix 2
HLT-36 ADMIN exam A.1.a - SRO Page 3 of 6 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 4. (step 5.2.3) Determine acceptance criteria of Using Figure 3 of the COLR S / U AFD from COLR. determines AFD limits.
Tolerance allowed: -18 to -19.8
- 5. (step 5.2.3) Check Acceptance Criteria Determines channels 3 and 4 are in S / U satisfied and initial Appendix 2 the unacceptable region.
Acceptance criteria is NOT met
- 6. (step 5.2.4) Report Acceptance criteria is Reports to Shift Supervisor STP S / U NOT met to SS. results.
Part 2 - administer this portion of the JPM after completion of the above task.
- 7. Determine Tech Spec entry requirements Evaluates Tech Specs and determine S / U Entry into T.S. 3.2.3 AXIAL FLUX DIFFERENCE Condition A is NOT required.
The reason the LCO is NOT required to be entered is due to N-44 is INOPERABLE and N-43 is outside the flux region, however N-41 & 42 are within the flux limits and per the NOTE The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.
STOP TIME Terminate when Tech Spec requirements are provided.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number.
Part 1 KEY ACCEPTANCE CRITERIA Step 5.1.3 (Rods) MET NOT MET Step 5.2.3 (Flux) MET NOT MET
HLT-36 ADMIN exam A.1.a - SRO Page 4 of 6 Part 2 KEY Tech Spec Evaluation YES NO Condition A is required Condition A is not required GENERAL
REFERENCES:
- 1. FNP-1-STP-37.0 Ver 25.1
- 2. COLR Unit 1 - Cycle 25
Tech Specs, COLR, STP-37.0 Critical ELEMENT justification:
STEP Evaluation
- 1. Not critical: This information is given in conditions.
- 2. Critical: This is the assigned task, results must be accurate.
- 3. Not critical: This information is given in conditions.
- 4. Critical: Accurately evaluating COLR is required to establish correct Acceptance Criteria.
- 5. Critical: This is the assigned task, results must be accurate.
- 6. Not critical: Notification step only.
- 7. Critical: This is the assigned task, results must be accurate. This is required since if t LCO was entered an unnecessary ramp to less than 50% power would be initiated.
COMMENTS:
ILT-36 ADMIN JPM A.1.a SRO Page 1 of 1 Part 2 HANDOUT CONDITIONS Based on your previously provided conditions, evaluate Tech Spec Implications (if any).
Circle your answer below.
Tech Spec Evaluation YES NO Condition A is required Condition A is not required
AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits specified in the COLR.
NOTE-----------------------------------------------
The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.
APPLICABILITY: MODE 1 with THERMAL POWER 50% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.1 Reduce THERMAL 30 minutes POWER to < 50% RTP.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore In accordance with channel. the Surveillance Frequency Control Program Farley Units 1 and 2 3.2.3-1 Amendment No. 185 (Unit 1)
Amendment No. 180 (Unit 2)
This page is intentionally blank.
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 5 of 11 (PLANT COMPUTER INOPERABLE) 1.0 Purpose To provide a means of determining and logging axial flux difference and rod position indication operability.
2.0 Acceptance Criteria 2.1 The indicated Axial Flux Difference (AFD) shall be maintained within the limits of the COLR.
2.2 All shutdown and control rod position indicator channels and the demand position indication system shall be operable and capable of determining the control rod positions within +/- 12 steps.
3.0 Initial Conditions 3.1 The version of this procedure has been verified to be the current version.
(OR 1-98-498) _____
3.2 This procedure has been verified to be the correct unit for the task.
(OR 1-98-498. _____
3.3 The plant is in Mode 1 or 2 _____
3.4 One of the following conditions requires performance of this test: _____
- The plant computer is inoperable, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Main Control Board Annunciator FF5 is inoperable, or in an alarm condition, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Main Control Board Annunciator FC4 is inoperable, or in an alarm condition, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
3.5 Record date/time condition entered requiring performance of this test.
Date Time 4.0 Precautions and Limitations 4.1 IF the plant computer goes out of service, THEN annunciators FF5 and FC4 are considered to have been inoperable. This procedure must be performed to completion.
KEY
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 6 of 11 (PLANT COMPUTER INOPERABLE) 5.0 Instructions NOTES If the plant computer and annunciator FF5 is returned to service within one hour step 5.1 is N/A.
FSAR Section 15.2.3.1 states If the rod deviation alarm is not operable, the operator is required to log the RCCA positions in a prescribed time sequence to confirm alignment.
Within one hour was picked as a conservative and realistic time frame to take this action.
If necessary, additional copies of Appendix 1, 2 or 3 may be attached, as required, until the computer is declared operable.
5.1 IF annunciator FF5, COMP ALARM ROD SEQ/DEV OR PR FLUX TILT, is inoperable either due to the computer being inoperable or due to some other cause, THEN perform the following:
5.1.1 Closely monitor individual rod position during control rod movement to ensure correct rod control system and control rod position indicator response. (NSAL-93-007) _____
5.1.2 Within one hour record current power level, bank demand position, and individual rod position, and every four (4) hours there after until the computer and the alarm are declared operable. (Appendix 1) _____
5.1.3 Check that Acceptance Criteria is met and initial Appendix 1 in the space provided. Inform Shift Supervisor of any readings not meeting Acceptance Criteria. _____
KEY
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 7 of 11 (PLANT COMPUTER INOPERABLE)
NOTES If the plant computer and annunciator FC4 is returned to service within one hour step 5.2 is N/A.
The ITS AFD surveillance frequency of seven days is considered adequate based on AFD being monitored by the computer and any deviation from requirements is alarmed. Within one hour to take initial compensatory actions is considered conservative and realistic. The old requirement to log AFD once per hour when the alarm is inoperable has been deleted.
5.2 IF annunciator FC4, DIFF FLUX DEV ALERT, is inoperable due to the computer being inoperable or to some other cause, AND power is greater than 50%, THEN record axial flux difference for each operable excore channel as follows, and inform Shift Supervisor of any readings not meeting Acceptance Criteria.
5.2.1 Record INITIAL DATA within one hour of the computer or the Student may alarm being declared inoperable. (Appendix 2) _____
N/A or leave 5.2.2 Every four hours record current target value and axial flux blank 5.2.2 difference until the computer and annunciator FC4 are since its not declared operable. (Appendix 2) _____
directed to be 5.2.3 Check Acceptance Criteria satisfied and initial Appendix 2 in completed space provided. _____
5.2.4 Inform Shift Supervisor of any readings not meeting Acceptance Criteria. _____
5.2.5 WHEN the computer and the alarm are declared operable, THEN record one set of OPERABLE DATA readings of target value and axial flux difference to channel check Delta I channels. (Appendix 2) _____
NOTE If the plant computer is returned to service within one hour step 5.3 is N/A.
5.3 IF the plant computer is inoperable, THEN record power level once per hour per Appendix 3. _____
KEY
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 Page Number 25.1 5/2/2012 14:40:31 POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE) 8 of 11 Appendix 1 CAUTION While annunciator FF5 is inoperable, closely monitor individual rod position during control rod movement to ensure correct rod control system and control rod position indicator response. (NSAL-93-007)
Time Time Rx Power 80%
Rod No. 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other CB A Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D Demand [ ] [ ] [ ] 147 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A F2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A B10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A K14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A P6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A K2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A B6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A F14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A P10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B F4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B D10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B K12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B M6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B K4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B D6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B F12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B M10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C D4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C D12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C M12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C M4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C H6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C F8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
KEY CB C H10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C K8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 Page Number 25.1 5/2/2012 14:40:31 POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE) 9 of 11 Appendix 1, continued Rod No. 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other CB D H2 [ ] [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D B8 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D H14 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D P8 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D F6 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D F10 [ ] [ ] 150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D K10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
150 CB D K6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A G3 [ ] [ ]
150 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A C9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A J13 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A N7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A J3 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A C7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A G13 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A N9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B E5 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B E11 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B L11 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B L5 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B G7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B G9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B J9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B J7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
ACCEPTANCE CRITERIA All Shutdown and Control Rod position indicator channels and the demand position indication system are operable and capable of determining control rod positions within +/- 12 steps.
Acceptance Criteria met:
(initials)
Record data every four hours, per step 5.1.2 KEY
UNIT 1 KEY Farley Nuclear Plant Procedure Number Ver FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 10 of 11 (PLANT COMPUTER INOPERABLE)
Appendix 2 Computer Inoperable Axial Flux Difference (%)
ACCEPTANCE CRITERIA Indicated AFD is within the limits specified in the COLR.
Date: today Time Target N-41 N-42 N-43 N-44 Acceptance Criteria met:
(initials)
INITIAL time -2.00%
DATA
-15.20% -15.03% -23.00% 30.00%
OPERABLE DATA KEY
- Record data every four hours, per step 5.2.2
This page is intentionally blank.
ILT-36 ADMIN JPM A.1.a SRO Page 1 of 1 HANDOUT CONDITIONS When I tell you to begin, you are to Evaluate Inoperable Plant Computer Based Alarm Functions.
The conditions under which this task is to be performed are:
- a. Unit 1 is Mode 1 and stable at 80% power.
- b. The Plant Computer became Inoperable twenty (20) minutes ago and is not expected to return for five (5) more hours.
- c. N-44 has been declared INOPERABLE.
- d. Another operator will record data for Appendix 3 of STP-37.0.
- e. Target Flux for 80% power is -2.00%
Your task is to complete the steps listed below of STP-37.0, POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE), using the data provided.
- 1. Step 5.1, to include step 5.1.2 and 5.1.3
- 2. Step 5.2 to include 5.2.1, 5.2.3 and 5.2.4.
- 3. Fill out the Acceptance Criteria table.
Circle your answer below ACCEPTANCE CRITERIA Step 5.1.3 (Rods) MET NOT MET Step 5.2.3 (Flux) MET NOT MET
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 1 of 11 (PLANT COMPUTER INOPERABLE)
S A
F E
T Y
POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE)
R E
L A
T E
D PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL
Reference:
NONE Information: NONE Approved By: David L Reed (for) Effective Date: April 8, 2012 Operations Manager
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 2 of 11 (PLANT COMPUTER INOPERABLE)
SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-1-STP-37.0 SR 3.2.3.1 Bases, FSAR 15.2.3 TITLE MODE(S) REQUIRING TEST:
POWER DISTRIBUTION SURVEILLANCE 1, 2 (PLANT COMPUTER INOPERABLE)
TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)
PERFORMED BY / DATE/TIME (PRINT) (SIGNATURE)
COMPONENT OR TRAIN TESTED (if applicable)
[ ] ENTIRE STP PERFORMED [ ] FOR SURVEILLANCE CREDIT
[ ] PARTIAL STP PERFORMED [ ] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL:
TEST COMPLETED: [ ] Satisfactory [ ] Unsatisfactory
[ ] The following deficiencies occurred:
[ ] Corrective action taken or initiated:
SHIFT SUPERVISOR/ SHIFT SUPPORT SUPERVISOR REVIEW
[ ] Procedure properly completed and satisfactory per step 9.1 of FNP-0-AP-5.0.
[ ] Comments:
REVIEWED BY / DATE (PRINT) (SIGNATURE)
ENGINEERING SUPPORT SCREENED BY DATE GROUP SCREENING (IF APPLICABLE)
[ ] Comments:
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 3 of 11 (PLANT COMPUTER INOPERABLE)
Procedure Version Description Version Number Version Description 25.0 Updated procedure to requirements of NMP-AP-002, SNC FLEET PROCEDURES WRITERS GUIDE.
25.1 Updated ARO Rod Height from 227 to 230 for Fuel Cycle 25.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 4 of 11 (PLANT COMPUTER INOPERABLE)
Table of Contents Page 1.0 Purpose .........................................................................................................................................5 2.0 Acceptance Criteria .......................................................................................................................5 3.0 Initial Conditions ............................................................................................................................5 4.0 Precautions and Limitations ..........................................................................................................5 5.0 Instructions ....................................................................................................................................6 Appendix 1 ....................................................................................................................................8 Appendix 2 ..................................................................................................................................10 Appendix 3 ..................................................................................................................................11
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 5 of 11 (PLANT COMPUTER INOPERABLE) 1.0 Purpose To provide a means of determining and logging axial flux difference and rod position indication operability.
2.0 Acceptance Criteria 2.1 The indicated Axial Flux Difference (AFD) shall be maintained within the limits of the COLR.
2.2 All shutdown and control rod position indicator channels and the demand position indication system shall be operable and capable of determining the control rod positions within +/- 12 steps.
3.0 Initial Conditions 3.1 The version of this procedure has been verified to be the current version.
(OR 1-98-498) _____
3.2 This procedure has been verified to be the correct unit for the task.
(OR 1-98-498. _____
3.3 The plant is in Mode 1 or 2 _____
3.4 One of the following conditions requires performance of this test: _____
- The plant computer is inoperable, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Main Control Board Annunciator FF5 is inoperable, or in an alarm condition, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Main Control Board Annunciator FC4 is inoperable, or in an alarm condition, and the inoperability is approaching 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
3.5 Record date/time condition entered requiring performance of this test.
Date Time 4.0 Precautions and Limitations 4.1 IF the plant computer goes out of service, THEN annunciators FF5 and FC4 are considered to have been inoperable. This procedure must be performed to completion.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 6 of 11 (PLANT COMPUTER INOPERABLE) 5.0 Instructions NOTES If the plant computer and annunciator FF5 is returned to service within one hour step 5.1 is N/A.
FSAR Section 15.2.3.1 states If the rod deviation alarm is not operable, the operator is required to log the RCCA positions in a prescribed time sequence to confirm alignment.
Within one hour was picked as a conservative and realistic time frame to take this action.
If necessary, additional copies of Appendix 1, 2 or 3 may be attached, as required, until the computer is declared operable.
5.1 IF annunciator FF5, COMP ALARM ROD SEQ/DEV OR PR FLUX TILT, is inoperable either due to the computer being inoperable or due to some other cause, THEN perform the following:
5.1.1 Closely monitor individual rod position during control rod movement to ensure correct rod control system and control rod position indicator response. (NSAL-93-007) _____
5.1.2 Within one hour record current power level, bank demand position, and individual rod position, and every four (4) hours there after until the computer and the alarm are declared operable. (Appendix 1) _____
5.1.3 Check that Acceptance Criteria is met and initial Appendix 1 in the space provided. Inform Shift Supervisor of any readings not meeting Acceptance Criteria. _____
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 7 of 11 (PLANT COMPUTER INOPERABLE)
NOTES If the plant computer and annunciator FC4 is returned to service within one hour step 5.2 is N/A.
The ITS AFD surveillance frequency of seven days is considered adequate based on AFD being monitored by the computer and any deviation from requirements is alarmed. Within one hour to take initial compensatory actions is considered conservative and realistic. The old requirement to log AFD once per hour when the alarm is inoperable has been deleted.
5.2 IF annunciator FC4, DIFF FLUX DEV ALERT, is inoperable due to the computer being inoperable or to some other cause, AND power is greater than 50%, THEN record axial flux difference for each operable excore channel as follows, and inform Shift Supervisor of any readings not meeting Acceptance Criteria.
5.2.1 Record INITIAL DATA within one hour of the computer or the alarm being declared inoperable. (Appendix 2) _____
5.2.2 Every four hours record current target value and axial flux difference until the computer and annunciator FC4 are declared operable. (Appendix 2) _____
5.2.3 Check Acceptance Criteria satisfied and initial Appendix 2 in space provided. _____
5.2.4 Inform Shift Supervisor of any readings not meeting Acceptance Criteria. _____
5.2.5 WHEN the computer and the alarm are declared operable, THEN record one set of OPERABLE DATA readings of target value and axial flux difference to channel check Delta I channels. (Appendix 2) _____
NOTE If the plant computer is returned to service within one hour step 5.3 is N/A.
5.3 IF the plant computer is inoperable, THEN record power level once per hour per Appendix 3. _____
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 Page Number 5/2/2012 14:40:31 POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE) 8 of 11 Appendix 1 CAUTION While annunciator FF5 is inoperable, closely monitor individual rod position during control rod movement to ensure correct rod control system and control rod position indicator response. (NSAL-93-007)
Time Rx Power Rod No. 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other CB A Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B Demand [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A F2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A B10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A K14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A P6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A K2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A B6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A F14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB A P10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B F4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B D10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B K12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B M6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B K4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B D6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B F12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB B M10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C D4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C D12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C M12 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C M4 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C H6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C F8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C H10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB C K8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 Page Number 5/2/2012 14:40:31 POWER DISTRIBUTION SURVEILLANCE (PLANT COMPUTER INOPERABLE) 9 of 11 Appendix 1, continued Rod No. 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other 222 228 230 Other CB D H2 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D B8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D H14 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D P8 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D F6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D F10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D K10 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
CB D K6 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A G3 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A C9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A J13 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A N7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A J3 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A C7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A G13 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D A N9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B E5 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B E11 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B L11 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B L5 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B G7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B G9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B J9 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
S/D B J7 [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]
ACCEPTANCE CRITERIA All Shutdown and Control Rod position indicator channels and the demand position indication system are operable and capable of determining control rod positions within +/- 12 steps.
Acceptance Criteria met:
(initials)
Record data every four hours, per step 5.1.2
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 10 of 11 (PLANT COMPUTER INOPERABLE)
Appendix 2 Computer Inoperable Axial Flux Difference (%)
ACCEPTANCE CRITERIA Indicated AFD is within the limits specified in the COLR.
Date:
Time Target N-41 N-42 N-43 N-44 Acceptance Criteria met:
(initials)
INITIAL DATA OPERABLE DATA
- Record data every four hours, per step 5.2.2
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-37.0 25.1 POWER DISTRIBUTION SURVEILLANCE Page Number 5/2/2012 14:40:31 11 of 11 (PLANT COMPUTER INOPERABLE)
Appendix 3 Computer Inoperable Reactor Power (%)
Date:
Time Reactor Power (%)
Record reactor power level hourly, per step 5.3
-15.20 -15.03 -23.00 30.00 CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 25 FEBRUARY 2012 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110
(-12, 100) (+9, 100) 100 UNACCEPTABLE UNACCEPTABLE 90 OPERATION OPERATION Power (% of RATED THERMAL POWER) 80 ACCEPTABLE 70 OPERATION 60 50
(-30, 50) (+24, 50) 40 30 20 10 0
-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Axial Flux Difference (Delta I) %
Page 11 of 12
HLT-36 ADMIN JPM A.1.b Page 1 of 5 A.1.b Conduct of operations - SRO + RO TITLE: Determine The Minimum Amount And Duration Required For An RCS Boration EVALUATION LOCATION: X CLASS ROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS:
- 1. This task can be conducted individually or in a group setting in which all the necessary references are available.
- 2. Provide student with HANDOUT pages and sign off applicable steps already completed.
- 3. Allow student time to review data.
- 4. Student will have access to the computer for material purposes. Access will be limited to the exam log in and NO internet access or lesson plan material can be accessed.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Determine minimum volume of required boration.
- Determine time required to achieve the boration requirement.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Aaron Forsha Date: 2/6/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3
HLT-36 ADMIN JPM A.1.b Page 2 of 5 CONDITIONS When I tell you to begin, you are to DETERMINE THE MINIMUM AMOUNT AND DURATION REQUIRED FOR AN RCS BORATION.
The conditions under which this task is to be performed are:
- a. Unit 1 is in Mode 3, 13,500 MWD/MTU, On-service BAT 7350 ppm.
- b. All RCPs are running.
- d. While warming up Main Steam lines in preparation for opening MSIVs, an inadvertent uncontrolled RCS cooldown occurred.
- e. Tavg is 501ºF on TC-4601, TC-4602 & TC-4603D and stable.
- f. Tcold is 501ºF on TR-410 Loop A, B, & C and stable.
- g. AOP-27.0, Emergency Boration, through step 8, has been completed.
- h. Emergency boration flow is 95 gpm.
You have been directed by the Shift Supervisor to evaluate AOP-27.0 EMERGENCY BORATION, Step 9 using the data provided and:
- 1. Determine the minimum amount of RCS boration required.
- 2. Determine minimum time required to complete the boration.
- 3. Record answers in table below.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME
- 1. (step 9.1) Determines reactor is not critical. Determines reactor is not critical. S / U
- 2. (step 9.2) Determines Tavg is less than Determines Tavg value is not used S / U 525ºF. because RCP are not running and Tcold is less than 525ºF.
Tave is 501°F.
- 3. (step 9.3) Determines from table that Determines minimum gal per ºF S / U 55gals/ºF<525ºF is the amount of boration for the existing Boron for the existing Boron concentration per concentration: 55gals/ºF<525ºF.
AOP-27 Table.
No tolerance allowed on table value
- 4. Determines number of degrees Tavg is Determines Tavg is 24ºF below S / U below 525ºF. 525ºF.
525 501 = 24º F No tolerance allowed on calculation
HLT-36 ADMIN JPM A.1.b Page 3 of 5 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 5. Determines total boration required for RCS Determines total boration required S / U Tavg 24º<525º . for RCS Tavg 24º<525º is 1,320 gals.
55 gals (24º F ) = 1,320 gals No tolerance allowed on
ºF calculation
- 6. Determines duration of emergency boration Determines duration of emergency at current flowrate. boration at current flowrate. S / U 1320 gals Tolerance 13.8-14.0 minutes due
= 13.895 min to potential differences in 95 gals rounding & significant digits.
min This converts to the tolerance of 13.8 - 14 minutes 00 secs.
(13 min 48 sec-14 min)
STOP TIME Terminate when minimum amount and duration of emergency boration have been determined.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number.
GENERAL
REFERENCES:
- 1. FNP-1-AOP-27.0 Rev. 16
- 2. Core Phyics Curves 61 Rev. 33, 61A Pgs 1 & 2 Rev. 21
- 3. K/A: G2.1.7 RO 4.4 SRO 4.7 G2.1.25 RO 3.9 SRO 4.2 G2.1.20 RO 4.6 SRO 4.6 GENERAL TOOLS AND EQUIPMENT:
Provide: FNP-1-AOP-27.0 Calculator Critical ELEMENT justification:
STEP Evaluation
- 1. Not critical: This information is given in conditions.
HLT-36 ADMIN JPM A.1.b Page 4 of 5
- 2. Not critical: Calculation only.
- 3. Not critical: Calculation only.
- 4. Not critical: Calculation only.
- 5. Critical: Answer is the assigned task.
- 6. Critical: Answer is the assigned task.
COMMENTS:
KEY Minimum RCS Boration Required 1320Gallons Time required to complete required 13.8 (13 MINUTES 48 SECONDS) TO Boration 14 Minutes
This page is intentionally blank.
HLT-36 ADMIN JPM A.1.b Page 1 of 1 HANDOUT When I tell you to begin, you are to DETERMINE THE MINIMUM AMOUNT AND DURATION REQUIRED FOR AN RCS BORATION.
The conditions under which this task is to be performed are:
- a. Unit 1 is in Mode 3, 13,500 MWD/MTU, On-service BAT 7350 ppm.
- b. All RCPs are running.
- d. While warming up Main Steam lines in preparation for opening MSIVs, an inadvertent uncontrolled RCS cooldown occurred.
- e. Tavg is 501ºF on TC-4601, TC-4602 & TC-4603D and stable.
- f. Tcold is 501ºF on TR-410 Loop A, B, & C and stable.
- g. AOP-27.0, Emergency Boration, through step 8, has been completed.
- h. Emergency boration flow is 95 gpm.
You have been directed by the Shift Supervisor to evaluate AOP-27.0 EMERGENCY BORATION, Step 9 using the data provided and:
- 1. Determine the minimum amount of RCS boration required.
- 2. Determine minimum time required to complete the boration.
- 3. Record answers in table below.
Provide your answer below Minimum RCS Boration Amount Required Time required to complete required Boration
07/13/10 8:07:19 UNIT 1 FNP-1-AOP-27.0 November 20, 2009 Version 16.0 FARLEY NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE FNP-1-AOP-27.0 S
A F
E T
Y EMERGENCY BORATION R
E L
A T
E D
PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Information Use Approved:
Jim L Hunter (for)
Operations Manager Date Issued: November 24, 2009
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Table of Contents PROCEDURE CONTAINS NUMBER OF PAGES Body 9 Attachment 1 3
[] A
- A A 1 Page 1 of 1
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 A. Purpose This procedure provides actions to emergency borate the RCS when a reactor trip is not required.
This procedure is applicable in Modes 1, 2, 3, 4, 5 and 6.
B. Symptoms or Entry Conditions I. This procedure is entered when emergency boration is required by any of the following:
- a. Shutdown margin is determined to be less than required by Technical Specifications {or the TRM}
- b. Unexplained or uncontrolled reactivity insertion
- c. Actuation of CONT ROD BANK POSITION LO-LO annunciator FE2
- d. Inadvertent cooldown below 525°F with critical boron concentration established 1 Page 1 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained 1°
__ 1 Start a boric acid transfer pump. 1 Perform the following.
1.1 BATP 1.1 Align charging pump suction to RWST.
[ ] 1A
[ ] 1B [ ] Q1E21LCV115B open
[ ] Q1E21LCV115D open VCT OUTLET ISO
[ ] Q1E21LCV115C closed
[ ] Q1E21LCV115E closed 1.2 1.2 Proceed to step 3.
NOTE: IF emergency boration is being aligned to the manual emergency boration flow path, THEN consideration should be given to starting a boration through the blender via FCV113A & B in accordance with FNP-1-SOP-2.3, CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM, while personnel are being dispatched to locally open Q1E21V185.
2
__ 2 Align normal emergency boration flow 2 Align manual emergency boration flow path.
path.
EMERG BORATE BORIC ACID TO CHG PUMP SUCT TO BLENDER
[ ] Q1E21MOV8104 open [ ] Q1E21FCV113A open MAN EMERG BORATION
[ ] Q1E21V185 open (100 ft, AUX BLDG rad-side chemical mixing tank area)
S
__Page Completed 8 ProcedureStepsMain Page 2 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained
° CAUTION: Oscillating flow indications and/or ammeter indications could be indicative of air or gas intrusion into the charging pump suction. IF such indications are present, THEN consideration should be given to securing both letdown and any running charging pump AND ensuring the charging pump suction piping is adequately vented per FNP-1-SOP-2.1 prior to return to service.(Ref. SOER 97-1) (AI 2008206545) 3
__ 3 Verify at least one CHG PUMP - 3 STARTED.
4
__ 4 Establish adequate letdown. 4 4.1 4.1 Verify 45 gpm letdown orifice - IN 4.1 SERVICE.
LTDN ORIF ISO 45 GPM
[ ] Q1E21HV8149A open 4.2 4.2 Verify at least one 60 gpm letdown orifice 4.2
- IN SERVICE.
LTDN ORIF ISO 60 GPM
[ ] Q1E21HV8149B open
[ ] Q1E21HV8149C open 5
__ 5 Establish adequate charging flow. 5
- IF boration is from boric acid storage tank, THEN verify charging flow - GREATER THAN 40 gpm.
- IF boration is from the RWST, THEN verify charging flow - GREATER THAN 92 gpm.
S
__Page Completed 8 ProcedureStepsMain Page 3 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained 6°
__ 6 Verify emergency boration flow adequate. 6 Verify boration flow path using ATTACHMENT 1, BORATION FLOW
- IF normal emergency boration flow path PATH.
aligned, THEN check emergency boration flow greater than 30 gpm.
BORIC ACID EMERG BORATE
[ ] FI 110 OR
- IF manual emergency boration flow path aligned, THEN check boric acid flow greater than 30 gpm.
MAKEUP FLOW TO CHG/VCT
[ ] BA FI 113 OR
- IF boration is from the RWST, THEN verify charging flow - GREATER THAN 92 gpm.
7
__ 7 Direct Chemistry to secure the zinc 7 addition system (ZAS).
S
__Page Completed 8 ProcedureStepsMain Page 4 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained
° NOTE: The intent of the following step is to optimize the effectiveness of an emergency boration when no RCP is running and RHR is in operation.
8
__ 8 IF no RCP is running AND RHR is 8 aligned for cooldown operation, THEN perform the following.
8.1 8.1 Verify alternate charging path in service.
[ ] Q1E21HV8147 open RCS NORMAL CHG LINE
[ ] Q1E21HV8146 closed 9
__ 9 Check emergency boration complete. 9 9.1 9.1 Check reactor - NOT CRITICAL. 9.1 Perform the following.
9.1.1 9.1.1 IF control rod insertion below rod insertion limit, THEN continue emergency boration and return to step 5.
IF NOT, proceed to RNO step 9.1.2.
9.1.2 9.1.2 IF emergency borating as a result of inoperable {untrippable} control rods per Tech. Spec. 3.1.3.1 {3.1.4.A},
THEN verify shutdown margin greater than Technical Specification requirement using FNP-1-STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG 547°F) WITH INOPERABLE OR IMMOVABLE CONTROL RODS(S) {WITH UNTRIPPABLE CONTROL ROD(S)}.
IF NOT, proceed to step 10.
Step 9 continued on next page
__Page Completed 8 ProcedureStepsMain Page 5 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained 9.1.3° 9.1.3 WHEN shutdown margin greater than Technical Specification requirement, THEN proceed to step 10.
9.1.4 9.1.4 Continue emergency boration and return to step 5.
NOTE: In response to an uncontrolled cooldown below 525°F, the cold shutdown boron concentration is the maximum boron concentration required regardless of the extent of the cooldown.
9.2 9.2 Check RCS TAVG - LESS THAN 525°F. 9.2 Perform the following.
9.2.1 9.2.1 IF RCP's are running, a) Verify shutdown margin greater than THEN use TAVG temperature Technical Specification requirement indication on MCB OR IPC. using FNP-1-STP-29.1, SHUTDOWN MARGIN CALCULATION (TAVG TAVG (NARROW RANGE - MCB) 547°F) or FNP-1-STP-29.2, 1A,(1B,1C) RCS LOOP SHUTDOWN MARGIN
[ ] TI 412D CALCULATION (TAVG < 547°F OR
[ ] TI 422D BEFORE THE INITIAL CRITICALITY
[ ] TI 432D FOLLOWING REFUELING).
b) WHEN shutdown margin greater than TAVG (WIDE RANGE - IPC) Technical Specification requirement, 1A,(1B,1C) RCS LOOP THEN proceed to step 10.
[ ] TC4601
[ ] TC4602 c) Continue emergency boration and return
[ ] TC4603 to step 5.
9.2.2 9.2.2 IF RCP's are not running, THEN use RCS cold leg temperature indication.
RCS COLD LEG TEMP RECORDER
[ ] TR 410 Step 9 continued on next page
__Page Completed 8 ProcedureStepsMain Page 6 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained 9.3° 9.3 Continue emergency boration based on 9.3 initial boron concentration and RCS TAVG.
Approximate Boration (4 wt% boric acid)
Initial RCS Each °F TAVG Boron Concentration Is Less Than 525 °F 0 ppm 50 gal 300 ppm 52 gal 600 ppm 55 gal 1200 ppm 60 gal 1500 ppm 64 gal 1800 ppm 68 gal NOTE: Step 9 must be complete before continuing with this procedure.
10
__ 10 Check BAT is emergency boration source. 10 Perform the following.
10.1 10.1 Stop running boric acid transfer pump. 10.1 Align charging pump suction to VCT.
[ ] 1A [ ] Q1E21LCV115C open
[ ] 1B [ ] Q1E21LCV115E open RWST TO CHG PUMP
[ ] Q1E21LCV115B closed
[ ] Q1E21LCV115D closed 10.2 10.2 Proceed to step 12.
S
__Page Completed 8 ProcedureStepsMain Page 7 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained 11°
__ 11 Check normal emergency boration flow 11 Secure manual emergency boration flow path.
path aligned.
11.1 11.1 Secure normal emergency boration flow BORIC ACID path. TO BLENDER EMERG BORATE [ ] Q1E21FCV113A closed TO CHG PUMP SUCT
[ ] Q1E21MOV8104 closed MAN EMERG BORATION
[ ] Q1E21V185 closed (100 ft, AUX BLDG rad-side chemical mixing tank area) 12
__ 12 Direct Chemistry to sample RCS for 12 boron concentration using FNP-1-CCP-651, SAMPLING THE REACTOR COOLANT SYSTEM.
13
__ 13 Verify reactor makeup control system 13 Manually control reactor makeup system using aligned for auto makeup using FNP-1-SOP-2.3, CHEMICAL AND FNP-1-SOP-2.3, CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR VOLUME CONTROL SYSTEM MAKEUP CONTROL SYSTEM.
REACTOR MAKEUP CONTROL SYSTEM S
__Page Completed 8 ProcedureStepsMain Page 8 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained 14°
__ 14 Check Shutdown Margin verified greater 14 Verify shutdown margin greater than than Technical Specification requirement Technical Specification requirement using by Step 9.2 RNO. applicable procedure:
- FNP-1-STP-29.1, SHUTDOWN MARGIN CALCULATION (TAVG 547°F)
- FNP-1-STP-29.2, SHUTDOWN MARGIN CALCULATION (TAVG < 547°F OR BEFORE THE INITIAL CRITICALITY FOLLOWING REFUELING)
- FNP-1-STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG 547°F) WITH INOPERABLE OR IMMOVABLE CONTROL RODS(S) {WITH UNTRIPPABLE CONTROL ROD(S)}
NOTE: After a completion of any fast ramp or emergency boration, the suction piping of any idle charging pump could have a significantly higher boron concentration than the existing RCS. (OE-17609 &
AI 2004200233) 15
__ 15 Go to procedure and step in effect. 15
-END-
__Page Completed 8 ProcedureStepsMain Page 9 of 9
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained ATTACHMENT 1 BORATION FLOW PATH 1°
__ 1 IF normal emergency boration flow path 1 IF manual emergency boration flow path aligned, aligned, THEN verify running charging pump THEN verify running charging pump header header valves open. valves open.
Running CHG PUMP 1A 1B 1C Running CHG PUMP 1A 1B 1C CHG PUMP CHG PUMP SUCTION HDR ISO SUCTION HDR ISO Q1E21MOV []8130A Q1E21MOV []8130A []8130A
[]8130B []8130B []8130B
[]8131A []8131A []8131A
[]8131B []8131B []8131B CHG PUMP CHG PUMP DISCH HDR ISO DISCH HDR ISO Q1E21MOV []8132A []8132A Q1E21MOV []8132A []8132A
[]8132B []8132B []8132B []8132B
[]8133A []8133A
[]8133B []8133B S
__Page Completed 3 Page 1 of 3
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained ATTACHMENT 1 BORATION FLOW PATH 2°
__ 2 Check boration flow adequate. 2 Perform the following:
2.1 2.1 IF normal emergency boration flow path a) Align charging pump suction to RWST:
aligned, THEN check emergency boration flow greater than 30 gpm RWST TO CHG PUMP
[ ] Q2E21LCV115B open BORIC ACID [ ] Q2E21LCV115D open EMERG BORATE
[ ] Q2E21LCV115C closed 2.2 2.2 IF manual emergency boration flow path [ ] Q2E21LCV115E closed aligned, THEN check boric acid flow greater than 30 gpm.
MAKEUP FLOW b) Stop running boric acid transfer pump.
TO CHG/VCT
[ ] BA
[ ] FI 113 BATP
[ ] 1A
[ ] 1B c) Secure normal emergency boration flow path.
EMERG BORATE TO CHG PUMP SUCT
[ ] Q1E21MOV8104 closed 3
__ 3 Verify charging flow path aligned. 3 3.1 3.1 Verify charging pump discharge flow path 3.1
- ALIGNED.
CHG PUMPS TO REGENERATIVE HX
[ ] Q1E21MOV8107 open
[ ] Q1E21MOV8108 open Step 3 continued on next page
__Page Completed 3 Page 2 of 3
07/13/10 8:07:19 FNP-1-AOP-27.0 UNIT 1 EMERGENCY BORATION Version 16.0 Step Action/Expected Response Response Not Obtained ATTACHMENT 1 BORATION FLOW PATH 3.2° 3.2 Verify only one charging line valve - 3.2 OPEN.
RCS NORM CHG LINE
[ ] Q1E21HV8146 RCS ALT CHG LINE
[ ] Q1E21HV8147 3.3 3.3 IF boration is from the boric acid storage 3.3 IF boration is from the RWST, tank, THEN verify charging flow - GREATER THEN verify charging flow - GREATER THAN 92 gpm.
THAN 40 gpm.
CHG FLOW CHG FLOW [ ] FK 122 manually adjusted
[ ] FK 122 manually adjusted 4
__ 4 Notify control room of boration status. 4 5
__ 5 Return to step 7. 5
-END-
__Page Completed 3 Page 3 of 3
HLT-36 ADMIN exam A.2 RO Page 1 of 4 A.2 Conduct of operations ADMIN RO TITLE: RCP Seal Injection Leakage Test EVALUATION LOCATION: X CLASS ROOM PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS:
- 1. This task can be conducted individually or in a group setting in which all the necessary references are available.
- 2. Provide student with HANDOUT and calculator.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Correctly assess and determine if STP-8.0 Acceptance Criteria is met.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Aaron Forsha Date: 2/6/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3
HLT-36 ADMIN exam A.2 RO Page 2 of 4 CONDITIONS When I tell you to begin, you are to complete the RCP SEAL INJECTION LEAKAGE TEST. The condition under which this task is to be performed is:
- a. Unit 1 is at 24% power.
Your task is to complete the steps listed below of FNP-1-STP-8.0, RCP SEAL INJECTION LEAKAGE TEST, using the data provided.
- 1. Step 5.5
- 2. Step 5.6
- 3. Complete answer table below to determine the flow limit and Acceptance Criteria.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME
- 1. (step 5.5.1) Transfers data from steps 5.3.1-5.3.3 S / U Determine total seal injection flow. and adds values.
13+13+13=39 gpm No tolerance allowed
- 2. (step 5.5.2) Transfers data from steps 5.3.5-5.3.7 S / U Determine average PRZR pressure. and averages the values.
(2240+2245+2235)/3=2240psig No tolerance allowed
- 3. (step 5.6.1) Transfers data from 5.3.4 and 5.5.2 S / U Determine differential pressure. and calculates the difference.
2600-2240=360psid No tolerance allowed Note: In the following element the calculated psid is off the chart and flow limit is determined by the note at the bottom of Figure 1.
- 4. (step 5.6.1) Using 360 psid from step 5.6.1 using S / U Determine flow limit from figure 1. Figure 1 determines that flow limit is 40 gpm.
- 5. Evaluate acceptance criteria. Determines total flow and individual S / U flow acceptance criteria is met STOP TIME Terminate JPM when answer table is completed.
HLT-36 ADMIN exam A.2 RO Page 3 of 4 CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number.
KEY Step 5.6.2 (FLOW LIMIT) __40__ gpm ACCEPTANCE CRITERIA Step 5.6.2 MET NOT MET GENERAL
REFERENCES:
- 1. Tech Specs Amendment 146 U1/ 137 U2
- 2. FNP-1-STP-8.0 Ver 22.1
Provide: Calculator Critical ELEMENT justification:
STEP Evaluation
- 1. Not critical: Calculation only.
- 2. Not critical: Calculation only.
- 3. Not critical: Calculation only.
- 4. Critical: Task depends on accurate interpretation of Figure to establish correct acceptance results.
- 5. Critical: This is the assigned task.
COMMENTS:
HLT-36 ADMIN exam A.2 RO Page 1 of 1 HANDOUT CONDITIONS When I tell you to begin, you are to complete the RCP SEAL INJECTION LEAKAGE TEST. The condition under which this task is to be performed is:
- a. Unit 1 is at 24% power.
Your task is to complete the steps listed below of FNP-1-STP-8.0, RCP SEAL INJECTION LEAKAGE TEST, using the data provided.
- 1. Step 5.5
- 2. Step 5.6
- 3. Complete answer table below to determine the flow limit and Acceptance Criteria.
Provide your answer below Step 5.6.2 (FLOW LIMIT) ____ gpm ACCEPTANCE CRITERIA Circle One Step 5.6.2 MET NOT MET
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 1 of 11 S
A F
E T
Y RCP SEAL INJECTION LEAKAGE TEST R
E L
A T
E D
PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL
Reference:
NONE Information: NONE Approved By: David L Reed (for) Effective Date: February 22, 2013 Operations Manager
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 2 of 11 SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-1-STP-8.0 SR 3.5.5.1 TITLE MODE(S) REQUIRING TEST:
RCP SEAL INJECTION LEAKAGE TEST 1, 2, 3 TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)
PERFORMED BY: / DATE/TIME: /
(Print) (Signature)
COMPONENT OR TRAIN TESTED (if applicable)
ENTIRE STP PERFORMED FOR SURVEILLANCE CREDIT PARTIAL STP PERFORMED NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL TEST COMPLETED Satisfactory Unsatisfactory The following deficiencies occurred Corrective action taken or initiated SHIFT SUPERVISOR/ SHIFT SUPPORT SUPERVISOR REVIEW Procedure properly completed and satisfactory per step 9.1 of FNP-0-AP-5 Procedure to be placed in Operations Office for IST Engineer review following OPS Review.
Comments REVIEWED BY: / DATE:
(Print) (Signature)
- Reviewer must be AP-31 Level II certified & cannot be the Performing Individual IST ENGINEER REVIEW (REQUIRED)
REVIEWED BY: / DATE:
(Print) (Signature)
Comments
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 3 of 11 Procedure Version Description Version Number Version Description 21.0 Updated procedure to requirements of NMP-OS-008-001, Operations Procedure Writing Instructions Rewrote procedure providing detailed guidance previously implied.
Added Appendix 1.
Changed requirement to verify throttle valves sealed for each performance, whether adjustments made or not.
22.0 Added check boxes to initial conditions.
Deleted check boxes from steps that also require recording data.
Step 5.9, corrected referenced step number. Inserted check boxes for P&L steps 4.1 & 4.2. Modified step 5.7.2 for clarity. Added CR references to step 5.9. Made all signoff blanks the INIT blanks per template configuration.
22.1 TE 497178 - Revised the STRS to require IST engineer review. Added new step to scan the procedure and email to FNP IST Engineer.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 4 of 11 Table of Contents Page 1.0 Purpose .........................................................................................................................................5
2.0 Acceptance Criteria .......................................................................................................................5
3.0 Initial Conditions ............................................................................................................................5
4.0 Precautions and Limitations ..........................................................................................................5
5.0 Instructions ....................................................................................................................................6
6.0 References ....................................................................................................................................8
Figure 1 .....................................................................................................................................................9
Appendix 1 ..............................................................................................................................................10
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 5 of 11 1.0 Purpose To determine the amount of seal injection flow to the reactor coolant pump seals and to verify operability of CVCS seal injection to RCP check valves (Q1E21V0115A/B/C) to pass full forward flow in accordance with the requirements of the ASME OM Code.
2.0 Acceptance Criteria 2.1 Manual seal injection throttle valves are adjusted to give a flow within the limits of Figure 1 with SEAL WTR INJECTION HIK 186 full open.
2.2 Flow through each CVCS seal injection to RCP check valve (Q1E21V0115A/B/C) is greater than 6.7 gpm.
NOTE Asterisked steps (*) are those associated with Acceptance Criteria.
3.0 Initial Conditions 3.1 The version of this procedure has been verified to be the current version.
(OR 1-98-498) 3.2 This procedure has been verified to be the correct unit for the task.
(OR 1-98-498) 3.3 Reactor coolant system pressure is between 2215 psig and 2255 psig.
3.4 RCP seal injection system is aligned per FNP-1-SOP-2.1A.
3.5 IF operating at power, THEN power level is constant.
3.6 Reactor coolant system temperature is > 290qF.
3.7 Pressurizer level is stable and in the normal operating band.
3.8 Charging Flow is stable.
1A 3.9 Record Charging Pump(s) in Service ______________.
4.0 Precautions and Limitations 4.1 Do not change power level during this test.
4.2 When letdown flow has been changed from two orifices in service to only one orifice in service, then FNP-1-STP-8.0 must be performed immediately to verify the requirements of Technical Specification SR 3.5.5.1.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 6 of 11 5.0 Instructions 5.1 Record seal injection flow to RCPs (MCB indication).
x 1A RCP SHAFT SEAL FLOW FI 130A 7 gpm 7
x 1B RCP SHAFT SEAL FLOW FI 127A gpm x 1C RCP SHAFT SEAL FLOW FI 124A 7 gpm 5.2 *Increase seal water flow to maximum by fully opening SEAL WTR INJECTION HIK 186. _____
Initial 5.3 *Record the following (MCB indication):
13 5.3.1 1A RCP SHAFT SEAL FLOW FI 130A gpm 5.3.2 1B RCP SHAFT SEAL FLOW FI 127A 13 gpm 5.3.3 1C RCP SHAFT SEAL FLOW FI 124A 13 gpm 5.3.4 CHG HDR PRESS PI 121 2600 psig 5.3.5 PRZR PRESS PI 455 2240 psig 5.3.6 PRZR PRESS PI 456 2245 psig 5.3.7 PRZR PRESS PI 457 2235 psig 5.4 Adjust SEAL WTR INJECTION HIK 186 to attain desired seal injection flowrate. _____
Initial 5.5 Perform the following calculations:
5.5.1 Determine total seal injection flow. _____
Initial Sum of values recorded in steps 5.3.1 + 5.3.2 + 5.3.3 Step 5.3.1 ______+ step 5.3.2 _____ + step 5.3.3 _____ = Total gpm 5.5.2 Determine average PRZR Pressure. _____
Initial Sum of values recorded in steps 5.3.5 + 5.3.6 + 5.3.7 y # of operable channels.
Step 5.3.5 ______+ step 5.3.6 _____ + step 5.3.7 _____ = Total psig Total psig y # of operable channels = Average pressure
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 7 of 11 5.6 *Determine the FLOW LIMIT from Figure 1 based on the differential pressure between average pressurizer pressure and charging header pressure.
5.6.1 Determine 'P as follows.
CHG HDR PRESS step 5.3.4 - Average PRZR Pressure value step 5.5.2 = 'P Step 5.3.4 - Step 5.5.2 = psid _____
Initial 5.6.2 FLOW LIMIT from FIGURE 1(Based on the 'P determined in step 5.6.1.
FLOW LIMIT from FIGURE 1 gpm _____
Initial ACCEPTANCE CRITERIA Total Flow within limits of Figure 1 with SEAL WTR INJECTION HIK 186 fully open.
Flow is t 6.7 gpm through each line.
5.7 IF flow adjustment necessary, THEN perform the following:
5.7.1 Adjust seal injection manual throttle valves to obtain proper flow using FNP-1-SOP-2.1, Appendix I, Balancing Seal Injection Flows To RCPs and Adjusting Total Seal Injection Flow. _____
Initial 5.7.2 Perform Appendix 1 of this procedure. _____
Initial 5.8 Verify the following seal injection throttle valves are sealed in position: (NRC Cmt.
0004355) (CR 2010113165) x 1-CVC-V-8369A (Q1E21V116A) _____
Initial x 1-CVC-V-8369B (Q1E21V116B) _____
Initial x 1-CVC-V-8369C (Q1E21V116C) _____
Initial
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 8 of 11 5.9 IF adjustments were made per step 5.7, THEN Independently verify the following seal injection throttle valves are sealed in position: (NRC Cmt. 0004355) (CR 2010113165) x 1-CVC-V-8369A (Q1E21V116A) _____
Initial x 1-CVC-V-8369B (Q1E21V116B) _____
Initial x 1-CVC-V-8369C (Q1E21V116C) _____
Initial 5.10 Scan the entire procedure to the following Email address: FNP IST Engineer. _____
Initial 6.0 References 6.1 D-175039 - CVCS P & ID, Sheets 1 & 2 6.2 Fourth 10-Year Interval IST Program 6.3 Technical Specification 3.5.5
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 9 of 11 FIGURE 1 250 Delta P (PI-121 - Pressurizer Pressure)
Unacceptable Acceptable 200 Region Region 150 31, 141 27, 113 100 24, 92 Unacceptable Region 50 15 18 20 25 30 35 40 GPM
- FOR Delta P's > 250 PSID the Flow Limit is 40 GPM.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 10 of 11 Appendix 1 Throttle Valve Adjustment and Re-calculation of Controlled Leakage NOTE Any throttle valve adjustments should be verified acceptable per SR 3.5.5.1 by performing two FNP-1-STP-8.0s, RCP SEAL INJECTION LEAKAGE TEST, within four hours. One FNP-1-STP-8.0 should be performed with the strongest charging pump supplying flow and one FNP-1-STP-8.0 performed with the weakest charging pump supplying flow. The strongest and weakest charging pump can be determined by comparing the data in the Surveillance Test Data book. (Engineering Support should be contacted if assistance is required in making this determination.) If it is not feasible to run FNP-1-STP-8.0 using either the strongest or weakest pump (i.e., pump not capable of running or breaker racked out),
then the surveillance should be run with the two available charging pumps and an admin LCO written for the inoperable pump to ensure FNP-1-STP-8.0 is run when the pump is returned to service.
7.0 Instructions 7.1 IF necessary, THEN adjust seal injection manual throttle valves to obtain proper flow and record the following below: {CMT 0004422} _____
Initial 7.2 *Increase seal water flow to maximum by fully opening SEAL WTR INJECTION HIK 186. _____
Initial 7.3 *Record the following (MCB indication):
7.3.1 1A RCP SHAFT SEAL FLOW FI 130A gpm 7.3.2 1B RCP SHAFT SEAL FLOW FI 127A gpm 7.3.3 1C RCP SHAFT SEAL FLOW FI 124A gpm 7.3.4 CHG HDR PRESS PI 121 psig 7.3.5 PRZR PRESS PI 455 psig 7.3.6 PRZR PRESS PI 456 psig 7.3.7 PRZR PRESS PI 457 psig 7.4 Adjust SEAL WTR INJECTION HIK 186 to attain desired seal injection flowrate. _____
Initial
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 11 of 11 7.5 Perform the following calculations:
7.5.1 Determine total seal injection flow. _____
Initial Sum of values recorded in steps 7.3.1 + 7.3.2 + 7.3.3 Step 7.3.1 ______+ step 7.3.2 _____ + step 7.3.3 _____ = Total gpm 7.5.2 Determine average PRZR Pressure. _____
Initial Sum of values recorded in steps 7.3.5 + 7.3.6 + 7.3.7 y # of operable channels.
Step 7.3.5 ______+ step 7.3.6 _____ + step 7.3.7 _____ = Total psig Total psig y # of operable channels = Average pressure 7.6 *Determine the FLOW LIMIT from Figure 1 based on the differential pressure between average pressurizer pressure and charging header pressure.
7.6.1 Determine 'P as follows.
CHG HDR PRESS step 7.3.4 - Average PRZR Pressure value step 7.5.2 = 'P Step 7.3.4 - Step 7.5.2 = psid _____
Initial 7.6.2 FLOW LIMIT from FIGURE 1(Based on the 'P determined in step 7.6.1).
FLOW LIMIT from FIGURE 1 gpm _____
Initial ACCEPTANCE CRITERIA Total Flow within limits of Figure 1 with SEAL WTR INJECTION HIK 186 fully open.
Flow is t 6.7 gpm through each line.
NOTE The surveillance can be recorded as satisfactory even if acceptance criteria not satisfied at step 5.6, providing acceptance criteria satisfied following adjustment per Appendix 1.
7.7 Return to step 5.8 in the body of the procedure. _____
Initial
HLT-36 ADMIN exam A.2 SRO Page 1 of 6 A.2 Conduct of operations ADMIN SRO TITLE: RCP Seal Injection Leakage Test EVALUATION LOCATION: X CLASS ROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS:
- 1. This task can be conducted individually or in a group setting in which all the necessary references are available.
- 2. Provide student with HANDOUT and calculator.
- 3. Computer with exam security log in.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Correctly assess and determine if STP-8.0 Acceptance Criteria is met.
- Correctly assess Tech Spec requirements.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Aaron Forsha Date: 2/6/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3
HLT-36 ADMIN exam A.2 SRO Page 1 of 6 CONDITIONS When I tell you to begin, you are to complete the RCP SEAL INJECTION LEAKAGE TEST. The condition under which this task is to be performed is:
- a. Unit 1 is at 24% power.
Your task is to complete the steps listed below of FNP-1-STP-8.0, RCP SEAL INJECTION LEAKAGE TEST, using the data provided.
- 1. Step 5.5
- 2. Step 5.6
- 3. Complete answer table below to determine the flow limit and Acceptance Criteria.
INITIATING CUE: You may begin.
Part 2 - administer this portion of the JPM after completion of the above task.
JPM DIRECTIONS:
- 1. Provide student with Part 2 HANDOUT.
CONDITIONS Based on your previously provided conditions, evaluate Tech Specs.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME
- 1. (step 5.5.1) Transfers data from steps 5.3.1- S / U Determine total seal injection flow. 5.3.3 and adds values.
14+13+14= 41gpm No tolerance allowed
- 2. (step 5.5.2) Transfers data from steps 5.3.5- S / U Determine average PRZR pressure. 5.3.7 and averages the values.
(2245+2240+2235)/3=2240 psig No tolerance allowed
- 3. (step 5.6.1) Transfers data from 5.3.4 and 5.5.2 S / U Determine differential pressure. and calculates the difference.
2600-2240=360 psid No tolerance allowed
HLT-36 ADMIN exam A.2 SRO Page 2 of 6 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
Note: In the following element the calculated psid is off the chart and flow limit is determined by the note at the bottom of Figure 1.
- 4. (step 5.6.1) Using 360 psid from step 5.6.1 S / U Determine flow limit from figure 1. determines using Figure 1 that flow limit is 40 gpm.
- 5. Evaluate acceptance criteria. Determines total flow and S / U individual flow acceptance criteria is NOT met.
Part 2 - administer this portion of the JPM after completion of the above task.
- 6. Evaluates Tech Spec Requirements. Tech Spec 3.5.5 Condition A is S / U entered and adjustments must be made within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
STOP TIME Terminate JPM when Tech Spec evaluation is complete.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number.
GENERAL
REFERENCES:
- 1. Tech Specs Amendment 146 U1/ 137 U2
- 2. FNP-1-STP-8.0 Ver 22.1
Provide: Calculator Critical ELEMENT justification:
STEP Evaluation
- 1. Not critical: Calculation only.
- 2. Not critical: Calculation only.
- 3. Not critical: Calculation only.
- 4. Critical: Task depends on accurate interpretation of Figure to establish correct acceptance results.
- 5. Critical: This is the assigned task.
- 6. Critical: This is the assigned task.
HLT-36 ADMIN exam A.2 SRO Page 3 of 6 COMMENTS:
KEY Step 5.6.2 (FLOW LIMIT) __40__ gpm ACCEPTANCE CRITERIA Step 5.6.2 MET NOT MET
This page is intentionally blank.
HLT-36 ADMIN exam A.2 SRO Page 1 of 1 Part 2 HANDOUT CONDITIONS Based on your previously provided conditions, evaluate Tech Specs.
HLT-36 ADMIN exam A.2 SRO Page 1 of 1 HANDOUT CONDITIONS When I tell you to begin, you are to complete the RCP SEAL INJECTION LEAKAGE TEST. The condition under which this task is to be performed is:
- a. Unit 1 is at 24% power.
Your task is to complete the steps listed below of FNP-1-STP-8.0, RCP SEAL INJECTION LEAKAGE TEST, using the data provided.
- 1. Step 5.5
- 2. Step 5.6
- 3. Complete answer table below to determine the flow limit and Acceptance Criteria.
Provide your answer below Step 5.6.2 (FLOW LIMIT) ____ gpm ACCEPTANCE CRITERIA Circle One Step 5.6.2 MET NOT MET
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 1 of 11 S
A F
E T
Y RCP SEAL INJECTION LEAKAGE TEST R
E L
A T
E D
PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL
Reference:
NONE Information: NONE Approved By: David L Reed (for) Effective Date: February 22, 2013 Operations Manager
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 2 of 11 SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-1-STP-8.0 SR 3.5.5.1 TITLE MODE(S) REQUIRING TEST:
RCP SEAL INJECTION LEAKAGE TEST 1, 2, 3 TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)
PERFORMED BY: / DATE/TIME: /
(Print) (Signature)
COMPONENT OR TRAIN TESTED (if applicable)
ENTIRE STP PERFORMED FOR SURVEILLANCE CREDIT PARTIAL STP PERFORMED NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL TEST COMPLETED Satisfactory Unsatisfactory The following deficiencies occurred Corrective action taken or initiated SHIFT SUPERVISOR/ SHIFT SUPPORT SUPERVISOR REVIEW Procedure properly completed and satisfactory per step 9.1 of FNP-0-AP-5 Procedure to be placed in Operations Office for IST Engineer review following OPS Review.
Comments REVIEWED BY: / DATE:
(Print) (Signature)
- Reviewer must be AP-31 Level II certified & cannot be the Performing Individual IST ENGINEER REVIEW (REQUIRED)
REVIEWED BY: / DATE:
(Print) (Signature)
Comments
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 3 of 11 Procedure Version Description Version Number Version Description 21.0 Updated procedure to requirements of NMP-OS-008-001, Operations Procedure Writing Instructions Rewrote procedure providing detailed guidance previously implied.
Added Appendix 1.
Changed requirement to verify throttle valves sealed for each performance, whether adjustments made or not.
22.0 Added check boxes to initial conditions.
Deleted check boxes from steps that also require recording data.
Step 5.9, corrected referenced step number. Inserted check boxes for P&L steps 4.1 & 4.2. Modified step 5.7.2 for clarity. Added CR references to step 5.9. Made all signoff blanks the INIT blanks per template configuration.
22.1 TE 497178 - Revised the STRS to require IST engineer review. Added new step to scan the procedure and email to FNP IST Engineer.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 4 of 11 Table of Contents Page 1.0 Purpose .........................................................................................................................................5
2.0 Acceptance Criteria .......................................................................................................................5
3.0 Initial Conditions ............................................................................................................................5
4.0 Precautions and Limitations ..........................................................................................................5
5.0 Instructions ....................................................................................................................................6
6.0 References ....................................................................................................................................8
Figure 1 .....................................................................................................................................................9
Appendix 1 ..............................................................................................................................................10
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 5 of 11 1.0 Purpose To determine the amount of seal injection flow to the reactor coolant pump seals and to verify operability of CVCS seal injection to RCP check valves (Q1E21V0115A/B/C) to pass full forward flow in accordance with the requirements of the ASME OM Code.
2.0 Acceptance Criteria 2.1 Manual seal injection throttle valves are adjusted to give a flow within the limits of Figure 1 with SEAL WTR INJECTION HIK 186 full open.
2.2 Flow through each CVCS seal injection to RCP check valve (Q1E21V0115A/B/C) is greater than 6.7 gpm.
NOTE Asterisked steps (*) are those associated with Acceptance Criteria.
3.0 Initial Conditions 3.1 The version of this procedure has been verified to be the current version.
(OR 1-98-498) 3.2 This procedure has been verified to be the correct unit for the task.
(OR 1-98-498) 3.3 Reactor coolant system pressure is between 2215 psig and 2255 psig.
3.4 RCP seal injection system is aligned per FNP-1-SOP-2.1A.
3.5 IF operating at power, THEN power level is constant.
3.6 Reactor coolant system temperature is > 290qF.
3.7 Pressurizer level is stable and in the normal operating band.
3.8 Charging Flow is stable.
1A 3.9 Record Charging Pump(s) in Service ______________.
4.0 Precautions and Limitations 4.1 Do not change power level during this test.
4.2 When letdown flow has been changed from two orifices in service to only one orifice in service, then FNP-1-STP-8.0 must be performed immediately to verify the requirements of Technical Specification SR 3.5.5.1.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 6 of 11 5.0 Instructions 5.1 Record seal injection flow to RCPs (MCB indication).
x 1A RCP SHAFT SEAL FLOW FI 130A 7 gpm 7
x 1B RCP SHAFT SEAL FLOW FI 127A gpm x 1C RCP SHAFT SEAL FLOW FI 124A 7 gpm 5.2 *Increase seal water flow to maximum by fully opening SEAL WTR INJECTION HIK 186. _____
Initial 5.3 *Record the following (MCB indication):
14 5.3.1 1A RCP SHAFT SEAL FLOW FI 130A gpm 5.3.2 1B RCP SHAFT SEAL FLOW FI 127A 13 gpm 5.3.3 1C RCP SHAFT SEAL FLOW FI 124A 14 gpm 5.3.4 CHG HDR PRESS PI 121 2600 psig 5.3.5 PRZR PRESS PI 455 2240 psig 5.3.6 PRZR PRESS PI 456 2245 psig 5.3.7 PRZR PRESS PI 457 2235 psig 5.4 Adjust SEAL WTR INJECTION HIK 186 to attain desired seal injection flowrate. _____
Initial 5.5 Perform the following calculations:
5.5.1 Determine total seal injection flow. _____
Initial Sum of values recorded in steps 5.3.1 + 5.3.2 + 5.3.3 Step 5.3.1 ______+ step 5.3.2 _____ + step 5.3.3 _____ = Total gpm 5.5.2 Determine average PRZR Pressure. _____
Initial Sum of values recorded in steps 5.3.5 + 5.3.6 + 5.3.7 y # of operable channels.
Step 5.3.5 ______+ step 5.3.6 _____ + step 5.3.7 _____ = Total psig Total psig y # of operable channels = Average pressure
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 7 of 11 5.6 *Determine the FLOW LIMIT from Figure 1 based on the differential pressure between average pressurizer pressure and charging header pressure.
5.6.1 Determine 'P as follows.
CHG HDR PRESS step 5.3.4 - Average PRZR Pressure value step 5.5.2 = 'P Step 5.3.4 - Step 5.5.2 = psid _____
Initial 5.6.2 FLOW LIMIT from FIGURE 1(Based on the 'P determined in step 5.6.1.
FLOW LIMIT from FIGURE 1 gpm _____
Initial ACCEPTANCE CRITERIA Total Flow within limits of Figure 1 with SEAL WTR INJECTION HIK 186 fully open.
Flow is t 6.7 gpm through each line.
5.7 IF flow adjustment necessary, THEN perform the following:
5.7.1 Adjust seal injection manual throttle valves to obtain proper flow using FNP-1-SOP-2.1, Appendix I, Balancing Seal Injection Flows To RCPs and Adjusting Total Seal Injection Flow. _____
Initial 5.7.2 Perform Appendix 1 of this procedure. _____
Initial 5.8 Verify the following seal injection throttle valves are sealed in position: (NRC Cmt.
0004355) (CR 2010113165) x 1-CVC-V-8369A (Q1E21V116A) _____
Initial x 1-CVC-V-8369B (Q1E21V116B) _____
Initial x 1-CVC-V-8369C (Q1E21V116C) _____
Initial
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 8 of 11 5.9 IF adjustments were made per step 5.7, THEN Independently verify the following seal injection throttle valves are sealed in position: (NRC Cmt. 0004355) (CR 2010113165) x 1-CVC-V-8369A (Q1E21V116A) _____
Initial x 1-CVC-V-8369B (Q1E21V116B) _____
Initial x 1-CVC-V-8369C (Q1E21V116C) _____
Initial 5.10 Scan the entire procedure to the following Email address: FNP IST Engineer. _____
Initial 6.0 References 6.1 D-175039 - CVCS P & ID, Sheets 1 & 2 6.2 Fourth 10-Year Interval IST Program 6.3 Technical Specification 3.5.5
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 9 of 11 FIGURE 1 250 Delta P (PI-121 - Pressurizer Pressure)
Unacceptable Acceptable 200 Region Region 150 31, 141 27, 113 100 24, 92 Unacceptable Region 50 15 18 20 25 30 35 40 GPM
- FOR Delta P's > 250 PSID the Flow Limit is 40 GPM.
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 10 of 11 Appendix 1 Throttle Valve Adjustment and Re-calculation of Controlled Leakage NOTE Any throttle valve adjustments should be verified acceptable per SR 3.5.5.1 by performing two FNP-1-STP-8.0s, RCP SEAL INJECTION LEAKAGE TEST, within four hours. One FNP-1-STP-8.0 should be performed with the strongest charging pump supplying flow and one FNP-1-STP-8.0 performed with the weakest charging pump supplying flow. The strongest and weakest charging pump can be determined by comparing the data in the Surveillance Test Data book. (Engineering Support should be contacted if assistance is required in making this determination.) If it is not feasible to run FNP-1-STP-8.0 using either the strongest or weakest pump (i.e., pump not capable of running or breaker racked out),
then the surveillance should be run with the two available charging pumps and an admin LCO written for the inoperable pump to ensure FNP-1-STP-8.0 is run when the pump is returned to service.
7.0 Instructions 7.1 IF necessary, THEN adjust seal injection manual throttle valves to obtain proper flow and record the following below: {CMT 0004422} _____
Initial 7.2 *Increase seal water flow to maximum by fully opening SEAL WTR INJECTION HIK 186. _____
Initial 7.3 *Record the following (MCB indication):
7.3.1 1A RCP SHAFT SEAL FLOW FI 130A gpm 7.3.2 1B RCP SHAFT SEAL FLOW FI 127A gpm 7.3.3 1C RCP SHAFT SEAL FLOW FI 124A gpm 7.3.4 CHG HDR PRESS PI 121 psig 7.3.5 PRZR PRESS PI 455 psig 7.3.6 PRZR PRESS PI 456 psig 7.3.7 PRZR PRESS PI 457 psig 7.4 Adjust SEAL WTR INJECTION HIK 186 to attain desired seal injection flowrate. _____
Initial
Procedure Number Ver UNIT 1 Farley Nuclear Plant FNP-1-STP-8.0 22.1 3/15/2013 Page Number 02:08:35 RCP SEAL INJECTION LEAKAGE TEST 11 of 11 7.5 Perform the following calculations:
7.5.1 Determine total seal injection flow. _____
Initial Sum of values recorded in steps 7.3.1 + 7.3.2 + 7.3.3 Step 7.3.1 ______+ step 7.3.2 _____ + step 7.3.3 _____ = Total gpm 7.5.2 Determine average PRZR Pressure. _____
Initial Sum of values recorded in steps 7.3.5 + 7.3.6 + 7.3.7 y # of operable channels.
Step 7.3.5 ______+ step 7.3.6 _____ + step 7.3.7 _____ = Total psig Total psig y # of operable channels = Average pressure 7.6 *Determine the FLOW LIMIT from Figure 1 based on the differential pressure between average pressurizer pressure and charging header pressure.
7.6.1 Determine 'P as follows.
CHG HDR PRESS step 7.3.4 - Average PRZR Pressure value step 7.5.2 = 'P Step 7.3.4 - Step 7.5.2 = psid _____
Initial 7.6.2 FLOW LIMIT from FIGURE 1(Based on the 'P determined in step 7.6.1).
FLOW LIMIT from FIGURE 1 gpm _____
Initial ACCEPTANCE CRITERIA Total Flow within limits of Figure 1 with SEAL WTR INJECTION HIK 186 fully open.
Flow is t 6.7 gpm through each line.
NOTE The surveillance can be recorded as satisfactory even if acceptance criteria not satisfied at step 5.6, providing acceptance criteria satisfied following adjustment per Appendix 1.
7.7 Return to step 5.8 in the body of the procedure. _____
Initial
ILT-36 ADMIN JPM A.3 SRO + RO Page 1 of 5 A.3 Conduct of operations ADMIN SRO + RO TITLE: Determine Access Personnel Exposure EVALUATION LOCATION: X CLASS ROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS:
- 1. Initiation of task may be in group setting, evaluation performed individually upon completion.
- 2. Provide student with HANDOUT and calculator.
- 3. Allow time to review data.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Determine the best route to minimize exposure and recognize workers current limit will not allow either route.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Aaron Forsha Date: 2/13/2013 NRC Approval SEE NUREG 1021 FORM ES-301-3
HLT-36 ADMIN exam A.3 Page 2 of 5 CONDITIONS This is pre-job brief: When I tell you to begin, you are to determine which route allows the lowest exposure and if total personnel exposure for a containment entry and valve operation is acceptable without exceeding your dose limits.
- a. Unit 1 is shutdown and the crew is attempting to place a system in service, but they are unable to remotely open a valve.
- b. You have been tasked with entering containment alone, manually opening the valve and then returning to your work location.
- c. Your allowable dose limit is 18 mrem.
- d. Health Physics personnel are currently unavailable to provide calculation assistance.
- e. Two routes are available to the valve:
- Route 1 consists of two segments.
Segment 1 has you walk through a 40 mrem/hr general field for 3 minutes.
Segment 2 has you walk through a 60 mrem/hr general field to the valve for 5 minutes.
Total time to reach valve is 8 minutes.
- Route 2 consists of two segments.
Segment 1 has you walk through a 10 mrem/hr general field for 6 minutes.
Segment 2 has you walk through a 60 mrem/hr general field to the valve for 5 minutes.
Total time to reach valve is 11 minutes.
- Manual operation of the valve is in a 120 mrem/hr field and you should be able to open the valve in 5 minutes.
- For each routes evaluation use the same route for leaving containment.
You task is to:
- 1. Determine the best route to minimize total exposure.
- 2. Determine if containment entry and valve operation is acceptable without exceeding your dose limits.
- 3. Complete answer table below.
INITIATING CUE: You may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME NOTE: The applicant can perform the calculations in any order.
- 1. Calculate exposure at valve 120 mrem/hr* 1hr/60 min
- 5 min = S / U 10 mrem
HLT-36 ADMIN exam A.3 Page 3 of 5 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 2. Calculate exposure from using Route 1 Segment 1 S / U 40 mrem/hr
- 1hr/60 min
- 3 min
- 2
= 4 mrem Segment 2 60 mrem/hr
- 1hr/60 min
- 5 min
- 2
= 10 mrem Total Dose 4 + 10 + 10 =24 mrem
- 3. Calculate exposure from using Route 2 Segment 1 S / U 10 mrem/hr
- 1hr/60 min
- 6 min
- 2
= 2 mr Segment 2 60 mrem/hr
- 1hr/60 min
- 5 min
- 2
= 10 mr Total Dose 2 + 10 + 10 =22 mrem
- 4. Determine the lowest exposure path Compared results of calculations and S / U determined that:
Route 2 to be the lowest exposure.
- 5. Compare calculated exposure to margin Compared exposure to margin and S / U determined: NOT acceptable be made within allowable margin of 18 mrem.
STOP TIME Terminate JPM when it is determined that no success path exists without exceeding dose margin limits.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number.
GENERAL
REFERENCES:
- 1. GEN-004 Radiation Worker Training/Retraining
Provide: Calculator
HLT-36 ADMIN exam A.3 Page 4 of 5 Critical ELEMENT justification:
STEP Evaluation
- 1. Not critical: This is common to both paths.
- 2. Not critical: Calculation only.
- 3. Not critical: Calculation only.
- 4. Critical: Answer is the assigned task.
- 5. Critical: Answer is the assigned task.
COMMENTS:
KEY Solution Matrix Circle One Best route to minimize exposure is:
Route 1 Route 2 Acceptable to perform this task:
Yes No
HLT-36 ADMIN exam A.3 Page 1 of 1 HANDOUT CONDITIONS This is pre-job brief: When I tell you to begin, you are to determine which route allows the lowest exposure and if total personnel exposure for a containment entry and valve operation is acceptable without exceeding your dose limits.
- a. Unit 1 is shutdown and the crew is attempting to place a system in service, but they are unable to remotely open a valve.
- b. You have been tasked with entering containment alone, manually opening the valve and then returning to your work location.
- c. Your allowable dose limit is 18 mrem.
- d. Health Physics personnel are currently unavailable to provide calculation assistance.
- e. Two routes are available to the valve:
- Route 1 consists of two segments.
Segment 1 has you walk through a 40 mrem/hr general field for 3 minutes.
Segment 2 has you walk through a 60 mrem/hr general field to the valve for 5 minutes.
Total time to reach valve is 8 minutes.
- Route 2 consists of two segments.
Segment 1 has you walk through a 10 mrem/hr general field for 6 minutes.
Segment 2 has you walk through a 60 mrem/hr general field to the valve for 5 minutes.
Total time to reach valve is 11 minutes.
- Manual operation of the valve is in a 120 mrem/hr field and you should be able to open the valve in 5 minutes.
- For each routes evaluation use the same route for leaving containment.
You task is to:
- 1. Determine the best route to minimize total exposure.
- 2. Determine if containment entry and valve operation is acceptable without exceeding your dose limits.
- 3. Complete answer table below.
Circle your answer below Best route to minimize exposure is: Route 1 Route 2 Acceptable to perform containment entry and valve Yes No operation:
ILT-36 ADMIN JPM A.4 SRO Page 1 of 8 A.4 Admin SRO only - Emergency Plan TITLE: Classify an Emergency Event per NMP-EP-110, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.
EVALUATION LOCATION: X CLASS ROOM PROJECTED TIME: 25 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL X PRA THIS JPM IS TIME CRITICAL JPM DIRECTIONS:
- 1. This task can be conducted individually or in a group setting in which all the necessary references are available.
- 2. Provide the candidate the HANDOUT page and a copy of Checklist 1, Classification Determination, to allow for familiarization with the task for the event in progress.
- 3. Allow the candidate time to review and understand the task.
- 4. Then, provide the candidate a copy of the procedure NMP-EP-110, NMP-EP-110-GL001, and EAL Boards and direct the candidate to begin; This starts the time critical time.
- 5. When the candidate indicates that he has completed his task, record the time of completion. This ends the TIME CRITICAL portion of the task.
- 6. Upon completion of EP-110, Checklist 1, provide a copy of EP-111, Figure 1 and give the instructions of step 2 of the task to complete EP-111, Figure 1, steps 10 and 11.
- 7. Ensure a clock is in the room in which this task will be conducted.
CAUTION: A KEY (2 pages) is included and precedes the student handout.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Correctly assess the Classification and correctly fill out EP-110, Checklist 1; which includes line 5; Name, Date and Time. The time is required to be within 15 minutes of the Start Time.
- Correctly assess the type of declaration and affected Unit and correctly fill out EP-111, Figure 1, steps 10 & 11.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Aaron Forsha Date: 2/6/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3
ILT-36 ADMIN JPM A.4 SRO Page 2 of 8 CONDITIONS When I tell you to begin, you are to Classify an Emergency Event per NMP-EP-110, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.
The conditions under which this task is to be performed are:
- a. FNP-0-AOP-49 IMMINENT SECURITY THREAT has been entered due to a confirmed attack at the AL- 95 main gate.
- b. Unit 1 was tripped from 70% power. ESP-0.1 and AOP-2.0 are in progress due to a 20 gpm SG tube leak.
- c. Unit 1 indications are as follows:
- R-15C, Condenser Air Ejector (High Range) is reading 0.070 R/hr.
- d. Unit 2 was tripped from 100% power. Entry conditions for FRP-H.1 have been met and FRP-H.1 actions are in progress.
- e. The current MET Tower data is as follows:
o Wind Direction from 125 degrees.
o Wind Speed 4.5 mph.
o Precipitation none.
o Stability Class E .
NOTE: The classification should NOT be based on ED discretion Your task is to classify the event, fill out NMP-EP-110, Checklist 1, Classification Determination Form, through step 6.
This task has TIME CRITICAL elements.
Upon completion, report to the proctor that you have finished.
INITIATING CUE: You may begin, Place the TIME in the START CRITICAL TIME space.
Part 2 - administer this portion of the JPM after completion of the above task.
JPM DIRECTIONS:
- 1. Provide student with Part 2 HANDOUT and page (1 of 2) NMP-EP-111 Figure 1.
CONDITIONS Based on your previously provided conditions, complete items 10 and 11 of NMP-EP-111, Figure 1, Emergency Notification Form (page 1 of 2). This task is NOT TIME CRITICAL.
ILT-36 ADMIN JPM A.4 SRO Page 3 of 8 Ensure the CANDIDATE places the START TIME on the HANDOUT SHEET.
Put that same time in the START CRITICAL TIME block below.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START CRITICAL TIME
- 1. Applicant completes Steps 1, 2, and 3 of Checklist
- Fuel Cladding Integrity: S / U 1 by providing all of the following information POTENTIAL LOSS (see answer key).
- Reactor Coolant System:
POTENTIAL LOSS
- Containment Integrity:
INTACT
- Highest applicable fission product barrier Initiating Condition:
FS1
- 2. Applicant completes Steps 4 and 5 of Checklist 1
- Highest applicable IC/EAL: S / U by providing all of the following critical FS1 information (see answer key) and provides the
- Classification:
completed Checklist 1 to the proctor within 15 Site Area - FS1 minutes.
- Name of Applicant, date, and current time Met data is not critical since it is not required to be added to the form for an initial
- Meteorological Data:
125°F, 4.5 mph, E, none STOP CRITICAL TIME Part 2 - administer this portion of the JPM after completion of the above task.
- 3. After the applicant has turned in his/her completed
- Step 10. Declaration Time: S / U Checklist 1, provide a copy of NMP-EP-111, From classification form Figure 1, Emergency Notification Form, Page 1 of
- Step 11. Affected Unit: Box 2 -
2 and ask the applicant to complete items 10 & 11. For Unit 2 STOP TIME Terminate when all elements of the task have been completed.
CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number.
ILT-36 ADMIN JPM A.4 SRO Page 4 of 8 GENERAL
REFERENCES:
- 1. NMP-EP-110 Version 4.0
- 2. NMP-EP-110-GL01, Version 2.0
- 3. NMP-EP-111 Version 7.1
- 4. KA: G2.4.41 SRO (4.6)
GENERAL TOOLS AND EQUIPMENT:
NMP-EP-110 NMP-EP-110-GL01 NMP-EP-111 Critical ELEMENT justification:
STEP Evaluation
- 1. Not critical since this part of the form is not required to be filled out to provide a correct classification.
- 2. Critical: Task completion; information provided is essential for correct classification and Emergency Notification form being correctly filled out within required time.
- 3. Critical: Task completion; information provided is essential for correct Emergency Notification form being correctly filled out.
COMMENTS:
This event has an overall classification of an ALERT, HA4, for the security event.
Unit 1 is in an ALERT, RA1.
Unit 2 is in a higher classification.
Filling out EP-111, figure 1, items 10 and 11 is appropriate since these are high miss issues and tests the applicants ability to find the correct instructions for these blocks and follow those directions correctly.
ILT-36 ADMIN JPM A.4 SRO Page 5 of 8 KEY part 1 Checklist 1 - Classification Determination (page 1 of 1)
NOTE Key Parameters should be allowed to stabilize to accurately represent plant conditions prior to classifying an event.
Initial Actions Completed by
- 1. Determine the appropriate Initiating Condition Matrix for classification of the _AF_
event based on the current operating mode:
X HOT IC/EAL Matrix Evaluation Chart (GO to Step 2) to evaluate the Barriers)
COLD IC/EAL Matrix Evaluation Chart (GO to Step 3)
- 2. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation.
- a. Select the condition of each fission product barrier:
_AF_
LOSS POTENTIAL LOSS INTACT Fuel Cladding Integrity X Reactor Coolant System X Containment Integrity X
- b. Determine the highest applicable fission product barrier Initiating Condition (IC): _AF_
(select one) FG1 X FS1 FA1 FU1 None
- 3. Evaluate and determine the highest applicable IC/EAL using the Matrix Evaluation Chart identified in step 1 THEN GO to step 4. _AF_
IC# FS1 or None
- 4. Check the highest emergency classification level identified from either step 2b or 3:
_AF_
Classification Based on IC# Classification Based on IC#
General Alert X Site-Area FS1 NOUE None N/A Remarks (Identify the specific EAL, as needed):
- 5. Declare the event by approving the Emergency Classification. _AF_
Candidate Signature Date: Date/ / Time: Time Emergency Director
- 6. Obtain Meteorological Data (not required prior to event declaration):
_AF_
Wind Direction (from) 125 Wind Speed 4.5 Stability Class E Precipitation none
- 7. Initiate Checklist 2, Emergency Plan Initiation. ________
ILT-36 ADMIN JPM A.4 SRO Page 6 of 8 KEY part 2 Figure 1 - Emergency Notification Form (page 1 of 2)
- 1. A DRILL B ACTUAL EVENT MESSAGE # _______
- 2. A INITIAL B FOLLOW-UP NOTIFICATION: TIME________DATE_____/_____/__ AUTHENTICATION #_______
- 3. SITE: _______________________ Confirmation Phone #_________________
- 4. EMERGENCY A UNUSUAL EVENT B ALERT C SITE AREA EMERGENCY D GENERAL EMERGENCY CLASSIFICATION:
BASED ON EAL# ____________ EAL DESCRIPTION:___________________________________________________________
- 5. PROTECTIVE ACTION RECOMMENDATIONS: A NONE B EVACUATE _________________________________________________________________________________________
C SHELTER __________________________________________________________________________________________
D Advise Remainder of EPZ to Monitor Local Radio/TV Stations/Tone Alert Radios for Additional Information and Consider the use of KI (potassium iodide) in accordance with State plans and policy.
E OTHER____________________________________________________________________________________________
- 6. EMERGENCY RELEASE: A None B Is Occurring C Has Occurred
- 7. RELEASE SIGNIFICANCE: A Not applicable B Within normal operating C Above normal operating D Under limits limits evaluation
- 8. EVENT PROGNOSIS: A Improving B Stable C Degrading
- 9. METEOROLOGICAL DATA: Wind Direction from _______ degrees* Wind Speed _______mph*
(*May not be available for Initial Notifications)*
Precipitation _______* Stability Class* A B C D E F G
- 11. AFFECTED UNIT(S): 1 X All
- 12. UNIT STATUS: A U1 _____% Power Shutdown at Time ____________ Date ___/_____/____
(Unaffected Unit(s) Status Not Required for Initial Notifications) B U2 _____% Power Shutdown at Time ____________ Date ___/_____/____
- 13. REMARKS:____________________________________________________________________________________________
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA NOT REQUIRED IF LINE 6 A IS SELECTED.
- 14. RELEASE CHARACTERIZATION: TYPE: A Elevated B Mixed C Ground UNITS: A Ci B Ci/sec C µCi/sec MAGNITUDE: Noble Gases:__________ Iodines:___________ Particulates:__________ Other: ____________
FORM: A Airborne Start Time __________ Date ___/_____/____Stop Time _________ Date ___/_____/____
B Liquid Start Time __________ Date ___/_____/____Stop Time _________ Date ___/_____/____
- 15. PROJECTION PARAMETERS: Projection period: ________Hours Estimated Release Duration ________Hours Projection performed: Time _________ Date ___/_____/____ Accident Type: ________
Site boundary 2 Miles 5 Miles 10 Miles
- 17. APPROVED BY: ____________________________ Title _____________________ Time ________Date___/_____/____
NOTIFIED RECEIVED BY: ___________________________ BY: ___________________________ Time ________Date___/_____/____
(To be completed by receiving organization)
This page is intentionally blank.
ILT-36 ADMIN JPM A.4 SRO Page 1 of 1 Part 2 HANDOUT CONDITIONS Based on your previously provided conditions, complete items 10 and 11 of NMP-EP-111, Figure 1, Emergency Notification Form (page 1 of 2). This task is NOT TIME CRITICAL.
Southern Nuclear Operating Company Emergency NMP-EP-111 Implementing Emergency Notifications Version 7.4 Procedure Page 35 of 47 Figure 1 - Emergency Notification Form (page 1 of 2)
- 1. A DRILL B ACTUAL EVENT MESSAGE # _______
- 2. A INITIAL B FOLLOW-UP NOTIFICATION: TIME________DATE_____/_____/__ AUTHENTICATION #_______
- 3. SITE: _______________________ Confirmation Phone #_________________
- 4. EMERGENCY A UNUSUAL EVENT B ALERT C SITE AREA EMERGENCY D GENERAL EMERGENCY CLASSIFICATION:
BASED ON EAL# ____________ EAL DESCRIPTION:___________________________________________________________
- 5. PROTECTIVE ACTION RECOMMENDATIONS: A NONE B EVACUATE _________________________________________________________________________________________
C SHELTER __________________________________________________________________________________________
D Advise Remainder of EPZ to Monitor Local Radio/TV Stations/Tone Alert Radios for Additional Information and Consider the use of KI (potassium iodide) in accordance with State plans and policy.
E OTHER____________________________________________________________________________________________
- 6. EMERGENCY RELEASE: A None B Is Occurring C Has Occurred
- 7. RELEASE SIGNIFICANCE: A Not applicable B Within normal operating C Above normal operating D Under limits limits evaluation
- 8. EVENT PROGNOSIS: A Improving B Stable C Degrading
- 9. METEOROLOGICAL DATA: Wind Direction from _______ degrees* Wind Speed _______mph*
(*May not be available for Initial Notifications)*
Precipitation _______* Stability Class* A B C D E F G
- 10. A DECLARATION B TERMINATION Time ________________ Date _____/______/_______
- 11. AFFECTED UNIT(S): 1 2 All
- 12. UNIT STATUS: A U1 _____% Power Shutdown at Time ____________ Date ___/_____/____
(Unaffected Unit(s) Status Not Required for Initial Notifications) B U2 _____% Power Shutdown at Time ____________ Date ___/_____/____
- 13. REMARKS:____________________________________________________________________________________________
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA NOT REQUIRED IF LINE 6 A IS SELECTED.
- 14. RELEASE CHARACTERIZATION: TYPE: A Elevated B Mixed C Ground UNITS: A Ci B Ci/sec C PCi/sec MAGNITUDE: Noble Gases:__________ Iodines:___________ Particulates:__________ Other: ____________
FORM: A Airborne Start Time __________ Date ___/_____/____Stop Time _________ Date ___/_____/____
B Liquid Start Time __________ Date ___/_____/____Stop Time _________ Date ___/_____/____
- 15. PROJECTION PARAMETERS: Projection period: ________Hours Estimated Release Duration ________Hours Projection performed: Time _________ Date ___/_____/____ Accident Type: ________
Site boundary 2 Miles 5 Miles 10 Miles
- 17. APPROVED BY: ____________________________ Title _____________________ Time ________Date___/_____/____
NOTIFIED RECEIVED BY: ___________________________ BY: ___________________________ Time ________Date___/_____/____
(To be completed by receiving organization)
This page is intentionally blank.
ILT-36 ADMIN JPM A.4 SRO Page 1 of 1 HANDOUT CONDITIONS When I tell you to begin, you are to Classify an Emergency Event per NMP-EP-110, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.
The conditions under which this task is to be performed are:
- a. FNP-0-AOP-49 has been entered due to a confirmed attack at the AL- 95 main gate.
- b. Unit 1 was tripped from 70% power. ESP-0.1 and AOP-2.0 are in progress due to a 20 gpm SG tube leak.
- c. Unit 1 indications are as follows:
- R-15C, Condenser Air Ejector (High Range) is reading 0.070 R/hr.
- d. Unit 2 was tripped from 100% power. Entry conditions for FRP-H.1 have been met and FRP-H.1 actions are in progress.
- e. The current MET Tower data is as follows:
o Wind Direction from 125 degrees.
o Wind Speed 4.5 mph.
o Precipitation none.
o Stability Class E .
NOTE: The classification should NOT be based on ED discretion Your task is to classify the event, fill out NMP-EP-110, Checklist 1, Classification Determination Form, through step 6.
This task has TIME CRITICAL elements.
Upon completion, report to the proctor that you have finished.
START TIME
Southern Nuclear Operating Company Emergency NMP-EP-110 Emergency Classification Determination Implementing Version 5.0 and Initial Action Procedure Page 13 of 25 Checklist 1 - Classification Determination (page 1 of 1)
NOTE Key Parameters should be allowed to stabilize to accurately represent plant conditions prior to classifying an event.
Initial Actions Completed by
- 1. Determine the appropriate Initiating Condition Matrix for classification of the event ________
based on the current operating mode:
HOT IC/EAL Matrix Evaluation Chart (GO to Step 2) to evaluate the Barriers)
COLD IC/EAL Matrix Evaluation Chart (GO to Step 3)
- 2. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation.
- a. Select the condition of each fission product barrier:
LOSS POTENTIAL LOSS INTACT Fuel Cladding Integrity Reactor Coolant System Containment Integrity
- b. Determine the highest applicable fission product barrier Initiating Condition (IC): ________
(select one) FG1 FS1 FA1 FU1 None
- 3. Evaluate and determine the highest applicable IC/EAL using the Matrix Evaluation Chart identified in step 1 THEN GO to step 4. ________
IC# or None
- 4. Check the highest emergency classification level identified from either step 2b or 3:
Classification Based on IC# Classification Based on IC#
General Alert Site-Area NOUE None N/A Remarks (Identify the specific EAL, as needed):
- 5. Declare the event by approving the Emergency Classification. ________
Date: / / Time:
Emergency Director
- 6. Obtain Meteorological Data (not required prior to event declaration):
Wind Direction (from) Wind Speed Stability Class Precipitation
- 7. Initiate Checklist 2, Emergency Plan Initiation. ________